ML20235C953
| ML20235C953 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 11/01/1976 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20235A754 | List: |
| References | |
| 11116, NUDOCS 8709250068 | |
| Download: ML20235C953 (163) | |
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HERLIN. CONNECTICUT P O. 901 270 H ARTFORD. CONNECTICUT 06101 Tat s peen.s 1 203 666-6911 l November 1, 1976 f t
"~:~ T77 Director of Nuclear Reactor Regulation Docket No. 50-213[gpJ.r q q' ' r r ., j Attn: Albert Schwencer, Chief. 4 i 2 bf fiA Operating Reactors Branch #1 Division of Operating Reactors & g- 1 Jg76, U.S. Nuclear Regulatory Commission '
Washington, D.C. 20555 U+5 $ $f m i g- 1 q tw1 M" ;e :SI Gentlemen: s O
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+ -4 Haddam Neck Station, Docket No. 50-213 Compliance with 10CFR50, Appendix I Per the requirements of Section V.B of 10CFR50, Appendix I and the guidance i given in enclosures 1 and 2 of your letter dated February 19, 1976, the -)
Connecticut Yankee Atomic Power Company hereby submits tl.e final (Part II) report of its demonstration of compliance with Appendix I. Part I, Volumes I and II were submitted on June 4, 1976.
The 10CFR50 Appendix I evaluation of the existing plant design was done utilizing the models of U.S. NRC Regulatory Guides 1.109, 1.111, 1.112 and 1.113 as issued in March 1976. The results indicate that the plant design is such that the offsite doses are within the design objectives of 10CFR50 Appendix I, Section II, items A, B and C. In addition compliance with the cost-benefit part,Section II, D, has been demonstrated using the criteria set forth in the Concluding Statement of Position of the Regulatory Staff in Docket RM-50-2 as recommended in your letter dated February 19, 1976, and in meetings with the Staff at King of Prussia on April 8, 1976.
A revised version of Table 2-1 from Part I, Volume I is attached. This up-dates the grazing animal census and corrects some of the distances.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY D. C. Switzer President 11116
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HADDAM NECK STATION DOCKET NO. 50-213 DEMONSTRATION OF COMPLIANCE WITH !
10CFRSO, APPENDIX I PART 2 l
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CONNECTICUT YANKEE ATOMIC POWER COMPANY P.O. BOX 270 HARFORD, CT 06101
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COMPLIANCE WITH 10CFR50 APPENDIX I Table of Contents Section Title- Page FOREWORD Section 1 - Responses to Enclosure 1 of February 19, 1976, NRC-Letter 1 1.1 (bmpliance with '10CFR50 Appendix I, Section II 1.1-1
. Enclosure 1, Item-1 1.1-1 j 1.1.1 Compliance with Section II.A, II.B, and i II.C 1.1-1 l i
1.1.2 Compliance with Section II.D 1.1-3 1.2 Radioactive Source Terms. 1.2 Enclosure 1, Item 2 1.2-1 1.2.1 Coolant Activities 1.2-1 1.2.2 Gaseous Releases 1.2-4 I Primary Auxiliary Building 1.2-4 Containment Purges 1.2 Turbine Building 1.2-7 Main Condenser Air Ejector 1.2-7 i Process Gas 1.2-7 )
Main Filter Bank 1.2-8 1.2.3 Liquid Releases 1.2-9 1.2.3.1 Steam Generator Blowdown 1.2-9 1.2.3.2 Aerated Wastes 1.2-10 i 1.2.3.3 Hydrogenated Wastes 1.2-10 !
1.2.3.4 Turbine Building Drains 1.2-11 l
1.2.3.5 Liquid Radioactive Effluents 1.2-11 ;
l 1.3 Meteorology / Hydrology 1.3-1 !
l Enclosure 1, Item 3 1.3-1 1.3.1 Meteorology 1.3-1 1.3.2 Hydrology 1.3-1 !
1.3.2.1 Quantitative Water Use Diagrams 1.3-1 4 1.3.2.2- Consumptive Plant Water Use 1.3-2 :
1.3.2.3 Location and Nature of Water Use 1.3-2' ;
1.3.2.4 Description of Discharge Structure .1.3-2 I Liquid Discharge Structure 1.3-2 i State and Incal Restrictions .1.3-3 1.3.2.5 Description of Ambient Flow in the .
-i Connecticut River 1.3-3 l 1.3.2.6 Liquid Radionuclides Releases 1.3-3 1.3.2.7 Radionuclides 7 Concentrations >and ;
.TraveleTimes 1.3-4 1 1.3.2.8 Sorption of Radionuclides by i Sediments 1.3-4 .I l
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Table of Contents (Cont 'd)
Section Title Page l- 1.3.2.9 Potential Radionuclides Pathway via i Groundwater 1.3-4 1.4 Dose Calculations 1.4-1 Enclosure 1, Item 4 1.4-1 1.4.1 Description of Models and Assumptions Used in Individual Dose Calculations 1.4-1 1.4.1.1 Liquid Effluents 1.4-1 Ingestion of Fish and Fresh-Water Invertebrates 1.4-1 Swimming and' Boating 1.4-2 Shoreline Recreation 1.4-2 l 1.4.1.2 Gaseous Effluents 1.4-3 1.4.1.2.1 Exposure to Noble Gases 1.4-3 Annual Gamma Air Dose l and Annual Beta Air i Dose 1.4-3 l Annual Dose to Indivi-duals from Noble Gas l Effluents 1.4-4 l 1.4.1.2.2 Inhalation Doses 1.4-5 1.4.1.2.3 Exposure from Contaminated Ground 1.4-6 1.4.1.2.4 Ingestion.ofcMilkc 11.4-7^ l' 1.4.1.2.5 Ingestion of Vegetation'1.4-10 1.5 Effluent Release Data 1.5-1 Enclosure 1, Item 5 1.5-1 Section 2 - Responses to Enclosure 2 of February 19, 1976, NRC L( tter 2.1 Data Needed for Radioactive Source Term Calculations 2.1-1 Enclosure _2, Item 1 2.1-1 2.1.1 General 2.1-1 2.1.2 Primary System 2.1-1
- 2.1.3 Secondary System 2.1-2 l 2.1.4 Liquid Waste Processing Systems 2.1-2 l 2.1.4.1 Sources, flow rates and expected i activities for all inputs to each system 2.1-2 2.1.4.2 Holdup times associated with collection, processing, and discharge of all liquid streams, with a discharge time of 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> for each release point 2.1-3 2.1.4.3 Capacities of all tanks and processing equipment considered in calculating holdup times 2.1-4 2.1.4.4 Decontamination factors for each process step 2.1-5 2.1.4.5 Fraction of each processing stream expected to be discharged over the ii
1 Table of Contents (Cont 'd)
Section Title Page life of the plant 2.1-5 2.1.4.6 The volume of liquid resulting from _;
regeneration of the demineralized 2.1-5 2.1.4.7 Liquid source term by radionuclides in Ci/yr for normal operation including anticipated operational' occurances 2.1-6 I
2.1.4.8 The liquid waste discharged 2.1-6 2.1.5 Gaseous Waste Processing Systems 2.1-6 1 2.1.6 Ventilation and Exhaust Systems 2.1-7 2.2 Radiological Pathway Analyses Parameters 2.2-1 j Enclosure 2, Item 2 2.2-1 l 2.3 Normalized Concentration (X/Q) and Deposition (D/Q)
Values 2.3-1 Enclosure 2, Item 3 2.3-1 1 2.3.1 Summary 2.3-1 l 2.3.2 Meteorological Data 2.3-2 2.3.3 Plant Design Parameters 2.3-2 2.4 Atmospheric Transport and Dispersion Models 2.4-1 1 Enclosure 2, Item 4 2.4-1 2.4.1 Nomenclature 2.4-1 1 2.4.2 X/Q Value Methodology 2.4-2 l 2.4.3 (X/Q) and D/Q Value Methodology 2.4-4 2.4.4 Methodology Employed for Intermittent Releases 2.4-4 "
2.5 Onsite Meteorological Data Conforming to Regulatory Guide 1.23 2.5-1 q Enclosure 2, Item 5 2.5.1 Onsite Meteorological Monitoring Program Specifications 2.5-1 2.5.1.1 Meteorological Measurements 2.5-1 2.5.1.2 Meteorological Instruments 2.5-1 2.5.1.3 Digital Recording System 2.5-2 2.5.1.4 Analog Recording System 2.5-3 2.5.1.5 Instrument Calibration Methods 2.5 -3 2.5.1.6 System Maintenance and Quality Assurance Procedures 2.5-4 2.5.1.7 Data Analysis Procedures 2.5-5 2.5.2 Joint Frequency Distributions 2.5-5 2.5.3 Representativeness of Data 2.5-5 2.6 Onsite Meteorological Data not Conforming to Regulatory Guide 1.23 2.6 Enclosure 2, Item 6 2.6-1 2.7 Description of Airtlow Trajectory Regimes 2.7-1 Enclosure 2, Item 7 2.7-1 2.8 'Ibpographical Information 2.8-1 Enclosure 2, Item 8 2.8-1 2.9 Dates and Times of Intermittent Radioactivity '
Releases 2.9-1 Enclosure 2, Item 9 2.9-1 iii L_____--__ . _ _ .___ __
COMPLIANCE WITH 10CFR50 APPENDIX I List of Tables gble Title 1.1.1-1 Comparison of Calculated Annual Doses with Appendix I Design Objectives 1.1.1-2 Maxirmim Annual Doses from Noble Gas Effluents 1.1.1-3 Annual Doses to Maximum Individual in Adult Age :
Group from Radioiodine and Particulate Gaseous Effluents (Residence and Vegetable Garden) 1.1.1-4 Annual Doses to Maximum Individual in Teen Age Group from Radioiodine and Particulate Gaseous Effluents (Residence and Vegetable Garden) 1.1.1-5 Annual Doses to Maximum Individual in Child Age Group from Radioiodine and Particulate Gaseous !
Effluents (Residence and Vegetable Garden) ;
1.1.1-6 Annual Doses to Maximum Individual in Infant Age 1 Group from Radioiodine and Particulate Gaseous l Effluents (Residence and Vegetable Garden) i 1.1.1-7 Annual Thyroid Doses to Maximum Individual in All Age Groups from Radioiodine and Particulate Gaseous Effluents Cow Location - 3,540 Meters ESE l 1.1.1-8 Annual Thyroid Doses to Maximum Individual in All Age Groups from Radioiodine and Particulate Gaseous Ef fluents Goat Location - 2,410 Meters SW I 1.1.1-9 Annual Doses to Maximum Individual in Adult Age ,
Group from Radioiodine and Particulate Gaseous Releases (Land) 1.1.1-10 Annual Doses to Maximum Individual in Teen Age Group from Radioiodine and Particulate Gaseous Releases i (Land) 1.1.1-11 Annual Doses to Maximum Individual in Child Age Group from Radioiodine and Particulate Gaseous Releases (Land) 1.1.1-12 Annual Doses to Maximum Individual in Infant Age Group from Radioiodine and Particulate Gaseous Releases (Land) 1.1.1-13 Annual Doses to Maximum Individual in Adult Age Group from Radioiodine and Particulate Gaseous Effluents Excluding a* Carbon (Residence and Vegetable Garden) 1.1.1-14 Annual Doses to Maximum Individual in Teen Age Group from Radioiodine and Particulate Gaseous Effluents Excluding ** Carbon (Residence and Vegetable Garden) 1.1.1-15 Annual Doses to Maximum Individual in Child Age Group from Radiciodine and Particulate Gaseous Effluents Excluding :* Carbon (Residence and Vegetable Garden) 1.1.1-16 Annual Doses to Maximum Individual in Infant Age Group frca Radiciodine and Particulate Gaseous Effluents Excluding ** Carbon (Residence and Vegetable Garden) iv
List of Tables (Cont'd)
Table Title 1.1.1-17 Annual Thyroid Doses to Maximum Individual in All Age. Groups from Radioiodine and Particulate Gaseous Effluents Cow Location Excluding *
- Carbon 1.1.1-18 Annual Thyroid Doses to Maximum Individual in All Age Groups from Radioiodine and Particulate Gaseous Effluents Goat Location Excluding ** Carbon 1.1.1-19 Annual Doses to Maximum Individual in Adult Age Group from Radioiodine and Particulate Gaseous Effluents Excluding 1* Carbon (Land) 1.1.1-20 Annual Doses to Maximum Individual.in Teen Age Group from Radioiodine and Particulate Gaseous Effluents Excluding 1* Carbon (Land) 1.1.1-21 Annual Doses to Maximum Individual in Child Age Group from Radioiodine and Particulate Gaseous Effluents Excluding 1* Carbon (Land) 1.1.1-22 Annual Doses to Maximum Individual in Infant Age Group from Radioiodine and Particulate Gaseous Effluents Excluding ** Carbon (Land) 1.1.1-23 Annual Doses to Maximum Individual in Adult Age Group from Liquid Effluents under Equilibrium Conditions 1.1.1-24 Annual Doses to Maximum Individual in Teen Age Group from Liquid Effluents under Equilibrium Conditions 1.1.1-25 Annual Doses to Maximum Individual in Child Age Group from Liquid Effluents under Equilibrium Conditions 1.1.2-1 Comparison of Calculated Doses from Haddam Neck Station Operation with Guides on Design Objectives Proposed by the Staff on February 20, 1974 1.2.1-1 Parameters Used to Describe the Haddam Neck Station Power Plant 1.2.1-2 Values Used in Determining Adjustment Factors for Pressurized Water Reactors 1.2.1-3 Adjustment Factors for Pressurized Water Reactors with U-Tube Steam Generators 1.2.1-4 Radionuclides Concentrations in Reactor Coolant and Secondary Liquid and Steam 1.2.2-1 Releases Via Primary Vent Stack and Turbine Building Roof Vent 1.2.3-1 Total Liquid Releases 1.3.2-1 Concentration of Sediment Radionuclides in the Discharge Canal 1.4.1-1 Swimming and Boating Dose Conversion Factors V
List of Tables (Cont'd)
I Table Title 1.4.1-2 X/Q Values for Noble Gas Doses at 710 Meters NE 1.4.1-3 X/Q and D/Q Values for Inhalation and Contaminated Ground at 630 Meters North 1.4.1-4 X/Q and D/Q Values for Ingestion of Cow's Milk at 3,540 Meters ESE j 1.4.1-5 X/Q and D/Q Values for Ingestion of Goat's Milk at 2,410 Meters SW 1.4.1-6 X/Q and D/Q Values for Ingestion of Vegetation at Residence, 630 Meters NNW 2.1.4-1 Calculated Annual Release of Radioactive Materials in Untreated Detergent Waste from a PWR 2.3-1 Annual Average X/Q Values ( x 106 sec/m3) for the Primary Vent Stack Release 2.3-2 Grazing Season X/Q Values ( x 106 sec/m a ) for the Primary Vent Stack Release 2.3-3 Annual Average D/Q Values ( x 10* m-2) for the Primary Vent Stack Release 2.3-4 Grazing Season D/Q Values ( x 108 m-2) for the Primary Vent Stack Release 2.3-5 Annual Average X/Q Values ( x 106 sec/m3) for the Containment Purge -
2.3-6 Grazing Season X/Q Values ( x 106 sec/m3) for the i Containment Purge 2.3-7 Annual Average D/Q Values ( x 108 m-2) for the Con-tairnent Purge '
2.3-8 Grazing Season D/Q Values ( x 10e m-2) for the Con- '
tainment Purge 2.3-9 Arulual Average X/Q Values (x 106 sec/m a) for the Process Gas Intermittent Release 2.3-10 Grazing Season X/Q Values (x 106 sec/m a) for the Process Gas Intermittent Release 2.3-11 Annual Average D/Q Values ( x 108 m-2) for the Process !
Gas Intermittent Release 2.3-12 Grazing Season D/Q Values ( x 10s m-2 ) for the Process Gas Intermittent Release ,
2.3-13 Annual Average X/Q Values ( x 106 sec/m a) for the i Turbine Building Vents Release 2.3-14 Grazing Season X/Q Values ( x 106 sec/m3) "for the Turbine Building Vents Release 2.3-15 Annual Average D/Q Values ( x 10e m-2) for the Turbine Building Vents Release 2.3-16 Grazing Season D/Q Values ( x 10s m-2) for the Turbine Building Vents Release 2.3-17 Plant Parameters Pertinent to Meteorological Calculations 2.5-1 Percentage Frequency Distribution of Pasquill. Stability Class for Haddam Neck, Concurrent Windsor Locks, and ;
Long-Term Windsor Locks Data Vi
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List of Tables (Cont ' d)
Table Titl_e 2.5-2 Percentage Frequency Distribution of Wind Direction by Quadrant for Haddam Neck, Concurrent Windsor Locks, and Long-Term Windsor Locks Data 2.5-3 Percentage Frequency Distribution of Wind Speed by Quadrant for 'Haddam Neck, Concurrent Windsor Locks, and Long-Term Windsor Locks Data 2.5-4 Meteorological Tower Instrumentation 2.5-5 Bradley Fld. Wind - Stability Summary, Stability class A, 1/1/49 to 12/31/75 (Annual) 2.5-6 Bradley Fld. Wind - Stability Summary, Stability Class B, 1/1/49 to 12/31/75 (Annual) 2.5-7 Bradley F1d. Wind - Stability Summary, Stability Class C, 1/1/49 to 12/31/75 (Annual) 2.5-8 Bradley Fld. Wind - Stability Summary, Stability Class D, 1/1/49 to 12/31/75 (Annual) 2.5-9 Bradley Fld. Wind - Stability Summary, Stability Class B, 1/1/49 to 12/31/75 (Annual) 2.5-10 Bradley Fld. Wind - Stability Summary, Stability Class F, 1/1/09 to 12/31/75 (Annual) 2.5-11 Bradley Fld. Wind - Stability Summary, Stability Class G, 1/1/49 to 12/31/75 (Annual) 2.5-12 Bradley F1d. Wind - Stability Summary, Stability All Class, 1/1/49 to 12/31/75 (Annual) 2.5-13 Bradley Fld. Wind - Stability Summary, Sta'oility Class A, 1/1/75 to 12/31/75 (Annual) ,
2.5-14 Bradley Fld. Wind - Stability Summary, Stability Class B, 1/1/75 to 12/31/75 (Annual) 2.5-15 Bradley Fld. Wind - Stability Summary, Stability Class C, 1/1/75 to 12/31/75 (Annual) 2.5-16 Bradley Fld. Wind - Stability Summary Stability Class D, 1/1/49 to 12/31/75 (Annual) 2.5-17 Bradley Fld. Wind - Stability Summary, Stability Class E, 1/1/75 to 12/31/75 (Annual) 2.5-18 Bradley Fld. Wind - Stability Summary, Stability Class F, 1/1/75 to 12/31/75 (Annual) 2.5-19 Bradley Fld. Wind - Stability Summary, Stability i Class G, 1/1/75 to 12/31/75 (Annual) 2.5-20 Bradley Fld. Wind - Stability Summary, Stability All Class, 1/1/49 to 12/31/75 (Annual)
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I LVi4PLIANCE WITH 10CFR50 APPENDIX I
~
List of Piqures t
Piqure Title ]
l 1.2.2-1 Gaseous Radwaste System - Simplified Flow Diagram j 1.2.3-1 Liquid Radwaste System - Simplified Flow Diagram la 1.2.3-2 Liquid Releases - Simplified Calculational Model 1.3.2-1 Schematic of Water Flow j 1.3.2-2 Location of Intake Structure and Discharge Canal j 2.1-1 Operating Flow Diagram - Liquid Waste System {
2.1-2 Operating Flow Diagram - Gaseous Waste System (
2.1-3 Operating Flow Diagram - Ventilation ]:
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1.1 Compliance with 10CFR50 Appendix I, Section II Enclosure 1, Item 1 Licensee's should provide an evaluation showing their facility's capability to meet the requirements set forth in Section II of Appendix 1 to 10CFR Part 50.
Response
'Ihis section summarizes the evaluation of the Haddam Neck Station capability to meet the requirements set forth in Section II of Appendix I to 10CFR50 (Reference 1) . The first part of this summary (Section 1.1.1) deals with the demonstration of compliance with the requirements set forth in Sections II.A, II.B, and II.C. The second part (Section 1.1.2) addressesSection II.D of Appendix I.
