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Text

Environ Rept
	ML20069F936
Person / Time
Site:	Robinson
Issue date:	01/15/1973
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20069F918	List: ML20069F915; ML20069F921; ML20069F936;
References
	ENVR-730115, NUDOCS 9406090159
	Download: ML20069F936 (550)
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{{#Wiki_filter:. . . _ . . _ _ _ _. _ ___ 84 - U.S. ATOMIC ENERGY COMMISSION O DOCKET NO. 50-261 E N VI R O N M E N T A.L REPORT r , , ! cpt 1

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J4' L J Carolina Power & Light Company l

H. B. R O B I N S O N STEAM ELECTRIC PLANT O u n i r N O. 2 ra638aa:ai8aaisi PDR C

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l H. B. ROBINSON () STEAM ELECTRIC PLANT UNIT No. 2 ENVIRONMENTAL REPORT j TABLE OF CONTENTS l SECTION TITLE PACE

1.0 INTRODUCTION

1.0-1 il 1.1

SUMMARY

1.1-1

2.0 BACKGROUND

INFORMATION 2.1-1 i 2.1 SITE DESCRIPTION 2.1-1 2.1.1 Location 2.1-1 2.1.2 Topography 2.1-1 : 2.1.3 Population 2.1-2 2.1.4 Land Use 2.1-3 ; 2.1.5 Meteorology 2.1-5 . 2.1.6 Geology 2.1-8 2.1.7 Seismology 2.1-9 ; 2.1.8 Hydrology 2.1-13 , 2.2 GENERAL PLANT DESCRIPTION 2.2-1 2.2.1 Introduction 2.2-1 i 2.2.2 2.2-2 O 2.2.3 2.2.4 Structures Reactor Reactor Coolant System 2.2-4 2.2-5 i 2.2.5 Reactor Control 2.2-6 ! 2.2.6 Turbine-Generator 2.2-7 j 2.2., Radwaste System 2.2-7 i 2.2.8 Condenser and Circulating Water System 2.2-8 i 2.2.9 Operation of Nuclear Unit 2.2-9 2.3 PERMITS AND ENVIRONMENTAL APPROVAL 2.3-1 2.3.1 AEC Construction Permit 2.3-2 2.3.2 AEC Operating License 2.3-5 2.3.3 State Waste Water Discharge Permits 2.3-7 2.3.4 S. C. State Permit for the Impoundment of Water 2.3-8 . 2.3.5 Corps of Engineers' Water Discharge Permit 2.3-10 l 3.0 ENVIRONMENTAL IMPACT OF THE NUCLEAR FACILITY 3.1-1 3.1 LAND USE COMPATIBILITY 3.1-1 , 3.2 WATER USE COMPATIBILITY 3.2-1 3.3 HEAT DISSIPATION 3.3-1 i 3.4 CHEMTtAL DISCHARGES 3.4-1 3.5 SANITARY WASTES 3.4-1 () 3.6 3.6.1 BIOLOGICAL IMPACT Environmental Effects 3.6-1 3.6-1 3.6.2 Environmental Studies 3.6-25 ; i

ENVIRONMENTAL REPORT TABLE OF CONTENTS (Continued) i SECTION TITLE PAGE 9 3.7 RADI0 ACTIVE DISC!!ARGES 3.7-1 3.7.1 Radioactive Waste Processing System 3.7-1 i 3.7.2 Radioactiva Releases 3.7-6 ; 3.7.3 Maximum Exposed Individual 3.7-14 l 3.7.4 Populaticn "ose 3.7-14 ! 3.8 AESTHETICS 3.8-1 ; 3.9 TRANSPORTATION EFFECTS 3.9-1 3.10 TRANSMISSION LINES 3.10-1 3.10.1 Description of Transmission Lines 3.10-1 ! 3.10.2 Environmental Effects of Transmission Lines 3.10-2 3.10.3 Environmental Ef fects of Transmission Lines i That Could Not Be Avoided 3.10-4 i 3.11 POSTULATED ACCIDENTS 3.11-1 3.11.1 Introduction 3.11-1 3.11.2 Evaluation of Class 2 Events 3.11-7 3.11.3 Evaluation of Class 3 Events 3.11-9 3.11.4 Evaluation C Class 4 Events 3.11-11 3.11.5 Evaluatinn ar Class 5 Events 3.11-12 3.11.6 Evaluation of Class o Events 3.11-15 : 3.11.7 Evaluation of Class 7 Events 3.11-21 ! 3.11.8 Evaluation of Class 8 Events 3.11-24 ; () 3.11.9 Conclusions 3.11-43 4.0 ENVIRONMENTAL EFFECTS WHICH CANNOT BE AVOIDED 4.0-1 5.0 ALTERNATIVES TO THE NUCLEAR FACILITY 5.1-1 , 5.1 SPEriFIC POWER NEEDS 5.1-1 5.2 IMPORTING POWER 5.2-1 5.3 ALTERNATIVE MEANS OF POWER GENERATION 5.3-1 5.4 ALTERNATE SITES 5.4-1 5.5 COOLING WATER ALTERNATIVES 5.5-1 ] i 6.0 SHORT-TERM USES VERSUS LONG-TERM PRODUCTIVITY 6.0-1 7.0 IRREVERSIBLE AND IRRETRIEVABLE COMMITMENTS OF NATURAL RESOURCES 7.0-1 8.0 COST / BENEFIT ANALYSIS OF THE NUCLEAR FACILITY 8.0-1 8.3 GENERAL CONSIDERATIONS 8.1-1 8.1.1 Multi-Dimensional Cost / Benefit Approach 8.1-1 8.1.2 Format and Scope 8.1-2 O " l l

ENVIRONMENTAL RFPORT TABLE OF CONTENTS (Continued) () SECTION TITLE PAGE 8.2 SELECTION OF ENERGY SOURCE 8.2-1 8.2.1 Environmental Costs and Benefits 8.2-1 8.2.2 Social Costs and Benefits 8.2-2 8.2.3 Economic Costs and Benefits 8.2-4 8.2.4 ' Establishing Energy Supply and Demand 8.2-4 8.3 SELECTION OF POWER PLANT SIZE AND TYPE 8.3-1 8.4 SELECTION OF SITE 8.4-1 8.5 SELECTION OF COOLING SYSTEM 8.5-1 8.5.1 Costs and Benefits of Existing Cooling System 8.5-2 8.6 SELECTION OF TRANSMISSION SYSTEM 8.6-1 , 8.7 SELECTION OF WASTE 11ANDLING SYSTEM 8.7-1 8.8 OVERALL PROJECT

SUMMARY

8.8-1 I i l I t i i o I r i I l

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H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 ; ENVIRONMENTAL REPORT LIST OF TABLES TABLE TITLE PAGE l l 2.1-1 Typical Industries in Regicn 2.1-18 j 2.1-2 Black Creek Flow Near McBee, S. C. 2.1-20 2.1-3 Black Creek Flow Near Hartsville, S. C. 2.1-21 2.1-4 Estimated Black Creek Peak Flows in Excess of 1700 CFS 2.1-22 2.1-5 Municipal and Industrial Ground Water Usage Within 20-Mile Radius From Lake Robinson 2.1-23 2.3-1 Chronology of H. B. Robinson Unit No. 2 FSAR Review 2.3-11 3.2-1 Average Evaporative Water Losses From Lake (} Robinson With Units 1 & 2 in Operation 3.2-3 l 3.6-1 Provisional Maximum Temperatures Recommended ! as Compatible With the Well-Being of Various Species of Fish and Their Associated Biota 3.6-30 3.6-2 Tolerance Limits for Certain Fishes 3.6-31 3.6-3 Maximum Thermal Tolerance (LD-50) for Several Species of Fish 3.6-33 3.6-4 The Final Temperature Preferenda for Various Species of Fish as Determined by Laboratory Experiments 3.6-34 3.6-5 Environmental Surveillance Program for the H. B. Robinson Nuclear - Electric Plant 3.6-35 3.7-1 Estimated Maximum Annual Liquid Isotopic Releases H. B. Robinson Unit No. 2 3.7-17 3.7-2 Radioactive Releases in Liquids From H. B. Robinson Unit 2 (Sept. 1970 - Aug. 1971) 3.7-18 3.7-3 Lake Robinson Fish Distribution 3.7-19 O i

3 ENVIRONMENTAL REPORT LIST OF TABLES (Continued) i TABLE TITLE PAGE l l 3.7-4 Whole Body Exposure From Estimated Maximum Annual Liquid Isotopic Releases-H. B. Robinson Unit No. 2 3.7-20 l 3.7-5 Whole Body Doses From Releases to Lake Robinson (Sept. 1970 - Aug. 1971) 3.7-21 3.7-6 Estimated Annual Gaseous Release by Isotope From H. B. Robinson Unit No. 2 3.7-22 ] 3.7-7 Gaseous Releases From H. B. Robinson Unit No. 2 3.7-23 3.7-8 Population Exposure From Caseous Releases at the H. B. Robinson Steam Electric Plant 3.7-24 I i l 3.9-1 Container Design Restrictions 3.9-6 3.11-1 Classification of Postulated Accidents and Occurrences 3.11-44 3.11-2 Summary of Doses From Postulated Accidents and () Occurrences 3.11-45 5.1-1 CP&L Power Resources, Load, and Reserves by Months With Robinson No. 2 in Service 5.1-4 5.1-2 CP&L Power Resources, Load, and Reserves by Months With Robinson No. 2 in Service 5.1-5 5.1-3 CP&L Power Resources , Load , and Reserves by Months With Robinson No. 2 Halted 11/71 - Capacity Included In Allocations 5.1-6 5.2-1 CP&L, Duke, SCE6G, & VEPCO Power Resources, Territorial Loads, and Reserves 5.2-3 5.2-2 CP&L, Duke, SCE&G, & VEPCO Power Mesources, Territorial Loads, and Reserves 5.2-4 5.2-3 CP&L, Duke, SCE&G, & VEPC0 Power Recources, Territorial Loads, and Reserves 5.2-5 8.8-1 H. B. Robinson Unit No. 2 Cost / Benefit Summary 8.8-2 () 11

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4 l H. B. ROBINSON STEAM ELECTRIC PLANT O UNIT NO. 2 ENVIRONMENTAL REPORT LIST OF FIGURES l l FIGURE TITLE I 1.1-1 Aerial Photograph of H. B. Robinson Plant Taken in October, 1971, Showing Fossil Unit No. 1 and Nuclear Unit No. 2 , 2.1-1 General Site Location Map l l 2.1 2 Plant Site Boundary

2. 1-3 General Site Topography 1

2.1-4 Site Environs Details I 2.1-5 Population Distribution 0-5 Miles j J 2.1-6 Population Distribution 0-50 Miles j 2 .1- 7 Annual Wind Rose H. B. Robinson Site Data i

          - (:)                        2.1-8                    Persistence Wind Rose H. B. Robinson Site Data i

2.1-9 Plant Site Geologic Map 2.1-10 Plant Site Geologic Column 2.1-11 Plant Region Earthquakes 2.2-1 Plant Plot Plan 2.2-2 Reactor Vessel Internals 2.3-1 Flow Diagram of the Normal Processing of an Application for the AEC Construction Permit 2.3-2 Flow Diagram of the Normal Processing of an Application for the AEC Nuclear Facility Operating Permit 4 2.3-3 Flow Diagram of the Normal Processing of an Application for the State Waste Water Discharge ; Pe rmits . j . () . i i

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l ENVIRONMENTA'L REPORT i (} LIST OF FIGURES (Continued) l 1 FIGURE TITLE 2.3-4 Flow Diagram of the Normal Processing of an Application for South Carolina Permits for Impoundment of Water ; t 2.3-5 Flow Diagram of the Normal Processing of an { Application for the Discharge Permit in ; Navigable Waters , f 3.3-1 Lake Robinson Isotherms at 100 Ft Upstream [ of Dam (From Survey on October 14, 1971) 3.3-2 Lake Robinsca Isotherms at 0.8 Miles Upstream of Dam (From Survey on October 14, 1971) 3.3-3 Lake Robinson Isotherms at the Central Co-op Line (From Survey on October 14, 1971) : k 3.3-4 Lake Robinson Isotherms from the Gas Lines j to Easterlings Landing (From Survey on October 14, 1971) ! 3.3-5 Lake Robinson Isotherms at the Lower Road (From Survey on October 14, 1971) 3.3-6 Lake Robinson Isotherms at the Discharge (From Survey on October 14, 1971) 3.6-1 Thermal Tolerance of Life Stages (Jensen, 1969) 3.6-2 Surface Water Temperature ( F) Isotherms in Lake Robinson in September 1971 3.6-3 Temperature Isotherms ( F) in Lake Robinson Along Cross Section A With Unit No. 2 Operating (9/17/71) 3.6-4 Temperature Isotherms ( F) in Lake Robinson Along Cross Section B With Unit No. 2 Operating (9/17/71) 3.6-5 Temperature Isotherms ( F) in Lake Robinson Along Cross Section C With Unit No. 2 Operating (9/17/71) O 11

ENVIRONMENTAL REPORT LIST OF FIGURES (Continued) FIGURE TITLE 3.6-6 Temperature Isotherms ( F) in Lake Robinson Along Cross Section D With Unit No. 2 Operating (9/17/71) , 3.6-7 Temperature Isotherms ( F) in Lake Robinson Along Cross Section E With Unit No. 2 Operating (9/17/71) 3.6-8 Temperature Isotherms ( F) in Lake Robinson . l Along Cross Section P With Unit No. 2 Operating (9/17/71) 3.6-9 Temperature Isotherms ( F) Along 500 Foot Radius Around Discharge With Unit No. 2 i Operating (9/17/71) ; 3.6-10 Temperature Isotherms ( F) in Lake Robinson Along Cross Section A Prior to Operation of Unit No. 2 (9/62) 3.6-11 Temperature Isotherms ( F) in Lake Robinson Along Cross Section B Prior to Operation of Unit No. 2 (9/62) 3.6-12 Temperature Isotherms ( F) in Lake Robinson I Along Cross Section C Prior to Operation of Unit No. 2 (9/62) j 3.6-13 Temperature Isotherms ( F) in Lake Robinson Along Cross Section D Prior to Operation of Unit No. 2 (9/62) 3.6-14 Theoretical Limits of Oxygen That Can Be Dissolved in Water at Various Temperatures 3.6-15 Lag In Dissolved oxygen Content of a Stream Due to the Discharge of Biodegradable Material (Krenkel & Parker, 1968) 3.6-16 Response of the Protozoan Community to a Brief Temperature Shock of 48 F (Cairns, 1969) 3.6-17 Environmental Sampling Points i O 111

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t i ENVIRONMENTAL REPORT LIST OF FIGURES (Continued) ; O

i l FIGURE TITLE i !

3.10-1 Transmission System in Vicinity of Robinson 7

P lan t ;

l 3.10-2 Location of 230 KV Transmission Lines Extending From Robinson Plant , ! 3.10-3 230 KV Transmission Line Tangent Structure . a 8.1-1 Cost / Benefit Decision Process A L i 4 I p f 1 i

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1.0 INTRODUCTION

j On July 31, !970, the AEC issued to Carolina Power & Light Company a facility operating license DPR-23 which permitted operation of . the 11. B. Robinson Unit No. 2 at a power level not to exceed 5 MWt. The unit attained initial cri'.icality on September 20, 1970. The low power , level restriction was rer.oved on September 23, 1970 and CP&L was authorized to operate the unit at power levels not to exceed the licensed power level ; of 2,200 MWt. The unit was declared to be in commercial operation on + March 7, 1971 and has provided 1,473,666 MW-hr. of net electrical output for the CP&L system as of November 1,1971. On September 9,1971, the Atomic Energy Commission caused to be published in the FEDERAL REGISTER (36 F.R. 18071) a revision of Appendix D of its regulation in 10 CFR Part 50, which became effective upon publica- h tion. Revised Appendix D is an interim statement of Commission policy and i procedure for the implementation of the National Environmental Policy Act of 1969 (NEPA). The revised Appendix D is divided into five sections. Section A deals with the basic procedures for implementing NEPA, while Sections B, C, and D deal with procedures applicable to certain categories of permits or licenses aircady issued or for which applications are pending. ; Section E defines the categories of proceedings in which the Commission will f consider and determine whether a permit or license already issued should be suspended pending ecmplction of the NEPA environmental review and sets out the factors to be considered by the Commission in making its determinations. This Environmental Report is submitted in response to Section B of the revised Appendix D. It discusses and assesses the various environ- i 1 mental implications of the operation of the !!. B. Robinson Unit No. 2. The l l report also includes additional background information describing the site, j the environmental monitoring programs and the components and systems of the unit related to the analysis of the environmental impact of the facility. The operating history of the unit to date is also discussed in the report to demonstrate the unit's compatability with the environment and its ability to operate with no significant adverse effects on the environment. 1.0-1 !

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. 1.1

SUMMARY

j !O l I CP&L is an electric utility which serves an approximately j l 30,000 square mile area in North Carolina and South Carolina. This _! area includes a substantial portion of the Coastal Plain and lower . i l Piedmont regions of North Carolina and South Carolina and an area of i western North Carolina in noc around the City of Asheville. Electric j t service is renderert to m er 200 communities with populations of over 500 persons. In addition, CP&L provides wholesale service to 24 munic- ! ipal electric systems, 18 rural electric cooperatives and 2 privately J

owned utilities. The estimated total population in the territory served -

i by CP&L is in excess of 2,800,000 persons. , I t I ! The operation of the Robinson Unit No. 2 is essential to the , ability of CP&L to meet its load requirements. The decision to construct the unit was based on CP&L's load projections in 1965 which indicated i that a unit of this size was required to meet system load requirements in 1970 and beyond. The Robinson Unit No. 2 is CP&L's largest generat- I O ing unit constituting approximately 16% of its generating capability. With reserve margins in the Virginia-Carolina territory smaller than { desirable to assure a reliable power supply for the territory, the energy supplied by the unit is also important to neinboring utility l l ! systems. ; The H. B. Robinson Plant site is in northeastern South Carolina 56 miles ENE of Columbia, the state capital. The location is about 25 miles NW of Florence and about 35 miles NNE of Sumter, S. C. The site i is located on the southwestern corner of Lake Robinson which was impounded in the late 1950's to furnish cooling water for the Robinson Plant, both ! the initial 185 MWe fossil unit that was placed in service in 1960 and i i future plant additions. The total site area including Lake Robinson is more than 5,000 acres. Farming is the predominant activity in the sparsely l populated environs of the plant site. The region is gently rolling and .

is not subject to severe persistent inversions. l O ;

1.1-1 i

l l 1 ! l 1 I The H. B. Robinson Unit No. 2 is a nuclear generating unit de-signed to produce initially 2200 MWt and 739 FMe of gross power. The j unit is expected to be capable of an ultimate output of 2300 MWt. All steam and power conversion equipment, including the turbine generator, is designed to permit generation of 769 }Me of gross power. l

1 1

I The nuclear power plant incorporates a closed-cycle pressurized l water Nuclear Steam Supply System and a Turbine-Generator System both ' ! provided by the Westinghouse Corporation. Equipment includes systems for the processing of radioactive wastes, handling of fuel, electrical dis-tribution, cooling, power generation structures, and all other on-site facilities required to provide a complete and operable nuclear power plant. 8 4 The Nuclear Steam Supply System consists of a pressurized water 1 i reactor, Reactor Coolant System, and associated auxiliary fluid systems. The Reactor Coolant System is arranged as three clo1ed reactor coolant loops connected in parallel to the reactor vessel, each containing a i reactor coolant pump and a steam generator. An electrically heated 4 pressurizer is connected to one of the loops. The reactor core is com- , posed of uranium dioxide pellets enclosed in Zircaloy tubes with welded a > , end plugs. l q The plant is equipped with systems for processing radioactive , 1 gaseous and liquid wastes. Radioactive fluids enter the Waste Disposal j System and are collected in sumps and tanks until determination of treat-l ment is made. The system design and operation are characteristically I directed toward minimizing releases to unrestricted areas. The bulk of I radioactive liquid waste is processed and retained inside the plant by i the Chemical and Volume Control System recycle train, while radioactive gases are held up in gas decay tanks a suitable period of time for decay. J. i All discharge routes are appropriately monitored and safety features are incorporated to preclude releases in excess of 10 CFR 20 and Appendix I

of 10 CFR 50.

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i Several engineered safety features have been incorporated into the reactor containment design to' reduce the consequences of postulated accidents. These safety features include a Safety Injection System; an Air Recirculation Cooling System; and a Containment Spray System. The inherent design of the pressurized water, closed-cycle reactor significantly reduces the quantities of 11ssion products which I might be released to the atmosphere. Four barriers exist between the < 1 fission product accumulation and the environment. These are the uranium dioxide fuel matrix, the fuel cladding, the reactor vessel and coolant loops, and the reactor containment building. .) The major structures of the nuclear plant are the Reactor Containment Building, Auxiliary Building, Turbine Building, and Fuel Handling Building. These structures provide an aesthetically pleasing appearance. The unit condensers are cooled by water taken from Lake Robinson which then is returned to the lake by a 4.2 mile discharge canal to provide an effective cooling system. O There has been no opposition to the construction or operation of Robinson Unit No. 2. From the inception of the project, CP&L has > worked with numerous Federal, State, and Local governmental agencies in an effort to assure compatibility of the unit with its environs. CP&L will continue to cooperate with appropriate governmental agencies to ensure that all provisions of applicable permits and licenses are met. The impact of the operation of Unit No. 2 on the environment has been assessed with regard to land use, water use, heat dissipation, chemical discharges, sanitary wastes, biological effects, radioactive discharges, aesthetics, transportation, transmission lines, and postulated accidents. Althougl the assessment has indicated that some impact in these areas will be experienced, the ef forts which Cp6L has expended to reduce these impacts will assure compatibility with the environment. O 1.1-3

l CP&L considered various factors in arriving at the decision f to construct an additional generating unit at the Robinson Plant. Evalua-I tion was made of the need to provide electrical service to its customers, the possibility of importing power to meet the requirements, the type of generating unit to be installed, cooling water requirements, and alternate sites. A nuclear addition to the Robinson Plant was the most feasible j alternative for providing the required generation. 1 Figure 1.1-1 is an aerial photograph of the plant taken in i October 1971, showing fossil Unit No. 1 and nuclear Unit No. 2. This ' photograph illustrates the minimum aesthetic impact on the environs created by the nuclear unit and indicates the progress in eliminating construction effects. The construction and operation of the Robinson Unit No. 2 necessarily involves the commitment and use of certain natural resources. Ilowever, Robinson Unit No. 2 represents a reasonable commitment of resources consistent with benefits to be derived from its operation. The resulting cost / benefit analyses confirms the environmental responsibility shown in the design, construction and operation of the H. B. Robinson Unit No. 2. O l.1-4

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2.0 BACKGROUND

INFORMATION 2.1 SITE DESCRIPTION l 2.1.1 Location ) i The site is located in the western corner of Darlington County, South Carolina, on the southwest shore of Lake Robinson about 4.5 miles WNW of llartsville. The location is about 25 miles NW of Florence, about 35 miles NNE of Sumter and about 56 miles ENE of Columbia, South Carolina. , Coordinates of the site are latitude 34" 24.2' N and longitude 80* 09.5' W. L The Universal Transverse Mercator (UTM) coordinates are 3,806,800 meters north and 577,500 meters east. Its location is shown in Figure 2.1-1. The North Carolina-South Carolina border is 28 miles north of the site and the Atlantic Ocean is about 88 miles to the southeast. , N Initial development of the Robinson Plant site began in 1957 with the construction of Unit No. 1, a 185 MWe fossil unit which was placed in O commercial operation in 1960. Development of the site anticipated future f expansion of the plant and included the construction of Lake Robinson built to accommodate a total plant capacity of 1200 MWe. Figure 2.1-2 is an aerial photograph depicting the site boundaries and details of the site which totals more than 5,000 oeres (including the lake). The nuclear j plant is located on the sh- e of Lake Robinson adjacent to the coal-fired Unit No. 1. 2.1.2 Topography 1 The Robinson Plant is on the southern edge of the Sand Hills region of South Carolina. General topography of the region within a 50-mile radius of the plant is shown in Figure 2.1-3. This region is typified by rolling hills interspersed with water courses and covered with wooded areas which can be seen in Figure 2.1-3 and Figure 2.1-4 which is a topographic map covering the area within a 5-mile radius of the plant. To the south and i cast of the site, the terrain becomes flat and swampy in the coastal plain. O 2.1-1

P Lake Robinson, a principal feature of the site, is about 4,000 feet wide at the plant and about 7-1/2 miles long at its high water ele-vation of 222 ft. m.s.1. Minimum lake elevation is 210 ft. m.s.1. Land surface surrounding the lake rises to about 40-50-feet above the maximum lake elevation. The surrounding terrain reaches an elevation of 510 ft. m.s.1. about 5 miles northeast of the site. 2.1.3 Population Figure 2.1-1 shows the location of population centers of over 25,000 people within a radius of 100 miles of the site. On the basis of population projections, Florence (25 miles SE), 1970 population of 25,997 is the only center within a 50-mile radius of the site. Other population centers of 25,000 or more are Columbia (56 miles WSW) with 113,542 people and Charlotte, North Carolina (67 miles NW) with 241,178 according to the 1970 census. Figure 2.1-5 shows the 1966 and projected (1976 and 1986) popu-lation distribution in 16 directional sectors centered on the site and within 1, 2, 3, 4, and 5-mile radii . Figure 2.1-6 shows cimilar informa-tion for 1966, 1976, and 1986 population distributions for 10, 20, 30, 40, and 50 miles. The 0-5 mile population area indicated by an asterisk is derived from Figure 2.1-5 and is included in all sector totals. l The nearest off-site residence is 1,400 feet south of the plant while the nearest residence across the lake is approximately 4,200 feet , l east. l l The current population estimates in Figure 2.1-5 are based on house counting from February 1964 aerial photographs, and 1970 census data on household occupancy for Hartsville (urban) and Darlington County 53,642 (1970) (rural). The 1970 census of Hartsville yielded 8,017 people as l compared to 6,302 (1960 census) and 5,658 (1950 census). Population pro-- jections for the years 1976 and 1986 were derived from a study of past 2.1-2 I l

1 a i trends and probable future industrial, commercial, residential and

recreational development performed by Southern Bell Telephone Company in

! the areas they serve. Hartsville and its immediate environs are expected to reach 25,000 during the 40-year lifetime of H. B. Robinson Unit 2. Outside of the Bell Telephone Company's service area, projections were based on data obtained from the South Carolina Development Board which used the Decennial Census data. In every case, the largest estimated projections of county population growth, based on the appropriate decades, were used for the data presented in Figure 2.1-6. 2.1.4 Land Use Regional Land Use i Darlington County, in which the site is located, and the adja-l cent counties of Chesterfield, Kershaw and Lee are predominantly rural. j Agriculture accounts for approximately 40-73 percent of the total county I acreage with individual farms ranging in average size from 100 to 175 acres. Principal crops are cotton, tobacco, soybeans, sweet potatoes, oats, watermelons, peaches, corn, wheat and peanuts. Agricultural receipts in the four-county area amounted to about $40,000,000 in 1961 and 1962 according to the South Carolina Crop Reporting Service of the

U. S. Department o f Agriculture.

i i One third of the workers in the four-county area were engaged in manufacturing operations; about one quarter were occupied in agriculture; about one quarter in the retail and service industry with the remainder in i all other occupations. Lee County varied'from this generalization in that i about half of their workers were in agriculture and about one sixth in ) manufacturing. 4 Typical industrics within an eighteen-mile radius of the site are listed in Table 2.1-1. { I

O l 2.1-3

_.__..-._.m_.-._.m_...... L Local Land Use 4 The region within a radius of five miles of the site is devoted primarily to agri cul ture. Within one-half mile of the site, 25 homes are occupied, with the nearest residence about 1,400 feet south of the plant, North of the site, Chesterfield county has truck farming with some soy-f , beans, butterbeans, and tomatoes grown. About 3,000 acres of watennelons j are currently grown in the Sand Hills State Forest 4.2 miles to the north of the plant. The nearest dairy farms, presently in operation, are 7 miles to the east and 9 miles to the southwest of the site. A spur track of the Seaboard Coast Line Railroad branches off the main line from McBee to Hartsville and passes 1,600 feet west of the , a site and connects with another main line of the railroad in Florence, l South Carolina. Coal for H. B. Robinson Unit No. 1 is delivered over this spur on the average of three trains per week. There is no passenger l i

traffic on this spur track.

i i l j The activities on the site will include those normally associated i I with the operation of conventional and nuclear power units. There are no i residences or agricultural activities inside the 1,400-foot exclusion j l distance. i A modern, attractive Information Center is located on the site. l The Center, which is open to the public free of charge, contains numerous l l i l exhibits and displays on nuclear energy and the production of electricity, ; Including a large-scale model of the Robinson Nuclear Plant. Film and i I l slide presentations are presented to regularly scheduled groups, and a l l l picnic area is available adjacent to the Center. The Center is a modern, l

architecturally pleasing structure, built of brick and wood, and contains l a 100-seat auditorium for presenting programs to large groups. l ! i r a i 1 l a ! (:) i l 2.1-4 i 4

Recreational Land Use Hartsville, five miles ESE of the site, is bordered on the north by Prestwood Lake, a small industrial impoundment downstream of Lake Robin-son. Prestwood Lake was built on Black Creek to serve the Sonoco Products Company, which manufactures various paper products. The lake is also used ; for fishing, boating, and swimming. The creation of 2250-acre Lake Robinson some ten years ago created a large recreational attraction for the residents of surrounding : areas. A variety of water-based activities which were very limited, if ; not nonexistent prior to creation of the lake, are available to the public and large numbers of people have taken advantage of the opportunities for l boating, swimming, water skiing, and fishing. Since the impoundment of ; Black Creek to form the lake, a bass-bluegill fishery has developed. As ; with the Information Center, all recreational use of Lake Robinson is open to the public free of charge. Because of the easy access to the lake, and ! its attractiveness as a center for water sports it is expected that residents of Hartsville and the surrounding area will continue to take advantage of Lake Robinson's recreational value. f 2.1.5 Meteorology , i r The climate in the Lake Robinson area is relatively temperate with the Appalachian Mountain chain some 150 miles to the northwest fre-quently acting as a buf f er for winter storms. Summers are hot and humid with temperatures in excess of 100*F occurring during a few days. Winters , usually are mild with a few cold waves during which the temperature drops j i below 20 F. The annual precipitation cycle has a mid-summer maximum and j a fall minimum. A secondary maximum occurs in late winter and early spring v and a secondary minimum occurs in late spring. Thunderstorms and tropical ; storms account for most of the summer rains. Maximum recorded rainfall in ! 24 hours was 6.36 inches during a tropical storm in October 1954. Snow flurries occur, but snow accumulation is rare; however, sleet or freezing rain does occur at least once each winter. 2.1-5 i i I

Rainfall records collected from 1929 through 1966 indicate that the average yearly rainfall is 46.65 in. per year. A maximum yearly rain-fall of 60.71 in, was recorded in 1937 and a minimum of 31.64 in. In 1951. A maximum monthly rainfall of 19.28 in, was recorded in September 1945 and a minimum of 0.00 in, in October 1944. Extreme mile winds (defined as a one mile passage of wind with the

\'

l highest speed for a day) are 47 mph with a probability of 0.50 per year (a l recurrence interval of once in two years); a fifty-year recurrence interval is associated with an 80 mph wind (a probability of 0.02 per year); a 100-year recurrence interval is associated with an 85 mph wind (a probability of 0.01 per year). l l The probability of a tornado striking any given point within the one-degree square which includes the site is .000582, or one tornado every i 1,708 years. During the 52-year period from 1916 through May 23, 1968, twenty-three tornadoes were reported within 30 miles of the site, but only one was reported within five miles. This tornado' occurred on April 12, 1961 at 5:10 p.m. with a 40-yard track width and one-half mile length, and re-sulted in one death. Property damage was estimated to be between $5,000 and $50,000. Since 1871 five hurricanes have passed within 25 miles of the plant site. They occurred on October 3, 1877, September 12, 1878, October 12, 1885, July 1, 1886, and September 29, 1896. No other storms have been recorded in the site region with wind speeds of hurricane intensity (74 mph). The distribution of wind direction at the site is somewhat bimodal with prevailing wind direction from the northeast quadrant (Figure 2.1-7). Winds are from the north 11.4 percent of the time and from the north-northeast 10.3 percent of the time. A secondary maximum frequency of wind direction is from the southeast quadrant. Winds are from the south-southwest 8.1 per-cent of the time and from the southwest 8.5 percent of the time. The high percentage of north and northeasterly winds may be a result of the effect O 2.1-6

        .                   - -                                     _                   l

o f Lake Robinson on local meteorology. Average wind speed is approximately O s.8 mi1es ver hcer. >-w wina seeeds << > meh> eccerred 1e eech eeasen ef , the year; however, the frequency of low wind speed conditions increased during the wirter. Iow wind speeds occurred 3.67 percent of the time. Persistences of winds at the site for the one-year period of record are characterized in Figure 2.1-8. Wind persistence exhibits a bimodal distribution similar to wind directions. The most persistent winds were of 19 hours duration from the north-northeast under neutral , and slightly stable atmospheric conditions. Winds from the south-southwest persisted for 18 hours under slightly unstable and neutral conditions. An assessment of atmospheric stability at the site was made based on data collected in Florence, South Carolina, and on data collected at the site. These data were analyzed according to methods described by Holland and Slade. Hourly surface observations from both Florence and on-site stations were analyzed for seasonal stability, dispersion (X/Q) calcula-tions and persistence. O Analysis of data collected at the site indicated that slightly stable or stable conditions exist 31.2 percent of the time, neutral condi-tions exist 36.4 percent of the time, and unstable conditions exist 32.4 percent of the time. Stability occurrences are fairly uniform throughout the year, with slightly higher frequencies of stable conditions during the winter. This is consistent with the higher frequencies of low wind speeds which also reach peak values during the winter. An estimate of the atmospheric diffusion on an annual basis was obtained from frequency of occurrence of wind speeds and directions and concurrent stability condi tions. The average X/Q distribution was calcu-lated using a computer codc, WINDVANE, developed by NUS Corporation. Site meteorology was reviewed by the U. S. Atomic Energy Commis-sion and its meteorological consultants. Data from the site was accepted as representative of the site area. 2.1-7 l l

e 2.1.6 Geology The Robinson plant is located in the Coastal Plain physiographic province approximately 15 miles southeast of the Piedmont province. As shown on Figure 2.1-9, the site lies in the northeentral portion of South , Carolina, adjacent to the Orangeburg Scarp. The Orangeburg Scarp is a dividing line between the upper and lower coastal plain. The site is situated in recent alluvial soils, underlain by late Cretaceous sediments, , underlain in turn by prsrCambrian crystalline rock. The major structural features of the region include Triassic grabens (down-faulted basins) and the Cape Fear Arch, a basement ridge which trends southeastward from the Fall Line to the Atlantic Coast just northeast of the North Carolina-South Carolina Boundary. The Cape Fear Arch has caused the overlying Coastal Plain sediments to dip away from its structure, thereby modifying the normal regional dips on its flanks. It should be noted that the site has been extensively reviewed by

 \  the U. S. Geological Survey and the U. S. Coast and Geodetic Survey (seis-mology group) who found it to be geologically and seismologically accept-       3 able for a nuclear power plant. The site also complies with the USAEC seismic design criteria.

The test boring program, refraction surveys, and laboratory tests, , when combined, present the following picture of the subsurface and geologic site conditions: The Piedmont crystalline basement rock at the site is overlain with approximately 460 feet of unconsolidated coastal plain sediment. These sediments are comprised of about 30 feet of surface alluvium over 430 feet o f the Tuscaloosa formations. The Tuscaloosa formation consists of light-colored feldspathic and slightly micaceous quartz and interbedded with red, purple, gray and brown silty and sandy clay. The alluvium and portions of t the Tuscaloosa formation occurring near the surface exhibit lenses of com-pressibic material; and for this reason, piles were selected for the support o'f all major structures. 1 2.1-8 >

l l i The subsurface materials encountered in the test borings drilled O at the site are completely consistent with recent alluvium and Tuscaloosa ; l formations encountered throughout the vicinity. Discontinuities within the strata are sedimentsry, and no structural deformation is apparent in the 4 caloosa formation in the site area. The Tuscaloosa is about 400 feet , thium and overlies an eroded slightly sloping surface of Piedmont crystal-lines. The Piedmont may be somewhat weathered near the surface. ; l Triassic basins are known in the area; however, it is believed , that the likelihood of a Triassic basin at the site is quite small. The basement rock at the site is the Piedmont and is considered to be crystalline since the results of the seismic surveys indicate a high velocity material at a depth consistent with the depth of Piedmont crystallines encountered in wells in the area. Figure 2.1-10 is a graphic presentation of the ; subsurface materials. In general, the upper alluvial sands and gravels are moderately j compact. Layers of compressible material occur in the upper 30 to 50 feet. < Because of the quantity of fines in the sand and gravel, it could not be considered free-draining material. The underlying Tuscaloosa contains generally compact relatively incompressible sands and firm to hard clayey . I soils. Several strata of cemented sandstone were encountered in the borings at depths of roinghly 90 to 100 feet. From a geological standpoint, the Tuscaloosa is considered to be l l an unconsolidated sediment. From an engineering point of view, however, the j materials are firm and compact and provide good foundation support for the l construction. The materials range in texture from a hard or compact soil to a soft rock. 2.1.7 Seismology

.                           A study of the possibility of the existence of faults was made

' during the geologic study of the area. No active faulting was apparent. i ^ l (:) 1 1.1-9

No faulting is apparent in the unconsolidated sediments of the Coastal Plain. The underlying basement rocks are effectively masked by more than 400 feet of sediments at the site and cannot be directly observed below the Fall Zone. However, faulting'in the basement complex is known from exposures above the Fall Zone and cores from scattered borings drilled through the Coastal Plaln sediments. Faulting of the Triassic Period is evident along the edge of- the Deep River Basin, which extends from the vicinity of Durham, North Carolina, into South Carolina near Chesterfield. The precise location of the fault border near Chesterfield is unknown because of the cover of Coastal Plain sediments. Other Triassic basins are known to exist below the Coastal Plain. Deep borings at the Savannah River Nuclear Facility near Barnwell, South Carolina, and in Florence. South Carolina, have penetrated Triassic rocks. Suspected Triassic rocks have been encountered below Summerville and Sumter. A magnetometer survey inferred a basin below Florence and Dillon, paralleling the trend of the Deep River Basin. Triassic basins in this area are down-faulted grabens and, therefore, bounded by faults. Another major fault in the region is the Blue Ridge Scarp. This scarp forms the Southeastern boundary of the Appalachian Province. However, it is more than 120 miles to the northwest and not likely to significantly affect the site. A definite alignment of earthquake epicenters can be seen paral-lel to the Blue Ridge Scarp in the mountains of western North Carolina. The Charleston earthquakes may have been associated with a Triassic graben below the Summerville area, and the smaller earthquake of 1959, near McBee, may be associated with faulting along the Deep River Basin. O 2.1-10

Most shocks with an intensity greater than V in the region have manifested themse1ves in a narrow zone in the Applachian Province paral- t leling the Blue Ridge Scarp. Figure 2.1-11 indicates all earthquakes in , the region with a Modified Mercalli Intensity of V or greater. Many ; other smaller carthquakes have been experienced in the Carolinas, but t poor records and lack of damage gives them little significance in this study. The largest earthquake in this region occurred at Charleston in August, 1886. Charleston is approximately 120 miles south of the site. This shock had an intensity of about Modified Mercalli IX at the epicenter , and it is estimated that this shock had a magnitude of 6-1/2 to 7 at the site with epicentral acceleration of 0.25g to 0.30g. However, damage was confined to a relatively small area and no permanent scars remain to give testimony to the shock. Aftershocks of the main earthquake had intensities ranging up to Modified Mercalli VII. Another shock (Modified Mercalli VII) occurred in the Charleston area in 1912. Succeeding shocks from 1914 to the present appear to have > decreased in intensity and in the affected area. The last shock in 1960 (Modified Mercalli V) was felt over only 3500 square miles. i An earthquake of Intensity Modified Mercalli VII-VIII occurred i in Union County, South Carolina, on New Year'n Day in 1913. This is the second largest shock in the Carolinas, and its epicenter lies about 90 miles from the site, t In 1959, an earthquake of Intensity Modified Mercalli V-VI occur-f red about 15 miles from the site in the vicinity of McBee.- No permanent effects of this shock are noted in the literature or in a geologic recon-naissance, although it is presumed to have been felt at-the site. It is estimated that this shock had a magnitude no greater than 4.5 at the site with an epicentral acceleration of vell under 0.10g. Except for the aforementioned trend of epicenters paralleling the Blue Ridge, there is no apparent trend of other epicenters in the 2.1-11

f-region. Most of the smaller historical shocks were reported in scattered ( population centers. The seismicity of the region is generally moderate. Of those shocks that do occur, only two earthquakes with epicenters out-side of the Charleston area have had intensities exceeding VI. The only earthquake to occur in South Carolina in 1966-1967 was in Orangeburg County at 0504 on October 23, 1967. The intensity was judged to be about IV at Ridzeville and Summerville. Only one earthquake of intensity V or greater has ever been re-corded within 50 miles of the site. This was the shock which occurred near . McBee in 1959. The epicenters of two other shocks are located within 100 > miles of the site. The epicenter of the 1913 earthquake in Union County . (Modified Mercalli VII-VIII) was approximately 90 miles from the site and the epicenter of the 1945 Lake Murray shock (Modified Mercalli VI) was [ approximately 70 miles distant. Damage was slight in both epicentral areas and nonexistent at the site. While the aforementioned shocks were probably felt in the locality of the site, no damaging effects were experienced. The amplitude of ground motion at the site would not cause damage to any reasonably well-built struc- l ture. In addition this site is located in Zone 1 of the Uniform Building Codes' Map & Equal Seismic Probability. Zone 1 is characterized as a zone ; of light earthquake activity which would result in minor damage. Therefore, ; on a historical basis, it would appear that the site will not experience 7 damaging earthquake motion during the life of the planned facilities. The sediments underlying the site are quite thick and undisturbed. The surface of the buried crystallines is an ancient eroded one, and active faults are unknown in the vicinity of the site, on the basis of historical data, it is expected that the site area could experience a shock in the order of the 1959 McBee shock once during the life of the plant. This shock could be as far distant as in 1959 or perhaps l closer. On a conservative basis, magnitude 4.5 earthquake was selected ; O with an epicentral distance of less than ten miles. This carthquake is 2.1-12 i

i the design earthquake and although the probable ground acceleration O would be 0.U7 to 0.09g, a value of 0.lg was used. 1 To provide an adequate margin of safety, a maximum earthquake ground acceleration of 0.2g was selected for the hypothetical earthquake. It is inportant to note that even if an earthquake comparabic to the > Charleston shock were to occur 35 miles from the site, the ground ac-celeration would not exceed 0.2g. , 2.1.8 Hydrology l Surface Water Hydrology A principal feature of the site is Lake Robinson, developed in the late 1950's as a cooling water reservoir for the Robinson Plant. The lake is impounded by an earth dam on Black Creek approximately 5 miles northwest of Hartsville, South Carolina. Black Creek is a tributary of the Pee Dee River and has its headwaters in the vicinity of Pageland, S. C. The creek flows in a southeasterly direction to its confluence with the Pee Dee River, approximately 8 miles upstream of Peedee, S. C. At the ! Lake Robinson dam, the creek drains a watershed of 173 square miles. A smaller impoundment of approximately 250 surface acres lies ESE of the site near Hartsville. The impoundnent, known as Prestwood Lake, is also located on Black Creek and was constructed in 1895. The lake is utilized , 1 by Sonoco Products Company as an integral part of their industrial complex, l which is located adjacent to the lake. The regional watershed is typified by low relief and meandering l streams. Runoff in the Black Creek basin, while slightly greater than that of the Pee Dee River basin, is typical of other watersheds in the Coastal Plains. inflow to Lake Robinson has been monitored and recorded con-tinuously by the U. S. Geological Survey since October 1959, at a gaging station 5.3 miles northeast of McBee, S. C. Records of flow for the O October 1959-September 1969 period are tabulated in Table 2.1-2. 2.1-13

                                  - - - . ,, _  _,      . . . _ . , , ..-      .._..,-__,,,_.---,.--m.... , - - , -

I 1he stream flow record of Black Creek at McBec has been extended ; O to 35 years by using the records of the Lynches River at Effingham, S. C., f to estimate the mean monthly discharges in Black Creek for the period October 1929 to September 1959. The Lynches River is located in the l valley immediately west of the Black Creek watershed. Rainfall, topography and soil conditions within the two basins are comparable. Total inflow to Lake Robinson during this period has been calculated from the estimated ; McBec flows using the correlation between flow at McBee and total lake , inflow, which also have been developed for the period of record. From i this analysis, the calculated average and minimum monthly inflows into ; Lake Robinson are 169 and 21 cfs, respectively. During the 10-year period of stream flow record of Black Creek ; at McBee, the maximum peak flow occurred on October 18, 1964, and on June 18, ! 1969, and had an instantaneous peak discharge of 1100 cfs. Other maximum ! l instantaneous peak discharges recorded during the period of record were 804 cfs in 1960, 840 cfs in 1961, 906 cfs in 1962, 678 cfs in 1963, 888 cfs in 1965, 670 cfs in 1966, 715 cfs in 1967, and 635 cfs in 1968. The i O maximum flow of record in the area since 1891 occurred in September 1945. 1 I Based on the computed relationship between peak flows recorded in Black Creek at McBee and in the Lynches River at Bishopville, and on the recorded peak discharge of the September 1945 flood at Bishopville, it i.s estimated that the peak discharges in Black Creek during this flood were about 3000 cfs at McBee and about 5100 cfs at the site of the Lake l Robinson dam. Table 2.1-4 shows estimated and recorded flows in excess of 1700 cfs in Black Creek for the period 1891-1969. The Lake Robinson dam and spillway are designed to pass a flow of 40,000 cfs at a lake icyc1 of 221.67 feet, which is about 8 feet less ; i than the height of the dam and about 3 feet less than the plant grade. l i To check the capacity of the dam and spillway to handle the maximum peak i flow which might conceivably occur during the life of the project, an analysis has been made of the peak flow which would result from the Probabic Ebximum Precipitation for the area. O, 2.1-14 , i r- ++ + - - - - , , , y ~q. , ,-. ,,m,,__7 ,.-e, -ve n,, iw8

t i i i A design unit hydrograph for the drainage area above the dam j was prepared from the McBee gaging station records and the Probable , Maximum Precipitation for the area was taken from charts prepard by the liydrometeorological Section of the Weather Bureau. The analysis produced l 5 a peak flood discharge into the lake of 39,000 cfs, a flow well within the ; i flood capacity of the Lake Robinson dam and spillway. : l. Ground Water Ilydrology 1 e i The principal ground water aquifer in the vicinity of the ! Robinson Plant is the Tuscaloosa formation. This formation consists of ! feldspathic and slightlymicaceous quartz sand interbedded with impure ! clay and kaolin. The kaolin occurs in lenticular bodies which extend laterally for several square miles and have a maximum thickness of 30 to ! i 40 feet. In some areas, the presence of this kaolin is responsible for ; a perched water condition in the overlying sands. i At the site, about 30 feet of surface alluvium overlies the () Tuscaloosa formation. This formation then extends approximately 430 feet to the crystalline basement rocks. i Ground water occurs in the Tuscaloosa formation under both water table and artesian conditions. Under water table conditions, the water surf ace is unconfined (under atmospheric pressure) and is free to move in a vertical direction. Under artesian conditions, the water in the aquifer ' i is confined under a relatively impermeable layer of material, and hydro- l static pressure causes the ground water to rise above the bottom of the confining layer when the aqui fe r is penetrated. l Water in the shallow aquifers is generally unconfined, and since I the water table is usually fairly close to the surface, recharge of the shallow aquifers is by direct percolation and seepage of precipitation. i In the deeper aquifers, ground water is usually artesian. Recharge to j an artesian aquifer is controlled in a large measure by the difference ' (:) ; 2.1-15

i i. in the head of the water in the artesian aquifer and the head of the water ! O in aquifers above or below. ! Recharge to artesian aquifers can take place in out-crop areas, ! although studies to date indicate that the Tuscaloosa formation receives < most of its recharge by leakage from overlying aquifers and actually dis-charges in the out-crop areas. The direction of ground water movement is normal to the . piezametric contours, and movement occurs from points of higher potential to points of lower potential. Water recharging the aquifer moves down the hydraulic gradient to discharge into the overlying strata in areas where the head is lower or where there are piezometric lows. The discharge is controlled both by water moving toward piezometric lows along rivers and by water moving down the dip, with discharge occurring by upward leakage , into the Black Creek valley. Thus, the piezometric low of the Black Creek f r valley results in a net ground water discharge rather than a net recharge to the Tuscaloosa formation aquifer. , O ! Data collected by the U. S. Geological Survey indicate that the static head of ground water in the Tuscaloosa formation is about 330 feet above mean sea level at Bethune, South Carolina, and that the gradient in the area is approximately 2.9 feet per mile. The plant site is about 10 l miles down the dip of the formation from Bethune; therefore, the static head of the ground water underlying the site should be approximately 300 feet above mean sea level, or about 80 feet above the normal level of Lake : Robinson. This situation indicates that there is little if any recharge j to the Tuscaloosa formation aquifer from the ground surface at the plant

sitz. . i The Tuscaloosa is a permeable formation, and in several areas of the coastal plain, individual wells yield up to 2000 gpm. Wells in the i site area that have been developed in this formation are usually artesian. Potable water usage from ground water in the areas around the site is , obtained primarily from artesian wells; and all of the domestic water 2.1-16 i

I i used in the vicinity of the plant is artesian in origin. Table 2.1-5 [ shows the municipal and industrial ground water usage within a 20-mile ; radius of Lake Robinson. , i b , I ll 6 1 1 i i 1 t O t 2.1-17 1

J O O O TABLE 2.1-1 TYPICAL INDUSTRIES IN REGION Company Product Town and Location CHESTERFIELD COUNTY Catarrh Feed Mill Animal Feed Angelus, 17 miles NW W.A. Clark Gin & Fertilizer Co. Fertilizer Mixing Angelus, 17 miles NW Mar Mac Manufacturing Company Fabricated Structural Metal McBee, 7 miles NW Products McBee Chip & Machine Company Wood Chips McBee, 7 miles NW Tenner Bros., Inc. Wine Patrick, 15 miles NNE y MAFC0 Textured Fibers Textile Fibers McBee, 7 miles NW

     ~
     ,                                                                                     DARLINGTON COUNTY on American Can Company                            Paper Cups, Containers and        Darlington, 17 miles WSW                     -

Dixie Cup Division Lids Asphalt Products, Inc. Asphalt Darlington, 17 miles WSW Bonnoitt's Mill, Inc. Meal, Grits and Animal Feed Darlington, 17 r. iles WSW City Ice & Fuel Co. Ice Darlington, 17 niles WSW Coca Cola Bottling Company Soft Drinks Darlington, 17 niles WSW , Darlington Construction Co. Ready Mixed Concrete Darlington, 17 titles WSW Darlington Monument Works Monuments and Concrete Darlington, 17 miles WSW

Products Darlington Roller Mills Flour and Animal Feeds Darlington, 17 miles WSW Darlington Veneer Co. Veneer Products Darlington, 17 miles WSW Diamond Hill Plywood Co. Plywood Darlington, 17 miles WSW General Instruments- Capacitors, Electrical Products Darlington, 17 miles WSW Hunt Food - Southern Cotton Cottonseed Oil Darlington, 17 miles WSW Oil Division Modern Print Shop Commercial Job Printing Darlington, 17 miles WSW News & Press, Inc. Newspapers Darlington, 17 miles WSW Perfection Gear Co. Gears, Gearhouse Assemblies Darlington, 17 miles WSW Sherman Manufacturing Co. Ladies' House Dresses 'Darlington, 17 miles WSW Boyd Vault Co. Concrete Burial Vaults Hartsville, 5 miles WSW Carolina Refractories Co. Plastic Fire Brick Hartsville, 5 miles WSW

                                                            - _ . ~ . .             .- _

, O O O TABLE 2.1-1 (Continued) l l 1 Company Product Town and Location l DARLINGTON COUNTY (Cont.) l l Carolina Colonial Corporation Bearings Hartsville, 5 miles WSW Textile Fibers, Cotton Hartsville, 5 miles WSW Hartsville Mills Agricultural Pesticides Hartsville, 5 miles WSW Hartsville Chemical Co. Hartsville, 5 miles WSW Hartsville Machine Shop General Machine Shop Hartsville Manufacturing Co. Dresses Hartsville, 5 miles WSW Cottonseed Oil, Meal, Shortening Hartsville, 5 miles WSW Hartsville Oil Mill Hartsville Poultry Co. Poultry Processing Hartsville, 5 miles WSW Hartsville Publishing Co. Newspapers, Job Printing Hartsville, 5 miles WSW Public Buildings Furniture Hartsville, 5 miles WSW 1 Hartsville Woodcraft Hartsville, 5 miles WSW . , Hucks Bakers Bakery Products

           "                                                Sheet Metal Products                                                                                       Hartsville,                          5  miles WSW Hughes Roof & Sheet Metal Co.

l Y International Minerals & Hartsville, 5 miles WSW G Chemical Corp. Fertilizer Sheet Metal Products Hartsville, 5 miles WSW Moores Heat & Sheet Metal Co. Hartsville, 5 miles WSW Pacolet Industries Broadcloth and Oxford

                                                           . Poultry Processing                                                                                         Hartsville,                          5 miles WSW Pc; See Hatchery Commercial Job Printing                                                                                     Hartsville,                          5 miles WSW Porter'r Service Press Sonoco Products Co.                        Paper Tubes, Fiber Pipe, Paper                                                                                                                                                                                '

Drums, Cones, Formic Acid and i Miscellaneous Chemicals Hartsville, 5 miles WSW Linen Yarns Hartsville, 5 miles WSW Texlin Co. Lamar Knitting Mills Hosiery Lamar, 17 miles S , Textile Printing & Dyeing Society Hill, 18 miles NNE Klopman Mills, Inc. - American Manufacturing Co. Ladies Garments Lamar, 17 miles S 4 Furniture & Wood' Society Hill, 18 miles NNE Maynard Lumber Co. Ready Mix Concrete Hartsville, 5 miles WSW Rock Hill Concrete Co. Hartsville, 5 miles WSW Triple City Iron Works- Steel Fabrication-

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

y _ . . _ _ . - - _ - . _ . . . _ m m _ __ _ _ . _ - . . - m . .- . . . . _, C l 9 6 6 !

