ML20138G627
| ML20138G627 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/19/1996 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20138G515 | List: |
| References | |
| PROC-961219, NUDOCS 9705060347 | |
| Download: ML20138G627 (200) | |
Text
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i n t OFFSITE DOSE CALCULATION MANUAL FOR
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l GEORGIA POWER COMPANY l ! EDWIN I. HATCH NUCLEAR PLANT l 1 l l s I l Revision 11 December 19, 1996
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1 l Hatch ODCM EFFECTIVE P3frI.E Revision No, Qg33 gggg i 11 12/96 11 11 12/96 , iii 8 1/94 i iv 10 7/95 v, vi 9 2/94 . vii 10 7/95 l viii 11 12/96 ix 8 1/94 ' i 1-1 10 . 7/95 2-1 10 , 7/95 2-2 9 2/94 2-3 8 1/94 2-4 10 . 7/95 2-5 thru 2-6 8 1/94 i l 2-7 10 7/95 2-8 thru 2-9 8 1/94 2-10 10 7/95 2-11 8 1/94 2-12 10 7/95 2-13 10 7/95 2-14 thru 2-33 b 1/94 2-34 9 2/94 2-35 thru 2-47 8 1/94 3-1
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10 7/95 3-2 9 2/94 3-3 8 1/94 3-4 10 7/95 3-5 8 1/94 3-6 8 1/94 3-7 10 7/95 " 3-8 8 1/94 3-9 8 1/94 3-10 10 7/95 1 3-11 10 7/95 3-12 8 1/94 3-13 10 7/95 i 3-14 8 1/94 !
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3-15 10 7/95 3-16 10 7/95 3-17 thru 3-30 8 1/94 3-31 10 7/95 3-32 thru 3-41 8 1/94 i 3-42 thru 3-43 10 7/95 l 3 -4 4 thru 3 -55 8 1/94 4-1 thru 4-3 10 7/95 i 4-4 thru 4-8 8 1/94 l 4-9 thru 4-10 10 7/95 4-11 11 12/96 4-12 thru 4-19 8 1/94 5-1 10 7/95 5-2 thru 5-4 8 1/94 6-1 thru 6-6 8' 1/94 7-1 10 7/95 7-2 11 12/96 7-3 10 7/95 7-4 thru 7-7 10 7/95 8-1 thru 8-20 8 1/94 8 1/94 9-1 thru 9-45 10-1 thru 10-8 10 7/95 i Rev. 11, 12/96 l
Hat'ch ODCM PELE OF CONTENTS .O Eara \g i l EFFECTIVE PAGE LIST . . . . . . . . . . . . . . . . . . . . . . . . . . .
. . . . . . 11 TABLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . .
.. . . . . . . . . . v LIST OF TABLES . . . . . . . . . . . . . . . . . .
vii LIST OF FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . REFERENCES ............................... viii 1-1 CHAPTER 1: INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . 2-1 CHAPTER 2: LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . 2-1 2.1 LIMITS OF OPERATION 2-1 2.1.1 Licuid Ef fluent Monitorina Instrumeritation Control
- 2-7 2.1.2 Licuid Effluent Concentration Control 2-10 l 2.1.3' Licuid Effluent Dose Control Licuid Radwaste Treatment System Control 2-12 2.1.4 Systems 2-13 2.1.5 Maior Chances to Licuid Radioactive Waste Treatment
\ 2-14 2.2 LIQUID RADWASTE TREATMENT SYSTEM 2-17 2.3 LIQUID EFFLUENT MONITOR SETPOINTS 2-17 2.3.1 General Provisions Recardino Setooints 2-19 2.3.2 Setooints for Radwaste System Discharce Monitors 2-27 2.3.3 Setooints for Monitors on Normally Low-Radioactivity Streams 2-29 2.4 LIQUID EFFLUENT DOSE CALCULATIONS 2-29 2.4.1 Calculation of Dose 2-30 2.4.2 Calculation of A.3 2-31 2.4.3 Calculation of CFiy , 2-41 2.5 LIQUID EFFLUENT DOSE PROJECTIONS 2-41 2.5.1 Thirtv-One Day Dose Proiections 2-41 2.5.2 Dose Proiections for Specific Releases 2-42 2.6 DEFINITIONS OF LIQUID EFFLUENT TERMS 3-1 CHAPTER 3: GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . 3-1 3.1 LIMITS OF OPERATION 3-1 3.1.1 Gaseous Effluent Monitorina Instrumentation Control 3-7 3.1.2 Gaseous Effluent Dose Rate Control 3-11 3.1.3 Gaseous Effluent Air Dose Control 3-13 D Q 3.1.4 Control on Gaseous Effluent Dese to a Member of the Public l 1 11 Rev. 11, 12/96 )
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f j
J Hatch ODCM TABLE OF CONTENTS (Continued 1 1 i EAGT. 3.1.5 Gaseous Radwaste Treatment System Control 3-15 , Systems 3-16 3.1.6 Maior Chances to Gaseous Radioactive Waste Treatment 3-17 4 3.2 GASEOUS RADWASTE TREATMENT SYSTEM 3-19 a 3.3 GASEOUS EFFLUENT MONITOR SETPOINTS 3-19 i 3.3.1 General Provisions Recardine Noble Gas Monitor Setooints 3.3.2 Setooint for the Final Noble Gas Monitor on Each Release 3-21 Pathway 3-26 3.3.3 Setooints f or Noble Gas Monitors on Ef fluent Source Stre=== 3-29 3.3.4 Determination of Allocation Factors. AC 3-31 3.3.5 Setoolnts f or Noble Gas Monitors with Soeeial Reauirements Setnoints for Particulate and Iodine Monitors 3-32 3.3.6 3-33 3.4 GASEOUS EFFLUENT COMPLIANCE CALCULATIONS 4 Dose Rates at and Beyond the Site Boundary 3-33 3.4.1 Noble Gas Air Dose at or Beyond Site Boundary 3-35 j 3.4.2 3.4.3 Dese to a Member of the Public at or Beyond Site Boundary 3 39 , 3-42 3.4.4 Dose Calculations to Sucoort Other Reauirements 3-47 3.5 GASEOUS EFFLUENT DOSE PROJECTIONS 3-47 3.5.1 Ibirtv-One Day Dose Proieetions 3-48 3.5.2 Dose Prciections for Soecific Releases 3-49 3.6 DEFINITIONS OF CASEOUS EFFLUENT TERMS [ - a
. . . . . . . 4-1 CHAPTER 4: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4-1 4.1 LIMITS OF OPERATION 4-1 4.1.1 Radiolecical Environmental Monitorino 4-9 4.1.2 Land Use Census 4-11 4.1.3 1Dterlaboratory Comoarison Procram 4-12
' 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS
. . . . . . . . . . . . . . . . . 5-1 CHAPTER 5: TOTAL DOSE DETERMINATIONS
} 5-1 ; 5.1 LIMIT OF OPERATION 5-1 l 5.1.1 Aonlicability 5-1 5.1.2 Actions I 5-2 5.1.3 Surveillance Recuirementa 5-2 I 5.1.4 Basis 5-3 J 5.2 DEMONSTRATION OF COMPLIANCE CHAPTER 6: POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR
. . . . . . . . . . . . 6-1 ACTIVITIES INSIDE THE SITE BOUNDARY 6-1 I
6.1 REQUIREMENT FOR CALCULATION 6-1 6.2 CALCULATIONAL METHOD l Rev. 8, 1/94 111
_ _ _ ~ _ . - - . .- Match ODCM TABLE OF COnir NTS (Continued) 4 P.EsE t 7-1 $ CHAPTER 7: REPORTS .......................... 7-1 T ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l 7.1 7-1 1 7.1.1 Recruir--- nt for Report 7-1 7.1.2 Renort contents 7-3 [ RADIOhCTIVE EFFLUENT RELEASE REPORT l 7.2 7-3 7.2.1 Reauir'- nt for Renort 7-3 } 7.2.2 Renort contente 7-7 ) 7.3 MONTHLY OPERATING REPORT 7-7 7.4 SPECIAL REPORTS ! 8-1 ; CHAPTER 8: METEOROLOGICAL MODELS . . . . . . . . . . . . . . . . . . . 8-1 1 1 8.1 ATMOSPHERIC DISPERSION 8-1 I 8.1.1 Ground-Level Releases 8-3 B.1.2 Elevated Releases 8-4 i 8.1.3 Mixed-Mode Releases 8-5 I RELATIVE DEPOSITION l 8.2 ' 8-5 8.2.1 Ground-Level Releases 8-5 8.2.2 Elevated Releases 8-6
- 8.2.3 Mixed-Mode Releases 8-7 8.3 ELEVATED PLUME DOSE FACTORS CHAPTER 9: METHODS AND PARAMETERS FOR CALCULATION OF GASEOUS EFFLUENT 9-1 l PATHWAY DOSE FACTORS, Rg . . . . . . . . . . . . . . . . . .
9-1 I 9.1 INHALATION PATHWAY FACTOR 9-2 9.2 GROUND PLANE PATHWAY FACTOR 9-3 9.3 GARDEN VEGETATION PATHWAY FACTOR 9-6 9.4 GRASS-COW-MILK PATHWAY FACTOR 9-10 9.5 GRASS-GOAT-MILK PATHWAY FACTOR 9-14 , 9.6 GRASS-CON-MEAT PATHWAY FACTOR !
. . . . . . . . . . . 10-1 l CHAPTER 10: DEFINITIONS OF EFFLUENT CONTROL TERMS 10-1 l 10.1 TERMS SPECIFIC TO THE ODCM 10-6 l l 10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS l l
l I i iv Rev. 10, 7/95 l
__ m _ _ _ _ _ . __ _ _ m--_ .- - . _ _ _ _ . _ . . _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ . -- . __ ' Match ODcM
. LIST OF TABLES l
F.ans Table 2-1. Radioactive Liquid Effluent Monitoring Instrumentation 2-3 Table 2-2. Radioactive Liquid Ef fluent Monitoring Instrumentation surveillance Requirements 2-5 Table 2-3. Radioactive Liquid Waste sampling and Analysis Program 2-9 Table 2-4. Applicability of Liquid Monitor Setpoint Methodologies 2-13 Table 2-5. Parameters for Calculation of Doses Due to Liquid Effluent Releases 2-34 l Table 2-6. Element Transfer Factors 2-35 Table 2-7. Adult Ingestion Dose Factors 2-36 Table 2-8. Site-Related Ingestion Dose Factors, A , 2-39 Table 3-1. Radioactive Gaseous Effluent Monitoring Instrumentation 3-3 Table 3-2. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3-5 Table 3-3. Radioactive Gaseous Waste Sampling and Analysis Program 3-9 Table 3-4. Applicability of Gaseous Monitor setpoint Methodologies 3-20 Table 3-5. Dose Factors for Exposure to a semi-Infinite Cloud of Noble Gases 3-37 Table 3-6. Dose Factors for Exposure to Direct Radiation from Noble Gases in an Elevated Finite Plume 3-38 Table 3-7. Attributes of the Controlling Receptor , 3-41 3-44 Table 3-8. R,;pj for Ground Plane Pathway, All Age Groups Table 3-9. Raipj for Inhalation Pathway, Child Age Group 3-45 3-46 Table 3-10. R,;p; for Garden Vegetation Pathway, Child Age Group Table 4-1. Radiological Environmental Monitoring Program 4-4 Table 4-2. Reporting Levels for Radioactivity Concentrations in Environmental Samples 4-7 Table 4-3. Values for the Minimum Detectable concentration 4-8 Table 4-4. Radiological Environmental Monitoring Locations 4-13 Table 6-1. Attributes of Member of the Public Receptor Locations Inside the SITE BOUNDARY 6-3 Table 8-1. Terrain Elevation Above Plant Site Grade 8-10 Table 9-1. Miscellaneous Parameters for the Garden Vegetation Pathway 9-5 Table 9-2. Miscellaneous Parameters for the Grass-Cow-Milk Pathway 9-9 Table 9-3. Miscellaneous Parameters for the Grass-Goat-Milk Pathway 9-13 Table 9-4. Miscellaneous Parameters for the Grass-Cow-Meat Pathway 9-17 Table 9-5. Individual Usage Factors 9-18 Table 9-6. stable Element Transfer Data 9-19 Table 9-7. Inhalation Dose Factors for the Inf ant Age Group 9-20 v Rev. 9, 2/94
_ _ . _ _. . . - _ . ._. - - - _ ~ . _ . - _ . .. - - . . Match ODCM l LIST OF TERfFS (Continuedi EMil Q ,/ \ Table 9-8. Inhalation Dose Factors for the Child Age Group 9-23 l Table 9-9. Inhalation Dose Factors for the Teenager Age Group 9-26 l i < Table 9-10. Inhalation Dose Factors for the Adult Age Group 9-29 Table 9-11. Ingestion Dose Factors for the Infant Age Group 9-32 Table 9-12. Ingestion Dose Factors for the Child Age Group 9-35 Ingestion Dose Factors for the Teenager Age Group 9-38 Table 9-13. Table 9-14. Ingestion Dose Factors for the Adult Age Group 9-41 4 Table 9-15. External Dose Factors for Standing on contaminated Ground 9-44 l i i i 1 1 l l O l l O vi Rev. 9, 2/94
Hatch ODCM LIST OF FIGURES EMIE i Unit 1 Liquid Radwaste Treatment System 2-15 Figure 2-1. Unit 2 Liquid Radwaste Treatment System 2-16 - Figure 2-2. Schematic Diagram of the Condenser Offgas Treatment System 3-18 Figure 3-1. 4-15 Figure 4-1. Sampling Location Map, Site Periphery
- Figure 4-2. Sampling Location Map Beyond Site Periphery, North and 4-16 West of Site ,
Figure 4-3. Sampling Location Map Beyond Site Periphery, South and West of site 4-17 Sampling Location Map Beyond Site Periphery, East of Site 4-18
- Figure 4-4.