1.1.1 Compliance With Section II.A, II.B, and II.C Table 1.1.1-1 presents a comparison of the calculated annual doses with the design objectives contained in 10CFR50 Apper: dix I.
The calculated doses are shown to be within the design objectives. The calcualtional methods, models, and assumptions are in accordance with current NRC accepted procedures, as discussed in the remaining sections of this report.
In relation to Table 1.1.1-1, it should be pointed out that two calculated annual organ doses are reported for the gaseous release of iodines and particulate. The first is for the m*ximum calculated individual organ dose from iodines and particulate, which is 14.0 mrem for the bone of an adult individual located at the residence and vegetable garden with the highest deposition, 630 meters NNW, including consumption of vegetables grown at that location. The second maximum calculated annual organ dose included in this summary table is the adult bone dose of 0.91 mrem at the same loca tion with a revised analysis of the * *C contribution, as discussed below.
An extremely large fraction of the 14 mrem calculated adult bone dose is associated with the inclusion of **C in the iodine and j particulate grouping of Regulatory Guide 1.109. The method of l calculating the concentration of a*C in vegetation results in an over estimate of the dose via this pathway. The Regulatory Guide 1.109 model uses an annual release rate assuming the interchange between 2*C in the air and the vegetation occurs continuously. In reality, however, all **C releases from the Haddam Neck Station are intermittent, 167 hr/yr from the process gro and 192 hr/yr from the containment purge with the only uptake of 1*C into the vegetation occurring during the release periods. For this reason, the 84C equilibrium concentration in vegetation should be reduced by the ratio of the 1.1-1 J
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specific release period to the annual daylight period, i approximately 4400 hours0.0509 days <br />1.222 hours <br />0.00728 weeks <br />0.00167 months <br />. This results in the maximum individual dose of 14 mrem to the bone of an adult being reduced to approximately 0.91 mrem /yr. If C-14 is excluded this dose is 0.19 mrem / year. '
The summary presented in Table 1.1.1-1 is prepared from the more detailed data reported in Tables 1.1.1-2 through 1.1.1-25.
Table 1.1.1-2 describes the locations at which the annual doses trom noble gas effluents are calculated.
Table 1.1.1-3 through 1.1.1-6 presents calculated annual doses i for the adult, teen, child, and infant age groups associated with !
the release of radioiodines and particulate in gaseous j ef fluents. (Note: All of these data include * *C, *1Ar, and 3H). 1 Data are presented for the total body and the skin, bone, liver, i thyroid, kidney, lung, and gastrointestinal tract of individuals {
in each of the above age groups located at the residence and l vegetable garden with the highest deposition, 630 meters in the !
NNW sector. Dose contributions from inhalation, deposition on l ground, ingestion of fresh vegetables and ingestion of stored j vegetables are included in their dose assessments. l 1
The annual thyroid dose, for individuals in each of the four age )
groups, is presented in Table 1.1.1-7 for the milk cow location with the highest D/Q, 3,540 meters in the ESE sector. Similar j data is presented in Table 1.1.1-8 for the goat location with the '
highest D/Q, 2,410 meters in the SW sector.
I In addition to the above data, annual doses calculated for the land location with the highest value of D/Q, at 630 meters in the north sector, are presented in Tables 1.1.1-9 through 1.1.1-12. j A complete set of comparable data to that presented in Tables 1.1.1-3 through 1.1.1-12 is presented in Tables 1.1.1-13 through 1.1.1-22 for the iodine and particulate releases, excluding **C.
When the * *C is not included in the analysis, considerably lower dose rates are calculated.
The maximum calculated annual doses to individuals in the adult, teen, and child age groups resulting from liquid effluents are reported in Tables 1.1.1-23 through 1.1.1-25. The calculated dase is reported for the total body and various organs of individuals in these age groups. The following pathways are considered: ingestion of fish, ingestion of aquatic invertebrates, swimming, boating, and shoreline recreation. All of these pathways are conservatively assumed to involve only the dilution of' the liquid releases in the discharge canal.
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l'.1. 2 Compliance With.Section II.D l
In lieu of perfonaing the. cost-benefit analysis described in' 3 Section II.D of 10CFR50, Appendix I, the licensee has. chosen.'to demonstrate compliance. with the. September 4, 1975 Ammendment to Appendix I. Table ~1.1.2-1 demonstrates compliance. with the design objectives set forth' in the. concluding -statement of' position of the regulatory.-staff (Docket RM-50-2) , which 'is reproduced as an annex to Appendix I as amended September 4, 1975.
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TABLE 1.1.1-1 COMPARISON OF CALCULATED ANNUAL DOSES WITH APPENDIX I DESIGN OBJECTIVES i
HADDAM NECK STATION CONNECTICUT YANKEE ATOMIC POWER COMPANY APPENDIX I
. MAXIMUM CRITERION DESIGN OBJECTIVE CALCULATED DOSE Ganuna Air Dose 10 mrad /yr 1.4 mrad /yr(*)
Beta Air Dose 20 mrad /yr 2.3 mrad /yr(s)
Noble Gas 'Ibtal Body 5 mrem /yr 0.89 mrem /yr(1)
Noble Gas - Skin 15 mrem /yr 1.9 mrem /yr( )
Iodines and Part. 15 mrenVyr 14.0 mrem /yr(2)
Any Organ 0.91 mrem /yrC3)
Liquid Effluents
'Ibtal Body 3 mrem /yr 2.4 mrem /yrC * )
Any Organ 10 mrem /yr 3.8 mrem /yrC5)
(
(1) Site boundary 4710 meters Northeast (See Table 1.1.1-2) . '{ <
i cm) Adult bone dose for residence and vegetable garden at l 630 meters NNW, using Draft Regulatory Guide 1.109 model l for inclusion of **C in iodine and particulate category. I (See Table 1.1.1-3) .
(*>Same conditions as note (2) with revised model of **C uptake as discussed in Section 1.1.1.
(*) Adult individual (See Table 1.1.1-23) .
(5) Adult liver dose is maximum calculated organ dose from liquid effluents. (See Table 1.1.1-23) .
1 of 1
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l l TABLE 1.1.1-7 ANNUAL THYROID DOSES TO MAXI 14UM INDIVIDUAL IN ALL AGE GROUPS i FROM RADIOIODINE AND PARTICULATE GASEOUS EFFLUhhTS COW IhCATION WITH llIGHEST D/O - 3540 METERS ESE i
HADIRM NECK STATION l CONNECTION YANKEE ATOMIC K)WER COMPANY ]
PATHWAY ANNUAL THYROID DOSE mrem /yr)
ADULT TEEN CHILD INFANT i I
Inhalation 1.0x10-2 8.0x10 3 1.1x10-2 1.6x10-2 i l
Deposition 1.1x10-2 1.1x10-2 1.1x10-2 1.1x10-2 'l on Ground {
1 Leafy Vec,etables 4.8x10-2 4.1x10-2 7.6x10-2 -
l I
Stored Vegetables 3.7x10-2 5.9x10-3 1.5x1oo -
q Cow's Milk 1.3x10-1 2.4x10-1 5.7x10-8 1.2x100 i
j Total of 5.7x10-1 8.9x10-8 2.2x100 1.2x100 l Above Pathways ]
l Note: See Section 1.1.1 for the relative contribution of
- Carbon to the maximum individual dose.
A dash (-) indicates not applicable.
1 1 of 1
TABLE 1.1.'1-8 ANNUAL THYROID DOSES TO MAXIMUM INDIVIDUAL IN ALL AGE GROUPS FROM RADIOIODINE AND PARTICULATE GASEOUS EFFLUENTS GOAT LOCATION WITil HIGHEST D/O -' 2410 METERS SW l IIADDAM NECK STATION-CONNECTIQJT YANKEE ATOMIC POWER COMPANY
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PATHWAY' ANNUAL THYROID DOSE (mrem /yr)
ADULT TEEN-:
CHILD INFANT Inhalation 4.7x10-3 3.7x10-3 5.2x10-3 7.5x10-3 Deposition on Ground 3.2x10-3 3.2x10-3 3.2x10-3 3. 2x 10'-3 Leafy Vegetables 2.8x10-2 2.5x10-2 4.4x10-2 -
Stored Vegetables 2.2x10-8 3.6x10-8 8.7x10-1 -
Goat's Milk 8.3x10-2 1.4x10-s 3.4x10-8 7.2x10-2 t
i Total of Above Pathways 3.4x10-8 5.3x10-8 1.3x100 7.3x10-8 Note: See Section 1.1.1 for the relative contribution of-
- Carbon to the maximum- individual dose.
l A dash (-) indicates not applicable.
1 1 of 1
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P R US E OT T RN_
GE E
M m 1 2 2 1 U d - - - - -
EL T 0 i 0 0 0 0 0 GF h 3 o 1 1 1 1 1 AF A 6 r y
x8 x 2x x4 x E P 0 4 N M T h ES O A T 2 1 3 6 2 EU C TO M E R O NS E T IA NW T a 1 a a 1 G4 OO I - - - - -
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1 VU*
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- 8 3 a 8 L MPD *. K T S - - - - -
B U U AN H O 0 0 0 0 0 A MDL DA D 1 1 1 1 1 T INC XAX DY A
E e x x2 x 4x x A E HT M Ln e.
9 1 i Ao ME U UB 6 1 7 7 2 N C f r
T OI I T N' TD T I A O C W SI E EO N N 1 8 SI N E - -
OD O D 0 0 DA C R 1 1 R A n - x - - x L G i 4 4 AM k UO E S 1 1 NR L NF B A A T
E G y E d .
V o 2 1 3
- 1 e
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t a x6 x 2x x6 1 5 x c
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E a D y I a t S n d w o
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_ t o s a s a r s e P e
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i i e v f t t V o )
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t 0 E H T T A o 1 E U b 1 1 1 -
M N C H I I T O D T I T O C W _
I E S O N N 1 1 -
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G i - 4 4
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x x2 - - x l p
7 4 E a p _
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n l b e i I n b a v d -
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=
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1
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s TABLE 1.1.1-17 .
1 ANNUAL THYROID DOSES 'IO MAXIMUM INDIVIDUAL IN ALL' AGE GROUPS FROM RAD 1010 DINE AND PARTICULATE GASEOUS' EFFLUENTS I COW LOCATION _WITH llIGliEST D/0 - 3540 METERS ESE !
EXCLUDING 8* CARBON ;!
HADDAM NECK STATION CONNECTION YANKEE ATOMIC POWER COMFAt.'Y PATHWAY AI!NUAL THYROID DOSE mrem /yr)
AIXJLT TEEN CHILD INFANT j J
Inhalation 5 '. 0x 10-3 3.3x10 3 3.9x10-3 . 5.5x10-3 1 Deposition 1.1x10-2 1.1x10-2 1.1x10-2 1.1x10-2 l on Ground u!
'I Leafy Vegetables 4.0x10-3 2.8x10-3 4.1x10-3 -
1 l
Stored Vegetables 9.2x10-a 8.8x10 3 -1.4x10-2 -
q Cow's Milk 8.4x10-3 1.1x10-* 2.0x10-2 4.4x10-2 1
Total of 3.8x10-2 3.7x10-2 .5.3x10-2 6.0x10-2 Above Pathways .j i
1 A dash (-) indicates not applicable. s i
l i
l l ,
.1 i
i .
1 of 1 'I l
1
\
TAfsLE - 1.1.1-18 !
ANNUAL THYROID DOSES'TO MAXIMUM I11DIVIDUAL IN ALL AGE GROUPS ,
FROM RADIOIODINE AtJD-PARTICULATE GASEOUS EFFLUENTS 1 GOAT LOCATION WJTH HIGilEST D/O - 2414 IETERS SW $
EXCLUDING
- CARBON HADDAM NfjCK STATION . ;
CONNECTICUT YANKEE ATOt41C POWER COMPANY j PATHWAY ANNUAL THYROID DOSE - (mrem /yr) l d
ADULT TEEN CHILD INFANT I l
Inhalation 2.1x10-3 1.3x10-3. - 1.5x10 3 1 '. 9x 10 -3 ..
1 Deposition on Ground 3.2x10-3 3.2x10-3 3.2x10-3' 3.2x10 ia
'1 Leafy Vegetables 1.3x10-3 8.6x10-* 1 '. 2x10 -a - -
]
1 Stored Vegetables 5.3x10-3 5.1x10-3 8.2x10-3 -
j Goat's Milk 4.6x10-3 S.4x10-3 9.3x10-3 :1.8x10-2
-i Total of Above Pathways 1.6x10-2 1.6x10-2 2.3x10-m '2.3x10-2 i
'i A dash (-) indicates not applicable.
i i
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1! ; II ll ! i IiI!i, w
-1 TABLE 1.1.2-1 COMPARISCN OF CALCUIATED DOSES FROM HADDAM NECK . i STATION OPERATION WITH GUIDES ON DESIGN OBJECPIVES PROPOSED BY THE STAFF ON FEBRUARY 20, 1974 I
Maximum.
RM-50-2 Calculated .
Criterion Design Ob-jectives Values Liquid Effluents .j Dose to total body or 3 any organ from all l pathways 5 mrem /yr 3.8 mrem /yr(*) ')
Noble Gas Effluents Gamma dose in air 10 mrad /yr 1.4 mrad /yr(2).
-Beta dose in air 20 mrad /yr 2.3 mrad /yrca) j Dose to total body of .
an individual 5 mrem /yr 0.89 mrem /yr(2) !
Dose to skin of an 1 individual 15 mrem /yr 1.9 mrem /yr(2) )
l Radioiodine and Particulate Dose to any organ from 15 mrem /yr 14 0 mrem /yr(s) all pathways (3) 0. 91 mrem /yr (6 )
i Liquid release per unit ( *) 5 Ci/yr 2.5 Ci/yr l 1
Gaseous I-131 release I per unit 1 Ci/yr .00060 Ci/yr
( 5 ) Adult liver dose is largest organ dose, . total body dose is :
2.4 mrem /yr (see Table 1.1.1-23) . ;
(2)See Table 1.1.1-2.
ca) Carbon-14, Argon-41 and Tritium have been added to this category.
( * ) Exclusive of Trititmt.
(5) Adult bone dose (see Table 1.1.1-3) .
( 8 ) Same as (5) above with revised C-14 model. If C-14 is excluded the dose is 0.19 mrem /yr.
1 of 1 J
.m _m__ -.___ _.__ _ _ _-_____m_ . _ . - _ - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ . _ __ _ . _ . _ . _ . . _ . _ __ . . _ _ _ . .._..__.______m.____.____.__m.m__.____.
1.2 Radioactive Source Terms , Item 2 Radioactive Source Terms used in the evaluation should be con-sistent with the parameters and methodology set forth in Draft Regulatory Guides 1.BB or 1.CC (as appropriate) . Note: For BWR's, gaseous releases from the containment building and auxiliary building should be combined to form reactor building release for pre-BWR/6 Mark III Containment designs.
Response
This section discusses radioactive effluent releases which are calculated using the basic approach and assumptions contained in Regulatory Guide 1.112 (Reference 1) which references NUREG-0017 (April 1976) (Reference 2) and replaces Draft Regulatory Guide 1.BB. These analyses conform to the methodology of NUREG-0017.
Values of parameters are based on NUREG-0017 data, Haddam Neck Station design data, or Haddam Neck Station operating data.
Section 2.1 lists additional source term data requested in Appendix B to Regulatory Guide 1.112.
Coolant source terms are based on both actual operating experience at Haddam Neck Station and NUREG-0017. Since no pure beta emitting nuclides are measured using the counting techniques available at the Haddam Neck Station, the coolant concentrations for these nuclides are based on NUREG-0017. All other coolant l source terms are based on actual operating experience at Haddam Neck Station with stainless steel clad fuel in lieu of the NUREG-0017 coolant source terms which are based on zircaloy clad fuel. i Additional data are provided, relative to radioactive source terms, in the response to Request 2.1 (i.e., the information requested in Appendix B to Regulatory Guide 1.112) .
1.2.1 Coolant Activities Most of the primary coolant concentrations are measured values based on the sixteen quarters of operating data as recorded between 1972 and 1976. Measured values are reported since the Haddam Neck Station 304 stainless steel clad fuel has considerably less cladding defects than the 0.12 percent weighted average fuel defects reported for PWR's with zircaloy clad fuel (Page 2-18 of NUREG-0017). These measured values do not account for the pure beta emitters, which include Br-85, Fe-55, Sr-89, Sr-90, Ru-106 and Pr-143. Therefore, the primary and secondary coolant activities of the pure beta emitters are determined in accordance with NUREG-0017. The adjustment factors and parameters used are discussed in Tables 1.2.1-2 and 1.2.1-3.
The secondary system activities calculated for the measured primary system nuclides are a function of the plant dependent parameters given in Table 1.2.1-1, the values used to determine 1.2-1
i i
)
the adjustment f actor for pressurized water reactors listed in Table 1.2.1-2 and the following equations accounting for the buildup and decay of an isotope in a control volume.
For a holdup tank with bleed flow (blowdown and/or condensate ,
demineralizers), l R = N, x 0, where:
l 1
R = net intlow of isotopes into control volume (atoms /sec) ; I N,= concentration of iostope in inlet stream (atoms /gm) ;
and Q= inlet flow (gm/sec) [100 lbs/ day].
The effective constant for the rate of removal of the isotope is' A', and may be detined as:
f i
A' = A + Qb v j where:
l A = decay constant of any isotope (sec-1) ; J t
Qb = bleed flow (gm/sec) , for steam generator blowdown .
and main steam cleanup flow; and
)
V = volume of steam generator liquid (gm) .
Only the first order isotope was considered as there were no parent-daughter relationships associated
)
with the primary j coolant, and no additional isotopes were to be generated for the secondary system concentrations. The first order equation is
{
given as follows: ji d_ll = Ri - A N i '
dt Following integration and substitution, the concentration of an !
isotope contained in the steam generator liquid can be calculated as shown below:
0; =A, Aj Rj
, y [1 - e-Ab) or:
0; = j_ Ai )[ gs Q )( 3_,-( Aj + h;
,, 3 A+Qi _b V where: V 1.2-2 I m--m.-_----
Ci = concentration of isotope i in the steam generator liquid (UCi/gm).
1 The concentration of the isotope in steam (excluding noble gas) is a function of the ratio of concentration in steam to that in water as listed in Table 1.2.1-2.
The tritium concentrations for the primary and secondary systems .
will not be calculated since the liquid and gaseous releases of l tritium are average measured values from the Haddam Neck Station (Response to Enclosure 1, Item 5) .
l The radionuclides concentrations in the rea ctor coolant and j secondary liquid and steam are listed in Table 1.2.1-4. j l
I 1.2-3 l
L-__ _ ____
1 1.2.2 Gaseous Releases The primary vent stack is one of two release points for the gaseous effluents releasing the containment purge activity, primary auxiliary building (PAB) leakages, the main condenser air ejector releases, and the waste gas processing system activity.
The turbine building roof vent provides the release point for the turbine building leakage. The methodology for determining the releases is given in NUREG-0017. The individual release point descriptions are given below with the releases for the primary J vent stack and turbine building listed in Table 1.2.2-1. A simplified flow diagram is shown in Figure 1.2.2-1. A more ;
detailed listing of the parameters is given in Section 2.1.
This section also provides information for each building housing systems that contain radioactive materials, the main condenser air ejector, and the waste gas processing system as follows: )
A. Ventilation system flow rates and provisions incorporated to reduce radioactivity releases through the ventilation or exhaust system.
B. Decontamination factors assumed and the bases (include charcoal adsorbers and HEPA filters) .
C. Release rates for radioiodine, noble gases, and radioactive particulate (Ci/yr), and the bases.
D. For the containment building, the building free volume (fta) and a description of the internal cleanup systems including the recirculation rate and the expected venting frequencies and duration of purges.
E. Nuclides not included in the primary coolant inventory are excluded from the gaseous effluent releases (including nuclides given as averaged plant releases in NUREG-0017) .
