ML18018A878

Applicant'S Environmental Report Operating License Stage Conversion to Full-Term Operating License

ML18018A878
Person / Time
Site:	Nine Mile Point
Issue date:	06/30/1972
From:	Niagara Mohawk Power Corp
To:	US Atomic Energy Commission (AEC)
References
Download: ML18018A878 (914)

Text

File +: U. S. Atomic Energy RegulatoFf Commission av/Ltr oatid~7+

.Riieelved Docket 50-220 APPLICANT'S ENVIRONMENTAL REPORT OPERATING LICENSE STAGE CONVERS ION TO FULL-TERM OPERATING LICENSE inc i e oin Uc ear 4 a ion nl June I972 NIAGARA MOHAWK POWER CORPORATION Syracuse, New York 13202

0 FOREWORD On August 22, 1969, 'iagara Mohawk Power Corporation (Niagara Mohawk) received its provisional operating license (DPR No. 17) from the United States Atomic Energy Commission (Commission) to operate Nine Mile Point Nuclear Station Unit 1 at 1,538 MWt (500 MWe) . On April 14, 1971 the power rating for this license was increased by the Commission to 1,850 MWt (610 MWe).

Pursuant to Section A of revised Appendix D to 10 CFR Part 50, this environmental report accompanies Niagrara Mohawk's applica-tion to convert the provisional operating license for Nine Mile Point Unit 1 to a full-term license. The contents of this report generally conform to the <<Draft Guide to the Preparation of Environmental Reports for Nuclear Power Plants" issued by the Commission February 1971, as amended, including the substance of the information required by the May 1972 <<Guide to the Preparation of Benefit-Cost Analyses <<, Those other points at which this report deviates from the above guidelines are noted in this Foreword.

Since Unit 1 is an operating facility, the report describing its environmental impact must necessarily differ in both scope and content from that appropriate to the construction permit stage.

The primary concern at the operating license stage is whether there has been any adverse impact to date from the operation of the facility or whether any adverse impact can be predicted from its continued operation. Consideration of alternatives must of necessity be limited to those which have a bearing on either of these two impacts. The benefit of the possible adoption of any of these alternatives must be balanced against the cost to Niagara Mohawk of their implementation and to the public from. the interruption of service.

A further difference is that this report focuses solely on the interaction of an operating facility upon its environment.

Accordingly, analysis of the facility s impact on the environment begins with start-up in 1969 until the present. References to preconstruction site environment are made only for comparison to the site at present. The discussion of construction effects is limited to contemplated modif ications of the facility.

This report describes in detail the steps taken by Niagara Mohawk in the design and operation of the station to avoid adverse environmental effects. Also discussed are the efforts by Niagara Mohawk to enhance the site and the nearby environment. Some of the interpretations chosen in preparing this document, which are supported by the legislative history of the National Environmental Policy Act, (83 Stat. 852, January 1, 1970) as well

as by the Guidelines issued on April 23, 1971 by the Council on Environmental Quality, are summarized below:

(a) The human environment includes that created by man for his subsistence, saf ety, and comfort as well as that provided by nature.

(b) The geographical area considered not only includes the immediate Niagara Mohawk service area, but also the area serviced by the New York Power Pool of which Niagara Mohawk is a member. Thus, the benefit to residents in the major population centers in the New York Power Pool area from using this source of power for lighting, heating, and cooling the urban environment has been con-sidered appropriate for the cost-benefit analysis involved in this report.

(c) <<Long-term productivity<< is presumed to mean produc-tivity over an extended period toward an economic or other purpose generally accepted as a constructive use of some part of the national environment.

Xn June 1972, Niagara Mohawk filed an application with the Commission to construct a new 1, 100 MWe nuclear power generating Mile Point site. This proposed facility (to facility on its Nine Point be called Nine Mile Station Unit 2), if approved, will be constructed adjacent to Unit 1 and scheduled for operation in 1978. The description of the proposed Unit 2 and its environmental impact are presented in a report entitled <<Nine Mile Point Nuclear Station Unit 2 Applicant's Environmental Report Construction Permit Stage,<< which accompanies its construction permit application.

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TABLE OF CONTENTS Section. Title Pacae.

1 o FOREWORD INTRODUCTION

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~ o ii 1o 1 1 1 1 DESCRIPTXON OF OPERATING STATION AND SITE 1 ~ 1 1 1 2 NEED FOR LOCATING THE POWER STATXON AT THE SITEo o o ~ o o o o o ~ o o o 1 ~ 2 1 2o THE SITE o o o o o ~ ~ o o o o o ~ o 2o 1 1 2.1 LOCATXON OF STATXON ~ 2o 1 1 2.1.1 Project Site. 2o 1 1

2. 1.2 Transportation .. 2o 1 1 2 2 HUMAN ACTIVITIES IN THE ENVIRONS. 2. 2-1 2.2.1 History of Land and Water Use 2o 2 1 2.2.2 Population 2 2-4 2 3 HXSTORIC SIGNIFXCANCE 2o 3 1 2 4 GEOLOGY 2 4-1 2.4 1 Topography o o o 2 4-1 2.4.2 Geology 2. 4-1 2.Q.3 Seismicity 2. 4-2 2 5 HYDROLOGY 2. 5 2 6 CLIMATOLOGY AND METEOROLOGY 2. 6-1 2.6.1 Data Sources. '

2. 6-1 2.6.2 General Climatology 2. 6-1

2. 6. 3 Winds 2. 6-1 2.6.4 Tornadoes and Hurricanes. 2. 6-2 2.6.5 Turbulence Classes. o 2. 6-3 2.6.6 Lapse Rates 2. 6-3 2 7 BIOTAo o 2o 7 1 2 7 1 Terrestrial Ecology of Surrounding Area and Station Site 2o 7 2.7. 1. 1 Abandoned pasture and orchard 2o 7 2 2.7. 1.2 Overgrown land 2o 7 2 2.7 1.3 Northern hardwood forest, . 2o 7 2 2.7. 1.4 Cleared land .. 2o 7 3 2 7 1 5 Animal Associations. 2o 7 3 2 7 2 Aquatic Ecology. 2. 7-4 2-8 PRESENT RADIOLOGXCAL CONDITIONS AT THE SXTE AND IN ITS ENVXRONMENT 2. 8-1

TABLE OF CONTENTS (CONT'D)

Section- Title Pacae.

3. THE STATION ~ 3& 1 1 3 1 EXTERNAL APPEARANCE 3& 1 1 TRANSMISSION LINES 2-1 3 2 3 3 3 REACTOR AND STEAM ELECTRIC SYSTEM 3.3-1 3.4 WATER USE 3 4-1 3 5 DESCRIPTION OF COOLING WATER SYSTEM DESIGN 3. 5-1 3.5.1 Intake System 3 5-1 3.5.2 Discharge System 3. 5-2 3 6 RADWASTE SYSTEM 3. 6-1 3.6.1 Waste Processing System . 3. 6-1 3.6.2 Gaseous Radioact=ive Waste System . 3. 6-2 3.6.2. 1 Sources of Radioactive Gas 3. 6-2 3.6.2.1.1 Process Offgas. 3. 6-2 3.6.2.1.2 Mechanical Vacuum Pump Offgas. 3. 6-2 3.6.2. 1.3 Drywell Ventilation . 3. 6-3 3.6.2. 1.4 Turbine Gland Seal 3. 6-3 3.6.2. 1.5 Miscellaneous Building Service Releases. 3 6-4

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3.6.2.2 Description of the Original Offgas System 3. 6-4 3.6.2.2. 1 30-.Minute Delay Pipe. 3. 6-4 3.6.2.2.2 Offgas Filter (Aftercooler) 3. 6-4 3.6.2.2.3 Radiation Monitors 3. 6-5 3.6.2.2 4 St.ack. 3. 6-5 3.6.2.3 Description of Upgraded Offgas System. 3. 6-5 3.6.2.3.1 Catalytic Recombiner. 3- 6-6 3.6.2.3.2 Condenser 3 6-6 3.6.2.3.3 Delay Pipe . 3. 6-6 3.6.2.3.4 Dehumidification System. 3. 6-6 3.6.2.3.5 Pre-absorber 3. 6-6 3.6.2.3.6 Charcoal Absorbers 3. 6-6 3.6.2.3.7 Vacuum Pump. 3. 6-7 3.6.3 Liquid Radioactive Waste System 3- 6-7 3.6.3.1 Description of the Original Liquid Radwast System. 3 6-7 3.6.3.1.1 Waste Collector Subsystem 3. 6-7 3 6.3. 1.2 Floor Drain Subsystem 3. 6-8 3.6.3. 1.3 Regenerant Chemical Subsystem. 3. 6-8 3.6.3.2 Description of the Upgraded Liquid Radwast Syst: em 0 1 0 ~ 0 0 0 0 0 0 0 3. 6-8 3.6.3.3 Original and Upgraded System Operational AnalysisO 0 0 0 0 0 0 0 0 0 0 3. 6-9 3.6.3.4 Original and Upgraded System Operational Evaluation 3 6-14 3.6.3.4. 1 Regenerant Chemicals Subsystem 3. 6-14 3.6.3.4.2 Waste Collector Subsystem- 3. 6-15

TABLE OF CONTENTS (CONTEND)

Section- Title Pa<ac 3.6.3. 4. 3 Floor Drain Subsystem 3. 6-15 3.6.3.5 Control of Waste Activity Movement. 3. 6-16 3.6.3.5.1 Release of Processed Waste. 3. 6-17 3.6.4 Solid Radioactive Waste System. 3. 6-17 3.6.4.1 Sources of Solid Waste . 3. 6-19 3.6.4.2 Processing and Handling 3. 6-20 3.6.4.3 Performance Analysis 3. 6-20 3.6.5 Transportation of Fuel and Radioactive Wa ste se . 3. 6-21 3.6. 5. 1 Packaging Criteria 3. 6-21 3.6.5.2 New Fuel Shipping 3. 6-22 3.6.5.3 Spent Fuel Shipping. 3 6-23 3.6. 5.4 Radioactive Waste Shipping 3 6-24 3 7 CHEMICAL AND SANITARX DISCHARGES 3& 7 1 3.7.1 Liquid Chemical Discharge 3& 7 1 3.7.2 Sanitary Waste System. 3&7 3 3 8 OTHER WASTES 3 8-1 4- ENVIRONMENTAL EFFECTS OF CONSTRUCTION 4 0-1 5 ENVIRONMENTAL EFFECTS OF STATION OPERATION ~ . 5 1-1 5.1 EFFECTS OF OPERATION OF COOLING WATER INTAKE AND DISCHARGE FACILITIES 5 1 5.1.1 Intake Structure and Operation. 5. 1-2 5.1 2 Discharge Structure and Operation. 5 1-2 5.1.3 Effects on Aquatic Biota. 5. 1-5 5 2 EFFECTS OF RELEASED RADIOACTIVE MATERIALS 5. 2-1 5.2.1 General 5 2-1 5.2.2 Aqueous Releases 5 2-2 5.2.2. 1 External Radiation Exposure from Water Related Activities. 5. 2-3 5.2.2. 1.1 Individual Exposure . 5. 2-3 5.2.2. 1.2 Population Exposure-Recreational., 5. 2-5 5.2.2.2 Internal Radiation Exposure from Ingestion of Food and Water 5. 2-6 5.2.2.2.1 Individual Exposure . 5 2-6 5.2.2.2.2 Population Exposure . 5 2-7 5.2.2.3 Radiation Exposure of Primary Producer and Consumer Species from Discharged Radionuclides 5 2-10 5.2.2.3.1 External- 5. 2-10 5.2.2.3.2 Internal. 5. 2-10 5.2.2.4 Radiation Exposure of Fish from Discharged Radionuclides. 5. 2-11 5.2.2. 4. 1 External. 5. 2-11 Vi

TABLE OF CONTENTS (CONT'D)

Section. Title Pacae.

5.2. 2. 4.2 Internal. 5. 2-12 5.2.3 Radionuclides Discharged to Ambient Air. 5. 2-12 5.2.3. 1 Individual. 5. 2-12

5. 2.3 2 Plants and Animals 5. 2-13 524 Radionuclide Contamination of Ground Water. 5. 2-13 5.2-5 Individual Exposure Estimate 5. 2-13 5.2.5. 1 Liquid Releases 5. 2-15

5. 2. 5. 2 Gaseous Releases 5. 2-15 5 3 EFFECTS OF CHEMICAL AND SANITARY WASTE TREATMENT EFFLUENTS 5. 3-1 5- 4 OTHER ENVIRONMENTAL EFFECTS 5 4-1 5.4.1 Transmission Line Effects 5. 4-1 5.4.2 Radioactive Material Transport Ef fects 5. 4-2

5. 4.3 Noise Ef fects 5. 4-3 5.4.3.1 Plant Environment 5. 4-3 5.4.3.2 Plant Noise Sources. 5. 4-3 5.4.3.3 Acoustical Impact 5. 4-4 5.4.4 Measures Which Will Be Taken To Preserve The Existing Environment or Enhance its Use 5. 4-8 5.4.5 Interaction with Neighboring New York State Power Authority Facilities. 5. 4-10 5.4.6 Disposal of Miscellaneous Solid Waste 5. 4-5 5.4.7 Changes in Site Land and Water Use 5. 4-5

5. 4. 7. 1 Land Use 5. 4-5 5.4.7.2 Water Use 5. 4-6 5.4.8 Effects of Released Combustion products. 5 4-7 5 5 ASSESSMENT OF ENVIRONMENTAL EFFECTS OF STATION OPERATI ON 5. 5-1 5.5.1 Fish Distribution . 5 5-1 5.5.1. 1 Fathometric Surveys. 5 5-2 5.5.1.2 Fish Netting . 5. 5-3 5.5. 1.3 Food preference Surveys 5. 5-4 5.5.2 Benthic Studies. 5. 5-4 5.5.3 Nutrient Distribution Studies 5. 5-6 5.5.4 Plankton Distribution and Entrainment 5. 5-7 5.5.5 Three-Dimensional Thermal Surveys. 5 5-8 5.5.6 Future Field, Laboratory, and Monitoring Px'ogramso o o o o o e o o o 5 5-8 5.5.6.1 Effects of Entrainment on Fish Eggs and Larvae. 5. 5-8 556.2 Fish Population Study . 5 5-9 5.5.6.3 Benthos and Cladophora Survey 5. 5-10 5.5.6 4 Physical-Chemical Analysis 5 5-10 5.5.6.5 Meteorology 5 5-10 5.5.6.6 Radiation Environment . 5 5-11

TABLE OF CONTENTS (CONT'D)

Section Title. Pacae

6. ENVXRONMENTAL EFFECTS OF ACCIDENTS 6. 1-1 6 ~ 1 SCOP Ee e e ~ e ~ e e e ~ e e 6 1-1 6.1.1 Probability in Perspective . 6 1-1

6. 1. 2 Probability Categories 6 1-2

6. 1. 2. 1 Normal Condition.

. e ~ 0 6 1-2 6.1.2.2 Upset Condition . 0 ~ 0 6. 1-2 6.1.2.3 Emergency Condition. ~ ~ e ~ e 6. 1-2 6.1.2.4 Fault Condition . 0 e 0 6 1-2 6.1.3 Basis for Probability Estimation .

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6. 1.4 Transient and Accident Occurrences Reactor Facility . 6 1-3 6 2 CLASS 2 MISCELLANEOUS SMALL RELEASES OUTSIDE CONTAINMENT 6. 2-1 6.2. 1 Event Xdentification 6 2-1 6.2.2 6.2.3 Calculation of Sources and Doses Radiological Results

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. 6. 2-1 6.2.4 Event Probability Considerations 6 2-2 6.3 CLASS 3 RADWASTE SYSTEM FAILURES 6. 3- I 6.3. 1 Liquid Radwaste 6 3-1 6.3.1.1 Calculation of Sources and Doses 6. 3-1 6.3. 1.2 Radiological Results 6 3-1 6.3. 1 3 Event Probability Considerations 6. 3-2 6.3.2 Gaseous Radwaste 6. 3-2 6.3.2. 1 Calculation of Sources and Doses 6 3-3 6.3.2.2 Radiological Results 6 3-2 6.3.2.3 Event Probability Considerations 6.-3-3 6.4 6 5 PRIMARY SYSTEM ......

CLASS 4 EVENTS THAT RELEASE ACTXVXTY INTO CLASS 5 EVENTS THAT RELEASE ACTXVXTY INTO

-. 6 4-1 SECONDARY SYSTEM 6 5-1 6 6 CLASS 6 REFUELXNG ACCIDENTS XNSXDE.

CONTAINMENT 6 6-1 6.6. 1 Heavy Object Dropped onto Core 0 0 e ~ 6. 6-1 6.6.1.1 Calculation of Sources and Doses e e e e 6. 6-1 6.6. 1.2 Radiological Results 6. 6-2 6.6. 1.3 Event Probability Considerations 0 0 6. 6-2 6.6.2 Spent Fuel Cask Drop . ~ ~ ~ ~ 0 6. 6-3 6.6.2.1 Calculation of Sources and Doses e 0 6. 6-3 6.6.2.2 Radiological Results 0 \ 0 0' 6. 6-4 6.6.2.3 Event Probability Considerations 6. 6-4 6 7 CLASS 7 SPENT FUEL ACCIDENT OUTSIDE SECONDARY CONTAINMENT 0 * ~ 6. 7-1 viii

TABLE OF CONTENTS (CONT'D)

Section. Title Pacae.

6.8 CLASS 8 ACCIDENT INITIATION EVENTS CONSIDERED IN DESIGN-BASXS EVALUATXON IN THE PRELIMINARY SAFETY ANALYSIS REPORT 6. 8-1 6.8. 1 Loss-of-Coolant Accident (LOCA) 6 8-1 6.8.1.1 Calculation of Sources and Doses 6 8-1 6 8. 1.2 Radiological Results 6. 8-2 6.8. 1.3 Event Probability Considerations 6. 8-3 6.8.2 Steam Line Break Accident (SLBA) 6. 8-3 6.8.2. 1 Calculation of Sources and Doses 6. 8-3 6.8.2.2 Radiological Results 6 8-4 6.8.2.3 Event Probability Considerations 6. 8-4 6.8.3 Control Rod Drop Accident (CRDA) 6. 8-4 6.8.3. 1 Calculation of Sources and Doses 6. 8-4 6.8.3.2 Radiological Results 6 8-5 6.8.3.3 Event Probability Considerations 6. 8-5 6.8.4 Radioactive Liquid Storage Tank Accident (LSTA) 6. 8-5 6.8.4. 1 Calculation of Sources and Doses 6. 8-5 6.8.4.2 Radiological Results 6. 8-6 6.8.4.3 Event Probability, Considerations 6. 8-6 6.8.5 Offgas System Accident (OGSA) 6. 8-6 6.8.5. 1 Calculation of Sources and Doses 6. 8-6 6.8.5 2 Radiological Results 6 8-7 6.8.5.3 Event Probability Considerations 6. 8-7 6 9 RADIATXON BACKGROUND AND RADIOLOGICAL IMPACT 6. 9-1 6.9. 1 Natural Radiation Background 6. 9-1 6.9.1.1 Total Radiation from Nature 6. 9-1 6.9.1.2 Man-Rem from Natural Radiation Background 6. 9-1 6.9.2 Man-Made Radiation Background . 6. 9-1 6.9.2. 1 Man-Rem from Man-Made Radiation 6. 9-2 6.9.3 Total Average Radiation Background 6. 9-2 6.9.4 Man-Rem from Nuclear Power Stations . 6. 9-3 6.9.5 Radiological Impact Conclusion 6. 9-4 70 UNAVOIDABLE ADVERSE ENVIRONMENTAL EFFECTS OF OPERATION 7. 0-1 8 'ALTERNATIVES TO THE EXISTING POWER STATION 8 0-1 9 BENEFXT COST ANALYSIS 9. 0-1 9 1 NOT PROVIDING THE POWER 9. 1-1, 9. 2-1 9 2 PURCHASXNG THE POWER 9. 1-1i 9 2-1 9 3 ALTERNATIVE SITES 9 3-1 9.4 REPLACING THE POWER 9 4-1

TABLE OF CONTENTS (CONTtD)

Section Title. Pacae 9 5 ALTERNATIVE COOLING SYSTEMS 9. 5-1 9.5. 1 Existing Once-Through Cooling System 9. 5-1 9.5. 1.1 Economics of the Existing System 9. 5-1 9.5. 1.2 Environmental Considerations of the Existing Systm o o o ~ o o o o o 9. 5-2 9.5.1.2. 1 Heat Discharge to Water Body . 9. 5-2 9.5.1.2.2 Effects of Intake Structure on Water Bod 9. 5-4 9.5.1.2.3 Chemical Discharge to Water Body 9. 5-6 9.5.1.2.4 Comsumption of Water 9. 5-6 9.5.1.2.5 Chemical Discharges to Ambient Air . 9- 5-6 9.5.1.2.6 Salts Discharged from Cooling Tower 9. 5-6 9.5.1.2.7 Chemical Contamination of Ground Water (Excluding Salts) 9. 5-6 9.5-1.2.8 Radiological Effects. 9. 5-7 9.5.1.2.9 Fogging and Icing. 9 5-7 9.5. 1. 2. 10 Raising/Lowering of Ground Water Levels 9. 5-7 9.5.1.2.11 Ambient Noise. 9 5-7 9.5. 1. 2. 12 Aesthetics. 9. 5-8 9.5.1.2. 13 Permanent Residuals of Construction ACtlVlty oo o o o o o o ~ o ~ 9. 5-8 9.5.1.2.14 Combined or Interactive Effects.. 9 5-8 9.5.2 Once-Through Cooling System with Diffuser Discharge 9- 5-8 9.5.2. 1 Economic's of this System . 9. 5-9 9.5.2.2 Environmental Considerations of this SyStemo o o o o os os o o o o o 9. 5-9 9.5.2.2.1 Heat Discharge to Water Body . 9. 5-9 9.5.2.2.2 Effects of Intake Structure on Water B ody o o ~ o o o o - ~ 9 5-10 9.5.2.2.3 Chemical Discharge to Water Body., 9 5-10 9.5.2.2.4 Consumption of Water. 9 5-10 9.5.2.2.5 Chemical Discharge to Ambient Air 9 5-11 9.5.2.2.6 Salts Discharged from Cooling Tower.. 9. 5-11 9.5.2.2.7 Chemical Contamination of Ground Water (Excluding Salts) 9. 5-11 9.5.2.2.8 Radiological Effects. 9. 5-11 9.5.2.2.9 Fogging and Icing. 9. 5-11 9.5.2.210 Raising/Lowering of Ground Water Levels 9. 5-11 9.5.2. 2. 11 Ambient Noise. 9. 5-11 9.5.2. 2. 12 Aesthetics. 9. 5-11 9.5.2.2.13 Permanent Residuals of Construction ActlVlty o, o o o ~

~ ~ o o o o o 9 5-11 9.5.2.2.14 Combined, or Interactive Effects., 9. 5-12 9.5.3 Wet, Cooling Tower Systems 9. 5-12 9.5.3.1 Economics of Wet Cooling Tower Systems 9 5-14 9.5.3.2 Environmental Considerations of Wet Cooling Tower Systems. 9. 5-14 9.5.3.2. 1 Heat Discharged to Water Body.. 9. 5-15 9.5.3.2.2 Effects of Intake Structure on Water Bod 9. 5-15

(CONTEND)

TABLE OF CONTENTS Section Title Pacae.

9.5.3.2.3 Chemical Discharge to Water Body. 9. 5-16 9.5.3.2.4 Consumption of Water. 9. 5-16 9 5.3.2.5 Chemical Discharges to Ambient Air 9. 5-17 9.5 3.2.6 Salts Discharged from Cooling Tower. 9. 5-17 9.5.3. 2.7 Chemical Contamination of Ground Hater (Excluding Salts) 9 5-18 9.5.3.2 8 Radiological Effects. 9. 5-18 9.5.3.2.9 Fogging and Icing. 9. 5-19 9.5.3.2. 10 Raising/Lowering of Ground Water Levels 9. 5-20 9.5.3.2.11 Ambient Noise. 9. 5-20 9.5.3. 2. 12 Aesthetics. 9. 5-21 9.5.3. 2. 13 Permanent Residuals of Construction Actlvlty

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.'5;5 't8ofing Pd system 9.5.5.1 Economics of the Cooling Pond 9. 5-23 9.5.5.2 Environmental Considerations of the Coolin P ond e 0 0 Q 0 0 9. 5-23 9.5.5.2.1 Effects on Water Body 9. 5-24 9.5.5.2.2 Consumption of Water 9. 5-24 9.5.5.2.3 Chemical Discharge to the Ambient Air 9. 5-24 9.5.5.2.4 Salts Discharged from a Cooling Tower 9. 5-24 9.5.5. 2. 5 Chemical Contamination of Ground Water (Excluding Salt) . 9. 5-24 9.5. 5. 2. 6 Fogging and Ic ing. 9. 5-24 9.5.5.2.7 Raising/Lowering of Ground Water. 9. 5-25 9.5.5.2.8 Ambient Noise 9. 5-25 9.5.5.2.9 Aesthetics 9. 5-25 9.5.5.2.10 Permanent Residuals of Construction Actlvlty e

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o o 9. 5-25 9.5.5.2.11 Combined or Interactive Effects. 9. 5-25 9.5.6 Spray Pond System . 9. 5-26 9.5.7 Supplemental Cooling System. 9. 5-26 9 6 ALTERNATIVE CHEMICAL EFFLUENT SYSTEMS 9. 6-1 9.6. 1 Existing Chemical Effluent System. 9. 6-1 9.6. 1. 1 Economics of Existing System- 9. 6-1 9 6.1.2 Environmental Considerations of Existing System. 9. 6-1 9.6.2 Evaporative Chemical Effluent System. 9. 6-3 9.6.2. 1 Economics of Evaporative Chemical Effluent Systems 0 . 0 . . I 0 Q Q 0 0 0 9. 6-3 9.6.2.2 Environmental Considerations of this System. 9. 6-3 9.6.2.2. 1 Chemical Discharge to Hater Body. 9. 6-4 9.6.2.2.2 Consumption of Water. 9. 6-4 9.6.2.2.3 Chemical Contamination of Ground Water (Excluding Salts) 9 6-4 Fogging and Icing. 9. 6-4 Ambient Noise 9. 6-4 Aesthetics 9. 6-4 X3.

TABLE OF CONTENTS (CONT'D)

Section- Title. Pacae.

9.6.2.2.7 Activity................

Permanent Residuals of Construction or Interactive Effects.....

9. 6-4 9.6.2.2.8 9 7 9 8 Combined ALTERNATIVE RADWASTE SYSTEMS ALTERNATIVE STATION DESIGNS

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9 7-1 8-1 9.8.1 Existing Power Station Design . 9. 8-1 9 8.1.1 Benefits of Existing Design . 9. 8-1 9.8.1.2 Economics of the Existing Power Station 9. 8-3 9.8.1.3 Environmental Considerations of Existing DeslgnO ~ 0 . 0 ~ 0 i i ~ 0 0= 9. 8-3 9.8. 1.3. 1 Heat Discharge to Water Body ..

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9. 8-3 9.8. 1.3.2 Effects of Intake Structure on Water Bod 9. 8-3 9.8.1.3.3 Chemical Discharge to Water Body., 9. 8-3 9.8.1.3.4 Consumption of Water. 9. 8-4 9.8.1.3.5 Chemical Discharge to Ambient Air 9. 8-4 9.8.1.3. 6 Salts Discharged from Cooling Towers 9. 8-5 9.8.1.3.7 Chemical Contamination of Ground Water. 9. 8-5 9.8.1.3.8 Radiological Effects. 9. 8-5 9.8.1.3.9 Fogging and Icing. 9. 8-5 9.8.1.3. 10 Raising/Lower of Ground Water Levels 9. 8-5 9.8.1. 3. 11 Ambient Noise. 9 8-5 9.8. 1.3. 12 Permanent Residuals of Construction Actlvlty

~ e o i o o e o o o o ~ ~ 9. 8-5 9.8. 1. 3. 12 Aesthetics. 9. 8-5 9 1. 3.. 13 Permanent Res iduals of Construction Activity . 9. 8-6 9.8. 1. 3. 14 Combined or Interactive Effects.. 9 8-6 9.8.2 Station Design Considered to produce Minimum Water Impact. 9. 8-6 9.8.3 Station Design Considered to Produce Minimum Land/Air Impact. 9 8-7 9.8.4 Station Design Considered to Produce Minimum Overall Environmental Effect 9 8-7 10 LONG-TERM EFFECTS OF STATION OPERATION 10.0-1 11 IRREVERSIBLE AND IRREZRIEVABLE COMMITMENTS 11.0-1 12 ENVIRONMENTAL APPROVALS AND CONSULTATIONS 12 0-1 LIST OF REFERENCES APPENDICES A Industrial Firms in Oswego County. A-1 B Inventory of Game Species in Oswego County. B-1 Xll

TABLE OF CONTENTS (CONT~ D)

Section Title Pacae.

C Inventory of Historic, Natural, and Scenic Sites in Oswego County 0 0 . 0 . 0 ~ I 0 0 0 0 C 1 D Meteorological Data Summaries at Nine Mile Point Nuclear Station ~ o o ~ e i o o o o E Plant and Animal Species Observed at Nine Mile Point Nuclear Station F Studies Conducted as Part of Nine Mile Point Lake Surveillance G Regulatory and Review Procedures Documents G-1 H Thermal Effects of Heated Discharges on Lake Ontario. H-1 I Meteorological Calculations for Assessing Environmental Ef fects of Accidents

LIST OF FIGURES After

~Fi ure Title. Pacae ..

Frontispiece 1e 1 1 e ~ ~ ~

Plot Plan.

e lli 1e 1 2 2e 1 1 Location Map. ~ ~ e 2e 1 1 2e 1 2 Site Vicinity Map . 2e 1 1 2e 1 3 Transportation Map. 2e 1 2 2e 2 1 Economic Viability of Farm Areas 2e 2 2 2e2 2 Future Land Use 2e 2 2 2e 2 3 Study Area'ap 2e 2 2 2 2-4 Aerial View of Nine Mile Point 2e 2 3 2 2-5 1970 Population within 50 Miles e e e 2. 2-4 2.2-6 Population Distribution 5 Mile Radius 2. 2-5 2 4-1 Regional Geologic Map Showing Physiographic provinces 2. 4-1

2. 5-1 Average Monthly Temperature of Lake 2. 5-2

2. 5-2 Lake Ontario Dominant Circulation Patterns. 2. 5-4

2. 5-3 Public Water Supplies in Vicinity of Site 2. 5-4

2. 5-4 Private Water Wells Near Site 2. 5-4

2. 6-1 Average Wind Rose . 2. 6-1 2e7 1 Vegetation Categories. 2e 7 1 2 8-1 Lake Sampling Transects and On-Site Radio-logical Monitoring Stations . 2. 8-4

2. 8-2 Off-Site Radiological Monitoring Station Locations 2. 8-4 3e 2 1 Transmission Facility Map 3' 2 1 3e 2 2 Photographs of Transmission Line Right Of Way e e e e e e e e e ~ ~ 3e 2 1 3e 2 3 Photographs of Transmission Line Right of Way e e e e e ~ e e e e e 3e 2 1

3. 2-4 Transmission Line Structures North of Clay and Typical Vegetation Growt 3e 2 2 3e 3 1 Simplified Diagram, Nuclear Boiling Water Reactor Station . 3e 3 1

3. 4-1 Water Usage Flow Diagram. 3. 4-1 I

3. 5-1 Plan Circulating Water System. 3. 5-1

3. 5-2 Profile Circulating Water System 3 5-1 3 5-3 Intake and Discharge Structures Details. 3. 5-1

3. 5-4 Schematic Digram of Screenwell. 3. 5-2

LIST OF FIGURES (CONTEND)

A fter

~Pi ere Title Pacae

3. 6-1 GaseousRadwaste System Flow Diagram, Original System Design e e e e e 3e6 4

3. 6-2 Gaseous Radwaste System Flow Diagram, Upgraded 3 6-3

System Design

Liquid/Solid Radwaste System ee ceo Flow Diagram, 3e65 Original System Design . e 3 6-7 3 6-4 Liquid/Solid Radwaste System Flow Diagram, Upgraded System Design 3. 6-7 3e7 1 Makeup Water Treatment System..... 3.7-1 5- 1-1 Basic Mechanism of Dilution and Flow Patterns. 5. 1-3 5 1-2 Nine Mile Point Unit 1 Three-Dimensional Thermal Survey Surface Temperatures C, 7/13/71 5. 1-4

5. 1-3 Nine Mile Point Unit Three-Dimensional Thermal Survey Surface Temperatures C, 7/23/71 5. 1-4

5. 4-1 Sound Level Measurement Locations. 5. 4-3

5. 4-2 Sound Pressure Levels. 5. 4-3

5. 4-3 Travel Time vs Lake Current. 5. 4-7

5. 4-4 Dilution Factor vs Lake Current 5. 4-7 5 5-1 Lake Sampling Transects and On-Site Radio-logical Monitoring Locations 5. 5-1 951 Separate Diffuser Discharge. 9. 5-8

9. 5-2

9. 5-3 t

Mechanical Draf Cooling Tower Scheme Natural Draft Cooling Tower Scheme

9. 5-8

9. 8-13

9. 5-4 Mechanical Draft Cooling Tower Plume. 9. 5-19

9. 5-5 Natural Draft Cooling Tower Plume. 9. 5-19 9 5-6 310-Foot Elevation Cooling Lake Site. 9. 5-27.

9. 5-7 Supplementary Cooling Tower Effect on Circulating Water Discharge Temperatures 9. 5-27

9. 6-1 Scheme for Evaporative Treatment of Regeneration Wastes 9. 6-3 xv

LIST OF TABLES Table. Title Pacae-1e 2 1 Niagara Mohawk Power Corporation Winter 1971 Maximum Power Capabilities, (MW) 1- 2-1 2 2 Niagara Mohawk Power Corporation Predicted Power Supply Capabilities for Winter 1972-1973, Mw 1. 2-2 2e 2 1 Population of Oswego and Neighboring Counties (Thousands); 2. 2-4 2o 2 2 Oswego County Population. 2. 2-5 2e2 3 Location and Enrollment of Schools in Oswego County . 2. 2-7

2. 5-1 Lake Ontario Water Quality Data . .. . . 2. 5-3 2 5-2 Public Water Supplies . . . . .. . ., 2. 5-4

2. 5-3 Private Water Supplies . . . .. .. . . 2. 5-5 2 6-1 Average Temperature, Humidity, and Precipitation at Nine Mile Point 2. 6-2

2. 6-2 Annual Stability Frequency of Occurrence with respect to Wind Direction, Percent 2. 6-4

2. 6-3 Percent Occurrence of Total Observations 2. 6-5 2e7 1 Provisional Maximum Temperatures Recommended as Compatible with the Well-Being of Various Species of Fish and Their \

Associated Biota e e e ~ e o e e 2e7 6 2 8-1 Preoperational Environmental Monitoring Program Samples.and Analyses 2 8-1 2 8-2 Sample Collection Analysis 2. 8-2 2 8-3 Nine Mile Point Aquatic Sample Radloanalyses 2 8-S

2. 8-4 Radiation Dose Measured at Environmental Sampling Diagrams. 2. 8-9

2. 8-5 Gross Beta Activity of Precipitation Samples e e e e e ~ e ~ e e e e 2 8-9

2. 8-6 Environmental Air Sample Gross Beta ACtlVltleS e e e e e e e e e e 2 8-10

3. 6-1 Estimated Quantities of Fission-Product Isotopes Released to the Environs from the Offgas Processing System . . . .. . 3. 6-3

3. 6-2 Fundamental Liquid and Solid Radwaste XVl

LIST OF TABLES (CONT'D)

Table- Title Pa<ac System 0 0 3. 6-11 3 6-3 Concentration for Significant Isotopes in the Discharge Tunnel from Nine Mile Point Unit 1 for both the Original and the Upgraded System 3. 6-19 3 6-4 Solid Radioactive Waste Shipping Information 3. 6-26 3& 7 1 Chemical Discharges from Makeup Hater Treatment 3. 7-4 Effect of Entrainment on Fish Larvae

5. 1-1

5. 2-1 Station e e ~ 1...

Population for Nine Mile Point Nuclear 0

Summary of Dose Calculations for an 0 0 0 ~ 5. 1-9 Individual (mrem per year) . 5. 2-4

5. 2-2 Recreational Population Exposures, mrem/yr. 5. 2-6

5. 2-3 Equilibrium Levels in Lake Ontario for the Continuous Discharge of Radionuclides 5. 2-8

5. 2-4 Population Exposure from Nine Mile Point Unit 1 Liquid Releases 5. 2-9

5. 2-5 Summary of Doses to Biota in the Ma.xzng Zone 5. 2-10 5 2-6 Tritium Release Data . 5. 2-12

5. 2-7 Gas Release Rates from Nine Mile Point Unit 1 and Calculated Whole Body Dose Rate at One Miles East of Stack . 5. 2-14 5 2-8 Individual Exposure Estimates (mrem/year) from Site Effluent Releases for Upgraded Unit 1. 5. 2-16

5. 3-1 Chemical Discharge from Makeup Water Demineralizer Regeneration . 5. 3-2

5. 4-1 Comparison of Ambient and Maximum Transformer Noise at Measurement Sites for Unit 1, Decibels, A Scale, Re 0.0002 . 5. 4-4 6 2-1 Summary of Population Exposure from Natural and Man-Made Background Compared with Nuclear Radiological Effects 6. 2-3 9 5-1 Cost Description of Alternative Cooling Systems 9. 5-28

9. 6-1 Cost Description of Alternative Chemical Effluent Systems 9. 6-6

(CONTEND)

LIST OF TABLES Title Pacae Benefit Description of Alternative Station Designs 9. 8-9 Cost Description of Alternative Station Desiqns 9. 8-10 Regulatory and Review Procedures . 12.0-2 I

SECTION 1 INTRODUCTION Nine Mile Point Nuclear Station Unit 1 is owned and operated by Niagara Mohawk Power Corporat,ion of Syracuse, New York.- The station is located on the south shore of Lake Ontario in the Town of Scriba, Oswego County, New York. The station site is approximately 7 miles northeast of the city of Oswego, New York, 36 miles northwest of Syracuse, New York and 135 miles east of Buffalo, New York.

Unit 1 is a boiling water reactor (BWR) licensed for operation at 1,850 thermal megawatts (MWt) and approximately 610 megawatts net electric (MWe) output from the station. The station has been in operation since December 1969 and has generated approximately 4,858,000,000 kilowatts of electricity through December 31, 1971, for 1.24 million electricity customers in the Niagara Mohawk electric service area comprising 24,000 square miles of upstate New York.. As of December 31, 1971 construction costs including construction modifications have totalled $ 164,492,000.. To date, environmental surveys of the Nine Mile Point site have cost about

$ 400, 000..

Nine Mile Point Unit 1 site shares a common site boundary with the Power Authority of the State of New York (PASNY) whose James A. FitzPatrick Nuclear Power Plant is presently under construction about 3,300 feet to the east of Unit 1, and will generate 821 MWe of electricity (Ref. 1+). It will utilize once-through cooling discharging into a submerged high velocity diffuser.

An additional nuclear-fueled unit, known as "Nine Mile Point Unit 2," has been proposed by Niagara Mohawk for location on the Nine Mile Point site adjacent to Unit 1. Proposed Unit 2 would have an electrical generating capacity of 1, 100 MWe and a rated thermal output from the reactor of 3,300 MWt. The two Niagara Mohawk units and the Power Authority's FitzPatrick Plant will be operated by Niagara Mohawk.

1 1 DESCRIPTION OF OPERATING STATION AND SITE Unit 1 consists of a General Electric direct-cycle boiling water reactor which produces steam at 1,000 psig for use in a steam-driven turbine generator. The station rejects heat from the steam condenser by employing a once-through circulating water system. Water is withdrawn from Lake Ontario, passed through the condenser, and discharged to the lake through a submerged

~References are given in the bibliography following Section 12 at the end of this report.

discharge system. With the construction of proposed Unit, 2 the circulating water system for Unit 1 would be modified to a combined discharge for both units.

The Unit 1 site comprises about 900 acres of partially wooded land. Of these 900 acres, about 45 are occupied by the unit and its auxiliary systems. The successfulcan blending of these structures into the surrounding area be seen in the frontispiece. Figure 1. 1-1 shows a plot plan of the site.

The site is generally a flat featureless plain with .a maximum elevation of 310 feet at. the, southern extremity. Unoccupied portions of the site consist of natural growth providing a variegated habitat for diverse species of wildlife. The surrounding area has a permanent population of fewer than 200 persons living within a two-mile radius of the site.

" II 1 2 NEED FOR LOCATING THE POWER STATION AT THE SITE During 1971, Niagara Mohawk's peak load was 4,551 megawatts (MW) and was met by an electric supply system consisting of installed capacity and power purchases as described below:

Table 1.2-1 Niagara Mohawk Power Corporation Winter. 1971 Maximum Power Ca abilities. MW Conventional Thermal Plants 2,395 Gas Turbine and Diesel Plants 371 Nuclear Plant 610 Hydro Plants 627 Purchase from Power Authority 1,352 Purchase from Others 316 Total 5,671 1971 Winter Peak Load 4,551 Installed Reserve Capability, MW 1~120 Installed Reserve Capability, percent 24. 6 The usage of energy supplied to customers of Niagara Mohawk in its f ranchised territory was as follows: residential 27 percent, commercial plus industrial 61 percent, and others, including municipalities, street lighting, towns and schools 12 percent.

In 1972, Niagara Mohawk's peak load is expected to increase to 4,910 MW, a load growth of 359 MW from 1971. This projection is conservative in that it does not include speculative additions which might appear through demands for service by new, large industries.

Niagara Mohawk's generating resources in 1972, including firm power purchases and new generating capacity will total 6, 110 MW with Nine Mile Point Unit 1 in service, and 5,484 MW with Nine Mile Point Unit 1 not in service. The new generation is Niagara Mohawk~s 240 MW portion of the Roseton Station. An additional capacity purchase of 275 MW is expected from the Blenheim-Gilboa pumped storage station which is now being developed by the Power Authority of the State of New York. No retirements of any substantial generating facilities are contemplated in the near future. The load and capacity data described above are included in Table 1.2-2.

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With Nine Without Nine Mile-Unit.4 Mile. Unit 1..

Conventional Thermal Plants 2i 635 (1) 2,635 (1)

Gas Turbines 8 Diesel Plants 371 (2) 365 (2)

Nuclear Plants 610 0 Hydro Plants 627 627 Purchase from Power Authority 1i 601 (3) 1i 601 (3)

Purchase from Others 256. 256 6 ~ 100 5i086 1972 Winter Peak Load 4,910 4~910 Installed Reserve Capability, MW 1i190 574 Installed Reserve Capability, percent 24 2 11. 7 (1) Includes Niagara Mohawk5s share (240 MW) of Roseton Plant (2) Includes 6 MW NMP Unit 1 Diesel (3) Includes 275 MW share of Blenheim-Gilboa Pumped Storage Plant The aim of the New York Power Pool member companies is for each member to attain an installed generating capacity reserve of at least 18 percent to allow proper margin for reductions in capability caused by forced outages, maintenance, or daily partial deratings. As indicated in Table 1.2 2, Niagara Mohawk s resources without Nine Mile Point Unit 1 are clearly inadequate because they would provide an installed reserve of only 574 MW, a margin of 11.7 percent. With Nine Mile Point Unit 1 in service, Niagara Mohawkls installed reserve in 1972 would be 24.4 percent enabling it to provide reliable electric service. Loss of this unit would have 8 serious effect on Niagara Mohawk's ability to meet its obligations in 1972 and beyond.

Niagara Mohawk chose to construct and operate a nuclear generating unit at the Nine Mile Point location for several reasons Among these were the excellent environmental characteristics of 'the site, including absence of seismic activity; superior meteorological ventilation; scarcity of population and land use activities; and the abundance of cooling water. Surveillance programs at the site, both before and after operation of the generating unit, have verified these factors and confirmed the minimum impact on the environment caused by these factors. The site also has ready access to the high-voltage cross-state transmission system company s franchise territory, thus It is at the mid-point of the providing a central location from which transmittal of the unit output can be directed to the 1w2 2

three ma jor metropolitan load centers served by the company:

Buffalo, Syracuse and Albany.

Niagara Mohawk and the other members of the New York Power Pool (Central Hudson Electric and Gas Corporation, Consolidated Edison Company of New York, Inc., Long Island Lighting Company, New York State Electric and Gas Corporation, Niagara Mohawk Power Corporation, Orange and Rockland Utilities, Inc., Rochester Gas and Electric Corporation, and the Power Authority of the State of New York) coordinate p3.ans for expansion of power supply facilities based on the Northeast Power Coordinating Council "BASIC CRITERIA FOR DESIGN AND OPERATION OF INTERCONNECTED POWER SYSTEMS." Under this criterion, new generating capacity is planned such that the probability of loss of. load under contingency conditions would not exceed one weekday in ten years.

The Nine Mile Point Unit 1 is an integral part of the New York Power Pools~ plan for meeting this criterion on a total Pool basis.

The foregoing demonstrates that the Nine Mile Point Unit 1 is vital to Niagara Mohawk~ s ability to meet conservative projections of its power demands in 1972 and beyond and is also an integral part of the New York Power Pool's plan to meet generating supply reliability criteria in use by the Pool and other areas of the Northeast Power Coordinating Council.

Retirement of this unit would therefore have an adverse impact on the pcwer supply situation throughout this region.

1 & 2 3

SECTION 2 THE SITE 2~ 1 LOCATION OF STATION

2. 1. 1 Pro ject Site The project site comprises about 900 acres and is located on the south shore of Lake Ontario in the town of Scriba~ Oswego county, New York, on land owned by the Niagara Mohawk power corporation.

The Nine Mile Point Nuclear Station Unit 1, including all Unit 1 buildings, switchyards, Progress Center, parking areas, access roads, and associated facilities, occupies about 45 acres of the total site acreage. The James A. FitzPatrick Nuclear Power Plant, which is currently under construction for the Power Authority of the State of New York, is located on a 700-acre plot immediately east of the project site. Centerline-to-centerline distance between Unit 1 and the FitzPatrick plant is about 3,300 feet.. Most of the land immediately to the south and west of the site is pasture or inactive farm land. The Ontario Bible Conference operates a summer camp on the lake'ront adjacent to the western boundary of the site. The general and specific locations are shown in Figures 2. 1-1 and 2.1-2.

The nearest. population center is the city of Oswego, 7 miles southwest of the site. The site is 36 miles northwest of Syracuse and 135 miles east of Buffalo. Other towns and points of interest are shown on the map in Figure 2.1-2.

The nearest significant manufacturing facility to the Nine Mile Point site is the Alcan Aluminum Corporation with about 750 employees; it is located about 3 1/4 miles southwest in Scriba.

The largest manufacturing plants are those of the Nestle Co. and Sealright Co., both located in Fulton about 15 miles south of the site; neither has more than 2,500 employees.

2. 1. 2 Transportation The location of the station on the south shore of Lake ontario places it outside any normal ship traffic lanes associated with vessels traveling on Lake Ontario. Vessels traveling to the Oswego, New York area, the near'est commercial port, pass about six miles from the site.

The station is located about one mile from the nearest public road, County Route No. 29, which forms the eastern boundary of the FitzPatrick plant site. A private hard-surface east-west road bisects the site connecting with Route 29 which extends to Oswego to the west and which connects on the east with U. S.

Highway 104, 3 3/4 miles south of the site. A spur of the Penn-Central Railroad provides rail service to the station.

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2 2 HUMAN ACTIVITES IN THE ENVIRONS 2.2.1 History of Land and Water Use The first Europeans to visit Oswego County were a party led by Samuel de Champlain in 1616, and French missionaries who arrived in the 1650 s.. Forts were built by the British in 1727 (Ft.

Oswego) and in 1755 (Ft. Ontario) . Fort Ontario, in Oswego, was destroyed and rebuilt several times.

recently between 1839 and 1842. It It was rebuilt 'ost remained an Army post until 1945 and is now a state-owned historic site and museum.

The first civilian settlement was begun in 1796.. In 1799 the port of Oswego was established, and in 1816 the area became a County (Chapter 16, Laws of 1816).

The first, incorporated villages were Oswego (1828) which became a city in 1848 and Pulaski (1832) . The newest village is Central Square, incorporated in 1889.

In the 19th century the area was primarily agricultural. The principal products were, and still are, dairy products, poultry and livestock, but the relative importance of agriculture has steadily decreased. The trend in the county since 1880 has been a steady decline in land use for farms and in agricultural employment and a corresponding increase in manufacturing employment. Total population has remained constant until recently. In 1880, there were 7,500 farms covering over 500,000 acres, which was 80 percent of the area. In 1964, which

'was the most recent census of agriculture, there were 1,592 farms covering 210,555 acres, which is 34 percent of the county. In 1880, improved land totaled 356, 564 acres. In 19 64, only 153,532 acres were used for crops or pasture. The number of dairy cattle declined from 37,752 in 1880 to 17,314 in 1964. In the 30-year period from 1935 to 1964, the population living on farms decreased from 22,390 to 6,470. The 1960 census indicated that only 1,643 persons were employed in agriculture, which was 8.4 percent of total employment.

The size, value, and efficiency of remaining farms, however, has increased. The average farm size increased from 67 acres in 1880 to 101 in 1949 and to 132 in 1964; the value of an average farm increased from $ 6,550 in 1949 to $ 18,697 in 1964. Milk yield per person employed in dairying increased more than 50 percent between 1959 and 1966..-

Land use for agriculture in the county is expected to decline further in the future. The State Office of Planning Coordination in a 1969 report on farming in New York State made the following comment about the area:

<<Poor ,s'oil conditions and expanding urbanization from Syracuse have discouraged new investments in farming, 2& 2 1

particularly in dairying. Land in farms will continue to decline more rapidly in thi's region than in the state as a whole.~~

The report noted, however, that there are limited areas of responsive mineral soils and scattered areas of muck land which could be intensively developed. These areas are shown on the map entitled "Economic Viability of Farm Areas in New York State,"

also published by the Office of Planning Coordination, part of which is reproduced here as Figure 2.2-1. There is no such area on or near the site. There is a good supply of land for industrial, commercial, and residential use.. See Map of Future Land Use, Figure 2.2-2.

Much of the land in Oswego County which was formerly farmed is now covered with second-growth trees or brush. Such areas now constitute about half the land in the county. About 37,000 acres are used for commercial forestry.

An inventory of industrial firms in Oswego County was provided by Operation Oswego County, Inc., and is reproduced as Appendix A to this report. The ma jor concentration of industrial facilities lies along the Oswego River in Fulton and Oswego, although other plants are scattered throughout the county.

Manufacturing employment in 1960 was 11,231, which was 57.5 percent of total employment in the county.

Other nuclear facilities within 50 miles of the Nine Mile Point Unit 1 site are the James A. FitzPatrick Plant owned by the Power Authority of the State of New York currently being constructed adjacent to the project site, and the Robert E. Ginna Nuclear Station owned by Rochester Gas and Electric Corp. and located about 50 miles southwest of Nine Mile Point Station. There are no nuclear fuel manufacturing or reprocessing facilities within the 50-mile radius.

Oswego County has' wide variety of recreational and wildlife resources.. See Study Area Map, Figure 2.2-3. Lake Ontario on the north, the Oswego River, Oneida Lake and the New York State Barge Canal in the south, the Salmon River on the north, Salmon Reservoir in the east and the many cold water streams in between, provide areas for water-based recreation. State parks at Battle Island near Fulton and at Selkirk Shores ten miles northeast of the plant site attract over 250,000 visitors a year. Inland, the abundance of wetlands, forested areas and abandoned farmland areas, many of them publicly owned, supplement the county>.

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Most commercial fishing takes place in the extreme northeast section of the lake. United States fish landings are generally dominated by whi,te perch. Eels, bullheads, and carp make up.most of the rest of the catch. Canadian fish landings are dominated by the abundance:

following species, listed in decreasing order of carp, yellow perch, white perch, sunfish, eel, smelt, and bullheads..

The following statistics for 1968 through 1970 fish landings in pounds and dollar value derive from the Fishery Statistics of the United States for 1968, 1969, and 1970, published by the U.S.

Department of Commerce, National Marine Fisheries Service:

~ -Pounds- Thous Value Thous..of-S Year. Ua Sa ~ Canada- Total U.S.. Canada Total 1968 1969 342',009 293 2~272 2~351 2~565 71 44 284 336 355 380 1970 330 2~905 3~235 79 429 508 In the towns of Scriba, where the station is located, and New Haven, which is adjacent, slightly more than half the land is covered with brush or trees. About one-eighth is used for pasture. About one-fifth is farm land, most of which is inactive. Residential, commercial, and industrial uses account for less than one-thirtieth of land usage.

Niagara Mohawk purchased the 1,600 acre Nine Mile Point site for power generation purposes in 1963 and later sold about 700 acres to the Power Authority of the State of New York. Figure 2.2-4 shows aerial photographs of the area in 1963 and with Unit 1 nearly completed. The only other major use in recent years was as an Army artillery post, which occupied a portion of the land until 1957. In addition there were a few cottages, farmhouses, and a restaurant which were removed after the site was purchased.

The site shoreline provides access for sport fishing.. Small-mouth bass, yellow birch, white perch, walleye, bullhead, and northern pike are the principal sport fishes. Since the lake bottom is largely bedrock, and since there are no available beaches, the site is not suitable for swimming. Strong winds and summer thunderstorms make the area near the Nine Mile Point promontory frequently hazardous for small craft. Most of the land area, except for that in the immediate vicinity of the generating station, has recreation possibilities.

The Niagara Mohawk <<Progress Center,<< which shares part of the site west of Unit 1, provides visitor facilities, including educational exhibits, picnic and playground areas, and nature study trails. The Center officially opened in 1967 and has averaged 50,000 visitors annually.

2a 2 3

P NINE MILE POINT l963 cA$ 3 flW H I r

• NINE MILE POINT SHOWING UNIT I FIGURE 2.2-4 AERIAL VIEW NINE MILE POINT

2 2.2 Population The area within, a 50-mile radius of the station site was investigated and found to include. all or part of ten counties in New York State and three counties in the Province 'of Ontario.

The nearest. large settlement is the city of Oswego, centered about 7 miles southwest of the site, with a 1970 population of 23,744. Population distribution based on the 1970 census is shown on Figure 2.2-5.

The population of Oswego County remained fairly constant for the first half of the 20th century. While some towns in the eastern part of the county have shown a decrease in population since 1910, the population increase in the towns near the manufacturing centers of Syracuse (Onondaga Co.,), Fulton, and Oswego has more than offset the decline in the more rural sections of the area.

The county population of 77,181 in 1950 increased 11.6 percent to 86,118 in 1960, and increased another 17.2 percent to 100,897 in 1970.. Projected populations for the area within a 50-mile radius of the Nine Mile Point site during the anticipated life of the plant are given in Table 2.2-1.

Table 2.2-1 Population of Oswego and Neighboring'ounties (Thousands)

--Actual- ' ~ ~ Pro- ected-Count . 1960 1970 1980 ~199". 2000 2010 2020.

Cayuga 73. 9 77 4 82. 6 85 8 89 6 94 4 99 3 Jefferson 87.8 88 5 91 4 93. 5 96. 6 100.2 104. 5 Lewis 23.2 23. 6 23 3 22. 9 22 9 23. 1 23. 3 Madison 54. 6 62.9 75. 1 85. 1 102 3 124. 0 150 2 Oneida 264. 4 273 0 289 9 301-2 337 2 378 2 425 9 Onondaga 423.0 472 2 525. 8 597. 4 684. 7 779. 5 889. 3 Ontario 68. 1 78 8 94. 9 111. 4 122 8 135 7 149. 8 Oswego 86. 1 100. 9 118. 6 134 4 157. 1 185 1 218. 4 Seneca 32.0 35. 1 37 0 40.5 42 4 44 1 46. 0 Wayne 68.0 79 4 97. 3 117-1 139. 7 167.2 200. 9 The population for 1960 and 1970 are from U.S. Census Bureau data. The 1980 and 1990 statistics are from provisional population estimates made by the State of New York Office of Planning Coordination. The statistics for the years 2000, 2010, and 2020 are computed from provisional estimates and percentage increases obtained from "Demographic projections for New York State Counties to 2020 A.D.,~~ published by the Office of planning Coordination. Population figures from 1910 to 1970 for cities and towns in Oswego County are given in Table 2.2-2.

The land area within five miles of the station lies within the towns of Scriba and New Haven and the city of Oswego. Both the site and the adjacent land east of the site, which is owned by

2. 2-4

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SCNCCA LAKE KCVKA LAKC FIG UR E 2.2- 5 I 970 POP U LATION WITHIN 50 MILES

the Power Authority of the State of New York, are uninhabited.

The nearest dwellings are on Lakeview Road approximately one mile southwest of the station. The population distribution within five miles of the station is shown in Figure 2.2-6 on a polar grid with 1-.mile radial increments., The number of people living within each grid segment was determined by surveying the number of dwellings, in 1971. The average number of people per dwelling was calculated for the town of New Haven from the 1970 census population count and the total number of dwellings in the town as given by the Oswego County Planning Board map of residential land use of November 1970.. This information gave 3.57 people per dwelling, which generally agrees with the Oswego School District estimate of 3.5. Because the dwelling types of the entire area within the 5-mile circle are very similar, this value of 3. 57 was used throughout the area.

Table 2.2-2 Oswego County Population Annual 5 Increase Town- 1940 1960 ~

1970 ~ 1910-1970-Albion 1,472 1i 094 1,125 1,452 Decrease Amboy 736 493 524 557 Decrease Boylston 667 365 293 276 Decrease Constantia 2i023 1,538 2, 730 3,547 1.75 Fulton City 10i480 13i363 14'61 14,003 1 ~ 34 Granby 2i 022 2~220 3~704 4 718 2 33 Hannibal 2i148 2,010 2,673 3, 165 1.47 Hastings 2,315 2,361 4~457 6i042 2 61 Mexico 2i982 2~710 3,435 4~ 174- 1.40 Minetto 1i052 1i290 1i688 New Haven 1,461 1,194 1i478 1i 845 1.26 Orwell 929 806 663 836 Decrease Oswego Town 2i 671 Ig972 2,796 3i583 1.97 Oswego City 23,368 22i062 22'55 23'44 0.03 Palermo 1,255 1i148 1i663 2S321 1.85 Parish 1s311 1r 199 1i 439 1,782 1.36 Redfield 803 517 388 386 Decrease Richland. 3i 791 3,848 4,554 5i324 1 40 Sandy Creek 2~106 1~821 2i 506 2i 644 1. 25 Schro eppel 2i 707 3i219 5 i 554 7i153 2.64 Scriba 2i199 2i 184 2e 489 3i619 1.65 Volney 2,407 2,659 3, 785 4i 520 1.88 West Monroe 915 731 1i 417 2i535 2 77 Williamstown ~ ~

896 ~

710 739 ~ ~ 883= Decrease Total 71i664 71,275 86~ 118 100~ 897

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FIGURE 2.2-6 I I

SCALE-MILES POPULATION D ISTRIBUTION-5 Mll E RADIUS

In addition to the year-round population displayed in Figure 2.2-6, there is a weekend and vacation populati.on that occupies the few cottages along the lake-shore in the warmer months. A sunmer camp is operated on a 12-acre plot known as Lakeview located outside the station site and about 4,500 feet to the southwest of the station. Groups of up to 500 persons use this camp and as many as 1,500 people may gather there for short periods on Sundays. The facility is unused the rest of the year except for an occasional weekend in the spring and fall There are two hospitals in Oswego County. The Oswego Hospital, located seven-miles southwest of the plant site at 110 West Sixth Street, Oswego, presently has 176 beds and will soon open a 38-bed extended care unit. The Lee Memorial Hospital, with 60 beds, is located 14 3/4 miles south of the plant on South Fourth Street, Fulton. Oswego County formerly maintained a sanitarium in Orwell, but this facility is now a private institution for alcoholic s.

Oswego County is divided into nine public school districts.

There are also two parochial schools in Fulton and four in Oswego, and the State University College at Oswego maintains a nursery through eighth grade school on its campus where its education students may practice teaching. The State itself has 8,650 students, of which 6,000 are full-time andCollege 4,000 are residents.

Student enrollment of Oswego County schools for 1971-72 and school location relative to the Nine Mile Point site (approximate 30-mile radius) are given in Table 2.2-3. Total enrollment is 37,817 students.

2. 2-6

H 4

H s'1 7

Table 2% 2 3 Location and Enrollment of Schools in Oswego County Distance (Miles) and School- Direction*from-Station. Enrollment.

Altmar .. - ~

Parish - ~ Williamstown -

District.

Altmar Elementary 21 E 322 Parish Elementary 16 ESE 377 Williamstown Elementary 27 ESE 133 A.P.W. Middle High 19 ESE 869 Central- S uare- District-Paul V. Moore High 20 SE 1,255 Millard W. Hawk Junior High 21 SE 806 Central Square Elementary 21 SE 544 Brewerton Elementary 23 SSE 568 Hastings-Mallony Elementary 19 SE '86 Anna A. Cole Elementary 32 SE 599 Main Street 21 SE 387 Fulton District-G. Ray Bodley High 15 S 1~ 460 Erie Street 14 S 217 James R. Fairgrieve 13 S 655/

Fourth Street 14 S 52 James E. Lanigan 15 S 311 Oak Street 14 S '70 Phillips Street 14 S 475 State Street 13 S 154 Volney Elementary 13 S 543 Walradt Street 13 S 89 Fulton Junior High 13 S 810 Hannibal District.

Fairley Elementary 16 SSW 555 Cayuga Street 16 SSW 403 Hannibal High 16 SSW 748 Mexico District-Mexico Academy Junior and Senior High 9. 5 ESE 1, 212 Fravor Road Elementary 8 5 ESE 687 Mexico Elementary 9 5 ESE 474 Palermo Elementary 13 SSE 245 New Haven Elementary 5 0 SE 325 2% 2 7

~ q Table 2.2-3 ~

Cont; Distance (Miles) and Schoo3.- Direction-from. Station. Enrollment.

Oswe 0 - District Oswego High 7.5 SW 1,795 Oswego Middle 75SE 866 Fitzhugh Park 6 0 SW 704 Kingsford Park 75 SW 608 Minetto 10 SSW 450 Charles E. Riley 6.5 sw 743 Fredrick Leighton 7.5 SW 503 Phoenix-District-John C. Birdlebough High 20 SSE 839 Emerson J. Dillon 20 SSE 1i 042 Cherry Street 20 SSE 267 Elm Street 21 SSE 893 Pennellville 18 SSE 192 Pulaski.District-Pulaski Academy and Central 18 ENE 898 Junior-Senior High 14 ENE 570 Sand - Creek. District-Sandy Creek High 19 NE 508 Sandy Creek Elementary 29 E 608

'Arwell Elementary 21 ENE 99 Parochial Schools-Oswego Catholic High 6.5 SW 326 St. Paul s (Oswego)

~ 6 5 SW 312 St. Mary' (Oswego) 72 SW 308 St. John~ s (Oswego) 7.2 SW 139 Fulton Catholic Elementary 13 S 199 Fulton Catholic Middle 13 S 171 State-Universit Colle e at Oswe o Campus School 8 SW 470 College 8 SW 8i650 2 2-8

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2 3 HISTORIC SIGNIFICANCE The Oswego City Library, located on East Second Street, was designated a National Historic Site in the Federal Register of November 2, 1971. The library, given to the city by abolitionist Gerrit Smith in 1855, is of architectural interest and is one of the oldest buildings in continuous use as a public library in the country. At present, there are no other National Historic Sites in Oswego County, although the Oswego Market House, Fort Ontario, and several other sites are being considered for designation. An inventory of natural, scenic, state, and local historic sites furnished by the New York State Historic Trust and the Oswego County Planning Board and a map showing their locations are given in Appendix C to this report. This inventory indicates that there are no designated Registered National Historic. Landmarks in the vicinity of the station site.

The Nine Mile Point site is of no major archeological interest.

The lake-shore beaches and stream-mouths to the east have yielded many relics of prehistoric Indian fishing encampments and villages, but the rocky bluffs of the shore at Nine Mile Point seem to have been inhospitable to settlement (Ref. 2).

2% 3 1

i I ~

2 4 GEOLOGY

2. 4. 1 Topography The Nine Mile Point site is a generally flat featureless plain located on the south shoreline of Lake Ontario.. (See Figures 2.1-1 and 2.1-2.) The site area land elevation ranges from 260 feet at the station area to 310 feet at the southern extremity of the site about one mile distant. The surface soils consist of fill, recent sediments, and glacial till.. Soil depth in the vicinity of the plant area varies from 0 to 23 feet but is generally of the order of 10 to 13 feet. The site topography is a reflection of the irregular bedrock surface. No perennial streams cross the station site. Natural drainage is relatively poor. Water collects in local swales and low areas and the permeability of soil and rock is sufficiently low to prevent rapid'ercolation of water into the ground. Localized bogs and swampy conditions exist in the depressed areas.

2.4.2 Geology The station site area lies within the Erie-Ontario Lowlands Physiographic Province. This province is bounded on the south by the Appalachian Upland, on the east by the Tug Hill Upland and Adirondack Highlands, and on the north by the Canadian Shield.

This is shown in Figure 2.4-1. Strata of the Erie-Ontario Lowland are Paleozoic sediments which are essentially undeformed.

Regional dip is to the south or southwest at an average slope of less than 2 degrees. No folds or faults of any consequence are known in the general site area. The nearest significant fault is the Clarenden-Linden Fault, 90 miles to the west. This fault has a north-south trend with a maximum displacement of approximately 200 feet.

The surface of the site is mostly level, with generally a thin soil till. veneer consisting of These fill, recent sediments, and glacial soils are composed of a mixture of silts, sand, gravels, cobbles and boulders.

The underlying rock is flat-lying sandstone with some interbedded shale.

Sandstone.

It is of Ordovician Age and known as the Oswego (See Figure 2.4-1.) It is not commercially valuable, and there are no mineral deposits of commercial value in or underlying the area. The shale content increases with depth, and at approximately 125 feet below the surface, the Oswego sandstone grades into the underlying Lorraine Group, which is predominantly shale with some sandstone members. The Oswego sandstone is a hard, competent material, well suited for founding of the plant.

It is moderately jointed, the joints being the most common in the upper surficial zone. Below that depth, the joints are much more widely spaced and tight. Identifiable joint sets strike North 69 deg to 80 deg East and North 25 deg to 50 deg West.

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REFERENCE:

IO 0 IO 20 SO 40 50 BASE MAP PRCPARED FROM PORTIONS AERONAUTICAL CHARTS'AKE Dt'DRLD DESCRIPTION KIE Y COLOR ERIC (309) l967y HVDSCN RIVER (3IO) '0<<1 ~ ~ DEVONIAN VNDIFFERENTIATED 4 44 4 0 ~ 1 THRVST FAVLT l967 AND ST ~ LAWRENCE RIVCR (263) SILTS'IDNI'S ~ SANDS'I NE AND L IMCSTONE l967.

I/////g SILVRIANI LIMCSTDNCg SHALEe SANDSTCNEe SALT BEDS NORMAL FAVLT BEDLDSY AND PHYSIDQRAPHY PRCoARED ORDOVICIAN: SHALE St SANDSTCNES AND LIMESTDNES FROM A MAP BY THE VNIVCRSITY OF VNCL*SSIFIED FAVLT THE STATC CF NCW YORK THC STATC CAMBRIAN: SANDS'ICNL AND CVARTZDSE DDLDSTDNE EDVCATIDN DEPT y ENTITLED PRECAMBRIAN: VNDIFFERENTIATCD

~maQa26%a'QhnlRI CX LANDFDRMS AND BFDRDCK BKCLCDY DF N ~ Y STATF l99i ~

GU l<E 2. 4- 1

2. 4. 3 Seismicity The site is located in a region considered seismically inactive.

Earthquake activity within 50 miles of the site has been infrequent and minor and no earthquake damage has resulted.

There" has been no known earthquake epicenter within 50 miles of the site., Most of the reported earthquakes in the area are associated with well defined structural zones. The St. Lawrence River Valley , well to the northeast, beyond the Montreal/Quebec area, and about 135 miles from the site, is extensively faulted and has experienced considerable earthquake activity. The larger

,St. Lawrence Valley shocks were felt in New York State, including the site area. There has been some earthquake activity near Attica, New York, about 110 miles southwest of the site. This is believed to be associated with the Clarendon-Linden Fault. The earthquake of 1929 (Intensity VII-VIII-Modified Mercalli Scale) damaged some structures at the epicenter, near Attica, and may have been perceptible in the vicinity of the site. Some minor earthquake activity, which has not been related to knern geologic structure, has occurred in the vicinity of Buffalo, New York, to the west of, the site. It is likely that these earthquakes result from crustal readjustment in the areas of local stress concentrations associated with rebound of the general area following retreat of the continental glaciers. The closest earthquake (Intensity VI-Modified Mercalli Scale) which caused any damage at its epicenter occurred in 1853 near Lowville, New York, approximately 50 miles east-northeast of the site. Several minor shocks (Intensity generally less than III-Modified Mercalli Scale) have been reported within about 30 miles of the site.

These shocks were relatively insignificant.

2. 4-2

I

'l

2 5 HYDROLOGY Lake Ontario, the easternmost of the Great Lakes, is an international body of water forming part of the border between the United States and Canada. The lake is 193 miles long and 53 miles wide at its widest point, and has a surface area of 7,340 square miles (4.7 million acres) . It has a maximum depth of 802 feet, an average depth of approximately 283 feet, and a volume of 393 cubic miles or 1.34 billion acre-feet.

Inflow into the western end of Lake Ontario averages approximately 205,000 cubic feet per second (cfs). Runoff directly into Lake Ontario from 27,300 square miles of watershed in New York State and the province of Ontario amounts to an additional 36,000 cfs. The main feeder is the Niagara River; the other largest rivers draining into the lake are the Genesee and the Oswego from the south shore, the Black River from the east shore, and the Trent River from the north shore. The combined outflow from the lake via the St. Lawrence River averages about 241,000 cf s.

The average annual precipitation in the site area is about 36 inches. It is estimated that approximately 18 inches is directly attributed to run-off as stream flow. Of the remaining 18 inches, approximately 16 inches is lost to evaporation from land and water surfaces and transpiration by plants. These two processes are generally referred to together as evapotranspiration. The remaining two inches are available for groundwater recharge. The relatively high run-off can be attributed to the low permeability of the glacial soils and rock forma lions.

During winter, ice cover forms in the slack water bays but the lake itself is seldom more than 25 percent ice-covered and mostly in the eastern end of the lake only. Lake Ontario's outflow river, the st. Lawrence, is ice-covered from late December until the end of March, all the way from the lake to the International Boundary at Massena, New York.

Prior to the beginning of flow regulation, the elevation of the lake surface was controlled by a natural rock weir located about 4 miles downstream from Ogdensburg, New York in the Galop Rapids reach of the St. Lawrence River. The 111 year record of the U.S.

Lake Survey from 1860 to 1970, indicates a mean lake surface elevation of 246.00 feet above mean tide at New York City, 1935 datum.+

Over this period, the maximum monthly lake surface elevation was 249.29 feet and the minimum was 242.68 feet, a range of 6.61 feet. The annual range of elevations varies between 3.58 and 0.69 feet.

~All elevations in this report are referred to the U.S.

Lake Survey 1935 Datum To convert elevations to 1955 International Great Lakes Data, subtract 1.23 feet

2. 5-1

Dams on the St. Lawrence River, under the supervisory authority of the International St. Lawrence River Board of Control, are now used to regulate the lake level. The lower limit is set for E1..244 on April 1 and is maintained at or above E1..244 for the navigation season (April 1 to November 30) . The upper limit of the lake level is El. 248.

The Nine Mile Point site is at ground elevation 260 with the maximum flood level at elevation 263. This level is the result of adding the wave run-up and the wind set-up that would occur during a storm having a return interval of once in 10,000 years to the maximum controlled still water level. The existing dike on the lake shore would protect the unit from this flood. The maximum flood level in the screenwell was determined to be El.

252.5 from adding the maximum short-term risk occurring in 10,000 years to the maximum controlled still-water level. Waves will not affect the screenwell water level due to the slur response time of the intake and discharge tunnels. Essential station equipment will be located so that extreme water levels will not affect its operation.

The minimum water level at the site is elevation 236.5. This was determined by superposing the hypothetical minimum still water level occurring in the absence of the power and seaway projects existing on the St. Lawrence River and the once-in-10,000 yr instantaneous lowering of the still-water level due to the maximum probable seiche on the lake.'hese maximum and minimum elevations were determined by analytic and statistical methods.

Water surface set-up and seiche are produced by winds and atmospheric pressure gradients. These short-term lake fluctuations are generally of less than two feet amplitude for 10- to 16-year return periods. Winds are directly related to the formation of surface waves, the magnitude of which typically varies between 0 and 15 feet in total height during a given year.

Astronomical tide magnitudes amount to less than one inch.

The New York State Department of Environmental Conservation monitors the water quality of Lake Ontario as drawn into the Oswego City water supply intake 6,500 feet offshore at a depth of 40 feet. The 6-year cumulative record of this monitor is . shown in Table 2.5-1. The average monthly water surface temperature of Lake Ontario is shown in Figure 2.5-1.

As noted in a 1970 International Joint Commission Report, the lake is categorized as being in a stage of eutrophication between oligotrophic and mesotrophic. The inshore waters are more eutrophic than the offshore waters. This condition reflects the shallower depths involved and tne fact that most nutrient inputs, both natural and man-derived, enter along the shores.

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80

~70 0

LU AVERAGE WATER SURFACE

+ 60 TEMPERATURE X

UJ 50 I-X O

>40

+ 30 20 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC F I G UR E 2'.5 I AVERAGE MONTHLY TEMPERATURE OF LAKE ONTARIO

e

• Table 2.5-1 Lake Ontario Water Quality Data Recorded at Oswego, New York, City Water Intake 6,000 Ft Into Lake at 40 Ft Below Lake Level*

M'aximum No of Record ~ Concentrations.-- Concentrations, Parameter Units ~Sam les of Data Mean Max USPHS.or-NYS=

Hardness (CaCO ) mg/1 54 6/64- 1/7 1 112 146 240 Alkalinity (CaCO ) mg/1 ~16 3/65-11/66 85 94 101 Ammonia, Nitrogen (N) mg/1 54 6/64-1/71 0.0 0.47 1 31 Calcium (Ca) mg/1 54 6/64- 1/7 1 32. 0 44 0 54. 0 Chlorides (Cl) mg/1 54 6/64-1/7 1 3. 8 30 3 55. 5 250 Iron (Fe) mg/1 54 6/64- 1/71 0.0 0 6 .9 0.3 Manganese (Mn) mg/1 54 6/64- 1/7 1 .00 01 .13 0.3 Magnesium (Mg) mg/1 51 9/65- 1/71 4.9 8.9 29. 0 Nitrates (N) mg/1 54 6/64- 1/7 1 0.0 0.14 0. 51 10 Nitrates (N) mg/1 54 6/64-1/71 0.0 0.005 0. 029 Phosphates (PO ) mg/1 54 6/64- 1/7 1 0.0 0.19 1. 65 Potassium (K) mg/1 54 6/64- 1/7 1 .5 1.6 11 4 Sodium (Na) mg/1 54 6/64-1/71 1.0 16.6 45. 0 Sulfates (SO ) mg/1 54 6/64- 1/7 1 13. 0 30 1 50 0 250 pH 71 5/64-1/7 1 7 2 7.9 9 0 Turbidity ft 71 5/64- 1/7 1 5/64- 1/7 1 1.0 8 4 25. 0 Temperature F 70 34 49.3 73 4 Dissolved Oxygen ppm 70 5/64-1/7 1 6.8 10 9 14 4 5-Day BOD ppm 66 5/64-1/71 0.2 1.25 3.0 Color 68 6/64-1/7 1 2 8 5 20 15 Conductivity mmhos 53 6/64- 1/7 1 131 0 306 437 0 Coliform Bacteria No/1 00 70 5/64- 1/7 1 2. 2 56 240 COD Dichromate ppm 51 6/64-1/7 1 0. 2 7-9 28 1 Res. on Evap. (Total) ppm 54 6/64- 1/7 1 128 243 533 Res. on Evap. (Fixed) ppm 51 9/65-1/71 73 135 367 Suspended solid (Total) ppm 51 9/65- 1/7 1 1 10 5 44 Suspended Solid (Fixed) ppm 26 8/66- 1/7 1 0 5.5 17

• Data recorded by New York State Department of Environmental Conservation

Winds are the primary cause of lake currents in Lake Ontario.

Temperature gradients in the lake produce currents of considerably smaller magnitudes. Currents are af fected locally by lake geometry and Coriolis forces. In general, the currents are only a few tenths of a foot per second. The direction of current is variable, depending primarily on the direction, magnitude, and duration of winds. Dominant circulation patterns in the lake are counterclockwise, west to east, past the site as shown in Figure 2.5-2.

On the basis of the annual inflow and outflow of the lake, water should be replaced every eight years. However, because of current, circulation, mixing, and stratification, actual replacement time for 90 percent of the lake water is estimated to be three times as long.

There are 16 public water supplies within 30 miles of the station site, as shown in Figure 2. 5-3 and listed in Table 2.5-2. The city of Oswego and the Onondaga County Water District (OCWD) is draw water from Lake Ontario through a common intake. There one well within 10 miles, three between 10 and 20 miles, and ten between 20 and 30 miles. Most public supplies beyond a 10-mile radius obtain their water from wells drilled into alluvium adjacent to larger streams. All are upgradient from the proposed plant site.

Table 2.5-2 Public Water Supplies 1 Onondaga County Water 9 Phoenix District, OCWD 10 Baldwinsville 2 Oswego 11 Fairhaven 3 Mexico 12 Cato 4 Pulaski 13 Wolcott 5 Fulton 14 Adams 6 Sandy Creek 15 Bed Creek 7 Central Square 16 Constantia 8 Orwell Many of the residents 'in the site vicinity obtain their water supply from dug wells completed in the glacial overburden. These wells normally do not yield more than 5 to 8 gallons per minute.

Some water is obtained from drilled wells that are completed in the upper 5- to 10-foot fractured zone of the Oswego sandstone.

Yields in this material average about. 10 gallons per minute. The nearest known private well is one mile from the site. All private wells within two miles of the site are upgradient from the proposed site. The locations and depths of private water supplies are listed in Table 2.5 3 and shown on Figure 2. 5-4.

2.5-4

} I Jt 'I E

e ~ l

SURFACE VIII III 6IIG6 g.I.

KINGSTON TREJVT RIVER BLACK'IVER TORONTO A

E o 4'- A P

\

NINE MILE POINT

( ~

OSWEGO OSIVEGO RIVER ROCHESTER iVIAGARA RIVER NIAGARA FALLS GEAESEE Rl VER LOWER LEVELS BOTTOM FIGURE 2.5-2 LAKE ONTARIO DOMINANT CIRCULATION PATTERNS

I 'el a eevlfv 0 sao TIr eo

$4

• He 0

~pSmlt li~ E Rodma ok Har He erson Conte Stony PL

'ts Be evil!4 skI v ~

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~ Maple View 4 I 0

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stanti /

/

Fai ave Panrker Fult n <t Lake~

IHa Maikwy snnlbal Gayvlll l annlbal ennellvg rI Central Squaro tto ntsr a W Mon Ile OBowens Cs ghde H v AN Cents I 0 I Come hsnS Bay 1 Be Constanti Creek 20 I LE gHI olcott Wostbury Pro I Victory y

l o Lysandef < ere ~

n

~a.

i o Throe Rivers 0 y

/

Cleveia 4

lglu Euclid 0 JAerldlsn Cicero ro aldwln Center oRose I Ills Bridge port Pr S Butler rl g 4r Cross Id Sp 0N Syracuse 0Conrluest Eako 30 MILES efpool me N Manaus Ktst emphls arn4rs East Mlno C Klrkvlllo sh Jordan My~naso r

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rengo V S AC SE Marco us Ono dsga anlius oM sums o a Lot 0 us Tyroo nett( Sks 44'telos ~ Ils smesvtgo Casenovl Thr vlllq 0 Msfc41lus Ora 0 Lake Mo II~ Cede wale o 0Nsdrow Ha lacy Cpp 0 o Skanea 4 Ies Q B Q D'A G A t4rval Po pey Cen er I

S ~ gs 0 naca Falls uburn ~ rl4tte I 0 IIIIIO lg ber Csr I . Foyers PUBLIC WATER SUPPLIES IN VICINITY OF SITE STATuTE MILES 5 IO 15 20 Note I RELL DATA DcscnrocD IN TA4LC 2 5 2 Rr'F ERENCE THIS MAP was PREPARED FROM APORTION Or' S 0 ~ 5 ~ STATE Or NEW Vower PATE MAP l957 DAMaks gk Moogacs FIGURE 2. 5-3

T > R 0 nr y E L

UNIT I I C PROGRESS 1 I "I PLANT I5 72 CENTER I IR 2.

Yi \

'1 I

I I I

I I I 1 I I

\ I I 'I 1 I 44 ROAD 1

I l I 1 \

I ROpy) 46 47 71 I RRIVATe c+48 ~ 75 Lakeview I

I NliQE MILE POINT SITE

'1 JAMES A. ~ l6 449 ~ 76 FITZPATRICK SITE 774 MILE IA O3 POg ER AUTHORITYOF THE 50 TATE OF NEW YORK OO ~5 PROPERTY NE 6 69

<70 qO O I 78 x~79 NIAGARA MOHAWK 81 IT~

~

I POWER CORP 24/2 ~ 60 ~ 67 62 68 22 2lh1 I PROPERTY LINE 52 8URT VIROR I ( OA 62 ~ 66

~ lie 57 80 20~o O55 IO l2 Lyco ming 3

35~

33 ~32

~303I O

28 ~ 29

~ 27 I 23 82 I3 26 4I 42 4 39 ~ 40 25 tforth Scrlba 122 In In I

I I

ROAD IIIODLe IO IOA FIGURE 2.5-4 SCALE - MILES PRIVATE WATER WELLS NEAR SITE NOTE DATA DESCRIBED IN TABLE 2.5-3

Table 2.5-3 Private Water Supplies

~Ma Mo. Well De th. Feet ~Ma NO. Well.De th. Feet 1 18 41 18 2 60 42 22 3 50 43 42 4 14 45 40 6 30 46 18 7 40 47 6 8 18 48 34 9 18 49 26 10 22 50 11 14 51 70 12 22 52 30 13 126 1/2 53 32 14 81 54 30 15 62 55 30 16 9 56 30 17 Shallow 57 15 18 25 58 30 19 15- 20 59 15-20 20 30 60 68 21 25 61 37 22 40 62 18 23 24 63 20 24 33 64 12 25 104 65 29 26 131 ,

66 (3 wells) 27 26 67 15-18 28 11 68 3 29 12 69 25 30 24 70 90 31 57 1/2 71 24 32 15 72 10 33 35 73 31 34 8 74 to Data Not Available 35 0 82 36 55 37 82 38 37 39 20 (3 wells) 40 No Data Available

2. 5-5

P P 1

F

2~ 6 CLIMATOLOGY AND METEOROLOGY

2. 6.1 Data Sources Average and extreme values of standard meteorological parameters were obtained from the U.S. Weather Bureau Station in Oswego, which ceased operations in 1960, and from the U.S. Coast Guard Station at Oswego (wind observations 1936 to 1945). Data on the micrometeorology of the site was obtained from an instrumented 204-foot tower operating during a two-year study (1963 1964) at Nine Mile Point. The instruments measured temperature at 30-,

64.5-, 106.5-, and 204-foot levels, wind speed and direction at 30 and 204 feet and wind fluctuation at 31 feet.