Figure 4-5. Location of Additional Control Station for TLDs and Vegetation 4-19 j i Vertical Standard Deviation of Material in a Plume (c,) 8-11 l Figure 8-1. 1 Terrain Recirculation Factor (K,) 8-12 l Figure 8-2. Plume Depletion Effect for Ground Level Releases 8-13
- Figure 8-3.
i Plume Depletion Effect for 30-Meter Releases 8-14 j Figure 8-4. Plume Depletion Effect for 60-Meter Releases 8-15 Figure 8-5. Plume Depletion Effect for 100-Meter Releases 8-16 Figure 8-6. Relative Deposition for Ground-Level Releases 8-17 Figure 8-7.' ) 8-18 I Figure 8-8. Relative Deposition for 30-Meter Releases Relative Deposition for 60-Meter Releases 8-19 Figure 8-9. Relative Deposition for 100-Meter (or Greater) Releases 8-20 Figure 8-10. l Figure 10-1. Site Map for Effluent Controls 10-8 l i i
- O vii Rev. 10, 7/95 l
Hatch ODCM REFERENCES
; J.S. Boeglir R.E. Bellamy, W.L. Britz, and A.L. Waterfield, " Preparation f/
1. of Radiological Ef fluent Technical Specifications for Nuclear Power (_, Plants, " NUREG-0133, October 1978. l
- 2. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. NRC Reculatory Guide 1.109, March 1976.
- 3. " Calculation of Annual Doses to Man from Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR 50, October 1977.
Appendix I," U.S. NRC Reculatorv Guide 1.109. Revision 1,
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous 4.
Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. NRC Reculatory Guide 1.111,-March 1976.
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous 5.
Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. NRC Reaulatory Guide 1.111. Revision 1, July 1977.
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine 6.
Reactor Releases for the Purpose of Implementing Appendix I," U.S. NRC Reaulatory Guide 1.113, April 1977.
- 7. Edwin I. Hatch Nuclear Plant - Unit 1 Final Safety Analvsis Reoort, Georgia Power Company.
- 8. Edwin I. Hatch Nuclear Plant - Unit 2 Final Safety Analysis Report, Georgia Power Company, Georgia Power fs 9. HNP-2 Environmental Report - Ooeratino License Stace,"Edwin I. Hatch Plant - Unit 1 Company, July 1975 (including Appendix A, 1," March 1975).
('-) Preoperational Environmental Surveillance Report Number
- 10. Hatch Nuclear Plant Land Use Survey - 1987, Georgia Power Company, February 1987,
- 11. Hatch Nuclear Plant Land Use survey, Georgia Power Company, November 1987.
- 12. Hatch Nuclear Plant Land Use Survey - 1988, Georgia Power Company, November 16, 1988 and December 10, 1988.
- 13. Letter to Georcia Power comoany from Pickard. Lowe. and Garrick. Inc.,
Washington, D.C., May 11, 1987,
- 14. Letter to Georcia Power Company from Pickard. Lowe. and Garrick. Inc.,
Washington, D.C., June 3, 1987.
- 15. Letter to Georcia Power Company from Pickard. Lowe. and Garrick. Inc.,
Washington, D.C., June li, 1987.
- 16. Letter to Georcia Power Comoany from Pickard Lowe, and Garrick. Inc.,
Washington, D.C. , November 3 0, 1987.
- 17. L.A. Currie, Lower Limit of Detection: Definition and Elaboration of a Precosed Position of Radiolocical Effluent and Environmental U.S. NRC Report NUREG/CR-4007, 1984.
Measurements,
- 18. " Radiological Assessment Branch Technical Position", U.S. Nuclear Regulatory Commission, Revision 1, November 1979, i
N-Rev. 11, 12/96 viii
m _ . _ _ _ _ . _ _ . . _ - . _ _ _ . _ . . _ . _ . _ _ _ _ . _ _ _ , _ _ _ _ _ _ . _ . _ . ~ . . . _ . . _ . _ . _ _ I I Hatch ODCM l REFERENCES (Continued 1 !
- 19. D.H. Slade (ed.), Meteoroloov and Atomic Enerov - 1968, U.S. Department i l
of Commerce, July 1968.
- 20. M. Abramowitz and I.A. Stegun (eds.), Handbook of Mathematical Functiogg with Formulas. Craohs. and Mathematical Tables, National Bureau of 1 I
Standards, U.S. Department of Commerce, 1965.
- 21. M.C. Nichols and S.D. Holder, Plant Edwin I. Hatch Units 1 and 2 Thermal 4
Pla== Model Verification, Georgia Power company Environmental Affairs ! 5 center, March 1981. l i l 22. Internal Memorandum. Bill Duval to Howard Rooers, Georgia Power Company, I October 11, 1990. l l
- 23. Internal Fa=arandum. W.H. 0111ncer to D.M. Hooper, Georgia Power Company, '
j June 9, 1987. 4 24. Letter to Georcia Power Co=nany from Quantum Technoloov. Inc., Marietta, ; Georgia, June 17, 1987. 1 W.W. Meinke and T.H. Essig, "Offsite Dose Calculation Manual Guidance l
- 25. j Standard Radiological Effluent Controls for Boiling Water Reactors,"
Generic Letter 89-01 Supplement No. 1, NUREG-1302, April 1991.
- 26. D.C. Kocher, " Radioactive Decay Data Tables," U.S. DOE Report DOE / TIC- ,
I 11026, 1981.
