ML18038A284

Compliance W/ 10CFR50,App I.

ML18038A284
Person / Time
Site:	Nine Mile Point
Issue date:	10/01/1976
From:	NIAGARA MOHAWK POWER CORP., STONE & WEBSTER, INC.
To:
Shared Package
ML17055D312	List: ML17055D311 ML18038A284
References
NUDOCS 8710280035
Download: ML18038A284 (334)

Text

NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET 50-220 COMPLIANCE WITH 10 CF R50 APPENDIX I NIAGARA MOHAWK POWER CORPORATION SYRACUSE, NEW YQRK

~ 8710280035 76100>

PDR ADOC)( 05000220 P PDR

COMPLIANCE WITH 10CFR50 APPENDIX I Table of Contents Section Title Pacae FOREWORD Complian ce with 10CFR50 Appendix I, Section 1.1.1 II Compliance with Section II.A, II.B, and 1 % 1 1 1 1.2 II C Compliance with Section II.D Cost/Benefit 1 & 1 1 Analyses 1 1 2 1.1.2.1 Effluent Treatment Systems 1 & 1 3 1.1.2.2 Cost of Money 1. 1-4 1.1.2.3 Cost/Benefit Parameters and Methods 1.1-4 0102 Radioact ive Source Tern+ 1 %2 1 1.2.1 Coolant Activities 1 ~2 2 122 Gaseous Releases 1 &2 3 1.2.2.1, Reactor Building 1 &2 3 1.2.2.2 Waste Disposal Building 1 2-4 1.2.2.3 Turbine Building 1. 2-5 1.2.2.4 Stack 1 2-6 1.2.2.5 Mechanical Vacuum Pump 1 & 2 7 1.2.2.6 Turbine Gland Seal System 1 w 2 7 1.2.2.7 0l:f-Gas System 1 &2 7 1.2.2.8 Provisions to Reduce Radioactive Releases 1 2-8 1.2.2.9 Primary Containment System 1.2-9 1.2 3 Liquid Releases 1.2-10 1.2.3. 1 Laundry Wastes 1 2-10 1.2.3.2 Regenerant Chemicals 1 2-11 1.2.3.3 Low Purity Waste 1.2-11 .

1.2.3.4 High Purity Waste 1 2-12 1.2.3.5 Liquid Radioactive Effluents 1 2-12 1 3 Meteoro logy/Hydrology 1 &3 1 1.3.1 Meteorology 1 & 3 1 1.3.1.1 On-Site Meteorological Progran Data &3 1 1.3.1.2 Regional Meteorological Conditions 1.3-2 132 Hydrology & 3 3 1.3.2.1 Quantitative Water Use Diagrams 1 3-4 1.3.2.2 Consumptive Plant Water Use 1.3-5 1.3.2.3 Location and Nature of Water Use Within 50 Miles 1.3-6 1.3.2.4 Description of Discharge Structure 1.3-9 1.3.2.5 Description of Ambient Flow in Lake Ontario 1.3-10 1.3.2.6 Liquid Radionuclide Releases 1 %3 12 1.3.2.7 Radionuclide Concentrations and Travel Times in Lake Ontario 1 &3 13 1.3.2.8 Sorption of Radionuclides by Sediments 1. 3-16 3.

1t Table of Contents (Cont'd)

Section Title Pacae 1.3.2.9 Potential Radionuclide Pathway via Groundwater 1 ~ 3 1 7 1 4 Dose Calculations 1.4-1 1.4.1 Description of Models and Assumptions Used in Individual Dose Calculations 1.4-1 1.4.1.1 Liquid Ef fluents 1.4-1 1.4. 1.2 Gaseous Ef fluents 4-4 1.4.2 Description of Models and Assumptions Used in Population Dose Calculations 1.4-12 1.4.2.1 Liquid Effluents 1.4-12 1.4.2.2 Gaseous Effluents 1. 4-20 1.5 Effluent Release Data 1.5-1

2. 1 ,Data Needed for Radioactive Source Term Calculations 2 &1 l

2. 1. 1 General 2 1

% 2 2.1.2 Nuclear Steam Supply System 2 &1 2 2.1.3 Reactor Coolant Cleanup System 2%1 3 2.1.4 Condensate Demineralizers 2~1 3 2.1.5 Liquid Water Processing Systems 2~1 3

2. 1.6 Main Condenser and Turbine Gland Seal Air Removal Systems 2 % 1 7 2.1.7 Ventilation and Exhaust Systems 2. 1-8 2.2 Tabular Environmental Data 2&2 1 2.3 X/Q and D/Q Data 2~3 1 2.3. 1 X/Q Values 2~3 1 2.3.2 D/Q Values 2&3 1 2.3.3 X/Q and D/Q Computations 2~3-1 2.4 Description of Meteorological Data, Models, and Parameters 2 4-1 2.5 On-Site Meteorological Data (R.G.1.23) 2.5-1 2 6 Description of Meteorological Measurements Program 2.6-1 2 7 Description of Airflow Trajectory Regimes 2 &7 1 2.8 Topographical Map 2. 8-1 2.9 Dates and,Times of Intermittent Radioactivity Releases 2.9-1

Y COMPLIANCE WITH 10CFR50 APPENDIX I List of Tables Table Title

'j-1 1-1 Comparison of Calculated Annual Doses with Appendix I Design Objectives 1 1 1-2 Annual Doses from Noble Gas Effluents 1-1 1-3 Annual Doses to Maximum Individual in Adult Age Group from Radioiodine and. Particulate'aseous Effluents 111-0 Annual Doses to Maximum Individual in Teenage Group from Radioiodine and Particulate Gaseous Effluents 1.1 1-5 Annual Doses to Maximum Individual in Child Age Group from Radioiodine and Particulate Gaseous Effluents

1. 1.1-6 Annual Doses to Maximum Individual in Infmt Age Group from Radioiodine and Particulate Gaseous Effluents

1. 1- 1-7 Annual Thyroid Doses to Maximum Individual xn all Age Groups from Radioiodine and Particulate Gaseous Effluents Cow Location 8,900 ft ESE 1 '1.1-8 Annual Thyroid Doses to Maximum Individual in All Age Groups from Radioiodine and Particulate Gaseous Effluent Goat Location 19,000 ft SSh 1 1 1-9 Annual Doses to Maximum Individual in Adult Age Group from Liquid Effluents under Equilibrium Conditions 1 1-1-'jo Annual Doses to Maximum Individual in Teen Age Group from Liquid Effluents under Equilibrium Conditions 1-1-1-11 Annual Doses to Maximum Individual in Child Age Group from Liquid Effluents under Equilibrium Conditions

1. 1 1-12 Annual Doses to Maximum Individual in Infant Age Group from Liquid Effluents under Equilibrium Conditions 1-1 2-1 Calculated Annual Doses for Population Within 50 Mile Radius 1 1 2-2 Population Man-Rem Dose Assessment from Ingestion of Potable Water and Fish

1. 1.2-3 Population Man-Rem Dose from Fishing and Boating 1.1 2-4 Population Max-Rem Dose Assessment, from Swimming 1.1 2-5 Population Man-Rem Dose Assessment from Shoreline Recreation 1 1 2-6 Population Man-Rem Dose Assessment from Gaseous Effluents

'I I

0

List of Tables (Cont'd)

Table Title 1 1 2-7 Gaseous Augment No. 1 100% Filtration of Reactor Building Gaseous Effluent 1.1 2-8 Gaseous Augment No. 2 100% Filtration of the Condenser Vacuum Pump Effluent 1.1 2-9 Liquid Augment No. 1 2 GPM Reverse Osrmsis (Detergent Wastes) 1 1 2-10 Summary of Annualized Costs

1. 1.2-11 Summary of Cost-Benefits 1 1 2-12 Cost-Benefit Comparison 1 2 1-1 Parameters Used to Describe the Reference Boiling Water Reactor 1 1-2 Values Used in Determining Adjustment Factors for Boiling Water Reactors 1 2 1-3 Adjustment Pactors for Boiling Water Reactors 1'.1-0 Radhonuclide Concentrations in Boiling Water Reactor Coolant and Mam Steam

1. 2-2-1 Releases Via Main Stack 12 3-1 Total Liquid Releases 1-3 2-1 Dilution Factors and Travel Times 1e3eL 2 Water Pumpage Prom Lake Ontario 1 3 2-3 Concentrations at Water Use Locations 132-4 Concentration of Sediment Radionuclides at LakeView Summer Camp Shoreline 1 3 2-5 Concentration of Sediment Radionuclides at; Selkixk State Park Shoreline Source Activity for Swimming and Boating Model Parameters Used in Calculating Population Doses trom Injestion of Vegetation 2.1 5-1 Calculated Annual Release of Radioactive Materials in Untreated Detergent Waste from a BWR 2e2 1 Nearest Milk Cow Within 5 Miles 2e 2 2 Nearest Meat Animal Within 5 Miles 2 e2 3 Nearest Milk Goat Within 5 Miles 2 2-4 Nearest Residence Within 5 Miles 2 2-5 Nearest Vegetable Garden (Greater than 500 ft~)

Within 5 IQ.les 2 2-6 Distribution of All Milk Cows Within 3 Miles 2e2 7 Distribution of All Meat Animals Within 3 Miles 2.2-8 Distribution of All Residences Within 3 Miles 2 2-9 Distribution of All Vegetable Gardens (Greater than 500 ft~) Within 3 Miles

-iv

4 List of Tables (Cont'd)

Toble Title 2e3 1 X/Q at Ground Level Applicable to Long Term Gaseous Releases (0 to 180 Degrees)

2. 3-2 X/Q at Ground Level Applicable to Long Term Gaseous Releases (180 to 360 Degrees) 2 3-3 (Grazing Season) Stack X/Q at Ground Level Applicable to Long Term Gaseous Releases (0 to 180 Degrees)

2. 3-'4 (Grazing Season) Stack X/Q at Ground Level Applicable to Long Term Gaseous Releases (180 to 360 Degrees) 2.3-5 D/Q at Ground Level Applicable to Long Term Gaseous Releases (0 to 180 Degrees) 2.3-6 D/Q at Ground Level Applicable.to Long Term Gaseous Releases (180 to 360 Degrees) 2e3 7 (Grazing Season) Stack D/Q at Ground Level Applicable to Long Term Gaseous Releases (0 to 180 Degrees) 2.3-8 (Grazing Season) Stack D/Q at Ground Level Applicable to Long Term Gaseous Releases (180 to 360 Degrees)

2. 3-9 Turbulence Class Systems and Temperature Differences

COMPLIANCE WITH 10CFR50 APPENDIX I List of Fi ures

~icixre Title 1.2.2-1 Gaseous Releases Simplified Flow Diagram 1 2 3-1 Liquid and Solid Radwaste System 1 2.3-2 Liquid Releases Simplified Calculational Model 1 32-1 Water Usage Flow Diagram 1.3. 2-2 Water Pumpage from Lake Ontario 1 3 2-3 Discharge Tunnel Plan and Profile 2e2 1 Residences, Farm Animals and Vegetable Gardens within 3 Miles of Site

i, FOREWORD This report is submitted in response to a letter dated February 17, 1976, from George Lear, Chief of Operating Reactors Branch No. 3, Division of Operating Reactors, U.S. Nuclear Regulatory Commission to Mr. Gerald K. Rhode, Vice President-Engineering, Niagara Mohawk Power Corporation.

This report supersedes and replaces the earlier interim submittal made on June 4, 1976. The data contained in the earlier submittal have been incorporated into this report. The system design on which these analyses are based is identical to that described in the Petition for Conversion from Provisional Operating License to Full Zerm Operating License and the Environmental Report and their associated amendments. The mathematical models used to calculate liquid and gaseous radioactive releases were obtained from the Nuclear Regulatory Commission's Regulatory Guide 1.112, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors," April, 1976 and the referenced document specific to Boiling Water Reactors, NUREG-0016, April, 1976. No design changes have been made to cause increases in source terms. Any changes in releases between this report and those previously reported in the Petition for Conversion from Provisional Operating License to Full-Term Operating License and Environmental Report are caused by the new mathematical models and revised flow rates for the liquid radioactive waste system to be consistent with Regulatory Guide 1.112 and NUREG-0016 and are not caused by any change to the radioactive waste system components themselves.

All'alculated dose rates resulting from releases from Nine Mile Point Unit 1 are shown to be within the design objectives set forth in Sections II.A, II.B, and II.C of 10CFR50 Appendix I. The calculated doses to the population residing within a radius of 50 miles are 0.18 man-rem and 6.3 m n-thyroid-rem from liquid effluents and 0.23 man-rem and 3.3 man-thyroid-rem from gaseous effluents. Cost-benefit analyses are presented in accordance with Section II.D of 10CFR50 Appendix I. In performing these analyses, radwaste augments which are judged to be the most cost effective have been considered, based on the lists of potential augments presented in Regulatory Guide 1.110, "Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors,"

March, 1976. These analyses demonstrate (Tables 1.1.2-11 and

-12) that additional radwaste equipment of reasonably demonstrated technology cannot be justified on a cost-benefit basis.

1.1 Com liance with 10CFR50 A endix I Section II This section is divided into two parts. The first (Section 1.1.1) deals with the demonstration of compliance with the requirements set forth in Paragraphs A, B, and C of Section II of Appendix I to 10CFR Part 50. The second (Section 1.1.2) presents the results of a cost/benefit analysis performed in accordance with the requirements set forth in Paragraph D of Section II.D of Appendix I.

1.1 1 Com liance with Section II.A II.B and II C A canparison of the Appendix I design objectives and the c lculated annual dose rates for individuals in the unrestricted area adjacent to Nine Mile Point Unit 1 is presented in Table 1.1.1-1.

This comparison demonstrates that all design objectives set forth in Sections II.A, II.B, and II.C are met. The calculated .dose rates for individual pathways, from .which the Table 1.1.1-1 summary has been prepared, are presented in Tables 1.1.1-2 through 1.1.1 12.

Table 1.1.1-2 presents the maximum calculated annual doses from noble gas effluents at the location of highest dose rate level (6,300 ea) . Tables 1.1.1 ft east, at the boundary of the restricted 3 through 1.1.1-6 present maximum calculated dose rates in the adult, teen, child and infant age groups resulting from radioiodine and particulate gaseous effluents.

The dose rate to the total body and various body organs is reported on the following bases: The individuals, are assumed to be located at the least favorable location in the unrestricted area (i.e., 6,300 ft east) relative to contributions to the dose rate from inhalation and deposition on the ground. These individuals are assumed to consume fresh leafy vegetables grown at the nearest actual vegetable garden (7,300 ft east) and stored vegetables from the nearest. developed orchard (7,000 ft. east).

They are further assumed to consume meat from the nearest actual location of meat animals (8,900 ft east.-southeast) . These are intentionally conservative assumptions.

Tables 1. 1. 1 7 and 1. 1. 1-8 present calculated annual thyroid southeast) doses at the nearest milk cow location (8,900 and goat location (19,000 ft ft east-south-southeast) . The infant thyroid dose at the cow location is seen to be the largest calculated value, i e., 0.75 mrerq/yr.

The calculated maximum annual doses for individuals in the adult, teen, child and infant age groups resulting from liquid effluents are reported in Tables 1.1.1-9 through 1.1.1 12.

For the purposes of these analyses, these individuals are assumed to receive contributions to their annual con-'ervatively doses from: ingestion*of potable water from the nearest public

0 water intake; ingestion of fish caught near the discharge; ingestion of aquatic invertibrates taken near the discharge; and a combination of exposures to the liquid effluents in water-related sports activities at the most conservative locations for which such activities could be postulated to occur. The resulting calculated maximum annual doses are 0.089 mrem/yr to the total body for an individual adult and 0.22 mrem/yr to the thyroid of an infant as summarized in Table 1.1.1 1.

1.1.2 Com liance with Section II.D Cost Benefit Anal ses This section presents the results of cost/benefit analyses performed in accordance with Section II.D of Appendix I to 1 0CFR50 The estimated costs of the radwaste augments are arrived at by use of the data contained in Regulatory Guide 1.110. All costs are in terms of 1975 dollars. The benefit associated with each radwaste augment is calculated by multiplying the change in population dose by a conversion factor of $ 1,000 per man-rem and

$ 1,000 per manMyroid-rem.

The dose to the population residing within a radius of 50 miles is calculated with the plant systems and equipment as described in Sections 1.2 and 2.1 in this report. These population doses're for the same base case used to calculate the individual doses reported in Section 1.1.1. The resulting population doses are presented in Table 1.1.2-1.

The resultant population exposures are 0.18 and 6.3 man-rem and man-thyroid-rem, respectively, from liquid effluents and 0.23 and 3.3 man-rem and man thyroidrem, respectively, from gaseous effluents. These data form the base case from which the cost/benefit analyses are performed.

The potential dose from the ingestion of aquatic invertebrates is considered in computing doses to individuals (see Table 1.1.1-9) . However, this is considered to be an inconsequential pathway relative to large population groups and is not considered in the population man-xem calculations. It is a small fraction of the fish contribution which has been shown to be an extremely small population dose consideration (see Table 1.1.2 1) .

As can be seen in Tables 1.1.2 2 through 1.1.2-6, which present the detailed calculations from which Summary Table 1.1.2-1 is constructed, all potential pathways have been considered. No additional significant pathways which could contribute 10 percent or more to either individual or population doses are known to exist in the region around the site.

The following radwaste augments are considered in these analyses:

C t

li l ~

P

Gaseous Augment No. 1 Addition of 100 percent filtration of the reactor building effluent with HEPA/charcoal filters.

Gaseous Augment No. 2 Addition of 100 percent filtration of the condenser vacuum pump effluent with HEPA/charcoal filters.

Liquid Augment No. 1 Addition of a 2 gpm reverse osmosis system in the detergent waste stream.

These augments were judged to be potentially the most cost-beneficial of the potential augments listed in Regulatory Guide 1.110, based on the calculated releases and doses for the base case. None of these augments is shown to be cost-beneficial. As these are the most promising of the potential augments, no additional augments are considered to be cost-beneficial.

1. 1.2.1 Effluent Treatment S stems The following Cost Estimate Sheets, Tables 1.1.2-7, -8, md -9, explain the cost of the augments to the gaseous and liquid radwaste systems. Table 1.1.2 10 summarizes the estimated annualized costs. The augments were analyzed using Regulatory Guide 1.110. They are as follows:

GASEOUS AUGMENTS

1. One hundred percent filtration of the reactor building gaseous effluent (see Table 1.1.2-7) .

2. One hundred percent filtration of the condenser vacuum pump effluent 1.

Ml" *

(see Table 1.1.2-8) .

Addition of a 2 gpm reverse osmosis system to the discharge of the laundry drain tanks (see Table 1.1.2-9) .

Cost Benefit The potential reductions to the annual population exposure based on the items of augmentation described above are shown in Table 1.1.2 11. This table also shows the "benefit" of each augment, calculated by multiplying the dose reduction by

$ 1,000 per man-rem or $ 1,000 per man-thyroid-rem as appropriate.

As shown in Tables 1.1.2-10, 11, and 12, the "benefit" of each augment is much less than the corresponding annualized cost, resulting in cost/benefit ratios of much greater than one.

Therefore, any addition of items of reasonably demonstrated technology which have the potential of reducing population dose would not be cost/benefit effective.

1.1.2.2 Cost of Mone The Niagara Mohawk Power Corporation has established that the annual cost of money is 11.5 percent. This represents the annual cost of money for 1975.

1.1.2.3 Cost Benefit Parameters and Methods Decontamination Factors and "On-Line~ Time Gaseous Au ents A decontamination factor of 10 for iodine and 100 for particulates was used in each gaseous augment. These are consistent with Regulatory Guide 1 .112 and NUREG 0016.

The >>on-line" time is conservatively assumed to be 100 percent for the purpose of this analysis.

Li uid Au ent A decontamination factor of 10 for Anions, 10 for Cesium and Rubidium, and 10 for othe nuclides was used for the liquid augment, which is consistent with Regulatory Guide 1.112 as referenced above.

The "on-line" time is conservatively assumed to be 100 percent for the purpose of this analysis.

Parameters and Methods The Indirect Cost Factor (ICF) is based on a three-unit site and separate, nonshared radwaste systems. Using the formula presented in Table A5 of Regulatory Guide 1.110, a value of 1.58 is obtained for the ICF for Nine Mile Point Unit 1.

The Capital Recovery Factor (CRF) was determined using 11.5 percent as the cost. of borrowed money and a service life of 25 years. Using these parameters and the formula presented in Table A-6 of Regulatory Guide 1.110, a value of 0.1231 is obtained for the CRF for Nine Mile Point Unit 1.

1. 1-0

'F l

TABLE 1 1 1-1 COMPARISON OF CALCULATED ANNUAL DOSES WITH APPENDIX I DESIGN OBJECTIVES Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation CRITERION APPENDIX I DESIGN OBJECTIVE CALCULATED DOSE Gaseous Effluents Gamma Air Dose 10 mrad/yr 0.11 mrad/yr Beta Air Dose 20 mrad/yr 0.067 mrad/yr Noble Gas Tot'al 'Body 5 mrem/yr 0.074 mrem/yr Noble Gas Skin 15 mrem/yr 0.14 mrem/yr Iodines and Particulates 15 mrem/yr 0.75 mrem/yr~

Any Organ (Thyroid)

Li uid Effluents Total Body 3 mrem/yr 0.089 mrem/yr Any Organ 10 mrem/yr 0.22 mrem/yr++

+ Infant thyroid dose for cow location (8,900 ft ESE)

• +The infant thyroid dose is calculated to be the highest 'organ dose

TABLE 1 1 1-2 ANNUAL DOSES FROM NOBLE GAS EFFLUEXTS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power CorPoration CALCULATED CRITkRION LOCATION OF *DOSE EVALUATION DOSE Gamma dose in air (mrad/yr) Boundary of restricted area 6300 ft East 1.1x10-~

Beta dose in air (mrad/yr) Boundary of restricted area 6300 ft East 6.7x10-~

Dose to total body of an individual (mrem/yr) Boundary of restricted area 6300 ft East 7.4x10-~

Dose to skin of an individual

(~~) Bound~ of restricted area 6300 ft East 1.4x10-~

TABLE 1 1 1-3 ANNUAL DOSES TO MAXIMUM IhDIVIDUALIN ADULT AGE GROUP PROM RADIOIODINE AND PARTICULATE GASEOUS EFFLUI2FZS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Pathwa and Location ~total nod Bone Liver T~nroid ~ridne ~Lnn GI Tract Inhalation 6300 ft East 1 4x10-i N A 3 4x10-+ 2 6xlO-~ 2 2x10-< 2 5x10 ~ 3 7x10-~ 1 5x10~

Deposition on Ground 6300 ft East 1 2x10-> 1 4x10-> 1 2x10=~ 1 2x10-~ 1 2x10-> 1.2x10-> 1 2x10-< 1 2x10-*

Ingestion of Leafy+

Vegetables 7300 ft East 1 3x10-~ N Ae 3.4x10-> 1 7x10 ~ 2 2x10-> 1 &x10-> 5 3x10-~ 1 Ox10 Ingestion of Stored+

Vegetables 7000 ft East 7 Ox10-3 N A 2 2x10-~ 7.9x10-> 1 4x10-> 5 2x10-3 4 3x10-3 5 9x10->

Ingestion of Meat+

ESE 8900 ft 4.0x10-+ N A 1 7x10 3 4 3xlO ~ 3 &x10 3 3 &x10~ 3 4xlO-~ 4 4xlO:~

Total of Above Pathways 2.0x10-* 1.4x10-> 3.9x10-~ 2.2x10-* 2.7x10-~ 2.0x10-* 1.&x10-> 2.0x10->

+Leafy vegetables, stored vegetables, md neat from these locations are conservatively assumed to be consumed by individuals located at the boundary of the restricte'd area, 6 300 ft east.

1 TABLE 1 1 1-4 ANNUAL DOSES TO MAXIMUM INDIVIDUAL IN TEENAGE GROUP FROM RADIOIODINE AND PARTICULATE GASEOUS EFFLUENTS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Pathwa and Location r~ota1 nod Bone Liver ~rn roid ~ridne ~Lvn GI Tract Inhalation 6300 ft East 1.1x10-~ N A 1 lxlO-~ 2 2xlO-~ 1 9x10-> 1 7xlO-~ 3 5x10 ~ 1 lx10-~

Deposition on Ground 6300 it East 1-2xlO 1.4x10-~ 1.2x10-~ 1.2x10-> 1.2x10-~ 1.2x10-> 1.2x10-~ 1.2x10->

Ingestion of Leafy+

Vegetables - 7300 ft East 9.6x10-~ N A 1 4x10-~ 1 5x10-> 1 7x10-~ 1 2x10-> 4 6x10 ~ 7 3x10-~

Ingestion of Stored>>

Vegetables 7000 ft East 9.1x10-3 N A 1 2x10-> 1 2xlO-> 2 Ox10-~ 6 4x10-> 6 8x10 3 8 2xlO Ingestion of Meat+

ESE 8900 ft 2.9xlO-i N A 3 Ox10-~ 3 3x10-~ 2 7x10-3 2 2x10-~ 2 6x10-~ 3 lx10-+

Total of Above Pathways 2 2xlO ~ 1 4x10 > 2 6x10-> 2 6x10 > 2 2x10 ~ 2 Ox10-~ 2 OxlO-~ 2 lx10->

+Leafy vegetables, stored vegetables, and meat from these locations are conservatively assumed to be consumed by individuals located at the boundary of the restricted area, 6,300 ft east.

TABLE 1 1 1-5 ANMHG DOSES TO MAX%KM INDIVIDUALIN CHILD AGE GROUP FROM RADIOIODINE AND PARTICULATE GASEOUS EFFLUENTS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Pathwa and Location ~~1 ~y Bone ~Th mid ~Kidne ~Lan GI Tract.

Inhalation 6300 ft East 1.0x10-~ N A~ 1.8x10-~ 2.3x10-~ 2 7x10-~ 9.2x10-s 3-Sx10-~ 2.6x10-~

Deposition on Ground 6300 ft East 1.2x10-> 1 4x10-> 1 2x10-> 1 2x10-> 1 2x10 > 1.2x10-> 1 2x10-> 1.2x10->

Ingestion of Leafy+

Vegetables 7300 ft East 9.9x10-~ NoAo 2 5x10 ~ 2 1x10-s 2 Sx10-> 7 5x10-~ 8 Ox10-~ 9 4x10-~

Ingestion of Stored+

Vegetables - 7000 ft East 1.8x10-~ NCAA+ 2 9x10 > 2 Sx10-> 4 3x10 > 5 2x10-3 1 6x10-> 1.6x10-<

Ingestion of Meat+

ESL 8900 ft 5. 1x10-i N.A. 5 6x10 ~ 5 7x10 ~ 4 1x10-3 1 4x10~ 4 9x10-,~ 5 1x10-+

Total of Above Pathways 3 2x10-> 1 4x10-> 4 4x10 > 4 Ox10-< 3 4x10 > 1.8x10 ~ 3 Ox10-~ 3 Ox10-~

+Leafy vegetables, stored vegetdd.es, and aaat from these locations are conservatively assumed to be consumed by individuals located at the boundary of the restricted area, 6,300 ft east.'

TABLE 1 1 1-6 ANNUAL DOSES TO MAXIMUM INDIVIDUALIN INFANT AGE GROUP PROM RADIOIODINE AND PARTICULATE GASEOUS EFPLUENTS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation PATHWAY AND LOCATION ANhUAL DOSE mrem r TOTAL BODY SKIN BONE LIVER THYROID KIDNEY LUNG GI TRACT Inhalation&300 ft East 2 OxlO NiA 2.6x10-~ 3.5x10-~ 4.6x10-~ 6.5x10-~ 5.2x10-~ 1.5x10-~

Deposition on Ground-6300 2x10 1 4x10-> 1 2x10 > 1 2x10-> 1 2x10-~ 1 2x10-> 1 2x'lO-> 1 2x'IO->

ft East 1

Ingestion of Leafy vege- N.A NeAi N A N A N A N A N A N A tables - 7300 ft East Ingest@on of Stored vege- N~A N A N A N A N Ai N Ao N+Ai N A tables 7000 ft East Ingestion of Peat-8900, N A N A N A N A N A NiA NoA N A ft ESE Total of Above Pathways 1.2xl0-> 1.4x10-~ 1.2x10-2 1.2x10-~ 5.8x10-~ 1.2x10-* 1.3x10-~ 1.2x10-~

t TABLE 1 1 1-7 ANNUAL THYROID DOSES TO MAXIMUM INDIVIDUALIN ALL AGE GROUPS FROM RADIOIODINE AND PARTICULATE GASEOUS EFFLUENTS COW LOCATION 8900 FEET ESE Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation PATHWAY ADULT ANNUAL THYROID DOSE mrem r TEEN CHILD Inhalation 1.2x10-~ 1. 1x10-2 1.5x10-~ 2.5x10-~

Deposition on Ground 6.6x10-3 6.6x10-3 6.6x10-3 6.6x10-3 Leafy Vegetables+ 5. 9x10-~ 4 . 6x10-~ 6. 9x10-~ N A.