Ten years of hourly wind, temperature, and humidity observations taken at Rochester (1955-64), 63 miles to the west southwest of Nine Mile Point, as well as the Oswego Weather Bureau data, were used to develop the climatology of the site. Rochester is considered more representative of Nine Mile Point climatology than Syracuse because Rochester is located near the shore of Lake Ontario which has a profound influence on the climate.

2.6.2 General Climatology The Nine Mile Point area has relatively short cool summers, with average temperatures near 70 F, and rather severe winters, with average temperatures near 25 F and heavy snowfall. Extreme temperatures of 100 F and -23 F were observed during the 90 years ending in 1960. The exposure of the area to Lake Ontario and the flatness of the surrounding terrain causes wind speeds to be higher at the site than those experienced in most inland areas.

Precipitation is moderate and rather uniformly distributed through the year. It consists mainly of thundershowers during the summer and snow during the winter. Winter snowfall averages 1 to 2 feet per month during December through March. The maximum 3-day snowfall on record was 75 to 90 inches during the winter of 1965-1966. Table 2.6-1 shows mean temperatures, humidityg precipitation and snowfall at Nine Mile Point.

2. 6. 3 Winds The site is near the mean path of many cyclonic wind systems which cross North America at the rate of approximately 10 per month. Therefore, substantial tropospheric mixing occurs during most of the year. Stagnant conditions occur infrequently.

Prevailing winds range from west to south to southeast. The annual wind <rose~~ showing percentages of winds from each direction at the site is shown in Figure 2.6-1. No northerly compass point has a frequency as high as 10 percent, except for northwest during December.

2. 6-1

NNW NW NE WNW ENE

'OTA L WI ND 20%

IO%

WSW SE SW SE SSW SSE S

SR I- 10 MPH I 1-20 MPH 21-IOO MPH l965- l964 NINE MILE POINT FIGURE 2. 6-I AVERAGE WIND ROSES

Table 2.6-1 Average Temperature, Humidity and Precipitation at Nine Mile Point RELATIVE PRECIPI- SNOW-TEMPERATURE ~F+ HUMIDITY~5 TATION~ IN. 4+ FALL~ IN MONTH MAX .. MIN MAX. MIN Jan 32.7 16 7 81 73 2. 70 23. 6 Feb 32.5 15. 5 81 69 2. 62 21. 4 Mar 41 ~ 8 24 1 81 64 2 80 12. 7 Apr 54.7 34. 2 79 57 2. 72 2. 3 May 67.8 45. 0 81 54 2.97 0 Jun 78.2 54.9 84 52 2. 28 0 Jul 82 7 59 7 84 50 2. 74 0 Aug 80 3 57 5 86 52 2.51 0 Sep 73.0 50.9 87 55 2.78 0 Oct 61. 1 40.4 84 57 3.26 0.4 Nov 47.4 32 0 81 66 3. 01 7 3 Dec 35 4 21. 0 81 70 3.17 20 4 Annual 57.3 37.7 83 60 33. 56 88 1 4U.S. Weather Bureau, Rochester, N.Y., 1931-1960.

+~U.S. Weather Bureau, Oswego, N.Y., 1884-1960.

The most prominent peak in the distribution is west-southwest, which becomes especially marked in May and June when the overall frequency reaches more than 20 percent from this direction. An absolute 3-minute peak wind speed of 73 miles per hour was observed during two years of observation at the site.

Monthly wind roses and atmospheric stability frequency and precipitation frequency as a function of wind speed and direction are shown in Appendix D.

2.6.4 Tornadoes and Hurricanes I

High winds in the Lake Ontario area result from intense winter storms, remnants of tropical storms, and severe thunderstorms.

The nearest tornadoes shown on a tornado summary map of the area completed in 1960 occurred in Jamestown (1945) and Allegany County (1920), both approximately 150 miles southwest of Nine Mile Point. A tornado in Sinclairville, New York, on May 17/

1969, about 150 miles southwest of the site, did substantial damage to residential structures but caused no fatalities.

Remnants of hurricanes and tropical storms have affected the Nine Mile Point vicinity, but such occurrences are rare.. Storms moving toward the site from the North Atlantic Ocean are substantially weakened by travel overland so that winds are

2. 6-2

0 C

~

reduced below hurricane force (75 miles per hour) before they reach the site (Ref. 3) .

2.6.5 Turbulence Classes The classification system used to differentiate stack effluent dispersion regimes was based on the directional fluctuations of an aerovane wind instrument (Brookhaven type) mounted 204 feet above ground on the Nine Mile point meteorological tower. The four turbulence classifications are related to other descriptions of turbulence in the following way:

Niagara Mohawk Pasquill Brookhaven Qualitative Class.- Classy ~ Class. ~-

I A B2 Very Unstable II III B D

B1 C

Unstable Neutral IV F D Stable The Brookhaven classification is based on turbulence measurements from strip charts of the wind speed and direction. In the absence of onsite wind measurement, the Pasquill classification is widely used as an approximation of turbulent conditions. The Pasquill classification is based on wind speed and cloud cover parameters that are routinely measured at most airports. Of the seven pasquill classifications (A through G) the four listed above most closely correspond to the four Brookhaven types, except that Brookhaven Class B2 and B1, actually correspond to Pasquill Classes A and B.

The madel'or Niagara Mohawk classifications are defined to be the same as the corresponding Pasquill and Brookhaven classes as listed above. Stability frequency as a function of wind direction is shown in Table 2. 6-2. Table 2.6-3 lists the frequency of wind speeds observe'd for each wind direction as a percentage of total observations each of the four turbulence classifications.

2.6.6 Lapse Rates Another measure of stability is the lapse rate measurements taken between the 30- and 204-foot levels on the tower. These are summarized as mean diurnal lapse rates for each month in Appendix D.

These figures reflect the importance of the lake-land relationship. In the winter months (December, January, and February) the mean diurnal lapse rate never passes into the inversion regime. However, in May and June the mean diurnal lapse rate lies in the inversion regime close to 75 percent of the day.

2. 6-3

Table 2.6-2 Annual Stability Frequency of Occurrence with respect to Wind Direction, Percent Brookhaven Stabilit Class. Totals Wind Direction B2 B1 ~ D--

N 14 2.79 .05 1-04 4. 02 NNE .09 3.56 .31 .84 4. 80 NE .08 2. 35 ;17 .76 3. 36 ENE .02 .78 .00 .50 1. 30 03 .90 09 .72 1. 74 ESE .15 2.05 .71 .72 3. 63 SE .44 4.66 3.25 1. 25 9. 60 SSE .89 3.04 1. 91 .95 6. 79

1. 13 4. 33 1. 97 .67 8. 10 SSW .36 3.36 1 74 .51 5. 97 SW 20 6.10 3 41 .56 10. 27 WSW .22 7. 96 3. 87 . 96 ~

13 01

.19 8.09 1.79 1 62 11. 69

.06 4.76 33 .65 5. 80 I

NW .06 4.49 .19 .62 5. 36 NNW ~ 11 2.79 .04 .69 3. 63 Calm 01 .01 .00 03 05-Total 4 18 62. 02 19. 83 13. 09 2 6-4

Table 2.6-3 Percent Occurrence of Total Observations Brookhaven Turbulence Class B2: Very Unstable 641 Observations Wind Wind Speed (Knots)

Direc- 1-3 4-7 8-11 12-19 20-29 >30 All Sp-tion N 07 .05 00 02 .00 .00 .14 NNE .06 02 01 .00 .00 .00 .09 NE .03 .03 .01 .01 .00 .00 .08 ENE .01 .01 .00 .00 .00 .00 .02 E 01 .02 .00 .00 00 .00 .03 ESE 05 04 .03 03 .00 .00 .15 SE .03 .15 ~ 13 .13 .00 .00 44 SSE .05 .28 22 31 03 .00 .89 S .12 ~ 44 .25 . 32 00 00 1. 13 SSW .08 16 . 07 .05 .00 .00 36 SW .05 .09 .04 . 02 .00 .00 .20 WSW 02 .10 .07 03 .00 .00 .22 W .06 07 00 .05 .01 .00 .19 WNW .03 .01 .01 .01 .00 .00 .06 NW 03 .03 .00 .00 .00 .00 .06 NNW .03 03 .02 -01 00 .00 .11 Calm .01 .01 All 74 1. 53 86 .99 04 .00 4. 18 Brookhaven Turbulence Class B1: Unstable 9567 Observations Wind Wind Speed (Knots)

Direc- 1-3 4-7 8-1 1 1 2- 19 20-29 >30 All Sp.

tion N 22 .51 38 1 30 37 .01 2.79 NNE .16 . 60'9 .52 1. 40 .80 .08 3. 56 NE 19 .60 .75 21 01 2.35 ENE .18 .36 .17 .06 .01 .00 .78 E 09 .40 .29 .12 .00 .00 .90 ESE ~ 13 .45 .62 82 .03 .00 2. 05 SE 10 .82 1. 24 2. 39 11 .00 4. 66 SSE .11 .69 .98 1. 19 .07 .00 3 04 S .39 1. 91 1 32 71 .00 .00 4. 33 SSW 21 1. 06 1. 34 . 75 .00 .00 3. 36 SW .30 1. 74 1. 82 1. 78 .41 .05 6. 10 WSW .18 1 21 1 93 2. 74 1. 41 49 7.96 W 19 1 18 1. 29 2 77 1-95 71 8 09 WNW 12 56 61 1. 91 1. 19 37 4. 76 NW 23 .63 .65 2. 06 .82 .10 4.49 NNW 18 .58 .50 1. 16 .36 .01 2 ~ 79 Calm .01 .01 All 2.99 13.29 14 26 21. 91 7. 74 1. 83 62. 02

2. 6-5

Table- 2. 6-3 Cont.

Brookhaven Turbulence Class C Neutral 3057 Observations Wind Wind Speed (Knots)

Direc- 1-3 4-7 8-11 1 2-19 20-29 >30 All Sp tion N 00 .02 .01 .01 .00 .01 .05 NNE .00 00 .05 . 12 .12 02 .31 NE .00 .00 .02 13 .02 .00 .17 ENE .00 .00 00 .00 .00 00 .00 E .00 .01 .03 . 05 .00 .00 .09 ESE ~ 00 .03 .10 .53 .05 .00 .71 SE .01 .02 30 2. 42 49 01 3. 25 SSE 00 04 .23 1.56 08 . 00. 1 91 S .00 32 .73 .92 .00 .00 1. 97 SSW .00 13 .60 1 01 .00 .00 1 74 SW .01 .29 82 1. 78 .45 .06 3. 41 WSW .01 .05 .35 1. 95 1. 14 .37 3. 87 W .00 02 .06 . 59 .87 .25 1.79 WNW 00 .00 .01 . 16 .15 .01 33 NW 00 01 04 .08 .06 .00 .19 NNW 00 .01 .01 .01 0 1 00 04 Calm .00 .00 All .03 . 95 3. 36 11. 32 3 44 .73 19 83 Brookhaven Turbulence Class D Stable 1998 Observations Wind Wind Speed (Knots)

Direc- 1-3 4-7 8-1 1 1 2-19 26-29 >30 All Sp tion N .19 .38 16 26 .05 .00 1 04 NNE 18 32 .12 .13 .09 .00 .84 NE 13 33 .12 .08 00 .00 .76 ENE .14 . 23'4 .11 .02 .00 .00 .50 E 13 .22 .03 .00 .00 72 ESE .07 .26 .25 .14 .00 .00 .72 SE .11 30 .40 .47 .00 . 01 1.25 SSE .08 ~ 34 .36 .17 .00 .00 .95 S 24 .36 .06 01 .00 .00 .67 SSW 12 .27 .08 .06 .00 .00 .51 SW 19 .34 .03 .00 .00 .00 .56 WSW .13 .35 .31 .16 .01 .00 .96 W .18 .55 .42 . 40 .07 .00 1. 62 WNW 22 ~ 23 .05 .12 03 .00 .65 NW .10 30 08 .12 .02 00 .62 NNH .22 .23 .10 .14 .00 .00 69 Calm .03 03 All 2 46 5.13 2.87 2.31 . 27 .01 13. 09

2. 6-6

'I ~

P

2 7 BIOTA 2.7.1 Terrestrial Ecology of Surrounding Area and Station Site The physiographic regions of Oswego County can be categorized into three broad land groupings: (1) the Tug Hill Plateau in the northeast, (2) the low Oneida Plain extending south of Lake Ontario, and (3) an intermediate region referred to as the Tug Hill Transition zone. This is shown in Figure 2.4-1. Due to the differences in topography and elevation among these regions, the plant and animal species in each region are variable.

The Oneida Plain area, which includes the Nine Mile Point Station site, is low undulating land, much of which has been cleared in the past for farming but over half of the farm land in the county has been abandoned.

The wildlife species found in this region consist of the typical fauna associated with much of the northeastern United States.

This area is goal range for woodcock (Philchela ~minor and

'I ""

abundance is low. Furbearers, including raccoon (Proc~on lotor),

mink (Mustela venison, red fox (Vuul es fulva), grey fox (UUro ron.

cinereoar enteus) and skunk (~Me hitis m~ehitis) also occur on the Oneida Plain.

The south shore of Lake Ontario is an important concentration area for diving ducks in the winter with lesser scaup (~A thea affinis) being the most abundant species. Dabbling ducks such as wood duck (Aix ~sonsa)., black duck (Anas r~ubri es), mallard (Anas.

1st rh chas), green-winged teal (Anas carolinensis) can be found on the marshes and ponds of the region.

The Department of the Interior, Bureau of Sport Fisheries and Wildlife, has compiled a list of 101 species and subspecies of wildlife in the United States that are now threatened with extinction. Two avian species on the list which have been previously recorded in New York State include the American (Haliaeetus leucoce halus leucoce halus) but neither is ww'agle common to the site.

The vegetation on the. site may be divided into four categories:

abandoned pasture and orchard, overgrown land, Northern hardwood forest and cleared land. The division is based on the various successional stages in a plant community as cleared land reverts back to the normal forest condition which is the climax stage for the area. This is shown in Figure 2.7-1. A list of identified plant and animal species associated with these habitat areas is presented in Appendix E.

2~7 1

,'i'w+P'~. ~M;P~ i~ +gal

~

)

$ j~+j<Qf..!f!gp '

(

NORTHERN HARDWOOD FOREST ABANDONED PASTURE 6 ORCHARD v<

J r I ~ j qy OVERGROWN LAND POWERLINE CUT CLEARED F I GURE 2.7- I V E G E TAT I 0 N C ATE G OR IE S

2.7.1.1 Abandoned pasture and orchard Abandoned pasture and orchard is the first stage in land succession after abandonment.

and herbaceous It is characterized by low grassy vegetation with the average height below three feet. Extensive areas of this vegetative stage appear east and south of the existing power station. There is a large abandoned apple and pear orchard in the northwestern portion of the site.

the tallest vegetation in this successional stage. Also, some (Rhus Anne'

( '""'S s

area southwest of the station.

( ~ ~

~thing) and poplar (~Po lus sp.) are found in hedge rows and other small patches of brush that had not been cleared when the rest of the area was used for commercial orchard or pasture.

The dominant vegetation in this successional stage is orchard

.( ~

lace (Daucus. carota) . A small planting of scotch pine Q

2.7. 1.2 Overgrown land There is no distinct division between this successional stage and the abandoned pasture and orchard stage, but it can generally be identified where low woody vegetation has replaced the grasses and herbs. Woody'vegetation becomes dominant shading the herbs and grasses causing many to die out due to lack of sunlight. The vegetation in the overgrown land is dense, providing good cover for wildlife which inhabits the area. Many small transitional tree species, including pin cherry (Prunus enns lvanica),

overgrown land. Some young forest trees such as red maple (Acer.

r~~e) and black cherry (Prunus serotina) also occur in this area Al.der (Ainus. sp.) and willow (Salix sp.) can be found in the wetter areas, especially along the western boundary off Lakeview Road. The low woody shrub, arrowwood (Viburnum sp.) and grape (Vitis. sp.) are prevalent on overgrown land. This serai stage is prevalent along the periphery of the site.

2-7-1.3 Northern hardwood forest The northern hardwood forest is the climax community in this area. This is characterized by four dominant+ species: sugar maple (Acer. saccharum), yellow bizch (setula ~lutea, beech (Fa(aus-species that are common are red maple (Acer.rubrum), white ash cherry.

Ground cover in the mature forest is low and sparse. Canada mayflower (Maianthemum canadense), five-leafed ivy 9RHI 2m 7 2

a I

partridge berry (Mitchella ~re ens) and ferns (polypodiaceae) are some of the more common ground cover plants. More than one third of the site is in forest, primarily in the central and eastern section.

2.7.1e4 Cleared land Sections of the site were cleared for the Nine Mile Point, Station. An area approximately 500 feet wide extends from north to south through the site and serves as a transmission line right of way.

The transmission line right of way has a great diversity of vegetation. The timber has been cut and removed giving a brushy effect. Some species from each of the previously described sections occur here with some additional species not associated with the other areas. The most common plant on this area is blackberry (Rebus elle heniensis) which forms thick cover and provides abundant fruit for (cirsium.

(Verbascum ~tha sus) ~ thistle animals and birds. Mullein sp.) ~ and chicory (Cichorium ~int bus) are three common species in this area not often encountered in the other areas. Several depressions on the right-of-way contain standing water and some species of water loving plants, including cattail (~T pha latifolia), smartweed 2.7 1.5 Animal associations The Nine Mile Point Station site, due to the diversity of vegetation, provides habitats for many of the typical wildlife species found throughout the Northeast. A large number of predatory birds appear to be associated with the more open areas of the site, at least during certain times of the year. Sparrow m H been observed in the vicinity of the site. Extensive tunneling in the grass indicates that the area supports a large 'population of voles (Microtus enns lvanicus) . The vole is an important food item in the diet of many hawks as well as some predatory mammals. Two species of game birds, ru ffed grouse (Bonasa the site. Several species of small birds are also found throughout the area, including blackcapped chickadees (Parus I!

also abundant in the area. Many other species of birds of the Northeast are found on the site during different times of the year.

floridanus), red fox (~Vul s fulva), raccoons (~proc on lotor),

2e 7 3

a the

(~Me 2.7.2

"'"'~.

hitis ~me hitis) and site appears Aquatic Ecology to The Great Lakes support a wide mink (Mustela vison) .

be capable 1

The vegetation of supporting white tailed deer ranging and diversified population of fish species as reported by Hubbs and Lagler (Ref. 0), Beeton on (Refs. 5 and 6), and Dambach (Ref. 7). Lake Ontario supports a fishery as mentioned in valuable commercial and sport

(~

Section 2.2.

The "I!

commercial

( ~

American eel (A cCuilla rostrate),

walleye (Stizostedion vitreum vitreum) .

landings are dominated by white (Ictalurus.nebulosus), yellow perch (Perca. flavescens), whitefish sunfish (I~amis spp.), and fishes are various panfishes as well as smallmouth bass The principal sport lucius), coho salmon

""4 "

(Oncorh nchus kisutch), and yellow perch.

The blue pike (Stizostedion vitreum ~laucum is listed on the endangered species list of the United States Department of Interior and was once quite abundant in Lake Ontario. This species, however, has not been observed in the vicinity of Nine Mile Point during the ecological field surveys.

A comprehensive research program, designed to monitor various parameters of the aquatic environment in the vicinity of Nine Mile Point was initiated by the Niagara Mohawk Power Corporation in 1963. Since 1969 this program has been closely coordinated with studies initiated by the Power Authority of the State of New York for the James A. FitzPatrick Nuclear Power Plant. These continuing lake surveillance studies have provided much information regarding the aquatic ecology of the region. The detailed results of these studies are presented in Section 5.5.

Throughout the ecological field studies at Nine Mile Point, eight to twelve species of fish were generally encountered during the netting operations. The major species taken in descending order of numbers are:

Alewives (Aloes- seudoharen s)

(~

Yellow perch (Perca flavescens)

$ 8ite perch Northern redhorse sucker Rock bass Smallmouth bass H!

Bluegill (~re omis macrochirus)

Brown bullhead (Ictalurus nebulosus)

Also taken in the nets have been various minnows (~Notro is spp) and an occasional carp, coho salmon, walleye, smelt, gizzard shad

2. 7-4

C

'I II

Other species of fish besides those collected during the field surveys may frequent the inshore waters near the site during certain times of the year. Some of the species which may periodically be found in the vicinity of the site could include the following: other species of sunf ishes (family Centrarchidae), species of pike (family Esocidae), largemouth (f'

troutperches (family Percopsidae), sticklebacks (family Gasterosteidae), killf ishes (family Cyprinodontidae), as well as occasional coldwater salmonids during the colder months.

In general,'he most abundant species of fish collected in the vicinity of the site are principally species indicative of the shallow water regions of Lake Ontario where natural summer'water temperatures are suitable for warm-water fish populations.

Natural maximum water temperatures in this region during the summer approach the upper seventies (77 F) which is generally above the optimum temperatures for cold-water species of fish, such as the salmonids (Refs. 8, 9, 10, and 11). Under natural summer conditions, it would be expected that the cold-water species of fish in Lake Ontario would retreat to more optimum thermal strata in the deeper off-shore waters in preference to the warmer in-shore regions of the epilimnion. Table 2.7 1 presents the maximum temperatures recommended by the National Technical Advisory Committee to the Secretary of the Interior as compatible with the well-being of various species of fish, some of which have been observed in the vicinity of the Nine Mile Point Nuclear Station.

Fish larval abundance appears to be quite low. The only fish which appears to spawn actively in the vicinity of Nine Mile to the shore during the spring.

Food preference studies of fish in the area indicated that small alewives, darters, minnows and alewife eggs are the primary food supply in the spring of the year. As the season progresses the freshwater amphipod (Gammarus) assumes greater importance as a food source. For some of the less abundant fish species, crayfish and small forage fish comprised a major portion of their diet during the autumn months.

Many researchers have studied the benthic communities of Lake Ontario. Henson (Ref. 12) reviewed the various research programs associated with benthos studies on the Great Lakes. Neil and Owen (Ref. 13) and Herbst (Ref. 14) described the distribution of region in the vicinity of Nine Mile Point. Brinkhurst (Ref. 15) discussed the changes in the benthic communities of Lake Erie and Ontario in recent times. The Great Lakes Laboratory of the State

2. 7-5

~'S University College at Buffalo (Ref. 16) interactions of light and temperature on the growth The Federal Water discussed Pollution Control Administration stated in 1966 the and (Ref. 17) that there are seven principal types of benthic invertebrates present in Lake Ontario. The Amphipoda- and Oligochaeta account for about 95 percent of the organisms. The remaining five percent are Sphaeriidae (fingernail clams),

Tendipedidae (bloodworms), Isopoda (aquatic sow bugs), Mysidacea (opossum shrimp), and Hirudinea (leeches) . The amphipods are the predominant invertebrates throughout the lake. The abundance in number of organisms per square meter during a 1965 survey ranged from 0 to 5,400 in deep water sampling stations.

Table 2.7-1 Provisional Maximum Temperatures Recommended as Compatible with the Well-Being of Various Species of Fish and Their Associated Biota 93 F: Growth of catfish, gar, white or yellow bass, spotted bass, buffalo, carpsucker, threadfin shad, and gizzard shad.

90 F: Growth of largemouth bass, drum, bluegill, and crappie.

84 F Growth of pike, perch, walleye, smallmouth bass, and sauger.

80 F Spawning and egg development of catfish, buffalo, threadfin shad, and gizzard shad.

75 F: Spawning and egg development of largemouth bass, white, yellow, and spotted bass.

68 F Growth or migration routes of salmonids and for egg development of perch and smallmouth bass.

55 F: Spawning and egg development of salmon and trout (other than lake trout) .

48 F: Spawning and egg development of lake trout, walleye, northern pike, sauger, and Atlantic salmon.

From: Table III-1, Water Quality Criteria, Report of the National Technical Advisory Committee to the Secretary of the Interior, April 1, 1968, Washington, D.C.g Federal Water Pollution Control Administration.

The benthic studies conducted at Nine Mile Point as part of the Unit 1 preoperational and postoperational studies indicate that

2. 7-6

N I

t 1

the maximum biomass occurring along the 10-f oot contour and decreasing rapidly down to the 20-foot. depth contour. Beyond the 20 foot depth contour growth was so sparse that adequate samples for analysis could not be obtained. The benthic animal community is dominated by the fresh water amphipod of the genus Gammarus.

The largest biomass of Gammarus appeared to be associated with maximal algal growth along the 10-f oot depth contour. Other benthic animals included three species of gastropods and the chircncmid larva, ~Tendi s.

In general, the quantity of plant and animal material found along the Nine Mile Point promontory is less than other areas in the lake. Wave activity and bottom composition along the promontory probably play a role in reducing the total biomass.

As discussed by Beeton (Ref. 5), Lake Ontario has characteristics associated with both oligotrophic and eutrophic conditions. The water quality studies at Nine Mile Point indicate that in general, concentrations of nitrates and phosphates are low and evenly distributed offshore from the promontory. Dissolved oxygen concentrations were found to be high, even during the warmest period of the year.

The United States Department of Interior (Ref. 18) stated that recent samplings have revealed a change in phytoplankton composition, indicative of nutrient enrichment.. Surveys in 1965 indicated that the phytoplankton population of Lake Ontario varied from 50 to 3,600 organisms per milliliter. The dominant species during the spring was Scenedesmus, while in July and September the population was dominated by Chlam domonas. An extensive bloom of Anabaena was recorded in mid-July.

Other species of plankton identified during field studies in 1964 and 1971 included the following:

Copepoda

""K! "'ES Cladocera

~Da hnia. dnbia.

D. ga1eata.

Bosmina. ion irostris.

a Ostracoda Rotatoria Keratella- adrata.

K..cochlearis ~

Prachionus sp.

2e77

l' Protozoa Traechelo lum.

Amoeba-Gastrotricha Chlorophyta Pandorina-Volvox-A detailed discussion of effects of station operation is given in Section 5. Ecological studies and preliminary re suits are described in Section 5.5.

2. 7-8

2.8 PRESENT RADIOLOGICAL CONDITIONS AT THE SITE AND ITS ENVIRONMENT The radiological conditions at the site and in its environment have been monitored in an extensive program initiated by the Niagara Mohawk Power Corporation in 1967, two years prior to startup of the Nine Mile Point Station Unit 1. The results of this phase of the program were reported to the AEC in a document entitled "Environmental preoperational Survey, Nine Mile point,<<

dated December 1969. The scope of the measurements made is summarized in Table 2.8-1.. Presently the program yields operational phase data for the Nine Mile Point Station Unit 1.

Table 2.8-1 Preoperational Environmental Monitoring Program Samples and Analyses Air Filters-Gross beta Gamma pulse height analysis on representative samples Preci itation.

Gross beta Gamma pulse height 'analysis on representative samples Milk-Gross beta Routine and spiked test samples to be run for Sr-90 and I-131 The ob jective of the preoperational environmental monitoring program was to assure that there were no radiological anomalies in the site area.

The present radiological monitoring program is divided into two parts as listed in Table 2.8-2.

1. Aquatic surveillance of Lake Ontario in the vicinity of the site.

2. Land surveillance in areas surrounding the station site.

In the lake surveillance, after determination of types, abundance, and distribution of aquatic organisms, samples are taken at representative and repeatable locations and analyzed for the following activities:

2 8-1

Table 2.8-2 Sample Collection Analysis Nine Mile point Station - Environmental Monitorin Pro~ ram.

A. Lake Pro ram (Described in Appendix D-4 of Ref. 19)

Type of Sample Type of Analysis Collection Frequency Number of Locations

1. Fish GB and Sr-90 Spring and Fall Two 2 Clams GB, GSA, Sr-90 Spring and Fall Two

3. Gammarus (Fresh Water Shrimp) GB, GSA, Sr-90 Spring and Fall Two

4. Lake Water GBi GSA Weekly Downstream of Effluent Discharge Coding: GB - Gross beta GSA Gamma spectral analysis Notes on Graded Program:

A. No environmental lake program for effluent discharged at less than 1 x 10-~ uCi/ml average concentration.

B. Standard environmental lake program as shown for items 1 thru 3 for effluent discharged between 1 x 10-~ to 1 x 10-~ uCi/ml average concentrations.

C. Standard environmental lake program as shown for items 1 thru 4 for effluent discharged above 1 x 10-~ uCi/ml but less than MpC in accordance with Appendix B, Table II, Column 2, of CFR 20 and note 1 thereto.

D. An appropriate number of samples shall be taken at each location.

Table 2. 8-2 Continued B. Land Pro ram (Five on-site and six off-site sampling stations are employed as described in Appendix D-4 of Ref. 19.)

Type of Sample Type of Analysis Collection Frequency Number of Stations Location Air Particulates Eleven on-site

- (monthly) Weekly

1. GSA 5 GB all (24 hrs. decay) 6 off-site

2. Precipitation GB 8 GSA Monthly Eleven 5 on-site 6 off-site

3. Film Badges Gross Gamma Monthly Eleven 5 on-site or TLD~s 6 off-site Radiation Monitors Gross Gamma Continuous Six 5 on-site 1 off-site Adjacent 5 Farm Milk Gross Beta, SR-90, I-131 Monthly Dairy Herds Plant Vicinity

6. Airborne Halogens GSA Weekly Eleven 5 on-site 6 off-site Coding: GSA - Gamma spectral analysis GB Gross beta GB 8 GSA Gross beta and gamma spectral analysis Notes on graded Program:

A. No environmental land program for stack releases less than approximately 3 percent of maximum release rate.

B. Standard environmental land program as shown for items 1 thru 5 for stack releases between approximately 3 to 10 percent of maximum release rate.

C. Standard environmental land program as shown for items 1 thru 6 plus weekly for farm milk samples for stack releases between 10 to 30 percent of maximum release rate.

D. Environmental land program upgraded to twice weekly onsite for item 1, weekly onsite for item 2, bi-monthly on-site for item 3 and weekly for item 5 for stack releases greater than approximately 30 percent of maximum release rate.

E. After substantiating data is analyzed for any of the release rate levels, the environmental land program is degraded by one level, i.e., B. to A., C. to B. and D. to C.

~ ~

Gross Beta Sr-90 Gross Gamma Zn-65 Cs-137 Co-60 The results of radioanalyses of aquatic samples collected through 1971, are presented in Table 2.8-3.

Five on-site and six off-site environmental monitoring stations were originally provided; four additional on-site stations have recently been installed at the FitzPatrick Plant site for future use. Their locations are shown on Figures 2.8-1 and 2.8-2.

~

Locations have been selected where no radiological anomalies exist and where the stations are accessible under all weather conditions. They have also been located in each significant sector relative to the site.

All monitoring 'stations are equipped with constant flow particulate air samplers, rain and snow fallout collectors, and integrating gamma dosimeters. On-site stations and the off-site Sector C station also include a recording gamma radiation monitor. This equipment has been operated intermittently over a two-year period since unit startup.

Table 2 '-4 shows the radiation exposure measured with thermo-luminescent dosimeters (TLD) for the period from July 1970 through December 1971, at the five Nine Nile Point Nuclear Station environmental sampling stations and the six off-site sampling stations. (No data is available as yet. from the four sampling stations recently installed at the FitzPatrick Plant site )

The gross beta activity of precipitation samples collected from three on-site and two off-site stations in July, September, October, and November of 1970, and for five on-site and'ix off-site stations in October, November, and December, 1971 are presented in Table 2.8-5.

The radioactivity of air is determined by passing 2-inch fiber glass filter at a nominal .flow rate of 2 cfm, it through a changing the filters weekly, and measuring the radioactivity after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decay time. Results obtained during the second half of 1970 are listed in Table 2.8-6. Results obtained during the period from September through December 1971 are listed in Table 2.8-7.

The results of the data collected from the environmental monitoring program indicate that no anomalies exist at the monitoring locations. Radiation levels have been observed to be generally consistent with data collected in New York State by the Department of Environmental Conservation.

2. 8-4

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ARD NINE MILE POINT JAMES A. FITZPATRICK NUCLEAR STATION NUCLEAR POWER PLANT PROPERTY LAKEVIEW LINE APPROXIMATE LAKE DEPTHS DISTANCE DEPTH FROM SHORE (BELOW L.W. DATUM) 50 6 0 000 1COO 400 12 600 18 SCALE - FEET 900 24 I 'I 00 50'0 5000 FIGURE 2.8" I LAKE SAMPLING TRANSECTS AND ON-SITE RADIOLOGICAL'ONITORINGLOCATIONS

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OFF-SITE RADIOLOGICAL MONITORING STATION LOCATIONS

4

Table 2. 8-3 Nine Mile Point Aquatic Sample Radioanalyses Picocuries er ram Ci/ m -d *wei ht Loca- Weight (gms) Gross Gross Sample Type tion Date wet dry Beta Gamma ('s 1 3 7 Zn<< ('o6 0 Northern Pike 6/69 2170 482 1 97%0 06 1 02%0. 1 1 0. 15%0 02 0 91%0 05 0.34%0 02 0.0%0 02 (Esox lucius)

Brown Bullhead 6/69 481 105 4 14%0. 11 0. 93%0.09 0.04%0.02 0. 73%0 06 0.09%0.02 0.0%0.02 (Ictalarus 6/70 91 24 0.0%0.58 0. 30%0. 08 0 0%0 2 0. 26%0. 03 0.0%0.58 0.0%0.58 nebulosus) E-1 6/71 511 148 8.64%0.48 ND 1. 92%0.31 1. 46%0. 34 0.0%0.5 0.62%0.08 E-1 8/7 1 551 169 6. 1%0 ~ 4 ND 0.8%0.1 0. 3%0. 1 0.0%0.5 0.'6%0. 1 White Perch 6/69 273 66 2 04%0.09 1 89%0 21 0.54%0.01 0.7%0.04 0.03io 02 0.06%0.02 (Morone 6/70 167 52 4.1%0. 3 1.9%0. 2 0.0%0.2 1. 6%1. 1 0.0%0 58 0.0%0.58 americana) E-3 6/7 1 363 101 11 2i0.6 ND. 0. 61%0. 14 1. 48%0 ~ 18 0.0%0.5 0 67%0.0 E-1 6/7 1 690 366 6.9%0.43 ND 0. 87%0 18 0. 24%0. 05 0.0%0.5 0.0%0.5 E-3 6/7 1 662 287 1 1. 6%0. 6 ND 1.5%0.23 1. 33%0. 26 0.0%0.5 0.6%0.08 E-3 6/7 1 878 441 10. 1%0. 5 ND 0.64%0.15 1. 18%0. 21 0.0%0.5 0.0%0.5 E-1 8/71 380 150 13%1 ND 0.2%0.1 0.3%0. 1 0.0%0.5 0.0%0.5 Yellow Perch 6/69 200 49 2.94%0.1 2. 04%0.22 0 16%0.02 2 08%0. 1 0.03%0.02 0.0%0.02 (Perca 1 1/70 150 35 3. 88%0. 21 1. 80%0. 09 0.39%0-04 0.0%0.58 0.0%0.58 flavescens) E-1 6/7 1 1151 149 13 3%0 7 ND 0. 24%0. 07 0. 6310. 14 0.0%0-5 0.0%0-5 E-3 6/7 1 535 75 14.7%0.7 ND 0.32%0.07 2 49%0. 22 0.0%0.5 0. 56%0. 10 E-0 6/71 275 119 9.35%0.5 ND 1 42%0. 23 0. 3110. 08 0.0%0.5 0.0%0.5 E-1 6/7 1 491 159 6.37%0.4 ND 0. 98%0.21 1 11%0. 21 0.0%0.5 0.0%0-5 E-3 6/7 1 596 242 11. 3%0. 6 ND 0.73%0.23 0. 97%0. 17 0.0%0-5 0.0%0.5 E-1 8/71 307 84 10%1 ND 0. 8%0. 1 0. 2%0. 1 0.0i0.5 0.0%0.5 E-1 11/71 323 101 5.0%0.3 ND 0.4%0.1 0. 5%0. 1 0.0%0.5 0 0%0 5++

N. Redhorse Sucker 6/69 973 225 1. 58%0. 08 0.81%0.09 0.0%0.02 0. 33%0. 03 0.03%0 02 0.0%0.02 (Moxostoma 6/70 1580 368 7.0%0.4 0.46%0.03 0-0%0.2 0.99%0.22 0.0%0.58 0.0%0.58 macroiepidotum) 1 1/70 1962 512 5.7%0.15 2.01%0.09 0. 51%0. 05 0.0%0.58 0.0%0.58 E-1 6/71 1588 138 13.5%0. 7 ND 0.5%0.09 0. 52%0. 07 0.0%0.5 0. 84%0. 14 E-3 6/7 1 6621 614 12.5%0.7 ND 0. 21%0.04 4.95%0.66 0.0%0.5 0.0%0.5 E-3 6/71 460 184 10.8%0.5 ND 0.53%0 15 0.32%0.06 0.0%0.5 0.0%0.5 E-1 1 1/71 1264 516 3.8%0.2 ND 0 6%0.1 1 0%0.2 0.0%0.5 0.0%0.5++

Alewife 6/69 39 8.5 4.0%0.23 2. 57%0.23 0. 19%0.01 2.0%0.47 0. 23%0. 1 0.0%0.02 (Pomolobus 6/70 26 8 0.0%0.58 1. 8%0. 1 0.0%0.2 0 22i0.05 0.0%0.58 0.0%0.58 pseudoharengus) E-1 6/71 111 21.5 13.5%0.8 ND 0. 54%0. 15 7.54%0.59 0.0%0.5 0.51%0.08 E-3 6/71 65 17.5 . 12.2%0 ~ 7 ND 0. 14%0. 05 11. 3%1. 9 0.0%0.5 0.44%0.07 E-3 8/71 34 7 12%1 ND 0.8%0.2 1. 3%0. 3 0.0%0.5 0.0%0.5 E-1 1 1/71 14 2 12i2 ND 0.0%0.1 4. 6%1. 0 0.0%0.5 2.3%0.4*+

• measured as Mn~~ which was the major gamma component in the algae sample.

• • co<< includes co<<

ND No detectable activity above background and system sensitivity on entire wet sample gamma scan.

Table 2.8-3 (Cont)

Picocuries er ram Ci/ m -d wei ht Loca- Weight (gms) Gross Gross Sample Type tion Date wet dry Beta Gamma Cs 1 37 Srvo Znd5 Coda Smallmouth Bass 6/69 385 90 3.6i0.1 1. 68io. 19 0.42i0.02 1 2io-3 O.oio. 02 O.oio.02 (Micropterus 6/70 270 54 7.0i0.4 0.72i0.02 0.43i0.02 1 9io 2 O.oio.58 O.oio.58 dolomieui) E-1 6/71 349 152 10 5i0.5 ND 0. 87io. 18 1 07i0.22 O.oio.5 0.52i0.07 E-3 6/7 1 755 309 8.74i0.49 ND 0.49i0.14 0.22i0.05 0. Oio. 5 O.oio.5 E-3 6/7 1 262 130 4. 94io. 36 ND 0. 74i0.18 0. 78io. 10 0. Oio. 5 O.oio.5 E-1 8/71 816 295 11i1 ND 0.7i0.1 0. 2io. 1 0. Oio. 5 O.oi0.5 Rock Bass E-1 6/7 1 175 49 4.75i0.36 ND 0.41i0.12 1 12io 21 0. Oio. 5 O.oio.5 (Ambloplites E-1 6/71 117 37 7.39i0.44 ND 2 23iO 28 0. 88io. 17 0. Oio. 5 '.oio.5 rupestris) E-3 6/7 1 264 94 6.53i0.42 ND 0 ~ 6io 16 1 2io 22 O.oio.5 0-Oio-5 E-3 8/7 1 419 146 13il ND 0.6i0.1 0. 3io. 1 O.oio.5 O.oio.5 E-1 1 1/71 470 152 3.8i0.2 ND 0 4i0.1 0. 6io. 1 O.oio.5 O.oio.5++

E-1 1/71 195 59 4.9i0.3 ND 0 6io 2 0. 9io. 1 O.oio.5 O.oio.5++

'.3.44i0.09 1

Lamprey Eel 6/70 8 2 O.oi0.58 29i1 29i0.07 O.oio.07 O.oio.58 O.oio.58 (Petromyzon 1 1/70 154 31 11 4i1 1 0. 09io. 02 O.oio.58 O.oio.58 marinus) 6/71 24 1 1628i33 ND 162i13 6. 29i1. 95 O.oio.5 0.8i0.19 Smelt 6/70 15 4 0. 59i0.05 7 3+0.2 0.48i0.03 11io. 02 O.oio.58 O.oio.58 (Osmerus E-1 6/71 29 5.5 15 3i1 6 ND 3.28i0.8 0. 81io. 28 O.oio.5 0. 95i0.18 mordax) E-3 6/7 1 51 10.5 24. 5i1. 5 ND 1. 41io. 33 0. 59io. 17 O.oio. 5 0. 67io. 12 E-3 6/71 19.5 5.5 17.6i1.5 ND 0. 10i0.04 0. 98io. 32 0. Oio. 5 O.oio.5 E-1 11/71 59 14 11il ND 1. 4io. 4 0 7io 1 0. Oio. 5 0. 6io. 1*e Minnow 1 1/70 26 6 11.4i1. 1 6. 19io 40 3. 16io. 70 O.oio.58 0. 63io. 12 E-1 6/71 56.5 13.5 11.2i1 0 ND 0. 11io 04 1. 49io. 36 O.oio.5 O.oi0.5 E-3 6/7 1 74.0 17 0 18. 1ii 0 ND 1. 19i0.28 1. 05io. 22 O.oio.5 0. 16io 11 E-1 6/71 85.5 14.0 15.5i1 0 ND 0.54i0.15 0. 65io. 19 O.oio. 5 0. 78io. 12 E-3 6/71 38 10 23 6i1.3 ND 0. 90io. 24 0. 65io. 14 0. Oio. 5 O.oio.5 E-3 8/7 1 18 4 10i2 ND 1.0i0.3 2.3i0.5 O.oio. 5 O.oio.5 E-1 11/71 7 1 14i3 ND 4. 1i1.4 16i4 0. 9io. 2 2.5i0.4++

Sculpin 6/70 5 1 1.4i0.4 110i10 O.oio.2 0. 27io 06 O.oio.58 O.oio.58 (Cottus sp.) E-1 6/7 1 15. 5 2.5 16.6i2 3 ND 2.44i0.54 2.24i0.76 1. 14io. 24 0. 74io ~ 16 E-3 6/7 1 12. 0 0.5 33.8i6 1 ND 11.0i3.6 6. 41i2. 40 0. Oio. 5 O.oio.5 W-2 7/71 3 1 22i5 ND 7.2i1.9 19i4 3.3i0.5 O.oio.5 Eel 6/7 1 839 361 4. 94io. 36 ND 1.3i0.23 0.21i0.07 O.oio. 5 O.oio.5 (Anguilla bostoniensis)

Carp 6/7 1 3780 1262 7. 31io. 44 ND 0.22io 07 0. 15io. 04 1.12io 21 O.oio.5 (Cyprinus 8/71 2934 1580 3.4i0.3 ND 0.7io. 1 0 1io. 1 O.oio-5 O.oio.5 Car pio)

• measured as Mnsd which was the major gamma component in the algae sample.

Co<< includes Cosd ND No detectable activity above background and system sensitivity on entire wet sample gamma scan.

Table 2.8-3 (Cont)

Picocuries er. ram Ci/ m ~ d -wei ht Loca- Weight (gms) Gross Gros's Sample Type tion Date wet dry Beta Gamma Csx 3> Znss Co<<

White Bass 6/7 1 371 193 5.55i0.38 ND 0. 43i0- 13 0- 43io. 10 0.0i0.5 0.0i0.5 (Roccus chrysops)

Calico Bass E-1 8/71 401 148 7 8io 4 ND 0.5io. 1 0. 110. 1 0. 0i0. 5 0.0i0.5 (Pomoxis nigromaculatus)

Sunfish E-1 6/7 1 68 16 12.4iO. 9 ND 0.95i0.24 2. 51i0. 37 0. Oi0. 5 0. Oi0. 5 (Lepomis ) E- 1 8/71 283 71 10 i1 ND 0.5i0.1 0. 2io. 1 0. OiO. 5 0.0i0.5 Gizzard Shad 1 1/70 2090 739 5.75i0.53 2.03iO 09 0. 47i0. 05 0. Oi0. 58 0.0i0.58 (Doro soma E-1 8/7 1 618 274 6.6i0.4 0.8i0.1 0. 1io 1 0. Oi0. 5 0.0i0.5 cepedianum) E-1 1 1/71 867 542 3.6i0. 2 ND. 0. 1i0. 1 0. 3i0. 1 0. OiO. 5 0.0i0.5~+

Freshwater Shrimp 6/69 0 083 6.4i2.6 (Gammarus sp.) 6/70 1 0.5 5.9i0.8 E-1 6/71 1 0.5 6. 12i0.87 E-3 6/7 1 1 0. 5 9. 28i1. 13 Walleye (Yellow) E-1 8/71 1 102 532 8.2i0.5 0.5i0.1 0. Oi0. 1 0. Oi0. 5 0.0i0.5 Pike (Stizostedion vitreum)

Crayf ish W-2 8/71 4 1 8 8i1 9 ND 1 9io 9 19i4 3 1i0.5 1.2i0.2 E-1 8/7 1 53 5 11i1 0 ND 1.9i0.7 32il 0.0i0. 5 1-710.5 Clams 6/69 689 363 0. 15i0.05 0. 46i0.05 0. 16i0.02 0.46i0.04 0.29i0.02 0.05i0.02 6/70 380 298 3 01i0.46 3.1io. 1 0.0i0.57 2. 14io ~ 13 0.0i0.58 0.0i0.58 W-2 7/7 1 244 168 0.4iO. 1 ND 0.2i0.1 1.7i0. 1 0.0i0.5 0.0i0.5 E-1 7/7 1 142 24 1.0i0.1 ND 0 2i0.1 0. 4i0. 1 0.0i0.5 0.0i0.5 *.

W-2 8/7 1 210 128 0.7i0.1 ND 0.1*0.1 3. 2iO. 1 0.0i0.5 0.010.5 Algae 6/69 1820 61 13.5i0. 2 35.6i5.9 0. 2i0. 01 2. 4110. 12 0.07i0.02 0.03i0.02 E-1 6/70 70 9 1.7110 71 35i1 0.0i0.57 0 54i0.01 0.0i0.58 1. 1810. 08 1 1/70 843 14 18. 111. 2 85i2.5 1.14i0 12 0. 15iO. 03 0.0i0.58 15-4io. 9 E-1 6/71 116 1 57.7i7.9 ND 10.310.8 34. 3i7. 6 12.7i3.4 15.1i2. 5 E-3 6/7 1 223 1 112i12 ND 8. 97iO. 76 43. 2i9. 5 1.33i0.32 133i9 E-1 8/7 1 84 4 71i3 ND 17.9i2.5 1. 7io. 4 2. 1io 3 41i244 W-2 8/7 1 79 6 17i1 ND 2. 1io. 6 1 Oio 2 0.610. 1 1. 8iO. 2~*

E-1 1 1/71 20 5 51i4 (All co60) 1. 88i0. 63 4 95i1 09 0.0i0.5 5.4i0.5 W-2 11/71 114 23 19i2 ND 0.0i0.03 2.02i0.45 0.0i0.5 0.0i0.5

~ measured as Mns~ which was the major gamma component in the algae sample.

Co<< includes Co<<

ND - No detectable activity above background and system sensitivity on entire wet sample gamma scan.

Table 2.8-3 (Cont)

Picocuries er ram Ci/ m -d -wei ht.

Loca- Weight (gms) Gross Gross Sample Type tion Date wet dry Beta Gamma Csi37 Sr90 Znas Co<<

Miscellaneous Anal ses Bottom Sediment E-1(15 ft depth)

E-1 (Discharge area) 6/70 6/70 370 602 297 3 90 19i2 13X1 9813 6913 0 5510.02 0-4810.29 0.010.07

0. 0810-01 0.010.58

0. ORO. 58 8.5%0.6

5. 510. 5 E-4(20 ft depth) 6/70 423 350 1.610.3 4.310.3 0.010.29 0.010.07 O.OX0.58 0.010.58 Yellow perch E-3 6/71 29 4 15.811.6 ND 2. 14%0. 43 0. 66RO 22 0. 6510. 13 0 68%0. 14 eggs M

CO I

CO

• measured as Mn~~ which was the major gamma component in the algae sample.

• • Co<< includes Co~~

ND No detectable activity above background and system sensitivity on entire wet sample gamma scan.

Table 2.8-4 Radiation Dose Measured at Environmental Sampling Stations Ex osure- mrem Durin - Period. of-7/70 to '0/70 to 1/71 to 4/71 to 7/71 to 10/71 to Location 9/70 12/70 3/7 1 6/74 - 9/71 12/71 ~

D1 on-site 21 20 12 23 7.6 12 '6 D2 on-site 19 18 13 20. 4.6 15 2 E on-site 14 23 16 20 5.6 13. 6 F on-site 16 17 16 20 4.8 16. 0 G on-site 27 21 10 19 8.6 17. 4 C off-site 18 22 12 20 6.0 13. 8 D1 off-site 23 26 16 22 11.2 11. 0 D2 off-site 18 20 21 3.4 20 0 E off-site 16 20 11 22 5 2 13. 6 F off-site 16

'4 10 19 6.0 12. 4 G off-site 15 24 12 23 8.0 12 4 Table 2.8-5 Gross Beta Activity of Precipitation Samples in Units of 10-~ uCi/ft~/month SAMPLELOCAT

.-. .On-Site Stations.

ION S Period* ~

D1 D2 E F July, 1970 26. 9 22.8 19 1 September, 1970 3 3 3.0 7 1 October, 1970 10. 9 11.0 7 2 November, 1970 2 3 3.1 8 6 October, 1971 3 8 8.3 5 2 11 9 6 3 November, 1971 3. 8 2.5 5.2 5.9 6 2 December, 1971 40. 6 28.2 4 5 34-9 32 3 Off-Site Stations.

D1 D2 E G July, 1970 23. 0 30.3 September, 1970 6 8 3 4 October, 1970 6.5 10.2 November, 1970 4. 8 3 6 October, 1971 95 3 3.6 5. 8 November, 1971 7.1 4 3 123. 27.7 110. 5. 8 December, 1971 28-0 5.5 2.1 22 2 15 8 14 1

2. 8-9

Table 2.8-6 Environmental Air Sample Gross Beta Activities (10->> uCi/cm~)

~ On-Site.- ~ Off-Site.

Date D D 2

~ ~

7-14-70 0.3 0.4 3.7 3.5 3.8 7-21-70 2 8" 3.3 3 3 2.9 3 9 7-27-70 3 9 4.5 4.2 3.7 3 9 8-4-7 0 1 9 2 2 2.3 2. 1 2 2 8-11-70 3.6 4~2 4.2 3.9 4.3 8-18-70 3.5 4 0 4.2 3.5 3.9 8-24-70 2 0 2.6 2 5 2 4 2 4 9-8-7 0 1.2 1.6 1.5 1 4 9-15-70 1 2 1 5 1 2 1.3 1.5 9-21-70 1.1 1.6 1 3 1.1 1.3 10-2-70 0.7 0 9 0.6 0.6 0.8 10-12-70 1 0 1.2 0.5 0.8 1.0 10-21-70 0.7 1.0 0.5 0 7 0.9 10-26-70 0.6 0.9 0 4 0.6 0.8 11-3-70 1 1 1 5 0.8 1 1 1 4 11-9-70 1.8 2.7 1.4 1.6 2.4 1 1-1 6-70 1 1 1.3 6.9 0.9 1 1 11-24-70 0.8 1.3 0 7 0.7 1.0 1 1 70 0.6 0.7 0.5 0.5 0.6 12-7-70 0.6 0.9 0.4 0.6 0.7 12-14-70 0.6 0 8 0.6 0.5 0.7 2~ 8-10

Table 2.8-7 Environmental Air Sample Gross Beta Activities in units of 10->> uCi/cc Collection SAMPLE ON-SITE STATIONS-

~

LOCATIONS OFF-SITE. STATIONS-Period Week of: D1 -D2 E D1 D2 9/11/71 0.70 0.96 0.86 0.70 0.20 0.61 0 97 0 50 0 77 0 33 9/24/71 1. 49 2 30 1. 6 1 3. 50 0.32 1. 00 1. 64 1.37 1. 66 0. 80 10/ 1/71 0-51 0 48 0.69 0-49 0.15 0-35 0. 73 0. 73 0. 59 0. 37 m

I 10/ 8/71 1-06 0.98 1.35 1 02 0.35 0.89 0.97 1.30 1.46 1.35 0.66 10/19/71 1 15 1. 42 1.09 0.43 0.89 1.09 1.33 1.54 1.09 0.70 11/ 3/71 1.17 1.05 1.44 1 14 1.31 1.26 1.51 1.75 1-78 1.30 1.06 11/10/71 0.60 0.50 0.79 0. 66 0.69 0.47 0.68 -

0.83 0.93 0. 64 0.49 11/17/71 0 32 0 41 0.39 0 36 0.30 0 23 0.34 0.39 0.37 0 34 0.24 11/24/71 0.44 0.45 0.39 0.39 0 36 0.34 0.36 0.53 0.55 0.34 0.28 12/ 1/71 0 68,. 0 72 0.57 0.74 0.69 0 49 0.48 0.77 0.84 0.46 0.39 12/ 8/71 0 42 0 55 0.46 0 48 0 49 0 41 0.42 0.53 0.65 0 35 0.38 12/15/71 0. 53 0. 66 0.77 0. 67 0.46 0. 40 0. 60 0. 72 0. 65 0. 55 0. 50 12/22/71 0-35 0 53 0.45 0.42 0.46 0.28 0.40 0.50 0.56 0.35 0.32

't SECTION 3 THE STATION 3 1 EXTERNAL APPEARANCE OF THE STATION The Nine Mile Point Unit 1 (see Frontispiece) station consists of several structures of various sizes. These include the Progress center, the administration, reactor, turbine, and radwaste buildings, the screenwell pump house, the sanitary waste treatment plant, and the 350-foot stack which rises from the radwaste building. The tallest of the buildings is the reactor building, which is approximately 140 feet high.. All the buildings, except for the Progress Center and sanitary waste treatment plant, are interconnected to form a complex of buildings. A plot plan of the station site which shows the arrangement of the station facilities is presented in Figure 1.1-1.

The architecture of the station'emphasizes the simple rectangular forms of the containment structure, turbine, and auxiliary def ined in a composition of panels buildings. The masses are which relate the buildings to each other in treatment and scale.

Particular consideration was given to materials and color.

Around the entire base, precast concrete units form a stron'g horizontal motif which lends an appearance of solidity and unity to the complex of structures. The dominant russet color of the base contrasts well with the light grays and greens of the fluted metal siding.

An independent landscape architect was responsible, for the external appearance of the station grounds. Initially, a master landscaping plan for the entire site was developed. The various structures have been located for functional efficiency, and planting has been used extensively to create vistas, establish horizons, and effect a pleasing relation between building and natural surroundings.

~ The Progress Center, located in the northwest portion of the site, is a contemporary stone and glass'anch-style structure which is used for public education and as a tourist attraction.

A three-part show is offered on nuclear-electric power, the growth of energy in upstate New York, the story of Niagara Mohawk, and the operation of Nine Mile Point Nuclear Station.

The exhibits include a working scale model of Unit 1, and an atomic fission display. There are also exhibits of live game fish common to the area. nature trails through the woods, and picnic'reas on bluffs overlooking Lake Ontario. Over 50,000 persons a year visit and enjoy the Progress Center's presentations.

~ f I

If 1 f )

3 2 TRANSMISSION IZNES In conjunction with the construction of Nine Mile Point Unit 1 Niagara Mohawk constructed two single circuit 345 kV transmission lines in .1965 to connect the generating station output into New York's cross-state transmission system. Figure 3.2-1 presents a map of the transmission route.

Following a review of suitable termination points of these lines, a tie-in to Niagara Mohawk Power Corporation's existing substation in the town of Clay, New York, which is about 27 miles southeast of the site, was selected. This location provided ready access to the cross state 345 kV grid.

The route selected runs due south of the site for a distance of about 4 miles, and then about 23 miles southeast to the Clay substation. This route caused minimum disruption to existing private, homes, farms, and businesses and also offered accessibility and ease of construction.

The probable need for future transmission lines from this generating area led to the decision to purchase a right-of-way 500 feet wide which was sufficient to accommodate Nine Mile Unit 1 needs and provide space for future 345 kV line requirements. The two 345 kV lines associated with Nine Mile Point Unit 1 were positioned in the center of 'he right-'of-way.

Two single-circuit 115 kV lines are also located along the initial reach of the Nine MileofPoint to Clay route. These lines the 345 kV lines to a point parallel the west side approximately four miles south of the site in the town of Scriba.

At that point the 115 kV lines join Niagara Mohawk's Lighthouse Hill Oswego 115 kV lines while the two 345 kV oflines continue route southeasterly to Clay. Photographs of portions the are shown in Figures 3.2-2 and 3.2-3.

The 27-mile long 345 kV transmission line traverses terrain ranging in elevatioh from 250 feet at the plant site to 400 feet at the Clay station.

of the It passes through of 10 miles of relatively Scriba, Volney, .Palermo, open farm areas Towns Schroeppel, and Clay. Approximately four miles of wetlands and five miles of wooded areas'ere encountered, particularly in the Volney-Palermo-Schroeppel areas.. See Figure 3.2-1.

Right-of-way route preparations consisted of selectively cutting a width of approximately 400 feet to remove undesirable wood species and maintain ornamental type trees and shrubs. Ground foliage was cleared through application of state approved herbicides. Several , pine tree plantations totaling about 10 acres in the town of Schroeppel were left undisturbed and continue to be farmed as multiple use of the right-of-way.

3~2 1

L A /I' 0 N 7 A R / 0 NINE MILE POINT JAMES A. FITZPATRICK NUCLEAR 'OWER STATION NUCLEAR POWER PLANT

~le:

I I

I I

I I N E W I

H A V E N I

I SCRI BA I

I I

I I

I

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I I

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I P A L E R M 0 I

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I V 0 L N E Y I I I. /

I I /

I I I /

I I I

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/ iS CH R E P P L CLAY SUBSTAT I ON F I GURE 3. 2 - I TRANSMISSION FACILITY MAP

I

~ 4

FIGUR E 3 ~ 2-2 TRANSMISSION LINE R IGHT OF WAY

F(GUR E 3. 2-3 TRANSMISSION LINE R IG HT OF WAY

Wood pole, H-frame structures shown in Figure 3.2-4 were selected to carry the ma jor portion (about 25 miles) of the 345 kV transmission cables, while lattice steel tower structures support the initial 1.7 mile of line from Nine Mile Point and the final 0.3 mile into the Clay substation. Figure 3.2-4 also illustrates the typical vegetation growth in the right-of-way area.

3 ~ 2-2

1 FIGURE 3 ~ 2-4 TRANSMISSlON LlNE STRUCTURES NORTH OF CLAY AND TYPI GAL VEGETATION GROWTH

3. 3 REACTOR AND STFAM ELECTRIC SYSTEM Nine Mile Point Unit 1 is a single unit nuclear steam generating system using a General Electric Company boiling water reactor with a thermal rating of 1,850 Mw and a net electrical output from the station of approximately 610 MW. The unit was designed by Niagara Mohawk power Corporation and constructed for Niagara Mohawk by Stone 6 Webster Engineering Corporation, Boston, Massachusetts. This unit has been in commercial operation since December, 1969. The principal components are the turbine-generator and nuclear steam generating system with the latter presently using nuclear fuel manufactured by General Electric. The major components and diagramatic operation of a Boiling Water Reactor are shown in Figure 3.3-1.

The reactor feedwater is heated to steam as reactor core of uranium fuel elements.

it Heat passes through the is developed by controlled fission of Uranium-235, producing fission products with slightly less total mass than the original uranium. This mass difference is converted to energy. The trillions of atom fissions taking place every second develop the heat to convert large quantities of water into steam.

This steam produces electricity in the conventional way, by spinning a turbine which drives an electric generator. This part of the plant is in principle the same as any other steam electric station. The steam, after spinning the turbine, is condensed into water and recycled to the steam generators. The nuclear reactor takes the place of a conventional boiler, and the energy source is fission of atomic fuel rather than combustion of fossil fuel.

The turbine-generator, also manufactured by General Electric Company, is a tandem compound 6-flow unit consisting of a high-pressure turbine section on the same shaft with three low-pressure turbine sections and the electric generator. The turbine cycle includes five stages of regenerative feedwater heating, utilizing'extraction steam from the turbine. Steam exhausting from the turbine flows to the main surface condenser and is condensed by cooling water. The resulting condensate is pumped to the regenerative feedwater heaters. The turbine generator plant is complete with auxiliary systems, controls, instrumentation, electrical switchgear and fire protection equipment.

Water 'for condenser cooling, the fire protection system and for auxiliary water service is drawn from Lake Ontario through an intake structure and tunnel leading from the lake to the screenwell and pump house building where large pumping equipment is located. Condenser cooling requires 250,000 gpm and service water requires 18,000 gpm. During shutdowns, a service water-flow of about 6,000 gpm is used for reactor cooldown.

3M3 1

TRANSFORMER REACTOR TURBINE REACTOR I NTAKE STRUCTURE r)f CORE CONTROL RODS FEED PUMP CONDENSER DISCHARGE TUNNEL DEMINERALIZER DI SCHARGE STRUCTURE FEEDWATER HEATER FIGURE 3. 3 - I SIMPLIFIED DIAGRAM NUCLEAR BOILING WATER REACTOR STATION

3 4 WATER USE Cooling water for the main condenser, auxiliary systems, reactor shutdown heat removal, and for water system makeup is withdrawn from Lake Ontario via the submerged intake tunnel. This water is circulated by the main condenser circulating water pumps and/or the service water pumps. The flow and heat dissipation rates are indicated on the Water Usage Flow Diagram, Figure 3.4-1.

During normal station operations, the closed loop cooling system heat exchangers are in use. However, when the station is shut down, this water use is reduced. At this time the Shutdown Cooling System utilizes the balance of the fler from the service water pumps.

No chemicals or inhibitors are added to the circulating water or service water systems. Chemicals in the quantities described in Section 3.7 are added in the makeup water treatment system, analytical sampling system, and decontamination system.

Maximum flows indicated for auxiliary heat exchangers and reactor shutdown are based on the most severe usage expected, i.e., ~

design heat loads on exchangers and 77 F lake temperature. Three pumps and exhangers are run at this time rather than two which are used during normal operation The water flow rates from waste regeneration, residual heat removal, makeup water, domestic water, laundry, and floor drain water usages are variable and are dependent upon such things as the phase of demineralizer regeneration, time of year, and station operating status Consumption of water furnished by the City of Oswego water system has averaged 3300 gpd.

All systems which use water discharge to the lake, and an exact determination of water consumption cannot be made. However, is estimated that water consumption due mainly to evaporation it would not exceed 0.02 cfs or 10 gpm. This does not include evaporation from the lake surface due to thermal dissipation of the circulating water discharge.

3. 4-1

P I'

l "

t lt P

t

LA A'E INTAKE TUNNEL CONDENSER 0 A'AR10 FROM LAKE 250,000 0 PM 4.0 x I 09 BTU/HR ONTARIO ( CONSTANT )

268,000 GPM (NORMAL) (WHEN OPERATING) SHUTDOWN HEAT DISCHARGE TT F MAX REMOVAL SYSTEM STRUCTURE 6000 GPM 272s000 GPM (NORM) 3?.5 x IOO BTU/HR 9000 GPM (MAX) SETTLING (MAX) (MAX) BASIN OVERFLOW

~ 20 GPH IBOOOGPM CLOSED LOOP (NORM ) COOLING 22,000 GPM SYSTEM HEAT (REG MAX) EXCHANGERS WASTE NEUTRALIZING SYSTEM 100 GPM CLARIFIER WASTE MAX REGENERANT WASTE PRE-TREATMENT SYSTEM POLISHING REGENERATION CLAR I FI E R MAKE-UP .

DEMINERALIZER WASTE RADWASTE

% FOR SYSTEM NOT IN SYSTEM DECONTAMINATED CONTINUOUS OPERATION WASTES(FLOOR DRAINS>LAUNDRY)

CONDENSATE MAKE-UP AUXILIARY SYSTEMS RADWASTE SHIPPING CONTAINERS.

MAKE-UP IOO GPM MAX CITY OF DOMESTIC OSWEGO FLOW METER

~~ WATER USAGE SANITARY WASTE TREATMENT TO LAKE ONTARIO 3300 GPD AVG SYSTEM 2400 GPD(NORMAL)

SUPPLY 3800 GPD (MAX )

FIGURE 3.4-I WATER USAGE FLOW DlAGRAM

3.5 DESCRIPTION

OF COOLING WATER SYSTEM DESIGN Circulating water for Nine Mile Point Unit 1 is drawn from Lake Ontario into a submerged inlet, circulated through the condensers, and returned to the lake through a submerged hexagonal-shaped discharge structure. Figure 3.5-1 shows the locations of the existing structures for Unit in Lake Ontario.

1 3.5.1 Intake System Cooling water for Unit 1 is withdrawn from Lake Ontario, at a rate of 600 cfs (268,000 gpm) into a hexagonal intake structure located in a water depth of approximately 18 feet below the mean lake surface elevation of 246.0 feet (USLS'935 Datum) - It is designed and located to minimize the possibility of fish entering it as discussed in Section 5.1. The structure lies about 850 feet from the existing shoreline and is connected to the screenwell by a tunnel beneath the lake bed as shown in Figure 3.5-1.

Structural details of the intake design are shown in Figures 3.5-2 and 3.5-3. The structure is covered by a roof of sheet piling supported on steel beams and each of the six sides has a water inlet about five feet high by ten feet wide, with the inlet openings guarded by galvanized steel racks. This design provides for water to be drawn equally from all directions with a minimum of disturbance and with no vortex at the lake surface, and also prevents the entrance of unmanageable flotsam to the circulating water system. The velocity at the intake openings is approximately 2 fps when the station operates at maximum output.

There is about a 16-foot clearance between the top of the structure and the lake surface at mean low water level (assumed to be 244.0 feet, USLS 1935 datum).

The intake tunnel runs under the lake from the intake structure to the screenwell and pump house located on shore, adjacent to the turbine building. The water drops through a vertical concrete-lined shaft to a concrete-lined tunnel through which it flows to the foot of a concrete-lined vertical shaft under the forebay in the screenhouse. The foot of this shaft contains a sand trap to catch and store any lake-bottom sand which may wash over the sills of the inlet structure. The tunnel'has a cross-sectional area of approximately 74 sq ft, which yields a tunnel velocity of approximately 8.0 fps.

There are two main condenser circulating water pumps in the pump house, with a total capacity of 250,000 gpm. They take suction from three separate interconnected bays in the screenwell.

Before reaching the pumps, the circulating water passes through trash racks and traveling water screens. The system design is flexible and partial flow can be maintained during system

3. 5-1

N BUILDING NORTH g$ 5 INTAKE g ggO II II I

II II IO 07 I

II 2.'E II I

II II II DISCHARGE ~ I o II 0

0 > IIII 0

~g5 0 II 0

g,O I II ih II STONE DIKE EL. 263.0

~ SCREEN AND PUMP HOUSE NOTE: 0 IOO 200 300 400 ALL ELEVATIONS ARE REFERENCED TO USLS I935 DATUM SCALE I = 200 FIGURE 3. 5 I PL A N - CIRC UL AT ING WAT ER SYSTEM

HOUSE E. INTAKE LOW W.S. EL. 244.0 KAK. W.S.

EL.242,0'CREEN ~STONE DIKE EL. 228.5 EI.. 222.5 I

II 00 INTAKE TUNNEL (LOOKING EAST) 0 SCREEN HOUSE DISCHARGE EL. 263.0'TONE DIKE ETS 44 EL.

234.0'L GAEL.230.0 a aa o a SECTION I- I SECTION 2-2 I 0 5 IO 0 S IO 565 SCALE-FEET SCALE-FEET DISCHARGE TUNNEL (LOOKING EAST)

NOTESI ALL ELEVATIONS ARE REFERENCED TO USLS I935 DATUM 400 HORIZONTAL SCALE-FEET I 00 200 VERTICAL SCALE-FEET EXCEPT WHERE SHOWN FIGURE SS-2 PROFILE- CIRCULATING WATER SYSTEM

L O

hl O I I N TUNNEL 0 TUNNEL lO O II I I Ig I

O CV ll II 22-6-I 27-82 PLAN PLAN LW EL 244.0 LW EL 244.0 O

0 O

EL 228 6 6' EL 250.0 EL 222 EL 227.0 EL 219 6 CV 1

't 77lf O

I stl E LE VATI ON ELEVATION I NTAKE DISCHARGE 0 I 0-0 20.0 SCALE-FEET ALL ELEVATIONS ARE REFERENCED TO USLS 1955 DATUM FIGURE 5.5-3 INTAKE BI DISCHARGE STRUCTURE DETAILS

1' maintenance and servicing.. Figure 3.5-4 is a.schematic diagram of the screenwell.

There are also two service water pumps in the screenwell pump, house which..operate separately, each rated at 22,000 gpm but.

generally throttled to 18,000 gpm single-pump operation..'lso located in this pump house are two 2,500 gpm, 125 psig vertical turbine fire pumps. One pump, is driven by an electric motor and the other by a separate diesel engine.. These pumps are tested once a week for .at least 30 minutes.

3.5 2 Discharge System Structural details of the discharge design are shown in Figures 3.5-2 and- 3.5-3., Water is returned to the .lake at a point about 0. 1,mile ,off-shore through a bell-mouthed outlet surmounted by. a hexagonal-shaped concrete discharge structure.

The top of this structure, is about 4 feet above .lake bottom and 8 1/2 feet below the. lowest anticipated lake level.. The geometry of the structure closely resembles the inlet structure, although reduced in size.. The six exit ports are about 3 feet high by 7 feet 4 inches, feet wide.

Unit 1 operates at rated output with a main condenser flow of 557 cfs'250,000 gpm) and a maximum temperature rise of 32 F, and a service water flow of 40 cfs (18,000 gpm) with .a maximum temperature rise of 20:F.. To&1 flow for Unit 1 is thus approximately 600 cfs (268,000 gpm), with a temperature .rise of 31.2 F. These water flows and temperature increases remain essentially the same throughout the year. The seasonal temperature variation of the cooling water temperature at the intake is approximately 33 to 77 F.

A discharge tunnel, approximately 78 sq ft in cross-section, runs under the. lake from the screenwell to the discharge structure as shown in Figure 3.5-1. The design velocity in the tunnel is approximately 8 fps. The discharge structure is located at a point about 535 feet north of the screenwell, in a depth of approximately 12 feet below the mean lake level of 246.0 feet (USLS 1935 Datum) .

The total time of travel of water through the cooling system is about 6 minutes of which passage through the condenser alone is about 14 seconds and travel time from the condenser to the exit from the discharge structure is 3 minutes.

Circulating water algicide treatment has not been required during the operation of Nine Mile Point Unit 1. The silt (fine glacial till) content in the raw lakewater has proven sufficient to prevent attachment of biological growth on exposed surfaces (condenser tubes) of the cooling system.

3 5-2

DISCHARGE SHAFT INTAKE SHAFT II II II I

I I

I TRASH RACKS (lil SCREEN BACKWASH COLLECTION RECEPTACLES DISCHARGE Q TRAVELLING WATER FLUME SCREEN 0 0 SERV ICE WATER AREA

+ f CW PUMPS FIGURE 3.5-4 SCHEMAT IC DIAGRAM OF SCREENWELL

The traveling screens are backwashed with about 2, 400 gpm of service water on an automatic time cycle of 3 minutes duration every 30 minutes. Screen washings are sluiced into the discharge tunnel. Trash racks ahead of the screens deposit their collected materials into receptacles. This debris is trucked away and disposed of at a state-approved disposal site.

With the construction of the propesed Unit 2, the circulating water system for Unit 1 would be modified to a combined discharge system for both units, as described in the Nine Mile Point Unit 2 Environmental Report (Ref. 27).

3. 5-3

0 3~ 6 RAINASTE SYSTEMS The radioactive waste systems collect, treat, and dispose of anticipated and potential radioactive wastes in a controlled and safe manner.

The original radioactive waste (radwaste) system as described in the Final Safety Analysis Report (FSAR) was designed to comply with the limits set forth in 10 CFR Part 20 of the AEC regulations, which were in effect when Unit 1 was constructed.

Modifications are planned to upgrade the original radwaste system to conform with the limits established in the proposed Appendix I to the 10 CFR PM 50 guidelines. The radwaste systems consist of a gaseous, a liquid, and a solid radwaste system. Each of these systems is discussed in this section both as described in the FSAR (original system design) and as planned to be upgraded.

itit is is The radioactive input to the radioactive waste systems is due to:

a. Activation products resulting from irradiation of reactor water impurities.

b. Fission products resulting from use-related perforations in the fuel cladding or uranium contamination within the reactor coolant system.

3.6. 1 Waste Processing Systems Radioactive wastes resulting from station operation are classified as gaseous, liquid, and solid. These three major categories of radioactive wastes are defined as follows:

a. Gaseous Radioactive Wastes Gases or airborne particulates vented from reactor or turbine .equipment containing radioactive material.

b. Liquid Radioactive Wastes Liquid received directly from portions of the reactor coolant system or liquids which can become contaminated from contact with radioactive material within the station

c. Solid Radioactive Wastes Solids from the reactor coolant system, solids in contact with reactor coolant system liquids or gases, solidification of liquid waste, and solids used in reactor coolant and steam and power conversion system operation or maintenance.

Flow diagrams for the gaseous radwaste system are shown in Figure.3.6-1 for the original system design and in Figure 3.6-2 for the upgraded system design. Flow diagrams for the original and upgraded liquid and solid radwaste system designs are shown in Figures 3.6-3 and 3.6-4, respectively.

3. 6-1

3.6.2 Gaseous Radioactive Waste System 3.6.2. 1 Sources of Radioactive Gas The principal sources of potentially radioactive gas which exist in the unit are listed below and described in the sections that follow:

Process offgas Mechanical vacuum pump offgas Drywell ventilation Turbine gland seal Miscellaenous building service releases 3.6.2.1.1 Process Offgas Noncondensible radioactive process offgas are continously removed from the main condensers by the steam jet air ejectors. This is the major source of radioactive gas and is greater than all other sources combined.

The condenser offgas normally contains activation gases, principally N-16, 0 19, and N13. The gases N16 and 0-19 have short half-lives and decay readily. N-13 with a half-life of 10 minutes is present in small amounts. The process offgas also contains the radioactive noble gas parents of the biologically significant Sr 89, Sr 90, Ba-140, and Cs-137. The concentration of these noble gases depends on the amount of tramp uranium in the coolant arid on the cladding surfaces (usually extremely small) and on the number and size of fuel cladding performations.

Table 3.6-1 gives the estimated activity flow rates after 30 minutes of holdup for the original system and after 20 days of holdup for xenon and 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> for krypton for the upgraded system.

3. 6. 2. 1.2 Mechanical Vacuum Pump Offgas During unit start-up, air is removed from the main condenser by a mechanical vacuum pump. This vacuum pump discharges to the stack through suitable piping and is in service during unit start-up when little or no radioactive gas is present.

3. 6-2

3. 6. 2.1.3 Drywell Ventilation Exposure of the drywell air to neutron leakage fluxes around the reactor vessel results in some activation products. Activity may also be introduced into the drywell atmosphere by the venting of the primary system relief valves into the suppression chamber.

The drywell forms a closed system that may be purged with normal reactor building air, if necessary, when access is required. The drywell can also be vented during start-up to accommodate the expansion of air as the temperature increases. This gas is discharged to the main stack.

Table 3.6-1 Estimated Quantities of Fission Product Isotopes Released to the Environs from the Offgas Proce ssing System Activity Activity Plow Rate Flow Rate of of Upgraded System After Original System 20 Days Holdup for Xenon After 30 Minutes and 33 Hours for Krypton

~Isoto es Half Life Holdu uCi/sec uCl./sec Kr-83m 1 86hr 750 0. 02 Kr-85m 4.4 hr 1i450 8. 06 Kr-85 10.76 yr 4 4 0 Kr-87 76 min 3, 750 Kr-88 2.8 hr 4~ 500 2. 00 Kr-89 3e2 ml.n 45 Xe-131m 12 days 4 1 17 Xe-133m 2.3 days 70 0. 16 Xe-133 5 27 days 2f 050 144. 86 Xe-135m 16 min 1,725 Xe-135 9.2 hr 5, 500 Xe-137 4.2 min 1f 675 Xe-138 17 min 5 250 25~0004 158. 27

~For conservatism, a value of 50,000 uCi/sec was used as a basis for calculating off-site radiation exposures.

3.6.2.1.4 Turbine Gland Seal Main steam is used for the turbine gland seals of Nine Mile Point Unit 1. Although a larger volume of gases is handled by this system than by the process offgas system, the total activity discharged is considerably less because of the relatively small amount of steam leaking through the gland seals. The larger volume results from dilution of the steam with the air that leaks into the gland seals. Since the activities are low, the steam packing exhaust gases are held up for only about 1.75 minutes

3. 6-3

- I (essentially to allow N-16 and 0-19 to decay) and then exhausted to the stack. (See Figure 3.6-1.)

3.6.2.1.5 Miscellaneous Building Service Releases Ventilation system exhausts for the turbine building, reactor building, and the waste building are individually monitored by radiation detectors to locate areas of activity before being discharged to the stack.

High efficiency particulate absolute (HEPA) filters are installed in the exhaust duct of the radwaste building, in radiochemical laboratory hoods, and in miscellaneous tank vent s and decontamination area exhausts. These HEPA filters remove airborne particulate activity before discharge to the main stack, as seen in Figure 3.6-1.

3.6.2.2 Description of the Original Offgas System The process offgas is a major source of gaseous radioactive waste. In the original system, process offgas is removed from the main condenser by a steam jet air ejector which provides sufficient pressure to move the offgas through the system. The estimated volume flow rates of offgas handled by the original system are:

Dry air 22 scfm H2 79 scfm 02 39 scfm Water vapor Saturated Noble gases Negligible Total 140 scfm These quantities were used as the design basis for the offgas system. The system was also designed to accommodate variations in flew rates without compromising the systemIs cleansing abilities. The system includes~the equipment described below and is shown in Figure 3.6-1.

3. 6. 2.2. 1 30-Minute Delay Pipe The 30-minute delay pipe allows for the ho dup and decay of short-lived radioisotopes in the process offgas. It~also allows for the agglomeration of particulate daughters so that they may be removed by filtration.

3.6. 2 2 2 Offgas Filter (After Filter)

The original process offgas filters are high efficiency ~'absolute type" (HEPA) filters which remove solid decay products before the gas is released to the stack. Based on a Dioctyl-Phthalte (DOP)

3. 6-4

test, this type of filter has a 99.97 percent efficiency for particulates larger than 0.3 micron.

3.6.2.2.3 Radiation Monitors Two flow-through offgas radiation monitors are provided to monitor the process offgas in the gaseous waste system as seen in Figure 3.6-1. One radiation monitor is located at the entrance to the 30-minute holdup piping. This monitor would automatically close valves at the piping exit if the offgas activity is in excess of the allowable release limit. A second monitor continuously measures the gaseous activity discharged from the stack.

3.6.2.2.4 Stack The building service ventilation exhausts, together with that of the offgas system, the gland seal vent, the mechanical vacuum pump system, and the emergency ventilation system, are released through the main stack.

The stack is approximately 350 feet high and about 2 1/2 times the height of surrounding buildings, and has a normal effluent release volume of about, 130,000 scfm. The stack is a reinforced concrete structure which is designed to ensure the best mixing and dilution of the station offgases. This is accomplished by introducing higher activity waste gas (i.e., process offgas and gland seal exhaust) into the stack at a point 20 feet above the entrance of the main gas stream containing negligible activity (i.e., building ventilation exhausts) .

3.6.2.3 Description of the Upgraded Offgas System The proposed upgraded waste gas system is shown in Figure 3.6-2 and will include the additional equipment described below.

The upgraded system provides a minimum of 20 days decay period for xenon isotopes and 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> for Krypton isotopes. The design bases are an assumed condenser air inleakage of 22 scfm and a 820,000 uCi/sec continuous activity flow rate for noble gases measured after a 30-minute decay period. This design basis value is recognized to be a conservative one which is not expected to be approached or exceeded in station operation. Thus, the activity flew rate used as a design basis is higher than the activity flow rate of 25,000 uCi/sec given in Table 3.6-1, which is a value considered more representative for normal station operation (see Section 5.2. 1) .

3.6.2.3.1 Catalytic Recombiner The process offgas from the main condenser air ejectors will be diluted with steam to a maximum hydrogen concentration of 4 percent by volume at all power levels. Radiolytic hydrogen and

3. 6-5

oxygen will catalytically react in the recombiner to form water, thus eliminating the hydrogen hazard and reducing the volume of gas to be handled in the rest, of the offgas system. The hydrogen concentration downstream of the recombiner will be less than

0. 1 percent at a low airflow condition of 4 scfm at all power levels.

3.6.2.3.2 Condenser The gaseous waste system condenser will be designed to provide the following functions:

a. Condense out the excess steam provided in the steam jet air ejectors for hydrogen dilution

b. Condense out the water of reaction formed in the catalytic recombiner

c. Remove the exothermic heat of reaction which takes place in the recombiner 3.6.2.3.3 Delay Pipe In the upgraded system, the first two-thirds of the original delay pipe will be used to provide 2 1/2 hours delay after the recombiners. The final one-third of the original pipe will be used after the charcoal adsorbers to provide an additional delay of 1 1/2 hours.

3.6.2.3.4 Dehumidification System The discharge from the 2 1/2-hour delay pipe will flow through freeze out chillers. In passing through this dehumidification system, the moisture content of the gas stream will be reduced so that essentially a <<dry<< gas is produced before charcoal adsorbers.

it reaches the 3.6.2.3.5 Pre-Adsorber The discharge from the freeze-out chillers will flow through pre-adsorbers which remove solid decay products.

3.6.2.3.6 Charcoal Adsorbers The discharge from the pre-adsorber will flow through the charcoal adsorbers which will provide for selective adsorption of the xenon and krypton isotopes from the bulk carrier gas (essentially air) . This adsorption will delay gas flow and permit the xenon and krypton isotopes to decay in place thereby reducing activity releases to those indicated in the last column of Table 3.6-1. A holdup time of 20 days for xenon and 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> for krypton will be provided.

3. 6-6

3.6.2.3.7 Vacuum Pump The liquid ring type vacuum pump will be installed to pull the offgas through the recombiner charcoal adsorber system. This allows the system to operate at a negative pressure which prevents the leakage of any radioactive gases into the building.