- 27. J.E. Till and H.R. Meyer, eds., Padiolooical Assessment, U.S. NRC Report NUREC/CR-3332, 1983. i Letter to Georcia Power comoany from J.H. Davis. Health Physics
[ ] 28. l (,,/ Consultant, Lilburn, Georgia, September 17, 1990. , Letter to Georola Power CS=cany from J.H. Davis. Health Physics
- 29. ;
consultant, Lilburn, Georgia, March 25, 1991. O ix Rev. 8, 1/94
- - _ . - . _ ~ . - - - - - --. - ..- -- - . _ . . . . . - . . - . - ..
t i Match ODcM i CHAPTER 1 INTRODUCTION - ) j The Offsite Dose calculation Manual is a supporting document of the Technical l Specifications. As such, it describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous l effluents, and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm setpoints. In addition, it contains the following: i , I i s j e The controls required by the Technical Specifications, governing the radioactive effluent and radiological environmental monitoring programs. l U e Schematics ., f liquid and gaseous radwaste effluent treatment systems, which include designation of release points to UNRESTRICTED AREAS. f 4 i !
- A list and maps indicating the specific sample locations for the Radio-
- j. logical Environmental Monitoring Program.
I i j e specifications and descriptions of the information that must be included ! in the Annual Radiological Environmental Operating Report and the i Radioactive Effluent Release Report required by the Technical Specifications. l . i j The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calculations. Changes in the l calculational methods or parameters will be incorporated into the ODCM in order to ensure that it represents current methodology in all applicable areas. Any f- computer software used to perform the calculations described will be maintained j current with the ODCM. Equations and methods used in the ODCM are based on those presented in NUREG-0133 (Reference 1), in Regulatory Guide 1.109 (References 2 and 3), in Regulatory Guide 1.111 (References 4 and 5), and in Regulatory Guide 1.113 (Reference 6). O 1-1 Rev. 10, 7/95
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l Match ODcM l CHAPTER 2 LIOUID EFFLUENTS 2.1 LIMITS OF OPERATION The following Liquid Effluent Controle implement requirements established by Technical specifications section '5.0. Terms printed in all capital letters are l defined in Chapter 10. 2.1.1 Liould Ef fluent Monitorino Instrumentation control In accordance with Technical specification 5.5.4.a. , the radioactive liquid j effluent monitoring instrumentation channels shown in Table 2-1 shall be OPERAELE with their alarm / trip setpoints set to ensure that the limits specified in ; l section 2.1.2 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with section 2.3. I 2.1.1.1 Applicability i As shown in Table 2-1. D . 2.1.1.2 Actions With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, inunediately suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint to a conservative value. With less than the minimum number of radioactive liquid affluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-1. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS. When the ACTION statement or other requirements of this control cannot be met, Entry into steps need not be taken to change the Operational Mode of the unit. an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satiefied. O Rev. 10, 7/95 2-1
l 1 Hatch ODCM 2.1.1.3 surveillance Requirements
/
Each radioactive liquid effluent monitoring instrueentation channel shall be i demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in j
- Table 2-2.
1 2.1.1.4 Basis l l The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alare/ Trip } } Setpoints for these instruments shall be calculated and adjusted in accordance ] with the methodology and parameters in section 2.3 to ensure that the alare/ trip i j will occur prior to exceeding the limits of Section 2.1.2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design 1' Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. i i i !O 4 4 1 4 1 I t j 1 l I i i i I
.i O Rev. 9, 2/94 ll 2-2 l
._ ~ . ~ . . . - - . . _.
Hatch ODCM i Table 2-1. Radioactive Liquid Effluent Monitoring Instrumentation D O i OPERABILITY Requirementsa f ' Minimum Channels b OPERABLE Applicability ACTION Instrument l Gross Radioactivity Monitors Providing Automatic Termination of Release i
- 1. i j
Liquid Radwaste 100 Effluent Line 1 (1)
- 2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System 1 (2) 101 Effluent Line ,
1 C
- 3. Flowrate Measurement Devices
- a. Liquid Radwaste 102 Effluent Line 1 (1)
Discharge Canal 1 (1),(2) 102 b.
- 4. Differential Pressure Measurement Devices l
Service Water System to closed Cooling 103 O Water System 1 At all times i
- a. All requirements in this Table apply to each unit.
l
- b. Applicability of requirements is as follows: !
l Whenever the radwaste discharge valves are not locked closed. ; (1) l (2) Whenever the Service Water System pressure is below the closed cooling Water System pressure, or AP indication is not available. I
- c. Pump curves may be used to estimate flow; in such cases, ACTION statement 102 is not required.
l l l ((() 2-3 Rev. 8, 1/94 I f l l
Hatch ODCM l I 1 Table 2-1 (contd). Notation for Table 2 ACTION Statements b
- V i l
ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, affluent releases may continue l provided that prior to initiating a releases l - a. At least two independent samples are analyzed in accordance with ! Section 2.1.2.3, and l 4
- b. At least two technically qualified individuals independently verify discharge line valving and verify the release rate j the i
l calculations. , Otherwise, suspend release of radioactive af fluents via this pathway. If ' the channel remains inoperable for over 30 days, an explanation of the
; circumstances must be included in the next Radioactive Effluent Release l ;
Report. I i ACTION 101 - With the number of channels OPERABLE less than required by the ; Minimum Channels OPERABLE requirement, af fluent releases via this pathway 1 may continue, provided that once per shift grab saeples are collected and l j ] analyzed for gross radioactivity at a MINIMUM DETECTABLE CONCENTRATION no i higher than 1 x 104 pCi/mL. If the channel remains inoperable for over 30 l l days, an explanation of the circumstances must be included in the next !
- Radioactive Effluent Release Report. l ACTION 102 - With the number of channelm OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fluent releases via this pathway i may continue, provided that the flowrate is estimated at least once per 4 O
l hours during actual releases. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report. l ACTION 103 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, assure that the Service Water System effluent monitor is OPERABLE. O 2-4 Rev. 10, 7/95
1 4 5 Hatch ODCM l Table 2-2. Radioactive Liquid Ef fluent Monitoring Instrumentation Surveillance j 1 h v Requirements i 1 Surveillance Requirements a CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION TEST Instrument i I I i 1. Cross Radioactivity Monitors Providing Automatic Termination of Release ; Liquid Radwaste C Db P' i R Q ! Effluent Line
- 2. Gross Radioactivity Monitors not Providing Automatic Termination of Release l
1 Service Water System f Db M R Q ! Effluent Line l
- 3. Flowrate Measurement Devices I
- a. Liquid I Radwaste Effluent Db 'd NA R Q j Line '
i
- b. Discharge Canal Db*d NA R Q l
I 4. Differential Pressure Measurement Devices j service Water System 1 to Closed Cooling NA D NA R Water System O 2-5 Rev. 8, 1/94
Hatch ODCM { l Table 2-2 (contd). Notation for Table 2 Surveillance Requirements I 1
- a. All requirements in this Table apply to each unit. i l
- b. During releases via this pathway, l l
4
- c. In addition to the basic functions of a CHANNEL FUNCTIONAL TEST (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
(1) Instrument indicates measured levels above the alarm / trip setpoint; l I (2) Instrument indicates an isolation on high alarm; or ; (3) Instrument controls are not set in operate mode. q
- d. CHANNEL CHECK shall consist of verifying indication of flow during periods l of release. CHANNEL CHECK shall be made at least once daily on any day on J
which CONTINUOUS, periodic, or BATCH releases are made.