PRIMARY AUXILIARY BUILDING (PAB)
The primary auxiliary building releases are based on an assumed primary coolant leakage rate of 160 lb/ day with an iodine partition factor of 0.0075 as reported on page 2-24 of NUREG-0017. In addition to the noble gases and iodines released from the primary coolant, Table 2-17 on page 2-33 on NUREG-0017 gives a list of the particulate released from the auxiliary building. Only the particulate which occur in the primary coolant or those which are daughters of nuclides in the coolant will be released from the PAB. The normal exhaust ventilation air is released by way of a HEPA filter and charcoal filter to the primary vent stack.
Ventilation for the PAB consists of two supply units, the ventilation and purge system, and the associated supply and 1.2-4 l
exhaust ducting. Flow paths from all supply and exhaust units are interrelated to provide one common ventilation system for the building. The design flow path is from areas of lower contamination to areas of potentially higher contamination. This is accomplished by exhausting each compartment separately.
Design flows are such that the exh1ust capacity exceeds the supply capacity by approximately 10 percent, maintaining a slight infiltration into the building, thereby ensuring contamination is not released to the atmosphere. The system is sized to provide a minimum of 10 air changes per hour to all spaces in the PAB.
Where necessary, the number of changes per hour exceeds 10 in order to limit compartment mean temperature to 1040F, based on an outside air temperature of 880F.
The ventilation and purge system exhausts air and noncondensibles from the primary auxiliary building, waste disposal building, reactor containment (during containment purge operation), and from various vented components connected to the two process line plenums. The system consists of two parallel prefilters, a high efficiency particulate absolute (HEPA) filter, a high efficiency charcoal absolute (HECA) filter, and two parallel ventilation and purge fans rated at 52,000 cfm. The system can be operated to provide simultaneous operation of normal ventilation exhaust and reactor containment purge.
The ventilation and purge system draws exhaust air into process line plena from:
- 1. Air vent header
- 2. Air ejector discharge l 3. Boron recovery system startup vent
- 4. Waste gas blower vent hood
- 5. Waste gas release line
- 6. Sampling hood
- 7. Aerated drain holdup tank
- 8. Steam generator blowoff tank condenser vent
- 9. Containment monitor purge line l
- 10. Waste distillate tank and waste evaporator overhead condenser vents
- 11. Decay gas filter and tanks
- 12. Waste disposal building floor and equipment drain tank vent 1.2-5
- _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._ - - _ _ - - _ _ _ -A
l l
l The discharge from each fan combines in a common exhaust header that leads to the primary vent stack. Entering the combined discharge header are exhaust connections from the following:
- 1. New and spent tuel exhaust fan
- 2. Waste gas degasifier pressure relief line ;
- 3. Waste gas surge tank and waste gas decay tank pressure relief line 1
- 4. Steam generator blowoff tank pressure relief line CONTAINMENT PURGES The containment air recirculation system consists of four 65,000 cfm fan-cooling coil units and associated ductwork and controls. l Those units, located at quarter points in the annulus between the crane wall and the containment wall, provide 50,000 cfm each at 40 psi. All fan-cooler units are normally in operation when the primary system is above 2000F and 300 psig. The filtration system located in the containment is designed to operate following a hypothetical accident only and will not be operated to remove iodine prior to a containment purge.
The purge system is designed to reduce the level of airborne activity in the containment prior to personnel entry. The system includes two 52,000 cfm ventilation fans and a 2,000 cfm iodine removal unit. The shielded iodine removal unit contains an I absolute filter and an activated charcoal filter.
Eventhough the containment air is normally recirculated through charcoal filters prior to purging, no credit is taken for these filters, resulting in a conservative iodine release. The duration of the purges is assumed to be two days as recorded in Table 2-16 of NUREG-0017. Only cold purges are considered since the primary system must be less than 2000F and 300 psig before purging.
The iodine removal unit may be operated, if required, during plant operation to maintain levels in the containment to permit personnel entry. This type of operation also reduces the duration of containment purge following shutdown.
The daily leakage rate of 1 percent of the noble gas inventory and 0.001 percent of the lodine inventory in the primary coolant is used to calculate the inventory in the containment (page 2-23 of NUREG-0017) . The 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of decay of activity in the containment during the shutdown and couldown of the plant is considered, whereas the four cold purges conservatively assume no iodine removal prior to discharge of the act)vity to the primary vent stack through the HEPA and charcoal filters.
1.2-6 1 - - _ _ - _ _ _ _ _ _ _
The particulate releases from the containment purge are taken from Table 2-17 on page 2-33 of NUREG-0017. The C-14 release of 1 Ci/yr, from page 2-48 of NUREG-0017 is expected to be in the form of a volatile gas and no credit is taken for C-14 removed by the filtration system. The Ar-41 and H-3 are also assumed to be released directly to the environment during the containment purge . The H-3 release of 18 C1/yr is an averaged value based on seven years of data from 1969 through 1975 as reported in I Section 1.5, whereas the Ar-41 is taken from page 2-48 of NUREG-0017.
'IURBINE BUILDING (TB) l 1
The turbine building ventilation is provided by a combination !
natural and forced ventilation system. Louvered supply openings j provide natural ventilation air, which is supplemented by fans l providing the forced ventilation air. Continuous roof ventilators on the turbine building roof exhaust all of the !
heated ventilation air.
The activity released from the turbine building roof vent is a ;
result of a 1,700 lb/hr steam leak rate into the turbine building ;
dtniosphere with an lodine partition coefficient of 1.0. There l are no special design features provided for steam line valves l 2-1/2 in. in diameter and larger to reduce leakage. It is assumed that the leakage is in the vapor form and is exhausted directly to the atmosphere (no filtration) .
MAIN CONDENSEP. AIR EJECTOR (MC/AE)
The main condenser air ejector releases are dependent on the primary to secondary leakage of volatile iodines and noble gases.
The iodine leakage is composed of 5 percent volatile and the remainder nonvolatile. Volatile iodines and noble gases leaking into the steam generators are sent directly to the main condenser where the noble gases are ejected and the iodines are affected by a partition factor of 0.15. The effective PF for the iodine leakage is 0.0075 and the noble gas PF is 1.0. All releases are exhausted to the environment by way of the HEPA and charcoal filters and the primary vent stack.
PROCESS GAS
'Ibe waste gas processing system is designed to strip gas from the primary coolant system and provide a storage volume for radio-active and cover gases. The activity accumulated in a waste gas decay tank (WGDT) is a function of the degasification rate of primary coolant using the feed rate for hydrogenated wastes of 2,632 gpd at 35 sec of hydrogen gas per kgm of primary coolant.
The noble gas activity contained in the primary coolant is'also sent to the WGDT's to account for two complete primary coolant degasification cycles each year. The total volume of gas assumed to be released from the gaseous waste system following one year of operation is 50,000 scf (140 scf/ day) per NUREG-0017.
1.2-7
The fill and holdup times are calculated using the equations listed on page 1-16 of NUREG-0017 as a basis, resulting in both !
times equal to 10.1 days, since there are only three tanks. The process gas is discharged at a rate of 5 scfm giving a total time .
of 167 hr/yr for 50,000 cubic feet. In addition to the noble gases, Table 2-17 on page 2-33 of NUREc-0017 lists the particulate activity expected to be released from an operating plant. The C-14 release of 7 Ci/yr is given on page 2-48 of NUREG-0017. It is assumed that most of the carbon-14 will form volatile compounds that are collected in the waste gas processing system.
All releases from the WGDT's are sent through the HEPA and )
chctrcoal filters prior to being exhausted to the environment l through the primary vent stack. The C-14 releases are not !
assumed to be reduced by the filtration system. 1 MAIN FILTER BANK The main filtration system is used to filter all releases except the turbine building. These release points are as follows: j
- 1. Primary Auxiliary Building (PAB) l
- 2. Containment Purges
- 3. Main Condenser Air Ejector
- 4. Process Gas Each system consists of a prefilter, a High Efficiency Particulate Absolute (HEPA) filter, and a High Efficiency Charcoal Absolute (HECA) filter. The efficiencies used for these filters are given on page 2-29 of NUREG-0017 and listed below:
HEPA Filter: DF = 100 for particulate Charcoal Filter: DF = 10 for iodines 1.2-8 l
l
1.2.3 Liquid Releases The liquid radwaste system, shown in Figure 1.2.3--1, is composed of tour substreams; steam generator blowdown, hydrogenerated wastes, aerated wastes, and turbine building drains. Each stream will be discussed in detail in the following sections. Figure 1.2.3-2 depicts all of the liquid radwaste treatment parameters used in the analysis. The liquid effluents are diluted by 2x1011 4 gal /yr of circulating water prior to discharge into the Connecticut River.
The values used in the analysis were obtained from Connecticut Yankee Atomic Power Station based on quantities suggested in NUREG-OO17 (April, 1976). l The pertinent recommendations taken from NUREG-0017 are summarized below:
Plant cdpacity tactor - 0.8 Decay times Collection time:
Volume of Initial Tank x
- Tank Fill Capacity Average input flow rate Process time:
Volume of Initial Tank x
- Tank Fill Capacity Processing Capacity Flow Rate Discharge time: O, for all streams Decontamination factors Detergent evaporators: 100 - all isotopes Radunte ionexchanger: 2-Cs, Rb; 100 - others Second radwaste ionexchanger in series: 10 - all isotopes Polishing demineralized: 10 - all isotopes Radwaste demineralized: 2 - Cs, Rb; 10 - others Boron Recovery evaporator: 100 - I; 1000 - others The treatment assumed for each liquid radwaste stream is I discussed below.
1.2.3.1 Steam Generator Blowdown Steam generator blowdown feeds into a blowoff tank at a rate of 57,600 gpd. There is no time delay between blowdown and discharge of the secondary side liquid activity. Thirty percent of the blowdown liquid, in the form of distillate, returns to the main condenser, while 70 percent of the liquid is directly discharged without treatment. The untreated portion of the liquid wdste stream contains 100 percent of the particulate activity and 95 percent of the iodine activity. Five percent of 1.2-9
the iodine activity returns to the main condenser and is incorporated into the secondary side liquid activity balance.
1.2.3.2 Aerated Wastes The feed rate into the aerated waste stream consists of containment sump wastes, primary auxiliary building drains, laboratory drains, sample drains, decontamination and cask washing wastes and uncontaminated and miscellaneous drains totaling 3,268 gpd. The decontamination and cask washing activities are taken from Table 2-20 of NUREG-0017, (April, 1976). The rest of the source streams contain primary coolant.
Table 2-19 of NUREG-0017 establishes the fractions of primary coolant activity for each stream.
The total waste flow rate of the six individual source streams, as obtained from operating data (1975-1976) at the Haddam Neck Station, is 954,000 gal per yr. The individual values listed in Table 1.2.3.1 are quantities taken from NUREG-0017, Table 2-19, ratioed up to satisfy this known total quantity.
The aerated waste stream teeds into a holdup tank, filling this 99,280 gal tank to 40 percent capacity in 291.6 hr before emptying into two 16,000 gal test tanks at a rate of 20 gal per minute. The 16,000 gal test tanks fill to 80 percent capacity betore discharging the waste stream into the discharge canal.
'Ihe discharge time is assumed to be zero while the processing time is 33.09 hr.
1
- Treatment of this liquid waste stream includes a mixed bed l l ionexchanger, a waste evaporator, and a mixed bed polishing demineralized producing total decontamination factors of 2x103 l for Cs and Rb and 105 for all other isotopes. .
l l l 1.2.3.3 Hydrogenerated Wastes l
The feed rate into the hydrogenerated waste stream consists of boron recovery letdown and valve leakoff and primary drains for a total of 769,000 gal per yr, a value obtained from Haddam Neck Station operating data. The average boron recovery letdown flow
! (shim bleed) of 475,000 gal /yr, Section 3 of the Haddam Neck FES, 1 October 1973, (1,630 gpd) is the major source of hydrogenated wastes while it is assumed that the valve leakoff and primary drains produce un additional 320 gpd. These subsystem flow rates were ratioed up to satisfy the known measured total hydrogenated waste flow rate of 769,000 gal per yr, approximately 2,632 gpd.
Reactor coolant letdown is processed through a mixed bed demineralized before part or the flow is diverted to the volume ,
control tank. The remaining 2,200 gpd combines with 432 gpd of primary drains tank effluent and feeds into two boron waste storage tanks. The storage tanks are filled to 80 percent .l capacity in 682.0 hr before emptying into two 16,000 gal recycle I test tanks at a rate ot 15 gal per minute. That portion of the test tank flow rate due to shim bleed is 12.5 gai per minute.
1.2-10
___- b
The process time for the boron recovery letdown stream is 83.1 J hr.
The decontamination factors used on the stream are based on a Li 3 B03 mixed bed demineralized, a degassifier, a mixed bed ion-exchanger, a boron evaporator, and a mixed bed polishing demineralized. The overall DF is 107 for iodines, 2x10e for Cs and'Rb, and 10' for all other isotopes. !
Valve leakoff and primary drains feed into the primary drains tank at a rate of 432 gpd. This tank is filled to 40 percent capacity in 166.7 hr betore emptying into the boron waste storage tanks. The boron waste storage tanks are intermediate tanks for j this flow path and no credit is taken for them. The process time i for the primary drains tank ef fluent stream is 20.31 hr as it teeds into the recycle test tanks at a rate of 2.5 gal per minute. The discharge time from the test tanks is assumed to be ]
zero.
The decontamination factors used on this stream are aased on a i degassifier, mixed bed ionexchanger, boron evaporator, and a '
mixed bed polishing demineralized. The overall DF is 107 for iodines, 2x107 for Cs and Rb, and 10' for all other isotopes.
1.2.3.4 Turbine Building Drains l
The turbine building drains, consisting of condensed secondary steam activity, is directly discharged without treatment to the discharge canal. The feed rate to the canal is 7,200 gpd as specified in NUREG-0017 (April, 1976) , Table 2-19. l 1.2.3.5 Liquid Radioactive Ef fluents The liquid releases are listed in Table 1.2.3-1, a total of 2.5 Ci/yr of non-tritium activity is calculated to be released.
Tritium releases from yearly averaged operating data at Connecticut Yankee Atomic Power Station are 5761 Ci/yr as l presented in Enclosure 1, Item 5.
1 J
f 1
1 1.2-11
Section 1.2 References
- 1. Draft Regulatory Guide 1.112, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors," USNRC, April, 1976.
- 2. NUREG-0017, " Calculation of Releases of' Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors," USNRC, April, 1976.
1 j
l/ .v i-TABLE:1.2.1-1 l PARAMETERS USED TO DESCRIBE THE HADDAM-NECK STATION NUCLEAR POWER PLANT CONNECTICUT YANKEE' ATOMIC-POWER COMPANY Parameter Unit Value l
Thermal power (P) .MWt 1,825-Steam flow rate (FS) lb/hr. 8.2x106' '
Weight of water in' reactor coolant system . (WP) ' lb 283,000 Weight-of. water in all steam generators 1 (WS) lb- 235,000 Reactor coolant letdown (FD) lb/hr 46,000-Reactor coolant letdown flow (yearly average for boron control) (FB) lb/hr' 765 Steam generator blowdown flow (total) (FBD) lb/hr 15,500 Fraction'of radioactivity in blow-down stream that is not returned See Foot-to the secondary coolant system (NBD) -
note.2 Flow through the purification system cation demineralized (FA) lb/hr N.A.
Ratio of condensate demineralized .
flow rate to total steam flow rate (NC)
'0.0
- Volatile chemistry.
rFive percent of the iodine sent to the flash tank from the steam generator blowdown is assumed to be-entrained in the' flashing.
steam. In this Case, the flash tank is not vented: to the atmo-sphere, thus the flashing' steam and the iodine activity will be returned to the secondary system via c condenser. The remaining-activity,' including 95 percent of.the iodine and 100 percent'of-all other nuclides, is removed'from-the secondary system and sent-to the discharge canal as liquid waste.
1 of 1
4 i
!i TALLL 1.2.1-2 PART OF UUREG-0017 (TABLE 2.o) I J
VALUES USED IN DETERMINING ADJUSTMENT I FACTORS }OR PRESSURIZED WATER REACTORS HADDAM NECK STATION l CONNECTICUT YANKEE ATOMIC DOWER COMPANY -]
l Other-Descritation Noble Gases Halogens Cs, Rb Nuclides )
I I
Ratio of concentra- (a) 0.01 0.001 0.001 tion in steam to that '
in water in a U-Tube steam generator (NS)
Fraction of activity removed in passing N.A N.A N.A N.A J
]
through the condensate 1 demineralizers (NX) - .]
Primary-to-secondary 100 100 100 100 leakage (lb/ day) (FL)
Fraction of materia 1 N.A. N.A. N.A. N.A.
removed in passing l through the cation "
demineralized (NA) j Fraction of material N.A. N.A. N.A. N.A. ;
removed in passing through the purifica- a tion demineralized '(NB)
I (a) All noble gases leaking from the prisnary system to the steam generators are transported rapidly out of the liquid and into the steam and are stripped from the ' system in the main condenser ; therefore, the concentration is approximately i equivalent to the ratio of the primary to secondary leak and 1 the total . steam flow rate.
i
= _ _ _ _ _ . _ _ . _ _
1 1
TABLE 1.2.1-3 _
PART OF NUREG-0017 (TABLE 2-7) j ADJUSTMENT FACTORS FOR PRESSURIZED WATER REACTORS i WITH U-TUBE STEAM GENERATORS ****
Element Reactor Secondary Coolant Class Water (f) Water Steam Halogens _16 2P (0.0 6 + A) (4.5x105) (0.36+A) { _(4.5x105) (0.36+ A ) 9 WP R*+ A WS ( r **+ A ) WS ( r**+ A ) :1 i
I Other I
Nuclides*** 162P (0.06+A) (4.5x105) (0.19+A) g (4.5x105) (0.19+ A ) 9 WP R*+ A WS ( r**+ A ) WS ( r ** + A )
l
- r = (FBD) (NBD) + (NS) (FS) (NC) (NX) !
WS ,
1 Note: All other symbol defintions and values used are found in 1 Table 1.2.1-1 and Table 1.2.1-2.
- "other nuclides" does not include Cs, Rb, noble gases,_ water activation products or H-3.
- Used only for the pure beta emitters. l i
i l
1 l
a I
i
TABLE 1.2.1-4 RADIONUCLIDES CONCENTRATIONS IN REACTOR COOLANT AND SECONDARY LIQUID AND STEAM (uCi/qm)
HADDAM NECK STATION CONNECTICUT YANKEE ATOMIC POWER COMPANY SECONDARY SYSTEM DECAY CONSTANTS NUCLIDE REACTOR COOLANT LIQUID STEAM (1/ SECONDS)
NOBLE GASES Kr-85m 1.5x10-3 Nil 7.7x10-10 4.30x10-5 Kr-87 1.9x10-2 Nil 9.5x10-9 1.52x10-4 Kr-88 6.9x10-2 Nil 3.5x10-e 6.88x10-5 Xe-133 1.2x100 Nil 6.0x10-7 1.52x10-6 Xe-135 3.6x10-1 Nil 1.8x10-7 2.10x10-5 HALOGENS Br-85* 3.1x10-* 4.1x10-10 4.1x10-12 4.03x10-3 I-131 1.3x10-2 3.5x10-6 3.5x10-e 9.98x10-7 I-132 1.1x10-2 5.5x10-7 5.5x10-* 8.43x10-5 I-133 9.5x10-2 1.8x10-5 1.8x10-7 9.26x10-6 I-134 6.2x10-4 1.3x10-e 1.3x10-10 2.20x10-*
I-135 2.0x10-* 2.1x10-e 2.1x10-10 2.92x10-5 CESIUMS Cs-134 1.0x10-* 2.7x10-s 2.7x10-11 1.07x10-e Cs-137 3.4x10-2 9.0x10-6 9.0x10-* 7.30x10-10 Cs-138 1.1x10-3 1.4x10-e 1.4x10-11 3.59x10-4 UPHERS Mn-54 3.2x10-* 8.5x10-e 8.5x10-11 2.56x10-8 Fe-55* 6.9x10-* 1.9x10-7 1.9x10-10 8.14x10-9 Co-58 4.4x10-3 1.2x10-6 1.2x10-0 1.12x10-7 Co-60 8.0x10-3 2.2x10-6 2.2x10-S 4.18x10-9 Sr-89* 1.5x10-* 4.7x10-e 4.7x10-11 1.59x10-7 Sr-90* 4,3x10-6 9.4x10-10 9.4x10-13 7.58x10-10 Pb-99 9.4x10-* 2.2x10-7 2.2x10-10 2.92x10-6 Ru-106* 4.3x10-6 9.4x10-10 9.4x10-ta 2.17x10-a Sb-124 1.3x10-5 3.6x10-9 3.6x10-12 1.33x10-7 Pr -14 3
- 2.2x10-5 4.7x10-9 4.7x10-12 5.91x10-7 Ce-144 1.3x10-2 3.4x10-6 3.4x10-9 2.82x10-e
- Pure Beta emitters - calculated using NUREG-0017 method 1 of 1
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' TABLE 1.2.3-1 TOTAL LIQUID RELEASES. ~!