The original offgas filters (Section 3.6.2.2.2) will serve as afterfilters to remove any solid particulates or charcoal fines carried out of the charcoal adsorbers before they reach the vacuum pumps. The effluent from the vacuum pumps will discharge to the stack.

3.6.3 Liquid Radioactive Waste System The liquid radioactive waste system collects, monitors, and processes for reuse or disposal all potentially radioactive liquid wastes in a controlled manner.

The original system has the capacity and capability of processing the quantities and activities of liquid wastes resulting from normal operation and maintenance. Discharges from the original system meet the requirements of 10 CFR Part 20 and are well below the MPC. (1.64 percent of allowable, average value for period July through December, 1971.)

The proposed upgraded system will have the capability of processing the liquid waste such that most of the liquid can be reused and such that waste discharges comply with the proposed Appendix I to the 10 CFR Part 50 guidelines.

The liquid radwaste system is divided into several subsystems so that the liquid wastes from various sources can be segregated and processed separately. Cross-connections between the subsystems provide additional flexibility for processing of the wastes by alternative methods. The wastes are collected, treated, and disposed of according to their conductivity, suspended 'olids content, and/or radioactivity. Operation of equipment is primarily by manual valve setup and start, with automatic stop.

Simplified flow diagrams are shown in Figure 3.6-3 for the original system and in Figure 3.6 4 for the upgraded system.

3.6.3.1 Description of the Original Liquid Radwaste System 3.6.3.1. 1 Waste Collector Subsystem Wastes entering the waste collector subsystem have variable activity levels, dependent on their source, and relatively low Radioactive conductivity (generally less than 50 umho/cm).

materials are removed from these wastes by filtration (insolubles removal) and ion exchange (soluble and colloidal removal).

Following batch sampling and analysis, the processed liquids are either returned to the condensate storage tanks for reuse in the plant, or reprocessed.

3.6-7

Waste collector subsystem influents include drains from piping and equipment containing high quality wate r wastes from the reactor coolant system, condensate system, feedwater system, offgas system drains, and associated auxiliaries. Influents also include reactor expansion drainage via the reactor water cleanup system, selected equipment drains, low conductivity wastes from the condensate demineralizer regeneration system (resin transfer and backwash water), and regenerant evaporator distillate.

Nonroutine process effluents, such as water of relatively high radioactivity concentration (e.g., greater and 10-~ uCi/cc) are recycled to the waste collector tank or other appropriate subsystems for reprocessing. Sample analysis indicates which method is most appropriate. (Refer to Section 3.6.3.5.)

3.6.3.1.2 Floor Drain Subsystem Potentially high conductivity wastes are collected in thereactor floor drain collector tank from radwaste building sumps, building floor drain sumps, turbine building floor drain sumps, laboratory drains, centrifuge liquid effluent, and decontamination area drains. Floor drains are a source of recoverable water, if not contaminated with chemicals prior to collection. Floor drain wastes are processed through a filter to produce filtrates suitable for either recovery or discharge. The filter sludge is packaged for offsite disposal as described in Liquids which are to be discharged are Section 3'.6.4. 1.

collected in the floor drain sample tanks, sampled, and, after suitable monitoring, pumped to the circulating water discharge tunnel at a flow rate controlled to obtain substantial dilution.

Laundry wastes are collected in laundry drain tanks, sampled, and, after suitable monitoring, are pumped to the circulating water discharge tunnel at a controlled rate.

3.6.3.1.3 Regenerant Chemical Subsystem Chemicals resulting from the regeneration of condensate demineralizers are collected, neutralized, and sampled in the waste neutralizer tank. The neutralized chemical solution is then processed through the waste concentrator (evaporator) .

Concentrator bottoms are collected in the concentrate waste tank and then pumped to the mixer in the radioactive solid waste system (Section 3.6.4) . Concentrator distillate is routed to .the waste building equipment drain tank for transfer to the waste collector subsystem (Section 3.6.3. 1. 1) .

3.6.3.2 Description of the Upgraded Liquid Radwaste System The following proposed modifications to the original system will be made to lower the release of activity in the liquid waste effluent from the station {see Figure 3.6-4) .

3. 6-8

0 Additional piping has been added to allow increased flexibility in processing. The waste collector subsystem has been modified so that the floor drains from the drywell, which have proven to be of high quality, will flow directly to the waste collector tank.

A new waste concentrator will be installed for the floor drain subsystem or high conductivity waste system. Floor drains may be processed either through the filter or concentrated in the waste f

evaporator as required to produce distillate s suitable or recovery.

In addition, a traveling belt filter has been installed. This filter will reduce the backwash water from the floor waste collector filters. It should also reduce the operation of drain and the waste centrifuge in the solid waste handling section which, in turn, will result in a reduction of liquid radioactive waste from the floor drain waste processing system.

An ultrasonic resin cleaner will also be installed to clean the condensate demineralizer resins to reduce the frequency of chemical regeneration. It will reduce the 'mount of resin regenerant liquids presently processed by the waste concentrator.

3.6.3.3 Original and Upgraded System Operational Analysis Table 3.6-2 supplies the following information for both the original and upgraded design for each major flow path of the liquid and solid radwaste systems:

Normal time period in days per,batch Volume per normal batch Average daily volume Maximum activity concentration.

Only significant contributions to volume and activity are considered. The following bases were used to develop the quantities estimated in Table 3.6-2.

1. For conservatism, a value of 820,000 uCi/sec (at 30-minutes decay) has been used as the design basis, and a value of 50,000 uCi/sec has been used in calculating radiation exposures in the station environment.

2 A reactor water fission product concentration exclusive of tritium of about 3.0 uCi/g and a <carryover" in reactor steam equivalent to 1.0 percent for halogens and

0. 1 percent for all other isotopes by weight.

3. A 20-hour minimum decay for all streams based on recycle of water content of most liquids, sump and tank sizes, and daily volume.

3. 6-9

4. Credit for decontamination due to concentrator and demineralizer processing capability of about 5,000 and 1,000, respectively. The actual design capability is as follows:

A design decontamination factor (DF) for the new waste concentrator of about 2,250 calculated in the following manner:

Va or disen a in X de-entrainment X se aration DF Feed concentration ratio Where numerical values are:

900 X 1000 X 2 DF = 800 A design decontamination factor for the existing waste concentrator of 2,250 based on a similar analysis.

A design decontamination factor for the mixed bed waste demineralizer of 20 for Cs, Y, Nb, and Zr, and of 100 for other isotopes, based on control of intermediate activity and flush bed (nonregenerative) type units.

3 6-10

0 Table 3. 6-2 Fundamental Liquid and Solid Radwaste System A. Ori inal Station Desi n Item( ~) 2 3 4 5 6 1 7

Normal time 2.8 1 05 1.05 1.05 1.05 0 83 0.83 to 0.83 to 1.6 0. 44 period per 1.6 1 6 batch, days Volume per 35,000 24,000 24, 000 24,000 24,000 9,600 9,600 to 9,600 to 14,600 9,600 normal batch, 14i600 14 600 gal Average daily 12,500 10e400 22e900 22m 900 31e600 31r600 8e500 11 F500 20,800 20,800 9,300 21,800 volume g gal/day Maximum 0- 02 0.045 0. 025 0. 023 2. 3x10-< 2.3x10-s 2x10-* 1. 95x10-~ 0. 4 1.7x10-> 0.4 1x10-~

activity, concentration, uCi/cc Normal time 2.8 0.46 1 1 1 1 period per batch, days Volume per 24,360 10,500 10,500 2,550 2,550 9s600 9,600 3,000- 1,000 500 50 50 normal batch, gal Average daily 8,700 20,000 F 000 1~000 500 50 50 volume, gal/day Maximum activity, 0 4 0 39 5.8x10-4 0.12 0.12 <1x10-< 1.7x10-~ 77 1x10->>1x10-s 1x10-4 0 1 concentration, uCi/cc

i Table 3.6-2 (Contend)

B.. raded Station Design.

Item~ <) 2 3 4 5 6 ~ 9 Normal time 14 0 33 0 33 0.33 0.33 period per batch, days Volume per 35,000 24~000 24~000 24~000 24,000 T,000 normal batch, gal Average daily 2,500 63,000 71,975 71,975 71,975 71,975 1,000 volume, gal/day Maximum 0 025 0 11 0. 039 0. 039 3. 9x10-~ 5x10-~ 2x10-~

activity,

.concentration, uCi/cc It.em- 10 1 2 3 4 5 Normal time 5.6 1 8 3 5 3 ~5 3 8 3 8 3.8 period per batch, days Volume per 8,400 9~600 9~600 9~600 '~600 9,600 9~200 900 normal batch, gal Average daily 1,500 4,000 5,300 2,775 2,700 2,525 2,525 2,425 100 ~

volume, gal/day Maximum 0.045 2.6x10-~ 2.6x10-~ 2.6x10-~ 2.3x10-~ 2 ~ 6x10-> 2.6X10-~ 8.8x10-4 12 activity, concentration, uCi/cc

0-0

Table,3. 6-2 Cont d

~

B. Upgraded Station Design (Cont'd)

Item~ >> 0 1 2 4 0 Normal time 3. 2 .24 4 6.6 6.6 6.8 51 17 3 6 period per batch, days Volume per 9,600 24i360 10s500 10'00 10i500 2e550 2e550 9c600 9,600 .

normal hatch, gal Average daily 3,000 1,000 1,600 1,600 1,550 50 150 2,700 volume, gal/day Maximum :1x10 > 3 0 2.9 2.9 5 8x10-> 20 15. 4 <1x10-~ 2. 3x10---

activity, concentration, uCi/cc Item.

Normal time 3 33 period per batch, days Volume per 1,300 1i 000 500 50 50 normal batch, gal Average daily 5 1,300 300 500 50 50 volume, gal/day Maximum 77 0.1x10-~ <1x10-~ 1x 10=~ Q. 1 activity, concentration, uCi/cc

0 0

5. Activity concentrations in condensate demineralizer regenerants result from a two-week interval between chemical regenerations for the original system, and a three-month interval for the upgraded system due to ultrasonic cleaning of the ion exchange resins.

6. For the upgraded system, activity concentrations in ultrasonic -resin cleaner waste due to collection of corrosion/activation products over a two-week period and subsequent complete removal from the condensate demineralizer resin.

7. Filter decontamination factor of about 5. 0 for corrosion/activation products.

In addition, the following processing assumptions have been made with regard to Figure 3.6-4 and Table 3.6 2 for the upgraded system:

All drywell and turbine equipment drains have been routed to the waste collector tank.

2 Up to 92 percent of all normal waste collector influent liquid will be recycled to the condensate storage tanks.

About 3 percent of the condensate demineralizer chemical regenerant will be packaged and about 3 percent of condensate which could otherwise be recovered is assumed to be discarded from the plant due to mismatch between processing and plant inventory requirements. As a conservative estimate of the effects of start-up and inventory mismatch, about 10 percent the influent volume shown in Table 3.6-2 is considered discharged.

3 Except for initial large quantities of floor drains resulting from shutdown or initial start-up, most floor drains can be recovered. Occasionally, conductivity and radioactivity will be sufficient to warrant evaporation.

4 The majority of radioactivity entering the system will be contained in the condensate demineralizer regenerant chemicals. Use of ultrasonic resin cleaning will result

'in long intervals between chemical regenerations, thus substantially reducing radioactivity entering the system because radio isotopes will decay on the condensate demineralizer resin, rather than in the radwaste system.

3.6.3.4 Original and Upgraded System Operational Evaluation

3. 6.3.4. 1 Regenerant Chemicals Subsystem The bulk of radioactivity processing has been identif ied as regeneration chemicals from the ccndensate demineralizer system.

These chemical wastes are evaporated in both the original and

3. 6-14

I upgraded systems The concentrated liquids removed as bottoms from the waste concentrator (evaporator) are packaged for offsite shipment as described in Section 3.6.4. Distillate produced from the evaporator is routed to the waste collector tank for recovery as condensate, hence, little or no releases result from the treatment of regeneration chemicals. When releases of condensate are deemed necessary to maintain a water balance within the station, preference will be given to release of condensate which has a minimum activity. In the upgraded system the use of the ultrasonic resin cleaner for the condensate demineralizer resins will result in longer intervals between regenerations and hence a decreased liquid contribution to the regenerant waste subsystem.

3.6.3.4.2 Waste Collector Subsystem The major source of waste collector volume is from the equipment drains. Condensate demineralizer backwash equipment drainage and phase-separator tank decant are intermittent in normal operation.

With the upgraded system, the ultrasonic resin cleaning will supplement resin regeneration. Some equipment drainage will be routed to the condenser hotwell on conductivity control, and cleanup filter/demineralizers will require infrequent replacement of resins after start-up.

The upgraded system includes a new traveling belt filter which has been installed to reduce the backwash water from both the existing floor drain and waste collector filters, as well as supplement the operation of the existing centrifuge in the solid waste system. This filter is designed to discharge damp solid waste as a cake, thereby reducing the recirculating water flow in the system that would otherwise result from normal backwash.

3.6.3.4.3 Floor Drain Subsystem This subsystem has influent activity, conductivity, and volume that varies widely with a point in reactor cycle. During start-up, floor drainage contains high conductivity from the general cleanup of the station, leaks from equipment, or washdown from start-up maintenance. These wastes do not contain significant radioactivity. They are filtered and held for- discharge pending the outcome of sampling and analysis. In the upgraded system, if activity is sufficient to warrant evaporation, a new waste concentrator is employed as needed. Filtration and subsequent demineralization in the waste collector subsystem is provided to allow recovery as condensate. With the upgraded system, the operation of the ultrasonic resin cleaner on a regular basis will allow crud from the condensate demineralizer resins to be collected at a concentration too high to allow efficient filtration in the waste collector subsystem. It is anticipated that the low flow per unit area and precoat stability characteristic of the traveling belt filter will be more amenable to cycle interruption and greater crud removal per pound of 3 6-15

precoat. However, unless fission pxoducts or solubles are adsorbed on the crud, the quality of the filtrate for recovery as condensate should remain high.

An estimate of the conditions which would guide the disposition of batches of floor drains are as follows:

1. Greater than 1, 000 umho/cm conductivity: evaporate and recover distillate.

2. Less than 10-4 uCi/cc fission product activity and greater than 50 umho/cm conductivity:. filter and discharge.

3. Greater than 10-~ uCi/cc fission product activity and less than 50 umho/cm conductivity: filter, demineralize, and recover or discharge.

0. Greater than 10-4 uCi/cc fission product activity and greater than 50 to 100 umho/cm conductivity: evaporate, demineralize, and recover.

3.6.3.5 Control of Waste Activity Movement In the upgraded system, the primary method of restricting the movement of waste activity will be to minimize the generation of waste volume prior to and within the radioactive waste system.

The major reduction in regenerant chemical volume and activity which will be afforded by use of ultrasonic resin cleaning of condensate demineralizer resin is the best example of how the system design capability will be improved. 'nother will be the routing of high quality (low conductivity) equipment drains to the hotwell of the condenser instead of to the waste collector subsystem. However, capacity will be retained in the waste collector subsystem in case conductivity of equipment drains is higher than normal. The use of a dry cake discharge traveling belt filter will reduce the need for processing of filter backwash. Wherever possible, condensate, used for flushing or transport of solids, such as clean resin beads or spent filter/demineralizer precoat, will be reused.

Direct packaging of decontamination solutions where possible will free equipment from excessive flushing to remove materials which would make subsequent, recovery of influent water difficult.

In summary, wastes will be combined to make the most effective use of processing equipment available and to minimize the number of times that a batch of waste must be handled prior to final disposition. The recirculating load of water within the radioactive liquid waste system will be restricted to the minimum possible.

3. 6-16

0 0

3.6.3.5.1 Release of Processed Waste Liquid wastes are released in the discharge tunnel from one of two waste discharge sample tanks on a batch basis. Each batch is analyzed prior to release for gross beta gamma activity and the resulting activity used to determine the discharge flow rate.

The integrated total activity discharged to the lake is recorded.

Complete isotopic analyses of composites or retained samples is done in accordance with the procedures outlined in AEC Safety Guide No. 21. Detailed administrative records of all radioactive liquid releases are maintained. Table 3.6-3 presents the discharge tunnel concentrations for significant isotopes from Unit 1 for both the original and upgraded systems. About 20 Ci per year .of tritium will be released from the station. Initially tritium releases for the upgraded systemwaste design will be lower than for the original system because less water will be discharged. However, reactor water tritium levels will build up to a new higher equilibrium concentration which is expected to offset the reduced waste water flow. Therefore, is it is assumed for both that the total curies of tritium released the same the original and the upgraded station designs. An average release rate of about 21,750 gallons of water per day for the original system and about 3,000 gallons of station water per day for the upgraded system is finally released from the after being processed in its respective liquid radwaste system.

The figures in Table 3. 6-3 for fission product concentration are based on an offgas activity flow rate of 25,000 uCi/sec at 30-minutes delay. However, for conservatism, an offgas activity flow rate of 50,000 uCi/sec was used for calculating radiation exposures in the station environment, and a value of 820,000 uCi/sec was used as a design basis.

3.6.4 Solid Radioactive Waste System The solid radioactive waste system is designed to collect, process, package, and provide temporary storage facilities for solid was'tes prior to shipment for offsite disposal as discussed in Section 3.6.5.4.

The system is designed to provide collection, processing, packaging, and storage of solid wastes resulting from normal station operations such that operation and availability of the station is not limited.

In addition, both the original and the upgraded system design:

1. Includes equipment and instrumentation, and utilizes administrative controls such that the solid radioactive wastes collected and prepared for offsite shipment do not result in radiation exposures to station personnel in excess of the limits set forth in 10CFR Part 20.

3. 6-17

2. Utilizes, where necessary, shielded casks which conform to 10 CFR Part 71 Packaging of Radioactive Material for Transport.

3 6-18

Table 3.6-3 Concentration of Significant Isotopes in the Discharge Tunnel of Nine Mile Point Unit 1 for Both the Original and the Upgraded System A Corrosion Products Discharge Conc.

DC uCi/ml Dischar e Conc./MPC

~zsoto e Oricrinal ~Uraded Oricrinal ~Uraded Mn-56 0. 205E-134 0- 205E-9 Ni-65 0. 112E-15 0. 1 12E-11 Na-24 0.238E-09 0. 818E-12 0. 791E-05 0. 272E-7 Zn-69m 0 11 1E-13 0- 188E-9 P-32 0. 266E-12 0 133E-7 Cr-51 0 366E-07 0. 792E-1 1 0. 184E-04 0. 395E-8 Fe-59 0 123E-07 0. 136E-11 0. 245E-03 0 271 E-7 Co-58 0. 136E-07 0 886E-10 0 151E-03 0. 980E-6 Zn-65 0. 313E-11 0 191E-9 Ag-110m 0. 113E-11 0. 374E-7 Co-60 0. 228E-07 0. 995E-11 0. 758E-03 0. 316E-6 B. Fission Products I-134 0. 160E-18 0. 441E-14 Sr-90 0. 994E-10 0. 352E-11 0.329E-3 0. 117E-04 Cs-137 0. 569E-8 0 370E-11 0 284E-3 0. 185E-06 I-132 0. 323E-09 0. 397E-05 I-135 0. 763E-11 0 190E-05 I-133 0.77E-09 0. 880E-10 0.770E-03 0. 880E-04 Np-239 0. 107E-09 0. 109 E-05 Mo-99 0.897E-09 0. 128E-10 0. 224E-04 0. 320E-06 I-131 0.465E-08 0. 243E-09 0. 155E-02 0. 810E-03 H-3 0.432E-07 0 432E-07 0. 142E-04 0. 142E-04

+Symbol E with signed numeral means exponent. of 10; e.g.,

0.205E-13 is equal to 0.205 x 10-~3.

3. 6.4. 1 Sources of Solid Waste Radioactive solid wastes resulting from station operation using either the original or the upgraded system are as follows:

a. Absorbed concentrated liquid wastes from the radwaste evaporator(s). Medium to highly radioactive (1 to 12 uCi/cc) .

b. Spent resins and filter sludge from the spent resin tank.

Medium to highly radioactive (1 to 12 uCi/cc) ..

3. 6-19

c. Solid wastes, such as paper, air filters, rags, etc. Low radioactive level (<0.1 uCi/cc or <100 mr/hr).

d. Solid wastes, such as control rods, fuel channels, etc.

High radioactive level ()100 mr/hr).

3.6.4.2 Processing and Handling Process liquids which are not suitable for disposal to the environment either because of ionic content or radioactivity are concentrated in the radwaste evaporator(s) . The concentrates are cooled prior to transfer to the packaging facilities, mixed with an adsorbent, loaded in containers, and stored for shipment.

Spent resins from the mixed bed demineralizers are flushed to the packaging facilities, dewatered, loaded into containers, and stored for shipment.

Filter sludge from the existing floor drain and waste collector filters is dewatered, transferred into containers, and shippedof offsite for disposal. Xn the upgraded system, the addition the traveling belt filter is designed to reduce the backwash water from both the existing floor drain and waste collector filters, as well as to supplement the operation of This the existing filterthe is centrifuge in the solid radioactive waste system.

designed to discharge damp solid waste as a cake directly to packaging facilities thereby reducing the amount of backwash water which must still be processed by the existing centrifuge.

Backwash from the reactor cleanup filter demineralizer is decanted in the phase separator tanks where the sludge is held for radioactive decay and then transferred to the spent resin storage tank. From there, the sludge is transferred to a shielded shipping container and stored for shipment.-

Low activity solid wastes are loaded into containers and stored for shipment.

High activity solid wastes are packaged in approved shipping containers and stored for shipment.

3.6.4.3 Performance Analysis The general plan for handling of solid wastes is to package all solid wastes in containers for eventual offsite disposal. The containers are shielded as necessary.

Process waste containing medium to highly radioactive solids are packaged with semi-remote handling equipment. These wastes consist of concentrated process fluids, filter sludges, and spent ion exchange resins.

3 6-20

The activity of most other categories, of solid wastes is low enough to permit handling of the packages by contact. These wastes are collected in containers located in appropriate zones around the station as dictated by the volumes of wastes generated during operation and maintenance. The containers are monitored periodically during filling to ensure that the dose rate does not, exceed a maximum of 200 mrem per hour on the surface before final packing. The containers are then sealed and moved to a controlled access enclosed storage area for temporary storage.

Packaged wastes are shipped to an approved offsite facility for storage or burial.

Contaminated equipment too large to be handled in the normal manner is treated as a special case at the time. Handling of such equipment depends upon the radiation level, transportation facilities, and available storage sites. Suitable operating procedures for decontamination, shielding, storage, and shipment of such items are developed and followed for these special cases.

3. 6.5 Transportation of Fuel and Radioactive Wastes

3. 6.5.1 Packaging Criteria Refer to Section 5.4.2 for possible environmental effects of radioactive material transport.

The shipment of all radioactive materials to and from nuclear power stations is covered in detail by Atomic Energy Commission (AEC) Regulation 10 CFR Part 71 and by Department of Transportation (DOT) regulation 49 CFR Parts 170-178. These regulations establish def inite performance standards which must be met if radioactive shipping container designs are to receive approval of the AEC and DOT. The standards are intended to ensure that a radioactive material package ha s suf ficient integrity to provide definite safeguard against radiation hazards during transportation. The package design criteria take into consideration the type, concentration, and amount of radioactive material to be transported in the given container.

All packaging must meet specified shielding requirements during normal shipment. The shielding requirements for >>exclusive use>>

vehicles, the normal shipment mode used by a nuclear power station, include maximum allowable radiation levels during normal shipping of (1) 1,000 millirem per hour at 3 feet from the external surface of the container, (2) 200 millirem per hour at the external surface of the vehicle, and (3) 10 millirem per hour at 6 feet from the vehicle.

In addition to these shielding requirements, the design of many of the containers must prove the container~s ability to withstand a variety of postulated normal use and accident conditions; The very stringent accident conditions apply to packages designed to transport large quantities of radioactive materials and >>fissile>>

3. 6-21

materials. A series of tests were formulated to simulate postulated accident conditions. These test conditions include, in sequence, a 30-foot free fall onto a completely unyielding diameter'steel surface, a 40-inch drop onto the end of a 6-inch bar, 30 minutes in a 1,475 F fire, and, finally, immersion tests, under 3 feet of water for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. At the completion of these the design package must have maintained sufficient shielding to limit radiation levels to 1,000 millirem per hour at 3 feet from the package surface. It is also stipulated that during and after the accident tests, the maximum release of radioactive materials will be limited to slightly contaminated package coolant and Maintenance of subcriticality, 1,000 curies of noble gases.

during both normal shipping and the postulated accident tests, is also a very important criterion placed upon casks designed to transport <<fissile<< materials.

This section is not intended to be comprehensive of all standards applicable to the transportation of radioactive materials.

Instead, the section~s purpose is to point out that these stringent regulations do exist. Packages conservatively designed for in accordance with these regulations must then be approved sufficient use by the AEC and DOT. These containers must provide safeguards for the environment against radiation hazards during both nuclear fuel and radioactive waste shipment.

3.6 5.2 New Fuel Shipping The reactor core of Nine Mile point Nuclear Station Unit 1 contains 532 fuel assemblies. The reactor is refueled annually and approximately 25 percent of the core or 133 fuel assemblies are replaced during each refueling period.

The new fuel shipping, containers have been designed and constructed to meet applicable AEC and DOT requirements. These packages are General Electric containers, models RA-1, EQ 2, and RA-3, known collectively as the RA packaging series.

Authorization to use these containers for nuclear fuel is contained in General Electric license SNM-1097 (Wilmington, North Carolina) Amendment 71-16. This license authorizes use of the RA packaging series under general licensing Section 71.7(b) of 10 CFR Part 71. These containers are designed to hold two new fuel assemblies and weigh 2,800 pounds in a loaded condition. to It the is considered that the loaded containers aie shipped station by legal weight truck. Due to weight limitations, each truck has the capacity for 16 containers loaded with 32 new fuel assemblies.

Each annual refueling requires approximately five truck shipments of new fuel. These shipments are routed by the most direct and fastest route to minimize the probability of accidents. The new fuel containers are furnished by the nuclear fuel supplier and, after the fresh fuel has been unloaded, the empty containers are returned to the fuel fabrication plant for reuse.

3.6-22

It should be emphasized that the which is basically a cushioned metal new fuel shipping container, container supported within an outer wooden box, is primarily designed to protect the new assemblies from physical damage due to normal handling and shipping vibrations. Because the new fuel, uranium oxide, contains no fission products or radioactive gases, the external radiation will be insignificant. The results of an accident, even if the fuel should be damaged, would be only an economic loss 3.6.5.3 Spent Fuel Shipping Due to the refueling requirements discussed in the previous section, there is an annual requirement to ship approximately 133 spent fuel assemblies. These assemblies are shipped by a fuel reprocessor, under contract, to one of the reprocessing facilities presently located in West Valley, New York; Morris, Illinois; and Barnwell, South Carolina.

A variety of spent fuel shipping casks are being designed and constructed to accommodate fuel assemblies of the type used in Unit 1. All of these casks are massive and their payload-to-cask weight ratio is extremely low (1 to 4 percent). About 90 percent of the cask weight is the radiation shielding, with supplemental weight in the auxiliary cooling equipment and additional structural material necessary to meet the stringent shipping requirements There are several features which are common to all spent fuel containers. They consist of heavy stainless steel shells on the inside and outside separated by dense shielding material, such as lead or depleted uranium.

The casks are equipped with energy absorbing impact structures, such as fins, to absorb energy equivalent to the 30-foot drop test and to limit the forces imposed on the casks and their contents The casks also contain a basket used to support the fuel assemblies during transport. Special provisions are made for high exposure fuel through the use of a neutron capture shielding material to limit radiation from the fast neutrons generated through spontaneous fission and alpha-neutron reactions of the transuranium isotopes.

In the design of the spent fuel shipping cask, special attention was given to the removal of decay heat. The shipping cask has extended surface areas for the dissipation of'ecay heat and if necessary, auxiliary cooling equipment can be connected to the larger casks to assist in heat removal.

In addition, the fuel is allowed to decay in the plant, underwater, in a shielded spent fuel storage pool for at least 100 days prior to being placed in the cask for shipment. This decay time greatly reduces the level of decay heat produced by

3. 6-23

the assembly and also reduces the radioactive fission products, including Krypton88 and Iodine-131, to low levels.

The number of annual shipments of spent fuel assemblies is a function of the type of cask and the mode of transportation selected by the fuel reprocessor.

One possibility is the use of a legal weight truck cask (gross vehicle. weight not exceeding 70,000 pounds) is capable of holding only two BWR fuel assemblies. The cask in a fully loaded condition weighs about 23 tons. Use of such a.cask would require about 67 individual truck shipments per year.

A second transportation possibility is the use of overweight trucks (gross vehicle weight up to 110,000 pounds). A cask for this type of truck carries 4 to 7 BWR fuel assemblies and weighs between 30 and 40 tons. The use of an overweight truck would require 19 annual shipments. Disadvantages include obtaining individual state permits for each shipment and probable restriction of shipping to periods of light traffic and good weather.

The use of larger rail casks is a third possibility and is considered to be the most appropriate transportation mode, particularly for longer shipping distances. Rail facilities are available at the Nine Mile Point site. There are several large rail casks in the design and licensing stages, including the General Electric IF300. This particular cask will be capable of transporting 18 BWR spent fuel assemblies and will weigh about 70 tons in a fully loaded condition. Use of this cask could reduce the shipping frequency to about eight casks per year.

Even larger casks, in the conceptual stages of design, would hold up to 32 BWR fuel assemblies and weigh about 115 tons. With such a cask, annual shipments could be reduced to about five. The environmental effects of spent fuel transport are discussed in Section 5.4.2.

3.6.5.4 Radioactive Waste Shipping Solid radioactive waste material is packaged and shipped offsite for proper disposal at AEC licensed radioactive waste disposal facilities. Typical disposal facilities currently available to the Nine Mile Point Nuclear Station are located in West Valley, New York; Aiken, South Carolina; and Moorehead, Kentucky.

Containers (drums) which meet appropriate AEC and DOT requirements are used for the packaging of radioactive wastes.

These containers . provide the required containment of the wastes during normal and accident transport conditions and also provide sufficient shielding for low level radioactive waste shipments to meet AEC and DOT external radiation level requirements.

Additional shielding, in the form of concrete or 'lead overpacks, 3 6-24

are used wastes.

if required for the shipment of high level radioactive Most solid wastes produced at Nine Mile Point Nuclear Station Unit 1 have a relatively low radioactive concentration. This limited concentration plus the solidified nature of the waste ensures minimal environmental effects during transportation.

Solid wastes generated with high radioactive concentrations are shipped in special containers (identified by DOT as "Type B packaging") . These containers are designed to withstand the various accident conditions as described in Section 5.4. 2. The containers are designed to minimize the environmental impact of an accident during the transportation of high level radioactive wastes.

Legal weight trucks are the mode of transportation for solid radioactive wastes from Nine Mile Point Nuclear Station Unit 1.

Overweight trucks and railcars are possible alternative modes of shipment of radioactive wastes.

The number of yearly shipments of solid radioactive waste during periods of normal operation has been from 20 to 40. During periods of unusual maintenance or operation, the number of annual shipments could possibly approach 60. Table 3. 6-4 presents a summary of the solid radioactive waste shipment history for the period January 1, 1971, through December 31, 1971, at the Nine Mile Point Nuclear Station.

3. 6-25

0 Table 3.6-4

~ Solid Radioactive waste shipping Information volume Total Number of Drums Time Number of Ship- Curies Number of ~ ~ Per-Shi ment<>>- - ~ ~ - - - - - - ~ - ~ -Curies/Ft~--- ~ - ~ - ~ ~-

Period Shipments<< ~ ped (Ft~) <<> Shippedc ~ > Drums<>> Average Maximum Minimum Average Maximum Minimum Jan. 1, 1971- 20 6,792 67. 26 924 46.2 131 14 9.9 x 10-> 1 68 x 10 ~ 2.1 x 10-s June 30, 1971 July 1, 1971 6,118 133.95 832 34.7 75 14 2.2 x 10-~ 1.2 x 10-~ 2.5 x 10"~

Dec. 31, 1971 Jan 1, 1971- 12,910 201 21 1i756 40 131 14 1. 6 x 10-~ 1. 68 x 10- ~ 2. 1 x 10- s Dec 31, 1971 (1) Number of shipments, volumes, and total curies from Nine Mile Point semiannual reports (2) Number of drums based on 7.35 ft~/55 gal drum (3) Average, maximum and minimum number of drums per shipment are based on the actual waste volumes (ft~)

per shipment as given in the semiannual reports (4) Average, maximum, and minimum curies/ft~ figures are based on actual waste volumes (ft~)

and curie content of each shipment as given in the semiannual reports.

that the maximum allowable curies/ft~ to meet low specific activity requirements is It should be noted 8.946 Ci/ft~ (0.3 uCi/gram)

0

'I

3.7 CHEMICAL AND SANITARY DISCHARGES This section describes liquid effluents discharged from the chemical and sewage waste treatment facilities serving the Nine Mile Point Nuclear Station Unit 1. The ef fects of these effluents upon Lake Ontario are discussed in section 5. 3. All radioactive and potentially radioactive liquid wastes, such as decontamination solutions, laboratory chemicals, condensate demineralizer regeneration wastes, and reactor and turbine building floor drainage are conveyed to the radwaste building for processing and treatment. The radwaste system is discussed in Section 3.6.

3.7.1 Liquid Chemical Discharge Circulating water chlorination has not been required since the silt content in the raw lake water is present in sufficient quantity to prevent attachment of biological growths on exposed surfaces of the cooling system. The chemical waste treatment system handles the liquid waste associated with the operation of the makeup water treatment system. During normal operation the makeup water treatment system pxovides 100 gpm of high quality demineralized water for the nuclear steam system and other station facilities. Raw water from Lake Ontario is taken from the discharge side of the service water pumps and conveyed to the makeup water treatment system. This treatment system consists of a sludge recirculating clarifier, clear well, pressure filter containing anthracite, activated charcoal filter, and.cation, anion and mixed bed ion exchange units. The demineralized water from the makeup water treatment system is stored in a 36,000 gallon tank prior to use in the reactor condensate cycle.

A schematic diagram of the makeup water treatment system and associated chemical waste treatment facilities is shown in Figure 3.7-1.

In the sludge recirculating clarifier, chemicals are added to the lake water to promote flocculation and precipitation of suspended material. In addition, partial softening of the raw lake water is achieved. Chemical flocculant and softening doses include 50 ppm of iron sulfate (Ferrifloc) and 150 ppm of lime.

Effluent from the clarifier is conveyed to the clear well which affords sufficient head to supply the demineralizer feed pump.

From the clear well, the water is pumped through a pressure filter containing graded anthracite which removes remaining small quantities of residual suspended solids. The water then passes through an activated carbon filter which adsorbs the small quantities of dissolved organic materials present in the lake water.

Effluent from the activated carbon filter passes through a demineralizer system consisting of one cation, one anion, and one mixed bed unit arranged in series. The cation and anion units remove essentially all dissolved solids initially present in the 3~7 1

P lake water. The mixed bed unit, or polishing demineralizer, removes remaining trace quantities of dissolved solids which pass through the cation and anion units.

High quality demineralized water is conveyed to the demineralized water storage tank.. This storage tank has a capacity of 36,000 gallons prior to utilization in the nuclear steam system.

Chemical wastes associated with the makeup water treatment system consist of intermittent blowdown of solids from the clarifier, backwashings from the pressure filter and solutions activated charcoal filter and neutralized resinspent acid and regeneration caustic cycles.

resulting Table 3.7-1 from ion exchange presents the chemical characteristics of neutralized regenerant wastes from the makeup water treatment facility, and presents the associated chemical waste discharges.

The clarifier blowdown of about 20 gph is conveyed to a 13,500 gallon settling basin for solids thickening. Approximately one ton of solids is dredged from the basin every three months and disposed of in a spoil area on site. At steady state, about 20 gph of clear overflow from the waste retention basin is conveyed to Lake Ontario via a drainage ditch. During station shutdown, about 80 gpm of clarified water is allowed to overflow from the clearwell and then conveyed to a storm drain prior to discharge in Lake Ontario.

The anthracite pressure filter and the activated charcoal filter are backwashed 3 to 4 times a month to maintain acceptable pressure drop through the filters by removal of accumulated solids. Waste water resulting from these backwashing cycles is conveyed to the storm drain prior to discharge in Lake Ontario.

Regeneration of the makeup demineralizer system includes backwashing, introduction of dilute acid or caustic solution, and slow and fast rinsing of exchange units. Spent acid and caustic solutions and associated rinse water are drained to a 20,000 gallon neutralization tank for pH adjustment to within 6.5 to 8.5 before being discharged at a rate of 100 gpm to the lake via the circulating water as seen in Figure 3.7-1.

Cation and anion units require regeneration approximately three to four times a month. The mixed bed unit requires regeneration once or twice a month. prior to discharge to the circulating water, the dissolved solids level (mainly sodium sulfate) in the effluent from the neutralization tank is about 9,000 ppm. The maximum accumulation of wastes resulting from demineralizer regeneration is about 16,000 gallons which is routed to the regeneration waste neutralization tank. After plant adjustment to between 6. 5 and 8.5 by either acid or caustic as required, the effluent is discharged at a rate of 100 gpm to the is circulating water discharge flow of about 268,000 gpm where After complete mixing, it the diluted by incremental a factor of about 3,000.

3&7 2

increase of dissolved solids in the circulating water is about 3 ppm as seen in Table 3.7-1. Niagara Mohawk obtained a permit in 1965 to discharge these chemical wastes to the waters of N'e w York State. A copy of the permit is included in Appendix G.

Chemical regeneration radioactive wastes from the condensate demineralizers are not discharged to the circulating water but are processed in the radwaste system by evaporator concentration and solidification for off-site disposal as discussed in Section 3.6.

Drainage from roof, floor, and equipment drains which has no potential for radioactive contamination is conveyed to Lake ontario via a storm drain.

Wastes from the laundering of protective clothing are processed in the radwaste system prior to disposal by mixing with the circulating water discharge as discussed in Section 3.6. A low foaming detergent is used containing about 50 percent by weight of sodium hexametaphosphate. During normal operation, about 100 pounds per month of this detergent is utilized to produce a laundry waste of about 130 gpd. After complete mixing with the circulating water, the incremental increase in the level of phosphates in the lake water measured as phosphorus is about 0.2 parts per billion (ppb). During scheduled outages about 450 pounds per month of this detergent is utilized to produce a laundry waste of about 1,700 gpd. After complete mixing with the circulating water, the incremental increase in the level of phosphates in the lake water measured as phosphorus is about 0 7 ppb.

3.7.2 Sanitary Waste System The sanitary sewage system collects sanitary waste from all nonradioactive sanitary fixtures within the station. This sanitary waste is conveyed to an activated sludge package plant of the extended aeration-type, followed by chlorination and oxygenation.

The sanitary sewage passes through a communitor which reduces the solids to fine particles prior to entering the activated sludge aeration tank. Digested sewage from the sludge tank is conveyed to a clarifer where inert solids are removed and the clear overflow flows into a chlorination tank for disinfection by the addition of chlorine. The disinfected liquid is pumped to a 2,800 square foot oxygenation pond which has sufficient surface area to restore dissolved oxygen to the effluent before cascades over a weir into a drainage ditch. The ditch carries it the effluent to a rivulet which flows into the lake.

3~7 3

Table 3. 7-1 Chemical Discharges from Makeup Water Treatment Total Anions Cations Chemicals Chemicals Resulting Incremental Removed Removed Added Added to Circ Water Change in During During During Circ. Water Analysis*** Analysis of Circ..Water One Regen. One Regen. One Regen. During One at Discharge Lake Ontario Analysis Cycle* Cycle Cycle Regen. Cycle During Regen. Water During Regen.

Ion (Lb/Regen.) (Lb/Regen.) (Lb/Regen.) (Lb/Regen. ) Cycle (Ppm) (Ppm) Cycle (Ppm)

HCO 3

51 51 94. 11 94. 00 0 11 Cl 33 33 30 38 30.30 0 08 SO+ = 51 676 727 32.11 30. 10 2. 01 Ca++ 41 41 44. 10 44. 00 0 10 Mg++ 8 92 8 90 0. 02 Na+ 18 324 342 17 55 16. 60 0. 95 K+ 1.60 1 60 Total Dissolved Solids 228.77 225. 50 3 27

+Regeneration cycle occurs for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> with resultant effluent from the neutralization tank discharged to circulating water at 100 gpm.

• +Includes SO+ associated with ferric iron sulfate addition in clarifier.

+*~Prior to discharge of chemicals associated with regeneration, the circulating water analysis is identical to that of Lake Ontario water. The resulting chemical composition of the circulating water is computed by material balance.

o Settled sludge from the clarifier is recycled to the aeration tank where it is mixed with incoming sewage. Experience has indicated that the excess sludge is removed on a quarterly basis from the station by a licensed disposal firm to a state-approved disposal area.

The sanitary waste treatment facility has a capacity of 15,000 gpd. The number of employees required during normal operation of Unit 1 is about 68. In addition, refueling and annual overhaul operations may require the presence of an additional 40 employees. Based on a sanitary flow of about 35 gpd per capita, the maximum anticipated flow would be about 3,800 gpd. Based upon the number of employees required during normal operation of Unit 1, the normal anticipated flow would be about 2~400 gpd. Sample analysis has shown that the sewage treatment facility has the capability of meeting the operation requirements listed below:

0 ratin Ef ficien Settleable Solids 100%

Suspended Solids 95%

BOD (5 Day) 95%

Chlorine Residual 1.0 ppm The design of the sewage treatment facility and associated equipment conforms to the New York State Department of Health Requirements for Waste Treatment Works, Bulletin 1, Part 1, as well as to the rules and regulations of the Town of Scriba, Oswego County. In 1965 Niagara Mohawk obtained a permit to operate the waste treatment facility and discharge wastes to the waters of New York State. A copy of the permit is in Appendix G.

3. 7-5

I l

S I N

)

0

3.8 OTHER WASTES Two standby diesel generators and one diesel-driven fire pump are available for use during emergency conditions. The generators provide. electrical power for essential needs when normal reserve and offsite power are unavailable. The diesel generators are tested on a monthly basis and the fire pump on a weekly basis.

The diesels burn fuel oil containing 0.4 to 0.7 percent sulfur and a negligible amount of ash. The generator diesel engines exhaust to atmosphere through the roof of the diesel generator room. Exhaust from the diesel fire pump engine passes through the upper portion of the screenhouse side wall. Overall combustion products released from the two standby diesel generators and the diesel-driven fire pump are insignificant because this equipment is normally driven only a few hours a month for test purposes.

An electrically heated auxiliary boiler is used for space heating purposes. There are no emissions from this source.

3 8-1

SECTION 4 ENVIRONMENTAL EFFECTS OF CONSTRUCTION The construction phase of Nine Mile Point Unit 1 was completed September 1, 1969. The unit has been in commercial operation since December, 1969. However, certain modifications are planned to upgrade the original radwaste system to conform to proposed Appendix I to 10CFR Part 50 of the Commission~s regulations.

These modifications will be to construct a new.radwaste building and install additional liquid and gaseous radwaste control equipment to upgrade the radwaste treatment system as described in Section 3.6. Planned modifications to the station are scheduled to begin'ubsequent to AEC approval and will be completed in accordance with the requirements of proposed Appendix I. Construction will require about two years time and about 75 people..

The new radwaste building will be about 80 feet by 60 feet by 30 feet above grade and 30 feet below grade. Excavation for the

'building foundation will be done with conventional earth-moving equipment and rock blasting where necessary and possible. Any blasting will be carefully planned and executed to maintain the structural integrity of the station Dust and debris from blasting operations will be controlled by protective mats over the blasting zone. The material excavated will be used for onsite grading or for landfill at off-site areas owned by Niagara Mohawk.

During the construction of this building, heavy equipment and trucking noises will be produced mainly to the east of the station. Material deliveries to the site will be made by trucks using the existing roads in the area, and no new access roads to the station area, will be required. Since construction is presently underway on the James A. FitzPatrick Power Station to the east, the modifications to Nine Mile Point Unit 1 will result in only modest incremental disturbance to the area.

The limited nature of this construction activity is not expected to have any impact on Lake Ontario or the terrestrial ecology of the site or the surrounding area. Maintenance of the present site grade will eliminate the possibility of land erosion to the lake. The new building will have external treatment and landscaping that will blend with the aesthetic appearance of the present station. The effects of the radioactive releases from the modified radwaste system are discussed in Section 5.2.

4. 0-1

1 SECTION 5 ENVXRONMENTAL EFFECTS OF STATION OPERATION

5. 1 EFFECTS OF OPERATION OF COOLING WATER INTAKE AND DISCHARGE FACILITIES The area of the lake in the vicinity of Nine Mile Point is designated water quality Class <<A<< by New York State. The Official Compilation of the Codes, Rules, and the best usage Regulations of the state of New York, part 701.3, Title 6, defines for this class as a source of water for drinking, culinary, or food processing purposes. The standards for Class <<A<< waters include the following specifications regarding heated liquid discharges:

None alone or in combination with other substances or wastes in sufficient amounts or at such temperatures as to be injurious to fish life, make the, waters unsafe, or unsuitable as a source of water supply for drinking, culinary, or food processing purposes or impair the waters for any other best usage as determined for the specific waters which are assigned to this class.

(6NYCRR, 701.3)

The New York State Department of Health issued the cooling water discharge permit for Nine Mile Point Unit 1, in April 1965 (Refer to Appendix G). Four years after this approval New York State implemented the water quality standard quoted above with thermal discharge criteria~. These criteria specifically state that the numerical limitations <<... are intended only to be a frame of reference<< for existing discharges. (6NYCRR 704.4) .

Therefore, while Unit 1 is not subject to the strict application of the specific numerical limitations contained in the 1969 criteria, Niagara Mohawk believes that the existing cooling water

'esign for Unit 1 conforms to the 1967 water quality standards quoted above. The studies discussed in Section '5. 5 form the basis for this belief. These studies (Ref. 20) indicate that the thermal effluent has not been injurious to fish life and has not made the waters unsafe or otherwise unsuitable for any usage which the standards assign to this class of waters.

+These criteria are the applicable wat er qual ity standa rds under Section 21(b) of the Federal Water Pollution Control Act (33 U.S.C.A. Section 1171) See "Notice of Proposed Rule Making" to 40 C.F.R. Part 115, 36 Fed. Reg. 23398, December 9, 1971.

5. 1-1

5. 1.1 Intake Structure and Operation The circulating water intake for Unit 1 is located in about 20 feet of water and has an intake approach velocity of about 2.0 fps. Operating experience at this station since 1969 indicates that velocities of this magnitude have resulted in the entrapment of only a very few fish, primarily alewives, in the onshore screenwell. The intake was designed and is operated so that water is withdrawn from the lake in the horizontal plane.

Refer to Section 3.5.

As discussed by several authors (References 21 through 26), flow in a horizontal plane into the structure has advantages for helping fish sense a positive velocity gradient. It is also believed that the steel bar racks at the face of the intake structures create turbulence and an up-current pressure wave which apprises fish of an increasing velocity. The configuration and relative location of the intake and discharge structures minimize recirculation of heated water which may attract fish to the intake.

Location of the intake structure relative to the discharge structure has a direct effect on plant efficiency. If heated dischar'ge water recirculates to the intake structure and the intake water is significantly warmed, the result could be a decrease in plant efficiency as well as attraction of fish to the intake area. It was consequently necessary to locate the intake and discharge structures some 550 feet relative to each other to minimize recirculation.

5. 1.2 Discharge Structure and Operation The effects of the plant discharge on the temperature distribution in Lake Ontario are minimized by the use of the design described in Section 3.5.

The published analytical and experimental investigations on the mechanisms of warm Vatei discharge into a large body of receiving water form the basis for a general understanding of the hydrothermal mechanism of heat dispersion in the vicinity of the discharge structure. Comprehensive thermal field surveys, as discussed in detail in section 5.5, were conducted in the summer of 1970 and 1971 after the station was in operation. The results of these studies and investigations have been incorporated in the following description of the hydrothermal mechanism prevailing in the near field and far field areas. (In the terminology of the hydraulics field, "near field area~~ refers to that area in the vicinity of the discharge structure where turbulence is the predominant factor in the temperature reduction of the thermal effluent. The term ~>far field area~~ refers to that area some distance away from the discharge structure where heat loss to the atmosphere is the predominant factor in the temperature reduction of the thermal effluent) .

5. 1-2

As mentioned in Section 3.5, the station circulating water flow is 600 cfs with a maximum temperature rise of approximately 32 F.

The total waste heat, a maximum of 4.0 x 10~ Btu/hr at full load, is dissipated in two ways. First, by the mixing of the warm discharge water with the ccoler surrounding ambient water and secondly, by the transfer of heat from the water surface to the atmosphere by radiation, evaporation, and conduction. Each of these heat transfer phenomena contributes to the total cooling effect in varying degrees depending upon the coincident meteorological and lake conditions.

The heated water discharges into the lake through a hexagonal shaped discharge outlet which has a total opening area of 152 square feet.. The effluent has an initial velocity of approximately 4 fps which is gradually reduced by shear forces as it encounters the relatively quiescent receiving water body. In consequence, considerable turbulence develops which causes entrainment of the cooler ambient water. The entrained flow mixes with the station discharge and,lowers the overall effluent temperature while consuming the energy of the discharge by turbulent mixing. Due to the buoyancy of the heated discharge, the effluent rises to 'he water surface and establishes a stratified flow system.

Field measurements and hydrothermal data collected during station operation were employed in a mathematical model of the discharge area as part of the FitzPatrick Plant hydraulic model study.

The results of this undistorted hydraulic sector model were used to determine the thermal effects of the near field area. Based on these results, a stratified flow system was found to be well established at about 75 feet from the Nine Mile Point Unit 1 discharge outlet. Field measurements have demonstrated that a consistent dilution factor of about three is achieved and that a temperature rise of about 11 F above ambient exists at the water surface with a flow depth of about 9 feet at the 75-foot distance. This agrees favorably with the results of the mathematical model analysis.

Figure 5.1 1 shows the basic mechanism of dilution and flow pattern of the Nine Mile Point Nuclear Station discharge in the near field area.

The thermal field surveys have confirmed that after mixing with ambient lake water, the heated discharge plume forms a lighter, upper layer which flows in the direction of the prevailing lake current (predominantly west to east-northeast) but varies with wind direction. At the same time, the cold water current induced toward the discharge plume underrides the lighter, upper layer and is therefore available as dilution water.

As the surface plume travels away from the discharge structure, it expands in size but decreases in temperature and depth. The

5. 1-3

OF DISC HARG E STRUCTURE HEAT TRANSFER TO ATMOSPHERE DI LUTE D WARM WATER SHEARING STRESS RE-EN TR A I N MENT DIFFUSION AND MIXING E NTRAINMENT INDUC E D AMBIENT COLD WATER P

FIGURE 5. I -I BASIC MECHANISM OF DILUTION AND FLON PATTERN IN NEAR FIELD AREA

A 1 ~

~,

C

stratification weakens as the temperature difference between the upper warm layer and bottom cold layer lessens.

Since two of the openings of the discharge structure are directed toward the shoreline, a temperature rise of about 6 F above ambient lake water was expected along a 4500-foot total length of shoreline due to the poor dilution experienced with the shallow bottom topography. The temperature in fact decreases with the increase of the water depth and there is distinct thermocline at about 5 feet below the surface. The results of this survey indicate that the surface area and volume of the lake within the 3 F isotherm are approximately 300 acres and 3,000 acre-f t, respectively. These results agree with the descriptions. of the hydrothermal mechanism prevailing in the far field area.

Niagara Mohawk has conducted a continuing program of Lake Ontario ecological studies to determine effects of station operation upon the aquatic biota of the area, including a number of thermal field surveys. Twelve of these ~~triaxial temperature surveys~~

were performed during a period from May to November of both 1970 and 1971. These studies as well as other pertinent investigations and surveys listed in Appendix F, were conducted by Dr. John F. Storr, a consultant in Limnology and Associate Professor of Biology at the State University of New York at Buffalo.

A description of the methods employed in conducting the thermal surveys is discussed in Section 5.5.5. The results of these surveys indicate that the surface area of the lake within the 3 F isotherm could range from about 60 to 460 acres, depending upon the meteorological and lake conditions as shown in Figures 5.1 2 and 5.1-3.

In conclusion, the thermal conditions prevailing at the Nine Mile Point site with the Nine Mile Point Nuclear Station in operation can be summarized as follows:

1. In the neak-field area, in the vicinity of the discharge structure, the predominant effect is that of turbulent mixing of the buoyant discharge with the surrounding water. At the end of this near-field area, a stratified flow system is developed, with the warmer, diluted water flowing at the surface in the direction of the predominant lake current.

2. In the far-field area, which extends to a distance where the temperature rise above ambient is insignificant, the stratified flow system persists. The cold water is induced from offshore in the lower layer to replace the warmer diluted water flowing away in the upper layer In this fax'-field area, the predominant effects are heat transfer to the atmosphere and interfacial entrainment

5. 1-4

r I

I I

between the discharge plume and the underlying cold water.

3. In the vicinity of the intake area, a fairly strong stratified discharge flow system prevails. about The centerline of the intake openings

, are located

'18 feet below the mean water datum, and they are approximately '550 feet from the discharge structure.

The velocity at the intake openings is at most approximately 2 fps. With the combination of the strong stratification and low induced intake flow velocity, the recirculation of warm water is negligible under normal lake conditions.

5. 1.3 Effects on Aquatic Biota No adverse effect has been observed on aquatic biota in the Nine Mile Point area due to thermal, chemical, or radioactive releases from the station. The effects of chemical and radioactive releases on the biota of the receiving waters are discussed in Sections 5.2 and 5.3, respectively. Thermal effects are described below.

As discussed in Section 2.7.2 the species of fish collected in the vicinity of the site during the warmest months of the year are typical of warm-water fish populations. Natural summer temperatures sometimes reach 77 F, as reported by Dr. J..F. Storr (Ref. 20), so it would be expected that the cold-water species of fish, such as salmonids, would inhabit in-shore the deeper off-shore waters rather than the naturally warmer regions of the epilimnion.

As discussed in Section 5. 1.2 the thermal plume is confined to the surface waters in the vicinity of the promontory.. Since the discharge is located in an open area of the lake, the thermal effluent does not create a barrier to fish that may utilize the adjacent tributaries, which include the Oswego River eight'miles west of the site, the little Salmon River eight miles east of the few miles further east. Since the site, and the Salmon River a discharge does not affect these tributaries, and since there is ample room for fish to travel around the plume in the lake proper, no interruption of fish migration has or will occur.

Fish are able to select or avoid areas of the thermal plume in response to preferred temperatures. Studies at the station since 1969 have verified this phenomenon. During the colder months, the thermal plume attracts certain species of fish, including carp, smallmouth bass, sunfish, and alewives., Smelt and troutperch do not appear to be attracted to the vicinity of the thermal plume. As ambient temperatures increas'e, there appears to be no attraction of fish to the plume and some species, alewives and white perch, appear to avoid the warmest portions of the plume.

5. 1-5

It is also colder months recognized that sudden plant shutdowns during the may stress fish which are acclimated to warmer temperatures (Ref. 28) . In the advent of an unplanned shutdown, it would be expected that fish which temperatures would follow the are acclimated dissipating plume to to elevated minimize thermal stress. When a scheduled plant shutdown occurs, thermal stresses are minimized by the continuing operation of the circulating water system. This allows a gradual reduction in the temperature of the discharged water.

Spawning of the species of fish encountered in the vicinity of the site generally occurs in the spring when natural water temperatures are low. However, the only fish whose eggs have been observed in the vicinity of the site is the alewife. As discussed in sections 2.7.2 and 5.5, the field studies indicate that the alewife spawns and deposits its eggs in the algal mat close to the shore. As discussed in section 5.1.2 a limited area of the shoreline is elevated by the thermal plume. Whether the increased temperatures adversely affect the development of these eggs is unknown at this site. However, considering the abundanCe and fecundity of alewives in Lake ontario there is expected to be no adverse effect on the population of alewives as a whole.

Results of the ecological surveys performed at this site since 1963 indicate that most of the benthic plant and animal life is found between the shore and the 20-foot depth contour.

Comparison of pre- and postoperational results indicates that proceed earlier in areas within the influence of the plume.

However, growth in these regions tends to be suppressed during the summer. The net effect is that the biomass of algae produced

~

is essentially the same inside and outside of the influence of the thermal discharge.

The predominant benthic invertebrates are amphipods of the genus Gammarus which are an extremely important food source for fish.

There appears to be a direct relationship between the abundance Gammarus appears to be higher in areas within the thermal discharge; however, more studies will be necessary to determine if a cause-effect relationship exists.

distribution of other species of benthic invertebrates do not Abundance and appear to be affected in areas within the thermal plume.

Nutrient studies conducted by Dr. J. F. Storr (Section 5.5) during 1969 and 1970 indicated that there is no significant difference in nutrient concentrations with depth. The induced bottom flow due to the intake structure therefore, has no effect on vertical nutrient redistribution.

Preliminary plankton distribution studies in the vicinity of the site, conducted by Dr. J. F. Storr in 1964, (Section 5. 5) indicated that plankton concentrations were generally higher in

5. 1-6

V the surface waters than in the deeper bottom waters. Since the intake structure draws water from the deeper depths, the proportion of planktonic species in the circulating water flow will be lower than in the surface waters.

Additional plankton studies were conducted in 1971 at Nine Mile Point Nuclear Station Unit 1 to assess the effects of entrainment on the planktonic species in Lake Ontario (section 5. 5) . The studies were carried out from June through autumn under different temperature and lake conditions Both zooplankton and motile phytoplankton were collected in the intake and discharge and held for varying periods of time. The plankton were examined immediately and again 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after collection. Estimates of the percent killed in passing through the system were established for each group of organisms.

Results of the studies varied depending on time of the year, wave conditions, temperature rise, and duration of exposure to the elevated temperatures. Plankton entrained in the cooling water system for the station are subjected to mechanical and thermal stress for about 6 minutes from the time of entering the intake to the time of reaching the boundary of the mixing zone. The preliminary results of this study, however, conservatively indicate that the overall level of mortality of plankton passing through the plant ranges'from 19 to less than 30 percent. This higher value includes no allowance for sampling errors. A detailed discussion of the methods of estimating plankton mortality is in Section 9.5. 1.2. 2.

As mentioned previously, the circulating water flow for the station is approximately 600 cfs. The intake is located off-shore in an open expanse of the lake'here natural prevailing currents will prevent the depletion of local plankton populations.

Since the proportion of the circulating water flow is small compared to the free flowing volume of water at the site and, since the preliminary plankton studies indicate relatively low mortality rates on entrained org'anisms, there is believed to be no significant effect on the plankton community in the vicinity of the Nine Mile Point Nuclear Power Station.

Although the studies conducted to date have revealed no fish eggs or larvae in the intake of Unit 1, it is recognized that some fish eggs and larvae may be entrained in the circulating water system. Little quantitative data is available, but there is general agreement that concentrations of fish eggs and larvae might be found as far as ten miles from shore because of the upwellings in this area. Based on limited data, the effect of entrainment on the fish population has been evaluated. The results of this analysis are summarized in Table 5.1 1. Three different methods were used to ccmpute mortality for a once-

5. 1-7

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through cooling system. The assumptions of the various methods are as follows:

1. Model of Entire Lake:

Fish and larvae are equally distributed throughout the entire lake.

Water containing these stages of fish life will pass through the condenser system during the approximately 90-day spawning season.

2. Ten Mile Inner Lake Fish eggs and larvae are found equally distributed in the water within a 10-mile limit from shore all around the lake, and none are found in the rest of the lake. All water passing through the plant is withdrawn from this 10-mile inner lake.

Water containing these stages of fish life will pass through the condenser system during the approximately 90-day spawning season.

3. One Mile Inner Lake Similar to second model, except the larval forms are found only within a 1-mile inner lake.

For each of the models, three cases were investigated, as recorded in the columns labeled <<100 percent mortality," <<30 percent mortality<<and <<30 percent mortality with selective withdrawal.<<The results in the first column are for the case where it is assumed that all forms of fish life passing through the cooling water system will be destroyed. Preliminary data indicate that approximately 10 to less than 30 percent mortality of larval forms occurs as a result of passage through the cooling water systems of similar units. This mortality rate may be high since it is not possible to determine the mortality which occurred as a direct result of the sampling technique. While these results are not directly applicable to the Nine Mile Point Station, they do provide a basis for estimating an actual mortality rate.

Similarly, preliminary data indicate that surface water contains higher concentrations of fish eggs and larvae than do lower depths. The intake structure is designed to draw water selectively from the deeper water and the results listed in column 3 in Table 5. 1-1 reflect this factor.

Even on the basis of the most conservative model investigated, less than 0.2 percent of fish eggs or larvae could potentially be damaged by passage through the Nine Mile Point Station.

5. 1-8

Although mechanical and thermal effects are usually considered the major cause of plankton mortality in circulating water systems, recent studies (Ref. 29) indicate that chlorine is responsible for increased mortalities of zooplankton. However, biocides are not used in the cooling water system for condenser cleaning so that this increment of plankton mortality is not a factor. Refer to Section 3.7 for a discussion of treatment to prevent biological growth in makeup water.

Table 5.1-1 Effect of Entrainment on Fish Larvae Population for Nine Mile Point Nuclear Station Percent of Reduction of Po ulation Nine Mile Point Case 2 3 30% Mortality with Direct Selective 100% Mortalit 30% Mortalit Withdrawal- ~

1. Entire 0. 0074 0. 0022 0. 0007 Lake

2. Ten Mile 0. 0133 0. 0040 0. 00 12 Inner Lake

3. One Mile 0. 1478 0 0444 0. 0133 Inner Lake

5. 1-9

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5 2 EFFECTS OF RELEASED RADIOACTIVE MATERIAL

5. 2. 1 General Nine Mile Point Unit 1 is an operating station which was licensed prior to the publication of the proposed guideline Appendix I to 10 CFR Part 50., This section will discuss both the licensed Unit 1 stati'on as it was originally designed and described in the FSAR as well as the future Unit 1 station after the radwaste system is upgraded.

The upgraded radwaste system is designed and will be operated to minimize discharge of radionuclides to the environment. The concentrations of the releases to the water and air will comply with the limits specified in Title 10, Code of Federal Reglulations (CFR) Part 20, and with the design objectives specified in the proposed Appendix I to 10 CFR Part 50..

This released radioactivity adds only very slightly to the natural background radiation To estimate the dose from these releases, the following factors are considered:

1. The isotopic composition and concentrations released

2. Dilution of the discharge in the air and water and removal mechanisms, such as sedimentation and adsorption

3. Concentration in aquatic and terrestial food chains

4. Local environmen'tal characteristics, such .as meteorology, hydrology, and land use

5. The daily habits and activities of the potentially exposed population.

All principal exposure pathways have been considered. These are:

1. External exposure to people from radionuclides in water and air

2. Internal exposure to people from ingestion of food con-taining radionuclides and from drinking water and milk 3 0 Exposure of fish and primary producer and consumer species in water from radionuclides in water and internally deposited

4. Exposure of plants and animals directly from radio-nuclides discharged to air and indirectly from deposition

5. 2-1

Each of these modes of exposure is considered in detail in the following sections as they apply to the aqueous and airborne radionuclide releases.

It is appropriate here to explain the basis for the discussion of release rates of radioactive materials and for the evaluation ,of the resulting radiation exposures.

The Nine Mile Point Unit 1 offgas system design was based on a noble radiogas activity flow rate (source term) of 820,000 uCi/sec after 30-minute retention. This design basis value is recognized to be a conservative one which is not expected to be approached or exceeded in station operation.

Since the goal in fuel performance is to achieve a source term below the design basis, a lower value is appropriate as a basis for the discussion of radioactive release rates as averaged over the years of station operation. Based on BWR operating experience to date (about ten plants), an average activity flow rate of the order of 25,000 uCi/sec as measured after 30-minute delay is higher than the average rate of flow experienced at the operating plants.

In estimating the exposures from radioactive releases, and in conformance with Appendix D of 10 CFR Part 50, a conservative assumption of fuel failure is that the gaseous activity flow rate at 30-minute delay is 50,000 uCi/sec, with the reactor operating at steady-state full power and the cleanup system at normal operation. Radiation, exposures to the public have been calculated on the basis of a gaseous activity flow rate of 50,000 uCi/sec at 30-minute delay for all principal radiological pathways. Due to design features and site and environs characteristics, the resulting dose estimate to any member of the public is low compared to the useful benchmark of dose from natural background radiation.

5.2.2 Aqueous Releases During routine operation, Nine Mile Point Unit 1 releases minute amounts of radionuclides to Lake Ontario. The important isotopes and their discharge concentrations for both the original and upgraded station designs are as presented in Table 3.6-3. The sum of the ratios of the discharge concentration to the maximum permissible concentration (MPC) for each isotope is also presented in this table for both station designs.

The resulting magnitude of exposure, which is extremely small for all exposure pathways, depends on the radionuclides released, the

~

concentration of each, dilution in Lake Ontario to the point of use, the concentration of the radionuclides in biota, and the recreational and dietary habits of people in the vicinity of the Nine Mile Point Station.

5. 2-2

In estimating the dose rate to individuals and the general population, the modes or pathways of exposure that must be considered are:

1. Direct external beta and gamma exposure received while engaged in such water-oriented recreational activities as swimming, water skiing, boating, and fishing.

Commercial fishing must also be considered.

2. Ingestion of fish in which radionuclides may accumulate at concentrations in excess of the concentrations in water.

3. Drinking water from Lake Ontario or from wells in the vicinity of the plant.

4. The food eaten from crops irrigated with Lake Ontario water.

Aquatic biota would be exposed as a result of:

1- Submersion in water containing radionuclides

2. Concentration of radionuclides in body tissue.

5.2.2.1 External Radiation Exposure from Water Related Activities 5.2.2.1.1 Individual Exposure Since the discharge from both the original Unit 1 station design and the upgraded Unit 1 station design utilizes the same submerged discharge system, dilution reduces the surface radionuclide concentration by at least a factor of 3..

Assumptions used to calculate individual radiation exposures from recreational activities are: (1) the swimming season lasts only a few months, roughly from July to September, and (2) -the dose rate to a water skier is about half the dose rate to a swimmer.

Consequently, a person who spent 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> per year swimming in the mixing zone would receive roughly the same dose as an individual who water skis for 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> per year in the area of-the discharge. These dose estimates are summarized .in Table 5 2-1 The exposure of individuals boating or fishing in the discharge area would be due to the presence of the gamma emitters in the water. A recreational fisherman or boater could be exposed for 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> a year, or roughly 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> each weekend from April through September. Similarly, a commercial fisherman could be exposed for about 1,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> per year while fishing in the mixing zone. These dose estimates are summarized in Table 5.2-1.

5. 2-3

0 Table 5.2-1 Summary of Dose Calculations For An Individual (mrem/yr) Due To Aqueous Releases A. U raded Unit 1 Station Desi n<>) 0.0007 NA NA NA Water Skiing (400 hr/yr, MZ) 0.0007 NA NA NA Boating (300 hr/yr, MZ) 0 0003 NA NA NA NA Commercial Fishermen (1000 hr/yr, MZ) 0 001 NA NA NA NA Internal ~

Drinking Water (2.2 l/day<+i) 0 0009 0 002 0. 06 0. 26 0. 002 Eating Fish (200 gm/day<ii) 0.01 0.35 0.01 0 02 B. Ori inal Unit 1 Station. Desi External.

Swimming (200 hr/yr, MZ~>>) 0.01 NA NA NA NA Water Skiing (400 hr/yr, MZ) 0.01 NA NA NA NA Boating (300 hr/yr, MZ) 0. 008 NA NA Commercial Fishermen (1000 hr/yr, MZ) 0.02 NA NA NA NA Internal Drinking Water (2.2 1/day<ii) 0. 018 0.061 0.27 1. 1 0. 030 Eating Fish (200 gm/day~+>) 2.0 28 0.046 3 3

<<iBases: 50,000 uCi/sec offgas activity flow rate after 30-minuite delay and an aqueous release rate (excluding tritium) of 2 Ci/yr for the upgraded station design and 32.2 Ci/yr based on the identified radionuclides released (excluding tritium) obtained from actual 1971 operating data for the original station design.

<<>Gastro-Intestinal Tract ~~iSee Section 5.2.2.2.1

<<>>Mixing Zone NA-Not Applicable

5. 2-4

At other reactor locations, the contamination of fishing gear has been a potential exposure pathway for fishermen. Sediment has been shown to be one source of such contamination. Experience has shown, however, that the level of contamination of gear is likely to be at least one order of magnitude less than that in sediments (Ref. 30). The nature of the lake is such that there are no deposits of sediment in the immediate vicinity of the discharge. Hence, this particular exposure pathway is of no concern.

Experience at the Dounreay installation in Britain indicates that hemp nets have acted as ion-exchange resins in salt water with the result that the radionuclide content of the net exceeded the concentration in the water. Discharge rates at Dounreay were from 600 to 2,000 curies per month in 1965-66. Beta radiation dose rates measured at experimental nets were less than

0. 15 mrad/hr. Because of the several orders of magnitude lower releases from Nine Mile Point, this exposure pathway is of no consequence (Ref. 31) .

Another possible mode of exposure is from the presence of radio-nuclides on beaches. Since beaches in the area consist of relatively large grained and coarse materials, the absorption of radioactive materials is minor compared to beaches consisting of smaller particle size materials, such as muds (Ref. 32) . No significant buildup is expected.

5.2.2 1.2 Population Exposure Recreational The Lakeview Summer Camp, adjacent to the northwest corner of the site, provides access to the bathing beach nearest the discharge.

About 500 people use the camp daily from June through September, and about 1,500 on weekends. The closest public beach at Selkirk Shores is about 10 miles east of the site and has roughly 1,000 swimmers per week through the summer. The factor-of-three dilution of the discharge has already been mentioned. Transport and mixing of the effluent provide additional dilution, which is a function of the direction and the distance from the discharge.

Since the prevailing currents are from west to east (Section 5.4-7.2), the proximity of the Lakeview camp just west of the site is not indicative .of the dilution which can be expected.

Assuming that each person at the camp swims two hours per day, and that there is only a threefold effluent dilution, the total dose to the population is as presented in Table 5.2-2.

5. 2-5

Table 5.2-2 Recreational Population Exposures, Man-rem/yr.

~Oraded Oricrinal.

Swimming+

Lakeview Camp 0.0005 0.008 Selkirk Shores 0.00003 0.0005 2 Fishing+

Mixing Zone 0. 0007 0. 017

~Basis: See Note <<> of Table 5.2-1 At Selkirk Shores to the east of the station, dilution is increased by a factor of 235 (Section 5.4.7. 2).

would take over 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> for the current-carried discharge to Typically, it reach the beach. Neglecting radioactive decay in this travel time, and assuming a dilution of 235 and two hours per day spent in the water, the population exposure at Selkirk Shores is as presented in Table 5.2-2.

As many as 40 fishing boats have been observed near the Nine Mile Point Unit 1 discharge at the same time. If it is assumed that dilution by a factor of 3.0 occurs and that there are two men per boat fishing six hours a day for 20 weeks a year, the dose to the population from recreational fishing is as presented in Table 5.2-2.

5.2.2.2 Internal Radiation Exposure from Ingestion of Fish and Water 5.2.2.2. 1 Individual Exposure Fish tend to concentrate radionuclides in their bodies and this must be taken into account in determining the dose to man due to the concentrations of various isotopes in the water. The maximum permissible concentration considering reconcentration (MPCC) is the concentration of a radionuclide in water that would result in an intake by man from eating fish equal to that which he would get from drinking water containing the maximum permissible concentration in water (MPCW) of that nuclide. The MPCC is directly proportional to the MPCW, and inversely proportional to the product of the quantity of fish ingested and a concentration factor (K) . The concentration factor K is the ratio of the radionuclide concentration in biota to that in water. The representative values of K compiled by Chapman et al (Ref. 33) for elements in freshwater fish have been used for dose calculations.

An individual who obtained 100 percent of his minimum daily protein requirement of 200 grams from eating fish would receive doses to the gastro-intestinal (GI) tract, to the whole body, to the bone, and to the thyroid, as presented in Table 5.2-1. Due to seasonal conditions, it is assumed that half of the

5. 2-6

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individual' yearly intake is obtained from near the station discharge, while the balance comes from sources originating randomly throughout the lake. Those fish obtained near the station discharge are assumed to have spent half of their life in the mixing zone and half throughout the lake.

Due to the seasonal residency in the immediate site area, the dose from drinking water is based on an individual drinking his daily intake (infant 1 liter/day, adult 2.2 liters/day) from the water at the site boundary during one half of the year and from the Osewgo water supply during the other half of the year. Based on these daily intakes, adults and infants would receive doses to the GI tract, to the whole body, to the bone, and to the thyroidf as presented in Table 5.2-1. Even though an infant ingests a smaller daily water intake than an adult, it would receive a somewhat larger thyroid dose because of its smaller thyroid mass.

The infant thyroid dose is calculated using the MPCW from 10 CFR Part 20.

The use of lake water for the irrigation of food crops could result in an uptake of radionuclides by the plants which could result in an exposure to man when the plants were consumed. In Oswego County in 1964, only 1,660 acres were irrigated out of a total of 210,555 acres farmed (Ref- 34). One or two orchards, some five miles east of the site, use lake water for irrigation (Section 5.4.7.2) . Because of the limited acreage irrigated and the distance to the nearest user, it is not expected that exposures are significant in comparison to the doses received via other pathways.

5.2.2.2.2 Population Exposure The radionuclides discharged to the lake at a constant rate reaches an equilibrium value governed by the radiological half-life of each nuclide and the mean residence time of water in the lake. The normal discharge of water from Lake Ontario down the St. Lawrence River is about 240,000 cfs. Assuming the lake volume to be 393 cubic miles, the effect of water exchange was examined with an assumed turnover rate of 90 percent in 24 years.

For all isotopes, except Co-60, Cs-137, and Sr-90, the equilibrium level of activity in the lake is governed by the radiological half-life of the radionuclides. Expected equilibrium levels for selected isotopes for the exchange and no-exchange conditions are compared in Table 5.2-3.

assumed If that these radionuclides are uniformly distributed it is throughout the lake and are concentrated in fish to the degree predicted by the concentration factor, a population exposure estimate can be made. This exposure estimate is based on a value of 3,235,000 pounds for the combined U.S. and Canadian fish catch in 1970 (Section 2.2) .

The population doses to the whole body, GI tract, thyroid and bone are given in Table 5.2-4.

5. 2-7

Table 5.2-3 Equilibrium Levels in Lake Ontario for the Continuous Discharge of Radionuclides< >>

E uilibrium Activit Ci -

Annual Discharge

~Isoto e. ~Ci/Yr A. U raded Unit 1 Station-Desi n.

Co-58 0 084 0 023 0. 023 Co-60 0. 009 0.065 0. 033 Sr-89 0. 050 0.010 0. 005 Sr-90 0 006 0. 1344 0. 042 I-131 0 460 0. 014 0. 014 Cs-134 0.004 0. 012 0.010 Cs-137 0.006 0. 1484 0. 044 Ba-140 0.050 0 002 0 002 Np-239 0 100 0. 0009 0. 0009 H-3 20 300 130 B. Ori inal Unit 1 Station Desi n.

Co-58 6 3 1.7 7 Co-60 10. 6 87 44 Sr-89 0.24 0. 048 0. 024 Sr-90 0. 046 0. 94~ 0. 29 I-131 2.2 0. 069 0. 069 Cs-137 2.6 64* 19 Ba-140 0 070 0.003 0. 003 H-3 20 300 130

+Activity after 30 years of discharge

<<~35-year station life and same basis as given in Note < >> of Table 5.2-1 Since the Oswego Metropolitan Water Board and the Onondaga County Hater District provide potable water from Lake Ontario ta the general public, ingestion of water must be considered as a passible mode of exposure. The water supply intake is about eight miles west of the site boundary. The prevailing lake currents flow from the OCWD intake toward the unit's discharge.

These water supplies serve as many as 190,000 persons per day (Ref. 35) . An annual average dilution factor of 4.9 x 10~ is expected at the Oswego intake from discharges for Nine Mile Point Unit 1 (Exhibit D-2 of Ref. 19) . Instantaneous dilution is by a factor of 156 to the water supply inlet. If this dilution factor of 156 is assumed and the 30 or more hours of decay from the discharge to the inlet, as well as the removal of radionuclides

5. 2-8

by water treatment and subsequent decay in the distribution system are neglected, the dose to the population is as presented in Table 5.2-4.

The total projected population for the year 2000 within 50 miles of the station is about 1,430,000., The Lake Ontario-City of Oswego water supply intake serves Oswego County and parts of Onondaga County. These counties are expected to have about 930,000 people, about 65 percent of their projected year 2000 population, within 50 miles of the station. For estimating the projected year 2000 population man-rem doses in Table 5.2-4, a factor of 4.9 has been used.

Table 5.2-4 Population Exposure (man-rem per year) from Nine Mile Point Unit 1 Liquid Releases<<>

Mode. of E osure. ~Th eid. Bone.

A. U raded-Unit.1 Station-Desi n.

Year- 1970 ~

Ingestion

a. Water 0- 087 0. 17 12 0.16 b Fish 0. 012 0 0022 0 00002 0 01 Year. 2000-Ingestion

a. Water 0. 43 0.83 58 0.80

b. Fish~ >> 0. 049 0 0088 0.00008 0 04 B. Ori inal Unit 1-Station.Desi n.

Year 1970 ~

Ingestion

a. Water 1.6 5.6 52 3 2.76 be Fish 0 44 0.038 0. 0000 1 1. 0

<>>Bases:. Same as given in Note <>> of Table 5.2-1.

<<>It is conservatively estimated that fish catches increase by a factor of four even though the past 30-year trend has been in the direction of decreasing fish catches. A report by the U.S. Fish and Wildlife Service in 1969 estimates that projected demand for fishery products from U.S. landings in Lake Ontario will increase to about 1.25 to 1.5 million pounds annually by the year 2020 (Ref. 18).

5. 2-9

5.2.2.3 Radiation Exposure of Primary Producer and Consumer Species from Discharged Radionuclides

5. 2. 2.3. 1 External Benthic and plankton studies have been conducted in Lake Ontario at the Nine Mile Point site. Most of the benthic plant material depth. Of the animals present, the fresh water amphipod Gammarus.

was most abundant. Limited numbers of snails and insect and fish in the vicinity of the discharge demonstrated seasonal variations in numbers (Ref. 1, page 52).

The submersion dose to these organisms from the radionuclides in the mixing zone can be assumed to be the same as the dose to water several gamma mean-free paths below the surface. Using a mixing zone dilution factor of 3 and assuming year-round residence in this region, the doses to biota are as presented in Table 5.2-5.

Table 5.2-5 Summary of Doses to Biota in the Mixing Zone<<~

A. U raded Unit 1 Station Desi n.

'ose mrads er ear External Internal Fish 0. 015 11. 0 Primary producers and consumers 0 03 12. 0 B. Ori inal Unit 1 Station Desi n Fish 0. 27 400 Primary producers and consumers 0. 53 120

~>>Bases: Same as given in Note ~>> of Table 5.2-1 5.2.2.3.2 Internal Radionuclides can concentrate in biota to levels exceeding their concentrations in water. The internal dose to the primary producer and consumer species. can be calculated using the radionuclide concentration in the mixing zone and the larger of Chapman's values (Ref. 33) of concentration factors for either freshwater plants or invertebrates. Because of the near-microscopic size of the organisms involved, the internal gamma dose is assumed to be zero. The internal dose, assuming deposition of all the beta radiation energy in the organism (Ref. 36), is as presented in Table 5.2 5.

5. 2-10

5.2.2.4 Radiation Exposure of Pish from Discharged Radionuclides 5.2.2.4.1 External Surveys of fish species important to sportfishing in Lake Ontario in the vicinity of Nine Mile Point indicate that fish are randomly distributed in the area during the daytime. At night they tend to concentrate at depths of 20 feet or more, with a maximum at 30 to 40-foot depths. The largest fish concentrations were encountered in the spring of the year when alewives were actively spawning in the warmer inshore water of the lake.. At this time of year, alewives and alewife eggs are the primary food supply for other fish. As the season progresses, fish populations decline sharply as the alewives disperse and move further offshore. Gammarus.then assume a greater importance as a food supply. By October, the inshore food supply has greatly diminished and most fish have moved offshore (Section 2.7.2).

Taking into account these diurnal and seasonal patterns of movement, and assuming that a fish spends half of its lifetime in the mixing zone, the dose rate can be assumed to be about half that of the mixing zone water or as presented in Table 5. 2-5.

5.2.2.4.2 Internal By assuming that radionuclides concentrate in fish as indicated by the concentration factor discussed in Section 5.2.2.2. 1, the total activity in a fish of known mass can be calculated.

Essentially all of the energy of the beta particles emitted from a uniform activity distribution is absorbed in a fish. Because of the long mean-free path of gamma radiation, only a portion of the gamma energy is absorbed by the fish. The fraction of the energy absorbed depends on the shape, mass, and density of the fish, as well as the distribution of activity and the energy of the gamma rays. If it is assumed that a fish is approximated by a flat ellipsoid with axes in the ratio of 1:0.5:2.0, and that the radionuclides are uniformly distributed throughout a 2-kg mass of unit density, then the absorbed fraction does not exceed 0.2 for gamma energies from 0.05 to 2.75 Mev (Ref. 37) .

Employing these assumptions then, and assuming also that the fish live in the mixing zone for half the year, the dose rate is as presented in Table 5.2-5.

Tritium occurs naturally from interactions of cosmic rays with gases in the upper atmosphere. It was also produced in abundance as a result of nuclear weapons testing and entered the biasphere through precipitation. The tritium concentrations of Lake Ontario as measured at the. Nine Mile Unit 1 cooling water intake has averaged about 330 pCi/1. Assuming this concentration is representative of tritium activity throughout the lake, there are about one half million curies of tritium present in the lake.

5. 2-11

The release rate of tritium into the lake, the discharge concentration of tritium in the mixing zone, and the percentage of the 10 CFR 20 MCPW for this concentration are given in Table 5.2-6 for both station designs. Initially tritium releases vill be lower for the upgraded station design than for the original station design because less waste water will be discharged. However, tritium levels in the reactor water will build up to a nev equilibrium concentration which is expected to offset the reduced waste water flow. Therefore, that the total curies of tritium released will be the same for it is assumed both the original and upgraded station design. There are no knovn mechanisms by which tritium would concentrate in biota to levels higher than those in water. Hence the doses from drinking vater and from eating fish from the same location would be identical. The tritium contribution to the whole-body dose to an individual from drinking water at Oswego is also presented in Table 5.2-6.

Table 5.2-6 Tritium Release Data<<>>

Upgraded Original Station Station

- ~ Desi n Desicen.

1. Release rate, Ci/day 0.06 0.06

2. Discharge Concentration, uCi/cc 4. 3x10-~ 4. 3x10-8

3. Percent of 10 CFR Part 20 MPCW 0. 002 0.002

4. Contribution to whole body dose<<>,

mrem/yr 0.00002 0.00002

< >>Basis: See Section 5. 2.2. 4.2

~>>From drinking water at Oswego 5.2.3 Radionuclides Discharged to Ambient Air

5. 2. 3. 1 Individual The external radiation dose to an individual due to releases of radioactivity to the ambient atmosphere will depend on the relea se rates of the various radionuclides, the height above ground of the releases, and the meteorological conditions governing the long- term average movement of air-borne radioactivity across the site boundary.