- e. The SOURCE CHECK shall consist of verifying that the instrument is reading onecale.
- f. In addition to the basic functions of a CHANNEL FUNCTIONAL TEST (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate that control l
O room alarm annunciation occurs if any of the following conditions exists: (1) Instrument indicates measured levels above the alarm setpoint; 1 (2) Instrument indicates a downscale failure; or l I (3) Instrument controls are not set in operate mode. j l 4 l ! i i f 1 i s 2-6 Rev. 8, 1/94
_ - - - - . - - .- .. .-- - - - . . - . . _ ~ - - . - . . . ..__ . . - . . . . _ 1 ! ! Hatch ODCM j 2.1.2 Liauid Effluent Concentration control
\
1 In accordance with Technical Specifications 5.5.4.b. and 5.5.4.c., the l f l concentration of radioactive material released in liquid effluents to , 1 UNRESTRICTED AREAS (see Figure 10-1) shall be limited at all times to ten times I the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for i radionuclides other than dissolved or entrained noble gases. For dissolved or d i entrained noble gases, the concentration shall be limited to 1 x 10 pci/mL total
- activity.
l 2 l l 2.1.2.1 Applicability j i. This limit applies at all times. l 4 i 2.1.2.2 Actions With the concentration of radioactive material released in liquid affluents to j UNRESTRICTED AREAS exceeding the limits stated in Section 2.1.2, imunediately restore the concentration to within the stated limits. j l When the ACTION statement or other requirements of this control cannot be met, j steps need not be taken to change the operational Mode of the unit. Entry into j l . an operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 2 . '1. 2 . 3 Surveillance Requirements 1 The radioactivity content of each batch of radioactive liquid waste shall be , determined by sampling and analysis in accordance with Table 2-3. The results of radioactive analyses shall be used with the calculational methods in Section { 2.3 to acaura that the concentration at the point of release is maintained within l the limits of Section 2.1.2. 4 2.1.2.4 Basis This control is provided to ensure that the concentration of radioactive materials released in liquid waste affluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR 20, Appendix B, Table l 2, Column 2. This limitation provides additional assurance that the levels of f radioactive materials in bodies of ' water in UNRESTRICTED AREAS will result in
; exposures within (1) the Section II. A design objectives of Appendix I,10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.1301 to the f population. The concentration limit for dissolved or entrained noble gases is i 2-7 Rev. 10, 7/95 4
h
- . ., _ .-_ ~ _ . - _ . _-._~. ._ - . _ _- _-. .. _ . _ . . -
l Hatch ODCM i based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Conunission on Radiological Protection
.I (ICRP) Publication 2 (1959). The resulting concentration of 2 x 10 4 was then multiplied by the ratio of the effluent concentration limit for Xe-135, stated in Appendix B, Table 2, Column 1 of 10 CFP. 20 (paragraphs 20.1001 to 20.2401), j to the MPC for Xe-135, stated in Appendix B, Table II, Column 1 of 10 CFR 20 !
4 (paragraphs 20.1 to 20.601), to obtain the limiting concentration of 1 x 10 pCi/mL. i 1 l i l i J e l 1 l
, O ,
- C I i l
i i I l I I 2-8 Rev. 8, 1/94 i n
s Hatch ODCM i Table 2-3. Radioactive Liquid Waste Sampling and Analysis Program V Sampling and Analysis Requirements a,b MINIMUM DETECTABLE Minimum CONCENTRATION Liquid Sampling Analysis Type of Activity (MDC) Release Type FREQUENCY FREQUENCY Analysis (uci/mL) PRINCIPAL GAMMA 5 E-7c p P EMITTERS Each BATCH Each BATCH I-131 1 E-6 P Dissolved and 1 E-5 < One M Entrained Gases l Batch Wast.e BATCH /M (Gamma Emitters) Release Tanks g H-3 1 E-5 p Each BATCH COMPOSITE Gross Alpha 1 E-7 Sr-89, Sr-90 5 E-8 p g Each BATCH COMPOSITE Fe-55 2 E-6
- a. All requirements in this table apply to each unit.
- b. Terms printed in all capital letters are defined in Chapter 10.
- c. For certain radionuclides with low gamma yield or low energies, or for !
certain radionuclide mixtures, it may not be possible to measure radio- l nuclides at or near the required MINIMUM DETECTABLE CONCENTRATION. Under 1 these circumstances, the required MINIMUM DETECTABLE CONCENTRATION may be l increased ir,versely proportionally to the magnitude of the gamma yield ! (i.e., SE-7/I, where I = photon abundance expressed as a decimal j fraction). In no case shall the MINIMUM DETECTABLE CONCENTRATION, as calculated in this manner for a specific radionuclide, be greater than 10 j percent of the corresponding Ef fluent Concentration Limit value specified in 10 CFR 20 Appendix B, Table 2, Colurta 2. ; I l l 9 i
\
2-9 Rev. 8, 1/94
~ - . . . - - --.c . -_ .. _ _ _ . . - . _ - - - - . - . - - . - . _
l I Hatch ODCM 2.1.3 Licruid Ef fluent oose control O In accordance with Technical Specifications 5.5.4.d. and 5.5.4.e., the dose or l dose coannitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid ef fluents released, from each unit, to UNRESTRICTED AREAS (see Figure 10-1) shall . be limited: 4
- a. During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or equal to 5 arem to any organ, and
, b. During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrom to any organ. l l f 2.1.3.1 Applicability 1 l These limits apply at all times. l i 2.1.3.2 Actions _ . _ . _ With the calculated dose from the release of radioactive materials in liquid 3 ef fluents exceeding any of the limits of Section 2.1.3, prepare and submit to the Nuclear Regulatory Commission within 30 days a Special Report which identifies l the cause(s) for exceeding the limit (s); defines the corrective actions to be taken to reduce the releases; and defines the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the limits of Section 2.1.3. This report shall also include (1) the results of radiological l analyses of the drinking water source, and (2) the radiological impact on finished water supplies with regard to the requirements of 40 CFR 141, the Safe ; 4 Drinking Water Act. l j ' t
- When thc ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an operational Mode or other specified CONDITION may be made if, as a minimum, j the requirements of the ACTION statement are satisfied.
t 2.1.3.3 Surveillance Requirements At least once per 31 days, cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined, for each unit, in accordance with Section 2.4.