HADDAM NECK STATION-CONNECTICUT YANKEE ATOMIC POWER COMPANY 4I i
ANNUAL ACTIVITY PRTJ'ASED '
l CONCENTRATION. RELEASE NUCLIDE fuCi/qm) (Ci)
.1 I-131- 3.0x10-10 L 2.2x10-1 >
i I-132 4.7x10-11 3.6x 10-a I-133 -1.5x10-* 1; 1x 100 ' . .;
I-134' 1.2x10-12 '8.2x10-* j I-135 1.8x10-12 1.3x10-3 J I
Cs-134 2.5x10-12 1.9x10-a i Cs-137
^
8.1x10-10' 6.1x10-1 l Cs-138 1.2x10-12 8.7x10-*
1 Mn-54 7.6x10-12 5.7x10-3 Fe-55 1.7x10-11 -1.3x10-2 0o-58 1.1x10-to. 8.0x10-2 .
Co-60 1.9x10-to 1.5x10 4 Sr-89 4.2x10-12 :3.2x10-3 "
Sr-90 8.4x10-1* 6.4x10 i Y-90 9.9x10-** .7.5x10-to 1 Mo-99 2.0x10-11 1.5x10-2 Tc-99m 5.9x10-17 4.5x10-8 Ru-106 8.4x10-1* 6.4x10-5 Sb-124 2.9x10-13 2.2x10-*
Ce-144 3.1x10-10 2.3x10-1 Pr-143 4.2x10-13 3.2x10-*
Pr-144 -3.7x10-10 2.8x10-1 Br-85 3.6x10-** 2.8x10-5 'i
.J H-3 7.6x10-6 5.8x103, NOTES:
(1) Anticipated operational occurrences: 1.5x10-2: Curies, included in'the above releases as described in NUREG-0017.
(2) Discharge canal flow: 7.57x102* gm/yr.- l (3) Total release (excluding tritium) : 2.5'Ci/yr.
(4) Concentration in discharge canal: 3.3x10-* uCi/gm.
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CONNECTICUT ' YANKEE 1.3 METEOROLOGY / HYDROLOGY 0 Enclosure 1, Item 3
! Meteorology / Hydrology information used in. the calculation of
' doses should be consistent with Draft Regulatory . Guide L 1.DD and 1
.1. EE .
Response .
3 This response is in two parts. Section 1.3.1 addresses: '!
meteorology and 1.3.2 addresses hydrology.. d 1.3.1 Meteorology The meteorological information .used in .the calculation.'of continuous release X/Q and D/Q values, and ' ultimate,. dose .value j assessment, is consistent with the guidance set ' forth s .in j Regulatory Guide 1.111 (Reference .1) .
Statf guidance (Ref erence 2) , issued at the May-13, 1976-meeting ;
at Bethesda, Maryland, on intermittent (non-continuous)- release i X/Q and D/Q calculational techniques, provided' a basis for such '
calculations (see Section 2.4.4) . j 1
1.3.2 Hydrology I This section and the dose calculations are based'on a hydrology model which is consistent with the low. velocity surface discharge-mentioned in Table.A-1 of Regulatory Guide 1.109. All. liquid ;
based doses are on no dilution of the discharge- . canal-radionuclides concentrations . prior to uptake by the fresh water ,
fish and invertebrates and concentration in the sediment' f or-'
shoreline recreation doses. Additional information about water ,
use in the vicinity of the Haddam Neck Station is discussed in i Section 1.3.2.3. q 1.3.2.1 Quantitative Water Use Diagrams
'Ihis section . discusses the quantitative water use for:the plant ~
showing flow rates.to and from the various plant: water systems ,
-l (heat dissipation system,' sanitary system, radwaste and chemical- "
waste systems, process water system, etc )' in support Lof liquid radionuclides release rate and concentration estimates.
Cooling water for. the main condenser,' auxiliary systems, and-i reactor shutdown heat removal is withdrawn from the. Connecticut =
River via-the intake structure. This water is circulated by the-main condenser circulating water pumps and/or.the - service:' water pumps. Demineralized water is used for the.. plant ~ processes.
l Well water is used as'the source of make-up. water and domestic l wa ter. The flow rates are indicated on'the Water Usage Flow i Diagram, Figure.1.3.2-1. a i
1.3-1
l CONNECTICUT YANKEE 1.3.2.2 Consumptive 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, and floor drain water usages are variable and are dependent upon such things as the phaae of demineralized regeneration, time of year, and station operating status. The water for station use is furnished by the well water and has averaged 58,000 gpd.
All systems which use water discharge to the Connecticut River or-underground (sanitary waste) , and an exact determination of water consumption cannot be made. However, it is estimated that the net water consumption due mainly to evaporation and miscellaneous losses from the Reactor and Turbine buildings would not exceed 5 gpm. This does not include evaporation from the river surface due to thermal dissipation of the circulating water discharge.
During normal station operation, the closed loop cooling system heat exchangers are in use. However, when the station is shut down, the cooling water use may be reduced if there is no discharge from the radwaste system.
1.3.2.3 Location and Nature of Water Use This section identifies the location of water use (e . g . , water supply, irrigation, fishing, and recreation) assumed for the purpose of calculating doses to a maximum individual. The Connecticut River is not used as either a potable water supply or for irrigation purposes downstream or in the vicinity of the plant (Section 5.4.3 of Haddam Neck Final Environmental Statement, October 1973). In accordance with Regulatory Guide 1.109, the fishing, boating, swimming and shoreline recreation are assumed to take place in the discharge canal.
1.3.2.4 Description of Discharge Structure The following section provides a detailed description of the liquid discharge structure. It also discusses institutional restrictions (state or local) on releases.
Liquid Discharge Structure As shown on Figure 1.3.2-2, the cooling water from the condenser discharges into a concrete channel from which the water enters the discharge canal. Water is maintained at a constant level by a low dam (weir) placed across the canal a short distance from the condenser outlet. The 1.16 mile-long canal, 10 ft deep and about 60 ft wide, discharges into the Connecticut River. Water in the canal moves at 1 to 2 fps (depending on tidal conditions) .
I 1.3-2
)
i CONNECTICUT YANKEE I
At the discharge point, the width of the canal is increased to over 600 ft and the discharge velocity is about 0.2 fps.
Travel time in the canal ranges from 50 to 100 minutes. A boat I barrier is presently installed across the outlet of the canal.
State and Local Restrictions Specific regulations pertinent to pollutant discharges and water quality standards are published as " Water Quality Standard for I Suriace Waters of the State of Connecticut," as adopted by the Department of Environmental Protection, State of Connecticut on November 30, 1973.
1.3.2.5 Description of Ambient Flow in the Connecticut River The Connecticut River is the major surface hydrologic feature in the region and makes up the southwest boundary of the site. The river serves as the main pathway for stream flow originating within the Connecticut River watershed and terminating in Long l Island Sound. The Connecticut River is a tidal river (for about 40 miles) and thus the flow is a combination of streamflow, !
treshwater runoff, and tidal exchange. Although the river experiences tidal flow reversals, ocean waters do not extend to the site. The salt water edge extends to about 2 miles southeast i of the site. The tidal range in the river is approximately 2.5 ft and the minimum average daily flow past the site is 15,000 cfs.
More detailed information about flows in the Connecticut River have been described in the following references:
- 1. Environmental Report, Operating License Stage, Haddam Neck Plant, Connecticut Yankee Atomic Power Company, Sections 2.6.1 and 5.4.2.
- 2. Final Environmental Statement , related to the Haddam Neck (Connecticut Yankee) Nuclear Power Plant, Section 2.4.2, October, 1973, U.S. AEC.
1.3.2.6 Liquid Radionuclides Releases The estimated monthly average of liquid effluent containing radionuclides, as calculated in accordance with NUREG--0 017 and plant operating data, is 1,300,000 gal. The effluent is diluted with 2 x 1011 gal / year of liquid trom the once-through moling flow. The resulting concentrations in pCi/gm, released to the Connecticut River, are listed in Table 1.2.3-1.
1.3-3
1 I
i l
CONNECTICUT YANKEE l l
i 1.3.2.7 Radionuclides Concentrations and Travel Times I i
4 This section provides estimates of radionuclides concentrations )
and the travel time to the only point of interest at the Haddam Neck Station, the discharge canal. The radionucide i concentrations in the discharge canal are listed in Table 1.2.3-1 assuming zero travel time and no dilution. i 1
1.3.2.8 Sorption of Radionuclides by Sediments 4 l
The buildup of radionuclides in sediment has been considered in the discharge canal. The dilution factor assumed for this analysis is 1.0, while the travel time from the release point to ;
the point of uptake by the sediment is zero.
The model used to calculate sediment concentrations is described ,
in Regulatory Guide 1.109, Appendix A, Section 2-C. Briefly, the I equation used is:
Ci = 3.18 x 10s x w x p; x e-A tih j 1.0 - e-Aiib )
DxF Ai where:
=
Ci the concentration of isotope i in sediment, in pCi /m2; 3.18x10s = a constant, converts (C /yr)/ (f t3/sec) /m-1 to pCi/m2; '
W =
the shore width f actor, 0.1 for discharge canal; ' I D = the dilution factor at given location, 1.0; F = the discharge flow rate, 847.9 ft3/sec;
= the release rate of nuclide i, Ci/yr; Qi
= the decay constant of nuclide i, hr-8; th = the holdup time, from release to uptake by the 1 j
sediment, 0.0 hr; and {
tb = the buildup time, hr (1.3Fix105 hr is assumed). 1 L
r" The resultant concentrations of radionuclides in sediment are ' I shown in Table 1.3.2-1.
1.3.2.9 Potential Radionuclides Pathway via Groundwater This section discusses the potential for the release of liquid radionuclides effluents to the groundwater regime as a significant
} pathway to man.
Groundwater is not expected to be a pathway to- man for l radionuclides at this site because the liquid radionuclides i effluents are normally released through the surface discharge canal described in Section 1.3.2.4. Groundwater conditions at the site are detailed in Environmental Report, Operating License Stage, Haddam Neck Plant, Connecticut Yankee Atomic Power Company, Section 2.6.2. ,
1.3-4 l
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ ._ _ ._s
Section 1.3 References
- 1. Draft Regulatory Guide 1.111, PMethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in i Routine Releases from Light-Water-Caoled Reactors" USNRC, j March, 1976.
- 2. United States Nuclear Regulatory Commission, " Calculation of Intermittent (Purge) Releases When Using Joint Frequency.
Data," Distributed during Public Meeting at Bethesda, Maryland, May 13, 1976.
- 3. Environmental Report, Operating License Stage, Haddam Neck Plant, Connecticut Yankee Atomic Power Company.
- 4. Final Environmental Statement, related to the Haddam Neck (Connecticut Yankee) Nuclear Power Plant, ' October, 1973, USAEC.
- 5. Draft Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," USNRC, March, 1976.
- 6. NUREG-0017, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water.
Reactors," USNRC, April, 1976.
1
').
i c
'l !
TABLE 1.3.2-1 CONCENTRATION OF-SEDIMENT RADIONUCLIDES IN THE' :i DISCHARGE CANAL Haddam Neck' Station.
Connecticut. Yankee ' Atomic TNwier Company j i
Sediment Concentration. 1 Isotope (pCi/m2) J j
i
-Mn-54 2.2x108~ j
'Fe-55 1.6x102 00-58 7.5x108 l 00-60 3.2x103 l Sr 2.1x100 1 Sr-90 2.6x100 Y-90 2.6x10-a. q i
Mo-99 5.5x10-8 Tc-99m 1.4x10-7 Ru-106 3.0x10-s Sb-124 1.7x10 Ce-144 8.5x102 -!
Pr-143 5.5x10-2 j Pr-144 4.4x10-7 ;
Br-85 7.0x10 7 )
I-131 2.3x10s "
I-132 4.4x10-2' I-133 1.2x102 !
I-134 3.9x10-*
I-135 4.6x10-3 i Cs-134 1.8x10s- :
Cs-137 2.6x10*
Cs-138 '2.7x10-*
H-3 2.0x10s l
i
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\ lNTAKE STRUCTURE ,.
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FIGURE f.3.2-2 LOCATION OF INTAKE STRUCTURE j AND DISCHA2G2 CAWAL :
STONE E. WEBSTER ENGINEERING CORPORATION 1
_j
1.4 Dose Calculation l Enclosure 1, Item 4 Dose Calculations should be consistent with Draft Regulatory Guide 1.AA (Regulatory Guide 1.109) .
Response
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)
1.
4.1 DESCRIPTION
OF MODELS AND ASSUMPTIONS USED IN ,
INDIVIDUAL DOSE CALCULATIONS I 1.4.1.1 LIQUID EFFLUENTS l
Ingestion of Fifth and Fresh-Water Invertebrates Ebr the maximum individual case, fish and fresh-water 1 invertebrates are conservatively assumed to reside and be caught i in the discharge canal. No dilution is assumed _to occur and 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) . i The dose, Raj , mrem /yr, to a maximum individual of age group a m: ,
1 R ag =
1100.0 ,UA [ B; Q; D, j e-A i ty l F (DF) -1 l
4 l
l where: i U, 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, 848 ft3/sec _j (Reference 2) ; i DF is the dilution factor in the discharge canal, 1.0; B; is the' bioaccumulation factor for aquatic food type 0, liters /kg (Table A-8, Regulatory Guide 1.109) ;'
is the release rate of nuclide i, C1/yr Qi (See Table 1.2.3-1) ;
1 1.4-1
i Daij- is the ingestion dose factor, _ mrem /pCi -ingested,- '
- (Table A-3, Regulatory - Guide .1.109) ;
Ai is the decay constant of nuclide i,-hr-1; tp is the- holdup time, 24.0 hr . (Page 1.109-30,. Regulatory Guide 1.109) ; and i i
1100.0 is the factor used _ to convert . (Ci/yr) / (f t3/sec) to l pCi/kg. 1 i
Swimming and Boating The point of exposure for calculating swimming and- boating doses i is assumed to be in the discharge canal with no dilution credit assumed. The adult and. teen 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 and the child age group usage factor is '56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> l per year. The- usage factor for the adult is based on the -l assumption on page F-15 in Volume 2 of WASH-1258.- The teen and I child usage factors for swimming were arrived at by using the<
~
'l same ratios as was given for boating. The boating usage 'is ')
assumed to be 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> per~ year for the adult and teen _ age groups and 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> per year for the child age group (Page ~ 1.109-19, Regulatory - Guide 1.109) . The- swimming and boating dose conversion factors are listed _in Table 1.4.1-1 . (Reference 4) . .
Additional details of the model are also discussed in' ;
Table 1.4.1-1. j Shoreline Recreation Shoreline recreation is assumed to exist along the.1.16 mile' discharge canal. It is assumed that negligible dilution .' occurs before the liquid reaches the shoreline. The decay time is also- ,
assumed to be negligible.
The dose, Raj , mrem /yr, to the total body or skin of a maximum ,
individual of age group a is: !
Raj = 3.18x103 Ua W E iQ e-A i ty ( 1-e-A i t ) p, j F (DF)' A where:
Ua is the usage tactor 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 .
A-2, Regulatory Guide 1.109) ;
W is the shore width factor,.0.1 (Table A-9, Regulatory Guide 1.109) ; ;
1.4-2 l i
-_ _w
1 F is the flow rate of the release stream, 848 ft3/sec; DF is the discharge canal dilution factor, 1.0; Qi is the release rate of nuclide i, Ci/yr (See Table 1.2.3-1) ;
Ai is the decay constant of nuclide i, hr-a; tp is the holdup time from release to deposition on the shore, 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />; t is the buildup time, 1.31 x 105 hr (Page 1.109-9, !
Dail is as previously defined; and 3.18x103 is the factor used for conversion from (Ci/yr)/(f t3/sec) to pCi/ liter, and to account for the proportionality constant used in the sediment radioactivity model.
1.4.1.2 GASEOUS EFFLUENTS 1.4.1.2.1 Exposure to Noble Gases The individual annual doses from noble gases are based on the releases from the primary vent stack and turbine building roof vent shown in Table 1.2 and the X/Q values listed in Table 1.4.1-2. The offsite location of the maxilaum continuous air dose, total body and skin dose is 710 meters northeast of the ';
Haddam Neck Station. '
The process gus and containment purge releases are intermittent while the primary auxiliary building and main condenser air i ejector releases are continuous, all of which are exhausted from l the 175 ft primary vent stack at the rate of 44 ft/sec.
turbine building releases are sent to the environment by way of The i' the turbine building vent as a continuous ground level release.
Annual Ganna Air Dose and Annual Beta Air Dose The plume of gaseous effluents is considered semi-infinite in the case of noble gases released from the priJnary vent stack and turbine building vent. The concentration of the radionuclides in air at the receptor location may be determined from the atmospheric dispersion model described in Section 2.4 of this report (Reference 3) . The annual average ground-level concentration of gaseous effluent species i at location (r,0) from the release point is determined from equation B-4 from page 1.109-40 of Regulatory Guide 1.109 as follows:
Xi(r,0) =3.17x10*Qj [X/r/ ]O (r,0)
- 1. 4 -3
.l i
i where: 1 1
Xi (r,0) is the annual average ground-level concentration-of :(
nuclide i at the distance r in the sector at .!
angle 0 from the release. point, in pCi/m a; Q is the release rate of the radionuclides i, in d ci/yr, from Table 1.2.2-1 of this report; ;
i
[X/Q )(r,0) is- the annual average gaseous disper.sion factor in-the section at angle 0 at the distance r from the release point, in secAi 3 , from section 2.3 of this report; and i 3.17x10* is the product of the number of pCi/Ci and yr/sec..
ihe annual gamma or beta air doses associated with the airborne concentration of the effluent species are 'then determined. from equation B-5 from page 1.109-40 of Regulatory Guide 1.109 as follows:
DY(r,0) or D O (r,0) = E xi (r,0) (DFjY or DF )
where:
1 Dn(r,0) are the annual gamma and beta air does at the i or DF (r,0) distance r in the sector at angle 8 from the discharge point, in mrad /yr; and DFf,DF are the gamma and beta air . dose factors for.
radionuclides i, mrad per yr/pci per m, a from '
Table B-1 of Regulatory Guide 1.109.
Annual Dose to Individuals from Noble Gas Effluents ,
1 It is also necessary to determine annual doses to individuals in unrestricted areas. The total body dose from external radiation is computed at a depth of 5 cm into the body and the skin dose at ,
a depth of 7 mg/cm2 of tissue. "i The annual total body dose is computed according to equation (10) frcm page 12 of Regulatory Guide 1.109 as follows:
Db (r,0) = 1.11 x Sp EXi (r,0) DFB where:
D[ (r,0) is the annual total body dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle O trom the discharge point, in mrem /yr; 1.4-4 i
1 Xi(r,0) is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle O from the release point, in pCi/m a; Sp is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures (0.7) , dimensionless;
]
j DFBi is the total body dose factor for the radionuclides i which includes the attenuation cf 5 g/cm2 of tissue, in mrem-m3/pci/yr, from Table B-1 of Regulatory Guide 1.109; and 1.11 is the average ratio of tissue to air energy absorption coefficients.