5 3

4 , i e l 3 4 l 'f i 4 TABIE 2.1-2 ! y BIACK CREEK FtJ0W NEAR McBEE, S. C.

i (CFS) i 1

1 1959-1960 1960-1961 1961-1962 1962-1963 1963-1964 1964-1965 1965-1966 1966-1967 1967-1968 1968-1969 4 ! Oct. 353 133 81 56.9 59.9 347 146 73.5 71.2 124 l l Nov. 225 118 117 153 121 195 164 71.9 100 166 f j Dec. 191 134 167 119 187 242 131 96.4 166 137 I j Jan. 251 149 219 217 300 207 200 149 256 158 i Feb. 411 272 225 214 297 306 227 164 140 273

 .                                                                                                                                                                                                                                      i j                         Mar.                        318                                      264          285                237             34 0         342            262           127           144           271 Apr.                        338                                      286          200                135             246          256            165'          75.5         97.7           261
              .[

j c$ May 188 228 74.3 115 127 128 172 90.5 73.8 165 i June 134 200 108 114 110 181 79.9 45.3 71.5 272 l i July 150 151 66.4 81.4 195 204 49.4 62.1 132 201 ; , ? { Aug. 512 203 55.2 68.9. 168 264 63.2 191 47.4 244 i l f Sept. 142 140 80.8 68.5 210 138 68.5 128 26.7 2 16 Max. Daily 734 (4/7) 750 (2/26) 846 ,(3/13) 651 (1/22) 770 (3/18) 1020 (10/18) 560 (3/6) 630 (8/26) 615 (1/13) 1,010 (6/18) ; 1,100 (6/18)

Max. Instant 804 (4/7) 840 (2/26) 906 (3/13) 678 (1/22) 1070 (3/17) 1100 (10/18) 670 (3/6) 715 (8/26) 640 (1/13) Min. Daily 91 (7/23) 72 (9/30) 26 (9/4) 26 (8/20) 39 (10/15) 68 (5/7) 31 (8/3) 24 (6/20) 22 (9/25) 22 (10/3) Min. Instant 88 (7/23) 72 (9/30) 26 (9/4) 24 (8/20) 38 (10/22) 65 (5/8) 30 (8/3) 23 (6/21) 21 (9/25) 21 (10/3) Mean Daily 237 189 139 131 197 234 144 106 111 207 f

Water Resources Data For South Carolina, U. S. Geological Survey ;

i i I I r _ . _ _ . _ - _ . . . - _ . _ _ _ _ . _ . _ . . . . . . . _ , . - ~ - . - . - -

i l 6 9 O i. I i l i l l TABLE 2.1-3 i BLACK CREEK FIDW NEAR HARTSVILLE, S. C. * (CFS) ; 1960-1961 1961-1962 1962-1963 1963-1964 1964-1965 1965-66 1966-1967 1967-1968 1968-1969 l 19 8 152 126 118 458 213 137 139 180 i Oct. t 164 181 214 172 255 222 143 166 201 -! Nov. I Dec. 191 251 174 253 316 197 156 253 191 Jan. 222 302 317 4 17 281 253 257 358 234 l t 342 319 299 403 396 304 258 218 362 ; , Feb. I f 375 389 320 457 473 349 19 7 218 413

Mar.

404 281 197 330 349 231 128 166 301 w Apr.

i ~ L May 308 148 169 194 208 260 153 128 214 , j 4 - .j June 288 166 167 161 271 152 105 130 308 l i l July 229 138 150 276 268 113 132 192 218 ! i Aug. 274 125 123 247 356 117 269 109 328 i i sep, 222 151 127 275 212 121 212 79.7 231 Max. Daily 817 (2/26) 830 (3/14) 850 (1/21) 878 (3/18) 906 (10/19) 626 (3/7) 668 (8/26) 692 (1/12) 658 (6/25) I l 924 (10/19) 668 (3/7) 692 (8/26) 760 (1/12) 792 (6/24) j Max. Instant 1060 (2/25) 860 (3/14) 950 (1/22) 896 (3/18) t Min. Daily 143 (11/12) 101 (9/5) 105 (8/18) 96 (10/24) 136 (6/7) 80 (9/17) 76 (6/21) 64 (8/31) 82 (10/4) l l t Min. Instant 143 (11/12) 98 (9/14) 103 (8/19) 94 (11/1) 134 (6/7) 79 (9/15) 70 (6/21) 64 (8/31) 66 (10/7) i ' Mean Daily 267 216 19 8 275 320 213 179 180 264

Water Resources Data For South Carolina, U. S. Geological Survey l i,

1 i TABLE 2.1-4 O ESTIMATED BLACK CREEK PEAK FLOWS IN EXCESS OF 1700 CFS (1891-1964) Month & Year Estimated Peak Flows in CFS 9/1893 1800 8/1894 2200 10/1894 2000 1/1895 1900 2/1899 2300 4/1900 2100 6/1901 2300 2/1903 2100 8/1908 3700 2/1912 2000 7/1916 3000 2/1921 2000 3/1922 2400 1/1925 2300 9/1928 3200 9/1928 3600 10/1929* 3200 4/1936* 2900 3/1939* 2400 3/1944** 2200 0 9/1945** 12/1948** 5100 1900 i 9/1953** 2600 Flow peaks are based on gage heights in Lynches River at Effingham recorded by the U. S. Weather Bureau, except as noted below:

Based on flows in Lynches River at Ef fingham as recorded by the U. S.

Geological Survey.

             ** Based on flows in Lynches River at Bishopville as recorded by the U. S.

Geological Survey. O 2.1-22

TABLE 2.1-5 MUNICIPAL AND INDUSTRIAL GROUND WATER USAGE WITilIN 20-MILE RADIUS FROM LAKE ROBINSON Location & No. of Wells Depth Feet Total Yield Gpm McBec 3 188-190 65 Society 11111 3 157-360 305 Darlington 5 305-570 2,655 Ila r tsville 10 155-460 4,000+ Lamar 1 285 Unknown Bishopville 2 200 350+ Darlington County 7 155-220 900+ 0 0 2.1-23

2.2 GENERAL PLANT DESCRIPTION 2.2.1 Introduction The H. B. Robinson Unit No. 2 reactor is a pressurized light water moderated and cooled system. The unit is designed to produce ini-tially 2200 st, and 739 MWe of gross electrical power. The unit is expected to be capable of an ultimate output of 2300 MWt. All steam and power conversion equipment, including the turbine generator, is designed to permit generation of 769 MW of gross electrical power. The nuclear power plant incorporates a closed-cycle pressurized water Nuclear Steam Supply System and a Turbine-Generator System utilizing dry and saturated steam. Equipment includes systems for the processing of radioactive wastes, handling of fuel, electrical distribution, cooling, and all other on-site facilities and structures required to provide a com-plete and operable nuclear power plant. O The inherent design of the pressurized water, closed-cycle re-actor significantly reduces the quantities of fission products which could be released to the atmosphere. Four barriers exist between the fission product accumulation and the environment. These are the uranium dioxide fuel matrix, the fuel cladding, the reactor vessel and coolant loops, and the reactor containment. The consequences of a breach of the fuel clad-ding are greatly reduced by the ability of the uranium dioxide lattice to retain fission products. Escape of fission products through a fuel clad-ding defect would be contained within the pressure vessel, loops and auxiliary systems. Breach of these systems or equipment would release the fission products to the reactor containment where they would be re-tained. The reactor containment is designed to retain these fission pro-ducts under the most severe accident conditions. Several engineered safety features have been incorporated into the reactor containment design to reduce the consequences of a loss of O 2.2-1 1

-. -- - . . .. . ~ . -- - _. coolant incident. These safety features include a Safety Injection System; () an Air Recirculation Cooling System; and a Containment Spray System. The Safety Injection System will automatically deliver cooling water to the reactor core in the event that there is a loss of coolant. The Air Recir-culation Cooling System rapidly depressurizes the containment following a loss of coolant, while the Containment Spray System's function is to depressurize the containment and remove elemental iodine from the atmosphere. 2.2.2 Structures The major structures are a Reactor Containment, Auxiliary Build-ing, Turbine Structure, and Fuel Handling Building. A general plan of the building arrangement is shown on Figure 2.2-1. Reactor Containment l The reactor containment structure is a reinforced concrete vertical cylinder with pre-stressed steel tendons in the vertical wall, () a reinforced concrete hemispherical dome and supported on soil supported steel pipe friction piles. The reactor containment completely encloses the entire reactor and reactor coolant s: stem and ensures that an accept-abic upper limit for leakage of radioactive materials to the environment will not be exceeded even if a gross failure of the reactor coolant system were to occur. It also provides adequate radiation shielding for both nor-mal operation and accident conditions. The reactor containment system provides a highly reliable,'essen-tially leak-tight barrier against the escape of fission products. The l containment vessel penetrations are continuously pressurized. Pipes pene- j trating the containment which could become a potential path for leakage to the environment following a loss of coolant accident are designed with a vertical leg which provides a water seal. In most of these pipes, water always'is present to provide a liquid seal at the valve seats. For those where the water seal may not always be present, a redundant automatic O 2.2-2

system which does not rely on outside electrical power is provided to rapidly inject seal water betwcen the valve seats. The operation of the system can be monitored after the accident and provisions are included for manually replenishing the seal water if required. These provisions minimize leakage to the environment. Auxilia ry Building The Reactor Auxiliary Building contains such facilities as the emergency diesel generators, boric acid and waste evaporators, residual heat exchangers, the solid waste handling room, and the control room for Units 1 and 2. I Complete supervision of both the reactor and turbine generator I is accomplished from the control room. Units 1 and 2 share the control room located as an integral part of the Unit No. 2. The control room for the combined plant is approximately 40' x 40'. The control boards are arranged to give maximum distance between operator areas and preclude interference between them. The annunciators and alarms for the two units are in opposite corners of the room and have different audible tones which make them distinguishable to the operators, The waste disposal control board is located in the Auxiliary j Building, in the vicinity of the boric acid and waste evaporators. This board permits the auxiliary operator to control and monitor the processing of wastes from a central location in the same general area where equipment is located. Fuel Handling Building The Fuel Handling Building houses most of the Fuel Handling System including new fuel storage area and spent fuel pool. The building also contains gas decay tanks, hold-up tanks, the " hot" machine shop, and spent fuel cask loading area. The spent fuel storage pit is connected to lO 2.2-3

(} the reactor cavity by the refueling canal. The refueling canal and spent fuel storage pit are reinforced concrete structures with a seam-welded stainless steel liner. The reactor is refueled with equipment designed to handle spent - fuel under water from the time it leaves the reactor vessel until it is , placed in a cask for shipment from the site. Underwater transfer of spent fuel provides an optically transparent radiation shield, as well as a re-liable source of coolant for removal of decay heat. Turbine Structure The turbine generator is installed on a turbine structure. The turbine is a tandem-compound, 3-element, 1,800 rpm unit having 44-inch exhaust blading in the low pressure elements. Four combination moisture separator-reheater units are employed to dry and superheat the steam be-tween the high and low pressure turbines. O The turbine condensers and steam moisture separators are also located in the turbine structure. The condensers are cooled with water from Lake Robinson. Water is brought in through the intake structure on the lake; and after cooling use, it is delivered to the discharge canal shared with Unit 1. 2.2.3 Reactor The reactor for the H. B. Robinson Unit 2, furnished by Westinghouse, is of the pressurized water type shown in Figure 2.2-2. l The Robinson Nuclear Steam Supply System is similar to a number of pres- ) surized water reactors which have been operating successfully and safely-for years and have generated many millions of kilowatt hours of energy in the United States. 1 i O 2.2-4

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

l The reactor core is a three-region core. The fuel rods are () cold worked zircaloy tubes- containing slightly enriched uranium dioxide pellets. The core fuel is loaded in three regions with new fuel being , introduced into the outer region, moved inward in a checkerboard pattern j at successive refuelings and discharged from the inner region to the .j i spent fuel storage. l l The uranium dioxide fuel is enclosed in zircaloy tubes with welded end plugs which provide the second barrier against the release of fission products. The uranium dioxide lattice itself acts as the first barrier against the release of fission products. The control rods consist of groups of individual absorber rods which are held together with a spider at the top end and actuated as a group. The absorber material used in the control rods is silver-indium-cadmium alloy. In addition to normal control, provisions are also made for the rapid simultaneous insertion of all control rods for the rapid , shutdown of the reactor. 4 (:) The reactor core is contained within a reactor pressure vessel, which constitutes the third barrier against the release of fission pro-ducts. 2.2.4 Reactor Coolant System The water in the core serves as a moderator to slow down high energy neutrons generated in the fission process, as a neutron reflector, and for cooling the reactor core. The Reactor Coolant System consists of three similar heat transfer loops connected in parallel to the reactor vessel. Each loop contains a circulating pump and a steam generator. The system also includes a pressurizer, pressurizer relief tank, con-necting piping, and instrumentation necessary for operational control and protection. The Reactor Coolant System transfers the heat generated in the core to the steam generators where steam is generated to drive the turbine generator. 2.2-5

 . . - . _ .      .._.._.m     - - . . _ . .

Coolant enters the reactor vessel through inlet nozzles in a () plane just below the vessel flange and above the core. The coolant l flows downward through the annular space between the vessel wall and the core barrel into a plenum at the bottom of the vessel where it re-verses direction. Approximately ninety-five percent of the total coolant , flow is effective for heat removal from the core. The remainder of the flow includes the flow through the rod control cluster guide thimbles, l the leakage across the fuel assembly outlet nozzles, and the flow de- i flected into the head of the vessel for cooling the upper flange. All the coolant is united and mixed in the upper plenum, and the mixed cool-ant stream then flows out of the vessel through exit nozzles located on the same plane as the inlet nozzles. The Reactor Coolant System is of primary importance with re- ; spect to its safety function in protecting the health and safety of the public. 2.2.5 Reactor Control The reactor is provided with two independent reactivity control , systems, one involving neutron absorbing control rods, and the other a soluble chemical neutron absorber (boric acid) in the reactor coolant. The control rods are grouped into clusters, approximately half of which ; are fully withdrawn during power operation, serving as shutdown rods to shut the reactor down immediately if necessary. The remaining rods com-prise the controlling group which are used to control reactor coolant temperature. The concentration of boric acid in the coolant is varied as necessary during the life of the core to compensate for the more slowly , occurring changes in reactivity throughout core life, such as those due ; to fuel depletion and fission product buildup. Automatic protection systems are tied to the control systems and involve positioning of control rods and chemical absorber concentra-tion. Procedural controls are also used to assure that established limits

f. are not exceeded in reactor operation. The liquid control system is an independent system from the control rod system.

2.2-6 I

The reactor's protection system overrides all operational con-O trols and automatically initiates appropriate action. Such action in-cludes shutting down the reactor whenever specific conditions monitored by the system approach established safe limits. All sensor wiring and other equipment associated with the safety system is maintained physi-cally and electrically separate from the control system in accordance with industry standards. 2.2.6 Turbine-Gene rator The turbine is a three-element, tandem-compound, four flow exhaust, 1800 RPM unit with 44-inch last row blades, and has moisture separation and live steam reheat between the high pressure (HP) and low p re ssure (LP) elements. The turbine consists of one double-flow, HP clement in tandem with two double-flow, LP elements. Four combination mo is ture- se pa ra t or , live-steam reheater assemblies are located along-side the LP turbines. O All of the equipment in the turbine generator systems are de-signed to produce a maximum calculated gross output of 769,548 KW. The hydrogen inner-cooled generator is rated at 854,090 KVA at 75 psig of hydrogen gas pressure. The turbine oil system is of a conventional design and consists i of three parts: (1) High pressure oil system, (2) lubrication system, (3) electro-hydraulic governing control system. Lube oil is used to seal the generator glands to prevent hydrogen Icakage from the machine. 2.2.7 Radwaste System The H. B. Robinson Unit No. 2 is equipped with a Waste Proces-sing System capable of collecting, storing, and processing radioactive or potentially radioactive wastes (gases, liquids, and solids) for off-site shipment or disposal. The Waste Processing System enables the plant to comply with all regulations for the release of radioactivity to the O environment. 2.2-7

a Radioactive fluids entering the Waste Processing System are , t collected in sumps and tanks until determination of subsequent treat-ment can be made. They are sampled and analyzed to determine the quan- , tity of radioactivity, with a periodic isotopic identification, and then processed. The system is capable of handling liquid, gas, or solid wastes. Most radioactive liquids are processed and retained inside the plant by the Chemical & Volume Control System recycle train. Processed water from waste disposal is discharged through a monitored line into the circula-ting wate r discharge. Gases are held up in decay tanks to allow suffi-cient decay and then vented under strict control or returned to the Volume Control System. Solid wastes are packaged into 55-gallon drums by a hydraulically operated baler. Most of the components of the Radwar.ce ; System are made of stainless or carbon steel. Major camponents include the waste holdup tank, sump tanks and pumps, spent resin storage tank, gas decay tanks, waste evaporator package, compressors, gas analyzer, ; waste condensate tanks, chemical and reactor coolant drain tanks, and associated piping and valves. The system is controlled from a central panel in the auxiliary building, and appropriate alarms and indicators are located in the con- i trol room. All system equipment is located in or near the auxiliary building, except for the reactor coolant drain tank and pumps in the ! reactor containment. 2.2.8 Condensers And Condenser Cooling Water System The circulating water is supplied from an intake structure lo-

 ,   cated east of the plant on the bank of Lake Robinson.      With Unit No. 2 at full load, the cooling water requirement is approximately 482,100 gpm.       i Approximately 4.3 x 10 Btu /hr. of waste heat is removed from the conden-ser during normal full load operation and this results in a temperature increase across the condenser of approximately 18 F.      After passing through O

2.2-8 f

I the tube side of the condensers, the cooling water is discharged through a canal on the west side of the plant to a point in the lake about 4.2 ) miles upstream of the plant. l The intake structure is designed for three vertical one-third , capacity circulating water pumps each mounted in a separate pumping bay. Each bay is equipped with trash racks and 3/8-inch mesh traveling screens ! to remove debris and prevent the passage of fish through the plant conden-sers. At conditions of traximum flow, the velocity through the intake . screens is about 2.1 feet per second. A chlorination system is provided to control slime and algae growth in the cooling water system and to reduce fouling of the condenser tubes. The cooling water system is normally chlorinated twice daily for , periods of about thirty minutes during each cycle. This chlorination is controlled so that free chlorine residuals of about 0.5 ppm are achieved at the condenser outlet. ; I The surface area at Lake Robinson is approximately 2,250 acres, of which 807. is used for the dissipation of heat absorbed by the water that I passes through the plant. The lake is approximately 40 feet deep at the ' dam and provides storage for about 31,000 acre-f t. of water. The Lake ! Robinson dam and spillway structure are designed to pass a flow of 40,000 cfs at a lake flood level of 221.67 feet. The dam has a top elevation at 230 feet above mean sea level. The normal water elevation is 220 feet above mean sea level. Tainter gates having a top elevation at 220 feet and Howell Bunger valves at elevations of 178 f t. and 185.5 f t. are pro-vided at the dam for multi-level releases and re-aeration of the releases before they enter the stream below the lake. 1 2.2.9 Operation of Nuclear Unit , i The Robinson Unit No. 2 is a steam generating unit in which a nuclear reactor takes the place of an ordinary steam boiler. The elec-trical portion of the plant, the turbine-generator, is essentially the 2.2-9

same as that employed with a fossil unit, and the product, electricity, is identical. The heart of the nuclear unit is the Nucicar Steam Supply System, which consists of the reactor, the Reactor Coolant System, and various associated auxiliary systems. The reactor core is contained in the reactor pressure vessel and it is this core that produces the heat necessary fur the geacration of electricity. In the Robinson No. 2 unit, the core fuel is uranium, enriched in the uranium-235 isotope. Fission-ing of the uranium-235 fuel in the reactor core generates heat which is transferred to the reactor coolant. The amount of heat generated is con-trolled by a coordinated combination of soluble neutron absorbers in the form of borated water and silver-indium-cadmium control rods. Under full power operating conditions, approximately 2200 MW of heat is produced by fission in the Robinson No. 2 core. This heat is removed from the reactor core by the primary coolant water which circu-lates through the core under pressure with a sufficient margin to keep the coolant from boiling. From the reactor, the primary coolant water passes through the primary side of the steam generators where the heat is trans-ferred to a secondary water system to produce steam. It is this steam which turns the turbine-generator to produce electricity. Af ter the pri-mary coolant water from the reactor passes through the steam generators, it is returned to the reactor where the process continues. Steam in the secondary loop is converted to water in the condenser as it leaves the tu rb ine . The condensate is collected and is returned as feedwater to the steam generators to go through its cycle again. The electricity produced by the turbine-generator is stepped up in voltage to 230 KV by transformers in the plant switchyard. From the switchyard, the electricity flows ovea ne CP&L grid to its point of use by the consumer. Various auxiliary plant systems provide the means to supply make-up water for use in both the primary and secondary systems; to adjust the concentrations of chemicals used for corrosion inhibition and reactor control; to purify the reactor coolant water; to remove the 2.2-10

residual heat when the reactor is shut down; to sample the primary and O secondary coolant water; to process the wastes produced in the plant; and to carry out other functions essential to the operation of the nuclear unit. Direct operational control of the nuclear unit is exercised by operators who are formally licensed by the USAEC. A minimum of one year's training and the successful completion of written, oral, and physical ex-aminations are required before an operator's license is issued. Re-examination is required at two-year intervals to keep the operator's license current. Supervisory personnel are also required to be licensed as opera-tors. O 1 0 2.2-11

 -. . _ ~        .. .

a 2.3 PERMITS AND ENVIRONMENTAL APPROVAL O From the inception of the Robinson Unit No. 2, CP&L has worked diligently with numerous federal, state, and local governmental organf-zations in an effort to assure compatibility of the plant with its environs and to assure that the plant would be capable of operating safely. In addition to the AEC's review of plant design which preceded the issuance of both a construction permit and an operating license, there have been a number of other permit proceedings and reviews concerned with the environ-mental impact of the plant. Throughout all of these proceedings, there was an absence of expressed opposition to the then proposed construction and operation of Robinson Unit No. 2. At the public hearing held in Darlington, South Caro-lina, prior to the issuance of the nuclear facility construction permit by the AEC, there were no requests to intervene, and there were no limited appearances made in opposition to the construction of the facility. Likewise, there were no requests for public hearing in connection with the issuanca of the operating license for the facility. ) l The initial construction and proposed use of Lake Robinson as a cooling facility were authorized and approved by the South Carolina Board of Health and the South Carolina Pollution Control Authority. Two permits were obtained from the South Carolina Board of Health. The first, issued on May 12, 1958, was for construction of Lake Robinson. The second, dated January 26, 1960, was for the impoundment of water in the lake. Several permits have been issued by the South Carolina Pollution Control Authority in connection with the Robinson Plant. Permit #179, issued May 12, 1958, covered construction of the lake. Permit #217 was issued on Fby 15, 1961, granting permission to discharge cooling water from the plant into the lake. Since that date, the permit has been revised to modify the release requirements from the lake. This modification is contained in Permit #307 issued June 24, 1964. O 2.3-1

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

in addition to these parmits covering the lake and the discharge O of heated water into the lake, the South Carolina Pollution Control Authority has issued permits numbered 216 and 1732, dated May 15, 1961, and November 25, 1970, respectively. Permit #2':.6 granted permission to discharge effluent from the plant's sewage treating ftcility and permit #1732 covers the oper-ation of the liquid waste disposal facilities serving Unit No. 2. Application has also been made with the U.S. Army Corps of Engineers for a discharge permit for the H. B. Robinson Steam Electric Plant as required under the Corps recent program for inplementing the 1899 Refuse Act. The application was filed with the Charleston District Engineer on June 29, 1971. Two copies of this application were also filed with the South Carolina Pollu-tion Control Authority on the same date, along with a request for certifi-cation as required under the Water Qutlity Improvement Act of 1970. Both transmittals have been acknowledged, and instructions on filing Part B of the discharge permit application have been received by the Company. Response on Part B was made by CP&L in a letter dated September 28, 1971. CP&L knows of no other actions that have been taken on these applications at this time. O In the following sections, 2.3.1 to 2.3.5, a brief description is given of each major permit required in connection with the Robinson Plant and of the procedures that were followed in obtaining these permits. 2.3.1 AEC Construction Permit On July 12, 1966, CP&L, in connection with its proposed construc-l tion of the Robinson Unit No. 2, submitted to the AEC a document titled

        " Preliminary Safety Analysis Report" (PSAR) as required by Title 10, Code-of Federal Regulations, Part 50.        The PSAR described all areas of the pro-posed plant design including its design criteria, quality assurance program and site description with regard to meteorology, climatology, geology, seis-mology , hydrology, topography, and population. Sections of the report described the reactor core, its cooling system, auxiliary system, power conversion system, and electrical transmission system. Other sections of O

2.3-2

l the report were devoted to a description of the plant organization, the plant equipment testing program and a complete analysis of the consequences of r numerous postulated abnormal occurrences. Seventy-two copies of the PSAR and all amendments were submitted to the AEC. Copies of the complete filing were also sent to the Mayor of Hartsville and to the Chairman of the Dar-lington County Commissioners. The AEC distributed copies of the PSAR to various state and federal agencies including the S. C. Pollution Control-Authority and the S. C. Board af Health. A notice of the application was published in the Federal Register and the AEC established Document No. 50-261 for Robinson Unit No. 2. Copies of the PSAR and all subsequent documents related to the Robinson Unit No. 2 were made available to the public for in-l spection and reproduction in the AEC's Public Document Room, 1717 H Street, N.W., Washington, D. C., filed under the appropriate document numbers. i l The Division of Reactor Licensing (DRL) conducted an extensive review and served as coordinator for the AEC review of the application. l The project was assigned to a branch of DRL and a project reviewer was designated for the project. A portion of the review was conducted by specialists in the Division of Reactor Standards (DRS), a parallel division ! to DRL. In its review of the application, DRL called on selected outside consultants to assist them in evaluating the plant design features. These outside consultants included: l

1. Environmental Science Services Administration, Air Resources Environmental Laboratory. This agenc; reviewed the climate and meteorological sections or the application.

2. U.S. Army Corps of Engineers, Coastal Engineering Researcu Center. This agency reviewed the potential storm flooding of the proposed site.

3. U. S. Geological Survey. This agency reviewed the hydrologic and geologic aspects of the proposed plant location.

O 2.3-3

4. U. S. Coast and Geodetic Survey. This agency reviewed the seismicity of the proposed site.

5. U. S. Fish and Wildlife Service. This agency reviewed the potential ecological eff ects on tr e environment of the plant site.

6. U. S. Public Ilealth Service. This agency reviewed the radiological health aspects of the proposed plant.

In addition, various other firms and consultants not associated with the applicant were called upon by DRL to review the application. These consultants reviewed the structural adequacy and various design criteria for the plant. Following this extensive review, the AEC reported its findings to the Advisory Committee on Reactor Safeguards (ACRS) . The ACRS was com-posed of non-AEC personnel with recognized expertise in various disciplines who examined the entire technical aspects of the application and the AEC's review of the application. A subcommittee was formed and an on-site in-spection of the site was made December 13, 1966. On February 17, 1967, based upon this on-site investigation, and its thorough review of the proposed plant, the ACRS advised the Chairman of the AEC that they believed the plant could be built and operated "without undue risk to the health and safety of the public." The ACRS findings were published, a date was set for a public hearing, and an Atomic Safety and Licensing Board Panel was appointed to conduct the hearing. A waiting period was allowed so that interested parties having objections to the pro-posed plant could intervene in the proceedings. On March 10, 1967, prior the scheduled public hearing, a pre-hearing conference was hnid at Darlington, S. C. The purpose of the pre-hearing conference was to establish the agenda and order of the proceedings and to instruct all potential par-ticipants in the hearing. This pre-hearing conference was a public meeting l at which all interested parties were invited to participate. O 2.3-4

k I On March 28, 1967, the Atomic Safety and Licensing Board Panel ' O conducted a public hearing at which it examined the adequacy of the AEC 1 review of the proposed project. During the course of the hearing, the public was invited to offer its comments with respect to the construction of the i proposed generating unit. All public comments were in support of the project. j Following the hearing, construction permit No. CPPR-26 was granted to CP&L on April 13, 1967. Figure 2.3-1 is a flow diagram of the normal processing of an application for an AEC construction permit. .I 2.3.2 AEC Operating License -l l i The first step in obtaining an operating license for any nuclear

                                                                                          -}i facility is the preparation of a Final Safety Analysis Report (FSAR) by the              l proposed operator of the facility. The Robinson Unit No. 2 FSAR was sub-mitted by CP&L to the AEC on November 26, 1968. The report reflected the                 i final design of Robinson Unit No. 2, the anticipated testing programs, the planned plant organization and the proposed criteria to be followed in                   i operating the unit. Distribution of the FSAR and its review by the AEC and               !

its consultants were handled in substantially the same manner as that followed with respect to the PSAR. Copies of the FSAR were transmitted to the S. C. Board of Health; the Darlington, South Carolina County Commissioners; the Mayor of Hartsville, South Carolina; the AEC Public Documents Room; and those various state and federal agencies with an interest in Robinson Unit I i No. 2. t Again, DRL served as coordinator of the review, soliciting assistance from such consultants as the Environmental Science Services l Administration, the U.S. Army Corps of Engineers, the U. S. Geological Survey, the U. S. Coast and Geodetic Survey and the U. S. Fish & Wildlife Service. Aside from the numerous technical reviews which took place with the AEC Division of Reactor Licensing, Division of Compliance and ACRS during the 20 months after submission of the FSAR, CP&L met with AEC Compliance to discuss the pre-operational and operational environmental surveys, submitted various quarterly reports on the pre-operational environmental surveillance O 2.3-5

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

l i program, received and responded to the comments from the U. S. Fish & Wild-life Service, and met with the S. C. Pollution Control Authority to discuss j matters of interest to the state. On April 10, 1970, the ACRS held its full committee meeting on l t Robinson Unit No. 2 and on April 16, 1970, transmitted a letter to DRL j s recommending the issuance of an operating license for the facility. On i June 5,1970, the AEC issued an " Environmental Statement" for Robinson Unit No . 2. The statement covered various environmental effects of the unit including resource commitments, thermal discharges, long-term productivity and other areas of environmental concern. The areas discussed in the AEC's

                     " Environmental Statement" have received further investigation and are in-               !

cluded in this report. f A public hearing is not mandatory for an AEC operating license. l Upon completion of the AEC and ACRS review, the AEC publishes a notice of intent to license in the Federal Register. Any party desiring a public , hearing is allowed 30 days in which to intervene in the proceedings. In l the absence of a request for public hearing or permission to intervene, the AEC may issue the operating license upon a finding by its Compliance Division j I that "the plant is built in accordance with the application." In the case of Robinson Unit No. 2, notice of DRL's intent to license was published in the Federal Register on May 16, 1970. There were I i no requests for public hearing or permission to intervene filed, and on July 13, 1970, DRL issued to CP&L a 5 MWt operating license numbered DPR-23. The low power restriction was removed on September 23, 1970, and Robinson Unit No. 2 was authorized by the AEC to operate at power levels not to exceed 2200 MWt. A chronology of the H. B. Robinson Unit No. 2 FSAR review is ; given In Table 2.3-1. Figure 2.3-2 is a flow diagram of the normal processing of an application for an AEC operating license. i 1 i

2.3-6 l b - - - - - . - - _.- _ - e . - , . _

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

E i 2.3.3 State Waste Water Discharge Permits f The authority to abate, control, and prevent pollution in the l State of South Carolina is vested in the Pollution Control Authority. The l Authority was originally established within the State Board of Health. On July 1, 1971, it became a separate state agency. The Authority Membership-consists of: Director of the South Carolina Water Resources Commission; State Health Officer; Executive Director of S. C. Wildlife Resources Depart- i ment; Director of the Department of Parks, Recreation, and Tourism; Director , of the State Development Board; Executive Director of the State Soil and Water Conservation Commission; one member from each of the congressional l districts, and one member appointed by the Governor. The organization powers, and general procedures were established in Code of Law of S. C. 1962, Section l 63-195 through 63-195.36. The Authority is responsible for maintaining reasonable standards l of purity of the air and water resources of the state consistent with the public health, safety and welfare of its citizens, maximum employment, the industrial development of the state, the propagation and protection of terrestrial and marine flora and fauna, and the protection of physical !

property and other resources. l 1

Under South Carolina law, any person desiring to make any new l outlet or source, or to increase the quantity of discharge from existing outlets or sources, for the discharge of sewage, industrial wastes or other ; ] wastes, or the effluent therefrom, or air contaminants, into the waters or ambient air of the state, shall first make an application to the Authority ' for a permit to construct and a permit to discharge from such outlet or l source. If, after a hearing, the Authority finds that the discharge from such proposed outlet or source will not contravene the standards adopted by l the Authority, such permit to construct and such permit to discharge shall . be issued ta the applicant. The Authority may, if sufficient hydrologic l and environmental information is not available to make a determination of the effect of such a discharge, require the person proposing to make such O 2.3-7

1 l l discharge to conduct studies that will enable the Authority to determine ! O that its quality crandards will not be violated. l i Oc Febraary 14, 1958, Carolina Power & Light Company requested [ permission to appear before the March meeting of the South Carolina f Pollution Control Authority to present a request to design and construct a dam in South Carolina. An engineering report was submitted along with l application for a construction permit to construct a cooling lake. A tem- l t porary permit #179 was issued to CP&L for discharges during preliminary , operations. On March 10, 1959, a permit application was submitted for dis-charging heated water into the cooling lake. This permit #217 was issued on thy 15,1961. This permit was later updated on June 24, 1964, to modify the discharge requirements from the lake. In October of 1959 an application was made for a permit to dis-charge effluent from the plant sewage treating system. This permit #216 was granted May 15, 1961. [ t On November 25, 1970, permit #1732 was issued for the discharge ! t of chemical wastes that are made through the radwaste system serving Robinson t Unit No. 2. I t Figure 2.3-3 is a flow diagram of the typical procedures in i obtaining a permit from the Pollution Control Authority, i f 2.3.4 S. C. State Permit For The Impoundment of Water Pursuant to the Code of Law of South Carolina of 1962, Section 32-8, the S. C. State Board of Health in an effort to protect public health ; and prevent the incidence of insect-born diseases has adopted procedures which require a permit to construct a reservoir and impound' water within the reservoir. Application for a lake construction permit is submitted to 2.3-8

the Board of Health along with detailed plans and specifica; ions for clearing the area to be impounded. Particular attention is given to the public healta as it may be affected by the impoundment. Considerations include the removal of grass, trees, brush, and other vegetation which could create a nuisance or threat l to the public welfare. Consideration also is given to mosquito control j t.easures and protection afforded workmen engaged in constructing the dam and reservoir. l In connection with the proposed construction of Lake Robinson, an application for a lake construction permit was filed with the S. C. State Board of Health in May of 1958. Satisfied that the proposed con-struction would 1,ot create a hazard to public health, che Board issued a anstruction permit on May 12, 1958. l ) l Throughout construction, the Department of Health periodically incracted the progress of work. These inspections were made in an effort V to verify compliance with the permit and determine the adequacy of control measures. On February 24, 1959, a representative of the S. C. Board of Health inspected the construction of the lake to verify compliance with the construction permit. On September 8, 1959, the Board of Health gave permission to CP&L to begin the impoundment of water to an elevation approved by the Board. l On January 26, 1960, after a representative from the State Board ' of Health had determined that CP&L had complied with the construction pro-visions of the rcgulations for impoundment of water, an operating and main-tenance permit was issued defining the conditions by which water could be impounded. Since the issuance of that permit, the Board has periodically inspected the impoundment and adjacent area to guarantee that public health is being protected. O b 2.3-9 _ _ _ - - - - - - - _ - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - . - - - - - - - - - - - - - - - - - - - --- J

f 5 Figure 2.3-4 is a flow diagram of the normal procedures for , obtaining permits to impound water in South Carolina. l 2.3.5 Corps of Engineers' Water Discharge Pe rmit l In accordance with Section 13 of the Rivers and Harbors Appro- i priation Act of March 3, 1899, and the Refuse Act, an application for a pe rmit to discharge into navigable waters must be submitted to the U. S. ; Army Corps of Engineers in the district where the discharge is located. As , required by the Water Quality Improvement Act of 1970, a copy of the plans j and application must be sent to the state agency responsible for water quality in those waters affected by the discharge and to the Environmental Protection Agency (EPA). EPA makes a determination ou the application and submits their findings to the District Engineer. The South Carolina Pollution Control Authority coordinates the review between the Corps of

l Engineers and those state agencies who also forward their comments. In reviewing this application, these agencies consider: conformance with the National Environmental Policy Act, fish and wildlife, water quality, aes- i thetics and various other factors. In compliance with the U. S. Army Corps of Engineers' Refuse Act Permit Program, an application for a discharge permit for the H. B. Robinson , Steam Electric Plant was filed with the Charleston District of the Corps i l of Engineers on June 29, 1971. Two copies of this application were filed l . 1 with the South Carolina Pollution Control Authority on the same date along 1 with a request for certification as required under the Water Quality Improve-ment Act of 1970. Both transmittals have been acknowledged, and instruc-tions on filing Part B of the discharge permit application have been received by the Company. Response on Part B was made by CP&L in a letter dated September 28, 1971. CP&L knows of no other actions that have been taken on these applications at this time. Figure 2.3-5 shows the normal processing of an application for the Corps of Engineers' Water Discharge Permit. O 2.3- 10 1

_ - . . - ~ -. . . . . . -. __ . .- TABLE 2.3-1 CHRONOLOGY OF H. B. ROBINSON UNIT No. 2 FSAR REVIEW i 11/26/68 FSAR Submitted 2/17/69 AEC-DRL Letter requesting information on our medical , . plans 3/11/69 First Technical Review Meeting with DRL 3/24/69 AEC-DRL Letter Requesting Additional Information , 5/15 & 16/69 Second Technical Review Meeting with AEC-DRL 6/20/69 Third Technical Review Meeting with AEC-DRL - Meteorological 6/23,24,25/69 Meeting with AEC Compliance, (AEC-CO) at Site on Pre-operational and Operational Environmental Survey 6/27/69 Submitted 1st Quarterly Report of Pre-operational Environmental Surveillance Program 7/9/69 AEC-DRL Letter - Request Electrical Drawings 7/28/69 AEC-DRL Letter transmitting U. S. Fish & Wildlife Service comments 9/4/69 FSAR Amendment #1 - Responses to 2/17/69 and 3/24/69 O Letters , 9/10/69 Fourth Technical Review Meeting with AEC-DRL - Electrical Design 9/17/69 AEC-DRL Letter Requesting Additional Information 10/3/69 Meeting with AEC-DRL and AEC-C0 at Site on Instrumentation

                            & Control 10/10/69             AEC-DRL Letter requesting information on our Reactor              '

Vessel 10/15/69 Submitted 2nd Quarterly Report on Pre-operational Environmental Surveillance Program ' 10/16/69 Meeting with AEC-DRL, Blume & Associates at Site on Seismic Design 10/23 & 24/69 Fif th Technical Review Meeting with AEC-DRL - Instrument

                            & Electrical Design 10/27/69             FSAR Amendment #2 - Technical Specifications, Emergency Plan                                                          ,

11/4/69 AEC-DRL Letter - 4 outstanding concerns 11/5/69 AEC-DRL Letter - 2nd set of questions O 2.3-11

12/2/69 FSAR Amendment #3 - Answered Questions in 9/17/69 Letter 12/8/69 Submitted Report WCAP-7372-L, December 1969, concerning H 2 Control for H. B. Robinson 2 1 12/8/69 Submitted " Containment Design Report," August 1969 12/10/69 FSAR Supplement #5 - Responses to 9/17, 11/4, and 11/5/69 letters 12/11/69 AEC-DRL Letter requesting financial information 12/15/69 FSAR Supplement #4 - Responses to 9/12 and 11/4/69 letters 12/17 & 18/69 Sixth Technical Meeting with AEC-DRL - Misc. Items and Organization 7 12/31/69 AEC-DRL Letter requesting information on Robinson thermal : parameters l 1/15/70 Meeting with AEC-DRL at site - crew size and organization ; 1/20/70 Letter to AEC-DRL answering thermal parameters 1/21/70 ACRS Subcommittee Site Inspection 1/23/70 FSAR Amendment #6 - Page Changes and Answers to 11/5/69 [ 1etter 1/23/70 First Technical Specifications Review Meeting with AEC-DRL ! 1/29/70 Seventh Technical Meeting with AEC-DRL - Structural ; () 2/3/70 2/3 & 4/70 AEC-DRL Let ter - Organization Second Technical Specifications Review Meeting with AEC-DRL i 2/6/70 FSAR Amendment #7

2/12/70 Meeting with S. C. Pollution Control Authority at Site 2/12 & 13/70 Third Technical Specifications Review Meeting with AEC-DRL ;

2/17/70 AEC-DRL Site Visit - Electrical 2/18/70 Letter in response to U. S. Fish & Wildlife comments 2/19/70 Fourth Technical Specifications Meeting with AEC-DRL I 2/24/70 FSAR Amendment No. 8 - Organization f 2/27/70 FSAR Amendment No. 9 - Blow Down #2 2/27/70 Meeting with AEC-DRL - Miscellaneous Items 3/13/70 Meeting with AEC-DRL - Outstanding 1ssues 3/18/70 FSAR Amendment No. 10 - Miscellaneous Items 3/18/70 Meeting with AEC-DRL on Seismic Analysis 3/24/70 FSAR Amendment No.11 - Westinghouse Personnel O 2.3-12

I l 3/26/70 Second ACRS Subcommittee Meeting I 4/3/70 AEC Compliance Letter - Separation of Redundant Cables, Welding Procedures, Records at Plant ; 4/3/70 Letter to AEC-DRL transmit ting CP&L Annual Report [ 4/6/70 Letter to AEC-DRL Regarding Seismic Analysis 4/10/70 ACRS Full Committee Meeting ; 4/13/70 AEC-DRL Letter Denying Request to keep Amendment #11 proprietary 4/16/70 ACRS Letter to AEC-DRL k 4/17/70 Letter to AEC-DRL confirming containment design report and control of H reports are applicable 2 4/17/70 Letter to AEC-DRL informing them of Company management changes 4/24/70 AEC-DRL Letter Transmitting ACRS Letter ; 4/28/70 Letter to AEC-DRL requesting that WCAP Reports remain proprietary , 4/28/70 Response to AEC Compliance on their 4/3/70 Letter 5/1/70 Meeting with AEC-DRL on Tendons & Pipe Rupture 5/7/70 AEC Compliance Letter Acknowledging our 4/28/70 letter 5/8/70 FSAR Amendment #12 - Resubmittal of Amendment 11 with O names deleted 5/12/70 AEC-DRL Letter acknowledging CP&L regt.est in Amendment #12 5/14/70 AEC-DRL Letter requesting information on tendons , 5/14/70 AEC-DRL Letter transmitting notice and draf t license 5/16/70 Notice of license in Federal Register 5/20/70 AEC-DRL letter transmitting their public safety evaluation , 5/26/70 Submitted 3rd quarterly report on environmental monitoring program ; 6/5/70 Letter to AEC-DRL transmitting three reports : (1) Tendon, (2) Turbine overspeed, and (3) Seismic Analysis of Class I Pipe and Equipment 6/5/70 AEC-DRL Letter transmitting environmental statement ! 7/1/70 Letter to AEC-DRL transmitting supplement to Turbine Overspeed Report 7/1/70 Meeting with AEC-DRL - Turbine Missile 7/3/70 Letter to AEC-DRL transmitting " Steam Pipe Break" report j t 7/15/70 Meeting with AEC-DRL/C0 regarding outstanding items i 7/16/70 Letter to AEC-DRL on outstanding items & cable tray 2.3-13 i P

.. _ . = _ .     . . _ - _    _       . _ . - . _ _ _ .        . . . .    . . _ _ . _ _ _ .   . . - . _ . _ _ .     . _.__ __ _ _ . -

i e 7/20/70 Meeting with AEC Compliance at Site on Containment Air . O' Test l 7/23/70 Letter to AEC-DRL' submitting containment Integrated ' Leakage Rate Test Report , 7/23/70 Meeting with AEC Compliance at Site on Outstanding Items l 7/24/70 Meeting with AEC-DRL/DRS/C0 on Containment Test 6 Outstanding Items 7/28/70 Letter to AEC-DRL transmitting Addendum A to Containment ' Leakage Rate Test 7/30/70 Telegram to AEC-DRL Regarding Safety Injection Pump Performance 7/31/70 AEC-DRL Letter transmitting 5 MWt Operating License , 8/12/70 Letter to AEC-DRL transmitting re-analysis of Safety Injection Pump Performance 8/18/70 Letter to AEC-DRL transmitting Addendum to Seismic Design of Class 1 Piping and Equipment Report 9/23/70 AEC-DRL Letter transmitting approval to operate at a power level not to exceed 2200 MWt , C:) 1 I I 2,3-14 l

i 3.0 ENVIRONMENTAL IMPACT OF THE NUCLEAR FACILITY 3.1 LAND USE COMPATIBILITY Robinson Unit No. 2 was constructed on a site already dedicated to the generation of electrical power and as such minimized the conflicts i with other land uses. Construction at the Robinson site began in 1957 with installation of a 185 MWe fossil unit which was placed in commercial opera-tion in 1960. Development of the site in the late 1950's included construc-tion of the 2250-acre Lake Robinson which provides cooling water for both the i No. 1 and No. 2 Units. In the initial development of the Robinson site, a total plant capacity of 1200 MWe was considered and anticipated. The plant area was cleared and graded for future units and the cooling lake was sized accord- l ingly. The decision to expand an existing generating site rather than develop a new plant site minimized the effect of this required generating capacity on the environment. Except for the physical erection and resulting visual effect of additional structures in the plant area, the only alteration of the landscape with the construction of Robinson Unit No. 2 was the exten-sion of the cooling water discharge canal from a point approximately 1.2 miles upstream from the plant to a point 4.2 miles upstream. Extension of the canal was along the lake shore and involved land already owned by CP&L. Land clearing affected less than 100 acres of land, most of which was second growth pines. In many of those areas affected by clearing and construction, pine seedlings and various types of grasses have been replanted to control erosion, provide new ground cover for wildlife, and present an : aesthetically pleasing landscape. The construction of Robinson Unit No. 2 did not require the reloca-tion of any people, the construction of any additional cooling facilities, or the relocation of any highways or railroads. Land use characteristics in O , 3.1-1

the vicinity and region of the site with regard to industry, farming, and forestry were not affected. Figure 1.1-1 shows the Robinson plant. This indicates the com-patibility of the nuclear unit with its environs and the absence of signi-ficant impact from Unit No. 2 on surrounding land uses. l t I i O 1 l I O 3.1-2 ! l 1

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

1 3.2 WATER USE COMPATIBILITY O The source of cooling water for Robinson Unit No. 2 is Lake Robinson. The lake was constructed in the late 1950's as a cooling facility for a 185 MWe fossil fueled unit placed in operation in May of 1960 and for those future steam generating units anticipated for the plant. Construction and operation of Robinson Unit No. 2 had little effect on the water use compatibility of Lake Robinson. Lake Robinson has been and will continue to be used for fishing, boating, sailing, , and other aquatic sports. There will be an increase in consumptive losses of water as a result of the increased evaporation accompanying the added heat load on the lake. These losses are tabulated in Table 3.2-1. Water is stored in the lake during periods of high inflow, and flow downstream of Lake Robinson is augmented during dry periods by releases of stored water. The result is a more dependable water supply i in Black Creek downstream of Lake Robinson. O The biological effects of Unit No. 2 on the aquatic life in Lake Robinson are discussed in Section 3.6. Biological impacts from the operation of Unit No. 2 are not expected to extend beyond the lake. All the municipal and industrial sources of potable water within a 20-mile radius of the Robinson site are obtained from ground-water sources. Within the vicinity of the plant all domestic water is artesian in origin. With the construction of Unit No. 1, two water wells i of approximately 200 gpm each were provided at the Robinson site. These wells furnish water for boiler makeup, and for potable and sanitary uses. The construction of Robinson Unit No. 2 required three new water wells for make-up purposes and for beckup in the event safety injection should be required and the service water system not be available for such use. A total of approximately 10,000 gallons per day is taken from three new l water wells. This usage coupled with that of the Unit No. 1 has had no ef fect on the surrounding ground water as evidenced by the continued O 3.2-1

i artesian pressure in the area. A further description of the ground water { hydrology at the Robinson site is given in Section 2.1.8. f O G - 3.2-2

TABLE 3. 2-1 AVERAGE EVAPORATIVE WATER IDSSES FROM IAKE ROBINSON WITil UNITS 1 & 2 IN OPERATION Natural Fo rced Total Month Evapo ra tion Evaporation Evaporation (cis) (cfs) (cfs) Janua ry 3.16 12.04 15.20 f Feb rua ry 5.26 13.95 19.21 March 8.51 14.08 22.59 April 12.44 15.99 28.43 May 14.79 16.60 31.39 June 16.41 18.00 34.41 July 16.04 17.63 33.67 , l Au gus t 14.83 17.45 32.28 O September 12.03 17.21 29.24 October 7.88 15. 12 23.00 l November 4.97 13.84 18.81 December 3.06 11.91 14.97 Year Average 9.97 15.32 25.29 i O 3.2-3

L F f P 3.3 HEAT DISSIPATION O All steam electric generating plants must release heat to the environment as an inevitable consequence of producing useful electricity. , Heat from the fission of nuclear fuel in the Robinson No. 2 reactor is used to produce high temperature and pressure steam. This steam is ex-panded through a turbine where the thermal energy of steam is converted to mechanical energy. This mechanical energy is used to drive the gen- , erator which in turn converts the mechanical energy of rotation to elec-trical energy. The process has a limited efficiency, however, and the steam, after having expanded through the turbine, must be condensed back into water. This is done by extracting the latent heat of con-densation from the steam and transferring it to some other fluid. The fluid in this case is the circulating water and the heat transfer is made in the condenser. For the Robinson Unit No. 2, the circulating water is obtained from Lake Robinson. A total of 1070 cfs is taken from Lake Robinson at ! () the intake structure and passed directly to the condenser. The condenser consists of a large rectangular vessel containing thousands of small tubes j through which the circulating water passes. Exhaust steam leaving the i turbine flows over and around the outside of these tubes and, in so doing, l condenses to vater and drops to the bottom of the condenser where it is collected for reuse in the cycle. In the process, the latent heat of condensation of the steam is transferred to the circulating water. Under con-9 ditions of full load on the Robinson Unit No. 2, approximately 4.3 x 10 Btu /hr. of heat is transferred to the water, resulting in an approximately 18 F increase in the water as it passes through the condenser. There is no physical contact between the condensing steam and the circulating water. Furthermore, since the steam side of the condenser operates at a vacuum under normal conditions, the possibility of steam side materials leaking into the circulating water is remote. Af ter passing through. the condensers , the heated water is then discharged to a canal which returns the warmed water to the lake at a point 4.2 miles upstream from the plant. O 3.3-1

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

As the water flows through the lake either to be used again in plant condensers or to be released from the lake into the stream below, ( it cools by losing heat to the atmosphere. The major mechanisms of heat loss are back radiation, evaporation, and conduction. The magnitude of all three mechanisms is dependent upon the temperature of the water sur-face. Back radiation is proportional to the fourth power of the absolute temperature of the surface. Conduction from the surface is proportional to the difference in water temperature and air temperature. Evaporatis. heat losses are proportional to the difference in saturation vapor pressure at the water surface temperature and the water vapor pressure in the air. There are two primary effects of the plant discharge on the lake. One is a general warming over most of the lake surface, and the other is the , evaporation of water from the lake. The warming is confined essentially ! to the upper 10 or 15 feet of water. Below these depths, the water temp-erature remains near the natural temperature which might be expected in t any impounded reservoir. Figures 3.3-1 through 3.3-6 show isotherms for various sectors of the lake. O The evaporative losses which vary from season to season are shown in Table 3.2-1. However, in a broad sense water is never lost. The supply of water circles endlessly from sky to land to ocean and then back to sky again. Water rising from the oceans, lakes, streams, and ' land accumulates in the atmosphere partly as invisible vapor and partly as tiny condensed droplets. Some of this moisture in the air falls to earth as rain, snow, sleet, or hail. There is a small amount that quickly returns to the ocean as runoff via streams; some feeds vegetation, some sceps into the ground; but most of the water on the earth's surface returns to the atmosphere by evaporation. Within this mechanism the amount of , water remains essentially constant. 4 6 O 3.3-2 l 1 1

I ] 1 3.4 CHEMICAL DISCHARCES O In the operation of Robinson Unit No. 2, some chemical wastes are produced in the processing of high quality feedwater and in the operation of certain auxiliary systems. These chemicals include corrosion products such as iron and copper; corrosion inhibitors such as potassium dichromate, hydrazine and sodium phosphate; acids and bases such as boric acid, sulfuric i acid and sodium hydroxide; and small quantities of various chemicals used in the plant laboratory. Those chemical wastes that are subject to possible radioactive contamination or toxic concentrations are processed through the radioactive waste treatment system where they are collected, monitored, neutralized or otherwise treated prior to release into the environment. A detailed description of the Radioactive Waste Processing System and its operation is given in Section 3. 7.1 and 3. 7.2. Those other chemical wastes or chemical uses not subject to radioactive contamination or toxic concen- , trations are discussed in the following paragraphs. Sodium hydroxide (NaOH) and sulfuric acid (H2SO 4 ) s lutions are used to regenerate the make-up water demineralizers. After use, these solutions are collected in a tank where they are neutralized and subsequently discharged into the service water system which conveys them to the lake. A chlorinating system is utilized to inhibit the growth of slime and algae in the Robinson No. 2 condenser and the circulating water tunnels. This system uses sodium hypochlorite and is normally operated for only two 30-minute cycles per day. Chlorine residuals in the water leaving the con-denser are controlled so that concentration does not exceed more than 0.5 ppm. This residual is further dissipated in the discharge canal so that no more than a trace of chlorine is experienced in the lake. Phosphate is used in the steam generator to control hardness scaling and to prevent corrosion. Blowdown water from the steam generators is either processed through the liquid Radioactive Waste Processing system or discharged from a flash tank to the circulating water system in the absence of radioactive O 3.4-1

y contamination. Because of the extremely small quantities of phosphate that are discharged and because of the natural low levels of phosphate in the lake water supply, this disposal of blowdown water is not expected to have any effect on the environment. To date water samples from Lake Robinson have failed to reveal detectable quantities of phosphate. In the turbine building and other areas where oil spills and leaks might be reasonably expected, the floor drains discharge to an oil trap and catch basin. There the oil and water are separated. The oil is accumulated and the water is discharged to the environment. Periodically the oil is removed from the trap and used in the fossil-fired Unit No. 1. The only releases of chemical combustion products to the atmosphere are those associated with two auxiliary boilers which are provided for inter-mittent duty during startup, shutdown, and during liquid radwaste concentration operations, and from the two diesel generators provided for emergency power. Both the auxiliary boilers and the emergency diesels are fired with No. 2 fuel oil which has a maximum sulfur contant- of less than 0.17.. To control ground level concentrations of the resulting combustion gases, these gases are vented from stacks set at approximately 56 feet above plant grade in the case of the auxiliary boilers and 33 feet above plant grade in the case of the diesels. O 3.4-2

3.5 SANITARY WASTES i The Robinson sewage and sanitary waste treatment system . l consists of a 3000-gallon per day septic tank, sand filter, and chlorine ) contact chamber.' The wastes are collected and pumped to the septic tank ! l where the solids are allowed to settle and undergo aerobic digestion. 1 The septic tank produces an odorless liquid effluent and a granular sludge which is accumulated in the tank. The sludge is periodically ; removed for off-site disposal in accordance with state and local regu- [ 1ations. The liquid effluent from the septic tank drains away from the l tank through a sand filter, and is collected and chlorinated before being discharged into the condenser cooling water system canal. The removal of solids and reduction in biochemical oxygen demand (BOD) as I a result of this treatment is in excess of 907.. Permit No. 216 issued by the South Carolina Pollution Control Authority on May 15, 1961, covers the operation of the sewage and sanitary waste treatment system and the discharge of its effluent into the condenser cooling water system. 4 O 3.5-1

3.6 BIOLOGICAL IMPACT O 3.6.1 Environmental Effects 3.6.1.1 Biological Effects Lake Robinson was impounded with the construction of Unit No. 1, a 185 MWe coal-fired unit which went into operation in 1960. Creation of Lake Robinson converted about 2300 acres of second-growth pines, bottomland ' hardwoods, swamp forest, and peripheral lands into a 31,000 acre-f t, cool-ing reservoir. As a result of the impoundment and prior to the introduction of the plant heat load, waters in Black Creek from the point of entrance to the lake to the point of discharge to Black Creek downstream of the lake have been increased in temperature and dissolved oxygen (DO) . From the stream entering the lake to the stream leaving the lake, the temperature has been increased by about 5 F and D0 has been increased by about one ppm. This temperature increase is due to heat absorbed from solar radia-tion and the increase in DO is due to aeration of the lake discharge. The () black-water stream sport fishery in that stretch of the creek prior to construction of the lake was changed into a bass-bluegill-crappie impound-ment fishe ry . While limited information is available on the fishery resources of Black Creek prior to the lake construction, it is generally known that black-water stream sport fisheries are mediocre. Open waters of the lake provide boating and sailing opportunities, and have enhanced the recreational-residential value of surrounding land. Impact on Terrestrial Ecosystem Construction and operation of H. B. Robinson Unit No. 2 has had and will continue to have little effect on the terrestrial ecosystem. The I unit was constructed on land already cleared with the installation of Unit No. 1. Extension of the discharge canal toward the upper end of Lake Robinson required approximately 100 additional acres of second-growth O 3.6-1 e

pine woodlands which generally are recognized to provide poor habitat for () wildlife. Banks of the canal and of the maintenance road, which is lo-cated between the discharge canal and the lake have been seeded with several types of grasses and pine seedlings. In all, 187,000 pine seedlings have been planted along the canal and other areas disturbed during the con-struction of Unit No. 2. While erosion along the maintenance road is moderate to severe in some areas, efforts to stabilize these areas are continuing. Eventually, these areas will be vegetated which will prevent erosion and provide cover for wildlife. Impact on Aquatic Ecosystem A Federal Aid anadromous fish stocking project was initiated in 1967 by the S. C. Wildlife Resources Department. The Department stocked Lake Robinson with striped bass-white bass hybrid fry in the following j numbers: l t l Spring 1967 130,000 () Spring 1968 200,000 Spring 1969 520,000 Fish populations in Lake Robinson have always been at a rela-tively low level. Prior to the startup of Unit No. 2, the S. C. Wildlife Resources Department reported that " age and growth studies of the major game species in Lake Robinson indicated relatively poor growth rates" when compared to other impoundments in South Carolina. The low popula-tion and growth rate figures are likely due to low natural productivity l in the impoundment and not to heat rejected to the water from the genera-ting facilities. These slow growth rates are believed to be due to the low nutrient levels and associated low productivity characteristic of many sandy-bottomed black-water streams and lakes. O 3.6-2 f

E' 1 () Impact of Thermal Discharges There are several factors which must be considered in a dis-i cussion of the effects of thermal discharges on aquatic organisms. These , r include behavior, growth, development and reproduction of the organisms. Each of these factors is affected by chemicals present in the water, ac-climation to the temperature encountered, and many other factors such as ! the availability of food, pH of the water and dissolved oxygen in the water, t When subjected to uncomfortabic temperatures, organisms may re-spond in one of the following four ways: (1) mobile organisms may leave the area of elevated temperatures; (2) physiological changes in the orga-nism may adjust to the elevated temperature; (3) a protective position or behavior may be assumed such as the development of a dormant state; or (4) the organism may succumb. () The effect of elevated temperatures on a given species of fish is dependent on many factors including the temperature to which the fish , has become adjusted prior to being subjected to the elevated temperature. l Fish do have some ability to adjust to the physiological changes which occur with increasing water temperatures and, therefore, fish can with-stand warmer temperatures if the rate of temperature increase allows the { fish sufficient time to acclimate. Should the rate of temperature increase ; be too rapid to allow sufficient time for acclimation, or if the final temperature is too high, fish have the ability to leave the area of ele- ' vated temperature. i Persistent elevated temperatures are suspected of causing be- l havioral changes by (1) causing stratification of the water column, ' discouraging vertical movement of organisms; (2) creating thermal barriers to spawning and nursery grounds; (3) producing seasonal change in spawning and development; and (4) altering migration patterns.