Part of the modifications to-be made to NMP1 to conform to the intent of the proposed Appendix I to 10 CFR Part 50 is to increase the holdup within the offgas system.

5 2-12

Table 5.2-7 gives the release rates for fission and activation gases from the stack of the original station design. Table 5.2-7 also gives the expected release rates for fission and activation gases from the stack of the upgraded station design after a holdup time of 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> for the kryptons, 480 hours0.00556 days <br />0.133 hours <br />7.936508e-4 weeks <br />1.8264e-4 months <br /> for the xenons, and 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for nitrogen, argon, and tritium.

Radionuclides, other than halogens, whose emissions are less than 0.01 uCi/sec, are considered negligible and are excluded from this table. The calculations are based on a failed fuel basis corresponding to an offgas activity flow rate of 50,000 uCi/sec after 30 minutes delay. These gases are released from the main stack and result in doses as presented in Table 5.2-7 at the eastern boundary of the FitzPatrick Plant site 1.2 miles east of the Nine Mile Point Unit 1 stack. This determination is based on annual meteorology and the size and shape of the site itself.

The average annual ground-level concentration at this point may be calculated from the known release rates and the annual average normalized concentration, which for this site is 4.74 x 10-~

sec/m~ at that site boundary. The calculated ground-level concentrations at this location can be used to obtain the annual average dose to a hypothetical man continuously located there.

The immersion dose method of Committee Commission on Radiological Protection II of the International (Ref. 38) was used to calculate whole body dose from the ground-level concentrations..

For these activity releases, no significant ingestion dose is expected.

5.2.3.2 Plants and Animals The external exposure of plants and animals at the site boundary is essentially the same as that calculated for man. See Table 5.2-7. As is true for humans, no significant. ingestion dose is expected for animals.

5.2.4 Radionuclide Contamination of Ground Water While there are numerous private water wells in the vicinity of Nine Mile Point Unit 1, there are no anticipated releases that could cause ground water contamination. Since the water table slopes toward Lake Ontario, any changes in the ground water at the site do not affect wells located up-gradient; No expected increase in radiation levels in ground water is anticipated, therefore, there is no exposure to people, plants, or animals from this pathway.

5.2.5 Individual Exposure Estimate The values for individual radiation exposures in Table 5.2-8 represent a conservative estimate of station operation (i.e., 50,000 uCi/sec offgas activity flow rate after 30-minute delay and an aqueous release rate of 20 Ci/yr) which is higher than expected with the upgraded station des'ign previously described in Section 3.6. It is obvious from the values presented in the table that even with releas'ed quantities of

5. 2-13

Table 5.2-7 Gas Release Rates < >> from the Nine Mile Point Unit 1 Station and Calculated Whole Body External Dose Rate <>> at 1. 2 Miles East of Stack A. U raded Unit 1 Station Desi n.

Kr-88 2.8 hr 2.8 0.002 Kr-85m 4.4 hr 16. 8 0.003 Xe-133 5.3 days 312. 0 0.022 Xe-131m 11.8 days 2 4 Negligible Kr-85 10. 7 yr 7. 6 0 001 ~

Total 0 028 B. Ori inal Unit 1 Station Desi n.

External Whole Emission Rate Body Dose Rate Radionuclide- Half-life.

Kr-83m 1.86 hr 0.020 Kr-85m 4.4 hr 2900 0.461 Kr-85 10. 76 yr Kr-87 1.3 hr 8000 9 10 Kr-88 2.8 hr 8500 7.56 Kr-89 3a 2 min 0-309 Xe-133m Xe-133 Xe-13 5m yx'250

2. 3 days 5.27 days 16 min 150 100 2500 4000 0 009 0.174

0. 810 Xe-135 9.2 hr 9000 1.97 Xe-137 4. 2 min 450 0 371 Xe-138 17 min 675 9.75 N-13 9. 96 min 162 0. 140 Ar-41 1.83 hr 2. 6 0.002 H-3 12m 3 0 4 Total 30 6 C~)Basis: 50,000 uCi/sec offgas activity flow rate at 30 minutes delay

~>>Assumed to be continuous <fence-post~~ exposure Besides the offgas system, Unit 1 releases some radioactivity to the ambient atmosphere through turbine gland seals. The dose calculated from this release is 0.20 mrem per year.

5. 2-14

radioactivity several times in excess of that expected during facility operation, the radiation exposures to individuals and the population as a whole meet the requirements of Paragraph B of the proposed Appendix I to 10 CFR Part 50 and is negligible as compared to natural background.

5.2.5. 1 Liquid Releases Modifications to the Unit 1 liquid radwaste system are being designed with the objective that after modification the released radioactivity concentrations will be in accordance with the proposed Appendix I to 10 CFR Part 50, Section IIA. However, for conservatism, effluent releases employed in Table 5. 2-8 are arbitrarily based on aqueous releases of 20 Ci/year. The relative isotopic composition was assumed to be as shown in Table 3 6-3 with appropriate adjustments to account for the assumed release rate.

The individual exposure estimates from swimming, water skiing and boating are based on an individual's exposure of 200 hr/yr, 000 hr/yr, and 300 hr/yr, respectively in the mixing zone. Due to the seasonal residency in the immediate site area, the dose from drinking water is based on an individual drinking his daily intake (infant 1 liter/day, adult 2.2 liter/day) from the water at the site boundary during one half of the year and from the Oswego water supply during the other half of the year.

The doses due to fish consumption were calculated assuming that an individual eats 200 grams of fish per day. Due to seasonal conditions, it is assumed that half of the individual s yearly intake is obtained from near the station discharge, while the balance comes from sources originating randomly throughout the lake Those fish obtained near the station discharge are assumed to have spent half of their life in the mixing zone and half throughout the lake.

5.2.5.2 Gaseous releases The offgas system of -the upgraded. Unit 1 station design is designed for a holdup of 20 days for xenons, 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> for kryptons, and 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for activation gases.

The external exposures from gaseous effluents are calculated to occur at the eastern site boundary due to the prevailing winds.

The inhalation dose to the thyroid is calculated to occur at the same point. The thyroid dose from milk consumption assumes that an infant drinks one liter a day of undiluted milk from the nearest dairy farm.

In calculating exposures associated with the turbine building ventilation system, a 7-gpm leak rate into the building, an iodine partition factor of 10, and a building exhaust rate of 2 building volumes per hour are assumed. The turbine building ventilation system exhausts through the 350-foot main stack.

5 2-15

Table 5.2-8 Individual Exposure Estimates (mrem/year)

From Site Effluent Releases For Upgraded Unit 1<<>

External Ex sures Whole Bod Beta Skin-A. Gaseous Effluents<<~

Offgas 0. 013 0-015 Turbine Bldg. Ventilation 0. 014 0 0069 Turbine Steam Seals 0. 13 0. 06 B. Liquid Effluents~>>

Swimming 0. 007 Water Skiing 0. 007 Boating 0 003 Natural Background 75 (whole body) and 30 (beta skin)

External Exposure Internal Ex osures A. Gaseous Effluents Inhalation (infant thyroid) 0. 013 Milk Consumption (infant thyroid) 0 17 B. Liquid Effluents Drinking Water (infant thyroid) 2.6 Fish Consumption G.I. Tract 3. 5 Whole Body 0. 1 Natural Background 20 (K-40)

Internal Exposure

<<>Exposures listed here are estimates and in no event shall total exposures exceed the (as low as practicable) operating requirements of the proposed Appendix I to 10 CFR Part 50.

See Section 5.2.2.2. 1 and 5.2.5 for bases of this table.

C>>Exposures listed are based on a conservative offgas activity flow rate of 50,000 uCi/sec at 30-minute delay.

~~)Assumes a dilution factor of 3 at the surface from the discharge structure and an aqueous release rate of 20 Ci/yr.

5. 2-16

5.3 EFFECT OF CHEMICAL AND SANITARY WASTE TREATMENT EFFLVENTS The most frequent chemical discharges consist of neutralized spent acid and caustic solutions resulting from intermittent regeneration of makeup demineralizers. The maximum quantity of wastes accumulated during demineralizer regeneration is about 16,000 gallons which contain, after neutralization, approximately 9,000 ppn of dissolved solids, mainly sodium sulfate. These wastes, neutralized to a pH value between 6.5 and 8.5, are discharged to the circulating water at 100 gpm where they will be diluted by a factor of about 3,000. The discharge normally occurs for about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> once every 8 days. In addition to dilution of the wastes in'the circulating water, rapid dilution with the receiving lake water is achieved at the circulating water discharge.

Table 5.3-1 presents the resulting water quality analysis of the Nine Mile Point Unit 1 circulating water after complete mixing with the neutralized demineralizer regeneration wastes.

Table 5.3-1 also presents the total incremental change (i.e.,

about 3 ppm) in the dissolved solids content of Lake Ontario water resulting from the addition of the neutralized demineralizer regeneration wastes from Unit 1. This slight increase in dissolved solids content of the neutralized effluent is expected to have no adverse effect on Lake Ontario.

Effluent from the clarifier sludge settling basin, described in Section 3.7, is discharged to Lake Ontario via a drainage ditch and has a water quality comparable to that of Lake Ontario due to prior clarification and softening operations.

As discussed in Section 3.7, the chemical regeneration radioactive wastes from the condensate demineralizers are not discharged to the circulating water and consequently have no effect on Lake Ontario.

After the effluent from the laundering of protective clothing has been completely mixed with the circulating water, expected to increase the level of phosphates in the lake it is not water by more than 0.7 ppb measured as phosphorus. This slight increase is expected to have no adverse effect on Lake Ontario.

Effluent from the sanitary waste treatment facility serving Unit 1, as described in Section 3.7.2, meets the requirements promulgated by the New York State Department of Environmental Conservation and the Town of Scriba. The disinfected and aerated treatment effluent associated with Unit 1 operation is conveyed to Lake Ontario via a drainage ditch where, under certain conditions, it receives intermediate dilution from natural runoff prior to entering the lake. Effluent from the Unit 1 sanitary waste treatment facility is believed to have no adverse effect upon Lake Ontario

5. 3-1

Table 5.3-1 Chemical Discharge from Makeup Demineralizer Regeneration Total Chemicals Incremental Resulting Added to Circ. Change In Circ. Water++

Water During One Circ, Water Analysis Dis- Analysis of Drinking Water Regeneration Analysis During Charged During Lake Ontario Standards of Cycle~ Regeneration Regeneration Water USPHS and NYS Ion Lb/Re eneration C cle- m m HC03 51 0 11 94. 11 94.00 Cl- 33 0. 08 30 38 30. 30 250 SO4= 727 2.01 32. 11 30-10 250 Ca++ 41 0. 10 44. 10 44. 00 Mg++ 0 02 8.92 8 90 Na++ 342 0 95 17.55 16-60 K+ 1.60 1.60 Total Dissolved Solids 3i 27 228.77 225. 50 500

~Regeneration cycle occurs for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> with resultant effluents from the neutralization tank discharged to the circulating water at 100 gpm.

• ~Computed by adding the incremental changes during regeneration to the concentrations of the respective ions present in Lake Ontario water.

k 5 4 QZHER ENVIRONMENTAL EFFECTS 5.4.1 Transmission Line Effects The 27-mile route for electrical energy transmission from Nine Mile Point Unit 1 to the Clay substation in the town of Clay, New York, was acquired during station construction (1965) and has a total right-of-way width of 500 feet. The center of this right-of-way is presently occupied by two single circuit 345 kV lines supported by lattice steel towers for a distance of 1.7 miles from Nine Mile Point. Wood pole, H-frame towers (Figure 3. 2-4) support the lines the remainder of the distance with the exception of steel towers for the final 0.3 mile into the Clay substation.

The Nine Mile Point Unit 1 transmission route is. considered a rural corridor which results in minimal disturbance to private homes and farmlands. The route avoids established or proposed recreation areas, wildlife refuges and designated historical or scenic areas. The land mass beneath the lines is a combination of open farmland, wetland and wooded areas. Portions (about 10 acres) of the right-of-way corridor continue to be cultivated as pine tree plantations and farmland in keeping with Niagara Mohawk's policy of multiple land use for transmission lines.

Right-of-way maintenance along the transmission line is performed under supervision of Niagara Mohawk personnel in such areas and at such times as is necessary to maintain sufficient clearance between existing tree growth and the conductors. Approximately 30 miles of unpaved, dirt roads placed adjacent to the transmission line route during line construction continue to be used. These roads provide access for line inspection and service and are maintained for year-round access by Niagara Mohawk personnel. Periodic removal of growth along portions of the right-of-way is accomplished on a scheduled basis and through necessity includes those areas where growth was initially retained or selectively cleared Maintenance operation in all areas is accomplished by selective use of herbicides approved for such use by appropriate governmental agencies, supplemented by mechanical clearing. The principal objective of the right-of-way maintenance program is to promote service reliability. Niagara Mohawk has endeavored to encourage natural growth of desirable species of trees, shrubs, and ground covers, which in turn, should preserve and enhance the ecological value of the right-of-way and foster and sustain wildlife habitat.

Environmental disruptions which may have occurred during line construction have since been neutralized and the balance of terrestrial ecology has been restored.

5. 4-1

s J

J 1

'f t

5.4.2 Radioactive Material Transport Effects Adherence to the AEC and DOT regulations and various containment requirements discussed in Section 3. 6. 5 increase assurance of minimization of adverse environmental effects during the shipment of reactor fuels and radioactive wastes to and from the Nine Mile Point Nuclear Station. During normal shipping conditions, there is no release of any radioactive materials from new fuel, spent fuel, and solid radioactive waste shipping containers. The only effect anticipated would be the insignificant direct radiation exposure of the population located along the shipping route. At the maximum permitted level of 10 mrem per hour at 6 feet from the nearest accessible surface, an individual standing as close as 100 feet from the shipping vehicle could be exposed to a gamma radiation dose rate of 0.2 mrem per hour. This radiation dose would decrease further to 0.01 mrem per hour at about 300 feet.

Considering realistic exposure times for individual members of the general public, the resulting doses are very small and would be entirely negligible at greater distances. Radioactive material shipments are labeled as such in accordance with governing regulations, to alert shippers and other individuals in the vicinity of the shipment of their proximity to the radioactive material, thereby further minimizing exposure to radiation. Actual Unit 1 shipping experience has shown external dose rates below the maximum levels specified by the regulations.

Radioactive material shipping containers and packaging procedures are designed to restrict the release of radioactive material to a minimum under the most severe accident conditions. In addition, the mechanical properties of the reactor fuel and fuel assembly reduce the consequences of an accident by their tendency to bind the fission products within the basic fuel assembly. If a radioactive waste shipment were involved in an accident, the release of radioactive nuclides would be minimized by the "solidified" nature of the materials and the shipping container integrity.

Another important consideration in discussing the transportation of radioactive material is the outstanding safety record achieved by the nuclear shipping industry. Comprehensive records of shipping incidents involving radioactive materials have been maintained and reported by the AEC (AEC U/3613, TID-16764 including Supplements 1 and 2). Over the past 20 years, there have been very few incidents, most of which resulted in little or no radioactive releases.

It is anticipated that the safety record of future radioactive material shipments will equal, and probably surpass, the present safety record. This future record will reflect the more rigorous AEC and DOT regulations summarized in Section 3.6. The continuing efforts of fuel reprocessors, fuel suppliers, and waste disposal contractors to route shipments by the shortest and

5. 4-2

I, C f 'l 0

4 E

'I I

1 quickest routes and to minimize the required number of shipments reduce the probability of shipping incidents.

In summary, when all aspects of shipping radioactive material are considered, it must be concluded that no adverse environmental effects result from the normal shipment to and from Nine Mile Point Nuclear Station Unit 1. It must also be concluded that because of package design only insignificant environmental effects could result from a shipping accident.

5.4.3 Noise Effects There "are numerous sources of noise within the Nine Mile Point station, but this noise is confined to the structure s interior by the double-walled insulated siding on the station. The only noise significant enough to be considered is the main power transformers. This section discusses noise from the transformer and compares it with the present background level.

5.4.3.1 Plant Environment Day and night ambient sound level surveys were conducted in the vicinity of the plant in 1971 by the noise services group of Bolt, Beranek and Newman, Inc., Cambridge, Massachusetts.

Figure 5.4-1 shows the location of each of the measurement sites.

The entire area is rural or semirural, but with some residences along the country roads.

The ambient octave band sound level measurements from each of the sites are shown in Figure 5.4-2 These measurements were taken between midnight and 2:00 a.m. on a calm, clear morning and represent the minimum levels at that time. The Nine Mile Point Unit 1 Station was not on line, but the plant ventilation fans were operating. There was also a diesel engine running at low speed 3,200 feet east of the site. The levels at site 1 are highest because of the close proximity of the station and minor construction noise.

The station and construction noise was first barely audible at measurement sites Nos. 2, 3, 5, and 6 of Figure 5. 4-1 so the levels shown in Figure 5.4-2 are essentially background levels.

The peak in the data at 4,000 Hz is from the chirping of crickets which raised the ambient measurements approximately 10 decibels, A scale (dBA), Re 0.0002 microbar at some of the locations.

5.4.3.2 Plant Noise Sources A second noise survey was conducted in the vicinity of Unit 1 with Unit 1 in operation. Detailed measurements indicated that the main transformer is the only significant noise source and that the maximum Unit 1 transformer noise expected at the property line is as shown in Table 5.4-1. The transformer noise from Unit 1 is thus less than or equal to the existing ambient

5. 4-3

C. A Pt' ON TA R' 0 i

2 I

pO

,r pO gs  !

PROPERTY LINE I

'K 1

I I BURT MINOR ROAD UJ ILI hC NORTH BANKER ROAD FIGURE 5.4 -1 SOUND LEVEL MEASUREMENT LOCATtONS

60 IL

<<C LQ O

K O

F 50 N

O O

O 0

W K

Cl 40 K

IIJ UJ hJ 30 M

CO UJ 0

Cl

'z 20 D

O CO D

tQ UJ IO I-O O

0 31.5 63 I 25 250 600 IOOO 2000 4000 8000 OCTAVE BAND CENTER FREQUENCIES IN H Z SITE I SITE 4 SI TE 2 SITE 5 SITE 3 SITE 6 FIGURE 5.4 - 2 SOUND PRESSURE LEVELS

level after it. has been corrected to compensate for cricket noise. Most neighbors, however, actually receive signif icantly .

less noise because of intervening trees and terrain.

Table 5.4-1 Comparison of Ambient and Maximum Transformer Noise at Measurement Sites for Unit 1 Decibels, A Scale, Re 0.0002 Sites Measured ambient 38 29 39 38 28 33 Corrected ambient 37 23 27 29 26 34 Maximum transformer 37 22 24 22 28 30 5.4.3.3 Acoustical, Impact The peak transformer noise from the station is equivalent to or less than the background level at, the measurement locations and the station is usually inaudible at the property line.

5.4.4 Measures Taken To Preserve The Existing Environment Or Enhance Its Use Niagara Mohawk's Progress Center shares part of the site west of Unit 1 and has averaged 50,000 visitors a year officially opened in 1967. Sight and sound since exhibits it combine realistic sound effects and audio-visual techniques to demonstrate the historic evolution of energy from water wheels to nuclear power. The exhibits include an exact-scale model of the Nine Mile Point Station, the largest such model in the U.S., and exhibits of live game fish. The Center's walls are built of stone from one of the world's richest fossil deposits near Albany and clearly show well-preserved specimens of marine life dating back 400 million years, when 'much of New York State lay beneath an inland sea. A fully equipped classroom is available for visiting school and college classes.

Along the bluff and woods west of the Center are nature-study trails, and picnic facilities with a sweeping view of Lake Ontario.

Part of the site was established as a natural wildlife refuge in 1969 by posting the northwest corner of the site. The remainder of the site, including the shoreline sport fishing access area, is open for public use except during construction periods.

Offshore sports fishermen are also undisturbed.

5. 4-4

S 5.4.5 Interaction with Neighboring New York State Power Authority Facilities The James A. Fitzpatrick Nuclear power plant owned by the Power Authority of the State of New York is being constructed on land immediately adjacent to Niagara Mohawk's caste~ property boundary.

Niagara Mohawk personnel will operate the FitzPatrick Plant under contract to the Power Authority. Plant operation is scheduled to begin in 1973.

The Niagara Mohawk Unit and the Power Authority Plant are located on two distinct, but adjacent sites. They would be operated as a common site, multiple-unit station.

5.4.6 Disposal of Miscellaneous Solid Waste Solid waste, such as floating debris and trash collected on the cooling water inlet trash racks, lunchroom waste, office waste paper, and machine shop scraps, are trucked off-site for disposal at a State-approved waste disposal site.

5.4.7 Changes in Site Land and Water Use

5. 4. 7. 1 Land Use As described in Section 2. 1. 1, Niagara Mohawk purchased the 1,600-acre Nine Mile Point site in 1963 and later sold about 700 acres to the Power Authority of the State of New York. The most recent land use had been as an artillery range until 1957.

There were only eight farmhouses and a few summer cottages and a small restaurant on the site; these were removed when Niagara bought the site.

Use of the site as an artillery range prevented use of the lake shore for other purposes. As described in Section 2. 2, the shore front has never been suitable for year-round residence or for summer homes.

Only about 5 percent, or 45 acres, of the remaining 900 acres are actually used for power generation or transmission for Unit 1, including the Progress Center. Plans for use of portions of the off-site as a wildlife refuge, and for effects on shoreline and shore sports fishing, are discussed in Section 5.4.4.

5. 4-5

5.4.7.2 Water Use The only water resource which can be affected by operation of the station is Lake Ontario. The lake is bordered on the south and east by New York State and on the north, west, and southwest by the Province of Ontario in Canada The operation of the station does not affect Canadian waters or the waters of other states.

There are no streams on the site, and since the groundwater gradient slopes toward the lake, ground water users are not affected.

The hydrology of Lake Ontario is described in Section 2.5 and briefly summarized below As shown in Figure 2. 5- 1, Lake Ontario water temperature at the surface sometimes reaches 77 F during late summer and drops to a winter minimum of slightly above 32 F. There is very little diurnal change in water temperature. The lake is stratified during the summer and early fall. Ice cover forms in the slack water bays in winter, but the lake itself is seldom more than 25 percent covered with ice, which is usually concentrated in the eastern end of the lake. Lake Ontario~s outflow river, the St.

Lawrence, is ice-covered from late December until the end of March, all the way from the lake to the International Boundary at Massena, New York.

The supply to Lake Ontario is made up of about 85 percent from the upper Great Lakes and 15 percent from the Lake Ontario Basin.

Precipitation on the lake exceeds evaporation by about 6 inches annually: 30 inches vs. 24 inches. Records dating back to 1860 indicate that the long-term average supply to Lake Ontario from the upper Great Lakes has been about 200,000 cfs, and that the average outflow from Lake Ontario into the St. Lawrence River has been 240,000 cfs. Unit 1 utilizes about 600 cfs, of which approximately 0.02 cfs might be considered to represent consumptive use, as discussed in Section 3.4.

Lake currents in the area are generally less than 0. 5 fps.

Dominant circulation patterns are shown in Figure 2. 5-1.

Currents near the shore in the vicinity of the station site are generally from the west. The tidal effect is minimal and is measured in inches only.

A 1970 report by the International Joint Commission, which is responsible for settling questions involving use of boundary waters between the U.S. and Canada for water power, navigation, sanitation, and irrigation, notes that the lake is in a state of eutrophication between oligotrophic and mesotrophic. The Commission also notes that the in-shore waters are more eutrophic than the off-shore waters due to the shallower depths and the fact that most nutrient inputs enter along the shores.

5. 4-6

I~ V

~

i p h

Lake shore recreational areas are shown on Study Area Map (Figure 2.2-3) . The nearest is Selkirk Shores State Park, ten miles east of the site.

The nearest public water supply intake using lake water is for the city of Oswego and the Onondaga County Water District and is located about 8 miles west of the site at a 40-foot depth, 6,000 feet off-shore. One or two orchards, 5 miles east of the site, use lake water for irrigation.

Travel times for the diluted station discharge to the Oswego intake and Selkirk Shores State Park are shown in Figure 5. 4-3.

Dilution factors to the Oswego intake and Selkirk Shores State Park are shown in Figure 5.4-4. The type of discharge used for Unit 1 and its close proximity to the irregular shoreline make the results of a determination of the far field dilution factors extremely questionable using presently available methods.

Consequently, a jet diffuser type discharge, with double the heat load to account for the existing boundary (shoreline) effects, was used for dilution factor analysis. This analysis is assumed to be representative of actual dilution factors resulting from station operation. For a current of 0.4 foot per second, the travel times are 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> to the Oswego intake and 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> to the State Park. With this current, the unit discharge is diluted by a factor of approximately 156 by the times Oswego intake and a factor of 235 by the time State Park.

itit reaches the reaches the 5.4.8 Effects of Released Combustion Products Overall combustion products released from the two standby diesel generators and one diesel-driven fire pump discussed in Section 3.8 are insignificant because this equipment is normally operated only a few hours a month for test purposes.

Consequently these discharges do not alter the air quality of the region as established by the Environmental Protection Agency and the New York State Department of Environmental Conservation.

5. 4-7

C IO SELKIRK SHORES STATE PARK OSWEGO/OCWD P UBLIC WATER INTAKE lO 0 0.2 0.4 0.6 0.8 I.O LAKE CURRENT SPEED- FT. PER SEC, FIGURE 5.4" 3 TRAVEL TIME VS. LAKE CURRENT

X X

O O

O I SELK I RK SHORES STATE PA RK K

O I-O U.

K 0

I-D O

IO X

R OSWEGO / OCWD PUBLIC WATER INTAKE 00 0.2 04 0.6 0.8 I.O LAKE CURRENT SPEED - FT. PER SEC.

F I GURE 5.4-4 DI LUT I ON FACTOR VS. LAKE CURRENT

5.5 ASSESSMENT OF ENVIRONMENTAL EFFECTS OF STATION OPERATION Ecological and aquatic surveillance studies have been conducted along the two-mile stretch of the Nine Mile Point promontory since 1963 to obtain data regarding the effects of heated discharges upon the lake ecology. These studies are being closely coordinated between the Power Authority of the State of New York for the James A. FitzPatrick Nuclear Plant and Niagara Mohawk for Nine Mile Point Unit 1. In,1970 and 1971, the studies provided postoperational information reflecting the operation and actual heat discharged from Nine Mile point Nuclear station Unit 1.

These studies are being conducted by Dr.. John F. Storr, Consultant in Limnology and Oceanography and Associate Professor of Biology at the. State University of New York at Buffalo. The original program of studies was planned with the cooperation of the Department of Environmental Conservation. As the studies progressed, various refinements and extensions have been adopted to provide a more complete description of the study area.

Niagara Mohawk will continue to cooperate with the U. S. Bureau of Sport Fisheries and Wildlife and other interested State and

-Federal agencies on ecological studies until it has demonstrated conclusively that no significant adverse conditions exist.

The field program has covered fish distribution and food preference studies, benthic studies including attached algae and invertebrates, nutrient distribution studies, and studies of plankton distribution and entrainment. -

The various studies conducted as part of the Nine Mile Point surveillance program are listed in Appendix F.

Twelve north-south transects extending offshore of the site were established for sampling purposes (see Figure 5.5-1). The transects farthest east and west of the site (E-9 and W-3) are located far enough from the station to monitor conditions outside; of its influence. Sampling of aquatic organisms is conducted, along each transect to provide baseline information which will be.

used as a comparison with studies conducted during Unit 2 operation.

5 5. 1 Fish Distribution Two types of fish distribution studies were- conducted from 1968 to 1971 to determine the total number, location and species distribution of fish at the site: (1) fathometric surveys and (2) fish netting. In addition to these studies, a program was initiated in 1970 to determine the basic food habits of the dominant fish species in the vicinity of the plant. These stud'ies are performed four times per year, one each spring and fall, and two in summer.

5. 5-1

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NINE MILE POINT JAMES A. FITZPATRICK NUCLEAR STATION NUCLEAR POWER PLANT PROPERTY LAKE VIEW LIN E APPROXIMATE LAKE DEPTHS DISTANCE DEPTH FROM SHORE (BELOW L.W. DATUM) 50 6 0 e00 1%N) 400 I2 600 18 SCALE - FEET 900 24 I I 00 30 3000 60 FIGURE 5.5-I LAKE SAMPLING TRANSECTS AND ON- SITE RADIOLOGICA L MON) TORING LOCATIONS

0 f

5.5.1.1 Fathometric Surveys Fathometric surveys were made during the daytime along all the transects using a fine-line recording echo-sounder. Tracings were also made along two of the transects every four, hours during a 24-hour period to obtain both the maximum concentration and the diurnal pattern of fish movement. Each fish was recorded in terms of both vertical location and relative size.

Interpretation of the tracings was based on the fish net studies and general size distribution of fish.

The echo-sounding survey data indicated that fish were distributed randomly in the area during the daytime with some general tendency for the fish to concentrate along the 25-foot depth contour or in slightly deeper water. Pockets of concentration were found at many locations other than the 25-foot contour and at times such concentrations could be associated with bottom structural features. Z,arger concentrations of fish were recorded in May and June over the 1969-71 period than at any other time in the year. Alewives and small forage fish were most abundant at this time of year and the alewives were actively spawning in the algal growth on the bottom. Active feeding on both the alewives and alewife eggs by other species of fish occurred at this time. In June through August of 1969 to 1971, the numbers of fish sharply declined and very few were recorded in October (1971 data not completely analyzed). This appears the result of both movement offshore and lack of activity as to'e the food supply diminishes in the inshore waters.

The 24-hour fathometric studies indicated ma jor fish concentrations in the 20-foot depth and beyond, with maximum concentrations between the 30- to 40-foot depths developing in the middle portion of the night between 10 p.m. and 3 a m. Fish concentrations were lower and activity reduced in the area during the daylight period.

The echo-sounding traces indicated that the percentage of fish of a size larger than about six inches varied considerably. In May 1970, only about eight percent of the fish counted were larger than six inches. This number increased to over 40 percent in August and declined again to below 30 percent in October. The average number of fish larger than six inches for the four studies made in 1970 was about 18 percent.

Another method of calculating fish distribution using the echo-sounder was developed in 1970. This method entails mounting the transducer of the echo-sounder on a submerged pole so that scanning can be done horizontally as well as vertically.

Circular scans out as far as 100 feet were made in the area.

Although the irregular nature of the bottom makes interpretation difficult, this method gives an accurate count of fish in a .

defined area and is useful in shallower water of 7 to 15 feet for comparative values.

5.5-2

Surveys using this technique were conducted in July and August, 1970 and 1971.. The results in 1970 showed a gradual increase in numbers of fish from shallow water (less than 10 feet) to deeper water (more than 20 feet) by a factor of about two. During August in the area of the Nine Mile Point Unit 1 discharge, the number of fish in the shallow water was slightly greater than at the 15-foot depth contour.

5.5. 1.2 Fish Netting The fish netting program generally consisted of sampling with five experimental gill nets to determine the species distribution offshore from the site. One net was set on the bottom as close to the shore as practical; two nets were set at the 15-foot depth zone with one net suspended at the surface and the other placed on the bottom, and two nets were similary located at the 30-foot depth zone. Nets were set in the afternoon and removed the next morning for four to five consecutive days. For each net, the fish were identified, counted by species, and each fish weighed and measured. (Refer to Section 2 for list of species.)

In 1971, the netting pxogram was changed and 6 nets are now set in each 24-hour period. For two days nets were set at shore and in the 15-foot depth close to the location of the Nine Mile Point and FitzPatrick discharge structures, and for two more days at shore and in the 30-foot depths on both transects. While the actual net placements are unchanged, the new program has made possible a better comparison between the areas, since same-day catches are compared in each case.

Alewives were taken in the greatest number, with yellow and white perch next in order of occurrence. Relatively few alewives were caught in the nets set on the bottom, as these fish are wide ranging and normally stay fairly close to the 'lake surface. In 1969, the number of alewives caught in August were few compared to those caught in June. In August, the greatest numbers were found in the top nets farthest from shore, while in June the alewives tended to be along the shore. Perch along with minnows were primarily taken in the shore nets. There appeared to be some reduction in the number of those fish caught in the shore nets in August as compared to June. Except for alewives, very few fish were found near the surface.

The fish netting program in 1970 and 1971 indicated some changes from the studies in 1968 and 1969. The catches of alewives in May 1970 were only 5 to 10 percent of the number caught during the same period in 1969. Comparably low numbers remained throughout 1970. These trends are probably attributable to the natural mortality of alewives that occurred over the entire lake throughout the spring of 1970. %here was an increase of gizzard shad in the fall of the same year. The reduction of the alewife population, which forms part of the food supply for larger fish, also appeared to bring about a lessening of fish activity in the

5. 5-3

latter part of the year and a dispersal of the fish throughout the lake.

Preliminary results in 1970 and 1971 indicate that the thermal plume from Nine Mile Point Unit 1 tends to attract certain species of fish, including carp, sunfish, smallmouth bass and alewives, during the cooler months. Shen ambient temperatures are high, there appears to be no attraction of fish to the plume and some species, such as white perch, appear to avoid warmer portions of the plume. In 1971, the number of smallmouth bass observed in the vicinity of the discharge increased significantly. Observations by divers indicate that smallmouth bass made up a significant portion of the fish population over 6 inches in length.

The only fish which appears to spawn in the area is the alewife mat is concentrated primarily in water less than 10 feet deep and is essentially absent beyond the 20-foot depth. Hence, spawning takes place well inshore of the discharge and no effect on the reproductive potential of this species is anticipated.

5.5. 1.3 Pood Preference Surveys A program was initiated in 1970 to determine the feeding habits of the major fishes in the area and to ascertain any relationship between these fish species and their food supplies. The yellow perch was selected as the primary species of investigation since it was one of the few fishes present in the area in sufficiently large numbers to obtain significant results on feeding behavior throughout the year. Other species of fish were also examined during the latter part of the year. Length frequency distributions were tabulated and the various food items noted for the different size groups.

A number of species of organisms are used as forage by the fish population. The studies indicate that small alewives, sculpins, darters and alewife eggs are the primary food sources in the spring of the year. As the season progresses, the freshwater amphipod .(Gammarus- sp) assumes greater importance in the food chain Crayfish appear to be an important component of the diet for some fish species in the autumn, such as smallmouth bass. As Gammarus abundance declines in the autumn, small forage fish become a major food source.

5-5.2 Benthic Studies During August of 1968, and June and August of 1969, 1970 and 1971, samples of bottom organisms were collected by divers at 5, 10, 15 and 20-foot depths along the same 12 transects used for the fathometric fish count studies. Three samples of benthic organisms were scraped from rocks at each depth. In the laboratory, each sample was separated into plant and animal 5.5-4

material. Plant material was dried, ashed and weighed.. Animal species were separated and counted.

w structure (i.e. flatrocks) support a heavier growth of these algae than others and the plant is therefore very irregularly distributed over the bottom. Wave activity tends to diminish the biomass in water 5 feet deep or less, and decreasing light penetration at the 15 and 20-foot depths produces a corresponding decrease in growth. At 20 feet, growth was so short and scattered that a sample large enough for analysis could seldom be collected. Generally, the heaviest growth is at the 10-foot depth. By August, changes in light and in temperature reduced the algal growth considerably as compared to June. The amount of growth observed at any time was not heavy, but rather sparse and scattered, and the rock bottom was visible at all times.

In 1970, the survey results indicated that the Nine Mile Point Unit 1 effluent tended to eliminate the irregularities in growth along the promontory. Algal growth generally declined more sharply in August, 1970, as compared to 1969. In the area immediately inshore of the thermal discharge (400 feet offshore) algal growth in the 5-foot depth was found to be somewhat 65 F (Ref. 16) . With natural lake temperatures in the mid 70's and the water temperature at shore somewhat more elevated by the thermal discharge, the growth for a distance of several hundred feet along the shore was below that found elsewhere. The major 15 and 20-foot depths, which is below any influence of the thermal discharge. Several factors usually tend to reduce the algal growth in August. The long filaments developed in June tend to become fragile and break off because the light penetrates less deeply in late summer. Also, there are fewer'ours of sunlight and water temperatures are considerably above optimum for growth.

closely with the early 1970 survey. The biomass of algae in 1971, however, was generally higher along the sampling transects than previous years.

Total benthic animal abundance remained about the same during 1969 and 1970. Of the animals present, Gammarus was found in abundant. The greatest concentrations appear at the 10-foot depth along with the maximal algal growth. Considerably more Gammarus were found during the August surveys than in June.

Snails of three species were found only in small numbers, tending to concentrate at the 15-foot depth. The midgefly larvae

~Tendi s occurred in an entirely irregular pattern and were less abundant in late summer.

5.5-5

Results of the early benthic survey in 1971 indicate that Gammarus abundance was greatly increased in the area of the thermal plume. ~Tendi es ahundance was also higher in 1971 than previous years; however, the number also increased on the transects outside of the area of influence from the discharge, suggesting that that increase was probably associated with some factor not related to the operation of Unit 1.

The major effect of the thermal discharge on the benthos, therefore, is to depress algal growth in late summer. In addition, the population of Gammarus appears to have increased in the zone of the thermal discharge. These are preliminary results/ which will have to be verified by continuing studies in order to be conclusive.

5.5.-3 Nutrient Distribution Studies To assess the magnitude of a possible change in the distribution of nutrients at the site due to flow patterns established by the cooling water flow of the Nine Mile Point Unit 1, surveys of the nutrient distribution were made in August 1969, and May 1970..

A series of water samples were collected offshore from the FitzPatrick power plant in water depths of 30 and 100 feet. At the 30-foot depth location, water samples were taken from the surface and at each 10-foot depth to 30 feet. At the 100-foot depth location, water samples were taken from the surface and at 25-foot intervals to 100 feet. The water samples were analyzed for nitrate and total phosphorus content.

The results of the August 1969, survey indicated that at the 30-foot depth sampling station, the concentration of nutrients was quite low and fairly uniformly distributed in depth. The surface concentration of nitrate was 0.275 milligram per liter (mg/l) with concentrations at 10 to 30 feet varying between 0.102 and 0. 115 mg. Some decrease in nitrate was evident with increasing depth. The concentration of total phosphorus from top to bottom ranged from 0.015 to 0.024 mg/l. At the 100-foot depth sampling station, the concentration of total nitrates in the upper water column was less than at the shallower station and ranged from 0.080 mg/l at the surface to 0.047 mg/l at 75 feet.

At 100 feet the concentration was higher, rising to 0.920 mg/l.

This may be attributable to a release of ammonia from decaying organisms in the bottom sediments. Concentrations of phosphorus were similar to those found in shallower water ranging from 0.019 to 0.011 mg/l.

The nutrient levels found during the spring 1970 surveys were generally higher than those for the previous summer. At the 30-f oot depth sampling station, surf ace and bottom nitrate concentrations had increased two and six-fold, respectively, over the fall 1969 values. The concentrations of phosphorus were slightly higher than those of the previous fall, ranging from 0.020 to 0.022 mg/l from surface to bottom. The nitrate 5.5-6

concentration at the 100-foot depth sampling station ranged from 0.60-0.89 mg/1 from surface to bottom. 'Phosphorus concentrations at 100 feet were slightly higher than the fall sampling period.

The increase in nutrient concentrations in spring is to be expected following breakdown of the thermocline in late fall.

Xn general, the concentrations of nitrates and phosphates are low and evenly distributed offshore from the site. Therefore, flow patterns induced by pumping from the 30-foot depth zone should have no effect on the redistribution of nutrients in this region.

Dissolved oxygen measurements have been made in the discharge area during the fish netting survey. As the summer progresses, oxygen so that even during the warmest period of the year levels of dissolved oxygen of 11 to 12 ppm are not uncommon, with'o diminution at night. No significant loss in oxygen has been observed between the intake and discharge of Unit 1.

5.5.4 Plankton Distribution and Entrainment A preliminary sampling program was conducted from early June to late October 1964. Plankton samples were collected at three locations directly offshore (500 feet out 30 feet deep; 7,500 feet out 100 feet deep; and 10,000 feet out 200 feet deep) from the site and were generally dominated by ~Co)~e oda-and Cladocera Preliminary results indicated that populations drift toward shore with onshore winds and become less abundant near shore with offshore winds and currents. The pattern of movement will be affected by the operation of the plants, because the intakes will draw in water radially, while the discharge will maintain a steady offshore movement. It is anticipated that since more bottom water than surface water will be drawn toward shore and into the intake, fewer plankton will be entrained than would normally be expected, since studies indicated higher plankton concentrations in the surface waters. Very few fish larvae were taken in the 1964 plankton study.

anticipated that many fish larvae will be entrained, with the It is not possible exception of some alewive larvae.

Addit ional plankton studies were conducted at Nine Mile Point Unit 1 from spring through autumn 1971 to assess the effects of station operation on plankton passing through the circulating water system. Water from the intake and discharge lines was sampled in the screenhouse and the percent mortality of planktonic organisms determined for various groups of zooplankton and motile phytoplankton. Samples of plankton from the discharge were also held for 6 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to determine the time-temperature relationship on plankton mortality. . The rotifers generally dominated the plankton community during these inve s tiga tion s.

5.5-7

'L Results of the studies were variable, depending on time of the year, wave conditions, temperature rise, and duration of exposure to the elevated temperatures. The preliminary results of this study, however, indicate that the overall level of mortality of plankton passing through the plant is conservatively estimated to be between 10 and 30 percent.

5.5.5 Three-Dimensional Thermal Surveys Three-dimensional thermal surveys were conducted Dr. John F.

Storr in conjunction with his ecological studies inbyLake Ontario.

(Refer to Section 5.5). These surveys consisted of towing a line of four submerged thermistors along preselected courses.

Temperatures were measured at depths of 0.3, 3.7, 7. 1 and 10.5 feet along the same 12 transects which were used in the ecological surveys. Temperature measurement runs were also made on individual passes over the discharge structure.

A total of 12 thermal studies as listed in Appendix F, were made in 1970 and 1971. In 1970, four three-dimensional thermal studies were conducted in mid-July after the station was returned to an on-line condition after a shutdown for maintenance. In 1971, eight studies were conducted beginning on June 19 and continuing to November 16.

These temperature measurements were combined to form contour plots of lake temperatures at various depths. Areas were fairly well defined in terms of physical dimensions in which the thermal effects could be evaluated. The results of these surveys and the

,environmental effects are discussed in Section 5. 1.

5.5.6 Future Field, Laboratory, and Monitoring Programs The environmental study data that has been collected and evaluated to date demonstrates that the environmental impact of Nine Mile Unit 1 operation has been insignificant. Future programs will continue efforts in the area to corroborate the information previously gathered and to gain further knowledge.

Specific studies planned for 1972 are discussed in the sections that follow; these programs may be modified as information is obtained.

5.5.6.1 Effects of Entrainment on Fish Eggs and Larvae The purpose of these studies is to determine the amount of fish eggs and larvae that enter the intake and the mortality rate of these organisms attributed to their passage through the station's circulating water system. In addition, the mortality rate resulting from passage through the system would be related to the available population in the lake. The first objective will be accomplished by detailed field and laboratory experiments, while the second will require the use of mathematical models and statistical analysis.

5. 5-8

4 One of the ma jor difficul ties with entrainment studies is devising a sampling procedure that will not cause a significant mortality of the organisms being collected. Unless the mortality due to sampling is kept to a minimum, it may not be possible associate any statistical conf idence to the estimated mortality to rates of the eggs and larvae. Collection methods for fish larvae have been developed over the past few years that do ensure a satisfactory sampling error; however, these techniques must be investigated to determine their applicability at the Nine Mile Point Station.

Fish eggs and larvae will be collected at the intake and discharge of Nine Mile Unit 1 and in Lake Ontario offshore of the site. Differential mortality rates between intake and discharge will be determined and, if significant, an attempt will be made to determine whether damage to these organisms results from thermal, mechanical or pressure stress.

A program of detailed observation will be conducted during 1972 to measure fish collected on trash racks and travelling screens.

5. 5.6.2 Fish Population Study Fish surveys will be conducted at the site from April through November at 1-month intervals, resulting in a total of eight surveys during the year. Fish will be collected by trawling along transects in the lake.

Trawls will be made offshore of the site and west of the site.

The west trawl will be used as a control, i.e., this transect will be located at a point where the discharge does not significantly affect the lake ambient temperature. Thus, the condition and relative abundance of fish along the control transect can be compared with the fish in the presence'f the thermal discharge in order to determine whether the plant discharge has any significant effects on the fish.

Fish trawls will be made at the surface and near the bottom of each transect during the morning, mid-afternoon, and evening.

Fathometric fish traces will be made along each transect, simultaneously with the trawl run, in order to determine areas of unusual fish concentrations.

Field analysis of the fish will include taxonomic identification and length, and weight analysis. A subsample of the fish from each survey will be preserved for food preference, fecundity and age classification.

Length-weight relationships, age, specific reproductive rates and food preference can be derived from the above data base.

Differences among various regions and amoung subsequent years data will provide a basis for evaluating ecological impacts of the station~s discharge. Changes in growth rates, reproductive 5.5-9

II rates, etc., can be used as an indicator of stress on fish populations.

5.5.6.3 Benthos and Cladophora Survey Previous 'fish surveys at other Lake Ontario sites indicate that crayfish appear to be a significant food source for the fish in the area. Therefore, a population estimate will be made based on diver operations or catch per unit effort techniques. The crayfish investigation would be conducted with each fish trawling survey.

In addition to the crayfish, the other benthic organisms would be sampled three times during any one year. Samples will be collected by divers at various depths along the same transects used for the fish surveys. The samples will be preserved and sent to a laboratory where they will be sorted, identified and analyzed.

Simultaneously with the benthic surveys, qualified divers will site. Samples will be collected in order to measure the growth of this alga with depth.

5.5.6.4 physical-Chemical Analysis Water samples will be collected and analyzed at two stations in the discharge structure area at the lake surface and bottom in order to determine variability of water quality with depth.

Water samples will also be collected in the screenwell area from the intake and discharge of Unit 1 and from the sanitary waste treatment facility effluent outfall.

The samples will be analyzed in a laboratory to determine biochemical oxygen demand (BOD), chemical oxygen demand (COD),

total nitrogen, total phosphrous, nitrates, ammonia, solids, phenols, sulfates, chlorides, and trace metals (chromium and zinc) . Dissolved oxygen, temperature and pH measurements will be made in the field.

5.5.6.5 Meteorology Meteorological data was collected at Nine Mile Point during 1963-64 in sufficient guantity and detail to permit the evaluation of Unit 1 environmental impact.

Additional meteorological data will be collected for at least one more year. A 204-foot meteorological tower is in use at the site and is instrumented for measurement of wind velocity and direction, and dry bulb and dew point temperatures at the 30-,

100-,, and 200-foot levels. Additional dry bulb and dew point temperature measurements will be made at the 248- and 340-.foot levels on the Unit 1 stack. Precipitation will also be measured at the site and correlated to wind direction and velocity.

5.5-10

5.5.6.6 Radiation Environment The program of radiological sampling and monitoring discussed in Section 2.8 has been expanded to add four monitoring stations (to a total of 15) and increase the surveillance area to monitor the operation of the James A. FitzPatrick Power Plant scheduled for startup in 1973 as well as Nine Mile Point Unit 1.

5. 5-11

y, 4 SECTION 6 ENVIRONMENTAL EFFECTS OF ACCIDENTS 6~ 1 SCOPE This section considers the radiological environmental risks due to abnormal transients and postulated accidents as required bythe 10 CFR Part 50, Appendix D, (Ref. 39), and as directed by recently issued Supplement (Ref. 40) to the draft AEC guide for the preparation of envir cnmental reports (Ref. 41), herein referred to as the guide. This information is presented in the following manner:

a. A description ,and interpretation of the probabilistic considerations of the radiological effects.

b. An examination of characteristics of the station with respect to the suggested AEC-environmental report event classification.

c. determination of the radiological effects and their significance for each AEC classification category as it A

applies to a boiling water reactor (BWR) .

and

d. An evaluation of environmental impacts of the radiological effects. Data supporting meterological diffusion calculations and radiological dose calculations are included as Exhibits A and B in Appendix I. A summary of radiation exposure from natural background and man-made sources of radiation is presented in Section 6.9.

6. 1. 1 Probability in Perspective Consideration of the yearly probabilities of abnormal conditions is, of course, entirely necessary to an assessment of environmental risk for the cbvious reason that such conditions are not expected to occur as often as once a year or even once in a unit lifetime. Comparison of accident exposures with the man-'rems per year fully expected from natural sources and normal operation of the unit requires that the former be weighted by their annual frequencies in order to predict an average annual effect.

It will be noted, however, that the analyses have concentrated principally on prediction of population exposures given the.

occurrence of the accident; probabilities. of occurrence of each incident have been calculated and grouped into broad categories explained below, but no attempt has been made to calculate

6. 1-1

~,

man-rems per year for each class nor to sum these figures to a unit total. The reason for this treatment is two-fold:

(1) It, emphasizes the fact that radiological exposures due to the accidents are, in fact, acceptably low in themselves, without additionally complicating the issue with probabilities; (2) The "classes~~ of accidents tend to be less homogeneous in their probabilities than in their releases; thus, to propose a too-signif icant figure probability as "typical" of a class would be not only inaccurate but misleading as well.

6. 1.2 Probability Categories To alleviate the problem of inhomogeneity mentioned above, the probability of occurrence of each <<class~~ of accidents about and incidents has been placed in a broad probability category two decades wide. The system chosen for this categorization is derived from Section III of the ASME Boiler and Pressure Vessel Code (Ref. 42). These classes are used by the General Electric Company in design safety analyses and have appeared in safety analysis reports for several stations. A brief description of each class is given below. In each case, P represents the expected frequency of occurrence per reactor year.

6. 1. 2. 1 Normal Condition (P=1)

A normal condition is any planned and scheduled event that is the result of deliberate unit operation according to prescribed procedures.

6.1.2.2 Upset Conditions (1 >P>2.5x10-~)

An upset condition is a deviation from normal conditions that has a moderate probability of occurring during a 40-year unit lifetime. These conditions typically do not preclude subsequent unit operation.

6.1.2.3 Emergency Condition (2. 5x10->>P>2.5x10-~)

An emergency condition is a deviation from normal unit operation that has a low probability of occurring during a 40-year unit lifetime. Emergency condition events are typified by transients caused by a multiple-valve blowdown of the reactor vessel or a pipe rupture of an auxiliary system.

6. 1.2.4 Fault Condition (2.5x10-~>P>2.5x10-8)

A fault condition is a deviation from normal conditions that has an extremely low probability of occurring during a 40-year unit lifetime. These postulated events include but are not limited

6. 1-2

,H

'4

to, the most drastic that must be designed against (the limiting design basis) .

6. 1.3 Basis far Probability Estimation The occurrences described in this analysis are of such a nature that their frequencies cannot be derived from historical data.

As a result, probabilities on most events must be inferred from knowledge of other events.

'I The broad classification of probability ranges and the assignment of each event to a category does quantify the best that is and known is about the relative frequency of occurrence of many events informative and useful on a comparative basis.

Following 10 CFR Part 50, Appendix D Annex (Ref. 40) guidance of the nine different accident classes, two are not covered here.

They are Class 1, normal operation trivial accidents, and Class 9, hypothetical sequence of failures more severe than what is assumed ~ for Class 8 accidents and sufficiently remote in probability that the environmental risk is extremely low.

6. 1.4 Transient and Accident Occurrences in the Reactor Facility This section follows the guide which points out that it is not practical to consider all possible accidents, so a classes. spectrum of accidents is suggested which are divided into Each class is characterized by an occurrence rate and a set of consequences. As suggested by the guide, typical or average characteristics for each class are used. The calculation methods and assumptions utilized in this report utilize the that available are technical information and analytical techniques appropriate for a BWR station. In some instances, such as meteorology, the detailed assumptions differ from the December 1, 1971 annex to 10 CFR Part 50, Appendix D, since more suitable data are available for assessing on a realistic basis, the environmental impact of the various events in Classes 2 through 8.

The nature of the occurrence, the operating conditions at the time of the occurrence, and a justification of its use as typical of its class is presented. A few classes encompass events of such widely different consequences and frequencies of occurrence that two or more events are studied, no single class. one being In qualified to be called truly typical of the entire in the particular, each of the design basis accidents described Preliminary Safety Analyses Report is treated individually both in Classes 6 and 8.

Subsequent parts of this section will describe the source and dose calculation techniques, the resulting population exposures expressed in man-rem, and a statement of the probability with which the particular event could occur.

6. 1-3

4 l, 1

1 I

The exposures were computed for the population to 50 miles as extracted from the 1970 census, and extrapolated to the year 2000.. Furthermore, the exposure calculations are based on a coolant radioactivity inventory consistent with an of fgas activity flow rate of 50,000 gCi/sec after a 30 minute delay.

6 1-4

il 8

6 2 CLASS 2 MISCELLANEOUS SMALL RELEASES OUTSIDE CONTAINMENT 6 2.1 Event Identification A variety of leakage paths, and hence type of leaks, could exist in an operating unit. Such releases are variable and could range from trivial leaks to a steam or water leak of several gpm. For this section a continuous 7 gpm leak located in thereactor upper turbine building floor has been assumed together with a coolant inventory consistent with a 30-minute old 50,000 uCi/sec off~as release rate. Since this class of events must occur within the turbine building they must manifest themselves either in the building drains (in which case no release characterization to the environment occurs) or in the building ventilation. This of the class of events is simply stated in terms of building ventilation content. The release to the environment occurs from the main stack.

6. 2. 2 Calculation of Sources and Doses A leak rate of 7 gpm and a 10 percent iodine release to the environs would result in an environmental release rate of 0.013 uCi/sec of I-131 for this unit after condensation-plateout, with corresponding releases of I132 to I-135.

Due to the limited mobility of the particulate fission products, these products exist in lesser quantities in effluents and so their contribution to the overall environmental effects is negligible and therefore neglected in this analysis. Depending for on the type of leak (i.e., steam or liquid), the potential noble gas release may or may not exist. If the leak were between the main steam line isolation valve and main steam turbine, one could expect a release of noble gas activity; whereas insolubility of if the leak gases in were liquid, due to the relative noble water, one would expect no gaseous contribution from this source.

For the iodine activity the environmental effects were determined by comparing the average annual concentrations at various radial distances in 16 sectors (22.5 degrees per sector) to the Maximum Permissible Concentration in Air (MPCA) as set forth in 10 CFR Part 20 Appendix B, Table II, column 2. See Exhibit A of Appendix I for the mathematical model which was used in the calculations.

6.2.3 Radiological Results As shown in Table 6.2-1 the cumulative 50 mile thyroid exposure is 8. 9 thyroid man-rem. For the purpose oflevel this evaluation the thyroid exposure is compared on the same as the whole body exposures. As illustrated in Table 6.2-1, even using this conservative approach the cumulative thyroid man-rem exposures are orders of magnitude below the whole body exposures received from normal background.

6. 2-1

The whole body exposure for this event is 5 to 6 orders of magnitude below normal background. It can, therefore, be concluded that the environmental effects from a small leak external to the primary containment are of no importance with respect to the general population exposure.

6. 2. 4 Event Probability Considerations Experience with mechanical equipment shows that small, sometimes even undetectable, steam leaks do occur from time to time. Thus, this class is judged to fall into the <<upset" category.

6. 2-2

t A

Table 6.2-1 Summary of Population Exposure from Natural and Man-Made Background Compared with Nuclear Radiological Effects Cumulative Whole-Body Man-Rem<<> Integrated

~ ~ ~ Versus Distance

~

Annular Distance, Miles 10 20 30 40 50 50 Population, Thousands (year 52.3 133.9 315 990 1424 1424 2000 Radiation

Background

Natural 7,320 18, 800 44, 100 139,000 199,000 (199,000)

Man-Made 5,230 13~390 31,500 99,000 142~400 (142~400)

Postulated Accidents and Occurrences Class 2 0 047 0.062 0.067 0 072 0.074 8 9 Class 3 Liquid<<> 0-025 NA NA NA NA Negl.

Gaseous Negl. 0.011 0. 012 0. 013 0 013 0 053 Class 4 NA NA NA NA NA Negl.

Class 5 NA NA NA NA NA NA Class 6 Refueling 0. 058 0. 12 0. 18 0. 31 0. 36 Negl.

Cask Drop Negl. Neg1. Negl. Neg1. Negl. Negl.

CI,ass 7 Negl. Neg1. Negl. Negl. Negl. Negl.

Class 8 LOCA Negl. Negl. Negl. 0. 012 0 014 Negl.

SLBA Negl. Negl. Negl. Negl.. Negl. 5. 0 CRDA Negl. Neg1. Negl. Negl.. Negl. Negl LSTAC2> Negl. NA NA NA NA Negl.

OGSA 0. 011 0.018 0. 021 0. 027 0. 029 Negl.

<< ~Man-rem/year for radiation background; man-rem/event for postulated accidents and occurrences

<< >>Population affected is that population drinking water obtained from Lake Ontario in the year 2000 (about 930,000 people)

NOTE; "NA'~ means not applicable; <<Negl.~~ means negligible, i.e., less than 0.01 man-rem

6. 2-3

6 ' CLASS 3 RADWASTE SYSTEM FAXLURES pince the mechanisms leading to significant accidental discharges of liquid and gaseous radwaste are different, two events were selected to represent this class.

6. 3. 1 Liquid Radwaste A radwaste tank containing a concentration of 0. 002 uCi/cc is assumed inadvertently pumped to the discharge .tunnel at a pumping rate of 170 gpm for 20 minutes, at which time the error is detected and the situation corrected. This occurrence could arise through any of three single operator errors: (1) the operator commence s pumping without taking a batch sample, a procedural error; (2) a batch sample is incorrectly analyzed or the results of the analysis are incorrectly communicated to the operator: or (3) the operator, having been notified of an acceptable batch sample, pumps the wrong tank by mistake. This accident has been selected as typical of its class principally on the basis of its probability of occurrence.. Since radwaste equipment is manually operated, operational transients where it is not typically subject to malfunctions could lead to inadvertant release of system contents. The chance and consequences of human error overwhelms that of mechanical failure.

6.3.1.1 Calculation of Sources and Doses The radiological ef fects for this event are based on the assumption 'hat. the radwaste tank is inadvertently pumped directly to the circulating water discharge. Annual average discharge flow rates and the most unfavorable short-term lake dilution factor are used. Considering the nearest point of public water supply for the City of Oswego-Onondaga County Water District (OCWD), whose intake is located about 6,000 feet out and SO feet below the lake surface, and a cumulative reduction factor of 10 for the effects of fission product decay, settling, and water treatment pl'ant filtration, the resultant radiological 2-1. Additionally, the exposures are as presented in Table 6.

prevailing lake currents flow from the OCWD intake toward the unit's discharge. The drinking water population within this area is assumed to grow to about 930,000 by the year 2000.

6.3. 1.2 Radiological Results The radiological exposures resulting from this event are presented in Table 6.2-1. As shown in Table 6.2-1, these exposures are negligible in comparison'to those existing effects from normal background.

6. 3-1

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6. 3. 1. 3 Event Probability Considerations Recent data on operator errors of the types postulated for the liquid radwaste release (Ref. 43) suggest the assignment of the

<<emergency<< category of probability as defined in 6.1.2.3 above..

6.3.2 Gaseous Radwaste Examination of the equipment contained in the offgas system reveals that the only source of potential release, other than the normal effluent path, is via the drain lines. Drain lines for the removal of condensed steam are located in close proximity to the inlet and outlet of the holdup pipe and normally have a water seal to prevent gaseous leakage.

6.3.2. 1 Calculation of Sources and Doses For this event, it is assumed that the water seal to the inlet drain line is lost and a 2-minute-old gaseous diffusion mixture is available for release. Considering the diameters of the drain line and the holdup pipe and assuming that the flow in the drain line is proportional to the area ratios, approximately 0.2 percent of the 2-minute-old mix is released via the drain line.

Since gaseous effluents from the drain line are not positively contained in any storage tanks, the gaseous effluent is released to the environment from the main stack. It is assumed that the offgas activity flow rate is 50,000 uCi/sec diffusion mix as measured at 30 minutes which is approximately equal to 212,000 uCi/sec at 2 minutes.

6.3. 2.2 Radiological Results Considering that 0.2 percent of the offgas activity flow rate measured at two minutes, i.e., 424 uCi/sec, is released to the environment under the same environmental conditions as the normal stack effluent, the resultant off-site exposure is a very insignificant increase in the exposures received from the main stack effluent under normal non-accident conditions. In addition to the 424 uCi/sec o f fis sion product gases, approximately 13 uCi/sec of N-13, 1.4 uCi/sec of N-16, and 118 uCi/sec of 0-19 will be released to the environment. Considerati'on of the energy spectrum, abundance, and transport time to any receptor off site, results in the conclusion that these sources are minor. While the radiological exposures for this event are based on a 15day release period, when consideration is given to the relatively small amount of time that this condition would probably exist before being detected, the actual dose effects will be even lower than those presented in Table 6.2-1.

6.3.2.3 Event Probability Considerations An assignment of the <<emergency<< category of probability as defined in 6. 1.2.3 above is given for this event.

6. 3-2

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6. 4 CLASS 4 EVENTS THAT RELEASE ACTIVITY INTO PRIMARY SYSTEM Events which lead to release of radioactive material (activity) into the primary system must be associated with fuel cladding defects or perforations which in turn permits escape of the activity. Cladding defects or perforations can occur as a random defect due to manufacture or as a result of transitory stress which exceeds the cladding material mechanical properties. The fuel cladding is designed to eliminate random defects; however, the possibility of defects is considered under normal facility operations.

Unit design bases, as described in the Safety Analysis Report, include the recyxirement that any anticipated transient event concomitant with a single equipment malfunction or single operator error must not result in a minimum critical heat flux ratio less than 1.0 for any normal unit operating mode. Since the design bases correlation (Ref. 44) used in determination of the critical heat flux is conservatively selected with a large margin between predicted and observed critical heat flux; fuel which experiences a minimum critical heat flux ratio of 1.0 is not, likely to have cladding failure. Unit design assures that such events do not release activity into the primary system.

Thus, there are no events identified in the Safety Analysis Report which fit into Class 4.

6 4-1

I 6 5 CLASS 5 EVENTS THAT RELEASE ACTIVITY INTO SECONDARY, SYSTEM In the direct-cycle BWR, ~~Secondary System~~ is interpreted to mean the secondary sides of heat exchangers whose primary primary system coolant: in particular, the main sides'ontain condenser shell and the service water side of the .residual heat removal heat exchangers.

The main condenser is protected against outleakage during unit operation by normal vacuum.

The residual heat removal exchangers; with .the system operating in the shutdown mode, is protected against outleakage by a 20 psig service water pressure differential. Either of the two service water pumps is capable of delivering the full differential pressure independently of the other. Differential pressures less than 15 psig are alarmed in the contxol room, as are abnormal signals from radiation monitors on the secondary system discharge line and in the discharge canal. The unit's standby diesel generators power the service water pumps in the event of loss of off-site power. Failure of one diesel generator would not only disable the service water pumps, but would also disable the residual heat removal pump on that loop, thereby preventing outleakage.

Due to the prevention of outleakage it is concluded that there are no events identified in Class 5 which are applicable for this unit.

6 5-1

I 6 6 CLASS 6. REFUELING ACCIDENTS INSIDE SECONDARY CONTAINMENT Refueling accidents are of two essential types: dropping a heavy object onto the core and dropping a spent fuel cask. These events will be treated in this section.

6.6. 1 Heavy Object Dropped Onto Core The accident. chosen as typical of this category is the design basis refueling accident, wherein an equipment failure allows a fuel bundle to drop onto the core from the maximum permissible height, resulting in perforation of a maximum of 49 rods. This event is chosen because the fuel assembly is the only heavy object which is routinely suspended over the core and, if dropped, could cause damage to the core.

6.6.1.1 Calculation of Sources and Doses The environmental consequences of this accident are dependent upon many interrelated parameters, such as:. decay time between shutdown and fuel transfer, number of rods experiencing damage sufficient to release stored activity, type and quantity of activity released, safety systems (passive and active) in operation, meteorological conditions existing during the subsequent release period, and the like.

The associated values assumed applicable for the above parameters are, defined as follows:

1. Decay time 4 days between shutdown and commencement of fuel transfer

2. Rods experiencing fuel damage 49

3. Safety systems a.. Passive Water in the refueling cavity, plateout. in the 'secondary containment, and the secondary containment as an effective holdup barrier.

b. Active Emergency Ventilation System (initiated on high radiation) 4 Parametric values applicable to above safety systems:

a. Water Partition Factor of 10+ (Ref. 45)

b. Plateout

c. Emergency Ventilation System Filter Efficiency 99.9 percent for iodine, 0 percent for noble gas (Ref. 45) 6 6-1

0 I'

~

F

5. Type and fractional activity released as specified in Ref.,45.

6. Method for analysis of the meteorology, -as specified in Appendix I which is based on data collected at the site in 1963 and 1964.

7. Breathing Rates 232 cclsec

8. Volumetric leak rate from reactor building to environment 100 percent/day.

9. Release Height 106 meters The calculation models used to define the environmental dose effects for this event are the same as those used for Normal Reactor Facilities Operation off-gas effluent calculations presented in Exhibit A and B of Appendix I.

6.6.1.2 Radiological Results As noted in Table 6.2-1, the integrated man-rem exposure for this accident is between 5 and 6 orders of magnitude below those exposures received from normal radiation background. It can, therefore, be concluded that this event is of no significance with regard to the environmental effects.

6.6. 1.3 Event Probability Considerations Spent fuel is transferred from the reactor to the fuel pool by means of the refueling hoist. Each fuel bundle to be removed is grappled in the reactor, lifted vertically until the bottom of the fuel transfer channel is cleared, and then transported across the fuel pool, still under water. A brake is provided to prevent excessive drop velocity. A limit switch is provided to prevent excessive lifting velocity.

The accident postulated assumes that a spent fuel bundle drops from the maximum height above the core, falls through the water, and damages not only some of its own rods upon impact but also some of those of bundles still in the core. For the accident to occur, either the hoist must malfunction or one of the supporting equipment components must fail. For the hoist to malfunction, the limit switch must fail to decelerate the bundle's falling rate. The probability of either of these events occurring would constitute a fault condition. A random failure of the cable, grapple, handle, or tie rod would be no more likely than an emergency condition and probably closer to a fault condition.

Since there is less than one chance in four that such a failure could occur while the fuel is at the maximum height above the core, the combined event would be no more likely than a fault condition for each bundle transferred. Assuming that one-fourth

6. 6-2

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of the core is transferred each year, the likelihood of the event becomes that of an emergency condition.

6.6.2 Spent Fuel Cask Drop It is recognized that completely transported the present plans have the spent fuel cask from the reactor spent fuel pool to the reprocessing plant in a motor transport cask. However, transportation could be undertaken, the cask size would be if rail greatly increased to handle as many as 16 times the fuel assemblies per cask. Consequently, the drop of a rail cask could be a more significant consideration. Therefore, for this evaluation the more serious accident is the rail cask droppage.

A fully loaded spent fuel cask is assumed dropped while being lowered to a waiting flatcar. This event is chosen to represent its category because it has the potential for dropping the fuel cask from the maximum height and because the fuel could lose its containment if the cask integrity is lost. If the cask were dropped inside the fuel pool, there would be no damage to the reactor building and the cask integrity would still be assured with no release from the cask occurring.

The reactor, if operating, is assumed shut down via the main turbine heat sink. The cask is considered as dropping from a height of about 99 feet to a yielding surface (the flatcar and points below) resulting in a release within the limits of 10CFR Part 71.

6.6.2.1 Calculation of Sources and Doses The radiological consequences of the cask drop accident are based on the following considerations:

a. The rail car for transportaion will be in position under the cask being lowered, thus providing a yielding type of impact surface. (The 10 CFR, Part 71, 30-foot cask drop design criteria is on a nonyielding impact surf ace.)

b. The cask will be loaded with a maximum of 32 fuel elements which have been out of the reactor for a minimum period of 90 days.

c. The fuel is designed to withstand an impact of 500G and the cask 270G.

d. The maximum deceleration of the cask after falling 99 feet is approximately 148G.

e. Upon impact with the yielding surface of the rail car, the cask closure head will remain intact, thus preventing the spilling of fuel.

6. 6-3

f. Based damage on the cask will result design and fuel capability, no as a consequence of this event.

fuel While it f is expected that no release of ission products will occur as a result of the accident, the assumption is 1,000 curies of noble gas activity, as per 10 CFR Part 71 criteria, are assumed to be released to the environment via the unit's stack.

6.6.2.2 Radiological Results As noted in Table 6.2-1, the integrated man-rem exposure for this accident is negligible. in comparison to those exposures received from normal radiation background. It can therefore be concluded that this accident will have no significant influence on the environment..

6.6.2.3 Event Probability Considerations Fuel is transferred from the reactor fuel pool to a railroad flatcar by means of the reactor building crane. The crane lifts the .loaded cask from the reactor building fuel pool, and after decontamination lowers it through a hatch to the flatcar 99 feet below. All transfer components are tested under weighted conditions just prior to the actual transfer. It is anticipated that an average of ten cask transfers are performed each year.

In order for the postulated accident to occur, the hoist brake, cable crane hook, lifting yoke, cask trunnion, or support ring must fail while the cask is suspended from the maximum height, and the cask must rupture when it impacts upon the relatively yielding flatcar below. The probability that a drop could occur from any height after such careful planning and testing of

.equipment is expected to be low. The cask design is such that, even in the event of a drop, rupture is not likely.'his event is, therefore, assigned to the fault category of probability.

6~ 6-4

l

6. 7 CLASS 7 SPENT FUEL ACCIDENT OUTSIDE SECONDARY CONTAINMENT This class applies to the movement of a spent fuel cask on a railroad flatcar from the time it leaves the reactor building until it reaches the site boundary. In addition, accidental releases at off-site areas are also considered but are discussed in Section 5.4.2. Spent fuel movement outside the secondary containment is always performed with the fuel inside the cask.

The engineering and procedural precautions taken during the movement of spent fuel on-site, essentially preclude the possibility of the cask dropping on-site due to instability, improper attachement to the bed of the flatcar, or derailment; further, even if such a drop were to occur, it would be from such a height that the shipping cask would easily sustain it.. The cask could conceivably be damaged by fire, but the site arrangement precludes movement of the car in areas of appreciable fire hazard. Though fires aboard railroad cars due to overheated bearings have occurred, it is extremely unlikely in this case, considering the velocity at which such movement will occur.

Fires aboard the switching engine or other form .of locomotion, themselves highly unlikely, pose no hazard to the cask.

'Thus, exposure to the public due to on-site movement of spent fuel outside the containment is not expected.

6 7-1

r 0

6 8 CLASS 8 ACCIDENT INITIATION EVENTS CONSIDERED IN DESIGN BASIS EVALUATION IN THE SAFETY ANALYSIS REPORT These events are as described in Section 14 of the SAR, and are briefly detailed in the following paragraphs. These include the inside containment loss-of-coolant accident (recirculation pipe break), the outside containment loss-of-coolant accident (steam line break), and the reactivity excursion accident (control rod drop) .

The design basis refueling accident falls in Class 6 and has been treated in Section 6.6..

Two nondesign basis accidents (catastrophic failures of a liquid radwaste tank and of the offgas holdup system) are also treated here, in order that Class 8 contains one event of each type which could result in significant releases to the environment.

6.8. 1 Loss-of-Coolant Accident (LOCA)

A sudden circumferential break is assumed to occur in a recirculation line, permitting the discharge of coolant into the primary containment from both sides of the break. Concurrent with this failure, the worst single active component failure producing the maximum damage to the core, is also assumed to occur. This is failure of the low pressure core spray injection valve is the unaffected recirculation loop to open.

6.8.1. 1 Calculation of Sources and Doses The calculation of core heatup following the double-ended recirculation line break was predicted on a realistic basis, as suggested by the guide, by applying the results of parametric studies to the standard core heatup models currently in use (Ref.

46)

The approach in the thermal-hydraulic analysis was to select realistic values for those key assumptions normally used in the Safety Analysis Report (SAR) in which very conservativ'e estimates are made. Other assumptions which are of lesser significance use values as described in the SAR or in AEC safety guides. Where parameters are not specifically mentioned, AEC assumptions, whose inherent conservatism has been well documented, have been employed The values assumed for use in the thermal-hydraulic calculations for LOCA are identified as follows:

6 8-1

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Best Estimate AEC=Assum tions 1 0 Metal-Water Reaction Baker x 0. 5 Baker 2 Steam Cooling Included No Credit Blowdown Flow Rate Moody x 0. 7 Moody 30 4 Core Spray Wetting Time tSteady-State

+ 60 sec

5. Duration of Nucleate Boiling Transient Data Data

6. Lower Plenum Flashing Heat. Rewetting Data Groeneveld Transfer Correlation Peak clad temperatures were calculated for a spectrum of break sizes utilizing the assumptions listed.

The realistic core heatup analysis shows no heatup of fuel into the perforation range except for that caused by the double-ended recirculation pipe break. Perforation even in this case will be limited to 2.5 percent or less. The resultant radiological effects are a function of the quantity and type of activity released, natural fission product removal effects, containment leak rate, etc. These effects are based on release of the primary coolant activity to the primary containment and subsequent release via primary containment leakage to the secondary containment.

Those values assumed applicable for the radiological dose effects are identified as follows:

1. Fuel rods damaged 2.5 percent core

2. Fission products available for release as specified in Reference 45 c'ontainment leak rate 0.5 percent/day initial,

[1

3. Primary with .average 30-day release rate of 0.2 percent/day.

4. Plateout condensation effects 10 (Ref. 45)

5. Partition factor suppression pool 10~ (Ref. 45)

6. Mixing secondary containment 100 percent

7. Emergency Ventilation System efficiency 99.9 percent for Iodine (Ref. 45) .

8. Method for analysis of the meteorology as specified in Exhibit A in Appendix I which is based on data collected at the site in 1963 and 1964.

9. Breathing rate 232 cc/sec

10. Release height 106 meters

6. 8-2

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0

The calculation methods for the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 30-day whole body doses and thyroid doses are presented in Exhibits A 6 B of Appendix I of this report.

6.8. 1.2 Radiological Results The resulting population radiation exposures for this accident are presented in Table 6. 2-1. As noted, the exposures are negligible. It can therefore be concluded that the environmental of no ef fee ts, as a consequence of this accident, are significance.

6.8. 1.3 Event Probability Considerations The probability of a large break severance should fall within the range of an emergency condition based on estimates of pipe failure rates and on the number of pipes that satisfy the conditions for a large break design basis accident.

The probability that the low pressure core spray injection valve will fail when called upon should also fall within the range of failure rates, an emergency condition based on an analysis using (Ref. 47, 48, and 49), considering anticipated downtime and the interval between injection valve tests.

Since each probability is low and the outcomes are not critically interdependent, the joint probability of pipe break and injection valve failure is expected to be ~ver low, placing this event in the fault condition.

6.8.2 Steam Line Break Accident (SLBA)

The postulated accident is a sudden, complete severance of one main steam line outside the drywell with subsequent release of steam and water containing products to the pipe tunnel and the turbine building. Since this accident does not result in any fuel damage, the environmental effects are limited to those radiolgoical doses which may be received as a consequence of exposure to the activity associated with the primary coolant.

6.8.2. 1 Calculation of Sources and Doses The mass of coolant released during the 4-second isolation valve closure time is 47,400 pounds. As a consequence of depressurization, approximately 30 percent of the released liquid will be flashed to steam. Due to the affinity of iodine for water, it is not expected that any additional iodine will be released fro'm'he remaining coolant. Therefore, the iodine released to the turbine building, as a consequence of the accident, will be proportional to that quantity of water flashed to steam. Due to the condensation, plateout will occur on surfaces with which the steam will come in contact prior to release to the general environment. It is assumed that an iodine

6. 8-3

P' removal factor of two is applicable to these effects. The iodine activity associated with the coolant flashed to steam is based on a noble gas release rate of 50,000 uCilsec of a diffusion mix, as measured at 30 minutes decay.

6.8.2.2 Radiological Results The population radiation exposures for this accident are presented in Table 6.2 1. Due to the type of activity released, the primary dose'ffect from this accident is inhalation thyroid exposure. As noted in Table 6.2-1, the cumulative thyroid exposure is 5 orders of magnitude below the normal background whole body exposure.

accident does not It can therefore be concluded that this result in any environmental effects of significant concern to the general population.

6.8.2.3 Event Probability Considerations The design basis main steam line rupture accident postulates complete severance of one of the main steam lines while the reactor is at power followed by total isolation of the break from the reactor within 4 seconds. The probability of this event is essentially the probability of the severance. Based upon estimates of pipe failure rates contained in the literature (Ref.

50), and considering the number of locations where the rupture could occur in the main steam system, the probability of pipe severence should be well within the '~emergency category."

6. 8 3 Control Rod Drop Accident (CRDA)

The postulated accident is a reactivity excursion caused by accidental removal of a control rod from the core at a rate more rapid than can be achieved by the use of the control rod drive mechanism. In the control rod drop accident, a fully inserted control rod is assumed to fall out of the core a fter becoming disconnected from its drive and after the drive has been removed to the fully withdrawn position. The design of the control rod velocity limiter limits the free fall velocity to 3 ft/sec.

Based on this velocity and assuming the reactor is at full power, the maximum rod worth is approximately 1 percent, and the postulation assumes perforation of 10 fuel rods.

that none will actually fail.

It is expected 6.8.3.1 Calculation of Sources and Doses In addition to the assumed failure of 10 rods, the radiological effects are also based on rated steam and recirculation flow, an iodine carryover fraction of 1 percent, and a main steam line isolation valve closure time of 4 seconds.

In addition to isolating the main steam line, the main steam line radiation monitors also isolate the normal offgas system, thereby containing the activity between the main steam line isolation

6. 8-4

valves and the offgas isolation valves. The primary source of leakage from the system will therefore be via the turbine gland seals and will be due to changes in environmental pressure with respect to the turbine condenser.

The activity air-borne in the condenser is a function of the partition factor, volume of air and water, and chemical species of the fission product activity. The values associated with these parameters are: a partition factor of 10~ for iodine, a condenser plus turbine free volume of 99,200 ft3, and a condensate volume of 7850 ft~.

6.8.3.2 Radiological Results As noted in Table 6.2-1, the population radiological exposures for this accident are orders of magnitude below those effects received from normal background. It can therefore be concluded that environmental effects from this accident are of no significant concern to the general population.

6-8.3-3 Event Probability Considerations In order for a rod to drop from the core, it must first become detached from the drive, remain lodged in position while the drive is withdrawn from the core, and then, while the drive is still withdrawn, become dislodged and fall freely. This is a complex series of events, there being many possible actions (or inactions) that are interrelated, but this is offset by the many annunciators and procedures that are meant to indicate the occurrence and avoid such an event.

Conservative judgment and actual operating experience indicate that this event should be assigned to the emergency condition category.

6. 8.4 Radioactive Liquid Storage Tank Accident (LSTA)

The condensate storage and high level waste tanks are two potential sources of radioactive water spillage present in the station design. The 200,000 gallon condensate storage tank (containing 5 x 10-5 uCi/cc) is partially above grade level, which, poses a potential problem of the liquid spill reaching outside the facilities.. The high level radioactive waste tanks, however, are located below grade in the radwaste building basement, thus assuring complete containment of any spill.

6.8.4. 1 Calculation of Sources and Doses The activity released from the failure of the condensate storage tank is assumed to be emptied into Lake Ontario over a period of 10 minutes. The short;term lake dilution factor of 156 between the point of discharge and the drinking water intake at Oswego is considered applicable during this event together with the

6. 8-5

population served as indicated in Section 6.5.2. The nearest point of public water supply is about 8 miles from the unit.

Considering filtration by the processing facilities of the public water works as well as radioactive decay and settling, a factor of 10 is applied to these effects in evaluating the population radiological exposures which could result from the consumption of this water.

6.8.4.2 Radiological Results The radiological effects resulting from this event are presented in Table 6.2 1. As noted, these effects are orders of magnitude below those existing from normal background effects and are therefore of no significant concern with regard to the effects on the general environment.

6.8.4.3 Event Probability. Considerations The condensate storage tanks are unpressurized accumulators.

There are no valves or parts other than piping attached to the tank. Although the tank is not a pressure vessel, it in general accordance with appropriate American Petroleum is designed Institute Code 650.

Since the probability of occurrence of a release to the environment from a condensate storage tank failure is so very low, it is placed in the fault category.

6. 8. 5 Of f-Gas System Accident (OGSA)

The postulated accident for this category is an ignition of radiolytic hydrogen and oxygen in the offgas holdup volume, followed by a detonation of sufficient impulse to rupture the holdup pipe. The activity released to the environment would therefore be that activity contained within the holdup volume.

6.8.5. 1 Calculation of Sources and Doses

\

The source terms applicable to the base input to the system as well as the parameters appropriate to release and dispersion are as follows:

1. Base Input 212,000 uCi/sec of a 2 minute old diffusion mix which at 30 minutes is equivalent to 50,000 uCi/sec.

2. Release of 100 percent noble gas activity contained in pipe and 10 percent of the Iodine.

3. Height of releases 106 meters.

4 Meteorology the method for analysis of the meteorology is as specified in Appendix I and1964.is based on data collected at the site in 1963 and

6. 8-6

6. 8. 5. 2 Radiological Results The radiological exposures received as a consequence ofnoted, this hypothetical accident are presented in Table 6.2-1. As the environmental exposures are orders of magnitude below those exposures received from normal background.

It can therefore be concluded that the environmental exposure which could theoretically be received as a consequence of this accident are of neglibible importance in comparison to the actual exposures received from normal background.

6.8.5.3 Event Probability Considerations The noble gases generated in the nuclear process are allowed to decay for approximately 30 minutes before discharging up the stack. The small amount of noble gases are accompanied by a mix of hydrogen and oxygen, also generated in the nuclear process.

This hydrogen-oxygen mixture is subject to ignition and theoretically could detonate under proper conditions.

If the mixture ignites, portion of the noble gas it burns rapidly and forces a substantial inventory out the stack with less than normal decay time. Ignition has occurred in operating reactors without H -0 recombiners at a rate that should be classified as an upset condition.

Detonation is far less likely because rather ideal conditions of pressure, it can occur only under mixture, and piping geometry. A rupture disc is installed in the holdup pipe to protect the pipe from rupture. Xgnitions and most detonations would not create a high enough pressure to rupture the disc. A detonation of such force as to rupture the disc or the pipe is expected to have a low probability, probably at the low end of the emergency category in plants without H -0 recombiners.

6. 8-7

6~ 9 RADIATION BACKGROUND AND RADIOLOGICAL IMPACT

6. 9.1 Natural Radiation Background Everyday we receive radiation from the sky, the ground, the air around us, and the food we eat. The magnitude of this radiation level is strongly influenced by where we live, what we do, and even in what kind of house we live For most locations around the United States, this natural radiation level averages about 140 mrem/year. The various component contributions of this typical value are discuss ed below. Data is presented in Table 6.2-1.

6.9. 1.1 Total Radiation From Nature The following table summarizes the various contributions in arriving at an average natural radiation background of 140 mrem/year for people living in the United States.