Stored Vegetables* 3. Sx10-3 5.5x10-3 1. 2x10-2 N A.

Cowis Milk 1.0x10-i 1.5x10-i 3. Ox10-> 7.2x10->

Meat+ 3. Sx10-3 2.7x10-3 4. 1x10-3 N.A Pathways

'.9x10-~

Total of Above 2.2x10-~ 4.1x10-~ 7.5x10-~

• Conservatively assumed to exist at cow location

I TABLE 1 1 1-8 ANNUAL THYROID DOSES TO MAXIMUM INDIVIDUALIN ALL AGE GROUPS FROM RADIOIODINE AND PARTICULATE GASEOUS EFFLUENTS GOAT LOCATION 19 000 FEET SSE Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation PATHWAY ANNUAL THYROID DOSE mrem r 2G)ULT TEEN CHILD INFANT Inhalation 1. 9x10-~ 1. 6x10-~ 2. 3x10-~ 3.9x10-~

Deposition on Ground 9.5x10-~ 9.5x10-~ 9.5x10-~ 9.5x10-~

Leafy:Vegetables* 7.0x10-~ 5.4x10-~ . 8.1x10-~ N.A Stored Vegetables* 4.5x10-i 6.6x10-i 1.4x10-~ N.A Goat's Milk 1 4x10 > 2 1x10-~ 4.3x10-> 1.0x10 Meat~ 4.5x10-+ 3.2x10-i 4.9x10-~ N A.

Total of Above 2.5x10-~ 3.0x10-~ 5. 6x10-~ 1.0x10-~

Pathways

• Conservatively assumed to exist at goat's location

TABLE 1 1 9 AhNUAL DOSES TO MAXIMUM INDIVIDUAL ZN ADULT AGE GROUP FROM LZ ZD EFFLUENTS UNDER E UILZBRIUM CONDITIONS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation PATHWAY AND LOCATION ANNUAL DOSE mr em z TOTAL BODY SKIN BONE LIVER THYROID KIDNEY LUNG GI Ingestion of Potable Water

-8 miles West 1.6x10-3 N A 9 7xt0-~ 2 Ox10-3 4 6x10-2 1 3x10-3 7.6xt0-~ 1.2x10-a Ingestion of Fish near discharge 8.4xt0-~ NoA 2.0xt0-~ 1 2xt0-~ 3.3xt0-~ 3.7xt0-~ 1.2xt0-~ 2.9x10-2 Ingestion of Aquatic Invertebrates near discharge 2 2x10 N A 8 3x10-3 5 Ox10 3 2 9x10-3 3 5x10

• 1 4xt0-> 1 Sxt0-<

Summing 100 br s/yr near discharge 1 Sxt0-~ 2 txt0~ 1 SxtO-~ 1 Sxt0-~ 1 Sxt0-~ 1 Sxt0-~ - 1 SxtO-+ 1 Sxt0-~

Fishing and Boating 500 hrs/yr near discharge 4.5x10-+ 5 2xt0~ 4 5x10 ~ 4 5x10 ~ 4 Sxt0-~ 4 5xt0-~ 4 5xt0-~ 4 5xtO-~

Water Skiing 100 hrs/yr near discharge 9.0xt0-> Oxt0~ 9 Ox10-5 9 Ox10-5 9 Oxl0-s 9 Oxt0-> 9 Ox10-s 9 Oxt0-s Shoreline Recreation Lakeview Sunmar Camp (0-8 mile SW) 1 3x,t0-~ 1 5xt0~ 1 3xtO-~ 1 3xt0-~ 1 3xt0-~ '

3xtO-~ 1 3xt0-+ 1 3xt0-~

Total of Above Pathways 8.9x10-* 9 Sxt0-~ 2.1xlO-r 1 3xt0-~ 8.3xt0-> 4 3xt0-> 1.5xtO-i 4.6xtO-i

I ANNUAL DOSES TO MAXIMUM INDIVIDUAL IN TEEN AGE GROUP FROM LI UID EFFLUENTS UNDER E UILIBRIUM CONDITIONS Nine Mile Point Nuclear Station - Unit 1 Niagara Mohawk Power Corporation PATHWAY AND LOCATION TOTAL BODY SKIN LIVER THYROID LUNG GI Ingestion of Potable Water

-8 miles West 8 9xt0-i NCAA+ 9 Ox10 i 1 6x10 3 3 7xt0-> 8 9x10 i 5 Ox10 i 7 2xt0~

Ingestion of Fish near discharge 4.8xt0-~ N A 1 7x10 > 1 2x10 i 3 Oxt0-> 2.8x10-* 1 4x10 ~ 2 1x10 Ingestion of Aquatic Invertebrates near discharge 1.5x10-3 N A 6 6xt0-> 4 2x10-a 2 6x10-3 2 7x10-3 1 1x10 3 1 txt0->

Swimming 100 hrs/yz near discharge 1 SxtO + 2 1x10 i 1 Sx10 i 1 Sx10 i 1 SxlO-+ 1 Sx10 i 1 Sxt0-+ 1 Sxt0-i Fishing. and Boating 500 hrs/yr near discharge 4.5xtO-i 5 2xt0-i 4 Sxt0-i 4 Sx10 i 4 Sxt0~ 4 5xt0-+ 4 Sxt0-+ 4 5xt0-i Water Skiing 100 hrs/yr near discharge 9.0xtO-s t.Oxt0~ 9.0xlO-~ 9.0x10-s 9.0xt0-~ 9.0xtO-s 9.0x10-~ 9.0xtO-s Shoreline Recreation Lakeview Summer Camp (0.8 Mile SW) 7.4xtO-i 8 6xt0~ 7 4xt0-i 7.4x10 i 7 4xt0~ 7 4x10 i 7 4xt0-i 7 4x10 i Total of Above Pathways 5 2xt0-~ 1 7xtO-~ 1.8xtO-i 1.3xtO-i 7.txt0-> 3.3x10-* 1.7x10-* 3 4xt0->

l TABLE 1 1 1-1 1 ANNUAL DOSES TO MAXIMUM INDIVIDUALIN CHILD AGE GROUP FROM LI UID EFFLUENTS UNDER E UILIBRIUM CONDITIONS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation PATHWAY AhD LOCATION ANNUAL DOSE mrem r TOTAI BODY SKIN BONE LZVEk THYROID KIDNEY LUNG GI Ingestion of Potable Water

-8 miles West 1 lx10 > NA 2 5x10-> 3 2x10-> 9.0xlO-> 8 9x10-+ 9 lx10-~ 1 Ox10->

Ingestion of Fish near discharge 1 9xlO > N A 1 3x10 ~ 9 Sx10

• 3 2x10-~ 1 2x10 1. lx10-~ 8.5x10->

Ingestion of Aquatic Invertebrates near 5.6xlO-~ 5 lxl0->

discharge 7 4xl'0-+ N A 4 lx10 > 2 6x10-> 2 Sx10-.3 1 2xlO-3 Swimming 100 brs/yr SxlO-+

near ch.scharge 1. 8xl0-i 2 lx10 ~ 1 Sx10-~ 1 Sx10-~ 1 Sx10-~ 1 Sxl0-~ 1 Sx10-~ 1 Fishing and Boating 500 hrs/yr near discharge 4-Sx10-i 5 2x10 + 4 5x10 ~ 4 5x10-+ 4 5x10 + 4 5x10 + 4 SxtO + 4 SxlO Water Skiing 100 hrs/yr near discharge 9.0x10-5 1.0x10-~ 9 Ox10-> 9.0x10-5 9.0xl0-5 9.0x10-> 9.0x10-> 9 Ox10-5 Shoreline Recreation Lakeview Summer Camp (0.8 Mile SW) 1 5x10-~ 1 SxtO~ 1 5x10-~ 1 SxlO-+ 1 5x10 ~ 1 SxlO ~ 1 Sx10-~ 1 SxlO-~

Total of Above Pathways 2.2x10-> 1 Ox10-3 1.4x10 ~ . 1 Ox10 > 1 3x10 ~ 1 5x10 > 1 3x10

• 1 5x10-~

I TABLE 1 1 1-12 ANNUEQ DOSES TO MAXIMUM INDIVIDUALIN INFANT AGE GROUP FROM LI UID EFFLUENTS UNDER E UILIBRIUM CONDITIONS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation PATHWAY AND LOCATION ANNUAL DOSE mr em TOTAL BODY SKIN BONE LIVER THYROID KIDNEY LUNG GI Ingestion of Potable Water

-8 miles West 1 Sx10-~ N A 5 1x10-~ 7 Ox10-3 2 2x10 ~ 8 9x10 1.6x10-3 1.3x10-a Ingestion of Fish near discharge N~Ao N A NCAA+ N A N A N A N A NoA Ingestion of Aquatic Invertebrates near discharge N A N A NoA N A. N A N A N Ai N A Swimming 100 hrs/yr near discharge N A NiA N A N A N A NiA NCAA+ N A Fishing and Boating - 500 hrs/yr near discharge N~Ao NiAi NiAi N A N A. N A N Ao NCAA+

Water Skiing 100 hrs/yr near disch~ge N A NA NA N A'- N.A. N A N A N A Shoreline Recreation Lakeview Summer Camp (0.8 Mile SW) N A N.A NoA N A NCAA+ N A N A N A Total of Above Pathways 1 Sx10 N A 5 1x10-> 7 Ox10-3 2 2x10-> 8 9xtO-+ 1.6x10-3 1 3x10->

TABLE 1. 1. 2-1 CALCULATED ANNUAL DOSES FOR POPULATION WITHIN 50 MILE RADIUS Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation POPULATION MAN-REM WHOLE BODY THYROID Li uid Effluents Ingestion of potable water 1.7x10-~ 6.3x10o Ingestion of fish 5.0x10-~ 1.1x10-~

Fishing 7.2x10-~ 7. 2x10-'~

Boating . 4.4x10-i 4.4x10-~

Swimming 3.9x10-i 3.9x10-i Shoreline recreation 1.2x10-~ 1.2x10-~

Total 1.8x10-i 6.3x10o Gaseous Effluents Plume immersion 9.2x10-~ N A.

Inhalation 1.3x10-~ 2.2x10 on ground

'eposition 6.7x10-~ 6.7x10-~

Ingestion of milk 2.7x10-~ 2.0x10o Ingestion of vegetation 4.4x10-~ 9. 2x10-~

Ingestion of meat 4.1x10-~ 3.2x10 Total 2.3x10-i 3.3x10o

C TABLE 1 1-2-2 POPULATION MAN-REM DOSE ASSESSMENT IRON INGESTION OF POTABLE WATER AND FISH Nine hlile Point Nuclear Station - Unit 1 Niagara Mohawk Power Corporation Decay Dilution Time Age Usage Factor ANNUAL DOSE (man mern)

Pathwa and Location Factor ~hrs ~Grou 1 ork Bases ~~tal Bod ~Th grid Potable water 7 7 53 Adult 370 190,000 consumers 1 2x10-i 3 2x10o Oswego City and in 1970 incr. by Onondega County Pop. growth to 240,000 7 7 53 260 Same as above 1.5x10-~ 6 ~ Qx10-1 7 7 53 Child 260 Same as above 3 8x10 2.5x10o Potable Water Subtotal 1.7x10-i 6.3x10o Fish within 50 miles . 1x10i 240 Adult 6 9 Total fish catch 4 1x10-s 6.9x10-s of 6.0x10s Kg/yr 1x10+ 240 Teen 5 2 Same as above 5.2x10-s 1 4x10~

2-2, 3.4x10-s

'40 lx10+ Child Same as above 2 4x10 s Fish Subtotal 5.0x10-s 1 1x10-s Tote 1 of above p thways 1.7x10-i 6 3x10>

TABLE 1 1 2-3 POPULATION MAN-REM DOSE FROM FISHING AND BOATING Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Population Annual Dilution Dose kate Usage Population

~ActtVIt Factor ~res~~ Bases rson-hrs 1x10i 4.5x10->> f 6.4x10< isheraan 1 6x10> 7 2x10 days 8 2.5 hr/day 6.1 7.4x10-~ o 1,000 people/day 6.0x10s 4.4x10-i 9 2 hr/day 10,000 people/wknd. 8 4 hr/wknd. for 12 wks Total of Mve pathways 4.5x10-i

+Dose estimate is not dependent on age group.

TABLE 1 1 2-4 POPULATION MAN-REM DOSE ASSESSMENT FROM SWIMMING Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation PER CAPITA ANNUAL DILUTION DOSE RATE AGE USAGE NUMBER OF POPULATION LOCATION FACTOR ~rem~z~ GROUP ~hrs f~da PERSON-DAYS DOSE n-rem Lakeview Summer 5.0 1.8x10-~ Adult 2 11,200 500 pers/wkday 4 Ox10-s Camp 1,500 pers/wkend or 800 pers/day avg. for 10 wk season 5 0 1. Sx10-~ Teen 22,400 Same as above 1.6x10-i 5.0 1 Sx10 + Child 22i400 S~e ~ above 1.6xlO-i Camp Subtotal 3.6x10-+

Selkirk State Park 8.4 1 lx10 + Adult 6r200 1,000 swimmers/ 1 4x10-I wk for 10 wk season 8 4 1.1x10-~ Teen 1,400 Same as above 6 2x10 8 4 1 lx10-~ Child 2t400 Same as above 1 lx10-~

Park Subtotal 3.1x10-s Vicinity of 5.0 1.8x10-~ Teen 200 Conservative 1.4x10-+

ktucing Zone Estimate Total of above 3.9x10-i pathways

TABLE 1-1-2-5 POPULATION MAN-REM DOSE ASSESSMENT FROM SHORELINE RECREATION huxe Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation PER CAPITA ANNIIAL DILUTION AGE USAGE NUMBER OF POPULATION LOCATION FACTOR GROUP FACTOR PERSONS EASES Lakeview Summer 5 0 Adult 2 hr/day 11~200 500 pers/wkday 2 6x10-~

1,500 pers/wkend or 800 pers/day avg. for 10 wk season 5 0 Teen 4 hr/day 22i400 Same as above. 1.0x10-~

5 0 Child 4 hr/day 22 400 Same as above 1-Ox10->

Subtotal 2.3x10-~

Selkirk State Park 8.4 Adult 8.3 hr/year 62,000 10,000 pers/ 3.5x10-3 wkend for 10 wk season 8 Teen . 47.0 hr/year 14,000 Same as above 4 5x10-3 8 4 Child 9.5 hr/year 24 ~000 Same as above 1. 6x10-~

Park Subtotcal 9.6x10-~

Total from Above 1 2x10 Pathways

i TABLE 1 1 2-6 POPULATION MAN-REM DOSE ASSESSMENT PROM GASH)US EPFLUENTS Nine Mile Point Nuclear Station Unit, 1 Niagara Mohawk Power Corporation ANNUAL POPULATION DOSE PATHWAY AGE GROUP TOTAL BODY manmem THYROID Th oid man-rem Inhalation Adult 8 3x10-i 1.3x10-1 Teen 1.5x10-+ 2.5x10-~

Child 3.4x10-+ 6.0x10-~

Deposition on ground 6.7x10-> 6.7x10-<

Submersion 9.2x10-~ N Ai Ingestion of milk Adult 8.6x10-3 6.3x10-1 Teen 3.9x10-3 3 Ox10-1 Child 1.4x10-~ 1 1x100 Ingestion of meat Adult 2.4x10-3 2 Ox10 Teen 4.1x10-i 3.3x10-~

Child 1 3x10-* 8.7xt0-3 Ingestion of vegetation Adult 2 Ox10-> 3 7x10-I Teen 5.9x10-3 1 2x10-<

Child 1.8x10-~ 4 3x10 Total of above pathways 2.3x10-1 3 3x10o

+Dose estimate xs not dependent on age group.

0 TABLE I.I.2-7 TOTAL DIRECT COST ESTIMATE SHEET OF RADWASTE TREATMENT SYSTEM NINE MILE POINT NUCLEAR STATION-UNIT I NIAGARA MOHAWK POWER CORPORATION Description of AUgment GASEOUS AUGMENT N0.1-I00% FILTRATION OF REACTOR BUILDING GASEOUS EFFLUENT DIRECT COST (1975-$ 1000)

BASIS FOR ITEM LABOR EQUIPMENT/MATERIALS . TOTAL COST ESTIMATE I. P ROCESS EQUIPMENT S-S0,000 CFM CHARCOAL/HEPA 72 55l 423 FILTRATIONSYSTEM,PREFILTER

/4 CHARCOAL/HEPA,GIVEN IN REG. GUIDE I.IIO, P.44

2. BUILDING ASSIGNMENT 2B'x20'x l2 AT $ 5/ftP 96 40.8 , 136.8 (NON-SHIELDED AREA)GIVENIN REG. GUIDE I.IIO,P.44

3. ASSOCIATED PIPING SYSTEMS 24 BASIS GIVEN IN REG. GUIDE I.IIOi P.44

4. I N ST R U ME N TATION 8 CON TROLS IN ITEM 1

5. ELECTRICAL SERVICE ALLOWANCE GIVEN IN 28.8 l2 40.8 REG. GUIDE I.IIO, P;44

6. SPARE PARTS l5 l5 GIVEN IN REG. GUIDE I.IIOi P.44 SU 8 TOTAL 220.8 427.8 648.6

7. CONTINGENCY 22 42.8 64.8 I0%-GIVEN IN REG. GUIDE I.IIO

8. TOTAL DIRECT COSTS 242.8 470.6 7I5.4 LABOR COST INCLUDES THE LABOR COST CORRECTION FACTOR OF l.6 GIVEN IN TABLE A-4 OF REG. GUIDE I.IIO I OF2

Cl TABLE I.I.2"7 (CONT'D)

ANNUAL OPERATING 6 MAINTENANCE COST ESTIMATE SHEET OF RADWASTE TREATMENT SYSTEM NINE MILE POINT NUCLEAR STATION-UNIT I NIAGARA MOHAWK POWER CORPORATION Dt) SCRIP f Ipp P f AU g~6g t" GASEOUS AUGMENT No1-I00% FILTRATION OF REACTOR BUILDING GASEOUS EFFLUENT COST (I975- $ IOOO)

LABOR OTHER TOTAL BASIS FOR COST ESTIMATE I. OPERATING LABOR) SUPERVISION, AND OVERHEAD I5MIN./SHIFT+40HR. ANNUALTEST TIMES 3 UNITS (REG. GUIDE I.IIO)

2. MAINTENANCE MATERIAL 60HEPA OR PREFILTERS AT 4ISOEACH 6 AND LABOR CHARCOAL FILTERS AT 4900 EACH EVERY 2YEARS (REG. GUIDE I.IIO)

3. CONSUMABLES, CHEMICALS AND SUPPLIES IN ITEMS 2AND4

4. UTILITIES AND SERVICES WASTE DISPOSAL ~50/HEPA OR PREFILTER) 4IOO/CHARCOAL FILTER WATER STEAM I6KW ADDITIONALFAN HP FOR FILTER E L EC TR I C IT Y 7.8 AT O.OIB 4/KW-HR B U IL DIN G S E R V I C ES OTHER

5. TOTAL 0 AND M ANNUAL COST 82.2 20F2

TABLE 1.1.2-8 TOTAL DIRECT COST ESTIMATE SHEET OF RADWASTE TREATMENT SYSTEM NINE MILE POINT NUCLEAR STATION-UNIT I NIAGARA MOHAWK POWER CORPORATION DBSCI jpt jOII pf AUgn18ng GASEOUS AUGMENT No.2- 100 7o FILTRATION OF THE CONDENSER VACUUM PUMP EFFLUENT DIRECT COST (1975-$ IOOO)

BASIS FOR ITEM LABOR EQUIPMENT/MATERIALS TOTAL COST ESTIMATE I. P ROCESS EQUIPMENT 2000 CFM PREFILTER/4 52.5 CHARCOAL BED/HEPAO $ 15/CFM, 3.2 35.7 10Kw HEATER $ 250/Kw GIVEN IN REG. GUIDE 1.110, P28

2. BUILDING ASSIGNMENT TURBINE BUILDING 8 xl6 xl2 4.9. 1.5 6.4 Q $ 3/FT~ (NONSHIELDED AREA)

GIVEN IN REG. GUIDE I.110) P28

3. ASSOCIATED PIPING SYSTEMS 2.1 0.7 2.8 ALLOWANCE GIVEN IN REG. GUIDE 1.110i P28

4. INSTRUMENTATION G CONTROLS IN ITEM 1

5. ELECTRICAL SERVICE ALLOWANCE 1.6 1.5 GIVEN IN REG. GUIDE 1.110,P28

6. SPARE PARTS 0.5 0.5 GIVEN IN REG. GUIDE 1.110, P28 SU 8 TOTAL 11.8 56.7 48.5

7. CONTINGENCY 1.2 5.7 IO'Fo

8. TOTAL DIRECT COSTS 13.0 40.4 55.4 LABOR COST INCLUDES THE LABOR COST CORRECTION FACTOR OF I.6 GIVEN IN TABLE A-4 OF REG. GUIDE 1.110 I OF 2

TABLE 1.1.2-8 (CONT)D)

ANNUAL OPERATING E MAINTENANCE COST ESTIMATE SHEET OF RADWASTE TREATMENT SYSTEM NINE MILE POINT NUCLEAR STATION-UNIT I N I AGA RA MOH AWK P OWER CORP 0 R ATION De gCI j p f j pq p f A u g elf GASEOUS AUGMENT No.2 -100 Vo FILTRATION OF THE CONDENSER VACUUM PUMP EFFLUENT COST (1975- $ IOOO)

LABOR OTHER TOTA L BASIS FOR COST ESTIMATE I. OPERATING LABOR, SUPERVISION, AND OVERHEAD USED ONLY DURING NEG STARTUP AND SHUTDOWN

2. MAINTENANCE MATERIAL 4 HEPA FILTERS Q 8150 AND LABOR 1.2 AND 2 CHARCOAL FILTERS

@ $ 900, CHANGE EVERY 2 YEARS

3. CONSUMABLES, CHEMICALS AND SUPPLIES IN ITEMS 2 AND 4

4. UTILITIES AND SERVICES WASTE DISPOSAL 0.2 $ 50/HEPA FILTER, $ 100/CHARCOAL FILTER WATE R STEAM E L ECTRICITY BUILDING SERVICES OTHER

5. TOTAL 0 AND M ANNUAL COST 1.4 2 OF 2

TABLE I.I.2-9 TOTAL DIRECT COST ESTIMATE SHEET OF RADWASTE TREATMENT SYSTEM NINE MILE POINT NUCLEAR STATION-UNIT I N I AGARA MO HAWK POWER COR POR ATION Description of Augment LIQUIDAUGMENTNo.l-2GPMREVERSEOSMOSIS(DETERGENT WASTES)

DIRECT COST (I975-$ IOOO)

BASIS FOR LABOR EQ U IP MENT/ MATER I ALS TOTA L COST ESTIMATE I. P ROCESS EQUIPMENT SKID MOUNTED W/500GAL.

96 60 69.6 S.S. F EED TANKS AS ME 2K(GIVEN INREG. GUIDE I.IIOs P.BI )

2. BUILDING ASSIGNMENT I2' 25'x l6'AT $ 6/f t.

30.7 9.6 40.5 (GIVEN IN REG. GUIDE I.IIO)

3. ASSOCIATED PIPING SYSTEMS 4;8 2.0 6.8 ALLOWANCE GIVEN IN REG. GUIDE I.IIO

4. INSTRUMENTATION G CONTROLS IN ITEMl

5. ELECTRICAL SERVICE ALLOWANCEGIVEN 11.2 I5.0 24.2 IN REG.GUIDE I.IIO

6. SPARE PARTS 6.0 6.0 (GIVEN IN REG. GUIDE I.IIO)

SU BTOTAL 56.5 90.6 l46.9

7. CONTINGENCY 5.6 9.0 l4.6 (I0% GIVEN IN REG. GUIDE I.IIO)

8. TOTAL DIRECT COSTS 6I.9 99.6 l6I.5 LABOR COST INCLUDES THE LABOR COST CORRECTION FACTOR OF l.6 GIVEN IN TABLE A-4 OF REG. GUIDE 1.110 1 OF 2

TABLE I.I.2-9 (CONT)D)

ANNUAL OPERATING E MAINTENANCE COST ESTIMATE SHEET OF RADWASTE TREATMENT SYSTEM NINE MILE POINT NUCLEAR STATION-UNIT I NIAGARA MOHAWK POWER CORPORATION D e scp I pf I p p pf A U g I 6nf LIQUID AUGMENT No.l -2GPM REVERSE OSMOSIS (DETERGENT WASTES)

COST (I975- $ IOOO)

ITEM LABOR OTHE R TOTAL BASIS FOR COST ESTIMATE I. OPERATING LABOR, SUPERVISION, l60~000GPYi ISOOHRS/YR AT 20%

AND OVERHEAD 3.l ATTENDANCE -GIVEN IN REG. GUIDE I.IIO

2. MAINTENANCE MATERIAL 8.8 4% LESS BLDG+24MODULE AND LABOR W/SYR. LIFE AT 4600EACH

3. CONSUMABLES, CHEMICALS AND SUPPLIES NEG.

4. UTILITIES AND SERVICES IOO: I VOL. REDUCTION AT WASTE DISPOSAL 4,3 $ 20/FT~ DISPOSAL COST WATE R STEAM E L ECTRICITY NEG.

BUILDING SERVICES OTHER

5. TOTAL 0 AND M ANNUAL COST l6.2 2 OF2

TABLE I.I.2-IO

SUMMARY

OF ANNUALIZED COSTS NINE MILE POINT NUCLEAR STATION-UNIT 1 NIAGARA MOHAWK POWER CORPORATION AUGMENTS GASEOUS LIQUID A TOTAL DIRECT COSTS (TDG) 7I3.4 53.4 l6I.5 8 TOTAL 'CAPITAL COSTS (TCC) I, I 27.2 84.4 255.2 C. ANNUAL FIXED COST (AFC) I38.8 I 0.4 3I.4 D. TOTAL OPERATION AND MAINTENANCE ANNUALCOST 82.2 l.4 l6.2 E. TOTAL ANNUALIZEDCOST (TAC) 22I.O I I.8 47.6 NOTES:

I. ALL VALUES ARE IN THOUSANDS OF 1975 DOLLARS

2. FOR EXPLANATION OF THESE TERMS% SEE SHEET 20F2 OF THIS TABLE 10F2

TABLE 1.1.2-10 (Cont.'d)

A Total Direct Costs See Sheet 1 of Cost-Analysis Sheets B Total Ca ital Cost Total Capital Costs = Total Direct Costs x Indirect Cost Factor (TCC) = (TDC) (ICF) where:

Indirect Cost Factor (ICF) = 1.58 (From Reg. Guide 1.110, Table A-5) Assume Multi-unit site, unitized radwaste systems 3 units n 3 3 3 ICF = 1 58 C. Annual Fixed Cost Annual fixed cost = Total Capital Costs x Capital Recovery Factor (AFC) = (TCC) (CRF) where:

CAPITAL RECOVERY FACTOR (CRF) = 0.1231 (From Reg. Guide

1. 110, Table A-6)

(1+@)>>-1 i

25

=

=

cost of money, % per year = 11.5k service life of NMP-1 as defined by Niagara Mohawk (1.115) as 1 10.20098338 14 20098338 CRF = 0.1231 D. Total eration and Maintenance Annual Cost See Sheet 2 of Cost-Analysis Sheets E. Total Annualized Cost (TAC) (From Reg. Guide 1.110, Appendix A, page 2)

, (TAC) = (AFC) + (AOC) + (AMC) 2 of 2

Tab1e 1.1.2-11

SUMMARY

OF COST-BENEFITS NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Benefit (at $ 1,000

, Aucuments Man-Rem Reduction er Man-Rem Gaseous Augment No. 1 0 083 1.6 $ 83 $ 1,600 Gaseous Augment No. 2 0.0 0.16 $ 160 Liquid Augment No. 1 0.081 4.3 $ 81 $ 4,300

Table 1.1.2-12 COST-BENEFIT COMPARISON NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK'OWER CORPORATION Annualized Cost (at Benef it

$ 1,000 per Cost-Benefit A~oente Dollars man-rem Ratio Whole Whole

~Bod ~Th zoid ~Bod ~Th oid Gaseous Augment. No. 1 221,000 $ 83 $ 1,600 2,660 138 Gaseous Augment No. 2 11 800 NA $ 160 NA 74 Liquid Augment No. 1 47,500 $ 81 $ 4i300 586 11

a' 1.2 Radioactive Source Terms This section discusses radioactive effluent releases which are calculated using the basic approach and assumptions contained in Regulatory Guide 1.112 and NUREG-0016. The code used in these analyses conforms to the methodology of NUREG-0016.

Values of parameters are based on NUREG-0016 data, Nine Mile Point Unit 1 design data, or Nine Mile Point Unit 1 operating data. Section 2.1 lists additional source term data requested in Chapter 4 of NUREG-0016.

The licensee has previously reported expected liquid and gaseous release values in both the Nine Mile Point Nuclear Station FSAR and ER. The data described herein represent an attempt to analyze the releases using the NRC model and assumptions and conform to the actual plant configuration as closely as possible.