!O 2-10 Rev. 10, 7/95 i
I l l l l Hatch ODCM j l 2.1.3.4 Basis D l b This control is provided to implement the requirements of Sections II.A, III.A , and IV. A of Appendix I, 10 CFR Part 50. The limits stated in Section 2.1.3 ) implement the guides set forth in Section II. A of Appendix 1. The ACTIONS stated l in Section 2.1.3.2 provide the required operating flexibility and at the same l time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material. in liquid affluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculations in Section 2.4 implement the requirements in Section III.A of Appendix I, which state that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 2.4 for calculating the doses due to the actual release rates of radioactive materials in liquid affluents are consistent with I the methodology provided in Regulatory Guide 1.109 (Reference 3) and Regulatory cuide 1.113 (Reference 6). , This control applies to the release of liquid effluents from each unit at the site. The liquid ef fluents f rom shared LIQUID RADWASTE TREATMENT SYSTEMS are to be proportioned between the units. 2-11 Rev. 8, 1/94
- - - - - . -. ._ - = _ -.-
l l Hatch ODCM 2.1.4 Liauid Radwaste Treatment System Control
?
In accordance with Technical Specifiestion 5.5.4.f., the LIQUID RADWASTE l TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the system shall be used to reduce radioactivity in liquid wastes prior to their discharge when the projected doses due to the liquid ef fluent, f rom each unit, to UNRESTRICTED AREAS (see Figure 10-1) would exceed 0.06 mrom to the total body or 0.2 mram to ' any organ of a MEMBER OF THE PUBLIC in 31 days. , 2.1.4.1 Applicability This limit applies at all times. i 2.1.4.2 Actions
\
i With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the LIQUID RADWASTE TREATMENT SYSTEM not in operation, prepare and submit to the Nuclear Regulatory Commission within 30 days a Special Report which includes the following informations l l
- a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems and the reason
(~} (,/ for inoperability,
- b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- c. Summary description of action (s) taken to prevent a recurrence.
When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 1 2.1.4.3 Surveillance Requirements Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with Section 2.5, during periods in which the discharge of untreated liquid effluent containing radioactive materials occurs or is expected to occur. The installed LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by g ( meeting the controls of Sections 2.1.2 and 2.1.3. 2-12 Rev. 10, 7/95
. _ . ~ - - . . . -- . . . . . - . . . . . ~ . . __ .- ~ ~ . _ - . ~ . . . . . . . . - - . . , - .
Hatch ODCM , 2.1.4.4 Basis J The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the UNRESTRICTED AREAS. The requirement that the appropriate portions 2 of this system be used when specified provides assurance that the releases of l radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified l limits governing the use of appropriate portions of the LIQUID RADWASTE TREATMENT SYSTEM were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. f i This control applies to the release of radioactive materials in liquid affluents l j from each unit at tne site. For units with shared radwaste systems, the liquid j effluents from the shared system are to be proportioned among the units sharing 1 that system. I 2.1.5 Maior Chances to Liould Radioactive Waste Treatment Systems Licensee initiated MAJOR CHANGES TO LIQUID RADIOACTIVE WASTE TREATMENT SYSTEMS:
- a. Shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the change was implemented, in accordance with Section 7.2.2.7.
- b. Shall become effective upon review by the Plant Review Board and approval by the Nuclear Plant General Manager. i l
O 2-13 Rev. 10, 7/95
l Hatch ODCM
)
s 2.2 LIQUID RADWASTE TREATMENT SYSTEM i The Edwin 1. Hatch Nuclear Plant is located on the south bank of the Altamaha l River, which supplies make-up water to the circulating water system and receives j blowdown from the cooling tower. There are two boiling water reactors on-the j site. Each unit is served by a separate liquid radwaste treatment systee. Schematics of the liquid radwaste treatment systems are presented in Figure 2-1 and Figure 2-2. The dotted lines indicate alternate pathways through which liquid radwaste may be routed. ] The two units release liquid radwaste to separate discharge lines. Dilution flow is furnished by the cooling tower blowdown and plant service water systems, if ] necessary. Releases from plant service water systems are to the main condenser circulating flume, or to the cooling tower blowdown discharge line when needed for additional dilution. Since each unit is served by a separate dilution stream, liquid releases may be made independently from each of the two units. Although no significant quantities of radioactivity are expected in the plant service water systems, these effluent pathways are monitored as a precautionary l measure. 1
. l 4
l l i I l l l nv 2-14 Rev. 8, 1/94
i i i Hatch ODCM l l
.UBASTE OFF STaleOARO ASCvCLE )
sumot .____.T""**""""""""**8 TAsset 8 8 1 l I Opp ETANDAAO DECYCLE : I r - - - -T- - - - - - - - - - - - - - - 1I i - - - --- - - - '! '
. I i e e WoASTE WBASTE I 88487I 8 g 4373 SAartg CONOGMBATE OGaseg I e COLLSCTOR OOLLECTOa TAmeK A HLTE R T M TAssa a STemaet TANS
,e i l 8
1l 8 l OrasTAesOAaOmsCvets i! '. I I 8 A-------4 'u r*---------------- l 1 A l PLOOR I PLOOR PLOOR I RAOtetsOss FLOOm i I neDenTOa Oa As= 1 OaAim OaA8es Omaan FILTE R Osentes SAAsPLE i'9, COLLECTOn y . , i TAast l TANE g I ', l I J
' b_......J 70 Oe0CHAmet i
' CAseAL T
/
+
; CMt MsCAL CDeSaseCAL WAKTE -
wasts """ ! TAseK - gAsspe,g TAsea a 1 i l
' Osween a rato * ! TANK LauseOav LAu=Omv QRAnat U****
TA4K '8 LIEN rigure 2-1. Unit 1 Liquid Radwaste Treatment System i 2-15 Rev. 8, 1/94 l l l
i
)
l l' Hatch ODCM f~ 5 l 4 WASTE 088 BTANOAA0 mgCYCLE sW#eE e -... . p. -.q TAME e I l ' 8 I ' 3 g a g I l y Opp sTANOano necVCLE 1 8 p . . . . . . . . . . . - - - . - ./;b - . . . . .