The annual skin dose is computed according to equation (11) from i page 12 of Regulatory Guide 1.109 as follows:
d(r,0) = 1.11 x Sp E i
Xj (r,0) DFf +E X; (r,0) DFSj i
where:
D1(r,0) is the annual skin dose due to inmiersion in a semi-intinite cloud in the sector at angle 0 , at .the distance r trom the release point, in mrem /yr; j DFSj is the beta skin dose factor for the radionuclides i which includes the attenuation by the outer " dead" ,
layer of the skin, in mrem /m3/pCi-yr. This ;
attenuation is for 70 micrometers or 7 mg/cm2 of l tissue, from Table B--1 of Regulatory Guide 1.109; i DFY is the gamma air dose factor for radionuclides i, in I
mrad per yr/pci per m a ; and Sp is the attenuation factor due to shielding by residential structures, 0.7 (dimensionless) .
Values for the open field ground plane dose conversion factors for the skin and total body are given in Table A-7 of Regulatory Guide 1.109. The annual dose to all organs is taken to be equivalent to the total body dose.
1.4.1.2.2 Inhalation Doses The maximum inhalation dose occurs 630 meters north of the Haddam Neck Station.
This inhalation dose, individual of age group a is:
R,g , mrem /yr, to a maximum '
R aj = 3.2 x 10* U, E D jj a Q*
1.4-5
where:
'Q* =
(X/9))png. + (Qg (X/Q) ) coy,,,,,yy + (Qj (X/Q) )pge,33 ,,3 _
(Qi IYK/Af fs!n 6E
+ (Q; (X/Q))masar (Ci-sec) / (m a yr) ;
OVtLOfNG Q'. is the release rate of nuclide i, Ci/yr-(See Table 1.2.2-1) ;
X/Q. is the atmospheric' dispersion factor, sec/m3 The values are dependent on the release points and the release durations and are given in Table 1.4.1-3; Daij is the inhalation dose factor for isotope i,.
organ j, age group a, mrem /pci inhaled (Table C-1, Regulatory Guide 1.109) ;
U, is the amount of air inhaled yearly, m3/yr, taken to be 7,300, 5,100, 2,700, and 1,900 for an adult, teen, child, and infant, respectively (Table A-2, Regulatory Guide 1.109) ; and 3.2x10* is the factor to convert (Ci/yr) to (pCi/sec) .
1.4.1.2.3 Exposure from Contaminated Ground The maximum exposure point is located 630 meters north.of the Haddam Neck Station at the land location with the highest deposition. The dose, Rj , mrem /yr, to organ j is calculated as follows:
Rg = 1.0 x 1012 S p Q, * [ 1-e-A;t )Dij Al where:
O'j =
(Qi (D/Q))ppe4 +
(Qj (D/Q) ) p,,cf,3 gy, meiac (Qi (D/Q) )coueva. %numru r +
+ (Q; (D/Q))mewe Ci/ (yr-m2) ;
B Vn L ping Qi is the release rate of nuclide i, Ci/yr (See Table 1.2.2-1) ;
D/Q is the relative deposition rate at the point'of exposure. The values are dependent on the release durations and release points and are listed in Table 1.4.1-3; Sp is the shielding and occupancy factor, 0.7 (Page 1.109-12, Regulatory Guide 1.109) ;
is the decay constant of nuclide i, hr-1; t is the buildup time, 1.31 x 105 hr (Page 1.109-9, 1.4-6 w__ ___________.-_ _______ __ - __
D;j is the dose fdctor for organ j (total body or skin) ,
nuclide i adjusted to account for secular equilib-rium (mrem /hr)/(pCi/m a) (Table A-3, Regulatory Guide 1.109) ; and 1.0x1012 is a factor to convert Ci to pCi.
1.4.1.2.4 Ingestion of Milk A six month grazing season is assumed for the Haddam Neck Station analysis. The deposition rates for'the grazing season ~are given in Tables 2.3-7 and 2.3-8 of the response to Enclosure 2, Item 3.
The . location...of the ' milk' cow with the highest D/Q has been determined to be.3,540 meters ESE of- the Haddam Neck, Station. c.b2 M .
The relative deposition rates (D/Q) at this point are listed in I Table 1.4.1-4 along with the corresponding X/Q values. ,
'Ihe location of the goat with the highest D/Q has been determined to be 2,410 meters SW of the Haddam Neck Station. The relative deposition rates (D/Q) at this point are listed in Table 1.4.1-5 with the corresponding X/Q values.
The meat dose was not calculated for the maximum individuals since there are no meat animals within five miles of the plant.
The concentration, Cj, , pCi/kg, in the feed of isotope i is:
C;, = Q* 1.1 x 10a f
{ r (1-e Ei A it ) + B;. ( 1 -e- A tih )
AP )e
-A tih l
Ari Y i where:
=
Of (Qg (D/Q) ) png 4 me/gr +
(Q (D/Q))ccaresumrur PVRGf
+
(Q; (D/Q) )pgoeg3y g,g + (Qg (D/Q))meme Ci/ (yr-m )a ;
enwwg Q'. is the release rate of isotope i, Ci/yr (See Table 1.2.2-1) ;
I D/Q is the relative deposition rate at the location of !
the milk cow or goat, m-2 The values are dependent on the release durations and release points and are listed in Tables 1.4.1-4 and 1.4.1-5; I
fg is the fraction of the releases available for dep- l osition for isotope i, as follows:
0.5 for iodine l 1
1.0 for other nuclides (Page 1.109-54, Reg-ulatory Guide 1.109) ;
1.4-7 ;
i i
1
'1
)
r is the retention factor:
0.2 for particulate 'f j
1.0 for other nuclides (Page 1.109-9, Reg- !
ulatory Guide 1.109) ;
Ai is the decay constant for isotope i, hr-2; A Ei is the effective decay constant for isotope.i, adjusted to account for. weathering effects, as follows:
A=
g Ai + 0.0021 hr-2 l (Page 1.109- 0, Regulatory Guide 1.109) ; j tE is the exposure time, 720.0 hr (Page 1 1G8-58, 3
Regulatory Guide 1.109) ; . .i e
t b
is the buildup time, 1.31 x 10s hr (Page 1.109-9, j Regulatory Guide 1.109); ,]
Y is the crop yield for the feed, 0.75 kg/m2 for pasture grass and 2.0 kg/m2 for stored feed '
(Page 1.109-58, Regulatory Guide .1.109) ; j)
P is the effective surface density for soil, 140 kg/ma (Page 1.109-9, Regulatory Guide 1.109) ;
1 Bg is the concentration idctor from soil to crop for j isotope i (Table C-2, Regulatory Guide 1.109) ;
th is the holdup time for stored feed (f rom ' harvest to consumption by the milk cow or goat, 2.2 x 103hr ;
(Page 1.109-58, Regulatory Guide 1.109) ; and I i
1.10x10s is to convert (Ci/yr) to (pCi/hr) . j The concentration, C;, ,pCi/ liter, for tritium is:
C;,= 3.17 x 107 Qj gf/H (X/Q) pCi/kg where:
H is the absolute humidity in the region, 11.1 gm/m3; f 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) ; ;
g '
is the fraction of the total plant mass that is water, 0.75 (Page 1.10 9-54, Regulatory Guide 1.109);
and i
1.4-8
3.17x107 is to convert (Ci-sec/gm) to (pCi-yr/kg). .
1 The concentration, Cj, ,pci/kg, for C-14 is:
C;, = 3.17 x 107 Q;(L/)c) X/Q pCi/)cg where:
X/g is the atmospheric dispersion factor at the appropriate locatian, sec/m3; L is the fraction of the total plant mass that is natural carbon, 0.11 (Page 1.109-54, Regulatory Guide 1.109) ; and k is the concentration of natural carbon in the atmosphere, 0.16 gm/m3 (Page 1.109-54, Regulatory l Guide 1.109) .
Other terms for tritium and C-14 calculations are as previously detined.
The concentration, Cim , pCi/ liter, in milk is deternuned by:
i C, j = F; , [ (C;, fr( + (Cj, tr) ) Qp e-Ai t, where:
tr is the fraction of the animal's feed compoded of fresh or stored grain, 0.5 (Page 1.109-58, Regulatory Guide 1.109) ;
F;, is the fraction (uptake f actor) of the animal's daily feed which appears in a liter of milk, days / liter (Tables C-5 and C-6, Regulatory Guide 1 109) ;
Q I is the animal's daily feed, kg/ day. A value of 50 kg/ day is assumed for a milk cow and a value of 6 kg/ day is assumed for a goat (Page 1.109-58, Regulatory Guide 1.109); and 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. (Table D-2, Regulatory Guide 1.109) .
The ingestion dose, R,,I , mrem /yr, from milk to a maximum individual is:
l R ,; =fC;,
a Dj ai Ua 1
1.4-9 l
1 I
i where: I i
D,jj is the ingestion dose factor for isotope i, age group a, and organ j, mrem /pci ingested (Table A-3, Regulatory Guide 1.109) ; and U, is the usage factor for age group a, liters /yr. Values for the milk pathway of 310, 400, 330, and 330 liters /yr are used for an adult, teen, child, and infant, respectively. (Table A-2, Regulatory Guide 1.109) .
Other terms are as previously defined.
1.4.1.2.5 Ingestion of Vegetation
'Ihe stored vegetable modal is employed for a vegetable garden which is assumed to be at the residence with the highest deposition located 630 meters NNW of the Haddam Neck Station.
Ibr fresh, leafy vegetables, the calculation is made at 630 I meters NNW. The atmospheric dispersion factors, X/Q, sec/ma , and relative deposition rates, D/Q, m-2, are those presented in Table 1.4.1-6.
The concentration, Cj, ,pci/kg, of isotope i in the vegetation is:
C ,, = 1.1 x 10e Q* f ti t 3 + 3;, gi_e-A tih ih
[ r (1-e-A AI t 3 ) e-A t Ei v AP i
where:
=
Q; * (Q; (D/Q))pg + (Qg (D/Q))% + (Q; (D/Q) )p,cc,,,,,,
PVEG E
+ (Qg (D/Q)w Sm oy*G Ci/ (yr-m2) ;
Q; is the release rate of isotope i, Ci/yr (See Table 1. 2.2-1) ;
D/Q is the relative deposition rate at the location of the vegetc. tion, m-a. The values als dependent on the release durations and release points and are listed in Table 1.4.1-6; f 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) ;
r is the retention factor:
0.2 for particulate 1.0 for other nuclides (Page 1.109-9 Regulatory Guide 1.109) ;
1.4-10 L__________-.-- - - - - - - - - - - - - - - - - - -
Aj is the decay constant for isotope i, hr-1; I
AEi is the effective decay constant for isotope i, adjusted to account ror weathering effects, as follows:- 1 AEi = Ai + 0.0021 hr-8 (Page 1.109-10, Regulatory Guide 1.109) ;
tE is the exposure time, 1,4 40 hr ~-(Page 1.109-55, Regulatory Guide 1.109) ;
tb is the buildup time, 1.31 x 105 hr (Page 1.109-9, i Regulatory Guide 1.109) ; j Y, is the crop yield for the vegetation, 2.0 kg/m2 (Page 1.109-55, Regulatory Guide 1.109) ;
P is the effective surfuce density for soil, 240' kg/b2 (Page 1.109-9, Regulatory Guide 1.109) ;
Bj, is the concentration factor from soil to crop for -)
isotope i (Table C-5, Regulatory Guide 1.109) ;
th is the holdup ta.me from harvest to consumption by the maximum individual, 1,440 hr for stored .l vegetables, and 24.0 hr for fresh vegetables :
(Page 1.109-55, Regulatory Guide 1.109) ; and l
- i 1.10x10e is to convert (Ci/yr) to pCi/hr). '
Concentrations of tritium and C-14 are calculated as described in l Section 1.4.1.2.4.
The ingestion dose Ravj , mrem /yr, to a maximum individual is:
Rav) = f C,j Daij Ua where:
Dj ai is the ingestion dose factor for isotope i, age group a, and organ j, mrem /pCi ingested (Table A-3, Regulatory Guide 1.109) ; and U, is the usage factor for. age group a, kg/ year.
Values of'520, 630, and 520 kg/yr are ausumed for 1 an adult, teen, and child, respectively for the .
stored vetetables. For the leafy vegetables, the ;
corresponding values are 64, 42, and 26 kg/yr, respectively (Table A-2, Regulatory Guide 1.109) .
1.4-11
a 1
i l
All other terms are as previously defined.
]
i I
l
'1 1
]
i 1
I
\
i i
\
1.4-12
- j Section 1.4 References
-i
- 1. Draft Regulatory Guide 1.109, " Calculation of Annual Doses to~ ;
Man From Routine. Releases of . Reactor Effluents for- the Purpose 'of Evaluating '- Compliance with 10CFR Part 50,. >
Appendix I,".USNRC,' March, 1976. j l
- 2. Haddam Neck Station Final Environmental Statement', 1 October 1973.
- 3. Draft 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. ANISN, A One Dimensional Discrete Ordinates Transport Co'de, Oak Ridge. National Laboratory Radiation Shielding Information Center, Document No. CCC82.
.i i
i
'l i
4 l
_ _-___-_.____ _- w
TABLE 1.4.1-1.
SWIMMIIC AND BOATING DOSE CONVERSION FACTORS.
HADDAM NECK STATION i CONNECTICUT YANKEE ATOMIC POWER COMPANY
. Conversio'n Factors .
(mrem /hr Mev/cc-sec)
Gansna-Ray Energy (Mev) Swimming Boatinq )
0.4- 7.9x10-a -4.0x10-2 .
0.8 7.0x10-2 3.5x10-2 ]
1.3 6.7x10 3.4x10-2' 1.7 6.4x10-2 3.3x10-2 2.2 6.5x10-2 3.3x10'-2 2.5 6.4x10-a 3.3x10-2 j
\
3.5 6.3x10-a 3.3x10-2' ;
Note: The ANISN (Reference 4) code _was used to calculate the i
conversion factors.. The model~ assumes a twenty-foot l deep body of water (source medium) below.1,700 feet of air. The swiimning location is considered at 2 feet below the water / air interface, and the boating location is 2 feet above tne water / air interface.
l i
i
TABLE-1.4.1-2 X/Q VALUES FOR NOBLE GAS DOSES AT 710 METERS NE HADDAM NECK STATION-CONNECTICUT YANKEE ATOMIC POWER COMPANY -
Annual Average Release X/O - (sec/m3)
PAB and MC/AE- 3.42x10-5 Containment Purges 8.85x10-5 ,
Process Gas- 9.17x10-5 Turbine Building 4.27x10-5 l
TABLE 1.4.1-3
'X/O AND D/O VALUES FOR IN11ALATION' AND CONTAMINATED GROUND AT 630 METERS NORTIl
. HADDAM' NECK STATION CONNECTICUT ' YANKEE ATOMIC POWER COMPANY Annual Average Annual Average Release X/O (sec/m3) D/O - (m 2 )
PAB and MC/AE 2.81x10 7.49x10-8 Containment Purges 8.04x10-5 2.14x10-7 Process Gas 8.35x10-5 2.23x10-7 Turbine Building 3.38x10-5 7.17x10-8 i i
1 j
l 4
I i
t 4 l
l J
TABLE 1.4.1-4 .
I X/O AND D/V VALUES FOR INGESTION OF l COW'S MILK AT 3,540 METERS ES_E-HADDAM NECK' STATION CONNECTICUT YANKEE ATOMIC POWER COMPANY ]
X/O (sec/m3) D/O (m-2) .j Annual Grazing Annual Grazing .]'
Release' Average Season Average Season PAB and MC/AE 3.18x10-6 3.03x10-6 8.11x10
- 6.90x10
- o l Containment Purges 6.06x10-6 6.67x10 6 1.55x10-a 1.52x10-8
=
i Process Gas 6.37x10-6 7.00x10 6 1.63x10-s 1.59x10-e Turbine Building 2.87x10-6 2.64x10-6 1.01x10-a 7.20x10-*
i q
1
.I i
1 i
I l
l
TABLE 1.4.1-5 a i
l X/O AND D/O VP. LUES FOR INGESTION OF GOAT 8S !
MILK AT 2,410 METERS _ W j HADDAM NECK STATION CONNECTICUT YANKEE ATOMIC POWER COMPANY -4 X/O (sec/m 3) D/O (m-2 }
Annual Grazing Annual Grazing Release Average Season Average Season j PAB and MC/AE 5.06x10 7 5.45x10 7 9.60x10-80 9.30x10-10 l
Containment Purges 3.07x10 6 3.92x10-6 5.79x10
- 6.67x10 9 l Process Gas 3.28x10 6 4.21x10 6 6.19x10-9 7.17x10 * !
-l Turbine Building 1.17x10-6 1.74x10-6 1.14x10-9 1.77x10-9
-]
l
-l TABLE 1.4.1-6 X/Q AND D/0 VALUES FOR INGESTION OF' .
VEGETATION AT RESIDENCE WITH THE HIGHEST DEPOSITION' )
630 METERS NNW 9
HADDAM NECX STATION CONNECTICUT YANKEE ATOMIC POWER COMPANY X/O (sec/m a) D/0 (m-2) ;
Annual Crazing Annual Grazing l Release Average Season Average Season 1 1
PAB and MC/AE 2.02x10-5 2.07x10-5 7.43x10-a 1,oox10-7 ;
i Containment Purges 5.05x10-5 4.39x10-5 1.85x10-7 2.12x10-7 Process Gas 5.22x10-5 4.51x10-5 1.92x10-7 2.18x10-7 Turbine Building 3.75x10-5 3.96x10-5 6.95x10-a: 7,87x10-e l
l
4 1
1.5 Effluent Release Data Enclosure 1, item 5 i Effluent Release Data from previous reactor operation should be pro- l l
vided, if available, for use in evaluating the source term calculations.
Such data should include at least one full year of effluent release data ;
tabulated by effluent release point, month, mode of operation (e.g., j full power operation,. refueling shutdown), excluding the first year of reactor operation. 'j l
Response
The effluent release data has been submitted since the start of plant operation, to the U.S. NRC in the semiannual operating reports, as're-quired by the Technical Specifications.
The augmented liquid and gaseous waste treatment systems have been in operation since July 1, 1975. The initial year of operational break in was just over and hence one full year of operationally representative data with these systems is not yet available.
_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . bob"b _ _ _ _ _
2.1 Data Needed for Radioactive Source Term Calculcttions Enclosure 2, Item 1 Provide the information requested in Appendix D of Draft Regulatory Guide 1.BB or 1.CC, as appropriate.
Response j The information requested in Appendix D of Draft Regulatory Guide 1.BB, replaced by Appendix B of Regulatory Guide 1.112 )
(Reference 7) or Appendix B of NUREG-0017 (Reference 8), is I provided in this section.
The symbol (+) designates those parameters which are NUREG-0017 assumptions. All other parameters are from actual Haddam Neck i Station operating data.
1 For the major streams, where the Haddam Neck Station j operating data is less than the NUREG-0017 value, the NUREG-0017 l' value is used.
2.1.1 General
- a. The maximum core thermal power evaluated for safety considerations - 1,825 MWt.
- b. Measured Haddam Neck Station coolant activities are presented in Table 1.2.1-4 along with the pure beta l emitters which are calculated per NUREG-0017.
- c. The quantity of tritium released in liquid and l gaseous effluents - 18.3 Ci/yr Gaseous, 5761 Ci/yr Liquid, based on measured Haddam Neck Station releases from 1969 through 1975. j i
2.1.2 Primary System l a. The total mass of coolant in the primary system, l excluding the pressurizer and primary coolant purification system, at full power - 4.0x105 lb.
1
- b. The average primary system letdown rate to the I primary coolant purification system - 130 gal / min.
- c. The average flow rate through the primary coolant purification system cation demineralizers - not applicable.
- d. The average shim bleed flow - 1.53 gal / min.
d 2.1-1 i
________d
2.1.3 Secondary System
- a. Steam Generators' operation
- 1. Number of Steam Generators - 4.
- 2. Type of Steam Generators - U-Tube.
- 3. Type of chemistry used - volatile (AVT) .
- 4. Carryover iactors; Noble Gases - all activity leaking from the primary system is' carried in the steam to the main condenser; Halogens - 0.01; Cs and Rb -
0.001; other nuclides --
0.001.
Nonvolatile are treated similar to noble gases. [
i
- b. Total steam flow - 8.2x106 lb/hr
- c. Mass of liquid in each steam generator at full power
- 58,800 lb.
- d. Primary to secondary system leakage rate - 100 lb/ day (+) .
- e. Steam Generator blowdown -
15,500 lb/hr of steam generator liquid is blown down to the blowoff tank.