Additional data are provided, relative to radioactive source terms, in Section 2.1 (i.e., the information requested in Appendix D to Chapter 4 of NUREG-0016) .

'V 1.2. 1 Coolant Activities The coolant activities axe obtained using the methodology described in NUREG-0016. The plant dependent, parameters and method for determining the coolant activities are discussed below.

The plant dependent data, regulatory guide reference plant parameters, and applicable ranges are shown in Table 1.2.1-1. As the Nine Mile Point Unit 1 power level of 1,850 MWt is outside the range given in Table 1.2.1-1, the NRC references of plant coolant activities shown in Table 2-2 of NUREG-0016 have been adjusted. The method of adjustment of the reference coolant 'ctivities is shown in Tables 1.2. 1-2 and 1.2.1-3. Table 1.2.1-4 lists the resultant Nine Mile Point Unit 1 coolant activities using these adjustment factors.

1 ~ 2 2

0 TABLE 1 2.1-1 NUREG-0016 TABLE 2-3 PAEUQG TERS USED TO DESCRIBE THE REFERENCE BOILING WATER REACTOR NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK P(NER CORPORATION Nine Reference Mile Plant Ran e Point 1 Parameter ~Sbol Units Value Maximum Minimum Value Thermal Power 3,400 3,800 3,000 1,850 Weight of Water in the Reactor Vessel lb 3.8 (5) 4 4.2 (5) 3.4 (5) 4 0 (5)

Cleanup Demineral-izer Flow Rate lb/hr 1. 3 (5) 5(5) 1 1(5) 1 ~ 8 (5)

Steam Flow Rate FS lb/hr 1. 5 (7) 7 (7) 1 3 (7) 7.3 (6)

Ratio of Condensate Demineral-izer Flow Rate to Steam Flow Rate NC 1.0 1.0 0.8 1.0

+3.8 (5) = 3. 8 x 10~

0 TABLE 1. 2 1-2 NUREG-001 6 ABLE 2-4 VALUES USED 'IN DETERMINING ADJUSTMENT FACTORS FOR BOILING WATER REACTORS NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Water Acti-vation Other Noble Halo- Pro- Nu-S " Tritium clides Fraction of material re-moved in the reactor water clean-up system 0.0 0.9 0.5 0.0 0.0 Fraction of material re-moved by the conden-sate demin-eralizers 0.0 0.9 0.5 0.0 0.0 0.9+

NS Ratio of concentra-tion in re-actor steam to the concentra-tion in reac-tor water (a) 0.02 0.001 (b) 1.0 0.00 Removal rate from the re-actor water (hri) (d) (a) 1.0 0 . 19 (b) (c) 0.34 (a) All noble gases released from the core are transported rapidly out of the reactor water to the reactor steam and are stripped from the system in the main condenser; therefore, the concentration in the reactor water is negligible and the stream concentration .is approximately equivalent to the ratio of the release rate to the steam flow rate.

1 of 2

Table 1.2.1-2 (Contd)

(b) Water activation products exhibit varying chemical and physical properties in reactor coolant which are not well defined. However, most are stripped off as gases which are not effectively removed by the demineralizers of the systems but their concentrations are controlled by decay.

(c) The tritium concentration in the reactor water arid steam is

,expected to be equal and i's controlled by the losses of water from the main coolant system by evaporation or leakage. The concentration is therefore given by the ratio of the appearance rate in the coolant, which is about 120 Ci/yr,- to the total loss from the system.

(d) These values of R whose parameters are given in Table 2-3 apply to the reference BWR and have been used in developing Table 2-5. For BWRs not included in Table 2-3, 'the appropriate value for R may be determined by the following equation:

R = FA NA + NC FS=NS NB for Halogens, Cs, Rb, and other WP nuclides where the symbols are defined in Tables 2-3 and 2-4 and Figure 2-1. The values for R for noble gases and water activation products are not used in the adjustment factors of Table 2-5.

+These represent effective removal terms and include other mechanisms such as plateout. Plateout would be applicable to nuclides such 'as Molybdenum (Mo) and corrosion products.

2 of 2

0 TABLE 1. 2. 1-3 NUREG-00 1 6 ABLE 2-5 ADJUSTMENT FACTORS FOR BOILING WATER REACTORS NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Nuclide Reactor Water Reactor Steam Noble Gases (a) 1.0 1.0 Halogens (b) 51x 1.0+ .51 x 1.0 +

R+ R +

Cs~ Rb .51 x 0.19 + ~ 51 x 0.19 +~

R+ k +

Water Activation Products 1.0 1.0 Trit.ium (c)

Other Nuclides .51 x 0.34 + X 51x 034+

R + X R +

(a) Assumes that the ratio of power to steam flow is essentially the same for all BWRs.

(b) ) is the isotopic decay constant (hr-~) .

(c) See note (c) Table 1.2.1-2.

0 0

TABLE 1 2 1-4 RADXONUCLIDE CONCENTRATIONS IN BOXLXNG WATER REACTOR COOLANT AND MAIN STEAM PCi NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA. MOHAWK POWER CORPORATION NOBLE GASES DECAY REACTOR CONSTANT ISOTOPE STEAM 1 SECOND KR-83M 1 1E-03 1. 04E-04 KR-85M 1.9E-03 4 30E-05 KR-85 6.0E-06 2.05E-09 KR-87 6.6E-03 1 52E-04 KR-88 6'. 6E-03 6.88EW5 KR-89 4 1E-02 3 66E-03 KR-90 9 OE-02 2 15EW2 KR-9 1 1. 1E-01 7 70E-02 KR-92 1. 1E-01 3.77E&1 KR-93 2 9E-02 5 46E-01 KR-94 7 2E-03 3.30E+00 KR-95 6 6E-04 1 39E+00 KR-97 4 4E-06 6.93E+09 XE-131M 7E-06 6 69E-07 XE-133M 9 OE-05 3.60E-06 XE-133 2 6E-03 1.52E-06'.

XE-135M 8 4E-03 55E-04 XE-135 7 2E-03 2 10E-05 XE-137 7E-02 3 01E-03 XE-138 2 8E-02 8 14E-04 XE-139 9 OE-02 1. 75E-02 XE-140 9 6E-02 5-10E-02 XE-141 7.8E-02 4.03E-01 XE-142 2.3E-02 5 68E-01 XE-143 3.8E-03 2.31E+00 XE-144 1 8E-04 6 93E-Oi

Table 1 2 1-4 (Cont.'d)

DECAY REACTOR REACTOR CONSTANT ISOTOPE WATER STEAM 1 SECOND HALOGENS BR-83 1-9E-03 3 9E-05 8 02E-05 BR-84 2.9E-03 5 8E-05 3 66E-04 BR-85 1 6E-03 3 1E-05 4 03E-03 I-131 3.5E-03 6 9E-05 9 98E-07 I-132 1 9E-02 3.8E-04 8 43E-05 I-133 '1-4E-02 2 7E-04 9.26E-06 I-134 4.2E-02 6.0E-05 2 20E-04 I-135 1.3E-02 2 7E-04 2 92E-05 CS RB RB-89 2 5E-03 2 5E-06 7 60EW4 CS-134 1 2E-05 1 2E-08 1 07E-08 CS-136 8-3E-06 8.3E-09 6 17E-07 CS-137 2 9E-05 2 9E-08 7. 30E-10 CS-138 5 OE-03 5 'E-06 3-59E-04 WATER ACTXVATION PRODUCTS N-13 5 OE-02 7 OE-03 1 16E-03 N-16 6 OE+01 5.0E+01 9 75E-02 N-17 9 OE-03 2 OE-02 1 67E-01 0-19 7-OE-01 2 OE-01 2 58E-02 F-18 OE-03 4.0Z-03 1.05E-04 TRITIUM H-3 1.0E-02 1.0E-02 1 79E-09 OTHER NUCLIDES NA-24 3 8E-03 3 8E-06 1 28E-05 P-32 8 2E-05 8 2E-08 5 60E-07 CR-51 2. 1E-03 2 1E-06 2.88EW7 Nh-54 2.5E-05 2. 5E-08 2 56E-08 MN-56 2 3E-02 2 3E-Oc 7.46E-05 FE-55 4 1E-04 4. 1E-07 8 14E-09 FE-59 1 2E-05 1 2E-08 1 78E-07 CO-58 8 2E-05 8 2E-08 1 12E-07 CO-60 1 6E-04 1 6E-07 18E-09 2 QS 3

Table 1.2.1-4 (Cont'd)

NI-63 4 1E-07 4 1E-10 2.39E-10 NI-65 1 4E-04 1 4E-07 7.55E-05 CU-64 1.3E-02 1 3E-05 1 51E-05 ZN-65 8 2E-05 8 2E-08 3.29E-08 ZN-69M 8 4E-04 8-4E-07 1 38E-05 SR-89 4-1E-05 4 1E-08 1 59E-07 SR-90 2 5E-06 2 5E-09 7 58E-10 SR-91 1.7E-03 1.7E-06 2 03E-05 SR-92 4.5E-03 4 5E-06 7. 11E-05 Y-91 1 6E-05 1.6E-08 1.37E-07 Y-92 2 7E-03 2.7E-06 5.45E-05 Y-93 1.7E-03 1 7E-06 1-89E-05 ZR-95 2.9E-06 2 9E-09 1 23E-07

'R-97 2 1E-06 2-1E-09 1 15E-05 NB-95 2 9E-06 2.9E-09 2 29E-07 NB-98 1.9E-03 1 9E-06 2 26EW4 MO-99 8 3E-04 8 3E-07 2 92E-06 TC-99M 8.7E-03 8 7E-06 3 20E-05 TC-101 4 5E-02 4 5E-05 8. 14E-04 TC-104 4.0E-02 4.0E-05 6 42E-04 RU-103 8-'2E-06 8 2E-09 2.03E-07 RU-105 8 8E-04 8 8E-07 4.34E-05 RU-106 1 2E-06 1.2E-09 2. 17E-08 AG-1 10M 4. 1E-07 4. 1E-10 3 18E-08 TE-129M 1.6E-05 1 6E-08 2 40E-07 TE-131M 4. 2E-05 4.2E-08 6 . 42E-06 TE-132 4.1E-06 4. 1E-09 2 47E-06 BA-139 4.7E-03 4.7E-06 1.39E-04 BA-140 1.6Z.,04 1.6E-07 6 27E-07 BA-141 5 OE-03 5.0E-06 6-31E-04 BA-142 3 OE-03 3.0E-06 1 08E-03 LA-142 2 3EW3 2 3E-06 1.25E-04 CE-14 1 1.2E-05 1 '2E-08 2 47E-07 CE-143 1 2E-05 1 2E-08 5 83K-06 CE-144 1.2E-06 .1 . 2E-09 2 82E-08 PR-143 1-6E-05 1 6E-08 5. 91E-07 ND-147 1.2E-06 2E-09 7.33E-07 W-187 1.3E-04 1. 3E-07 8 06E-06 NP-239 2 9E-03 2 9E-06 3. 41E-06 NOTE: The reactor water concentration is specif ied at the nozzle where reactor water leaves the reactor vessel; similarly, the reactor steam concentration is specified at time t= 0.

3 of

0 1.2.2 Gaseous Releases The main stack is the only release point for the gaseous effluents which consist of the reactor building, turbine building, and radwaste building exhausts, turbine gland mechanical vacuum pump, and off-gas system releases. seal'ondenser, The methodology for determining the releases is given in Regulatory Guide 1.112 and NUREG-0016. The individual release point descriptions are given below. A simplified flow diagram is shown on Figure 1.2.2 1. A more detailed listing of the parameters is given in Section 2.1.

1.2.2.1 Reactor Buildin The reactor building has two separate ventilation systems. One system is used during normal operation while the other is a standby to be used under accident conditions.

The normal ventilation system supply fans ordinarily provide filtered air to various parts of the building at a rate of approximately one change per hour. However, when conditions warrant, a higher speed operating mode is available which will provide approximately two changes per hour. Unit coolers using service water are installed locally where necessary for additional cooling.

During normal operation the pressure inside the building is held slightly negative, approximately 0. 1 in. of water (gage) relative to the outside to minimize out-leakage. Exhaust fans discharge all ventilating air to the stack. Exhaust. ductwork is arranged to draw air from areas where contamination is most likely to occur, thus preventing its spread into relatively cleaner areas. Both supply and exhaust ducts are provided with, two quick-closing (less than 60 seconds) leak-tight valves in

.series which trip closed automatically on high radiation level signal within the building.

The normal ventilating flow rates are about 35,000 and 70,000 cfm, respectively, for normal flow and high-speed purging.

The appropriate rate is manually selected by means of a two-speed control on the ventilation fan motors. The air supply equipment consists of a fresh air intake, filter, electric heating units which will automatically control to a set temperature, and two full-capacity fans equipped with inlet vane dampers. Since either fan is capable of the 70,000 cfm rate, one will normally be a full-capacity standby. Supply ductwork with dampers is provided to distribute the air to various areas throughout the building. Two 70,000 cfm exhaust fans (one normally on standby) are provided with connecting ductwork which draws the air mainly from areas of highest potential contamination and exhausts to the stack.

1 A 2 3

Both the main supply and exhaust ducts are equipped with two leaktight isolation valves -

in series which close automatically upon detection of high radiation levels within the building. They also may be controlled manually from the main control room. The inlet, and outlet duct penetrations through the building walls are sealed against leakage. A steel pipe sleeve is integrally cast. in the concrete and the outer end of the sleeve has a gasketed flange which connects to the first isolation valve. The reactor building atmosphere is automatically held at a slight negative pressure (0.1 to 0.2 in.

water, gage) by regulation of the supply dampers, to prevent or reduce exfiltration to the 'utside, even under high wind conditions.

1.2.2.2 Waste Dis osal Buildin The waste disposal building releases are those reported in Table 2-9 of NUREG 0016 on page C-56. The particulate releases have been reduced to account for HEPA filtration of exhaust ventilation air prior to release to the environment.

The waste disposal building heating and ventilating system is designed to supply filtered and heated air at approximately 9,000 cu. ft per min and exhaust filtration. This corresponds to about one change of air perit after hour. Building exhaust is through the stack.

The supply fans, exhaust fans, and exhaust filters are provided in full-capacity duplicates. Either supply fan and either exhaust fan can then be used to operate the system while the others are standby.

Outside air is drawn into the system through a fixed, louver housed above the roof of the building and protected by bird and insect screening. The air is drawn through a filter designed to remove dust,, and an electric heater of 200 kw capacity. The heater is thermostatically controlled to warm the air to maintain at least 70 F in accessible areas and 50 F in inaccessible areas. Beyond the heater section, the supply duct is split with each half routed through a supply fan of 9,000 cfm capacity. Each fan is isolated in its section of duct by a butterfly valve damper on both inlet and discharge sides. Beyond the fan discharge control dampers, the ducts rejoin into a common

. manifold from which supply ducts convey fresh air to various areas of the building. At or near the discharge point of each of these ducts, a manually set damper determines the fraction of air delivered at that particular point.

The fresh air supply points are located where the rate of air contamination is lowest while the exhaust ducts are located where the rate of contamination is likely to be the highest.

1.2-4

0 0

An air outlet is located in each room and at each piece of equipment or other place where radioactive contamination in the form of, dust, gas, or vapor could be released. Ducts from these areas lead to an exhaust air manifold with each duct having a manually set control damper.

A shunt circuit draws air from the exhaust manifold and monitors its airborne radioactivity. The circuit is located so that it, monitors building air conditions and not exhaust from equipment vents. High activity is alarmed in both the waste building control room and the Station main control room.

Beyond this 'oint., the exhaust duct divides into two branches, each of which contains a roughing filter followed by a highwfficiency filter and an exhaust fan. Butterfly valves in the ducts, before the filters, between filters and fans and following the fans determine which of the alternate routes the exhaust will take and regulate the amount of air exhausted. From here on the ducts are reunited and discharge to the plenum leading to the stack. Backflow from other sys'tems is prevented by interlocks which require valves to close are not in operation.

if the exhaust fans Each high-efficiency particulate filter in the system has a minimum removal efficiency of 99.97 percent based on exhaust the 0.3 micron "DOP" (dioctylphthalate smoke) test.

Supplementing this exhauster system is a 300 cfm capacity auxiliary system which exhausts air directly from the hydraulic baler through a roughing filter and a high-efficiency filter by means of a small exhauster fan and discharges directly into the ventilation breeching. Also, a 500 cfm capacity.

auxiliary system exhausts directly from the drum filling area through a roughing filter by means of a small exhauster fan and discharges to the exhaust duct of the building ventilating system. Equipment vents and the sample station hood discharge directly to the exhaust duct.

Supplementing the heat supplied by the main intake air heater, small heating units 'are provided locally to maintain desired temperatures for comfort of personnel and protection of equipment.

1.2.2.3 Turbine Buildin The turbine building releases are those reported in Table 2-9 of NUREG-0016, since there is no treatment of the exhaust ventilation air.

The turbine building ventilating system is designed to provide filtered and heated air at an approximate rate of one change per hour, corresponding to 170,000 cfm. Two independent air supply systems are provided, each consisting of a fresh air

1. 2-5

1 intake, filter, electric heating unit, flow control damper, two fans, dampers, and ductwork to distribute air to various areas in the turbine building. Each fan system is capable of supplying one-half oi the required air, and either of the two fans in each system is considered an installed spare. The air, duct electrical heating units are automatically controlled to maintain the supply air temperature at the desired level.

The exhaust air system consists of two full-capacity fans, with one fan considered an installed spare, and connecting ductwork designed to induce flow of air through areas of progressively higher contamination potential prior to final discharge to the stack.

An air inlet is located in each room and at each piece of equipment or other place where radioactive contamination in the form of dust, gas, or vapor could be released. Ducts from these areas lead to an exhaust air manifold with each duct having a manually set control damper.

The radiation protection and laboratory facilities ventilating system discharges directly to the turbine building exhaust duct.

A shunt circuit draws air from the exhaust manifold and monitors its airborne radioactivity. The circuit is located so that it monitors building air conditions and not the exhaust from.

equipment.'ents. High activity causes alarm in the Station main control room.

The exhaust system discharges into a plenum which also receives air from the containment and other buildings. Backflow from other systems to the turbine building is prevented by interlocks which require valves to be closed e not in operation.

if the exhaust fans The turbine building atmosphere is automatically controlled at a negative pressure of about 0.1 in. of water relative to the outside by modulating the flow control dampers on the air supply systems. This is to control release of contaminated air and prevent out-leakage.

1.2.2.4 Stack The stack is a free-standing reinforced-concrete chimney, 350 ft high, located 100 ft east of the northeast corner of the reactor building.

The height of the stack and the velocity of discharge are designed to provide a high degree of dilution for routine or accidental Station effluents.

1.2-6

0 1

It is a tapered monolithic reinforcedmoncrete tube resting on a massive concrete base which extends to sound rock.

From this base, it rises through the turbine auxiliaries building extension from which it is completely isolated structurally. The top of the stack is at El. 611, or 212 ft and 6 in. above the top of the reactor building, the next highest structure in the Station. /

The top of the stack is in effect an 8 ft-6 in. inside diameter nozzle. For normal gas flows of 216,000 cfm, the

. corresponding velocity of the discharge jet is 63 This relatively high velocity assures that the ft per sec.

turbulence generated will thoroughly mix, dilute, and disperse the discharged gas even at times of low wind velocity. The exit temperature for these gases is normally between 85 F and 100 F.

1.2.2.5 Mechanical Vacuum Pum The mechanical vacuum pump releases are as reported on page 227 of NUREG-0016 since there is no treatment of this gaseous release source except for a 1.75 min hold-up time before being sent to the stack.

1.2.2.6 Turbine Gland Seal S stem

'I Two full-capacity steam packing exhausters pull a slight vacuum at the turbine shaft packing. Duplicate exhausters provide added protection in the event one becomes inoperative.

Main reactor steam is used for the turbine gland seal system.

Although a larger volume of gases is handled by this system than by the off~as system, the total activity discharged is considerably less because of the relatively small amount of stean leaking through the gland seals. The large volume results from dilution of the steam with room air. Since the activities are low, the steam packing exhaust gases are held up for 1.75 min (to allow N-16 and 0-19 to decay) and then exhausted to the stack 1.2.2.7 OffMas S stem The off-gas system releases are based on a charco'al delay bed process. The charcoal delay beds provide a holdup time of 50 hr for Krypton and 890 hr for Xenon prior to release to the environment as calculated using the equation given on page 2-28 of . NUREG-0016. It is assumed that only noble gases are released from the delay beds.

Figure 1.2.2 1 illustrates a simplified schematic of the gaseous release system and Table 1.2.2 1 lists the gaseous releases.

1 & 2 7

1.2.2.8 Provisions to Reduce Radioactive Releases Two of the systems described above should also be mentioned as "provisions to reduce radioactive releases." They are the turbine gland seal system and the off~as system. In addition to the descriptions above, the off-gas system includes the equipment. described below.

Catalytic Recombiner The process off-gas from the main condenser air ejectors is diluted with steam to a hydrogen concentration of less than 4,percent by volume at all power levels. Radiolytic hydrogen and oxygen catalytically react in the recombiner to form water, thus eliminating the hydrogen hazard and reducing the volume of gas handled in the rest of the off-gas system. The hydrogen concentration downstream of the recombiner is less than

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

Condenser The off-gas system condenser is designed to provide the following functions:

a. Condense out the excess steam from the steam jet air ejectors and for hydrogen dilution

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

c. Remove the exothermic heat of reaction which takes place in the recombiner

~ Delay Pipe The first two-thirds of the original delay pipe is used to provide 2 1j'2 hr delay after the recombiners.

Dehumidification System The discharge from the 2 1/'2 hr delay pipe flows through freezewut chillers. In passing thiough this dehumidification system, the moisture content of the gas stream is reduced so that essentially a "dry" gas is produced before charcoal adsorbers.

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

1 2-8

0 Charcoal Adsorbers The discharge from the pre-adsorber flows through the charcoal adsorbers which provide for selective adsorption of the xenon and krypton isotopes from the bulk carrier gas (essentially air) . This permits the xenon and krypton isotopes to .decay thereby reducing activity releases.

Vacuum Pump The liquid ring type vacuum pump is installed to pull the off-gas through the recombiner charcoal adsorber system.

This allows the system to opera'te at a negative pressure which prevents the leakage of, any radioactive gases into the building.

Afterfilters remove any solid particulates or charcoal fines carried out of the charcoal adsorbers before they reach the vacuum pumps. The effluent from the vacuum pumps discharges to the stack.

1.2.2.9 Prima Containment S stem A pressure suppression containment system consisting of a drywell, suppression chamber (torus), and interconnecting vent piping is the primary containment for the main coolant system.

When the reactor is hot and pressurized, the reactor building containing the pressure suppression system provides a secondary containment barrier. When the reactor is shut down for refueling or maintenance, the drywell head is removed, and the reactor building provides the principal containment.

The volumes for the primary containment-pressure suppression system are as follow:

Suppression Dr ell and Vents Chamber Total Volume (No Equipment) 202,700 cu ft 209,000 cu ft Approximate Free Volume 180,000 cu ft 120,000 cu ft

'he Nine Mile Point Nuclear Station Unit 1 does not have a containment building internal recirculation system nor pressurized storage tanks.

1.2-9

TABLE 1 2 2-1 RELEASES VIA MAIN STACK NINE MILE POINT NUCLEAR STATION - UNIT 1 NIAGARA MOHAWK POWER CORPORATION GASEOUS RELEASES Ci r TURBINE GLAND MECHANICAL REACTOR TURBINE RADWASTZ SEAL OFP~ VACUUM BUILDING BUILDING BUILDING SYSTEM SYSTEM PUMP KR-83M 0 0 0 0 0.0 2 5E+01 0.0 0.0 2 SZ+01 KR-85M 6 OE+00 6 8E+01 0.0 4.4E+01 1.7z+01 0 0 1 3E+02 KR-85 0 0 0 0 0.0 0 0 1.4E+02 0 0 1 4E+02 KR-87 6.0E+00 1 9E+02 0 0 1.5E+02 0 0 0 0 3 Sz+02 KR-88 6.0E+00 2 3E+02 0.0 1.5E+02 0 0 0 0 3 9E+02 KR-89 0 0 0 0 0 0 6 5E+02 0.0 0 0 6 5E+02 XE-131M 0 0 0 0 0.0 0 0 1 3E+01 0 0 1.3E+01 Xz-133M 0 0 0.0 0 0 2 1E+00 0.0 0.0 2 1E+00 XE-133 1 3E+02 2.8E+02 1 OK+01 6 Oz+01 4 7E+02 2 3E+03 3 2E+03 XE-135M 9 2E+01 6 SE+02 0.0 1 8E+02 0.0 0 0 9.2E+02 XE-135 6 8E+01 6 3E+02 4.5E+01 1 7E+02 0 0 3 5E+02 1 3E+03 Xz-137 0.0 0 0 0 0 8 OE+02 0 0 0 0 8 OZ+02 XE-138 1 4E+01 1.4E+03 0 0 6 OE+02 0 0 0 0 2 1E+03 I-131 3 4E-01 1 9E-01 4 6E-02 6E-02 0 0 3 OE-02 6 2E-01 I-133 1.4E+00 7 6E-01 1 8E-01 6 3E-02 0 0 0.0 2.4E+00 CO-60 2 OE-02 2.0E-03 9.0E-04 0 0 0 0 0 0 2 3E-02 CO-58 1 2E-04 6 OZ-03 4 5E-05 0 0 0.0 0 0 'l 8E-03 CR-51 6 OE-04 1 3E-02 9.0E-05 0 0 0 0 0 0 1. 4E-02 MN-54 6 OE-03 6 OE-04 3 6E-04 0 0 0 0 0 0 7 OE-03 PE-59 8 OE-04 5 OE-04 1 Sz-04 0 0 0.0 0 0 5E-03 ZN-65 4 OE-03 2 OE-04 1 OE-05 0.0 0.0 0.0 4 2E-03 ZR-95 8.0E-04 1 OE-04 5 OE-07 0.0 0 0 0 0 9 OE-04 SR-89 1 8E-04 6 OE-03 5 Oz-06 0 0 0 0 0 0 6 2E-03 SR-90 1 OE-05 2 OE-05 3 OE-06 0 0 0 0 0 0 3 3EMS SB-124 4 OE-04 3 OE-04 5 OE-07 0 0 0 0 0.0 7 OEM4 CS-134 8.0E-03 3 OE-04 4.5E-05 0 0 0 0 0 0 8 3E-03 CS-136 6 OE-04 S.OE-OS 4 5E-06 0 0 0 0 0.0 6 5E-04 CS-137 1 OE-02 6 Oz-04 9.0E-05 0 0 0.0 0.0 1 1E-02 BA-140 8 OE-04 1 1E-02 1 OE-06 0 0 0 0 0 0 1 2E-02 CE-141 2.0E-04 6 OE-04 2 6EWS 0 0 0.0 0 0 8 3E-04 C-14 0 0 0 0 0 0 0.0 9.5Z+00 0 0 9.5E+00 AR-4 1 2 5E+01 0 0 0 0 0.0 0.0 0.0 2 SZ+01 H-3 2.3E+01 NOTES 1. 6.8E+01 = 6.8 x The reactor building is equal to the combined NUREG-0016 containment 10'.

building and auxiliary building releases 3.

4.

Por noble gases, 0 is printed if the release is less than 1 curie/yr The tritium proportionment by release stream is not specified 1 of 1

1. TURBINE BUILDING EXHAUST VENTILATION

2. REACTOR BUILDING EXHAUST VENTILATION

3. WASTE DISPOSAL BLDG. HEPA EXHAUST VENTILATION FILTER

4. TURBINE GLAND SEAL HOLD-UP CONDENSER GASES

5. MECHANICAL VACUUM PUMP EXHAUST MAIN STACK

6. STEAM JET AIR CHARCOAL EJECTOR EXHAUST DELAY BEDS HOLD - UP T I ME KRYPTON 50 HOURS XENON 890HOURS FIGURE 1.2.2-1 GASEOUS RELEASES SIMPLIFIED FLOW DIAGRAM NORMAL OPERATION NINE MILE POINT NUCLEAR STATION - UNIT 1 NIAGARA MOHAWK POWER CORPORATION

0 1 2.3 Li uid Releases The liquid radwaste system, shown in Figure 1.2.3-1, is composed of four substreams. Figure 1.2.3-2 depicts the liquid radwaste treatment used in the analyses. A fraction ranging

.between 0 1 to 1 0 of each substream flow is assumed to be discharged to Lake Ontario via the once-through cooling system.

This assumption and the others used to determine the liquid releases are based on Regulatory Guide 1.112 and NUM%-0016.