Cosmic Rays 50 Ground (1/4 time) 15 Buildings (3/4 time) 45 Air Food and Water 24 ~

140 mrem/year 6.9. 1.2 Man-Rem From Natural Radiation Background Calculations of the total exposure to the population as a result of natural radiation background have been made. Certainly obvious that if it is assumed that every person in the it is United States receives an average of 140 mrem/year then the total population exposure would be about 30 million man-rem/year However, it is not appropriate to compare the'adiological effects of the operation of any one nuclear power station, as negligible as they are, with the total man-rem/year to the entire United States population. Therefore, the man-rem comparisons are made for the population within a 50 mile radius. If one million people living within a 50 mile radius, the natural there are radiation background will result in about 140,000 man-rem/year.

Table 6.2-1 lists man-rem/year from natural background for the population distribution at the Nine Mile Point Site.

6.9.2 Man-Made Radiation Background Man has added to his radiation exposure from nature in a number of ways. The largest contribution by far has been from medical

6. 9-1

exposure. It man-made exposure has been estimated (Ref. 51) that is from this radiation and 94 percent of of this, 90 percent is attributed to diagnostic X-rays. Typically, an average of 55 mrem/year is received by the average United States citizen.

However, recent reports (Ref. 52) indicate that 100 mrem/year is a more appropriate average.

Additional small levels of radiation can be received from luminous watch dials (about 2 mrem/year) and television viewing (1 to 10 mrem/year) .. Therefore, the resultant man-made radiation received by the average citizen ranges between 50 to 100 mrem/year.

6.9.2.1 Man-Rem From Man-Made Radiation Total population exposure from man-made sources is more difficult to evaluate since there can be an individual choice made as to whether such radiation is received. However, reasonable assumptions can be made in order to make estimates of man-rem/year since it is not feasible to monitor the population dose by measuring the dose to individuals.

The population dose as a result of viewing television to a sample million people can be estimated. Typically an individual would receive about 1 to 10 mrem/year from watching TV. Say the average dose received is 5 mrem/year , then this results in 5,000 man-rem/year. Looking at this same population one can determine the man-rem as a result of exposure from luminous-dial watches. ~

If only 10 percent of this sample population are exposed to 2 mrem/year, then the resultant population dose is 200 man-rem/year.

The use of medical X-rays is by far the largest contributor to population exposure from a man-made source. Again considering the sample million-person population, diagnostic X-rays would result in about 100,000 man-rem/year assuming that each person received an average of 100 mrem/year. However, if only 10 percent of this population received an'nnual chest X-ray of 200 mrem per examination, the result would , be 20,000 man-rem/year.

In summary, medical exposure results in the largest man-rem/year contribution from man-made sources. However, the examples of television viewing and wearing luminous watches do contribute to population exposure and should be included when comparing the impact on man from these and other man-made sources. Table 6.2-1 lists the man-rem/year for these sources appropriate for the station location.

6. 9.3 Total Average Radiation Background The total background radiation exposure received by the average citizen is the sum of the contributions received from natural

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background and manmade sources. The resultant total is the 140 mrem/year from natural sources and 50 to 100 mrem/year .from man-made sources giving about 200 to 250 mrem/year to the average resident of the United States.

6.9.4 Man-Rem From Nuclear Power Stations The radiological impact of nuclear power stations is compared with the already radioactive environment in which we live. There is a basic difference between the man-rem received from natural and man-made radiation background and that from the nuclear power stations. That is, everyone within a 50 mile radius is assumed to receive the average background exposure, whereas everyone does not receive the same contribution from the power station. The reason is that the natural atmospheric dispersion effects reduce the radiation source the farther one is from the station. A simple analogy should help in explaining this. Let us say that a bottle of perfume is opened and is sprayed into the air while one stands ten feet downwind, then chances are that the odor from the perfume would be detected at that distance. At 100 feet away there is only a hint of perfume in the air and at 1,000 feet, is impossible to detect any effect. Over the year, the wind it directions, wind speeds and atmospheric stability change to disperse an airborne source so that out to 50 miles from the release location, the radiological effect is not measureable but only estimated by means of a calculation.

Liquid sources are treated similarly to the gaseous one in that only, a portion of the total population out to 50 miles actually could be influenced from small amounts of radioactivity discharged from the unit. Considering drinking water as the primary mode of exposure to man, several factors affect the result. For example, some of these are effects of water dilution and dispersion in the lake, distance between station and locations where water is drawn for drinking, water treatment prior to transport into the domestic water supply, and the number of people using this water for drinking water purposes.

The total man-rem to the population out to 50 miles from the station for the various accident conditions evaluated in Section 6 are summarized on Table 6.2-1. This list includes the man-rem results for normal station operation considerations, transportation considerations, various abnormal conditions and postulated design basis accident conditions. One should not add the man-rem from each condition since the probability of occurrence was not applied to all conditions. The reason is that it is not correct to add man-rem/year with man-rem/event without first considering the frequency of occurrence (such as one-millionth of an occurrence per year) .

6. 9-3

6.9.5 Radiological Impact Conclusion The general conclusion that is drawn from the'total population exposure (Table 6.2-1) for each condition is that there is a negligible contribution from the nuclear power unit when compared to the natural and other man made exposures received by the population. The highest dose to an individual near the unit is less than a few percent of natural background. This dose would approach negligible proportions at a distance of 50 miles (two to three orders of magnitude less).

As mentioned above, the natural background and certain man-made sources of radiation overshadow the radiation exposure contribu-tion from normal operation and the postulated accidents discussed in this section.

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SECTION 7 UNADVOIDABLE ADVERSE ENVIRONMENTAL EFFECTS OF OPERATION Although it is inescapable that operation of Unit 1 affects the environment, Niagara Mohawk believes these effects are not adverse. Identification of these changes is important since many of their possible environmental problems are only recently beginning to be understood. These areas of alteration may be categorized as follows:

a. Physical presence aesthetic effects, noise, traffic

b. Land use recreational, historical

c. Water quality liquid releases chemical waste

d. Air quality gaseous releases radioactive, other Except for the release of very small quantities of radioactive effluents, all of the above effects are common, in varying degrees, to any large thermal generating plant, large manufacturing facility, large commercial building, and even large apartment building or complex. This section of the report discusses the nature of each of these alterations.

Public awareness of nuclear power stations has naturally increased as the number of stations increases. Along with this awareness has been an increasing concern over the qualities of the human environment. For nuclear power stations, this concern has focused primarily on their lccation and the effect of their physical presence on their immediate environments. Every effort to minimize the intrusion of this facility and its component parts upon its environment has been made by designing the structures to be as aesthetically pleasing as is economically possible and by containing major noise-producing mechanisms within the plant buildings.

Two of the principal questions often asked about nuclear power stations concern waste heat rejection and radioactive releases.

As previously indicated in Sections 5.1.2 and 5.5, the lasting temperature increase over ambient lake conditions of the cooling water returned to the lake will be slight, based on Lake Ontario studies in the Nine Mile Point area that have been conducted since 1963, and on Unit 1 operation to date.

The environmental effects of liquid and gaseous radioactive releases from Unit 1 and their interaction with other facilities

7. 0-1

in the area have been discussed in Sections 5.4.5 and 5.4.6. The resulting ambient levels of contaminants are expected to be well below those levels considered harmful by local, state, and federal standards.

Preliminary data resulting from water samples collected from Nine Mile Unit 1 (Section 5. 5.4) indicated that a small percentage of fish larvae are lost in passing through the circulating water system. Because of the relatively few fish in the vicinity of the existing intake structure, and the precautions taken in the design of the lake structures, no significant loss of more mature fish is anticipated in proportion to the fish population as a whole.

Only about 45 acres of the 900-acre site have been unavoidably removed from existing land uses for Unit 1. The remainder of the site serves principally as a habitat for native wildlife. Power units, such as Nine Mile Point Unit 1, are designed as suppliers to geographically extensive systems. Such power stations do not offer any greater incentive to development in the immediate vicinity of the station than in any other location within Niagara Mohawkis service area.

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~ 1 SECTION 8 ALTERNATIVES TO THE EXISTING POWER STATION The Nine Mile point Unit 1 Nuclear power Station-is an existing facility which started commercial operation in December of 1969.,

Therefore, it is evident that not as many feasible alternatives exist for this facility as would be available if a new unit were under consideration. However, every effort has been made to evaluate alternatives to the extent that they can be properly assessed.

The environmental considerations of the various feasible alternatives are discussed in detail along with a summary of environmental cost tabulations in the Benefit Cost Analysis, Section 9..

Alternatives to the existing power station include not providing the power or decommissioning the station and replacing the power by purchasing the power from other systems, rebuilding the station at other sites, or providing the power by an alternative means of generation.. Section 9 considers the benefits and costs, both environmental and economic, of these alternatives.

For the existing generating system, there are also several alternatives available, for handling the cooling water, chemical, and radioactive wastes. These subsystem alternatives for the existing facility are also evaluated in Section 9 from the standpoint of both economic and environmental costs.

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SECTION 9 BENEFIT COST ANALYSIS The decision to place a boiling water reactor at the Nine Mile Point site and to continue its operation involves trade-of fs among various environmental effects and economic costs. Niagara Mohawk chose to construct and operate a nuclear generating unit at the Nine Mile Point location for several reasons. Among these were the excellent environmental characteristics of the site, including absence of seismic activity; superior meterological ventilation; scarcity of population and land use activities; and the abundance of cooling water. The site consists mostly of scrub forest and rocky shoreline making it less suitable for recreational or farm uses than the other sites investigated The commitment to build a nuclear station at Nine Mile Point was made in late 1963. More than a yeax prior to that commitment, environmental studies were initiated to provide data on the meteorological, aquatic, seismic , geological and hydrological characteristics at the site.

The load growth estimates at the time of the commitment indicated the need for a new large base-load unit. The decision to build a nuclear unit rather than a fossil-fuel unit was made based on a balance of environmental and economic considerations. Operation of the station since 1969 has provided ample evidence that the economics of nuclear generation have been achieved with minimal environmental impact.

During the design of the Nine Mile Point Nuclear Station Unit 1 many trade-offs were made to minimize environmental impacts.

Stack height was determined by balancing the meteorological dispersion characteristics and the aesthetics of a taller stack.

The fluted metal siding on the building walls was color treated to harmonize with the surroundings. Alternative cooling water systems, such as surface discharge and various submerged diffuser schemes were also carefully investigated to arrive at a design which would avoid unacceptable thermal effects.

This section presents a benefit cost discussion of the alternatives to the existing power station. Those alternatives which are feasible at the Nine Mile Point site and are within available technology are tabulated with respect to benefits and costs. These benefits and costs are developed within the text of Section 9. In using the tables, reference should be made to the appropriate part of the text for the full explanation of the environmental costs.

These tabulations are similar to those suggested in <<Proposed AEC Guide to the Preparation of Benefit Cost Analysis to be Included in Applicant's Environmental Reports (For Defined Classes

• of Completed and Partially Completed Nuclear 9.0-1

Facilities)," issued in January 1972. As suggested by the Guide, the tabulations are of two types. The first compares incremental generating costs and environmental costs of various practical subsystems while the second compares benefits and costs of alternative station designs. The incremental generating costs and environmental costs of various practical subsystems are tabu3,ated following the discussion of these subsystems. These tabulations are used to derive the alternative station designs which result in minimum water, air, and land effects. These alternative station designs are summarized in tabulations at the end of Section 9.8.

During the final stages of preparation for this report the Atomic Energy Commission issue'd a final guide in May 1972. -This revised document, "Guide for Submission of Information on Costs and Benefits of Environmentally Related Alternative Designs for Defined Classes of completed and partially completed Nuclear Facilities,~~ has certain differences from the previously proposed January 1972 guide in both content and format presentation'. The additional information requested in this final AEC guide is discussed and incorporated in appropriate sections of the Benefit-Cost Analysis but is not tabulated in benefit cost tables. The reason is that the format used throughout the benefit-cost tables closely follows the text presentation and the earlier January 1972 guide, and it is not considered feasible to substantially change this format at this late date.

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9 1 NOT PROVIDING THE POHER The Niagara Mohawk Power Corporation (NMPC) is a regulated public utility operating which under the Public Service Law of obligates the Company the State of to provide safe and New York, adequate electrical service to its customers.

The Company~ s plans to meet future requirements under this Law axe.,descxibed i,n Section 1. 2. This section demonstrates the necessity for the generating capacity of Unit 1.

9 2 PURCHASING THE POWER Section 1. 2 demonstrates that the Nine Mile Point Unit 1 is not oddly necessary for NMPC to meet service obligations on its own system but is also an integral part of the New York Power pool's generating capacity. Among other functions, the Pool coordinates plans for new generation in such a manner that ample reserves are provided within the State. Long-term power purchase from within New York State is not an alternative to continued operation of this unit in terms of the New York Power Pool plan, as described in Section 1.2. Even if new generation were to be constructed elsewhere in the State from which NMPC might conceivably purchase power, environmental costs specific to these alternate locations could not be avoided.

The New York Power Pool and its members have found that possibilities for addi,tional long-term power purchases do not, realistically exist outside the Pool, particularly during the winter when NMPC experiences its peak load. There is no indication that either of the adjacent Power pools in the United States, that is, the Pennsylvania-Jersey-Maryland .,(PJM) or the New England Power Pool (NEPOOL), or Ontario Hydro in Canada, will have capacity available for sale for an extended period on a firm basis.

Accordingly, it is concluded that purchasing power on a long-term basis from either within the New York Power Pool or from outside the Pool is not a feasible alternative to the continued operation of Nine Mile Point Unit 1.

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'4 9 3 ALTERNATIVE SITES evaluation of alternative sites for Unit 1 must consider that this unit has been in commercial operation at Nine Mile Point since December, 1969. The costs of decommissioning this unit, abandoning the Nine Mile Point site, moving to a new locale, and rebuilding the station would be overwhelming. For a more detailed discussion o f these costs, see Section 9.'. The

'nvironmental effects associated with locating Unit 1 at its present site on Lake Ontario have been discussed in previous sections. Therefoxe, this section is limited to a discussion of reasons why the Nine Mile Point site is preferable 'over other sites for the location of a generating plant.

Projected demands of the Niagara Mohawk Power CorporatiOn system indicate that increased load requirements for the 'oming decade are to be in the central and western region of the system.

Alternative sites, therefore, must be limited to Niagara Mohawk~s central and western 'divisions. The availability'of adequate supplies of cooling water while staying within the projected growth area further narrows the choice of alternative sites to those on the St. Lawrence River or on the shore of Lake'ntario.

The thermal effects at a new site on Lake Ontario should be similar to those occurring at the Nine Mile Point site. The environmental effects on a river such as the St. Lawrence, however, would be di,fferent fram those occurring on the. lake.

Although it is not feasible to quantify the river effects based on only the preliminary investigations that have been made, Mohawk, it is estimated that the overall effects of thermal and liquid discharges would be minimal because of the by'iagara large volume flow of the river.

The effects of a nuclear unit on air quality should be essentially the same at any of the possible alternative sites.

Radioactive releases to the air at each site would be the same, and accordingly, be comparable.

it is estimated that the individual doses would Pxecise doses, however, have not been calculated since detailed meteorological studies have not been conducted for the altexnate sites.

Nine Mile Point has a definite advantage over other sites in terms of land usage. In the first place, the land is presently being used for power generation. Relocating Unit 1 at another site would require that new land be obtained and dedicated to the generation of power. Also, additional land would have to be required for the unit's transmission line right-of-way.

Secondly, construction associated with Unit 1 has terminated at its present location. Moving Unit 1 to one 'of the new sites would initiate construction anew at the alternate locale with all of its attendant effects. Construction at an alternative site would require the disturbance of additional land and would finally result in the utilization of the same amount of land 9 3-1

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presently allocated to power generation at the Nine Mile Point site. Clearly, good land usage dictates the continued operation of the existing facility at the Nine Mile Point site.

The Nine Mile Point site is seismically stable and has good meteorological dispersion characteristics as discussed in Section 2. It it shoreline, making consists of mostly scrub forest. and less suitable for recreational or farm uses rocky than the other sites considered.

remote, thereby minimizing offsite It is relatively large and environmental impact. None of the alternative sites offer significant improvement in any of the aforementioned factors. In addition, environmental data for Nine Mile Point has been collected and'valuated since 1962..

To collect similar preoperational data for each alternative site would be a major undertaking costing $ 750,000 and would take up to two years. To collect the data and to option the land would also take about two years. It would be another seven years before the unit were constructed and in operation. As the unit

=

would be decommissioned during the beginning of this time span to recapture as much of the hardware as possible for location at the new site, the 610 MWe output from this station would be lost to the public for about seven years. The impact of such a loss is discussed in Section 1. 2 and the possibilities for making up that loss by purchasing power on a long-term basis are discussed in Section 9.2. The possibilities of replacing the power are discussed in Section 9.4.

Therefore, in terms of the economic and environmental advantages, the most realistic alternative is to continue operation of Unit 1 at its present site.

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9 4 REPLACING THE POWER The replacement of power from Nine Mile Point Unit 1 would involve the following four steps:

A Decommissioning of the existing 610 MW nuclear unit B Short-term purchase of power C Installation and operation of gas turbines to expansion D Construction of a fossil unit in addition for load growth Various modes of decommissioning the unit, ranging from leaving the reactor sealed in place to complete removal of all structures and foundations, can be considered. Previously decommissioned demonstration reactor plants, such as Piqua, Hallam, and Bonus have been left more intact with the Utility playing a caretaker radioactivity.

role for protection of the public from residual At present the AEC is considering a proposal for the complete dismantling of the Elk River reactor in Minnesota. A more detailed description of the proposed dismantling plan may be found in the i'Draft Environmental Statement Elk River Reactor Dismantling Wash 1516<<, submitted by the United States Atomic Energy Commission in December 1971. The Elk River reactor was constructed in 1960 by the AEC as part of the power reactor demonstration program, and has a thermal power rating of 58.2 MW.

The techniques and experience for completely dismantling commercial reactors of the size of Nine Mile point Unit 1 are not presently available. Theref ore, no attempt has been made to prepare detailed glans and cost estimates for the complete dismantling of Nine Mile Point Unit 1. It is certain, however, that complete dismantling of the unit would be ver'y costly, probably be several times more than the cost of permanently shutting down the facility and maintaining it in a safe condition. This would be due to the immense complexity which would be involved in completely decontaminating, dismantling, and safely disposing of all reactor induced radioactivity from the massive concrete structures and equipment which exist at Nine Mile Point Unit 1. For the purposes of this report, decommissioning of the existing Unit 1, will be assumed to mean that the reactor and turbine units will be shut down permanently, sealed, and maintained in a safe condition.

Upon decommissioning Nine Mile Point Unit 1 both the installed capacity and energy produced would have to be replaced. During the first year after decommissioning only 310 MW can be supplied by older fossil fuel units, leaving a deficit of 300 MWe in installed capacity. This is based on an objective of 18 percent installed generating capacity reserve to maintain adequate system reliability as discussedfeasible alternative as discussed on ina in Section 1.2. Purchasing power long-term basis is not a Section 9.2. New generaticn alternatives necessary entail construction time. Therefore, if Nine Mile Point Unit 1 were to

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be decommissioned at this time a capacity deficiency would exist.

Loss of the unit would have a serious effect on reliability and Niagara Mohawk' ability to meet its obligations in 1972 and beyond.

Within a year after decommis sioning it is assumed that gas turbines could replace the capacity def iciency created by the early retirement of Nine Mile Point Unit 1. The full 610 MWe capacity would have to be replaced to account for load growth over the intervening year. An additional base load 610 MWe unit could be installed as replacement capacity for the decommissioned nuclear unit. For the purposes of th5.s analysis that an oilfired base load unit is installed by 1976. This it is assumed would be in addition to planned capacity additions intended for normal load growth.

The energy expected to be generated by the 610 MW Nine Mile Point Unit 1 is.4.54 x 10~ kWhr per year. It is assumed that all of this energy will be replaced by energy from the existing fossil units normally held in reserve. The high energy cost gas turbines would only be used in emergencies. In fact, however, these gas turbines would probably be required to generate significant amounts of energy during maintenance and forced outages of these units. After the replacement base. load oil fired unit is in operation in 1976, energy would come from that unit.

The estimated cost of decommissioning Nine Mile Point Unit 1 in 1972 is about $ 2 000,000. The estimated annual cost of maintaining the facility in a safe condition is about $ 150,000..

Since all alternatives included here and in subsequent sections will be complete by 1976, that year has been selec'ted as the basis for present worth calculations. The present value (1976) of decommissioning and maintaining the unit in a safe condition, based on a 9.6 percent cost of capital and the remaining 21.75 year economic life¹ will be about $ 4,860,000..

It is assumed that the energy that would have been generated by Nine Mile Point Unit 1 is replaced by older fossil units until 1976 when a new oil-fired unit is placed in operation. This replacement power would cost about 7.04 mills/kWhr or about

$ 32,000,000 annually for the kWhrs to be replaced. The present value (1976) of this annual cost at a 9.6 percent rate of return will be about $ 182,300,000.

The estimated cost of installing 610 MWe of gas turbines in 1973 is about $ 48,800,000 based on an installation cost of $ 80/KW.

Since it is assumed that all replacement energy will be supplied

¹Niagara Mohawk's employment of a 25-year service life for nuclear generating equipment depreciation computation has been adopted by the New York State Public Service Commission in rate making procedures.

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by the lower energy cost existing fossil stations, capital related charges are included. The estimated only annual annual cost of the gas turbines, including capital interest, depreciation, and other fixed charges will be about $ 8,300,000.. This annual cost would only be charged as a cost of decommissioning until 1976 when the replacement oil-fired unit is in operation. The present value (1976) of these annual costs at a 9.6 percent cost.

of capital will be about $ 35,600,000.

A completely new fossil unit at a different location on the Nine Mile Point site could be constructed by 1976. Use of existing equipment with a new fossil-fired boiler is impractical. The existing turbine could not accommodate the high-pressure, high-temperature steam from a fossil boiler. Since structures such as the reactor building contain induced radioactivity in their structural members, it is not feasible to use some buildings for a new fossil plant. Location of these buildings would that they be tom down to make room for the boiler room andrequire other structures. Tearing down these unuseable structures, building new structures in their place, and trying to accommodate a new fossil unit within the useable existing structures would take more time and would cost more than building a completely new fossil unit.

The estimated total construction cost of a 610 MW fossil fuel unit at Nine Mile Point for December 1976 operation would be about $ 200,000,000. Capital costs have been escalated from the present date at a rate of 5. 5 percent a year. The estimated annualized cost of capital including interest, depreciation, and other fixed charges would be about $ 36,800,000. The estimated annual fuel, operating, and maintenance cost would be about

$ 31,393,000.. These costs are based on a fixed charge'ate of 18.4 percent, a fuel cost of 5.6 mils/kWhr, operating and maintenance cost of 1.2 mils/kWhr, and a capacity factor of 85 percent. The total estimated annualized cost of the fossil annualized cost 't unit would be about. $ 67,700,000. The present value of this a 9.6 percent cost of capital and an amortization over the remaining 18 year economic life of Unit 1 would be about $ 570,000,000.

Therefore, the grand total present value (1976) of decommissioning Nine Mile Point Unit 1, maintaining the facility in a safe condition, and replacing the installed capacity and energy requirement, would be about $ 793,000,000.

In conclusion, the alternative of decommissioning the existing station and replacing the power is not realistic for several reasons. First, it is not economically nor environmentally desirable to decommission an existing station which is supplying much needed power with a minimum environmental impact. Also, since only 310 MWe of installed capacity could be replaced during the first year after decommissioning, a 300 MWe deficiency in installed capacity would exist based on an objective of an

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installed generating capacity reserve of 18 percent., This deficiency would not be offset by power purchased from other sources and therefore would result in a lost benefit.

Further, gas turbines are generally unsuited for continuous operation as base load units. They have a relatively low availability due to maintenance requirements and high fuel costs. Finally, if a fossil station were to replace the existing nuclear station, even under the Clean Air Amendments of 1970, such a plant could annually emit 3.7 x 10~ pounds of sulfur dioxides, 1.3 x 10~ pounds of nitrogen oxides, and 0.44 x 10~

pounds of particulate matter. These emissions would be. prevented by the continued operation of the existing nuclear station.

Hence the decommissioning of the existing station and subsequent replaceme'nt of the power is not a feasible alternative and is not considered further in greater detail.

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9 5 ALTERNATIVE COOLING SYSTEMS The existing cooling system for the Nine Mile Point 1 station employs once-through cooling which takes water from Lake Ontario, uses it for the main condenser, primary and auxiliary cooling within the station, and returns it to the lake, undiminished in quantity but increased in temperature. A diffuser system would be designed to combine the cooling water discharges from both Unit 1 and the proposed Unit 2, planned for operation in 1978. A presentation of this diffuser system is found in the Nine Mile Point Nuclear Station Unit 2 Environmental Report (Ref. 27),

Utilization of this diffuser system is contingent upon construction of Unit 2. However, for the purposes of this report only alternative cooling systems for the Unit 1 discharge alone are considered. These include a once-through system with diffuser discharge, a natural draft cooling tower system, a mechanical draft cooling tower system, and a cooling pond system.

A dry cooling tower, a spray pond, and supplementary cooling are discussed but are not considered to be feasible alternatives.

Alternative condenser sizes for the once-through system (i.e.

lower temperature rises across the condenser and higher circulating water flows) were not considered, since entrainment studies to date at Unit 1 indicate that mechanical effects are the major cause of plankton mortality rate. Only those various cooling systems which are considered feasible are discussed in detail in the following sections and form the basis for the comparative tabulation of environmental costs presented in Table 9.5-1 at the end of Section 9.5.

9.5.1 Existing Once-Through Cooling System The intake and discharge structures associated with the existing once-through cooling system are discussed in detail in Section 3.5 and are shown in Figures 3.5-1 through 3.5-3. This system was designed so that the effluent would comply with the New York Water Quality Thermal Standards of 1967 (6NYCRR701) as discussed in Section 5. 1.

9.5.1.1 Economics of the Existing System The Nine Mile Point Nuclear Power Station Unit 1 is an existing facility which commenced commercial operation in December of 1969. Therefore, the total costs associated with the construction of the existing once-through system will not be quantified, but will instead serve as a base cost. The costs for the alternative cooling me thods will be presented as an incremental cost to the base cost of the existing system. These costs will therefore reflect the amount necessary to transform the existing once-through cooling system to the alternative cooling water system.

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9-5.1.2 Environmental Considerations of the Existing System 9.5. 1.2. 1 Heat Discharge to Water Body The existing Once-through system discussed in Section 3.5 has a total circulating water flow of approximately 600 cfs. Tpe total heat rejection rate is approximately 4 x 10~ Btu/hr. Studies of the existing system as discussed in Section 5. 1 have shown that a 3,000 acre-feet volume of water is created within a 3 F temperature increase isotherm with a surface area of less than 300 acres. As presented in Section 5.5, the ecological studies prepared by Dr. Storr have shown that this discharge conforms to the New York State Water Quality Thermal Standards of 1967 (6NYCRR701) as discussed in Section 5. 1. These values for the volume and area affected by the thermal discharge are small in comparison to the volume and area of Lake Ontario, which are 1.3p x 10~ acre-feet and 4.7 x 10~ acres, respectively.

As discussed in Section 5.5.3, dissolved oxygen measurements have been made in the discharge area during the fish netting survey.

As the summer progresses, the amounts of phytoplankton '

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warmest period of the year levels of dissolved oxygen of 11 to 12 ppm are not uncommon, with no diminution at, night. No significant loss in oxygen has been observed between the intake and discharge of Unit 1.

Since the heat relea sed to the lake and the surface area and volume of the lake affected by Unit.1 are small in comparison to the lake's natural characteristics, no adverse thermal impact on the waters of Lake Ontario as a whole has or is expected to occur. However, for the purposes of this report an environmental impact has been assumed based on the area a ffected by the existing station design and the distribution of the fishery resource for the U.S. portion of the lake.

The area of the station~s impact was based on the New York State criteria for thermal discharges which assume that increases in ambient lake temperature of less than 3 F will not adversely affect the aquatic biota. By using the 300-acre surface area within the 3 F isotherm as the area which could adversely affect commercial fish production, of this facility on the it is possible to assess the impact commercial fishery of, Lake Ontario.

Lake Ontario supports a limited commercial fishery as described in Section 2 of this report. Commercial fishing in the United States from Lake Ontario for the three years 1968, 1969 and 1970 (Section 2. 2. 1) amounted to approximately 322,000 pounds per year for an average annual value of $ 65,000. A report by the U.S.

Fish and Wildlife Service in 1969 (Ref. 18) estimates that projected demand for fishery products from U.S. landings in Lake Ontario will increase four-fold to about 1.25 to 1.5 mi3.lj.on pounds annually by the year 2020.

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,The majority of the commercial landings in the U.S. portion of the lake are from Chaumont Bay and the nearby shoal a'reas in the northeastern portion of the lake over 30 miles from the site.

The remaining fishing effort is generally in the lake proper from the Oswego River eastward to the St. Lawrence River.

However, for environmental'ost quantification, it is assumed that the majority of the commercial U.S. fishing is, wi4hin the 100 foot depth contour, of the lake from the Oswego River to the northeastern U.S. boundary including the bays and shoal areas in the U.S. portion 'of the lake There are then approximately

. 350,000 acres of water available for commercial fishing. The pxojected annual U.S. commercial landings for the. year 2020 is 1.5 million pounds of fish per year. Uniformly spread over. the 350,000 acres results in an average rate of exploitation of 5 pounds of fish per acre of water. Actual studies of .the temperature distribution and aquatic life in the vicinity of the existing Nine Mile Point Unit 1 have demonstrated that there are no detrimental effects to fish life. However, for purposes .of this. evaluation it is assumed, perhaps unrealistically, that all fish within a 3 F isotherm, are adversely affected. If Unit 1 affects 300 surface acres, approximately 1, 500 pounds of fish could be lost to the commercial fishery each year.

Information on the utilization of Lake Ontario for sport fishing was also derived .from the U.S. Fish and -Wildlife Service

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(Ref. 18) There are approximately 2,000,000 surface acres in the U.S. portion of the lake plus thousands of acres of tributary area which offer fishermen a variety of warm and cold water species of sport fish. The estimated total fisherman days expended in 1960 was 3.2 million; this number is expected to double by the year 2020. The 1965 National Survey of Fishing and Hunting estimates that the tangible expenditures per freshwater fisherman in 1965 averaged $ 88.71 per year. This makes sport fishing a valuable source of revenue in the Lake Ontario Region.

The New York State Department of Environmental Conservation and the Great Lakes Bas'in Commission are presently determining the distribution of sport fishing effort in Lake Ontario. However, this information is not yet available and the sport fishing intensity in the vicinity of Nine Mile Point cannot be assessed.

Therefore, only a qualitative judgment can be made of the impact of the heated discharge on sport fishing.

Since the area of Lake Ontario af fected by the heated discharge from Unit 1, less than 300 acres, is small in comparison to the 2,000,000 acres available for sport fishing, Unit 1 is not expected to have an adverse impact on sport fishing.

The influence of the thermal discharges from the existing system C

on the migratory patterns of the fish in the lake and adjacent river systems was also considered. The ad jacent rivers are comprised of the Oswego River approximately eight miles west of

9. 5-3

the site, the Little Salmon River eight miles east-,of the site, and the Salmon River a few miles further east.'he New York State Department of Environmental Conservator.on expects to develop the fisheries associated with these xivers. Temperature increases in the area of these rivers due to the discharge from this unit would be immeasurable because of their distance from the site. In the lake proper the influence of the discharge will be limited to a localized area. Fish will be 'ble to move

'reely around the warmest. portions of the plume. The thermal flow from the site is described in more detail in Section 5. 1 of this report.

Since the thermal discharge will not affect the adjacent rivers and since there is ample room for fish to travel around the plume, no impaixment of fish migration is anticipated.-

As previously described in Section 2.7-1, the south shore of Lake ontario is an important concentration area for diving ducks winter. It is not anticipated that, this duck population in'he would be adversely affected by the thermal discharge since the results of the preoperational and post-operational surveys.

indicate that the effects on potential food sources, such as

-attached macrophytes and associated invertebrates, are small and localized. Likewise, the effects on any transient biota which may utilize:the lake are believed to be minimal.

9.5. 1.2.2 Effects of Intake Structure on Water Body Studies 'ave been conducted at the Nine Mile Point, Nuclear Station Unit 1 to evaluate the impact of the condenser 'cooling water system on entrained plankton. These studies are described in Section 5.5.

The total weight of organisms per cubic foot of water was computed as the sum of the average weights of the specific taxonomic groups of the zooplankton and phytoplankton,collected from eleven sampling periods from June to mid-November. The average yeight of 'plankton for the sampling period was estimated to be 0. 548 gram/cubic foot. This value is taken '.to be ",

representative of the entire year. However, the average annual biomass is actually lower since the biomass concentration is probably less during the winter months. These'estimates are believed to account, for approximately 90 percent of the plankton biomass. Small unabundant forms were not included in .this analy sis. i Two separate methods were used to compute the mortality of plankton passing through the condenser cooling system. The first method depends on- counting the difference in number of in the discharge 'nd intake. structures for each dead,'rganisms taxonomic group. The results showed that 0. 047 gram of plankton were killed per cubic foot of water passing through the cooling system. However, dead organisms may disintegrate or settle.out

9. 5-4

l

,l I

a'

in the system and could reduce the number of dead organisms counted in the discharge. This may bias the sample and lower the computed mortality rate.

The second method for determining the mortality is based on the number of living organisms per cubic foot measured in the discharge and intake structures. The difference is assumed to be the number of organisms killed in the cooling system. This more conservative method results in a mortality rate of 0. 161 gram of plankton per cubic foot of water passing through the cooling system having a condenser temperature rise of 32 F. Based on this more conservative mortality rate and a flow of 600 estimated cfs for Unit 1, the total weight of plankton killed annually is to be 6.7 x 10~ pounds per year. Further studies are being continued in 1972.

The impact of this mortality on the plankton population can best be assessed by considering several factors. The first, and probably most important factor, is that plankton populations are generally short lived (days to a few weeks) and have rapid regeneration times. Furthermore, the site is located in an open area of the lake where there is a continual renewal of waters so

-local populations should not become depleted. The increase in temperature in the vicinity of the discharge might also accelerate plankton production during the colder months. In addition to these factors, the dead plankton would not be lost to the food chain. Observations by divers at Unit 1 indicate that many small fishes are attracted to the discharge area and appear to be feeding on plankton detritus. For these reasons, the impact of this mortality on the ecosystem of the lake is expected to be minimal.

The effect of the intake and condenser cooling system on the fisheries of the lake can be evaluated by determining the number of fish that enter the system and become entrapped in the screenwell and the number of juvenile forms which may experience lethal conditions in passing through the system.

Fish eggs or larvae were not cbserved in the plankton samples which were collected at Unit 1 during the entrainment studies conducted from mid-June to mid-November in 1971. As described in Section 2, the only fish which has been observed to spawn in the area is the alewife. Alewife eggs are deposited on -the bottom and adhere to the bottom strata. As such, these eggs would generally not be entrained in the condenser cooling system. Many of the other fish species found in Lake Ontario, also have sinking eggs and would not, therefore, be entrained in the condenser cooling system during this life history stage.

Estimates of larval fish abundance during the early spring in the vicinity of Nine Mile Point are not presently available. Studies as discussed in Section 5.5, were initiated in the Spring of 1972 in order to establish the number and mortality of larvae which

9. 5-5

D k

be entrained in the condenser cooling system.. However, due may to the previ.ously mentioned factors,, it is anticipated that larval abundance would be.low and would be primarily composed of alewi.ves.

The effects of the circulating water intake system upon fish life have been discussed in Section 5. Occasional observations at Nine Mile Point Unit 1 during the first two years of operation (1970-71) indicate that only a few fish have been collected from the trash racks. A program of detailed observations. in this area (i..e.,trash racks and traveling screens) will be conducted during 1972 to measure fish collection.

9.5.1.2.3 Chemical Discharge to Water Body No chemical treatment is associated with the once-through cooling system to control organic growths in the condenser.. The silt entrained in the water is sufficient to clean the coolant passageways. This cooling system therefore does not increase chemical concentrations in Lake Ontario and does not produce any environmental impact.

Any chemi.cal concentrations that are released are due to mixing, of the stations chemical effluents with the circulating water.

However, these releases are considered to be part of the chemical treatment system presented in Sections 3.7 and 9.6 and not a part of the cooling system.

9.5. 1.2.0 Consumption of Water This cooling system returns all the cooli.ng water to the lake.

No consumption of water has or is expected to occur from the continued use of this cooling system.

9.5.1.2.5 Chemical Discharge to Ambient Air The existing once-through cooling system does not produce any particulate matter in the form of drift, and does not release any gases or odors. This system therefore does not adversely affect ambient air quality.

9.5. 1.2.6 Salts Discharged from Cooling Towers This area of environmental concern is not applicable to this cooling water system alternative.

9.5.1.2.7 Chemical Contamination of Ground Water (excluding Salts)

The existing once-through cooling system i.s i.solated from the ground and does not contaminate ground water.

9. 5-6

0 9-5-1-2.8 Radiological Effects The radiological effects that are produced from the station are presented in detail .in Section 5.2.

9.5.1.2.9 Fogging and Icing The existing power station uses a once-through cooling system to reject waste heat from the station. This cooling method does not rely on evaporation or the transfer of sensible heat to the atmosphere, and therefore, this station does not create a fogging or icing problem.

9 5. 1.2-10 Raising/Lowering of Groundwater Levels As previously discussed, all liquid systems are isolated from the ground and no alteration of ground water levels has or is expected to occur.

9.5. 1.2. 11 Ambient Noise The primary sources of noise for the unit with the existing once-through cooling system are the main transformer and turbine hall.

The transformer sound levels versus distance axe calculated from the transformer NEMA rating. Turbine hall noise is estimated from the sound levels anticipated within the turbine hall corrected for the txansmission loss of the walls.

The sound field in the vicinity of the station is calculated by a special computer pxogram. This program determines the sound power level for each sound source, the distance from each sound source to reference points on a polar coordinate grid system, and the octave band sound pressure level contribution for each sound source at each reference point. Corrections are made for source directivity, molecular absorption, and hemispherical radiation.,

At each reference point the individual source contributions are converted to dBA values and summed to determine the total sound level at that point.'onstant sound level contour lines may be drawn through the reference grid.

These contours were used in conjunction with the proposed <<HUD Criteria Guidelines for Nonaircraft Noise,<< Department Circular 1390.2 to estimate areas of acoustic acceptability in the region surrounding the site. The HUD criteria give sound levels which correspond to the categories <<clearly unacceptable," <<normally unacceptable," and <<normally acceptable.<<

Based on these guidelines and the constant station sound level, the "normally acceptable<< level was taken to correspond to an area receiving 45 to 65 dBA and the <<normally unacceptable<< level was taken to correspond to an area receiving over 65 dBA. This.

combination of noise guidelines and sound contours were superimposed upon" topographic maps of the area to estimate the

9. 5-7

lg number of residences, schools, and hospitals receiving an acoustical impact from the site.

The results of the acoustical impact study for the once-through cooling water system has determined that no residences, schools, or hospitals are within an area receiving a sound level greater than 65 dBA.. In addition, residences, it has been determined that no schools, or hospitals are within an area receiving a sound level between 45 and 65 dBA. Therefore, the acoustical impact of the existing once-through cooling water system is assumed to be neglible.

9.5. 1.2. 12 Aesthetics This cooling system presents no visible structures and therefore has no effect on the aesthetics of the area.

9.5.1.2.13 Permanent Residuals of Construction Activity The construction activity pertaining to the existing once-through cooling system has already been completed. The quantities of excavated material have been used as backfill around structures or for site grading. The intake and discharge structures do not interfere with shipping or water transportation in the area.

Therefore, no permanent. residuals of construction activity is considered to exist at the site.

9.5. 1.2. 14 Combined or Interactive Effects There is no evidence that the combined effects of a number of impacts result in a total effect which is not adequately indicated by measures of the separate impacts.

9.5.2 Once-Through Cooling System With Diffuser Discharge A once-through cooling system with diffuser discharge is one of several feasible alternatives which may be utilized to decrease environmental impact. With this system the water circulated through the condensers would be returned to the lake through submerged jet diffusers.

The system uses the existing intake tunnel, condenser and auxiliary systems. However, the diffuser scheme would require the installation of a new discharge shaft adjacent to the west side of the existing screenwell, and a new discharge tunnel extending about 1400 feet offshore. At this point the water depth at mean lake level is approximately 35 feet, as shown in Figure 9.5-1.

The new discharge tunnel would divide into two equal branch tunnels by means of a tee section. The combined total length of these branch tunnels would be about, 195 feet. Each branch tunnel section would also contain two diffuser heads spaced about

9. 5-8

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NEW DISCHARGE STRUCTURE 2 IO (2.5 Dia NOZ2LES 4 PAIRS)

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>gO EXISTING INTAKE STRUCTURE NEW DISCHARGE TUNNEL EXISTING DISCHARGE STRUCTURE

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48 t SLOWDOWN LINE LINE O PROGRESS- FF w N I,883,000 CENTER UNIT I ~ ~

84 t 84 t NOTESF 84 t BALANCE LINE EQUIPMENT FOR CHEMICAL ADDITIONS TO BE TOWER DISC. STRUCTURE (TYP) LOCATED IN EXISTING SCREENWELL.

MAKE-UP OBTAINED FROM SERVICE WATER DISCHARGE. SLOWDOWN CONTROLLED BY WEIR MECHANICAL DRAFT AT TOWER BASIN, WITH DISCHARGE INTO COOLING TOWER SWITCHYARD EXISTING DISCHARGE SHAFT IN SCREENWELL.

288 x55 (TYP) 0 I 00 ZOO O O O O O O SEXI.E EEET eI el e 'IF w N I,883,000

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FIGURE 9.5-2 MECHANICAL DRAFT COOLING TOWER SCHEME

0 45 feet on center and connected to the branch tunnel by vertical risers. In turn, each diffuser head would consist of twin 2.5 foot diameter nozzles which would enable,.the cooling water to be discharged in a horizontal direction.

The walls surrounding the existing discharge flume at. the screenwell would be raised to accommodate the increased discharge head created by the installation of the nozzles. Also, the motors on the existing circulating water pumps would be replaced with larger motors to efficiently operate against this increased discharge head;, Installation of the new tunnel shaft, tunnel, diffuser and structural changes to the screenwell could be accomplished without hindering the continued operation of the unit. However, the motor replacement and the connection of the new discharge shaft to the existing discharge:flume would have to be accomplished during a station outage.

9.5.2. 1 Economics of this System For the purposes of this report is is assumed that this sy'tem could be placed in operation by 1976.

The estimated total construction cost of transforming the existing cooling water system to the once-through" diffuser discharge system for operation in 1976 'is about $ 5,770,000..

Capital costs have been escalated from the present date at a rate of 5.5 percent a year. The estimated annualized cost of this alternative including capital, interest, depreciation, and other fixed charges is about $ 1, 160,000. The estimated annual fuel, operating and maintenance cost of the alternative would be about"

$ 55,000.. These costs are based on a fixed charge rate of 20.1 percent, a fuel cost of 2.8 mills/kWhr, an operating and maintenance cost of 0. 3 mill/kWhr and a capacity factor of 85 percent. The total estimated annualized cost is about

$ 1~215~000 Total estimated present value of this alternative at a 9. 6 percent cost of capital and an amortization over the remaining 18-year 'conomic life of the station is approximately

$ 10i230i 000 9.5.2.2 Environmental Considerations of this System 9.5.2.2. 1 Heat Discharge to Water Body The heat rejected from Unit 1 through its once-through cooling system is approximately 4 x10~ Btu/hr. This quantity of heat would be discharged through the new diffuser discharge structure to promote rapid dilution, as seen in Figure 9.5-1. The surface area within the 3 F isotherm above natural lake temperature would.

be about 6.0 acres and the volume within the 3 F isotherm would be less than 150 acre-feet.. Since this quantity of heated water small in comparison to the large volume of water in Lake

's

9. 5-9

Ontario, no measurable thermal impact on the waters of Lake .

Ontario, as the whole, are expected.

As discussed in Section 9.5.1.2. 1, no significant loss of oxygen has been observed from the results of the dissolved oxygen measurements which have been made in the discharge area during the fish netting survey. Therefore, it is considered that the discharge from this system would have no adverse impact on the oxygen availability of Lake Ontario.

Actual studies of the temperature distribution and aquatic life in the vicinity of the existing Nine Mile Point Unit 1 discharge system have demonstrated that there are no detrimental effects to fish life. However, for purposes of this evaluation assumed that all fish within a 3 F isotherm are adversely it is affected. It is estimated that the surface area affected, 6.0 acres, could result in a loss of approximately 30 pounds of fish per year to the commercial fishery. This is based on a rate of exploitation of 5 pounds of fish per acre of water as discussed in Section 9.5.1.2. 1. In addition, the impact of the discharge on the sport fishery is also considered to be neglible, and is judged not to impair the migration of fish in Lake Ontario or the adjacent river systems, as discussed in Section 9.5. 1.2.1.,

As discussed in Section 9.5.1.2. 1 the results of the preoperational and postoperational field surveys indicate that the effects on potential food sources for wildlife and transient-biota are small and very localized. Therefore, it. is considered that the discharge from this system would have no adverse impact on transient biota and associated wildlife.

9.5.2.2.2 Effects of Intake Structure on Water Body This area of environmental concern for the once-through cooling system with the diffuser discharge would be the same as that presented in Section 9. 5. 1.2. 2.

9.5.2.2.3 Chemical Discharge to Water Body This area'f environmental concern for the once-through cooling system with the diffuser discharge would be the same as that presented, in Section 9.5. 1.2. 3.

9.5.2.2.4 Consumption of Water This cooling system returns all the cooling water to the Lake.

No consumption of water is expected from this system and therefore no impact is expected to occur.

9-5-10

0 9.5.2.2.5 Chemical Discharge to Ambient Air This cooling system would not produce any particulate matter in the form of drift, and would not release any gases or odors.,

.This system would not adversely affect ambient air quality.

9.5.2.2.6 Salts Discharged from Cooling Towers This area of environmental concern is not applicable to this cooling water system alternative.

9.5.2.2.7 Chemical Contamination of Ground Water (excluding salts)

This once-through cooling system would be isolated from the ground and would not contaminate ground water.

9.5-2.2.8 Radiological Effects The radiological effects that would be produced from the station when a once-through cooling system with diffuser discharge is employed would be the same as those presented in Section 5.2.

9.5.2.2.9 Fogging and Icing This once-through cooling system would not rely on evaporation of water to release heat to the atmosphere. Therefore, this system would not create a fogging or icing problem.

9.5.2.2.10 RaisinglLowering of Ground Water Levels Since this cooling system would be isolated from the ground no alteration of ground water levels could occur.

9.5.2.2.11 Ambient Noise The acoustic impact of Unit 1 using the once-through cooling system with the diffuser discharge would be the same as that in Section 9.5. 1.2. 11.

9.5.2.2.12 Aesthetics This cooling system would present no visible structures and therefore would have no adverse effect on the aesthetics of the area.

9.5.2.2. 13 Permanent Residuals of Construction Activity There would be no permanent effects of installing the once-through cooling system with a diffuser discharge.

Construction of the new discharge system would require essentially no downtime beyond that required during normal refueling operations. The quantities of excavated material would

9. 5-11

be used as Tunneling backf activity ill would around structures or for site grading..

have no effect on lake water quality although, there may be some disturbance of benthic organisms within a small area during .installation of the discharge diffusers. The diffuser riser shafts would be drilled rather than blasted into the lake bottom and the steel liners grouted and the, large diffuser shaft liners inserted. The drilling would be conducted from a temporary surface platform similar to a

<<Texas Tower<<. The benthos in the vicinity of the. diffuser risers would be removed as a result of the drilling activity.

However, the affected area is small (less than 0. 1 acre) and is, therefore, not expected to adversely affect the overall benthic communities in the vicinity of, Nine Mile Point. Following placement of the diffuser shafts, the platform would be disassembled and removed from the lake. The intake and discharge structures would not interfere with shipping or water transportation in the area since the structures would be more than 12 feet below the low water datum.

9.5.2.2.14 Combined or Interactive Effects There is no evidence that the combined effects of a number of impacts result in a total effect which is not adequately indicated by measures 'of the separate impacts.

9.5.3 Wet Cooling Tower Systems Wet cooling towers remove heat by passing ambient air through the cooling water. Heat is released to the atmosphere by a combination of sensible and latent heat transfer. The cooling tower performance is thus dependent on meteorological conditions.

Wet cooling tower schemes are presented below that are closed loop systems and reject all of the power station's waste heat to the atmosphere. Cooling towers could also be used as a supplementary cooling system in combination with a once-through cooling system. A discussion of this type of system is presented in Section 9.5.7.

A mechanically induced draft cooling tower scheme for Unit 1 would consist of two separate tower units each having nine cells.

Each unit would have an approximate length of 288 feet and a width of approximately 55 feet. The towers would be approximately 65 feet high, which includes an 18 foot stack height for each cell. These dimensions assume a design wet bulb temperature of 74 .F with a design cold water approach of 14 F.

This 74 F wet bulb temperature is representative of design conditions for the summer months, and the 14 F cold water approach is the value which has been assumed to be representative of optimum conditions for a unit of this size in this climate.

This scheme is presented in Figure 9.5-2.

9. 5-12

A natural draft cooling tower scheme for Unit 1 would have a single tower approximately 360 feet in diameter and 370 feet high for an atmospheric design condition of 74 F wet bulb temperature and 60 percent relative humidity. These conditions are representative of summertime design conditions.. During these conditions, the tower is designed to operate at an 18 F approach which is estimated to be optimum for this type of tower in this climate.. This cooling tower design scheme is presented in Figure 9.5-3 For the wet cooling tower schemes, Lake Ontario would be used for supplying reactor and turbine service water and makeup water to the tower for evaporation loss and blowdown. The lake also would serve as a receiving body for tower blowdown.

Additional circulating water pumps would be installed in pump wells for each tower scheme and would pump water through a closed loop piping system between the ccoling towers and the condenser.

The 40 cfs-auxiliary system service water would be obtained from Lake Ontario from the existing intake tunnel as shown in Figure 3.5-2 and be returned to the. lake by way of the tower blowdown line. An additional screenwell structure would be required in

. the vicinity of the existing screenwell for the auxiliary service water system. The auxiliary system service water would be introduced as makeup to the towers by combining the auxiliary system water and main condenser discharge. lines downstream of the condenser. The design flow rates in the cooling towers would be as follows:,for a circulating water flow of 600 cfs, there would be about 20 cfs for evaporative and drift 1'osses and 20 cfs for blowdown. The required makeup water to the towers would be 40 cfs. These design conditions would produce a 2 times reconcentration of lake dissolved solids in the cooling towers.

The preliminary designs of the towers have not included additives to control scaling or algal growth. In the event that this would become a problem, a nontoxic nonphosphate scaling inhibitor would be used that would conform to the Food and Drug Administration criteria. Algal growths would be controlled by the addition of an algicide in quantities that would conform to New York State Water Quality Standards.

The use of cooling towers would require modifications to the proposed radwaste treatment system (Section 3.6) since less water would be available for diluting the radwaste effluent than with the once-through cooling system. To achieve the required discharge concentrations, the curies of radioactivity released would be reduced by adding a tray section to the regenerant chemical evaporator and adding a set of demineralizers to the radwaste effluent treatment. This modification would produce concentrations that would be within the limits set forth in 10CFR Part 20 and the proposed Appendix I of the 10CFR Part 50 guidelines, when the effluent is combined with the 20 cfs blowdown flow from the towers.

9. 5-13

0 I

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60" $ SERVICE WATER LINE ll4 $ INTAKE LINE~

PUMPWELL EXISTING SCREENWELL O STRUCTURE O 48 4BLOWDOWN LINE O lO II4 0 DISCHARGE LINE lal UNIT I 360 4 TOWER OSC. Nl, 283,000 NATURAL DRAFT STRUCTURE PROGRESS COOLING TOWER CENTER NOTES:

CENTER OF COOLING TOWER IS I. EQUIPMENT FOR CHEMICAL ADDITIONS TO BE LOCATED IN EXISTING SCREENWELL Nl >283,000 E545,000 2. MAKE-UP OBTAINEO FROM SERVICE WATER DISCHARGE. SLOWDOWN CONTROLLED BY WEIR AT TOWER BASIN, WITH DISCHARGE INTO EXISTING DISCHARGE SHAFT IN SCREENWELL.

SWITCHYARD O

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9.5.3. 1 Economics of Wet Cooling Tower Systems The following modifications are necessary to transform the existing cooling water system of Section 9.5. 1. to the natural draft cooling tower system. These modifications .include a natural draft hyperbolic tower; a separate makeup and service water screenwell; modifications to the existing circulating water screenwell, circulating water pumps, and motors; a circulating water pumpwell.and associated equipment; circulating water piping connecting the cooling tower, pumpwell, condenser, and various screenwells for tower makeup and blowdown; and the modifications to the liquid radwaste system as mentioned in Section 9 5.3.

The estimated total capital cost of transforming the existing cooling water system to the natural draft cooling tower system would be about $ 16,960,000 for operation in 1976.. Capital costs have been escalated from present date at the rate of 5.5 percent a year. The annualized cost of this alternative including capital, interest, depreciation and other fixed charges would be about $ 3,409,000. The estimated annual fuel, operating and maintenance cost would be about $ 568,000.. The annual capability loss compared to the existing station's generating capability would be about $ 1,096,000 due to a higher condenser inlet temperature. These costs are based on a fixed charge rate of 20.1 percent, a fuel cost of 2.8 mills/kWhr, an operating and maintenance cost of 0.3 milVkWhr, and a capacity factor of 85 percent. Total annualized cost would be about $ 5,073,000..

The total present value of the natural draft cooling tower scheme at a 9.6 percent cost of capital and an amortization over the remaining 18-year economic life of the station would be approximately $ 42,700,000.

The mechanical draft cooling tower system would consist of equipment similar to that of the natural draft tower, with the exception that two mechanical draft towers with .fans and motors would replace the hyperbolic cooling tower.

The estimated total cost of transforming the existing cooling water system to the mechanical draft cooling water system would be about $ 11,850,000 for operation in 1976., Capital costs have been escalated from present date at rate of 5.5 percent a year.

The annualized cost of the mechanical draft cooling tower system, including capital, interest, depreciation, and other fixed charges would be about $ 2,382,000. The annual fuel, operating and maintenance cost would be about $ 690,000. Annual capability loss compared to the existing station~s capability would be about

$ 854,000 due to a higher condenser inlet temperature. These costs are based on a fixed charge rate of 20. 1 percent, a fuel cost of 2.8 mills/kWhr, an operating and maintenance cost of 0.3 mill/kWhr, and a capacity factor of 85 percent. Total annualized cost would be about $ 3,926,000. The total estimated present value of the mechanical draft cooling tower scheme at a 9.5-14

9.6 percent cost of capital and an amortization over the 18-year economic life of the station would be $ 33,040,000..

9.5.3.2 Environmental Considerations of Wet Cooling Tower Systems 9.5.3.2.1 Heat Discharged to Water Body It is estimated that the blowdown from either the mechanical draft or natural draft cooling towers would contain approximately 1.4 x 10~ Btu/hr. This blowdown would be discharged from the existing discharge tunnel to promote rapid dilution.. The surface area within the 3 F isotherm above natural lake temperature would be about 0.72 acre and the volume within the 3 F isotherm would be less than 2.2 acre-feet.. Since this quantity of heated water is small in comparison to the large volume of water in Lake Ontario, no adverse effects to the water quality of the lake are expected.

As discussed in Section 9.5. 1.2. 1, no significant loss of oxygen has been observed from the results of the dissolved oxygen measurements which have been made in the discharge area for the existing once-through system during the fish, netting survey.

Because of the turbulent contact between the cooling water and the ambient air within the wet cooling tower system, significant aeration would occur. Therefore, .it is considered that this system would not adversely affect the oxygen availability in the cooling water but could conceivably increase the dissolved oxygen content.

It is estimated that the surface area affected, 0.72 acre, could result in a loss of approximately 4 pounds of fish per year to the commercial fishery. This is based on a rate of exploitation of 5 pounds of fish per acre of water as discussed in Section 9.5. 1.2. 1. The impact of the discharge on the sport fishery is also considered to be negligible. The heated water is also judged not to impair the migration of, fish in Lake Ontario or the adjacent river systems.

As discussed in Section 9.5. 1.2. 1 the results of the preoperational and postoperational field surveys indicate that the effects on potential food sources for wildlife and transient biota are small and very localized. Therefore, that the discharge from this system would have it no is considered adverse impact on transient biota and associated wildlife.

9.5.3.2.2 Effects of Intake Structure on Water Body The estimate of plankton mortality for the cooling tower schemes is based on'he assumption that all planktonic formstower. in the It makeup water would be killed in passage through the has been estimated that there are 0.548 gram of plankton per 9 5-15

cubic foot of lake water as explained in Section 9 5. 1.2.2.

Combining this value with the 40 cfs makeup water flow results in the approximation that 1.5 x 10~ pounds of plankton would be killed in the cooling towers annually. The environmental impact of plankton mortality 'on lake populations is believed to be minimal as discussed in Section 9.5.1.2.2.

The effects of the intake and condenser cooling water system on the fisheries of Lake Ontario are based on the information available from occasional observations made at. Nine Mile Point Unit 1 as discussed in Section 9.5.1.2.2. Assuming that the fish lost in the cooling tower makeup supply system is proportional to the total circulating water flow rate, then even fewer fish will be lost in the screenwell to the tower system than would be lost in the existing once-through system. This small quantity would have no effect on the fisheries of Lake Ontario.

Complete information of the loss of larval fish.through the condenser cooling system is not presently available as discussed in Section 9.5. 1.2.2. However, preliminary studies conducted at Nine Mile Point Unit 1 indicate that the mortality of larval fish is expected to be minimal with a cooling tower scheme.

9.5.3.2.3 Chemical Discharge to Water Body The 20 cfs tower blowdown would contain 2 times the concentra-tions of chemicals found in the natural lake water due to evaporation and recirculation of the coolant. See Table 2.5-1 for a listing of ambient water quality data for Lake Ontario.

After discharge into the lake the effluent would be diluted with the ambient lake water. Approximately 10 dilutions would occur before the effluent would reach the boundary described by the 3 F temperature increase isotherm as discussed in Section 9.5.3.2. 1.

The chemical concentrations in the blowdown would then be virtually the same as those in the natural lake water.

Therefore, no adverse chemical effects on the people using the water, aquatic biota, water quality or wildlife are expected.

The effects of combining the chemical effluents from the station with the blowdown is discussed in Section 9.6.

9.5.3.2.4 Consumption of Water Water loss from the power station resulting mainly from evapora-tion from the cooling towers would be nearly 20 cfs during peak meteorological conditions. Additional consumption from normal station operations would not exceed 0.02 cfs, as discussed in Section 3.4.

If total the peak conditions were continuous throughout the year, the consumption of water from Lake Ontario would be about 4.8 x 10~ gallons per year.

9. 5-16

This quantity is about 0.001 percent of the water contained in Lake Ontario which is approximately 4.4 x 10~~ gallons. It is not expected that this small quantity of water removed per year from Lake Ontario would have any effects on the people, property, or industries using the lake water.

9.5.3.2.5 Chemical Discharge to Ambient Air Droplets of the cooling water would be entrained in the air that passes through the cooling tower. These droplets, called drift, would contain the chemicals that occur in the lake water that have been allowed to concentrate to a maximum of 2 times. The amount of these particulates discharged from the top of the cooling tower can be estimated by assuming that the drift is 0.005 percent of the total circulating water flow in the towers.

This would produce a drift of 14 gpm that has a dissolved solids concentration of approximately 450 ppm. The total emission rate of solids would be about 0.05 pound per minute. Assuming that these solids would be uniformly distributed in the'air flow from the cooling towers, there would be a concentration of approximately 9 micrograms per cubic meter at the top of the cooling tower.

at the ground Ifitthis concentration was continually experienced would produce a concentration well below the annual average New York State and Federal secondary ambient air quality standards which are 55 and 60 micrograms per cubic meter, respectively. Furthermore, the actual concentrations experienced at the ground would be much less than the concentration at the top of the cooling tower due to plume rise and atmospheric dispersion. Therefore, ambient air quality would not be significantly altered by the solids concentrations produced from the cooling towers. In addition, no odors are associated with the operation of the cooling towers.

9. 5. 3.2. 6 Salts Discharged from Cooling Towers The 0.05 pound per minute of solids released to the atmosphere from the cooling towers are assumed to be salts. A preliminary study was performed to estimate the distribution of these salts in the vicinity of the site. This study indicates that salt deposition rates from natural draft towers could be approximately 1 pound/acre/year at a distance of 1,200 feet, the approximate distance to the closest site boundary. The deposition rate would decrease to about 0.4 pound/acre/year at a distance of one mile.

Salt deposition from a mechanical draft tower is expected to be approximately 120 pounds/acre/year at a distance of 1,200 feet, and approximately 11 pounds/acre/year at a distance of one mile.

The higher salt deposition rates of the mechanical draft tower are due to the lower height of this tower as compared to the natural draft tower.

The effect of the salt distribution on people and property beyond the site area is expected to be minor since the annual ambient salt concentrations would be below the annual average New York

9. 5-17

State and Federal Secondary Ambient Air Quality Standards for suspended solids.

The impact of this fallout on surrounding vegetation has not been determined, since specific studies are not available on effects of long-term exposure of the specific salts. However, Lake Ontario is used for irrigation and the chemical concentrations in the water appear to be suitable for terrestial vegetation.

considered that since the reconcentration It of chemical is constituents in the cooling tower drift is only 2 times that of ambient lake water, the effect of drift on terrestial vegetation would probably be minor.

9.5.3.2.7 Chemical Contamination of Ground Water (Excluding Salt)

The cooling tower would be completely isolated from the ground, except for the releases due to drift. This drift would be diluted by natural rainfall which amounts to approximately 35 inches a year. This rainfall combined with the estimated maximum solids deposition of 120 pounds/acre/year from a mechanical draft cooling tower would result in a ground level solids concentration of approximately 15 ppm.. Similarly, the maximum ground level solids concentration from a natural draft cooling tower would be approximately 0.1 ppm. It is anticipated that these solids concentrations percolating to the ground water would not adversely affect the uses of this resource.

9.5.3.2.8 Radiological Effects The effects of the proposed radwaste system modified for use in conjunction with cooling towers have been investigated. Gaseous releases and consequent environmental effects would be the same as for the proposed radwaste system design. These releases are explained in Section 5.2. With the use of cooling towers, less water would be available for diluting the radwaste effluent.

Therefore, the modifications to the proposed radwaste system as discussed in the introduction to Section 9.5.3 would be required to reduce the total activity of the liquid radioactive releases by about 10 percent. The combination of this reduced effluent activity and decreased coolant flow would result in essentially the same activity concentrations which result from the proposed radwaste system design presented in Section 3.6. As a result, the individual and population doses would correspond to those presented in Section 5.2 with the exception of the man rem per year from fish consumption. Since the, annual release rate would be reduced by a factor of 10, the expected dose from this pathway would be 10 percent of the tabulated values.

9.5-18

9. 5. 3.2. 9 Fogging and Ic ing The frequency and extent of fogging created by cooling towers would be dependent upon meteorological conditions at the Nine Mile Point site. Generation of visible vapor plumes is enhanced under conditions of high relative humidity and low ambient air temperature. The shape and range of a visible plume is highly dependent on wind velocity.

A numerical analysis was performed which uses local weather data in conjunction with tower performance curves to model the behavior of visible tower vapor plumes. Figures 9.5-4 and 9.5-5 summarize the results of the analysis for both mechanical draft and natural draft towers. The figures present the frequency that visible vapor plumes would occur at a given distance and altitude from the tower, assuming that the wind direction is constant throughout the year. Variations in wind direction would, however, tend to reduce the occurrence of fog in each direction by a factor approximately equal to the annual frequency of the wind from that direction. The wind direction frequencies are presented in Appendix D.

Vapor plumes produced by a natural draft tower would not be expected to reach the ground, due prirrarily to the height at which the plume is discharged. Mechanical draft towers, however, could produce ground level plumes and for the purpose of estimating the extent of such ground level fogging, visible vapor plumes at altitudes of approximately 100 feet or less, were considered to be essentially ground level.

During adverse weather conditions as seen in Figure 9.5-5, ground level fog from a mechanical draft tower could extend to as far as 1,200 feet with a frequency of 5 percent. As a result, an area of about 140 acres around the tower site could be subject to ground level fog at various times of the year. This area lies within the .Nine Mile Point power site, and extends approximately 800 feet onto Lake Ontario.

Drift and fog produced by a cooling tower which impinges upon the ground could contribute to surface icing. Zt is considered that the only area and road which would be affected by icing due to cooling tower drift in the colder months lies within the boundaries of the Nine Mile Point site.

The plumes from the cooling towers would not hamper air, ground, or water transportation since the range of the plumes would be limited. Elevated plumes would not interfere with commercial airports since there are none within the range of the visible plume; ground transportation would only be affected occasionally within the site area by ground level plumes from mechanical draft cooling towers; water transportation would not experience the cooling tower plumes beyond 800 feet from the shore.

9. 5-19

TOWER DESIGN DATA 2000 T4 WB ~ 14 A PP HEIGHT GS FT.

NOTES THE FIGURES DENOTE PERCENT OF TIME THAT VISIBLE PLUME I750 EXTENDS TO CONTOUR ONLT ONE DIRECTION IS CONSIDERED FOR WINO SPEEDS I 500 I 250 10 '/o 15%

I 000 20'Yo UI I

I 750 25'/o 5 'Yo 50o/o 250 500 750 I GOO 1250 I 500 I750 2000 2250 2500 2750 3000 3250 3500 3750 HORIZONTAL DISTANCE-FEET FIGURE 9$ -4 MECHANICAL DRAFT COOLING TOWER PLUME

,I 2250 TOWER DESIGN DATA Ti WB, l84APP.

2000 HEIGH T STO FT.

l0% NOTES THE FIGURES DENOTE PERCENT OF TIME THAT VISIBLE PLUME EXTENDS TO CONTOVR I 750 ONLY ONE DIRECTION IS CONSIDERED FOR WIND SPEEDS I500 15 '/o l 250 20%

I VI I 25%

I IOOO X

750 50'/o )p%

250 FIGURE 95-5 NATURAL DRAFT COOLING TOWER PLUME 250 500 750 IOOO 1250 l500 I750 2500 2750 3250 3500 3750 HORIZONTAL DISTANCE -FEET

It is also measurable considered that the cooling towers would not produce effects on vegetation due to fogging and icing in the area. Some sunlight attenuation by the plumes would occur but the effects would be comparable to those produced by clouds. Any icing from the cooling towers would be produced during the colder months when the vegetation would not normally be susceptible to damage from freezing.

Ice buildup on plants and trees on the site could occur from drift from a natural draft tower and,from drift and fog from a mechanical draft tower. The natural ice loadings due to snowfall and freezing rains would be slightly augmented by the operation of the cooling towers. The mechanical draft tower would have a greater effect than the natural draft tower since it is lower in height and its fog would occasionally reach the ground and its drift deposition would be higher closer to the tower. No studies are presently available on the effects of ice buildup on vegetation but considering the site climatology the additional effects of the cooling towers is expected to be insignificant,.

9.5.3.2.10 Raising/Lowering of Ground Water No water for the cooling towers is required from ground wells or municipal sources, and blowdown from the cooling towers is returned to Lake Ontario. Therefore, no change in the ground water levels is expected.

9.5.3.2.11 Ambient Noise Noise is generated in natural draft cooling towers by the cascading water. In mechanical draft cooling towers, fan noise is added to the noise of the falling water. Cooling tower sound levels are determined from manufacturers'ata or published references on tower noise. In order to assess the acoustical impact of these cooling water alternatives on the surrounding area, contours of constant sound level were determined for both natural draft and mechanical draft cooling tower systems utilizing the technique described in Section 9.5. 1.2.11.

Based on the noise guidelines discussed in Section 9.5. 1. 2. 11 and the constant station sound level, the ~~normally acceptable" level was taken to correspond 'to an area receiving 45 to 65 dbA and the "normally unacceptable" level was taken to correspond to an area receiving over 65 dbA.

For either cooling tower system it was determined that no residences, schools, or hospitals would receive a sound level greater than 65 dbA. Ten residences would be within the 45 to 65 dbA range with a natural draft cooling tower and forty residences would be within this range with a mechanical draft cooling tower.

It should be noted that the estimates used to determine the sound level contours are conservative and do not include attenuation

9. 5-20

from trees, terrain, or meteorological conditions which would reduce the offsite areas affected by the noise generated.

9.5.3.2.12 Aesthetics Of the two types of cooling towers considered in this report the natural draft tower would be the more aesthetically pleasing because of its hyperbolic shape. The mechanical draft towers would be more numerous and would create a more industrial-like appearance, but they would be less noticeable from the site boundary. Plumes from either of the tower schemesbeyond may be unappealing in appearance.

9. 5.3.2. 13 Permanent Residuals of Construction Activity Cooling towers would require use of additional land area on the site; about 2.1 acres for the mechanical draft towers and 2.3 acres for the natural draft cooling tower.

These uses of land would not affect wildlife or affect any historical or archeological sites of interest, since there are none in the site area. Values of surrounding property and uses of adjacent land are also not expected to be affected.

Construction of the cooling towers would not require modification of the shoreline or topography of the area, and therefore, would not contribute to flooding and erosion in the region.

9.5.3.2. 14 Combined or Interactive Effects There is no evidence that the combined effects of a number of impacts result in a total effect which is not adequately indicated by measures of the separate impacts.

9.5.4 Dry Cooling Tower System Dry cooling towers reject sensible heat directly to the atmosphere and thus do not depend upon the evaporation of water for their performance.. An indirect dry cooling tower system was examined which would be used in ccmbination with a direct contact spray condenser to condense the turbine's exhaust steam. Cooled water from the tower would be brought into contact with the turbine's exhaust steam, and a fraction of the condensate formed would then be returned to be cooled in the tower. The remainder of the condensate would recirculate to the reactor.

An optimum dry cooling tower system operates with turbine back-pressures in the order of 8 to 12 inches Hg abs. However, U.S.

manufacturers do not plan to market a turbine that is compatible with this tower design until 1978.

The state of the art for dry cooling towers is limited. The largest existing plant which uses a dry cooling tower of this type is only a 200 MWe unit. The lack of experience with a unit

9. 5-21

the size of Nine Mile Point Unit 1, has eliminated this system from further consideration.

9.5.5 Cooling Pond System A cooling pond is a large cooling water storage area used to reject heat directly to the atmosphere by the transfer of both sensible and latent heat. A pond large enough to remove the waste heat from the Nine Mile Point Unit 1 would have a surface area of about 880 acres and a volume of 19,000 acre-feet. A possible location for the cooling pond would be on site slightly south of the station between Lake Road on the north and the Penn Central Railroad on the south as shown in Figure 9.5-6.

The eastern edge of the pond would be parallel to and near the boundary with the property of the Power Authority of the State of New York (PASNY) . The westerly edge of the pond would be formed by a dike following the higher knolls and lying in a southwesterly-northeasterly direction and slightly west of Lakeview Road. The southern boundary of this pond would be formed by the 310-foot contour which lies roughly east and west in direction and parallel to the Penn Central Railroad. A dike approximately 40 to 50 feet high would therefore be required along the east, north, and western boundaries to retain the contents of the cooling pond. An approximately three mile long circulating path for the cooling water would be established by constructing baffle dikes to separate the inlet from the outlet.

The earthwork required for constructing the boundary and baffle dikes would amount to approximately 3,000,000 cubic yards of earth material.

The circulating water would have to be pumped a distance of approximately two miles. Two pipes would be required to carry the water to and from the pond. Rock excavation would be required if these pipes are to be placed beneath the ground surface in order to minimize stresses due to temperature changes and drainage interference.

The make up water flow would be 40 cfs and the evaporation could range up to approximately 30 cfs. This could result in a blowdown in the range of 10 to 20 cfs.

The proposed radwaste system would be modified to the same degree as would be required in conjunction with cooling towers because of the reduced coolant discharge. Dilution pumping may also be required occassionally for periods of lower blowdown flow. This alteration in the radwaste system is presented in Section 9.5.3.

9.5-22

C7 I

UNIT I 33 SWITCHYARD II V

~ l

~0 g LAKEVtEW RD.

lq lg

~

g PROPERTY LINE INCLUDING REQUIRED AQ VIS IT ION

~ V ~ PENH CEHTRAL FIGURE 9.5-6.

COOLING LAKE AT 310 FOOT E LE VATION ( 880. ACRES )

FROM SARGENT 6 LUNDY REPORT SL - 2775

9.5.5. 1 Economics of the Cooling Pond The following modifications are necessary to transform the existing cooling water system of Section 9.5.1 to the cooling pond system:

Pond structures (dikes and spillways), circulating water pumps and motors with associated screen house equipment, circulating watex piping to and from the pond and the condenser, makeup service pump house, makeup and blowdown lines, chemical treating equipment for makeup water treatment and the modifications to the radwaste system. The estimated total construction cost for operation in 1976 would be $ 21,600,000. Capital costs have been escalated from the present date at the rate of 5.5 percent per year. The annualized cost of the cooling pond alternative including capital, interest, depreciation, and other fixed charges would be about $ 4,342,000. The annual fuel, operating, and maintenance cost would be about $ 312,000. This includes pump power, chemical treatment and pond maintenance. Annual capability loss compared to the generating capability of the existing station would be $ 1,241,000 due to higher condenser inlet temperatures. These costs are based on a fixed charge rate of 20. 1 percent, a fuel cost of 2.8 mills/kWhr, an operating and maintenance cost of 0.3 mill/kWhr and a capacity factor of 85 percent. Total estimated annualized cost would be about

$ 5,895,000. The total estimated present worth of this alternative at a 9.6 percent cost of capital and amortization over the remaining 18-year life would be approximately

$ 49,620,000.

9.5.5.2 Environmental Considerations of the Cooling Pond System Many of the environmental considerations for a cooling pond are similar to those for a cooling tower explained in Section 9.5.3.2. Those areas of environmental concern that are applicable to a cooling pond are presented below.

9.5.5.2.1 Effects on the Water Body At the present time it is not possible to determine the dissolved oxygen content in the cooling pond blowdown. However, since the quantity of blowdown which would be discharged from the pond is small, there is expected to be no adverse impact on ,the oxygen availability of Lake Ontario.

It is assumed that there is a complete mortality of the plankton drawn into the cooling pond from the lake. In actuality specialized plankton communities would probably develop in the pond and be returned to the lake in the blowdown. However, for environmental cost quantification the mortality of plankton in the 40 cfs make up water is considered to be 100 percent. This would result in approximately 1.5x10~ pounds of plankton being removed annually from the lake based on a plankton density of 9.5-23

0.548 gram of plankton per cubic foot of water. An assessment of the environmental impact of this plankton mortality is in Section 9.5. 1.2.2.

The effects of this system on commercial and sport fishing and larvae would be the same as those of the cooling towers. These impacts are presented in Section 9.5. 1.2.2.

9.5.5.2.2 Consumption of Rater The cooling pond could have an evaporation rate of about 30 cfs; this natural evaporation would be higher than the forced evaporation from cooling towers The removal of water from Lake Ontario would be about 7. 1 x 10~ gallons per year. This is about 0.0016 percent of the approximately 4.4 x 10~4 gallons of water in the lake and no adverse environmental impact is expected from this water consumption.

9.5.5.2.3 Chemical Discharge to the Ambient Air Cooling ponds would not produce any drift since air would not be passed through the coolant There would thus be no chemical discharge or odor to the ambient air.

9.5.5.2 4 Salts Discharged from a Cooling Tower This area of environmental concern is not applicable to the cooling pond alternative.

9.5.5.2.5 Chemical Contamination of Ground water (Excluding Salt)

Although studies were conducted and some borings have been made, insuf ficient information is presently available with respect to the suitability of the area for the construction of the cooling pond. Therefore, it is not possible to properly assess the environmental impact at this time. However, it is considered that chemical concentrations would be reduced by passing through the overburden.

9.5.5.2.6 Fogging and Icing Analytical models for the production and dispersion of fog from cooling ponds have not been developed and tested to the same degree as have those for cooling towers. Experience indicates, however, that cooling ponds are a relatively diffuse source of fog and that downwind evaporation would be fairly rapid. Drift from the cooling pond would be practically nonexistent Therefore, the cooling ponds would not be expected to create any fogging or icing problems.

9.5-24

9.5.5.2.7 Raising/Lowering of Ground water Although studies were conducted and some borings have been made, insufficient information is presently available with respect to the suitability of the area for the construction of the cooling pond. Therefore, it is not possible to properly assess the environmental impact. Assuming conditions are similar to those around the station, such as relatively impervious overburden on sandstone, it can be expected that a rise in the ground water table would result in the vicinity of the pond. However, at this time it is not possible to estimate the effects or the extent of this rise.

9.5.5.2.8 Ambient Noise Since noise is not produced by cooling ponds, the station would generate noise levels that are comparable to those produced by the existing once-through cooling system explained in Section 9.5.1.2.11. No houses, schools or hospitals would receive a sound intensity of greater than 65 dbA, after the construction of a cooling pond.

9.5.5.2.9 Aesthetics The large cooling pond might he an attractive addition to the countryside. Careful landscaping could minimize the visual effect of the dikes.

9.5.5.2. 10 Permanent Residuals of Construction Activity The cooling pond would require approximately 880 acres of onsite land located b'etween one-half and two miles south of the station.

Since the cooling pond contains the cooling water above ground there is a potential for flooding of the surrounding area.

Because of this, all parts of the pond system related to impoundment would be designed to meet the requirements of Class 1 seismic conditions. In addition, all embankments and areas of possible erosion would be planted and seeded.

Inundating .the land would affect wildlife in the area. The number and specific types of wildlife in the 880 acres of land has, however, not been determined. Careful consideration would have to be given to the impact of flooding the land on present and potential wildlife uses. The cooling pond may however provide an area for increased recreational use. Fishing and boating may be practical on the pond.

9.5.5.2.11 Combined or Interactive Effects Where is no evidence that the combined effects of a number of impacts result in a total effect which is not adequately indicated by measures of the separate impacts.

9. 5-25

9.5.6 Spray Pond System Experience with spray ponds for units of 250 MRe and above is extremely limited, and although some large systems are being developed, there is not enough perf ormance data presently available to adequately design a spray pond for an 610 MWe unit.

The designs that have been evaluated indicate that the land area required and the economic cost of spray ponds is nearly the same as for wet cooling towers. There are known problems with this type of pond, however. The spray modules have to be carefully spaced to ensure adequate supplies of ambient air for evaporative cooling for efficient performance. Furthermore, some studies of existing smaller spray ponds show that severe drifting of the water spray occurs. In winter this would result in severe icing conditions onsite and offsite Further consideration of the spray ponds has been eliminated because of the limited experience with ponds of the required size and the possible environmental impacts of this cooling system.

9.5.7 Supplemental Cooling System In principle, wet cooling towers and cooling ponds may be used as a supplemental cooling system. In this type of system, the once-through system would be .supplemented by towers or ponds during those times when the heat rejecticn to the lake needed to be reduced. Part of the station waste heat would be rejected to the atmosphere by the towers or ponds. However, since there are wide variations of the atmospheric wet bulb temperatures, as compared to water temperatures at the Nine Mile Point site, there are inherent limitations in the performance of a supplemental cooling system. At certain times, ambient atmospheric wet bulb temperatures would be such that only a small fraction of the total heat could be rejected by the supplemental cooling method and the remaining heat would be discharged to Lake Ontario.

To clarify this 'point, a study was made based on the use of a supplemental mechanical draft cooling tower system. The tower was sized such that its cold water discharge temperature would be 3 F above the ambient lake temperature at the point of discharge during a period when the atmospheric wet bulb would be 74 F, and the lake temperature would be 77 F. The design temperatures were selected on the following basis:

1. The 3 F differential corresponds to the 1969 New York State thermal criteria which assume that an increase in ambient lake temperature of less than 3 F will have no adverse effect on the aquatic biota.

2. 74 F wet bulb temperature is that temperature which is used for design conditions for the summer months.

9.5-26

1,

3. 77 F lake temperature is that temperature. which is used for design conditions for the summer months.

One year of meteorological data that had been recorded in the vicinity of the site was used in this study. The year 1950 was selected as a typical year with respect to wet bulb temperature.

Average monthly. lake temperatures were used in this study because of the relative stability of the lake. Using these design criteria and data, the daily performance of the system was determined for a one-year period. The results of this study are depicted in Figure 9.5-7. The graph shows that the,3 F rise will be exceeded for extensive periods during the year, particularly in the spring and fall. There were several periods when large thermal discharges to the lake would have occurred; for example, on April 4, 1950, when the lake temperature was 40 F, and the ambient wet bulb temperature was 56 F, the temperature differential between the tower discharge and the lake would have been 22.5 F. This supplemental system, then, would not meet its stated objective of limiting the discharge to less than 3 F. A cooling pond or a wet cooling tower used in a supplemental system would also result in a large fraction of the total heat occasionally being discharged into the lake. For these reasons, supplemental cooling systems have not been considered in further detail.

9. 5-27

0 0

IIO NOTE - TOWER DESIGN DESIGN INLET WATER TEMP- I07 IOO DESIGN DISCH WATER TEMP" 80 DESIGN WET BULB-74 90 I OISCIIARGE WATER TEMPERATURE 4I z 80 2 AMSIEJIT LAKE TEMPERATVRE 4J CG z

4 I TP IJJ ILI ILJ 4J GJ ep IJI I

IL SO 4J 4J I

40 JAN. FEB. MAR. APR. MAY JUNE JULY AUG. SEPT. OCT>> NOV. DEC.

1950 FIGURE 9.5-7 SUPPLEMENTARY COOLING TOWER EFFECT ON CIRCULATING WATER DISCHARGE - TEMPERATURES

9 6 ALTERNATIVE CHEMICAL EFFLUENT SYSTEMS The existing system for the Nine Mile Point Unit'1 releases the chemical effluent to the circulating water of the existing once-through cooling system. An alternative to the existing system would employ evaporation to eliminate the discharge of chemical effluents to, Lake Ontario. These various chemical ef fluent systems are discussed in the following sections and form the basis for the comparative tabulation of environmental costs as presented in Table 9.6-1 at the end of Section 9-6.

9.6.1 Existing Chemical Effluent System Effluent from the existing chemical effluent system as described in Section 3.7 is released to the circulating water of the existing once-through cooling system. If an alternate cooling system were to be employed, then the effluent would be released to the blowdown of the cooling tower or cooling pond.

9.6. 1.1 Economics of Existing System The Nine Mile Point Nuclear Power Station Unit 1 is an existing facility which commenced the commercial operation in December of 1969. Therefore, total costs associated with the construction of the existing chemical effluent system will not be quantified, but will instead serve as base cost.. The costs for the alternative chemical effluent system will be presented as an incremental cost to the base cost of the existing system. These costs will therefore reflect the total amount necessary to transform the existing chemical effluent system to the alternative chemical effluent system.

9.6. 1.2 Environmental Considerations of Existing System The effluent from the existing system is discharged to Lake Ontario after dilution with the circulating cooling water. Only those environmental impacts which directly relate to this system are presented below.