Approximately 30 percent of the liquid flashes to steam and is returned to the secondary system, carrying 5 percent of the iodine activity. All of the particulate and the remaining 95 percent of the iodines are discharged to the environment in the '
remaining 10,800 lb/hr of liquid.
- f. Condensate demineralizers do not apply to the Haddam ,
Neck Station. '
2.1.4 Liquid Waste Processing Systems i
- a. Parameters used in calculating annual liquid i releases. (See Figure 1.2.3-1 for a diagram of the feed streams).
a 2.1.4.1 Sources, flow rates (gpd) and expected l activities (fraction of primary coolant '
activity PCA, or secondary system activity) for j all inputs to each system.
l 1
1 1
I I
2 .1 -2 l
2 l
-_J
i Flow-
' Rate Fraction.and Type Source (cod) Of Coolant 1
. . i Steam Generator 40,300 1.431 Secondary:
Blowdown
' Liquid.
'l Containment -72 1.0 (+)' Primary
. Building; Sumps. Coolant-Primary Auxili- 358 .1 (+) Primary j ary Building Drains Coolant Labaratory ~ 716 .002 (+) - Primary Drains . Coolant-
]
Sample Drains
~
63 1.0 (+) . Primary. ]
Coolant. ]
Decontamination Table 2-20: of NUREG ' :.
and Cask Cleaning 806 0017 Activities (+) a ;
Uncontaminated Drains and Primary, ;
Miscellaneous 1,253 . 01 (+) . Coolant '
l Boron Recovery : Primary. j Shim Bleed 2,200 1.0 , Coolant-Valve Leakoff and Primary ; Primary:
Drains 432 1. 0 (+) - Coolant Turbine Build- Secondary.
ing Drains 7,200 (+). 1. 0 (+) . : Steam Note: The flow rates for all streams except"the-SteamcGenerator Blowdown and Turbine Building are NUREG-0017 values ratioed' up to account for the Haddam Neck StationEyearly releases.
i 2.1.4.2 Holdup times associated with collection) processing, and discharge of all liquid streams, with a discharge. time of 0.0. hours for each release point.
Collection Processing Stream (hr)' -(hr)-
l Steam Generator 0.0- 0.0-Blowdown i
For all isotopes except Iodine which is 1.36, 2 Listed in Table 2.1.4-1 2.1-3
. _ _ . = _ _
a LJ
/
Collection" Processing Stream- (hr) (hr) J Containment Building 292. 33.1 d
8""P8 !! !
Primary Auxiliary 292 33.1 [
Building Drains Laboratory Drains 292 33.1 g y
Sample Drains 292 33.14 Decontamination and -292 33.11 Ca'sk Cleaning
\
Uncontaminated Drains 292 33.1 :w q
~~
and Miscellaneous
! '1 Boron Recovery 682 83 1 1 Letdown ;l
{
Valve Leakoff and 167 20 . '3 - 1 Primary Drains j
u4 Turbine Building Drains 0.0 0.0 m,
Note: Collection time is based on filling;the .;
initial tank .in the stream to 40 percent' l capacity if .there is only one _ tank,;or' on.
filling the initial tank.to 80 percent capacity .;
if there is.a' redundant tank. .The_ process time- ;
is the total time liquid remains in the system < . ' '
for processing,: based on the flow rate'through ' l the limiting process step. In the ~ event. .that the evaporators are unavailable ~for:-two-..
consecutive' days. per.- week (as discussedL in NUREG-0017, Page 2-43) , . there' is) stifficient ~
tank capacity to handle.the. waste'for- the two days. Thus, no- adjustment to'J the liquid-radwaste source term is necessary.:
2.1.4.3 Capacities of all tanks (gal) and . processing . !
equipment (gpd) considered .in calculating' l holdup. times: .j q
Tank / Processing Volume Processing: ~'
Equipment (4al) Capacitp icom)
Holdup Tank 99,280 -
Evaporator. -
20 l 2.1-4
. . . _ _ . _ _ __ m. _.i__.i.
i Tank / Processing Volume Processing _
Equipment .(qal) Capacity (qpm) '{
b Test Tanks (2) 16,000(each) . -
j d
Boron Waste (2) ^
Storage Tanks 93,500(each) q First Stage Evaporator 15 Second Stage Evaporator ' -- 15 Primary. Drains Tank 7,500- -
Recycle Test Tank (2) 16,000 (each) -
2.1.4.4' Decontamination factors for each process step:
Equipment DF Steam Generator Blowoff- 1.05 --Iodine Tank 1.0 - Others Mixed Bed Ionexchanger 2 - Cs, Rb 102 .Others Evaporator 102 - All J
Mixed Bed Iblishing 10.- All Demineralize 2.
Mixed Bed Demineralized 2 - Cs, Rb .y (Li3 803) 10 - Others 4 Degassirier 103 - Noble Gus 1.0 - Others Mixed Bed Ionexchanger 10 .All (Reactor Coolant Letdown) q
, Mixed Bed Ionexchanger 2 - Cs, Rb (Valve Leakoff) 102 - Others First or'Second Stage 102 - Iodine Evaporator 103 - Others 2.1.4.5 Fraction of each processing. stream expected to ,i be discharged over the life of the plant:
Fraction J Source Discharged '
- )
All Streams 1.0 i. i 1
1 2.1-5 "
j i
l l
J
2.1.4.6 The ' resins are 'non-regenerable.
2.1.4.7 Liquid source term by radionuclides in Ci/yr for.
normal '. operation including anticipated' operational ' occurrences. ~
The liquid source terms are listed in Table 1.2.3-1.
2.1.4.8 The liquid waste .is normally discharged:into
.the. circulating water discharge flow which amounts to 2.0 x 108* gal / year.
- b. Provide piping and instrumentation diagrams (PSID 's)
~and process flow' diagrams for the liquid radwaste systems along with all other systems influencing the source' term calculations.
This report includes a simplified' flow' diagram..for the liquid radwaste systems, Fig. 1.2.3-1, plus a PSIra ' showing the normal flow . path'of-the liquid
-waste system, Fig. 2.1-1.
2.1.5 Gaseous Waste Processing Systems
- c. The gases are stripped from primary coolant at.the.
rate of 2632 gpd (Boron shim bleed plus valve leak-off and primary drains) with an average Hydrogen content of 35 sec/kgm. In addition to the normal feed stream, it is assumed that the primary system is totally degassified twice each year 'and' additional cover gases result in a total 'of approximately . (+) 50,000 scf/ year.
- b. There are three waste gas decay tanks. (WGDT) which are designed to hold the ' gases .ge'nerated 'in this system. The following information describes the WGDT's:
}
- 1. Design' pressure - 225 psig.
- 2. Operating storage pressure - 200'psig.
- 3. Capacity - 132 ft3
- 4. Number of WGDTag - 3,
- c. Normal operation of the Haddam Neck Station gaseous waste system provided operating data which is quite different from several- of the values calculated using the method described in NUREG-0017. Since 2.1-6
using the NUREG-0017 guidelines will introduce conservatism and certain operating data is not available, the NUREG-0017 approach is used for most of the calculated values. During normal. operation, one of the three WGDT's is held in reserve for back-to-back shutdown operations.
The fill and holdup times are calculated using the 140 scf/ day (+) and 70 percent of the design pressure. A conservative value of 5 scfm is used for the re: lease rate from the WGDT's as operating data from 7/1/75 to 7/1/76 gives the average duration of a WGDT release as 7.26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> resulting in a 3.2 scfm release rate. The following values are indicative of the gaseous waste system operation:
- 1. WGDT fill time - 10.1 days.
- 2. WGDT holdup time -
~ 10.1 days (plant operating data lists the average holdup time as 80 days) .
- 3. Release rate = 5 scfm. I
- 4. Release period - 167 hr/yr.
- d. The intermittent releases from the WGDT's are exhausted through (1) a charcoal filter and. (2) a HEPA filter. The following decontamination t' actors are used:
- 1. HEPA - 100 for particulate.
- 2. Charcoal - 10 for iodines.
- e. The charcoal delay system does not apply to the Haddam Neck Station.
- f. A piping and instrumentation drawing of the gaseous radwaste system is shown in Fig. 2.1-2.
2.1.6 Ventilation and Exhaust Systems
- a. For each of the releases, the- provisions incorporated to reduce radioactive releases through the ventilation or exhaust systems are as follows:
- 1. Containment Building (containment purges):
HEPA filter and charcoal filter on exhaust ventilation. l 2.1-7
- 2. Primary Auxiliary Building (PAB) :
HEPA filter and charcoal filter on exhaust ventilation.
- 3. Main Condenser Air Ejector:
HEPA filter and charcoal filter on exhaust ventilation.
I
- 4. Process Gas:
HEPA filter and charcoal filter on exhaust ventilation.
- 5. Turbine Buildir.g:
There is no filtration of exhaust ventilation.
Note: Releases 1 through 4 are exhausted to the environment through the primary vent stack.
(+)b. Decontamination factors assumed and the bases (including charcoal adsorbers, HEPA filters, and mechanical devices) :
- 1. HEPA filters are 99 percent effective in removing !
particulate from air flow.
- 2. Charcoal filters are 90 percent effective in removing iodine from air flow.
- c. Release rates in Curies /yr are presented in Table 1.2.2-1.
- d. Release point description The primary vent stack and the turbine building roof vent are the two release points for the gaseous releases from the Haddam Neck Station as described in Section 1.2.2.
- 1. Primary vent stack:
- a. Height-- 175 ft.
- b. ID of stack - 5 ft.
- c. Temperature difference between gaseous effluent and ambient air - not applicable as plume rise is not considered for this release point.
l 2.1-8
- d. Exit velocity - 44 ft/sec. ;
- e. Stack is attached to l the containment (tallest adjacent structure) and extends 5 ft above the containment building 170 f t above grade.
4
- 2. Turbine Building Roof Vent . located 76.5 ft l above grade and is classified as a ground level l release point. 1 l
- e. Containment building
- 1. Building free volun.a - 2.23x106 fta. l I
- 2. Purge rate - 35,000 cfm.
(+) 3. Number of purges per year - 4 cold.
(+) 4. Duration of each purge - 48 hrs.
- 5. Recirculation system l
- a. Operation - 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> prior to purge. i
- b. Particulate and Charcoal Filters--However, it is conservatively assumed that the only reduction is from decay.
i l
l l
1 l i a
2.1-9
_ -_ - a
4 Table 2.1.4-1 i
NtJREG-0017 Table 2-20 Activities '
Haddam Neck Station Connecticut Yankee Atomic Power Company '
Calculated Annual Release of Radioactive Materials in -
Untreated Detergent Waste from a PWR j i
Nuclide Ci/yr Mn-54 0.001 Co-58 0.004 1
Co-60 0.009 I Zr-95 0.0014 I
Nb-95 0.002 Ru-103 0.00014 '
Ru-106 0.0024 Ag-110m 0.00044 I-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.
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i 2.2 Radiological Pathway Analyses Parameters Enclosure 2, Item 2 Provide, in tabular form, the distances from the centerline of the first nuclear unit to the following for each of the 22-1/2 f l
degree radial sectors centered on the 16 cardinal compass l 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 ft2 (to a distance of 5 miles)
- f. nearest site boundary For radioactivity releases from stacks which qualify as elevated releases as defined in Draft Regulatory Guide 1.DD, identify the locations of all milk cows, milk goats, meat animals, residences, and vegetable gardens, in a similar manner, out to a distance of 3 miles for each radial sector.
Response
i l Answered in PART 1, Volume 1 of the Demonstration of Compliance I with 10CFR50, Appendix I for the Haddam Neck Station, Docket
! No. 50-213, submitted on June 4, 1976 (Reference 3) . See Section 2.3.1 for modifications that have been made.
1 1
2.2-1
2.3 NORMALIZED CONCENTRATION (X/Q) AND DEPOSITION (D/Q) VALUES Enclosure 2, Item 3 Based on considerations in Draft Regulatory Guide 1.DD, provide estimates of relative concentration (X/Q) and deposition (D/Q) at locations specified in response to item 2 above for each release point specified in response to item 1 above.
i Response: I l
2.3.1 Summary l Tables 2.3-1 through 2.3-16 present annual average (1/1/75-12/31/75) and grazing season (4/1/75-9/30/75) relative ;
concentration (X/Q) , and relative deposition (D/Q) values; which !
were calculated according to the methods outlined in Regulatory ;
Guide 1.111_ (Ref erence 2) as demonstrated in Section 2.4. These ;
tables contain information for each of the 22.5 degree radial sectors, centered on the 16 cardinal compass directions, for the following receptor points:
- 1. Nearest site boundary distance.
- 2. Nearest land distance.
- 3. Nearest distance to a vegetable garden larger than 500 fta within 5 miles.
- 4. Nearest residence distance within 5 miles.
- 5. Nearest milk cow distance within 5 miles.
- 6. Nearest milk goat distance within 5 miles.
No commercial facilities of meat animals are located within a
, 5 mile radius of the site. Distances to receptor points 1 through 6 from the primary vent stack are defined in Table 2-1 of Volume 1 of the Connecticut Yankee Atomic Power Companya s (CYAPC) 6/4/76 partial compliance to Appendix I to 10CFR50 letter (Reference 3) .
Listed below are the following modifications to Table 2-1 distances:
. Nearest milk goat SE sector at 2,42 km
.Nedrest land SE sector, reduced to 1.30 km
. Nearest land SSE sector, reduced to 0.89 km
. Nearest land S sector, reduced to 0.74 km
. Nearest land SSW sector, reduced to 0.70 km
. Nearest land SW sector, reduced to 0.58 km
. Nearest land WSW sector, reduced to 0.58 km
. Nearest land W sector, reduced to 0.62 km 2.3-1
These adjusted distances were those utilized for X/Q and D/Q computations.
2.3.2 Meteorological Data Onsite meteorological data for the January 1, 1975 - December 31, 1975 period were used as input to the calculation models shown in .
Section 2.4. Hourly-averaged values of wind speed and wind t direction frcm the 196-ft level of the meteorological tower were used to approximate atmospheric conditions that the elevated portion of the release encounter, while data from the 33-ft level were used to represent the atmospheric conditions that the .
ground-level releases would encounter. Hourly-averaged values of I temperature difference between the 33- and 196-ft levels were used to estimate the atmospheric stability of the layer of air through which the plume passes before reaching the ground.
Stability was derived from hourly-averaged values of temperature difference using the method presented in Regulatory Guide 1.23 (Reference 4) .
For the primary vent stack release, which is conditionally elevated, 196-ft winds were used for the elevated portion of the release, and 33-ft winds for the entrained portion of the release. For the turbine building vents release, which is entirely entrained, the 33-ft winds were used exclusively. I Temperature difference between the 33- and 196-ft levels were used to estimate atmospheric stability for both release points.
The data collected on the meteorological tower should be representative of conditions in the vicinity of Haddam Neck because on the conformance of the data collection program to accepted practices, the high data recovery rates, and the proximity of the tower to the building complex. The meteorological monitoring program was conducted in accordance with Regulatory Guide 1.23 (Reference 4) specifications.
Composite data recovery for 196-ft wind speed, 196-ft wind direction, and 33-196 ft temperature difference measurements waa 95.6 percent. For coincident 33-ft wind speed, 33-ft wind direction, and 33-120 f t temperature difference measurements, the composite data recovery was 95.1 percent. Analyses showing the representativeness of these data with concurrent and long-term regional climatology are presented in Section 2.5.2. The meteorological tower is located approximately 1,870 ft ESE of the containment building. This distance is sufficiently nearby to provide meaningful data, yet sufficiently distant to minimize disturbances due to plant structures. The meteorological monitoring program specifications are described in more detail in Section 2.5.1.
2.3.3 Plant Design Parameters Table 2.3-17 presents the plant design parameter inputs which were used in the meteorological analyses.
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TABLE 2.3-17 PLAlfr PARAMETERS PERTINENT TO METEOROLOGICAL CALCULATIONS I. Reactor Building Height 51.8 m above grade Effluent Release Heigh,5 53.3 m above grade Effluent Velocity 13.4 m/sec II. Turbine Building Height 23.3 m above grade I
i I
i 1
l 1 of 1
I 1
l 1 I
l 2.4 g.'MOSPHERIC TRANSPORT AND DISPERSION MODELS Enclosure 2, Item 4 Provide a detailed description of the meteorological datu, nodels, and parameters used to determine the X/Q and D/Q values.
Include information concerning the validity and accuracy of the models, and assumptions for.your site and the representativeness of the meteorological data used.
Response: l Annual average and grazing season values of relative concentration (X/Q) , and relative deposition (D/Q) were calculated using guidance presented in Regulatory Guide 1.111 (Reference 2) . In order to remain conservative, it was assumed ,
that attendant p1tm.e depletion was always negligible {
(X/Q = (X/Q)d) . Hourly--averaged meteorological data as discussed in Section 2.3.2, and the plant design parameters presented in Table 2.3-17 were used as input to the models detailed in this- 4 section. I 2.4.1 Nomenclature 1
-a 1 2.032 = h f Y= 3.14159...
I exp = 2.718...
Et = dimensionless entrainment coefficient (from Regulatory Guide 1.111, pp.10-11) d = dimensionless terrain recirculation factor (from Regula-tory Guide 1.111, Fig. 2) l c = dimensionless building shape coefficient = 0.5 x = downwind receptor point distance (m) 01 = vertical diffusion coefficient (m) (from Regulatory Guide 1.111, Figure 1) .
I U33 = hourly-average wind speed near ground level, applicable to the ground release (m/sec)
U196 = hourly-average wind speed applicable to a conditionally elevated release (m/sec)
X/Q = relative concentration normalized by source strength (sec/m3) hb = building height (m) 2.4-1
i l
i hr a release height (m) he = effective release height (m) ht = topographic height of receptor above plant grade (m) j 20 Ue = effluent velocity (m/sec)
N = total number of valid hours of wind in all sectors for applicable averaging period j 8/Q = relarive deposition rate normalized by source strength (m-8) ]
l D/Q = relative deposition rate per unit area normalized by '
source strength (m-2) g = ground release subscript l
i = index for elevated release stability group 1 = unstable (classes A-C) 2 = neutral (class D) 3 = stable (classes E-G) j = index for number of hours k = index for a particular receptor distance 1 = index for a particular 22.5 degree sector n = number of hours of wind in a particular 22.5 degree sector 2.4.2 X/O Value Methodology Annual average and grazing season values of relative concentration (X/Q) were calculated for continuous releases of activity frara the primary vent stack, and turbine building vents, according to the straight-line airflow (Gaussian) model presented in Regulatory Guide 1.111. The basic equation of this model is as fol)ows: n ~
Y _ 2p2 A_ _
Et _ , (1-Et)sxpf ~i(k)[
,g N UNf + h Ul% Q (
The entrainment coefficient effluent velocity (Oe) to wind speed (EQ is a function of the ratio of (0196) for conditionally-elevated release points. For vent releases occurring below the level of a nearby structure, such as the turbine building vents, 100 percent downwash is conservatively assumed (Et = 1) . For 2.4-2
vent releases occurring between 1 and 2 times the heigM of a nedrby structure, such as the primary vent stack, a conditionally elevated release is assumed, and the entrainment coefficient is defined as follows:
Et = 0.0 when Ue/U196 25.0 Et = 0.30-0.06 (Ue/U196) when 1.5 < Ue/U196 <5.0 (2)
Et = 2.58-1.58 (De/U196) when 1.0 s Ue/U196 51.5 Et c 1.0 when Ue/U196 <1.0 The primary vent stack, which is between 1 and 2 times the height of the nearest adjacent solid structure, was considered to be a conditionally elevated release, while the turbine building vents were conservatively considered to be a ground release, since a nearby adjacent solid structure (the containment building) was taller.
Ibr the conditionally elevated containment building release, Equations 1 and 2 were used to evaluate X/Q. For the turbine building vents, Equation 1 was simplif~ied (Since Et = 1) to: i N I
_Q ,. A N J g ~ 3 k2ebWN -
(3)
J: 1 This equation was evaluated at the nearest site boundary and nearest land distances, and at the nearest vegetable garden ;
larger than 500 ft2, the nearest milk cow, and nearest milk goat I distances; all within 5 miles in each sector. Meteorological data for the entire year were used in the site boundary and l 4
residence calculations. For the vegetable and milk-pathway i calculations, data f rom April 1 through September 30 were used.