The pertinent recommendations taken from NUREG-0016 are summarized below:

Plant capacity factor 0.8 Decay times Collection time: Volume of Tank Average input flow rate x.4 Process time: Volume of Tank  :

Processing capacity flow rate x.4 Discharge time= 0, if capacity of first tank is less than or equal to last tank Condensate demin-eralizer regenera-tion frequency: 1/7 days Decontamination factors Detergent evaporators: 100 all isotopes Radwaste demineralizer: 2&si Rb; 100 others Polishing demineralizer: 10 all isotopes Anticipated annual operation occurrences: 0 15 curies/year The treatment assumed for each liquid radwaste stream is discussed below 1 2 3 1 Laund Wastes The laundry wastes feed into the laundry drain tanks at a rate of 450 gal per day. This analysis then assumes the total tank volume is discharged without treatment.

The source terms and flow rates for the laundry drain wastes discharged to Lake Ontario are taken directly from NUREG-0016, Table 2-32 (see Table 2.1.5-1) .

1 2-10

1 2 3 2 R enerant Chemicals NUREG-0016 assumes demineralizer regeneration, a volume that, of f or each 11,900 gallons condensate is sent to the waste neutxalizer tank. This number is also assumed for the reactor water clean-up demineralizex and waste demineralizer regeneration.

The feed rate into the regenerant chemical stxeam consists of condensate~ reactor water cleanup and radwaste demineralizer regenerations as well as, decontamination drains and chemical laboratory wastes for a total of 5,300 gal per day.

The regenexant chemical stxeam feeds into the xegenerant neutralizer tank, filling this tank to 40 percent capacity in 27 hr The tank volume is then processed via the regenerant chemical waste concentrator (20 gal per minute) with the distillate routed to the waste collector tank for process and release via the high purity system (Section 1.2.3.4) .

The decontamination factors used on this stxeam are based on a detergent waste evaporator (DP=100) ~d a polishing demineralizer (DF=10) in series for an overall DF equal to 1,000 on all isotopes.

In the event the waste concentrator is inoperable for two consecutive days per week (according to NUREG-0016), there is sufficient tank capacity (i.e. two days collection time by the waste neutralizer tank and waste surge tank when allowed to to 80 percent of capacity) so that there is no discharge of the fill chemical regenerant stxeam directly to the environment..

1.2 3.3 Low Purit Waste The low purity waste stream consists of the floor drains feeding into the floor drain collector tank The feed rate is 18,500 gal per day.

The low purity stream feeds into the floor drain collector, filling this t~dc to 40 percent capacity in 5.3 hr.

The tank volume is then processed in the exact same manner as the xegenerant chemicals (Section 1.2.3 2) .

In the event the waste concentrator is inoperable for two consecutive days per week (according to NUREG-4016), there is sufficient tank capacity (i.e two days collection time by the Floor Drain Collector Tank, Floor Drain Sample Tanks, and the Waste =Surge Tank when allowed to fill to 80 percent of capacity) so that alternate processing by the Waste Deminexalizer is not required.

1.2-11

1 2.3.4 Hi h it Waste The feed rate into the high purity waste stream consists of the drl~ll floor drains, the equipment drains, condensate demineralizer resin rinse and backwash, and waste concentrator distillate for a total of 87,000 gal per day.

The high purity stream feeds into the waste collector tank, filling this tank to 40 pexcent capacity in 2 7 hr. The stream is then processed via the radwaste demineralizer at 300 gal per minute, with the demineralized water routed to the waste sample tanks. The decontamination factors used on this stream are 2 for Cs and Rb and 100 for all others. It is assumed that 10 percent of this stream is discharged to .Lake Ontario.

1 2 3.5 Li d Radioactive Effluents The liquid releases are listed in Table 1.2 3-1. toA total of 1.3 Ci/yr of non~itium radioisotopes is calculated be released. This includes 0.15 Ci/yr to account for operational occurrences. Tritium releases are estimated to be 23 Cijyr.

1 2-12

't TABLE 1.2. 3-1 LE UID RELEASES NINE MILE POINT NUCLEAR STATION UNET 1 NIAGARA MOHAWK POWER CORPORATION

~1eoto e

'nnual Activit keleasea

~gCi~} ~Ci Na-24 5.3E-11 2.6E-02 P-32 1 7E-12 8 4E-04 Cr-51 4 9E-11 2 4E-02 Mn-54 2.9E-12 1 4E-03 Mn-56 2. 1E-10 1 OE-01 Fe-55 1.2E-11 5 9E-03 Fe-59 3-OE-13 1-5E-04 Co-58 1.0E-11 5 1E-03 Co-60 2.3E-1 1 1 1E-02 Ni-63 1-2E-14 6.0E-06 Ni-65 1.3E-12 6 1E-04 Cu-64 1.8E-10 8 6E-02 Zn-65 5.5E-12 2. 5E-03 Zn-69M 1 2E 11 5 6E-03 Sr-89 1. 1E-12 5 3E-04 Sr-90 7 5E-14 3 7E-05 Sr-91 2. 2E-11 1 -1E-02 Sr-92 4.2E-11 2 OE-02 Y-91 4 7E-13 2.3E-04 r-92 4E-1 1 2. 1E-02 Y-93 2.2E-11 1E-02 Zr-95 7. 6E-14 3 7E-05 Zr -97 2-9E-14 1 4E-05 hb-95 4 1E-12 2 OE-03 Nb-98 7 2E-12 3. 5E-03 Im-99 1.3E-11 6.5E-03 Tc-99M 1. OL-10 5. 1E-02 Tc-101 1.6E-11 8 OE-03 Tc-104 2.6E-11 1-3E-02 Ru-103 2.0E-13 ~ 9.8E-05 Ru-105 9 8E-12 4-8E-03 RU-106 4 9E-12 2.4E-03 Ag-1 10M 9.3E-11 4 5E-04 Te-129M 3; 8E-13 1.9E-04 Te-131M 6 2E-13 3.0E-04 Te 132 6. 8E-14 3 3E-05 da-139 2 e9E-11 1 4E-02 Ba-140 3 e3E 12 1 6E-03 Ba-141 3 4E-12 1. 6E-03 ba-142 4.8E-13 2 .3E-04 1 of 2

TABLE 1.2.3-1 (Cont'd)

Annual

~Isoto e Activit Released tu c~icggt ~ci La-142 1.8E-11 8-7E-03 Ce-141 2.9E-13 1. 4E-04 Ce-143 1.8E-13 8.8E-05 Ce-144 1.0E-11 5 OE-03 Pr-143 3 4E-13 1 7E-04 Nd-147 2. 4E-14 1. 2E-05 W-187 1 9E-12 9. 2E-04 Np-239 6E-11 2 2E-02 Br-83 1 7E-1 1 8. 1E-03 Br-84 5 6i'.-12 2 .7E-G3 Br-85 1 9E-16 9 3E-08 I-131 2. 6E-10 1. 3X.-01 I-132 1.6E-10 7. 9E-02 I-133 2.6E-10 1.3E-01 I-134 1.6L-10 8.0E-02 I-135 1 7E-10 8. 1E-02 Bb-8 & 5.4E-11 2 6E-02 Cs-134 3.5E-11 1 7E-02 Cs-136 6 2E-12 3.0E-03 Cs-137 7. OE-11 3. 5E-02 Cs-138 5 OE-10 2.4E-01 H-3 4.7E-08 2 3E+01 Grams Released 4 9E+14 2.3E-11 = 2.3X10-> i Isotope releases of less than 1.0E-10 curies/year are set to 0 Anticipated operational occurrences: 1.50E-O1 curies added to release Blowdown rate: 4. 8 6E+ 14 (yes f'year)

Total release (excluding tritium) is 1.3E+00 curies Total release (excluding tritium) is 2.5E-09 w Ci/gram 2 of 2

TI

<PKRVURE II ARD ULTRASONIC RESIN CLEANER

~so Available On 1 Aperture Card OFF-GAS DRAINS CONDENSATE DEMINERALIZER WASTE RINSE COLLECTOR WASTE TANK WASTE SAMPLE PUMPS (25) 000 GAL.) COLLECTOR (2 (R 300 GPM EACH)

RX. BLDG. FILTER EQUIPMENT DRAINS (300 GPM) WASTE WASTE OEM INERALIZER TURB. BLDG. COLLECTOR (300 GPM)

EQUIPMENT DRAINS PUMP (300 GPM)

TO CONDENSATE STORAGE TANK DRYWELL EQUIPMENT DRAINS WASTE SURGE WASTE TANK SAMPLE TANKS DRYWELL (50,000 GAL.) LAUNDRY (2'25TOOO GAL. EACH)

FLOOR DRAINS DRAIN TANKS NEW WASTE (2CS 1000 GAL.EACH)

WASTE CONCENTRATOR SURGE DISTILLATE PUMP FLOOR (300 GPM) DRAIN WASTE FILTER, CONCENTRATOR LAUNDRY DRAIN TANK PUMPS DISTILLATE (300 GPM) FLOOR DRAIN (2 Q 50 GPM EACH)

SAMPLE PUMPS (2($ 150 GPM)

TO WASTE COLLECTOR TANK FLOOR DRAIN RX. BLDG. COLLECTOR TANK FLOOR DRAINS (10,000 GAL.)

TURB BLDG.

FLOOR DRAINS FLOOR DRAIN TANK PUMP (300 GPM) WASTE RAD WASTE CONCENTRATOR FLOOR DRAINS (20 GPM)

CENTRIFUGE CONCENTRATOR FLOOR DRAIN EFFLUENT FEED PUMP SAMPLE TANKS (20 GPM) (2 (9 10,000 GAL. EACH)

I TO CIRCULATING WATER DISCHARGE TUNNEL TO WASTE RINSE TO WASTE COLLECTOR EUT. TANK NEUTRAL- TA$ K REGENERANT CHEMICALS TAN% SPENT i USED EXCLUSIVELY FOR HIGH CONDUCTIVITY FILTER SLUDGE RESIN TANK WASTE STORAGE (15,000 GAL.) STORAGE TANK L'ABORATORY DRAINS (4,000 GAL.)

WASTE NEUT. WASTE NEW CONCENTRATOR CONCENTRATE PUMP (300 GPM) WASTE TANK SPENT RESIN DECONTAMINATION 12 GPM)

DRAINS DIRTY CONDENSATE I (8,000 GAL) CENTRIFUGE TANK PUMP DEMINERALIZER RESIN 7 (20 GPM) (20 GPM)

FILTER SLUDGE To WASTE I STORAGE TANK COLLECTOR TANK PUMP (20GPM)

CONCENTRATOR RINSE t I ++ I TO FLOOR DRAIN COLLECTOR TANK I' WASTE TRAVELING I HOPPER FIGURE 1.2.3-1 CHEMICAL LAB WASTE BELT I LIQUID AND SOLID RADWASTE SYSTEM ULTRASONIC I I MIXER CLEANERI I FILTER I NINE MILE POINT NUCLEAR STATION-UNIT I CLEAN RESIN TO NIAGARA MOHAWK POWER CORPORATION HOLDING TANK SHIPPING CONTAINERS

) CONCENTRATE WASTE TANK (5TOOO GAL.)

- DI 9 7/Og g0035

WASTE PUMP WASTE HIGH PURITY WASTES WASTE COLLECTOR 300 GPM SAMPLE

1. DRYWELL (EQUIPMENT 8 FLOOR) DRAINS TANK DEMINERALIZER TANK 10% RELEASE

2. REACTOR, TURBINE AND RADWASTE TO ENVIRONMENT EQUIPMENT DRAINS (1) 251000 (2) 25,0vO GALLONS 300 GPM

3. CONDENSATE DEMINERALIZER RESIN RINSE GALLONS (EACH)

4. CONDENSATE BACKWASH

5. NEW WASTE CONCENTRATE DISTILLATE WASTE SURGE TANK (I ) 50,000 GALLONS LOW PURITY WASTES FLOOR DRAIN COLLECTOR PUMP 300 GPM J WASTE DISTILLATE

1. REACTOR, TURBINE AND RADWASTE TANK CONCENTRATOR TO HIGH PURITY BUILDING FLOOR DRAINS WASTES

( I) 10,000 GALLONS 20 GPM WASTE PUMP REGENERANT CHEMICALS NEUTRALIZER 20 GPM

1. WASTE, REACTOR WATER CLEANUP AND TANK CONDENSATE DEMINERALIZER REGENERATION

2. LABORATORY DRAINS (1) 15,000

3. DECONTAMINATION DRAINS GALLONS

4. CHEMICAL LABORATORY WASTE LAUNDRY PUMP IOO 1 RELEASE LAUNDRY DRAINS DRAIN 50 GPM TO ENVIRONMENT TANKS (2) 1,000 GALLONS (EACH)

FIGURE 1.2.3-2 LIQUID RELEASES SIMPLIFIED CALCULATIONALMODEL NOTE FLOW RATES ARE LISTED IN SECTION 2.1 NINE MILE POINT NUCLEAR STATION- UNIT I NIAGARA MOHAWK POWER CORPORATION

1.3 Meteorol drol This, section is in two parts Section 1.3.1 addresses meteorology and 1.3 2 addresses hydrology.

This section describes the meteorological data used in the dose assessments. The information referenced here and provided in the Nine Mile Point Nuclear Station Unit 2, Docket No. 50-410, Compliance with 10CFR50 Appendix I, June 4, 1976, is also applicable to Nine Mile Point Unit 1.

1.3.1 1 On-Site Meteorolo ical Pr ram Data The onwite meteorological data for the years 1974 and 1975 have been summarized in Response B-1 of the Nine Mile Point Nuclear Station Unit 2, Docket No 50-410, Compliance with 10CFR50 Appendix I, June 4, 1976. That response includes the following information:

a Monthly and annual wind speed and direction data, in joint frequency form, at all heights of measurement representative of wind characteristics for points of effluent release to, and transport within, the atmosphere

b. Monthly and annual joint frequencies of wind direction and speed by atmospheric stability class at heights and

~

intervals relevant to atmospheric transport of effluents

c. Total precipitation by month, number of hours with precipitation, rainfall rate distributions and monthly precipitation wind roses 1-3-1

0 1.3.1.2 Re ional Meteorolo ical Conditions The regional meteorology has been discussed in Response B-2 of the Nine Mile Point Nuclear Station Unit 2, Docket No. 50-410, Compliance with 10CFR50 Appendix I, information:

June 4, 1976. That response includes the following

a. Wind speed and direction data at all height(s) at which wind characteristic data are applicable or have been measured

b. Atmospheric stability data as defined by vertical temperature gradient or other well documented parameters that have been substantiated by diffusion test data

c. Monthly mixing height data

d. Total precipitation by month, number of hours with precipitation, rainfall rate distributions, and monthly precipitation wind roses

e. Describe airflow trajectory regimes of importance in transporting effluents to a distance of 50 miles from the plant, including airflow reversals 1 & 3 2

This section and, the dose calculations are based on

.hydrology models which are consistent with Regulatory Guide 1. 113.

The near field dilution factor at the edge of the initial mixing zone is based on the prompt lake dilution factor of 5, based on a submerged, high velocity, effluent discharge point in shallow, water in accordance With Table A-1 of Regulatory Guide 1.109.

The . dilution factors at larger distances are calculated in accordance with Regulatory Guide 1.113 and are summarized in Table 1.3.2 1.

1 % 3 3

A 1 3.2.1 uantitative Water Use Dia ams This section discusses the quantitative water use for the plant showing flow rates to and from the various plant water systems (heat dissipation system, sanitary system, radwaste and chemical waste systems, process water system, etc.) in support of liquid radionuclide release rate and concentration estimates.

Cooling water for the main condenser, auxiliary systems, reactor shutdown heat removal, and for water system makeup is withdrawn from Lake Ontario via the submerged intake tunnel.

This water is circulated by the main 'condenser circulating water pumps and/or the service water pumps. The flow'nd heat dissipation rates are indicated on the Water Usage Flow Diagram, Figure 1.3.2-1.

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

Maximum flows indicated for auxiliary heat exchangers and reactor shutdown are based on design heat loads for heat exchangers and a lake temperature of 77 F. Three pumps and heat exchangers are run at this time rather than two which are used during normal operation.

1 3-4

1.3.2.2 Consum tive Plant Water Use This section discusses the consumptive use of water by the plant, including the considerations of power operation and temporary shutdown.

In addition to the information included in Section 1.3.2. 1, the water flow rates from waste regeneration, residual heat removal, makeup water, domestic water, laundry, such and floor drain water usages are variable and are dependent upon things as the phase of demineralizer regeneration, time of year, and station operating status. Consumption of water furnished by the City of Oswego water system has averaged 3300 gpd.

All systems which use water discharge cannot to the lake, and an exact determination of water consumption be made.

However, evaporation it is would estimated not exceed that 0.02 water cfs or consumption 10 gpm.

due This mainly does to not include evaporation from the lake surface due to thermal dissipation of the circulating water discharge.

1. 3-5

1.3.2.3 Location and Nature of Water Use Within 50 Miles This'ection identifies the location, nature, and amounts of present and projected (over plant life) surface water use (e.g., water supply, irrigation, reservoirs, fisheriesg recreation) within 50 miles of the plant where detectable amounts of radioactivity from plant licgxid effluents may be expected to affect such use. The bases for estimating present and projected water use are provided and the users located on maps of legible scale. A tabulation of the following specific information .for water users is provided:

a. Map identification key

b. Radial and water route distance from the plant to the intake and discharge Ce Withdrawal and return rates in cfs or gpm for present and projected monthly use

d. Type of water use (e.g., municipal, industrial, irrigation)

'e. Source and projection dates of water use estimates.

Studies to determine the exact data were not performed.

However, a search of existing licensing documents has been performed and the results are presented below.

Water Su 1 and Industrial Use Information regarding the location and average pumpage of water from Lake Ontario for human consumption within 50 miles of the Nine Mile Point Nuclear Station Unit 1 (NMP1),site was obtained for U.S. shores from: the New York State Public Water Supply in Albany, 'ew York; from the local offices in Monroe, Wayne, Cayuga, Oswego, and Jefferson counties; from the water departments and water plants of various villages, towns, and cities; and from the Department of Environmental Conservation/

Bureau of Water Regulations and Water Resources Planning.

Table 1.3.2-2 summarizes the locations and the average amounts of water pumped from the U.S. shores of Lake Ontario within a 50 mile radius of NMP1. Figure 1.3.2-2 shows the locations of these intakes. Only three pumpage intakes are located within 30 miles of the NMP1 discharge point (Locations 4g 5, and 6) . The dilution provided by Lake Ontario for locations greater than 30 miles renders any dose to the population to be insignificant. The three locations within 30 miles are Sodus Point Village, East of Port Bay, and the City of Oswego. Of these three locations, the City of Oswego intake 'ccounts for approximately 99 percent of the pumpage. For the above reasons, 1 3-6

4 W

0 4

I 5~

the City of Oswego water intake is the only water usage for human consumption considered in this analysis.

Population projections may be used as an indication of future water usage. Population projections can be found from the following references:

1. Nine Mile Point Nuclear Station Unit 2 Preliminary Safety Analysis Report (NMP2-PSAR), Tables 2.1-1 and 2;1-2

2. Nine Mile Point Nuclear Station Unit 2 Environmental Report Construction Permit Stage (NMP2-ER), pages 2.2-4 and 2.2-5

3. NMP2-ER, Figure 2.2-6

4. NMP2-ER, page 5.2-8

5. NMP2-PSAR, Figures 2.1-5 through 2.1-14 Irri ation Irrigation data are located on page 5.2 6 of the NMP2 ER. The most recent surveys indicate that the orchards discussed in the NMP2-ER no longer use lake water for irrigation.

Recreation and Fishin Information on recreation and fishing within about 10 miles of the site is provided as follows:

1. NMP2-ER, pages 2.2-2 and 2.2-3

2. NMP2-ER, pages 5.2-3 and 5.2-5

3. NMP2-ER, page S2.6-2

4. NMP2-PSAR, pages 2.1-3 through 2.1-5

5. NMP2 PSAR, page R2.22 1 Additional information on fishing on Lake Ontario appears on page 8.4-5 of NMP2-ER.

General Area maps useful in locating recreation areas, projected future land use, and present industry in Oswego are located in the following references:

1. NMP2 PSAR, Figure 2.1-2 1 ~ 3 7

'I 0

2. NMP2-PSAR, Figure 2.1-18

3. NMP2ER, Figures 2.2-2 and 2.2 3

4. NMP2-ER, page 5.4-11 1.3-8

1.3.2.4 Descri tion of Dischar e Structure The following section provides a detailed description of the liquid discharge structure. It restrictions (state or local) on releases.

also discusses institutional Li uid Dischar e Structure As shown on Figure 1.3.2-3, water is returned to Lake Ontario at a point about oneWenth of a mile offshore (585 ft from the screenhouse) through a bell-mouthed outlet surmounted by a hexagonal-shaped discharge structure of concrete. The top of this structure is about 4 ft. above lake bottom and 8 1/2 ft There are six exit ports below the lowest anticipated lake level.

about 3 ft high by 7 1/3 ft wide. The vertical shaft connecting the discharge tunnel with the discharge channel under the screenhouse has a sand trap at its foot to catch and store any lake-bottom sand which may wash over the sills of the outlet structure.

Liquid waste is discharged directly to the vertical discharge shaft. A submerged diffuser in the vertical shaft ensures good dilution before discharge to the lake. Samples are drawn at a lower point in the shaft.

State and Local Restrictions The New York State Environmental Conservation Law, Article 17, "Mater Pollution Control," sets forth the state policy regarding "this subject. Specific regulations pertinent to pollutant discharges and water quality standards are published as parts 700 through 704, Title 6 of the New York Code of Rules and Regulations.

1.3-9

~ C

~ P

1.3.2.5 Descri tion of Ambient Flow in Lake Ontario This section describes the ambient flow field of the water body affected by plant liquid radionuclide effluents out to a radius of 50 miles. It also describes expected seasonal and other temporal variations of important parameters (e.g., flow, currents) .

New studies to determine exact ambient flow data were not performed. However, a search of existing licensing documents has been 'performed and the results are presented below.

Flows and currents in Lake Ontario have been described in the following locations:

1. Nine Mile Point Nuclear Station Unit 1 Environmental Report Operating License Stage (NMP1-ER), pages 2.5-1 through 2.5-4

2. NMP2-.ER, page 5.1-4

3. NMP1-ER, pages 5.4-6 and 5.4-7

4. NMP1-ER, page H-6

5. James A. FitzPatrick Nuclear Power Plant Environmental Report Operating License Stage (JAF-ER), Appendix I.

6. Preliminary Hazards Summary Report, Nine Mile Point Nuclear Station Unit 1 (NMP1-PHSR), Appendix B

7. Nine Mile Point Nuclear Station Unit 2 Preliminary Safety Analysis Report (NMP2-PSAR), page 2.7-6

8. NMP2-PSAR, Figures R2.34-4 and R2.34-11

9. 1970 Lake Temperature and Current Studies, Stone 6 Webster Engineering Coiporation, June 1971

10. Nine Mile Point Nuclear Station Unit 1, Final Safety Analysis Report (NMP1-FSAR), Appendix B The only water body 'ffected by plant liquid radionuclide effluents is Lake Ontario. The limited extent of detectable effects has been generally indicated on page 5.4-11 of the NMP2 ER. Data 'reported'n page B-4 of the NMP1-PHSR and dilution factors for Canada given on page 45 of the JAF-ER support the conclusion of limited affected areas.

Bathymetry and shoreline geometry have been well described in the following references:

1,. 3-10

Y y

1. NMP2-ER, Figure 3.2-1

2. NMP2-PSAR, Figure 2.1-3

3. NMP2-PSAR, Figure 2.7-1

4. NMP2-PSAR, Figure 2.7-35

5. NMP2-PSAR, Figure R2. 13-3

6. NMP1-PHSR, Appendix B'.

, 1970 Lake Temperature and Current Studies, Stone 6 Webster Engineering Corporation, June 1971

8. NMP1-FSAR, Appendix B Some of the above sources are complete reports of limnological studies. Other references are listed in the NMP2-ER on pages F1, 2, 5, and 6; on page H8; and on page S2.5-3.

1.3.2.6 Li uid Radionuclide Releases The estimated monthly average of liquid effluent containing radionuclides, as calculated in accordance with Draft Regulatory Guide 1.CC, is 260,000 gal. The effluent is diluted with 1.07 x 10~o gal/inonth of liquid from the once-through cooling flow. The resulting concentrations in p Ci/gm, released to Lake Ontario, are listed in Table 1.2.3-1.

1 w3 12

1 3 2.7 Radionuclide Concentrations and Travel Times in Lake Ontario This section provides estimates of radionuclide concentrations and travel times at use locations identified in Section 1.3 2.3, annually, and for the time periods used to identify. water use, flow fields, and release rates. The transport model(s) used, input data and parameters, sources of data and parameters, techniques and results are discussed Table 1.3.2-3 provides estimated radionuclide concentrations. These concentrations represent annual average values. Dilution factors and travel times in the lake for water use at locations identified in Section 1 3.2 3 (mixing zone, Lakeview Summer Camp, Oswego City Public Water Supply, and Selkirk State Park) are presented in Table 1.3.2-1

~

No travel time decay is considered in arriving at the Mixing Zone Concentrations. An approximate lake dilution factor of 5 is used based on a submerged, high velocity discharge in shallow water (See Table A-1 of Ref. 1). For other usage locations, lake dilution factors are calculated using the quasi-steady-state model as described in Section 3, "Great Lakes," of Regulatory Guide 1.113 (Ref. 2) . Specif ically, equations (17) and (18) of Regulatory Guide 1.113 are used for dilution factors:

D = W/(XQ)

"!y( = 227rayaz 5(<,i<i Ee.d) f(<y.yiye) where.

Volumetric discharge rate (m3/sec)

X Concentration at usage location (Ci/m>)

W Point source discharge rate (Ci/sec)

~ye ~z Standard deviations for coordinate directions Y and Z, respectively (m)

Mean velocity in the X direction (m/sec)

Ze iYe Z and Y coordinates at the point source discharge (m)

ZiY Z and Y coordinate of the usage point. (m) d Depth of the lake at the discharge point (m) j(,,z,za )

m=-o( exp (2md + Zo,- Z) .

+ exp (2md Zz Z) 2 0'z2 2

2 cTz2 f (ay Y<Ye) = exP

-(Y -Y)'

2 ETy2

+ exp -(Y + Y,.)

2 lTy2 2

1.3-13

The standard deviations ay> p> are given as follows:

ay =~~2K X 2K X'here

. K> and K~ are diffusion coefficients (m~/sec) .

Studies in'he Great Lakes and other large lakes (Ref. 2) suggest that K> is roughly in the range .05-0 1 m~/sec and that K~ is in the range .'0001-.003 m>/sec.

A stable coastal current. of .12 m/sec is assumed (Ref 3) . Normal current flow near the site is predominately west to east (Ref. 3) For conservatism, the flow is assumed to he westward in computing concentrations at the Lakeview Summoner Camp and Oswego City Water Supply. The straight line distances from the discharge point to the Lakeview Summer Camp, Oswego Public Water Supply intake and Selkirk State Park are 0.8 miles, 8 miles, and 10 miles, respectively. For conservatism, centerline concentrations are used in calculating lake dilution factors (i.e., no credit is -taken for the difference of depth between discharge point and water use locations) . For further conservatism, the diffusion coefficient values of the large lakes (Ref 2) that would result in the largest centerline concentrations are used (K> = .05 m~/sec~ K> = .0001 m>/sec) .

l. 3-14

Section 1.3.2.7 References

t. Draft Regulatory Guide 1.109, "Calculation of Annual Average Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I,>> U S. Nuclear Regulatory Commission, March 1976.

2 Regulatory Guide 1 113, >>Estimating Aquatic Dispersion of Effluents fran Accidental and Routine Releases for the Purpose of Implementing Appendix I," U.S. Nuclear Regulatory Commission, May, 1976.

3 Nine Mile. Point Nuclear Station Unit 1 Environmental Report Operating License Stage, pages 5.4H and 5.4-7 1.3-15

1 3 2 8 So ion of Radionuclides b Sediments The buildup of radionuclides in sediment has been considered at Lakeview Summer Camp, located 0.8 miles west of the site, and Selkirk State Park, approximately 10 miles east.

Dilution in Lake Ontario and the associated travel times are given in Table 1.3.2-1.

The model used to calculate sediment concentrations is described in Regulatory Guide 1.109, Appendix A Section 2-C.

Briefly,, the equation used is:

1.1 x 10 x W -),;th (1.0-e ~

b) where:

C; 1 1

=

x the concentration of isotope

'105' a constant, pCi/m~

i in sediment, W = the shore width factor, .3 for large lakes '

= the dilution factor at the given location F = the discharge flow rate, ft~/sec Q; = the release rate of nuclide

= is the decay constant of i, i, nuclide Ci/yr hr-~

X; th = is the holdup time, from release to uptake by the sediment, hr t> = is the buildup time, hr. (1.310 x 105 hr is assumed)

The resultant concentrations of radionuclides in sediment are shown in Tables 1.3.2-4 and 1.3 2 5.

1.3-16

1 3 2.9 Potential Radionuclide Pathwa Via Groundwater This section discusses the potential for the release of liquid radionuclide ef fluents to the groundwater regime as a significant pathway to man.