3.6-3 1 1

h Thermal tolerance of an organism depends on its most sensitive and exposed part, which appears to be its soluble protein complexes. The n'ost vulnerable soluble protein complex of the adult is its neuro-endocrine transmitter substances which function outside of cellular membranes and involve its highest level of organization. As shown by Figure 3.6-1, thermal tolerance varies considerably from one life stage to another > (Jensen, 1969). Young of a species are less complex than adults and can survive temperatures at which adults succumb. As organisms become more complex, resistance is exchanged for ability to adapt and thermal resistiv-ity decreases. Adults seem to tolerate the greatest rate of temperature change because of their ability to acclimate or compensate behaviorally. 1 In response to maximum temperature, the breeding adult is the most sensi-tive life stage. Table 3.6-1 indicates " provisional maximum temperatures , recommended as compatible with the well being of various species of fish and their associated biota". This is a partial listing only, but it 11-lustrates the limitations of temperatures on various activities of several fish species. O Temperature tolerance limits provide valuable information on the ability of fish to withstand elevated temperatures. There are, however, precautions which must be exercised in interpreting such data. These temperature tolerance limits were obtained, by necessity, through laboratory experiments and the results could be biased by additional stresses associated with capture and handling of the fish from stresses I associated with the artificial environment in which the fish are kept for the experiments, and from examining specimens in isolation from inter-actions with other species. The difficulties involved in keeping fish in aquaria water are well known to workers in the field (Jensen,1969) . Thermal tolerance tests conducted at the North Carolina State University Pamlico Marine Laboratory on estuarine organisms were complicated by the tremendous expenditure of time and effort in keeping estuarine organisms in artifi-cial environments (Copeland, 1970). Parasites are a problem because of l O 3.6-4

I i

overcrowding and because of other stresses which are not present in the natural environment. Nitrogenous wastes produced during captivity may prove lethal to some or all of the captive organisms, and water that is too pure may create problems. Temperature tolerance limits (LD-50) for several species'of fish and conditions of acclimation are included in Table 3.6-2 and Table 3.6-3. When acclimated to 86 F, the LD-50 of bluegill under labora-tory conditions was reported to be 93.2 F when held at the elevated temperature for 60 hours, and 96.9 F when held at the elevated temperature for 24 hours. The LD-50 for large-mouth bass was reported to be 93.2 F if the bass were held at the elevated temperature for 72 hours. Other work (Trembley,1960) found the LD-50 of bluegill to be 103 F when ac-climated to 79 F, and the LD-50 of large-mouth bass to be 100 F to 102 F when acclimated to 80 F and kept at the elevated temperature for 18 hours. Since fish can move freely in Lake Robinson and possess the ability to seek out favorable temperatures, it is not anticipated that they.will re-main in an area of elevated temperature for a sufficient period of time that water temperature could pose a threat to their survival. As shown in Table 3.6-4, bluegill prefer temperatures as high as 90.1 F and large-mouth bass prefer temperatures as high as 89.6 F; however, acclimation temperatures were not given. Based on this and other data, it is apparent that a moderate elevation of temperature in Lake Robinson, which is typical of cooling lakes, should not inhibit a viable population of fish in the lake. Of course, factors other than the increase in temperature may inhibit the growth and reproduction of fish in Lake Robinson or any other lake. There is little information that has been published on the ecology of cooling lakes. Many studies are presently underway and mean-ingful data should be available for prediction of effects within the next few years. O 3.6-5

I f Experience in Lake'Julian, a 365 acre cooling lake near Asheville North Carolina, suggests that a warm water fishery such as that of Lake Robinson can flourish at elevated temperatures. Lake Julian was impounded in 1964 and served a 200 MWe fossil unit until May of 1971 when a second fossil unit of 200 MWe was installed. Prior to the installation of Unit No. 2, water temperature near the discharge reached as high as 104 F during the summer months. With the operation of Unit No. 2, summer water tem-perature reached 109 F during 1971. Records maintained by the Lake Authority on catches by sports fishermen in the lake indicate that there is a healthy population of fish present in the lake, and only a portion > of the fish caught in Lake Julian are recorded by the Lake Authority. As shown in Figure 3.6-2, operation of both generating units at the Robinson Plant produced surface water temperatures of 90 F or above, over the upstream one-third to one-half of the lake. As shown by Figures 3.6-3 through 3.6-9, this wamer water is present only in the surface layer except in the immediate vicinity of the discharge to the lake. September 1971 thermal cross sections show the 90 F+ water to extend to the lake bottom in the immediate vicinity of the discharge and to extend downstream as a sheet overlying cooler water. In contrast to this con-dition, thermal cross sections during September 1962 when only Unit No. I was in operation (Figures 3.6-10 through 3.6-13) contained no areas of 90 F+. Comparison of lake temperatures from a survey in September 1962 prior to the operation of Unit No. 2 and from a survey in September 1971 with Unit No. 2 in operation shows that Unit No. 2 has had little effect on the tem-peratures of those waters below the lake surface. Summer conditions may produce slightly warmer water temperatures than those depicted and a larger area of the lake surface may have water temperatures of 90 F or greater; however, the effects on below surface water temperatures should remain small. , i The availability of adequate amounts of dissolved oxygen (DO) l is necessary to the survival and reproduction of fish. The amount of oxygen that can be dissolved in water decreases as temperature of the water increases. The maximum amount of oxygen that can be dissolved in l fresh water at standard atmospheric pressure is given in Figure 3.6-14. O 3.6-6

It should be noted that natural waters often do not carry the amount of DO that is theoretically possible. In those cases, an increase in tem-perature would not decrease the amount of DO present in the water but would only decrease the amount of D0 that the water is capable of carry-ing. In black-water creeks, DO is normally less than saturation. Another effect of increased temperature on dissolved oxygen levels in wcter is to increase the biochemical oxygen demand (BOD). Biodegradable organic material in water exerts a demand for oxygen during ; assimilation of the material. An increase in temperature intensifies l 1 l the action of micro-organisms responsible for the assimilation. The j material is assimilated over a shorter period of time and the amount of oxygen utilized during that time period is greater than the amount that would have been used during the same period at a lower temperature. The net result is a drop in the oxygen content as shown in Figure 3.6-15. In consideration of the possible effects of temperatures on DO, surveys of the amount of D0 present in the waters of Lake Robinson have been undertaken. A survey completed in October, 1971 shows that D0 concentrations range from 4.9 to 7.0 milligrams per liter. Based on recent field surveys in other reservoirs (Doudoroff & Shumway, 1970), which have shown that warm water fish can thrive in waters which contain less than 4.0 milligrams per liter, it is concluded that adequate DO is available for a thriving fish population in Lake Robinson. As stated earlier, Lake Robinson supports a limited bass-blue-gill-crappie impoundment fichery with somewhat reduced growth of most species when compared to growth in other South Carolina reservoirs con-structed on streams other than black-water creeks. Reduced growth which is typical of sandy bottomed black-water iarpoundments such as Lake Robinson is believed to be the result of poor nutrient availability. Water chemistry recently performed on samples collected in Lake Robinson support this position. Of course, other factors may be involved in the reduced growth. O 3.6-7 _ _ _ __ _ _ . _ ___ _ ____ _ o

          ,s...   -         .~.      . . _ . . .    &                     _.4.a_.m.- .2a..          . , 2 , ...

I i I l l l During operation of Unit No. 2, the fishery may continue to be f mediocre; however, Lake Robinson was designed as a cooling facility to ! dissipate waste heat to the atmosphere with a minimal impact on the en-vironment and was not designed to maximize the fishery resource. While it is believed that the additional' heat load from Unit No. 2 will not i significantly affect the existing mediocre imprundeent fishery, results i from the ecological study must be awaited before the effect of Unit No. 2 will be known. Impact of Passage Through The Plant Condensers [ The effect on organisms being passed through the plant conden-sers has received increasing attention from biologists during recent years. In part, this increased interest is due to the rapid expansion of in- > stalled steam electric generating capacity and to the greater demand for f cooling water in nuclear plants than is required in fossil plants of i similar size. Factors which influence the effect on entrained organisms i upon passage through the condenser include temperature rise through the condenser, maximum temperature attained, length of time the organisms are held at the elevated temperature, mechanical mortalities, and effects { 4 of blocides such as chlorine. i In the case of significant mortalities of entrained organisms, j a source for repopulating the discharge water is necessary for a continued viable population. The overriding consideration in determining the effect of passage through the condensers is the effect on populations in the vicinity of the power plant and not the effect on populations in the dis-charge canal. Some locations may show no significant change if all organisms passing through the condensers succumb while other locations may be sensi-tive to a small percentage of mortalities. Studies in the vicinity of the Dickerson Power Plant on the ! Potomac River (Patrick, et al, 1954) did not find a significant difference in the number of diatom species or the total number of individuals between 3.6-8

upstream and downstream stations. These results are supported by other () studies at the same plant which indicate that there were no significant effects on algae by passage through the condensers in August. Additional work (Patrick,1968) indicates that there will be little effect on algae being passed through the condensers if temperatures do not exceed 100 F - 101 F. In England, nanoplankton populations were not significantly affected by passage through the condensers of the Bradwell Nuclear Power Plant (Wood, 1963). However, at the Chalk Point Power Plant located on the Patuxent River in Maryland, significant effects on plankton being ' passed through the plant condensers were found (Mihursky,1969) . Samples taken at the intake and discharge locations showed reduction in photo-synthetic capacity of up to 947. during the warmest part of the summer. i However, it was noted that factors such as chlorine could have been par-tially responsible for the effect. Chlorine at this power station has been reported to be as high as 5 ppm in the discharge canal (Carter,1968) . At the same power plant, Morgan and Stross (1969) found that there was a () decrease in primary production over the period of a year. Loss of pro-duction during the summer months was calculated to be as high as 424 tons. Increased production during the winter months did not equal this loss and there was a net loss in production over a year. However, the effects of ' heat and chlorination were not separated and much of the loss may be at- i

tributable to abnormally high levels of chlorine. ; A report completed for the Edison Electric Institute by research- I era at Johns Hopkins University (Jensen,1970) found that photosynthesis was increased by increased temperatures from a power plant on the James River. 1 Photosynthesis was reduced during the summer months; however, the reduction in photosynthesis was not nearly as great as reported by Morgan

and Stross. In addition, increased photosynthesis during the cooler months !

{ was greater than the loss during warmer months and there was a net gain in - ! photosynthesis over the year. i

O 3.6-9 i

4

            +  - ~ - - - - - .

Trembley (1960) (1965) found fewer species in the varm water discharge of Martin's Creek Plant on the Delaware River but each species was represented by a greater number of individuals than were present in unaffected waters. Chlorination reduced the total numbers of individuals but did not appear to reduce the number of species. Heinle (1969) reported that estuarine copepods were killed during passage through the condensers of the Chalk Point Plant even though tem-peratures encountered were generally below the upper limits of thermal tolerance of the copepods. Chlorine was suspected by Heinle as being the maior factor in the kill. Population densities of copepods in the Patuxent River wera fa'ind to be relatively constant in spite of significant mor-talities in the plant condensers. This indicates that copepod populations have considerable resilience to changes in predation and to increased pre-dation and environmental temperatures. Studies in England of the effect of the Bradwell Nuclear Power Plant on zooplankton populations in the Blackwater River were conducted O both before and after the plant started operation (Whitehouse, 1965). No changes were detected that could be attributed to the effects of the power plant. Other work has demonstrated rapid recovery of fresh water proto-zoans af ter extreme temperature shocks (Cairns,1969) . When the temperature was increased from 74 F to 122 F, the number of species dropped from 26 to 7. Within 24 hours, the number of species had increased to 18 and com-plete recovery was demonstrated within 144 hours (Figure .,.6-16). Of course, a 48 F shock is much more severe than that produced in a power plant condenser. In the case of Robinson Unit No. 2, the temperature in-crease of the cooling water as it is passed through the condensers is about 18 F. Research on epifaunal organisms at the Chalk Point Power Plant

  'Nauman & Cory, 1969) found that a higher production or wrred in the O

3.6-10

discharge than in the intake during all months studied. This higher production occurred even though there was a dec rease in the number of spec ie s in the discharge canal during July and August . production in the e f fluent canal averaged three times as great as production in the in.ake during the period of a year. Studies in IAke Julian, a cooling lake serving the Asheville plant which carries a heavier heat load than Lake Robinson, during the Summer o f 1971 demons t ra ted t ha t a viable population of plankton can exi s t when d ischa rge t empe ra t u re s reach as high as 109 F. Species com-position of algae in the discharge canal shif ted from diatoms towa rd b lue- g re e n ; h owe v e r , populations in the main lake body are dominated by ( intome and vreen algae. populations in the lake can be described as "i calthy" and no large " blooms" have been observed. From data which is cited above, one can predict that there may be some loss of phytoplankton and zooplankton during the summer months in the wate r being passed through the condensers of the H. B. Robinson plant. It is not possible to predict the extent of these losses or what the effect of these losses will be on populations in Lake Robinson. The majority of the lake volume will have temperatures compatibic with abun-dant plankton populations. Inflow 1 rom Black Creek and other creeks which discharge to Lake Robinson are a constant source of zooplankton and phy-toplankton populations. Howeve r, low nutrient levels or other factors may limit these populations. Th e re fo re , ecological studies of IAke Robinson provide the only means of assessing tha effect of passage through the con-denser on plankton populations in the loke. These studies are discussed in Section 3.6-2. Unique or Endangered Species There are no known unique or endangered species present in Lake Robinson. The white bass-striped bass hybrid stocked in lake Robinson by the South Carolina Wildlife Resources Department is unique only in that it 3.6-11 a

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

is not native to the lake. The primary reason the hybrid was stocked in Lake Robinson was to determine if it could survive in a reservoir lacking the preferred forage species of the fish parental to the hybrid. Pre-dominant forage species available to the hybrid in Lake Robinson are sunfish and golden shiner. Studies in 1969 found that hybrid bass had survived since the original stocking in 1967. i Other Biological Impacts ) 1 On occasion, fish will enter the intake structure and be im-pinged upon the screens These fish will be removed and disposed of on-site. i Eutrophication of Lake Robinson will likely occur at a very low rate and, as such, should not be a serious problem. The eutrophication f rate will largely be dependent upon nutrient inflow in the watershed up- l stream of and at the lake. At the present time, the nutrient level in the lake is naturally low, and considering the rate of development in the O Lake Robinson watershed, the nutrient input should not increase rapidly in the near future. With the present levels of nutrients in Lake Robinson f and expected low nutrient levels in future years, it is unlikely that algal l blooms will occur in the lake. [ f i Waterfowl can be expected to use the lake as transient popula- l tions m! grate in the Atlantic flyway. Ducks, geese, and coots, may be occasional visitors. They will not contribute significantly to the nutrient load, nor can they be expected to be much affected by the warmed cooling j water discharge. The warmed waters of Lake Robinson will be an important ' haven for local and migrating waterfowl during times of severe winter f weather - especially when the small streams and ponds in the area freeze over. l 3.6-12

J i ? 3.6.1.2 Radiological Effects O The radiological effects analysis is a systematic examination of the normal steady state, abnormal transient, or postulated accident occurrences of all modes of the H. B. Robinson Unit No. 2 operation. This analysis includes both reactor facility operation and reactor material transportation, with events in the operational mode placed into AEC-classification category. Radiological effects from normal radioactive effluents are discussed in detail in Section 3.7, transportation effects are discussed in Section 3.9, and the radiological significance of abnormal transient and postulated accident occurrences are discussed in I detail in Section 3.11. Radiological ef fects are determined for the appropriate events in each category. The radiological effects determina-tion was conducted utilizing reasonable assumptions, justifiable calcu- l lational models and techniques, and realistic assessments of environmental effects. The radiological impact is a measure of the relative radiological influence the Robinson Plant has with respect to residence background , characteristics already present, as calculated in man-rem exposure to the , () population within a 50-mile radius of the site. Residence background characteristics are assumed to be a combination of the radiation received l by the population from natural radiation background and man-made exposure sources, such as medical X-rays. The man rem concept is the only meaning- , ful way of evaluating the radiological impact on the environment. A , summary of the man-rem for each of the categories discussed above is given l in the individual sections. l l bbn-Rem Concept i The integration of radiation exposure to a group of people, as ! exemplified by the unit man-rem, as contrasted with dose to an individual l in rem, is for genetic considerations. It is apparent that summation of i exposures to individuals at these low levels has no population group j ef fect from the somatic viewpoint. Therefore, the use of the unit man- ; rem is somewhat limited as it must be associated with a group of geneti- l t cally significant size. 3.6-13 > 1

 - , - - , , , .      ,r.- ,-    -
                                       , - - -     - , . . w   -   , . - - - ,

-.- _ _ . - . .- . _ = - . ~ . . _ - . - . - -- As has been shown in Section 3.7, the most significant mode of gene ral population exposure from the Robinson Plant is from direct external radiation from the elevated plume of noble gases. The contribution from the consumption of fish from Lake Robinson is insignificant. These levels ! of exposure are shown to be only a small fraction of permissible dose as estimated for the nearest neighbors. Calculations indicate that actual dose beyond the nearest neighbors reduces rapidly so that average doses to all inhabitants of the 50-mile radius are lower than the nearest neigh-bor estimates by about two orders of magnitude. This is so because of the extensive diffusion capacity of the atmosphere and the fact that the number of occupants in the immediate environs is low. 1 Any man-rem integration requires consideration of whether this population group is of genetically significant size. Also, for an expo-sure to groups in a nearby town (llartsville) or a small city (Florence), consideration must be given, considering population mobility, to whether the group remains intact for a time period of genetic significance, such as the human generation time of thirty years. O - Some insight on genetically significant population groups is available in the publications of the internationally recognized expert group, the International Commission on Radiological Protection. A review of publications of this group through Publication #16 shows general and l repeated use of phrases such as: "whole populations", " population at large", "large populations", " practices in some countries", and " circum-stances which vary from country to country". One might conclude that basic thinking is oriented to the population of a small country or to the , population of a significant section of a large country, which in either ! 6 case would be in the range of 10 to 10 people or more. At the Robinson Plant a 50-m11e radius from the site encompasses a population (1986 pro-jected) of less than 800,000 people. The low probability of statisti-cal detection of a genetic effect is applicable in considering a popula-- tion of this size. For example , ICRP Publication No. 8 considers the l probability of a dominant genetic. effect being experienced by the chil- l dren of a generation of exposed parents. The estimate (acknowledged as - O j 3.6-14 l 1

i may well be high for a number of reasons) was that "the effects of a O few rads would not be detected in the annual statistical returns of a population of 50 million". From this, perspective may be gained on the probable effects of a few rads per year to a few thousand people near i the Robinson Plant. Due to the small genetic significant population l around the plant and the small population dose, the only meaningful assessment of the radiological impact of the Robinson Plant is a com-f parison between the dose received fran operation of the plant to that , received from residence background. ; The whole body dose is the only dose of importance that con-tributes to a genetically significant exposure in man-rem. Critical organ doses have been calculated but are not considered in the evaluation l of the radiological impact from plant operations as the effect on the i t critical organ is not of genetic significance. Since the critical organ l can tolerate a much greater dose than the whole body, the effect on the j critical organ is less than the effect on the whole body. O Natural Radiation Background Radiation of various forms is a normal part of man's natural environment, as it has been throughout his development, and man has demonstrated the ability to develop in the presence of this natural radiation. Every day we receive radiation from the sky, the ground, j the air around us, and the food we eat. The magnitude of this radia-tion 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 ; per year. The various component contributions of this typical value l are discussed below. i i Cosmic rays provide one of the most significant natural , radiation sources. Cosmic radiation is to some extent dependent on latitude and to a large extent dependent on altitude. In the mid- , latitudes, the cosmic radiation varies from about 40 mrem per year at sea level to about 3800 mrem per year at altitudes that jet aircraft 3.6-15 I i 1

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

fly (35,000 feet). This does not mean that all commercial jet airliner crews receive 3800 mrem per year, since this would say they were continu-ously airborne. Assume, for instance, that these crews stay aloft a l tenth of the year; thus, their occupational radiation exposure due to cosmic radiation alone would be in the range of 300 to 400 mrem per year. Even one transcontinental roundtrip per year would give the busi-ness man or vacationer about 4 mrem. The average cosmic radiation of 40 mrem per year will increase to about 150 mrem per year at some mile-high locations such as Denver and Salt Lake City. It is assumed that i 50 mrem per year is a good average for people within a 50-mile radius ! of the 11. B. Robinson Plant. Another source of radiation in nature is the ground itself because it contains many radioactive minerals, particularly isotopes of the uranium and thorium series, together with the important uranium decay , product, radium. Another significant radioisotope in the ground is ! potassium-40, the naturally radioactive isotope of the element potassium. ' This incidence of radioactive material in the ground causes the earth to act, with respect to an individual, as a large plane radiation source. This produces an average radiation exposure in the continental United , States of about 60 mrem per year. Assuming that the average person ; spends about one-fourth of this time outside of buildings, this 6C mrem per year would reduce to 15 mrem per year. There are a number of locations , in the world where the radiation exposure from the ground is actually much higher. In various locations in Brazil, India, and in the French mountains, j the exposure may range from 180 to as high as 1600 mrem per year. This is i largely due to the presence of deposits of thorium near the surface of the l ground in such locations. There also have been reports of exposures higher than these. The fact that these radioisotopes exist in the ground gives l 1 rise to a secondary source of rediation, since the natural decay of the ) uranium and thorium series each contains a natural radiogas. These radiogases evolve from the ground at a fairly constant rate and thus, O 3.6-16 l

i l cause concentrations of natural radiogases in the air. The principal con-() stituent of this source of exposure of radiation in nature is the radio-gas radon, which has a 3.8-day radioactive half-life. This element, together with its daughter decay products, causes a world average whole body external exposure of about 5 mrum per year. Actually the inhala-tion of these radiogases and the deposition of their radioactive daughters in the lung may cause a lung dose of as high as 200 mrem. per year. Since man takes materials fran the ground to build homes and offices, natural radioisotopes from the ground are transferred to these structures. A significant variation will result from the use of different building materials. A wooden structure may give a radiation dose rate of about 50 mrem per year, while concrete may give 70, and brick as high as . 100. Even these may vary within a particular material based on where the material originated. For example, there are some types of stone (such as sane granite and marble) that will produce an exposure of 350 to 500 mrem / year. () All liquids in the world are now and have always been radio-f active due to the presence of many naturally radioactive materials such i as uranium, thorium, radium and carbon-14, all of which have very slow i decay rates ranging from thousands to billions of years. Ocean water is a good example of such natural radioactivity. The measure of radioactivity can'.ents in liquids is usually stated in units of picoeuries per liter. ! In the case of ocean water the natural radioactivity content is about 350 picoeuries per liter. Most of this is due to the naturally radio-active potassium - 40 which has a decay rate (half life) of 1.3 billion years. River water radioactivity usually averages between 10 and 100 picocuries per liter. l Due to these activities in liquids used for human consumption, the average concentration in the liquids of the human body is about 300 l picocuries per liter. The general average radiation exposure from food and water is about 25 mrem per year, due to the deposition and retention O 3.6-17

i of these radioactive materials within the body. In a typical case, about , ( ). 20 mrem per year of this exposure comes from the natural radioisotope potassium - 40, which is found particularly in protein type foods. Total Radiation from Nature The following table summarizes the various contributions in , arriving at an average natural radiation background of 140 mrem per year for people living in a 50-mile radius of the 11. B. Robinson Steam l Electric Plant. , Cosmic Rays 50 Ground (1/4 time) 15 Buildings (3/4 time) 45 Air 5 Food and Water 25 I 140 m. rem per year i 4 () Man-Rem From Natural Radiation Background i Calculations of the total exposure to the population as a - result of natural radiation background have been made. Certainly it I is obvious that if it is assumed that every person in the United States receives an average of 140 mrem / year then the total population exposure ' would be about 30 million man-tem per year. However, it is not appropriate to compare the radiological effects of the operation of any one nuclear power plant, as negligible as they are, with the total man-rem / year to the : entire U. S. population. Therefore, the man-rem comparisons are made E for the population within a 50-mile radius. Assuming the projected pop- I ulation within a 50-mile radius of the Robinson Plant is 783,831, the i i natural background radiation will result in about 156,762 man-r.em/ year . ; Man-Made Radiation Background Total population exposure from man-made sources is more difficult (I to evaluate since there can be an individual choice made as to whether such l 3.6-18 e e

radiattoa is received. However, reasonable assumptions can be made in

 'O    order to make estimates of man-rem per year since it is not feasibic to monitor the population 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 1-10 mrem / year from watching TV. Say the average dose received is 5 mitm/ year, then this results in 5000 man-rem / year. Look-ing at chis same population, one can determine the man-rem as a result of exposure from luminous-dial watches. If only 10 percent of this example is exposed to 2 mrum/ year, then the resultant population dose is 200 man-tem / year. The use of medical X-rays is by far the largest contributor to population exposure from a man-made source. Again considering the example 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 re-O ceived an annual chest X-ray of 100 mrem per examination, the result would ; be 10,000 man-rem / year. l In summary, medical exposure results in the largest man-rem per year contribution from man-made sources. However, the examples i of television viewing and wearing luminous dial watches do contribute 1 to population exposure and should be included when comparing the impact l on man from these and other man-made sources. For the purposes of comparison a value of 60 mrem / year due to all man-made sources has been used for determining man-rem exposures to the population within a 50-mile radius of the H. B. Robinson Steam Elcetric Plant. ! r Total Average Radiation Background l The total background radiation exposure received by the average ; citizen within a 50-mile radius of the Robinson Plant is the sum of the , 3.6-19 ,

contributions received from natural background and man-made sources. 'Ihe resultant total is the 140 mrem / year from natural sources and the 60 mrem / year from man-made sources giving an estimated total of 200 mrem / year to the average resident o f this area. Variations in Radiation Background So far, only average radiation background has been discussed, however, it is well established that variations do occur from place to place and from year to year. The following information substantiates this. Airborne radioactivity surveys conducted by the U. S. Geologi-cal Survey on behalf of the Division of Biology and Medicine of the USAEC have shown the variations of radioactivity 1cvel from place to place. These surveys are a part of the Aerial Radiological Measurement Surveys (ARMS) program, a program of airborne radioacitivity surveys of nuclear installations. O Measurements consist of whole body gamma dose from the ground, air and cosmic-ray sources. From the standpoint of airborne activity, only three naturally occurring radioactive elements are important: uranium, potassium-40, and thorium. The relative amounts vary with the type of geological formation. In fact, measurements have shown varia-tions of natural background of up to four to six times within a 10-mile distance. This means that values between 50 to 200 mrem / year have been measured. Some areas that have certain types of granite and marble will produce exposures of 350 to 500 m. rem / year. As stated earlier, this material has been used as building material for some of our most stately public structures. Variations can also occur from year to year even at the same location. For exampic, an annual variation of up to 10 mrem is not unexpected for some locations. The point is that spatial and temporal changes do exist in nature, though it is not obvious unless one is trying to measure such differences. Such variations are much greater than the total radiological effect from nuclear power plant i operation. 3.6-20

l l l l Cons ide ra tions in Minimizing One's Radiation Background Since there are variations in our natural radiation background, this leads one to a conclusion that if radiation is of concern to an individual, then an evaluation as to what could be done to minimize the radiation received from nature is in order. For example, the cosmic radiation contribution to an individual's background exposure can be minimized by living closer to sea level elevations. People living about a mile above sea level could reduce this cosmic radiation background by about 50 to 100 mrem / year by moving towards a sea level location. Whole body exposures can also be reduced by living in a home built of materials low in radioactivity content. For example, living in a wooden house instead of a concrete or stone one can result in a 50 mrem / year background reduction. Even buildings that we may work in are radioactive such that radiation exposure may be many times higher in some of the aesthetically designed granite and marble structures than other less radioactive buildings. No one is suggesting that people who work in buildings made of certain types of stone quit their jobs and seek employment where their background radiation levels would be minimized. If, however, one is concerned about the amount of natural radiation back-ground he receives, one of his main considerations should be his choice of habitat. Another example where one could minimize background exposure is by carefully selecting the types of food to be eaten, using those low in radioactivity content. This could reduce, not eliminate, the natural exposure by a few to about 10 mrem / year. One could also minimize his natural background by not flying i in airplanes since a transcontinental round-trip will result in about ] l l 4 mrem due to cosmic radiation. Reducing the number of cigarettes smoked a day from two packs to one cou13 lower the lung dose by several tens of mrem / year. Reducing the consumption of coffee and alcoholic beverages will also minimize an individual's exposure. Working on the I 2nd floor of a building instead of the 30th floor will also minimize 1 1 3.6-21 I i

background exposure. A long list of other examples could be made where f_s/\ each individual could minimize his exposure from natural radiation 9 background. Man-made radiation sources such as medical X-rays, television, luminous features on watches and appliances, and micro-wave ovens add to an individual's background exposure depending on the frequency of usage. The largest man-made radiation source is from medical exposure, as stated earlier. Certainly, if no diagnostic medical or dental X-rays are received, there would be no exposure. However, many of us have received much benefit from diagnostic X-rays to aid in medical treatment. Certainly, therapeutic X-ray treatments have also resulted in many lives being saved or prolonged even though massive doses of radiation have been received. Not receiving such X-ray treatments would minimize one's exposure but the risk to the patient could be quite detrimental. (D 's_,/ The radiation exposure from viewing television can be minimized by sitting farther away from the set or reducing the number of viewing hours per year. This could lower one's exposure by a few mrem / year. An additional few mrem / year reduction could be realized by wearing a wrist-watch ,ithout a luminous dial. Ta summarize the many choices that each person has in order to minimize his background radiation exposure, let us postulate two individuals. One lives near sea level, in a wooden house; does not receive medical X-ray examinations; does not smoke or drink alcoholic beverages; works on the first floor of a wooden building; and does not watch tele-vision. The second person lives in a stone house, in a mile-high city; receives his yearly chest X-ray and dental X-ray examinations; smokes cigarettes and drinks alcoholic beverages; works on the 20th floor of 4 3.6.22

a granite building; and watches television regularly. The difference in () the background radiation exposure between these two people could easily be several hundred mrem / year. They represent the range of possible exposures experienced by typical individuals. Most people would fall between these two extremes depending on the choices made, knowingly or unknowingly, to determine the background exposure received. With the numerous ways that man could reduce his background radiation, it would appear that if radiation were of concern to man l he would regulate his behavior to take advantage of the lowest possible level of natural radiation. Nowhere does he appear to have seen fit. r to regulate his behavior to chis extent. Thus, it could be concluded that this particular low level of na tural radiation has not been and is not currently a signi'_icant criterion to man when it is a matter of voluntary selection, even though these levels of exposure are several orders of magnitude greater than that received from the operation of the H. B. Robinson Steam Electric Plant. () Man-Rem From Nuclear Power Plants The radiological impact of nuclear power plants 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 plants. That is, everyone within a 50-mile radius is assumed to receive the average background exposure, whereas everyone does not receive the same dose contribution from the power plant. The reason is that the i natural atmospheric dispersion effects reduce the radiation concentration with increasing distance from the plant. Over the year, the wind directions, wind speeds and atmospheric stability change to disperse an airborne source so that out to 50 miles from the release location, the radio-logical effect is not measurable but only estimated by means of a calcu-lation. 3.6-23 ______ ___ _o

i 1 The total man-rem to the population out to 50 miles from the i plant for the various conditions evaluated in the nuclear environmental

effects determination are summarized in Sections 3.7 and 3.11. This list includes the man-rem results for normal plant operation considera- l tions, various abnormal conditions and postulated design basis accident f _a g conditions. One should not add the man-rem from each condition since .)e the probability of occurrence was not applied to all conditions. The 1 reason is that it is not correct to add man-rem / year with man-rem / event j 4 without first considering the frequency of occurrence (such as one- j millionth of an occurrence per year) . Radiolonical Impact ; The general conclusion that is drawn from the total population exposure for each condition is that there is a negligible contribution from the nuclear power plant when compared to the natural and other man-made exposures received by the population. The highest contribution to the population exposure from the plant is due to normal plant opera-tion. Even so, the highest dose to an individual near the plant 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 o f magni tude less). l As observed earlier, the many spatial and temporal changes in natural background and certain man-made sources more than mask out the contribution from normal operation of a nuclear power plant. l Transportation and abnormal occurrence considerations also -

                                                                                                                                                           -r result in a negligibic addition to the population exposure.                                                                          >

l t From a radiological viewpoint, the nuclear power plant is f indeed a good neighbor, one that has a negligibic impact on the environ- f ment. l l 0 ! 3.6-24 f i

  ...        - ---             --         .               .                   -        _      - _ _ _ _ _ _ _ _ _ _ _              _ _ _ _ _            :)

3.6.2 Environmental Studies O 3.6.2.1 Biological Studies Biological studies of Lake Robinson are to be conducted during a two-year period to assess the impact of Robinson Unit No. 2 on the aquatic environment. Primary emphasis of the study is to be on the lake fishery, including the primary producers. Nekton samples will be collected in an effort to indicate any shif t of populations in the lake as a result of the increased heat input from Unit No. 2. The fish will be examined t and classified according to species, age, and condition. The identification and assessment of phytoplankton will document the distribution of major groups throughout the lake and determine the dominant species in Lake Robinson. Samples of zooplankton will be collected, counted and identified. Biomass will be calculated and productivity will be estimated. Water chemistry to determine those constituents relevant to the biology of the lake or likely to be affected by the operation of the plant will supplement the biological parameters being investigated. O 3.6.2.2 Radiological Studies A pre-operational environmental monitoring program was conducted in the Robinson site environs to determine the magnitude and nature of radioactivity in the environment surrounding the site, to test the equip-ment, sampling and analytical procedures, the suitability of selected sampling points, and investigate the overall statistical variability of the system results. The information obtained is used as a baseline in evaluating any changes in environmental radioactivity levels that may result from plant operation. The pre-operational radiological monitoring program was conducted from December 1968 to September 1970 to determine background radiation levels and concentrations of radioactive materials in the aquatic and terrestrial environment surrounding the plant. The expected spatial distribution of plant effluents, meteorology conditions, lake diffusion, , 3.6-25

 -_a--m   --___s-__--,-                      - - , - - _ _ - _ _ - - , - - , - , - - - - .           --__------_-a.   - - - - - - , . , - - , - - - _ - _ _ - -                _m_ _ - - - - - _ - - -- - _ - - - - - _         -_----A

 .     -m  - .-       -        . _ _ _ . _ _ _ _ . .        ._      _        _ _ . . _ . . _ . _ _ _ . . ._

population distribution, and critical pathways were all considered in the selection of approximately 25 sampling and monitoring locations for the pre-operational monitoring program. The results of the pre-operational ' program were summarized in two reports: (1) " Pre-operational Environ-mental Monitoring at the H. B. Robinson Unit 2 Site - 1969 Annual Report" and (2) " Pre-operational Environmental Monitoring Report - January 1, 1970 - September 30, 1970". These reports have been transmitted to the AEC. The operational environmental radiological monitoring program was similar to the pre-operational program with only minor changes in locations, sampling frequency and analyses through March, 1971. Subse-quently, the program has been revised to place more emphasis on isotopic identification in the aquatic environment. The program shown in Table 3.6-5 represents the current monitoring program. Additional adjustments may be made in this program as necessary to place appropriate emphasis on specific radionuclides or groups of radionuclides and critical path- i vays for exposure to man after additional operational experience has been obtained. The only variance in the current program from that shown in Table 3.6-5 is in regard to benthic organisms. Several attemrats have been made to segregate benthic organisms from bottom sediments; however.due to the near absence of benthic organisms, there has never been a sample of suf ficient size for separate analysis, and the benthic organisms have been included in the analysis of the bottom sediments. By including the - benthic organisms with the bottom sediments, any buildup of radioactivity ' would be detected in the benthic organisms. ' In addition to the radiological monitoring program being con-ducted by Carolina Power & Light Company, an extensive monitoring program

is being conducted by the Eastern Environmental Radiation Laboratory of the Environmental Protection Agency in cooperation with the AEC Division of Compliance and the South Carolina Department of Radiological Health. O 3,6-26 i I i

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

Each participating organization is performing independent analyses of selected samples. The South Carolina Department of Radiological llealth is also conducting their own independent radiological monitoring program in the environs surrounding the plant. Environmental Monitoring Results A comparison of environmental monitoring dats for the last nine months prior to reactor startup (January 1, 1070 to September 30, 1970) and for the first six months of operation (October 1, 1970 to March 31, 1971) shows no significant dif ference in pre-operational and . operational levels. Since April 1, 1971, highly sensitive isotopic analyses of water, sediment, and fish have indicated trace amounts of 58 Co, and lesser amounts of other activation products, that can be 58 attributed to operation of the nuclear plant. Levels of co that have been measured in Lake Robinson water are more than four orders of mag-58 nitude below the (ftPC)w for Co. The principal radionuclides detected in Lake Robinson fish during the Spring of 1971 were K, Cs, and Co. The K naturally occurring and is the most abundant radio-nuclide. The Cs, from worldwide fall-out deposition as evidenced by the pre-operational environmental monitoring results, was the second most abundant radionuclide. The principal radionuclide present which l 58 i is attributable to operation of the nuclear plant is Co; however, ' a large portion of this activity was found in fish entrails with lesser amounts in the edible portion (less than 1 pCi/gm wet weight) . i O 3.6-27 j i

i SECTION

3.6 REFERENCES

I O Phillips, H. A., 1969. Fisheries Investigation in Lakes and Streams. South Carolina Wildlife Resources Department Annual Progress Report. Jensen, L. D., Davies, R. M., Brooks, A. S., and Meyers, C. D., 1969. The Ef fects of Elevated Temperature Upon Aquatic Invertebrates. Cooling Water Studies for Edison Electric Institute. Report No. 4, Research Project RP-49. The Johns Hopkins University. Copeland, B. J., 1970. North Carolina State University. Personal Communication. Trembley, F. J., 1960. Research Project on Ef fects of Condenser Dis-charge Water on Aquatic Life. The Institute of Research, Lehigh University, Progress Report. Patrick, R., Hohn, M. H., and Wallace, J. H., 1954. A New Method for Determining the Pattern of the Diatom Flora. Not. Nat. Acad. Nat. Sci., Phila. 259:12. Patrick, R., 1968. Some Effects of Temperature on Freshwater Algae. In Biological Aspects of Thermal Pollution, Edited by Krenkel & Parker 1969, pp. 161-185. Wood, M. J., 1963. Bradwell Biological Investigations: Nanoplankton. Central Electricity Research Laboratory Memorandum RD/L/M 27. Mihursky, J. A., 1969. Patuxent Thermal Studies N.R.I. Special Report No. 1. Chesapeake Biological Laboratory, University of Maryland.

Carter, H. H., 1968. The Distribution of Excess Temperature From a Heated Discharge in an Estuary. Chesapeake Bay Institute Technical Report 44, Ref 68-14, the Johns Hopkins University. Morgan, R. P. II and Stross, R. G., 1969. Destruction of Phytoplankton in the Cooling Water Supply of a Steam Electric Station. Chesapeake Science 10:165-171. Jensen, L. D., 1970. Cooling Water Studies for Edison Electric Institute Johns Hopkins University Research Project RP-49. Trembley, F. J., 1965. Effects of Cooling Water from Steam Electric Power Plants on Stream Biota. In Biological Problems in Water Pollution, pp. 334-335. U.S. Department of Health, Education & Welfare, 999WP-25. Heinic, D. R., 1969. Temperature and Zooplankton. Chesapeake Science,- 10:186-209. i Whitehouse, J. W., 1965. Zooplankton of the Blackwater. Central Elec-tricity Research Laboratory Note No. RD/L/N 131/65. Cairns,. J. Jr., 1969. The Response of Fresh-Water Protozoan Com unities to Heated Waste Waters. Chesapeake Science, 10:177-185. Cory, R. L., and Nauman, J. W., 1969. Epifauna and Thermal Additions in the Upper Patuxent River Estuary. Chesapeake Science, 10:210-217. O 3.6-28

SECTION

3.6 REFERENCES

(CONTINUED) O Cory, R. L., and Nauman, J. W., 1969. Thermal Additions and Epif aunal Organisms at Chalk Point, Maryland, Chesapeake Science, 10:218-226. ; Adams, J. R., 1969. Ecological Investigations Around Some Thermal Power Stations in California Tidal Waters. Chesapeake Science, 10:145-154. Flemer, D. A., 1970. Primary Production in the Chesapeake Bay. Chesa-peake Science, 11:117-129. Wurtz, C. B., and Renn, C. E., 1965. Water Temperatures and Aquatic Life. Cooling Water Studies for Edison Electric Institute. Research Project No. 49. The Johns Hopkins University. Cairns, J. Jr., 1955. The Effects of increased Temperatures Upon Aquatic Organisms. Proc. of the 10th Ind. W. Conf. , Purdue, pp. 346-354. Trembley, F. J., 1961. Recreational Uses of Reservoirs. Power Supplies and Water Resources Symposium, Reprint by Engineering. Bailey, R. M., 1955. Di f ferential Mortality from High Temperatures in a Mixed Population of Fishes in Southern Michigan. Ecology, 36:526-528. U. S. Department of the Interior, 1968. Industrial Waste Guide on Thermal Pollution. O l l il C:) 3.6-29 ; i j

gg TABLE 3.6-1 O PROVISIONAL MAXIML'M TE'tPERATURES 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, 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 develop-ment of perch and small:nouth bass. 55 F: Spawning and egg development of salmon and trout (other than lake trout). 1 i 48 F: Spawning and egg development of lake trout, walleye northern i pike, sauger, and Atlantic salmon. l

  *From Industrial Waste Guide on Thermal Pollution published by U. S. Depart-ment of Interior, 1968.

1 j j l () 3.6-30

f TABLE 3. 6-2 l 5 TOLERANCE LIMITS FOR CERTAIN FISilES O Values are LD50 temperature tolerance limits, i.e., water temperatures survived by 50 percent of the test animals. Counts were made by observing or estimating the , number killed during exposure, or within a reasonable time thereafter in which it l could be safely assumed that all deaths were attributabic to the temperature effects. { I (Thi s Table Taken in Part From Anon. , 1962) Acc11 mated to Lower Limit Upper limit , i Fish C (OF) C ( F) Hr C (OF) Hr , Bass, largemouth 20.0 C (68.0 F) 5.0 C (41.0 F) 24 32.0 C (89.6 F) 72 (Micropterus salmoides 30.0 C (86.0 F) 11.0 C (51.8 F) 24 24.0 C (93.2 F) 72. floridanus) Bluegill (Lepomis 10.0 C (50.0 F) 29.0 C (82.4 F) 24 l macrochirus macrochirus) 30.0 C (86.0 F) 36.0 C (96.9 F) 24 i I Bluegill (L. macrochirus 15.0 C (59.0 F) 3.0 C (37.4 F) 24 31.0 C (87.8 F) 60 l I purpurescens) 30.0 C (86.0 F) 11.0 C (51.8 F) 24 34.0 C (93.2 F) 60 I i Bullhead (Ameiurus n. 20.0 C (68.0 F) 1.0 C (33.8 F) 24 32.0 C (89.6 F) 96 f nebulosus, A. n. 30.0 C (86.0 F) 7.0 C (44.60F) 24 35.0 C (95.0 F) 96 na rmo rat us ) f O Catfish, channel 15.0 C (59.0 F) 0.0 C (32.0 F) 24 30.0 C (86.0 F) 24 ! (Ictalurus lac us t ri s 25.0 C (77.0 F) 6.0 C (42.8 F) 24 34.0 C (93.2 F) 24 l Jacustris, I.1 punctatus) !

l Chub, creek (Semotilus 5.0 C (41. 0"F ) 25.0 C (77.0 F) 96 l

a. atromaculatus) 25.0 C (77.0 F) 32.0 C (89.6 F) 96 Dace, blacknose (Rhinich- 5.0 C (41.0 F) 30.0 C (80.6 F) 340 thys a. atratulus, R.a. 25.0 C (77.0 F) 5.0 C (41.0 F) 24 29.0 C (84.'2 F) 340 meleanris)

Goldfish (Carassius 2.0 C (35.6 F) 28.0 C (82.4 F) 14 auratus) 17.0 C (62.6 F) 0.0 C (32.0 F) 14 34.0 C (93.2 F) 14 24.0 C (7.5.2 F) 5.0 C (41. 0 F) 14 36.0 C (96.8 F) 14 Greenfish (Gire11a 37.0 C (98.6 F) 15.0 C (59.0 F) 14 42.0 C (107.6 F) 14 j nigricans) 12.0 C (53.6 F) 5.0 C (41.0 F) 120 30.0 C (86.0 F) 120 ! 18.0 C (64.4 F) 13.0 C (55.4 F) 72 31.0 C (87.8 F) 120 ! Killifish (Fundulus 14.0 C (57.2 F) 1.0 C (33.8 F) 48 32.0 C (89.6 F) heteroclitus) 20.0 C (68.0 F) 2.0 C (35.6 F) 48 34.0 C (93.2 F) Minnov, fathead 20.0 C (68.0 F) 2.0 C (35.6 F) 24 32.0 C (89.6 F) 133 j (Pimephales promelas) 30.0 C (96.0 F) 11.0 C (51.8 F) 24 33.0 C (91.4 F) 133 Minnow, blunt-nose 15.0 G g (59.0 gF) 1.0g G (33.8 gF) 24 31.0 C (87.8 F) g 133 (llyborhynchus notatus) 25.0 C ' (77.0 F) 8.0 C (46.4 F) 24 33.0 C (91.4 F) 133 3.6-31 i

_ ~ , _ - _ . . _ TABLE 3.6-2 (Continued) Acclimated to Lower Limit Upper Limit d Pish OC ( F) C ( F) Hr C ( F) H r _ _ __ Mosquito fish 15.0"C (59.0 F) 2.0 C (35.6 F) 24 35.0 C (95.0 F) 66 (Grambusia affinis 35.0"C (95.0 F) 15.0 C (59.0 F) 24 37.0 C (98.6 F). 66 affinis, C.a. holbroki) Pe rch ( Perca flavescens) 5.0 C (41.0 F) 21.0 C (69.8 F) 96 Winter 25.0 C (77.0 F) 4.0 C (39.2 F) 24 30.0 C (86.0 F) 96 Summer 25.0 C (77.0 F) 9.0 C (48. 2 F) 24 32.0 C (89.6 F) 96 Shad, gizzard 25.0 C (77.0 F) 11.0 C (51.8 F) 24 34.0 C (93.2 F) 48 (Dorosoma cepedianum) 35.0 C (95.0 F) 20.0 C (68.0 F) 24 37.0 C (98.6 F) 48' Shiner, common 5.0 C (41.0 F) 27.0 C (80.6 F) 133 (Notropis cornutus 25.0 C (77.0 F) 4.0 C (39.2 F) 24 31.0 C (87.8 F) 133 - frontalis) 30.0 C (86.0 F) 8.0 C (46.4 F) 24 31.0 C (87.8 F) 133 Shiner, common 25.0 C (77.0 F) 32.0 C (89.6 F) 133 (Notropic cornutus 30.0 C (86.0 F) 34.0 C (93.2 F) 133 - chrysocephalus) Shiner, lake 5.0 C (41.0 F) 23.0 C (73.4 F) 133 (N. atherinoides) 15.0 C (59.0 F) 2.0 C (35.6 F) 24 29.0 C (84.2 F) 133 ' 25.0 C 8.0 C (46.40 F) 31.0 C (87.8 F) 133 (77.0 F) 24 shiner, golden 20.0 C (68.0 F) 8.0 C (46.4 F) 24 32.0 C (89.6 F) 66 (Notemigonus c. 30.0 C (86.0 F) 11.0 C (51.8 F) 24 35.0 C (95.0 F) 66 crysoleucas, N.c. auratus) Sucker, common 15.0 C (59.0 F) < (Catostomus commersoni) 25.0 C (77.0 F) 5.0 C (41.0 F) 24 29.0 C (84.2 F) 133 Sunfish 10.0 C (50.0 F) 28.0 C (82.4 F) 24 (Lepomis gibbosus) 30.0 C (86.0 F) 24.0 C (75.2 F) 24 , t Trout, brook 3.0 C (37.4 F) 23.0 C (73.4 F) 133 (Salvelinus fontinalis) 20.0 C (68.0 F) 25.0 C (77.0 F) 133 ' 25.0 C (77.0 F) 25.0 C (77.0 F) 133 1 Q 3.6-32 L-_------,---___---__----__------,a- _ - - - --:- , Ps- *ww -e~--we-*- *- '

TABLE 6-3 MAXIMLH TIIERMAL TOLERANCE (LD-50) FOR SEVERAL SPECIES OF FISil (Trembley, 1960) No. of Exposure Time Temperature OF r Fish Acclimation Duration at Each Temp. LD LD Fish Species in Test Temp. -F of Test Increment 50 100 Largemouth 10 80 18 hours 2 hours 100-102 103 l Bass (Micropterus salmoides) 22 81 15 hours 1 hour 98-99 100

                        "                                                                                      95                                                100 16              77               21 hours    1 hour Smallmouth                              20              55               10 hours     1 hour       85-90 Bass (Micropterus dolonieui) s Bluegills                               10              79               18 hours    2 hours       103 (Lepomis macrochirus)                  22              81               15 hours    1 hour       *Above 99
                        "                          12              77               21 hours     1 hour      101-102                                                  ,

w 12 73 8 hours 1 hour 99-100 100 ' T Brown 10 73 8 hours 1 hour 99 102-103

         $ Bullhead (Ictalurus nebulosus)

Redbelly 6 81 15 hours 1 hour *Above 99 Sunfish (Lepomis auritus) ! Rock Bass 6 81 15 hours 1 hour 95 98-99 (Amboloplites rupestris) Striped Bass 8 40 8 hours 1 hour 75 82 (Roccus saxatilis) White 16 40 8 hours -1 hour 82 83 Perch (Roccus americana) Walleye 10 81 8 days 1 day 99 100 (Stizostedion vitreum) 10 63 6 days 1 day 94 97

                         "                         10              70               24 hours     1 hour          90                                               92
           *None killed. Test stopped due to pump trouble.