; i I '
l t wasta l mAsta l wastg i TO COLLECTOR A COLLECTOA ,; ,,,,, ganspLC CONDOWTE FILTER
- 8T8"'88 TANS ge 3
- TA884 8
I 18 l i i il i i i. _ . - - _ . , I I I OFFBTANOAmpagCYCLE l 3 g
,. . . - - - - - ./76 - - - -.t"b u j e g 1 , ,
' l t I e l l AN l 800NITOR PLOOR FLOOR . g PLOOR e PLOOR g OmAIN DRAIN '
DaAsN , L ORAM ' COLLECTOR PILTEM j OttesN g mg TAME 4 i TAseg it O t- - - - - - - J s. -- CANAL C"8"' CAL cusesicAL mAsTE ,
,,,7g TAME - , mg TANK o
ir CMsuecAL warts WIWTR alt 2t m TAME ( Figure 2-2. Unit 2 Liquid Radwaste Treatment System 2-16 Rev. 8, 1/94
_ -- _ _ . . _. . ._ ._ _ _ m _ l l Hatch ODCM l I s l 2.3 LIQUID EFFLUENT MONITOR SETPOINTS
- (\ l 4 2.3.1 General Provisions Recardino Setooints 1
Liquid monitor setpoints calculated in accordance with the methodology presented in this section will be regarded as upper bounds for the actual high alarm I setpoints. That is, a lower value for the high slarm setpoint may be established a or retained on the monitor, if desired. Intermediate level setpoints should be 1 established at an appropriate level to give suf ficient warning prior to reaching the high alarm setpoint. If no release is planned for a particular pathway, or f e if there is no detectable activity in the planned release, the monitor setpoint should be established as close to background as practics.1 to prevent spurious j alarms, and yet alarm should an inadvertent release occur. j I Two basic setpoint methodologies are presented below. For radwaste system discharge monitors, setpoints are determined to assure that the limits of Section , 2.1.2 are not exceeded. For monitors on streams that are not expected to contain significant radioactivity, the purpose of the monitor setpoints is to cause an alarm on low levels of radioactivity, and to terminate the release where this is possible. Section 2.1.1 establishes the requirements for liquid effluent monitoring instrumentation. Table 2-4 lists the monitors for which each of the setpoint methodologies is applicable. l l l l I 1
)
v 2-17 Rev. 8, 1/94
. ... . _ - _ - -. . __ _ . .-_~ _ _ - _ _ _ . . - . - . _ . - . _ . . - - -
l Hatch ODCM t i Table 2-4. Applicability of Liquid Monitor Setpoint Methodologies Liquid Radwaste Discharge Monitors 4 Setpoint Method Section 2.3.2 4 Release Type BATCH 3, Unit 1 or Unit 2 Liould Radwaste System Effluent ] Monitor 1D11-N007 / 2D11-N007 4 Normally Low-Kadioactivity streams with Termination or Diversion upon Alarm J i Plant Hatch has no liquid effluent streams in this category. j l J Normally Low-Radioactivity Streams with Alarm Only i Setpoint Method: Section 2.3.3
- Release Type: CONTINUOUS Unit 1 or Unit 2 Plant Service Water System Effluent i
Monitors 1D11-N008 / 2D11-N008 ]1 l i I i l A J i 1 1 4 i l i i i 4 i k l I l 2-18 Rev. 8, 1/94 4 i
r Match ODCM setnoints for Redwaste System Discharoe Monitors l 2.3.2 1 2.3.2.1 overview of Method LIQUID RADWASTE TREATMENT SYSTEM effluent line radioactivity monitors are i intended to provide alarm and automatic termination of release prior to exceeding the limits specified in section 2.1.2 at the point of release of the diluted ef fluent into the UNRESTRICTED AREA. Therefore, their alarm / trip setpoints are established to ensure compliance with the following equation (equation adapted from Addendum to Reference 1): !
#*# (2.1) 5 TE
- CECL E*f where: ,
the Ef fluent Concentration Limit corresponding to the mix CECL = of radionuclides in the effluent being considered for discharge, in pCi/mL. i e= the setpoint, in pC1/mL, of the radioactivity monitor measuring the concentration of radioactivity in the effluent line prior to g dilution and subsequent release. The setpoint represents a concen-tration which, if exceeded, could result in concentrations ; exceeding the limits of Section 2.1.2 in the UNRESTRICTED AREA. f= .the ef fluent flowrate at the location of the radioactivity monitor, in gym. F= the dilution stream flowrate which can be assured prior to the release point to the UNRESTRICTED AREA, in gpm. A predetermined dilution flowrate must be assured for use in the calculation of the radioactivity monitor setpoint. TF = the tolerance factor selected to allow flexibility in the establishment of a practical monitor setpoint which could accommodate af fluent releases at concentrations higher than the ECL ' values stated in 10 CFR 20, Appendix B, Table 2, Column 2; the tolerance factor must not exceed a value of 10. While equation (2.1) shows the relationships of the critical parameters that , determine the setpoint, it cannot be applied practically to a mixture of radio- 1 2-19 Rev. 8, 1/94
--_-m _ _ - - . - __r-, - _ _ _ _ _ . - _ _ _ - , . - - - - _ , , , , , -
.,,--.7 , ~ . , -
l Hatch ODCM l 4 nuclides with dif ferent Ef fluent Concentration Limits (ECLs) . For a mixture of radionuclides, equation (2.1) is satisfied in a practicable manner based on the 1 b calculated ECL fraction of the radionuclide mixture and the dilution stream l flowrate that can be assured for the duration of the release (Fd ), by calculating the maximum permissible af fluent flowrate (f ,) and the radioactivity monitor setpoint (c). The setpoint method presented below is applicable to the release of only one tank of liquid radwaste per reactor unit at a given time. Liquid releases must be controlled administratively to ensurir thrit this condition is met; otherwise, the setpoint method may not ensure that the limits of Section 2.1.2 are not exceeded. l 2.3.2.2 Setpoint calculation Steps stee 1: Determine the radionuclide concentrations in the liquid waste being considered for release in accordance with the sampling and analysis requirements of Secticn 2.1.2. All liquid radwastes are collected in tanks for sampling and analysis prior to release. To ensure that a representative sample can be taken from a tank, its contents will be recirculated for a minimum time period to allow adequate mixing ) of the contents. Minimum recirculation times are as follows (Reference 22): l O G Minimum Recirculation Time (minutes) Tankis) Unit 1 Unit 2 Waste sample tanks 40 40 Floor drain sample tanks 70 105 Chemical waste sample tanks 65 65 115 NA Domineralizer feed tank Laundry drain tanks 50 NA The total concentration of the liquid waste is determined by the results of all required analyses on the collected sample, as follows: {Cf = C, + [ C, + Cf + C, + { CK 8 (2.2) i I where C, = the gross concentration of alpha emitters in the liquid waste, not less than that measured in the most recent applicable composite sample. O 2-20 Rev. 8, 1/94
Hatch ODCM 1 C, = the concentration of strontium radioisotope s (Sr-89 or Sr-90) in the liquid waste, not less than that measured in the most recent , applicable composite sample. J Cr = the concentration of Fe-55 in tha liquid waste, not less than that , measured in the most recent applicable composite sample. d the concentration of H-3 in the liquid waste, not less than that Ct= measured in the most recent applicable composite sample. Cg = the concentration of gamma emitter g in the liquid waste as )
- measured by gamma ray spectroscopy performed on the sample for the
$ release under consideration. l 4 l The C term will be included in the analysis of each waste sample; terms for , g 1 gross concentrations of alpha emitters, St-89, Sr-90, Fe-55, and tritium will be included in accordance with the sampling and analysis program required for the waste stream (see Section 2.1.2). For each analysis, only radionuclides l identified and detected above background for the given measurement should be included in the calculation. When using the alternate setpoint methodology of j step 5.b, the historical maximum values of C,, C,, cf, and Cg shall be used. l ,N ' Steo 2: Determine the required dilution f actor for the mix of radionuclides detect, in the waste. 1 Measured radionuclide concentrations are used to calculate ECL fractions. The ECL fractions are used along with a safety f actor to calculate the required dilution f actor; this is the minimum ratio of dilution flowrate to waste flowrate < that must be maintained throughout the release to ensure that the limits of Section 2.1.2 are not exceeded at the point of discharge into the UNRESTRICTED AREA. The required dilution factor, RDF, is calculated as the sum of the dilution factors required for gamma emitters (RDF )yand for non-gamma-emitters j (RDFny)8 J c; RDT = b ggp 8 + [ (ST) (TT) ). (2.3) I
=
RDTy + RDTm I l O 2-21 Rev. 8, 1/94
I l Hatch ODCM o C EC '. (2.4) I t
- er T .