As stated on page 5.2-13 of the Nine Mile Point Nuclear Station Unit 1 Environmental Report Operating License Stage (NMP1-KR), groundwater is not expected to be a pathway to man for radionuclides at this site. On-site groundwater contours, permeability, private use within two miles, etc., are detailed in the Nine Mile Point Nuclear Station Unit'2 Preliminary Safety Analysis Report, Appendix ID. Source data on permeability and borings are located on pages IB-8 through IB-10, Plate, IB-1 and Plate IB-2 Data on some additional private wells just beyond two miles distance are contained in Figure 2.5-4 and Table 2.5-3 of the NMP2-ZR.

1.3-17

TABLE 1 3 2-1 DILUTION FACTORS AND TRAVEL TIMES Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Usa e Location Lake Dilution Factor Travel Deca Time Hr Selkirk State Park 8 4 37 0 Lakeview Summer Camp 5.0 2.9 Vicinity Mixing Zone 5.0 0.0 Oswego Water Intake 7 7 29 0

q ~

4 l

0 8

4

~ {

TABLE. 1.3 2-2 WATER PUMPAGE FROM LAKE ONTARIO Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Average Water Location of Water Intake P a e (Million Gallons/Day)

1. At a point between Dennison Creek and Bear Creek at a site north of the intersection of Lake and Knickerbocker Roads 0.80

2. At Pultneyville 1.0

3. At a point north of the village of Sodus near the intersection of Shore Road and an extension of Maple Avenue 1.0

4. In Sodus Point Village on Lake Road 0.133

5. At East of Port Bay 0.095

6. In the western part of the City of Oswego between Sixth and Sheldon Avenues and north of West Schuyler Street 20.0

7. At east of the Village of Sackets Harbor 0.30

8. In Sawmill Bay at a location on Independence Point approximately 0.5 miles south of Chaumont Village's southerly limit 0.04

9. Cape Vincent, 0.246

10. Township of Pittsburg (Milton) 0.015

11. Township of Pittsburg (Glen Lawrence) 0.015

12. City of Kingston (2 intakes) 9.72

13. Township of Kingston (Pt. Pleasant) 0.705

14. Township of Kingston (Queen's Acres) 0.037

15. Township of Ernestown (Amherstview) 0 270

16. Village of Bath 0. 150 1 of 2

P I

/

TABLE 1 3 2-2 CONT D Average Water Location of Water Intake (Million Gallons/Day)

17. Town of Picton 0.679 Note: This table is reproduced from the James A. FitzPatrick Environmental Report Operating License Stage, Supplement 3, page 8.

2 of 2

~ II i

TABLE 1 3 2-3 CONCENTRATIONS AT WATER USE LOCATIONS iCi Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Selkirk Lakeview Vicinity Oswego

~Isoto e State Park Summer C- Mixin Zone Water Intake Ha-24 1.2 x 10-1 2 9.3 z 10->> 1 1 X 1Q 11 1.8 x 10->>

P-32 1.9 x 10-13 3 x 10->> 3.4 z 10->> 2.1 x 10->>

Cr-51 5.6 x ]0-iz 9.8 x 10->> 9.8 x 10 12 6.2 x 10->>

Mn-54 3.4 x 1Q 13 5.8 z 10->> 5 8 X 1Q 13 3.8 x 10->>

Mn-56 ~

1+2 x 1P 15 1.9 x 10->> 4 2 X 10-aa 1 1x 10 Fe-55 1.4 x 10-> 2.4 x 10->> 2.4 X 10-12 1.6 x 10->>

Fe-59 3.5 x 4 2'0->

6.0 x 10-~4 6 0 X 10 3.8 x 10-~4 Co-58 1%2 X 10 12 2 0 x 10-~2 2 0 z 1Q 12 1.3 x 10-~2 Co-60 2e7 x 1Q 12 4.e x 10->> 4.6 X 10-xz 3.0 x 10->>

Hi-63 1.4 z 10-> 5 2 4 x 10-~5 2.4 x 1Q 15 1.6 x 10->>

Ni.-65 6.7 x 1P 18 1.2 z 10->> 2.6 X 1Q 13 6.4 x 10-~~

(w-eu 2.9 x 10-1 2 3.1 x 10->> 3.6 X 1Q 11 4.9 x 10->>

Zn-65 6.5 x 10-x 3 1-1 x 10->> 1 1 X 10-xz 7.1 x 10->>

Zn-@9m 2.2 x 10-x3 x 10->> 2.4 X 10->> 3.6 x 10-i3 Sr-89 Sr-90 I ~3 8.9 x

x 1Q 13 10-x 5

'.2 2

1.5 1

z x

10->>

10-~4 2 2 X 1Q 13 1.4 x 9.7 x 10->>

10->>

1 5 X 1Q 14 Sr-91 1 9 x 1Q 13 3.6 x 10->> 4 4 X 1P x2 3.6 x 10->>

Sr-92 3.6 x 1P 16 4.0 x 10->> 8.4 x 1P 12 3.1 x 10->>

Y-91 7~1 x 10 9.9 x 10-~4 9.4 z 1P 14 7.7 x 10-~4 Y-92 1.4 x 10 7.5 10->> 8 8 X 1P 12 6.8 x 10-~4 Y-93 2 ~ 1 x 1P 13 3~6 x 10->> 4 X 1Q 12 4.0 x 10->>

Zr-95 8' x 1P 15 1.5 x 10-~4 1 5 z 1Q 14 9 8 x 10->>

Zr-97 7.S x 1Q 16 5 1 x 10->> 5 8 X 1Q 15 1.1 x 10->>

Nb-95 4.7 x 10->3 8 2 z 10-~3 8.2 X 1Q 13 5.2 x 10->>

Hb-98 Note 1 1 4 x 10->> 1.4 10-az Note 1 Mo-99 1.1 z 10->> 2.5 x 10->> 2.6 10-12 13z 10 Tc-99m 1.2 z 10->> 1 5 x 10->> 2 0 X 10 11 1.6 x 10->>

Tc-101 -

Note 1 6.6 x 10-~6 3.2 X 1Q 12 Note 1 Tc-104 Note 1 6.4 x 10-~5 5.2 X 10 12 Note 1 RL1-1 03 5.7 x 10 9 8 x 10-~4 9.8 x 1Q 14 6.2 x 10-i4 Ru-105 3.6 x 10 1.3 x 10->> 2.0 z 1Q 12 1.4 x 'lp-~4 RU-106 5 8 x 1Q 13 9.6 x 10->> 9.8 10 x3 6.4 x 10->>

Ag-1 1 0m 1%1 X 1P 13 1.9 x 10->> 1.9 X 1Q 13 1 2x 10 Te-129m 4.4 x 10-x 4 7.6 x 10-~4 7.6 X 1Q 14 4 8 x 10->4 Te-131m 3%1 X 10 1 2 x 10->> 1.2 X 10-x3 4.1 x 10-~4 Te-132 5.8 x 10->> 1 3 x 10-~4 'I 4 X 10 6.8 x 10->>

Ha-139 3 ~ 1 x 10-2 0 1 4 x 10->> 5 8 X 1Q 12 1.9 z 10->>

Ba-140 3.6 x 10-13 6.6 x 10->> 6 6 X 1Q 13 4.0 x 10->>

Ba-141 Note 1 9.4 x 10-~6 6.8 z 1P 13 Note 1 Ba-142 Note 1 1.2 z 10->> 9.6 X 10-x4 Note 1 La-142 1.3 x 10->> &.8 x 10->> 3.6 X 1P 12 5.0 x- 'lp-~8 Ce-14 1 3.4 x 10-i 4 5.8 x 10-~4 5.8 x 10-14 3.7 z 10-~4 1 of 2

~ t TABLE 1.3.2-3 (Cont'd)

Selkirk Lakeview Vicinity Oswego

~Ieoto e State Park. Summer Ca Mixin Zone Nater Intake Ce-143 9.8 x 1Q 15 3.4 x 10-1+ 3.6 x 10-1i 1.3 x 10-1i Ce-144 1e2 x iP 12 2.0 x 10->> 2.0 x 10->> 1.3 x 10->>

Pr-143 3.9 x 1Q-1 4 6.8 x 10-1i 6.8 x 10-1i 4.3 x 10-1i Nd-147 26x 1Q10-1i15 4.8 x 10-15 10->>

4.8 x 10-15 2.9 x 10->>

10->>

W-187 7e7 X 3.5 x 3 8 x 10->> 1.1 z Np-239 3.5 x 1Q 12 8.9 x 10->> 9.2 x 10->> 4.2 x 10->>

Br-83 4.6 x 1Q 17 1e5 x 10->> 3 x 10->> 5.1 x 10-16 Br-84 Note 1 2.5 x 10-1+ 1.1 x 1P 12 Note 1 Br-85 Note 1 Note 1 3 8 x 10->> Note 1 I-131 2e7 X 1Q-11 5.2 x 10->> 5.2 x 10->> 3. 1 x 10-11 I-132 '6.2 x 10-15 1.3 x 10 3.2 x 10->> 1.0 x 10-1i I-133 9.G x 1Q-12 4.7 x 10->> 5 2 x 10->> 1.3 x 10-11 I-134 Note 1 3.2 x 10->> 3 2 x 10->> Note 1 I-135 4.4 x 10->> 2.5 x 10->> 3 4 x 10->> 1.1 x 10->>

Ro-89 Note 1 3.9 x 10-15 1 1 x 10-11 Note 1 Cs-134 4 2 x 1Q-12 7.0 x 10-12 7.0 x 10-12 4.5 x 10->>

Cs-136 6.8 x 10 1.2 x 10-12 1 2 x 10-12 7.6 x 10->>

Cs-137 8 3 x 10-12 1.4 x 10->> 1.4 x 10->> 9.1 x 10->>

Cs-138 Note. 1 2.4 x 10->> 1 0 x 10-1o Note 1 H-3 5.6 x 10-9 9.4 x 10-~ 9.4 x 10-~ 6 1x 10 Notes: 1. The value is smaller than 1.0 x 10-2o

2. Concentrations are based upon the dilution factors and travel times stated in Table 1.3.2 202 2

4 q ~

/ ' t C

l LI

TABLE 1 3 2-4 CONCENTRATION OF SEDIMENT RADIONUCLIDES AT LAKEVIEW SUMMER CAMP SHORELINE Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation ISOTOPE SEDIMENT CONCENTRATION Q~Ci M~~

Na-24 1%7 x 10-~

P-32 1 5-x 10-~

Cr-51 8.4 x 10o Mn-54 5.2 x 10o Mn-56 6.0 x 10-~

Fe-55 6.7 x 10>

Fe-59 8.2 x 10->

Co-58 44x 10o Co-60 2~2 x 10>

Ni-63 2.6 x 10-1 Ni-65 3.6 x 10-~

Cu-64 4 8 x 10-1 Zn-65 7.4 x 10o Zn-69m 3..4 x 'lp-~

Br-83 43x 10-~

Br-84 1.6 x 'lp-~

Br-85 Note 1 Rb-89 1 ~ 2 x 10-~

Sr-89 3%2 x 10->

Sr-90 1.4 x 10o Sr-91 4.3 x 10-~

Sr-92 1~3 x 10-~

Y-91 1.6 x 10->

Y-92 2~1 x 10->

Y-93 4.7 -x 10->

Zr-95 2.9 x 10-~

Zr-97 1 a 1 x 10-+

Nb-95 8.5 x 10-~

Mo-99 2a1 x 'lp-~

Tc-99m 1~1 x 'lp-~

Tc-101 Note 1 Ru-103 1~1 x 10->

RU-105 6.9 x 10->

Ru-106 1e1 x 10~

Ag-110m 1.4 x 10o Te-129m 7~7 x 10-~

Te-131m 43x 10-~

Te-132 1~3 x 10->

I-131 1~3 x 10~

I-132 I-133 38x 10o 10-2 1.2 x I-134 3.6 x 10-~

I-135 2 0 x 10->

Cs-134 1.5 x 10~

Cs-136 4.7 x 10->

of 2

4

~f

TABLE 1.3.2-4 (Cont'd)

ISOTOPE SEDIMENT CONCENTRATION (pCi/M~)

Cs-137 1.4 x. 103 Cs-138 1.5 x 'l0-~

Ba-139 2~3 x 10->

Ba-140 2.5 x 10-~

Ba-141 Note 1 Ba-142 Note 1 La-142 1.8 x 10-3 Ce-141 5.5 x 10-~

Ce-143 1.4 x 10-3 Ce-144 1+7 x 10>

Pr-143 28x 10-2 Nd-147 1.6 x 10-3 W-187 1.0 x 10-2 Np-239 6.1 x 10-i Note: 1. The value is sinaller than 1.0 x 10-6 2 of 2

I'

~

I

TABLE 1 3 2-5 CONCENTRATION OF SEDIMENT RADIONUCLIDES AT SELKIRK'TATE PARK SHORELINE Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation ISOTOPE SEDIMENT CONCENTRATION (pCifin~)

Na-24 2.2 x 10-2 P-32 8. 1 x 10-2 Cr-51 4 8 x,100 Mn-54 3.1 x 10o Mn-56 3.7 x 10-6 Fe-55 4.0 x Fe-59 x 10-2 10'.8 Co-58 2.6 x 10o Co-60 1.3 x 10~

Ni-63 1 6x 10->

Ni-65 Note 1 Cu-64 4.5 x 10-2 Zn-65 4.4 x 10o Zn-69m 3.7 x 10-~

Br-83 Note 1 Br-84 Note 1 Br-85 Note 1 Rb-89 Note 1 Sr-89 1.9 x 10-i Sr-90 8.5 x 10-~

Sr-91 2.1 x 10 Sr-92 Y-9 1 1 3x 10-<

10-2 9.6 x Y-92 1 6 x 10-5 Y-93 2.7 x 10-3 Zr-95 . 1.7 x 10-2 Zr-97 1.5 x 10 Nb-.95 4.9 x 10-i Mo-99 8.8 x 10 Tc-99M 1.3 x 10-3 Tc-101 Note 1 RU-103 Ru-105 67x102 10-5 2.0 x R1L-106 6.4 x 10o Ag-110m 8.2 x 10-i Te-129m 4.4 x 10-2 Te-131m 1.2 x 10-3 Te-132 5.6 x 10-+

I-131 6.6 x 10o I-132 Note 1 I-133 2.4 x 10-i I-134 Note 1 I-135 3.3 x 10-'3 of 2

1 I

TABLE 1.3.2-5 (Cont'd)

ISOTOPE SEDIMENT CONCENTRATION JpCi~~

Cs-134 9 1x10>

Cs-136 2.6 x 10-~

Cs-137 8 1 x 10>

Cs-138 Note 1 Ba-139 Note Ba-140 1.4 x 10-~

Ba-141 Note 1 Ba-142 Note 1 La-142 Note 1 Ce-141 3 ~ 2K102 Ce-143 4.0 x 10-i Ce-144 1.0 x Pr-143 x 10-~

10'.5 Nd-147 8.6 x 10-i W-187 23x1010-~

Np-239 2.4 x Note: 1. The value is smaller than 1.0 x 10-~

2 of 2

L AKE INTAKE TUNNEL CONDENSER ON TA RID FROhl LAKE 250i000 GPM ONTARIO ( CONSTANT) 265,000 GPM

( NORMAL) (WHEN OPERATING) SHUTDOWN HEAT DISCHARGE STRUCTURE 6000 GPM REMOVAL SYSTEM 2721000 GF M (NORM) 9000 GPM SETTLING (MAX) (MAX)

ISOOOGPM BASIN OVERFLOW

~ 20 GPH CLOSED LOOP (NORM )

COOLING 22 l000 G P M SYSTEM HEAT (REG MAX) EXCHANGERS WAST E NEUTRALIZING SYSTEM 100 GPM CL A R I F I E R WASTE MAX REGENERANT WASTE IOO GPM SYSTEM POLISHING REGENERATION PRE-TREAT ME CLARIFIER MAKE-UP DE MIN. WASTE DEMINERALIZER RA DWASTE FOR SYSTEM NOT IN DECONTAMINATED CONTINUOUS OPERATION WASTES (FLOOR DRAINS, LAUNDRY)

CONDENSATE MAKEUP AUXILIARY SYSTEMS RADWASTE SHIPPING CONTAINERS MAKE-UP 100 GPM MAX CITY OF OSWEGO FLOW DOMESTIC SANITARY WASTE TO LAKE ONTARIO WATER WATER USAGE TREATMENT METER SUPPLY 3300 GPD AVG SYSTEM 2400 GPD (NORMAL) 3800 GPD (MAX)

FIGURE I.3,2 I WATER USAGE FLOW DIAGRAM NINE MILE POINT NUCLEAR STATION- UNIT I NIAGARA MOHAWK POWER CORPORATION

4

~ r

Kingston 11 14 s

17 Watertown JEFFERSON LA K E ONTAR IO F I TZ PATR ICK NUCLEAR POWER PLANT 50 MILES 6

OSWEGO Oswego 4 Fulton I 2 WAYNE CAYUGA Rochester V

NOTE: r THIS MAP IS REPRODUCED FROM THE JAMES A. FITZPATRICK ENVIRONMENTAL REPORT OPERATING LICENSE STAGE, SUPPLEMENT 3i PAGE 9.

FIGURE 1.3.2-2 WATER PUMPAGE FROM LAKE ONTARIO NINE MILE POINT NUCLEAR STATION-UNIT I NIAGARA MOHAWK POWER CORPORATION

0 7ROE 0

O l4 - 7'7~i I S TONE lO BUILDING NORTH D IKE EL. O 263-CI' SCREEN 1 TUNNEL 6 CO PUMP C4 I IOO 0 234'-3" HOUSE O O I

!O bl II 0ll INTAKE TUNNEL I3'8-6 9 0 0)

O I

22'-6I4" g+GE PLAN

)SCHWA REACTOR t REACTOR N- l,283,173 LW EL. 244.0' II BLDG. E- 545,760 585 22l 6/4 II I

O II'-3 le EL.234-0 PLAN EL.230-0 + EL.230.0 EL.227.0I IOO 200 300

)L I

]

l I n I I I I h ELEVATION DISCHARGE 300 MAXW.S. EL. 300 249.0'EAN 242.5'L.263.

W.S. EL.246.5'OW W.S, EL. SCREEN 244.0'IN 0 HOUSE 250 EL234.0'UTLET E L.230.CI W.S. EL.

250

'TONE 0

D I KE ' Il 1.0 200 200 ELI95.0 EL. I94.0 SECTION I- I TYPICAL SECTION 2-2 TYPICAL l50 l50 s 0 sIe 5 0 5 IO 585'-0" PROF I LE ALONG DISCHARGE TUNNEL 50 0 50 IOO TI FIGURE I2.2-5 APmXUBj<

CAR9 DISCHARGE TUNNEL. PLAN 6 PROFILE NILE MIL~E POINT NUCLEAR STATION- UNIT I NIAGAR'A MOHAWK POWER CORPORATION Also AvaQnbge On Aperture Card

II P

l

1.4 Dose Calculations The models and assumptions used for calculating doses to individuals are described in Section 1.4.1.

Section 1.4.2 presents the models and assumptions used for calculating doses to the population within 50 miles of the site.

1 4 1 DESCRIPTION OF MODELS AND ASSUMPTIONS USED IN INDXVIDUALDOSE CALCULATIONS 1 4 1 1 LI UID EFFLUENTS In estion of Potable Water The City of Oswego water supply, eight miles west of Nine Mile Point Nuclear Station Unit 1 (NMP1), is the closest Lake Ontario intake to the site. The lake dilution factor at this point is 7.7, as calculated using Regulatory Guide 1.113 (Ref. 4) . A decay time of 29.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> is sumed, to account for transit fram release to intake. An additional 12.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />'oldup for transport through the water purification plant is used (Page 1.109-20, Regulatory Guide 1.109, Ref. 2) ." The total time from release to consumption is 41.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

individual of The dose, RB~, mrem/yr, age group a is:

to organ j of a maximum t

Raj = 1100 0 Ua Dai Qi e Xi t>

FDF whexe:

UB is the usage factor for age group a, liters/yr, for a maximum individual. An adult usage of 730 liters/yr is assumed. For a teen, child, and infant 510 liters/yr are consumed (Table A-2, Regulatory Guide 1.109.

is the flow rate of the release stream, 544 ft~/sec DF is the, lake dilution factor at the point of intake, 7 070 is the release rate of isotope Table 1.2.3-1) i, Ci/yr (See Daii is the organ dose j,

factor for mrem/pCi age group ingested, a, isotope i and (Table A-3, Regulatory Guide 1.109) 1.4-1

t is the decay constant of nuclide i, hr-~

tp is the total time from release to consumption, 41.0 hr 1100.0 is the factor used to convert (Ci/yr)/(ft~/sec) to (pCi/liter) .

In estion of Fish and Fresh-Water Invertebrates For the maximum individual case, fish and fresh-water invertebrates are assumed to be caught. at the edge of the initial mixing zone. The approximate mixing zone lake dilution factor is 5.0 (Table =A 1, Regulatory Guide 1.109) . A holdup time of 24.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> is assumed (Page 1.109-30, Regulatory Guide 1.109) .

The dose, R~j, mrem/yr, to a maximum individual of age group a is:

R<j 1100 ~ 0 ~U 8) Q> D+ e->i p FDF where:

Ug is the usage factor for age group a, of aquatic food type 0, kg/yr. For fish, the factors are assumed to be 21-0, 16.0, and 6.9 kg/yr for an adult, teen, and child, respectively. The corresponding factors for seafood are 5.0, 3.8, and 1.7, respectively (Table A-2, Regulatory Guide 1.109)

F is the flow rate of the release stream, 544 ft~/sec DF is the lake dilution factor in Lake Ontario, 5.0 B; is the bioaccumulation factor for aquatic food type 0, liters/kg (Table A-8, Regulatory Guide 1.109)

Q; is the release rate of nuclide i, Ci/yr (See Table '.2.3 1)

Da)) is the ingestion dose factor, mrem/pCi ingested, (Table A-3, Regulatory Guide 1.109) is the decay constant of nuclide i, hr-~

1. 4-2

tp is the holdup time, 24 . 0 hr (Page 1 . 109-30 f Regulatory Guide 1.109) 1100.0 is the factor used to convert (Ci/yr)/(ft~/sec) to pCi/kg.

Swimmin Boatin and Fishin The point of exposure for calculating swimming, boating, and fishing doses is assumed to be near the point of discharge, with an approximate lake dilution of 5.0. All age groups are assumed to swim 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year; fishing and boating usage is assumed to be 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />. per year (Table 5.5, Ref. 7) .

Additional details of the model are discussed in Section 1.4.2.1.

Shoreline Recieation N

The Lakeview Summer Camp is the closest point to the site at which this pathway exists. A decay time of 2.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> is assumed, and a lake dilution factor of 5.0 is used based on the assumption that the initial mixing zone dilution is applicable at this location.

The dose, Roj p mlem/yrp to the total body or skin of a maximum individual of age group a is:

R~j = 3.18x10~ ~UN; Q,.e-~; p Daj)

FDF where:

Ug is the usage factor for a maximum individual of age group a, hr/yr. Values of 12, 67, and 14 hr/yr are used for an 'adult, teenager, and child, respectively (Table A2, Regulatory Guide 1.109) is the shore width factor, 0.3 (Table A-9, Regulatory Guide 1.109) is the flow rate of the release stream, 544 ft~/sec DF is the lake dilution factor~ 5.0 Q) is the release rate of nuclide i, Ci/yr (See Table 1.2.3-1) is the decay constant of nuclide i, hr 1.4-3

/

tp is the holdup time from release to deposition on the shore, 2.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> t, is the buildup time, 1.31 x 105 hr (Page 1.109-9, Regulatory Guide 1.109)

Dp [ j is as previously def ined

3. 18x103 is the factor used for conve'rsion from (Ci/yr)/(ft3/sec) to pCi/liter, and to account for the proportionality constant used in the sediment radioactivity model.

1 4 1.2 GASEOUS EFFLUENTS Ex sure to Noble Gases The individual annual gamma air dose, D (r,g),

mrad/yr, due to main stack release of noble gases at distance r meters from the main stack in the sector at angle 0 is calculated by the following equation as given in Meteorology and Atomic Energy, (Ref. 1) and Appendix B of Regulatory Guide 1.109:

D(?8)260~1(~p(k) r(80)~ U I)(H ll ~zEk)QQ)A where:

is the horizontal distance from the main stack to the receptor, 1,900 m (6,300 ft) is the sector width over which atmospheric conditions are averaged, radians is the wind speed assigned to wind speed class n, m/sec is the fraction of year for meteorological condition in wind speed class n and stability class j "a(Ek ) is the energy absorption coefficient in air for photon energy Ek MeV, m-~

H is the ef fective height of main stack, 110 m (350 ft) is the vertical standard deviation, m tj (H U o'E'k) is the integral accounting for the distribution of 1.4-4

radioactivity (Page 352, Ref. 1)

Q; is the release Table 1.2.2-1) rate o f nuclide i, Ci/yr (See A>, is the fraction of disintegration of. nuclide yielding photons in the kth photon energy group.

i The offsite location of maximum annual gamma air dose is found to be at r=1900 meters (6,300 ft), east of the plant (8=90~) . The wind velocities are classified into six groups (uz = 1.5 mph, u = 5.5 mph, u> = 10 mph, u4 = 10.5 mph, u> = 21 mph, anct u< = 24 mph) . Atmospheric stability classes equivalent to Pasquill classes A,B,D, and F are considered together with their frequency of occurrence (f; ) for winds from the west direction (Page 2.2 3, NMP2-PS4) .

Gamma emitters released from the stack are classified into seven energy groups (E~= 0.4 MeV, E>= 0.7 MeV, E>= 1.3 MeV, E4= 1.7 MeV, E>= 2.2 MeV, E8=2.5 MeV, and E>= 3.5 MeV) . The corresponding attenuation coefficients in air, p~ (Ej,), are obtained from Figure 7.8, Ref. 1.

The values of the integral I (H, u, o,, for each equivalent Pasquill stability class and gamma E>) energy group are obtained from Figure 7.21 and Figure 7.22 of Ref. 1. Other variables for the integrals Ij are as follows: The effective stack height is assumed to be 110 meters (350 ft) . The vertical standard deviations, for each equivalent Pasquill stability class are obtained from Figure 1 of Regulatory Guide 1.111 (Ref. 3) .

No credit for decay during travel from the point of release to the receptor is considered for this calculation.

Inhalation Doses NMP1.

The maximum inhalation This inhalation 'ose, dose occurs 6,300 R pj pmrem/yr, to ft maximum a

east of individual of age group a is:

R~j = 32x 10 UgP DB;j Q; where:

Q; = Q; ( /Q) Stack (Ci-sec)/(m -yr)

Q; is the release rate of nuclide i, Ci/yr (See 1 4-5

Table 1.2.2-1)

X/Q is the atmospheric dispersion factor, sec/m>. A value of 5.3 x 10-8 sec/m> is assumed for the stack releases D 8j I

l is the inha ation dose factor for isotope organ j, age group a, mrem/pCi inhaled i

(Table C-1, Regulatory Guide 1.109)

UB is the amount of air inhaled yearly, m~/yr, taken to be 7,300, 5,100, 2,700, and 1,900 for an adult, teen, child, and infant/

respectively.

3.2x10+ is the factor to convert (Ci/yr) to (pCi/sec) .

sure from Contaminated Ground The maximum exposure point is 'located 6,300 ft east, of NMP1.

follows:

The dose, R>, mrem/yr, to organ j is calculated as i'.

1 R) 0 x 10>> SF Q.4 1

1e where:

QQ (Q; 8 ) Stack /

Ci (yr-m~ )

Q,. is the release rate of nuclide Table 1.2.2-1) i, Ci/yr (See is the relative deposition rate at the point of exposure. A value of 5.3x10-~o m-~ is used for the stack releases SF is the shielding and occupancy factor, 0.7 (Page 1.109-12, Regulatory Guide 1.109) is the decay constant of nuclide i, hr-~

t is the buildup time', 1.31 x 10~ hr (Page 1.109-9, Regulatory Guide 1.109) i j is the dose factor for organ (total body or skin),

nuclide adjusted to account for secular equilib-rium (mrem/hr) /(pCi/m~) (Table A-3, Regulatory Guide 1.109) 1.0 x 10~~ is a factor to convert Ci to pCi.

1.4-6

In estion of Milk and Meat A six month grazing season is assumed for the NMP1 analysis. The deposition rates for the grazing season ,are given in Tables 2.3-7 and 2.3-8 of Response 2.3.

The location of the nearest milk cow and meat animal has been determined to be 8,900 feet ESE of NMP1.

The relative deposition rate at this point is 1.6 x 10-~o m-~ for the stack releases. The corresponding

</Q value is 1.6x10-< sec/m~.

The location of the nearest goat has been determined to be 19,000 ft SSE of. NMPt. The relative deposition rate at this point is 1.9 x 10->> m-~ for the stack releases. The corresponding X/Q value is 1.9 x 10-~ sec/H.