4 TABLE 3.6-4 O Ti[E FINAL TEMPERATURE PREFERENDA FOR VARIOUS SPECIES 0F FISil AS DETERMINED BY LABORATORY EXPERIMENTS Young -of the Year or Yearling Fish Were Used, Except as Noted. (This Table Taken in Part From Ferguson, 1958) Final _ Species Preferendum Authority Bluegill 32.3 C Fry & Pearson (Lepomis macrochirus) (90.1 F)' (MS, 1952) Bass, Largemouth 30.0-32.0C Fry (Micropterus salmoides) (86-89.6 F) (MS, 1950) Carp 32.0 C Pitt, Garside & (Cyprinus carpio) (89.6 F) Hepburn (1956) Pumpkinseed 31.5 C Anderson ' (Lepomis gibbosus) (88.7 F) (MS, 1951) Goldfish 28.1 C Fry (Carassius auratus) (82.6 F) 1947 Bass, Smallmouth 28.0 C Fry (Micropterus dolomieu) (82.4 F) (MS, 1950) Crass Pickeral 26.6 C Berst & Lapworth (Esox vermiculatus) (78.8 F) (MS, 1950) Yellow Perch 24.2 C Ferguson (Perca flavescens) (75.6 F) (1958) Yellow Perch 21.0 C McCracken & Stark , (Perca flavescens) (69.8 F) (MS, 1948) ' r F O 3.6-34

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RA e e o o o o o d d d d na OL l l . .n l l l l l n n n n iB FP p c s sf l l l l l u u u u s0 m yrr c - a a a a a o o o o e4 5iC a chh G G G G G G P P P P r1 6 PXI R S 350 1 e e e e e e e e e e ed CT / . t n n n n n n n n n n gn 3 OC 1 1 3 a O O O O O O O O O O na OLEPL BE RE AC - E y y y y y y y h a cr xS e0 TN gc l l l l l l 9 ARA nn r r r r r r n, l i e y e y y y e y e e e e o9 lE l u l t l l l t l t t t t i8 I L pq k r k k k r k r r r r t EC me e a e e e a e a a a a a , VU ar e u e e e u e u u u u cs RN U SF W Q W W W Q W Q Q Q Q C n7 S o3 1 L r d , A e ml h h ml e4 T t e oa t e t oa t3 N n t rn r k r rn c1 E e r i y e f a o a o e e f a e n C o S a k C ne L ne g k C l r 21 o e t w a m k k r a m l o g c r ae a 0 R I nst i t p i lir'se l a ae ec l l i I t n eg rrl t a aL d o o tal a h c t n ae eg rrl of c V l ni voE nn p t al I s ef w ef s t al ei N n pi r st a S t sh a go t go il t sh a b s E o noc t i f l r n ncf d s d Da n ncf y i aP s r s o l t n a wst i d e id n a wst ol t S e ai en a l oiu r n r rn na l oiu sa p D HVW WE D P DDO B e P B e IC P DDO l n i r aa . c l er s lt e e ii t D g wsr n oa g i t ) ) ) ) ) ) ) ) ) ) ) ) epu n l n 22 3 1 5 8 1 2 1 4 5 8 l mq i pi 2 2 1 2 3 2 2 po l p mo ( ( ( ( ( ( ( ( ( ( ( ( mcr e aP a m S syp a s l S t 1 rs s e n ee e d c me 0t l e l p nr ue ar f e om t i 0 r p rm 2 am O p ot rt td ua y i a r a ua oe Aq s _ T AS GW SW BS

s '

w ' o 5" i

O O O TABLE 3.6-5 (Continued) Sampling Des c rip tion Sampling , Sampling Points Sampling Type Point Description Frequency Sample Size Analysis Remarks 9 I 7 Soil (25) West of Lake Semi-Annual One Pound Sr, Cs Stored for future analysis (26) East of Lake Semi-Annual One Pound Gamma Spectra Fish * ( 8) Near Discharge Quarterly Two pounds flesh ** (bass , bream Canal outfall each of bottom crapple, cat- feeders and free fish, carp) swimmers Air Radia- (22) liartsville Monthly Gamma TLD tion Dosi-meters (10) Picnic Area Monthly Gamma TLD l F l p (17,18, 4 on east shore Monthly Gamma TLD ! g 19,20) of Lake (1,3,4, 4 on south Pro- Monthly Gamma TLD

12) perty Line (13,15, 3 on west Pro- Monthly Gamma TLD

16) perty Line (11) Dam Site Monthly Gamma TLD

( 5) Microwave Tower Monthly Gamma TLD l l (14) Four Corner Area Monthly Gamma TLD l i (6,7) Unit 1 Monthly Gamma TLD (28,29, 4 south of Unit Monthly Gamma TLD , 30,31) 2 in prevailing . wind direction

Location will vary to obtain necessary specimens and representative samples.

           ** Isotopic analysis by radiochemistry and gamma spectrometry for 58,60 Co, 89,90Sr, 134,137Cs, and                              140 Ba-La.
 - - - .        ..     -.--           --      -       .-  -          -   . . -        . . - - - . ~     _ - . - . . - . . . . . . - -         -.- -- - _____ _ -

                                                  ._                                                                                                                          _ _                     _     m. _ . ._

O O O i

TABLE 3.6-5 (Continued) r Sampling . i Sampling Points Sampling Type Point Description Frequency Sample Size Analysis Remarks Benthic (8) Downstream from Semi-Annual

Gross Beta Organisms Discharge Canal 58 60 134

                                                                                                                                                                                                     ,              ,         s, Outfall

, 137Cs, 90 Sr t (21) Bridge at north Semi-Annual -* (Ditto above) end of lake F m - a W N I I t t ,

Benthic Organisms will be segregated from the bottom sediments collected at these sampling points and analyzed as indicated. t 9

b

 *W r = t , w w - rw y   .7- 1ewem o w vw-        ----wy -ew    -'eee +w-'*--ew-c    w *a t- e ,-~~-e***V--Im--rws--'e-ws~5=vw-**-=w+e-e=e--*e'-*+=*=*=en--+"e=*e***'--------

i 3.7 RADIOACTIVE DISC 11ARGES O The operation of the H. B. Robinson Unit No. 2 results in the production of radioactive materials that for the most part are contained , within the fuel elements in the reactor vessel. The radioactive materials ; i are produced as a direcc result of the fission process or are radioactive i materials in the reactor core resulting from nuclear reactions. Any radio- ' active materials which escape from the fuel or are' activated within the reactor are contained in the primary coolant which is a completely enclosed i system housed within the Containment Building. Small quantities of gaseous , and liquid radioactive materials are removed from the primary coolant under j

 ' controlled conditions during purification processes or during deboration.

Also, small quantities of radioactive materials may escape from the primary coolant due to leakage. The Chemical and Volume Control System and the Waste Processing System are designed to contain and process these radio- j active materials. 3.7.1 Radioactive Waste Processing System O 1he Radioactive Waste Processing System is designed to collect, j store, process and prepare for off-site shipment or disposal plant wastes l which contain or could contain radioactive material, both gases and liquids. The system design is such that radioactive effluents from the plant during normal operations are in accordance with revised and expanded regulations, 10 CFR 20 and 10 CFR 50, issued in the Federal Register Volume 35, No. 234, l t December 3, 1970, effective January 3, 1971, which require that radioactive i effluents be restricted to "as low as practicable". Since that time, a reuised Appendix I to 10 CFR 50 has been issued which gives numerical guidance in regard to the "as low as practicable" concept. The Waste l Processing System has been evaluated using this numerical guidance and the ; system meets the design objectives as set forth in Appendix I to 10 CFR 50 (maximum of f-sitn dose to a singic individual due to normal releases will l not exceed 10 mrce/ year, integrated liquid effluent activity will not exceed 5 curies per year while maintaining a discharge canal activity of l i 3.7-1 i

                           -.-        . ..       .    - . - . =         -       .     ..

l I i 1 i l 1 less than 0.2 pCi/1 due to these releases, and the maximum integrated i

 ) dose to an individual will not exceed 5 mrem due to these liquid releases).            j Accidental release of radioactivity will be safeguarded against so that the likelihood of occurrence is very remote, and if such releases did occur,              ,

i the radiological consequences would be within applicable AEC guidelines. [ Accidents and the environmental consequences of accidents are discussed in Section 3.11. I The Waste Processing System is divided into three sections: , f

1. Liquid Radioactive Waste Processing System

2. Gaseous Radioactive Waste Processing System

3. Solid Radioactive Waste Processing System l 3.7.1.1 Liquid Radioactive Waste Processing System !

I i The liquid radwaste system collects, stores, and processes for j reuse or disposal all normally and potentially radioactive aqueous liquid i (I wastes from the H. B. Robinson Unit No. 2. Radioactive liquids entering the Waste Processing System are collected in sumps and tanks until deter- f mination of subsequent treatment is made. During normal plant operation, the Waste Processing System processes liquids from equipment drains and , t leak-offs, radioactive chemical laboratory drains, radioactive laundry ! i and shower drains, decontamination area drains and demineralizer regenera- , tion. The system collects and transfers to the Chemical and Volume ( Control System liquids from the reactor coolant loop drains, pressurizer relief tank, reactor coolant pump secondary seals, excess letdown during , i startup, accumulators, and valve and reactor vessel flange leak-offs. These i liquids transferred to the Chemical and Volume Control System are processed [ and returned for reuse within the plant. } t Liquid wastes are collected in the waste hold-up tank, the ! laundry and hot shower tanks, and the chemical drain tank. At these { points the liquids are sampled to determine what processing is required. i ( ! 3.7-2 i i

t Wastes collected in the waste hold-up tank will normally be ; . processed through the waste concentrator. The condensate is collected i in one of two waste condensate tanks where it is sampled to determine further action. If activity Icvels are high, these liquids are returned to the waste hold-up tank for further processing. If, after sampling, these liquids are determined to meet the requirements of 10 CFR 20 and 10 CFR 50 they are discharged to the circulating water system where they ; i are diluted by the circulating water. - During the first year of operation, there have been numerous [ problems with the operation of the waste concentrator and its performance j has not met design standards. Although the concentrator has not met de- l sign performance, releases have been only a fraction of 10 CFR 20, Appendix 1 to 10 CFR 50, and Technical Specification limits. Modifications ! are now planned which, when completed, should bring the performance of the waste concentrator up to design standards. In addition to improve-f ments in the waste concentrator, CP&L has on site two domineralizers ; e which will be installed downstream from the waste concentrator. The ; condensate from the concentrator will then be routed through these demineralizers and will be of suitable quality for reuse within the plant. When these demineralizers are installed, these liquids will'be ! discharged to the environment only when water inventories within the plant demand it and only then if the radioactive content meets all ap-I plicable AEC regulations. . I Other improvements are being made in the Liquid Processing System to further minimize releases to the environment. Sources of excessive liquid input to the system are being identified and corrected. , For example, modifications are in progress which will collect charging ptunp leakage and return it to the Chemical and Volume Control System where it will be processed for reuse in the plant. This will exclude from the Waste Processing System one of the largest sources of liquid both in activity and volume. ; i O , 3.7-3 i f

Laundry and decontamination shower drains are collected in the laundry and hot shower tanks. These wastes are of low radioactive con-tent (normally 1 x 10 Ci/ml). Because of the tendency of these liquids to foul ion exchange resins and the other process equipment, they are normally discharged, after sampling for compliance with discharge standards, through the laundry drain filter to one of the condensate tanks. The liquid is then resampled for radioactive content and released to the discharge canal where it is diluted by circulating water if the radioactive content does not exceed applicable regulations. I f radioactive content does not permit the release of these liquids, they are transferred to the waste hold-up tank for processing through the waste concentrator. All radioactive liquid releases from the plant are pumped through a flow meter to obtain the actual volume released and through a radiation monitor which will terminate the discharge if unexpected radiation levels are detected. Although the sample analysis for radio-active content prior to release provides the basis for recording activity releases, the radiation monitor provides surveillance over the operation by closing the discharge valve should the liquid activity level exceed a preset value. As stated previously, although some portions of the liquid waste system have not operated up to design specifications, releases have been only a fraction of the Technical Specification and 10 CFR 20 limits and have been in compliance with the design objectives of Appendix I of 10 CFR 50. 3.7.1.2 Caseous Waste Processing System The Gascous Waste Processing System is designed to collect radioactive and potentially radioactive gases and to hold these gases for decay or for reuse within the plant. The system is designed to give a minimum of 45 days decay prior to release to the atmosphere which results in only the isotopes Kr-85 and Xe-133 being released to the envir,nment. O 3.7-4

l i A secondary function of the Waste Gas System is to supply. nitrogen and hydrogen to primary plant components. Most of the gas received by this sytem during normal operation is cover gas displaced from the Chemical and Volume Control System hold-up tanks as they fill I with liquid. Since this cover gas must be replaced when the tanks are. emptied during processing, facilities are provided to return gas from , the gas decay tanks to the hold-up tanks, thus eliminating the need' , i to discharge these gases to the atmosphere. ; b Gases collected in the system flow to one of two compressors, ! f and from there to one of four decay tanks. Normal operation of.these ! tanks is to have one tank for collecting gas, one tank isolated for l decay, one tank for reuse as cover gas, and the fourth tank empty as a standby. Normally, the last tank to be filled will be the first tank j to be reused for cover gas in order to permit the maximum decay time ! before releasing to the environment. From time to time, as gas inventories in the system demand, > a gas decay tank will be released to the environment. Before a tank is released to the environment, it is sampled and analyzed to determine i and record activity levels and then discharged to the plant vent at a controlled rate through a radiation monitor only if it meets prescribed : standards for release. The radiation monitor will close the gas discharge valve if activity levels exceed a preset limit. As with liquid releases, the radiation monitor is for surveillance of the releases and the sample ; analysis provides the permanent record. With no fuel failure there will be essentially no release of i radioactivity to the atmosphere. However, assuming continuous operation t with 1% fuel failure, the releases to the atmosphere will comply with i all regulations including the numerical guides of Appendix I to 10 CFR 50. I 3.7.1.3 Solid Radioactive Waste Processing System The Solid Waste Processing System is designed to package all solid wastes in DOT approved 55-gallon or 30-gallon drums for removal O , 3.7-5 f i i

 ----.             ,   c, - _ - - . - -      .- ,,                    ~ - . , - -              - -   -   - . + -

i 1 i from the site to a licensed burial facility. Concentrates from the waste () evaporator are pumped into a battery of six 55-gallon drums previously fil-led with a mixture of vermiculite and cement. After filling, the drums are moved to a shielded storage area and held until a sufficient number i are accumulated for shipment. Spent resins are packaged in a similar manner. After the resin j !- t i has been agitated in the resin storage tank, water is pumped through the l tank at a controlled rate to sluice the slurry to the drumming room, f i There the resin is received in a battery of six drums. The slurry enters l; the drum and is dewatered by the absorption of the liquid in a mixture of ( vermiculi te and cement. Again the drums are held in a shielded area for ! shipment. f! Dry solid wastes such as air filters, paper, rags, and other f rad ioac tively centaminated items are collected throughout the plant, ft Those items which are compressibir '*a compacted into DOT approved 55-gallon drums in a hydraulic press-baili) c inc. Noncompressible wastes are () packaged in 55-gallon drums or other DOT " specification" containers. 3.7.2 Radioactive Releases During normal operation of the H. B. Robinson Unit No. 2 nuclear plant, small amounts of radioactive materials are discharged into the environment on a controlled basis. Although the resulting doses from these radioactive discharges, even under the most severe operating conditions, are considered insignificant when compared to residence background doses, they are assumed to impose a theoretically calculable radiation dose to the local population. A discussion of the maximum expected releases as well as the actual releases experianced to date is included in the following sections along with the calculated resulting doses from these releases. O 3.7-6 i

3.7.2.1 Radioactive Liquid Releases , O l The maximum estimated quantity of radioactivity in liquid i i releases from the 11. B. Robinson Plant on an annual basis is shown in Table 3.7-1. These values were obtained using the following assumptions I i as a basis: ;

1. A decontamination factor of 10 for the Waste Processing _.

System (waste concentrator) was used. Previous calcula- l tions to estimate maximum releases in the FSAR assumed i 6 a decontamination factor of 10 for the waste concentra- , tor; however, operating experience to date has shown this to be unobtainable in the present system and a system decontamination factor of 10 is used as a more realistic i value. There will, however, be an improvement in the per- l t formance of this system when modifications to the concen- l tractor and installation of the demineralizers, as dis-cussed in Section 3.7.1.1, are completed.

2. The value for tritium was obtained by using leakage of ;

ternary fission tritium from the Zircaloy fuel of 1 percent. l Original calculations in the FSAR assumed a 30% leakage of tritium from the fuel based on experience with stain- ; less steel cladding. A detailed study performed by Westinghouse at the Robert E. Ginna Station and other operating stations using Zircaloy clad fuel has shown j the leakage of fission tritium from the fuel to be less { than 1 percent. Semi-quantitative measurements at the H. B. i I Robinson Plant indicate the 1 percent leakage to be justified.

3. The values shown in Table 3.7-1 were based on continuous operation with 1 percent failed fuel. ;

4 i The total estimated annual releases shown in Table 3.7-1 l represent a maximum release rate as shown by the very conservative O 3.7-7

assumptions used and it is expected that these levels would never be reached in actua1' operation. Although these releases represent a maximum, they are used to calculate the radiological effects on the environment. Also shown in Table 3.7-1 is the equilibrium concentrations in Lake Robinson and the resulting fraction of the FTC for that isotope. -r Because the cooling water discharge flow is greater than the flow through f the lake, the dilution capability of Lake Robinson, rather than the cir- ' culating water flow, is used to determine the fraction of MPC. The equa- t tion used to obtain the equilibrium concentrations in the Lake is: A C = I

V (A + v1) - where: C = equilibrium concentration in the lake (4Ci/ml) A = annual release rate to the lake (PCi/ year) , V = volume of the lake (3.8 x 1013 ml) I Q = flow of water out of the lake (2.24 x 1014 ml/ year) R = decay constant (year-1) { Based on the equilibrium concentrations in the lake and MFC f values from Table II, Appendix B, 10 CFR 20, continuous release at the , levels shown in Table 3.7-1 would result in a total release of about l 0.3 percent of FTC limits for an identified mixture and would meet all the design objectives of 10 CFR 50, Appendix I. It should further be noted that actual releases are expected to be a small portion of those shown in . Table 3.7-1 as evidenced by actual releases experienced during the first year of operation. The actual releases of radioactive materials to the lake during the period September 1970 through August 1971 are shown in Table 3.7-2. A total of 0.583 curies of activation products and 38.274 i curies of tritium were discharged to the lake during this period resulting in a concentration in the lake of only 0.013 percent of the MPC for an j identified mixture. I l 1 Although releases of radionuclides from the H. B. Robinson Plant I are small, it is important to know the ultimate radiological consequences to , man. Of the possible pathways to man for isotopes in liquid waste, only the ) internal exposure from the water-fish-man pathway is considered significant. 3.7-8 i

i There is no amount of drinking water taken from Lake Robinson () or from Black Creek downstream from the lake. Approximately five miles downstream from Lake Robinson is Prestwood Lake. This impoundment was made exclusively for the industrial use of Sonoco Products Company, although recreational uses such as boating, swimming, and fishing are ! permitted. Radioactivity from the lake would not be expected to enter the g.ound water supply and, subsequently, local wells. Normally, ground water movement is toward a creek such as Black Creek resulting in a groand water discharge in the area. The artesian conditions in the Lake Robinson area prior to construction of the lake tend to verify this fact. If, howeve r, for some unknown reason, radioactivity did get into the ground water aquifer, it would show up in wells at the plant site before reaching other wells in the area. Wells at the plant site are I routinely monitored for radioactivity as part of the environmental monitor- 1 ing program. Based on the preceding information, drinking water is not i considered to be a significant pathway. O Although swimming and boating are permitted on Lake Robinson, direct external exposure from these activities is expected to have a negligible effect on people using the lake. Some magnitude of this path-way of exposure can be made by calculating the dose to a water skier from the surface exposure due to cesium-137, the anticipated predominant isotope I with a strong gamma emission (Table 3.7-1). The lake surface dose rate - is calculated as follows:

                                 ~9 rem = 2.1 x 10                  u Ci x 3.7 x 10' dps x 3.16 x 10                       sec    x 1 ml x 0.662 Mev year                               ml                          Ci                    year         gm           dis.

6 -5 x 0.82 x 1.6 x 10 etc x 0.5 x _17 gm-rad x 1 rem = 1.06 x 10 Mev 10 erg rad where 0.5 = 2 n geometry factor 0.82 = fraction of gammas actually emitted by Cs-137 which escape the atom O 3.7-9 , 1 l

If we assume an individual skis for 2 hours a day, fif ty days per year, his actual dose from this source would be 1.21 x 10~7 rem / year. lThis additional annual exposure is considered to be insignificant. There is no commercial fishing in Lake Robinson; however, sport fishing is permitted in the lake. Predominant fish in the lake are shown in Tabic 3.7-3. Although the information in this table was obtained at one time, samples were taken from several locations in the lake and the i data is expected to be representative of the fish population. Fish living in water that contains very low concentrations of radionuclides may concentrate some of these radionuclides through the microorganism - small invertebrate - fish food chain. The collective effect of these concentration mechanisms may be estimated from stable element concentrations in water and fish. An extensive review of stable element data availabic in the literature has been made(l) Concentra- . tion factors, Cf, for fish in Lake Robinson are based on data provided by this review. Where concentration factors are unknown, the suggested conservative concentration factor of 10 5, as stated in the report,.is used. Specifically, this pertains to tellurium. The projected maximum equilibrium concentrations in fish are-listed in Table 3.7-4 for key radionuclides that may be released in liquid effluents. Average per capita consumption of fish in the Middle Atlantic Region is 14.3 pounds / year ( ) but more than 1/3 of this is canned or frozen fish from cornnercial sources. Consumption of fish from Lake Robinson by even the most avid sport fisherman is not likely to. exceed the 50 grams / day which has been estimated for a commercial fisher-man ( } . An intake of 50 grams / day of fish and 2200 milliliters / day of water (4) has been assumed to estimate internal exposure via the aquatic path-way. Whole body doses are based on the limits for water released to unre-stricted areas. These limits were obtained from Reference 4 by dividing the O 3.7-10

 - - - -                      J   .u 4         m          w -.               ._r.

recommended 168 hour levels by 10 so as to obtain 168 hour maximum con-centration levels allowed for an average annual whole body dose of 0.5 rem. The following equation was used to obtain the resulting whole body , doses- ! Whole body dose (mrem / year) = 50 Cw x Cf x 500 x 2200 MPCw-wb Where: 50 = grams of fish consumed daily ( } ml of water consumed daily ) 2200 = Cw = calculated equilibrium concentration in the lake in C1/ml (Table 3.7-1) Cf = isotopic concentration f actor from water to fish (1) MPCw-wb = maximum permissible concentration in water to deliver 50 mrem / year whole body dose (5) 500 = maximum permissible mrem / year whole body dose (5) The total whole body dose as shown in Table 3.7-4 is 3.03 mrem / year. It should be noted that 0.59 mrem / year of this total is based V on a Cf of 1 x 10 5for Te-132, which is probably high by at least a factor of 100. In addition 0.79 mrem / year of the total is based on tritium. Unless the fish is consumed raw, the water content of the fish (and with it the tritium) will be greatly reduced by the cooking process. Also the primary contributors are all fission products (cesium, tellurium), which pre-supposes the 1 percent failed fuel. In the expected event that fuel failure is less than the 1 percent, then the whole body dose will be correspondingly less as evidenced by calculating doses a person might receive as the result of releases during the first year of operation. As shown in Table 3.7-5, this calculation shows a resulting dose of 0.065 mrem / year due to the con-sumption of 50 grams / day of fish from Lake Robinson. Since there is no commercial fishing from Lake Robinson and sport fishing is primarily by individuals in the local area, there will- be essentially no increase in the total population dose within the 50-mile radius. O 3.7-11

3.7.2.2 Gaseous Effluents O The estimated maximum quantity of gaseous radioactivity released from the H. B. Robinson Plant on an annual basis is shown in Table 3.7-6. These values are based on the assumptions of (1) continuous operation at 2300 MWt with cladding defects in fuel rods generating one percent of the rated core thermal power, and (2) a minimum of 45 days hold-up time in the gas decay tanks. The continuous operation for one year with one percent fuel defects is considered unrealistic and is presented for conservative calculation purposes. The estimated maximum expected quantity of gaseous radioactivity released from the H. B. Robinson Plant on an annual basis is also shown in Tabic 3.7-6. These values are based on the more realistic assumptions of (1) continuous operation at 2300 MWt with cladding defects in fuel rods generating 0.2 percent of the rated core thermal power, and (2) a minimum of 45 days hold-up time in the gas decar tanks. These assumptions are considered to be conservative and would be the maximum that could ever be expected on an annual basis. The conservatism of these assumptions can be illustrated by the fact that the annual release of 1476 curies per year estimated on this basis is significantly higher than estimates extra-polated from experience to date in operating pressurized water reactors and far exceeds the 0.022 curies released from the H. B. Robinson Plant during I the period September 1970-August 1971, as shown in Table 3.7-7. Radiation doses from these gaseous effluents as a function of distance and direction were calculated for each of the release modes shown above. A summary of resulting population doses is shown in Table 3.7-8. These doses were calculated using the annual average atmospheric dispersion for the site. The 1986 population projections as shown in Figures 2.1-5 and 2.1-6 were used to obtain the population distribution. Doses were calculated using the ICRP " infinite semispherical cloud" model(4) O 3.7-12

l The average annual radiation dose, in rems, was calculated for each sector of the individual population rings using the annual average meteorological conditions for that sector and distance from the plant. The population dose in each sector, in man-rem / year, was calculated by l multiplying the average dose for that sector by the projected population in that sector for the year 1986. The total population dose in each ring was obtained by summing the population doses within the 16 individual sectors within that ring. The total population dose is the sum of the doses in each of the rings out to 50 miles. The average per capita dose was calculated by dividing the total population dose by the total projected population within the 50-mile radius. Also included, for comparison purposes, in Table 3.7-8 are the-population doses estimated to result from residence background radiation-in the absence of the plant. Sources of background radiation are discussed in Section 3.6.1.2. It can be concluded from this data that the popula-tion dose due to. gaseous effluents will, under the most severe operating conditions, be only a small fraction of the background and that the plant can be operated safely within the limits of 10 CFR 20 and the design objectives of Appendix I,10 CFR 50. Although the only significant mode of general public exposure from effluents from the Robinson Plant is from direct external radiation , from the elevated plume of noble gases as described above, other modes of [t exposure were evaluated and judged to be by comparison of little or no i significance. Radiciodine and particulate effluents from the plant will be controlled within the design objectives contained in Appendix I, 10 CFR 50 and within the technical specifications from the plant. Since there are no commercially grown and locally marketed food crops in the local area, and since the nearest dairy herd is at least seven miles from the site, the resulting population dose from discharge of iodines and par-ticulates is expected to approach zero. O 3.7-13 a_ - - _ - _ . _ _ , . ,_. _ _ .. -_ -.

3.7.3 Maximum Exposed Individual O The maximum exposed individual is considered to be a person standing at the nearest site boundary 356 days per year and consuming 50 grams / day of fish from Lake Robinson. This also assumed that maxi- I mum discharges to Lake Robinson have continued for a sufficient length 1 of time to reach equilibrium concentrations in the lake and an additional length of time for fish to concentrate these nuclides (since C8-137 is the critical nuclide, this period of time would be several years). If gaseous releases continued for one year at the design release rates, the exposure to an individual at the site boundary would be 7.85 mrem / year. Adding to this the 3,03 mrem / year due to fish consumption would result in an annual exposure of 10.88 mrem. However, using the maximum expected annual release of 1476 curies of gaseous activity, the same i person's annual dose would be 1.56 mrem from this source and an additional 3.03 mrem from fish consumption for a total of 4.59 mrum/ year. This dose is considered to represent a maximum dose to an individual and would in practice never be achieved. Calculated dose to this individual resulting () from releases through August 1971 is only a small fraction of this 4.59 mrem as shown in Tables 3.7-5 and 3.7-8. 3.7.4 Population Dose As shown in Table 3.7-7, the total dose to the population with-in a 50-mile radius of the plant is 26,25 man-rem / year from gaseous releases assuming a maximum design basis annual release and 5.25 man-rem / year assuming a maximum expected annual release. It should be noted that the computed man-rem dose did not take credit for the shielding provided by occupying of homes, offices, cars, etc. which would in fact, reduce the man-rem doses by about a factor of 2. There is essentially no increase in the population dose due to fish consumption by a few local sport fishermen. O 3.7-14

As shown in Table 3.7-8 and discussed in Section 3.6.1.2, this 'O qj came population receives 156,762 man-rem / year exposure from natural and other man-made radiation. Even considering the unrealistic assumption of gaseous releases at the maximum design value, the total population dose due to plant operations is only 0.02 percent of that estimated to be received from natural background and other man-made sources of radiation in the absence of the plant. In actual practice the dose to the popu-lation would be expected to be much less than that shown. It can be concluded that the additional exposure received by the population from plant operations is of only very minor significance when compared to that received from background sources. 1 0 3.7-15

SECTION

3.7 REFERENCES

O 1 Chapman, W. H. , H. L. Fisher, and M. W. Pratt, " Concentration Factors of Chemical Elements in Edible Aquatic Organisms" Lawrence Radiation Laboratory, University of California, Livermore, California, Report No. UCRL 50564, December 1968. ; 2 Nash, Darrel A., "A Survey of Fish Purchases by Socio-Economic Charac-teristics" Annual Report, February 1969 - January 1970, Bureau of Commercial Fisheries, Working Paper No. 50.

3. Cowser, K. E. and W. S. Snyder " Safety Analysis of Radioactive "sicase to the Clinch River" ORNL 3721, Supplement 3,1966. '

4. ICRP Publication 2: " Report of Committee II on Permissible Doce for Internal Radiation, 1959". International Commission of Radiological Precection. Pergamon Press New York, 1959.

5. U. S. Atomic Energy Commission, Title 10 - Atomic Entrgy, Part 20 -

Jtandards for Protection Against Radiation, Appendix B, Table II, Column 2, Revised December 10, 1969. - O i O 3.7-16 J

TABLE 3.7-1 ESTIMATED MAXIMLH ANNUAL LIQUID ISOTOPIC RELEASES

H. B. ROBINSON UNIT NO. 2 O Equilibrium Concentration Annual Release T MPCv Decay Constant in Lake Fraction **

Isotope u Ci/ year uCi/ml Year ~1 uCi/ml of MPCw 1 -3 0 ~' 2.1x10

                                                                                              -11 Cr-51          2.40x10       27.8d     2x10            9.1x10        4.22x10 2                                     -1                             -9 Mn-54          1.08x10       303d      1x10~           8.4x10        4.2x10~         4.2x10 3                                       3              -14           -10 Mn-56          2.94x10       2.6h      1x10~           2.35x10       3.27x10         3.3x10 3                    -5                 0            -12 Co-58          3.29x10       71.3d     9x10            3.56x10       9.1x10          1.0x10~
                                              -5                 0            -13 Fe-59          1.27x10       45.6d     5x10            5.54x10       2.9x10          5.8x10~

2 -5 -1 -2 -8 Co-60 3.88x10 5.26y 3x10 1.33x10 1.7x10 5.7x10

                                              -6                 0              -13 Sr-89          1.33x10       52.7d     3< 10           5.03x10       3.22x10         1.1x10~

1 -2 -13 Sr-90 4.02x10 27.7y 3x10~ 2.5x10 1.78x10 6.9x10~ 1 -5 1 -14 -0 Y-90 4.62x10 64h 2x10 9.42x10 1.22x10 6.1x10

                                              -5                                -14           -10 Sr-91          3.43x10       9.67h     5x10            6.28x10       1.42x10          2.8x10 3                    -5 Y-91           2.36x10       58.8d     3x10            4.34x10       6.1x10~          2.0x10~

1 3 -16 -11 Y-92 5.43x10 3.58h 6x10~ 1.73x10 8.2x10 1.4x10

                                              -5                 0              -13    4.6x10
                                                                                              ~9     j Zr-95          1.02x10       65.5d     6x10            3.76x10       2.77x10
                                              ~0                 0              -13    2.0x10
                                                                                              ~9 Nb-95          1.01x10       35d       1x10            7.23x10       2.03x10 1                   -5                              -15             -10 Zr-97          6.60x10       17h       2x10            3.58x10       4.7x10           2.4x10 5                   -5                 1              -10           -6     j Mo-99          9.79x10       66.7h     4x10            9.05x10       2.67x10          6.7x10 1                   -4                  3           -16              -12 Ru-105         1.00x10       4.44h     h10             1.37x10       1.9x10           1.9x10 5                                      1               -10 1.8x10
                                                                                               -3 1-131         7.87x10       8.05d     3x10~           3.14x10        5.55x10
                                              -5                               -11             -6    l Te-132         8.28x10'      77.7h     2x10            7.77x10        2.6x10          1.3x10
                                               -6                 3              -13           -8 I-132         2.43x10       2.26h     8xiG            2.64x10        2.42x10         3.0x10 5                    -6                 2            -11             -5 I-133         9.94x10       20.3h      1x10            3.03x10       8.5x10          8.5x10
                                               -5                 3 I-134          3. 76x10      52m       2x10           6.86x10        1.44x10~        7.2x10~

5 -6 2 -12 -6 I-135 2.90x10 6.68h 4x10 9.05x10 8.2x10 2.1x10 0 -6 ~1 -10 -5 Cs-134 8. 65 x10 2.05y 9x10 3.01x10 3.67x10 4.1x10

                                               -5                 1 Cs-136         1.25x10       13.7d     6x10            1.95x10       1.3x10~         2.2x10~

5 -5 -2 ~9 -4 Cs-137 4.70x10 30.0y 2x10 2.3x10 2.1x10 1.0x10 1 -13 -8 Ba-140 3.17x10 12.8d 2x10 1.97x10 3.25x10 1.6x10

                                               -5                 2            -14      1.9x10
                                                                                               ~9 La-140         2.91x10       40.2h     2x10            1.51x10       3.7x10 3                                      -1           -12             -8 Ce-144         1.13x10       284d      1x10            8.90x10       4.7x10           4.7x10 6                                                                     -3 Total          3.74x10                                                                2.04x10
                                               -3               2                 -6    1.06x10
                                                                                                 -3 H-3            8.49x10       12.26y 3x10               5.6x10        3.17x10

Based on continuous operation with cladding defects in fuel rods generating one percent of the rated core thermal power.

 ** Based on equilibrium concentrations in the lake and MPC's from Table II, Appendix B, 10CFR20.

3.7-17

TABIE 3.7-2 O RADIOACTIVE REIEASES IN LIQUIDS FROM H. B. ROBINSON UNIT 2 (SEPT. 1970 - AUG. 1971) Total Release Concentration *** MPC ** f Isotope

mci in Lake (uCi/ml)

                                                               -11 C r- 31                  13.2                  2.3 x 10         1.15 x 10 -8
                                                               -10 he-54                    63.5                  2.5 x 10         2.5 x 10 ~0
                                                               -12 Fe- 5 9                    2.6                 7.2 x 10         1.44 x 10 ~7 Co-58                 450.0                    1.25 x 10~       1.4 x 10
                                                                                 -5
                                                                -10 Co-60                    29.0                  1.27 x 10       '4.2 x 10 -6 1-131                    23.0                  1. 6 x 10 -11    5.3 x 10
                                                                                 -5 !

Cs-137 1.9 8.4 x 10 -12 4.2 x 10

                                                                                 ~7 Total                 583.2                                     7.43 x 10 -5 H-3                  38,274                    1.7 x 10~                   -5 5.7 x 10 l

O

The isotopic distribution of releases shown here is based on represen-tative isotopic identification of individual releases and on conposite identification of other releases and is representative of the actual distribution of the total annual reicase.

l

      ** Based on MPC 's from Table II, Appendix B, 10 CFR Part 20.       The MPC f J

is the fraction of the MPC in the lake and is obtained by dividing the concentration in the lake by the MPC for that isotope.

      *** Concentration in the lake is calculated as follows:

X= y , 1 - exp - K+ Where X = concentration in the lake ( Ci/ml) C = addition rate to the lake ( Ci/ year) V = volune of lake (ml) t R = flow rate from the lake (ml/ year) A = decay constant (ye a r- 1) t = time (years) f 3.7-18 l

O O O TABLE 3.7-3 LAKE ROBINSON FISH DISTRIBUTION ( Total No. Total Wt. % Total No. 7. Total Wt. Redfin pickerel Esox americanus 0.2 1 0.03 0.04 Chain pickerel Esox niger 42 15.2 1.2 3.4 Golden shiner Notemigonus crysoleucas 1,113 113.1 30.9 25.3 Lake chubsucker Erimyzon sucetta 134 52.5 3.7 11.8 Spotted sucker Minytrema melanops 65 128.1 1.8 28.7 White catfish Ictalurus catus 1 Trace 0.03 Trace Bullhead Ic talurus spp. 38 4.7 1.1 1.1 Madtom Noturus spp. 3 Trace 0.1 Trace Starhead topminnow Fundulus notti 30 Trace 0.8 Trace-G Pirate perch Aphredoderus sayanus 68 3.0 1.9 0.7 Mud sunfish Acantharchus pomotis 1 Trace 0.03 Trace Warmouth Chaenob ryttus gulosus 227 25.7 6.3 5.8 Blackbanded sunfish Enneacanthus chaetodon 55 2.4 1.5 0.5 Bluespotted sunfish Enneacanthus gloriosus 169 5.4 4.7 1.2 Redb reas t sunfish Lepomis auritus 99 14.8 2.7 3.3 Pumpkinseed Lepomis gibbosus 25 3.4 0.7 0.8 Bluegill Lepomis macrochirus 1,273 37.4 35.3 8.4 Largemouth bass Micropterus salmoides 222 33.3 6.2 7.5 Black crappie Pomoxis nigromaculatus 39 1.1 7.3 1.6 (1)" Fisheries Investigations in Lakes and Streams, District IV", Annual Progress Report for period of July 1,1968 ' through June 30, 1969, South Carolina Wildlife Resources Dept., 1969

TABLE 3.7-4 WHOLE BODY EXPOSURE FROM ESTIMATED MAXIMUM ANNUAL LIQUID ISOTOPIC RELEASES H. B. ROBINSON UNIT NO. 2 O C Cw Whole Body Dose = Annual Concentration Concentration MPCw 50 Cw x Cf x 500 l Release In Lake Factor Whole Body 2200

MPCw Isotope C1/y r . Ci/ml C f

C1/ml (m.em/yr.)

2 -10 Cr-51 2.4x10 4.22x10 2x10 2x10~ 47.96x10

                                                                                                           -4              ~9 Mn-54                                        1.08x10         4.20x10~               2.5x10        8x10         14.91x10
                                                                        -14                   1                            -11 Mn-56                                        2.94x10         3.27x10                2.5x10        3x10~        30.97x10              l
                                                                        -12                 2 4x10 '
                                                                                                           ~
                                                                                                                           -5           !

Co-58 3.29x10 9.10x10 5x10 12.93x10 2 -13 2 -4 49.44x10

Fe-59 1.27x10 2.90x10 3x10 2x10

                                                                        -1                  2              -4              -6           l Co-60                                        3.88x10         1.70x10                5x10          1x10         96.60x10
                                                                        ~1                  1              -5              ~

Sr-89 1.33x10 3.22x10 4x20 7x10 20.91x10 1 -13 1 Sr-90 4.02x10 1.78x10 4x10 4x10~ 10.23x10~ i

                                                                        -14                                -1              -12 Y-90                                         4.62x10         1.22x10                1x10          4x10         34.66x10 2          -14                 1              ~
                                                                                                                           -10 Sr-91                                        3.43x10         1.42x10                4x10          7x10 '       92.22x10 3          -12                 2              -1              ~9 Y-91                                         2.36x10         6.10x10                1x10          2x10         34.66x10
                                                                        -16                 2              1               -13 Y-92                                         5.43x10         8.20x10                1x10          3x10         31.06x10
                                                                        -13                 2              -1              -10 Zr-95                                        1.02x10         2.77x10                1x10          1x10         31.48x10
                                                                        -13                 0                              -8 Nb-95                                        1.01x10         2.03x10                3x10          4x10~        17.30x10 1          -15                 2              0               -13          l Zr-97                                        6.60x10         4.70x10                1x10          4x10         13.35x10 5          -10                 2              ~0              -5 Mo-99                                        9.79x10         2.67x10                1x10          8x10         37.93x10 1          -16                                -2              -13 Ro-105                                       1.00x10         1.90x10                1x10          9x10         23.99x10 5          -10                 0              ~0              -6 1-131                                        7.87x10         5.55x10                1x10          2x10         31.54x10 4          -11                                -4 Te-132                                       8.28x10         2.60x10                1x10          5x10         59.10x10~

4 -13 0 4x10

                                                                                                           -3     68.76x10~

I-132 2.43x10 2.42x10 1x10 5 -11 1x10 0 ~4 10.73x10~ I-133 9.94x10 8.50x10 9x10 0 ~7 0 -2 -5 I-134 3.76x10 1.44x10 1x10 1x10 16.37x10 l 5 -12 0 -3 -9 I-135 2.90x10 8.20x10 1x10 2x10 40.60x10 4 -10 -6 -2 Cs-134 8.65x10 3.67x10 1x10 9x10 46.34x10

                                                                        -11                                -5              -4 Cs-136                                       1.25x10'        1.30x10                1x10          9x10         16.42x10 5          ~9                  3              -5              -1 Cs-137                                       4.70x10         2.10x10                1x10           2x10        11.93x10 2          -13                 1              -
                                                                                                                           -9 Ba-140                                       3.17x10         3.25x10                1x10          5x10 '       73.87x10 2          -14            1x10 2

2x10 1 21.03x10

                                                                                                                           -11 La-140                                       2.91x10         3.70x10 3          -12                 2              -2 17.81x10
                                                                                                                           -8           l Ce-144                                       1.13x10         4.70x10                1x10           3x10 8          -6                      -1         -3              -2 H-3                                          8.49x10         3.77x10                9.26x10        5x10        78.90x10 Total                          3.03 3.7-20 l

1

O O O TABLE 3.7-5 WHOIZ BODY DOSES FROM RELEASES TO IAKE ROBINSON (SEPT. 1970 - AUG. 1971) , Cw Concentration Concentration Whole Body Dose = Total Release In Lake Factor MPCw For 50 Cw x Cf 500 mrem Isotope To Sept.'71 (mci)_ (pCi)/mi Cf .bhole Body 2200

MPCw year

                                        -11                    2                 -2                -6 Cr-51            13.2         2.3 x 10                 2 x 10            2 x 10         2.61 x 10 8x 10 '                  -5
                                                                                 ~

Mn-54 63.5 2.5 x 10~ 2.5 x 10 8.88 x 10

                                        -12                       2              ~O                ~0 Fe-59             2.6         7.2 x 10                 3    x 10         2 x 10         1.23 x 10
                                         ~9                       2              -4                -2 Co-58          450            1.25 x 10               5     x 10         4x 10          1.77 x 10 Co-60            29           1.27 x 10~              5     x 10         1 x 10~        7.21 x 10~
                                         -1                                      -4 I- 131           23           1.60 x 10                1    x 10         2 x 10         9.08 x 10~
                                         -12                      3              -5                -3 Cs-137            1.9         8.4 x 10                 1    x 10         2 x 10         4.80 x 10 i
                                                                                 ~3               -2 H-3         38,274            1.7 x 10~               9.26 x 10'I        5 x 10         3.5 x 10
                                                                                                   -2 Total                                                     6.5  x 10     mrem Year

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

i TABLE 3.7-6 l O. J 1 ESTIMATED ANNUAL GASEOUS RELEASE BY ISOTOPE FROM H. B. ROBINSON UNIT No. 2 l

l l Maximum Design Maximum Expected Activity Activit Isotope Curies /yr. y) Curies /yr.{3) I Kr 85 3857 772 Kr 85m, 97, 88 Negligible Negligible Xe 133 3522(2) 704(2) Xe 133m,' 135, 135m, 138 Negligible Negligible Total 7379 1476 ! (1) Based on 1% defective fuel and 2300 Mut load follow operation (2) 45-day holdup (3) Based on 2% defective fuel and 2300 MWt load follow operation t I O 3.7-22 i

TABLE 3.7-7 O GASEOUS RELEASES FROM H. B. ROBINSON UNIT NO. 2 Activity Released Sept. 1970-Aug. 1971 Isotope Curies Mixture Xe-133, Kr-85 0.022 O O 3.7-23

O O O TABLE 3.7-8 POPULATION EXPOSURE FROM GASEOUS RELEASES AT THE H. B. ROBINSON STEAM ELECTRIC PLANT Maximum Man-Rem Maximum Actual Man-Rem Natural Distance From The Population Dose From Design Expected Dose Dose From Sept. Background Man-Rem Site in Miles (1986 Projection) Basis In Man-Rem 1970-Aut._ 1971 Sept. 1970-Aug. 1971

                                                                                                  -6 0-1               534                      2.91                  0.58          8.7 x 10                                      107
                                                                                                  -6 1-2               994                      1.20                  0.24          3.6 x 10                                      199
                                                                                                  -6 2-3              1534                      0.93                  0.19          2.8 x 10                                      307
                                                                                                  -6 3-4              2875                      1.12                  0.22          3.4 x 10                                      576
 "                                                                                                -6
 .        4-5              8003                      2.18                  0.43          6.5 x 10                                     1600 u
                                                                                                  -6 h        5-10            19624                      2.67                  0.53          8.0 x 10                                     3924
                                                                                                  -6 10-20            55905                      2.94                  0.59          8.8 x 10                               11182 20-30                                                                                    -5
                        -184893                      4.97                  1.00          1.5 x 10                               36978
                                                                                                  -5 30-40           223153                      3.75                  0.75          1.1 x 10                              44630
                                                                                                  ~

40-50 286298 3.58 0.72 1.1 x 10_5_ 57260

-5

TOTAL (0-50) 783813 26.25 5.25 8.0 x 10 156762 i

I Average Rem 3.35 x 10

                                                               -5 6.7 x 10
                                                                                    -6 1.02 x 10
                                                                                                    -10                                        ~1 2.0 x 10

Person i

i k 1 e2 e- u r- -_- - -- ---- - __._- - -

1 3.8 AESTHETICS 1

 /"                                                                                                 I V)

The site is located in a rolling wooded rural area in the north-eastern section of South Carolina. The terrain surrounding Lake Robinson has been preserved in its natural state except in the plant area and those areas where residential and recreational facilities have been developed by others on adjoining lands. Prior to construction of the nuclear unit, the site had been dedicated to the generation of electrical energy. The addition of the nuclear unit did not significantly alter the aesthetic value of the site area. The nuclear unit renders a minimum disturbance to the rural background and was designed with clean, architecturally pleasant lines. During the construction of H. B. Robinson Unit No. 2, some temporary upsetting of the environment was unavoidable. Every effort has been made to eliminate all temporary construction effects. A temporary access road was built on CP&L property from the main hardtop road serving the plant area for the purpose of bringing in materials and equipment for con-struction and for access by workmen. After completion of the unit, the land [) used for the temporary road was returned to its original state by reseeding and planting pine seedlings. To provide additional protection to the lake, the discharge canal was lengthened by 3 miles. After completion of the canal modification, the slopes and embankment were seeded and planted with pine seedlings to control erosion and to enhance the aesthetic qualities of the canal and make it harmonious with the surrounding environs. L After completion of construction, the plant area within the fenced enclosure was seeded and the area surrounding the plant was seeded ! and planted with a large number of pine seedlings for erosion control and enhancement of the aesthetic qualities of the area. Figure 1.1-1 is an aerial photograph of the H. B. Robinson plant site and local environs. This photograph illustrates the compatibility of the nuclear unit #2 with the environs and the progress made to date in elimina-() tion of temporary construction effects. 3.8-1

4 l l A visitor's center and picnic area are located at the site. The center is architecturally pleasing and the area, which is well landscaped. Provides an excellent vantage point to view the plant. , I h N I k l I O . 4 b i r i e I i I e 1

1 I F F O i 3.8-2

3.9 TRANSPORTATION EFFECTS O The generation of electrical energy in a nuclear power plant requires the periodic shipment of new fuel assemblies to the plant, spent fuel assemblies to a fuel reprocessing facility, and packaged low-level radioactive materials to licensed waste burial grounds. The ship-mene , made in compliance with Federal and State requirements pertaining to tru per packaging and transportation of the materials. New pressurized water reactor fuel (UO Pellets clad in Zir-2 caloy) for the Robinson Plant will be shipped by either rail or truck from the fabrica , ,lant in packages designed to protect them from physical damage u .o the normal handling and vibration of transportation and will be in accordance with U. S. Department of Transportation (DOT) regulations for the transportation of fissile materials. Because new fuel contains no fission products or radioactive gases, an accident involving a new fuel shipment in which the package and fuel assemblies were damaged we ' result in no release of radioactivity and would, therefore, have environmental effect. The only effect would be an economic loss for replacement of the damaged new fuel assemblies. Inherent in the generation of power with a nuclear reactor is the fact that fissionable isotopes in the nuclear fuel are depleted to the extent that they need to be replaced with new fuel. However, the spent fuel still contains residual fissionable uranium and plutonium. This recovery operation can most safely and economically be carried out at a separate fuel reprocessing facility serving many individual reactors. Therefore, the spent fuel must be transported to a recovery facility where valuable uranium and plutonium can be recovered and residual wastec packaged for safe disposal. The Robinson nuclear unit will discharge approximatcly 52 spent fuel assemblies each year. The spent fuel will be cooled in the plant fuel storage pools for at least three months prior to shipment during which time many of the isotopes present will decay away. When cooled, the spent O 3.9-1

l l 1 1 i fuel will be packaged in containers designed and constructed to meet the l O riserees re, iremeet ei ese usite a u s nee rt- t er tr vert tie - These requirements provide for protection of the public in case of j abnormal and accident conditions as well as normal conditions of trans-port. The nomal shipping conditions require that the package be able l to withstand temperatures ranging from -40 F to 130 F and to withstand the normal vibrations, shocks, and wetting that would be incident to nomal transport. We accident conditions for which the package must be designed include, in sequence, a 30-foot free fall onto a completely . unyiciding surface, a 40-inch drop onto a 6-inch diameter pin, 30 minutes j in a 1475 F fire, followed by 8 hours immersion in 3 feet of water. ne permissible radiation levels and releases for these shipping conditions i are given in Table 3.9-1. The radiation levels shown in Table 3.9-1 represent limits established by the regulations. The containers will exhibit radiation levels and releases under accident conditions less than those permitted by the regulations. Prior to their use, container designs and the transport system O 111 se revie ea a Perevea av usite be authorized by a license issued by the USAEC. a usoor. a tr evert tie 111 License provisions will include adequate Quality Assurance and Testing Programs to assura equip-ment is constructed and used in accordance with approved designs and procedures. When loaded, containers will be decontaminated, if necessary, and carefully surveyed and inspected to assure that they have been properly prepared for shipment and are in full compliance with license provisions governing transportation. Shipments will also be placarded in accordance I with Federal regulations. l CP&L has a long-term contract by which Allied Gulf Company will reprocess spent fuel. Spent fuel will be transported by both rail and exclusive-use truck. By rail 7 to 12 fuel assemblies can be handled in l one shipment; by truck, the capacity is limited to one fuel assembly per shipment. Since rail service is available at the Robinson Plant, most , spent fuel will be shipped by rail. Truck shipment will be used only ! for odd numbers of assemblies left over from full rail shipments. O 3.9-2

i i l l Based on this plan, approximately 5 rail shipments and approxi- l mately 2 truck shipments will be made each year. Destination for these ' shipments will be Allied Gulf Nuclear Services in Barnwell, South Carolina. Rail routing will be via Florence, S. C. and Orangeburg, ! S. C., a distance of 130 miles which will require approximately 48 hours, via direct movement over the Seaboard Coastline Railroad. Truck routing 4 will be via highways, SC 151, I-20, US 321, and SC 64, a distance of 132 miles, which will require 4 hours. i

i The total yearly spent fuel shipping program will be carried l t out in approximately one month. In all cases, truck shipments will be routed to avoid heavily populated and congested areas as well as tunnels, bridges or roads which prohibit such shipments. Progress of truck ship-ments will be frequently reported to the reprocessor while enroute and each truck will have two specially trained drivers. Instruments for detection of abnormal conditions and instructions for immediate action will accompany all truck shipments and will be available at rail con-nection and interchange points. Progress of rail shipments will be monitored and reported at all connections and interchange points. A formal Accident Control and Recovery Plan will be developed prior to the first shipment which will provide for rapid and orderly utiliza-tion of CP&L, carrier, Allied-Gulf, USAEC, State and Local Radiological Assistance Personnel as required in the event any abnormal condition or accident is encountered. The plan will include salvage and recovery as well as control of bodily injury and property damage. It is believed that there will be no significant adverse environmental effects asscciated with the transportation of spent fuel from the Robinson Plant. This conclusion is based on the following: (1) The volume of rail and truck traffic added in the region of interest is an insignificant part of existing traffic. O 3.9-3

                       -                                                              ~

(2) The packaging and vehicle will be designed to withstand both nomal and accident conditions without release of ' radioactive spent fuel or harraful radiation exposure to { the public. ) i (3) The hazards associated with possible accidents are largely ; those associated with conventional heavy object shipments, not radiological hazards. j (4) The probability of accidents is lower than comparable l heavy object shipments because of the additional equip- { ment design and operational safety requirements because l of thorough driver screening and training. I Shipment of solid waste containers of low level radioactive . material between the plant and a disposal location will be dona periodi- ! cally. Regulations pertaining to such packaging and shipments prescribed by the AEC and U. S. Department of Transportation will be met. Approxi-mately 1000 drums of solid waste will be shipped from the plant each j year. Each shipment will consist of from 15 to 100 drums. O i The only exposure to people from routine shipments is for the r brief period such a shipment is in direct view. A person standing along l the roadway while a solid waste shipment passes would receive an insigni- I ficant direct dose. i e The radiation exposure to the public in transporting new fuel, i spent fuel, and low level radioactive wastes from the plant will consti- l tute no hazard to the general public, nor result in any significant ' environmental effect. 1 The principal environmental effect from these shipments would j be_the direct radiation dose from the shipments as they move from the r plant to the reprocessing plant. In this regard, it has been assumed that the shipments will be made at the maximum permitted level of 10 mrem per hour at six feet from the nearest accessible surface. Based on this, O 3.9-4

and with the nearest person assumed to be 100 feet from the centerline of the tracks (because of railroad right of way) it is estimated that the dose rate at that point would be 0.2 mrem per hour. This would fall off to 0.01 mrem per hour at approximately 300 feet beyond which the reduction exposure received by the population is considered to be negligi-b le. O I 6 O i 3.9-5 o

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

TABLE 3.9-1 O CONTAINER DESIGN RESTRICTIONS NORMAL ACCIDENT CONDITIONS CONDITIONS r EXTERNAL RADIATION LEVELS SURFACE 200 MR/hr 3 FT. FROM SURFACE 1000 MR/hr 6 Fr. FROM SURFACE 10 MR/hr PERMITTED RELEASES NOBLE GASES NONE 1000 Ci O CONTAMINATED C001 ANT NONE 0.01 Ci alpha, 0.5 Ci mixed fission products . 10 Ci Iodine OTHER NONE NONE CONTAMINATION LEVELS 2 BETA AND GAMMA 2200 dpm/100 cm I ALPHA 220 dpm/100 cm O 3.9-6

3.10 TRANSMISSION LINES The transmission lines were planned, designed, routed and constructed to minimize the environmental impact. 3.10.1 Description of Transmission Lines The power generated at the Robinson Nuclear Unit is trans-mitted over four 230 KV transmission lines extending to the transmission grid. I The transmission lines which were constructed in 1970 with the Robinson Nuclear Unit are as follows: Robinson - Sumter 230 KV 38.6 miles Robinson - Florence South 230 KV 27.1 miles Robinson - Florence North 230 KV 17.6 miles Robinson - Rockingham 230 KV 17.6 miles The line to Rockingham and the north line to Florence consist of two short sections of new 230 KV line constructed from the plant to connect to an existing 230 KV line, near Society Hill, S. C. The line to Rockingham consists of 17.6 miles of new 230 KV line and a 31.9 mile section of the existing 230 KV line between Florence and Rockingham. The Robinson-Florence North 230 KV Line consists of 17.6 miles of new 230 KV line and 20.6 miles of the same 230 KV line from Florence to Rockingham. The line to Sumter and the southern line to Florence was constructed on completely new right of way from Robinson to the respective substations. See Figure 3.10-1 for the transmission system in South Carolina. , The location of the 230 KV lines superimposed on a portion of the South Carolina state highway road map is shown on Figure 3.10-2. Each of the transmission lines is operated at 230 KV, and consists of wood two pole H-frame structures, except for structures O l l 3.10-1

immediately adjacent to the Robinson Plant. The wood structures are shown on Figure 3.10-3. The basic structure consists of two 70-foot wood poles extending 61 feet out of the ground. Span lengths average 650 feet. The conductor is 1,272,000 45/7 ACSR (diameter = 1.345 inches) per phase. The overhead ground wires are either 2 - 7 #10 alumoweld (diameter = .306 inches) or 2 - 3/8" high strength steel (diameter = .360 inches). In the immediate vicinity of the Robinson Plant, galvanized steel lattice towers in place of H-frame structures were used to provide sufficient height to cross existing lines leaving the switchyard. 3.10.2 Environmental Effects of Transmission Lines The construction and the operation of the lines have a minimum ef fect on the environment. The lines have caused no change in population patterns and will have minimum change on land use in future years. No residences were removed or affected. The only lands committed to the lines are the areas they traverse. Ownership of the land is retained by the property owners who continue to use it for agricultural, recreational or other purposes not inconsistent with the operation of the lines. The Company continues to cooperate with State and Local agencies, property owners and other individuals in creating recreat.lonal and wild-life opportunities along portions of the right of way. The Company con-tinues to prepare the land, in cooperation with the property owners, for other uses such as pasture land and for agricultural purposes. The right of way affords excellent potential for game food plots and game cover, recreation areas, parks, golf courses, orchards, picnic areas, storage areas, parking areas, Christmas tree and other types of nurseries, wildlife sanctuaries, refuges and management areas, and access roads either private or public, 3.10-2

i Forest fires are a constant threat and can cause extensive damage , to the forests and wildlife. Where the right of way crosses wooded areas, it provides an excellent fire break to help limit and confine forest fires 1 to the immediate area. The right of way also provides a ready means of access for fire fighting equipment in inaccessible areas. To reduce the visual impact of the lines, wood pole H-frame structures using wood poles of minimum height were used. The poles blend in with the forested area and because they are of low height are generally not visible above the tree tops at a distance. At locations where the lines cross areas of public access such as roads, rivers, and streams, the existing growth in the right of way is left in its natural state during recicaring operations to provide a screen for the structures. The reelearing is limited to that material which poses a hazard to the line. Where necessary to remove large trees and other growth, special clearing techniques are used to reduce any possible damage to the remaining growth. Native types of plants, low growing trees, etc. are planted in areas where needed for effective screening. The wood pole structures are located behind the screening to I blend in with trees, and this together with their low profile provides a very effective means of reducing the visibility of the structures. , Access to the right of way behind the screening is by access roads lo-cated at an angle to the screening. It is the intent of the Company to preserve and enhance the natural growth in these areas. The wood pole structures were transported to each site and con-structed with a minimum disturbance to the environment. Their foundations, [ 2 per structure, required an absolute minimum of excavation, since the pole butt is directly buried in the ground. Excess soil removed from the pole hole was evenly distributed over the surrounding area. Pole holes were 36 inches in diameter and 9 feet deep. Each tangent structure only occupies an area of approxir2ately 4 square feet af ter erection. O 3.10-3 i i

  . .. ..           -       .-       _ _= .         -           .   .              .- . . . - . . _ . ..

i b Because of the very small area actually occupied by the struc-O. tures, normal agricultural practices are maintained on the lands where the lines cross agricultural areas. Normal operation and maintenance of the lines require infrequent traversing of the right of way. Airplane patrol of the lines is con-ducted on a regular basis. Maintenance personnel are directed to the precise area requiring attention as a result of the airplane patrol. Once

a year either 2 or 3 men in a suitable vehicle travel the entire line length closely inspecting the condition of structures and right of way.