Chemical effluents associated with operation of the makeup water treatment system described in Section 3. 7 consist of (1) neutralized spent acid and caustic wastes resulting from demineralizer regeneration; (2) clarified overflow from the settling basin; and (3) clarified water from the clearwell during shutdown operation.

The effects of the chemical effluent are dependent upon the amount of water available for dilution prior to discharge. The existing once-through cooling system provides 600 cfs of circulating water for dilution. When the chemical effluent of is mixed with this flow, the outfall contains a concentration dissolved solids of approximately 230 ppm. Combination of the chemical effluent with the 20 cfs blowdown from a cooling tower

9. 6-1

t ~ '4 V t

or cooling pond would result in a dissolved solids concentration of about 544 ppm. This is due to the combination of a relatively low blowdown flow and a concentration of dissolved solids in the cooling tower blowdown during normal tower operation of approximately twice that existing in ambient lake water. A comparison of the chemical effluents expected to be released from Nine Mile Point Unit 1 under the existing and alternate cooling water designs are presented in, the following table, along with Lake Ontario concentrations and applicable drinking water standards:

Existing Chemical Discharge as Affected by Alternative Cooling Methods

~Existin Alternative-Diluted with Diluted Wi;th Drinking Circulating Tower or Pond Water Lake-Gntario. Waxer. Blowdown. Standards-ppm ppm Ca++ 44.00 44. 10 90. 40 HCO~ 94.00 94. 11, 190. 10 Cl- 30 30 30. 38 62. 60 250 Mg++ 8.90 8. 92 18 30 1 60 1 60 3 30 Na+ 16. 60 17. 55 60. 60 SOW = 30 10 32. 11 118. 60 250 Total Dissolved Solids 225.5 228 77 543.90 500 These concentrations are further diluted with ambient lake water after being discharged. When the existing once-through cooling system is used, the chemical concentrations are diluted with lake water approximately 10 times at the boundary of a 300 acre surface area. If a cooling tower or pond scheme were used the concentrations would be diluted about 10 times at the boundary of a 0.72 acre surface area. At the boundaries of these surface areas the intermittent chemical concentrations from each cooling system would be close to lake water concentrations. It is,

,therefore, expected that these concentrations would not adversely affect people who use the water, aquatic biota, or water quality.

9. 6-2

Since the chemical concentrations in the existing cooling water system are essentially the same as ambient lake water, believed that there is no adverse impact on the utilization of it is

,the lake by associated wildlife. Similarly, considering that the blowdown concentrations are close to drinking water standards and will be further diluted within a very small area, there is expected to be no effect on wildlife utilization of lake waters.

There is no evidence that the combined effects of a number of impacts result in a total effect which is not adequately indicated by measures of the separate impact.

9.6.2 Evaporative Chemical Effluent System An alternative to the existing treatment would employ evaporation to eliminate chemical effluents resulting from demineralizer "regeneration cycles. The evaporation process would require use of a falling film evaporator and an adequately designed, lined, lagoon to store the concentrated brine bottoms produced in the evaporator. Alternate treatment of chemical effluents resulting from the settling basin overflow and clear well bypass would not be required since their chemical composition subsequent to pH adjustment would be comparable to that of Lake Ontario. A simplified sketch of the system is shown in Figure 9.6-1.

9.6.2.1 Economics of the Evaporative Chemical Effluent System The following modifications are necessary to transform the existing chemical effluent system to the evaporative chemical effluent system. These include a falling film evaporator for handling 750 gallons per hour, a condensing unit, and the lined lagoon for storing solids from the evaporator. The estimated capitalized cost of the equipment for operation in 1976 would be about $ 857,000. Capital costs have been escalated from the present date at the rate of 5.5 percent a year. The estimated annualized cost of this alternative including capital, interest, depreciation, and other fixed charges would be about $ 172,000.

The estimated annual cost of fuel, operating and maintenance, and chemical testing would be $ 50,000. These costs are based on a fixed charge rate of 20.1 percent, a power cost of 12 mills/

kwhr, and a capacity factor of 85 percent. Total estimated annualized cost would be $ 222,000. Total estimated present value of this alternative, at 9. 6 percent cost of capital and amortization over the remaining 18-year economic life, would be about $ 1,870,000.

9.6.2.2 Environmental Considerations of this System Areas of environmental concern affected by the application of an evaporative treatment for the regenerative wastes are presented below.

9.6-3

I J V 7 I

NOTE:

THE OPERATION OF THIS SYSTEM IS INTERMITTENT AND IS REOUIRED ONLY UPON ACCUMULATION OF LIOUIDS IN THE REGENERATION WASTE NEUTRALIZATION TANKS FALLING FILM EVAPORATOR PRODUCT WATER I TDS = 5 PPM DEMINERALIZER REGENERATION WASTES I3)000 PPM TDS WASTE BRINE 200) 000 PPM ELECTRICAL ENERGY LINED ONSITE POND I

)

I I

I I

I I

I

\ REGENERATION

) WASTE NEUTRALIZATION TANKS MAKEUP WATER (FIG. 3.7-I )

DElllNERALIZATION SYSTEM (FIG. 3.79)

I CLEARWELL IFIG.3.7 I)

FIGURE 9.6- I SCMEME FOR EVAPORATIVE TREATMENT OF REGENER'ATION WASTES

n 1 If

9.6.2 2.1 Chemical Discharge to Water Body The evaporative treatment would not re lease any chemical ef fluents associated with demineralizer regeneration cycles from to Lake Ontario. Overflow from the settling basin and bypass the clearwell would have a chemical composition, after pH adjustment, comparable to the that of Jake Ontario. Therefore, no adverse environmental impact is expected.

9.6.2.2.2 Consumption of Water It has been estimated that the evaporative chemical effluent treatment would remove about 16,000 gallons of water per year from Lake Ontario. This small quantity would have no effect on people, property or the ecosystem of the lake.

9. 6. 2. 2. 3 Chemical Contamination of Ground Water (Excluding Salts)

The brine storage, pond would be lined to prevent the chemicals from reaching the ground. Thus, no contamination of ground water would be expected to occur.

9.6.2.2.4 Fogging and Icing The ',only part of this system which would be open to the atmosphere and could produce fog or icing problems would be the brine storage pond. However, this pond would be small and fog would be localized. Also, the brine would have a high concentration and this would retard evaporation. There would, therefore, be no fogging or icing problems created by this system.

9. 6. 2.2.5 Ambient Noise The evaporators would be completely enclosed and would not produce noise levels above that produced by normal station operation.

9.6.2.2.6 Aesthetics The evaporators would be housed in a building that would blend in with the other station structures, and no additional visual impact would be produced.

The brine storage pond would cover about 0.25 acre and might appear objectionable. Plantings around the pond could lessen the visual impact.

9. 6-4

l

~ A ,

M IP

9.6.2.2.7 Permanent Residuals of Construction Activity The evaporator would be housed in a building that would use approximately 800 square feet of land. The brine storage pond would require an additional 10,000 square feet. This land usage is minor and employment of this system would not affect wild life, land values, or production in the area.

Erosion and flood control in the area would not be affected by the small amount of land used for this system.

9.6.2.2.8 Combined or Interactive Effects There is no evidence that the combined effects of a number of impacts result in -a total effect which is not adequately indicated by measures of the separate impacts.

9 6-5

TABLE 9+6-1 COST DESCRIPTION ALTERNATIVE Q9MCAL EFFLUENT SYSTEMS NINE MILE PO'AT NUCLEAR STATION UIKZ 1 Report Date: Juno 1@72 Existing Chemical Evaporative Chemical Effluent System(l) Effluent System(2)

Base Case $ 1,870,000 9.6.2.1 ENVIRONMElFZAL COSTS Primary Impact Population or Resource Affected

1. Heat discharged 1.1 Cooling capacity no effect no effect to water body 1.2 Aquatic biota no effect no effect 1.3 Migratoxy fish no effect no effect

2. Effects on water 2.1 Primary producers no effect no effect body of intake 8e consumers structure and condenser 2.2 Fisheries no effect no effect cooling system

3. Chemical 3.1 People no adverse effect 9.6.1.2 no adverse effect 9.6.2.2.1 discharge to water body 3,2 Aquatic biota no adverse effect 9.6.1.2 no adverse effect 9.6.2.2.1 3.3 Water quality- no adverse affect 9.6.1.2 no adverse effect 9.6.2.2.1 chemical

4. Consumption of 4.1 People no effect no effect water 4.2 Property no effect no effect

5. Chemic a1 5.1 Air quality- no effect no effect discharge to chemical ambient air 5.2 Air quality- no effect no effect odor

6. Salts'ischarged 6.1 People from cooling towers 6.2 Plants'ot applicable not applicable not applicable not applicablc 6.3 Property resources not applicable not applicable

7. Chemical 7,1 People no effect no effect 9.6.2.2.3 contamination of round water 7.2 Plants no effect no effect 9.6.2.2.3 excluding salt)

8. Red ionuclides 8.1 People-cxtcrnal not applicable not applicable discharged to contact water body 8.2 People-ingestion not applicable not applicable 8.3 Primary consumers not applicable not applicable 8.4 Fish not applicable not applicable 9.6 - 6

TABLE .6 "1 CONT 'D COST DESCRIPTION ALTEQGLTIVE CHEMICAL E1VLUENT SISTER NINE MILE POINT NUCLEAR STATION IHGT 1 Existing Chemical Evaporative Chemical Effluent System(1) Effluent System(2)

Primary Impact Population or Resource Affected 9, Radionuclides 9.1 People-external not applicable not applicable discharged to contact ambient air 9.2 People-ingestion not applicable not applicable 9.3 Plants snd animals not applicable not applicable

10. Radionuclides 10.1 People not applicable not applicable contamination of ground water 10.2 Planta and animals not applicable not applicable

11. Fogging 5 11.1 Ground transporta- no effect no effect 9.6.2.2.4 icing tion 11.2 Air transportation no effect no effect 9.6.2.2.4 11.3 Water transporta" no effect no effect 9.6.2.2.4 tion I1.4 Plants no effect no effect 9.6.2.2.4

12. Raising/lowering I2.1 People no effect no effect of ground water levels 12.2 Plants no effect no effect

13. Ambient noise 13.1 People no effect no effect 9.6.2.2.5 14, Aesthetics 14.1 Appearance no effect brine storage 9,6.2,2,6 area

15. Pe zmanent 15.1 Accessibility of no effect no impact, 9.6.2.2,7 residu81$ of historical sites construction activity 15.2 Accessibility of no effect no impact 9.6.2.2.7 archeological sites 15.3 Setting of no effect no impact 9.6.2.2.7 historical sites 15.4 Land use no effect lo,8OO ft2 9.6.2.2.7 15.5 Property no effect negligible 9.6.2.2.7 15.6 Flood control no effect no effect 9.6.2.2.7 15.7 Erosion control no effect no effect 9.6.2.2.7 Refer to the following sections for a discussion of the environmental costs:

1) Section 9.6.1

2) Section 9.6.2 9.6 - 7

9.7 ALTERNATIVE RADWASTE SYSTEMS The existing radwaste system for Nine Mile Point Unit 1 will be modified as discussed in Section 3.6 and will comply with the limits set forth in 10CFR Part 20 and the proposed Appendix I of 10CFR Part 50 guidelines. In accordance with the AEC's . most recent guide for the preparation of benefit cost analyses published in May 1972, no other alternative radwaste systems need to be considered if the proposed system is in compliance with these regulations. Any modification of the proposed liquid radwaste system which would be required in conjunction with the use of cooling towers or cooling ponds due to the reduced quantity of cooling water available for dilution, are considered to be integral parts of the cooling system and are described in the applicable portions of Section 9.5.

Therefore, for the purposes of the benefit cost analysis, both the existing and proposed radwaste systems are considered to be integral parts of the station design and are thus presented in Table 9.8-2 of the "Alternative Station Arrangements~~ in Section 9.8. Detailed descriptions and a comparison of the environmental effects of both the existing and proposed radwaste systems are developed in Sections 3.6 and 5. 2.

9. 7-1

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9 8 ALTERNATIVE STATION DESIGNS The purpose of this section is to compare the benefits and costs of alternative station designs. Included for comparative discussion in this section are the existing power station design, the station design considered to produce the minimum water impact, the station design considered to produce the minimum land/air impact, and the proposed station design for the license request.

The results of these comparisons are summarized in Tables 9.8-1 and 9.8-2 at the end of Section 9.8.

9.8.1 Existing Power Station Design The description, characteristics, and environmental effects of the existing facility at the Nine Mile point Site are presented in the preceeding sections of this report. However, the economic benefits and environmental considerations are further developed here in order to facilitate comparison with alternative system designs.

9.8.1.1 Benefits of the Existing Design The main benefit of the existing Nine Mile Point Nuclear Station Unit 1 is the generation 'of 610 MWe of electrical energy to NMPC residential, commercial and industrial customers. Annual production of electricity based on an annual capacity factor of 85 percent is about 4.54 x 10~ kW-hours.

The table below indicates the distribution of electrical power among the customers. The benefit to customers in 'terms of dollars is estimated by assuming that each customer gains a dollar benefit equal to the cost of the electricity.

Percent of Electricity Power Used Rate Benefit in Customer. - Used'. kWhr/Yr 4/kWhr++ Dollars-Residential 27. 3g 1.24 x 10~ 2.62 $ 32 49 x 10~

Commercial-Industrial 60.65*~~ 2.75 x 10~ $ 44.00 x 10<

Other 12. 1% 0.55 x 10~ $ 10. 28 x 10+

4. 54 x 10> $ 86.77 x 10~

+Based on 1971 usage This has not been adjusted for growth of electrical demands.

++Based on the rates of January 10, 1972 No adjustment has been included for possible future rate changes.

+++As combined in FPC Annual Report Form 1.

9. 8-1

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The minimum estimate of present value of power benef its is determined by multiplying the benefits of $ 86.77 x 10~ by the present worth factor, 9.03, for a remaining economic life of 22 years and an interest rate of 9.6 percent. This results in a present value of power benefit of $ 783,500,000.

The existing station benef its the local region by contributing approximately $ 3,000,000 in taxes each year based on the 1971 tax rate. This substantially increases the tax base for area residents.

In addition, the station operation creates 68 jobs in all phases of the station activities. The payroll of the facility is approximately $ 1,020,000 per year, and fringe benefits estimated at $ 400,000 are provided Additional jobs are created away from the site area in activities related to the production, shipment and disposal of radioactive materials.

The station facilities also provide educational benefits to the general public. The Progress Center has an presentation of the development of electrical energy which attracts about 50,000 people per year. The benefit 'f excellent Progress Center can be expressed in terms of the 50,000 people this visiting the center and enjoying the picnic area per year.

Building and operating the power station have resulted in many environmental studies that are of scientific interest. The following studies are part of a continuing effort to evaluate the effects of nuclear power stations and to confirm the environmental impact on the site and its surroundings:

Aquatic surveillance studies to identify the species in the area and to determine the effect of heat releases Plankton studies to evaluate the effects of plant operation on the organisms passing through the cooling system Meteorological studies to evaluate the dispersion characteristics in the site region Hydrological studies to determine the dispersal of heat in Lake Ontario Geological studies of the seismicity of the area Terrestrial ecology studies to identif y the dominant fauna and flora of the area Radiological studies to measure background radiation, the potential build-up of radionuclides in aquatic and terrestrial organisms and to monitor station emissions 9.8-2

The cost of these studies is approximately $ 400,000. However, some of these studies have provided information that is directly applicable only to this project. The rest of the studies have provided information that will aid the general development of power generation and prediction of environmental effects. These studies which have a wider range of scientific interest cost approximately $ 300,000, and are the basis for estimating the scientific benefit of the power station. The ultimate dollar benefit from this increased scientific knowledge cannot be assessed. However, for the purpose of benefit quantification is assumed that the benefit gained equals the cost of the it studies.

The operation of a nuclear power station instead of a fossil fuel unit provides a benefit of producing power without the emission.

of large quantities of air contaminants. For example, fired station were to replace the existing station, the plant if an oil could emit annually about 3.7x10~ pounds of sulfur dioxides, 1.3x10~ pounds of nitrogen oxides, and 0.44x10~ pounds of particulate matter under the clean air amendments of 1970. These emissions are prevented by the use of the nuclear power station and this prevention can be considered to be a savings to the environment.

9.8. 1.2 Economics of the Existing Power Station The Nine Mile Point Nuclear Station Unit 1 is an existing facility licensed under Section 104 of the Atomic Energy Act of 1954, as amended, and which commenced commercial operation in December, 1969. The total costs associated with the construction of the existing station design are about $ 164,492,000 as of Dec.

31, 1971 and serve as a base cost. The costs for the a1ternative station designs will be presented as an incremental cost to the base cost of the existing station design. These costs will therefore reflect the amount necessary to transform the existing station design to the alternative station design.

9.8. 1.3 Environmental Considerations of Existing Design 9.8. 1.3. 1 Heat Discharge to Water Body The heat rejected from Unit 1 through its once-through cooling system is approximately 4 x 10~ Btu/hr. Effects of this discharge on the oxygen availability, commerical and sport fishing, fish migration, and wildlife are discussed in detail in Section 9.5. 1.2. 1.

9.8.1.3.2 Effects of Intake Structure on Water Body This area of environmental concern -

is discussed in detail in Section 9.5.1.2.2.

9. 8-3

9.8.1.3.3 Chemical Di,scharge to Water Body Detailed descriptions of the chemical treatment systems are contained in Section 3.7.

The circulating water discharged from Unit 1 consists of lake water and the intermittent chemical effluent from the makeup deminexalizer associated with the makeup water treatment system.

No biocides are added to the circulating water for condenser treatment. The concentrations of chemicals that are released from the discharge system are listed in Table 5.3-1 along with the natural lake concentrations and the applicable drinking water stahdards. These concentrations are only slightly above ambient lake concentrations, and are diluted approximately 10 times with lake water at the boundary of a 300-acre area surrounding the discharge point. Furthermore, these concentrations could occur only for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> once every eight days when the demineralizers are regenerated. When no chemical effluent is mixed in the circulating water, the discharge concentrations are the same as that of the lake. For these reasons,'o adverse effects are anticipated on people, aquatic biota, associated wildlife, or on water quality.

The sanitary waste from Unit 1 is treated in a system, described in Section 3. 8, that has been designed to comply with New York State regulations for sanitary wastes. No detrimental effects are anticipated on people, aquatic biota, associated wildlife or water quality from the releases of the sanitary treatment facility.

9.8.1.3.4 Consumption of Water The systems of the existing station discharge to the lake and an exact determination of water consumption has not been made.

is expected that the water consumption principally due to It evaporation would not exceed 0.02 cfs or approximately 10 gpm, as discussed in 'Section 3.4. This amounts to about 5.0 x 10~ gallons of water consumed per year. This is a small amount compared to the volume of Lake Ontario which is about 4.4 x 10i~ gallons. Therefore, no impact is expected on water quality or water users.

9.8.1.3.5 Chemical Discharge to Ambient Air Nine Mile Point Unit 1 is not a potential source of air contamination since it does not utilize the combustion of fossil fuels. The auxiliary heating boiler will be electrically fired and will not produce air contaminants. diesel generators will burn diesel fuel with 0. 7 percent orStandby less sulfur content and a negligible ash content. These diesels are used infrequently and are controlled so that ambient concentrations of contaminants are insignificant.

9 8-4

The once-through cooling system of the existing station does not release any particulate matter in the form of drift, and only a small quantity of gaseous radwastes is released from the stack.

These radioactive releases and their impact are discussed in Section 5.2. Also, the existing station has no source of odor that would be noticed beyond the site boundaries..

In conclusion, this station has a negligible effect on local air quality.

9.8.1.3.6 Salts Discharged from Cooling Towers This area of environmental concern is not applicable to the existing station design.

9.8. 1.3.7 Chemical Contamination of Ground water The existing power station has no releases to the ground from the chemical, sanitary, radwaste or cooling water systems.

Therefore, contamination of ground water is not expected to occur>>

9.8.1.3.8 Radiological Effects The existing liquid and gaseous radwaste systems are described in Section 3.6. The radiological effects and their determination are presented in detail in Section 5.2.

There is no contamination of ground water from the radioactive releases from Nine Mile Point Unit 1 as discussed in Section 5. 2..

9.8.1.3.9 Fogging and Icing The existing power station uses a once-through cooling system to reject waste heat from the station. This cooling method does not rely on evaporation or the transfer of sensible heat to the atmosphere, and therefore this station does not create a fogging or icing problem.

9.8. 1.3.10 Raising/Lowering of Ground Water Levels As previously discussed, all liquid systems are isolated from the ground, and no alteration of ground water levels has or is expected to occur.

9.8. 1 3.11 Ambient Noise The acoustic impact of Nine Mile Point Unit 1 is discussed in detail in Section 9.5. 1. 2. 11.

9. 8-5

9.8. 1.3. 12 Aesthetics The architectural description of the existing power station is presented in Section 3. 1 of this Environmental Report. Careful design and landscape treatment has been applied to enhance the aesthetic appearance of the station.

9.8. 1.3.13 Permanent Residuals of Construction Activity Construction activities have been completed since September, 1969. The existing facilities utilize approximately 45 acres of the 900 acre site for buildings, switchyard, and acess roads.

These areas are devoted to power generation and are not available for other uses. As previously discussed in Section to 2.2.1, this area was utilized as an artillery testing range prior station wildlife construction and therefore was of limited value as a habitat. Any terrestrial-species which would have previously utilized portions of the site now occupied, could still utilize the remaining 855 acres of the site which have not been altered by construction or station operation. It is considered that no permanent residuals of construction activity exist outside the area utilized by the facility. The details of any future construction activities as they may affect the environment due to additional modifications to the existing station design are discussed in Section 4. In addition, since there are no known archaeological sites in the area and the nearest National Historical site is in the City of Oswego, there is no impact on such sites.

9.8. 1.3.14 Combined or Interactive Effects There is no evidence that the combined effects of a number of impacts result in a total effect which is not adequately indicated by measures of the separate impacts.

9.8.2 Station Design Considered to Produce Minimum Water Impact An attempt has been made to identif y an alternative nuclear station design which would result in a minimum detrimental effect on the water body. This alternative design would employ the existing station as a base design. Either a natural draft or to mechanical draft cooling tower or a cooling pond could be used minimize impacts to Lake Ontario For this analysis a natural draft wet cooling tower was selected to cool the condenser cooling water since it would also limit other ef fects associated with the alternative cooling methods. The environmental chemical treatment system would use an evaporative system to treat wastes from the regeneration of the makeup water demineralizer.

9. 8-6

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The concentrated brine from this treatment would be stored in a brine pond and there would be no discharge to Lake Ontario of effluent associated with. the demineralizer regeneration wastes.

Discharges of radioactivity to air and water are improved by adding the proposed radwaste system modifications mentioned in Sections 3.6 and 9.5.3 to assure that all such discharges are well within the limits of 10CFR Part 20 and the proposed Appendix I to 10CFR Part 50 guidelines.

The benefits of this alternate station design are included in Table 9.8-1. The economic and environmental costs are shown in Table 9.8-2. The data included in Sections 9.5 and 9.6, "Alternative Cooling Systems" and "Alternative Chemical Effluent Systems~~ have been used in deriving the alternative design which results in minimum detrimental effects on the natural water body.

9 8.3 Station Design Considered to Produce Minimum Land/Air Impact An attempt has been made to identify an alternative nuclear station design which results in minimum detrimental effects to ambient air and land. This alternative design would be the same as the station design proposed for license request as described in Section 9.8.5.

The data included in Sections 3.6, 5.2, and 9.8.1 have been used in deriving the alternate design which results in the minimum detrimental effects on land and air. The quantified results appear in Tables 9.8-1 and 9.8-2.

9.8 4 Station Design Considered to Produce Minimum Overall Environmental Effect The two previous sections have attempted to identify station designs considered to produce minimum effects on air and land, and minimum ef fects on the water body. The design which is considered to produce a minimum impact on the aquatic environment uses cooling towers and an evaporative chemical discharge system.

These systems use appreciable land area and have several impacts on ambient air. As discussed drift may result in fogging and inicing with consequentcooling Section 9.5.3.2.9 tower effects on transportation and vegetation. Drift also contains salts which contribute to ambient air particulate concentrations.

The station design which is considered to produce a minimum effect on land and air retains both the existing once-through cooling system and the existing chemical effluent system, but incorporates the proposed modifications to the radwaste system, as described in Section 3.6.

The station design which would reduce environmental effects in one area of the environment may, in turn, produce effects on other areas of the environment. It is but a subjective judgment

9. 8-7

't as to which area of the environment is more signif icant.

Therefore no further attempt has been made to identify a design which results in minimal overall environmental effects.

9.8.5 Proposed Station Design for License Request The proposed station design for license request retains both the existing once-through cooling system and the existing chemical effluent system. The proposed station design to control radioactive discharges to the air and water consist of the modifications discussed in Section 3.6. These modifications assure that all such discharges are within the limits set forth in 10 CFR Part20 and the proposed Appendix I to the 10 CPR Part50 guidelines.

The benefits of the proposed station design are included in Table 9.8-1. The economic and environmental costs are shown in Table 9.8-2. -

The development of these benefits and costs are found in Sections 3.6, 5.2, and 9.8. 1.

9 8-8

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TABLE 9eS-1 BENEFIT DESCRIPTION ALTERNATIVE STATION DESIGNS NINE MILE POINT NKIZAR STATXON )T)IT 1 Report Date: June 1972 Station Design that Pzoduces Station Design that Produces Proposed Static> Design Existing Station Design Hin)znzs Water Dzpact Min)nun ~A)r lnpact for License Request ELec. Po>>er Pzoduced f> Sold: Industrial d> Gccnezcial<< 2.75 x 109 kv hr/yr 9.8.1.1 2.75 x 109 kv hr/yz 9.8.1.1 2.75 x 109 kv hr/yr 9.S.1.1 2.75 x lP kv hr/yr 9.8.1.1 Residential 1.24 z 109 kv hr/yr 9.8.1.1 1.24 z 109 )or hr/yr 9.8.1.1 1.24 x 109 kv hr/yr 9,S.1.1 1.24 z 109 kv hr/yr 9.8.1.1 Other Uses 0.55 x 109 kv hr/yr 9.8.1.1 0.55 x 109 kv hr/yr 9.8.1.1 0.55 x 109 kv hr/yr 9.8.1.1 0.55 x 109 kv hr/yr 9.8.1.1 Reliability Index 99 96)5 9.1 99.9615 9.1 99 9615 9.1 99 9615 9.1 Process Stean Sold none none Env)ronnental Enhances>cnt ) Recreation picnic areas 9.8.1.1 picnic areas 9,8 l,l picnic areas 9,8,1,1 picnic areas 9,8,1,1 Navigation stack is a visual cooling tover is a stack is a visual stack is a visual aid visual aid aid aid Air Quality: 3.7 z 107 lb/yr 9.8.1.1 3.7 z 107 lb/yr 9.8.1,1 3.7 x 107 lb/yr 9.8.1.1 3.7 z 107 lb/yr 9.8.1,1

~d Savings as an 610 )tW to 1.3 x 107 lb/yr 9.8.1,1 1.3 x 10 lb/yr 9.8.1 1 1.3 z 107 lb/yr 9.8.1.1 1.3 x 107 lb/yr 9.8.1.1 OQ. Fired Particulates 0.44 z 10 lb/yr 9.8.1.1 Oi44 z 107 lb/yr 9,8,1,1 0.44 x l07 lb/yr 9.S.1.1 0 44 z 107 lb/yr 9.8 1.1 Pover Station:

Education 25,000 PeoPIe/yr 9.8.1.1 25,000 pecpl\>/yr 9.8.1.1 25,000 people/yr 9.8.1.1 25,000 people/yr 9.8.1.1 Research $ 300,000 4300,000 Regional Gzoss Product $ 1>020>000/yr 9.8.1.1 $ 1>020>000/yr 9.8.1.1 $ 1>020>000/yr 9.Salmi $ 1>020,000/yr 9.8.1.1 9811 <<<<<< 9 8,1,1

~nt Local Taxes Other Benefits

$ 3 >000,000 6S onsite offsite 9.8.1.1 68 onsite offsite 9.8,1 1 9>8,1,1 68 onsite offsite 9.8,1,1 9.8.1,1 9,8,1,1 68 onsite offsite 9.8,1,1 9,8.1,1 Jobs 9.8.1.1 Jobs 9.8.1.1 Jobs Jobs

<<As ccobined in FPG Annual Report - Fuzz> 1

<<<<See Section 9.8.4 for discussion of station design considered to pzodnce the nin)nuu overall environuental istpact

<<<<<<Any increase in taxes is not >B>sntifiablc

TABLE 9 8-2 COST DESCRIPTIOH ALTEIQIATIVE STATIOH DESIGHS HIRE NIIZ POIHT HIXKZAR STATIOH IEIIT 1 Report Date: Jane 15rI2 Existing Station Design Station Design that Produces Nizdzzun Water Izrpact Nhdnrzz LangdAIr I~

Station Design that Produces Proposed Station Design for License Request SUBSYSTEMS z Alternative Cooling Systeu Existing Once~ Hatural Draft Cooling Tover Existing Once Through (2)

Ezisting Once (2) through Rahraste Systen (1) (3)

Alternative Chenical Effluent Systcn Existing Chenical Evaporative Chcnical Existing Chezdcal Existing Chazical Effluent tea Effluent ten Effluent tea Effluent, tera

$ 51r320r000 Sgr330r0cxrr"" p330rONZr~~

Population or Resource Affected

l. Heat discharged 1.1 Cooling capacity 4 z IO9 Btu/hr acre-ft 9.8.1.3.1 1 4 x 10 Btu/hr 2.2 acre-ft 9.5.3,2.1 4 x IO9 Btu/hr 3,000 acre-ft 9,8,1,3,1 4 z I09 Btu/hr 3,000 acre-ft 9.8.1 3ol to vater body 3,000 1.2 Aquatic biota ccczzercial lr500 lb/yr fish 9.8.1.3.1 ccenercial fish -

4 lb/yr 9,5 3,2 1 ~iai 1,500 lb/yr fish- 9,8,1,3,1 ccanercial fish lr500 lb/yr

- 9.8,1.3.1 sport fish- sport fish-~ sport fish- sport fish insignificant" negiigible insignificant insignificant 1.3 Nigratozy fish no inyaiznent 9.8.1.3.1 no I~ant 9.5,3.2.1 no Inyairnent 9.8.1.3.1 no inyaiznent 9.8.1.3.1

2. Effects on vater 2.1 Prinary yzoduccrs 6.7 x 10 lb/yr 9.8.1.3.2 1.5 x 10 lb/yr 9.5.3.2.1 6.7 x 10 lb/yr 9.8.1.3.2 6+7 x lb/yz' Bolo3o2 body of intsIce 4 conscaers structure aud

-" -e condenser 2.2 Fisheries lazvae -" 9.8.1.3.2 larvae - e 9o5,3,2 1 Iarvae 9.8,1,3,2 larvae 9.8.1.3.2 cooling systen adults fev adults - very fev adults - fev adults - fcv

3. Cbenicel 3.1 People no adverse effect 9.8,1.3.3 no adverse effect 9.6.2.2.1 no adverse effect 9.8.1.3.3 no adverse effect 9.8.1.3.3 discharge to vater body 3.2 Aquatic biota no adverse effect 9.8.1.3.3 no adverse effect 9.6.2.2.1 no adverse effect 9.8.1.3.3 no adverse effect 9.8.1.3.3 3,3 Water quality no adverse effect 9.8.1.3.3 no adverse effect 9.6.2.2.1 no alverse effect 9.8.1.3.3 no adverse effect 9.8.1.3.3 chcnical

4. Consusytion of 4.1 People 5 0 z lit gal/yr 9 Bele3e4 4 8 x 109 gal/yr 9 5 3,2,4 5,0 z 10 gal/yr 9.8.1.3.4 5.0 x 106 gal/yr 9.8.1.3.4 vater 4.2 Proyerty 5.0 z gal/yr 9.8.1.3.4 4,8 z 109 gal/yr 9.5,3,2,4 5,0 x 10 gal/yr 9,8,1,3,4 5.0 z 106 gal/yr 9.8.1.3.4

5. Chcnicel 5.1 Air quality insignificant 9.S.1.3.5 drift&.05 lb/nin 9.5.3.2.5 insignificant 9.8.1.3.5 insignificant 9.8.1.3.5 discharge to chcnical of solids cabient air 5.2 Air quality 9.8.1.3.5 9,5,3,2,5 none 9.8.1.3.5 none 9.8.1.3.5 odor

6. Salts discharged 6.1 PeoPle nct applicable 9.8.1.3.6 zzinor effect 9,5,3,2,6 not applicable 9.8.1i3.6 not apylicable 9i8,1,3,6 fzcn cooling tovers 6.2 Plants not applicable 9.8.1.3.6 ninor effect 9.5.3.2.6 nct applicable 9.8.1.3.6 not ayylicahle 9.8.1.3.6 6.3 Property resources not applicable 9.8.1.3.6 niner effect 9.5.3.2.6 not apylicable 9.8.1.3.6 not applicable 9.8.1.3.6

7. Chenical 7.1 People no effect 9.8.1.3 7 no adverse effect 9.5.3.2.7 no effect 9.8.1.3.7 no effect 9.8.1.3.7 contenination of gzcrund vater 7.2 Plants no effect 9.8.1.3.7 no adverse effect 9.5.3.2.7 no effect 9.8.1.3.7 no effect 9.8.1.3.7 excludi salt

/"

TABIZ 9oS-2 (COSY'D)

COST XESCRIPTIOH ALTERHATIVE STATIOH DES IGHS HIRE IGIZ FOIE HOCIZAR SIATIOH IIIX' Station Desfgn that Produces Statica Design that Produces Propose4 Station Desiga Existing Statfca Design Mafmm Water Impact Minie'AfrImpact Population or Resource Affected Radfonuc lides 8.1 People-external 0.02 mcs/yr 9.8,1,3,8 0.0007 nrem/yr 9.5.3.2.8 0.001 mern/yr 9.8,1 3 8 0 001 mern/yl 9~8' y3 8 discharged to contact max individual msx fndf vidual max iadividual max iadividual vater body 8.2 People-fngestfca 2oO mcm/yr 9.S.1.3.8 0.008 mern/yr 9.5.3.2.8 0.01 mcm/yr 9.8.1.3.8 0.01 mern/yr 9.8.1.3.8 max fadfvfdual max iadfvidual max fadfvfdual max in4ividual vbole body dose vhole body dose vhole bo4y dose vbole body dose 28 ares/yr 0+23 mern/yr 0.35 mern/yr 0.35 mern/yr max individual GIT max individual GIT max fn4fvidual GIT max fndividual GIT 8.3 Primary consumers external 9.8.1.3.8 exteraal 9.5.3.2.8 external 9.8.1.3.8 external 9.8.1,3,8

.53 mrads/yr 0.02 mads/yr 0.03 mads/yr 0.03 mradk/yr interaal fnteznal internal internal 120 mradk/yr 8 mads/yr 12 mrads/yr 12 mrads/yr 8.4 Fish external 9.8.1.3.8 external 9+5o3.2+8 external 9.8,1,3,8 external 9,8,1,3,8

.27 mrads/yr 0.01 m sds/yr 0.015 mads/yr 0.015 mads/yr internal inta raal fnte mal fnte ruad 400 mrads/yr 7+3 mads/yr 11 msds/yr ll mra4s/yr

9. Rcdionuc fides discharged to 9.1 People-external contact 30.6 ~hr 9.8.1.3.8 0.028 mads/hr 9.5.3.2.8 0.028 madk/yr 9.8.1.3.8 0.028 mads/yr ~ 9.8.1.3.8 suhfent air 9.2 People-ingestfon neglfgible 9.8.1.3.8 neglfgfble 9.5.3.2.8 neglfgible 9.8.1.3.8 negligible 9.8.1.3.8 9.3 Plants and anLals 30.6 mern/yr 9.8.1.3.8 0.028 mern/yr 9.5.3.2.8 0.028 nrem/yr 9.8.1.3.8 0.028 ares/yr 9.S.1.3.8 Rcdfonucffdcs IOrl People neglfgible 9.8.1.3.8 negligible 9.5.3.2.8 negifgfble 9.8.1.3.8 negUgiblc 9,S,1,3.8 contsmfnatf on of ground vater 10.2 Plants sad anfnals ncgligfble 9.8.1.3.8 negligible 9.5.3.2.8 negligible 9.8.1.3.8 negligible 9.8.1.3.8

11. Fogging 4 11.1 Ground transportation no effect 9.8el+3,9 no effect 9 5 3 2 9 no effect 9.8.1.3.9 no effect 9e8,1,3 9 icing 11.2 Air trsnsportatfon no effect 9,8,1,3,9 no effect 9.5.3.2.9 no effect 9.8.1 3,9 no effect 9.8.1.3.9 ll 3 Hater transportation no effect 9o8,1,3,9 no etfect 9.5.3.2.9 no effect 9.8,1,3.9 no eftect 9.8.1.3.9 11.4 Plants no effect 9.8.1.3.9 iasfgnificant 95329 ao effect 9,8,1,3,9 no effect 9.8.1.3.9 ottsfte

12. Raising/ 12.1 People no alteration 9.8.1.3.10 no alteration 9.5.3.2.10 no alteration 9.8.1.3.10 no alteratioa 9.8 1,3,10 lowcrfng of ground vatcr 12,2 Plants no alteratfoa 9.S.1.3.10 no alteration 9.5.3.2.10 no alteration 9.8.1.3.10 ao alteratioa 9.8.1.3.10 levels

13. Jhbfcat noise I3.1 People 4H5 dBA- 9 8 1.3.11 45<5 dBA- 9 5+3 2 11 45%5 dBA- 9,S,1,3,11 4545 4BA- 9 8.1.3 11 0 houses 10 houses 0 houses 0 houses

14. Aesthetics lb.l Appearance not sfgafffcatly 9.8.1.3.12 visible cooling 9.5.3.2.12 not sfgnificantly 9.8.1.3.12 aot significantly 9.8.1.3.12 alter site toker alter site alter site appearance appcaraacc appearance

TARLE 9 8 2 (CORTrD)

COST DESCRIPTIOR ALTERRATIVE STATICS IKSIGRS Station Design that Produces Station Design that Pzoduces Proposed Station Design Existing Station Design Mnimun Water Impact )Gnhzum Land/Air Impact for License Request Ike

15. Permanent 15.1 Accessibility of Ro impact 9,8,1,3.13 no hrpact 9.5.3.2.13 9.8ilo3,13 9+8.lo3+13 residuals of historical sites construction activity 15.2 Accessibility of no impact 9.8.1.3.13 no impact 9.5.3.2.13 9.8.1.3.13 no impact 9a8.1.3+13 azeheological sites 15.3 Setting of no izrpsct 9'8,1,3 13 no impact 9.5.3.2 13 no impact 9,8olo3e13 9.8e1.3o13 historical sites 15.4 Land use 45 acres 9.8.1.3.13 45 acres plus 9.5.3.2.13 45 acres 9,8,1+3.13 9.8.1.3.13 2.3 acres for the tower 15.5 Pzoperty negligible 9.8.1.3.13 negligible 9 5.3.2.13 negligible 9.8.1.3.13 negligible 9,8.1.3.13 15.6 Plood contzol not, a problez 9.8.1.3.13 not a pzobles 9.5 3.2.13 not a problez 9,8 1.3,13 not a pzoblez 9,8.1.3.13 15.7 Erosion control protectica is 9.8.1.3.13 protection will be 9.5.3.2.13 protection wm. be 9.8.1.3.13 protection will be 9.8.1.3.13 provided pzovide4 pzovided pzovide4 (1) Original radrraste systea design describc4 in Section 3.6 (2) Upgraded radwaste systea design which meets 10 CPR PARl 50, Appen4ix I, for the once~ cooling systes describe4 in Section 3.6 (3) Radwaste system design which meets 10 CPR, PART 50, Appendix I, for a natural draft cooling tower systez described in Section 9.5.3 "A qualitative discussion of environmental cost is contained in the a~to part of Section 9.0

~Refer to Section 9.8.4 for a discussion of station design considere4 to produce the minimum overall envtrozmental impact a~Total present value of upgrade4 radwaste syst<<a base4 on a 20.1'$ fixed charge rate, a 6.5I( annual escalation factor, a 9.6'ost of capital, au4 an amortization over the

~ining 18 year economic life of the station.

"~~Doses for the Existing Station Design only are base4 on the identified radionuclides zeleased fzom the Rice Nile Point Unit 1 actual 19(l operating data.

LONG-TERM EFFECTS OF STATION OPERATION The local "short-term~~ use of the overall project involves of the station area over the life of the station. Niagara the'se Mohawk believes that there are no negative, cumulative, long-term effects from station operation.

The investigations and studies of the environmental effects of station operation are detailed in Section 5.5. It is believed, based upon the results of these studies, that there will be no injurious effects to aquatic species distribution or lake bottom productivity nor will the water quality be impaired as a result of continued station operation.

The heat energy content in the discharge water decays continuously as the energy transfers to the atmosphere and any cumulative heat effects of Nine Mile Point Unit 1 effluent alone it will be very small. In Appendix H, is computed that the total existing and expected thermal discharges into Lake Ontario from all sources within the next 10 years, including power plants, and sewage treatment plants, will produce an stations,'ndustrial overall lake temperature rise of 0.08 F over the original ambient. Long-range projections of heat discharge indicate that the overall lake temperature rise will increase to

'ndisturbed 0.28 F by the year 2000.. Superimposed on these long-range projection values will be an additional 0. 1 F rise due to flow into the lake at the western end. If only the eastern end of the lake is considered, the 'existing and proposed discharges will produce a temperature rise of 0. 17 F over the next 10 years, and a projected temperature rise of 0.60 F by the year 2000..

In considering thermal discharge effects, the question of long-term influence on the fish and other aquatic life is often raised. It is not expected that changes in fish population or condition accrue from the thermal discharge since the temperature increases are small and localized.

In considering long-term effects upon water quality Lake Ontario water is returned to the lake in essentially the same condition as that in which it is withdrawn.

The'se of the land on which the Nine Mile Point Unit is located may be considered a short-term use for the normal life expectancy of a nuclear generating station.

, 10. 0-1

Concerning the maintenance and enhancement of long-term productivity of the. land and adjacent water, the present use of the site for power generation purposes does not preclude its use for other productive short- or long-term purposes in the, future..

Among these are: the possibilities of development for recreational or'residential use, both of which are. impractical. or unsuitable.

at present..

The resources of water and land remain essentially unimpaired

'egardless of -the short-term use as a power generating station..

Beneficial uses of the area for industrial purposes will be .

reduced only to the extent that the, assimilative .capacity of the environment is reduced.

Niagara Mohawk is of the opinion that the range of beneficial uses of the surrounding environment is not narrowed by the project. Little change, if any, is anticipated with respect to wildlife in the vicinity, or the general ecosystem..

10 0-2

SECTION 1 1 IRREVERSIBLE AND IRRETRIEVABLE COMMITMENTS The operation of the Nine Mile Point "Nuclear Station Unit 1 has been conducted to minimize the irreversible and irretrievable-commitments of resources, materials, land, and lake bottom As described in Section 4, modifications to the station will have no permanent environmental effects from construction of the radwaste building.

With respect to lake bottom, the intake and discharge structures, occupying a few thousand square feet, would probably remain after retirement of the station. Although they could be removed, it would most likely be decided that the work required to remove them would have more of an impact on the environment than to leave them as they were installed.

Land used for the station could conceivably be reclaimed by removal of all buildings and other related structures, such as return to its natural transmission towers. The land would then state. The small area (about three acres) occupied by the -

reactor facilities could be placed on permanent restriction access and, therefore, would be irretrievably lost to the community.

Most of the materials used to construct the station would be for all practical purposes irretrievable. Except for the concrete, which would be considered lost for anything but sanitary land fill or similar use, most of the materials could be used elsewhere for their intended purpose. However, the cost of retrieving them would usually far exceed the purchase price of new materials. All structural components ofactivation the reactor facilities will have become radioactive through and contamination and, as such, will be irretrievably lost. These components and other radioactive wastes produced and accumulated throughout station operation will be buried on a permanently committed offsite land area licensed and approved by the AEC for disposal of radioactive waste.

The station presently uses approximately 527 kilograms per year of Uranium-235. This includes the depletion of 392 kilograms per year of U-235, the recovery of 135 kilograms per year of U-235, and the production of 112 kilograms per year of fissile plutonium.

Studies proposed and measures taken in the design of the facility for the protection of the terrestrial and aquatic ecosystems will assure that the impact on these communities will not be irreversible.

11. 0-1

H SECTION 12 ENVIRONMENTAL APPROVALS AND CONSULTATION The applicant has continued to maintain both formal and informal contacts and dissemination of information with concerned parties -

since the outset of the Nine Mile Point Nuclear Station project.

Particular emphasis has been placed upon consultation with regulatory agencies at Federal, State and local levels regarding the various permits and approvals necessary to the construction and operation of facilities at this site.

The major approvals obtained as the result of these consultations and approvals are listed in Table 12-1 and attached as Appendix G.

As part of the continuing program of auditing facility operations specific information regarding station performance and environment monitoring is routinely collected. This data has been made available to interested governmental agencies for their information and use.

Niagara Mohawk is currently seeking two additional authorizations connected with the operation of this facility:

(1) N. Y. State Water Quality certification (Section 21(b) of Federal Water Pollution Control Act as amended)

Date request filed: June 29, 1971 and October 15, 1971 (2) U. S. Army Corps of Engineers "Refuse Act~'ischarge permits (Section 13, 1899 River and Harbors Act)

Date application filed: June 29, 1971 and September 30, 1971 Application number assigned: 070/OX2/2/000/174 July 26, 1971 EPA and Corps of Engineers review and application returned: November 17, 1971 Application revised and resubmitted: June 1972 12.0-1

r Table 12-1 Regulatory and Review Procedures Documents Title of Authorization, Permit License A royal etc. Source. of-Issue Date of Issue-Installation of Temperature U.S. Corps of November 1962 Measuring Devices in Lake Engineers - U.S.

Ontario Coast Guard Installation of Submerged U.S. Corps of August, 1 96 3 Current Meters in Lake Engineers U.S.

Ontario Coast Guard Construction Permit- U.S. Army Corps October 1964 Circulating Water of Engineers Syst: em Intake and Discharge Tunnels Corps of Engineers Con- U.S. Coast November 1964 struction Permit Intake- .Guard Discharge Structures, Tunnels, Shoreline Pro-tection Cooling Water Discharge New York State April 1965 Permit Dept. of Health-Bureau of Water Resources Construction Permit- U. S. Atomic April 1965 Nuclear Station and Energy Commis-Associated Facilities sion (CPPR-16)

I Sanitary, Sewage Disposal New York State May 1965 System Dept. of Health-Bureau of Water Resources Stack Effluent Discharge New York State April 1966 Permit Dept. of Health-Air Pollution Control Board Approvals of Stack Federal Aviation October 1966 Construction Administra tion, U.S. Dept of Transportation License to Possess and Use U.S. Atomic June 1967 By-Product Material Energy Commis-sion 12.0-2

License to Possess and Use U.S. Atomic August. 1967 Special Nuclear Material Energy Commis-sion Provisional Nuclear Station U. S. Atomi c August 1969 Operating License (DPR No. 17) Energy Commis-sion Amendment No. 2 to Provisional U.S. Atomic April 14, 1971 Operating License No. DPR-17 Energy Commis-sion Transmission Line Highway New York State December 6, 1966 Crossing Permit Department of Public Works Transmission Line Harge New York State April 1, 1965 Canal Crossing Permit Department of Public Works 12.0-3

LIST.OF REFERENCES Reference

--No Power Authority of the State of New York, Environmental Report, Operating License Stage, James A. FitzPatrick Nuclear Power Plant, May.1971.

24 Personal communication, Mr., Gordon D'Angelo, New York.,

State Department of Transportation, Syracuse, New York.,

Referral by Robert Funk, State Archeologist, New York State Museum, Albany, New York.

34 Thorn, H.. C. S., Tornado Probabilities, Monthly Weather

~

Review (October-December 1963)..

4~ ~ Hubbs, C.. L., and Lagler, K..F., Fishes of the Great Lakes Region.. Cranbrook Institute of Science, Bulletin No .26 ( 1 958) 5 .Beeton, A. M., Eutrophication on the St. Lawrence Great Lakes., Limno logy and Oceanograph y, 10 (2): . 240-254 (1965) 6~ Beeton, A.M., Changes in the Environment and Biota of the Great Lakes, in <<Eutrophication: Causes, Consequences, Correctives.'! National Academy of Sciences, Washington, D C .pp .150-187 (1969) 70 Dambach, C.A., Changes in the Biology of the Lower Great Lakes., Proceedings of the Conference on-Changes in the Biota o f Lakes Erie and Ontario. Buffalo Soc. Nat.

Sci pp 1-17 (1969) 8 Federal Water Pollution Control Administration, Water guality Criteria, Report of the National Technical Advisory Committee to the Secretary of the Interior, April 1, 1968, Washington, D.C. (1968) .

9 Ferguson, R. G., The Preferred Temperature of Fish and their Midsumme r Distribution in Temperate Lakes and Streams.. J. Fish Res. Board Canada 15:607-624 (1958) .

10 Fry, F. E. J, In "Handbook of Physiology,<<Edited

~

'by D B. Bill, E. F. Adolph, and G. C. Wilbur. Amer ican Physiol. Soc., Washington, D.C. 715-728, (1964) .

Gibson, E. S. and Fry, F. E. J, The Performance of Lake and Oxygen Pressure. Can. J. drool. 32: 252-260, (1954) .

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12- Henson, E. B., A review of the Great Lakes Benthos Research. Publ.. Great Lakes Div., Univ. of Michigan, 14: 37-54 (1 96 6) .

13. Neil, J. H. and Owen, G.

~ .I! -

E., Distribution, Environmental 14 15.

Lakes.

R.

s Great Lakes Michigan, 11: 113-121 (1964) .

Herbst, Research Division, Univ. of P., Ecological Factors and Distribution of Midland Naturalists. 82 (1): 90-98 (1969) .

Brinkhurst, R.O., Changes in the Benthos of Lakes Erie and Ontario. Proceedings of the Conference on Changes in the Biota of Lakes Erie and Ontario. Buffalo Soc.

Nat. Sci. pp. 45-71 (1969) .

16. Great Lakes Laboratory, Interactions of Temperature and s

'uffalo, pp. 1-29 (1970) .

17. Federal Water Pollution Control Administration, Statement on Water Pollution in the Lake Ontario Basin, prepared for the National Resources and Power Subcommittee on Government Operations. Region 5, Rochester, New York (1966) .

18. United States Department of Interior, Fish and Wildlife as Related to Water Quality of the Lake Ontario Basin, A special report on fish and wildlife resources, Fish and Wildlife Service (1969) .

19. Final Safety Analysis Report (FSAR), Nine Mile Point Nuclear Station, (June 1967) 20 Storr, J. F., Limnology Study, Nine Mile Point, Lake Ontario, May 1963.

21 Kerr, J. E., Studies in Fish Preservation at the Contra Costa Steam Plant of the Pacific Gas and Electric Company. Fish Bulletin No. 92, Calif. Fish and Game, Sacramento (1953).

22 Weight, R. H., Ocean Cooling System for. 800 Mw Power Station. ASCE J. Power Div. PO6: 84 (1888): 1-22.

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c I

II ~

A

> *P

23. Adams, J. R., Thermal Effects and Other Considerations at Steam Electric Plants, Res. Report No. 6934. 2-68.

Pacif ic Gas and Electric Company, Department of Engineering Research (1968) .

24 ~ Zeller, R. W. and Rulifson, R.L., A survey of California Coastal Plants, FWPCA Northwest Regional Office, Portland, Oregon (1970) .

25- Bainbridge, R., The Speed of Swimming of Fish as Related to Size and to the Frequency and Amplitude of the Tailbeat. J. Exp. Biol. 35: 109-133 (1958) ..

26. Weaver, C. R., Influence of Water Velocity upon Orienta-tion and Per formance of Adult Migrating Salmonids.

Fishery Bulletin 63 (1)97-122 (1963) .

27. Exhibit E, Nine Mile Point Nuclear Station Unit 2 Applicant~s Environmental Report Construction Permit Stage Niagara Mohawk Power Corporation, Syracuse, New York 13202 (June 1972) 28 Alabaster, J.. S., Effects of Heated Discharge on Freshwater Fishes in Britain. In. "Biological Aspects of Thermal Pollution" Edited by P. A. Krenkel and F. L.

Parker. Vanderbilt Univ. Press, 354-370 (1969) .

29. Heinie, D. R., Temperature and Zooplankton, Chesapeake Sci ~, 10 (3/4): 186-209 (1969)

30. International Atomic Energy Agency, Radioactive Waste Disposal into the Sea, IAEA, Vienna, p. 137 (1961).

31 Panel on Radioactivity in the Marine Environment publication, Radioactivit in. the. Environment, National Academy of Sciences, p. 253 (1971) .

32 Eisenbud, M., <<Environmental Radioactivity, <<McGraw-Hill Book Co., New York, (1963).

33. Chapman, W. H., et al., Concentration Factors of Chemical Elements in Edible Aquatic Organisms, . UCRL-50564, (1968) .

34 Bratton, C. A., Census of Agriculture, Oswego County:

Department of Agricultural Economics, Cornell University, Ithaca, N.Y., October 1967 (A.E. Ext. 475-33), (1964) .

35. Dames and Moore Geotechnical Studies Report, Nine Mile Point Nuclear Station Unit 2 for the Niagara Mohawk Power Corporation (February 11, 1972) .

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/

36. Auerback, S., Nelson, D., Kaye, S., Reichle, D., and Coutant, C., Ecological Considerations in Reactor Power Plant Siting, IAEA-SM/146/53, (1970) .

37. Burnett, T. J., Health Physics, 18, p..73 (1970).

38 ~ International Commission on Radiological Protection.

Report of Committee II on Permissible Dose for Internal Radiation, 1CRP Pub. No. 2, Oxford, Pergamon Press.

(1959)

39. Code of Federal Regulations, Title 10, Chapter 1, Atomic Energy Commission Part 50, Licensing of Production and Utilization Facilities, Appendix D <<Interim Statement of General Policy and Procedure: Implementation of the National Environmental Policy Act of 1969 (PL91-190) "

(September 9, 1971) .

40. U.S. Atomic Energy Commission, "Scope of Reports with Respect to Transportation, Applicants'nvironmental Transmission Lines, and Accidents,<< (September 1, 1971).

41. U. S. Atomic Energy Commission, <<Draft Guide to the Preparation of Environmental Reports for Nuclear Power Plants," issued for comments and interim use, February, 1971.

American Society of Mechanical Boiler III,Engineers, 42 and Pressure Vessel Code, Section (1971).

43. Garrick, B. J., Gekler, W. C., Goldfisher, L., Shimizu, B., Wilson, J. H., The Effect of Human Error and Static Component F ailure on Engineered Sa fety System Reliability, HN-194, Holmes and Narver, Inc., Los Angeles, California, (November 1967) .

44. Design Basis for Critical Heat Flux in Boiling Water Reactors, APED 5286, General Electric Company, San Jose, California, (September 1966)

45. Horton, N. R., Williams, W. A., and Holtzclaw, J. W.,

Analytical Methods for Evaluating the Radiological Aspects of the General Electric Boiling Water Reactor, APED-5756, General Electric Company, San Jose, California, (March 1969) .

46. Slifer, B. C., and Hench, J. E., Loss-of-Coolant Accident and Emergency Core Cooling Models for General Electric Boiling Water Reactors; NEDO-10329, General Electric Company, San Jose, California, (April 1971) .

47 Garrick, B..J., Shimizu, B., Gekler W. C., Wilson, J. H.,

Collection of Reliability Data at Nuclear Power Plants, HN-199, Holmes and Narver, Los Angeles, California, (December 1968) .

48 Garrick, B. J., Gekler, N. C., Baldonado, O. C., Behrens, E. H., Shimizu, B., Classification and Processing of Reliability Data from Nuclear Power Plants, HN-193, Holmes and Narver, Inc., Los Angeles, California, (February 1968).

49 Failure Data Handbook for Nuclear Power Facilities, Vol. 1, Failure Data and Applications Technology, Vol. II, Failure Category Idenitifcation and Glossary, Liquid Metal Engineering Center, Revised, (June, 1970).

50.. Vandenberg, S. R., Reactor Primary Coolant System Rupture Study, Quarterly Report No. 22, GEAP-10 207-22, General Electric Company, San Jose, California, (July-September, 1970) .

51. Morgan, K.Z., Ionizing Radiation: Benefits Versus Risks.

Health Physics 17, p. 539 (1969) .

52. Hearings before the Joint Committee on Atomic Energy, "Environmental Effects of Producing Electric Power,~~

January 27-30 and February 24-26, 1970.,

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APPENDIX A INDUSTRIAL FIRMS IN OSWEGO COUNTY 1971

APPENDIX A INDUSTRIAL FIRMS IN OSWEGO COUNTY MINING Davies Sand 6 Gravel Co. Oswego Washed sand and gravel General Crushed Stone Co. Lacona Sand and gravel FOOD AND KINDRED PRODUCTS Borden~s Farm Products Mexico Milk processors (Div. of The Borden Co.)

B.W.B. Foods, Inc. Mexico Baked beans (Grandma Brown's Baked Beans)

Citrus Fruit Juice Co. Fulton Fruit juices General Foods Corp. Fulton Frozen vegetables (Birds Eye Div.)

McPhail Candy Co. Oswego Confectionery products, (Oswego Candy Co.) peanut butter The Nestle Co., Inc. Fulton Chocolate products TEXTILE MILL PRODUCTS Breneman, Inc. Oswego Window shade cloth, window shades, in-dustrial fabrics Columbia Mills, Inc. Minetto Book bindings, in-dustrial fabrics, artificial leathers APPAREL AND OTHER RELATED PRODUCTS Conn Knitting Mills, Inc. Oswego Knit sportswear and underwear Alma Foundations, Inc. Oswego Women's foundation garment Osted Manufacturing Co. Oswego Women's cotton dresses LUMBER AND WOOD PRODUCTS A. C. Duell Mexico Wood pallets Kenneth Fish Sandy Creek Sawing and planning mill Alfred Pierce Hannibal Sawmill Rayders Mill Williamstown Logging A-1

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,H JI

Whiting Hilton 6 Sons Orwell Ladders, wood dowels, rolling pins, crates Clifton D. Yerden Redfield Logging Webb Lumber Co. Bernhard's Bay Sawmill FURNITURE AND FIXTURES Blount Lumber Corp. Lacona Infant's bath equip-ment Wm. P. Curtis 6 Sons Richland Wood office, school and restaurant tables and chairs Webb-Way Wood Products Bernhard's Bay Hardwood products in-cluding wall "Plankets,"

bed slats, surveyor stakes, etc.

PAPER AND ALLIED PRODUCTS Armstrong Cork 'Co. Fulton Flooring, felts, fabricated industrial felts and gasket material Burrows Tissue Corporation Phoenix Tissue paper Container Corporation Fulton Corrugated shipping of America containers, paper products Hammermill Paper Co. Oswego Fine papers Schoeller Technical Pulaski Duplicating papers Papers, Inc.

Papertronics, Inc. Oswego Converted roll paper (Subsid. of Hammermill) products Robertson Paper Co. Fulton White and colored tis-(Subsid. of North End Paper Co.) sues Sealright Co., Inc., Fulton Sanitary single ser-Packaging (Subsid. vice paperboard, of Phillips Petroleum Co.) plastic-coated paper-board and all plastic packaging including the manufacture of packaging machinery to form, sterilize and seal PRINTING AND PUBLISHING Acme Plate Oswego Printing plates Bower Printing Co. Oswego Letterpress and off-set printing The Corse Press, Inc. Sandy Creek Newspaper, magazine, catalog, commercial printing Economy Printing Co. Oswego Commercial printing The Fulton Patriot, Inc. Fulton Newspaper, commer-cial printing A-2

0 Holstein-Friesan Sandy Creek Printing and publi-World, Inc. shing D. F. James Printing Co. Oswego Commercial printing Lincoln Printing Co. Fulton Commercial printing Mexico Independent, Inc. Mexico Newspapers, catalogs (Oswego County Weeklies)

W. P. Mitchell Printing Co. Oswego Commercial printing The Morrill Press Fulton Flexible packaging, printing and conver-ting Oswego Printing Co., Inc. Oswego Commercial printing Oswego Valley News Fulton Weekly newspaper Palladium-Times, Inc. Oswego Daily newspaper, letterpress and off-set printing The Phoenix Press Phoenix Letterpress and off-set printing Poison Press Fulton Commercial printing Photo Engraving Co.

'ontiac Oswego Photo engraving, flat and wrap-around Pulaski Democrat Publishing Pulaski Weekly newspaper, Co. commercial printing Todd Bros. Oswego Commercial printing CHEMICALS AND ALLIED PRODUCTS Everbrite Paints, Inc. Minetto Paints, varnishes, industrial finishes PETROLEUM AND COAL PRODUCTS Allied Chemical Corp. Fulton Bituminous concrete paving materials Logan Long Co. Fulton Asphalt slate shing-les, rool roofing, plastics and coatings, asphalt paints Tri-State Paint Co. Fulton Asphalt products for roofing and industrial use STONEi CLAY AND GLASS PRODUCTS Huron Portland Oswego Portland and masonry Cement Co., Inc. cement Marsellus Casket Co., Inc. Mexico Concrete vaults (Subsid. Marsellus Vault 6 Sales Co.)

Massaro Co., Inc. Fulton Blocks, sand and gravel Oswego Valley Con- Minetto Precast masonry forms structors, Inc.

A-3

PRIMARY METALS Alcan Aluminum Corp. Scriba Aluminum reroll and plate stock FABRICATED PRODUCTS Aluminum Products Corp. Fulton Metal stampings, drawn aluminum cans, tubes, screw caps and clo-sures, shield covers Coppexweld Steel Co. Oswego Flexible cables, fine (Flexo-Wire Div. ) sizes of copper covered steel wire, copper, bronze and other metals Foster Bros. Cutlery, Inc. Fulton Butcher knives and cleavers Fulton Boiler Works, Inc. Pulaski Steam boilers Fulton Sheet Metal Works Fulton Sheet metal fabrica-tion JSK Boiler Co., Inc. Oswego Boilers, heating and plumbing supplies, sheet metal fabri-cation Oswego Castings Corp. Oswego Aluminum permanent (Subsid. Oberdorfer molds, Foundries Inc.)

aluminum die cast-ings Pulaski Metal Products, Inc. Pulaski High speed and carbide rotary files Sectional Structures, Inc. Oswego Modular structures Williamstown Irrigation Williamstown Irrigation systems Inc. (p3. pe q pumps g f Et-tings), wheel chairs, walkers, canes, aluminum conveyors MACHINERY (except electrical)

Black-Clawson Co., Inc. Fulton Paper and plastics (Dilts Div.) machinery and static regenerative electric drives Bud-Air Co., Inc. Pulaski Air powered tree pruners, accessories and parts, compres-sors, air chain saws, unloaders, grease guns Car-Well Corp. Phoenix Machine shop, experi-mental work, special equipment A-4

Oswego Package Oswego Packaged steam gene-Boiler Co., Inc. rators (Cyclotherm Div.)

D. K. Machine Fulton production machining, 6 Tool Co., Inc. special machinery and machine shop Fulton Machine Fulton Precision, experimental 6 Tool Co tools, jigs, fix-tures, dies Industrial Precision Oswego Machine shop, cen-Products, Inc. trifugal pumps (Kingsford Foundry 6 Machine Works)

Lagoe-Oswego Corp. Oswego Machine shop, special machinery Leppert Machine Fulton Tools and dies, Tool Co., Inc. special machinery MacCordy Machine Tool Fulton Tools~ dies~ g z g 8 Die Corp. fixture, gages, special machinery Northern Steel Corp. Oswego Steel fabrication Fulton Manufacturing Div. Fulton Paper mill and labo-(RMP Corp ) ratory production machinery and con-verting equipment Oswego Sheet Metal Oswego Conveyors, belts, Works, Inc. screw feeders, ven-tilation components Phoenix Gage Co. Phoenix Machine works and gages Porter Cable Machine Co. Pulaski Concrete and mortar (Subsid. Speedmatic Research 8 mixers, firing pins Equipment Corp.) and assemblies Reydun Knife-Machine Co. Fulton Machine knives for pulp and paper, agriculture, steel and woodworking Sawyer Foundry and Machine Minetto vises, gray iron cas-Works ting, snowplow shoes West Side Machine Fulton Machine design, de-8 Tool, Inc. 'velopment and pro-duction Burton G. Cross, Inc. Phoenix Paper machine cylin-ders and dandy rolls PLASTICS AND RELATED PRODUCTS Elcon Plastics, Inc. Oswego Plastic signs Oswego Plastics, Inc. Oswego Silicone and rubber wax pads and miscel-laneous silicone moulded products Empire Sign Company, Inc. Fulton, plastic and metal signs A-5

MISCELLANEOUS MANUFACTURING INDUSTRIES Pearson Instrument Co. Pulaski Scientific instruments Pollution Abatement Oswego Incineration of liquid Services of Oswego, Inc. industrial waste Fulton Instrument Co., Inc. Fulton Clinical thermometers (Div of Will Ross)

INDUSTRIAL SERVICES There is a wide variety of industrial services available to Oswego County manufacturers provided by firms located within the County. Services include accounting, architecture, contracting (general and specialized), industrial oils and gases, business and management consulting, trucking and. other specialities.

In addition, Oswego~s position on the periphery of the Syracus-Onondaga County industrial complex provides rapid access to its many industrial service firms.

Prepared by:

Operation Oswego County, Inc.

22 West Van Buren Street Oswego, N. Y. 13126 A-6

A, 1' C

APPENDIX B INVENTORY OF GAME SPECIES IN OSWEGO COUNTY

APPENDIX B INVENTORY OF GAME SPECIES OSWEGO COUNTY Management Game Range Zones

~secies Abundance Potential. See. Fi re- B-1 Cottontail High popu- Good on extensively A, B and Rabbit lations Managed clear land Western C fluctuate Grey Squirrel Generally Limited to wood lots A, B and low locally containing beech, Western C high cherry and oaks Ringneck Generally Good on intensively A, more sparse Pheasant low locally cultivated row crop in B high land Ruffed Grouse High popu- Limited to clearing County-wide, lations edges and new hard- hunted mainly fluctuate wood forests on idle in C and D farm land Woodcock Moderate Limited Birds are County-wide locally migratory. Poor Stream valleys high pasture management and brushy attracts flight swamps birds in fall Varying hare High popu- Good Extensive C, D. An area lations conifer plantations of inte rmingling fluctuate concentrate hares with cottontail in winter rabbits occurs along Western C Water fowl High Good Population Highest in A 6 and habitat mana- B. Somewhat gement techniques more limited in are well established C Muskrats High Good Registered County-wide.

marsh program pro- Best habitat vides,for local in A and B management on pri-vate marshes

I' JCFFCNSON COUNTY OS'NCOO COU SANOT CNCCX J ONNCLL NINE MILE POINT

.NUCLEAR STATION gl".

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I OSWCOO COUIITY 1

ONCSIOAOA COUNTY FIGURE B-I GAME RANGE ZONE OSWEGO COUNTY

Management Game Range Zones

~secies. Abundance. Potential.'. See Fi re-B-)..

Mink Moderate Limited Population County-wide.

management possible Best habitat on marshes but stream in A and B populations limited by amount of good quality stream White-tailed Low Limited Deep snow County-wide.

deer ma jor limiting Best habitat C factor on Tug Hill. Most common, D People and dogs ma jor problem, elsewhere in county Beaver Moderate Good. Currently County-wide a county-wide nuisance problem.

High value fur bearer Red Fox Moderate Good. Current social County-wide.

attitude precludes Best habitat in good recreational cleared lands use. Low value fur bearer Bobcat Low Good. Current social D. As forests attitudes now permit develop in C, good recreational this should also use of this fine become optimal game animal Otter Low Limited. Dependent C and D upon good quality streams Fisher Low Limited to large C (increasing) tracts of nature forest Raccoon Moderate Limited. Prefers County-wide. Best swamp forests near habitat found in vegetable operations A and B in Oswego County.

Low value fur bearer B-2

Management Game Range Zones

~Secies Abundance- Potential See Fi ure B-1 Coyote Low Limited. Social at- Cand D titudes greatly pre-judiced. Easily trapped by skillful people but difficult to hunt. Mistakenly identified as deer predator dan-'erous B-3

~ p APPENDIX C INVENTORY OF HISTORIC'ATURAL, AND SCENIC SITES IN OSWEGO COUNTY

I

(

4

APPENDIX C INVENTORY OF HISTORIC (H) g NATURAL (N) g AND SCENIC (S) SITES Map Name or Description and Noi ~

~Xdenhih Town. Hicih~a Present- Use-Oswego City Oswego National Historic Site.

Library(H) Notable architecture and one of oldest con-tinually used city libraries in the country. Given to Oswego by Gerrit Smith in 1855.

Fort Oswego Main Built in 1755, first Ontario (H) entrance English. foothold in via East all Great Lakes region.

7st St. State historic site.

Just to the east is old military cemetery dating from French and Indian war.

Oswego Market Oswego Built in 1835, it is under consideration House (H) as a National Historic Site.

Fort Oswego Corner of Built by British in Oswego (H) West 1st 1727 and destroyed 6 Van by French in 1756.

Buren Site marked with Streets stone marker.

Oswego Oswego East 1st Oswego harbor is the Harbor(H) St most important port on the American side of Lake Ontario.

Here thrived a tremendous water commerce and an extensive milling industry in the latter half of the 19th century.

Map Name or Description and wo. - ~xodent~~ . Town" HicihHwa r. Present. Use-6 Fort Hastings US-11 at Fort was built by the Brewerton(H) north British to guard the side of supply route from Oneida Albany to Fort Ontario.

River Reputed outline of the fortification may be seen.

Battle Island Granby NYS- 48 Site of skirmish between State Park British supply force (H) and a French and Indian scouting force attempt-ing to cut off the forts at Oswego in 1756. Is now a State Park with 18-hole golf course.

Spy Island(H) Mexico NYS-1 04B Spy Island at the mouth of the Little Salmon River is the location of the grave of Silas Towne, Revolutionary War spy for General Washington.

Arthur Mexico Co. Rt. 16 Built about 1839 by Tavern (H) Alex Danby., Still in use as a tavern.

10 Allen-Conklin Mexico 5284 Neo-classical house House (H) Church in 1842 by Warren Allen, St Mexico still in use as a residence.

11 Chandler- Mexico North Georgian stone house Brown- Side built by Peter Roop- of Main Chandler in 1838, House (H) St. at Church still used as a residence.

St Mexico 12 Shubal and Mexico West Main Oldest house in Mexico.

Lucinda St. Built about 1811, now Alfred (exten- part of a larger House(H) sion) residence.

Mexico C-2

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Map Name or Description and No ~Identit Town Hicih~a Present Use-.-

13 Colosse (H) Mexico US-11 Town has the oldest church (still standing) in Oswego County.

Town is noted for its cheese.

14 Fruit Oswego US-104 Community contains grave-Valley West yard with burial place Community (H) of Dr. Mary Walker, noted feminist and winner of Congressional Medal of Honor for serving as a Civil War Nurse; and a house reputed to have been a station on the Underground Railroad aiding the escape of fugitive slaves.

15 Selkirk Richland NYS-3 Built in 1828 in expec-Lighthouse(H) tation of development of a major lake port at mouth of Salmon River.

Despite early lumber trade, permanent com-

.mercial growth never followed. Now a fishing, boating, and camping area.

16 County Court Richland Court 8 Built in 1819, rebuilt House(H) Jefferson and enlarge'd in 1859.

'Sts. i Still in use today, it Pulaski shares Court duties with Oswego Court House in Oswego, New York. One of only two existing dual Court House arrangements in New York State.

17 Village of Sandy Co.- Birthplace of I.J. Case, Lacona (H) Creek Rts. 48 6 inventor of the reaper 22 which revolutionized grain harvesting.

C-3

J II

Map Name or Description and Noe ~Ident it Town- Hicihwa r. present Use-18 George Scriba Constantia NYS-49 Built in Constantia during House(H) 1792 by Scriba, who had purchase 499,999 acres of public lands for

$ 1.00 an acre which later became Oswego County. He is credited with having done more to develop the region than any other man of the early days.

Frenchman ' Con stanti a Oneida Settled by Des Vatines Island (H) Lake Family from Prance in 1 mile 1791. At one time a north of resort linked by steam-South boat to Oneida Lake Bay Port.s.

20 Cleveland(H) Constantia, NYS-49 Village with a thriving glass industry in the old days. Cleveland glassware is now in demand by collectors.

21 Little Hastings Co A tiny community settled Prance (H) Rts. 84 6 by a colony of people

'37 from Prance. Interest-ing cemetery located there.

22 Rail City(H) Sandy NYS-3 One of the nation's Creek most complete railroad museums.

23 Van Buren Volney NYS-57 John Van Buren, cousin House and at Van of Martin Van Buren, Van Buren Buren Dr. his wife and four sons Tavern (H) built tavern and brick neo-classifical struc-ture on Oswego River Shore at Fulton, New York in 1796. Second family to settle in Fulton.

I

~ ~

Map Name or Description and No. ~Identat Town HiciHhwa ~ Present Use 24 Tug Hill(N) Redf ield, Co. Rt. 17 Heavily forested low hills Boylston, and ridges over 1,000 ft Orwell and in elevation. This is Williams- the ultimate in wilder-town ness for many people and abounds with numerous species of wild birds and animals.

25 North and Sandy Ct Rt 15 Long, narrow strip of South Creek undeveloped sand beach (Ni S) separates North Pond from Lake Ontario.

26 Kasoag Lakes Williams- Co. Rt. 30 Scenic series of small town lakes.

27 Salmon River Orwell Falls Road Picturesque waterfalls Falls(S) known to be higher than Niagara Falls.

28 Mad River Redfield Picturesque water falls Falls(S) in undeveloped wilder-ness area.

29 Beaver Schxoeppel Barnard 400 acres of developed Meadows Road muckland. Especially Muckland scenic to people who Region(S) have not seen large areas of this rich black soil.

30 Happy Valley Parish, NYS-126 The 8,620 acres are 75%

Game Albion, covered with hardwood Management Williams- and conifer forest. The Area (N) town remaining acreage is and Amboy maintained open fields, green strips, managed wildlife marshes, and ponds. Many species of wildlife are present.

C-5

Map Name or Description and NO4 ~1dentit Hicih~a. Present. Use.

31 Little John Redfield Ct. Rt. 17 The 8,02 0 acres are 90$

covered with hardwood Game and Management Boylston and conifer forest.

Area (N) The remaining 10$ of the acreage is brushy fields, old beaver meadows, and swamps.

Many species of wildlife are present.

32 Three Mile West Monroe Toad The area consists of 2,300 Bay Game and Harbor acres of swamp forest, Management Constantia Road old field, 500 acres of Area (N) formerly cleared muck-land and open marsh..

The area will soon be managed intensely for waterfowl production.

33 Peter Scott Schroeppel. Swamp Road Several hundred acres of Swamp(N) undeveloped marshland.

C-6

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l.OSWEGO GOINTY ONONOAGA GOLNITY )i / ~ CAATtIOA l9H Litt FIGURE C-1 OSWEGO COUNTY SHOWING HISTORICAL, NATURAL OR SCENIC SITES

'\

APPENDIX D METEOROLOGICAL DATA SUMMARIES AT NINE MILE POINT NUCLEAR POWER STATION

NNW NNE NW NE WNW ENE 30o/o 20'/o" I0% 707 A L W/rVD JANUARY WSW ESE SW SE SSW SSE M 'I I

l-

- IO MPH 20 MPH 2I-IOO MPH

'NW NNE NW NE WNW ENE 30%

20%

I0% TOTA/ W//I/D FEBRUARY WSW ESE SW SE SSW SSC FIGURE 0" I NOTE: AVERAGE WIND ROSES NINE MILE POINT WEATHER DATA JANUARY 6 FEBRUARY l963- l964 N I AG A RA MOHAWK POWER COR PORATI 0 N

I NNW NNE NW NE WNW ENE 30%

20%

l0% TO TA L JVIND MARCH WSW ESE SW SE SSW SSE M I-I-

IO MPH I 20 MPH 2I - IOO MPH NNW NNE NW NE WNW ENE l0%

20% 30'OTA L WIA'D APRIL WSW ESE SW SE SSW FIGURE D" 2 NOTE! AVERAGE WIND ROSES NINE MILE POINT WEATHER DATA ~ MARCH 6I APRIL l963-l960 NIAGARA MOHAWK POWER CORPORATION

~ I NNW NNE NW NE WNW ENE 30o/o 20 /o I0% TOTA L O'IND W

MAY WSW ESE SW SE SSW SSE M 'l I

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- IO MPH 20 MPH 2l-IOO MPH NNW NNE NW NE WNW ENE 30%

ZOo/o IO'/ TOTAL lVIND JUNE WSW ESE SE SSE FIGURE D-3 NOTE: AVERAGE WIND ROSES NINE'ILE POINT WEATHER ~A A MAY 6I JUNE l963-I964 NIAGARA MOHAWK POWER CORPORATION

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NNW NNE NW WNW ENE 30%

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I0% TOTA L Jf'IND JULY WSW ESE SW SE SSW SSE IO MPH I I - 20 MPH 2I - IOO MPH NNW NNE NE WNW ENE 30 ~/o 20%

IO / TOTAL iYIND AUGUST WSW ESE SW SE SSW SSE'OTE:

FIGURE D"4 AVERAGE WIND ROSES NINE MILE POINT WEATHER OATA JULY 6I AUGUST I963- I964 NIAGARA MOHAWK POWER CORPORATION

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NNW NNE NW NE WNW ENE 50%

20o I 0% TOTAL WIND SEPTEMBER

'SW ESE SW SE SSW SSE R 'I I

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20o I0% TOTAL WIND OCTOBER WSW ESE SW SE SSW SSE F I GUR E D" 5 NOTE: AVERAGE WIND ROSES NINE MILE POINT WEATHER DATA, SEPTEMBER 6 OCTOBER l965"l964 NIAGARA MOHAWK POWER CORPORATION

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NNW NNE NW NE WNW ENE 30oI 20%

104/, TO TA L WIND NOVEMBER WSW ESE SE

,SW SSW SSE I- 10 MPH I I 20 MPH 21-100 MPH NNW NNE NW NE WNW ENE 30 oIo 20oIo 10 oI TOTA L WIND DECEMBER WSW ESE SW SE SSW SSE F IGURE D-6 NOT c.. AVERAGE WIND ROSES MILE POINT WEATHER DATA. NOVEMBER 6 DECEMBER l963" l964 NIAGARA MOHAWK POWER CORPORATION

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NINE MILE POINT WEATHER DATA F I GURE 0" 7 AVERAGE DIURNAL LAPSE RATES NIAGARA MOHAWK POWER CORPORATION

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NINE MILE POINT WEATHER DATA F I GURE 0-8 AVERAGE D I U R N AL LAPS E R ATES NIAGARA MOHAWK POWER CORPORATION

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NINE MILE POINT WEATHER DATA F I G URE D-9 AVERAGE DIURNAL LAPSE RATES NIAGARA MOHAWK POWER CORPORATION

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NINE MILE POINT WEATHER DATA FIGURE 0-II AVERAGE DIURNAL LAPSE RATES NIAGARA MOHAWK POWER CORPORATION

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0 2 4 6 8 IO I2 I4 I6 I8 20 22 24 HOURS DECEMBER 62- 63 December data based on 62 plus 63 data

( 64 data unovaItabte because of Instrument malfunction)

NOTE:

NINE MILE POINT VjtEATHE R OATA F I GURE D-I2 AVERAGE DIURNAL LAPSE RATES NIAGARA MOHAWK POWER CORPORATION

0 APPENDIX E PLANT AND ANIMAL SPECIES OBSERVED AT NINE MILE POINT NUCLEAR POWER STATION

APPENDIX E Plants and Animal Species Observed at Nine Mile Point Nuclear Power Station PLANTS Abandoned. Pa stures.a d Orchard-milkweed chicory buttercup (Ranunculus sp.)

daisy (Chr santhemum-3.eucanthenum Queen Anne~s lace (Dances carota) goldenrod aster (Aster- sp.)

ragweed thissel L

(Cirsium sp.)

pokeweed purple nightshade (Solanum dulcamara) blackberry raspberry (Rubus sp )

yarrow (Achillea millefolium) lilac ~Serio a vulcuaris) hawthorn poplar (~Po ulus sp.)

apple ~prus malus) pear (~prus ~cmmunis) red osier dogwood (Comus stolonifera) scotch pine burdock (Arctium ~la a) red clover (Trifolium ~ratens foxtail (Setaria-sp.)

orchard grass s staghorn sumac (Rhus ~thing) strawberry Over rown land The previously mentioned plants are being dominated by the following woody species red cedar alder (Alnus sp. )

hawthorn Poplar (~Po ulus. sp.)

staghorn sumac (Rhus ~thing) apple (~prus ~mlus) pear (~prus communis)

E-1

willow arrowood meadowsweet groundpine grape (Salix. sp.

te'-1 (Viburnum sp-)

~

sp

)

)

'Vitis Northern hardwood forest.

Tr ees white birch yellow birch (Setula ~utes) black cherry (Prunus. serotina) hemlock (TTsu aa canadensis) white ash black ash (Fraxinus nina)

~

beech Poplar (~po ulus. sp.)

red maple (Acer rubrum) sugar maple (Acer saccharum) red oak (()nereus rubra)

'"""')

musclewood Ironwood wallow t 'um (Salix sp.)