The concentration, C; , pCi/kg, in the feed of isotope i is:

Civ Qi+ 1 1 x 10s f X t KEY XiP where:

Q + = (Q;5 ) Stack Ci/ (yr-m )

Q; is the release rate of isotope Table 1.2.2-1) i, Ci/yr (See is the relative deposition rate at the location of the milk cow, goat, or meat animal, m-~

is the fraction of the releases available for de-position for isotope i, as follows:

0.5 for iodine 1.0 for other nuclides (Page 1.109 54, Reg-ulatory Guide 1.109) is the retention factor 0.2 for particulates 1.0 for other nuclides (Page 1.109-9, Reg-ulatory Guide 1.109) is the decay constant. for isotope i, hr-~

XE is the effective decay constant for isotope adjusted to account for weathering effects, i,

as follows:

1 4-7

XE = ~j + 0.0021 hr (Page 1.109 10, Regulatory Guide 1.109) tE is the exposure time, 720.0 hr (Page 1.109-58, Regulatory Guide 1.109) tj, is the buildup time, 1.31 x 10> hr (Page 1.109-9g Regulatory Guide 1.109)

Y is the crop yield for the feed, 0.75 kg/m~ for pasture grass and 2.0 kg/m> for stored feed (Page 1.109-58, Regulatory Guide 1.109)

P is the effective surface density for soil, 240 kg/m~

(Page 1.109-9, Regulatory Guide 1. 109)

B jy isotope f

is the concentration factor rom soi 1 to crop i (Table C-2, Regulatory Guide 1.109) t>. is the holdup time for stored feed (from harvest to consumption by the milk cow, goat, or meat animal, 2.2 x 10~hr (Page 1.109-55, Regulatory Guide 1.109) 1.10 x 106 is to convert (Ci/yr) to (pCi/hr) .

The concentration, C;,pCi/liter, for tritium is:

Cjv 3 17 x 10+ Qj gf/HX/Q pCi/kg where:

is the absolute humidity in the region, 5.9 gm/m~

is the ratio of tritium concentration in atmospheric water to tritium concentration in the plant water, 0.5 (Page 1.109-54, Regulatory Guide 1.109) is the fraction of the total plant mass that is water, 0.75 (Page 1.109-54, Regulatory Guide'1.109) 3.17 x 10> is to convert (Ci-sec/gm) to (pCi-yr/kg) .

The concentration, Cjy fpCi/kg for C-14 is:

Cjv 3.17 x 107 Q.(L/k) X/Q pCi/kg where:

X/Q is the atmospheric dispersion factor at the appropriate location, sec~>

1. 4-8

L is the fraction of the total plant mass that is natural carbon, 0.11 (Page 1.109-54, Regulatory Guide 1.109) k is the concentration of natural carbon in the atmosphere, 0.16 gm/m3 (Page 1.109-54, Regulatory Guide 1.109)

Other terms for tritium and C-14 calculations are as previously defined.

The concentration, C; , pCi/liter or pCi/kg', in milk or meat is determined by:

im im iv f ~ fresh ( iv ~ ~<or~d QF a

-~iim where:

is the fraction of the animal's feed composed of fresh or stored grain, 0.5 Fim is the fraction (uptake factor) of the animal's daily feed which appears in a liter of milk, days/liter or a kilogram of meat, days/kg (Tables C-5 and C-6, Regulatory Guide 1.109)

QF is the animal's daily feed,,kg/day., A value of 50 kg/day is assumed for a milk cow or meat animal and a value of 6 kg/day is assumed for a goat (Page 1.109-58, Regulatory Guide 1.109) tm is the transport time, hr. For the milk pathway a value of 48.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> is used. For the meat, the appropriate'ime is 480.0 (Table D-2, Regulatory Guide 1.109) .

The ingestion dose, Ramj, mrem/yr, from milk or meat to a maximum individual is:

Ram j = im aij a where:

D a mj is the ingestion dose factor for isotope i, age group a, and organ Regulatory Guide 1.109) j, mrem/pCi ingested (Table A-3, Ua is the usage factor for age group a, liters/yr or 1 4-9

kg/yr. Values for the milk pathway of 310, 400, 330, and 330 liters/yr are used for an adult, teen, child, and infant, respectively. The corresponding values for the meat pathway are 110, 65, 41 and 0 kg/yr, respectively. (Table A2, Regulatory Guide 1 109)

Other terms are as previously defined.

In estion of V etation The stored vegetable model is employed for an apple orchard, located 7,000 feet east of NMP1. For fresh, leafy vegetables, the calculation is mad'e at 7,300 feet east- The atmospheric dispersion factors, X/Q, sec/m~, and relative deposition rates, 8, m-~, are presented below.

Stack Garden X/Q 5.9x10-8 5.9x10 Orchard X/Q. 5. 9x10-8

5. 9x10-i o vegetation The is:

concentration, C;~,pCi/kg, of isotope i in the Q

-X;tb e

~ X tQ j

) E Y where:

Q; = (Q; 8) Stack Ci/ (yr-m~)

Q; is the release ale 1.2.2-1) rate of isotope i, Ci/yr (See is the relative deposition rate at the location of the vegetation, m-~

is the fraction of the release available for deposition for isotope i, as follows:

0.5 for iodine ~

1.0 for other nuclides (Page 1.109-54, Reg-ulatory Guide 1.109) is the retention factor:

0.2 for particulates 1.0 for other nuclides (Page 1.109 9 Regulatory Guide 1.109) .

is the decay constant for isotope i, hr-~

1.4-10

XE is the effective decay constant for isotope adjusted to account for weathering effects, as i,

follows:

+ 0 0021 hr (Page 1.109-10, Regulatory Guide 1.109) is the exposure time, 1,440 hr (Page 1.109-55, Regulatory Guide 1. 109) tb is the buildup time, 1.31 x Regulatory Guide 1.109) 10'r (Page 1.109-9, Yy is the crop yield for the vegetation, 2.0 kg/ma (Page 1.109-55, Regulatory Guide 1.109) is the effective surface density for soil, 240 kg/m~ (Page 1.109-9, Regulatory Guide 1.109)

>iv is the concentration factor from soil to crop for isotope i (Table C-2, Regulatory Guide 1.109) th is the holdup time from harvest to consumption by the maximum individual, 1,440 hr for stored vegetables, and 24.0 hr for fresh vegetables (Page 1.109-55, Regulatory Guide 1.109) 1.10 x 10a is to convert (Ci/yr) to pCi/hr) .

Concentrations of tritium and C-14 are calculated as described in Section 1.4.1.2.

The ingestion dose Rayj p mrem/yr, to a maximum zadzvidual is:

= Civ Ravj aij Ua I

where:

Dalj is the ingestion group a, and organ dose j,

factor for isotope mrem/pCi ingested i, age (Table A-3, Regulatory Guide 1.109)

Ua is the usage factor for age group a, kg/year.

Values of 520, 630, and 520 kg/yr are assumed for an adult, teen, and child, respectively for the orchard. For the garden, the corresponding values are 64, 42, and 26 kg/yr, respectively (Table A-2, Regulatory Guide 1.109) .

All other terms are as previously defined.

1-4-11

0 1 4 2 DESCRIPTION OF MODELS AND ASSUMPTIONS USED IN POPULA-TION DOSE CALCULATIONS 1 4 2 1 LI UID EFFL'UENTS In estion of Potable Mater As discussed in Section 1.3.2 3, the only potentially significant public potable water supply intake is the City of Oswego water supply, eight miles west of the site. Users of the supply are residents of the City of Oswego and Onondaga approximately 24,000 and 166,000 County. 'n 1970, consumers, there were respectively (Pages 2.1 2 and 5.2-8 of Ref. 7) .

Based on the population growth estimate discussed in Section 2.1 of the RIP2 PSAR, the nenber of consuners of the potable water from this intake is increased from 190,000 to 239,000. This accounts for a 26 percent increase to the midpoint of operation of N&1Pl.

A lake dilution l'actor of 7.7 is calculated by using Regulatory Guide 1.113. Decay of radionuclides occurs based on a lake transit time of 29.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> from the point of discharge to the point of intake; transport time through the water purification plant and water distribution system is 24.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (Table D-2, Regulatory Guide 1.109) .

The model used for calculating population doses from ingestion of potable water is based on Regulatory Guide 1.109. The concentration, the point of intake is:

C;, pCi/liter, of isotope i at DF where:

Q; is the release rate of the nuclide, Ci/yr (See Table 1.2.3-1) tp is the time from the point of discharge to the point of intake (lake transit time), 29 0 hr is the decay constant of the nuclide, hr-~

D is the lake dilution factor, 7 7 F is the flow rate of the release stream, 544 it>/sec 1-4-12

0 1100.0 is the factor to convert (Ci/yr)/(ft>/sec) to pCi/liter.

The dose, Raj, mrem/year to an average individual of age group a, to organ j is:

R aj =

~ Ci D ..

aij Ua e-X'ti where:

C; is the concentration at the point of water intake, pCi/liter Da;. is the dose factor for ingestion to organ j, mren/pCi ingested (Table A-3, Regulatory Guide 1.109) is the distribution transport time, 24.0 hr Ua is the usage. factor for age group a of potable water, for an average individual. For an adult, 370 liters/yr are consumed; for a teenager and child 260 liters/yr are consumed (Table D2, Reg-ulatory The - dose, D population (total body or thyroid) j, Guide 1.109)

P man rem/yr, is:

to the 50-mile D P = 0~001 PWka f where:

is the population served is the dose,to an average individual of age group a, to organ j, mrem/yx fa is the fraction of the population served belonging to age group d 0.001 is the factor to convert mrem to rem.

1 4-13

In estion of'ish A total commercial fish catch for Lake Ontario of 3.2 x ]0< pounds is reported for 1970 (Page 2.2-3, Ref. 7) .

Por the purposes of this analysis, the catch was increased by a factor of four for conservatism (to 1.3 x 10~ lb) to reflect sport fishing and growth in commercial fishing over the life of NMPl.

Most commercial fishing occurs in the extreme northeast portion of Lake Ontario (Page 2.2 3, Ref. 7) .

is conservatively assumed that the lake dilution factor is It 1 Ox 10~

catch It is for is conservatively human consumption.

assumed that the entire fish Distribution transport time is assumed to be 10 days, in accordance with Table D-2 of Regulatory Guide 1.109. A total annual United States'fish consumption by humans of 3.2 x 10~ pounds is used (Table 1106, Ref. 5),

b" sed on a consumption rate of. 11 lb/person/yr and ¹ U.S.

population of 200 million. This assumption is conservative, since the model considers the Lake Ontario catch as part of the total U.S. catch. A larger U.S. fish consumption by humans would thus result in a smaller dose. The Lake Ontario catch, however, is increased by a factor of four to account for future growth in the fishing industry and consumption of the sport catch.

The model used in calculating the dose from ingestion of fish is based on Appendices A and D of Regulatory Guide 1.109. The concentration, C;F, pCi/kg, of i

nuclide in the fish is:

3 e-> itp DP where:

8;~ is the bioaccumulation factor in fish for water type s, fresh water in this case (Table A-S, Regulatory Guide 1.109) .

All other terms are as previously defined.

The dose, D j ~, man-rem/yr, to the population (total body or thyroid) is:

1.4-14

0 a

where:

P)o is the 50~ile population m is the mass of fish caught. annually from Lake Ontario, 6.0 x 10+ kg/yr M is the total annual U.S. fish consumption by humans, 1.5 x 10~ kg/yr f, is the fraction of the population in age group a C.,<

pCijkg i

is the concentration of radionuclide in fish, U~ is the usage factor for age group a, kg/yr. Fish ingestion for adult, teen, and child are 6.9, 5.2, and 2.2 kg/yr, respectively (Table D-1, Regulatory Guide 1 109)

D~; is the ingestion dose factor (total body or thyroid) for age group a, isotope i, and organ j, mrem/pCi (Table A-3, Regulatory Guide 1.109) t is(Table the distribution tramport time, 20.0 hr D-2, Regulatory Guide 1.109) 0.001 is the factor to convert mrem to rem.

1 0-15

Fishin Boatin and Swimmin The COHORT-II Monte Carlo Radiation Transport Code, (Ref.. 6) has been used to determine the dose rates to which fishermen, boaters, and swimmers may be exposed. The source activity is presented in Table 1.4 1 for the initial mixing zone, Lakeview Summer Canp, Selkirk State Park, and for an average lake dilution five miles from the discharge structure for recreational boating and fishing and 25 miles for commercial fishing.

~Swinmd.n The COHORT-II Monte Carlo program (Ref. 6) is used to calculate the dose rate for swimming. A cylindrical source 5 ft in radius is enclosed in an annular mass of water of 10 ft in outside radius. The economics of computer time resulted in limiting the source region to the 5 ft radius cylinder. The attenuation of this much water can readily be shown to be a sufficient representation of source contributions to a submerged receptor on the axis of the cylinder. The 10 ft outer .cylinder is added to include b ckscattering into the source region, in the Monte Carlo analysis. A receptor point 2 ft below the surface is used.

An estimated 1,000 persons are assumed to swim at Selkirk State Park each week during a 10 week season (Page 5.2-5, Ref 1) . Adults are assumed to spend 2 hr per day swiaming and children and teenagers are assumed to spend 4 hr per day swimming.

At Lakeview Summer Camp, 11,200 personMays are assumed for adults cind 22,400 personMays for teenagers and children In addition, it is assumed that 10 teenagers swim 8 hr per weekend during a 10 week season, in the vicinity of the mixing zone.

The large dilution afforded by the lake at more distant recreational areas within the 50 mile radius is sufficient to make additional contributions to population m'n-rem estimates of negligible proportions.

Fishin arid Boatin The dose rate for fishing and 'boating is

~

approximated as being half the value obtained in the analysis for the swimming .dose rate (as previously discussed) . This approximation has been substantiated in the NNP2 Submittal for Compliance with 10CFR50 Appendix I, Volume ZI, pages C9A1 17 and 18.

1 4-16

In computing the population dose from fishing, an estimate of the number of hours of exposure is made as follows An estimated total of 3 2 x 10~ fisherman-days in 1960 is reported on page 8.4 5 of the NNP2-ER (Ref. 8) .

This number is assumed to double to a value of 6.4 x 10< for the purposes of this analysis.

Each fisherman is assumed to spend 2.5 hr per day on the lake. This results in a population usage of 1.6 x 10~ person-hours per year. An average lake dilution factor of 1'.0 x 104 is used in this analysis.

In computing . the population 'dose from boating, a twelve week season is assumed. An estimated 1,000 persons are assumed to spend an average of 2 hr per weekday boating during this season. On weekends, 10,000 persons are assumed to use Lake Ontario for boating within a 50 mile radius for an average time of 4 hr per weekend. These assumptions result in a total oi 6.0 x 105 person hours per year for boating. A. lake dilution factor of 6.1 is conservatively estinated, corresponding to an average distance of 5 miles from the discharge.

Shoreline Recreation Near the NNP1 site, there are two predominant beach areas. The review Surnrner Camp, located 4,200 feet southwest of the station, is occupied for approximately 10 weeks per year. Maximum usage is 500 persons/weekday and 1,500 persons/weekend (Page 2.2-6, Ref. 7) . This yields an average of approximately 800 persons per day during the 10 week period each year. It is assumed that, of these, 160 are adults, 320 are teenagers, and 320 are children. An adult usage of 2 hr per day is assumed; for teenagers and children, a usage of 4 hr per day is assumed. This is conservative, since'he combined swimming and shoreline usage'is 8 hr per day An initial mixing zone dilution factor of 5.0 is conservatively assumed for this beach location. A decay time of 2.9 hr is assumed Selkirk State Park is located 10 miles east-northeast of the station. According to page 2.1-4 of the NHP2-PSAR, an estimated 10,000 people use the park each weekend; based on a 10-week season, the total usage is assumed to be 100,000 personMays Age group distributions of 62 percent adult, 14 percent teenager, and 24 percent child are used. Usages of 8.3, 47.0 and 9.5 hr per year are assumed for adults, teenagers, and children, respectively.

Regulatory Guide 1.113 serves as '. basis for calculation of a lake dilution factor of 8.4; a decay time of 37 0 hr is used 1 4-17

The model used for estimating population doses from this pathway is in accordance with Regulatory Guide 1.109.

A shore width factor of 0 3 is used (Table A-'9, Regulatory Guide 1.109) . For the buildup time, a power plant lifetime midpoint of 15 years is assumed (Page 1.109-9, Regulatory Guide 1.109) .

The footnote on Page 1.109 30 of Regulatory Guide 1 109 identifies a necessity to account for secular equilibrium of parent and daughter. In lieu of the HRC model, dose factors of each parent isotope are increased by that of its daughter isotope, where appropriate. This model has the advantage of accurately rmdeling a situation where the parent release is small and. the daughter release is large.

The concentration, C;,, pCi~~, in the shoreline sediment of isotope i is:

FD where =

Q; is the release rate of isotope Table 1.2.3-1) i, Ci/yr (See is the decay constant of isotope i, hr-~

is the buildup time, 1.31 x 105 hr (Page 1.109-9, Regulatory Guide 1.109) 1 4-18

0 t p, is the hol dup time, hr W is the shore width factor, 0.3 (Table A-9, Regulatory Guide 1.109)

D is the lake dilution factor F is the flow rate of the release 'stream, S44 ft3/sec 3.18 x 103 is a factor for conversion from (Ci/yr)/(ft~/sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.'he dose, R3j, mrem/yr, to an organ Z (total body or thyroid) of an average individual of age group a, due to the release of isotope i, is:

Re. = C U3 D3 where:

C;, is the concentration in the sediment., pCifla~

Ua is the usage factor for age group a, as previously defined, hr/yr Da> j is the external dose factor for isotope (mrem/hr) /(pCi/m>) (Table A-7, Regulatory Guide i, organ j, 1 109)

The dose, Dj, population using the recreational man-retd/yr, described above to the facility is:

D = 0~001 P faa Ra.aj

)

where:

P is the population using the recreational facility fa is the fraction of the population in age group a Raj is the dose to an average individual, mrem/yr 0.001 is a factor for converting mrem to rem.

1 4-19

0 1.4.2.2 GASEOUS EFFLUENTS Ex sure to Noble Gases Noble gas exposure (total body) population doses, D,, man rem/yr, are calculated based on a semi-inf inite P

cloud model. This model provides a good approximation over a 50-mile region. The appropriate equation is:

DT 1-11 x 0-001 x 3-2 x 10h SF DFBI Pr e jj i r,e 'r~e where:

Q*.

Ir g r

= (Q; (X/Q) r,e ) /

stack (Ci-sec) (m3-yr)

Q. is the release rate of isotope Table 1.2.2.1) i, Ci/yr (See X/Q is the atmospheric dispersion factor, sec/m3, for the sector centered at distance r, angle e DFB j l is the tota body dos e fa ctor for isotope i, (mrem/yr)/(pCi/m3) (Table B-1, Regulatory Guide 1 109)

P<< is the population of sector (r,o)

SF is a shielding and occupancy factor, 0.5 (Page 1.109-68, 'Regulatory Guide 1.109) 0.001 is the factor to convert from mrem to rem 3.2 x 10~ is the factor to convert (Ci/yr) to (pCi/sec) 1.11 is the ratio of tissue to air energy absorption coefficient (Page 1.'l09-42, Regulatory Guide 1.109) .

1. 4-20

Inhalation Doses Inhalation doses, DP , man-rem/yr are:

D = 3~ 2x 10~++ Q Uq Dq, P,~ Q+;

where:

Q = (Q ('</Q) ) (Ci-sec) /(m3-yr)

Q; is the release rate of isotope Table 1.2.2-1) i, Ci/yr (See (xy<) is the atmospheric dispersion factor,, sec/m3, associated with the sector centered at r, angle o U is the usage factor for age group a, m~/yr air-These factors are, for adult, teen, and child, 7,300, 5,100, 2,700, respectively is the inhalation dose factor for age group a, isotope i, organ j, mrem/pCi inhaled (Table C-1, Regulatory Guide 1.109) 1<< is the population occupy'.ng the sector centered at. (r,o) 3.2 x 10>> is the factor required to convert (Ci/yr) to (pCi/sec)

De sition on Ground Dose factors are adjusted to account for secular equilibrium.

The total body exposure dose, D 1

, man-rem/yr, due to deposition on ground is:

= 0.001 1.0 x 10>>

D SF r,e r,e Q lt;

1. 4-21

where:

>re = (>re ) stack is the relative deposition rate, m-~, for the sector centered at r, angle e SF is the shielding and occupancy, factor, 0.5 (Page 1.109-69, Regulatory Guide 1.109) is the decay constant of nuclide i, hr-~

is the buildup time, 1.31 x 10~ hr (Page 1.109-9, Regulatory Guide 1.109) is the release rate, Ci/yr (See Table 1.2.2-1) is the total body dose factor, (mrem/hr)/(pCi/m~)

(Table A-3, Regulatory Guide 1.109) . These factors have been adjusted to account for secular equilibrium between parent and daughter, where appropriate.

P~ < is the population in sector (r,e) 0.001 is the conversion factor from mrem to rem 1.0 x 10>> is the conversion factor from Ci to pCi.

In estion of Milk Distribution of milk production in the 160 subregions has been obtained using county data (Refs. 9 and

10) . The area of each subregion is ratioed to the area of the county, and an appropriate percentage of the county production is calculated.

The average cow is assumed to consume 50 kg/day of feed.; during the sixwonth grazing season, the cow's diet is assumed to be comprised of pasture grass only. For the remaining six months, no direct intake of pasture grass is assumed. Crop yields of 0.75 and 2.0 kg/m~ are assumed for fresh and stored feed, respectively. A surface density for soil was taken to be 240 kg/m~. No holdup time is assumed for pasture grass;

average, it 90 days pass is assumed, however, that on the between harvest and consumption of stored grain. A growing season of 30 days is applied for all feed. Four days are allowed for distributing the milk.

The above data represent values of Appendix C and Table D-2 from Regulatory Guide 1.109. For conservatism, is assumed that all milk is consumed fresh (i.e., no canning it or other processing); 100 percent fresh daily feed is also a conservative assumption.

1.4-22

C The concentration, C;F, pCi/kg, in feed (fresh or stored)'for any isotope except tritium or C14 is determined by:

CiF 1.1 x 10e 8" Q f r 1-e-"EitE hi YEi Y x;p where:

breI ( ~r e ) stack is the relative deposition rate of sector I (r, 0 )

Q; is the release of isotope i, Cifyr (See Table 1.2.2-1).

is the fraction of the isotopic release available for deposition, as follows:

0.5 for iodines 1.0 for other nuclides (Page 1.109-54, Reg-ulatory Guide 1.109) is the retention factor:

0.2 for particulates 1.0 for other nuclides (Page 1.109-9, Regulatory Guide 1. 109) is the effective decay constant, hr-~

'AE; is the effective adjusted to account decay constant for isotope for weathering effects, i,

as follows:

+ .0021 hr-~ (Page 1. 109-10, Regulatory Guide 1.109) is the decay constant, for nuclide i, hr-~

tE is the crop (pasture) exposure time, 720 hr (Page 1.109-58, Regulatory Guide 1.109) is the crop yield, 2.0 kg Jln2 for stored feed and 0.75 kg+~ (Page 1.109-58, Regulatory Guide 1.109) is the concentration factor from soil to crops for isotope i (Table C-2,'egulatory Guide 1.109) is the buildup time, 1.31 x 10> hr

1. 4-23

(Page 1.109-9, Regulatory Guide 1.109) is the effective surface density for soil, 240 kg/m~

(Page 1.109 9, Regulatory Guide 1.109) is the holdup time from harvest to consumption, 0.0 hr for pasture and 2,160 hr for stored. feed (Page 1.109-58, Regulatory Guide 1.109) 1.1 x 108 is a factor to convert (Ci/yr) to (pCi/hr) .

For tritium the concentration C;F, pCi/kg, is:

C.

iFr 1.7 x 107 Q;'re e

H where:

Q ~

e= (Q; ( X/Q) e ) stack (Ci-sec)/(m3-yr)

H is the absolute humidity in the atmosphere, 5.9 gm~3 is the release of isotope Table 1.2.2-1) i, Ci/yr (See

( x/Q) e t is the atmospheric dispersion factor associated with the sector centered at (r,o), sec/m3 All other parameters are as defined above.

For C-14 the concentration, C;F, pCi/kg is:

1Fr e 2 2x 10> Q.

'rre All parameters are as defined above for tritium.

For a six~onth grazing season the concentration C F fpCi/kg/ +S ~

I C'F + C.

C. re lsrt e ijr e

1. 4-24

where:

C.

Fr e is the concentration of nuclide pCi/kg in sector (r,e) .

i in fresh feed, C.

jsrF g is the concentration of nuclide feed, pCi/kg in sector (r,e) .

i in stored The concentration, C; r6 , pCi/liter, in milk is:

I C.

jmr

= FmCjFr QFe-"i e e where:

is the uptake factor from feed to milk, days/liter (Tables and Regulatory Guide 1.109)

QF is the animal~s daily feed, kg/day (Page 1.109-58, Regulatory Guide 1.109) is the distribution transport time, 96.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (Table D2, Regulatory Guide 1.109) .

The 50mile average concentration, Cjm f pCi/liter, in milk is approximated by:

Cjm r,o

~

M5p Cjm 8 where:

m, e is the quantity of milk produced in the sector defined by (r, g ), liters/yr M5 p is the quantity produced within 50 miles, liters/yr.

The concept of effective population was applied for this pathway, as recommended in Appendix D of Regulatory Guide 1.109. The effective population, P~, is used when the 50-mile population does not consume the total production.

The equation used is:

1. 4-25

where:

M50 is the quantity produced within 50 miles, literfyr fa is the fraction of persons in age group a Ua is the usage factor for age group a. Values of 110, 200, and 170 liters/yr were applied for adult, teenager, and child, respectively. (Table D-1, Regulatory Guide 1.109)

P* for milk is calculated to be 4.5 x 10~.

The dose, D. , man-rem/yr to the population from the milk pathway is:

= ~ " Cma fa Da"

) 50 -

i a where:

P50 is the 50 mile population Da i i i s the ingestion dose factor for age group a, isotope i, organ j, (mrem/hr) /(pCi+g) (Table A-3, Regulatory Guide 1.109)

All other parameters are as previously defined.

In estion of Ve etation Vegetable production is obtained using county data (Refs. 9 and 10) . Five categories of vegetables are considered, and parameters which vary with the vegetable type are presented in Table 1.4-2. A retention factor of 1.0 and a soil surface density of 240 are applied in all calculations. A growing season of 60kg+~

~

days is assumed (Page 1. 109-55, Regulatory Guide 1 .109), and the midpoint of plant operation is 15 years (Page 1.109-9, Regulatory Guide 1.109) .

1. 4-26

The model for calculating the concentration of an isotope on vegetation is the same as that for concentration in feed, described in the previous section.

The dose, D~P ,man-rem/yr, is computed by the following equation:

Dy 0+ 001 P50 CivUafa D aij i a where:

C lV is the average concentration in vegetation over the 50-mile region, pCi/kg All other parameters are as previously defined.

In estion of Meat The model for calculating the dose to the population due to ingestion of meat is identical to that presented in the section dealing with ingestion of milk.

County distribution data are used (Refs. 9 and 10) . Beef cattle, pigs, sheep, lambs, and hogs are considered; feeding habits of beef cattle are assumed for all livestock. Twenty days are allowed for distributi'on of the meat. Usages of 95, 59, and 37 kg/yr are assumed for adults, teenagers, and children, respectively. Stable element transfer data for meat are taken from Table C-5 of Regulatory Guide 1.109.

All other parameters are identical to those used in the milk ingestion calculation.

1. 4-27

Section 1.4 References Meteorology and Atomic Energy, D.H. Slade Editor, U.S. Atomic Energy Commission Of fice of Information Services, July 1968.

20 Draft Regulatory Guide 1.109, "Calculation of Annual Doses to~Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance With 10CFR Part 50, Appendix I," USNRC, March, 1976.

3. Regulatory Guide 1. 111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," USNRC, March 22, 1976.

/

4 ~ Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, "U.S. Nuclear Regulatory Commission, May, 1976.

5- A Statistical Abstract of the United States, U.S.

Department of Agriculture, 1968.

6. Cohort II Monte Carlo Radiation Transport Code, National Laboratory Radiation Oak Shielding Ridge Information Center, Document No. CCC198.

7 ~ Nine Mile Point Nuclear Station Unit 1 Environmental Report, Operating License Stage, Niagara Mohawk Power Corporation, U.S. Atomic Energy Commission, Docket 50-220.

8. Nine Mile Point Nuclear Station Unit 2 Environmental Report, Construction Permit Stage, Niagara Mohawk Power Corporation, U.S. Atomic Energy Commission, Docket 50-410.

9. "1969 U.S. Census of Agriculture," New York Crop Reporting Service, Albany, New York, July, 1972.

10. "New York Agriculture Statistics, 1974," New York Crop Reporting Service, Albany, New York, July, 1975.