This infrequent traveling of the right of way has a minimum effect on r the land and growth. Right-of-way maintenance is scheduled on a 4 to 5 year cycle to control vegetation growth. Areas such as major road and stream crossings are being maintained and improved so as to preserve the effects obtained by special reclearing. The screening at these crossings , will improve each year as selective pruning will enhance the growth and thickness of the vegetation. Right-of-way maintenance also takes into , account any uses of the land for recreation and wildlife purposes. O The lines do not cross any designated historical sites, recrea- ; tion areas, or wildlife management areas. Public lands were avoided in the route selection. The regulatory agencies involved in the review of the transmission lines were l I. Federal Aviation Administration - Issued permit to obstruct navigable airspace. II. South Carolina Hinhway Commission - Issued permits to cross certain highways. l 3.10.3 Environmental Effects of Transmission Lines that Could Not Be Avoided $ The visibility of the lines in aome areas and the curtailed use- , of the land for timber production in the right of way are the only. O .I 3.10-4

r environmental effects which could not be avoided in the construction ( and operation of the transmission lines. 4 The visibility is reduced to a minimum through the use of low ! structures which do not generally project above the tree tops of mature timber and through selective reclearing and planting at points of high visibility such as road and river crossings. Although timber production capacity of those lands in the c1 cared portion has been curtailed, other uses are made of the right of way such as providing food and better habitat for many species of wildlife. e i O i I i i O 3.10-5

P 3.11 POSTULATED ACCIDENTS

O 3.11.1 Introduction This section evaluates the environmental impact of postulated : accidents and occurrences which may occur, however remote, during the operating life of the H. B. Robinson Unit No. 2 Nuclear Plant. The i evaltation follows the guidelines given in the AEC document " Scope of Applicants' Environmental Reports with Respect to Transportation, Trans-mission Lines, and Accidents" issued on September 1, 1971. The results of this evaluation reveal that the consequences of the postulated accidents , and occurrences have no significant adverse environmental effects. The postulated accidents and occurrences are divided into the , nine accident classes identified in the AEC guide of September 1, 1971 . as shown in Table 3.11-1. The environmental impact of the postulated incidents is evaluated using assumptions in the analyses as realistic ao the state of knowledge permits. Past operating experience has been () considered in selecting the assumptions, and the analyses are based on , those conditions that are expected to exist if the postulated accident would occur. The radiological consequences of an accident are evaluated , on the basis that average meteorological conditions, as calculated from i the actual site meteorology data and.the population distribution projected for the year 1986, exist at the time of an accident. This is considered ) realistic for random events. i In the following pages, a typical accident for each clast is described and its consequences evaluated. Where only one accident example is considered in a class, the postulated accident was selected from consid- i 1 eration of several possible accidents in that class on the basis that it con- l servatively represents a potential accident situation. Consideration of < the nine classes reveals that these classes can be conveniently grouped on the basis of their likelihood of occurrence as follows l (1) 3.11-1 m

4 3.11.1.1 Class 1 through Class 5 This group deals with events which may occur at one time or another during the life of the plant. The compilation of a complete list of events with their corresponding frequency which fall in this group is not practical nor necessary. The environmental impact of each event, as will be shown later, is very small. Throughout plant operating life, 4 a record of the magnitude and consequences of each event is maintained and the cumulative effect of subsequent occurrences is evaluated. Any possible cumulative effects or trends leading to unacceptable environmental effects will be identified. This will also allow corrective actions (such as equipment repair, changes in procedure, frequent inspection, temporary plant shutdown, etc.) to be taken before a significant adverse impact on the environment can be imposed. Postulated occurrences for Class 2 through 5 are considered in the following pages. Class 1 events, because of their trivial consequences, ) are not considered in this report, as indicated in the AEC guidelines. 3.11.1.2 Classes 6 and 7 This group deals with refueling and fuel handling accidents inside the containment. Detailed procedures are provided to handle irradiated fuel. However, considering the large amount of fuel assemblies handled during the life of the plant, an incident falling in this category could conceivably occur during the plant life. The consequences of such an accident, as shown in the subsequent pages, are of no significant adverse impact on the environment. 3.11.1.3 Class 8 This class includes those accidents that are not expected to occur during the life of this plant and whose initiation events are con- , i sidered in the Final Safety Analysis Report (FSAR), available in the Public I Document Room. Each accident is treated separately in the following pages. O 4 3.11-2

                                                                                  .-y-----..., . v.w-~

The treatment consists of a brief description of the accident, a summary ; () of the steps taken in the design, manufacturing, installation, and operation to essentially eliminate the possibility of its occurrence, a list of the

most significant assumptions used in the analyses and the results of the dose calculations. The accident consequences are evaluated by using the analytical models described in the FSAR. The basic difference between the FSAR evaluations and those presented in this section is represented by the L values of the parameters used as input in the analytical models. The FSAR analyses are based on extremely conservative input parameters while the analyses performed in this report are based on realistic assessments of the performance of the nuclear plant safeguards. It can be concluded that accidents falling in this class have no significant adverse environmental effects because:

1) hypothetical FSAR types of accident initiation events are not expected to occur during the life of this plant because of the numerous steps taken in design, manufacture, construction, operation, and maintenance

() to prevent them,

11) and, the expected environmental consequences,1f any one of the acci-dents were to occur, are below the limits considered safe for normal operation (10 CFR 20).

If any of the accidents covered in this category were to occur, assessment of the actual impact on the environment will be performed and a comprehensive plant inspection conducted before a return to power. 3.11.1.4 Class 9 This accident class involves hypothetical sequences of failures ; more severe than Class 8, i.e., successive failures of multiple barriers normally provided and maintained. O 3.11-3

r Considering, as an example, the rupture of a Reactor Coolant () System pipe, Class 8 covers the case of this initiation event and expected performance of plant safeguards. Class 9, on the contrary, would consider i the initiation event, i.e., rupture of a Reactor Coolant System pipe plus, hypothetically deturiorated performance of plant safeguards, for example, failure of outside power supply, and/or failure of a diesel, and/or failure of a high head safety injection pump, and/or' failure of a low head safety injection valve, and/or failure of a containment spray pump, and/or failure of a containment spray valve, etc. This chain of failures can, theoretically, be carried as far as an individual's imagination can go. The Final Safety Analysis Report contains studies en the conse-quences of many successive failures. The 14.selihood of the combination of the initiation event and these successive failures is extremely remote. The consequences, as presented in the FSAJ., are within the allowable limits for remote probability accidents (10 CFR 100 limits) . () The occurrence of successive failures as presented in the r3AR is so remote that its environmental risk is extremely low. Hence, is is not necessary to discuss these multiple barrier failures in the present report, as indicated in the AEC guide published on September 1, 1971. , 3.11.1.5 Meteorology Data The meteorological data used in this section is obtained from the site atmospheric stability analysis contained in the Final Safety Analysis Report (FSAR). Average values are used for establishing the X/Q for each sector which is a conservative estimate of the exponential type X/Q versus distance function. The annual average dilution factor at the site boundary used in this analysis is the annual average dilution factor at the nearest O 3.11-4

                                                                      -5 site boundary of 2x10                                                               sec/m contained in the Technical Specifications for the H. B. Robinson Unit No. 2 Plant.

3.11.1.6 Population Distribution The population distribution used in this analysis is taken from the FSAR and described in Section 2.1.3 of this report. Since the expected plant life is 40 years, the average environmental effect on the population is estimated by using the projected population for the year 1986 to represent the mid-point of the plant life. Using this population t distribution, the average environmental effect of the plant over its expected lifetime is estimated by the methods shown in Section 3.11.1.7. 3.11.1.7 Calculation of Doses For each of the accident classes considered in this report an average site boundary thyroid and whole body dose was computed. The average total body dose includes the beta skin dose contribution. In O addition, the total dose to the population within a 50-mile radius of the site was analyzed for each accident class using the meteorological and population data described in sections 3.11.1.5 and 3.11.1.6. The models used to compute the thyroid, whole body, and popula-t tion doses are presented below. 3.11.1.7.1 Thyroid Dose The average thyroid dose at the site boundary was computed , using the equation: Thyroid Dose = (X/Q)S.B.x x Ai xM y where: A = Activity release to the environment of isotope i f

DCF = Dose conversion factor of isotope i B = average breathing rate of the average man

                                                                                           = average annual X/Q at the site boundary as (X/Q)S.B.

O given in Section 3.11.1.5 3.11-5

3.11.1.7.2 Whole Body Dose i O l The average whole body dose, including the beta contribution, at the site boundary was computed using the equation for a semi-infinite spherical cloud as given by: [ Whole Body Dose = 0.246 x (X/Q)S.B.

i ^1 x (E_. 1+E_vi) where: A = activity released to the environment of f

isotope 1 5 f

                                 = Gamma energy of isotope i
                                 = Beta energy of isotope 1 1

(X/Q)g,3, = Average annual X/Q at the site boundary as given in Section 3.11.1.5 O (The assumption of a semi-infinite spherical cloud is conservative.) 3.11.1.7.3 Population Dose The total population dose was computed using the equation: Population Dose = 0.246 A x (Eg +S)g j j P j where: A,h and Eg are the same as given for the total body dose model, and X/Qr,6 = the X/Q for a given sector (d) and distance (r) as given in Section 3.11.1.5. O 1 3.11-6 i

P j

                                                                                   = the population estimate for a given sector (d) and distance (r) as given in Section 3.11.1.6 3.11.2               Evaluation of Class 2 Events                                                                                        l l

3.11.2.1 Discussion of Class 2 Events Class 2 events include spills and leaks from equipment outside the containment. Small valve leaks and pipe leaks may be expected during the lifetime of the plant. There is expected to be a low level of continuous leakage from components such as valve packing and stems, pump seals, flanges, etc. Infrequent increases in leakage from specific components might occur; however, these would be detected by operators and/or in-plant monitoring and appropriately repaired to minimize any potential off-site effect. 3.11.2.2 Description of Representative Class 2 Event A significant valve and/or pipe leak in the reactor coolant letdown line may occur during the lifetime of the plant. A conservative example of such an occurrence would be a leak in the volume control tank sampling line which would allow a fraction of the contents of the. volume control tank to be released. Were such a leak to occur, the Radiation ! I Monitoring System would detect the activity and with appropriate operator action the release could be limited to 10 percent of the gas contained in the tank. The event used to evaluate the environmental effect is defined as the release to the outside atmosphere of 10 percent of the noble gas activity in the volume control tank. 3.11.2.3 Discussion of Remoteness of Possibility of Volume Control Tank Release The volume control tank is designed for 75 psig with a normal ! internal operating pressure of approximately 15 psig. 1 1 I i O i 3.11-7 I

                                                                                                                                                              .1
   - - . . - , - . .              _ .             ,.._s, .   . . ~ , _ _ . , , , ,       , , , ,_,,,.,,,_..,.%.m.m,,.,,.._.,_,_,.r,_,,,,.__ ,,py y.,-,,, ..s,

The volume control tank design philosophy provides for level I

 .( alarms, pressure relief valves and automatic tank isolation and valve control to assure that a safe condition is maintained during system operation.

Quality control in the design, manufacture, and installation introduces a high degree of reliability and confidence to further assure ' I that no failure in this system will occur. In summary the release of 10 percent of the noble gas inventory is considered to conservatively represent i the accident or occurrences falling in this class. Since the volume control tank is not subject to high pressure or stress and is of 75 psig design, an accidental release from the-tank L is considered very remote. ; ~ 3.11.2.4 Assumptions Used in The Analysis and Evaluation of Volume 1 Control Tank Release , The following assumptions are used in che evaluation of the ' environmental effect of the release of the volume control tank activity: t

1) The activity in the tank is based on 0.2 percent equivalent l fuel defects.

2) Within two hours after initiation of a noble gas activity release from the volume control tank, 10 percent of the tank noble gas inventory is released. ,

3) Immediately after the noble gas activity escapes from the ,

volume control tank, it is released from the Auxiliary Building at ground level to the outside atmosphere. Holdup in the Auxiliary Building is expected, thus reducing even further the environmental effect of this occurrence. However, no credit is taken in the analysis. O 3.11-8 9

 --        - - . . . -- .-. - . .                 -         -     - . -      ..~

4) Natural decay is neglected after the activity is released to the outside environment.

3.11.2.5 Justification for Assumptions a) The 0.2 percent defect level is based on reactor operating experience with W PWR Zircaloy fuel to date, b) Nonvolatile fission product concentrations are greatly reduced as the reactor coolant is passed through the purifi-cation demineralizers. An iodine removal factor of at least 10 is expected in the mixed bed demineralizere. c) The released noble gas will be detected by the plant vent monitor and cause en alarm in the control room. Once the operators have been alerted, the leak can be detected and isolated to hold the activity release to 10 percent of the total noble gas inventory of the volume control tank 3.11.2.6 Doses at the Site Boundary and Total Population Dose (Man-Rem) With the above assumptions the whole body dose at the nearest site boundary resulting from the volume tank release as calculated by the method shown in Section 3.11.1.7, is 0.322 mrem from the released noble gas activity, while the total population dose is 0.073 man-rem. 3.11.3 Evaluation of Class 3 Events 3.11.3.1 Discussion of Class 3 Events Class 3 events cover equipment malfunction and human error which may result in the release of activity from the Waste Processing System. The malfunction of a valve or the inadvertent opening of a valve by an operator may cause such a release. This type of event is expected to occur infrequently during the operation of the plant. O 3.11-9

. - - - - . . - - - ~ ~ - . _ _ . - - - . . . - . - - - - - - l 3.11.3.2 Description of Representative Class 3 Event The major collection point for activity outside the containment is the gaseous waste section of the Waste Processing System. A conservative example of a Class 3 event would be a malfunction or error which would allow : initiation of activity release from the waste gas decay tank. This activity would leak into the fuel handling building atmosphere and pass through the vent to the outside atmosphere. The fuel handling building vent monitor would detect this radiation and transmit an alarm signal to the control , room. The event used to evaluate the environmental effect is defined as the release of 10 percent of the noble gas activity in the waste gas decay tank to the outside atmosphere. 3.11.3.3 Discussion of Remoteness of Possibility of A Gas Decay Tank Release The gas decay tanks contain the gases vented from the Reactor e Coolant System and the volume control tank. Sufficient volume is provided in these tanks to store the gases evolved during a reactor shutdown. L Because of the conservative design, quality assurance, the close monitoring and sampling throughout the system, and since the gas decay tanks t are not subjected to any high pressures or stresses and they are of 150 psig design, any accidental release from any of the tanks is highly unlikely. For these reasons the release of 10 percent of the noble gas stored in the gas decay tank is considered to conservatively represent accidents and occur-rences falling in this class. 3.11.3.4 Assumptions Used In The Analysis and Evaluation of Gas Decay Tank Release The following assumptions are used in the evaluation of the en- ; vironmental effect of the release of activity from the waste gas decay tank: 1

1) 0.2 percent fuel defects.

O 3.11-10 1 1

f

2) Within 2 hours after initiation of a release from the gas

() decay tank, 10 percent of the noble gas is released.

3) Immediately after the noble gas activity escapes from the ,

waste gas decay tank it is released at ground level from the i fuel handling building to the outside atmosphere.

4) Natural decay is neglected after the activity is released to the outside environment.

3.11.3.5 Justification for Assumptions ; a) The 0.2 percent equivalent fuel defect level is based on reactor operating experience with W PWR's. l b) The fuel handling building vent monitor will detect the noble gas activity being released to the outside atmosphere and annunciate in the control room. This alerts the operators () and the leak can be detected and isolated to hold the activity release to 10 percent of the total noble gas activity in the ! waste decay tank. . 3.11.3.6 Doses at Site Boundary and Total Population Dose (Man-Rem) With the above assumptions the whole body dose at the nearest ! site boundary resulting from the gas decay tank release is 1.204 mrem and ; the total population dose is 0.274 man-rem. 3.11.4 Evaluation of Class 4 Events ! s 3.11.4.1 Discussion of Class 4 Events This is described as those events that release radioactivity into the primary system. Examples given include assumptions of fuel failures dur- I ing normal operation and transients outside the expected range' of variables. (:) 3.11-11 , F i k

_. ._ ..- ~ . _ _ _ _ ._ _ _ _ . . . . _ _ _ ._ .___ _ . . _ _ __ l The Nuclear Steam Supply System is designed so that it may operate with an equivalent 1 percent fuel defect. The defect level , averaged over the life of the plant will be much less than the design value as shown by the experience of similar plants to date. The occur-rence of a fuel defect in itself will not result in any environmental impact because of the multiple barriers provided in the Westinghouse pressurized water reactor. Nevertheless, this occurrence may result in activity levels which could affect the consequences in normal operation and in other accident classes all of which are evaluated in other appropriate sections

of this report. Operational transients for the plant such as turbine trip, load changes, rod withdrawals and any other conceivable transient within accident conditions covered in other classes are not expected to increase the defect level. No additional events are identified in this l

class. 3.11.5 Evaluation of Class 5 Events v 3.11.5.1 Discussion of Class 5 Events O The Class 5 events are defined as those accident events that transfer the radioactivity in the reactor coolant into the secondary system through steam generator tube leakage, with a fraction of the transferred radioactivity in turn being released into the environment through the con-denser off-gas. Radioactivity releases into the environment resulting from the events in this class require a concurrent occurrence of two independent events of fuel defects and steam generator tube leakage. Since the simul-taneous occurrence of these two independent events is remote, significant radioactivity release to the environment is unlikely. However, if the fuel defects and steam generator tube leakage do occur simultaneously, these concurrent faults at worst would be evaluated continuously in terms of plant secondary system activity technical specification limits and corrective steps taken before any limit is approached. ~ O 3.11-12

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

3.11.5.2 Description of Class 5 Events - Fuel Defects With Steam Generator O. Tube Leakage In the unlikely event of fuel defects with a concurrent steam generator tube leakage, the secondary system would contain fission products ; and radioactive corrosion products. The degree of fission product trans- ; port into the secondary side is a function of the amount of defective fuel in the core and the primary-to-secondary leak rate. These parameters also determine the radioactivity releases from the secondary system if the plant were to continue to operate under these off-normal conditions. Since the condenser off-gas effluent is monitored with a radiation monitor, it would alarm upon the steam generator tube leakage. The blowdown would be termi-nated automatically upon receipt of a high radiation signal from the steam l generator liquid sample monitor which provides backup information to indi- , cate primary-to-secondary leakage. The operator must evaluate secondary system activity in terms of the plant technical specifications. If the primary-to-secondary leak rate and the resultant releases are insignificant, the operator may continue to operate the plant until a convenient time is available to shut down and repair the leaking steam generator, i 3.11.5.3 Discussion of Remoteness of Possibility of an Off-Normal Operational Release , An off-normal operational release requires fuel defects and a i simultaneous steam generator tube leakage. Since the occurrence of these-two events are not related to each other, the possibility of an off-normal release resulting from these two independent events is very remote. In addition, the radiation level of the condenser off-gas dis-charge and steam generator liquid are monitored and any excessive gaseous or liquid releases would be detected by the monitor system and terminated by the operator. To conservatively represent events in Class 5, it has been assumed, for the purpose of analysis, that full power operation with 1 gpm primary-to-secondary leakage and 0.2 percent equivalent fuel defects is continued for one day. l 3.11-13 1

3.11.5.4 Assumptions Used in the Analvsis and Evaluation of Off-Normal ; Operational Release f An analysis has been perfonned of possible releases of radio-activity from the secondary system in the event of fuel defects with concurrent steam generator tube leakage. The analysis is based on the following assumptions:

1) 0.2 percent defective fuel

2) The primary-to-cecondary leak rate is 1 gpm

3) No steam generator blowdown during off-normal operation and the condenser off-gas discharge is the only release.

4-) The period of off-normal operation is one day at full power.

5) The atmospheric dispersion factor at site boundary used in the dose calculation is the annual average.

6) Secondary system decontamination factors:

Steam generator water to steam DF = 10 " "" "" (all halogens) Ci/gm steam DF = 1 "Ci/gm steam (all noble gases) > p Steam to condenser off-gas DF = 10 4 W m s u am (all halogens) < C1/cc air

4 ' E" * ***

DF = 1 (all noble gases) pCi/cc air

7) No nobic gas accumulated in the steam generator water since these are continuously released from the condenser off-gas system.

8) Air flow rate through the condenser off-gas system is 60 scfm.

O 3.11- 14 l l

-1

3.11.5.5 Justification for Assumptions The first assumption is based on plant operating experience to date. The second assumption is a conservative one well within the leak rate which can be detected and result in remedial action. The third as-sumption is based on the fact that the steam generator blowdown is terminated automatically by the steam generator liquid monitor within a few minutes of initiation of the off-normal operation. The one day off-normal operation therefore will not result in blowdown release. The one day off-normal operation at full power of the fourth assumption is based on the expected off-normal operational time. The operator can shut the plant down sooner if the releases are excessive. Assumption 5 is based on the site meteorological data. Assumption 6 is based on the reference: Styrikovich M. A., Martynova 0. I., Katkovska K. Ya., Dwbrovskii

1. Ya., Smrinova I. N. " Transfer of Iodine from Aqueous Solutions to Saturated Vapor," Translated from Atomnaya Energiya, Vol. 17, No. 1, P. 45-49, July, 1964.

O The condenser off-gas flow rate of 60 scfm is a system parameter. 3.11.5.6 Doses at Site Boundary and Total Population Dose (man-r em) With the above assumptions the thyroid dose and the whole body dose at the nearest site boundary resulting from the condenser off-gas re-lease are 1.28 mrem and 0.285 mrem, respectively. The total population whole body dose is 0.065 man-rem and 0.290 man-rem thyroid. 1 3.11.6 Evaluation of Class 6 Events 1 3.11.6.1 Discussion of Class 6 Events Accidents which fall into accident Class 6 are: fuel element mishandling and mechanical malfunctions or loss of cooling in the transfer tube. 3.11-15

l t l s The only event in this accident class which may possibly result

       )
 ' [N /  in a release of radioactive gases from a fuel assembly is the mishandling of a fuel element. The fuel handling procedures are such that no objects can be moved over any fuel elements being transferred or stored. A loss of cooling in the transfer tube will not cause the cladding of a fuel assembly to be damaged. The residual heat generated by the assembly will be removed by natural convection.

3.11.6.2 Description of Class 6 Event - Refueling Accident Inside Containment The accident is defined as the mishandling of a spent fuel as-sembly. The accident is assumed to result in the equivalent of one row of fuel rods in the assembly being damaged. The subsequent release of radio-activity from the damaged fuel element will bubble through the water covering the assembly, where most of the radioactive iodine will be en-trained, and be released to the containment atmosphere. 3.11.6.3 Discussion of Remoteness of Possibility of a fuel gS

   \-                 llandling Accident Inside Containment The possibility of the postulated fuel handling incident is remote due to the administrative controls and physical limitations imposed on fuel handling operations.      All refueling operations are conducted in accordance with prescribed procedures under the direct surveillance of personnel tech-nically trained in nuclear saf ety.      In addition, before any refueling opera-tions begin, verification of complete rod cluster control assembly insertion is obtained by tripping each rod individually to obtain indication of rod drop and disengagement from the control rod drive mechanisms.        Boron concen-tration in the coolant is raised to the refueling concentration and verified           1 l

by sampling. Refueling boron concentration is sufficient to maintain the clean, cold, fully loaded core suberitical with all rod cluster assemblies withdrawn. The refueling cavity is filled with water meeting the same boric acid specifications. A k 3.11-16 i

After the vessel head is removed, the rod cluster control drive I k ,) s shafts are removed from their respective assemblies. A spring scale is used to verify that the drive shaft is free of the control cluster as the lifting force is applied. The fuel handling manipulators and hoists are designed st that fuel cannot be raised above a position which provides adequate shield water depth for the safety of all operating personnel. This safety fea-ture applies to handling facilities in both the containment and in the spent fuel pool area. Adequate cooling of fuel during underwater handling is provided by convective heat transfer to the surrounding water. The fuel assembly is immersed continuously while in the refueling cavity of spent fuel pit. Even if a spent fuel assembly becomes stuck in the transfer tube, natural convection will maintain adequate cooling. Two nuclear instrumentation system source range channels are continuously in operation and provide warning of any approach to criticality during refueling operations. This instrumentation provides a continuous audible signal in the containment, and would annunciate a local horn and a horn and light in the plant control room in the unlikely event that the count rate increased above a preset low level. Refueling boron concentration is sufficient to maintain the clean, cold, fully loaded core suberitical by at least 10 percentajs with all rod cluster control assemblies inserted. At this baron concentra-tion the core would also be mere than 2 percent a subcritical with all control rods withdrawn. The refueling cavity is filled with water meeting the same boric acid specifications. Special prceautions are taken in all fuel handling operations to minimize the possibility of damage to fuol assemb, lies during transport to and from the spent fuel pool and during installation in the reactor. All handling operations on irradiated fuel are ccnducted under water, u-] 3.11-17

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

l The handling tools used in the fuel handling operations are conservatively designed and the associated devices are of a fail-safe design. In addition, the tnotions of the cranes which move the fuel assetablies are limited to a j low maximum speed, j l i The design of the fuel assembly is such that the fuel rods are j restrained by grid clips which provide a total restraining force on each fuel rod. If the fuel rods are in contact with the bottom plate of the { fuel assembly, any force transmitted to the fuel rods is limited due to the restraining force of the grid clips. The force transmitted to the j fuel rods during fuel handling is not sufficient to breech the fuel rod cladding. If the fuel rods' are not in contact with the bottom plate of l the assembly, the rods would have to slide against the 60-pound friction force. This would absorb the shock and thus limit the force on the in-dividual fuel rods. After the reactor is shut down, the fuel rods contract during h the subsequent cooldown and would not be in contact with the bottom plate. O of the assembly, i Considerable deformation would have to occur before the rod l would make contact with the top plate and apply any appreciable load on ! the fuel rod. Based on the above, it is unlikely that any damage would 7 occur to the individual fuel rods during handling. If one assembly is lowered on top of another, no damage to the fuel rods would occur that i would breech the integrity of the cladding. f Refueling ope ration experience that has been obtained with Westinghouse reactors has verified that no fuel cladding integrity failures l occur during any fuel handling operations involving over 50 reactor years l of W PWR operating experience in which more than 2200 fuel assemblies have been loaded or unloaded. i t 2 i O ! 3.11-18 i I

        - . . - .                              . - .   .-.    ~.     --       ....    - -     -  . . _ . - .- .
 ,                                                                                                                i' i

I i

3.11.6.4 Assumptions Used in the Analysis and Evaluation of Fuel Handling l

   .O                      Accident Inside Containment                                                            l t

l The following assumptions are postulated for a' calculation of the fuel handling accident: j

1) The accident occurs at 100 hrs. following the reactor shut- !

down; i.e., the time at which spent fuel would be first moved.

2) The accident results in the rupture of the cladding of the !

i equivalent of one row of fuel rods.

3) The damaged assembly is the one that had operated at the highest power level in the core region to be discharged. !

i

4) The power in this assembly, and corresponding fuel tempera- ,

tures, establish the total fission product inventory and the fraction of this inventory which is present in the fuel O pellet-cladding gap at the time of reactor. shutdown.

5) The fuel pellet-cladding gap inventory of fission products ,

in these rods will be released to the refueling canal water at the time of the accider.t.

6) The refueling canal water retains a large fraction of the gap activity of halogens by virtue of their solubility and I hydrolysis. Noble gases are not retained by the water as !,

they are not subject to hydrolysis reactions. A decontami- 7 nation factor of 760 for the halogens is used in this analysis. - t 7) A small fraction of fission products which are not retained { by the water are dispersed into the containment. f i i

(:) 3.11-19 4

1

8) After isolation of the containment, the radioactive gases in the containment are leaked from the containment to the environment at a small leak rate. The amount of activity leaking from the containment after isolation is assumed negligible compared to that escaping from the purge line ;

during the first five minutes prior to isolation. 3.11.6.5 Justification for Assumptions I I a) It is approximately 100 hours after shutdown that the first l fuel assembly is removed from the core. The time delay be-tween shutdown and removal of the first assembly is due to ! the time required to depressurize the Reactor Coolant System, l remove the vessel head and othet refueling procedures. f i

b) Analyses have shown that mishandling of a spent fuel as- l sembly is not expected to result in damage _of the cladding , of any fuel rods in the ar.sembly. The impact of a spent O ree1 e1eme t eete e ewere e83ect mex re 1t 1 the treeca l of the cladding of some fuel elements in the assembly. The rupture of the equivalent of one row of fuel elements is considered to be a conservative upper limit. c) The highest powered assembly in the discharged region would have the largest quantity of radioactivity in the fuel pellet-cladding gap of all the assemblies to be discharged. d) The quantity of radioacitivity in the fuel pellet-cladding gap is dependent on the power 1cvel and temperature distri-bution of the assembly. e) Since all fuel handling operations are conducted under water, the release of any radioactive gases from a damaged assembly ! would be in the form of bubbles to the water covering the j assembly. O 3.11-20

                             . . ~ . - = - - . - - - . ~ . - , . -. - ~ - -- -      - - - - - - - - ~ - - - ~ ~ - - -~

l f) An experimental test program was conducted by Westinghouse (h to evaluate the extent of iodine removal as the halogen gas bubbles rise to the surface of the pool from a damaged ir- j radiated fuel assembly. j l ! g) The radioactive gases remaining in the bubbles when they l l reach the surface of the pool are released to the atmos- j phere atop the pool. . i h) Any increase in radioactivity concentrations in the contain- l ment will be detected by the radiation monitors. Upon high radiation signal the purge line from the containment vill be 6 j automatically isolated. It is conservatively estimated that f the purge line will be isolated within five minutes follow- I i , ing a refueling accident which releases radioactivity into ! the containment. l f l i) Since the pressure in the containment will be atmospheric at l the time of the postulated accident and no pressure rise will ~ occur due to the accident, the leak rate from the containment t

is expected to be near zero.: I l

l 3.11.6.6 Doses at Site Boundary and Total Population Dose (man-rem) : i The doses at the nearest site boundary from a refueling accident i inside the containment are 0.644 mrem thyroid and 0.129 mrem whole body.

The total population dose from this accident is 0.029 man-rem whole body i

and 0.146 man-rem thyroid. , 3.11.7 Evaluation of Class 7 Events ! l ! 3.11.7.1 Discussion of Class 7 Events [ i i f l Accidents which fall into accident Class 7 are: Mishandling of f f l fuel element, dropping of heavy object onto fuel, dropping of shielding .I l

                  )                     cask or loss of cooling to cask and transportation incident on site.

j 3.11-21 i l 8

4 h

i

  -..-,--.~,. - -   ,~-,c-...,,.---,----.-,r.,--,.               .._,,,,-......-.,_._,m                         - - . - - - . - . - - . -

The only event in this accident class which could possibly re-( sult in a release of radioactive gases from a fuel assenbly is the mis-handling of a fuel element. The fuel handling procedures are such that no objects can be moved over any fuel elements being transferred or stored. The shielding and shipping casks are designed to be dropped with no sub-sequent damage to the cask or the assembly. The spent fuel is not moved off-site until 90-120 days after refueling; thus, most of the major con-tributing isotopes to the thyroid and whole body dose have decayed to a negligible level. 3.11.7.2 Description of Class 7 Event - Refueling Accident Outside Containment The accident is defined as the mishandling of a spent fuel assembly. The accident is assumed to result in the equivalent of one row of fuel rods in the assembly being damaged. The subsequent release of radioactive gases from the damaged fuel element will bubble through the water covering the assembly, where most of the iodine will be entrained, and be released to the spent fuel building. The activity is then exhausted to the environ-ment via the fuel handling building vent. 3.11.7.3 Discussion of Remoteness of Possibility of a Fuel Handling Accident Outside Containment f A fuel handling incident outside the containment is considered , to be equally as remote as that inside the containment. The administrative controls and physical limitations imposed on fuel handling operation are { essentially the same as those described for the Class 6 events. As described I earlier, the fuel handling manipulators and hoists are designed so that the fuel assembly is continuously immersed while in the spent fuel pool. In , addition, the design of storage racks and manipulation facilities in the , spent fuel pool is such that: a 6 6 3.11-22 i e

l a) Fuel at rest is positioned by positive restraints in an eversafe, always subcritical, geometrical array, with no credit for boric acid in the water. l b) Fuel can be manipulated only one assembly at a time. l l c) No configuration of one fuel assembly in racks j l will result in criticality. l t l l ; 2 In summary, those factors which are discussed under Section ! l 3.11.6 regarding remoteness of possibility of fuel handling accidents { within the containment also apply here. -! I i 3.11.7.4 Assumptions Used in the Analysis and Evaluation of Refueling Accident Outside Containment i f The identical assumptions a) through g) of Section 3.11.6 are '

also postulated for calculation of the fuel handling accident outside the containment.

s

i

;                                                      3.11.7.5             Justification for Assumptions j

1 l l The justification for the assumptions are the same as given in j Section 3.11.6. l i l 3.11.7.6 Doses at site Boundary and Total Population Dose (man-rem) I s I l t l The doses at the nearest site boundary from a refueling accident j outside the containment are 3.789 mrem thyroid and 0.763 mrem whole body. , 4 i The total population dose from this accident is 0.164 man-rem whole body l ) i ! j and 0.866 man-rem thyroid. l i i a t b i 3.11-23 1 1

e 3.11.8 Evaluation of Class 8 Events 3.11.8.1 Discussion of Class 8 Events Accidents considered in this class are loss of coolant, steam line br eak, steam generator tube rupture, rod ejection, and ruptures of the waste gas decay tank and the volume control tank. These extremely unlikely accidents are used, with highly conservative assumptions, as the design basis events to establish the performance requirements of engineered ; safety features. For purposes of this environmental report, the accidents j are evaluated with the realistic basis that these engineered safeguards ! will be available and will either prevent the progression of the accident ' or mitigate the consequences. i 3.11.8.2 Description of Class 8 Event - loss of Coolant [ [ A LOCA is defined as the loss of primary system coolant due to y a rupture of a Reactor Coolant System (RCS) pipe or any line connected to - () that system. Leaks or ruptures of a small cross section would cause ex-pulsion of the coolant at a rate which can be accommodated by the charging i pumps. The pumps would maintain an operational water level in the pres- j surizer permitting the operator to execute orderly shutdown. A quantity [ of the coolant, containing fission products normally present in the coolant would be released to the containment. ' Should a break occur beyond the capacity of the charging pumps, depressurization of the RCS causes fluid to flow from the pressurizer to the break resulting in a pressure decrease in the pressurizer. Reactor . I trip occurs when the pressurizer low pressure set point is reached. The Emergency Core Cooling System (ECCS) is actuated when the pressurizer low f pressure and low level set points are reached. Reactor trip and ECCS actuation are also provided by a high containment pressure signal. These countermeasures limit the consequences of the accident in two ways: i O 3.11-24 h l l

a. Reactor trip and borated water injection supplement void formation in causing rapid reduction of the core thermal power to a residual level corresponding to the ,

delayed fission product decay,

b. Injection of borated water ensures sufficient flooding of the core to limit the peak fuel cladding temperature ;

to well below the melting temperature of Zircaloy-4 in addition to limiting average core metal-water reaction [ to substantially less than 1 percent. i Before the reactor trip occurs, the plant is in an equilibrium condition, i.e., the heat generated in the core is being removed via the j secondary system. Subsequently, heat from decay, hot internals,-and the j vessel is transferred to the RCS fluid and then to the secondary system. f The ECCS signal terminates normal feedwater flow to the steam generators by closing the main feedwater line isolation valves and initiates auxili-ary feedwater flow by starting the motor-driven auxiliary feedwater pumps. If off-site power is available, steam may be dumped to the condenser, de-pending on the size of the break. The secondary flow aids in the reduction of Rea: tor Coolant System pressure. If the Reactor Coolant System pressure falls below the setpoint, the passive accumulators inject borated water due to the pressure differential between the accumulators and the reactor cool- L ant loops. t While the ECCS prevents fuel clad melting, as a result of the increase in cladding temperature and the rapid depressurization of the core, some cladding failures may occur in the hottest regions of the core. Some of the volatile fission products contained in the pellet-cladding gap may be released to the containment. These fission products, plus those present in that portion of the primary coolant discharged to the containment, are partially removed from the containment atmosphere by the spray system and f plateout on the containment structures. Some of the remaining fission O - 3.11-25

1 i

                                                                                       -i products in the containment atmosphere will be slowly released to the ex-           ;

O ternal environment through minute Icaks in the containment during the time when the containment pressure is above atmospheric pressure. These minute , i leaks could be expected to be choked by water and water vapor although credit ! I for this was not taken in evaluating releases. 3.11.8.2.1 Discussion of the Remoteness of Possibility of Loss of Coolant : t The rupture of a reactor coolant pipe or a pipe connected to it is not expected to occur because of very careful selection of design, con-struction, operation and quality control requirements. A very strict and j detailed " Quality Assurance Program" is instituted to make sure that the i specific requirements are met during the various stages of design, construc-tion, erection, and fabrication. ! The Reactor Coolant System is designed to withstand the Design Basis Earthquake at the site and assure capability to shutdown and to l maintain the nuclear unit in a safe condition. Pressure-containing O components of the Reactor Coolant System are designed, fabricated, in-spected and tested in conformance with the applicable codes. The design loads for normal operational fatigue and faulted conditions are selected i E by conservatively predicting the type and number of cycles that the plant is expected to experience. Also, essential equipment has been placed in a structure which is capable of withstanding extraordinary natural phenomena, such as tornadoes, flooding conditions, high winds, or other natural phenomena. The materials and components of the Reactor Coolant System are l subjected to thorough nondestructive inspection prior to operation and a ! pre-operational hydro test was performed at 1.25 times the design pressure. i; The unit is also operated under very closely controlled conditions , to ensure that the operating parameters are kept within the limits assumed f i C:) i 3.11-26 i

l () in the design. The reactor pressure vessel is paid particular atten-tion because of the shif t in nil ductility transition temperature i 1 (NDTT) with irradiation. Technical specification limits are imposed on the maximum heatup and cooldown rates to make sure that the vessel wall temperature is above the NDTT whenever the stresses become signifi-cant. The materials of construction were selected for the expected environment and service conditions and are in.accordance with the appropriate code requirements. { It is expected that for pipes of the size, thickness, and material used in the RCS, significant leakage will occur before catastrophic failure. The unit is provided with various means of detecting leakage from the Re-actor Coolant System. The sensitivity of these leak detection systems give reasonable assurance that a small crack will be detected and repaired before it reaches the size that will cause f ailure. 1 1 Furthermore, provisions are made for periodically inspecting, ! () in-situ, all the areas of relatively high stress in order to discover _po-tential problems before significant flaws develop. The inspection pro-cesses vary from component to component and include such inspection tech- , niques as visual inspection, ultrasonic, radiographic and magnetic particle } examinations. This in-service inspection program provides additional assurance of the continuing integrity of the Reactor Coolant System. ' To further demonstrate the adequacy of the Reactor Coolant System, certain abnormal conditions are analyzed in detail in the FSAR. Those credible transients which could. cause pressure surges have been considered in the design and will be limited by the following features: O 3.11-27 l l l l l

4

1) Reactor Protection System trips - i

2) Incorporation of relief and safety valves in the pressurizer and appropriate sizing of the steam side safety and relief valves.

These features insure that the system pressures and temperatures attained under expected modes of plant operation or anticipated system interactions, will be within the design limits giving further assurance that a rupture of the Reactor Coolant System is very remote. Assumptions Used in the Analysis and Evaluation o f Loss-of- ' 3.11.8.2.2 Coolant Accident The analysis for this accident is based on:

1) Only activity in the fuel pellet-clad gap (1.5 percent of core halogen and 1.2 percent of core noble gases) would

() be available for release.

2) Fuel clad perforation ranges from zero for small breaks to a maximum of 70 percent. The fuel rods represented in this 70 percent, however, generate 90 percent of the core power, so that less than 90 percent of the total gap inven-tory would be released.

i

3) Of the fission product activity, which is released from ;

the gap, 25 percent of the halogens and 100 percent of the noble gases are availabic for leakage from the containment. I i

                                                                                                                                  -3           -1

4) The spray efficiency is 5.2 x 10 see for elemental ;

iodine.

5) The containment leak rate is 0.1 percent for the first 24 l 1

hours and 0.045 percent / day for the next 29 days. 1 (k . 3.11-28 l l 1 l

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

b l l 3.11.8.2.3 Justification for Assumptions a) Fission product diffusion through the fuel pellet is a tempera-ture dependent process. Since the reactor has been made sub-critical, fissioning essentially ceases and the pellet temperature begins to drop from the operating value almost immediately. The gap activity represents 1.5 years of opera-l tion. The additional fission product diffusion to the gap j after the accident is negligible. I b) Extensive analyses of the core behavior during a LOCA, based on theoretical and experimental evidence, have been performed. These analyses are reported in the FSAR, supplemented by l l Emergency Core Cooling Performance, September 29, 1971. l c) As used in the model in TID 14844, 25 percent of the released iodine is considered available in the containment atmosphere l after plateout on reactor internals and containment structures and entrainment in the coolant and condensed steam. d) Data presented in the FSAR indicate that little organic iodine is released from the fuel, e) The calculation of the spray effectiveness for iodine removal is based on the drop diffusion model developed by L. F. Paralyf1) The spray drop-size data used in this model are based on drop-size measurements performed by Westinghouse. The effects of liquid phase resistance, steam condensation, i and drop coalescence are accounted for in the model. The i input parameters for the spray evaluation are based on realis-tic estimates of the expected performance of the spray system. j (1)L. F. Parsly, " Design Considerations of Reactor Containment Spray Systems, Part VII", ORNL-TM-2412, Part VII, Oak Ridge National Laboratory. O l 1 3.11-29 ] i

3.11.8.2.4 Doses at Site Boundary and Total Population Dose (man-rem) - [" With the above assumptions the thyroid dose and the whole body dose at the nearest site boundary are 0.399 mrem and 4.280 mrem, respectively. The total population whole body dose is 1.026 man-rem and 10.005 man-rem thyroid. 3.11.8.3 Description of Class 8 Event - Steam Line Break A rupture of a steam line is assumed to include any accident which results in an uncontrolled steam release from a steam generator. ; The release can occur due to a break in a pipe line or due to a valve malfunction. The steam release results in an initial increase in steam flow which decreases during the accident as the steam pressure falls.

i The following systems limit the potential consequences of a steam line break: O 1) Safety Inj ection System. 1

2) The overpower reactor trips (nuclear flux and AT) and i the reactor trip occurring upon actuation of the Safety injection System.

3)- Redundant isolation of the main feedwater lines. Sustained high feedwater flow would cause additional cooldown; thus, l in addition to the normal control action which will close the main feedwater valves, any safety injection signal will rapidly close all feedwater control valves; trip the main feedwater pumps; and close the feedwater pump discharge valves.

4) Trip of the fast-acting steam line isolation valves on high containment pressure signals.

l 6 O 3.11-30

Each steam line has a fast-closing isolation valve and a check valve. These six valves prevent blowdown of more than one steam genera-tor for any break location even if one valve fails to close. For example, for a break upstream of the valves in one line, closure of either the check valve or the isolation valve in that line or the isolation valve in the other lines will prevent blowdown of the other steam generators. If there are no steam generator tube leaks (Class 5), there would be no fission product release to the atmosphere from this accident. With tube leaks, a portion of the equilibrium fission product activity in the secondary system will be released. In addition, some primary coolant with its entrained fission products will be transferred to the secondary system as the reactor is cooled down. The steam is dumped to the condenser, and the noble gases transferred from the primary system would be released through the condenser off-gas system. 3.11.8.3.1 Discussion of Remoteness of Possibility of a Steam Line Break Accident O A steam line break is considered highly unlikely. The steam system valves, fittings and piping are conservatively designed according to USAS B31.1. The piping is a ductile material completely inspected prior to installation. After installation, the entire system was hot , functionally tested prior to fuel loading. This test is designed to uncover any flaws that may exist in the piping, fittings, or valves. In addition to pre-operational tests to insure the steam system integrity during operation, the water in the secondary side of the steam generators is held within chemistry specifications to control deposits and corrosion inside the steam generators and steam lines. The phenomena of stress-corrosion cracking and corrosion fatigue are not generally en-countered unless a specific combination of conditions (i.e., combination ; of susceptible alloy, aggressive environment, stress and time) is present. l The steam system is designed to avoid any critical combination of these conditions. [ 3.11-31 I

                                                                                                              -      l l
                                                                                                                . .l

i With this combination of conservative design, quality control j i and assurance, pre-operational testing, and control over steam chemistry, f the potential for a steam line break is minimal. 3.11.8.3.2 Assumptions Used in the Analysis and Evaluation of Steam Line Break { s The analysis for this accident is based on:

1) An equilibrium radioactivity in the secondary system of ;

0.2 percent equivalent fuel defects with a 20 gpd steam l l generator leakage occurring prior to the accident. t

2) No additional fuel defects or additional releases from ' i; fuel occur due to the accident. j

3) Primary to secondary leakage of 20 gpd occurs for 8 !

hours after the accident. ! O ! i P

4) The break occurs outside the containment.

i

5) The condenser (and thus off-site power) is available !

for steam dump af ter the faulted line is isolated. l h 3.11.8.3.3 Justification for Assumptions j t a) The fuel defect level and steam generator leak rate are de- ! e rived from the operating experience with Westinghouse pres- l i surized water reactors. 1 1 i i b) Fuel rods will not have a minimum DNBR (Departure from Nucleate Boiling Ratio) of less than 1.3, and thus there is ; no clad damage, f i ( 3 3.11-32 i I f

i B i i c) Eight hours are required for an orderly cooldown and depressurization of the primary system. Primary-secondary ; r coolant transfer occurs for this time period. ; 3.11.8.3.4 Doses at Site Boundary and Total Population Dose (man-rem) With the above assumptions the thyroid dose and the whole body dose at the nearest site boundary are 0.015 mrem and 0.002 mrem respectively. The total population whole body dose is 10.005 man-rem j and 0.005 man-rem thyroid. '

                                                                                                  'i 3.11.8.4      Description of class 8 Event - Steam Generator Tube Rupture                                                                    f i

I This accident consists of a complete single tube break in a 1 steam generator. Since the reactor coolant pressure is greater than the j i steam generator shell side pressure, contaminated primary coolcat is j transferred into the secondary system. A portion of this radioactivity l

would be vented to the atmosphere through the condenser off-gas. The sequence of events following a tube rupture is as follows: f

1) The operator will be notified within seconds by the condenser off-gas vent monitor of a radio-activity release.

2) Pressurizer water level will decrease for one to j four minutes before an automatic low pressure .

trip occurs. Seconds later, low pressurizer level will automatically complete the safety j injection actuation signal. i I i i 3.11-33 ,

Automatic actions and cooldown procedures are as follows: a) Automatic boration by high head safety injection pumps. b) Restoration of discernible fluid level in the pressuri- ; zer by safety injection pump operation. c) Operator-controlled reduction of safety injection flow to permit the RCS pressure to decrease below the set-ting of the lowest affected steam generator safety valve. d) Operator-controlled steam dumping to the condenser in order to: (1) reduce the reactor coolant temperature; (2) maintain primary coolant subcooling equivalent to a suitable overpressure; (3) to minimize steam discharge from the affected steam generator. Isolation of the affected steam generator will be achieved by: , a) Identifying the affected s aam generator by observa- - tion of rising liquid level and use of the liquid s sample activity monitor. b) Closing the steamline isolation valve connected to the affected steam generator. c) Securing the auxiliary feedwater flow to that steam generator. d) Blowdown from all steam generators is terminated at the start of accident. 3.11.8.4.1 Discussion of Remoteness of Possibility of Steam Generator Tube Rupture O- The potential for failure of a steam genarator tube is considered d 1 3.11-34 1 i

    . . - - - . - - , , ,      ,       ,   ---  vn,---,,----,.r   wen--- , , -o,--,,,,.+-,-,,n-,,-r,    ,,e,.w ,- ,,--, e s w w. erp~,*v,--,-,,w-vo,-.~w. m--w-y w-+tr- -

g --

I minimal. The steam generator tube is constructed out of a highly ductile O material (SB-163). Further, based on ultimate strength at design tempera-ture, the calculated bursting pressure of a steam generator tube is in

excess of 11,100 psi compared t o the maximum operating differential pres- ,

sure the tube wall sees of about 1530 psi. This margin applies to the longitudinal failure modes. An additional factor of two applies to ultimate pressure strength in the axial direction tending to resist double-ended failure. t It is expected that rupture would be preceeded by small perfora-tions, which could be induced by fretting, corrosion, erosion or fatigue. The activity in the secondary system is continuously monitored via the condenser off-gas discharge monitors, the steam generator liquid monitor, and periodic sampling, and continued unit operation is not permitted if the leakage exceeds Technical Specification limits. As a result, any failure of this nature would be detected before the large safety margin in pressure strength is lost and a rupture develops. j O Finally, in over 400,000 tube years for Westinghouse built steam , generators, there have been no gross tube ruptures. This experience, com- ! bined with stringent quality control requirements in the construction of i the generator tubes and constant monitoring of the secondary system renders ; che likelihood of a steam generator tube rupture highly remote. , 1 3.1; . 8. 4.2 Assumptions Used in the Analysis and Evaluation of Steam I Generator Tube Rupture The analysis of this accident is based on:

1) Activity in primary coolant based on 0.2 percent equivalent fuel defects. The accident will cause no additional fuel damage.