Ground cover five-leafed ivy partridge berry (Nitchella ~re ens) ferns (Polypodiaceae) poison ivy (Rhus toxicodendron) canada mayflower (Maianthemum canadense)

Powerline ri ht f wa Mullein goldenrod Queen Anne's L'ace (Daucus carota) red clover (Trifolum ~ratens) thissel (Cirsium sp.)

pin cherry (Prunus enns lvanica) staghorn sumac (Shun ~thing) red osier dogwood (comus stolonif era) raspberry (Rubus sp. )

blackberry (Rubus alle heniensis) hawthorn meadowsweet (~S irea latifolia) arrowood (~Viburnu ~s .)

rush (Juncus effusus) sedges (Cyperaceae) white snakeroot butter-and-eggs (Linaria ~lqaris) smartweed E-2

bracken fern sensitive ferm purple nightshade (Solanum dulcamera) purple loostrife pokeweed teasel cottail (~~ha latifolia) cardinal flower (Lcbelia cardinalis.

jewelweed K VERTEBRATE ANIMALS Birds red-tailed hawk sparrow hawk kildeer king bird baltimore oriole (zcterus )(albula.

yellow shafted flicker robin blue jay )

white-breasted nut hatch mourning dove goldfinch ~s inus tristis>

ruffed grouse (Bonasa-umbellus) purple grackle crow (Corvus. brach rh chos-red-winged blackbird Eastern meadowlark Mammals.

white-tailed deer Odocoileus vir iniana) cottontail rabbit S lvila s floridanus-chipmunk (Tamias ~triatus) vole

~Re tiles watersnake (Natrix ~si edan) snapping turtle grass frog (Rang ~iiens green frog (Rang clamitans)

E-3

N f

APPENDIX F STUDIES CONDUCTED AS PART OF NINE MILE POINT IAKE SURVEILLANCE

0 APPENDIX F STUDIES CONDUCTED AS PART OF NINE MILE POINT LAKE SURVEILLANCE 1964-1969 ~

Estimate of the Effects of Water Current July-September 1963 Patterns on the Placement of the Intake and Outflow Structures for the Proposed Power Plant at Nine Mile Point Supple-mental Report ¹1 Temperature Lake Water Samples April 1, 1964 Limnological Studies 1964 Limnological Studies 1964 (Summary) May 15, 1964 Dilution Factor May 28, 1964 Thermal Effects on Aquatic Organisms May 28, 1964 Physical Factors Affecting Zooplankton June-October 1964 Composition and Distribution in Eastern Lake Ontario Summary of Various Aspects of the Disper- December 1, 1964 sion of Higher Temperature Water and Thermal Effects on Aquatic Organisms Discussion of Dilution Factor at Oswego December 10, 1965 Water Intake Seasonal Fluctuations of Elements of the Zooplankton Population in Lake Ontario Limnology Report January 4, 1966 Limnology Report, Dilution of Effluent December 22, 1966 on Rise from Discharge Structure Biological Program December 22, 1965 Analyses of Dr. Storr's Chapter on January 7, 1966 Dilution Biological Studies Carried on at Nine Mile Point Area Temperature Variation with Depth June 26, 1968 F-1

~Re ort Date- of Stud Temperature Profile Nine Mile Point October 15, 1968 (Profile of the Temperature from May 1 to November 1 using data from 1964 and 1963 combined)

Summary of Reports and Studies Submitted August 4, 1969 to Niagara Mohawk Power Corporation Which Contain Material Related to Thermal Effects Summary of Ecological and Ecologically December 15, 1969 Related Studies in Lake Ontario Off the Nine Mile Point Nuclear Power Station Fish Distribution Study, Nine Mile December 15, 1969 Point, July 27, 1968 Ecological Benthic Study off Nine Mile December 15, 1969 Point, Lake Ontario, August 12-16, 1968 1970-Fish Net Study May 26-29, 1970 Yellow Perch Food Preference Analysis May 26-29, 1970 Nitrate and Total Phosphorus Study May 29, 1970 Fish Distribution Study May 28-29, 1970 Benthic Study June 26-28, 1970 Fish Distribution Study July 9-10, 1970 Fish Net Study July 8-11, 1970 Yellow Perch Food Preference Analysis July 8-11, 1970 Preliminary Temperature Survey July 22, 1970 Final Temperature Survey July 22, 1970 Fish Net Study August. 18-22, 1970 Fish Distribution Study August 18-20~ 1970 Yellow Perch Food Preference Analysis August 19~ 1970

~Re ort Date. of Stud Benthic Study August 14-20, 1970 Temperature Survey August 14 1970 Temperature Survey August 16~ 1970 Temperature Survey September 23, 1970 Temperature Survey October 21, 1970 Fish Distribution Study October 21-23, 1970 Fish Net Study October 21-24, 1970 Yellow Perch Food Preference Analysis October 21, 1970 1971 Fish Suneary Report March 13, 1971 Fish Food Preference Study June 1-2,611-12, 1971 Fish Net Study June '1-12, 1971 Fish Distribution Study June 1-12, 1971 Fish Net Catch Study June 29-July 2, 1971 Fish Food Preference Study June 29-July 2, 1971 Benthic Study July 7-12, 1971 Physiological Factors Affecting Zooplankton June-October 1964 Composition and Distribution in Eastern Lake Ontario Plankton Studies Nine Mile Point June 14-17 Nuclear Station Fish Net Catch Study Nine Mile Point August 17-20 Benthic Study, Nine Mile Point August 31 to September 1 Fish Distribution Study Nine Mile Point June 30 July 1 Fish Distribution Study, Nine Mile June 30-July 1 Point Plankton Study, Nine Mile Point July 1, 1971 F-3

~Re ert Date of Stud Plankton Study, Nine Mile Point Nuclear July 14-15, 1971 Power Station $1 Plankton Study, Nine Mile Point July 29, 1971 Fish Distribution, Nine Mile Point August, 17-19, 1971 Plankton Study August. 16'971 Fish Food Preference Study August, 17-20'97 1 Fish Food Preference Study November 2,4,6, 1971 Plankton Study, Nine Mile Point August 24 i 1971 Plankton Study, Nine Mile Point October 9, 1971 Fish Distribution Study, Nine Mile Point November 1,2 and 5, 1971 Three Dimensional Thermal Studies February 15, 1972

POWER AUTHORITY.OF THE STATE OF NEW. YORK.

REPORTS LISTED BY TITLE AND DATE Date. of Issue- Title.

December, 1969 Lake Structure, Hydrothermal Effects and Ecological Report of the James A. FitzPatrick Nuclear Power Plant December, 1969 Fish Distributi.on Studies Using Fathometric Tracing Records Nine Mile Point, Summer 1969 November 1, 1969 Ecological Benthic Survey off Nine Mile Point, August 11-15, 1969 September 2, 1969 Ecological Benthic Survey off Nine Mile Point, June 9-19, 1969 August'. 3, 1970 Summary of Fish Net Studies for 1969 for PASNY Fish Net Catch Report for Nine Mile Point, October 7-10, 1969 September 2, 1969 Fish Net Catch Report from Nine Mile Point, August 12-15, 1969 July 31, 1969 Fish Net Studies off Nine Mile Point June 1969 for PASNY June, 1970 Nitrate and Total Phosphorus Study off Nine Mile Point Area, August 13, 1969 June 15, 1970 PASNY Supported Cladophora Study:

Comments on PASNY Supported Cladophora Study by Great Lakes Laboratory May, 1970 Great. Lakes Laboratory Interactions of Temperature and Light on the Growth and Reproduction of Cladophora Glomerata (L.) Kutz June-August, 1969 August 25, 1969 Nitrate and Phosphate Study off Nine Mile Point Area, August 13, 1969 February, 1970 Cladophora Study for PASNY. Supplemen-tal Report on Second Temperature Growth Study, June-August 1969 November 10, 1969 Cladophora Study Preliminary Report.

F-5

February 1, 1969 Permanent Current Meter Study Report for PASNY, November 5, 1963 to February 26, 1964 F-6

APPENDIX G REGULATORY AND REVIEW PROCEDURES DOCUMENTS

TABLE- QF- CONTENTS-

1. Installation "

of Temperature Measuring Devices in Lake Ontario, Corps of Engineers, U.S.C G., November, 1962

2. Installation of Submerged Current Meters in Lake Ontario, Corps of Engineers, U.S.C.G., August, 1 963

3. Corps of Engineers Construction Permit Intake Discharge Structures, Tunnels, Shoreline Protection, October, 1964 4.. U.S.. Coast Guard Intake and Discharge Structure Approval, November, 1964..

'5. NYS Cooling Water Discharge, April, 1965

6. AEC Construction Permit, April, 1965

7. NYS Sewage Treatment Plant Permit, May, 1965 8.. NYS Stock Discharge Permit, April, 1966

9. Federal Aviation Agency Stack Approval, November, 1966

10. AEC By Product Material License, July, 1967

11. AEC Special Nuclear Material License, August, 1967 12.. AEC Provisional Operating License, August, 1969

13. Amendment No.2 to Provisional Operating License, April, 1971

14. Transmission Line Highway Crossing Permit, December, 1966

15. Transmission Line Barge Canal Crossing Permit, April, 1965.

X 9.~

U. S. ARMY ENGINEER DISTRICT. BUFFALO CORPS OF ENGINEERS.

FOOT OF BRIDGE STREET BUFFALO 7. NEW YORK 26NOV lS62 NCBOD J. H, Erart~ Chief Systems Project Engineer Niagara Mohawk Power Corporation Buffalo 3~ New York

Dear Sir:

In accordance ~rith your request dated 19 Septerher 1962, there is inclosed Department of the Army permit to install a te~rature measuring device in Lake Ontario~ at Nine .H.le Point~ Town of Scriba, Oswego County, New York.

Your attention is particularly invited to condition (i) con-tained in the permit which reauires that this office 'oe in ormed of the commencement and. completion of th'e authorized srork. Forms for this purpose are inclosed.

Should any mat-~.".1 chan~es in the location or plans of the proposed work be found necessary on'ccount of unforeseen or altered conditions or ot¹r~zse revised plans should be pror.ptly submitted to this office to the end tnat these revised plans, jectionable from the standpoint of navigation may r if found uno'o-ce've the approval required by la"r before construction is begun.

Acknowledgment of the inclosed petit is 'requested.

Very truly yours, 4 Incls

1. Permit ';r/print atchd 2 ~ Form 6 LEON J. HAMEBLY

3. Form 9 Colonel, Corps of EngfnoeeII 4o Ceo~ Notice Destruct Engineex

DEPARTMENT OF THE ARMY.

NOTE.It is to be understood that this instrument docs not give any property rights either in real estate or mate-rial, or any exclusive privileges; and that it does not authorize any injury to private property or invasion of private rIghts, or any infringement of Federal, State, or local laws or regulations, nor does it obviate thenecessityof obtaining Sfotg eggcnt to the work authorized. IT MERELY ExPREssEs THE AssENT 0F THE FEDERAL GovER.(MENT so FAR As coN-cERNs THE PUBLIc RIGHTs 0F NAvIGATioN (See Cummings v. Chicago, 188 U. S., 410.) to tgtco PERMIT U. S. Armp'ngineer District Buffalo Corps of Engineers.

Buffalo 7s 'tew York NC30D. 21 November l9 62 Niagara ilohawk Power Corporation Buffalo 3, New York Gentlemen:

II Referring to lsritten request dated 19 September 1962, addressed to the Di.strict mgineers U.S. ~ ~a.g ~ineer Districts Buff lo, Buffalo, New Yorks

~

I have to inform you that, upon the recommendation of the Chief of Engineers, and under the provisions of Section 10 of the Act of Congress approved March 5, 1899, entitled "An act making appropriations for the construction, repair, and preservation of certain public vorks on rivers and harbors, and for other pur-poses,'ou are hereby authorized by the Secretary of the Army.

to install a temperature measuring device (Here describe the nronoecd structure or work.)

in Lake Ontario (Here to be named the river. harbor. or waterwar concerned.)

at i;ine (Here ale Point, to be named the To;In of Scriba, Oswego County, Ne;I York nearest well known locantr nreferablr a town or city and the distance ln relies and tenths from some dcanltenolnt tho same, stating whether above or below or giving direction br points of comnass.)

in in accordance with the plans shovm on the drawingattached hereto marked: HDetail (Or drawings; give ale nnmbcr or other dean(to fdenttecatlon marks.)

I@p to Accompany Apo~wcation by Niagara .'.ohawk Power Corp .>>or Proposed 'nstallation of Temperature .'!easer~~ Device at i!inc ~ e Point wn of Sc iba New York September 19, 1952" Subject to the following conditions:

0 (a) That the work shall be subject to the supervision and approval of the District Engineer, Corps of Engineers, in charge of the locality, who may temporarily suspend the work at any time, ifin his judgment the interests of navi-gation so require.

(b) That any material dredged in the prosecution of the work herein authorized shall be removed evenly and no large refuse piles, ridges across the bed of the waterway, or deep holes that may have a tendency to cause injury to

'nnavigable channels'or to the banks of the waterw'ay shaHe left.'f any pipe,'w'ire',"or'cable'hereby authorized is laid a trench, the formation of permanent ridges across the bed of the. waterway shall be avoided and the back filling shall be so done as not to increase the cost of future dredging for navigation. Any material to be deposited or dumped under this authorization, either in the waterway or on shore above high-water mark, shall be deposited or dumped at the locality shown on the drawing hereto attached, and, if so prescribed thereon, within or behind a good and substantial bulkhead or bulkheads, such as will 'prevent escape of the material in the waterway. If the mate-rial is to bc deposited in the harbor of New York, or in its adjacent or tributary waters, or in Long Island Sound, a permit therefor must be previously obtained. from the Supervisor of New York Harbor, New York City.

(o) That there shall be no unreasonable'interference with navigation by the work herein authorized.

(d) That if inspections or any other operations by. the United States are necessary in the interest of navigation, aH experises connected therewith shall be borne by the permittee.

(e) That no attempt shall be made by the permittee or the owner to forbid the full and free use by the public of aH navigable waters at or adjacent to the work or structure.

(f) That if future operations by the United States require an alteration, in the position of the structure or work herein authorized, or if, in the opinion of the Secretary of the Army, it shall cause unreasonable obstruction to the free navigation of said water, the owner will be required upon due notice from the Secretary of the Army, to remove or alter the structural work or obstructions caused thereby without expense to the United States, so as to render naviga-

,tion reasonably free, easy, and unobstructed; and ii, upon the expiration or revocation of this permit, the structure, 3tH, excavation, or other modification of the watercourse hereby authorized shall not be completed, the owners shall, without expense to the United States, and to such extent and in such time and manner as the Secretary of the Army may require, remove aH or any portion of the uncompleted structure or filland restore to its former condition the navi-gable capacity oi the watercourse. No ciaim shall be made against the United States on account of any such removal or alteration.

(g) That the United States shaH in no case be liable for any damage or injury to the structure or work herein authorized which may be caused by or result from future operations undertaken by the Government for the conserva; tion or improvement of navigation, or for other purposes, and no claim or right to compensation shaH accrue from any such damage. I (h) That if the display of lights and signals, on any work hereby authorized is not otherwise provided for by law, such lights and signals as may be pres ".'bed by the U. S., Coast Guard, shaH be installed and maintained by and at the expense of the owner.

(i) That the permittee shall notify the said district engineer at what time the work will be commenced, and as, far in advance of the time of commencement as the said district engineer may specify, and shall also notify him promptly, in writing, of the commencement of work, suspension of work, if for a period of more than one week, resumption of work, and its completion.

( j) Th t if the structure or wogg herein authorized is not completed on or before @~~Vs .=..:".;.'.:.ST....'... day of D<CF".R~R

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be null and void.

19 .,

-), this permit, if not previously revoked or specificaHy extended, shall cease and C:-

By authority of the Secretary of the Army:

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RETURN To ENG!NEER~NG DEPARTMENT UN)yEg SyA>ES COAL GUARD

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COMMANDER

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o CLRVPLAND IS, OHIO <%1/~1 Serials oan 1029 2JI, December 1963 Kr. Z. N. Ewart Chief System Project En~in sneer agexa II'ohavk 'i'over Corporation Buffalo 3, New York

Dear hr. i:

vart:

Enclosed is an approved Private Aid to Navi ma n nance of the aids described therein reine Your attention is invited to the Rules and He to N i ti ho o the firs t sheet he t of the application form, Please inform this office vhen the aids have been established so that their e Notices to Mariners and an inspection conducted.

Sincerely yours, cvin". Chief, Aids to .'tavi ation Branch Bg direction of the District Colander

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'COhST GUARD (Sou fnstnrctions on reverso of etteched copy of Code of Fe<f. Reff., :r, t r No. 48 554 (Rev. 3-62) Tltfo 33, Chop. I, Sect. 66.) R379,'o TIQN REQUESTED fQR PRIVATE AIDS TO NAVIGATION 2- DATE ACtION TO START A.Q fSTABLISH AND MAINTAIN B.+ DISCONTINUE C.+ CHANGE O.Q CHANGE QSHFRSHIP 6 November 1963

3. PERIOD AIDS wlLL BC OPERATCQ A. THROUGHOUT YEAR 8.+ TEMPORARILY UNTIL C.Q ANNUALLY FROM TO

4. NECESSI TY FOR AID (Continue in ccotorka) 5 CORPS OF ENGINEERS AUTHORI ZCO THIS STRUCTURE OR BUOY Studies for steam power plant By ~ PERIII T OR ~ LETTER DATED Cols. A ond B for District Commender'5 use Appllconl will fill In opplf cubic remoinln9 columns

6. LIGHTS LIGHT I. I 5 CHARACTERISTICS ILLUMINANT CANDLE I'UMBER NAME Of AIO rL ASH r CCI. I SC COLOR I'OSI Tl ON POWER LENS VOLTS ANPCACS E E'I OR PAGE t. CN CTH I CNCTH A C 0 J K

7. BUOYS LIGH't LIST NUMBER DEPTH NUMBER NAME OF AIO OR REFLECTOR POSITION OF TYPE COLOR EEr OR PAGE LETTER WATER COLOR A C D E H NINE 1lILS POINZ A lat, 43o 31'3" W long. I2" Ma Inter- 3 vicle OBSERVJL1 ION BOvY 6o 248 04" 750.31'rom by national horixe A 'eteorological tover 10'g.buoy ora~e silver t N lat, 43 31T 26" w extend- and vtLLte bands long t6 24'lla ing ap- EIoriz, at 12" proxe4 banded cent-(4608 offshore) above 'er vatert iber 1

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IS MAINTAINED Corp. 300 Erie Blvcl~ West Syracusep HY - 13202 118. THE APPLICANt AGRECS TO SAVE THC COASt GUARD HARQLESS wl TH RESPECT TO ANY CLAIM OR CLAIMS THAT MAY RESULT ARI SING FROM THE ALI,EGEO GLIGENCE OF THE MAINTENANCE OR OPERATIONS OF THf. APPROVED Al OISI JB. TELEPHONE NUMBER PI 3 2110 II +5v lc+o3 llo, SIQNAtURE Allu TI I e'.czeLQ~L s<<NING ClLI.ef Systenr~rogect in+neer

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o. Notice to Mariners will be issued H. DATE I ~ 'SIGNATURE E. Light List should be corrected P~,g@zMAN

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'PAUG l963 h Kelt To'CBOD J. H. Evart, Chief System Pro)ect Engineer Niagara Mohavk Power Corporation Buffalo 3, Nev York

Dear Sir:

Reference is made to your letter dated 16 July 1963 and the accompanying plans, relative to your temporary installation of tvo submerged current meters in Lake Ontario at Nine Mile Point, Town af Scriba, Osvego County, New York.

This office viU. interpose no ob)ection to the fnstaPation of the tvo current meters provided they are'nstalled in accordance with your letter of application and the a'cca'npanying plans.

Your attention is invited to the fact that the type and char-acteristics of the marker buoys must be approved by the Canmander Ninth Coast Guard District, Main Post Office Building, Cleveland 13, Ohio.

It is to be understood that the above action does not give any property rights either in res1 estate or material, or any exclusive privQ.eges; and that it does not authorize any in)ury to private property or invasion of private rights, or any infringement of Federal, State, or local lavs or regu1ations, nor does the necessity of obtaining State assent to the proposed vork.

it obviate It merely expresses the assent of this office"insofar as the rights of navigation are concerned.

It is requested that this office be notified of the canmence-ment and caapletion of the above vork.

Very tru1y yours'T II'tUNT Chief~ Eaginseri~ kivie10%

'NlTED STATES COAST GUARD

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AOOREOI ItCtLYlOs COMMANDER

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Serials oan 34.

23 January 1964.

Mr. J. N. Ewart Chief System Project Engineer Niagara Mohawk Power Corooration Buffalo 3,'ew York D88r Mro Ewart~

Enclosed is an approved Private Aid to Navigation Application authorizing the establishment and maintenance of the aids described therein, Your attention is invited to the Rules and Regulations Governing Private Aids to Navigation shown on the first sheet of the application form, Please inform this office when the aids have been established so that their existence may be published in the Notices to Mariners and an inspection conducted.

Sincere+ yours, M ~ JOcdMi>>

Li utenant Comrwnder, U S. Coast Guard Acting Chief, Aids to Navigation Branch By direction of the District Commander

'Encl'1) Form CG-2554,

ASURY DEPARTME'NT PRIVATE AIDS TO NAVIGATIONAPPLICATION Form epprored Budget Bureeu S. COAST GUARD (See Inatntcttona on reverse of attached copy of Code of Fed. ROII., No. OS-ICS79 2SS4 (Rev. 3-62) Tftle 33, Chap. f, Sect. 66.)

CTIOH REOUESTED FOR PRIVATE AIDS TO NAVIGATION 2. 0~AT ACTION<'TO START A.ti ESTABLISH ANO MAINTAIN B.Q DISCONTINUE C.Q CHANGK 0.+ CHANGE OWNERSHIP ffoveniber ..5~ 1963

3. CRIOD AIDS WILL BE OPERATKO A.+ THROlIGHOU.T YEAR BI+ TEMPORARILY UNTIL,STgQggQ+,.ILPJP$ 5 .. C.+ ANNUALLY PRES TO 4 NECESSIWY FOR AI0 (Continuo In rrmerkeJ 5 CORPS OF ENGINEERS AUTHORIZED THIS STRUCTURE OR BUOY To ueaeure Xeke Ontario'e current BY ~ PERMIT OR gj LETTER DATED ........--...M............13.............-..'

Cols. A ond B for District Commender'5 use Appllcont will fill In oppllcobl ~ romolnln9 columns

6. LIGHTS LIGHT LIST CHARACTERISTICS CANDLE ILLUMINANT NUMBER , NAME OF AID COLOR POSITION Hcl our LENS FLAsH ccL Ipse POWER toLT5 Aurcscs OR PAGE I CNOTH LCNOTH A '0 0 '

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7. BUOYS LIGHT LIST tNBSBBtr DEPTH REFLECTOR NUMBER NAME OF AID POSITION OF TYP E COI.DR OR PAGE LETTER", WATER A C E H HIlE SQLE POX?C 43 31'0"M) '/6 24'0 32" Buay'OLOR Xntex OBKRVATXOki BUGYS 52t Round. national NEcS Marker orange SE 43 31'5"N; 'l6 2Io'9" white Horis banded

8. FOG SIGNALS LIGHT LIST CHARACTERISTICS NUMBER NAME OF AIO Nuo ~ Ce POSITION TYPE RANGE OR PAGE 5 reoc 55 PCNIOO ~ LA5r SET LCNOTH Oe ~ LAST A

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Syracuee, Hew York 110. THE APPL I CANT AGREES

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F. DATE G. Sl G NATURE

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U. S. ARMY ENGINEER DISTRICT, BUFFALO g4.58 CORPS OF ENGINEERS FOOT OF BRIDGE STREET BUFFALo 7. NKw YoRK . ZIP code 142+.

Jcs iIj Rare To) ~

NCBOD 19 October 1964 J. H. Ewart, Chief System Project Engineer Niagara Mohawk Power Corporation Buffalo, New York 14203

Dear Sir:

In accordance with your request dated 21 July 1964 there is inclosed Department of the Army permit to construct submerged water intake and discharge structures, shore connection tunnels, approximately 975 linear feet of rubblemound stone dike and to dredge in Lake Ontario, at Nine llile Point, Town of Scriba, Oswego County, New York, about 6-1/8 miles northeasterly of Oswego Harbor, New York, Your attention is particularly invited to conditions (b) and (i) contained in the permit. In compliance with condition (b) no refuse piles or ridres shall be left on the bed of the waterway.

A sweep survey wilL be made when the work is completed and the Niagara Hohawk Power Corporation will be reouired to remove any excavated material that extends above the undisturbed existing lake bottom. The Niagara Hohawk Power Corporation will be charged f'r the cost of this survey and any further surveys or inspections to insure that the conditions of the permit are complied with.

Care must be exercised during construction to insure that the intake.

and discharge structures provide the clearance below low water datum shown on the approved plans. Condition (i) requires that this office be advised of the commencement and completion of the proposed work. Forms for this purpose are inclosed.

Should any material changes in the location or plans of the work be found necessary on account of unforeseen or altered condi-tions, or oth'ermse, revised plans should be promptly submitted to this office to the end that these revised plans, if found unobjec-tionable from the, standpoint of navigation, may receive the approval required by law before construction is begun.

NCBOD J. H. Ewart, Chief System Prospect Engineer Acknowledgment of receipt of the inclosed permit is requested."

Very truly yours, 4 Incls R WILSON NEPP

1. Permit w/prints (3) atchd

2. Form 8 Colonel, Cozps of EnglI1BBzs

3. Form 9 Dlstzfct Engineez

4. C.G. Notice

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DEPARTMENT OF THE ARMY NOTE It is to be understood, that this instrument does not give any property rights either in real estate, or mate-rial, or any exclusive privileges; and that it does not authorise any injury, to private property or invasion of private rights, or any infringement of Federal, State, or local laws or regulations, nor does it obviate thenecessityof obtaining State ttesent to the work authorised. IT bIEREI Y EZPREssEs THE AssENT oF THE FEDERAI. GovERNMENT so FAR As coN-CERNR THE PUBLIC RlGHTs oP NAvIQATIQN. (See Ctttttmittge v. Chicago, 188 U. S., 410.) Io tslsoe Contract No. iR-30-023-CIVENG-65-18 PERMIT U. S. Arne Engineer District, Buffalo.

Corps of Engineers.

Buffalo, New York 14207

~1 October , lg 64 .

NCBOD Niagara IIohawk Power 'Corporation Buffalo, New York 14203 Gentlemen:

Referring to written request dated 21 July 1964, addressed to the District Engineer, U. S. Army Engineer District, Buffalo, Buffalo, New York I have to inform you that, upon the recommendation of the Chief of Engineers, and under the provisions of Section 10 of the Act of Congress approved March 3e 1899, entitled 'An act making appropriations for the construction, repair, and,.

preservation of certain public works on rivers and harbors,*and for other pur<<

poses," you are hereby authorized by the Secretary of the Army.

to construct submerged water intake and submerged water discharge structures, (Here describe tbe Droooecst structure ot work,)

two shore connection tunnels, approximately 975 linear feet of rubblemound stone dike and to dredge the dredged material to be deposited shoreward of the proposed stone dike in Lake Ontario (Here to be names) tbe river. harbor, or waterway concerned.)

at Nine labile Point, Town of Scriba, Osweso County, New York, about 6-1/8 miles (Here to be named tbe nearest <<ell known locality pre(erably a town or ctty and the distance ln mlles and tenths the same, stattne whether above or below or sirius stlrectlon by yolnta oI comyass ) kern some deanlte Point ln northeasterly of Oswego Harbor, New York in accordance with the plans shown on the drawing attached hereto in three sheets (Or draw!nest Siva sle number or other deentte tdenttttcatfon marks.)

marked "Application by Niagara Mohawk Power Corp. For Proposed Intake Ec Discharge Tunnels, Dike, and Barge S'Iio at Nine ale Point July 21, 1964eu sub)ect to the following conditions:

(a) That the work shall be subject to the supervision and approval of the District Engineer, Corps of of navi-Engineers, in charge of the locality, who may temporarily suspend the work at any time, if in his judgment the interests gation so require.

evenly and no (b) That any material dredged in the prosecution of the'work herein authorized shall be removedcause injury to large refuse piles, ridges across the bed of the waterway, or deep holes that may have a tendency to navigable channels or to the banks of the waterway shall be left. If any pipe, wire, or cable hereby authorized is laid in a trench, the formation of permanent ridges across the bed of the waterway shall be avoided and the back filling shall be so done as not to increase the cost of future dredging for navigation. Any material to be deposited or dumped under this authorization, either in the watervray or on shore above high-water mark, shall be depositedgood" or dumped at the locality shown on the drawing hereto attached, and, if so prescribed thereon, within or behind a and substantial bulkhead or bulkheads, such as will prevent escape of the material in the watervray. If the mate-rial is to be deposited in the harbor of New York, or in its adjacent or tributary waters, or in Long Island Sound, a permit therefor must be previously obtained from the Supervisor of New York Harbor, New York City.

(c) That there shall be no unreasonable interference with navigation by the work herein authorized.

(d) That if inspections or any other operations by. the United States are necessary in the interest of navigation, all expenses connected therewith shall be borne by the permittee.

(e) That no attempt shall be made by the permittee or the owner to forbid the full and free use by the public of all navigable waters at or adjacent to the work or structure.

(f) That if future operations by the United States require an alteration in the position of the structure or work herein authorized, or if, in the opinion of the Secretary of the Anny, it shall cause unreasonable obstruction to the free navigation of said water, the owner will be required upon due notice from the Secretary of the Army, to remove or alter the structural work or obstructions caused thereby without expense to the United States, so as to render naviga-tion reasonably free, easy, and unobstructed; and if, upon the expiration or revocation of this permit, the structure, fillr excavation, or other modification of the watercourse hereby authorized shall not be completed, the owners shall, without expense to the United States, and to such extent and in such time and manner as the Secretary of the Army may require, remove all or any portion of the uncompleted structure or filland restore to its former condition the navi-gable capacity of the watercourse. No claim shall be made against the United States on account of any such removal or alteration.

herein (g) That the United States shall in no case be liable for any damage or injury to the structure or work authorized which may be caused by or result from future operations undertaken by. the Government for the conserva-tion or improvement of navigation, or for other purposes, and no claim or right to 'compensation shall accrue from any such damage.

(h) That if the display of lights and signals on any work hereby authorized is not otherwise provided for by law, such lights and signals as may be pre- robe by the U. S. Coast Guard, shall be installed and maintained by and at the expense of the owner.

(i) That the permittee shall notify the said district engineer at what time the work will be commenced, and as far in advance of the time of commencement as the said district engineer may specify, and shall also notify him promptly, in writing, of the commencement of work, suspension of work, if for a period of more than one week, resumption of work, and its completion.

(j) That if the structure or work herein authorized is not completed on or before ..tl)iit'rX".QXQt'r......... day of DCCallbeI'............., 19..67., this permit, if not previously revoked or specifically extended, shall cease and be null and void.

By authority of the Secretary of the Army:

R. ':JILSOll NEF."

Colonel, Corns of Engineers District Engineer ED perm 95, dered 1 hyr dd. which msr be used unia ezhsurred.

j 7g ) (Q~y jj) Tbb term superseded

~ . e. eorraasret re>suea erricr id idled.d EM 1145-&403

l Pi)

L+

4 lA ~0~11 P~QQQ/QlI~

OPPgyfh Ipg t UNITED STATES COAST GUARD

~ IKH Y TO>

,COMMANDER Om COAST OUA!%D DISTRICT b MAINPOST OFFICE SLDCiI

%%ST THIRD AND PIIOSPECT STS.

'264 CLÃIIELAND13, OHIO Serial: oin 890 3 November 1964 Mr, K. C, Swanson Chief Structural Design Engineer Niagara Mohawk Power Corporation Buffalo', New York 14203

Dear Mr. Swenson:

.Your letter of 26 October 1964 forwarded a copy o'f a Corps of Engineers Permit which authorized construction of a submerged water intake and discharge structures in Lake Ontario near Nine Mile Point, New York.

The Coast Guard has no objection to your project and navigational marking wi11 not be required. However, should the structures become obstructions to navigation during the construction or upon completion, lighting will be necessary.

la the event you decide to establish navigational aids for your own pro-tection against possible liability claims, prior approval for such private aids to navigation must be obtained from the COImandsnt, U. S. Coast Guard via this office.

Please contact us if we may be of further service.

Sincerely yours, Mc.D E, W. CONAN BM Commander, U. S. Coast Guard Chief, Aids to Navigation Branch By direction of the District Caanander

I

'PJv SHORN To

• DIVISION OF ENVIRONMENTALHEAL'TH SERVICES KNGfNEERfNQ DEt'ARTMENf STATE OF HEW YORK MEREDITH H THOMPSON D KNO,

~

DEPARTMENT OF HEALTH ASSISTANT COMMISSIONKR HOLLIS 5 IHGRAHAMy Me Do COMMISSIONKR 84 HOLLAND AVENUE BUREAU OF ALBANY, N. Y. 12208 TIATKR RESOURCE SERVICES AHSELMO F. DAPPERT, MoS.S.E.

DIRKCTOR April 28, 1965 Niagara Mohawk Power Corporation 300 Erie Boulevard Vest Syrac'use, New York 13202 Attention. John V. Keib, Attorney Gentlemen:

Re! Approval of Final Plans Cooling Water Discharge and Industrial Waste Treatment Works Nine Mile Point Nuclear Station Scriba (T), On)ego County Ve are enclosing a permit issued this day, and are forwarding under separate cover approved plans, consisting of 2 B/tf sheets, for the above referenced project.

The permittee's attention is directed to the conditions which are part of the accompanying permit. All of the conditions are important and you are aovised that the validity of the permit is contingent upon compliance.

Since this facility processes no sanitary'ewage, a certified operator under the New York State Sanitary Code is not required. How-ever, the facility must be operated at all times in conformity to the Public Health Law and State Health Department regulations.

Aspects of the proposed discharge are as follows.'.

Heat, from the condensor cooling facility, which at full load is stated to cause a 32 F temperature rise in a flow of'50,000 gallons per minute;

2. Salts, from approximately 2,500 gallons per day of acidic

.and caustic ion exchange resin regeneration which re ult when these t;:. omTIonents are held and mixed for neutraliza-tion before discharge; and

1 Niagara Mohawk Power Corporation April 28, 1965 3, Discharge from the "hold-and-decay tanks whose function is to monitor possible radioactive material accidents, and whose operational procedures have been approved under the Nuclear Safety Hazards Analysis subnitted to the Atomic Energy Commission.

The storm sewers are not part of this approval. Since these shall receive only the resultant runoff from natural precipitation, and a smaU. quantity of screen washwater to which no contaminants or pollutants are added, then no permit is required for their installation and use.

The total flow at full operational capacity is 385 million gallons per day, or 275,000 gallons per minute.

Very truly yours, I

~l jy.

Joseph J. Kosman, P.E.

Senior Sanitary Engineer Municipal-Industrial Vastes Section Enclosure cc: Syracuse Regional Office Syracuse District Off' Julius A. Lind, P.E.

gl lt 'I

NEW YORK STATE DEPARTMENT, OF HEALTH PERMIT TO DISCHARGE SEWAGE OR WASTES'INTO THE WATERS OF THE STATE This permit is issued under the provisions of hrticle 12 of the Public Health Law in connection with approval of plans for

'g che project described below:t Name b Location of Storks (city,village or town) Check type ot works and discharge Ches ttmttctpst Sutface Discharge Nine Mile Point Institutional +Ground tfatet g] Sewers + Addltlons ot Alterations Nuclear Power Station Private (individual) Tteatment works gg pumptog station Private (other) Other Scriba (T) industrial Waste ounty Osage o Name end Address of Board, Corporation, individual or Oflice making Name of receiving water course. If Name of City, Village or Town ln ppllcstlon surface waters: if subsurface, nam which point of discharge ls of water course to which ground located Niagara Mohawk Power Corporation water ls tributary Oswe .o 300 Erie Boulevard Iieet Lake Ontario Name of major drainage basin ln hlch point of discharge i ~ locate Syracuse, New York 13202 Lake Ontario

~ scription of works such as number, name snd capacity of units Estimated cost of Design flow gals.

works per day Cooling Mter 250,000 gpn s Service $1ater 25, 000 gpn; including ion exchange resin 22 400, 000 385 )GD.

regeneration and holding tank discharge hpproval of plans and permit to discharge is granted on condition:

I. THhT chis permit shall be revocable ac any time or subject co modification or change when in the judgment of the Department of Health such revocacion, modification or change shall become necessary.

. I.

waste treatment II THhT'he proposed

~ KiQQQeigc works shown on the plans approved this day shall be fully constructed in complete conformity with such plans or approved amendments therefor uncer the supervision of a licensed Professional ~npineer.

)ct)ljaxc(mown&

IV. TllhT the

~ ~ works shall be operated oc maintained at V.~ THhT this per'mit shall be deemed null a:.d Qs(OGxdcx.

all times co the satisfaction of che Department L void unit ss the works for which it is issued shall have been fully of Health.

completed by Anril 28 lc70 and a certif icate of construction ccmpliance ubnitted to and approvec '8p'the Syracu e District Office, Nets York State Department of Health,'ithin thirty (30) days after completion of construction.

III, THAT only the tp~ ana volume of va ste s covered by the En gin e er ' Report, entitled Exhibit A, undated, and the Safety Hazarcs Analysis report, and no sanitary cage, storm water, or surf'ace vater frcm streets, roofs, or other areas shall be ac)nitted to the waste treatment @or'ks.

issued for the State Commissioner of Health: Date Office(%PCS)

~ ,~Cd'~, z '/5 4/2s/B Scrvtc ~ e Directors'ureau of+ ter Resource ~

FOR:

Dl~ trlbutlont S/hite Apptlc ent Yellow FHe (LHO or DHO)

Sano 2 (Reve d/d2) Pink Central Green Other 1

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'0 E,

I

UNITED STATES ATOM IC ENERGY COMM ISSlON WASHINGTON, D.C. 20545 gl4rE 0I NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 PROVISIONAL CONSTRUCTION PERMIT Construction Permit No,'PPR-16  ?

1. Pursuant to Section 104b of the Atomic Energy Act of 195II, as amended (the Act), and Title 10, Chapter 1, Code of Federal Regulations, Part 50, Licensing of Production and Utilization Facilities, and pursuant to the order of the Atonic Safety and Licensing 'Board, the Atomic Energy Commission (the Commission) hereby issues a provisional construction permit to Niagara Mohawk Power Corporation (the applicant) for a utiliza-tion facility (the facility), described in the application and amendment thereto filed in this matter by the applicant and as more fully described in the 'evidence received at the public hearing upon that application.

The utilization facility is a single cycle boiling, light watex reactor which is part of a facility designed to operate at 1538 megawatts (thermal) to be located on 'Lake Ontario in the Town of Scriba, New York.

2. This permit shall be deemed to contain and be subject to'he conditions specified in Sections 50.5II and 50,55 of said regulations; is subject to all applicable provisions of the Act, and rules, 'regulations and orders of the Commission now or hereaftex in effect; 'and is subject to the con-ditions specified oz incorporated below:

A, The earliest date fox the completion of the facility is December 1, 1966, and the latest date for completion of the facility is December 1, 1967.

B. The facility shall be constructed and located at the site as described in the application as amended, in the Town of Scriba, New York.

C. This construction permit authorizes the applicant to construct the facility described in the application and the hearing record in accordance with the principal architectural and engineering criteria set forth therein.

3. This permit. is provisional to the extent that a license authorizing oporation of the facility will not be issued by the Commission unless:

(A) the applicant submits to the Commission, by amendment to the applica-tion, tho complete final hazards summary report, portions of which may be submitted and evaluated from time to time; (B) the Commission finds that the final design provides reasonable assurance that the health and safety of the public will not be endangered by the operation of the facility in

-~

accordance with procedures approved by it in connection with the issuance of said license; and (C) the applicant submits proof of financial protec-tion and the execution of an indemnity agreement as required by Section 170 of the Act.

4. Pursuant to Section 50,60 of the regulations in Title 10, Chapter l, CFR, Part 50, the Commission has allocated to the applicant for use in the operation of the reactor l4321 kilograms of uranium 235 contained in uranium in the isotopic ratios specified in the application. Estimated schedules of special nuclear material transfers to the applicant and returns to the Commission are contained in Appendix A which is attached hereto, Transfers by the Commission to the applicant in accordance with column 2 in Appendix A will be conditioned upon t'e applicant's return to the Ccmmission of material substantially in accordance with column 3 (including the sub-columns headed Scrap and Depleted Fuel) of Appendix A.

FOR THE ATOi~fIC ENERGY COP>'HISSION R. L. Doan, Director Division of Reactor Licensing

Attachment:

Appendix A D t of I anc:

~1 I

7.

AD@URN TO y' Q D - Z ~~ DIVISION OF

'. I P,'G!'" RING DIPRRTMENT STATE OF NEW YORK DEPARTMENT OF HEALTH ENVIRONMENTALHEALTH SERVICES MEREDITH H, THOMPSOII, Dr ENOI A55I5TANT COMMI55IONER HOLLIS S. IHQRAHAM, M. D.

C 0 MM I 5 5 I 0 N E I%

May 0, 196'UREAU 84 HOLLAND AVENUE AL8ANY, N. Y. 12208 OF WATER RESOURCE SERVICES ANSELMO F. DAPPERT, M.S.S.E.

DIRECTOR Niagara Mohawk Power Corporation 300 Erie Boulevard >Test Syracuse, New York 13202 Attention: Mr. John V. Keib Attorney Gentlemn:

Re: Approval of Final Plans Sewage Treatment Works Nine Yd.le Point Nuclear Station Scriba (T), Oswego County

':Te are enclosing a permit issued, this day, and are forwarding under separate cover approved plans, consisting of 6 B/H sheets, for the above referenced project.

The period.ttee's attention is directed to the conditions which are part of the accompanying permit. All of the conditions are important, and you are advised that the validity of the permit is contingent upon compliance.

A qualified Grade IX-A Operator shall be continuously employed to supervise operation of the sewage treatment plant as outlined in Part 11 of the t'.ew York State Sanitary Code. Ne advise that the operator be engaged prior to construction of facilities so that he, will be fand.liar with the treatII. nt units and their proper operation.

Laboratory analyses and determinations shall be made to indicate waste characteristics, treatment efficiencies, and com-pliance with receiving waters'tandards. Analyses should include determinations for settleable, total, and susoended solids, (SS),

biochemi.cal oxygen demand, (BOD), dissolved oxygen, (DO), and 'pH of the raw and partial+ treated wastes and final effluent; chlorine residual and coliform of the treated wastes; blanket measurement of the sludge; and dissolved oxygen and settli.ng index of the mixed liquor. Certain analyses may be contracted out upon approval of the local health office indicated below.

P<rr 'a ~pre,g g Vrr /rr 0 rr P'- 3-~-". ">>> 7

~ rr/) C. r'..i h'I

Niagara 1hhawk Nay 4, 1965 Power Corporation Information and inquiries should be directed to Nr. Peter Guala, F.E., District Engineer, Syracuse District Office, 333 East Washington Street, Syracuse, regarding the following:

1~ Selection, .supervision, and training of the treatment plant operator.

2. Certificate of construction compliance.

3~ Details and frequency of laboratory ana~es and determinations.

Submission of monthly operation reports.

The plant has been designed to receive an average flow of 15,000 gpd from an exoected population of 150 persons. Approval has been granted on the basis that the plant plus oxidation pond will remove 95 percent each of the influent suspended solids and biochemical oxygen demand.

In order to expedite approval of these plans, we are making part hereof one aspect of design .that did not appear on said plans. That is the peripheral railing for the aeration tank.

As you have agreed to provide this item,'we will assume its omXssion from the plans was an oversight. It is therefore incumbent upon to install sai" miling in the finally constructed plant. 'ou Very t~ yours, I

Joseph J. Kosman, P.E.

Senior Sanitary Engineer Municipal-Industrial Wastes Section Enclosure c/c Syracuse R.O.

Syracuse D.O.

Julius A. Q.nd, P.E.

NEW YORK STATE DEPARTMENT.OF HEALTH t

PERMIT TO DISCHARGE SEWAGE OR WASTES'I)4TO THE WATERS OF THE STATE This permit is issued under the provisions of Article 12 of the Public Health Law in connection with approval of plans for the projecc described below:

Name SI I ocatton of lforks (cuy,village ot town) Check type of works snd discharge Check ItImklpat ~

Qg Smfsce Discharge Nime Mile point -Nuclear InsTliuilonsl +Ground Water Pg Sewers Q Additions or Alietauons Power Station Private (individual)

Ptlve'ie (other) i l

+X Treatment Works

+ Other + Pumping Station Scriba (T) Indusitlal Waste ounty Oswecfo frame end Addres ~ of Board, cofIIorstton, Indivfduat or office making game of teceivlng waist course, lf frame of City Village or Town'in ppllcailon ~ 'Uflac ~ waiefs'l ~ ubsutfsce ~ nsm which point of discharge ls TO: of water course to which gtound located Niagara Mohawk Power CorporatioTj 'wei@t la tributary 300 Erie Boulevard >lest Lake Ontario

)fame of maJor drainage basin ln hlch point of discharge la locate Syracuse, New,York 13202 Lake Ontario esctlpilon of works such ss number> name and capacity or united EsuuIsied cost of Design flow gals.

wofks pet day 5

See Reverse Side II8,000 15,000 hpprovai of plans and permit to discharge is granted on condition:

I THAT this permit shall be revocable at any time or subject co modification or change when in the judgment of che Departmenc of Health such revocation, modificacion or change shall become necessary.

THhT the proposed sewerage works shown on the plans approved this day shall be fully conscructed in complete conformity with such plans or approved amendmencs thereto.f under the supervisien of a li.censed P.E THhT only sewage and no ground'water, storm water, cooling water, or surface water from screets, foundations, roofs or other areas shall be admicced to the proposed sewerage works.

i TllhT the sewage works shall be operated or maincained ac all times co the sacisfaction of the Department of llealth.

THhT this perinit shall be deemed null OI 8 void unless the works for which it is issued shall have been fully completed by 1~&~, 1970, and a cert-'icate of. constructi.on compliance submitted to and approved Up"Syracuse District Offi.ce of the State Health Department aithin thirty (30) days after completion of construction.

VI. THAT the leakage outward or the infiltration shall not exceed 500 gallons per inch of sewer pipe diameter per mile per day for any section of the sewerage system.

VII. TFAT'sufficient personnel meeting the aualifications for 'sewage treatment works operators as reauired by the llew York State Sanitary Code, shall be employed to satisfactorily operate the treatment facilities.

VIII. THAT chlorine shall be applied continuously to the sewage at a point indicated on the approved plans at a rate sufficient to maintain at all times a minimum residual of five-tenths parts per million (0.5 p.p.m.) of chlorine or greater in the final effluent to provide for effective disinfection.

IX. THAT monthly reports on the daily operation of the sewage treatment works shall be regularly submi.tted to the Department qf Health on forms furnished by or satisfactory to the Department of Health.

Issued pr the Stole Commissioner of Health: Date:

5/4 /65 lv ~~ Dltectoto Buttau 0 ty Walel'eeo Cea SetVIC ~ S Dl ~ ttlbutlonf White APPl kant Yellow - plf~ (I.HO ot DHO) ssn. 2 (Rev. d/d2) Pln'k Central Office ('WPCS) Green - Other

%I 8.

'State Of New York Department Of Health AIR POLLUTION CONTROL BOARD s4 HOLoLAH0 Avso~ hleSAHY ~ Ne Y>>

April 25, l966 Mr. J.N. Ewart Chief System Project Engineer Niagara Mohawk Power Corporation 535 Washington Street Buffalo, New York 14203 APPROVAL OF CONSTRIJCTXON'

'Application having been made, as required by the Rules to Prevent New the installation described below,'Plan No. HA"66O88 Air'ollution, Stack for ventilation air and process gases discharged.to atmosphere Niagara Mohawk Power Corporation Nine Mlle Point Nuclear Station (T) Scrlba, Oswego County, New York is approved subject'to the following conditions:

1. The approval shall be revocable at any time or subject to modification or change when, in the judgment of the Board, such revocation, modification, d'or or change shall become necessary.

2~ The proposed construction shall be completed in conformity with the descrip-tion in the report or as shown on the plans approved this day, or in accord-

'ance with any approved amendments.

3 Whenever required by the Board, additional or more effective air pollution control devices or. systems shall be installed and put into operation, reports or plans for which shall first be submitted to the Board for approval.

4~ This approval shall not be transferable either from one location to another, from one piece of equipment to another.

5~ The Board shall be. notified in writing within 30 days after the completion of this installation that it is completed and placed or will be placed in opera-tion, and of the time and place of any tests to be p'erformed.

6~ This approval shall become invalid if the work for this approved installation is not comPleted by November I, 1968 7~ This approval in no way precludes the right of any governing body of any municipality to impose additional requirements for the control of air pollution.

8, lf other than the above Is instal'led, a new application ls required.

APCB 3 (rev. 11/64) si/ t', (OVER)

(q

K pVlhty FEDERAL AVIATION AGENCY BOSTON hREh'FFICE

+trrs ot +

Building ¹3 Northwest Industrial Park Burlinyon, Mauachuset(s 0(80( .:, ~" C

~

0

> 2~ ~'7 N attLY area to BQQ-520 Case No. 13O"-OR-66-365

~

Iir. 0. K. BrotIn Chief Electrical En+neer Mni,am Yohn~ik Power Corp.

535 )1nshington St. RHINO buffalo~ II Y

Dear Nr. Brown:

This rofors to your 1"orm PAA-117, Hotico of Froposcd Construction or Alterations, dated October 14~ 1966, for the fo&owinC described construction:

TYPE SidUCTUBZ: Concrete Chimney LOCATION Lycoming, N. Y.

Lntitude 43 31'7" ABOVB IKL 610 Longitude 76'4t 36" An aeronautical study conducted in accordance with Fart 77'ederal Aviation Ro~~tions, has resulted in a Qotemination thnt tho construction or alteration vrould not exceed anv standard of'ubpart C and. would not be n hazard to air navigation. Supplomontnl notice to this office is required within five days after the construction or alteration reaches its Greatest height. Hotice form is enclosed,.

The structure should be mnrIcod nnd lighted in nccorQnnce with the standards in FAA's Iinnunl, "Obstruction Iinrlcinc and, L1~".tine. u Unless other~rise revised or tered.nntcd, thi" determination trill emire on liny 3, 1963~ or upon earlier abandonment of the construction proposal Sincoro1y yours, Sidney L. , Chiof Air Traffic ranch

9. That portion of wastes which inc1udes radioactive materials shall not be discharged in amounts or concentrations which exceed the 1 lmlts specified ln Section 10 of the Code of the Federa1 Regulations, Part 20.

STATE OP NEW YORK AIR POLLUTION CONTROL BOARD Wl 1 1 1 am L. 0 'onnor, P. E, Senior Sanita En ineer j

Alexander Rihm, Jr., P. E.

For Executive Secretary

1 g g

U. S. ATOMIC ENERGY COMMISSION Page 1 of D Pages BYPRODUCT MATERIALLICENSE

'j'":; .',

Pursuant to the Atomic Energy Act of 1954 and Title 10, Code of Federal Regulations, Chapter 1, Paris 30, 32,33, 34, and 35, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, own, possess, transfer and import byproduct male-rial listed below; and to use such byproduct material for the purpose(s) and at the place(s) designaled below.

This licen e shall be deemed to contain the conditions specified in Section 183 of tho Atomic Energy Aci of 1954, and is subject to all applicable rules, regulations, and orders of the Atomic Energy Commission now or hereafter in effect and to any conditions specified below.

License'e Niagara lhhawk Power Corporation 3. License number 31<<07489-02

2. 300 Erie Boulevard, liest Syracuse, New Yorlc 13202 4. Expiration date ]9)

July 31

8. Reference No.

6. Byproduct material 7. Chemical and/or physical 8. Maximum amount of radioac-(element and mass number) form tivity which licensee may possess at any one time A. Cobalt 60 A. Sealed source A. 24 curies (AECL Hodel C-163)

B Cobalt 60 B~ Sealed source BE 400 millicuries (Nuclear-Chicago liodel 850213)

C. Cobalt 60 C. Sealed sources CD 5 sources not to exceed 100 microcuries each D. Cobalt 60 D. Any D. 10l millicuries E~ Strontium 90 E. Any ED 3 millicuries F~ Iodine 131 F. Any F ~ 101 millicuri.es G. Cesium 137 G. Any G ~ 102 millicuries H. Any byproduct H Any H. 13 millicuries material with Atomic Nos. be>>

tween 3 and 83, inc lu s ive I. Antimony 122 - 124 I. Sealed sources I. 5 sources not to exceed 2,500 curies each J. Americium 241

~

~

J ~ Sealed source J~ 6 curies Authorized use A. and B. To be used in calibration wells to calibrate instruments.

C, through li. Instrument calibration and checlcing, source fabrication and technician training.

I. and J. Storage only.

- ~

FORM AKOi$7<8A (8 ~ II U. S. ATOMIC ENF<RGY COMMISSION Page~of ~Pages BYPRODUCT MATERIAL LICENSE Supplementary Sheet License Number 31~Or<89 02 CONDITIONS 10, Byproduct materi.al may only be used at and i.n connection wi.th the operation of the licensee's facility at the Nine Mile Poi.nt Nuclear Station, Oswego, New York.

11. The li.censee shall comply with the provisions of Title 10, Part 20, Code of Federal Regulations, Chapter 1, "Standards for Protection Against Radiation."

12. Byproduct material shall be used by, or under the supervi.sion of, P. Allister Burt, Melvin A. Silliman, or Richard k. Bowers.

13, A(1) Each sealed source containing byproduct material, other than Hydrogen 3, with a half-life greater than thirty days and form other than gas shall be tested for leakage and/or in'ny contamination at intervals not to exceed six months. In the absence of a certziicate from a transferor indicating that a test has been made within six months prior Co the transfer, the sealed source shaL,L not be put into use unti1. tested.

(2) Notwithstanding the periodic leaK Cest required by t1ie prec< 'wp paragraph, any l.icei.seu seaLea sou-ce contai.ning" byproduct material is exempted from periodic leak tests provided the quantity of byproduct materi.al contai.ned i.n Che source does not exceed ten times the quantity specified for the byproduct material 9.n Column II, Schedule A, Section

'00, 10 CFR 31

'1 The periodi.c leak tesC required by this condiCion does noC

'3) apply to sealed sources that are stored and not being used The sources excepted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within six months pri.or to the date of use or transfer.

V J'

SrOIIII AtCoSY4A Ia asI U. S. ATOMIC I;NERGY COMMISSION Page 3...3

..of... Pages BYPRODUCT MATERIAL LICENSE Supplementary Sheet.

License NumbeP 1-07489" 02

13. continued COi'EDITIONS B The test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. The test sample shall be tal:en from the sealed source or from the surfaces

'r of the device in whicn the sealed source is permanently mounted stored on which one might expect contamination to accumulate.

.records of lealc test results shall be kept in units oi microcuries and maintained for inspection by the Comlaission.

C, If the test reveals the presence of 0.005 microcurie or more of removable contamination, the licensee shall imlaediately withdraw the sealed source from use and shaLl cause it ted and repaired or to be disposed of in accordance'with to be decontamina-Co>nmission re ulations, A report shall be filed within 5 days of tile test with the Director, Division of &Iaterials Licensing, U ~ S. Atomic Energy Commission, 'lashington, D. C ~, 20545, describing the equipment involved, the test results, and the corrective action taken. A copy of such report sha1.1 also be sent to the Director, l<egion I, Division of Compliance, USAEC, 376 lludson Street, llew York, New York, 10014.

D. Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State to perform such services.

14, Except as specifically provided otherwise by this license, the licensee shall possess and use byproduct material described in Items 6, 7, and 8 of this license in accordance with statements, representations and procedures contained in

.application dated June 6> 1567 and telegram from I." J. ~

Schneider received June 30, 1967.

For the.P. S. Atomic Energy Commission

-j<::f'cz,", gi; .z.

Date JUL Brnh Dtvtston of Materials Llcenslng Washtnlfton. D. C. 20SS5

'I rottsn AEC-401

( u-ss) UNITED STATES ATOMIC ENERGY COMMISSION SPECIiLL NUCLEAR MiLTERIRL LICENSE Pursuant to the Atomic Energy Act of 1954 and Title 10, Code of. Federal Regulations, Chapter 1, Part 70, "Special Nuclear Material Regulations," a license is hereby issued authorizing the licensee to receive and possess the special nuclear material designated below; to use such special nuclear material for the purpose(s) and at the place(s) designated below; and to transfer such material to persons authorised to receive it in accordance with the regulations in said Part. This license shall be deemed to contain the conditions specified in Section 70.32(a) of said regulations, and is subject to all applicable rules, regulations, and orders of the Atomic Energy Commission now or hereafter in effect and to any conditions specified below.

Licensee 3, License No,

1. Name Niagara Mohawk Power Corporation SNM-1028

4. Expiration Date

2. Address 300 Erie Boulevard West December 31, 1968, or upon Syracuse, New York 13202 conversion + cont. next age S. Docket No.

70-,1072

6. Special Nuclear Material 7. Maximum quantity of special nuclear material which licensee may possess at any one time Uranium enriched in the U-235 under this license U-235: 2230.2 kilograms isotope; and. plutonium. contained in 540 fuel elements, and, 5.54 grams contained in in-core detectors. + cont. next a e)

8. Authorised use Fuel e1ements: For storage and. inspection on1y in accordance ith the statements, representations, and conditions specified. in the licensee's pplication dated. July 7, 1967, and supplement submitted by the licensee's

t. once s Le Bceuf Lamb and. Leib dated. Au st 10 1 6 . e cont. nex~t a e

9. Quantity of special nuclear material allocated to licensee pursuant to Section 70.31(b) of said part

~e A eI CONDITIONS

10. Unless otherwise specified, the authorised place of use is the licensee's address stated in Item 2 above.

Authorized place of storage for the fuel elements: The fresh fuel vault and the spent fuel pool at the licensee's Reactor Building, Nine Mile Point Nuclear Station, Scriba, New York.

Authorized place for inspection of the fuel elements and for using the other special nuc1ear materia1 listed in Item 7, above: The Nine Mile Point Nuc1ear Station, Scriba, New York.

'4 h 1

I 4 1

I j

'OI4 Ah4401/410A U. S. ATOMIC ENERGY. COMMISSION Page 2 of 2 Pages SPHClAL NUCLEAR License Number MATERIALLICENSE Supplementary Sheet

11. Pursuant to 10 .CFR 70.24(d) the licensee is exempted from the requirements of 10 CFH 70.24(a)(1 ) in the spent fuel storage area during the period of time that the spent fuel pit is flooded, provided that the procedures described in the licensee's supplementary application submitted by the licensee's attorneys, Le Boeuf, Lamb,'

Leiby, dated. August 10, 1967, are followed.

J

'12. The licensee shall comply with the 'attached leak test condition for the sealed.

plutonium source.

+4. of Construction Permit CPPR-16 to an operating license, whichever is earlier.

Plutonium; 1.0 microgram contained in plated discs and, 480 milligrams encapsulated as a Pu-Be neutron source.

+8, Xn-core detectors, plated discs, and the Pu-Be neutron source: For use in accordance with the procedures described in the licensee's application dated July 7, 1967, and supplement submitted by the licensee's attorneys, Le Boeuf, Lamb, h Leiby, dated August 10, 1967.

For the U. S. Atomic Energy Commission Date August 1 6, 1967 b~

Robert L. Lett leld Dlvlalon of Materials Llaanalnp Waahlnpton, D. C 20545

II-CCCCI pp+

UNITED STATES

~+

~ ~

ATOMIC ENERGY COMM ISSION WASHINGTON, D.C. 20545

+~

EAtt$ CI NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 PROVISIONAL OPERATING LICENSE

'License No. DPR-17 The Atomic Energy Commission (the Commission) having found that:

a. The application for provisional operating license (application Amend-ments Nos. 2 through 13, dated May 29, 1967, July 14, 1967, September 6, 1967, May 16, 1968, September 27, 1968, October 14, 1968, November 4, 1968, January 17, 19lI9, January 17, 1969, March 10, 1969, March 28, 1969 and April 10, 1969, respectively) complies with the requirements of the Atomic Energy Act of 1954, as amended, and the Commission's regulations set forth in Title 10, Chapter 1, CFR;

b. The facility has been constructed in accordance with the application, as amended, and the provisions of Provisional Construction Permit No. CPPR-16;

c. There are involved features, characteristics and components as to which it is desirable to obtain actual operating experience before ir the issuance of an operating license for the full term requested the application;

d. There is reasonable assurance (i) that the facility can be operated at power levels not in excess of 1538 megawatts (thermal) in accord-ance with this license without endangering the health and safety of the public, and (ii) that such activities will be conducted in com-pliance with the rules and regulations of the Commission;

e. The applicant is technically and financially qualified to engage in the activities authorized by this license, in accordance with the rules and regulations of the Commission;

f. The applicant has furnished proof of financial protection to satisfy the requirements of 10 CFR Part 140;

g. The issuance of this license will not be inimical.to the common defense and security or to the health and safety of the public; Provisional Operating License No. DPR-17 is hereby'ssued to Niagara Mohawk Power Corporation (Niagara Mohawk), as follows:

1. This license applies to the Nine Mile Point Nuclear Station, a single cycle, forced circulation, boiling light water reactor, and electric

generating equipment (the facility) . The facility is located on the Nine Mile Point site on the southeast shore of Lake Ontario in Oswego County, New York, approximately seven miles northeast of the City of Oswego and thirty-six miles northwest of Syracuse, and is described in license application Amendment No. 2, "Final Safety. Analysis Report,"

as supplemented and amended (Amendments Nos. 3 through 13).

2. Subgec't to the conditions and requirehents incorporated herein, the Commission hereby licenses Niagara Mohawk:

A. Pursuant to Section 104b of the Atomic Energy Act of.1954, as amended (the Act), and Title 10,.CFR, Part 50,,"Licensing of Production and Utilization Facilities," to possess, use, and operate the facility as a utilization facility at the designated location on the Nine Mile Point site; B. Pursuant to the Act and Title 10, CFR, Part 70, "Special Nuclear Material," to receive, possess and use at any one time up to

<3800 kilograms of contained uranium 235 in connection with opera-tion of the facility; C. Pursuant to the Act and Title 10, CFR, Part 30, "Rules of General Applicability to Licensing of Byproduct.Materia1.,".to receive, possess, and use in connection. with operation of. the. facility

~'24 curies of Cobalt 60 as a sealed source; 430.millicuries of Cobalt 60 as two sealed sources of not more. than 400.millicuries and 30 millicuries each;~500 microcuries of Cobalt 60,as five sealed sources not to exceed 100 microcuries each; X01 millicuries Cobalt 60, 3 millicuries Strontium 90, 101 millicuries Iodine 131, 3.02 millicuries Cesium 137, and 3.3 millicuries of any byproduct material with Atomic Nos. between 3 and 83, inclusive, in any chemical and/or physical form; 12,500 curies Antimony 122-124 as five sealed sources not to exceed 2,500 curies each; and six'uries Americium 241 as a sealed source; and D. Pursuant to the Act and Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.

3~ This license shall be deemed to contain and is subject to the condi-tions specified in the following Commission regulations in 10 CFR Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50 '4 and 50.59 of Part 50, and Section 70.32 of Part 70, and is sub-ject to the additional conditions specified below:

A. Maximum Power Level Niagara Mohawk is authorized to operate the facility at steady state power levels up to a maximum of 1538 megawatts thermal.

B. Technical S ecifications The Technical Specifications contained in Appendix A attached hereto are hereby incorporated in this license. Niagara Mohawk shall operate the facility at power levels not in excess of 1538 megawatts thermal in accordance with the Technical Specifi-cations, and may make changes therein only when authorized by the Commission in accordance with the provisions of Section 50.59 of 10 CFR Part 50.

C. ~Re orrs In addition to the reports otherwise required under this license and applicable regulations:

(1) Niagara Mohawk shall inform the Commission of any incident or condition relating to the operation of the facility which prevented or could have prevented a nuclear system from performing its safety functions as described in the Technical Specifications. For each'such occurrence, Niagara Mohawk shall promptly notify by telephone or telegram the appropriate Atomic Energy Commission Regional Compliance Office listed in Appendix D of 10 CFR 20, and shall submit within ten (10) days a report in writing to the Director, Division of Reactor Licensing (Director, DRL),

with a copy to the Division of Compliance.

(2) Niagara Mohawk shall report to the Director, DRL, in writing, within thirty (30) days of its observed occurrence any sub-stantial variance disclosed by operation of the facility from performance specifications contained in the Final Safety Analysis Report (safety analysis report) or the Technical Specifications.

(3) Niagara Mohawk shall report to the Director, DRL, in writing within thirty (30) days of its occurrence any significant changes in transient or accident analysis as described in the safety analysis report.

(4) As soon as possible after the completion of six months of operation of the facility (calculated from the date of initial criticality), Niagara Mohawk shall begin submitting reports in writing in accordance with the requirements of the Technical Specifications.

D. Records Niagara Mohawk shall keep facility operating records in accord-ance with the requirements of the Technical Specifications.

4~ Pursuant to Section 50.60, Title 10, CFR, Part 50, the Commission has allocated to Niagara Mohawk for use in the operation of the facility 14,321 kilograms of uranium 235 contained in uranium in the isotopic ratios specified in the application. Estimated schedules of special nuclear material transfers to Niagara, Mohawk.and returns to the Commission are contained in Appendix B which. is attached hereto.

Transfers by the Commission to Niagara Mohawk in, accordance with column 2 in Appendix B will'e conditioned upon Niagara Mohawk's return to the Commission of material substantially in accordance with column 3 (including the subcolumns headed "Scrap" and "Depleted Fuel" ) ~

5 ' This license is effective as of the date of. issuance and shall expire eighteen (18) months from said date, unless extended for good cause shown, or upon the earlier issuance of a superseding operating license.

FOR THE ATOMIC ENERGY COMMISSION IhfalnaT signal Sy F, Rchroeder Peter A. Morris, Director Division of Reactor Licensing

Enclosures:

Appendix A - Technical Specifications w/Attachment A Appendix B - SNM Transfer Schedule Date of Issuance: gUg 8 2 3969

'7 UNITED .STATES. ATOMIC ENERGY COMMISSION DOCKET NO. 50-220 NIAGARA MOHAWK POWER CORPORATION

. NOTICE OF ISSUANCE OF PROVISIONAL OPERATING L'ICENSE Notice is hereby given that no request for a hearing by the appli-cant or petition for leave to intervene by any interested person having been filed following publication. of the- notice of proposed action in the FEDERAL REGISTER, the Atomic Energy Commission (the Commission) has issued Provisional Operating License No. DPR-17 to Niagara Mohawk Power Corporation (Niagara Mohawk) authorizing the licensee to possess, use, and operate the Nine Mile Point Nuclear Station, a single cycle, forced circulation, boiling w'ater nuclear reactor, located on the Nine Mile Point site on the southeast shore of Lake Ontario in the Town of Scriba, Oswego County, New York. The license authorizes Niagara Mohawk to operate the reactor at thermal power levels not to exceed 1538 megawatts, in accordance with the provisions of the license and the Technical Specifications (Appendix A) appended thereto.

.The Commission has inspected the facility and has determined that it has been constructed in accordance with the application, as amended, and the provisions of Construction Permit No. CPPR-16.

The provisional operating license was issued as set forth in the Notice of Proposed Issuance of Provisional Operating License published in the FEDERAL REGISTER on June 5, 1969, 34 F.R. 8977, except for modi-fication of the Technical Specifications as set forth in Attachment A

to the Technical Specifications as issued with Provisional Operating License No. DPR-17. These modifications (1) delete the requirements for the nondestructive testing of safety valves since all of these tests have been completed, and (2) modify the pressure for performing a leak rate test on a main steam line isolation valve to permit testing at the same pressure specified for the containment test.

A copy of License No. DPR-17, complete with Technical Specifications and Attachment A thereto, is available for public inspection at the Commission's Public Document Room at 1717 H Street, N.W., Washington, D. C.

Dated at Bethesda, Maryland,.this R< day of August, 1969.

FOR THE ATOMIC ENERGY COMMISSION

~."! ~':~"8 Cy F. ScF.-.aetna Peter A. Morris, 5irector

,Division of Reactor Licensing

P' UNITED STATES ATOMIC ENERGY COMMISSION C

WASHlNGTON, D.C. 20545 0 y+

>>14)[C NlAGARA MOHAN POHER CORPORATION DOCKET NO. 50-220 AMEND".IENT TO PROUISIONAL OPERATING LICENSE License No. DPR-17 Amendment No. 2 The Atomic Energy Commission ("the Commission" ) has found that:

A. The application for amendment dated April 20, 1970, as supplemented by Amendments 1 through 5 thereto and letter dated November 23, 1970, complies with the requirements of the Atomic Energy Act of 1954, as amended ("the Act"), and the Commission's regulations set forth in 10 CFR Chapter I; B. There is reasonable assurance (i) that the facility can be operated at power levels up to 1850 megawatts (thermal) in accordance with the'license, as amended, without endangering the health and safety of the public, and (ii) that such operation will be conducted in compliance with the regulations of the Commission, and C, The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Accordingly, Provisional Operating License No. DPR-17 issued to Niagara Mohawk Power Corporation for operation of the Nine Mile Point Nuclear Station is hereby further amended to restate subparagraphs 3.A., 3.B.,

and 3.C. in their entirety to read as follows:

3.A. Maximum Power Level Niagara Mohawk is authorised to operate the facility at steady-state power levels up to a maximum of 1850 megawatts (thermal) ~

3.B. Technical S ecifications The Technical Specifications contained in Appendix A to the license, as modified by Changes Nos. 1 through 3 and Change No, 4 appended hereto as Attachment A, are hereby incorporated in this license. Niagara Mohawk shall operate the facility

in accordance with these Technical Specifications. No changes shall be made in'the Technical Specifications unless authorized by the Commission as provided in Section 50.59 of 10 CFR Part 50.

3.C.'Re orts Niagara Mohawk sha11 make certain reports in accordance with the requirements of the Technical Specifications.

This amendment is effective. as of the date of issuance.

FOR THE ATOMlC ENERGY CO>iMISSXON Peter A. Morris, Director Division of Reactor Licensing Attachment A - Change No. 4 to the Technical Specifications Date of Xssuance: April 14, 1971

LlNlTED STATES ATOMIC"'NERGY',COMMISSION WASHINGTON, D.C, ROSis

~

April 14, 1971 Docket No. 50-220 Niagara Mohawk Power Corporation ATTN: Hr. Thomas J. Brosnan .

300 Erie'oulevard Mest Syracuse, Nev York 13202 Gentlemen:

Xn response to your application dated April 20, 1970, and amendments thereto, Amends ent No. 2 to Provisional Operating License No. DPR-17 is enclosed, 'The amendment authorizes operation of your Nine defile Point Nuclear Station at power levels up to 1850 megawatts (thermal) and incorporates changes to the Technical Specifications to provide for such .operation.

A copy of a related notice that has been forvarded to the Office of the Federal Reg'ister for publication is also enclosed.

Sincerely, Peter A. Horris, Director

~

Division of Reactor Licensing

Enclosures:

l. Amendment No. 2 to License No DPR-17 v/Change No 4

2. Federal Register Notice cc w/enclosures:

Arvin E. Upton, Esquire LeBoeuf, La=b, Leiby & >fcRae 1821 Jefferson Place, N. M.

Mashington,'. C. 20036

~ ~

o lcl. cy tSN)TL O', SPATE8" ATOMIC ENERGY COMMISSION WASHINGTON, D.C. 20545

~any oi NIAGARA'OHAWK POWER CORPORATION DOCKET- NO. 50-220 A~KND~iIENT TO PROVISIONAL OPERATING LICENSE License No. DPR-17 Amendment No. 2 The Atomic Energy Commission ("the Commission" ) has found that:

A. The application for amendment dated April 20, 1970,-as supplemented by Amend,.ents 1 through 5 thereto and letter dated November 23, 1970, complies with the requirements of the Atomic Energy Act of 1954, as amended (" the Act"), and the Commission's regulations set forth in 10 CFR Chapter I;

'. There is xeasonable assurance (i) that the facility can be operated at power levels up to 1850 megawatts (thermal) in accordance with the'license, as amended, without endangering the health and safety of the public, and (ii) that such operation will be conducted in.

compliance with the regulations of the Cori5iiission, and C. The issuance of this amendment will not be inimical to the common.

defense and security or to the health and safety of the public.

Accordingly,'rovisional Operating License No. DPR-17 issued to Niagara Nohawk Power Corporation for.operation of the Nine ~H.le Point Nuclear Station is hereby further amended to restate subparagxaphs 3.A., 3.B.,

and 3,C. in their entirety to read as follows:

3.A. Xiaximum Power Level Niagara hhhawk is authorized to operate the facility at steady-state power levels up to a maximum of 1850 megawatts (thermal) .

3.B. Technical S ccifications The Tcchnical Specifications contained in Appendix A to the license, as r::odified by Ch-nges Nos. 1 through 3 and Change No. 4 appended hereto as Attachment A, are hereby incorporated in this license. Niagax'a ~<<ohawk shall operate the facility

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in accordance with these Technical Specifications. No changes shall be made in the Technical Specifications unl'ess authorized by the Commission as provided in Section 50.59 of 10 CFR Part 50.

'3.C. ~Re orrs'iagara Mohawk shall make certain reports in accordance with

'he requirements of the Technical Specifications.

This amendment is effective as of the date of issuance.

FOR THE ATOMIC ENERGY COiiQHSSION pm',7=-

Division of Reactor Licensing Attachment A - Change No. 4 to the Technical Specifications Date of Issuance: April 14, 1971

~ a ns Hd C 27o tel se 64) STATE OF NEW YORK , DEPARTMENT OF PUBLIC WORKS Permit Fee. o~ ~ HW rermit No. g86 03 I4.

4s Deposit Rec'd for Ins. Fe I s Ck. or M. O. ~

Total Received Dated Ck. or M. O. ~~ HIGHWAY WORK PERMIT or Dated chargeable to I thmovnt)

Liability Ins. Bond g ev Policy ~

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Undertoking on file.

Expiring Under the provisions of the Highway Law, permission is hereby granted to (name ol Pcrmsttee) whose add,ess., -CO r J.R '.:.0:.1.Cr=ru ';... 4. -,.-, -.-0 ."..-.t, to (CQ .s~i n('.0 9.C s '@GING-:gg Q)O l 1XT19 cl{:rOQS Vs r< OssS  !:s.r"...".~

)brief svmmory ot work ovshotired including type of instottotion ond number ot fees)

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63.

on SH No. County as set forth and represented in the attached opplica-tion; ot the particular location or orea, or over the routes as stated therein, if required; and pursuant to the con-ditions and regulations, whether general or special, and methods of perforn)ing.work, if qnyf oil of which are set forth in the opplication and form part of this permit.

g gfn!cC Estimated Dote of Completion~ Superintendent of Public Works Doted at , New York By Dote District Engtneer, Dist, IMPORTANT THIS PERMIT, WITH APPLICATION AND DRAWING (OR COPIES THEREOF) ATTACHED, SHALL BE PLACED IN THE HANDS OF THE CONTRACTOR BEFORE ANY WORK IS STARTED.

NOTICE-It is ahsalately necessary that the permittee nayrfy~cssVZknn'~no.

, Resident Engineer, whose address is

~

s:0-t'n Tel before work is started and upon its completion.

The issuing authority reserves the right to svspond or revoke this permit, at its discretion without o hearing or the necessity of showing cause, either before or during the operations authorized.

The permittee will covse an approved copy of the application to be ond remoin attached hereto until oil work under the permit is sotisfoctorily com-pleted, in occordonce with the terms of Ihe ottoched application.

ISEE OTHER SIDE)

0 rona 4iR, sate< i P~~No 5~0 yq,. a STATE OF NEW YORK DEPARTMENT OF PUBLIC WORKS 39fbidioII of 8yeratioII arrb NailltellaIICe REVOCABLE PERMIT Issued Pursuant to Article X of the Canal Law Albrr>>y AprQ 2s QC 19.'i t

agara Noh-;>k Power Coaa. 300 Erie Blvd. hest, Syracuse, Vew York, '3202, hereinafter referred to as the "lieensec," has made application for permission t u tain nn aerial crossin~ of State Canal lands of twn c.lrict ic trans..icsinc linn cit-cuits of a potential 345 KV carried in six power wires and four st.",tic wires a" sitcom on h"fpC drawing C-7229-C, in the Town of Clay, east of Loclc 23 at Center Mne Statinns 2930+29 and 2929+12, and has filcd in this offiec maps, phns and profile, showing the state land at the location referred to and the details of the work proposed to be done.

THEREFORE, permission is hereby granted to said licensee t '""or"r crossi ~ of Sta~r t'1 7".~ n nf '>>> tr~" . gi ~ Q d of a otential 345 KV carried in six ower Y"..cs nrd four static wfren ns nliotr. o F~~C drawinr'-72?9-C in the Tctm of Cln erst nf Tnck '23 nt Cont 2930+29 nnd 2929+12.

as asked for in said application and described above, a wn'ost and expense, upon the following conditions and restrictions:

1st. This permit shall not be assigned or transferred without the written permission of thc Superintendent of Public Works.

2nd. All work authorized by this permit shall be done in accordance with thc maps, plans and profilc now on file in this ofifice, and in accordance with the special and general conditions hereinafter set forth, or directions which may bc given by the Superintenden of Public Works. Ary structures erected upon canal lands by right of this permit shall not be changed in any way without first rcceivirg written perinission of the Superintendent of Public Works to do so.

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3rd. All work authorized by this permit shall be done under the supervision of the Supcrintcndcnt of Public Works or an Inspector to be appointed by him. The work shall not be commcztccd until such time as the oflieiallv signed copy of the permit is received by the licensee. The work shall be done at such times as thc Superintcndcnt of Public Works shall direct, so as not to interfere with the free and perfect usc of the canals, or endanger thc lives or property of any persons, and particularly of those engaged in repaiv'ng, operating or navigating thc canal.

4th. In thc event that any vessel or float is subjected to delay by reason of the work authorized by this pcr-mit, the licensee shall pay to the owner of such vessel or float so delayed, such amount as will fairly compcnsatc such owner for the delay or loss of time occasioned to birn by thc operations hcrcin authorized; and in thc cvcnt that the licensee and the owner are unable to agree as to thc amount of compensation to be paid for such delay shall the amount of such payment shall be determined by the Superintendent of Public Works. Thc sum fixcd by him e binding upon and paid by the licensee to such owner. The Inspector appointed by thc Supcrintcndcnt of Public Works pursuant to the third paragraph of this permit, shall ascertain whether or not any boats have been delayed shall report such facts by thc work herein authorized, and shall determine the extent of thc damages suffered, and to thc Superintendent of Public Works, for his final determination.

5th. Any and all'canal banks or other structures which may be disturbed'or interfered with during thc of the work shall be restored to a perfect condition by thc licensee a its progress own cost and expense.

6th. Except insofar as they are specifically modified herein, the rules and regulations governing terminals and the rules and regulations governing navigation on thc Ncw York State Canals, arc hereby made a part of this SPECIAL SPECIFICATIONS AND CONDITIONS:

(a) irc trarenisaion Hre shaG be kplsced an" u.aintaincd on tlte state property. in ac-cordat:cc witn Drawing C-722o~ on fMc in this ofiice or directions which tnay be given by the Sure xintcndc".t oC Public l or'~ or his x pz sc:ntativc.

(b) Ko intcrxerencc shQl bc had with ravigation interests or with any repair or ~rove>>

tacnt trork cn or cormectcd wit)t thc canal.

(c) Zf dcc:.cd to be ncccssa~>, suit"ble ard*p:vipb"'afety devices shall bc prov:ded by thc liccnscc at its cnat cost and cxpcnse, in fora to bc approved by the Supcrintcndcnt of Pub3.ic hoxlts or his representative.

(d) Tnc Supcrintcndcnt oC Pub'tac l oxk" rcservcs the right at'ny tirte during the period in which tltis pc+it vy rennin ir. forces to attaclt to txan=dsaicn lira o'r'alas "t s 'anger cab3.c, wires, crossaxns, fixtures> ctc. as r".g bc rcc,uircd .:ir thc usc of thc depart;. nt, I".herc w~ be no cltax'gc to thc St" 0 of l<s:i York for tbc above attac.lt:.antes if ."--.". arc r ado<

(e) ne liccrsce shU~ ccrc>ly with a31 xti3es, 3ai<s ard xcgDations cC thc St-"tc "philic"ble to tii<<const ction or cvtcns.on of trans:aission lines.

(f) It is to be un".crstncd encl agreed <<!tat this tr;<nsrtission line cvcr st'a"e pro~:!rt<i is not tn be xeconst;.ctcd in ary way, withe t first receiving the written penEsaion of thc Suac.ri"-:ender<t of Public i<or'." or ni" rcprc"cntative.

(") Thc State slink oc protected agains<. clai".Lss cl KQ cs ctc s as covered by Undcrtahirg darted July 2Ss 9SSs sub 'caby the 3.ic<'nso.e and cn file with this dcpa&cnt<

(h) The licensee shQ1 pay to the State oC-?:cw Yor?c thxouglt tne Superint'cndcnt oC. Public Voxt's an issuance fec or" $ 28.00 ard q2.6.00 pcr year or fraction thcrcof, pay."..cnt t'o be r.:ade in adv"ncc. tterc w&l also be a renewal Ccc oC. v5.00 duc each year on the ar".'vcrsary c.atc oC tice pcx.".it.

~ dr ham nds Siaddd S 7th. The use of said land shag be subject at all times to the interest of the State in thc making of improve ments and repairs to thc canal system or work in connection therewith. The Superintendent of Public Works, his agents, <<mployecs and contractors, shall at all times have thc right of entry thereon, if in'he judgincnt of the "

Superintcndcnt of Public Works the State's interest shall require.

Sth. The licensee undertakes and agrees to indemnify and save harmless the State, its officers, or employees, from any and all chims, demands and recoveries arising out of the use or manner of use made by the licensee of the property which is thc subject matter oE this pernut.

9th. Thc work authorized by this permit shall be commenced promptly and progressed to completion without delay; and in the event that such work is not so commenced and progressed to the satisfaction of the Superintendent oE Public Works, this permit shall be deemed to be revoked, and said work shall not bc resumed without a renewal of this permit in writing by the Superintendent of Public Works.

10th.

he eupon The Superintendent oE h ehatt heeome the duty of the heentee, a~

Public Works reserves the right at any time to revoke and annul this permit, emote d eapente, fo th thc property which is the subject matter of this permit, any and all works and structures crcctcd by tth\a rema e 1,t:

pro e'otice thcrcon, and vacatd and surrcndcr to thc State possession thereof. Upon failure of the liccnscc to rcmove such works and structures, thc Superintendent of Public Works may summarily enter upon and remove from said prcmiscs any and all cncroachmcnts and pr'opcrty of the licensee, at the licensee's own cost and cxpcnsc Notice of revocation may bc given to thc licensee personally, or by mailing t o that

' No ctIcct enclosed in a postpaid wrapper addre ssedt BlVad ~ lee~a ea 11th. This permit shall not become effective, nor shall any work be Icommenced under thc sarnc, until thc l h

~

original thereof has been executed by the applicant, signed by thc Superintendent of Public Works, thc official seal of thc State of New York attached hereto, and an executed copy of the perinit receivedby thc liccnsce.

12th. In accepting this permit thc said licensee has in mind the possibility of thc sale or otheiwisc disposal by thc State of thc land referred to, without notice, and in such event the permission hcrcby granted will auto-matically tcrminatc.

13th. No refund will bc inade to the licensee or other party, of any portion of the fee paid for thc usc of the State property should this permit be cancelled within the specified tiine for which the fee has been paid.

IN TEsrtstoNY WttEREOF I have hereunto set my hand and affixcd thc official seal of said once, the day and year first above written.

J. BURCH McMORRAN Spdprripitrxdrpit of Pi lie IYorks.

dhaa4 superintendent od Operation M hdnhnlananen ACCEPTANCE OF PERMIT Thc undersigned hereby accepts the foregoing revocable permit and agrees faithfully to con:ply with all the terms and conditions thereoE.

Syracuso N. Y., Auri.l 20 196+

tlIAG~fta ."Blitt'odM co< 0 "aTIo't V o president

sheet c (Acknowledgment, if an individuaL)

STATE OF NEW YORK COUNTY oF On thi ay of 19 before me, the subscriber, personally appeare to me known to be the person described in, and who executed thc foregoing instrument, and he duly acknowledged to Ine that he executed the same.

Notary Public (Acknowledgment, if a corporation.)