This period corresponds to the grazing season, and also approximates the vegetable growing season.
I Effective release height was computed from the following l relationship: j l
he = hr - (hyg (4) j I
l In the ground level portion of Equation (1) , the building wake i correction term was constrained to be less than or equal to 1.732 7z. ]
1 1
l ;
1 l
2.4-3
._m..m. . .--.
2.4.3 (X/0)g and D/O Value Methodology Annual average and grazing season depleted relative concentration values were conservatively assumed to be equal to annual average and grazing season relative concentration values (X/Q = (X/Q)d /
- respectively. Therefore, no credit for attendant plume depletion on radiciodines and particulate was taken.
Annual average and grazing season relative deposition values were ,
calculated using Regulatory Guide 1.111 Fig. 7 (ground-level '
release), Fig. 9 (60 meter release) with the following equation:
N 2 _,
O ( / Q, + -
() N {
l M gg, (XK L Ib L.
A -
)
a -
For the conditionally elevated release, Figures 7 and 9 were used to calculate the (d/Q) g and (d/Q) (i = 1-3) , values, respectively. For the ground release;, Figure 7 was used to calculate the (d/Q)g values.
2.4.4 Methodology Employed for Intermittent Releases The methodology employed in the calculation of X/Q and D/Q for intermittent releases is as tollows, and reflects current Site Analysis Branch practices (Reference 1) :
l 1. One-hour sector-averaged X/Q values are calculated, using the model presented in Section 2.4.2, but without incorporating the terrain recirculation factors. I l'
- 2. The 15 percent highest one-hour X/Q value was plotted at 1-hour on log-log coordinates of X/Q vs. time, while the annual average or grazing season value was plotted at 8,760 hours0.0088 days <br />0.211 hours <br />0.00126 weeks <br />2.8918e-4 months <br />. A straight line was drawn, connecting tlese two points.,
l 1
- 3. log-log interpolation, based on the total intermittent i release period hours, versus annual (8760) hours yielded l both an X/Q and D/Q multiplier.
- 4. This multiplier was then applied to the continuous )
release annual average and grazing season X/Q and D/Q values for the applicable release point, to obtain appropriate intermittent X/Q and D/Q values.
l \
l 1
2.4-4 l 1
3
ht the Connecticut Yankee Nuclear Plant, two intermittent releases occur through the primary vent stack:
- 1. Containment Purge - 192 hours0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br /> / year
- 2. Process gas purge - 167 hours0.00193 days <br />0.0464 hours <br />2.761243e-4 weeks <br />6.35435e-5 months <br /> / year 2.4-5
l i
1 2.5 OASITE METEOROLOGICAL DATA CONFORMING TO REGULATORY GUIDE 1.23 Enclosure 2, Item 5 If an on-site program commensurate with the recommendations and j intent of Regulatory Guide 1.23 exists: j a). Provide' representative annual and monthly,.if available, !
joint' frequency distributions of wind speed and'- ;
- g. direction by atmospheric stability class covering'at' l least the .most recent one year' period- of record, preferably two or more years of record. . Wind speed'and direction should be measured at levels applicable 'to' release point elevations , and stability, should be determined from the vertical temperature gradient i' between measurement' levels that represent conditions-into which the effluent is released.
b) Describe the representativeness- of the available data )
with respect to expected long-term conditions at the -i site.
RESPONSE:-
2.5.1 Onsite Meteorological Monitoring Program Specifications 2.5.1.1 Meteorological Measurements !
Meteorological measurements are made at three levels on the tower:
Sensor Height Above Ground Level (feet) Parameter (s) Measured 33 wind speed, wind direction temperature, and dewpoint 120 temperature difference'to 33-foot level-196 wind speed, wind direction, temperature and temperature difference to 33-foot level 2.5.1.2 Meteorological Instruments Meteorological instruments used on the tower- are listed in Table 2.5-4. These instruments were selected to' conform to the recommendations of Regulatory Guide 1.23 (Reference 4) .
Wind direction sensor accuracy for instantaneously recorded values is' 13 degreen, with a threshold of 0.6 mph.- Wind speed ,
2.5-1 4
5
sensor accuracy for time averaged values is 10.2 mph, and the starting speed is 0.8 mph. Temperature sensor accuracy for time averaged values is better than 10.2 degree C. Temperature differences are determined by matched pairs of sensors in a bridge network system in which the different lengths of cables are accounted for. System temperature difference accuracy for time-averaged values is approximately 10.1 degree C. All sensors are mounted in aspirated radiation shields. Dew point temperature sensur accuracy figures are not quoted by the manufacturer for time-averaged values. However, the operating experience of The Research Corporation of New England with these sensors (if properly equipped with F.osemount signal conditioning electronics) in east coast and midwest locations indicates that the average error is within il degree F of psychrometric determinations of dew point for properly calibrated and maintained sensors, very close to the Staff's reommended 10.5 degree C.
Signal conditioners, interfacing devices, ancillary electronics, and recording equipment are located in an instrument building at the base of the tower. The accuracies of data transference through signal conditioners, interfacial and ancillary electronic systems, and into recording equipment are in all cases much greater than the inherent accuracies of the sensors.
2.5.1.3 Digital Recording System Meteorological parameters are reduced to digital form and recorded under the control of a minicomputer located in the instrument building. The field digital data reduction and recording system is comprised of a Data General Model 1220 Nova minicomputer, a Model 4055 analog to digital converter, a Model 4008 real time clock, a Model 4010A/1220 ASR-33 teletype with paper tape reader and punch, and a Western Electric Model 202C Dataset. The continuous output of each meteorological sensor is signal conditioned to a 0 to 5 volt de level. These conditioned sensor outputs are scanned at five-second intervals by the digital system. The dwell time of the digital system on each sensor output is on the order of microseconds, resulting an in essentially instantaneous value every five seconds for each sensor'. The digital system sums and averages these five-second values over 15-minute intervals. In the case of wind direction sensor output, the digital system also computes the true mathematical variance over 15-minute intervals (i.e., the everage and variance of 180 5-second values). The 15-minute average and variance data are stored by the field digital system for one hour. At the end of each hour this system receives a telephone call from a host computer system located in the Berlin offices of the Northeast Utilities Service Company and transmits its data to the host machine where the data is logged on disc, examined twice daily and transferred to a magnetic tape for storage and editing.
The host digital system consists of a Data General Model 1220
} Nova minicomputer, Model 4046 Diablo moving head disc assembly, 2.5-2
E Model 8,030 magnetic tape transport assembly, Model 4012A high speed paper tape punch, Model 4011B high speed paper tape reader, Model 4010A ASR-33 teletype with paper tape reader and punch, and a Western Electric Model 202C Dataset. If the field digital system is not called for a period of two hours, it automatically starts its paper tape punch and teletype, and prints out the data
, for later manual collection and integration into the record. The i
digital system telemetered information is normally the primary source of data, with analog data used only as backup where required, and for comparison checks on the digital data.
i 2.5.1.4 Analog Recording System f The analog recording system is used to fill in data gaps caused l
by digital system failure, and to provide routine operational I cross checks of digital data validity. It is composed of four Esterline Angus Model E1102R twin pen recorders for wind speed and direction, and two Esterline Angus Model E1124 E eight point recorders for other parameters.
l l 2.5.1.5 Instrument Calibration Methods !
Instrument calibration is performed semi-annually by a meteorological consultant, under contract. Wind speed sensors are calibrated using a reference hot wire anemometer in a low speed wind tunnel for starting and stalling speeds; while manufacturer's specifications are relied on for higher speeds.
Wind direction sensors are calibrated on a large bench protractor, and sensor output is checked against the protractor I direction indication. '
Temperature and temperature difference sensors are calibrated -
using an ice bath. The temperature sensors are immersed in ice water and their output is compared to 320F. The temperature difference sensor elements are both immersed in ice water and the I resultant output is compared to 00F. This calibration is
) accomplished with the appropriate lengths of signal cable in the l bridge network in order to accurately account for cable j l electrical resistance. Dew point temperature sensors are calibrated with a mechanically aspirated psychrometer fitted with precision laboratory thermometers which are acceptable secondary I standards; the dewpoint sensor output is compared to the dewpoint
! value determined by conversion of the wet-bulb and dry-bulb temperature psychrometer readings. The visiometer is calibrated by two internal met.manisms: a black shutter that cuts off the light beam and simulates zero visibility, and a diffuse reflecting surface that, when inserted into the light beam, provides a constant reference. The pyranometer requires no l continuing field calibration, but is returned to the manuf acturer annually for a calibration check.
2 . 5 -3
~
l i
i 2.5.1.f System Maintenance and Ouality Assurance Procedures !
A matber of procedures are exercised to insure that the physical 4 components of the system are properly maintained and that the data received are of assured quality. These procedures are of .
four types: routine inspection and maintenance, preventative {
maintenance, trouble-shooting, and data quality control. The I first three types are applicable to the physical components of j the system; that is, the sensors and their associated hardware, the analog recording systert, and the digital data reduction and recording system. The first and fourth types of procedures are applicable to the analog and digital data produced by the system.
Routine maintenance of sensors and their associated hardware and I inspection visits are conducted weekly (unless some problem is revealed by daily inspection of telemetered data) by Northeast Utilities Service Company (NUSCo) personnel. A checklist is executed and kept on file to determine the reasonableness of ;
j indicated values of meteorological parameters; and to assure that l all sensors are functioning properly.
i Preventative maintenance of the sensors is accomplished through semi-annual inspection and calibration performed by a meteorological consultant, under contract.
\
Troubleshooting functions are performed by NUSCo personnel. The response time to a trouble call is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less, and an inventory of spare parts is maintained in a ready condition.
The analog recorders are function checked during the routine maintenance visits for correct operation, timing, and calibration; the recorders are serviced, inked, and the charts changed as necessary by NUSCO personnel. A checklist is executed and kept on file. Preventative maintenance of the recorders is accomplished semi-annually through inspection and servicing by a meteorological con sultant, under contract.
The digital data collection system undergoes a preventive maintenance routine performed once every two months by the manufacturer under contract. Functional diagnostic programs are run through the minicomputer, and the correct operation of the l computer itself, the analog / digital converter, and the l input / output devices are checked. The moving parts of the teletype and paper-tape punch are inspected and serviced.
Troubleshooting is also accomplished by the manufacturer, with a contract response time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less.
Analog and digital data produced by the meteorological system are cross-checked for reasonable agreement during weekly maintenance visits by NUSCO personnel. Digital data telemetered to the NUSCo Berlin offices are examined twice daily by a trained meteorologist for reasonableness. This facilititates a rapid detection and remedy of equipment problems and data outage.
2.5-4
Analog strip charts are removed from the recorders every two weeks. The charts are archived and are not reduced to digital form unless required for comparative checks with the digital system data or to fill gaps in the digital data.
2.5.1.7 Data Analysis Procedures The digital data reduction and recording system produces ;
15-minute average data that are directly suitable (after editing l of bad data) for input into site climatology or atmospheric j diffusion programs. Analog data, where required, are obtained by j analysis of the strip charts by a meteorological consultant.
Strip charts are manually analyzed and converted to digital data ,
using a Gerber GADRS 4 analog-to-digital conversion system. One 15-minute average value per hour (minutes 00 to 15) is obtained for each meteorological parameter, and wind direction variance is !
estimated from the average maximum range of wind direction. (
These data are then arranged in a chronological listing suitable for comparison with or merging with the digital system data.
2.5.2 Joint Frequency Distributions Annual and monthly joint frequency distributions of wind speed, j wind direction, and atmospheric stability were provided for both j tower levels (33 ft and 196 ft) in Volume 2 of CYAPC's partial l compliance letter of June 4, 1976 (Reference 5) . Atmospheric j stability was determined from hourly-averaged values of temperature difference in accordance with Regulatory Guide 1.23 Procedures (Reference 4) . In each of these joint frequency summaries, wind speeds below the 0.8 mph anemometer threshold were classified as calm.
2.5.3 Representativeness of D3ta l
Meteorological data collected at the Connecticut Yankee site from January 1, 1975 through December 31, 1975, form a one-year data base upon which the atmospheric dispersion analyses are based.
It is therefore necessary to determine whether this data base is representative of long-term climatological conditions of the region. The premise upon which the data have been tested for representativeness is that any significant climatic changes which af fect the Haddam Neck area, will also affect nearby weather stations. Bradley Field, located in Windsor Locks, Connecticut, was selected as a suitable station for this study because of its location with respect to Haddam Neck, approximately 31 miles north-northwest. In addition, both sites are located near the Connecticut River.
Onsite data representativeness was briefly addressed in Table 4b-1 of Connecticut Yankee Atomic Power Company 8s partial compliance letter (Reference 3) . Two annual cycles of data (4/63 - 3/64 and 1/75 - 12/75) were compared to one another. The 4/63 - 3/64 data was acquired on a meteorological tower that did 2.5-5
not meet Regulatory Guide 1.23 specifications. Table 4b-1 shows the effect of the WNW-ESE valley flow at the site for both annual cycles of data.
In order to expand this analysis, 27 years of National Weather Service data (1949-1975) at Windsor Locks (Reference 6) were acquired. 'Ite last year of this period represents a concurrent period to the onsite data, while the entire 27-year period is i indicative of the long-term climatology of the area.
Table 2.5-1 shows comparative stability class frequencies at the two sites, for the concurrent and long-term time periods. As indicated in the table, on the whole, the stability frequencies show good similarity between Haddam Neck and Windsor Locks. The differences in the A, D, and E stability classes are directly attributable to the methodology employed in stability class determination. The STAR program used by the National Weather Service is based on gross parameterization of solar angle, cloudiness, and wind speed, while the AT classification is more indicative of the turbulent structure of the atmosphere's lower level. Since "A" stabilities rarely occur using STAR program methodology at Haddam Neck latitudes, and since "E" stability is j
, restricted by its inability to occur during the day, one can j
! reasonably conclude that the differences in atmospheric stability between Haddam Neck and Windsor Locks are highly attributable to the stability determination methodology.
Table 2.5-2 shows comparative wind frequency percentages by guadrants for Haddam Neck, and the concurrent and long-term Windsor Locks data. Both sites exhibit a tendency towards valley channeling. At Windsor Locks, where the Connecticut River valley is oriented North-South, wind flow along that axis on an annual basis occurs more frequently than at other stations outside of the valley influence. The same phenomenon is also i present at Haddhm Neck, except that the valley orientation is
! West North West -
East South East. In the NNE-E quadrant, in which neither area is affected by valley flow, wind frequencies correspond quite well. Although Table 2.5-2 is obfuscated by the channeling along nonparallel va ley axes, it can be concluded that wind characteristics at Haddam Neck are similar to Windsor Locks.
Table 2.5-3 shows the large canopy effect that the nearby tree cover exerts at 33 feet above the meteorological tower base.
l Wind speeds in each quadrant average M ut 40 % of the less l af fected dindsor Incks wind speeds. It is Jpt ? worthy, that wind speed ratios on a quadrant-by-quadrant basis etre quite consistent between the data bases.
l Realizing that the methods of stability determination differ, the valley orientations are unparallel, and the Haddam Neck site is exposed to higher levels of tree cover, with respect to Windsor Locks; one can reasonably judge the 1975 meteorological data at 2.5-6
Haddam Neck to be reasonably representative of the long-term climatology of the region.
l
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ri TABLE 2.5-4 METEOROLOGICAL' TOWER' INSTRUMENTATION Parameter Inst >uments Wind speed Climatronics Model F460' wind speed' transmitter Wind direction Climatronics Model F460 wind direction transmitter-Temperature Rosemount Model 104-MN-100C platinum resistance elements-l- in Teledyne.Geotech Model 327 l
. aspirated radiation shields Temperature difference Rosemount Model 104-MN-100C matched platinum. resistance-elements in Teledyne-Geotech Model'327 aspirated radiation.
shields, wired in a Wheatstone bridge network.
l l
1 1 of 1
N 1
1 l'
TABLE 2.5-5 I 0
BRADLEY FLD. WIND '- STABIL'ITY
SUMMARY
~
STABILITY CLASS - A -~ 3 PERIOD: ANNUAL -1/ 1/49 TO 12/31/75 Number.of Hourly Observations !
. Winds. Wind Speed (raph)
From 1-3 4-7 8-12 13-18 '19-24 25+ Total-
.1 N 35 -41 0 0 0 -0 76 l
NNE 12 30: -0 0 0 0 42 ji l
NE 26 50 0 0 -0 0 76 -
ENE 19- 24 0 0 0 0- 43 E 11 19 0 0 0 0 30 1 ESE 12 14 0 0 0 0 26 SE 18 34 0 0 0 0 52 SSE 15 38 0 0 0 0 53' .
1 S 35 63 0 0 0 0 98 )
SSW 14 34 0. 0 0 0 48 SW 28 43 0 0 0 0 71 WSW 15 26 0 0 0 0 41 W 18 29 0 0 'O O 47 WNW 11 20 0 0 0 0 31 NW 18 24 0 0 0 0 42 NNW 12 24 0 0 0 0 36 Total 299 513 0 0 0- 0 812 i
Number of Calm Observations -
289 Total Number of Observations -
1101 1 of 1
I l
TABLE 2.5-7 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY. CLASS - C - 4 PERIOD: ANNUAL 1/ 1/49 TO 12/31/75
~
Number of Hourly Observations Winds Wind Speed (mph)
From 1-3 4-7 8-12 13-18 19-24 25+ Total N 468 705 814 74 0 0 2061 NNE 189 356 493 33 0 0- 1071 NE 240 369 349 22 0 0 980 l ENE 97 95 96 6 0 0 294 {
E 87 99 61 6 0 0 253 ESE 108 81 48 2 0 0 239 SE 230 197 141 5 0 0 573 SSE 189 260 322 32 0 0 803 l S 307 582 940 103 0 0 1932 SSW 141 258 598 89 0 0 1086 SW 222 291 544 58 0 0 1115 1 I
WSW 183 214 353 54 0 0 804 W 257 224 464 49 0 0 994 WNW 222 203 472 91 0 0 988 I
NW 270 281 542 73 0 0 1166 NNW 249 286 478 57 0 0 1070
~
Total 3459 4501 6715 754 0 0 15429 ;
l Number of Calm Observations -
1217 Total Number of Observations -
16646 l
l 1 of 1 1
.. 1 I
- l TABLE 2.5-8 ;
.l BRADLEY ' FLD. WIND - STABILITY
SUMMARY
1' STABILITY CLASS - D -
PERIOD: ANNUAL 1/ 1/49 TO 12/31/75 Number of Hourly Observations Winds Wind Speed (mph)
From- 1-3 4-7 8-12 13-18. 19-24 25+ Total N 1130 3698 5167 3321 417 78 13811 :
NNE 597 1546 1940 1557 356 73 6069 .)
NE 661 '1180 1306 942 193 77 4359 ENE 276 447 429 231 42 12 1437 E 268 441 364 185 24 6 1288 ESE 254 486 368 130 11 2 1251 SE 491 1053 832 261 37 7 2681 SSE 459 1543 2198 1173 118 23 5514 l S 696 2924 6017 4344 597 69 14647 SSW 300 939 2474 2427 301 54 6495 SW 345 1111 1992 1891 196 12 5547-WSW 277 667 1018 1372 252 57 3643 l W 362 847 1293 2036 525 142 5205 WNW 318 781 1831 4779 1564 512 9785 NW 495 1197 2513 5382 1577 326 11490 NNW 550 1649 2154 2445 496 98 7392 Total 7479 20509 31898 32478 67E 1548 100616 Number of Calm Observations -
2204 Total Number of Observations - 102820 1 of 1
p
. TABLE 2.5-9 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - E -
PERIOD: ANNUAL 1/ 1/49 TO 12/31/75 Number of Hourly Observations Winds Wind Speed-(mph)
From 1-3 4 8-12 13-18 19-24 25+ Total
-N ~0 781 1013- 0 0 0 1794 NNE O 215 174 0 0 0' 389 NE O 172 70 0 0 0 242 ENE O 53 28 0 0 0 81 E O 57 31 0 0 0 88 ESE O 101 19 0 0 0 120 SE O 316 93 0 0 0 409 SSE O 656 426 0 0 0 1082 S 0 1383 1589 0 0 0 2972, SSW 0 436 590 0 0 0 1026 SW 0 492 747 0 0 0' 1239.