2) 126.000 pounds of primary coolant are carried over to the secondary side.

O , 3.11-35 j r

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

3) An iodine partition factor of 10 ff * "" " in the steam generator.

4) The faulty steam generator is isolated within 30 minutes. ;

i

5) An iodine partition factor of 10 f*****inthe '

condenser. 1 3.11.8.4.3 Justification for Assumptions l a) The 0.2 percent defect level is based on average reactor { operating experience with W PWR Zircaloy fuel. No clad damage is anticipated. i b) The steam generator leakage is based on plant operating experience with W PWR Inconel steam generr. tors. i c) The 126,000 pounds of primary coolant carryover is based on O the amount of time it takes for the primary system pressure to come into equilibrium with the secondary side, d) The iodine partition factors in the steam generator and con-denser are based on the following reference: Styrikovich M. A., Martynova 0. I., Katkovska, K. Ya., Dwbrovskii 1. Ya., Smrinova I. N. " Transfer of Iodine I form Aqueous Solutions to Saturated Vapor", Translated from Atomnaya Energiya, Vol. 17, No. 1, P. 45-49, July, 1964. l ( l e) The 30-minute steam generator isolation time is based on ! estimates on the time it would take for the operator to i identify the faulted steam generator from the instrumenta- l tion provided in the control room, and effect isolation. O : 3.11-36 l 1 l 1 w--. . , - - , , -, - .- __ _ . , _ _ _, )

I 3.11.8.4.4 Doses at Site Boundary and Total Population Dose (man-rem) ~ With the above assumptions the thyroid dose and the whole body dose at the nearest site boundary are <0.001 mrem and 4.042 mrem respec-tively. The total population whole body dose is 0.908 man-rem and <0.005 man-rem thyroid. 3.11.8.5 Description of Class 8 Event - Rod Ejection Accident A highly unlikely rupture of the control rod mechanism housing, creating a full system pressure differential acting on the drive shaft, must be postulated for this accident to occur. The resultant reactor core thermal power excursion is limited by the Doppler reactivity effects of the increased fuel temperature and terminated by a reactor trip actuated by a high neutron flux signal. The operation of a plant with chemical shim control is such that the severity of an ejection accident is inherently limited. Normally there O are only a few control rods in the core at full power. Proper positioning of the rods is monitored by a control room alarm system. There are low and low-low level insertion monitors with visual and audio signals. Opera-ting instructions require normal boration at low level alarm and rapid bora-tion at the low-low alarm. By utilizing the flexibility in the selection of control rod cluster groupings, radial locations, and axial positions as a function of load, the design minimizes the peak fuel and clad tempera-tures for the worst ejected rod. No clad melting occurs as a result of this accident. Activity in the primary coolant is released to the containment. There, sprays and plateout reduce the airborne fission product concentration. Fission products escaping to the external environment do so through minute leaks in the containment structure. I r 3.11-37

3.11.8.5.1 Discussion of Remoteness of Possibility of a Rod Ejection Accident A failure of a control rod mechanism housing sufficient to allow a control rod to be rapidly ejected from the core is considered very remote. Each control rod drive mechanism housing is completely assembled and shop tested at pressures higher than normal operating pressures. On-site, the mechanism housings are individually hydrotested at higher than operating pressures as they are installed, and checked during the hydrotest of the comple ted Reactor coolant System. Stress levels for the mechanism are not affected by antici-pated system transients at power, or by the thermal movement of the coolant loops. The latch mechanism housing and rod travel housing are each a single length of forged type-304 stainless steel. This material exhibits excellent notch toughness at all temperatures that will be encountered. O Finally, periodic inspections of the housings are made during the plant lifetime to insure against de fec ts. Because of the conservative design, the number of pre-operational tests, the material of construction and the periodic inspection program, the potential of a rod ejection accident is considered minimal. 3.11.8.5.2 Assumptions Used in the Analysis and Evaluation of Rod Ejection Accident The analysis for this accident is based on:

1) Activity in primary coolant due to 0.2 percent equivalent fuel defects.

O 3.11-38

2) All activity in the coolant prior to accident is assumed to be released to the containment.

3) Iodine from 50 percent of the coolant is released to con-tainment with a partition factor of 10 Ci/gm water, u, Ci/gm steam

4) The remaining assumptions are the same as for the LOCA.

3.11.8.5.3 Justification for Assumptions i a) The 0.2 percent equivalent fuel defect is based on W PWR reactor operating experience with Zircaloy fuel clad. b) Based on the expected value of the ejected rod worth and be-ginning of life (i.e., low feedback values), approximately 2 percent of the fuel rods fall below a DNBR of 1.3; however, no rods fall below a DNBR expected to cause clad perforation. It is therefore concluded that no rods will suffer clad perfora-tions during the transient. ' c) The amount of coolant is based on the time it takes to reduce the primary system pressure to ambient. Since the coolant activity has been in equilibrium with 0.2 percent fuel defects, ; the additional activity released to the coolant during the time it takes to depressurize the system is minimal. I d) The remaining assumptions are the same as for the LOCA. ; 3.11.8.5.4 Doses at Site Boundary and Total Population Dose (man-rem) With the above assumptions the thyroid dose and the whole body dose at the nearest site boundary are < 0.001 mrem and 0.012 mrem, re-spectively. The total population whole body dose is 0.003 man-rem'and

   < 0.001 man-rem thyroid.

O 3.11-39 I y ,n- - , . , , , - - - -

m l l

                                                                                   .i i

3.11.8.6 Description of Class 8 Event - Waste Gas Decay Tank Rupture The postulated accident is the gross structural failure of a . Waste Gas Decay Tank. I The decay tanks contain the gases vented from the Reactor Cool-ant System, the volume control tank, and the liquid holdup tanks. 3.11.8.6.1 Discussion of the Remoteness of Possibility of a Waste Gas Decay Tank Rupture l Most of the gas received by the Waste Processing System during normal operation is cover gas displaced from the chemical and volume con-trol system and consists mostly of hydrogen and nitrogen. Special pre-cautions are taken throughout the system to prevent in leakage of oxygen- - l carrying gases. Out-leakage from the system is minimized by using Saunders ! diaphragm valves, bellows seals, self-contained pressure regulators and l soft-seated packless valves throughout the radioactive portions of the system. i 1 i i During operation, gas samples are drawn automatically from the i gas decay tanks and automatically analyzed to determine their hydrogen and oxygen content. There should be no significant oxygen content in any of the tanks. An alarm will warn the operator if any sample shows 2 percent or higher by volume of oxygen. Since the components of the waste gas system are not subjected to any high pressures or stresses and they are of 150 psig design, rupture or failure of any of the components is highly unlikely. l i O l 3.11-40 1

                                   - + - ' ' "                               '
 ,,       y w m- +-e       r'++T-'             PF#"'**W"T        #"#'

, 'I Because of the conservative design, extensive quality assurance, the close monitoring and sampling throughout the system, and the fact that the system components are not subjected to high pressure or stresses, an accidental release of waste gases is highly unlikely. : 3.11.8.6.2 Assumptions Used in the Analysis and Evaluation of Waste Gas Decay Tank Rupture The analysis for this accident is based on: i

1) Operation with 0.2 percent equivalent fuel defects.

2) Noble gas release only.

3.11.8.6.3 Justification for Assumptions , r P The equivalent 0.2 percent fuel defect icyc1 is based on W PWR operating experience with Zircaloy Ltel. > 3.11.8.6.4 Doses at Site Boundary and Total Population Dose (man-rem) With the above assumptions the whole body dose at the nearest site boundary is 12.074 mrem. The total population whole body dose is 2.736 man-rem. 3.11.8.7 Description of Class 8 Event - Volume Control Tank Rupture The accident is the sudden and total structural failure of the volume control tank, releasing the contents to the atmosphere. The volume control tank is in the Recctor Coolant System letdown line and contains primary coolant. Its function is to regulate the primary coolant volume as the fluid expands and contracts with temperature changes. It is phy-sically located in the Auxiliary Building. Any leakage is collected by the building sump and pumped to the liquid waste system. The sump and () 3.11-41

sump pit are sufficient to hold che entire tank contents without overflowing to areas outside the building. 3.11.8.7.1 Discussion of Remoteness of Possibility of Volume Control Tank Rupture 1 The volume control tank is designed for an internal pressure of 75 psig. The normal internal operating pressure is approximately 15 psig. Level alarms, pressure relief valves, and automatic bank isolation and valve control assure that safe conditions are maintained during system operation. Since the volume control tank is not subjected to high pressures or stresses and is designed to 75 psig, structural failure of the tank is considered very remote. No similar tanks have failed in W PWR operating experience. 3.11.8.7.2 Assumptions Used in the Analysis and Evaluation of Volume Control Tank Rupture This accident analysis is based on:

1) Plant operation with 0.2 percent equivalent fuel defects

2) Noble gas release only

3) Tank inventory based on noble gas equilibriuta values.

3.11.8.7.3 Justification for Assumptions The 0.2 percent equivalent fuel defect level is based on W PWR _ operating experience with Zircaloy fuel. l 3.11.8.7.4 Doses at Site Boundary and Total Population Dose (man-rem) With the above assumptions the whole body dose at the nearest site (mundary is 3.22 mrem. The total population whole body dose is 0.728 l0 . 3.11-42 i

.- .- . ~ . . . . . . _ - 3.11.9 Conclusions Based on the evaluations of the various postulated accidents and occurrences in Sections 3.11.2 through 3.11.8 and the resultant radiological results as summarized in Table 3.11-2, it is concluded that the environmental impact from these accidents and occurrences are insig-nificant and inconsequential. In fact, the maximum man-rem realistically established as a result of any accident is well within the increment of exposure to the general public corresponding to variations in natural background as discussed in Section 3.6.1.2. 1 O 9 C:) - 3.11-43 l l

TABLE 3.11-1 CLASSIFICATION OF POSTULATED ACCIDENTS AND OCCURRENCES NO. OF DESCRIPIION EXAMPLE (S)- CLASS l 1 Trivial Incidents Small spills , Small leaks inside containment 2 Misc. Small Releases Spills outside Containment Leaks and pipe breaks 3 Radwaste System Failures Equipment failure Serious malfunction or human error 4 Events that release radio- Fuel failures during normal activity operation. Transients outside expected range of variables. 5 Events that release radio- Class 4 & Heat Exchanger Leak activity into secondary system 6 Refueling accidents inside Drop fuel element containment Drop heavy object onto fuel Mechanical malfunction or loss (} 7 Accidents to spent fuel of cooling in transfer tube Drop fuel element outside containment Drop heavy object onto fuel . Drop shielding cask - loss of ' cooling to cask Transportation incident on site 8 Accident initiation events Reactivity transient considered in design-basis Rupture of primary piping evaluation in the Safety Flow decrease - Steamline break Analysis Report 9 Hypothetical sequences of Successive failures of multiple f ailures more severe than barriers normally provided and Class 8 maintained O 3.11-44 l 1

TABLE 3.11-2 O.

SUMMARY

OF DOSES FROM POSTULATED ACCIDENTS AND OCCURRENCES NEAREST SITE BOUNDARY POPULATION DOSE 50-MILE RADIUS THYROID WHOIE BODY THYROID WHOLE BODY EVENT mrem mrem man-rem man-rem Class 2 NA 0.322 NA 0.073 Class 3 NA 1.204 NA 0.274 Class 4 NA NA NA NA Class 5 1.280 0.285 0.290 0.065 e Class 6 0.644 0.129 0.14 6 0.029 Class 7 3.789 0.763 0.866 0.164 Class 8-LOCA 0.399 4.280 <0.005 1.026 SLB 0.015 0.002 <0.005 <0.005 SGTR <0.001 4.042 <0.005 0.908 REA <0.001 0.012 <0.005 0.003 WGDTR NA 12.074 NA 2.736 NA - not applicable O 3.11-45

4.0 ENVIRONMENTAL EFFECTS WilICH CANNOT BE AVOIDED O Construction and operation of Robinson Unit No. 2 has and will continue to have some impact on aesthetics, land and water resources and on the quality of air and water. Efforts have been made to avoid and minimize these environmental effects. Those which cannot be avoided will be discussed in this section. Any effort on the part of man to provide a service or product necessary to maintaining or improving human life standards involves some possibility of impact on the environment. CP&L has attempted to balance the benefits of providing electric power against the risks to the environ-ment in such a way that the risks are minimized using technically and economically feasible systems. In order to implement this policy, CP&L , located II. B. Robinson Unit No. 2 adjacent to Unit No. 1, on an existing CP&L plant site, thereby minimizing an unavoidable environmental effect { of additional land use required by a new site. By locating on an existing site, the plant does not interfere with any existing use of the e environment, nor prevent any reasonably foreseeable beneficial use or enjoyment of the environment. Since the unit uses nuclear fuel as a > I heat soutcc and is on an existing CP&L site, there has been no significant diversion of resources from any existing source. Wherever possible, areas affected by clearing and construction have been replanted with trees and grasses to control erosion, to provide ' new ground cover for wildlife, and to reduce the aesthetic impact. f l As a result of the operation of any nuclear power plant, there l are certain radioactive products which must be disposed of. To minimize .

                                   -                                            l any effects these materials might have on the environment, the unit is      !

equipped with a waste processing system. This system collects radioactive i fluids and these fluids are sampled, analyzed, and processed as required , I and then released only under controlled conditions in accordance with all ! appropriate regulations of 10 CFR 20 and 10 CFR 50, so that effluents will be held as low as practicable. . O I 4.0-1 i

I i P Solid wastes, which consist of waste liquid concentrates, spent resins, j and miscellaneous materials such as paper and glassware, are packaged i and shipped of f-s tcc for disposal at approved sites in accordance with i AEC and U. S. Department of Transportation regulations. { The spent fuel from each fuel cycle will be stored for a time ; necessary to reduce its radioactivity, and then it will be shipped j off-site for reprocessing in specially designed casks meeting all the i AEC and U. S. Department of Transportation regulations. By strictly adhering to these regulations, the environmental impact of these ship-ments will be negligibic. . I f In order to assure that all possible environmental effects ! are minimized, monitoring programs have been established and implemented f to detect any environmental change which might be attributed to the operation of the unit, thereby assuring safe and healthful surroundings j for the area. + Operation of Unit No. 2 will result in an additional heat f discharge to Lake Robinson. However, this additional heat is not l t expected to result in significant changes to the aquatic or terrestrial j environment. l l H. B. Robinson Unit No. 2 was constructed and is being operated [ in compliance with all applicable federal and State of South Carolina regulations designed to protect the environment. All discharges to the ! air and water will conform to these regulations and will meet applicable l quality standards. l l By practicing environmental responsibility such as those measures described above, it is the desire of CP&L to attain the widest range of ; benefits for its customers through harmonious use of the enstronment l vithout risk to health or safety, or other undesirable conseqt.ences. If en-f vironmental effects are detected by the environmental monitoring program or other surveillance methods which show that the regulatory requirements ! O 4.0-2 1

are exceeded, CP&L will take appropriate action to reduce environmental impact to acceptable levels. f I 9 : l 1 I l l 1 l I h 1 4 a 1 1 I s d I i I l il ! l l 4.0-3 !

4 . i

t l 5.0 ALTERNATIVES TO THE NUCLEAR UNIT 5.1 SPECIFIC POWER NEEDS l i Carolina Power & Light Company provides electrical service to its j customers in North and South Carolina. The electrical energy requirements of its customers are doubling every six years compared to the national average of doubling about every ten fears. CP&L's commitment to provide 1 electrical energy to its customers has required an accelerated pace of

providing new electrical generation capability. l 1

The operation of Robinson Unit No. 2 is essential to the ability of Carolina Power & Light Company to meet its current and predicted load } requirements. As of November 1, 1971, CP&L owned and operated seven steam i electric generating plants with a net winter capability of 3,622,000 KW; I four hydroelectric plants with a net winter capability of 211,500 KW; and ; internal combustion generating units with a net winter capability of 560,000 KW; for a total net winter capability of 4,393,500 KW. The Robinson Unit .! O No. 2 provides 700,000 KW of this total electric generating capability. [ The Robinson Unit No. 2 is vitally important to the ability of CP&L and its neighboring power systems to meet the current energy demands of the Virginia-Carolinas territory. The reserve margins of systems serving this territory are smaller than desirable to assure reliable power supply for the territory. As CP&L and its neighboring utilities bring into operation addi- ! tional electric generating units, the vital importance of Unit No. 2 to the territorial power supply will diminish somewhat; however, the unit will con- ; tinue to be an essential resource for the CP&L system. Virginia Electric and Power Company (VEPCO) and Duke Power Company (Duke) each have a large nuclear unit scheduled to become operational in early 1972. The specific l short-term power needs which the Robinson Unit No. 2 will fulfill are graphi-l cally illustrated by looking at CP&L's resources, loads, and reserves during i l the next ten months. Table 5.1-1 shows CP&L's resources, loads, and reserves .! i i by month for the period November 1971 through August 1972, assuming the avail-ability of Robinson Unit No. 2 for the entire period,the availability of i 5.1-1 I J

VEPCO's Surry nuclear Unit No. I and Duke's Oconee nuclear Unit No. 1 at I their rated capacities for the period February 1972 through August 1972 and the availability of VEPCO's Surry Unit No. 2 in August 1972. Even with such assumptions, the CP&L reserves will be only 8.7 percent in January 1972, con-sidering maintenance schedules. The reserve margin during the critical summer months of July and August is 15.8 percent. CP&L considers that it needs approximately 18 percent reserve or the largest unit plus 100 W to provide reliable service to its wholesale and retail customers. This reserve margin is necessary to accommodate the unscheduled outage of its largest generating unit, reduced capability of its other units due to equipment failure, varia-tions in actual load from that forecasted and extreme weather conditions which experience has indicated could result in load increases of as much as 4 percent above that forecast for normal conditions. The importance to CP&L of the availability of the Robinson, Surry, and Oconee nuclear units is to maintain adequate or near adequate reserve except for January 1972 when its reserve margin will be only 8.7 percent. Table 5.1-2 shows CP&L's resources , loads, and reserves for the same ten-month period as shown in Table 5.1-1, assuming that Robinson Unit No. 2 is available for the entire period and the surry and Oconee units are l not placed in service during the period. It will be observed that CP&L's reserves will be only 8.7 percent in January and 3.4 percent in August. Table 5.1-3 shows CP&L's reserves for the same 10-month period as in Tables 5.1-1 and 5.1-2, assuming Robinson Unit No. 2 is not available and the burry and Oconee nuclear units are not placed in service during the period. It will be noted that CP&L will not be able to carry its load in any month of the 10-month period if necessary maintenance of existing units (some of which is for the installation of additional pollution abatement equipment) is undertaken. If necessary maintenance is omitted, CP&L will not be able to carry the load in six of the ten months and will be critically short of reserve margin in the remaining four months. Tables 5.1-1, 5.1-2, and 5.1-3 also assume the availability in June 1972 of a 420 W e fossil unit addition to CP&L's Sutton Plant which is pre-sently 62 percent complete. 5.1-2

i. 1. 1 i i Robinson Unit No. 2 is the largest generating unit on the CP&L system, constituting approximately 16 percent of CP&L's present generating ; capability. In terms of actual electrical energy production, it is even more

i. significant than its relative size would indicate since it is a base load unit.

I During 1972, it is expected to supply 3,810,240 megawatt-hours of electric ! energy or 17.7 percent of the expected system requirements. I 1 I

l. ,i 4

i t I k e 1 h f i !, ) a I l 5 i r I i L f

                                                                                                                                                           ,I i

i n

                                                                                                                                                           .t 9                                                                                                                                                 i

, 5.1-3 ! i ; i

O O O TABLE 5.1-1 CP&L POWER RESOURCES, LOAD, AND RESERVES BY MONTHS WITH ROBINSON NO. 2 IN SERVICE i Limited Term Sales Based on Surry 1 and Oconee 1 in Service by Feb. 1, 1972 and Surry 2 by Aug. 1 1972 i 1971 1972 Nov. Dec. Jan. Feb. Mar. Apr. bbv June Julv Aug. Installed Capacity Hydro 211.5 211.5 211.5 211.5 211.5 211.5 213.5 213.5 213.5 213.5 Fossil 2922.0 2922.0 2922.0 2922.0 2922.0 2922.0 2894.0 3314.0 3314.0 3314.0 i Nuclear 700.0 700.0 700.0 700.0 700.0 700.0 700.0 700.0 700.0 700.0 l IC's 560.0 560.0 560.0 560.0 560.0 560.0 487.0 487.0 487.0 487.0 ! Total Owned Capacity 4393.5 4393.5 4393.5 4393.5 4393.5 4393.5 4294.5 4714.5 4714.5 4714.5 [ Long Term Purchases 213.2 213.2 213.2 213.2 213.2 213.2 2 12.7 212.7 212.7 212.7 Other Purchases & (Sales)

Wateree #2 61.0 61.0 61.0 61.0 61.0 61.0 61.0 61.0 61.0 61.0 SCPSA Reserve Exchange 32.0 32.0 32.0 32.0 32.0 32.0 20.0 20.0 20.0 20.0 ,

Asheville #2 (155.0) (155.0) (155.0) (155.0) (155.0) (155.0) (115.0) (115.0) (115.0) (115.0) Sutton #3 - - - - - - - (140.0) (140.0) (140.0) I AEP 60.0 - - - - - - - - - Limited Term Purch or (Sale) (360.0) (352.0) (342.0) 6 6 6 104 29* 29* 203* Total Power Resources 4244.7' 4192.7 4202.7 4550.7 4550.7 4550.7 4577.2 4782.2 4782.2- 4956.2 t Forecast Peak Load 3289 3535 3818 3600 3480 3200 3400 4000 4130 4279 Reserve 955.7 657.7 384.7 950.7 1070.7 1350.7 1177.2 782.2 652.2 677.2 Percent Reserve 29.1 18.6 10.7 26.4 30.8 42.2 34.6 19.6 15.8 15.8 Sched. Maint. (293) (190) (51) (51) (308). (685) (401) 0 0 0 Reserve 662.7 467.7 333.7 899.7 762.7 665.7 776.2 782.2 652.2 677.2 Percent Reserve 20.1 13.2 8.7 25.0 21.9 20.8 22.8 19.6 15.8 15.8

                        *100 MW APS Purchase from 5/1/72 to 9/1/72 included on VEPCO System in Limited Term Calculation

T . y . li: ;! , ' :t , ; :'

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S n r. 12003 3 1 25 - - 2 2 0 21 57 9 H i p 1 2069 1 635 1 0 0 03 81 . T A 29755 2 1 3 2 2 0 63 N t 2 4 ( ( 4 3 1 ( o W N n o , s i Y ) ) t B t 78 79 a _ i 50005 2 000 0 7 SE n . ) l EC U r 12003 3 1 25 - - 2 2 0 20 841 u - VI a 12069 1 635 4 0 8 22 011 c - RV e M 297 53 2 1 3 2 4 7 34 l ER e 2 4 ( ( 4 3 ( a SE n C ES o R c m N O r - 2 DI ) ) e N d 50005 2 000 0 7 77 73 T 1 A2 n . ) a b 1 2003 3 125 - - 2 2 0 26 115 d 5 , . e 1 2069 1 635 4 0 0 01 551 e - DO y F 29753 2 1 3 2 6 6 (5 t 9 E L B A T AN O LN SN

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~ l 5 y a - t ) e S m i s g ( o - c e n r - a l a r f p a h o s e a S c e v e C s ( x . c . r s y e E h r d t e a t d s & c a a n s h . i e a e r o o i e cr n u e a R c h s v2 s L a w c e r# P e v M u p O r s2 e R k r et P a u a# s e3 m a e . vn 9 c d eoie l a l r sl sT r l a t o P T m r e h ceRl re urAvo P eS et el# tPht P i n d T r e e P r e w o P t e s a et vn R s e d re eec h s r cee SRP S P A M a y o u 'C l d s c raC s uE t l c re t t HFNI g eWSASA i a e ec 0 s n h m t r sr 0 n o t i o o ee 1 I L O L T F RP *

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    ! :11ii     il  J   ,        li1f iI 'lj                                                                                                                       L

O O O I IABLE 5.1-3 CP&L POWER RESOURCES, LOAD, AND RESERVES BY MONTHS WITH ROBINSON NO. 2 HALTED 11/71 - CAPACITY INCLUDED IN ALLOCATIONS L Limited Term Sales Based on Surry and Oconee Units Not in Service 1971 1972 j Nov. Dec. Jan. Feb. Mat. Apr. May June July Aug. Installed Capacity , Hydro 211.5 211.5 211.5 211.5 211.5 211.5 213.5 213.5 213.5 213.5 i Fossil 2922.0 2922.0 2922.0 2922.0 2922.0 2922.0 2894.0 3314.0 3314.0 3314.0 Nuclear - - - - - - - - - - IC's 560.0 560.0 560.0 560.0 560.0 560.0 487.0 487.0 487.0 487.0 Total owned Capacity 3693.5 3693.5 3693.5 3693.5 3693.5 3693.5 3594.5 4014.5 4014.5 4014.5 P' Long Term Purchases 213.2 213.2 213.2 213.2 213.2 213.2 212.7 212.7 212.7 212.7 7 Other Purchases & (Sales) Wateree #2 61.0 61.0 61.0 61.0 61.0 61.0 61.0 61.0 61.0 61.0 I SCPSA Reserve Exchange 32.0 32.0 32.0 32.0 32.0 32.0 20.0 20.0 20.0 20.0 Asheville #2 (155.0) (155.0) (155.0) (155.0) (155.0) (155.0) (115.0) (115.0) (115.0) (115.0) Sutton #3 - - - - - - - (140.0 (140.0) (140.0) AEP 60.0 - - - - - - - - - Limited Term Purch, or (Sale) (360.0) (352.0) (342.0) (342.0) (342.0) (342.0) (253.0) (328.0)* (328.0)* (328.0)* ! Total Power Resources 3544.7 3492.7 3502.7 3502.7 3502.7 3502.7 3520.2 3725.2 3725.2 3725.2 Forecast Peak Load 3289 3535 3818 3600 3480 3200 3400 4000 4130 4279 Reserve (Deficit) 255.7 (42.3) (315.3) (97.3) 22.7 302.7 120.2 (274.8) (404.8) (553.8) :' Percent Reserve (Deficit) 7.8 (1.2) (8.3) (2.7) 0.7 9.5 3.5 (6.9) (9.8) (12.9) Sched. Maint. (293) . (190) (51) (51) (308) (685) (401) 0 0 0 Reserve (Deficit) (37.3) (232.3) (366.3) (148.3) (285.3) (382.3) (280.8) (274.8) (404.8) (553.8) Percent Reserve (Deficit) (1.1) (6.6) (9.6) (4.1) (8.2) (11.9) (8.3) (6.9) (9.8) (12.9)

                      *100 MW APS Purchase from 5/1/72 to 9/1/72 included on VEPCO System in Limited Term Calculation                                                                                                                                       ;
  . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ ~ . _ . _ . . _ , . _                                  _ . _ . . _ . .         _ _. _ ._... _ ._. .. _ ... .._ _ __ _ _ ..,_. .. _ _ ,...__ _ _ _._ _. _ .~. -...._. _

5.2 IMPORTING POWER O Carolina Power & Light Company and the neighboring utilities with which CP&L is interconnected are in similar power supply situations. Each utility is confronted with long lead times for construction of generating facilities, high rates of load growth and a need to increase reserve capa-city margins. The operation of Robinson Unit No. 2 was planned to provide export power to neighboring utilities in 1970 and 1971 while they were bringing into operation other large nuclear units. The importance of the Robinson Unit No. 2 to CP&L's neighboring utilities is demonstrated in Section 5.1 for the period November, 1971,through August, 1972, especially if the other large nuclear units are not available as scheduled. The reliance of neighboring utilities upon the operation of Robinson Unit No. 2 and CP&L's ability to export power to them is illus-trated by looking at the resources, loads, and reserves for CP&L and its neighboring utilities over the next year. Tables 5.2-1, 5.2-2, and 5.2-3 show the resources, loads and reserves for CP&L, VEPCO, Duke and South Carolina Electric & Gas systems for Winter 1971-1972 and Sumer 1972. under the same set of assumptions as are shown in Tables 5.1-1, 5.1-2, and 5.1-3 for the CP6.L system. With Robinson Unit No. 2 available for the entire period, Surry Nuclear Unit No. 1 and Oconee Nuclear Unit No. I available in February, 1972, and Surry Nuclear Unit No. 2 available in August, 1972, the territorial reserves will be 17.4 percent for Winter 1971-1972 and 17.2 percent for Summer 1972. With the Robinson Unit No. 2 available for the full period and the Surry and Oconee Units unavailable, the territorial reserves are 17.4 percent for Winter 1971-1972 and only 4.3 percent for Summer 197;2. With none of the three nuclear units available, the territorial reserves are 13.2 percent for Winter 1971-1972 and less than 1 percent for Summer 1972. With the critically low reserves in the Virginia-Carolinas territory, it is apparent that purchase power is not available to CP&L from neighboring utilities on a firm basis. In fact, the other companies in the territory are dependent upon energy sales from CP&L to support 5.2-1 s

- r l

l I i l 1 !- their system reliability through Winter 1971-1972 and, if the Oconee and Surry nuclear units are not placed in cervice as scheduled, for such a period of time as it takes to place those units in service. The operation , I of Robinson Unit No. 2 is essential, therefore, not only to the CP&L system but also to the limited energy resources of the Virginia-Carolinas territory, f i . ! The neighboring utilities are not planning to install extra l l generating capacity in the quantities required to allow CP&L to import l the necessary power in years after 1972. Interchanges of large blocks of ! power on a firm basis will not be possible between CP&L and its neighbors. l The primary function of the interconnections established with the neigh-j boring utilities aside from the purchase and sale of small blocks of i j power is to provide emergency assistance in the event of equipment failure. f e i 'I 4 i O i I i j t I h 4 J i 2 4 O 5.2-2 i i i . - - _ . _ _ _ _ _ . _ . . _ _ _ _ _ . _ _ _ _

- .. . ~. . . . . . -. _. .- . . . . - . . - -. .-. . - . . . . - .- -- i O TABLE 5.2-1 CP&L, DUKE, SCE&G, & VEPCO POWER RESOURCES. TERRITORIAL LOADS. AND RESERVES P With Robinson No. 2 In Service With Oconee No. 1 and Surry No. 1 & 2 In Service For Summer 1972 1971-72 Winter Load - MW 16,873 ,. Capacity - FM 19,802 Reserve - MW 2,929 Reserve - 7. 17.4 O 1972 Summer Load - MW 19,951 < Capacity - MW 23,380 Rcserve - FM 3,429 Reserve - 7. 17.2

                                                                                                                                                         \
                               .                                                                                                                          i O

5.2-3

r. O TABLE 5.2-2 CP&L, DUKE, SCE&G, & VEPCO POWER RESOURCES, TERRITORIAL LOADS, AND RESERVES With Robinson No. 2 In Service With Oconee No. 1 and Surry No. 1 & 2 Not In Service For Summer 1972 1971-72 Winter Load - MW 16,873 Capacity - MW 19,802 Reserve - MW 2,929 Reserve - % 17.4 . O 1972 Summer i Load - MW 19,951 Capacity - MW 20,800 Reserve - MW 849 Reserve - % 4.3 l l 1 I l 5.2-4 i i

i O TABLE 5.2-3 CP&L, DUKE, SCE6G, & VEPCO POWER RESOURCES, TERRITORIAL LOADS , AND RESERVES With Robinson No. 211alted 11/71 With Oconee No. 1 and Surry No. 1&2 Not In Service For Summer 1972 1971-72 Winter Load - MW 16,873 Capacity - MW 19,102 Reserve - FM 2,229 Reserve - % 13.2

O 1972 Summer Load - MW 19,951 Capacity - MW 20,100 Reserve - MW 149 Reserve - % J0. 7 i

l I l 1 5.2-5 . l j l

h y 5.3 ALTERNATE MEANS OF POWER GENERATION Carolina Power & Light Company is continuously conducting planning studies to determine the amount of additional generation required to meet projected load demands. Previous planning studies in 1965 indicated that a base load unit of approximately 700,000 KW would be required on the CP&L system to be operational in 1970. Having identified the amount of power needed, CP&L evaluated various generating means for meeting this need. Four means of generation were con-sidered; hydroelectric, internal combustion, fossil / steam, and nuclear / steam. The first means, hydroelectric, was ruled out as there were no sites having sufficient flow for plants of the size required. The second generation scheme, internal combustion turbines, was ruled , out due to the size limit of this means of generation, the high cost per (} kilowatt-hour of generation, and they are not designed for base load operation. i The types of fuel available on the CP&L system for steam electric units are: coal, oil, and nuclear. Production costs and capital investment cost studies were performed to aid in the determination of the type of steam electric plant to be constructed at the site. The results of studies which projected the operation of the CP&L system for a number of years into the future indicated an economical advantage in favor of building nuclear units as compared to fossil units. Factors which strongly influenced these studies were the high cost and uncertainty of availability of fossil fuels. For these reasons, CP&L elected to construct a nuclear unit at the Robinson Plant. I 5.3-1

5.4 ALTERNATE SITES , (:) : Site selection for a steam electric plant begins with load pro-jections which show the amount of additional power required during the next decade,and which indicate where and when the additional power will be needed. Once the need for additional generation is established, selec-2 tion of a site for the generating facility proceeds. Site selection involves an analysis and optimization of many factors such as availability. of adequate condenser cooling water, population density, location of schools and churches, proximity of parks and recreation areas, wildlife refuges, impact on historical monuments and areas of historical interest,- effect on airports, other industries, availability of adequate transporta-tion facilities, cost of developing the site, local geology, effect of potential sources of pollution in the watershed, transmission requirements, ; and other environmental impact. Generally, when the alternative is avail- ) abic, the impact of a new facility can be minimized by the use of an exist-ing site instead of a new site.

O The decision by CP&L in 1965 to expand an existing generating site rather than develop a new plant site is an example of this minimiza-tion of environmental impact. The selection of the Robinson site permitted i CP&L to utilize an approved cooling water system and land already dedicated to the generation of cicetric energy. The plant area had been cleared for future expansion during the construction of Robinson Unit No. 1 in the late 1950's. Except for the physical erection and resulting visual effect J of additional structures in the plant area, the only alteration of the 1andscape with the construction of Robinson Unit No.2 was an extension of ) the cooling water discharge canal from a point approximately 1.2 miles l above the plant to a point 4.2 miles above the plant. Extension of the canal was along the lake shore on land already owned by CP&L and required the clearing of only a small amount of additional land. Choosing any other site would have necessitated the building of a new cooling facility, either a cooling lake or a cooling tower. Such a choice would have had a larger impact on the environment than the decision O 1 5.4-1

i to utilize a site already dedicated to the generation of electrical energy. Load studies which provided the basis for CP&L's 1965 decision on a new generating facility showed a need for additional capacity in'the central or south-central part of the system. Two existing CP&L plants satisfied this geographic requirement. The Robinson Plant, however, was the only one of the two existing plants which could accommodate a 700 FMe instal- l 1ation without extensive modifications to the then existing cooling water systems. i O : O 5.4-2

5.5 COOLING WATER ALTERNATIVES O Operation of Robinson Unit No. 2 requires approximately 1070 cfs of cooling water which is elevated in temperature by about 18"F as it passes ' through the plant condensers. Aside from the existing cooling lake, wet cooling towers provided the only workable alternative for the dissipation of this heat. Dry cooling towers were not feasible either technically or I cconomically, and stream flows in Black Creek are not sufficient for once l through cooling. ' Wet cooling towers, like cooling lakes, dissipate heat through the process of evaporation. As the water evaporates, heat is removed at the rate of about 1,000 Btu /lb of water vaporized. Most of this heat is taken from the water that remains, thereby lowering its temperature. Wet cooling towers, in addition to adding substantially to the , costs of the unit, would have created environmental impacts which on balance would have been greater than those associated with the use of Lake Robinson as a cooling facility. Towers would have created a large visual structure which would have detracted from the aesthetic appearance of the plant, would , have increased consumptive water losses, would have increased the incidents of fogging and would not have substantially reduced the land clearing require-ments. 1 Either closed cycle towers or open cycle towers could have been installed to serve Robinson Unit No. 2; however, the added expenditures required for construction and operation of the towers were not considered , appropriate in view of the already existing Lake Robinson which was designed, , i approved by the state regulatory agencies and constructed to serve as.a heat dissipation facility and which, from experience, had shown the lake to be an efficient and economical method of dissipating heat. While towers and other methods of cooling are suitable at some locations, the use of Lake Robinson as a cooling facility for Unit No. 2 provided the most reason-able method of dissipating the waste heat. ! 5.5-1 i

l 6.0 SHORT-TERM USES VERSUS LONG-TERM PRODUCTIVITY O The ability of man to harness the energy resources of the earth has been an essential component of man's ability to survive and develop socially. Electrical energy is a key factor in providing food products, sewage treatment, the manufacture of goods, numerous physical comforts and necessities, and it is vital to the health and welfare of the nation. With the development of our modern society, electricity has advanced from a novel luxury to an essential requirement for the innumerable necessary services and products demanded by our present civilization. Electricity has become essential to the health, welfare, safety and economy of the residents of the area served and the orgcnization entrusted to provide the residents with electrical energy must assure an adequate supply of elec-tricity. Electric power requirements in this country have been doubling every ten years. CP&L customer requirements for power have doubled in the past six years, and further expansion is expected to continue in much the same pattern. In order to provide the residents of CP&L's service area with the electricity necessary to meet this growth, it was necessary to build a power plant the size of H. B. Robinson Unit No. 2. CP&L is aware of its 4 responsibility to provide electricity to its customers in a manner con-sistent with responsible environmental practices. As described in various parts of this report, detailed consideration was given to the different environmental aspects of the plant in making decisions concerning design, construction and operation of the plant. The short-term use of the environment to produce electricity for ; our immediate requirements must be evaluated with respect to the enhance-ment of long-term productivity and any adverse environmental effects which might be realized by future generations. Considered in this respect, the nuclear unit now in operation at the Robinson Plant is compatible with the environment. The resources which must be diverted from the earth's environment to operate the nuclear power plant are small. This consump-tion of natural resources is an important consideration when attempting 6.0-1 1 - __ _ .____ - ._____. ._ . ._. _ ___ __.._-- _. _ . _ ., _ _._. _ .,_. _ ,_ ,,__ _ ......, ,_-- _ .., ,

O to evaluate the quality of environment we are creating or leaving for future generations. In evaluating the short-term use of the environment, it is also important to consider the fact that the electricity being produced will be used to facilitate social progress and technological developments that will aid in protecting our environment. At this stage in our technology, even with nuclear power and its very low radioactive release concepts, there does appear to be some possible slight but inevitable, short-term impacts on the environment. These impacts are associated with the basic principle of steam electric plants, the need to provide cooling water and the resultant heating of the air and water. These short-term effects have been minimized, as explained in other sections of this report. Any environmental impact associated with the short-term use of the land is expected to be the least amount practicable and then must be evaluated relative to the benefits derived from use of the electricity pro-duced. O The short-term effects resulting from construction and operation of the plant will result in no cumulative adverse effects, and there is no reason why af ter the plant is decommissioned, the environment could not be returned to its original state of existence prior to the nuclear unit, with the possibic exception of a very small part of the site. Before the lake was created, the land the site is on was mostly idle scrub land. Less than 10 percent of the land was devoted to agricultural production, and possessed little or no recreational value. Construction of Lake Robinson created a large recreational attraction which, at the end of the plant's life, could be left intact for recreational purposes, or, if desired, the dam could be removed and the area could be returned to its original environmental condition, with no remaining adverse effects on its long-term productivity. O l 6.0-2

__ , . - . - . - . - . - - _ _- -. .~ _ - .- _. _ . - . . - 1 The operation of the H. B. Robinson Unit No. 2 will not curtail the range of beneficial short-term uses of the environment. The unit will result in incicesed productivity which will actually enhance long-term productivity for future generations. If future generations elect to con-vert the lake area back to terrestrial uses, this can be done over a period of time and the lake area restored to essentially its natural state.

O 1

l i O 6.0-3 l J

7.0 IRREVERSIBLE AND IRRETRIEVABLE COMMITMENTS OF NATURAL RESOURCES O 1 The construction and the present operation of the H. B. Robinson Unit No. 2 necessarily involves the commitment and use of a certain amount of natural resources. Only man has the unique ability to alter the environ-ment on a large scale. With this ability, however, comes the responsibility of using the environment in a manner consistent with protecting and pre- 7 serving the environment to the fullest extent practicable while advancing the standard of living of mankind. With respect to this responsibility, CP&L is fulfilling its responsibility to supply electricity to its customers by the methods which minimize the environmental impact. Considering the many benefits to society of electric power, and the small diversion or use of natural resources by the plant, the resulting cost-benefit ratio is very favorable. In terms of the necessary benefits provided by electric power, there is no other available alternative which has so little impact on the environment. In terms of resources which are consumed, converted, or diverted for temporary use, the following commitments are considered: 4

1) Land ,

2) Water (this is only a partial commitment, or diversion, since it is not consumed but only used briefly and returned in essentially its original condition)

3) Materials of Construction

4) Fuel (Uranium)

5) Human Resources During the life of the plant, the immediate land area occupied by the plant and its structures cannot be used for other purposes, although the cooling lake has been and will continue to be used for recreational purposes. At the end of the useful life of the plant, there is no intrinsic reason why the land and water use could not be returned to the full range of uses prior to plant construction, since the land, air, and water quality will not be altered by the plant's operation. Upon decommissioning the O

7.0-1

unit, it may be necessary to restrict the use of a small portion of the plant site. It should be pointed out here that the plant is located on a site which was in existence before the nuclear plant was built and that con-struction and operation of the nuclear plant did not require acquisition ' of any new land resources. The water used for cooling the plant condensers is drawn from Lake Robinson which was created for the purpose of cooling a. power facility some ten years before the nuclear plant was brought into operation. A number of recreational activities are now enjoyed on the lake and at the end of the plant's useful life, there should be no curtailment of the full range of water usage. The materials used in the construction of the plant could, for the most part, be recycled or reused if necessary. However, these materials . should probably be considered an irreversible commitment although if it be-came necessary for future use, some of the materials could be reclaimed. The fuel consumed by the operation of the unit will be an irre-trievable use of a resource. However, to simply state it is irretrievable does not give a full picture. The use of nuclear fuel (uranium) affords l i an opportunity to conserve our fossil reserves for future generations and also to utilize them for more preferred usage. This is made possible be-cause using uranium as an energy source does not establish a competitive situation, since uranium is not used or required in significant amounts as , a resource in other industry or operations necessary for maintaining our modern society. This is in contrast to the depletion of fossil type re- ! sources which are required in many other essential industries and operations. Thus, while the nuclear fuel cannot be recovered in its original form, its depletion will not deprive other activities of essential resources, as does depletion of fossil resources. In addition, as uranium is consumed, other valuable materials are produced, including additional fuel (plutonium) l which will be used in the breeder reactors expected to be in operation in the not too distant future. l O 7.0-2 l i i f

 -...-.....-m           _ . . _ . , . . . . .         __      , . , _ . . . . ,     . , , , _ _ . . . , _ _ . . . _ , . _ . . , . . . . ., .._..,_,....,_...,,m . ,y .-

As far as uranium is concerned, there were 204,000 tons of U 0 38 reserves available (at $8,00 per pound) on January 1,1970, and 243,000 tons as of December 31, 1970.(1, For the reserves of the free world pro-ducible at $10.00 per pound, there was an estimated total of 700,000 short tons at the end of 1969, of which an estimated 250,000 tons are estimated to be in the U. S.( ) The cumulative requirements for U 03 8 '" #** #8 I"

United States are expected to reach 212,000 short tons by 1980 and 450,000 short tons by 1985. (3) By the mid 1980's commercial breeder reactors are expected to come onto the scene.

In summary, there appears to be a more than abundant supply of nuclear fuel available for the unit during its useful life, without depleting resources necessary for other-facets of our society. In the consideration of human resources as an irreversible re-source, the benefit from the human effort expended to design and construct the plant must be evaluated relative to the benefits to society derived from the electricity now being produced. Considered in terms of the necessity O- of availability of electricity for normal living conditions, and the instru-mental part electricity plays in aiding social and technical progress, the effort to design and build the plant is a good investment in the future of the area being served by the plant. By seeking to design for a compatible balance between the popu-lation and the resources committed to previde them with the energy supplies necessary to achieve and/or maintain high standards of living, CP&L has achieved the production of electricity for its customers in a manner which does not adversely affect the environment in terms of irreversible and/or irretrievable commitment of resources. ( ) Annual Report to Congress of the USAEC, for 1971. ( ) Major Activities in the Atomic Energy Programs, Jan-Dec 1969. USAEC, Jan, 1970.

     )Op. Cit. USAEC , Jan. ,1970.

7.0-3 a

l l 8.0 COST / BENEFIT ANALYSIS OF THE NUCLEAR FACILITY Carolina Power & Light Company has been an important participant in the social and economic development of the area which it has served 1 for more than 63 years. In more recent years the Company's increasing l l' commitment to environmental concerns has been reflected in numerous decisions, many of which have reached fruition in the Robinson Unit No. I 2 and in subsequent major decisions. In recognizing its obligations to society to supply not only the electrical power required for public health, safety, and comfort, but also a consideration of enhancing the overall quality of life of its customers through responsible environmen-tal management , CP&L has examined ways and means whereby its major decisions on generation capacity could provide additional benefits other than economic. Two such decisions affecting the Robinson Plant were made almost 20 years ago:

1. The recognition that additional generation capacity would be needed in the future and that a cooling lake could serve a dual benefit to society - power plant cooling and a new recreational facility. This recognition resulted in the commitment to build Lake Robinson. The wide public acceptance and high degree of utilization by the public of Lake Robinson encouraged the Company to build similar lakes as a part of the generating facility at two other sites. The utilization and acceptance by the public of these facilities has also confimed the wisdom of these decisions.

2. During the same decade the Company decided that nuclear power should play an important role in meeting the area's requirements for electrical power with minimum impact upon the natural environment. This decision was implemented through participation in the Carolinas-Virginia Nuclear Power Associates in the development, construction, and operation of one of the first privately financed nuclear power projects.

O 8.0-1

  . . . - . . - . - . . - - . . . - ~ - - - . - -

t i . The commitment of the H. B. Robinson Nuclear Unit in early 1966 constituted a culmination of these two major long-range policies, and CP&L is pleased to have this opportunity to present the benefits and costs of this important project. 'l b O 4 Y D O 8.0-2 - T l

8.1 CENERAL CONSIDERATIONS O As a result of the recent U.S. Court of Appeals decision in the Calvert Cliffs case, emphasis has been placed on the evaluation of alter-natives for power generation using the cost / benefit approach. This approach has been developed by economists as a tool for governmental decision making where proposed projects can be compared on the basis of the dollar benefit per dollar cost. It should be understood that (1) various philosophies and approaches have been applied in the cost / benefit problems encountered to date so that no real uniformity exists in the techniques applied by various individuals in specific cases, and (2) a formalized cost / benefit technique has not been applied extensively in the past to the decisions relative to power plants and their envirormiental impact. However, most of the more important factors were weighed in the decision-making process. In view of the existence of some diversity in approach, the following discussion is provided to define the underlying philosophy and logic of the cost / benefit analysis presented in this report. 8.1.1 Multi-Dimensional Cost / Benefit Approach In the past, " costs" and " benefits" have been placed in mone-tary terms whenever possible, and a ratio of benefit to cost (or cost to benefit) derived on a dimensionless basis of dollars cost to dollars l benefit. Alternatives could then be ranked on the basis of the dimen- ) sionicas ratio. Although this approach is the least cumbersome to use l 1 from the standpoint of comparative ranking, it cannot realistically be applied in cases where the input data is subjective and not readily ; quantified. For example, one would like to present aesthetic benefit ; or cost in quantitative or monetary terms but would find that any two I observers would have quite diverse views on the aesthetic pleasantness or obtrusiveness of a given structure. 1 The approach used in this report is to quantify costs and benefits where possible but to present a range of values or value i O 8.1- 1 i

judgments where objective analysis is not practical. Moreover, these cost I () and benefit statements represent an aggregate in multi-dimensional form. That is, some quantities are in dollars while others are in quantities and qualitative descriptions more applicable to measurement in the er.- vironmental and social spheres. Furthermore, the " costs" and ' benefits" as defined herein are defined on a broad scope. The apparent philosophy of the Court of Appeals decision and later Atomic Energy Commission guidelines appears to be that costs in terms of environmental effects be compared against the benefits to society of a given project or alternative. In the context of this report it is assumed that costs and benefits can be realized in three distinct areas:

1. Environmental Effects

2. Social Effects

3. Economic Effects

() It is the combined social, environmental and economic costs that are compared with the combined social, environmental, and economic benefits. For example, considering plant siting, typical costs might be displace-ment of wildlife or forest (environmental), displacing loca1 agricultural pursuits (economic), or encroachment on historical sites (social); some benefits might include reduction in air pollutants (en.vironmental) , broadening of the tax base locally (economic), or er.hancement of recre-ational areas (social). 8.1.2 Format and Scope The cost / benefit analysis is a tool for decision making. It allows one to weigh factors comparatively between alternatives before the decision is reached. Ideally, the process occurs in matrix form for several decision points in the planning, design, siting, and con-struction of the project. The decision-nmking process occurs at numerous O 8.1-2

t

t i points in the chronology of the project with each decision affecting , those that follow. In addition, some decisions previously made need to ! be reviewed in terms of the results of later decisions or inputs to those decisions. While these feedback loops cannot be ignored, they are usually economically costly and somewhat unwieldly mathematically, i Figure 8.1-1 illustrates the decision-making process in a generalized approach for a power generation project and presents the ! logic followed throughout the remainder of this discussion. Six ele-ments are defined as the primary model or decision points in the analysis: , Establishing energy requirements and energy source, selection of power plant type and size, selection of site, selection of cooling system, selection of waste systems, and selection of transmission method and route. t While, in general, a matrix of alternatives can be drawn so ; that each alternative in the six decision points can be simultaneously evaluated in a way that assesses interactions between and among alter-natives using mathematical modeling techniques, the approach has been simplified for this report. The simplification is a linearization of cost / benefit analysis with one analysis being performed for each chron-ological decision point. This simplification is included for two reasons: (1) The limited time available for the preparation and analysis of this report, and (2) the fact that much of the decision making for the H. B. I Robinson Unit No. 2 is history. i The weak point in the cost / benefit approach is not the logic but the availability of realistic input data on many of the parameters. Although energy requirements, hardware costs, and economic considerations are relatively easy to predict, biological data, social costs and bene-fits, and the more subjective data are less reliabic. The H. B. Robinson Unit No. 2 has been built and is operational. Most of the decisions have been made with regard to need, siting, cooling O . 8.1-3 l I

system and so on, and these are traced by heavy lines on Figure 8.1-1. O The coments which follow attempt to sumarize the reasons for past decisions and to point out wherever possible the costs and benefits. 1 I t b f h r h I O , 1 I l i I I 1 I 1 l 2 l J l t O 8.1-4

I 8.2 SELECTION OF ENERGY SOURCE Technological man, or post-industrial man as he is sometimes called, has increased his standard of living remarkably in the twentieth century. He has largely done this by effectively harnessing energy and making it perform useful work or provide useful heat through various l machines or energy converters. The energy demand per capita has increased i f rom an estimated 12,000 kilocalories per day in primitive. agriculture societies to 70,000 kilocalories per day in the mid-nineteenth century .j and, finally, to 230,000 kilocalories per day in 1970 in the United States. [ In the area served by Carolina Power & Light Company increas- 1 ing quantities of energy are required to keep pace with rising production l I of farm and factory, improved housing for middle and low income families, ! increased population influx to this area, and increased mobility of society. ; Electrical energy use has been increasing at nearly twice the rate of in-crease for energy use as a whole. An examination of the cost / benefit . relationships of the use of centrally generated electricity as opposed ( to numerous, individual, point energy sources reveals the reason for society's emphasis on electricity. ; 8.2.1 Environmental Costs and Benefits , t Space heating, process heating, transportation, and electric power are the major uses of energy in this area. All of these uses except electric power require the conversion of raw energy to useful energy at the point of use. For example, coal, oil, natural gas and ; wood are burned in homes to provide space heating. Each of these pollute the air in an uncontrolled manner with regard to both quantity and geo-graphical distribution since no air pollution control equipment is required on individual units. In addition, both primary and secondary waste heat is discharged to the environment. Transportation systems l 1 often pollute the air to an even greater extent because of their high index of pollution coupled with a low delivered efficiency which requires more fuel per unit of useful work. 8.2-1

1 1 I i Electric power is a more efficient means of converting raw energy () I to useful energy than most point source conversion systems with an overall { efficiency advantage of 15 to 20 percent. Thus, the Robinson Unit No. 2 i 2 has provided a raw energy savings of 10 Bru/yr. In addition, fuel, par-t2cularly liquid and gaseous hydrocarbons, are becoming more difficult to find. Because nuclear fuel is used for Robinson Unit No. 2, this plant , reduces society's requirements for oil and gas resources by approximately 35 billion cubic feet of gas per year or by approximately 350 million gallons of oil per year. l l l The transmission systems for electric power have some environmental ; costs associated with clearing of right of ways, construction of transmission lines and substations, and visual impact of structures. It is important to , realize, however, that no storage space or storage facilities are required

                                                                                                                           ,i at the point of use.                            Energy systems converting raw energy at the point of use generally involve the allocation of storage space :ad facilities each having adverse environmental impact and attendant safety problems, i

(k Noise abatement in cities also supports the increasing rate of electrical power in the energy use pattern. The noise problem always ac-i companies the conversion of fossil energy to useful work. The nuclear-steam power plant presents a manageable problem in this regard; the other ! small conversion systems do not. l

1 8.2.2 Social Costs and Benefits ,

Among the more important social benefits accruing to the citizens in the area served by the Robinson Plant are:

1. A more f avorable environment in terms of public health, safety, and comfort.

2. The development of a modern, technologically oriented group of design, construction, operating, and management employees.