STATE OF NEW YORK Co NTY OF

)-

On thi ay of 19! 6~ before me, the subscriber personally cam to mc known, who being by mc duly sworn, did depose and say that hc resides i

that he is th Vice President Niagara Ãohattk Povor Corporation the corporation described in and which executed thc foregoing instrument; that he knows the seal of said c'orpora-tion; that the seal affixed to said instrument is such corporate seal; that it was so afiLxcd by authority of thc Board r

of Directors of said corporation, and that he signed his name ther by like authority.

t0 RTJ.

RT J. M Notary Public McttAMARA NOtitr Ville IO Ilto Sl ~ te ot itew qoeotlfle4 Io oooo Co Ho 54 voak M1 cootottiitoo eeet toe u'i CI, 181055 50 (Acknotvlcdgment, if a firm or co-partnership.)

STATE OF NEW YORK

$$ . 1 COUNTY OF On thi ay of 19 before Ine, the subscriber, personally appcare , to Ine known and knotvn to me to bc the individual who executed thc foregoing instrument as a metnber of the co-partnership of

, who, being by Inc duly sworn, did depose and say that he resides i 'hat hc is a mcmbcr oi the above-named co-partnership which is composed of himself an

who are all the persons interested therein; that he executed the foregoing instrument on behalf of the said co.partnership and as a metnber thereof; that he 'was authorized to execute the same; and he acknowledged to me that he executed thc same on behalf of the said eo.partnership for the purposes therein stated.

Notary Pubhc

1 P APPENDIX H THEEQGQ EFFECT OF HEATED DISCHARGES ON LAKE ONTARIO

APPENDIX H THERIAC EFFECT OF HEATED DISCHARGES ON LAKE ONTARIO 1 ~ THE ENTIRE LAKE The approximate heat load expected within the next 10 years from the existing and presently proposed power (including the operating Nine Mile Point Unit 1 and the proposed Unit 2), steel, and sewage plants located on Lake Ontario is 1,800x10~ BTU/day (see Table H-1) . It is predicted that this load will produce an overall lake temperature rise of 0.08 F above the ambient lake temperature that existed bef ore the addition of heat of artificial origin.

A long-range projection of heat discharge to the lake (Ref. H-1) gives a figure of 6,350x10~ BTU/day by the year 2000. It predicted that this load will produce an overall temperature rise is of 0.28 F. In addition, the residual temperature rise in water entering the lake at its western end in the year 2000 is predicted to be about 0.1 F.

These effects were computed by use of a rather conservative model (Ref. H-2) of heat transport and dissipation in the lake, including heat lost to the atmosphere.

Complete mixing in the horizontal plane of the lake~s surface and over sufficient depth to support the lake throughout is assumed in the model.

The model consists of a steady state heat balance over the lake.

The lake temperature rise due to lake heat sources, is designated

~T and is referenced to the lake inlet temperature. See Table H-2 for the relationships involved.

An estimate of 'he yearly average overall heat transfer coefficient, K, is 100 BTU/sq ft/day F. Lake Ontario surface area, Az, is 7,500 sq miles. Yearly average flow, Q, in the St.

Lawrence River at the outlet of Lake Ontario is approximately 240 000 cfs 2 THE EASTERN END OF LAKE ONTARIO A similar computation can be performed for the portion of Lake Ontario adjacent to Nine Mile Point. Only the plants in the eastern end of the lake are considered. They include Niagara Mohawk's Units 1 4 and 5 at Oswego, and Units 1 and 2 at Nine Mile Point, PASNY's FitzPatrick Plant, an assumed plant at Sterling and the sewage plant at Oswego.

H-1

Table H-1 Thermal Inputs Into Lake Ontario Heat, Rejec-Capacity Discharge T Above Lake tion to Lake Plant. -.MW.- - Flow Cfs Ambient -F- 10~.BTU/Hr.--

NMPC Oswego, Fossil, 4 units 407 762 12.4 2..114 NMPC Oswego, Fossil, Unit 5 890 635 28.6 4 09 NMPC Nine Mile Point, Nuclear, Unit 1 610 597 '31.2 4. 18 NMPC Nine Mile Point, Nuclear, Unit, 2 ',100 1~ 188 30.9 8.21 PASNY J . A FitzPatrick, Nuclear 850 825 31.5 5 ~ 714 RGSEC Russell, Fossil 282 239 19.6 1.051 RGSEC Ginna, Nuclear 470 779 19. 6 (design) 2. 975 Ontario Hydro Richard L. Hearn, Fossil 1,200 1i 760 16.0 6. 325 Ontario Hydro-Lake view, Fossil 2i400 2~810 17.0 "10. 727 Ontario Hydro-Pickering, Nuclear 2~160 3,921 20.0 17.614 Sterling Site (Assumed) 1,000 1,000 32.0 7. 187 Stelco, Hamilton, Ont. '(Steel Co.) 1. 25~

Sewage Plant, Oswego, N.Y.

H-2

0

'I

Sewage Plant, Rochester, N.Y.

Sewage Plant, Somerset, N.Y.

Sewage Plane, Toronto, Ont. .0 ~ 9+

41980 Projection 70. 837 Table H-2 A Model of Heat Transport and Dissipation in a Lake Steady-state heat balance:

H Wj)QQT KA QT = 0 coo (1) where:

H = Heat discharged into the lake, BTU/day fC = Density x Heat capacity, BTU/cf/ F Q = Lake outflow, cfd QT = Surface temperature rise, F K = Overall surface heat transfer coefficient, BTU/sg ft/day/ F A< = Lake surface area, sq ft Rearranging:

bT H/(PCpQ + KAs) so o (2)

The approximate heat load to be discharged by the above plants into the lake is 760x10~ BTU/day. This load will produce a it temperature rise for this portion of the lake of 0. 17 F, when is assumed that there is no mixing with the rest of the lake.

Projecting to the year 2000, as previously, the overall temperature rise for the eastern end of the lake is computed to be 0.6 F.

The above temperature rises are for the plants operating continuously at 100 percent of capacity.

H-3

3- THE EFFECT OF NMP1~ NMP2~ AND FITZPATRICK ON LAKE ONTARIO In analyzing apparent that.

the effect of all three plants on the lake, the distance between the plant' it was discharge facilities is too great to permit the assumption that their input was one large discharge flow. Therefore, the area involved as broken up into two sections, one for the NMP1-NMP2 complex and the other for'he Fitzpatrick plant.

The NMP1-NMP2 complex will have a discharge flow, of 1,788 cfs with an effluent temperature of 30.9 F above the ambient water temperature. These conditions, along with a nozzle header of 57S feet will produce a heated layer with a maximum surface temperature of less than 3 F above the ambient water temperature.

By utilizing mathematical models and analyses made of existing hydraulic models of other plants, the hydrothermal patterns that will be produced offshore from the NMP1 NMP2 complex can be determined.

A mathematical analysis (Ref. H-3) prepared by QLSM provides a method for predicting surface temperature contour lines from discharges. (See Table H-3) . For the NMP1-NMP2 complex, the distance along the center line of the discharge plume to the 0.5 F surface temperature contour is approximately 4,800 feet under zero lake current conditions.

Under zero lake current, conditions, the velocity of the jets from the submerged multiport nozzle header is rapidly reduced as the surrounding lake water is entrained. when currents occur in the lake, the flow patterns of the discharge from the NMP1-NMP2 complex will change because the cooling water discharges are deflected in the direction of the prevailing current. These flow patterns are stretched out in proportion to the current velocity.

(Ref . H-4)

Using current velocities ranging from 0.2 fps to 0. 8 fps, mathematical analysis shows that the distance to the 0. S F 6 T contour has a maximum value of 21,000 feet downstream from the discharge jet (see Figure H-1) . (If the boundary between the "near" thermal field and the ~~far~~ field is that line where the initial jet reaches the lake surface, "far~~ the 0.5 F QT contour can be said to be boundary between the field and the "remote<<

field.)

H-4

50

<<C v 60 O

CP

~ 70 OQ~

o I- 8 0.0 Q 80 z

O 1.0

~90 20 100 Jl =.8 FPS 2 25 30 DISTANCE ALONG 0 OF PLUME-IO FT x

AI =.5 FPS 4.0 0

O 5.0 O

I-C7

u. 6.0 l

- 2FPS z

8.0 9.0 10.0 I I.O 0 I 2 3 4 5 6 7 8 9 10 II 12 13 14 15 16 17 18 19 20 DISTANCE ALONG %OF PLUME-10 FT FIGURE H-I DILUTION FACTOR VS. DISTANCE ALONG CENTERLINE OF PLUME-FEET

Table H-3 Model for Predicting Surface Temperature Contour Lines g (En) =

[~]

(nQ

(~) Kn Y) 2.

dimensionless temperature rise =

QTjr dT temperature rise at distance r from source temperature rise at source dimensionless radial distance = E(r) temperature dissipation coefficient radial diffusion coefficient integer parameter obtained by. rounding off 2.~ DE Q plant cooling water discharge flow D depth of the discharge layer angle between effluent outlet boundaries K(E) = modified Bessel function of 2nd kind, of argument4 and order n Also, for a given point downstream, the widths of the flow patterns decrease as the current speeds increase. See Figure H-2.

At the FitzPatrick plant, there will be a discharge flow of 825 cfs with an effluent, temperature of 31.5 F above the ambient water temperature. Also, the nozzle header will be approximately 800 feet long.

The FitzPatrick report (Ref. H-5), describes certain flow patterns that were predicted on the basis of hydraulic testing and mathematical models. Those described here for the NMP1-NMP2 complex are similar. The magnitudes of the flow pattern dimensions differ because the magnitudes of the discharges differ. (Ref. H-5)

The range of distances from the NMP1 NMP2 discharge jets to the 0.5 F 6T contour is between 4,000 feet for no lake current conditions and 35,000 feet for a 0.8 fps current in the eastward direction.

Due to the complexity of the currents in the eastern end of the lake, an extensive limnological study program was conducted by John F. Storr in May, 1963 (Ref. H-6) . The program's objectives H-5

O 0

U ll=0 2fps M =0.5 fps N= 0.8 fps O

x I

O 2

5 0 I 2 3 4 5 6 7 8 9 10 II 12 13 14 15 16 17 18 19 20 OI STANCE ALONG  % OF PLUME (IO F T.)

F I GURE H-2 WIDTH OF FLOW FIELD VS. DISTANCE ALONG CENTERLINE OF PLUME

were as follows: (1) define the offshore currents at Nine Mile Point, (2) correlate these currents with various wind regimens, and (3) determine the dilution factors applicable to the water leaving the Nine Mile Point site.

The limnological study was based on the discharge of Oswego River (located 7 miles west of NMP1-NMP2 complex) into a primarily eastward lake current. Since the Oswego River has a greater salinity than the lake, it was possible to make measurements downstream, thus, determining the percent mixing per mile.

Based on these experimental results, mathematical computations indicate that the "remote" field begins between 27,000 and 42,000 feet downstream. This range is of the same order of magnitude as the value of 21,000 feet obtained by the mathematical model of Ref. H-4 (Figure H-1), and somewhat larger than the values that the model of Ref. H-2 (Figure H-2) would predict.

4 INTERACTION BETWEEN ADJACENT PLANTS AND RECIRCULATION The effect of NMP1-NMP2 complex's thermal, discharge on FitzPatrick depends entirely on the direction of flow and the time of travel from the outfall. As the travel time (which is based upon current and wind velocities) is reduced, higher water temperatures appear at FitzPatrick with smaller depths of heated layers over the intake and the discharge structures.

Thermal studies were conducted between July and October, 1970 in the NMP1 area (Ref. H7). The plant was operating with radial flow discharge at 1/3 of the capacity of the total proposed NMP1-NMP2 complex. Also, the surface temperature contours in the immediate vicinity of the discharge were considerably higher than for the proposed complex.

The studies were made using thermistors that were located. in depths up to 10 feet below the surface. These measurements were used to provide temperature contours in the NMP1 area.

The results of the studies indicated that NMP1's radial discharge did not materially affect the locality of the FitzPatrick intake.

FitzPatrick was not constructed at the time of these thermal studies, and the influence of its intake flow was not established in the prevailing temperature contours.

The proposed NMp1 NMp2 complex is designed with a diffuser system, and has a jet velocity. and a dilution effect much greater than the existing NMP1 discharge. Furthermore, field measurements of the existing system indicated insignificant recirculation. Therefore, will occur.

it is assumed that no recirculation H-6

4 I

lt

Using a mathematical model developed by Brooks (Re f. H-4),

dilutions of 3.6, 1.7, and 1.3 are found for discharge flows at 3,200 feet downstream (distance between NMP1-NMP2 complex and FitzPatrick) under current conditions of 0. 2, 0. 5, and 0. 8 fps, respectively. These dilutions produce surface temperature rise contours ranging from a minimum of 0. 8 F to a maximum of 2. 3 F at the 3,200-foot distance.

According to a limnological study (Ref. H6) performed in the Nine Mile point area under the influence of an eastward current in the lake, distance of it is found that the percent mixing per mile for a 3,200 feet downstream ranges between 25 and 42. This mixing established dilution factors between 1. 14 and 1.24 producing surface temperature rise contours of 2.63 and 2.42, respectively.

The combined, discharge of Nine Mile Point Units 1 and 2 will, by virtue of the jet velocity, yield a surface plume with a stong lakeward trend. It would require a southeasterly current to overcome this trend and divert the plume to the vicinity of the FitzPatrick intake. Furthermore, as stated above, it would require a'urrent velocity of 0. 8 fps to yield a surface temperature rise of approximately 2.5 F at a distance of 3,200 feet downcurrent. Lake measurements (PASNY report) show that southeasterly currents of any strength are rare, and currents of the required intensity in this direction extremely so. Taking all these factors into account, the actual temperature rise sensed in the FitzPatrick plant intake will be only a fraction of this figure, for a few hours a year. Using a mathematical analysis prepared by QLSM (Ref. H-8) describing the

'characteristics of the discharge jet (such as jet diameter, velocity, flow, temperature, and dilution along the center line of the plume), one observes that the resulting surface temperature rise contour values are increased by approximately one tenth of the increase in temperature at the intake. Hence, the area within a contour of given value is increased. However, the New York State criteria applicable to the discharge of heated liquids to Lake Ontario are still not contravened.

Analyzing FitzPatrick' effect on the NMP1 NMP2 complex, one has practically the same conditions as above except the proposed intake is located in about 23 feet of water which is greater than the intake depth at FitzPatrick. Accordingly, the heated layer over the intake has a maximum temperature of about 2.5 F in a depth approximately 1/3 of the total depth at the intake. The maximum temperature rise in the intake would be 0.8 F and the surface temperature rise contours would increase by approximately 0.1 F.

It should be noted that the increase in the rise contours is partly due to the fact that surface temperature the diluted flow from the adjacent plant will mix with the other plant's discharge jets as they reach the surface.

H-7

Also, the major portion of the total jet dilution takes place near the jet nozzles, where the relative velocities are highest.

This examination of in-situ-studies, mathematical analyses and hydraulic models reveals that the criteria established by the State of New York will be met by the proposed NMPI-NMP2 complex without any problem.

5 REFERENCES H-1. Acres, H.G., Limited., Thermal Inputs to the Great Lakes, 1 96 8 2000. Niagara Falls, Ontario (February, 1 970) .

H-2 Lawler, J.P., Leoprati, J.L., and Lawler, P.J. Receiving Water Temperature Distributions from Power Plant Thermal Discharges A Lake Model. Presented at the 5th Annual Environmental Health Research Symposium, Albany, New York, May, 1968.

H-3 Letter of May 10, 1971 to Mr.,Charles V. Mangan of Niagara Mohawk Power Corporation from Dr. John P. Lawler of Quirk, Lawler 6 Matusky Engineers.

Subject:

<<Nine Mile Point Cooling Water Discharge Schemes. "

H-4. Brooks, N.H. "Diffusion of Sewage Effluent in an Ocean Current," Preen In.ternational Conference on Waste ~Dis osal in the Marine Environment, Pergamon, Press, New York,

~

(1960) .

H-5. Power Authority of the State of New York. Engineering and Ecological Studies for Design of Intake and Discharge Structures, (January 1970)

H-6. Storr, J.F. "Limnology Study Nine Mile Point, Lake Ontario,<< May, 1963.

H-7.. Storr, J.F. '-<<Three Dimensional Thermal Studies Nine Mile Point,<< July October, 1970.

H-8. Quirk, Lawlers; Matusky Engineers. Effect of Circulating Water Systems on Lake Ontario and Oswego Harbor Water Temperature and Aquatic Biology, Report

~

prepared for Niagara Mohawk Corporation, April 1971.

H-8

I 0

APPENDIX I Meteorological Calculations for Assessing Environmental Effects of Accidents

~ ~ ~ r.

1~

0 c

APPENDIX I EXHIBIT A RADIATION EXPOSURE MODELS 1 . WHOLE BODY EXPOSURE The basic mathematical model used to calculate the whole body exposures is .defined in Reference I-1 and modified as follows:

4 13

/$ 5 c(c'p x G ~Y~ z ~T (Eq- 1) ~

where:

Cloud gamma dose (rem) 9 Cg Conversion factor (3.7 x 10+ Dis/sec-ACi)

C. Flux to dose conversion factor for the i isotope I

(rem/sec-Y/cc)

Number of photons of the i'sotope emitted per disintegration ($ 's/dis)

G I

Dose (dimensionles s) i attenuation kernel for the .th isotope (Eq- 2) where:

X Average annual isotopic air-borne concentration of the i isotope (pCi/cc)

Accumulative frequency for wind speed, stability, and sector (dimensionles s)

Qi Plant release rate of the i isotope (ACi/sec)

I'I

~y,~q = Horizontal and, vertical diffusion coefficients (cm)

= Wind speed (cm/sec)

YZ = Horizontal and vertical distances from plume center line (cm)

= Sector angle over which plume is averaged (radians)

R = Distance from release point to detector postion (cm)

Equation 1 provides the yearly offsite dose to a detector located a distance of R-cm from the release point and within a sector angle of p radians. The man rem/yr is determined by multiplying the result of Equation 1 by the population density located with the sector of concern.

Values of sector dose at a distance of R (cm) are assumed to be applicable to all individuals located in that sector from a distance of R~R to R + bR. In Table 6.2-1, the cumulative man-rem for any radial distance is determined by summing the dose contributions from all sectors for the additional radial distances and adding this to the previous radial man-rem exposures.

2 THYROID EXPOSURES Mathematically the population radiological exposures can be described as follows:

hyroi J (Eq- 3)

@ R(MPC) where:

Thyroid dose (rem/yr)

Thyroid Dose Conversion factor (i.e.,~<<<.I = 1 = 1-Sr/yr) r other parameters as previously defined.

Equation 3 applies to the dose in a given sector at a radial distance R. Therefore, to determine the integrated population exposure it is necessary to multiply Equation 3 by the population distribution in a given sector and at the given distance R and sum this product for all sectors and distances to 50 miles.

Concerning the whole body dose effects from the release of noble gas activity, the steam and hence activity release rate is based on an equivalent 7 gpm water leak. The cloud gamma exposures are based on mathematical models and are presented in Tab'le 6.2-1.

I-2

C EXHIBIT-B.

DIFFUSION- -DOSE MQDELS ~

1.. 0-8 HOUR ATMOSPHERIC DIFFUSION MODEL 2 0-8 HR CLOUD GAMMA DOSE MODEL (Eq. 5) where:

Q; = Activity of the i isotope release in 0-8 hours D~~ = Cloud gamma dose received in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (rem) 3~ THYROID INHALATION DOSE (0-8 HOURS)

(Eq- 6)

= Thyroid inhalation dose" received in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (rem) 9~ = Breathing rate (cc/sec)

Qz = Dose conversion factor (rem/ci)

4. THYROID INHALATION DOSE (8 HOURS 30 DAYS) j f35 where:

= Inhalation dose received between 8 hours and 30 days (rem) in 5 REFERENCE I-1. May, M.T., and Stuart, I.F., <<Comparison of Calculated and Measured long term Gamma Doses from a Stock Effluent of Radioactive Gases,<< in Environmental Surveillance in the Vicinity of Nuclear Facilities, W.C. Reining, ed.',

Springfield, Ill., Charles C, Thomas, c..1970..

APPENDIX H THERMAL EFFECT OF HEATED DISCHARGES ON LAKE ONTARIO

I NTRODUCT I ON Supplement 1 to the Nine Mi.le Point Nuclear Station Unit 1 Environmental Report is in reply to requests transmitted to Niagara Mohawk on February 1, 1973.

4 II

1. BIOLOGICAL REQUEST 1-1 Provide all available information to substantiate the statement "Operating experience since 1969 indicates that velocities of this magnitude (2 fps) have resulted in the entrapment of only a very few fish primarily alewives, in the onshore screen well," (p. 5. 1-2).

~Res onse The statement was based upon infrequent observations of fish in the screenwell area. 'A study program was initiated in May, 1972 and is continuing to determine by actual count and physical examination the number and condition of fish entrapped in this area.

A total of 12,987 fish have been collected in a total of 146 hours0.00169 days <br />0.0406 hours <br />2.414021e-4 weeks <br />5.5553e-5 months <br /> of monitoring, spread over eight months. Of these, 5,932 were alewives.

Table Sl-l lists monthly average fish impingement rates, and indicates that the average rate for all species, for the entire sampling period, was 89 fish per hour. Using the monthly average rates, and assuming average fish weights of 0.75 ounces for alewives, 0.25 ounces for rainbow smelts and 0.4 ounces for all others, the total fish impingement for the eight months of the program so far, is:

Alewives 12,500 pounds Rainbow Smelt 1,800 pounds All Others 2,700 pounds To provide some perspective of what these values mean, the following comparisons are offered. The total commercial catch of all fish from Lake Ontario during 1970 was 3,235,000 pounds as shown in Section 2.2 of the Environmental Report.

This quantity does not include alewives which are considered to have no commercial or sport value. Therefore, the amount of 4,500 pounds presented above as an estimate of the eight month poundage of impinged fish, excluding the alewife, is only 0.14 percent of the total landings.

REQUEST 1.2 Provide details and rationale of your fish impingement monitoring program.

~Res onse A fish impingement monitoring program was carried out during the summer and fall of 1972 and early 1973 at the Nine Mile Point Nuclear Power Station Unit 1, with-;the following objectives.

1 Al

TABLE Sl-l FISH IMPINGEMENT RATES Number of Fish/Hour Month All Species Alewives Rainbow Smelt Others

'Max. Ave. Max. Ave. Max. Ave. hoax Ave June 1459 629 747 287 544 245 230 97 July 121 85 75 56 31 17 21 12 August 135 33 79 13 68 18 Sept 19 13 2 1 Oct 30 15 22 17 3 Nov 4 1 Dec 22 41 15 18 7 95 88 38 23 11 Average for entire sampling period 85 39 31 Sl. 1-2

To determine the number of fish entering the existing intake structure and retained on the traveling screens.

b . To identify diurnal and seasohal variations in the number of fish impinged per day.

To relate the monitoring program results to the design, and assess the potential for fish impingement at the proposed Unit 2 intake.

The general procedure for the impingement studies is to examine the back-washings of the traveling screens. Screen backwashing is done automatically for three minutes every hour, and all three are backwashed simultaneously.

Material washed from the screens flows into a common trough running trans-versely across the screenhouse. It then enters a conduit running north along one wall of the discharge channel at an elevation above that of the cooling water flowing in the discharge channel. At a point still inside the screenhouse the conduit ends and the washings drop into the cooling water discharge channel.

At this point in the screenhouse floor there is a removable trapdoor through which a steel basket. is lowered to catch the screen washings before they enter the discharge channel. The basket is lined with netting of 14 inch mesh size to capture small organisms. It is removed after completion of an hourly screen backwash cycle, and the collected fish are examined for physical appearance, sized, speciated, and the quantities and weights recorded.

In order to identify dirunal fluctuations in impingement, and any seasonal variation in the time of day of peak rates, intensive runs, lasting twelve hours and more, are performed at approximately quarterly intervals. Inter-spersed between these, long runs, daily programs are run twice a month, con-sisting of two or three hours in each of the three shifts.

In addition, during each shift, the trash racks are raked to capture any larger fish that may have entered the intake. So far, any large fish seen have been easily able to squirm off the rakes and drop back into the screenwell.

Finally, during every run, appropriate plant data is recorded. This includes lake temperature, intake screenwell temperature, cooling water flow rate, station power output, and ambient weather and lake conditions.

S l. 1-3

I REQUEST 1. 3 Provide number and kinds of fish collected at the bar racks in the intake bays for each day of observation.

S~es onse The studies of fish impinging on the traveling screens were conducted on sixteen days between May 30, 1972 and January 30, 1973. The number of fish impinged on the screens during a one hour period were collected from four to fourteen times a day for a total of 146 hours0.00169 days <br />0.0406 hours <br />2.414021e-4 weeks <br />5.5553e-5 months <br />.

The total catch for the monitoring period is listed in Table Sl-2, Alewives and rainbow smelt constitute more than eighty percent of the total.

Studies of daily fish movement in the lake have shown that the density of the fish population close inshore reaches a maximum during the night hours. It seemed reasonable to expect that the number of fish removed from the screens would show a similar maximum. Consequently, the first study was made from 10:00 p.m. to 8:30 a.m. on the night of May 30-31. The screen backwash (i.e., all the material that had accumulated on the screens during the hour previous) was collected each hour. The study was repeated on the night of June 22-23, from 6:30 p.m. to 6;30 a.m. with all plant systems in operation.

A third extended study was performed on July 14 from 9:30 a.m. to 10:30 p.m.

Figures Sl-l, S1-2, and S1-3 are plots of the numbers of fish impinged per.

hour during the three extended runs. The maximum catches were recorded between 11:00 p.m. and 3:00 a.m. in these studies while the minimum catches tended to occur during the late morning hours.

After the three initial studies additional studies were scheduled for two days a month. During those days, backwashings were collected for 2 or 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at a time in each of the three operating shifts. The fish analysis was expanded to measuring the length and weight of practically every fish, determining its sex and recording its appearance.

These monthly studies were conducted under various conditions of waves, winds and other weather conditions.

Table S1-3 summarizes the total catch according to date of capture and species. The table shows how many hours of monitoring were performed on each day.

REQUEST 1.4 Give percentage of fishes collected on the traveling screens which have been found to be alive.

~Res onse No studies. were conducted to determine the actual survival rate of impinged fish, but visual observation indicates that many fish are alive at the time of collection. In 1973, studies will be done to evaluate the survival for different modes of screen operation. These studies will be done throughout the year.

n J

l'

TABLE S1-2 TOTAL FISH IMPINGEMENT CATCH May 30, 1972 to Jan. 30, 1973

~seciee Number Percent to Total Alewife 5,932 45.67 Rainbow Smelt 4, 709 36. 26 Three-spine Stickleback 783 6.03 Johnny Darter 355 2. 73 Mottled Sculpine 287 2. 21 Spottail Shiner 232 1. 79 Yellow Perch 232 1:79 Troutperch 132 1.02 Gizzard Shad 100 0.77 White Perch 68 0.52 Emerald Shiner 54 0.42 Sunfish 24 0.18 Rock Bass 20 0.15 Smallmouth Bass 10 0.08 Carp

~

7 0.05 American Eel 7 0.05 Lamprey Eel 7 0.05 Common Shiner 6 White Sucker 5 Brown Bullhead 4 Mud Minnow 3 Longnose Chub 2 Goldfish 2 1 of each of 7 species 7 TOTAL 12,987 99.77 S1.1-5

NINE M IL E PO I NT NUCLEAR POWER STAT I 0 N FISH IM P IN GEMENT STUDY g 490 200 VALUES PLOTTED ARE NOS.

OF FISH CAUGHT IN THE 180 HOUR ENDING AT THE TIME SHOWN (APPROX. )

SPECIES OTHER THAN ALEWIVES SMELT G.L MOTTLED SCULPIN 3-SPINE STICKLEBACK CENTRAL JOHNNY DARTER CENTRAL MUD MINNOW I40 BLACK SCULP IN WHITE PERCH I20 ALL FISH IK 0

LLI I

Q3 80 ALEWIVES OTHER THAN ALEWIVES 0

2200 0200 0400 0600 0800 ~

IOOO l2 5-3O- 5-3I -72 TIME Figure Sl-1

NINE MILE PONT NUCLEAR POWER STATION FISH IMPINGEMENT STUDY VALUES PLOTTED ARE NOS.

OF F ISH CAUGHT IN THE HOUR ENDING AT THE TIME SHOWN I600 ALL FISH l400 l200 l000 Cl 800 OT HER THAN ALEWIVES I

I z

600 l 7m

/

400 /

/

/ // /

/ 4 J/

/

200

/

ALEWIVES 0

I800 2200 0000 0200 0400 0600 0800 6- 22-72 6-23-72 TIME Figure S1-2

I 4 " /-

A 't c

'F ~

7 r ~

'I p

NINE MILE PO INT NUCLEAR POWER .STATION FISH IMPINGEMENT STUDY JU LY I 4, I 972 VALUES PLOTTED ARE NOS.

OF FISH CAUGHT IN THE HOUR ENDING AT THE TIME SHOWN 130 120 IIO 100 ALL F IS 9O O

80 hJ ALEWIVES CL 70 M

6O LLJ 40 Z 30 OTHER THEN ALEWIVES:

20 I.E: TR. PERCH, SMELT, 3-SP. STICKBK S. SHINER'M. EEL 7 C.J. DARTER'.

10 SHINER, G.L.M. SCULPIN W. SUCKERS LAMPREY, ROCK BASS 0900 1000 IIOO 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 KKO TIME Figure S1-3

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I

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~

~

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~

~ ~

~ ~ ~

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~ ~ ~

~ ~

~ ~

"I l

REQUEST 1.5 Provide information on the spacings between the bars of the bar racks-(a) at the offshore intake (b) in the intake bay onshore

~Res onse (a) In the intake structure, the bar racks are fabricated of ~~> inch bars, spaced 10 inch on centers.

(b) In the intake screenwell, the trash racks are fabricated of 3/8 inch x 3 inch bars, spaced 3.5 inch on centers.

REQUEST 1.6 Provide measurements of intake velocity at the face of the vertical traveling screens.

~Res onse No measurements have been made of approach velocity to the traveling screens.

A velocity of 0.85 fps has been computed from the design cooling water flow rate, the known geometry of the intake screenwell, and an estimated water depth in the screenwell.

REQUEST 1. 7 Describe the extent of participation of NY State Environmental Conservation Department, U.S. Bureau of Sport Fisheries and wildlife, and other State and Federal agencies in planning of ecological studies. (p. 5.5-1).

~Res ense Prior to the beginning of these studies, the aquatic program was set up and discussed in detail with the New York State Department of. Environmental Conservation. Some field work was carried out in conjunction with their personnel. Since then, conferences have been held with that Department, annual reports have been reviewed by them and results of the program have been discussed. Some changes have been made in the program at the suggestion of the Department of Environmental Conservation.

Some conta'cts with the U.S. Bureau of Sp'ort Fisheries and Wildlife have been made. There have been personal conversations with their consultant and occasional telephone conversations with the bureau. Some limited contacts with local representatives of the U.S. Environmental Protection Agency have also been made.

I L I f I

P I

RE/VEST 1.8 Describe which portion of studies conducted since 1963 has been designated as providing "baseline information." Give the extent of natural variability and sampling error for various parameters being measured. Explain exactly how each of these measured parameters will be used to assess the operational effects of the plant in view of such natural variability and sampling error.

~Res ense

a. Baseline Information No portion of the studies has been designated as "baseline information"=

becasue of extensive natural variability. Lake Ontario is approximately 7,244 square miles in surface area with 857 linear miles of shore line and 413 cubic miles of water. The lake may be considered as an infinite biological source for any one point along the shore and as variable in biological concen-tration as any ocean coastal point. The lake is also large enough to have considerable natural variability due to heavy storms, rains, light conditions and other factors, similar again to variability of an ocean coastal site.

i<ide variability has occurred in the samplings of the various biological parameters as described below. Three examples serve to show the impracticality of establishing a "baseline".

(1) In the plankton studies of 1964, it was Sound that on any one day it was possible to find differences in zooplankton numbers up to 100 times between the shore area and a point 2 miles offshore and as much as a factor of 8 between two points a mile apart along the shore.

(2) Tagging studies of fish in August 1972 showed that individual fish were only resident in the area for a short period of time and tagged fish have been picked up as much as 10 miles to the east and 20 miles to the west. There is, therefore, no resident population to form a "baseline".

(3) In early 1970, a massive kill of alewives, probably due to extended cold conditions in the spring, reduced the alewife population to between 5 and 10 percent of that of the year before.

This in turn affected the size of the populations of larger fish in the area which were dependent (inpart) on the alewives for food. Since then, some populations of other species have changed dramatically along the southern shore of the lake including that part which is out of any influence of the station.

Sl. 1-8

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b.. Natural Variability and Sampling Error In a noncontrolled biological population, it is impractical to separate the natural variabi'lity of a given sample from any sampling error which may exist. Examples of natural variability and sample error can be seen using, as a benthic parameter, the total organic weight of the algae C~lado hera glomerata collected in a given time period, at a specified depth for all transects combined. Table Sl-4 shows the range of total weights for early summer diving at the five foot depth. The standard deviation is half of the mean value for early summer dives and exceeds the mean for late summer dives. The number of fish netted shown in table Sl-S is a representative parameter of the natural variability of fish populations. The data is from transient E-3 shore nets.

c. Operational Assessment In the strictest sense the concept of "baseline" would be the actual amount of biomass at any one location averaged over a period of years. While such information is valuable in following the trends in natural variability,'he comparison of the various biological parameters between transects and the variations in the pre-and post operational periods have proved to be most useful in assessing the impact of the discharge on the environment.

The various biological parameters have been compared at the transect nearest the discharge (E-1) with that at transect E-3, 2,000 feet to the east, an area almost free of impact by the discharge, yet similar ecologically. It is these comparisons for the pre-and post operational periods which, have been used to assess impact of the discharge. This method overcomes the problem resulting from natural'ariability and the necessity to use baseline infor-mation at any one point for comparative studies.

If some point far removed from the'ischarge were used as the control, the differences in natural variability between the control and the discharge would be so great that no information could be derived from comparison of the measurements.

S l. 1-9

C 0

C'

Table Sl-4 Total Weight - Cladophora Clomerata Weight (grams)

• Standard Deviation (grams)

Season 1969 1970 1971 1972 Mean Early Summer 35. 2 11. 44 74 5

~ 35. 1 Late Summer 72. 7 0.7 27. 5 27. 8

• Only maximum and minimum averages are shown

1 f'I K

I'C

Table Sl-5 Fish Net Studies Season Number (Fish er net)* Standard Deviation

, 1969 19 70 1971 1972 Mean (Fish per net)

Spring 139. 8 11. 5 90. 8 75. 7 Early Summer 63.0 89. 0 77.9 13. 4 Late Summer 69. 3. 33. 0 52.1 17. 7 Fall 94. 3 36.6 55.9

• Only maximum and min~urn averages are shmn

t

'I

)

REQUEST 1.9 Provide rationale for selecting 12 transects in a two mile stretch of the shore.

~Res onse The Nine Mile Point Promontory is about two miles in length. Preliminary physical limnology studies in 1963-64 had shown that current patterns in the area would carxy the thermal discharge from Nine Mile Point Unit 1 to either end,of the promontory, depending on current direction, and then out into the lake in either an east or west direction. It was decided that ten lakeward transects would be established along the promontory and that two additional transects would be located on the east and west sides of the promontory out of the influence of any discharge effluent.

The ten transects were required and have been useful for several reasons.

(a) It was important to establish the extent of variability occurring along the promontory so that the more detai,led data collected along the primary transect (E-1) and the comparative transect (E-3) could be interpreted with some degree of accuracy and intelligence. The major concentration of work is along the two transects E-1 and E-3. The work along the other transects is of a moni,toring nature.

(b) The work has not been limited to assessing the discharge at Nine Mile Point Unit 1 but has also proven valuable as a preliminary study for the FitzPatrick station.

(c) The thermal discharge does extend as far as the ends of the promontory in either direction and the transects provide repeatable locations to detect and monitor any measureable effects.

(d) The transects are also used as sighting points for the three dimensional thermal studies.

REQUEST 1.10 Give reasons for not shnchronizing data collection for various biological and water chemistry parameters.

~Res onse There is very active mixing in the lake and the purpose in measuring the water chemistry parameters was to substantiate the fact that mixing was taking place. Other parameters such as temperature, wave activity, variability of light, and water currents are of such major importance and produce such a considerable flux in biological parameters that, by comparison, any flux caused by chemical variability is of much lesser importance at this site. In addition, the thermal discharge is directly affected and modified by the physical parameters and temperature found in the lake; but not by the chemical parameters.

REQUEST 1.11 Provide quantitative data to substantiate the statement "In general the quantity of plant and animal material found along the Nine Mile Point promontory is less than other areas in the lake." (p. 2.7.7).

~Res onse There is no published quantitative data which show that the quantity of plant and animal material found along the Nine Mile Point promontory is less than other areas. This statement xesulted from research by Dr. John F. Storr Who has studied this xegion of Lake Ontario for several years,. including underwater walks for direct observations of lake bottom conditions. It continues to represent his professional judgement of the charactexistics of this promontory.

REQUEST 1.12 Provide data analyses and records of observations which show that "No adverse effect has been observed on aquatic biota in the Nine Mile Point area due to thexmal, chemical, or radiological xeleases from the station."

(p. 5, 1-5) .

~Res onse The statement was meant to indicate that no adverse effect has been observed on aquatic biota in the Nine Mile Point area due to the overall operation of.

Nine Mile Point Unit 1. Results of radiological sampling of aquatic species are presented in Table 2.8-3 of the Environmental Report. Water quality samples were collected and analyzed during the 1972 ecological investigations.

Surface and bottom samples were taken at two lake locations. Grab samples at the cooling water intake and discharge and a composite sample at the plant compositor were also taken. The suxvey was conducted for six months between April and November 1972 (May and October excluded) with samples taken monthly.

The analyses perfoxmed and the results of the analyses are presented in Table S1-6 which lists the lowest and the highest of the six values for each location. Similar measurements were made in the lake at Oswego to collect data in an axea not influenced by the Station discharge.

The nitrate-nitrogen values at Nine Mile Point ranged from 0.02 mg/l. to Oe4 mg/1 and do not appear to be significantly different from values observed at Oswego in 1970 and 1973. The average value of 0.19 mg/1 in 1972 Sor Nine Mile Point compares to 0.18 mg/1 in 1970 and 0.22 mg/1 in 1972 at Oswego.

Phosphorous values ranged from 0.01 mg/1 to 0.28 mg/1, being generally lower at Nine Mile Point than at Oswego, with averages of 0.06 versus 0.20 mg/1 respectively. The five day biological oxygen demand (BOD5) values of the lake water at Nine Mile Point in 1972 wexe similar to values observed at Oswego in 1970 and 1972. They ranged from 0 to 5 mg/1 with" an average of 1.9 mg/1 in 1972 at Nine Mile Point, whereas the average BOD5 value at Oswego in 1970 was reported as 1.2 mg/l.

0 TABLE S1-6 1972 WATER QUALITY MEASUREMENTSLAKE ONTARIO NEAR NINE MILE POINT NUCLEAR STATION SITE 30-foot Water De th 40-foot Water De th Unit 1 Sur ace Bottom Sur ace Bottom Int e Discha e ompos1 te Alkalinity ng/1 86 90 86 90 77 87 81 84 83 90 72 89 86 88 Color Units 20-30 30-40 20-3Q 40-50 10-20 30-40 20 30 30 40 1P 2P 30 4P 0-30 30-40 20-30 20-30 Sp. Conductivity, who/cn 326 330 341 344 3Q2 319 347 367 298 360 314 354 294 396 Turbidity 2 4 2 4 2 4 2 6 2 3 2 4 4 4 Phenol mg/1 0 2.25 0 1.51 0 1.32 0 1.45 0 1.32 0 2.15 . 0 1.38 mg/1 1 5 0 4 1 3 1 2 1 3 0 3 0 2 mg/1 2 42 2 51 3 40 3 41 1 44 1 25 4 13 0 7.5 0 2.2 0 3 0 2.5 0 3.25 0 4.5 0 1.3 NH3-N ng/1 N 0 4.7 0 1 0 1.7 0 0.6 0 2.30 0 0 0 NitrateN ng/1 N 0.04 0.30 0.04 0.28 0.04 0.40 0.02 0.30 0.04 0.30 0.04 0.36 0.04 0.32 T-Phosphorous ng/1 P 0.02 0.11 0.03 0.10 0.01 0.09 0.02 0.10 0.01 0.11 p.pl 0.28 0.01 0.12 Ortho Phosphate ng/1 P 0.005" 0.010* 0.005* 0 01~ Q.Q10 0.01* 0.01*

T. Volatile Solids ng/1 109 133 90 111 95 187 82 114 114 141 134 153 112 153 Chloride ng/1 22 72 23 83 22 75 24 62 28 72 26 58 36 39 Sul fate ng/1 26.5 31 23.2 31.2 28.4 36 26 30 24.5 30 26.8 29 23.5 - 33 Total Solids ng/1 266 302 197 297 250 324 223 309 284 291 271 306 255 300 Total SS ng/1 0 5 0 11 0.1 4 0 9 0 5 0 16 0 9 Beryllium ug/1 <1 5 <1 <1 15 <1 8 8 <1 <1 <1 13 Cadmium ug/1 <1 12 10 <1 4 <1 4 1 4 <<1 7 <1 4 Chronium ug/1 <15 slS <15 <15 <15 <15 =

<15 <15 $ 15 "<15 <15 <15 <15 <15 Copper ug/1 <2 <2 17 s2 <2 <2 <2 <2 68 <2 <2 <2 13 Lead ug/1 <20 164 <20 <20 <20 <20 <<20 s20 <20 25 <20 50 S20 <20 Mercury ug/1 <1 1 2 <1 1 <1 17 <1 5 <1 2 Vanadium ug/1 <60 <60 429 <60 353 <60 404 <60 353 <60 93 S60 116 Zinc Temperature ug/1 oF

<2 66

<2 70.5 18 62

8. 0*

28 68

<2 8

65. 5 0'.0* 75 72 22 61*

24 <2 6 8*

61" 52 8

~

8.0*

87.

20 26 8.0*

32 Streptococci 10. 6* 10 8* 10. 8* 30.8i 1Q,B*

8'ecal a/100 nl

~single value **taken at screenhouse discharge channel

The alkalinity, color, specific conductivity, turbidity and sulfate values showed only minor variations during the 1972 survey. The chloride concen-tration varied from 22 mg/1 to 83 mg/1 with an average of 45 mg/1, compared to the average chloride concentration of 48 mg/1 reported for Oswego in 1972.

The results of the metals analyses indicate that'he majority of samples analyzed were below the detection limits of the analytical procedure. A statistical analysis of the data was made to determine what effect sampling location had on each water quality parameter within the Nine Mile Point area.

The techniques employed were "Analysis of Variance" and "Multiple Comparison".

In all'ases, the data for a particular sampling station for any parameter was grouped by the number of observations taken over the course of the year.

Thus, it was assumed that the value of any parameter at any station was not a function of time. Any values below the appropriate detection limits were not used in the analysis, even though, in some cases, this resulted in certain stations being omitted from the analysis. The results of the statistical analysis indicated that zinc was the only measured parameter that exhibited a significant difference at the 95 percent confidence level within the sampling area. The average value for zinc was 36 p g/1, with a range from less than 9 g/1 to 75 p g/l. All in all, the water quality of the Nine Mile Point area does not appear to be drastically different from the water quality observed at Oswego in 1970 and 1972.

As discussed in the response to request 1.8, true "baseline" data for evaluation of thermal effects does not exist. However, the comparison of the various biological parameters between transects within the influence of the plume and transects outside this influence have been useful.

The basic data to show that no adverse effects have occurred due to the thermal aspects of the discharge are contained in all the study reports listed in Appendix F of the Environmental Report.

In general, these studies show that the area of the thermal discharge has become more heavily populated with fish and forage material for fish. It has become an important fishing spot for fishermen from as far away as Sodus Bay (approximately 40 miles). It is apparent from the increase in numbers of the small bottom fish and crayfish in the immediate vicinity of the discharge that plankton killed in passage through the cooling cycle are being used as food, and in turn these are attracting the larger fish..'he impingement of the warmer water from the discharge on the shore area has resulted in a decrease in overall Clado hora growth in the area, but Gammarus has increased about 6 times (as compare to areas outside the influen~ce o the discharge) and are being used heavily for food.

All the key organisms in the shore area, with the exception of Cladophora, have temperature preferendum higher than the maximum summer temperatures of the lake. The thermal discharge is, therefore, enhancing the thermal aspects of the shore area.

Sl. 1-15

i&ile the concentration of fish in the area is generally low (except for the zone close to the discharge), the total number of fish in the general area is large. Excluding fish such as darters and sculpin which are too close to the bottom for detection, the estimated number in the'rea two miles long and out to the 50 foot depth contour is at least 5,000,000. This calculation is based upon actual counts made by a recording echo-sounder along transects.

In the summer this number may dwindle to about 350,000.

I By comparison, the number of fish being entrained in the intake per day is small. The species distribution of these fish are alewives (50 percent),

smelt (33 percent), stickleback, darters, sculpin, the spottail shiner (14 percent), and others (3 percent). Yellow perch, the most abundant fish taken in the gill nets, made up only about one percent of the total number of fish entrained over a six month period. This indicates that these abundant sport fish are not being trapped.

More than 98 percent of the fish are, therefore, forage fish and even if entrained, they are returned to the lake from the backwash of the traveling screens. A number of the entrained fish undoubtedly are returned to the lake in either a dead or dying condition. Despite this, the number of dead fish seen on the bottom in the area of the discharge is very small, 2-3 at most on any one extended exploratory dive. Also they are not observed at the lake surface. It can only be concluded that almost all dead or dying fish are being used as food by the larger fish and water fowl. Since these fish are being used as food instead of living fish, the actual effect of entrainment on the fish populations would appear to be very limited.

It may be concluded, that since there is a positive factor in attraction of fish, and an increase in amounts of forage organisms for these fish, and also, low detrimental effects of plankton and fish entrainment, that the overall impact is minimal.

REQUEST 1.13 Provide quantitative information to substantiate the statement "Fish larval abundance appears to be quite low." (p. 2. 7-5) .

~Res ense This statement was based on a 1971-72 analysis of one-liter plankton samples taken from the Nine Mile Point Unit 1 screenwell. No fish or larvae were found in these samples. Additionally, both plankton tows made in the lake in 1964, and the plankton samples taken in the 1971-72 Unit 1 screenwell entrainment studies indicated an absence of fish larvae.

During benthic sampling conducted in the lake from 1968 through 1972, alewife feet of water. This occurred only during the months of June and July. Since they are pelagic and positively phototropic, alewife larvae would be expected to be found near the surface and not subject to entrainment.

S l. 1-16

REQUEST 1.14 If the fish larval abundance is quite low explain how were the larvae obtained for entrainment studies and how were the studies conducted.

Dischss the significance of these entrainment studies if the larval abundance is quite low.

~Res onse Entrainment studies to date have concentrated on effects on plankton.

Plankton tow collections were examined for presence of fish larva with little success. However, recognizing that some fisheggs and larvae may be entrained in the circulating water system, a simple model was used to hypothetically evaluate the effect of entrainment upon the fish population. This model is desctibed in Section 5.1 of the Environmental Report.

It is intended to conduct additional fish larvae studies, examining and employing new methods . \

REQUEST 1.15 Provide reasons for not proposing phyto-and zooplankton entrainment studies.

~Res onse Phyto and zooplankton entrainment studies have been conducted and will continue. However, the studies as perfoxmed to date have not provided complete answers concerning the effects of plankton entrainment. They have been considered pilot studies and have been used as an attempt to determine the best method of collection and analysis of data. The data would be used in calculating the impact of the cooling cycle on the plankton community and the lake ecosystem as a whole. When these pilot studies indicate the possibility of methods which would yield more complete answers, additional programs will be developed to measure the total effect of plankton entrainment.

Sl. 1-17

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REQUEST 1.16 The preliminary results of entrainment study conservatively indicated plankton mortality.between 10'o and 30'o (ambient temperature, bT, and residence time not mentioned) . Provide the final results for hT, of 32 F and a residence time of over 4 minutes for various ambient temperatures (including 77o F ambient) .

~Res ense The mortality rate indicated must be viewed in relationship to the species involved. The intake is in water of about 25 foot depth, and the major species being entrained are rotifers. These species are more susceptible to mechanical damage than copepods or cladocerans. In addition, the rotifer community in the holding tanks used in the experiments have been shown to completely change in species make-up at the end of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> holding period, indicating their rapid reproduction rate. lilith this rate of regen-eration, the effect of mortality is of lesser impact.

Ambient temperature, temperature difference and residence time are taken into account in the studies. The discharge sample is routinely placed in a holding t'ank and 'temperature decay takes place either naturally or with the assistance of cooling coils. The maximum temperature is maintained for far longer than the normal residence time experienced by the organisms in passing from the condenser to the point of discharge. The time lapse between initially placing the discharge sample in the holding tank and the point at which ambient temperature is reached is between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

In the experiments reported, no thermal effect could be found with temperature differences up to 20 F. i0hen temperature differences were between 20 F and 27 F (1971 data), no obvious thermal effect could be detected. However, when these data were subjected to mathematical tests there was an indication that there was a probability that some mortality was occurring due to thermal impact. In the 1972 data, when temperature differences of over 31 F were occurring, survival rates were about the same order as for lower temperature differences when ambient temperatures were low. However, 100 percent mortality occurred when maximum discharge temperatures reached 105 F or more. Subsequently, laboratory experiments were carried out to relate mortality to the temperature range from 80 F to 105 F. This experiment showed that thermal kill was related to upper temper'ature limits.

Sl. 1-18

REQUEST 1.17 Explain how the plankton data from 1964 can be used in assessing the impact of plant operation on plankton populat'ion.

~Res onse The results of the 1964 plankton studies are useful in two ways.

(a) They are sufficiently detailed to indicate that there is a sequence in dominance of species over the year, and also indicate which species were dominant.

(b) The quantitative results were of such a nature as to show that in the area of Nine Mile Point, variability in numbers between sample points could be as much as 100 times in any one day. This is due to the fact that strong currents along the Oswego-Nine Mile Point shore, which are a very persistent feature, will result in upwellings along the Nine Mile Point shore in the area of the intake. Slight changes in wind direction will also result in either sinking or upwelling along the shore.

All of these physical factors plus the normal random clumping of the plankton which occurs in the lake make any attempt to establish a "background" level a frustrating impossibility. Attempts are being made to develop studies which will indicate and measure some aspects of impact of any plankton kill on the lake ecosystem.

REQUEST 1.18 Provide the dirunal and seasonal distribution pattern for zoo-and phytoplankton in the vicinity of the intake structure at various depths.

~Res ense The thxust of the entrainment studies was to determine the effect of mechanical and thermal kill of plankton. In addition, the data from these studies indicate, in part, the variability in both species and numbers of plankton being entrained on a seasonal basis. Studies have been made 'in the lake to attempt to establish some pattern of the distribution of plankton in the area of the discharge and rate of rain-out dead plankton. These studies have had inconclusive results due to poor weather and other conditions.

REQUEST 1.19 Explain if the 20 foot depth contour covers AT isotherm of the thermal plume.

all the area underlying 1 F

~Res onse

~s The 20 foot depth contour does not cover all of the area'underlying the 1 F 4T isotherm of the thermal plume. The 20 foot depth is the compensation point

1t REQUEST 1.20 Give the size of the area sampled for each of the benthos samples taken by the divers.

~Res onse The size of the benthic area sampled by the divers is 25 x 25 centimeters.

REQUEST 1. 21 Explain usefulness of weighing ashed plant material and use of this parameter in evaluating power plant operational effects.

~Res onse major discrepancies in comparisons of dry and ashed samples were noted. It was obvious that any comparison of samples based on either dry or wet weights would, therefore, contain a large sample error due to the fact that very fine silt is engrained in the Clado hora sample and incorporated into the Clado hora filaments. Repeated washings of t e sample removed some of this silt, ut also tended to break up the filaments which were lost in the washing process.

The method of preparation of the sample was changed. Samples are washed to remove excessive silt and then dried and weighed. These samples are subse-quently ashed, and the difference between the dry weight and ashed weight gives tht; weight of th'e organic material lost by ashing. Comparison of. the organic weights eliminated the error introduced by the silt content.

The ashed weight was not used directly in evaluating the impact of plant operation, but only obtaining a parameter (organic weight) which was almost entirely free of a sampling error encountered in the laboratory analysis of the samples, Using this organic weight parameter, a pattern of distribution of Cladophora could be established and comparison of these weights has given both the pattern of impact and the factor of impact of plant operation. These represent "standing crop" as seen in the environment. The "instantaneous" thermal impact has been determined by laboratory experimentation and the construction of a graphic mathematical model into which various temperature differences can be inserted to determine the variations in growth under ambient temperature conditions within the seasonal rate of growth pattern.

Sl. 1-20

I I REQUEST 1.22 Explain the reason for not using east transect as a control for trawl sampling for fishes.. (p. 5.5-9) .

~Res onse As described in the response to request 1.8 an East transect (E-3) has been used as a control for many of the studies of effects of station operation. This transect is 2000 feet to the East of the discharge and is an area almost entirely free of impact by the discharge. The area of transect E-3 is similar ecologically to the discharge area.

To get a trawling area to the East which was as large as desired would result in trawling much further East than the East control transect E-3.

This would place the trawling area in Mexico Bay, an area that is not similar in gormorphological characteristics to Nine Mile Point. Nhile no relatively large area could be selected that would be exactly like the Nine Mile Point promontory, the lake to the Nest was considered to be more like that area than Mexico Bay.

The Nest control was also selected to aid in establishing a broad picture of the lake shore. Samples were also taken at Oswego and about 2 miles Nest of Oswego. The four sampling sites cover about 11 miles of the lake shore without leaving any large areas of lake shore unmonitored.

REQUEST 1 23 ~

Provide rationale for trawling along the whole transects. This assumes no change in populations from near shore areas to 40 ft. depth (end of transect) which may not be true.

~Res onse The twelve lakeward transects were not set up for trawling, but for other methods of fish population study, i.e., gill netting, and fish population density estimation by fathometer.

At the outset of the 1972 ecological program, one set of trawls was performed along one lakeward transect located at Nine Mile Point Unit 1 and one control transect to the west. The results were inconclusive and, thereafter, trawling was done parallel to shore along the 20 and 40 foot contours at the surface and bottom. Trawling was conducted during the daytime and the nighttime to aid in evaluating diurnal fish movements. An echo-sounding fathometer was used for maintaining course on the contour selected. The length of. the run was approx-imately one mile, extending from Niagara Mohawk's Progress Center to the James A. FitzPatrick Nuclear Power Plant. Nets are trawled just below the surface, and 5 feet above the bottom for comparison with gill net catches.

Sl. 1-21

I REQUEST 1.24 Provide complete details of studies conducted since 1969 which have verified the phenomenon that,"Fish are able to select or avoid areas of the thermal plume in response to preferred temperatures." (p. 5.1-5).

~Res onse The details substantiating the behavior of fish in relationship to the thermal discharge are contained in the reports of fish netting, fish distribution and ecological surveillance referenced in Appendix F of the Environmental Report. Copies of these reports have been provided to the Atomic Energy Commission Staff and their consultants for their information.

The pattern of attraction or avoidance to higher temperatures has been shown to be very complex. It is rarely 100 percent attraction or avoidance and is highly modified by the flow of the water in a plume and the amount of food available in the plume, It has also been recorded that the stimulus for attraction to or avoidance of areas of slightly different temperatures is weaker in the lower temperature range than in the upper temperature range.

REQUEST 1.25 Provide quantitative information obtained from diver studies which have shown significant increase in the small mouth bass population in the vicinity of the discharge. At what level were these observations significant? (p. 5.5-4)

~Res onse No quantitative measurements were made by the divers since this could have been no more than a count within a time period during which fish would come within 8 feet of the diver, the maximum visual range. Prior to plant operation, the event of seeing one bass was recorded as an unusual occurrence. In the post operational period, a diver will see 5 to 10 bass constantly while diving in the area between the shore and the discharge.

Prior to operation, fishermen in the area were a rare sight. In the post operational period, as many as 40 boats at one time have been counted. One of the field crew captured and tagged 267 fish in one day by standing onshore and casting with a rod and reel. A large majority of these were smallmouth bass . The rest were sunfish.

Sl. 1-22

REQUEST 1.26 Provide copies of data records that show no significant loss in oxygen content of water (mg. of oxygen/liter of water) during the warmest period of the year, giving exact locations of sampling. (p. 5.5-7).

~Res onse The majority of the oxygen measurements were made during the fish net studies referenced in Appendix F of the Environmental Report. The information on oxygen levels of the discharge is contained in the data for the shore net at transect E-1. These data are collected at the surface at a point about 30 feet from the discharge where surface water temperatures are those experienced at the point of upwelling from the discharge.'hese oxygen values have been compared to those found at the 7 to 10 meter'epth at transect E-1, the general location of the intake. In Table S1-7, a series of records have been compared for periods when there was a thermal discha'rge. The dates of these readings are given along with the number of readings on that date. The third column gives the mean difference between the oxygen values at the surface and the 7 to 10 meter depth. The last two columns give the saturation values for the particular temperature in which the oxygen reading was made. Oxygen loss was noted when saturation values near the intake were high. Oxygen gained was noted when these same values were low.

REQUEST 1.27 List any rare and endangered species of plants and animals found in your terrestrial survey of the plant area and transmission right-of-way. Give names of plants and animals and their locations. Describe precautions taken to preserve them.

~Res onse A cursory terrestrial survey was performed of the site area to note and record presence of flora and fauna. No rare or endangered species of plants and animals were noted either as a result of the site survey or a literature search regarding the site area.

Sl. 1-23

TABLE S1-7 Net Oxygen Change Surface vs. Intake Depth Transect E-1 humean No. of O2 Saturation ('o)

~Readin a 0~pm Discharge 7 to 10 m.

June 10-11, 1971 0.0 113. 9 103. 4 June 29-July 1, 1972 -2. 3 114. 7 105. 6 Augus t 17- 18. 19 71 +3. 7 138. 0 79. 3 August 2, 1972 +0,8 100. 0 77. 4 August 5, 1972 +l. 2 113. 9 71.6 November 5, 1971 -1.0 107. 5 97. 3 Total 14 +0.14 S1.1-24

2. TRANSMISSION LINES REQUEST 2.1 Provide the number of transmission lines which will ultimately be carried in the right-of-way. Give tower dimensions. The Environmental Report states that the 27 mile right-of-way passes through 10 miles of farmland, 4 miles of wetland, and 5 miles of wooded areas. Describe the environment the line passes through in the other 8 miles. Provide number of homes removed during construction of the right-of-way.

~Res oese The right-of-way, which was acquired at the time of the construction of. Nine Mile Point Unit 1 has a total width of 500 feet suitable for four 345 KV singlecircuit lines. The center of this right-of-way is presently occupied by two single-circuit 345,KV lines. Two single-circuit 115 KV lines are also located along the initial part of the Nine Mile Point to Clay Route. These lines parallel the west side of the 345 KV lines to a point approximately four miles south of the site in the Town of Scriba. At that point, the 115 KV lines join Niagara Mohawk's Lighthouse Hill-Oswego 115 KV lines while the two 345 KV lines continue south-easterly to Clay.

Future use of this right-of-way contemplates the installation of the proposed 765 KV transmission line associated with Nine Mile Point Unit 2. This future line would use the east side of the existing right-of-way and an additional 120 foot wide strip of land adjacent to the eastern edge of the existing right-of-way. The construction of the new line will parallel the existing 345 KV lines from Nine Mile Point Unit 1 to the proposed Volney Station site about, 9 miles south of Nine Mile Point.

Use of the remaining right-of-way is dependent upon the development of generating sites in the area.

The tangent structure used along much of the'ine Mile Point-Clay Tran..mission Line is the standard wood pole "H" frame. Tower dimensions for this structure are shown on Figure S1-4. The lattice structure was used at all strain locations such as at angles in the line. Tower dimensions for these structures are shown on Figure S1-5.

The right-of-way for the transmission line is 27 miles long. The lines pass through ten miles of farmland, four miles of wetland, five miles of wooded areas and eight miles of fallow or pasture land.

During the location of the 500 foot corridor for the Nine Mile Point-Clay Transmission Line ten (10) homes were displaced.

Sl. 2-1

4 WOOD 'H'RAME SINGLE C I RCU I T 26 26 VO,LTAGE: 345kv MINIMUM HEIGHT: 80 MATERIAL:Wood (treated) MAXIMUM HE IGHT: 100 AVERAGE SPAN:700 FOUNDAT ION: To be backf il led with crushed stone Sca le 1 = 15 Figure Sl-4

LATTICE STEEL TOWER SINGLE C IRCUIT 28- 6 28-6 VOLTAGE: 345 I<V M I N I MUM HE I GH T: 61'(to crossarm)

MATERIAL:Gal'vanized Steel MAXIMUM HE I GH T: 95 (to crossa rm)

AVERAGE SPAN: 800 FOUNDATION: Grillage or Reinforced Concrete Scale 1 =

16'igure Sl-5

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REQUEST 2 '

Describe herbicides used for maintenance of the right-of-way. Give details of location and schedule of use.

~Res onse Helicopter application of Tordon 101 with thickener was made to the northern 4 miles in the summer of 1966. The balance of the right-of-way was given a foliar application of 2,4.5-T in water from the ground in the summer of 1970.

Future application will be on the ground at five (5) year intervals with approved herbicides.

REQUEST 2,3 Provide information if the transmission facilities follow:

(a) The "Environmental Criteria for Electric Transmission Systems," published by U.S. Depts. of Interior and Agriculture.

(b) The New York Public Service Commission and Department of Environmental Conservation Rules and Regulations affecting transmission lines.

(c) Federal Power Commission's "Guidelines for the Protection of Natural, Historic, Science and Recreational Values in the Design and Location of Right-of-1fay and Transmission Facilities."

~Res onse The location and clearing of the original 500 foot corridor and construction of the two Nine Mile Point-Clay 345 KV Transmission Lines was done before 1965 and prior to the publication of the above guidelines.

in general the following guidelines were considered during design

'owever, and construction:

(a) Low-lying wet lands or marshes were avoided wherever possible.

(b) Areas of existing or future (to the extent definable) high density land use w'ere avoided.

(c) The more heavily traveled highways encountered were crossed perpendicularly wherever feasible.

(d) Only the central part of the 500 foot wide corridor was cleared leaving existing vegetation at the edge to provide visual screening until such time as additional transmission lines would be required.

(e) In certain areas continuing agricultural use of the right-of-way by the original owners is permitted providing that the use is consistent with maintenance of the reliability of the t'ransmission line.

(f) The number of large angles requiring larger steel dead end structures in the line was minimized.

S l. 2-2

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3. CHEMISTRY AND SANITARY WASTES REQUEST 3.1 Give the volume of the oxygenation pond (2800 sq. ft. area) used for sewage effluent.

~Res ense Operation is at selected depths between two and five feet. Based on the mode of operation, the volume of the pond will be between 5,600 cubic feet at a two feet depth and 14,000 cubic feet at a five feet depth. During winter'operation, the operating level can be lowered before ice formation and gradually increased to five feet by the retention of winter flows. In the spring, the level can be lowered at the time surface runoff and dilution water are generally at a maximum.

REQUEST 3.2 If it becomes necessary to clean the condenser or service water system, describe the process which will be used.

~Res onse If cleaning of the condenser or service water system becomes necessary, a high pressure water flush or other mechanical cleaning method will be used. There will be no chemical cleaning.

REQUEST 3.3 Provide data on average flow of makeup water through the demineralizer.

~Res ense The average flow of makeup water through the demineralizer is 600,000 gallons per month.

REQUEST 3.4 Describe provisions preventing oil which enters floor and equipment drains from being discharged into Lake Ontario via a storm drain.

~Res onse No equipment drains in the Station are discharged via storm drains. One floor drain from the administration building shop and stores area enters the storm drain by way of an eight inch tile drain. I(hile some small amounts of oil could possibly enter the drain the amount is minimal. No other floor drains enter the storm drain.

S l. 3-1

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REQUEST 3.5 Describe location in the lake where the detergent phosphorous concentration is measured. Give a detailed calculation showing how 0.2 ppb concentration for phosphorous was obtained. If the laundry waste discharge is not continuous, give frequency of discharge and maximum phosphorous concentration at the point of discharge.

s

~Res onse A water quality analysis recorded by the New York State Department of Environ-mental Conservation gives the minimum, maximum, and mean phosphorous concen-trations. The data that was recorded was based on samples taken at Oswego, New York, 6000 feet into the lake at a depth of 40 feet. This information is in Table 2.5-1 of the Environmental Report. The figure of 0.2 ppb reported in Section 3.7.1 of the Environmental Report is the average concentration which is is the discharge (above the concentration already existing in the lake) prior to mixing in the lake. The calculation is based upon 100 pounds of detergent released per month, fifty percent of which is sodium hexametaphosphate, and complete mixing in the discharge tunnel. The laundry waste is dumped in batches on a frequency of about one per 3.33 days as shown in Table 3.6-2 of the Environ-mental Report. Each batch is 1000 gallons, If the maximum pump rate of 50 gpm is assumed, then the maximum increase in the concentration in the discharge tunnel is 0.038 ppm. This compares to a mean lake phosphorous concentration of 0.12 ppm. Actually, the pump rate in pumping out a tank is about 20 gpm.

Therefore, as "a rule, the increase in phosphorous concentration while discharging would be on the order of 0.015 ppm.

The detailed calculations for the average concentration are based on complete mixing of 100 pounds per month of detergent in the discharge canal. Half of this is hexametaphosphate (NaP03). The mole weights of the components and the compound are:

Na = 22.99 Mole weight P = 30.97 Mole weight 0 = 16.00 Mole weight NaP03 =101. 96 Mole weight The fraction of phosphorous (P) in the compound (NaP03) is 30.97/101.96 or 0.303. This results in 15.2 pounds per month of phosphorous discharged.

The normal circulating water flow is 600 cfs. At a density of 62.32 pounds per cubic foot this represents 9.68 x 1010 pounds per month of water dis-charged. The ratio of phosphorous discharged to cooling water is 15.2/9.68 x 10 or 1.57 x 10-10. This is average concentration of phosphorous in the discharge (0.16 ppb).

A similar calculation is done to determine the maximum concentration of phosphorous in the discharge. The normal batch frequency is nine per month.

At 15.2 pounds of phosphorous per month and the normal batch frequency there are 1.69 pounds of phosphorous per batch. The volume of the batch is 1000 gallons and the maximum flow rate to the discharge canal is 50 gpm. At this flow rate it takes 20 minutes to transfer the batch to the canal. Since the circulating water flow is 600 cfs the batch is mixed with 4.48 x 107 pounds of water. Assuming complete mixing results in a maximum phosphorous concen-tration of 1.69/4.48 x 10 or 3.8 x 10 8 (0.038 ppm).

S'1. 3-2

4. NEED FOR POWER REQUEST 4. 1 Provide the 1972 summer and winter electrical power peak loads for the following New York State Power Pool members and other utilities:

Central Hudson Gas and Electric Corp.

Consolidated Edison Co, of N.Y., Inc.

Long Island Lighting Company New York State Electric and Gas Corp.

Niagara Mohawk Power Corporation Orange and Rockland Utilities, Inc.

Rochester Gas and Electric Corporation Power Authority of the State of New York Jamestown Municipal Electric System Long Sault, Inc.

Village of Freeport

~Res onse The peak electrical power loads for the New York State Power Pool members and other associated utilities are listed below. These are for the summer of 1972 and the winter of 1972-1973.

MW MW Utility Summer 1972 Winter 1972-73 Central Hudson 566 603*

Consolidated Edison 7872 6104 Long Island Lighting 2620 2277*

New York State Electric 5 Gas 1421 1724*

Ni agara- Mohawk 4392 4827 Orange 5 Rockland 579 481 Rochester Gas 5 Electric 854 827 Power Authority 800 894 James town 60 56 Long Sault, Inc. 27 14 Village of Freeport 34 29 Total 19225 17836

• January 1973 Peaks S1.4-1

REQUEST 4.2 Provide a tabulation by months of the power production of Nine Mile Point Unit 1 during 1971 and 1972.

~Res onse A tabulation by month of the power production of Nine Mile Point Unit 1 is shown below for 1971 and 1972.

Kw-Hrs Kw-Hrs Month 1971 19 72 January 295 132 000 353 762 000 February 330 811 000 377 961 000 March 372 873 000 375 008 000 April 24 068 000 5 053 000 May 7 246 000 June 184 784 000 98 875 000 July 281 706 000 341 292 000 August 344 899 000 365 996 000 September 210 617 000 240 055 000 October 52 735 000 313 025 000 November 403 058 000 399 175 000 December 429 440 000 432 104 000 Yearly Total 2 937 369 000 3 242 306 000 S1.4-2

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REQUEST 4.3 Describe problems and their resolution (if any) encountered by Niagara Mohawk in providing for the electrical load, during periods when Nine Mile Point Unit 1 was not operating or was operated at less than 80<e power in 1971 and 1972. Discuss any additional problems which Niagara Mohawk would encounter if Unit 1 were shut down.

R~ee onse When Nine Mile Point Unit 1 is shutdown or if the capacity is limited to less than 80 percent, the deficiency might be made up by increasing the output of conventional steam stations, operating gas turbines, or making purchases from any other sources available, An analysis was made for those times during 1971 and 1972 when Nine Mile Point was shutdown or operating at less than 80 percent power. Although Niagara Mohawk was able to adequately meet its customers requirements without load curtailment or voltage reduction during these particular years, it was necessary on several occasions to resort to gas turbine operation and reliance on power purchases, These details are provided on Table S1-8. The maximum purchase during this time period was 460 W during November 1972.

Since Niagara Mohawk is a member of the New York Power Pool and the Northeast Power Coordinating Council (NPCC), it has an obligation to coordinate plans for expansion of power supply facilities based on the NPCC "Basic Criteria for Design and Operation of Interconnected Power Systems". Under this criterion, new generating capacity is planned such that the probability of. loss of load under contingency would not exceed one day in ten years. Since Nine Mile Point 1 is an integral part of the New York Power Pool's plan for meeting the above criterion, a shutdown of the facility would result in Niagara Mohawk's inability to meet its reserve obligation to the New York Power Pool, thereby jeopardizing system reliability.

If Nine Mile Point Unit 1 was shutdown, both the installed capacity and energy produced by the unit would have to be replaced. As stated in Section 9.4 of the Environmental Report, a 300 hà installed reserve deficiency would be created initially by the shutdown. Lead-time constraints restrict the con-sideration of new generation for the short term. Attempts would be made to purchase capacity on a short term basis to provide for this deficiency.

However, power purchases, as discussed in Section 9.2 of the Environmental Report can not be considered as a feasible alternative on long term basis.

Therefore, if Unit 1 were to be shutdown, a capacity deficiency would exist resulting in degradation of system reliability.

S l. 4-3

TABLE S1-8 GAS TURBINE GENERATION AND PURCHASED POWER DURING PERIODS OF NINE MILE UNIT NO. 1 REDUCED OUTPUT OR SHUI'DOWNS Maximum Gas Amount of Year Period Turbine Generation (MW) Purchased Power (MW) 19 71 Jan. 13-19 260 None Jan. 24 84 None Feb. 11 298 None April 5-June 14 262 275 MW June 20 None None July 16-22 217 None Aug. 18, 19 249 None Aug. 29, 30 285 None Sept. 19-Oct. 28 262 150 Dec. 31 238 None 1972 Jan. 1 None None Jan, 11-17 136 hN 295 MW Feb. 8 None None Feb. 28-hIar. 6 292 None Mar. 23 None None April 1-July 2 190 None July 7-July 24 None None July 26-Aug. 1 None None Aug, 5 None None Aug. 26-Sept. 13 228 300 Sept. 21-27 250 40 Oct. 7-9 202 100 Oct. 28-31 237 200 Nov. 19-25 255 460 S l. 4-4

Within a year after shutdown, it is assumed that gas turbines could replace the capacity deficiency created by the shutdown. The full 610 MW would have to be replaced to account for load growth over the intervening year. An additional base load unit of at least 610 MW could be constructed as a replace-ment for Nine Mile Point Unit 1. For the purposes of this analysis it was assumed that another oil-fired base load unit would be scheduled for 1976 in addition to the Oswego Unit 6 which is already committed for that year.

In summary, as discussed in Section 9.4 of the Environmental Report, the grand total present value (1976) of shutting down Nine Mile Point Unit 1, maintaining the facility in a safe condition, and replacing the installed capacity and energy requirement would be approximately $ 793,000.000.

S l. 4-S

4 S. GENERAL REQUEST 5.1 Give the acreage found in the temporary game refuge. Describe the status of the plans for creation of, a permanent game refuge.

~Res onse Approximately 130 acres of the site were established as a natural wildlife refuge in 1969 by posting the northwest corner of the site. This posting has been maintained. There are no plans for creation of a larger refuge.

REQUEST 5.2 Provide information if the landscaping of Unit 1 is complete. Describe any erosion on the Station site or along transmission line since the plant has been operating.

~Res onse The landscaping for Unit 1 was completed in 1969, although replacement of injured or dying shrubbery continues as normal maintenance. No significant erosion on the site or along the transmission route has been observed. Land disturbed during the construction phase (1965-1969) has long since reestablished natural regrowth of ground cover which acts as an erosion deterent ~

REQUEST 5.3 Provide information and describe navagational buoys marking intake and discharge s tructures .

~Res onse The Nine Mile Point Unit 1 cooling water intake and discharge tructures, in-accord with. U.S. Coast Guard approval, are not marked with navagational buoys.

This approval was included as item 4 in Appendix G of the Environmental Report.

REQUEST 5.4 The horizontal scale on Figure 3.5-2 is inconsistent with the drawing.

Provide correct scale. Give distance from the shoreline to the discharge structure. The 0.1 mile stated in Section 3.5.2 appears to be in error.

~Res onse Figure 3.5-2 presents an incorrect scale. A revised figure is attached.

Dimensions indicated are correct. The 0.1 mile distance represents 585 feet from s cree nw el 1 to discharge structure.

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%. INTAKE SCREEN HOUSE NAX. W.S. EI..248.0'L 283 Oi ~ STONE OIKE LOW W.S. EL. 2440 EL. 228.5'L.222.5 2

I I I 00 INTAKE TUNNEL (LOOKING EAST)

SCREEN HOUSE 234.0'L EL.

230.0'L.283.0'TONE DISCHARGE DIKE A 0 8 8 0 EL. p SECTION I-I SECTION 2-2 I 0 585 0 5 IO 5 IO SCALE FEET

~ SCALE ~ FEE'Y DISCHARGE TUNNEL (LOOKING EAST)

NOTES!

ALL ELEVATIONS ARE REF ERENCEO TO USLS I935 OATUN I 00 200 S1 SCALE FEEI'XCEPT WHERE SHOWN FIGURE 3$ -2 PROFILE- CIRCULATING WATER SYSTEM

REQUEST 5.5 Provide current status of authorizations, permits and licenses connected with the operation of the facility.

~Res ense License or Permit Authorizing Agency Current Status State of New York State of New York Issued April 28, Cooling Water Discharge Department of Health 1965-Still Valid State of New York State o f New York Issued May 4, Sewage Treatment Plant Department of Health 1965-Still Valid Stack Approval US Federal Aviation Issued November 3, Agency 1966-Still Valid License to Possess or USAEC Active under Paragraph 2.C Use By-Product Material of Provisional Nuclear Station Operating License No. DPR-17, August, 1969.

License to Possess or USAEC Active under Para'graph 2.B Use Special Nuclear of Provisional Nuclear Material Station Operating License No. DPR-17, August, 1969.

State of New York State of New York Active-renewed Radioactive Material Atomic Energy Council August 28, 1972 License Provisional Nuclear USAEC Active-amendment No. 2 Station Operating Apri 1, 19 72 License No. DPR-17 Full Term Nuclear USAEC Filed July, 1972 Station Operating License Water Quality Certification State of New York Filed most recent Department Environmental request November, 1972 Conservation Liquid lfaste Discharge USEPA Filed most recent Permit (NPDES) information October, 1972 Sl, 5-2

0 REQUEST Se6 Provide results of all thermal surveys made in the Nine Mile Point area.

~Ree onse The material containing the results of all thermal surveys in the Nine Mile Point area is quite voluminous. Sorting of reports and studies concerning thermal surveys is in progress and the most pertinent will be transmitted under separate cover.

S1.5-3

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U. S. Atomic Energy Commission Docket 50-220 APPLICANT'S ENVIRONMENTAL REPORT OPERATING LICENSE STAGE CONVERSION, TO FULL-TERM OPERATING LICENSE lA8 I8 OIA UC8ar a IOA Al SUF F LEMEWT 2 A P R I L 1973 NIAGARA MOHAWK POWER CORPORATION Syracuse, New York 13202

A INTRODUCTION Supplement 2 to the Nine Mile Point Nuclear Station Unit 1 Environmental Report is in reply to re-quests transmitted to Niagara Mohawk on April 9, 1973.

REQUEST 1.

Provide fuel, operating and maintenance cost breakdown for Nine Mile Point Unit 1 facility for calendar years 1971 and 1972.

~Res onse Nine Mile Point, Unit No. 1 Cost Breakdown

• 1971 1972 Fixed 9.43 mills/kwhr 8.60 mills/kwhr 0 & M 0.94 0.85 Fuel 2. 24 2.89 Total 12.61 12. 34 Capacity Factor 63.36% 60.51%

• From Financial Reports and Semi-Annual Report of Operations REQUEST 2.

Response to Request 1.12:

2.1 Provide the physical location in Lake Ontario at which each of the measurements were taken. (Table Sl-6).

2.2 Provide all available fecal coliform data as close to the sewage discharge as possible. (Table S1-6).

2.3 provide actual location in Lake Ontario where similar measurements were made to collect data not influenced by the Station discharge. (p. Sl.l-13).

~Res onse t The request refers to Response 1.12 previously submitted by the Applicant as part of Supplement No. 1 to the Nine Mile Point Unit 1 Environmental Report.

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2.1. The physical locations in Lake Ontario of 'the various measurements presented in Table Sl-6 of Supplement 1 are illustrated on Figure S2-1 "Sampling Locations Nine Mile Point 1972".

2.2 Fecal coliform and total coliform concentrations were measured in a 24 hour composite sample collected from the effluent of the Unit 1 sanitary sewage treatment plant oxygenation pond in September 1971. During 1972 six samples collected at the locations shown in Figure S2-1 were analyzed for Fecal Streptococci. Average concentrations of these analyses are presented below including data resulting from analysis of lake water brought into Unit l.

Ox enation Pond Outlet Unit 1 Lake Xnlet Fecal Coliform (I/100 ml) 430 14 Total Coliform (5/100 ml) 9300 9300 Unit 1 Surface Bottom Surface Bottom Inlet Disc.

Fecal Strep. (8/100 ml) 10. 6 10. 8 10. 8 10. 9 10. 8 10. 6 2.3 Similar measurements of water quality of .areas not influenced by the Unit 1 discharge were made in the Oswego area, lake-ward of Niagara Mohawk's Oswego Steam Station. Specific sample locations are shown on Figures S2-2 and S2-3. (The Oswego Steam Station is located on the lakeshore about eight miles west, of Nine Mile Point).

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REQUEST 3.

Response to Request 2.2:

Provide specific herbicides planned for use on the entire trans-mission line right-of-way.

~Res ense This request also refers to data previously submitted by the Appli-cant as part of Supplement l.

The Applicant's guides for the use of. herbicides are as follows:

a) Use herbicides such as 2, 4, 5-T or similar com-pounds which are approved for use by the U. S.

Department of Agriculture, U. S. Food and Drug Administration and U. S. Environmental Protec-tion Agency for the purpose intended and as pre-scribed and directed by registered label.

b) Use no herbicides which .are on the New York State Department of Environmental Conservation restricted use list.

c) Use no herbicides within 100 feet of .water-courses or state reforestation areas.

d) Employ selective use of herbicides to maintain "tight ground cover" which will allow growth of compatible weeds and woody species and en-courage wildlife habitat growth.

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FIGURE 'S2-1 0 RADIO MEAST 0 0,000 ROOOO WSGO SCALE IN FEET OS VJ EGO SAI~AP Ll NG LOCAT l 0 '.I 3 TRAV/LINEG STATIONS NINE M I LE PO I ! 7 G iL LNETTi N G STATiONS 9 WATER QUALITY STATIONS I972 QUIRK, LAWLER 8 fs'.ATUSKY EYGINEERS TAPPAN s NEVl YORK

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OSVtEGO HAR80R wi INTAKE 8 DISCHARGE~

OSWEGO FIGURE S2-2 0 500 IOOO l500 2000 STEAM STATION WATER QUALITY AND BENTHIC (N MPC) SAM P L I NG LOCAT IONS SCALE FEET OSWEGO STEAM STATION l972 Q WATER QUALITY SAMPLING STATIONS BENTHIC SAMPLING STATIONS QUIRi<, LAWLER 8 VATUSKY ENGINEERS X

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6 i STAT ION INTAKE 8 DISCHARGE I97 I Q5 OSVIEGO STEAM STATION (NMPC.) LOTEL

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REQUEST 1 t

Provide capital cost of. Unit 1 at time of first commercial operation in 1969.

~Res onse At the time of first commercial operation on December 13, 1969 the total capital cost of Nine Mile Point Nuclear Station Unit' was $ 164,385,253.

This includes the cost of land, structures, equipment, engineering, interest and distributable costs. The. cost of the substation is also included.

REQUEST 2 Provide the capital cost of modifications to the radwaste system at time of completion and estimated time of completion.

~Res onse The costs of radwaste system modifications and estimated or actual completion dates are listed in Table S3:l.

REQUEST 3

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estimated annual fuel cost, levelized over lifetime, and assumed

'rovide capacity factor.

~Res onse The estimated levelized annual fuel cost over life is 2.8 mills per kilowatt hour at a capacity factor of 85 percent.

RESPONSE 4 Provide estimated annual operation and maintenance cost, levelized over lifetime.

~Res onse The estimated levelized annual operating and maintenance cost oyer life is 0.3 mills per kilowatt hour at a capacity factor of 85" percent.

REQUEST 5 Provide the levelized fixed charge rates applicable to Unit 1 and the breakdown into its components .

~Res onse The levelized fixed charge rates applicable to Unit 1 modifications are shown in Table S3.2. 'Ihese assume completion of modifications in 1976 and a remaining economic life of 18 years.

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tern Table S3.1 Radwas te Sys Modi ficat ions System Cost Com letion Date Upgraded Offgas 83,9SS,OOO Summer, 1975 Upgraded 'Liquid Radwaste Traveling Bed Filter 193> 000 April, 1972 Drywell Floor Drains $ 1,200 April, 1972 Remaining Modifications $ 1,081,000 Spring, 1974

Table S3.2 Fixed Charge Rates (levelized)

(Annual Charges - Percent of Initial Investment)

Cost of Capital 6.3 Federal Income Tax 3.9 Depreciation 5.6 Other Taxes 3.6 Insurance 0.5 iforking Capital 0.2 Total 20.1 Notes: a. Economic lifetime remaining - 18 years

b. Incremental cost of new capital is 9.6 percent

c. Depreciation is straight line

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