1 4-28

C TABLE 1.4-1 SOURCE ACTIVITY FOR SWIMMING AND BOATING MODEL Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Average Energy Source Activit h Location Mev cc-sec hIev ~mmn Zone Lakeview Summer Cam SelKirk State Park at 5 miles at 25 miles 0.4 1 2x 10-~ 1.2 x 10-< 7.3 x 10-> 1.0 x 10-~ 5.5 x 10->

0 8 8.7 x 10-~ 8.7 x 10<<a 5-2 x 10 7.1 x 10-~ 3.9 x 10-~

1.3 4.5 x 10-~ 4.5 x 10-~ 27x 10-~ 3.7 x 10"~ 2 0 x 10 1 7 6.8 x 10-~ 6.8 x 10-~ 4.1 x 10-~ 5.6 x 10-~ 31x10 2 2 1.9 x 10-~ 19x10 1 x 10-+ 1.5 x 10"~ 8 4 x 10->

2.5 23x10+ 2.3 x 10-+ 1.4 x 10-~ 1.9 x 10-~ 1 1x10-~

3 5 1.8 x 10-~ 18x10 1 lx 10-~ 1.5 x 10-~ 82K107

TABLE 1 a-2 PARAMETERS USED IN CAI~LATING POPULATION DOSES FROM INGESTION OF VEGETATION Nine Mile Point Nuclear Station Unit 1 Niagara Mohawk Power Corporation Adult Teen Child Crop Mass Holdup Vegetation Effective Usage Usage Usage Yield Produced Time

~Cate a ~PO lllRt1alla ~kerr gkq~r~ ~kyr~ ~k~e ~kyr~ +r~

Fruits 1.9 x 10~ 6.6 8 3 6 9 1 26 1.3 x 10e 1.a x 10e Fresh Vegetables 19x10e 44 5 56 2 ae.8 2'.60 8.9 x 10~ 3.a x 10'.a Processed Vegetables 11x10e 29 5 37 3 31 1 1.01 3.5 x 10~ x 10'.4 Potatoes 1 1x10e 52.7 66.6 55 5 2.92 62x10> x 10e Grains 2.7 x 10e 66 6 8a 1 70 1 .a1 19x10e 1.a x 103

+ Note estimated actual population within 50 miles is 1.3 x 10e.

1.5 Effluent Release Data The information regarding effluent release data is available in the Nine Mile Point Unit 1 Semi-annual and Annual Operating Reports previously submitted to the Commission.

1. 5-1

2 1 Data Needed for Radioactive Source Term Calculations The information requested in Chapter 4 of NUREG-0016 is provided, in this section.

The symbol (+) designates those parameters which are NUREG-0016 assumptions. All other parameters are from actual Nine Mile Point Unit 1 operating data.

For the major streams, where the Nine Mile Point Unit 1 operating data is less than the NUREG-0016 value, the NURPG-0016 value was used.

2-1-1

2.1.1 General

a. The maximum core thermal power evaluated for safety considerations 1 '50 MWt b 1 The total mass of uranium and plutonium in an equilibrium core (metal weight)

Uranium ~B.O.C. = 211,800 lb

+E 0 C = 210 100 lb Plutonium B.O.C = 900 lb E 0 C = 1 300 lb.

+B O.C. = Beginning of Cycle E O.C. = End of Cycle

2. The percent enrichment of uranium in reload fuel No Plutonium recycle 2.74 wt 4 Plutonium recycle 1.73 wt A

3. The percent of fissile plutonium in reload fuel No Plutonium recycle 0 wt 5 Plutonium recycle 1.43 wt X

c. Parameters used in calculations of source terms in the primary coolant per NOREG-0016. Table 1.2 1-4 lists the resultant coolant activities

(+)d. The quantity of tritium released in liquid and gaseous effluents 23 Ci/yr Gaseous, 23 Ci/yr Liquid 2 1.2 Nuclear Steam Su 1 S stem

a. Total steam liow rate 7.29 x 10~ lb/nr

b. Mass of reactor coolant and steam in the reactor vessel at full power Water reactor vessel and recirculation lines 3 96x 105 lb Steam 15,000 lb 2 &1 2

2 1 3 Reactor Coolant Cleanu S stem

a. Average flow rate 1.8 x 105 lb/hr

b. Demineralizer type Deep bed

c. Regeneration frequency 3/yr (1 bea on line 4 months) d Regenerant volume and activity (+) 11,900 gal/event with a demineralizer activity input into radwaste system, based on all activity collected by the danineralizer from flow (a) at reactor coolant activity for time (c) .

2 1 4 Condensate Demineralizers

a. Average flow rate 7.29 x 106 lb/hr b Demineralizer type Deep bed

c. Number and size of Qemineralizers Number 6, Size -165 ft>; 55 ft~ = anion 110 ft~ = cation

d. Regeneration frequency 1 bed/3.5 days

e. Indicate whether ultrasonic resin cleming is used and waste liquid volume associated with its use No Regenerant volume and activity (+) 11,900 gal/event with a condensate demineralizer activity prior to regeneration equal to the buildup of main steam activity at a flow rate of 7.29 x 106/6 lb/hr for 21 days (+) (3 5 days times 6) . Note: six condensate demineralizer beds operate in parallel.

2.1.5 Li uid Hater Processin S stems

a. Sources, flow rates (gpd) and expected activities (fraction of primary coolant activity, PCA) for all inputs to each systera.

Plow Rate Fraction aid Type Source ~G)~d Of Prima Coolant

(+)Drywell Equip-ment Drains 3i400 1 0 Liquid

(+)Drywell Floor Drains 700 1 0 Liquid e

2 1-3

Flow Rate Fraction and Type Source ~Gc~t Of Primar Coolant Reactor Build-ing Equipment Drains 8,500 01 (+) Liquid

• Turbine Build-ing Equipment Drains 37,000 01 (+) Liquid

(+) Condensate Demin. Resin Rinse 5,000 002 Liquid .

(+) Condensate Backwash 8,100 2 x 10-< Liquid

(+) Radwaste Build-ing Equipment Drains 1,060 01 (+) Liquid Reactor Build-ing Floor Drains 7,500 01 (+) Liquid Radwaste Build-ing Floor Drains 3,000 01 (+) Liquid Turbine Build-ing Floor Drains 8,000 .01 (+) Liquid Hater Demin-eralizer Re-generation 720 '-

See Section 2. 1.5f Reactor Mater Cleanup Demin-eralizer Regen-eration 100 See Section 2.1.3d

(+)Condensate Demineralizer Regeneration 3~400 See Section 2.1.4f

(+) Lab Drains 500 02 Liquid 2 1W

Flow Rate Fraction and Type Source ~Gx~i Of Primar Coolant

(+)Decontamination Drains 450 See Table 2.1.5-1

(+) Chemical Lab.

Waste 100 02 Liquid

(+)Laundry Drains 450 See Table 2 1.5-1

b. Holdup times associated with collection, processing, and discharge of all liquid streams:

Collection Proce'ssing Hr Hr Waste Collec-tor Tank 2-7 -56 Floor Drain Collector 5 3 3 3 Waste Neu-tralizer 27 5 0 Laundry Drain For Calc. 0.0 For Calc 0.0 4

Note: Collection time is based on filling tank to 40 percent capacity In the event the waste concentrator is inoperable for two consecutive days per week (according to NUREG-0016), there is sufficient tank capacity (i.e., two days collection time by the waste neutralizer tank when allowed to fill ~k and waste surge to 80 percent of capacity) so that there is no discharge of the chemical regenerant strewn directly to the environment.

Similarly, there is sufficient tank capacity (i.e.,

two days collection time by the Floor Drain Collector Tank, Floor Drain Sample Tanks, and the Waste Surge Tank when allowed to fill to 80 percent, of capacity) so that alternate processing of the low purity wastes by the waste demineralizer is not.

required.

c. Capacities oi all tanks (gal) and processing equipment (GPD) considered in calculating holdup times:

2 1-5

Tank/Processing Volume Processing E ui ent Waste Collector TcDlk 25i000 Waste Surge Tank 50 000 Water Demineralizer 300 Floor Drain Collector Tank 10~000 Floor Drain Sample Tank 10,000 Waste Neutralizer Tank 15 F000 Waste Concen-trator 20 Laundry Drain Tank 1,000

(+)d. Decontamization factors for each process step:

E ui ment DF Waste Evaporator Polishing Demineral izer 1000 All Waste Demineralizer 2 Cs, Rb 100 Others

(+) e. Fraction of each processing stream expected to be discharged over the life of the plant:

Fraction Source Dischar ed Laundry Drains 0 All Others 0 1

f. For waste demineralizer regeneration:

a. Demineralizer type deep bed

b. Regeneration frequency 22/yr (1 bed on line for 19 days)

0

c. (+) 11,900 gal/regeneration which is sent to the waste neutralizer tank for subsequent process and discharge.

d The activity on the waste demineralizer prior to regeneration is based on the radwaste ilow scheme shown in Figure 1 2.3 2 and the parameters are listed in Sections 2.1.3 to 2.'l.5.

g. Liquid source term by radionuclide in Ci/yr for normal operation including anticipated operational occurrences. The liquid source terIns are listed in Table 1.2.3 1.

h. The liquid waste is normally discharged into the circulating water discharge flow which amounts to 1.07 x 10~< gal/month.,

2.1.6 Main Condenser and Turbine Gland Seal Air Removal

~Sstsms

a. The holdup time for off~ases from the main condenser air ejector prior to processing by the offgas treatment system 0.0 hr ior calculational purposes

b. Description and expected perform nce of the gaseous waste treatment systems for the off~ases from the condenser air ejector and mechanical vacua pump:

(+) 1. Expected air inleakage per condenser shell 10 cfm 2 Number of condenser shells 1

(+) 3. Iodine source term from the condenser I-131 5 curies/yr

c. 1. The mass of charcoal in the charcoal delay system used to treat the off-gases from the main condenser ~ir ejector 39.05 tons

2. The operating temperature of the delay system 70 F

3. The dew point temperature of the delay system

-4 F

4. Dynamic adsorption coeificients Xe 440 cc/gm, Kr 25 cc/gm 2w17

d. Description of cryogenic distillation systems not applicable

e. The steam flow to the turbine gland seal and the source of the steam. Primary steam 7 29 x 103 lb/hr

f. The design holdup time for gas vented from the gland seal condenser, the iodine partition factor for the condenser, and the fraction of radioiodine released through the system vent Description of the treatment systein used to reduce radioiodine and particulate releases from the gland seal system.

1. Holdup time 0.029 hr

(+)2. Iodine removal by condensing steam 0.99 Description See Section 1.2.2 2.1 7 Ventilation and Exhaust S stems For each plant building housing system that contains radioactive materials, the main condenser evacuation system and the turbine gland sealing system exhausts, the provisions incorporated to reduce radioactive releases through the ventilation or exhaust systems are as follows:

1. Reactor Building:

There is no filtration of normal exhaust ventilation.

2. Turbine Building:

There is no filtration of exhaust i'

ventilation Radwaste Building:

HEPA filters on exhaust ventilation.

(+)a. Decontamination factors assumed and the bases (including charcoal adsorbers, HEPA fi:lters, mechanical devices)

1. HEPA filters are 99 percent effective in removing particulates from air flow.

b. Release rates in curiesjyr are presented in Table 1.2.2-1.

2.1-8

c. Release point description The main stack which is the only release point at the Nine Mile, Point 1 Plant is described in Section 1.2.2.

1. Location 100 ft east of the northeast corner of the reactor building.

2. Height 350 it

3. XD of stack 8 fthm in.

0. Effluent temperature normally between 85 F and 100 F

5. Exit velocity 63 ft/sec

d. Additional containment building information is dis-cussed in Section 1.2.2.

Table 2. 1.5-1 NUREG-0016 able 2-32 Calculated Annual Release of Radioactive Materials in Untreated Deter ent Waste from a BWR Nine Mile Point Nuclear Station Unit 1 Nia ara Mohawk Power Co ration Nuclide ~Ci yr Mn-54 0 001 Co-58 0 004 Co-60 0.009 Zr-95 0 0014 Nb-95 0.002 Ru-103 0 00014 Rll-106 0.0024 Ag-1 10m 0.00044 Z-131 0.0006 Cs-134 0.013 Cs-137 0 024 Ce-144 0.005 Total 0.06 Note: Detergent wastes include laundry drains, personnel and equipment decontamination drains, and cask cleaning drains

1 I=

2. 2 Tabular Environmental Data This section provides tabulations of, the distances from the centerline of Nine Mile Point Unit 1 to the following locations for each of the 22-1/2 deg radial sectors centered on the 16 cardinal compass directions:

a. nearest milk cow (to .a distance of 5 miles)

b. nearest meat animal (to a distance of 5 miles)

c. nearest milk goat (to a distance of 5 miles)

d. nearest residence (to a distance of 5 miles)

e. nearest vegetable garden greater than 500 ft~ (to a distance of 5 miles)

f. nearest site boundary In addition, the locations of all milk cows, milk goats, meat animals, residences, and vegetable gardens out to a distance of 3 miles for each radial sector are identified.

Field surveys were conducted on November 21, 1975, December 8, 1975, April 21, 1976, and April 22, 1976, to obtain the data reported herein. Maps of the Scriba and New Haven townships, provided by the Oswego County Planning Board, were used to plot the locations of residences, vegetable gardens, and meat and dairy livestock. U.S. Geological Survey Maps (7.5 minute series) for the Oswego East, New Haven, Texas, and West of Texas quadrangles were used in addition to the maps of Scriba and New Haven.

Interviews were conducted with persons known or believed to have meat or dairy livestock. Vegetable gardens and residences were located visually and their. locations were plotted on the maps. Local, county, and federal agencies were contacted with reference to determining the number and locations of livestock in the study area.

Table 2.2-1 presents the locations of the nearest milk cows within a radius of 5 miles. Table 2.2-2 tabulates the locations of the nearest meat animals. As shown in Table 2.2-3, only one milk goat was located within a radius of 5 miles. The nearest residences within 5 miles are presented in Table 2.2-4.

The nearest vegetable gardens greater than 500 ft~ are presented in Table 2.2-5.

Tables 2.2-6 through 2.2-9 summarize the location of all milk cows, meat animals, residences, and vegetable gardens 2 &2 1

greater than 500 ft~ within a radius of 3 miles. As noted earlier, only one milk goat was located in the surveys. It was at a radius of 3.6 miles.

Figure 2.2-1 shows the locations of these tabularized residences, farm animals, and vegetable gardens within 3 miles of the site.

2 &2 2

0 TABLE 2 2-1 NEAREST MILK COW WITHIN 5 MILES NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Sector Distance ft N

ESE 8i900 SE 15,000 SSE 12,300

'11,000 SSW 16,000 11,100 WSW NOTE: A dash (-) indicates none within 5 miles

TABLE 2 2-2 NE2GU ST MEAT ANIMAL WITHIN 5 MILES NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Sector Distance ft N

ENE 22e400 ESE 8i900 SE 10,400 SSE 12,000 9,400 12e500 SW 7,700 NOTE: A dash (-) indicates none within 5 mil.es

TABLE 2 2-3 NEAREST MXLK GOAT WITHIN 5 MILES NXNE MXLE POXNT NUCLEAR STATXON UNXT 1 NIAGARA MOHAWK POWER CORPORATION Sector Distance ft N

E SE SSE 19,000 SSW WSW NOTE: A dash (-) indicates none within 5 miles

J TABLE 2 2-4 NEF3&ST RESIDENCE WITHIN 5 MILES NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Sector Distance ft N

E 6,900 ESE 6,400 SE 8,700 SSE 8,100 8,600 6,900 5,100 4~500 NOTE: A dash (-) indicates none within 5 miles

TABLE 2 2-5 NAB&ST VEGETABLE GARDEN GREATER THAN 500 FT> WITHIN 5 MILES NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Sector Distance ft, N

7,300 ESE 8,800 9,600 SSE 8i000 9,400 SSW 12'00 5, 100 NOTE: A dash (-) indicates none within 5 miles

TABLE 2 2-6 DISTRIBUTION OP ALL MILK COWS WITHIN 3 MILES NINE MILE POXNT NUCLEAR STATION - UNIT 1 NIAGARA MOHAWK POWER CORPORATXON Sector 0-1 Mile 1-2 Mile 2-3 Mile N

E ESE 35 SE SSE NOTE: A dash (-) indicates none within 3 miles

TABLE 2 2-7 DISTRIBUTION OF ALL MEAT ANIMALS WITHIN 3 MILES NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Sector 0-1 Mile 1-2 Ni.le 2-3 Mile N

ESE 58 32 70 27 33 20 NOTE: A dash (-) indicates none within 3 miles

'TABLE 2 2-8 DISTRIBUTION OF ALL RESIDENCES WITHIN 3 MILES NINE MILE POINT NUCLEAR STATZON UNIT 1 NIAGARA MOHAWK POWER CORPORATZON Sector 0-1 Mile 1-2 Mile 2-3 Mile N

10 23 SE 41 42 SSE 46 23 SSW 2

38 2'3 27 NOTE: A dash (-) indicates none within 3 miles

TABLE 2 2-9 DISTRIBUTION OF ALL VEGETABLE GARDENS GREATER THAN 500 FT~

WITHIN 3 MILES NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION Sectoz. 0-1 Mile 1-2 Mile 2-3 Mile C

E ESE 17 SSE 8

NOTE: A dash (-) indicates none within 3 miles

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1 J

, ~

2 3 X and D Data This section provides the following information concerning concentration evaluations as calculated using Smith-Singer Methodology:

a. Estimates of relative concentrations (X/Q) and or deposition (D/Q) at points of potential maximum concentrations outside the site boundary, at points estimated maxiznum individual exposure, and at points within a radial grid of sixteen 22.5 degree sectors (centered on true north, etc.) and extending to a distance of 50 miles from the plant. A. set of data points should be located within 'ach sector at increments of .25 mile to a distance of 1 mile, at increments of .5 mile from a distance of 1 to 5 miles, at increments of 2.5 miles from a distance of 5 to 10 miles, and at increments of 5 miles thereafter to a distance of 50 miles.

b. Estimates of X/Q for noble gas effluents and, if applicable, X/Q depleted by deposition aid D/Q for iodine effluents at each of these grid points, as well as averages of these X/Q and/or D/Q values between all adjacent grid points along the radials.

c. A detailed description of the model(s) and the model assumption(s) used to determine the air concentrations and/or deposition, and information concerning the validity and accuracy of the model(s) and assumptions, and the identity of the meteorological data used.

Combined annual X/Q values from the stack release, are given in Tables 2.3-'1 and 2.3-2. The corresponding data for the grazing season are shown in Tables 2.3-3 and 2.3-4.

The annual deposition (D/Q) values are given in Tables 2.3-5 and 2.3-6. Tables 2.3-7 and 2.3-8 represent the grazing season.

2.3 3 X and D Com utations The Nine Mile Point Site has been studied in detail in two separate periods, 1963-1964, when Nine Mile Point Nuclear Station Unit 1 was being designed and constructed, and again during 1974-1975 for the development of Nine Mile Point Nuclear Station Unit 2 data 2 3-1

,e 0

The analysis of diffusion and deposition is based on the meteorological data collected during 1974-1975. The following formulas and assumptions were used in deriving the X/Q and Djg estimates.

a. Stack Plume Rise Radioactivity is released from a 350 ft stack, isolated from other structures. The large volume (101 m3/sec) and speed of emission (19 m/sec) preclude any likelihood of significant downwash associated with other structures or the stack itself'.

Plume rise has therefore been calculated by the momentum formula in ASME Guide~.

1.4 he = hs + D We where:

he Effective height of the plume, meters Actual stack height, meters D Diameter of the stack, meters Vertical efflux velocity at release temperature, meters/second Mean wind speed at actual stack height, meters/second b Diffusion Modelin The Gaussian diffusion equation applicable to 22.5 deg sectors was used for the computations. The stability was determined f'rom the temperature difference between tlute 200 ~d 27 ft levels and grouped as shown in Table 2.3-9.

The equations expressing the change in o, with distance are shown in the following table:

~Ver Unstable Unstable Neutral Stable Sources Hi her Than 50 Meters

'z .40x .33x 22x 06x ~ >>

where:

2w3 2

/

= Vertical standard deviation of the Gaussian plume, meters x = Distance downwind, meters The X/Q and D/Q estimates have not been adjusted for possible changes in wind trajectories and diffusion conditions with distance. The Nine Mile Point site is open and.

uncomplicated, with a vigorous, reliable wind flow. The data from the Nine Mile Point Unit 2 tower should be quite representative of' large area. Furthermore, the data available from other locations are insufficient to define variations in

- trajectories and diffusion in a meaningful way.

Changes in terrain elevation are considered too small to have a significant effect on the estimates, and the calculations are developed on the basis of flat terrain.

c. Wind S ed Profile The winds taken from the 200 Point Nuqlear Station Unit ft level on the Nine Mile 2 tower were adjusted to stack height according to the formula:

= z "

Uh U1 where:

u> = Wind speed at upper elevation, meters/second u1 = Wind speed at lower elevation, meters/second z = Upper height meters z1 = Lower height, meters q = Exponent, ranges from 0.06 in unstable conditions to 0.50 in stable conditions One of the most complex problems in radiological evaluations is the representation of the deposition ol halogens.

A1though some field data are available, considerable evidence exists (Pelletier~, Barry>, Hill~) to suggest. that an average deposition velocity (Vg) of 0.01 m/sec is often found witls active chemical compounds such as iodine. Therefore, reasonable estimates of D/Q should result, from the single assumpu.on of a 2 w3 3

0

'I unifovn deposition velocity of 0.01 m/sec. The D/g estimates are based on this value.

Correction of the X/Q for removal by deposition has been made. For the tall stack source, it deposition and depletion are very small.

is evident that both The formulas for depletion follow those given in Chamberlain~.

2 3W

Section 2 3 References

1. Smith, M.E. {ed): Recanunended Guide for the Dispersion of Airborne Effluents, ASME 1968.

2. Pelletier, C.A., Zimbrick, J.D., 1968, Kinetics of Environmental Radioiodine Transport Through the Milk-Food Chain, in Proceedings of, Environmental Surveillance in the Vicinity of Nuclear Facilities,-

W.W. Reinig, Editor, Thomas, Springfield, Ill., 1970.

3. Barry, P.J. and Chamberlain, A.C., Deposition of Xodine onto Plant Leaves from Air, Health Ph s. 9:1149 (1963) .

4. Hill, Clyde, A. ~ 1971, Vegetation: A. Sink for Atmospheric Pollutants, Journ. of the Air Pollution Control Association, V. 21, No. 6, June 1971

5. Chamberlain, A.C., 1953, Aspects of Travel arid Deposition of Aerosol and Vapor Clouds, A.E.R.E., EB'/8, H.M.S.O.

2 3W

TABLE 2.3-1 NINE MILE POINT 1 STACK X AT GROUND LEVEL APPLICABLE TO LONG TERM ROUTINE GASEOUS RELEASES (Seconds/m~)

SECTOR ANNUAL X AT GROUND LEVEL BEARING 22 5 45.0 67.5 90 0 112 5 135 0 157. 5 180-0 25 9 6976E-,09 7 3463E-09 3.4796EWS 6.0694E-OS 5 7012E-08 6. 8108E-OS 6 0101E-08 6. 1983E-08 50 1 3910E-08 1 2830E-08 4 9250E-08 8 0757E-08 7 0662E-OB 6.7425E-OB 4.8922E-OB 5.5045E-OB 75 1 8386E-08 1 7835E-08 4.8093E&8 6.6358EWB 5.4818E-OB 4 .8364EWS 3 3392E-08 3 9082E-08 1 00 2.0684E-OB 2.0038E-OB 4 5868E-08 5 5687E-OB 4 3624E-OB 3 6642E-08 2.4674K-OB 2.9667E-OB 1 50 1 9908E-08 1 9124E-08 4 0209E-OS 4 4820E-08 3.3603EWS 2.7202E-OB 1 8019E-08 2. 2231E-08 2 00 1 4788E-08 1 3959E-08 2 7564E-OB 2 8506E-08 2 0430E-OB 1.5908E-OB -

1 0392E-08 1 3368E-08 2 50 1 1593E-08 1 0853E-OB 2 1064E-08 2 1284E-OS 1.5035EWB 1 1544EWS 7.5132EM9 9. 8814E-09 3 00 9 2131E-09 8 5757EW9 1 6481E-08 1 6422E-08 1. 1503E-OB 8.7573EW9 5.6870E-09 7 6053EW9 3 50 7.4631E-09 6 9214E-09 1 3212E-08 1 3043E-OS 9.0870E-09 6 8827E-09 '.4622E-09 6 0411E-09 4.00 6. 1810E-09 5 7013EW9 1 0822EWS 1 0611E-08 7.364 9E-O 9 5. 5631' 3 6012E-09 4. 9190E-09 4 50 5. 1823E-09 4.7897E-09 9 0389E-09 8 8150E-09 6 0990E-09 4 6021EW9 2 9747E-09 4.0891E-09 5.00 4 4408EW9 4 1011E-09 7 6840E-09 7 4595E-09 5.1443EW9 3 ~ 8822E&9 2 5061E-09 3.4600E-09 7 50 2 6232E-09 2 4143E-09 4 2155E-09 4 0028E-09 2 6783E-09 2.0359E-09 1. 3125E-09 1.8209EW9 10 00 2 0301E-09 1.8620E-09 2.9434EW9 2.7272E-09 1.7368E-09 1 3253E&9 8.6167E-10 1. 1868E-09 15 00 5291E-09 1 4047E-09 1.9270E-09 ~

1 7216E-09 1.0086E&9 7 6008E-10 5.0707E-10 6 8857E-10 20 00 1 2094E-09 1 1199E-09 1. 4310EW9 1.2549E-09 7. 0570E-I 0 5'. 2041E-10 3.5461E-10 4. 8051E-10 25 00 9 7816E-10 9 0670E-10 1 1134E-09 9 6715E-10 5.3466E-10 3 8653E-10 2 6744E-10 3 6421E-10 30.00 '.9057K-10 7 4523E-10 8 9229E-10 7 7100E-10 4 2370E-10 3. 0132E-10 2. 1088E-10 2 8925E-10 35 00 6 5510E-10 6 2203E-10 7 3171E-10 6 3042E-10 3.464 1E-10 2.4299E-10 1.7162E-10 2 3701E-10 40 00 5 5166E-10 5 2687E-10 6 1161E-10 5.2621E-10. 2 9018E-10 2. 01 11E-10 1.4318E-10 1. 9881E-10 45 00 4 7141E-10 4 5226E-10 5 1952E-10 4.4686E-10 2.4791E-10 1 6994E-10 1. 2187E-10 1 6989E-10 50 00 4 0810E-10 3 9286E-10 4.4742E-10 3 8502E-10 2 1527K-10 1.4608E-10 1. 0547E-10 1. 4739E-10 Based on 1974-1975 1 of 1

TABLE 2 3-2 NINE MILE POINT STACK X AT GROUND LEVEL APPLICABLE TO LONG TERM OUTINE GASEOUS RELEASES (Seconds fin)

SECTOR ANNUAL X AT GROUND LEVEL

'ISTANCE BEARING

~HILII 202 5 225.0 247 5 270 0 292 5 315-0 337.5 360.0 25 3 3650E-08 2 6981E-08 5.895&EW9 5 1630EM9 1.4296E-O& 2.4926E-O& 2 7996E-08 2 961&E-08 50 3 4790E-08 3 3961E-OS 1. 1759E-08 9 1740E-09 2.2360E-O& 3 9006E-0& 3.4686E-OB 3.940&E;08 75 2 7701E-OS 2 8645E-0& 1 1919EWB 1.0577EWB 2.6042E-O& 4 7934E-08 3.5600E-OB 4.3969E-Q&

1.00 2.2872E-OB 2 4369E-08 1. 1410EW8 1304E-O& 2 7366E-08 5 0833E-O& 3 5141E-08 4. 5213E-08 1 50 8236E-08 1 9807K-08 1 0139EWS 1.0866E-OB 2.5443E-OB 4.7040EWB 3. 1530EWB 4 1304E-08 2 00 1 1585E-08 1 2737EMS 7 221&E-09 8 3284E-09 1 8325E-08 3 3565E-O& 2.2149E-OS 2 9191E-OS 2 50 8 6857E-09 9 5483E-09 5 6503EW9 6 6626E-O9 1 4204E-08 2 5950E-08 1 70&&EM& 2 2490EW&

3 00 6.7314E-09 7 3870E-09 4.5025E-09 5 3760E-09 1 1200E-08 2 0443E-08 1 3456' 1 7675k-08 3 50 5 3673E-09 5 8795E-09 3 6593EW9 4 4039E-09 9. 0 195E-09 1.6461E&8 1.083&E-OB 1 4210E-08 4 00 4 3810E-09 4.7928E-09 3.0281E&9 3.6654E-09 7.41OOE-O9 1 3525E-08 8. 9132E-09 1. 1670E-OS 4 50 3 64&BE-09 3 9894E-09 2 5482E-09 3 1013E-09 6 2047E-09 1326E&8 7.4779E-09 9-7807E-09 5.00 3.0929E-09 3.3823E-09 2. 1786EW9 2 6684EW9 5 2907EW9 9 653&EM9 6.3943E-09 8-3602E-09 7 50 6459K-09 1 826&E-09 1 2234E-09 1 6009E-09 3.0087E-09 5.3890EW9 3 7134E-09 4 9006E-09 10 00 1 0860E-09 1 2426E-09 8 8932E-10 1.2757EW9 2. 2193E-09 3.8003EW9 2 77&OEM 9 3 7372E-09 15 00 6 3793E-10 7 7129E-10 6 4156E-10 1 0211E-09 5652E-09 2 4483E-09 1 95&OE-09 2 7109E-09 20 00 4 4456E-10 5 5251E-10 5 1215E-10 8. 4224E-10 1. 19&BE&9 1.7697EW9 1 4863E-09 2.0855E-09 25.00 3 3471E-10 4 2024E-10 4. 1869E-10 6 9646E-10 9 4551E-10 1 3474E-09 1 1643E-09 1 6427E-09 30.00 2 6387E-10 3 3197E-10 3. 4757E-10 5 8091E-10 7 6303K-10 1.0628E-09 9 3535E-,IO 1 3221E-09