O 8.2-2 e

As an integral part of the Robinson Unit No. 2, CP&L coc:menced a ; program of staff upgrading through extensive training courses for existing personnel. In addition, the staff was expanded through the acquisition of ; acknowledged experts in various fields of scientific training. The new staff has been of great service to the community through participation in i civic affairs and through their contribution in helping the people of local communities to develop scientific understanding by participating in local ! forums and other educational programs, i i CP&L constructed one of the first nuclear plant information centers in the nation. More than 5,000 people, including students from primary and j secondary schools, have visited the Robinson Information Center. The social benefit to be gained by stimulating the imagination and initiative at the formative stage of even one of these students cannot be overemphasized. In ! i addition to the Information Center project, CP&L has worked with the local universities to develop research programs in science and engineering. ! The introduction of the Robinson Unit No. 2 has had a social benefit in that plant construction provided employment for over 500 skilled j workers and current plant operating personnel number over 50 highly skilled technicians and professional personnel. In addition, the power produced by g ! the plant should be further leverage for the labor market by creating new ; jobs in other industries. Also, the continuing need to meet AEC regulatory requirements has provided full employment for at least 20 new professional ; employees on the CP&L staff. 8.2.3 Economic Costs and Benefits The H. B. Robinson Unit No. 2 was one of the first large nuclear l projects in the U. S. Since CP&L had been involved in the Carolinas-Virginia Nuclear Power Association for several years, they were familiar with i technical f easibility of nuclear power as a method of generating electrical f energy in a large power plant and were aware of the future role which nuclear energy would play in the power industry. Based on this insight and the O ! 1 8.2-3 l

b economic and environmental advantages offered by nuclear power, a nuclear

      )                unit was selected for the H. B. Robinson site.                  The economic advantage to     l 5

the customer in the service area was apparent in 1965 from conditions pre- j valling at that time which included the availability of fossil fuel at i 26 cents /million Etu. The energy crisis which occurred in the past two l years has pushed the cost of fossil fuel far above the 1965 value and has resulted in even greater benefits accruing because of the nuclear project , than were originally contemplated. While the capital cost of a new plant l is higher than for a fossil plant, nuclear fuel costs are much lower and j 5 far less subject to inflationary trends. i On a local basis, electrical generating plants are, in general, ; an economic benefit too. Tax bases for local areas are expanded after a ! p] ant is in operation and often new industries are spawned by the influx ; L of dollars, people, and other industries in the locale of the plant. . In general, the electrical energy source alternative has a clear ; advantage over other energy sources from the cost / benefit standpoint. [ i 8.2.4 Establishing Enernv Supply and Demand - [ Having accepted society's decision to demand an increasing amount of electrical energy, CP&L is confronted with the decision to define, by suitable forecasting methods, the energy needs of its customers and then ! to choose from among several alternatives how it should go about filling [ these needs. As indicated on Figure 8.1-1, these alternatives are: I t f 1

1. To ignore the need and not provide the electrical power.

2. To inport or purchase the power from other producers in or near the area where the need exists.

3. To expand the presently available operating units of the Company. l 1

4 To construct new generating units. 1 l l 8.2-4 1 l

Of course, the first alternative is unacceptable. Utilities are obligated morally, legally, and economically to respond to customer demands for power. One can hardly imagine the profound effects on our whole techno-logical society's structure if adequate power were not available on demand to keep our public health and safety systems, our homes, our communications, our industrial processes, and our transportation systems functioning. - The second alternative is a somewhat more realistic alternative , t and is often employed by utilities on a temporary basis to fill power demands. To understand this one must review the electricity supply-demand situation in the Carolinas-Virginia area. Carolina Power & Light Company serves customers in the North and South Carolina area and shares the territorial load network with Virginia Electric and Power Company (VEPCO), South Carolina Electric & Gas Company, and Duke Power Company. In 1965, when the Robinson Unit No. 2 nuclear steam generating plant was conceived, a projection of the 1970 energy use j pattern for the Carolina Power & Light Company customers was predicted. l O The present experience with power demand bears out these longer term pre- l t dictions. As shown in Section 5.1, the present power reserves even with the Robinson Unit No. 2 in operation are below the Company's established [ adequate reserves requirements. Furthermore, the supply of power from other utilities in the Carolinas-Virginia area is also limited as indicated by the low total power reserves for all the utilities in the area. As a , consequence of this situation, the possibility for purchase of power by CP&L on a long-term basis was not a practical alternative to meet the needs of its customers. ! The third alternative, expansion of presently operating units, was also evaluated as a technically, economically, and socially costly alter-native. Most plants are designed as generating units with all the inter-related equipment such as steam generators and turbines of a compatible l size. It would not be technically feasible to increase the capacity of ! these units by an additional piece of equipment unless the entire unit was ; i (]) l h 8.2-5 ; l l

.)

replaced by one of a larger size. This alternative would, therefore, be expensive and would be unacceptable since extended power outages would be i required during the replacement period. The only practical alternative, and the one chosen for implemen- ! tation, was the construction of a new unit. This alternative obviously had l the highest overall benefit since it fulfilled the demand for power and j environmentally resulted in a net benefit: new plants using the latest pollution abatement technologies tend to minimize adverse impact on the environment. l 8.2-6

8.3 SELECTION OF POWER PIANT SIZE AND TYPE Once the decision was made to build a new unit, the Company had to decide how large a unit to build and what type. The four types given consideration were:

1. Hydroelectric Generation

2. Gas Turbine Generation

3. Fossil Generation

4. Nuclear Generation

Since there were no suitable water resources in the area, the hydroelectric alternative was abandoned. Gas turbines are useful in pro- , viding peak load service but are not designed for continuous base-load ; service. Theoretically, one could operate sufficient gas turbines to pro- ! vide the required base load but such a scheme would not be economically competitive with the fossil or nuclear alternatives. Both the fossil-steam l l and nuclear-steam generating alternatives were given careful scrutiny in-O 1965 when this decision point was reached. From the standpoint of environ-l l mental cost, the decision was made to minimize environmental impact for l l J either type of plant as a basic Company philosophy. Therefore, the coet/ benefit couparison was made essentially on economic grounds. A total evaluated cost per year for a 700 MWe electrical unit was estimated for both a nuclear and a fossil unit. The analysis showed that a nuclear unit would involve a higher evaluated cost initially because of ; the higher capital cost and a slightly higher fuel investment initially. Within two years the escalation of fossil fuel cost would increase the evaluated yearly cost of the proposed fossil unit to a value greater than the nuclear unit. The nuclear unit would maintain this advantage in eval-uated cost for the remaf r. der of the unit life based on fuel cost projections. , As a result, the decision was made in favor of the nuclear unit. The in-i crease in cost of fossil fuel has proved the soundness of the analysis. l l O 8.3-1 l l

i The size of the unit was established on the basis of two criteria demand and availability of " standard" commercial nuclear units. A plant of approximately 700 MWe was indicated by load projections and this size was being offered by nuclear reactor suppliers at that time. I f i I k 6 I f c i s O 8.3-2 ,

, . ~ . . . -. -- - -- .. -- - . . . . . .. 8.4 SELECTION OF SITE Following the decision to build a new, 700 MWe nuclear unit, a site had to be selected. In a general sense, two alternatives were avail-able: new sites or expansion at an existing site. The cost to benefit comparison was clearly in favor of utilizing the existing Lake Robinson site. During the initial site development, the waters of Black Creek were impounded to form a 2250 acre coo 11ng lake to provide condenser cooling water and service water for a total generating capacity of about 1200 MWe, The construction and operation of the lake were approved by the South Carolina Board of Health and by the South Carolina Pollution Control Authority. These permits authorized construction of the lake and set forth regulations for use of the lake including the amount of water flow from the dam, limits on water temperature, and use of water from the lake for ash sluicing. The site was also attractive for the addition of a nuclear unit in that the area was sparsely populated near the site. Since the land had been cleared during the construction of Robinson Unit No. 1 to provide for a second unit, the addition would preclude the environmental impact of clearing a new site. The benefits of the decision for locating Robinson Unit No. 2 at the Lake Robinson site were:

1. An existing, approved cooling water supply constructed expressly for steam electric generating plant cooling.

2. Company owned property already committed to electricity generation with plant personnel and services available.

3. Minimum impact on the environment from construction effects as compared with the clearing and grading of a new site elsewhere.

O 8.4-1

                                                                                                             .lA i

4

4. Minimum impact on the aquatic resources of the area I 1

since the existing lake was designed for the expanded heat load. ' l 4 i

5. Location in a sparsely populated area.

l 1 The costs incurred from the Lake Robinson siting decision were: l

1. Increased heat load for Lake Robinson.

2. Small radioactivity releases to Lake Robinson.

3. The visual presence of an additional structure in the plant area.

4 Construction of an extension to the cooling water canal from a point approximately 1.2 miles above the plant to a point 4.2 miles above the plant which was initially planned and for which land was provided. () The heat load to the lake, a problem which will be discussed as part of the cooling system cost / benefit analysis, was not considered a severe deterrent because of the Company's foresight in the 1950's when the lake was created. It was designed to dissipate the added load and ! was an impoundment dedicated to power plant cooling as a basic purpose. Radioactive liquids released to the lake were recognized as an environ-mental and public health impact which could be prevented by proper selection of treatment and handling procedures as will be discussed below. The aesthetic cost was minimum since a fossil unit already existed on the site. To minimize the environmental cost of additional construction for the new canal, land clearing was minimized and confined to the lake shore and areas , used for borrowing and wasting construction materials were improved by , planting pine seedlings and various grasses. In view of the many benefits at a minimum cost, Carolina Power & , Light Company elected in 1965 to proceed with the Robinson Unit No. 2 project at the Lake Robinson site. l O 8.4-2 E

  ~. __               -.-m-.           __ . _ . - _ _       _ _ _ . . __ _    _.     .- __ ._. __

t

c. 8.5 SELECTION OF COOLING SYSTEM With the site selected, the cooling system selection was the next decision confronted in the cost / benefit analysis. Three alternatives were included:

1. Once-through stream cooling.

I

2. Cooling Towers.

3. Cooling Lake.

The only water sources available at the chosen site are Black Creek and Lake Robinson, a 2250 acre impoundment of Black Creek. Since Lake Robinson existed at the time the siting decision was made for Robin-son Unit No. 2, the once-through stream cooling method was not really available. Even if Lake Robinson did not exist, Black Creek with its average flow of 115 cfs would not have the capacity to supply the 1070 cfs flow required for Unit No. 2. Wet mechanical draft cooling towers were an acceptable alter-native technically to dissipate the waste heat load. Cooling towers would minimize impact on the aquatic biota in Black Creek and Lake Robinson because of their lower water appropriation and the elimination of a ther-mal plume in the lake. However, towers create other environmental costs: j they are large, visually obtrusive structures that present aesthetic intrusion on the landscape; they contribute to fog, icing and high l humidity in the local area; drift or water carryover from the towers can be a nuisance and can cause arcing in local power transmission equip-i ment; and they increase water consumption to some degree from the lake, j wot.omically, the cooling tower alternative was not justified for the Robinson site. Towers would cost approximately $15,000,000 as compared with approximately $1,000,000 for extending the discharge canal and using Lake Robinson which already existed as a cooling facility. Based on these high environmental, social, and economic costs as compared with a modicum of benefits, cooling towers were not chosen for Robinson Unit No. 2. l O 8.5-1 1

t 8.5.1 Costs and Benefits of Existing Cooling System The final decision for Unit No. 2 was to select the existing , Lake Robinson cooling system. This system takes water from the down-stream end of Lake Robinson through a screen arrangement designed to keep fish and debris out of the plant. The water is pumped at 1070 cfs through cooling water pumps to the main steam condenser where its tempera-ture is increased 18 F as it takes on the unit's waste heat load. From the condenser, the heated water flows to the upper end of the lake through , a specially constructed discharge canal. As the hot water flows into the lake, it rises to the surface because of its lower density and most of the waste hcat is dissipated by . evaporation. During the course of its flow from the upper end of the - lake to the lower end, the " thermal plume" cools by the evaporation of from 4500 to 7500 gallons per minute and the temperature in the ' plume drops by 18 F. The heated water in the lake is confined to the top 10 to 15 feet of surface water; below these depths to the maximum lake depth of about 40 feet, temperature distributions are typical of the normal or natural temperatures for impounded waters in a warm water zone. 1 On a typical operating cycle with both Robinson Unit No.1 and 2 operating, the temperature of Black Creek at the outlet of Lake Robinson averages about 10 F higher than at the inlet. Experience indicates that, on the average, natural solar radiation accounts for about 6 F of this increase and that the operation of both the nuclear and fossil units accounts for the remaining 4 F increase. The current water quality standards , applicable to Black Creek, set forth by the South Carolina Pollution Control Authority allow a 5 F 6 rise in stream temperature after complete mixing and a maximum of 90 F. F The existence of temperatures in the lake and in Black Creek downstream of the dam which are higher than those above the lake would not O 8.5-2

                                                                 ....,cr      ,i. - -      ,-w...-w.-r.n,w w. r w - r.          ..re.- w,     vew-

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require close scrutiny per se were it not for two considerations: the O effect of temperature on aquatic organisms and the effect of temperature on downstream users of Black Creek. The only user within four miles , from the discharge is Sonoco Products Company, a manufacturer of specialty paper products that uses the water from their own impoundment of Black Creek for dilution of wastes and for cooling. The flow stability over a yearly cycle which the Lake Robinson impoundment provides has been noted as a beneficial effect to Sonoco. Black Creek in the area above and below the lake is classified as an A-2 swamp area by the South Carolina Pollution Control Administration. As such, standards for discharges are: for pH from 5 to 8, dissolved oxygen 2.5 ppm minimum and phenolic content 1 microgram per liter. The operation of both Robinson units has not only been within these limits but has actually improved some characteristics of the water quality in the lake and in Black

Creek downstream where dissolved oxygen has been increased by about 1 ppm by aeration due to special design features at the dam and where suspended solids and turbidity have been decreased due to the settling action in the lake.

t The water in Black Creek and Lake Robinson does not naturally have characteristics suitable to maintain a large fish population. Nutrient { content is low and the pH is relatively low at about 4.8 - 5.5. Predominant species as sampled by the South Carolina Wildlife and Resources Department , in 1968 are shown in Table 3.7-3. The Wildlife and Resources Department achieved a modest success in stocking a hybrid striped-white bass in 1969; however, in spite of this stocking, Lake Robinson's future as a sports fishery is questionabic even without the fossil and nuclear units because of the low quality of water upstream. The primary impact of the unit on the existing fish population is the thermal stress caused by the plume and the predation of the plant intake screens. While some fish have been collected on the screens, there is no evidence to suggest that a significant alteration of the fish O 8.5-3

l l population has occurred. Fish can avoid high temperature watera in the heated plume, particularly since the plume is confined to the surface waters at the upper end of the lake. i i Predation and heating the waters of the lake can, on the other hand, have beneficial effects on fish. If nutrients are available, growth rates of fish can be increased at higher temperatures which are below the lethal limits, and predation on the plant screens can help to maintain a stable fish population by culling rough fish and allowing others of interest to the sports fisherman to increase in number. l l l In addition to fish predation, the unit's operation can impact on the planktonic or free floating organisms in the water. These include many small phytoplankton (plants), zooplankton (animals), and fish eggs and larvae. Passage through the condenser and intake pumps can result in ! a plankton loss of from 20 to 100 percent based on experiments at other ; locations. In general, however, these losses in the plant should have l a relatively minor impact on the population of plankton in the lake because ( these small organisms reproduce rapidly. A long-term effect of the heated water in the lake may be anticipated as species more able to survive the heated water increase in numbers at the expense of those less able to sur-vive. This may represent an environmental cost or a benefit depending on the surviving species. The important consideration from a biological point of view is t that Lake Robinson does not contain a natural ecosystem. It was formed to provide cooling water for a generating plant; the fish and planktonic communities were secondary considerations. Fish populations in the lake were mediocre prior to the construction of Robinson Unit No. 2, primarily due to the water quality inherent in the black water impoundment. 1 In addition to the quite minimal environmental costs and the i environmental and economic benefits noted above, Lake Robinson provides social benefits for the South Carolina area. Before Lake Robinson existed, O 8.5-4 n

                 - - , . - -       ,.~

_ _ _ _ _ _ = . - _ . - - _ _ _ . _ . . - i i A I the area was largely second growth pines and some stream fishing was available to local residents. Today, the lake affords greatly expanded

recreational opportunities for the area including a sports fishery and 2250 acres of open water for swimming, sailing, boating, water skiing,

! and other water sports. In addition, picnicking and hiking around the lake are added recreational benefits. 1 1 i i i i t e ) l i 8.5-5 i d

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

a 8.6 SELECTION OF TRANSMISSION SYSTEM O Having made the above cost / benefits decisions on siting, cooling system and plant type, the next selection was the transmission system. The existing 115 KV transmission lines which had been installed to accom-modate the existing 185 MW fossil-fired unit did not have the capacity to transmit the additional power from the new 700 MWe nuclear unit. A transmission system having adequate capacity was required to deliver the additional power to the area load centers. The continued use of 115 KV transmission was not desirable because of the number of trans-mission lines that would have been required. Based on thermal capacity, one 230 KV line is equivalent to 2-115 KV lines. The social and environ-- mental costs of right of way, lines and equipment prohibited serious con-sideration of 115 KV transmission. A separate 230 KV transmission system was then planned to connect the 700MWe nuclear unit to the area load centers. The new 230 KV lines were planned, designed, routed and constructed to minimize environmental cost. The existing 230 KV line from Rockingham to Florence was routed into the Robinson Plant by constructing two short segments of 230 KV line from a point near Society Hill, S. C., to the plant. These two extensions to-gether with the existing line provided two of the required 230 KV circuits with one circuit extending to Rockingham and the other extending to Florence. In addition to the above two circuits, only two other lines were required, one to Sumter and an additional line to Florence. The four circuits were the minimum transmission required for system reliability and to deliver the power to the load centers were it was required. The 230 KV system was also connected to the 115 KV system at the plant through a transformer bank. Consideration was given to uprating the existing 115 KV trans-mission lines to 230 KV operation, but this would have required removing the existing 115 KV structures and conductors and replacing them with > larger 230 KV structures, heavier insulation and larger conductors. in addition, 15-115 KV substations that were connected to these 115 KV lines 8.6-1

                     , .m,, ...        . - . _ _ . _r._ r   -- , , . . - - . ,       .
                                                                                         ..m.-,_.v. _. . - _ ,      _    . - .

() would.have required the replacement of 115 KV equipment with 230 KV equip-ment. During the reconstruction period large segments of the transmission network would have been removed from service, placing the reliability of the power supply to the areas in jeopardy. Lengthy service interruptions would have been required at the 115 KV substations during the replacement i of the 115 KV equipment. The environmental cost of land use for line ' right of way was also greater, as more acres of new right o' way were re- ! quired for uprating the 115 KV lines than for the new 230 KV lines. ; I L In view of the above social and environmental costs, the re-construction of the 115 KV system to 230 KV operation was not found to be feasible. 1 , As previously stated in Section 3.10, the new 231 KV lines were designed to minimize the environmental impact. Pole design was selected to be unobtrusive and blend with surroundings, land use c.hanges were minimized, and screening was provided at highway and stream crossings. O The Company cooperated with state and local agencies and property owners in the development of beneficial uses of the right of way for agriculture, wildlife and recreation. The routing was selected to minimize environmental and social costs by avoidance of public lands, major construction, historical and archeological sites, airports and other sensitive areas. 3

O 8.6-2 L 4

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i 8.7 SELECTION OF WASTE RANDLING SYSTEMS O In the selection of systems or methods of handling the radio-active and sanitary wastes for the Robinson Unit No. 2, three alterna-tives were available as shown in Figure 8.1-1:

1. Direct release to the environment.

2. Shipment off-site or to municipal treatment systems.

3. Pre-process on-site to a condition suitable for shipment or release.

Direct release of wastes would involve severe environmental costs in terms of water contamination, damage to aquatic biota, air pollution, and public health. This alternative was not considered accept-able. Shipment of radioactive wastes off-site was a feasible alternative , but was too costly and inefficient because of the large volumes of liquids and gases involved. Off-site disposal of chemical and sanitary wastes was not possible because no local municipal facilities were available. O The final alternative was chosen as the only cost effective one. The Company decided for a commitment to minimize environmental costs by pre-treating all wastes on site until the radioactivity or biological activity reached low enough values for release. , t A complete description of the present radwaste system is included ' in Section 3.7. As noted in that description, all radioactive liquids are either processed and retained by the Chemical and Volume Control System or by the Waste Processing System. The Waste Processing System collects low-activity fluids from drains, leak-offs, and demineralizer regeneration and concentrates them in the waste evaporator. Concentrated bottoms from the evaporator are stored in drums for off-site disposal at licensed burial grounds; condensates are held in storage tanks and analyzed for activity level prior to dilution and discharge in the condenser cooling 1 water flow to the lake. O. 8.7-1 l l l

Gaseous wastes originating in the degassing operation for the reactor coolant, cover gases in holdup tanks, and miscellaneous vents, reliefs, and sample points, are held in storage tanks until the activity has decayed to a level low enough to allow safe discharge to the atmos-phere. The gas in the tanks is analyzed for activity level prior to re-lease at a controlled rate. Solid radwastes such as paper, spent demineralizer resins, and waste concentrator bottoms are packaged in drums for shipment to off-site licensed burial facilities. With the above operating procedures during the past eleven months, actual releases of radioactive 11gulds to Lake Robinson hAve been 0.583 curies of fission and corrosion products and 38.3 curies of tritium. Gaseous releases of noble gases krypton and xenon were 0.022 curies. These releases have resulted in equilibrium concentrations in Lake Robinson which

                                                -5 are a factor of 10            to 10~ less than the MFC limits for various isotopes.

The resulting maximum dose to an individual exposed continuously at the site-boundary and eating 50 grams daily of Lake Robinson fish is 0.065 mrem per year. This dose is insignificant when compared with a background dose of 200 mrem from natural and other man-made sources. I From a cost / benefit standpoint, the only alternative available at ] this time is to modify the existing radwaste processing system so as to achieve even lower releases of radioactivity to the environs. Carolina Power & Light Company has modifications in progress which should reduce ! releases to levels even lower than those previously experienced. Sanitary wastes from the plant are filtered and chlorinated before i i being discharged to the lake. No contamination of the lake has resulted from this source. All operation of this system is in accordance with permits i issued by the South Carolina Pollution Control Authority. No need for improvement of these systems exists and, therefore, no alternatives need to be evaluated from a cost / benefit standpoint. O l 8.7-2

                                                                                                           ,i l

 ~           - -

l 8.8 OVERALL PROJECT

SUMMARY

. O The overall benefits of the H. B. Robinson Unit No. 2 clearly overbalance the environmental and economic costs. These costs and benefits )

in the social, environmental, and economic areas are present in summary form in Table 8.8-1.

I e 1 O O 8.8-1

O O O TABLE 8.8-1 H. B. ROBINSON UNIT NO. 2 COST / BENEFIT SL71 MARY DECISION COSTS BENEFITS Selection of Energy Source Terrestrial impact and diversion of Overall energy savings due to in-(Electricity) land for transmission system creased efficiency 1012 Btu /yr. Reduction in noise level in urban areas Development of skilled work force Enhanced quality of life in locale C* including public health, safety, 3 and personal comfort w

                                                                                             . Enhanced local tax base Selection of Power Plant Size           Higher initial capital cost                          Lower yearly evaluated cost based and Type                             Radioactive materials releases n 1 wer fuel costs (700 MWe nuclear)                                                                                            .   .

Maximum utilization of available site and cooling water lake at minimum additional expense Availability of " standard" size

nuclear unit at 700 FMe

! Compatible output and demand level i i Minimum environmental impact from ~ standpoint of land use, fuel com- , mitment, aquatic resources Fuel savings 35 billion cu. ft/yr. i natural gas or 350 million gallons /yr. oil i 4 h

                                                      ---.---_-----_.-._:.-_-_---_-_--         2  -.n,.   -     v,-            , ~ ,

O O O l TABLE 8.8-1 (Continued) t 4 l i DECISION COSTS BENEFITS I ( Selection of Plant Site Increased heat load for lake Available cooling water supply i (Lake Robinson Site) Radioactivity releases to lake air ady dedicated to power plant and air cooling Visual presence of unit Ava a , clearedsitealreagy dedicated to power generation Extension of cooling water discharge canal 3 miles and environmental Available, trained employees for i a diereof c nstruction, design and opera-tion tunimum impact from construction oo effects k Minimum impact from waste heat load on South Carolina waterways Sparsely populated area

.                             Selection of Cooling System                 Increased evaporative load and       Increase in water quality of Black (Lake Robinson)                          more water consumption                Creek Possible diversity and abundance      Maintaining stable flow for down-changes in plankton community         stream users Possible heating of Black Creek       Enhancement of area sports fishery downstream 3 to 5 F.                  to a limited degree through im-poundment, increase in quality, s

and stocking program ' Recreational asset for area for swimming, boating, and other water sports as well as picnick-ing.and hiking Available cooling capacity at mini-mum capital and operating costs

O O O ' TABLE 8.8-1 (Continued) DECISION COSTS BENEFITS Selection of Transmission System New rights of way High safety and reliability (New 230 KV Lines) . No power outages during construction No substation replacement Funimum e:onomic cost Aesthetically compatible support design Minimum visual intrusion Available for development of wild-life areas, recreation, and P access for forest fire fighting co E Avoidance of sensitive areas - historical sites, parks, etc.

                                                                                                                                          -5 Selection of Waste Handling                                                3 x 10      mrem /yr. dose to maximum             Nearly total containment of rad-Systems                                                                    exposed individual (200 mrem /yr.                 wastes (In-plant treatment and                                                    background)                                    Fu imum biological impact from controlled releases off-                                                                                                    sanitary wastes and chemical Operating costs of processing site)                                                                     facilities                                        wastes Control of level and amounts of releases based on weather, activity level, etc.

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STEAM ELECTRIC PLANT
'C UNIT NO. 2 Environmental Report a ..,u, w s. ~,
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et w co ,# g UNITED STATES s
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Docket No. 50-261 Carolina Power and Light Company ATTN: Mr. J. A. Jones Senior Vice President 336 Fayetteville Street Raleigh, North Carolina 27602
Dear Mr. Jones:
During the course of the review of the Environmental Report for the
11. B. Robinson Steam Electric Plant, Unit No. 2, it has been determined that additional information will be needed before we can complete our Environmental Statement. Accordingly, please submit the information identified in the enclosure to this letter. Your reply should consist of three signed originals and 297 additional copies as a sequentially numbered supplement to your Environmental Report.
In order to maintain our licensing review schedule we will need a O completely adequate response by November 24, 1972. Please inform us within 7 days after receipt of this letter of your confirmation of the schedule or the date you will be able to meet. If you cannot meet our specific date or if your reply is not fully responsive to our requests, it is highly likely that the overall schedule for completing the licensing review for this project will have to be extended. Since reassignment of the staf f's ef forts will require completion of the new assignment prior to returning to this project, the extent of extension will most likely be greater than the extent of delay in your response. Sincerely, s- ,& N Daniel R. Muller, Assistant Director for Environmental Projects Directorate of Licensing j
Enclosure:
l As Stated cc: George F. Trowbridge, Esquire Shaw, Pittman, Potts, Trowbridge & Madden b' s h i n , I 200 (> l
O - P ADDITIONAL INFORMATION FOR 11. B. ROBINSON STEAM ELECTRIC UNIT NO. 2 J
1. OBJECTIVES OF THE FACILITY

a. Provide information on anticipated snd projected power demands through 1975 or later, i

b. Provide information on projected peak load figures for the period 1962-1972 and a comparison with actual peak load demand f or this
(} same period,
c. Describe additional plants or increase in capacity of present plants which are pinnned in the CP & L service area. Indicate distance to and location of any which will be closer than 100 miles from the H. B. Robinson site.

d. Describe agreements which exist for obtaining power from neighbor-
, ing utility systems.
c. Indicate the status of the Refuse Act Perriit Applications which were made to the U. S. Army Corp of Engineers and the S. C. Pullution 4
Control Authority in June and September of 1971 (see p. 2.3-2 of ER) . If the Company has received the permit to discharge into Lake Robinson, E
C:) and certification under WQIA/70, what are the permit / certificate numbers, dates, etc.?
2. THE SITE 2.1 Site Location

a. Provide a map of the area which indicates the extent of the boundaries of the complete plant site. It should include all of Lake Robinson, l 1
show the run of the discharge canal and its point of discharge into the lake, and indicate run of transmission lines. O
b. Provide a listing of the allocation of land area on site to its ,
various uses in appropriate and convenient categories. 2.2 Demography and Land Use l
a. Furnish estimates on water and shore side recreational use of Lake Robinson in terms of person hours in or on the lake and on-site i
per year. .j
b. Discuss action taken or planned, if any, and the CP & L basic philosophy for the encouragement of recreational utilization of Lake Robinson: c.g. , boat ramps, fish stocking programs, etc.
O 1 1
O c. Provido an estimate of the sport fishing yield of Lake Robinson (pounds per year) and Black Creek to and including Prestwood Lake.
d. Provide a detailed map or an aerial photograph showing the location of residences, farms, businesses and industry within a two-mile i radius of the reactor.

e. Provide a copy of or a reference to the report of the study for Southern Bell Telephone Company and the South Carolina Development i
Board on population projections discussed in the ER, page 2.1-3, and of any other studies which have been made in addition. O f. Provide information on the economic impact of the plant on the surrounding community. Include numbers of persons employed, total wages, taxes paid, etc. 2.3 llistoric and Natural Landmarks i Provide a copy of correspondence from the State of South Carolina Concerned Agency relative to the existence of any historic or natural landmark or site of archaeological significance on site or on the transmission lines' right-of-way.
i I 1 2.4 Geology 1 i Provide a copy of or a reference to the Dames and Moore report from which the geologic map Figure 2.1-9 was taken. I
)
2.5 Hydrology Provide a copy of the permit from the State of South Carolina for j the use and control of water flow in Black Creek and Lake Robinson. i 2.6 Meteorology + O Provide joint frequency distribution of wind direction, wind speed and stability in the format requested in the AEC Safety Guide 23, in accordance with Sections 50.34 (a)(1) and 50.34 (b)(1) of l 10 CFR Part 50, or provide data necessary to prepare this informa-tion. i 2.7 Ecology ; l
a. Provide lists of fauna and flora common ;o the Lake Robinson region.

b. Provide a copy of the student report >n Lake Julian.
l
P i _5 I
c. Provide information on fish stocking programs with threadfin shad and striped bass-white bass hybrids since 1968. -

3. THE STATION 3.3 Plant Water Use f Provide information on the qualitative use of water at the plant with indication of flows to and from cach use category during the ;
various conditions of reactor operation and shutdown. Indicate the quality of the water from cach system before it enters the general water discharge system as well as that of the general dis- j l charge system. Include water for sanitary as well as for industrial 1 purposes. 3.4 Heat Dissipation System , i
a. Provide inf ormation on the design of .the intake and outf all structures i
for the condenser cooling water system. Include design of screens, trash handling systems, canal intersection at lake, etc. Provide i necessary sketches or drawings which describe these. 4 1 4 1 C:) i
i ( , i ! 6- l LO i i i 4
b. Provide information on flow velocity and transit time of water in l the discharge canal during full power operation of 11. B. Robinson Units 1 and 2.
4 l 4 1
c. Provide inf ormation on inside dimension of condenser tube and water i
i : 1 l velocity within them. , t i
3.5 Radwaste Systems i
i i n. Furnish copies of reports giving monthly releases of radioisotopes t in liquid and gaseous effluents for the past year. Give isotopes I breakdown if availabic. i O i ! b. Furnish distances f rom Plant to site boundary, nearest occupied )
dwelling, and nearest herd (> 1 cow) in the 16 principal compass ;
i i directions. Describe milk sampling program. l ' i } ! c. Describe operating procedures that govern use of extended treatment system for exhaust air from selected areas in the auxiliary building. f i J ' l d. Response to question 17 for Scurce Torn Data (letter J. A. Jones to E. J. Bloch, June 7, 1972) indicates that the containment air is purged through IIEPA filters. Figure 5.3.3-1 of the FSAR indicates. O
a
)
_7_ () no treatment of containment purge. Please reconcile the apparent discrepancy. e. Purnish details about the history of containment purges, Also furnish i information from plant records regarding radiation levels (direct ' and air concentrations) measured in the containment building. To wha
extent are the recirculation filters operated. '
f. Describe the plant history of primary coolant Icakage (water, steam) i to the containment and elsewhere. Describe its collection and ; treatment. ' t
g. Describe proccos monitoring on release line from CVCS monitor tanks. !

h. Furnish the following information about process radiation monitoring l of gas and liquid effluent streams:

1. sensitivity limits in terms of expected radionuclide mix;

2. trip icvcis and alarm set points and basis for setting;

3. operation response to alarms or trips; i

4. any changes (actual or expected) from monitors described in '
Section 11 of the FSAR. l l I i
1. Purnish history of radioactivity 1cvels measured in the primary and secondary coolants. ,
1
t _ .3_ l
j. Describu downstream use of Black Creek f or potable water for a i distance of 50 miles.
?
k. Furnish inf ormation on volume and flows into and out of Prestwood ;
i Lake. ! 1, Describe in core detail the vents and release points from which airborne or gasecun radioactive materials are cmitted. Their height ' in relationship to adjacent buildings as well as effluent velocity I and volume flow rat e should be indicated.
m. Provide Jocation relative to visitors center, nearest site boundary
() and nearest duelling of any cucside storage tanks which may contain radioactivity. Also give the capacity and expected concentrations of radionuclides of these storage facilities. - 3.6 Chemical and Biocide Systcms
a. Provide a detailed list of all chemicals discharged into Lake Robinson indicating frequency and quantities of discharge,

b. Describe methods which will be used to control chlorine residuals at discharge canal outlet to .ucet EPA requirements if it becomes necessary to use chlorine in connection with the operation of Unit 2 ,
i in the future. , (:) .
.. -- - . -. . .~ . . . - - . - - .- . _ - . . . . . . - . - . . -
O 3.7 Sanitary and other Uaste systemn i a, Provide the following information: the quantity of sanitary waste discharged to the lake per day, the residual chlorine level of dis-charged sanitary waste, the biochemical oxygen dcaand (BOD) of the discharged waste, f
/c b. Describe the dicposal practices for other nonradioactive wastes (solid, liquid, and gaseous) including debris and fish from trash 4
racks and screens in the condenser water supply system. Provide a ' copy of State regulations which control such disposal. O Y 3. xxv1xoxxexrit tzrzcrs or rtixr ortairrox 3.1 Effects of operaticn of lleat Dissipatien System
a. Provide inf craation on daily, ucekly and monthly fluctuations in lake level during various seasons of the year with the operation i of the plant. Values during spring are of special importance, i

b. Provide representative temperature and dissolved oxygen concentration inf ormation f rom surveys during July or August and February or March for two years before startup of Unit 2 and for cach year since.
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c. Provide a copy of or reference to the EPA document on black waters, i Provide a copy of available nutrients data for Lake Robinson.

d. Paragraph 3 on p. 8.5-2 of the ER states that natural solar radiation accounts f or about 6*F of the 10*F temperature rise between the inlet and outlet waters of Lake Robinson, Please provide information on measurements which have been made to support this.

c. Provide a copy of the data on fish taken from the intake screens.
i 5.2 Eff ects of Operation of the Plant on Resources O Provide information on annual consunption of fuel for'the diesel engines and auxilliary boiler which support Unit 2. 5.6 Effects of Operation and Maintenance of the Transmission System Provide information on the effect of the existence of the transmission lines. Provide information on and break down into categories of land use of transmission line right-of-ways f or Unit 2.
'6. EFFLUENT AND ENVIRONMENTAL ?IASURE:5NTS AND MONITORING PROGRAMS a-. List and describe all ptograms for monitoring the environmental impact
(} of the operation of the plant. Radiological, chemical and sanitary r
I O effluents and their effects en the ecology should be included. Descriptions should be in detail covering such factors as 'l l frequency, type of sampling, method of co11cetion, analytic methods, sample holding times and pre-cnalysis treatment, instrumentation , used and its sensitivity, etc. - Monitoring programs being carried out by public or other agencies not supported by CP & L should be included. Include programs listed in Tabic 3.6-5 in the ER with cdditional information necessary to , update it and provide the information requested above.
b. Provide information on the location of other wells being monitored ;
( (p. 3.7-9) in addition to the sampling point No. 23 listed in the Tabic.
9. ALTERNATIVE E::ERGY SOURCES C;D SITES T

a. Provide information on the other CP & L site centioned on p. 5.4-2 r
of the ER and describe the coaling water modifications that would ; i have been necessary to accommodate a 700 MWe plant there. ;
b. Provide information on cost versus benefit studies of alternate.
types of power plants which may have been made. Include breakdown O 1 f
! -1; - : O of costa considered such as capital, operr. ting, fuel and othere which affect the cost of generated power, I
11.
SUMMARY
BENEFIT-COST AXALYSIS l Provide data on electrical production from Init 2 since the { beginning of operation in terms of dollars and kilowatt hours, and f or a five-year projection.
12. TRANSPORTATION

a. Provide the follouing information ccncerninl; transportation of new fuel:

1. Source of supply;

2. Distance from supplier to plant;

3. Mode of shipment (truck or rail);

4. Number of shipments (rail cars or trucks) in initial loading;

5. Number of shipments annually of reload fuel.

b. Provide the following information concerning transportation of solid radioactive waste:

1. Location of burial' site;

2. Distance of site f rom plant; O
I 1 d 3. Mode of shipment (truck or rail);
4. Number of shipments (rail cars or trucks) per year.
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i II . B. Robinson Unit No. 2 s1.a-1 0
1. OBJECTIVES OF TFIE FACILITY Question 1.a Provide information on anticipated and projected power demands through 1975 or later.
Response
This information is supplied in Table s1.a-1, " Carolina Power & Light Company Forecast Power Demands" covering the period 1972 through 1981. TABLE s1.a-1 CAROLINA POWER & LIGIT COMPANY FORECAST POWER DEMANDS () Year 1972 MWe 4279 1973 4766 1974 5315 1975 5942 1976 6591 1977 7318 1978 8106 1979 8971 1980 9912 1981 10951 O Environmental Report Supplement No. 1 j
H. B. Robinson Unit No. 2 s1.b-1 O Question 1.b Provide information on projected peak load figures for the l period 1962-1972 and a comparison with actual peak load demand for this ) same period.
Response
This information is contained in Table s1.b-1, " Carolina Power & Light Company Comparison of Annual Demands With Forecast Demands" covering the period 1962 through 1972. TABLE s1.b-1 CAROLINA POWER & LIGHT COMPAtW COMPARISON OF ANNUAL PEAK DERWD WITIl FORECAST DEMANDS Forecast Peak Demand Variance {} Year 1962 MWe 1507 MWe 1516 Percent
-0.6 1963 1650 1638 0.7 1964 1810 1749 3.5 1965 1950 1943* 0.4 1966 2230 2184 2.1 1967 2437 2445* -0.3 1968 2650 2834 -6.5 1969 3043 3171* -4.0 1970 3415 3484 -2.0 1971 3818 3625 5.3 1972 4279 4119** 3.9**
Winter Peak in January of following calendar year
**1972 Summer Peak Environmental Report
() Supplement No. 1
H. B. Robinson s1.c-1 = Unit No. 2 Question 1.c Describe additional plants or increase in capacity of present plants which are planned in the Carolina Power & Light Company service area. Indicate distance to and location of any which will be closer than 100 miles from the
11. B. Robinson Site.
Response
The planned capacity additions for the Carolina Power & . Light system through 1980 are listed in Table s1.c-1. None of these additions are within 100 miles of the 11. B. Robinson site. The liarris Plant site is located approximately 110 miles northeast of the Robinson site. The Company has purchased 630 MW of IC turbines, but the location for the turbines has not been decided as of this date. It is possible that they might be within the 100-mile radius. TABLE sl.c-1 CAROLINA POWER & LIGHT COMPANY SCHEDULE OF CAPACITY INSTALLATIONS O Size Expected In Unit (MW) Type Site Service Date Roxboro #3 720 Fossil Extension 3/1/73 Brunswick #2 821 Nuclear New 3/1/74 Brunswick #1 821 Nuclear Extension 3/1/75 Roxboro #4 720 Fossil Extension 3/1/76 lbrris #1 900 Nuclear New 3/1/77 Ilarris #2 900 Nuclear Lxtension 3/1/78 Harris #3 900 Nuclear Extension 3/1/79 Harris #4 900 Nuclear Extension 3/1/80 0 Environmental Report Supplement No. 1
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H. B. Robinson Unit No. 2 O Question 1.d Describe agreements which exist for obtaining power from neighboring utility systems.
Response
Carolina Power & Light Company has contracts for purchases of firm capacities with the Appalachian F.n er Company for 100 MW and with South Carolina Electric & Cas Company .oi 53 MW. Additionally, there is , an agreement which allows the purchase of unit capacity for 61 W from - South Carolina Electric & Gas Company. There are no other long-term purchases being made from others. Carolina Power & Light does have interchange agreements which permit short-term and emergency exchanges of capacity and energy with all of the neighboring utility companies with which it is interconnected. These interchange agreements with Virginia Electric & Power Company, Duke Power Company, Appalachian Company, the Tennessee Valley Authority, and South Carolina Electric and Gas Company permit the exchange of capacity and ( nergy between companies for the purpose of enhancing the reliability of each company. However, they do not provide for the long-term purchase of capacity in the amount of or the type required to replace the base load-carrying capability of a unit such as Robinson No. 2. ' i 4 O Environmental Report ! Supplement No. 1 l
H. B. Robinson el.e-1 Unit No. 2 O Question 1.e ; Indicate the status of the Refuse Act Permit Applications which were made to the U. S. Army Corps of Engineers and the S. C. Pollution Control Authority in June and September of 1971 (see p. 2.3-2 of ER). If the Company has received the permit to discharge into Lake Robinson, and certification under WQIA/70, what are the permit / certificate numbers, dates, etc.? Response i The permit application filed with the U. S. Army Corps of Engineers on June 29, 1971 as required under the Refuse Act Permit Program is pending. The South Carolina Pollution Control Authority which, on the i same date, was requested to certify that continued operation of the Robinson ' Plant is not likely to contravene State Water Quality Standards has issued a letter of certification dated November 16, 1972. A copy of this letter of certification is shown on page sl.e-2. i O ! Environmental Report Supplement No. 1 ;
.e-2 Bautly Garnlina "
l Valluttmt Gantral Auffi ority 0 AUTHORITY M EMetRs
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A UT H O RITY M E M P ER S l F ROBER .TURNfR , CMantasToM M' BEN N M ILL E R. M.O. Cotuusia JAMES W. WEDB C ol u u s t A ,!OHN MLCR A OY, JR CMa mL a s t oN ( . J' CL AIR P. GUESS, JR. COLuween J A C K t . POW E R s . . SewesoNVILLg 800 HICKM AN ., Colu u s ta WILLI A M M. B RICE. JR. Yong HUBERT J. WEDB. PH D. JOHN W. PARRi$ COLUwera ) JOHN F, ANDREWE. PM D. .ClausON EXECUTIVE DIRECTOR J. BONNER M ANLY Cot u u s sa . 1 C. M ARION SHIV E R. JR. CAMOEM g g j p,gg s aa t LAOY STREET P. o. Box niane TELEPHONE. 7 58 2 91$ Golunthia, Soutl} Garolina 29211 ! November 16, 1972 Carolina Power and Light Cornpany Raleigh North Carolina Re: H. B. Robinson Steam Electric Plant Unit No. 2
Dear Sir:
The South Carolina Pollution Control Authority has evaluated information supplied to the Authority by Carolina Power and Light Company. Based on this information the Pollution Control Authority certifies that there is reasonable assurance that this project will not violate applicable water quality standards. Yours very truly, c
/ ,
[4.g4b H. J/Vebb Exe' cut'ive Director ILTW/CRJ:as O Entironmental Report Supplement No. 1
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t-H. B. Robinson s2.la-1 I Unit No. 2 ,. L I i 2. Tile SITE ) 8 2.1 Site '9 cation i j Ouestion 2.la Provide a map of the area which indicates the extent of the ; 1 boundaries of the complete plant site. It should include all of Lake . 2 Robinson, show the run of the discharge canal and its point of discharge i l Into the lake, and indicate run of transmission lines. Response , An aerial photograph with the property boundary and transmission line runs indicated is provided in rigure 2.la-1. t i 1 4
@ l 1
r W l i 1
6 4
e Environmental Report i Suppleraent No.1
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l i H. B. Robinson i Unit No. 2 s2.lb-1 l l Question 2.lb Provide a listing of the allocation of land area on site to its various uses in appropriate and convenient categories. l l I - Response of the total 4,750 acres in the Robinson Plant site area shown on Figure 2.la-1, 2,250 acres are devoted to the lake; 1,000 acres ; to utility property, including the Visitor's Center; 1,300 acres to forestry and watershed protection; and 200 acres are leased to a farm management program. d l i O i a i 1 1 ) i i 1 I l t Environmental Report Supplement No. 1
H. B. Robinson Unit No. 2 s2.2a-1 0 2.2 Demography and Land Use Question 2.2a Furnish estimater on water and shore side recreational use , of Lake Robinson in terms of person hours in or on the lake and on-site per year. b Response t The folic;,ing estimate is derived from conversations with people in the area. Weekends for 31 weeks of the year 50 people at 4 hours per trip - 6,200 person hours Weekdays for 31 weeks of the year ..- O 10 people per day at 4 hours per trip - 6,200 person hours Weekends for 21 weeks of the year 5 people at 4 hours per trip - 420 person hours Weekdays for 21 weeks of the year i 2 people per day at 4 hours per trip - 840 person hours Total - 13,660 person hours I O Environmental Report Supplement No. 1
H. B. Robinson s2.2b-1 Unit No. 2 l
O question 2.2b Discuss action taken or planned, if any, and the CP&L basic I philosophy for the encouragement of recreational utilization of Lake Robinson. e.g., boat ramps, fish stocking program, etc.
Response
A picnic area has been constructed near the lake by CP&L. However, as the primary purpose of Lake Robinson is to 5:erve as a cooling device, there are no plans for further recreational development. Two boat ramps (Atkinson Landing and Lasterlings Landing) and one marina (J6M Marina) are located on the lake. The South Carolina Wildlife Resources Department stocked 850,000 hybrid fry (white bass x striped bass) into Lake Robinson during the period 1967-69. In the winter of 1971 threadfin shad were stockec. A sampling program was performed in December, 1972, at which time no hybrid fish or threadfin shad were collected. O Environmental Report Supplement No. 1
H. B. Robinson Unit No. 2 s2.2c-1
/'T U
Question 2.2c Provide an estimate of the sport fishing yield of Lake Robinson (pounds per year) and Black Creek to and including Prestwood Lake.
Response
in the absence of creel census data, a quantitative estimate in pounds per year of the sport fishing yield of Lake Robinson would amormt to no more than untenable speculation, llowever, a serien of news articles f rom the Darlington County Tribune _ provides some valuable inf ormation con-conerning the sport fishing opportunities at Lake Robinson. According to EP'(Rw) a November 9, 1972, article titled " Lake Robinson Offers Good Fishing."
......."the lake has provided excellent fishing f or largemouth bass, crappie, bluegill, pickerel and catfish." The article further states that "Largemouth basa fishing along the entire edge of the lake along the eastern shore and from the ' hot hole' northward on the western shore is exec 11ent during the spring, summer, and early fall." Bluegf11 fishing is also rated as excellent during the spring and summer mont hs.
Similar information for Black Creek and Prestwood Lake in not available. f~h O Environmental Report Supplement No. I
11. B. Robinson Unit No. 2 s2.2d-1 Question 2.2d Provide a detailed map or an aerial photograph showing the location of residences, farms, businesses and industry within a two-mile radius of the reactor.
Response
This information is provided on Figure 2.la-1 submitted in response to Question 2.la. ) i i
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t 5 i L T i Environmental Report Supplement No. 1 v ..-, , , , , , , _ , . ~ , _. , _ _ _ _ __ _ _E
H. B. Robinson Unit No. 2 s2.2e-1 O Question 2.2e Provide a copy of or a reference to the report of the study for Southern Bell Telephone Company and the South Carolina Development Board on population projections discussed in the EP, par;e 2.1-3, and of any other studies which have been made in addition.
Response
In developing the population projections for the area surrounding H. B. Robinson Unit 2, prior dicennial census data from 1940 onward was used. The numbers which appear on Figures 2.1-5 and 2.1-6 were arrived at using the most optimistic growth projections based on historical data. No out-migration was assumed; if losses occurred during the previous dicennial census , data, the population projection was taken to be a constant value and no further losses were assumed. Southern Bell Telephone has a very intimate knowledge of how the region is developing both industrially and residentially, gg Each year, Southern Bell performs a house-count of their service area and assumes about 3.6 persons per house for projecting residential growth. Additionally, Southern Bell representatives meet with industrial representa-tives and are well-informed with regard to the industrial growth anticipated for their region. Southern Bell Telephone data was used in all cases where the historical projections were less optimistic. Due to yearly update and elapsed time, Southern Bell Telephone's 1966 projections are no longer available. 1 l l l O l l l Environn.cntal Report l Supplement No. 1 I
H. B. Robinson Unit 'f o . 2 s2.2f-1 Question 2.2f i Provide information on the economic impact of the plant on the ) surrounding cor:munity. Include number of personn employed, total wages, taxes paid, etc.
Response
'I h e addition of the Robinson (! nit ::o . 2 has had a substantial and positive effect upon p ropert.y t a xes in F riington County. In 1971, CP&L paid $540,484 in property taxes. This was 15 percent of the total county tax revenues. In 1972, the first year CP6L will pay on the basis of the total nuclear operation, the tax bill will amount to about $1,272,000.
This will represent 29 percent of the real taxable property in Darlington County. CP&L is the largest taxpayer in the county. Since 1966 when the nuclear plant was announced, $431,270,000 has been invested in new and expanded Industries through 1971 in the South I Carolina area served by CP&L. This has resulted in the creation of 22,7% new jobs with an added payroll of S95,556,000. The nuclear p} ant requires c o rre 77 pernanent employees , whose l annual payroll is about S776,000. According to a United States Chamber of 1 Commerce economic research study, these 77 workers resJding in the same I community would produce the following. econonic results: 77 more households 24 more school children 278 more peop]e 75 more passenger cars 50 more er.p!oyed in non-m auf acturing or non-industrial 2 more retail establtshnents
$1,034,200 more personal income 3 349,n48 more bank deposits $ 505,237 nore retail sales Environmental Report Supplement "o. 1
i 11 . B. Robinson Unit t;o. 2 s2.3-1 0 2.3 Regional llistoric and Natural Landmarks Question 2.3 Provide a copy of correspondence from the State of South Carolina Concerned Agency relative to the exist ence of any historic or natural landmark or site of archaeological significance on site or on the transmission lines' right-of-way.
Response
The 11. B. Robinson plant site at Ibir t s vi l l e , South Carolina, and the transmission lines' right-of-way associated with the Robinson No. 2 unit do not lie upon nor pass near enough to any known historic, natural, or archaeologically significant properties to adversely affect then. Page 2.3-2 is a copy of a letter from the South Carolina Department of I Archives and History validating the above ;t atemen t . i l 1 l l I l Environmental Report Supplement No. 1
II. B. Robinson Unit No. 2 s2.3-2 p South Carolina Department of Archives and History f 1430 Senate Street t Columbia, S.C. eq u L}4
%..) .#6 P. O. Box 11,18 8 Capitel Station 29: 1i Octotier '0,1972 Mr. Robert W. f>cDonald Principal Engineer Carolina Power & Light Company P. O. Box 1551 Raleigh, florth Carolina 27602
Dear Mr. Mcdonald:
This letter will acknowledge the fact that we have been informed of the Robinson Steam Plant at Hartsville, South Carolina, and that we have on file the mapping of the three areas affected by the Carolina Power and Light Company lines. No National Register properties are located in these areas; nor do we know of any other historically significant properties near enough to adversely affected. Enclosed is a list of the 195 South Carolina properties currently on the National Register of Historic Places. In addition, our Historic Preservation Division has an inventory of more than 3,500 South Carolina places of historic interest. We will be happy to identify these for Carolina Power and Light in any future environmental impact studies. Since , O 0AX/ Charles E. Lee State Liaison Off cer for Historic Preservation CEL:czf Enclosure ()\ Q Javircamental Report l S upp le. men t No. 1 i
H. B. Robinson Unit No. 2 s2.4-1 0 2.4 Geology Question 2.4 Provide a copy of or a reference to the Danes and Moore report from which the geologic map Figure 2.1-9 was taken.
Response
The geologic map shown on Figure 2.1-9 was taken from the Danes & Moore report " Site Environmental Studies Proposed H. B. Robinson Nuclear Powe r Plant . " A copy of this report was provided directly to Dr. Mike Novick, Argonne National Laboratory. (Letter dated January 2, 1973). O' l l l l l In:!re'1 mental Report c opplement No. 1
H. B. Robinson Unit No. 2 s2.5-1 O 2.5 Hydrology Question 2.5 , Provide a copy of the permit from the State of South Carolina for the use and control of water flow in Black Creek and Lake Robinson. , i
Response
A copy of permit No. 307 dated June 24, 1964 and issued by the South Carolina Pollution Control Authority for operation of Lake Robinson as a cooling facility is included in this Supplement on page s2.5-2. c { O O Environmental Report Supplement No, 1 !
H. B. Robinson
,s Unit No. 2 s2.5-2 6.S.T.PREPLES. N.D h W. T. LINTON. OssacTom MMM. W Ar$8 POLLW O st f 8 EC. O R , W ATift POL TSO CONTROL AWTMontif x CONTSOL AUTMDeity 0' . Bau11; Carolina State U.iuarb of lirultt; Etatston of Osniturg Enginerring AND hter 1.lallution Control Au11;ority CoLUMulA. SOUTH CAROLIN A PERMIT For the Dische:qo cf Sowago, Industrial Wastes cmd Other Wasto In accordance wit h the provisions of Chapter No. 3. Title 70. Vol. 6.1952 South Carolina Code of laws, and Regulations of the South Carolina Water Pollution Control Authority, PERMISSION IS HEREBY GRANTED TO _
Carolina Pouer & Light Company Hartsville, South Carolina, Generating Station FOR THE DISCHARGE OF inductrial cooling water s O into t?nM m inkn(ninck cmek) Receiviry* Stream Pee Dee Drainage Basin ( in accordance with the application filed on t'Ph 10 , 19 CO in this office and in conformity with plans, specifications and other data submitted in support of the chove application, all of which are filed with and considered es a part of this permit together with the following conditions ord requirements: Diccharge of cooling water to Robinson Lake by way of canal. Canal to be extended upstream as generating capacity is increased, in accordance with engineering report of Ebasco Services, Inc., Engineers, dated May 1,1958. Ach sluice water and boiler cnd evaporator bloadown diccharged to cettling basin. Effluent from settling basin returned to Robincon Iake. Discharge from Inke Robincor, dam to be maintained at or cbove 1.47 ticec flow measured by U.S.O.S. Cause on Black Creek near Mc:ce, South C;rolina. Flow ratio cubject to review at 5-year intervals as data accumulates, or as enjor conctructica cay indicate a need. This Permit superoedes: WPC Pemit to Diccharce 8217-5/13/61 ' Ref: WPC Pemit to Construct fl79 - 5/12/58 , l Nof ICE = =Tb is pe r mi t s h211 not be con. [SSued this 2h day of UUUC h
% 19 s t r ued to a u t h or is e the c r ea t ion or 3 en l a te to rc e of a m u s e a nc e . A la o . it T%I pI g
ma y be re v oke d be ca us e of sa te r ia l c ha nge s in t he e nou n t of mostes d ie . j,D S M g I V i charged or f a ilure t o au tato in treet-se a t pr oce s s e s or ot he r c orid i t ions of ,/
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T Peeples, d , ( d is c ha r ge s pec i f ied above . The fater
',e /
j Pellut ion Cent e of A ut hor it y should be 'f
d//, M '
net ti sed of ecy .ch so i .e c ha ng. , E T. Wtm Permit No. 307 I Environmental Report 1 Supplement No. 1 I l .
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H. B. Robinson Unit No. 2 s2.6-1 e 2.6 Meteorology Question 2.6 Provide joint frequency distribution of wind direction, wind speed and stability in the format requested in the AEC Safety Guide 23, in accordance with Section 50.34(2)(1) and 50.34(b)(1)' of 10 CFR 50, or provide data necessary to prepare this information. R e s po_ns e, The above information was provided directly to Dr. James Carson, Argonne National Laboratory. (Letter dated December 5, 1972). i 1 J Environmental Report Supplement No. 1 ) _J
i, H. B. Robinson j- Unit No. 2 s2.7a-1 i LO l 2.7 Ecology I Question 2.7a i ! j- Provide lists of fauna and flora common to the Lake Robinson region. t Response !
A species list of dominant plants observed at or near Lake Robinson- j
' I September 21, 1972 follows: l 1 Trees i Longleaf Pine (Pinus palustris) Mockernut liickory (Carya tormentosa) Black Willow (Salix niger) Dogwood (Cornus floridanus) Mimosa (Allizzia spp.) l Persimmon (Diospyros virginiana) ; Red Cedar (Juniperus virginiana) l Water Oak (Quercus nigra) () American Walnut (Juglans nigra) Chinaberry (Melia azedarach) Loblolly Pine (Pinus taeda) Sweet Bay (Magnolia virginiana) Tulip Poplar (Liriodendron tulipifera) Red Fbple (Acer rubra) Iaurel Oak (Quercus laurifolia) Black Gum (or Tupelo) (Nyssa sylvatica) Sweet Gum (Liquidambar styraciflua) Southern Red Oak (Quercus falcata) Blackjack Oak (Quercus marilandica) Turkey Oak (Quercus laevis) Black Cherry (Prunus serotina _) Sassafrass (Sassafras albidum) Post Oak (Quercus stellata) Scarlet Oak (Quercus coccinea) Red Bay (Persea borbonia) American Holly (Ilex opaca) Shrubs Wild Plum (Prunus sapp.) Smooth Sumac (Rhus glabra) Huckleberry (Gaylussacia spp.) Wax Myrtle (Myrica ceri fera)
-p Alder (Alnus serrulata)
Honeysuckle (Lonicera spp.) v Summer Grape (Vitis spp.)
Environmental Report Supplerent No. 1
i H. B. Robinson 1 Unit No. 2 s2.7a-2 1 () Herbaceous j Numerous weeds of the Aster and Chenopediace families ) Dandelion (Taxaracum spp.) j Polk Weed (Phytolaca spp.) i Beggar's Lice (Desmodium spp.) i Blackberry (Rubus spp.) 3 Ragweed (Aster spp.) Cane (Arundinaria_spp.) Bear Grass (Yucca spp.) Spatterdock (Nuphar advena) ! Crab Grass (Digittaria spp.) , Wire Grass (Aristida stricta) l Smart Weed (Polygonum spp.) + Water Lily (Nymphaea spp.) , 4 1 List of amphibians, reptiles and mamnals common to the H. B. Robinson site: '!
Turtles Snapping turtle (Chelydra_ serpentina) l Stinkpot (Sternoth_erus odo ratus)
Mud turtle (Kinosternon subrubrum) . Spotted turtle (Clemmys guttata) ; Box turtle (Terrapene carolina) Cooter (Pseudemys florida) Pond slider (Pseudemys scripta) _ Lizards e Eastern fence lizard (Sceloporus undulatus) Slender glass lizard (Ophisaurus attenuatus) Six-lines racerunner (Cnemidophorus sexlineatus) , Ground skink (Lvgosoma laterale) Five-lines skink (Eumeces fasciatus) Broad-headed skink (Eumeces laticeps) Southeastern five-lined skink (Eumeces inexpectatus) Snakes Common water snake (Natrix sipedon) ! Brown water snake (Storeria delsayi) ! 5 Red-bellied snake (Storeria occipitomaculata) Ribbon snake (Thamnophis sauritus)
]*
Common garter snake (Thamnophis sirtalis) > ] Smooth carth snake (Haldea valeriae) l Eastern hognose snake (Heterodon. platyrhinos) " Eastern ringneck snake (Diadophis punctatus) Worm snake (Carphophis amoenus)
Black racer (Coluber constrictor)
.O Eastern coachwhip (Fbsticophis flagellum)
Rough green snake (Op_heodrys aestivus) , Corn snake (Elaphe guttata,g,uttata) Environmental Report ; Supplement No. 1. eu--- i r n.e ww e rs, wemr -w
i H. B. Robinson Unit No. 2 s2.7e-3 Black rat snake (Elaphe obsoleta obsoleta) Gray rat snake (Elaphe obsoleta spiloides) Pine snake (Pituophis melanoleucus) Prairie kingsnake (Lampropeltis calligaster) Common kingsnake (Lampropeltis getulus) Milk snake (Lampropeltis doliata) Scarlet snake (Cemophora coccinea) Crowned snake (Tantilla coronata) Copperhead (Agkistrodon contortrix) Cottonmouth (Agkistrodon piscivorus) Pigmy rattlesnkae (Sistrurus miliarius) Timber rattlesnake (Crotalus horridus) Eastern diamondback rattlesnake (Crotalus spp.) Salamanders and Newts Greater siren (Siren lacertina) Spotted salamander (Ambystoma maculatum) Marbled salamander (Ambystoma opacum) Tiger salamander (Ambystoma tigrinum) Newt (Diemictylus viridescens) ' O. Amphiuma (Amphiuma means) Dusky salamander (Desmognathus fuscus) Slimy salamander (Plethodon glutinosus) - Mud salamander (Pseudotriton montanus) Two-lined salamander (Eurycea bislineata) Long-tailed salamander (Eurycea longicauda) _ Toads Common American toad (Bufo terrestris) Woodhouse's toad (Bufo woodhousei) Frogs Cricket frog (Acris gryllus) Spring peeper (Hyla crucifer) Pinewoods treefrog (Hyla_ femoralis) Barking treefrog (Hyla gratiosa) Little grass frog (Hyla ocularis) Gray treefrog (Hyla versicolor) Chorus frog (Pseudacres nigrita) Bullfrog (Rana catesbiana) Green frog (Rana clamitans) Leopard frog (Rana pipiens) Environmental Report Supplement No. 1 a
i H. R. Robinson Unit No. 2 s2.7a-4 I l Mammals Opossum (Didelphis marsupal_ia) t Southeastern shrew (Sorex longirostris) Short-tailed shrew (Blarina brevicauda) Least shrew (Cryptotis parva) Eastern mole (Scalopus aquaticus) Little brown myotis (Myotis lucifugus) ' Silver-haired bat (Lasionycteris noctivagaus) Eastern pipistrelle (Pipistrellus suliflavus) Big brown bat (Ef tesicus fuscus) Red bat (Lasiurus borealis) lloary bat (Lasiurus cinereus) Evening bat (Nyct_iccius humeralis) Rafinesque's big-eared bat (C_o rynorhinus rafinesquii) Eastern Cottontail (Sylvilagus floridanus) Marsh rabbit (Sylvilagus palustris) Gray squirrel (Sciurus carolinensis) Fox squirrel (Sciurus niger) Southern flying squirrel (Glaucomys_ volans) ' 1 Beaver (Castor canadensis) Marsh rice rat (Oryzomys palustris) Eastern harvest mouse (Reithrodontomys humulis) i White-footed mouse (Peromyscus leocopus) Cotton mouse (Peromyscus gossylinus) ) i O Colden mouse (Peromyscus nuttalli) llispid cotton rat (Sigmodon hispidus) { I i Pine vole (Microtus pinetorum) { Muskrat (Ondatra zibethicus) j Norway rat (Rattus norvegicus) Black rat (Rattus rattus) , , House mouse (Mus musculus) l Red fox (Vulpes fulva) l Gray fox (Urocyon cinerecargenteus) l Black bear (Euarctos americanus) Raccoon (Procyon lotor) Long-tailed weasel (Mustela frenata) Mink (Mustela vison)_ , i Striped skunk (Spilogal_e putorius) ! , River otter (Lutra canadensis) f Bobcat (Lynx rufus) l White-tailed deer (Odocoileus_ virginianus) f
.j j
O l l Environmental Report , Supplement No. 1 1
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H. B. Robinson Unit No. 2 n2.7b-1 O Question 2.7b Provide a copy of the student report on Lake Julian.
Response
The student report was provided directly to Dr. Mike Novick, Argonne National Laboratory. (Letter dated December 19, 1972). O Environmental Report , Supplement No. 1 l
H. B. Robinson s2.7c-1 Unit No. 2
(:)
I r Question 2.7c Provide information on fish stocking programs with threadfin shad and striped bass-white bass hybrids since 1968. Response t The fish stocking program at Lake Robinson is being conducted by 'the Fish Division of the South Carolina Wildlife Resources Department. In 1973, some 800,000 two-day old hybrid fry were stocked in Lake Robinson bringing the total number (since 1967) to 1,650,000, i During 1971, 2,500 threadfin shad were stocked. Plans were to , stock threadfin shad again in December, 1972; however, they were not available at this time. According to Mr. Logan of the South Carolina Wildlife Resources Depart-ment threadfin shad wf.11 be stocked as they become available, probably in January , or February 1973. Also, a sampling program was performed in the Lake during ; December, 1972, and no hybrid striped bass x white bass or threadfin shad were l collected. d P I i L f O , Environmental Report Supplement No. I j
H. B. Robinson Unit No. 2 s3.3-1 0 3.3 Plant Water Use r Question 3.3 - Provide information on the qualitative use of water at the plant with indication of flows to and from each use category during the various conditions of reactor operation and shutdown. Indicate the quality of the i water from each system before it enters the general water discharge system as vell as that of the general discharge system. Include water for sanitary as well as for industrial purposes, f l
Response
In the operation c,. Robinson Unit No. 2,some chemical wcetes are produced in the processir.g of high quality feedwater and in the operation of certain auxiliary systems. These chemicals include corrosion products such as iron and copper, corrosion inhibi tors such as potassium chromate and sodium phosphate; acids and bases such as boric acid, sulfuric acid, sodium hydroxide, () lithium hydroxide (Li 70H) and small quantities of various chemicals used in the plant laboratory. Figure 3.3-1 is a functional flow diagram of water uses at H. B. Robins < 'init No. 2. The following paragraphs discuss the water uses and chemica: - s outlined in Figure 3.3-1. Tabic s3.3-1 summarizes the plant water use. Line A. The fire water system is supplied by two pumps. The fire water pump and the emergency fire water pump each have a capacity to supply water at a rate of 2500 gpm for a combined maximum capacity of 5000 gpm. Under normal plant operatiog no water is used and no chemicals are introduced into the water. l 11 7 B. I The condenser water is supplied by the circulating water pumps at a rate of 482,100 gpm. The water flows through the condenser tubes for cooling of () the exhaust steam leaving the turbines. In the cooling process, there is an 18 F temperature rise in the wate- being d!scharged into the canal. Environmental Report Supplement No. 1
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1 F. B. Robinson l Unit.No. 2 s3.3-2 () A chlorinating system capability is provided for use when necessary to inhibit the growth of algae in the condenser and the circulating water tunnels. t j This system uses sodium hypochlorite and would normally be operated for two 30-minute cycles per day during June, July, and August. Chlorine residuals in the l water leaving the condenser will be controlled so that concentration would not exceed more thar 0.5 ppm. The residual is further dissipated in the discharge canal. so that no more than a trace of chlorine is in the lake. Minute particles of corroded materials may also be passed into the lake due to corrosion of the circulating water system materials. To date, the chlorinating system has not been utilized for H. B. Robinson Unit No. 2. If it is ever deemed necessary, it would be operated in accordance with the above description. + Line C. The service water is supplied by the service water pumps with a - design capacity of 32,000 gpm. Under normal plant eperatior., 24,000 gpm is - suppled by three of the service water pumps. The service water is used to supply the water needed to cool the component cooling water and a 14 F temperature rise () occurs before the water is discharged to the canal. The system also incorporates the chlorinating system explained in the preceding paragraph. hjne D y . The water uses under the miscellaneous section consist of such , systems as the water coolers, lab sinks, washing of machinery, and emergency seal water at the intake structure. This water consists of well water and is , not processed but sent directly to the storm drains. [ t Line D., , The Robinson sewage and sanitary waste treatment cystem consists ! of a 3000 gpd septic tank, sand filter, and chlorine contact chmiber . The > wastes are collected and pumped to the septic tank where the solids are allowed , to settle and undergo aerobic digestion. The septic tank produces an odorless } 11guld effluent and a granular sludge which is accumulated in the tank. The ; i sludge-is periodically removed for offsite disposal in accordance with state and local regulations. The liquid ef fluent from the septic tank drains l () from the tank through the sand filter and is collected and chlorinated before ; being discharged into the condenser cooling water system canal. The removal of f I i Environmental Report Supplement No. 1
H. B. Robinson s3.3-3 ) Unit No. 2 l l O solids and reduction in BOD, as a result of this treatment, is in excess of ) 90%. Permit No. 216, issued by the South Carolina Pollution Control Authority on - May 15, 1961, covers the operation of the sewage treatment system and the l discharge of its ei!.uent into the condenser cooling water system. { ! Lines Ey and E 2 The turbine and reactor cycles are supplied by well water that has been demineralized by the makeup water demineralizers. Under normal plant ; operation, some leakage of reactor secondary coolant and turbine coolant watt._ escapes from the system through valve seals, packing, and pump seals. Steam generator blowdown is processed through the liquid radioactive waste processing system or discharged from a flash tank to the circulating water system in the i absence of radioactive contamination. The steam generator blowdown water also l contains some phosphates which are used to control scaling. Because of the ( t extremely small quantities of phosphate that are discharged and the natural low ; le.els of phosphate in the lake water supply, this disposal does not have any-discernible effect on the environment. Some potassium chromate waste is evolved through valve leakage and maintenance activities. This waste is collectrl and processed for disposal through Line E3 . The release of chromate through Line E 2 is covered by liquid waste disposal Parmit No. 1732, issued November 25, 1970, t c by the South Carolina Pollution Control Authority and limits the amount of chromates in the lake to 50 ppb and is not in excess of the U. S. Public Standards for drinking water. The liquid radioactive waste treatment consists of a system capable of collecting, storing, and processing radioactive or potentially radioactive waste ., (gases, liquids, and solids) for of f site shipment or disposal. The vaste l processing systen enables the plant to comply with all applicable regulations for the release of radioactivity to the environment. Radioactive fluids entering the waste process:.ng system are ; collected in tanks until determination of subsequent treatment can be made. , They are analyzed to determine the quantity of radioactivity, with periodic' [ isotopic identification and then processed. There is no recycle of liquids Environmental Report - Supplement No. 1
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H. B. Robinson s3.3-4 Unit No. 2 in the CVCS System. All liquids are processed through the boric acid evaporator and discharged to the circulating water system. Most of the liquids (85 percent) which are shown as discharged through E2 w uld come from the CVCS. Processed waste from waste disposal is discharged through a monitored line into the circulating water discharge system. Line F 1
; The resteneration water contains sodium hydroxide (NaOH) and I 4 l sulfuric acid (H 0 ) which are used to regenerate the makeup water demineralizer, q 2 4 j After use, these solutions are neutralized and subsequently discharged into the l-4 l service water system where dilution of the mineral water can take place before entering the lake.
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H. B. Robinson Unit No. 2 83.3-5 O TABLE s3.3-1 WATER USAGE DATA Design Normal Line* Capacity Use A 5,000 gpm 0 B 482,100 gpm 482,100 gpm C 32,000 gpm 24,000 gpm D 3,538 gpd 3,538 gpd E 250 gpm 10 pm Ay 5,000 gpm 0 B 482,100 gpm 482,100 gpm 7 C 32,000 gpm 24,000 pm 1 D 538 gpd 538 gpd 1 D 3,000 gpd 3,000 gpd 2 E 25,000 gpd 7,382 gpd E 5,750 gpd 4,673 gpd F 75 gpm 710 gpd
*These lines are shown on Figure 3.3-1 of Supplerient No. 1.
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O O O LAKE WELL WATER WATER n E i SANITARY WATER A B C MAKE UP WATER FIRE SERVICE WATER WATER I SEWAGE REGENERATION TYPE USE WATER . CONDENSER WATER MISCELLANEOUS USES TURBINE REACTOR CYCLE CYCLE
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! H. B. Robinson { Unit No. 2 s3.4a-1 i > 3.4 Heat Dissipa_ tion System Question 3.4a ; Provide information on the design of the intake'and outfall
structures for the condenser cooling water system. Include design of
. screens, trash handling systems, canal intersection at lake, etc. Pro-vide necessary sketches or drawings which describe these, i r
Response
The intake structure is a reinforced concrete structure that
. contains the circulating water pumps which provide water to the condenser < cooling system. The structure also contains traveling water screens. Slots are installed in the concrete for the future installation of stop logs, fine log screens, and coarse log screens. Figures 3.4a-1 and 3.4a-la show the intake structure and a cross sectinn of the structure. 1 The sealwell structure is made from reinforced concrete and is dec1gned to reduce the velocity of the water entering the discharge canal. The structure combines the use of splitter walls and vanes to chante the direction and reduce the velocity of the water to prevent eroston and rapid flowing water into the discharge Cand1. Figures 3.4a-2 ; and 3.4a-2a show the scalwell structure. The traveling water screens consist of a motor and chain which drive the continuous screens that are cleaned by spraying water at 50 psi through them. All trash removed ftom the screens is washed through a : concrete trough to a junction and then through a pipe to the storm drains. The traveling screens are shown on Figure 3.4a-3. , The intersection of the discharge canal and the lake is a weir s made from reinforced concrete and is designed to prevent erosion of the canal sides and bottom. The intersection is shown on Figures 3.4a-4 and 3.4a-4a. , (:) The discharge canal, as sF3wn on Figure 3.4a-5 is 115 feet wide, j 16 feet 6 inches deep and the normal water depth is 13 feet. Environmental Report Supplament No. 1
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H. B. Robinson s3.4b-1 Unit No. 2 .
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i Question 3.4.b Provide information on flow velocity and transit time of water , in the discharge canal during full power operation of H. B. Robinson Units ) 1 and 2. l l l 4 l Response 'j During full power operation of H. B. Robinson Units 1 and 2, the flow velocity in the discharge canal is approximately 1.75 feet per second and the transit time of water in the discharge canal is approximately 3.5 hours. i ! I f (l> I Environmental Report Supplement No. 1
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I i l 1 H. B. Robinson s3.4c-1 Unit No. 2 ! Question 3.4c 0 Provide information on inside dimension of condenser tubes and water velocity within them.
Response
The condenser tubes have an inside diameter of 0.92 inches and - a water velocity of 7.0 fps. Figure 3.4c-1 shows a cross-section of a i condenser tube. ) i i i !O i, l : P I b 7 i F O , Environmental Report Supplement No. 1
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H. B. Robinson Unit No. 2 s3.5a-1 O 3.5 Radwaste Systems Question 3.5a Furnish copies of reports giving monthly releases of radio-isotopes in liquid and gaseous effluents. Give isotopes breakdown if available.
Response
Table s3.Sa-1 is a copy of radioactivity released in liquid and gaseous effluents with isotopic breakdown for the period of January 1, 1972, through June 30, 1972. Monthly effluent summaries are included in the four Operating Reports for the periods September 20, 1970, to March 20, 1971, March 20, 1971, through September 30, 1971, and October 1, 1971, through March 31, 1972 and April 1, 1972 through September 30, 1972. These reports have been submitted to the AEC. During the period covered by these four Operating Reports, radioactive effluents were low and isotopic identification was not required by the Tech Specs in the Operating License. Consequently, no data is available regarding the isotopic composition of these effluents. l i l . l O l I l Environmental Report Supplement No. I l
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H. B. Robinson s3.5b-1 Unit No. 2 O guestion 3.5b Furnish distances from plant to site boundary, nearest occupied dwelling, and nearest herd (> 1 cow) in the 16 principal compass directions. Describe milk sampling program.
Response
Distances from the plant to the site boundary and nearest occupied dwelling are shown on Table 83.5b-1. As shown on this table, the nearest site boundary and nearest occupied dwelling are south of the plant, 1400 and 1500 feet respectively. The nearest dairy farms, presently in operation, are seven miles to the east and nine alles to the southwest of the site. There are no lactating cows within a two-mile radius of the site (1). Since the nearest dairy herd is seven miles from the plant, the radiological environ-
~
mental program does not include milk sampling. 1 (1) Personal conversation with Mr. Spivey Rowell, local dairy inspector for () South Carolina State Board of Health and personal observation of plant employees. l 1 I Environmental Report Supplement No. 1
H. B. Robinson s3.5b-2 Unit No. 2 O Table s3.5b-1 Distances from H. B. Robinson Plant l Nearest Site Nearest S e c t o r_ Boundary (ft.) Dwelling (ft.) N 13,750 15,250 NNE 6,500 8,250 NE 5,750 6,000 ENE 4,500 4,750 E 4,500 4,750 ESE 2,000 3,250 SE 1,600 5,000 SSE 1,600 1,750 1,400 1,500 S SSW 2,000 2,150 SW 2,000 2,500 WSW 1,750 2,000 W 2,750 3,000
'l WNW 3,250 3,500 l l
NW 6,250 7,000 NNW 7,500 15,000 J O Environmental Iteport
. Supplement No. 1
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H. B. Robinson s3.5c-1 j Unit No. 2 O Question 3.5c Describe operating procedures that gover, use of extended treat-ment system for exhaust air from ' elected areas in the auxiliary building. l
Response
The extended treatment system (HVE-5) for exhaust air from selected areas in the Auxiliary Building is designed to exhaust air from areas within the Auxiliary Building where potential iodine activity could exist through HEPA and charcoal filters before entering the plant vent. The system is operated whenever iodine activity is present in any of the areas served by the system as determined by air sampling. In addition to the above require-ment, this exhaust system would be utilized during the recirculation phase of the safety injection system. (3
V l
[ r 4O V Environmental Report Supplement No. 1
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i H. B. Robinson s3.5d l Unit No. 2 () Question 3.5d ] Response to question 17 for Source Term Data (Jetter J. A. Jones l to E. J. Bloch, June 7,1972) indicates that containment air is purged through HEPA filters. Figure 5.3.3-1 of the FSAR indicates no treatment of containment purge. Please reconcile the apparent discrepancy. !
Response
Figure 5.3.3-1 of the FSAR is correct; containment purge does not pass through HEPA filters. l l l t O , Environmental Report
Supplement No. 1
" * "~
H. B. Robinson Unit No. 2 O Question 3.5e Furnish details about the history of containment purges. Also furnish information from plant records regarding radiation levels (direct and air concentrations) measured in the containment building. To what extent W e2 the recirculation filters operated.
Response
The containment is purged prior to and during maintenance in the containment as required to reduce temperature and airborne activity. After the initial startup period, it was anticipated that containment purges would exceed four times per year. Also, the containment is purged from 0.5 to three minutes each month in order to perform the periodic test of the containment isolation system. From January 1, 1972 through October 31, 1972 there were a total of seven containment purges lasting from a few minutes to several hours and a total of 11 purges for periodic testing which were typically of one minute duration. Total activity released during these purges were 22 curies of gaseous activity, 0.83 millicuries of particulate activity, 1.56 curies of tritium activity, and 0.039 curies of gross iodine activity. Radiation levels in the containment are monitored using area monitoring badges (TLD), as well as other areas within the plant. Results of these area monitoring badges for a six-month period are shown on Table s3.5e-1. At the present time, the recirculation filters in the Containment Building are run continuously. These recirculation filters contain both HEPA and charcoal filters. O Environmental Report Supplement No. 1
e3.5e-2 Tabic s3.5c-1 MONITOR BADCE RESULTS
l h '
1972 Badge No. Location April May June July August Sept. 2001 North Fence 0 0 0 0 20 0 l 2002 South Fence 0 0 0 0 0 0 2003 East Fence 0 0 0 0 0 0 2004 West Fence 10 0 0 10 0 0 ; 2005 Top Unit No.1 0 0 0 10 0 0 2006 Bottom Unit No.1 0 20 0 10 10 0 2007 Maintenance Shop 20 10 0 0 10 0 2008 Hot Lab. 10 70 120 50 110 60 2009 Charging Pump Rm. 490 2720 4620 3110 5010 1880 2010 Demineralizer Rm. 670 600 2200 1580 3350 1360 { l11 Waste Evap. Rm. 570 10350 Lost 11440 8210 5550 2012 Boric Acid Evap. Rm. 480 1300 1450 2360 2870 930 2013 Control Rm. 0 0 0 0 0 0 2014 C. v. On Pressurizer cubical 13720 820 13810 13170 23830 14930 2015 C. V. Polar Cran Wall, Across from Reg Ex. 0 4530 11820 10020 12400 4200 2016 volume Control Tank Ra. 10370 5370 47710 26450 58000 47690 Boron Analyzer Rm. 2017 280 280 320 540 1350 350 2018 Waste Disposal System Boric Acid Panel 0 50 180 80 120 60 2019 C. V. Seal Table Rm., on 2nd Elev. 13350 3800 59160 29430 98570 43580 2020 Spent Fuel Storage Area 10 0 20 0 20 0 2021 New Fuel Building 460 330 510 720 2790 100 .2022 H. P. Office 0 90 70 10 40 0 : 2023 not Machine shop 10 50 110 110 140 70
*All Readings Are In MREM
l H. B. Robinson s3.5f-l ] Unit No. 2 O Question 3.5f Describe the plant history of primary coolant leakage (water, steam) to the containment and elsewhere. Describe its collection and treatment. Response ; i Total primary coolant leakage is determined daily at the Robinson Plant. During the first 10 months of 1972, this leakage ranged from !. 0.1 gpm to 0.6 gpm with an average of 0,3 gpm. At 1 cast 50 percent of this l leakage can be associated with leakage of the charging pump seals. The 1 i leakage from the charging pumps is collected and returned to the CVCS holdup i tanks. This leakage is subsequently processed through the boric acid l evaporators. Of the total leakage, another 30 percent would be leakage in the Auxiliary Building, most of which would be associated with sampling. Leakage in the Auxiliary Building is collected in the waste holdup tank and is processed
; through the waste evaporator prior to discharge. Leakage to the Containment 4
(} Building accounts for the remaining 20 percent. Leakage in the containment is collected in the reactor coolant drain tank which is processed through the CVCS system or the building sump which is processed through the waste processing system. 't i (:) Environmental Report Supplement No. 1
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E~ I H. B. Robinson Unit No. 2 O Question 3.5g Describe process monitoring on release line from CVCS monitor tanks.
Response
The CVCS monitor tanks are discharged through the same release line as the waste condensate tanks. This line is monitored by the Waste Disposal System Liquid Effluent Monitor (R-18) as described in Section 11.2.3 of the FSAR. O l i i l O Environmental Report Supplemental tio. 1
H. B. Robinson-Unit No. 2 s3.Sh-1 O Question 3.5h Furnish the following information about process radiation monitor-ing of gas and liquid effluent streams:
1. Sensitivity limits in terns of expected radionuclide raix;

2. Trip levels and alarm setpoint's and basis for setting;

3. Operation response to alarms or trips:

4. Any changes (actual or expected) from monitors described in Section 11 of the FSAR.
Response
1. The radiation monitoring system is described in detail in Section 11.2.3 of the FSAR. Included in the description of the instrumenta-tion are sensitivity limits of the individual instruments. Sensitivity limits are based on an individual isotope rather than an isotopic mix since the radionuclide mix is variable and is controlled by many factors, such as percent failed fuel and/or primary system leakage.

2. Trip levels and alarm set points and the basis for these settings are as follows:
R-ll Containment or Plant Vent Air Particulate Monitor This monitor measures the air particulate radioactivity in the containment with an additional function to ensure that the release rate during containment purge does not exceed 10CFR20 and technical specifications. The alarm closes the purge valves, terminating the purge. The alarm setpoint, as calculated below, is to be used during containment purging and does not have any real basis at other times. The alarm point is based on sampling from the containment atmosphere during the purging operation. During times other than purging, the alarm should be set at MPC for unidentified activity in a restricted area of 3 x 10~9 pci/cc. The alarm setpoint is calculated using the following (1) Containment purge rate = 35,000 cfm (1.65 x 10 cc/sec) i Environmental Report Supplement No. 1
H. B. Robinson i Unit No. 2 a3.Sh-2 (2) MPC for particulates in an unrestricted area
= 1.43 x 10 -13 ci/cc (contains the 1/700 factor required by the technical specifications).
(3) Annual average X/Q = 2 x 10 -5 sec/m (4) Setpoint is calculated as follows:
-13 c17,3 x 106 uci/ci x 60 sec/ min -10 1.43 x 10 = 4.35 x 10 uci/cc 2 x 10 -5 g, f,3 x 3.5 x 100 ft /3 min x 2.83 x 10 0 cc/ft R-12 Containment or Plant Vent Gaseous Monitor As with R-11, this monitor measures the gaseous activity in the ,
Containment Building with the additional function to ensure the release rate of gaseous radioactivity Nring purging does not exceed limits set by the technical specifications and 10CFR20. The alarm closes the purge valves, j terminating the purge. The alarm point, as calculated below, is to be used during containment purge. This monitor does not have the required sensitivity to monitor the containment atmosphere at the MPC level for A-41 in a restricted ; area (4 x 10-8 uci/cc). The alarm setpoint is calculated using the following assumptions: (1) Containment purge rate = 35,000 cfm (2) MPC for noble and activation gases of 3 x 10~ uci/cc in an unrestricted area. (3) Annual average X/Q = 2 x 10 -5 sec/m 3
^
(4) Setpoint is calculated as follows: 3 x 10
-8 ci/m x 10 6 ci/ci x 60 sec/ min = 9.1 x 10 ~ uci/cc -5 3 0 3 0 3 2 x 10 sec/m x 3.5 x 10 ft / min x 2.83 x 10 cc/ft O
Environmental Report Supplement No. 1 ,
H. B. Robinson l Unit No. 2 s3.Sh-3 l i () R-14 Plant Vent Gas Monitor l P The purpose of this monitor is to detect radioactive gases being discharged through the plant vent and to ensure that releases to the environ-ment are maintained within limits. The alarm set point is calculated using the following assumptions: (1) Annual average X/Q = 2 x 10 -5 cc/m 3 (2) Flow rate up plant vent = 50,000 cfm (3) MPC for gaseous activity at the site boundary = 3 x 10-8 ci/cc (4) Setpoint is calculated as follows: 3 x 10 -8 ci/m x 10 6 ci/ci x 60 sec/ min 3 , 3
= 6.4 x 10 -5 uci/cc 2 x 10-5 sec/m x 5 x 10' ft3 / min x 2.83 x 10* cc/ft O R-15 Condenser Air Ejector Gas Monitor The purpose of this monitor is to give an indication of primary-to-secondary. leaks and ensure that (in such cases) limits at the plant boundary are not exceeded. An alarm setting equal to one percent of technical specifications should be used to give an early warning of leaks and to divert the effluent to the plant vent for iodine and particulate monitoring as well as gaseous monitoring. The setpoint is calculated using the following assumptions:
(1) Annual average X/Q = 2 x 10~ sec/m (2) MPC for gaseous activity = 3 x 10 -8 cfjcc (3) Exhaust rate from air ejector = 45 cfm l ( i Environmental Report Supplement No. 1
H. B. Robinson ; Unit No. 2 s3.5h-4 ) 1 0 (4) Setpoint is calculated as follows:
-8 3 6 <
3 x 10 ci/m x 10 pei/ci x 60 sec/ min x .01
- 7.1 x 10 ~ pci/cc I 2 x 10 -5 3 3 0 sec/m x 45 ft / min x 2.83 x 10 cc/ft 3
R-16 Containment Fan Cooling k'ater Stonitor The purpose of this monitor is to indicate a leak from the con-tainment atmosphere to the containment fan cooling water during a loss-of-coolant accident. Upon indication of an alarm, each heat exchanger should be sampled to determine which unit is leaking. There is no real basis for determining a setpoint for this monitor. Westinghouse has shown a level
-5 o f 5 x 10 uci/cc which is sufficiently above the maximum sensitivity of the instrument to avoid false alarms. The setpoint should be based on co-60 activity. From the graph, the setpoint corresponding to Co-60 -5 activity of 5 x 10 ci/cc is 3000 cpm.
R-17 Component Cooling Liquid Monitor This monitor serves to indicate a leak from primary coolant to the component cooling system and closes the component cooling surge tank vent before technical specification offsite dose limits are ex-ceeded. The primary function of this monitor should be to give early noti-fication of a primary system leak to the component cooling system. A setting of 5 x 10
-5 ci/cc should be adequate to do this and is sufficiently above the maximum sensitivity of the instrument. In addition, this will close the ,
surge tank vent before reaching 10 percent of offsite release concentrations. This conclusion is arrived at by making the following conservative assumptions: (1) Offsite MPC = 3 x 10 -0 uci/cc (2) There is an instantaneous surge volume in the component cooling system of 1000 gallons. (3) Air activity in the vent is the same as the activity of the water. Environmental Report [ Supplement No. 1
f H. B. Robinson Unit No. 2 s3.Sh-5 l O
-5 3 (4) Annual average X/Q = 2 x 10 sec/m , -8 6 3 x 10 ci/m x 10 CI/CI = 4 x 10 ' pel/cc 2 x 10-5 , j 3 6 3.75 x 10 cc/sec :
I a R-ld Waste Disposal Liquid Effluent Monitor The purpose of this monitor is to continuously monitor liquid f releases f rom the plant and prevent the release of radioactive liquid f waste by automatically closing the discharge valve when the alarm setpoint ; is reached. The controlling release limit is 26 millicuries per day to j the lake of unidentified beta-gamma activity. If we continuously discharged so as to maintain a concentration of 1 x 10- uci/cc in the discharge canal ; with the dilution of all three circulating water pumps running, we would dis- - charge a total of 26 millicuries in a 24-hour period. If, however, we j administrative 1y maintain this 26 millicurie per day limit, then we can go , up to 1 x 10- pci/cc in the circulating water system with periodic releases. " () Assuming this MPC of 1 x 10- pei/cc in the circulating water canal, then ' the setpoint actually has two variables: (1) the liquid discharge flow rate and (2) the dilution water flow rate. In actual practice, this alarm r point should be calculated and set for each release. A typical example , would be a waste discharge flow rate of 20 gpm and a circulating water flow with one pump running of 175,000 gpm. 1 x 10 -7 pei/cc x 175,000 gpm = 8.8 x 10-0 l pel/cc i 20 gpm ! l If, however, the waste discharge flow rate was 10 gpm and all three circu- l lating water pumps were running with a J11ution flow of 482,000 gpm, then the setpoint would be:
-7 1 x 10 pci/cc x 482,000 rpm = 4.82 x 10 pei/cc 10 gpm i
1 Environmental Report Supplement No. 1 i i 1
H. B. Robinson Unit No. 2 s3.Sh-6 l i -O R-19 Steam Generator Liquid Sampic Monitor i 4 The purpose of this monitor is to indicate a primary to secondary leak and autotaatically close the blowdown and sample isolation valves and blowdown tank spray valve when the alarm level is reached. 4 The setpoint should be calculated considering the limiting release to the lake in the blowdown liquid. Since it is desirable to detect leaks as early as possible, the monitor should be set at 10 percent of our liquid release limit. This will give an earlier indication of leaks and will limit releases to the lake to less than 10 percent. The following assump-l tions are used in the calculation: (1) Alarm will be set at 10 percent of release limits. Since this is considered a continuous release, the limit will be 2.6 mei per day. t (2) Blowdown rate = 12.5 gpm per steam generator for a total of 37.5 gpm. (3) Setpoint is calculated as follows:
-5 2.6 x 10 vei/ day x 0.1 = 1.3 x 10 17 3 3 1.44 x 10 min / day x 37.5 gal / min x 3.8 x 10 cc/ gal ;
t R-20 Fuel Handling Building Basement Exhaust Monitor This monitor monitors the exhaust ventilation from the Fuel l Handling Building basement and gives an indication of a leak in the gas decay or liquid holdup tanks. Upon reaching the alarm, this monitor will automatically shut down the ventilation system (HVE-14) in this area. This monitor should be set at 10 percent of the offsi te MPC in order to get an early warning of Icaks and have time to take corrective action before reaching limits. The setpoint is calculated using the following assumptions:
-8 (1) MPC for gaseous acti4rity at site boundary = 3 x 10 ci/cc P
Environmental Report Supplement No. 1
,.,g., . , , , , , , , . , , , , , , , , _ ,, ., ,
l H. B. Robinson. Unit No. 2 s3.Sh-7 (2) Annual average X/Q = 2 x 10~ sec/m 1 1 (3) Normal exhaust flow rate for lIVC-14 = 10,200 cfm 1 (4) Setpoint is calculated as follows: h
-8 3 6 3 x 10 ci/n 10 ci/ci x 0.1 x 60 sec/ min = 3. 2 x 10 ~ pei/cc 4 3 2 x 10~ sec/m x 1.02 x 10' ft /nin x 2.83 x 10 jf R-21 Fuel Handling Building Upper Level Exhaust Monitor This monitor monitors the exhaust ventilation from the upper levels of the Fuul nandling Building, including the new and spent fuel storage areas. Upon reaching the alarm setpoint, the monitor will auto-matica11y shut down the ventilation system (HVF-15). As with R-20, this monitor should be set at 10 percent of MPC for the same reasons. The set-(} point is calculated using the following assumptions: -8 (1) MPC for gaseous activity at site boundary - 3 x 10 uci/cc (2) Annual average X/Q = 2 x 10 -5 sec/m 3 ;
(3) Normal Exhaust flow rate for HVE-15 = 13,400 cfm ; l i (4) Setpoint is calculated as follows: l l 6 3 x 10~ ci/m x 10 ci/ci x 0.1 x 60 sec/ min -5
= 2.4 x 10 ff -5 3 2 x 10 sec/m x 13.4 x 10' ft / min x 2.83 x 10' cc/ft Plant Vent Iodine and Particulate Monitors These monitors continuously sample the plant vent for particu-late and iodine activity. The sample is drawn through a particulate filter
() paper, and then an activated charcoal cartridge. These filters are removed Environmental Report Supplement No. 1
~ -_ . .-_ _ _ ._- ._
H. B.-Robinson Unit No. 2 s3.Sh-8 and counted in the counting room on a regular schedule and serve as the permanent record for offsite releases of particulate and iodine activity. The maximun permissible concentration of particulates or lodines in the stack is calculated using the following assumptions: (1) MPC at the site boundary = 1.43 x 10 -13 ci/cc for both iodine and particulate activity.
-5 3 (2) Annual average X/Q = 2 x 10 sec/m (3) Normal flow rate in plant vent = 50,000 cfm 1.43 x 10 -13 ci/m x 10 6 ci/ci x 60 sec/ min -10 = 3 x 10 ci/cc -5 3 0 2 x 10 sec/m x 5 x 10' ft / min x 2.83 x 10 cc/ft The particulate and iodine monitors should each be set to alarm O at a level equivalent to sampling either particulate or iodine activity at the average annual release rate (3 x 10~ uci/cc) for a period of eight hours - 480 min (480 MPC-min); and assuming a sampling flow rate of six cfs,- the alarm point should be: -10 3 x 10 ci/cc x 480 min x 6 ft / min x 2.83 x 10' cc/ft x 2.22 6
x 10 dpm/pci = 5.43 x 10 dpm As shown above, the particulate and iodine monitors should be set to alarm when a total of 5.43 x 10' dpm has been collected on either filter. Corresponding alarm points for each monitor are as follows: (1) The particulate monitor has a SC-2B beta scintillation detector with an approximate efficiency of 32 percent. Using this 32 percent efficiency and the 5.43 x 10 dpm alarm level, the corresponding setpoint on the count rate meter is 1.74 x 10' cpm. O Environmental Report Supplement No. 1
H. B. Robinson Unit No. 2 s3.5h-9 O (2) The iodine monitor has a SC2-1S ganma scintillation detector with a gross ef ficiency of approximately 17 percent. Using this j 17 percent efficiency and the 5.43 x 10 dpm alarm level, the corresponding setpoint is 9.2 x 103 cpm. .
3. All process radiation monitoring instrumentation that monitors gaseous and liquid effluents has automatic response which would terminate the release if the setpoint is exceeded. This automatic response for each instrument is described in detail in Section 11.2.3 of the FSAR. 5 P

4. The only change in process radiation monitoring instrumenta-tion from that described in Section 11 of the FSAR is the addition of a particulate and iodine monitor on the plant vent. This monitor was manu-factured by Nuclear Measurements Corp. and is their Model No. AM-22I.
i O i O Environmental Report ! Supplement No. 1
H. B. Robinson Unit No. 2 O Quection 3.51 -) Furnish hastory of radioactivity levels measured in the primary and l secondary coolants. l
Response
Radioactivity levels in the primary coolant have ranged from 0.1 uci/ml to a maximum of 0.5 uci/ml during the proceeding year. Primary coolant l activities have generally increased over the past six months and generally follow a linear regression curve, y=0.00lx + 0.323 based on a least scuarea I fit. In the above equation, y is the primary system coolant activity in microcuries per milliliter and x is the day of the year using June 1, 1972 as 1. The above activities are based on counting a primary coolant sample dried on a planchet after 15-minutes decay. Seven day activities are generally about 1 percent of the 15-minute activities. ; Secondary coolant activities at the present time range from about 1 x 10 uci/ml in "A" steam generator to about 2 x 10~ uci/ml in "B" and "C" steam generators. Iodine activity in the secondary system ranges from about 2 x 10~ uci/ml in "A" steam generator to less than 1 x 10~ uci/ml in "B" and "C" steam generators. The above activities are typical of secondary { system activities since leaking tubes were plugged during the period of May 13, ; 1972 to June 5, 1972. P O : t Environmental Report Supplement No. 1 '
. - . . . _ _ . . _ _ _ _ . . _ _ _ . . . . - _ . _ . . . . . . _ . . _ . _ _ _ _ _ . _ - - _ _ . _ _ _ . ~ . _ _ . _ _ _ _ . _ _ _ _ . _ _ _
H. B. Robinson s3.5j-1 l Unit No. 2 ; f LO guestion 3.5j l j Describe downstream use of Black Creek for potable water for a ' distance of 50 miles. l i
_ Response j
[ Black Creek flows into the Pee Dee River 40 to 45 miles downstream j from Lake Robinson. There is no potable water use of Black Creek prior to its junction with the Pee Dee River. . I j- i I l a j O ; i l l l l l 1 l O Environmental Report -l Supplement No. 1 j i
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H. B. Robinson Unit No. 2 O Question 3.5k Furnish information'on volume and flows into and out of Prestwood . Lake.
Response
Exact flow information for Prestwood Lake is not available at this
time. However, there are no significant tributaries to Black Creek between Lake Robinson and Prestwood Lake. Consequently, the only difference between flows shown for Lake Robinson, as described in Section 2 of the FSAR, and Prestwood Lake flows would be the small amount of runoff between the two lakes.
For nurposes of defining the dilution canabilitv of Prestwood Lake, it should be adequate to use the flows shown for Lake Robinson. O b t ( P f (I) ! Environmental Report 4 Supplement No. 1
H. B. Robinson s3.51-1 Unit No. 2 O Question 3.51 Describe in more detail the vents and release points from which airborne or gaseous radioactive materials are emitted. Their height in relationship to adjacent buildings as well as effluent velocity and volume flow rate should be indicated.
Response
Since all release points for gaseous effluents are below the ; height cf the Containment Building, no credit has been taken for elevated releases in dose calculations for the Robinson Plant (all calculations are based on a ground release). Specific points of release of gaseous effluents , are described as follows: l 1. Plant Vent - The Reactor Auxiliary Building ventilation and the containment purge are exhausted through the plant vent. The reactor auxiliary ventilation is approximately 50,000 cfm and the containment purge is normally , 35,000 cfm. The plant vent is 54" in diameter and exhausts at elevation () 375', or 149' above ground elevation of 226'.
2. Fuel Handling Building Upper Level Exhaust - This system (l~/E-15) exhausts ventilation air from the upper levels of the Fuel Handling Building including the new and spent fuel storage areas. The flow through this system ;
l is 13,400 cfm. The system exhausts below the roof elevation (302') of the Fuel , i Handling Building. At the present time this is being revised to exhaust through the plant vent. This modification will take another approximately two months. j
3. Fuel Handling Building Lower Level Exhaust - This system (HVE-14) ;
j exhausts ventilation air from the lower levels of the Fuel Handling Building; ' 1 l including gas decay tank room, CVCS holdup tank areas, hot machine shop, and cask decon area. The system has a normal capacity of 10,200 cfm. The exhaust { r is below the roof elevation of the Fuel Handling Building. !
4. Condenser Air Ejector - This system exhausts air required to maintain a vacuum on the condenser. The normal flow is about 15 cfm with a r maximum capacity of 45 cfm. The exhaust is below the 292' elevation.
l I Environmental Report ( Supplement No. 1 l
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1" H. B. Robinson s3.51-2 ' (4 Unit No. 2
5. Steam Generator Blowdown Tank vent - Blowdown from all three steam generators is routed to a flash tank which is vented to atmosphere ;
through an 18-inch vent below the 292' elevation. The system has a maximum blowdown capacity of 12.5 gpm per steam generator with normal blow- , ,. down being about 5 gpm per steam generator. Approximately 30 percent of the liquid entering the flash tank excapes through the vent as steam. y ! i o ; i I i t i d i b l lo 3 i i i f Environmental Report j Supplement No. 1 i
I H. B. Robinson 8 * "~ Unit No. 2 .I l Question 3.5m
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j Provide location relative to Visitor's Center, nearest site boundary, and nearest dwelling of any outside storage tanks which may contain radio-j activity. Also give the capacity and expected concentrations of radionuclides i of these storage facilities. !~ j Response i Outside storage tanks which could contain radioactivity are the l 1 two CVCS monitor tanks (10,000 gal. capacity each), the refueling water storage , tank (350,000 gal. capacity) and the primary water storage tank (150,000 gal. ! capacity). All of these tanks are at the same location; directly north of the Reactor Auxiliary Building. These tanks are approxinately 1000 feet from the Visitor's Center, 1,500 feet from the nearest site boundary, and 1,600 feet. k from the nearest d' welling . The Reactor Auxiliary Building, Containment l Building, and Turbine Building are located between these tanks and the i Visitor's Center, nearest site boundary, and nearest dwelling thus providing shielding from any radiation from the tanks. Maximum expected activity in these i O tanks is about 1 x 10 ~ uci/ml. l i 9 i i b O . Environmental Report Supplement No. 1
11. B. Robinson s3.6a-1 Unit No. 2
@ 3.6 Chemical and Blocide Systems i
Question 3.6a Provide a detailed list of.all chemicals discharged into Lake Robinson indicating frequency and quantities of discharge.
Response
The chemicals discharged into Lake Robinson and their amounts are given on Table s3.6a-l. O i i l l 1 l i l i l l I l 9 . Environmental. Report Supplement No. 1
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i H. B. Robinson ~s3.6a-2 Unit No. 2 O I TABLE s3.6a-1 H. B. ROBINSON UNIT No. 2 CHEMICAL DISCHARGE ESTIMATES TO LAKE ROBINSON Concentration Quantity Chemical Prior Source (Gallons / Year) Content to Dilution Released to 6 CVCS 2 x 10 Boric Acid 0. 2 ppm Cire. Water-5 WDS (Waste 3 x 10 Chromate <1 ppb Circ. Water Disposal System) Detergent 1 ppm i Boric Acid 0.1 ppm : E 6 Steam Generator Hydrazine 8 x 10 0.02 ppm Cire. Water Ammonia 0.3 ppm Cyclohexy- 5 ppm lamine Phosphate 25 ppm , 6 Makeup Water 4 x 10 Sulfate 11,500 ppm Cire. Water Treatment Sys. Salts Sewage Treatment 1.5 x 10 Residual C1 0. 3 ppm - Circ. Water 2 O ; i Environmental Report i Supplement No. 1
H. B. Robinson s3.6b-1 i Unit No. 2 O Question 3.6b Describe methods which will be used to control chlorine residuals g at discharge canal outlet to meet EPA requirements if it becomes necessary to use chlorine in connection with the operation of Unit 2 in the future.
Response
Although the chlorinating system has not been necessary since the start-up of Unit No. 2, when a chlorinating system is in operation at Robinson Unit No. 2, samples are taken regularly from the sealwell to determine the concentration of chlorine residual. If the chlorine residual rises above 0.5 ppm, the chlorinating system will be taken out of operation until the problem can be corrected. The Company has not experienced difficulties in controlling chlorine residuals at our other plants. O i O Environmental Report Supplement No. 1
H. B. Robinson Unit No. 2 s3.7a-1 3.7 Sanitary and Other Waste Systems Question 3.7a Provide the following information: the quantity of sanitary waste discharged to the lake per day, the residual chlorine level of dis-charged sanitary waste, the biochemical oxygen demand (BOD) of the dis-charged waste. Response ! The maximum quantity of sanitary waste discharged to the lake e is approximately 3000 gallons per day and has a residual chlorine level of 0.3 ppm. Biochemical oxygen demand (BOD) has not been measured on the Robinson Plant sanitary waste effluent. However, from tests at other plants, the BOD is normally around 10 ppm for the sanitary waste effluent. (:) i i f t t Environmental Report Supplement No. 1
H. B. Robinson Unit No. 2 s3.7b-1 0 Question 3.7b Describe the disposal practices for other nonradioactive wastes (solid, liquid, and gaseous) including debris and fish from trash racks and screens in the condenser water supply system. Provide a copy of state regu-lations which control such disposal.
Response
Solid waste from the plant is transported to an open pit and burned. Such burning is controlled by Regulation No. 2A of the S. C. Air Pollution Control Regulations and Standards. Trash collected on the intake screens of the circulating water system is washed off the screens and into the storm drainage system. Waste from the makeup water demineralizer is discharged to the circulating water system. I 1 A copy of state regulations on on open burning is included on pages s3.7b-2 and s3.7b-3. l l 1 I l l 1 Environmental Report Supplement No. 1
_ . - - _ - . - . . . .- ~ _ - . - k H. B. Robinson s3. 7b -2 Unit No. 2 REGUId. TION NO. 2A-OPEN BURNING SECTION I - PROHIBITION OF OPEN EURNING Open burning is prohibited except as provided below: ) Open burning may be conducted in certain situations if no " undesirable . levels" are or will be created. The authority to conduct open burning under this Regulation does not excmpt. or excuse the person responsible for the burning from the consequences of or the damages or injuries resulting from the burning and does not excupt or excuse anyone from complying with other applicable inws and with ordinances, regulations, and orders of governmental entities having jurisdiction, even though the burning is other-wise conducted in compliance with this Regulation. 'The situations which are exempt from this Regulation and the conditions for exempt 58n"are enumer-ated in the following paragraphs (A--J): A. Open burning of leaves, tree branches or yard trimmings originating on the premises of private residences or dwellings of four families ,
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or less, and burned on those premises. B. Open burning in connection with the preparation of food for immediate consumption. C. Campfires and fires used solely for recreational purposes or for ceremonial occasions. O a- r1rc verve e17 eet te re=eet 1 ed rer Pecitic retest me seme c purposes in accordance with practices acceptable to the South Carolina , Pollution Control Authority. , E. Fires purposely set to agricultural lands for purposes of disease, weed and pest control and for other specific agricultural practices acceptable to the South Carolina Pollution Control Authority. F. Open burning of trees, brush, grass and other vegetable matter for game management purposes in accordancq with practices acceptable to the South Carolina Pollution Control Authority. G. Open burning in other than predominantly residential area for the purpose of land clec. ring or right-of-way maintenance. This will be exempt only if the following conditions are met:
1. Prevailing winds at the time of the burning are away from any city or town, the pubient air of which may be significantly affected by smoke from the burning.

2. The location of the burning is at least one thousand (1,000) f eet from ar.y dwelling located in a predominantly residential area other than a dwelling or structure located on the property on which the burning is conducted.

3. The amount of dirt on the material being burned is minimized. l

4. Hecvy oils, asphaltic materials items containing natural or synthetic rubber, or any materials other than plant growth which produces smoke of a shade darker than No. 2 on the Ringelmann Chart are not a part of the material burned.

5. The initial burning may be commenced caly between the hours of O 9:oo ^ " eed 3 oo r x > #e cemde tid 1e meter 1 1 te edded te the fire between 3:00 P.M. of one b.y and 9:00 A.M. the following day.
1 Environmental Report. Supplement No. 1
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H. B. Robinson s3.7b-3 Unit No. 2
6. No more than one pile 60' x 60' or equivalent will be burned within a six acre area at one time. *

7. In the case of land clearing, all sa1vageable timber and pulpwood must be removed.

8. A written report or warr.ing to a person of a violation at one site shall be considered adequate notice of the Regulation and subsequent observed violations at the same or different site will result in immediate appropriate legal action by the Authority.
H. Fires set for the purposes of training public fire-fighting personnel when authorized by the appropriate governmental entity, and fires set by a private industry as a part of an organized program of drills for-the training of industrial fire-fighting personnel will be exempt only if the following condition is met:
1. The drills are solely for the purpose of fire-fighting training and the duration of the burning held to the minimum required for such purposes.
I. Open burning of rubbish and garbage on the premises of and originating from private residences or dwellings of four families or less where services for the disposal of such materials are not available and open burning on the property where it occurs of trade waste from building and construction operations will be exempt only if the following conditions are met:
1. The location of the burning is at least five hundred (500) feet from any dwelling located in a predominantly residential area other than a dwelling or structure located on the property on chich the burning is conducted.

2. Heavy oils, asphaltic materials, items containing natural or syn-thetic rubber, or any other trade vaste which produce smounts of smoke of a shade darker than No. 2 on the Ringelmann Chart is .o t burned.

3. The initial burning is commenced only between the hours of 9:00 A.M. l and 3:00 P.M.; no additional fuel shall be added before 9:00 A.M.
of the follouing day, J. Open burning, in remote or specified areas:
1. Of such trade waste as constitutes > rubbish as defined in this Regulation provided smoke of shade darker than No. 2 on the
, Ringelmann Chart is not emitted except for a reasonable period L to get the fire started, and the burning is conducted in accordance with Section I. G. of this Regulation. I
2. Of highly explosive or other dangerous material for which there is no other feasible method of disposal.

3. For non-recurring unusua? circumstances.

4. For experimental bur}}

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Dear Mr. Jones:

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Dear Mr. Mcdonald:

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