W5V 0 325 449 0- 0 0 774 W 0 410 887 0 0 0 1297 WNW 0 385 1417 0 0 0 1802 NW 0 534 1867 0 0 0 2401 NNW 0 426 824 0 0 0 1250 Total 0 6742 10224 0 0 0 16966 Number of Calm Observations -
0 Total Number of Observations -
16966 1'of 1
/> ;
i____..______.____________
_m._
I
.i TABLE 2.5-10 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY. CLASS - F -
PERIOD: ANNUAL 1/ 1/89-TO 12/31/75 Number of Hourly Observations I Winds Wind Speed (mph)
From 1-3 4-7 8-12 13-18 19 25+ Total u 465 1269 0 0 0 0 1734 ,
NNE 199 314 0 0 0 0- 513 NE 202 219 0 0 0 0 421 ENE 86 84 0 0 0- 0 .170 I E 110 55 0 0 0 0 165 l
ESE 95 77 0 0 0 0 172 SE 239 329 0 0 0 0 568 SSE 267 673 0 0 0 0 940 S 418 1666 0 0 0 0 2084 SSW 173 568 0 0 0 0 741 SW 239 838 0 0 0 0 1077 WSW 167 773 0 0 0 0 940 W 264 1154 0 0 0 0 1418 WNW 248 1120 0 0 0 0 1368 l
NW 310 1257 0 0 0 0 1567 NNW 237 994 0 0 0 0 1231 .. j Total 3719 11390 0 0 0 0 15109 Number of Calm Observations -
1075 l Total Number of Observations -
16184 i
1 of 1 ;
t
TABLE 2.5-11 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - G -
PERIOD: ANNUAL 1/ 1/49 TO.12/31/75 4 Number of Hourly Observations Winds- Wind Speed (mph)
,From 1-3 4-7 8-12 13-18 19-24 25+ Total N 803 0 0 0 0 0 803 NNE 295 0 0 0 0 0 295 NE 312 0 0 0 0 0 312 ENE 138 0 0 0 0 0 138 E 122 0 0 0 0 0 122 ESE 129 0 0 0 0 0 129 SE 428 0 0 0 0 0 428 SSE 450 0 0 0 0 0 450 S 713 0 0 0 0 0 713 SSW 309 0 0 'O O O 309 SW 443 0 0 0 0 0 443 WSW 463 0 0 0 0 0 463 W 713 0 0 0 0 -0 713 WNW 668 0 0 0 0 0 668
( NW 702 0 0 0 0 0 702 NNW 463 0 0 0 0 0 463 l Total 7151 0 0 0 0 0 7151 Number of Calm Observations -
2456 Total Number of Observations -
9607 1 of 1
1 TABLE 2.5-12 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - ALL-PERIOD: ANNUAL 1/ 1/49 TO 12/31/75 ,
Number of Hourly Observations Winds Wind Speed (mph)
From 1-3 4 -7 8-12 13-18 19-24 25+ Total N 3339 6811 7147 3395 417 78 21187 NNE 1566 2725 2746 1590 356 73 9056 NE 1784 2260 1830 964 193 77 7108 ENE 778 806 592 237 42 12 2467 E 763 754 472 191 24 6 2210 ESE 727 838 451 132 11 2 2161 SE 1696 2089 1111 266 37 7 5206 SSE 1589 3368 3025 1205 118 23 9328 S 2535 6998 8761 4447 597 69 23407 SSW 1122 2459 3797 2516 301 54 10249 SW 1511 2983 3406 1949 196 12 10057 WSW 1279 2149 1896 1426 252 57 7059 W 1809 2802 2734 2085 525 142 10097 WNW 1625 2644 3800 4870 1564 512 15015 NW 2041 3442 5035 5455 1577 326 17876 1
NNW 1708 3539 3551 2502 496 98 11894
~
Total 25872 46667 S0356 33232 6706 1548 164379 Nunber of Calm Observations -
7994 Total Number of Observations - 172373 1 of 1 1
TABLE 2.5-13 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - A -
PERIOD: ANNU,'G 1/ 1/75 TO 12/31/75 Number of Hourly Observations Winds Wind speed (mph)
From 1-3 _4 -7 8-12 13-18 19-24 2S+ Total N O 1 0 0 0 0 1 NNE O O O O O O O NE- 0 3 0 0 0 0 3 ENE O 1 0 0 0 0 1 E O 1 0 0 0 0 1 ESE O 1 0 0 0 0 1
'[ SE O 1 0 0 0 0 1 SSE O 2 0 0 0 0 2 S 1 2 0 0 0 0 3 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 1 0 0 0 0 1 W 0 1 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 1 0 0 0 0 0 1 NNW 0 1 0 0 0 0 1 Total 2 15 0 0 0 0~ 17 Number of Calm Observations -
2 Total Number of Observations -
19 >
l , of 1
TABLE 2.5-14 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - B -
PERIOD: ANNUAL 1/ 1/75 TO 12/31/75 Number of Hourly Observations Winds Wind Speed (mph)
From 1-3 4-7 8-12 13-18 19-24 25+ Total N 6 6 4 0 0 0 16 NNE 6 1 5 0 0 0 12 NE 8 1 0 0 0 0 9 ENE 2 1 0 0 0 0 3 E 2 0 0 0 0 0 2 ESE O 3 1 0 0 0 4 SE 5 4 3 0 0 0 12 SSE O 4 0 0 0 0 4 S 5 5 4 0 0 0 14 SSW 3 6 4 0 0 0 13 SW 1 3 1 0 0 0 5 WSW 2 4 0 0 0 0 6 W 4 2 1 0 0 0 '7 WNW 4 1 2 0 0 0 7 NW 3 8 3 0 0 0 14 NNW 3 6 2 0 0 0 11
~
Total 54 55 30 0 0 0 139 Number of Calm Observations -
8 Total Number of Observations -
147 1 of 1 i
TABLE 2.5-15 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - C -
PERIOD: ANNUAL 1/ 1/75 TO 12/31/75 Number of Hourly Observations Winds Wind Speed (mph)
From 1-3 4-7 8-12 13-18 19-24 25+ Total N 9 10 17 2 0 0 38 NNE 1 6 5 1 0 0 13 NE 4 3 1 0 0 0 8 ENE 1 3 1 0 0 0 5 E 2 2 1 0 0 0 5 ESE 4 2 1 0 0 0 7 SE 6 0 1 0 0 0 7 SSE 5 3 5 0 0 0 13 S 2 8 22 0 0 0 32 SSW 1 3 6 0 0 0 10 SW 1 6 8 0 1 0 16 WSW 6 8 4 0 0 0 18 W 2 6 7 0 0 0 15 WNW 5 4 11 1 0 0 21 IM 4 7 10 2 0 0 23 NNW 2 7 13 2 0 0 24 Total 55 78 113 9 0 0 255 Number of Calm Observa.tions -
18 Total Number of Observations -
273 1 of 1
TABLE 2.5-6 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - B -
PERIOD: ANNUAL 1/ 1/49 TO 12/31/75 Humber of Hourly Observations Winds Wind Speed (mph)
From 1-3 4-7 8-12 13-18 19-24 25+ Total N 438 317 153 0 0 0 908 NNE 274 264 139 0 0 0 677 NE 343 270 105 0 0 0 718 ENE 162 103 39 0 0 0 304 E 165 83 16 0 0 0 264 ESE 129 79 16 0 0 0 224 SE 290 160 45 0 0 0 495 SSE 209 198 79 0 0 0 486 S 366 380 215 0 0 0 961 SSW 185 224 135 0 0 0 544 SW 234 208 123 0 0 0 565 WSW 174 144 76 0 0 0 394 W 195 138 90 0 0 0 423 WNW 158 135 80 0 0 0 373 NW 246 149 113 0 0 0 508 NNW 197 160 95 0 0 0 452 Total 3765 3012 1519 0 0 0 8296 Ntunber of Calm Observations -
753 Total Ntunber of Observations -
9049 1 of 1
TABLE 2.5-16 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - D -
PERIOD: ANNUAL 1/ 1/75 TO 12/31/75 Niunber of Hotcly Observations Winds _
Wind Speed Dnph)
From 1-3 4-7 8-12 13-18 19-24 25+ Total N 25 75 109 78 5 0 292 NNE 14 26 12 18 1 0 71 .
NE 6 16 14 5 1 0 42 i
ENE 3 5 6 1 0 0 15 E 6 4 7 1 0 0 18 ESE 6 13 12 3 1 0 35 SE 9 17 15 2 1 0 44 SSE 5 37 53 14 0 0 109 S 7 57 151 85 6 0 306 SSW 4 4 45 33 1 0 87 SW 2 10 29 22 4 0 67 WSW 2 17 12 14 3 2 50 W 7 16 20 19 8 3 73 WNW 3 12 37 74 15 3 144 NW 7 15 55 106 23 4 210 NNW 7 32 47 60 4 1 151 Total 113 356 624 535 73 13 1714 Number of Calm Observations -
32 Total Number of Observations -
1746 1 of 1
TABLE 2.5-17 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - E -
PERIOD: ANNUAL 1/ 1/75 TO 12/31/75 Number of Hourly Observations Winds Wind Speed (mph)
From 1-3 4-7 8-12 13-18 19-24 25+ Total N O 20 12 0 0 0 32 NNE O 8 3 0 0 0 11 NE O 3 0 0 0 0 3 ENE O 3 0 0 0 0 3 E O 3 1 0 0 0 4 ESE O 2 0 0 0 0 2 SE O 6 1 0 0 0 7 SSE O 20 11 0 0 0 31 S 0 23 22 0 0 0 45 SSW 0 6 5 0 0 0 11 SW 0 2 4 0 0 0 6 WSW 0 7 6 0 0 0 13 W 0 14 9 0 0 0 23 WNW 0 11 24 0 0 0 35 tm 0 13 34 0 0 0 47 NNW 0 13 18 0 0 0 31 Total 0 154 150 0 0 0 304 Number of Calm Ob.servations -
0 Total Number of Observations -
304 1 of 1
TABLE 2.5-18 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - F -
PERIOD: ANNUAL 1/ 1/75 TO 12/31/75 thimber of Hourly Observations Winds Wind speed (mph)
From 1-3 4-7 8-12 13-18 19-24 2S+ Total N 10 20 0 0 0 0 30 NNE 6 8 0 0 0 0 14
.?E 5 5 0 0 0 0 10 ENE 3 1 0 0 0 0 4 E O 3 0 0 0 0 3 ESE 6 1 0 0 0 0 7 SE 3 5 0 0 0 0 8 SSE 2 19 0 0 0 0 21 S 6 22 0 0 0 0 28 SSW 2 10 0 0 0 0 12 SW 1 8 0 0 0 0 9 WSW 1 7 0 0 0 0 8 W 3 19 0 0 0 0 22 WNW 8 33 0 0 0 0 41 NW 10 32 0 0 0 0 42 NNW 8 13 0 0 0 0 21 Total 74 206 0 0 0 0 280 Number of Calm Observations -
17 Total Number of Observations -
297 1 of 1
TABLE 2.5-19 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - G -
PERIOD: ANNUAL 1/ 1/75 TO 12/31/75 Number of Hourly Observations Winds Wind Speed (mph)
From 1-3 1-2 8-12 _13-18 19-24 25+ Total N 15 0 0 0 0 0 15 NNE 6 0 0 0 0 0 6 NE 4 0 0 0 0 0 4 EIE 1 0 0 0 0 0 1 E 5 0 0 0 0 0 5 ESE 3 0 0 0 0 0 3 SE 2 0 0 0 0 0 2 SSE 4 0 0 0 0 0 4 S 7 0 0 0 0 0 7 Sb1 1 0 0 0 0 0 1 SW 2 0 0 0 0 0 2 WSW 7 0 0 0 0 0 7 W 14 0 0 0 0 0 14 WIN 9 0 0 0 0 0 9 tM 19 0 0 0 0 0 19 N!M 5 0 0 0 0 0 5
~
Total 104 0 0 0 0 0 104 Number of Calm observations -
30 l Total Number of Observations -
134 1 of 1
TABLE 2.5-20 BRADLEY FLD. WIND - STABILITY
SUMMARY
STABILITY CLASS - ALL-PERIOD: ANNUAL 1/ 1/75 TO 12/31/75 Number of Hourly Observations Winds Wind Speed Dmph)
From 1-3 4 -7 8-12 13-18 19-24 25+ Total N 65 132 142 80 5 0 424 NNE 33 49 25 19 1 0 127 NE 27 31 15 5 1 0 79 ENE 10 14 7 1 0 0 32 E 15 13 9 1 0 0 38 ESE 19 22 14 3 1 0 59 SE 25 33 20 2 1 0 81 SSE 16 85 69 14 0 0 184 S 28 117 199 85 6 0 435 SSW 11 29 60 33 1 0 134 SW 7 29 42 23 4 0 105 WSW 18 44 22 14 3 2 103 W 30 58 37 19 8 3 155 WNW 29 61 74 75 15 3 257 NW 44 75 102 108 23 4 356 NNW 25 72 80 62 4 1 244 Total 402 864 917 544 73 13 2813 Number of Calm Observations -
107 Total Number of Observations -
2920 l
1 of 1
2.6 ONE.ITE METEOROLOGICAL DATA NOT CONFORMING TO REGULATORY GUIDE 1.23 Enclosure 2, Item 6 If recent on-site meteorological data are not available, if the meteorological measurements program does not meet the commendations and intent of Regulatory Guide 1.23:
- a. Provide the best available meteorological data in the format described in Item 5.a above.
- b. Describe the representativeness of the available data with respect to on-site and near-site atmospheric transport and diffusion conditions, and with respect to expected long-term conditions at and near the site.
- c. Provide a description of the meteorological measurements used for collection of the data presented. This description should include the location of the sensors with respect to the power plant (s) and other prominent topographic features (including buildings) and accuracy of the instrumentation.
- d. Provide a commitment to establish a program to meet the recommendations and intent of Regulatory Guide 1.23, or provide sufficient justification to allow the present program to remain unchanged.
RESPONSE
This item does not apply to Connecticut Yankee, since the onsite meteorological data have been recently collected, and are in conformance to Regulatory Guide 1.23.
l l
l 2.6-1
2.7 DESCRIPTION
OF AIRFLOW TRAJECTORY REGIMES Enclosure 2, Item 7 Describe air flow trajectory regimes of importance in transporting effluents to the locations for which dose calculations are made.
Response
'1he Connecticut Yankee Nuclear Plant, in Haddam Neck, is located sufficiently northward of the Long Island Sound (about 13 miles) to be only slightly affected by any distantly penetrating sound breezes. These sound breezes occur during the mid-spring to late-summer (April through September) months, when Long Island Sound is generally colder than the land. When synoptic-scale meteorological conditions are weak and not very well established, a shallow flow from water to land develops during the late morning to late afternoon hours near the coast. This airflow reversal phenomenon is called a " sound breeze." At the Connecticut Yankee Nuclear Plant, it is unlikely that more than one percent of the annual period has winds that have their trajectory affected by the sound breeze.
The Plant is located on the Connecticut River Valley, at a point where the orientation is WNW-ESE. Katabatic winds occasionally drain down the valley walls, with some degree of valley flow as evidenced by an increase in frequencies from the WNW and ESE sectors. Topographic relief in the general vicinity of the Plant is slight to moderate, with some air trajectory reversals in the vicinity of specific topographic obstacles. However, these reversals are also ot small order of magnitude spatially, and occur infrequently.
Hours of thunderstorm activity, squall line passage, and frontal passage, are comparatively low within the vicinity of Haddam Neck. Airflow reversals as a result of their presence are minimal; since these meteorological phenomena are short-lived and transitional, generally affecting the overall local airflow one to three percent of the year. Based on the short duration of these phenomena, as compared to an overall annual period, the airflow reversal effect due to the above phenomena is also relatively insignificant.
In order to conservatively account trajectory reversals with the Gaussian for the effect of airflow single-line trajectory mdel, the terrain recirculation factor (It) , shown in Figure 2 of Regulatory Guide 1.111, was applied to all continuous release X/Q and D/Q calculations.
This factor assunes that the sam air is advected four times over the same receptor location, at distances of 1,200 meters or less from the plant, approaching unity at further distances. The application of the Figure 2 Regulatory Guide 1.111 terrain recirculation factors more than adequately 2.7-1
compensates for the level of air tra ;cetory reversul that would be experienced at Haddam Neck.
2.7-2
2.8 F POGRAPHICAL INFORMATION Enclosure 2, Item 8 Provide a map showing the detailed topographical features as modified by the plant, on a large scale, within a 10-mile radius of the plant; and a plot of the maximum topographic elevation versus distance from the center of the plant in each of the sixteen 22-1/2 degree cardinal compass point sectors (centered on ;
true north) , radiating from the center of the plant, to a distance of 10 miles.
Response
In Volume 1 of CYAPC's 6/4/76 letter of partial compliance with Appendix I to 10CFR50 (Reference 3) , detailed topographical descriptions within a 10-mile radius of the site were provided in Figures 3-1 through 3-9.
2.8-1 1
2.9 Intermittent Airborne Release Data Enclosure 2, Item 9 Provide the dates and times of radioactivity releases from intermittent sources by source location based on actual plant operation and, if available, appropriate hourly meteorological data (i.e., wind direction and speed, and atmospheric stability) during each period of release.
Response
The two sources of intermittent airborne radioactive releases are the containment purges and the waste gas decay tanks. The release point is the plant stack.
The first year of operational " break in" of the augmented gaseous waste treatment system was completed in June 1976. The first full year of representative operating experience is now being acquired. The experi-ence so far during the period 8/10/75 through 7/01/76 has been that the average hold up time for any tank is 80 days and the average duration of release is about 7.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
The containment cannot be purged during plant operation. The purging, etcept for 1972 has been done during the refueling shutdown. In 1972 two additional purges occurred owing to a faulty yoke in the isolation valve on the containment purge bypass line. The duration of the purges l
are given below for the period 1970 through July 1976, 1970: Start 14:45 on 4-22-70 End 08:30 on 6-23-70 2.9-1
1971: Start 17:40 on 4-17-71 End 11:00 on 5-19-71 1972: Start 10:25 on 1-18-72 End 15:00 on 1-18-72 Start 20:36 on 6-13-72 End 21:30 on 7-08-72 Start 12:55 on 12-19-72 End 13:47 on 12-19-72 1973: Start 00:21 on 6-04-73 End 16:15 on 6-13-73 Start 16:10 on 7-20-73 End 15:50 on 12-06-73 1974: Start 23:00 on 4-05-74 End 00:40 on 4-07-74 1975: Start 09:56 on 5-20-75 End 20:30 on 6-22-76 1976: Start 03:13 on 5-26-76 End 24:00 on 6-30-76 2.9-2
Section 2 References
- 1. United States Nuclear Regulatory Commission,. " Calculation of Intermittent (Purge) Releases When Using Joint Frequency Data." Distributed during Public Meeting at Bethesda, Maryland, May 13, 1976.
- 2. United States Nuclear Regulatory Commission, Office of Standards Develoinent, Regulatory Guide 1.111 (for comment),
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous iffluenta in Routine Releases from Light-Water-Cooled Reactors," March, 1976.
- 3. Connecticut Yankee Atomic Power Cbmpany " Demonstration of Compliance with 10CFR50 Appendix I," Volume 1, June 4, 1976.
- 4. United States Nuclear Regulatory Commission, Office of Standards Development, Regulatory Guide 1.23, "Onsite Meteorological Programs," February, 1972.
- 5. Connecticut Yankee Atomic Power Company,'" Demonstration of Compliance with 10CFR50 Appendix I," Volume 2, June 4, 1976.
- 6. National Oceanic and Atmospheric Administration, Environmental Data Service, National Climatic Center, Bradley International Airport (Windsor Locks) Meteorological Data from 1/1/49-12/31/75 (on magnetic tape) , Asheville, North Carolina, 1976.
- 7. Draft Regulatory Guide 1.112, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors," USNRC, April, 1976.
- 8. NUREG-0017, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors," USNRC, April, 1976.
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