35. 00 2 1493E-10 2 6999E-10 2. 9276E-10 4 9026E-10. 6 2843E-10 8 614&E-10 7. 6797E-10 1 0855E-09 40 00 1 '959E-10 2 2492E-10 2 5006E-10 4 1890E-10 5 2701E-10 7 1395E-10 6. 4256E-10 9. 0714E-10 45 00 1 5320E-10 1 9119E-10 2 1637E-10 3 6216E-10 4 489&E-10 6 0256E-10. 5 4641E-10 7. 6 994E-10 50 00 3292E-10 1.6529E-10 1 8939E-10 3 1649E-10 3 &776E-10 5 1638E-10 4 7116E-10 6. 6233E-10 Based on 1974-1975 1 of 1

TABLE 2 3-3 STACK X AT GROUND LEVEL APPLICABLE TO LONG TERM ROUTINE GASEOUS RELEASES NINE MILE POINT NUCLEAR STATION - UNIT 1 NIAGARA MOHAWK POWER CORPORATION GRAZING SEASON (APRIL 1 SEPTEMBER 30)

SECTOR X/Q AT GROUND LEVEL (Seconds/m3)

DISTANCE BEARING

~MILES 22 5 45.0 67 5 90 0 112.5 135 0 157. 5 180.0 25 9 1689E-09 7 6903E-09 5 &711E-08 6.8033E-OS 2.9963E-08 1 2241E-08 2.3411E-OS 5. 1432E-08 50 6069E-08 1 4877E-08 8 0257EW& 8 7166E-08 3.6690E-OS 1 6656E-08 2 ~ 1972E-08 4 0410h-08 75 2.2277E-08 2 6503EW& 8.9933E-QS 7 4667E-08 2.9080K-08 1 3207EW& 1.5279E-O& 2.5375E-O&

1.00 2 525&E-08 3.2644E-O& 9 2673E-08 6.3550E-Q& 2.3663E-Q& 1- 1052E-08 1 ~ 1307E-08 1 7451E-O&

1 50 2.4309E-O& 3 2593E-08 8.4722EWS 5.0761E-QS 1 841&E-08 9 1035EW9 8 1989E-09 1 2146E-08 2-00 1 7866E-08 2 4556E-08 6 0111EW& 3. 1369EW& 1 1166E-08 6 0945E-Q9 4 633&E-09 7 153&E-09 2 50 1 3902E-08 1 9231E-08 4.6510E-08 2.3056EW& 8 1675E-09 4 6589E-09 3 3104E-09 5 4753E-09 3 00 1.09&OEM& 1.5244E-Q& 3.6702E-O& 1 7584E-08 6 2134E-09 3 6510E-09 2 4818E-09 4.3860E-09 3 5Q 8 8488E-09 1 2314E-08 2 9603E-08 1 3842E-08 4.8837K-09 2. 9311E-09 1. 9318E-09 3. 6100E-09 4 00 7 2714E-09 1 0135E-O& 2 4360EWS 1 1184E-QS 3 9407E-09 2 4053E-09 1 5494E-09 3 0272E-09 4.50 6 0863E-09 8.4930E-09 2 0422EWS 9 239&E-09 3 2512K-09 2 0160E-09 1 2762E-09 2 5769EW9 5.00 5 183&E-09 7 2400E-09 7420EW 8 7.7852E-09 2.7346E-09 1 7254EW9 1~07&QE-09 2.2224E-09 7 50 2 8880E-09 4 0360EW9 9 7356E&9 4 1384E-09 .1 4285E-09 1 0462E-09 6 6026E-10 1.2312E-09 10 00 2.0609EW9 2.8682E-09 6 908&E-09 2.8273E-09 9 44&3E-10 & 4611E-10 5 931&E-10 8.0948E-10 15.00 1 3812E&9 1 9141E-09 4 5495EW9 1. 8261E-09 5.5934E-10 6.654&E-10 5 662&E-10 4.5114E-10 20 00 0269E-09 1.4407E-09 3.339&EW9 1.3662E-09 3 8646E-10 5 3035E-10 5. 0285E-10 2. 957 4E-10 25 00 7 9445E-10 1. 1394E-09 2.5627E-09 1 0743E-09 2 8609E-10 .4.2449E-10 4 2849E-10 2 1104E-10 30 00 6-3208E-10 9.2870E-10 2 027&E-09 8 6843K-10 2 2122E-10 3 4431E-10 3 6161E-10 1.5904E-10 35.00 5 1460E-10 7 7349E-10 1 6446EW9 '7 1662E-10 1 765&E-10 2.8375E-10 3. 0615E-10 1 2459E-10 40 00 4 2717E-10 6 5513E-10 1 3614E-09 6 0143E-10 1.444&E-10 2 3750E-10 2.6125E-10 1. 0050E-10 45.00 3 6046E-10 5 6251E-10 1. 1463EW9 5 1206E-10 1 2059E '10 2 0161E-10 2 2501E-10 8 2958E-11 50.00 3 0846E-10 4 886QE-10 9 7933E-10 4140E-10 1 0231E-10 1 7331E-10 1 9559E-10 6 975&E-11 Based on 1974-1975 1 oi 1

TABLE 2 3-4 STACK X AT GROUND LEVEL APPLICABLE TO LONG TERM ROUTINE GASEOUS RELEASES NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION, GRAZING SEASON (APRIL SEPTEMBER 30)

SECTOR X/Q AT GROUND LEVEL (Seconds/m~)

DISTANCE BEARING

~MILES 202 5 225 0 247.5 270 0 292-5 315.0 337 5 360.0 25 4 7392E-08 7 8964E-08 3.4278E&9 8 4766E-10 7.4911E-09 1 8600E-OS 3. 3918E-08 2.9656E-08 50 4 1947E-OS 7 2184E-08 6.6739E 6 5865E-09 9 7337E-09 2 6287E-08 2 7612E-08 3.7989EWS 75 3 0024E-08 5 0578E-08 6.6702E-09 1. 1562E-OS 9 0273EW9 2 3790E-08 2.1087E-08 3 5851E-08 1 00 2 3767E-08 3 7847E-08 6. 4156E-09 1 3462E-08 8 4121E&9 2 0939E-08 1.7387EWS 3 2776E-08 1 50 1 8818E-08 2.8008EWS 5 6870EW9 1 2893E-08 7.2535E-09 1.7105EWS 3909E-OS 2 7533E-08 2 00 1 2452E-08 1 6430E-08 3 9444E-09 9 2980E-09 4 8647E-09 1 0796E-OS 8.8078E-09 1 7853E-08 2 50 9.6959E-09 1 1943E-08 3.0212E-09 7 1684E-09 3 6795E-09 7 9920EW9 6 '622EW9 1.3334EWS 3 00 7 7659E-09 9 0601E-09 2 3645EW9 5.6258E-09 2 8570E-09 6 1232E-09 5 0536E-09 1.0272E-08 3.50 6 3576E-09 7 t 102EW9 1.8940E-09 4.5136EW9 2 2763E-09 4 8369E-09 4 0083E-09 8. 1452E-09 4.00 5 2963E-09 5.7315E-09 1. 5487EW 9 3.6969E-09 1 8540E-09 3.92ttEW9 3 2625E-09 6 6256E-09 4 50 4 4786E-09 4 7263E-09 1.2900E-09 3. 0881E-09 1 5392E-09 3 2550E&9 2 7217E-09 5. 5213E-09 5.00 3 8368E-09 3.9760EW9 1 0925EW9 2 6291E-09 1 2990E-09 2.7638E-09 2 3266E-09 4.7114E-09 7 50 ,2 0406E-09 2 1253E-09 5.8322E-10 1 5223E-09 6 6078E-10 1 6441E-09 1 4658E-09 2 9146E-09 10.00 1 2707E-09 1.4947EW9 0 t54E-10 1 1867E-09 4 0321E-10 1 3376E&9 1 2525E-09 2 4513E-09 15.00 6 3691E-10 1 0081EW9 2 7765E-10 9 1782E-10 1 9863E-10 t 0752EW9 1.0629EW9 2.0386E-09 20 00 3.8620E-10 7 5799E-10 2 3639E-10 7. 3375E-10 1. 1963E-10 8.6788E-10 9 1495E-10 1.6908E-09 25 00 2 6135E-10 5.9161E-10 2 1470E-10 5 9026E-10 8 0934E-11 6 9998E-10 7 9404E-10 1.4000E-09 30 00 1 9084E-10 4 7583E-10 1 9804E-10 4.8188E-10 5.9974E-11 5. 7163E-10 6 9332E-10 1. 1687E-09 35.00 1 4830E-10 3 9462E-10 1. 8368E-10 4 0114E-10 4.8655E-11 4 7539E-10 6.0830E-10 9 8658E-10 40.00 1 2168E-10 3 3732E-10 1 7129E-10 3 4092E-10 3045E-11 4 0317E-10 5.3626E-10 8 4241E-10 45 00 1 0455E-10 2 9628E-10 1 6064E-10 2 9541E-10 4 0759E-11 3 4830E-10 4 7513E-10 7 2707E-10 50 00 9 3149E-ll 2 6612E-10 1.5139E-10 2 6035E-10 4 0265E-11 3 0584E-10 4 2314E-10 6.3372E-10 Based on 1974-1975 1 of,l

TABLE 2 3-5 NINE MILE POINT 1 STACK D AT GROUND LEVEL APPLICABLE TO LONG TERM ROUTINE GASEOUS RELEASES (Seconds~~)

SECTOR ANNUAL D AT GROUND LEVEL BEARING 22.5 45.0 67.5 90.0 112 5 135.0 157 5 180. 0 25 9 6929E-11 7 3448E-11 3 4791E-10 6.0683E-10 5 7000E-10 6.8078E-10 6 0065E-10 6 1944E-10 50 1 3881E-10 1 2810E-10 9167E-10 8 0612E-10 7 0536E-10 6.7277E-10 4 8794E-10 5.4896K-10 75 1 8339E-10 1 7798E-10 4 7962E-10 6 6127E-10 5.4621E-10 8165E-10 3.3235E-10 3.8890E-10 1 00 2 0595E-10 1 9980E-10 4 5702E-10 5 5417E-10 4 3400E-10 3 6433E-10 2 4514E-10 2.9466E-10 1 50 1 9802E-10 1. 9031E-10 3 9994E-10 4 4516E-10 3 3362E-10 2 6993E-10 1.7861E-10 2 2031E-10 2 00 4612E-10 1 3809E-10 2 7266E-10 2 8156E-10 2 0178E-10 1.5709E-10 0243E-10 1 3175E-10 2 50 1 1395E-10 1 0683E-10 2.0741E-10 2 0928E-10 1 4788E-10 1 1356E-10 7 3732E-11 9 6951E-11 3 00 9 0068E-11 8 4007E-11 1 6154E-10 '1 6074E-10 1 1267E-10 8 58 16E-1 1 5. 5569E-1 1 7 4269E-11 3 50 7 2568E-11 6 7480E-11 1 2892E-10 1 2710E-10 8 8650E-11 6 7199E-11 4 3419E-11 5. 871 1E-11 4.00 5 9597E-11 5 5335E-11 1 0514E-10 1.0297E-10 7. 1569E-1 1 5. 4125E-1 1 3 4900E-11 4 7576E-tl 4 50 4 9885E-11 4 6292E-11 8 7455E-11 8 5195E-11 5.9046E-11 4 4625E-11 2 8719E-tl 3 9362E-li 5 00 4 2554E-11 3 9485K-tt 7.4061E-11 7. 1823E-11 4.9627E-11 3 7526E-11 2.4t07E-11 3 3153E-11 7.50 10 00 2.4801E-11 1 9140E-11 2 2970E-11 7653E-11 4.0053E-11 2.7761E-11 3.7992E-11 2 5681E-11 2 5456E-11 1 6334E-11 l 9410E-11 2493K-11 1 2435E-11 8'0736E-12 1.7103E-11 1 1 0991E-11 15 00 4256E-11 1 3141E-11 1 7916E-11 1.5982E-11 9 3274E-12 7 0157E-12 4. 6592E-12 6 2489E-12 20 00 1 0950E-11 1 0160E-11 1 2947E-11 1355E-11 6 3737E-12 4. 6817E-12 3. 1744E-12 4 2586E-12 25 00 8 4336E-12 7 8873K-12 9 7011E-12 8. 4413E-12 4 6714E-12 3 3681E-12 2 3142E-12 3 1284K-12 30.00 6 5824E-12 6 1786E-12 7 4425E-12 6 4523E-12 3 5560E-12 2. 5317E-12 1 7544E-12 2. 3918K-12 35 00 5 1828E-12 4 9011E-12 5 8274E-12 5. 0450E-12 2 7818E-12 1 9639E-12 1 3688E-12 1 8778E-12 40 00 4 1606E-12 3 9419E-12 4. 6485E-12 4 0247E-12 2 2267E-12 1 5625E-12 1 0938E-12 1 5050E-12 45.00 3 3940E-12 3 2146E-12 3.7712E-12 3 2690E-12 1.8186E-12 1 2700E-12 8. 9233E-13 1 2276E-12 50.00 2 8103E-'12 2 6562E-12 3 1063E-12 2 6981E-12 1 5120E-12 1 0513E-12 7.4115E-13 1. 0168E-12 Base'd on 1974-1975 1 of 1

TABLE 2-3-6 NINE MILE POINT 1 STACK D AT GROUND LEVEL APPLICABLE TO LONG TERM UTINE GASEOUS RELEASES (Seconds/m>)

SECTOR ANNUAL D AT GROUND LEVEL DISTANCE BEARING

~NZLES 202.5 225.0 247.5 270.0 292 5 315.0 337.5 360.0

.25 3 3632E-10 2 6969E-10 5 8941E-11 5 1612E-11 1 4291E-10 2 4916E-10 2.7984E-10 2 9606E-10 50 3. 4707E-10 3.3883E-10 1 1731E-10 9 1532E-11 2 2316E-10 3 8929E-10 3.4613E-10 3 9330E-10 75 2 7581E-10 2 8518E-10 1 1864E-10 1.0538E-10 2.5964E-10 4 7801E-10 ,3 5488E-10 4 3846E-10 1 00 2 2734E-10 2.4219E-10 1 1340E-10 1 1250E-10 2 7256E-10 5 0646E-10 3 4999E-10 4 5049E-10 1.50 1 8084E-10 1 9640E-10 1 0053E-10 1 0790E-10 2 5288E-10 4 6778E-10 3 1345E-10 4. 1077E-10 2 00 1 1420K-10 1.2551K-10 7 1117E-11 8 2102E-11 1 8095E-10 3.3185E-10 2 1892E-10 2. 8862E-10 2 50 8 5210E-11 9 3628E-11 5 5321E-11 6 5262E-11 1 3950E-10 2 5535E-10 1 6808E-10 2 2130E-10 3 00 6 5711E-11 7 2073E-11 4 3814E-11 5 2304E-11 1 0940E-10 2 0021E-10 1 3169E-10 1 7309E-10 3 50 5 2137E-11 5 7086E-11 3 5389E-11 4 2553E-11 8 7640E-11 1 6046E-10 1 0555E-10 1 3851E-10 4 00 4 2351E-11 4.6319E-11 2 9103E-11 3. 5178E-11 7 1638E-11 1 3125E-10 8 6395E-11 1 1325E-10 4.50 3.5108E-11 3 8386E-11 2. 4343E-11 2 9569E-11 5 9703E-11 0944E-10 7 2159E-11 9 4525E-11 5.00 2 9627E-11 3 2412E-11 2.0691E-11 2 5287E-11 5 0689E-11 9 2918E-11 6 1450E-11 8.0495E-11 7 50 1.5479E-11 1 7231E-11 1 1368E-11 1 4886E-11 2 8427E-11 5 1151E-11 3.5221E-11 4 6664E-11 10 00 1 0088E-11 1 1609E-11 8 1947E-12 1 1833E-11 2. 088 1K-11 3 5836E-11 2 6232E-11 3 5480E-11

15. 00 5 8192E-12 7 0870E-12 5 8447E-12 9.3793E-12 1 4555E-11 2 2790E-11 1 8265E-11 2 5428E-11 20.00 3 9648E-12 4.9466E-12 4. 5264E-12 7 4859E-12 1 0842E-11 1 6114E-11 1.3519E-11 1. 9044E-11 ZS 00 2 8982K-12 3 6349E-12 3. 5331E-12 5. 9081E-12 8 2312E-12 1 1926E-11 1 0244E-11 1 4480E-11 30 00, 2 2065E-12 2 7613E-12 2.7749E-12 4 6703E-12 6 3619E-12 9 1149E-12 7.9303E-12 1. 1207E-11 35 00 1 7302E-12 2 1562E-12 2.2011E-12 3 7219E-12 5.0089E-12 7. 1504E-12 6.2648E-12 8 8372E-12 40.00 ~

1 3901E-12 1 7255E-12 1.7678E-12 2 9985E-12 4 0155E-12 5 7337E-12 5.0424E-12 7 0944E-12 45.00 1. 1405E-12 1 4114E-12 1 4388E-12 2.4442E-12 3.2736E-12 4.6844E-12 4 1272E-12 5.7896E-12 50 00 9 5270E-13 1-1766E-12 1 1866E-12 ~ 2. 0 157E-12 2.7098E-12 3.8894E-12 3.4291E-12 4 7952K-12 Based on 1974-1975 1 of 1

TABLE 2 3-7 STACK D AT GROUND LEVEL APPLICABLE TO LONG TERM ROUTINE GASEOUS RELEASES NINE MILE POINT NUCLEAR STATION UNIT 1 NIAGARA MOHAWK POWER CORPORATION GRAZING SEASON (APRIL 1 - SEPTEMBER 30)

SECTOR D/Q AT GROUND LEVEL (1/ln>)

DISTANCE .BEARING

~ISLES 22 5 45.0 67 5 90 0 112 5 135 0 157. 5 180 0 25 9 1676E-11 7 6890K-11 5. 8700E-10 6 8024E-10 2 9958E-,10 1 2239E-10 2.3400E-10 5 1407E-10 50 1 6047E-10 1 4860K-10. 8. 0144E-10 8 7039E-10 3 6634E-10 1 6623E-10 2. 1926E-10 4 0325E-10 75 2 2233E-10 2 6470E-10 8 9756E-10 7 4471E-10 2 9000E-10 1 3157E-10 1 5220E-10 2 5278E-10 1 00 2 5186E-10 3 2576K-10 9 2424E-10 6.3310E-10 2 3575E-10 1 0997E-10 1 1 247E-10 1 7359E-10 1 50 2 4189E-10 3 2458E-10 8 4351E-10 5. 0477E-10 1 8322E-10 9. 0424E-11 8 1410E-11 1 2062E-10 2 00 7664E-10 2 4298E-10 5 9525E-10 3 1049E-10 1 1064E-10 6 0180E-11 4.5816E-11 7 0781E-11 2 50 1 3673E-10 1 8930E-10 4 5852E-10 2 2744E-10 8 0686E-11 4.5752E-11 3 2629E-11 5 3981E-11 3 00 1 0743E-10 1.4927E-10 3 6018E-10 1.7290E-10 6 1205K-11 3 5645E-11 2.4389E-11 4 3038E-11 3.50 8 8149E-11 1 1998E-10 2 8921E-10 1 3571E-10 4 7975E-11 2 8449E-11 1 8931E-11 3. 5218K-11 4 00 7 0454E-11 9 8279E-11 2 3694E-10 t. 0 934E-10 3. 8612E-1 1 2 3214E-11 1.5 t44E-11 2. 9335E-11 4.50 5 8709E-11 8 1994E-11 1 9780E-10 9 0109E-11 3 1781E-11 1 9353E-11 1.2444E-11 2. 4792E-1'l 5 00 4 9798E-11 6 9612E-11 1. 6805E-10 7-5749E-11 2 6672K-11 1 6484E-11 1.0491E-11 2. 1222E-11 7 50 2.7354E-11 3 8260E-11 9. 2556E-11 3-9944E-11 1 3818E-'l1 9 8716E-12 6.4065E-12 1 1338K-tt 10 00 1 9411E-11 2 7028E-11 6 5223E-11 2. 7187E-11 9 0939E-12 7 9808E-12 5 7673E-12 7 2394E-12 15 00 1.2843E-11 1 7813E-11 4.2363E-11 1 7389E-11 5 3149E-12 6.2098E-12 5 4093E-12 3 8639E-12 20 00 9 2921E-12 1 3081E-11 3.0313E-11 1 2707E-11 3 5897E-12 4 7997E-12 4 5971E-12 2.4415E-12 25 00 6 9281E-12 1 0004E-11 2 2486E-11 9 6358E-12 2 5809E-12 3. 6888E-12 3. 6959E-12 1. 68'l9E-12 30 00 5.2895E-12 7 8376K-12 1.7137E-11 7 4510E-12 1 9329E-12 2 8619E-12 2 9229E-12 1.2248E-12 35 00 4 1274E-12 6 2457E-.12 1 3374E-11 5 8566E-12 1.4935E-12 2 2541E-12 2. 3134E-12 9 2837E-13 40.00 3.2850E-'l2 5 0446E-12 1 0658E-11 4. 6751E-12 1. 1836E-12 1 8045E-12 1 8455E-12 7 2565E-13 45 00 2 6610E-12 4 1220E-12 8 6503E-12 3 7869E-12 9 5775E-13 1. 4670E-12 1.4879E-12 5 8123E-13 50.00 2 1894E-12 3.4043E-12 7. 1339E-12 3 1098E-12 7. 888 2E-13 1 2097E-12 1.2132E-12 4.7496E-13 Based on 1974-1975 1 of 1

TABLE 2 3-8 STACK D AT GROUND LEVEL APPLICABLE TO LONG TERM ROUTINE GASEOUS RELEASES NINE MILE POINT NUCLEAR STATION - UNIT 1 NIAGARA MOHAWK POWER CORPORATION GRAZING SEASON (APRIL 1 SEPTEMBER 30)

SECTOR D/Q AT GROUND LEVEL (tW~)

DISTANCE BEARING

~MILES 202.5 225 0 247.5 270 0 292 5 315.0 337 5 360.0 25 4 736&E-10 7 8934E-10 3 4274E-11 8 4763E-12 7 4899E-11 1. 8597E-10 3 3899E-10 2 964&E-10 50 4 1859E-10 7 205&E-10 6 6594E-11 6 5760E-11 9 7182E-11 2 6239E-10 2 7550E-10 3 7924K-10 75 2 991&E-10 5 0396E-10 6 6427E-11 1 152&E-10 9.0045E-11 2 3718E-10 2 1009E-t0 3 5752E-10 1.00 2 3658E-10 3 7649E-10 6 3807E-11 1 3404E-10 8 3837E-11 2 0857E-'10 1.7303E-10 3 2657K-10 1~50 8703K-10 2 7803E.-10 5 6439E-11 1 2806E-10 7 2163E-11 1 7013E-10 1 3820E-10 2 7389E-10 2 00 1 2312E-10 1. 6223E-10 3 8879E-11 9 1740E-11 4 8130E-11 1 069&E-10 8 7088E-11 1 7683K-10 2 50 9 5421E-11 1 1741E-10 2 9613E-it 7.0367E-11 3 6243E-11 7 8971E-ll 6 4617E-11 1 3163E-10 3 00 7 6013E-11 8 8674E-11 2 3047E-11 5 4952E-11 2 8019E-11 6 '343E-11 4 9554E-11 1 010&E-10 3 50 6 1860E-11 6.9291E-11 1 836 1E-11 4 3882E-11 2 2231E-11 4 7546E-11 3. 9146E-11 7 9911E-11 4 00 5 120&E-11 5 5626E-11 1 4937E-11 3 5785E-11 1 8036E-11 3 8454E-11 3 1740E-11 6 4822E-11 4 50 4 3019E-11 4 5692E-11 1 2381E-11 2. 9772E-11 491&E-1 1 3 1854E-11 2 638&E-11 5 3884E-ll 5 00 3 6612E-11 .3 8299E-11 1 0438E-11 2 5255E-11 1 2546E-11 2 6997E-11 2 2490E-11 4-5884E-11 7~50 1 8857E-11 2 0216E-11 5 4775E-12 1 447&E-11 6.2&71E-12 1 5995E-11 1.4091E-11 2 8273K-tt 10 00 1 . 14 t4E-11 1 4149E-11 3 7433E-12 1 1276E-11 3 790&E-12 1 3006E-11 1 2Q57E-ll 2 3784E-lt 15 00 5 4632E-12 9 4122E-12 2 5636E-12 8 6042E-12 1 8330K-12 1 0282E-11 1 0109E-11 9495E-11 20 00 3 1951E-12 6 8554E-12 2 13&BE-12 6 6345E-12 1 0882E-12 8 0067E-12 8 465&E-12 1 5658E-11 25 00 2 0997E-12 5 1253E-12 1 8796E-12 5 0884K-12 7 27&3E-13 6 1737E-12 7 0905E-12 1.2443E-11 30 00 1 4983K-12 3 9337E-12 1 ~ 654 1E-12 3.9446E-12 5 3543E-13 4 8061E-12 5 9269E-12 9 9191E-12 35 00 1 1464E-12 3 1185E-12 4466E-12 3 1200E-12 4 3396E-13 3. 8132E-12 4. 9360E-12 7 9696E-12 40 00 9.337&E-13 2 562QE-12 1 2634E-12 2 52&OE-12 3 &565E-13 3 0945E-12 4 0999E-12 6 4635E-12 45 00 8 0142E-13 2 1774E-12 1 1075E-12 2 0983E-12 3 6683E-13 2 5680E-12 3 4040E-12 5 2934E-12 50 00 7 146th-13 1 9024E-12 9 7681E-13 1. 7793E-12 3 6171E-13 2. 1740E-12 2 8315E-12 4 3777E-12 Based on 1974-1975 1 of 1

TABLE 2 3-9 Turbulence Class S stems and Tem erature Differences Nine Mile Point Nuclear Station Unit, 1, Niagara Mohawk Pcarer Corporation Brookhaven Smith-Singer Temperature National Lab Difference S stem 4C 100m Bg <-1.9 BI -1.9(DT<-0 7

-0 7<AT<0 0 D AY>0 0

2.4 Descri tion of Meteorolo ical Data Models and Parameters The information regarding meteorological data requested by the NRC has been discussed in the response to Request B4 of the Nine Mile Point Nuclear Station Vnit 2, Docket No. 50-410, Compliance with 10CFR50 Appendix I, June 4, 1976.

2. 4-1

2.5 On-Site Meteorol ical Data R.G. 1.23 The information regarding on site meteorological data requested by the NRC has been discussed in the response to Request B-1 of the Nine Mile Point Nuclear Station Unit 2, Docket No. 50-410, Compliance with 10CFR50 Appendix I, June 4, 1976.

2.5-1

2.6 Descri tion of Meteorolo ical Measurements Pro ram The radiological conditions at the site and in its environment have been monitored in an extensive program initiated by the Niagara Mohawk Power Corporation in 1967, two years prior to start-up of the Nine Mile Point Station Unit 1. The results of this phase of the program were reported to the AEC in a document. entitled >Environmental Preoperational Survey, Nine Mile Point " dated December 1969. Presently the program yields operational phase data for the Nine Mile Point Station Unit 1.

Additional meteorological information has been discussed in Part B, Meteorology, of the Nine Mile Point Nuclear Station Unit 2, Docket No. 50-410, Compliance with 10CFR50 Appendix Zg June 4, 1976.

2.6-1

0 2.7 Descri tion of Airflow Tra ector Re imes The information regarding airflow trajectory regimes requested by the NRC has been discussed in the response to Request B2 of the Nine Mile Point Nuclear Station Unit 2, Docket No. 50 410, Compliance with 10CPR50 Appendix I, June 4, 1976.

2 &7 1

2.8 To o ra hical Ma The information regarding the Topographical Map requested by the NRC has been discussed in the response to Request B3 of the Nine Mile Point Nuclear Station Unit 2, Docket No. 50-410, Compliance with 10CFR50 Appendix E, June 4, 1976.

Figures B3b-1, B3b-2, B3b-3, and B3b-4 show the maximum topo-graphical elevations out to 50 miles from the plant.

2-8-1

0 2.9 Dates and Times of Intermittent Radioactivit Releases As stated in Section 1.2.2, the only release point for Nine Mile Point Unit unintermittent 1 is the main stack and, therefore, no releases are being reported.

2.9-1

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