(SE) (TE) Ca C, C Cg
.g . f. ,
ECL ECL g' ECL a , ECL, J gg,5, MT 9 = (ST) (TE) i where ! Cj = the measured concentration of radionuclide i as defined in step 1, in pCi/mL. The C,, C,, Cg, and C: terms will be included in the calculation as appropriate. ECL; = the Effluent Concentration Limit for radionuclide i from 10 CFR Part 20, Appendix B, Table 2, Column 2 (except for noble gases as discussed below). In the absence of information regarding the 5 solubility classification of a given radionuclide in the waste stream, the solubility class with the lowest ECL shall b0 assumed. j For dissolved or entrained noble gases, the concentration shall be limited to lx10 4 yCi/mL. For gross alpha, the ECL shall be 2x10-9 pCi/mL; if specific alpha-emitting radionuclides are measured, the , ECL for the specifir radionuclide(s) should be used. i SF = the safety factor selected to compensate for statistical fluctuations and errors of measurement. The value for the safety factor must be between 0 and 1. A value of 0.5 is reasonable for j liquid releases; a more precise value may be developed if desired. TF = the tolerance factor (as defined in Section 2.3.2.1). Stoo 3: Determine the release-specific assured dilution stream flowrate. Determine the dilution stream flowrate that can be assured during the release period, designated F; d this value is the setpoint for the dilution stream flowrate measurement device. If simultaneous radioactive releases are planned f rom the same reactor unit, the unit's dilution stream must be allocated among all the simultaneous releases, whether or not they are monitored during release. Normally, only the batch tank i 2-22 Rev. 8, 1/94
. _ . . .. - - .= . . _ - - - . . - . - - ._ .. ,
l 5 Hatch ODCM effluents need be considered, unless there is detectable radioactivity in one of the normally low-radioactivity streams (see Table 2-4). Allocation of the
~]
~/ dilution stream to multiple release paths is accomplished as follows:
Tdp
- Id ( AI,p) (2.6)
,i where:
Fdp the dilution flowrate allocated to release pathway p, in gpm. 1
=
AF p = the dilution allocation factor for release pathway p. AFp may be 4 assigned any value between 0 and 1 for each active release pathway, under the condition that the sum of the AF p for all active release pathways for each unit does not exceed 1. [ Note Because the two units have separate dilution streams, the two units do not affect each other with respect to dilution allocation.) the assured minimum dilution flow for the unit, in gpm. For Plant
- Fd=
Hatch, Fd is normally established at 10,000 gpm. If more precise allocation f actor values are desired, they may be determined 4 based on the relative radiological impact of each active release pathway; this , h("'N may be approximated by multiplying the RDF of each effluent stream' by its f respective planned release flowrate, and comparing these values. If only one release pathway for a given reactor unit contains detectable radioactivity, its AFp may be assigned the value of 1, making Fdp equal to Fd* For the case where RDF s 1, the planned release meets the limits of Section 2.1.2 without dilution, and may be released with any desired effluent flowrate and i 1 dilution flowrate. Elf 2_i: Determine the maximum allowable waste discharge flowrate. For the case where RDF > 1, the maximum permissible ef fluent discharge flowrate for this release pathway, fmp (in gpm), is calculated as follows: i f mp . dP (2.7) {g,7) For the case RDF s 1, equation (2.7) is not valid. However, as discussed above, when RDF s 1, the rolesse may be made at full discharge pump capacity; the radio-2-23 Rev. 8, 1/94 k l l
. - . -. ~ . . ..- - - - . . . ~ . _ . - . ~ _ . . - _ . - . . _ - - ~-. .~- ~ . _ _ _ . . _ - - - . . - . . ~ -
I . l Hatch ODCM activity monitor eetpoint must still be calculated in accordance with Step 5 i l below. 4 NOTE 1: Discharge flowrates are actually limited by the discharge pump l i capacity. When the calculated maximum permissible release flowrate ( exceeds the pump capacity, the release may be made at full j capacity. Discharge flowrates less than the pump capacity must be achieved by throttling if this is available; if throttling is not i available, the release may not be made as planned. I i f I , NOTE 2: If, at the time of the planned release, there is detectable radio- i [ activity due to plant operations in the dilution stream, the t diluting capacity of the dilution stream is diminished. (In 1 addition, sampling and analysis of the other radioactive effluents ; af fecting the dilution stream must be suf ficient to ensure that the f liquid effluent dose limits specified in the controls of section 1 2.1.3 are not exceeded.) Under these conditions, equation (2.7) must be modified to account for the radioactivity present in the dilution stream prior to the introduction of the planned release r 1 T f C I mp = RDF , 1-{r d{ Tg i , ECLp , (2.8) wherw: Cir = the measured concentration of radionuclide i in release pathway r that is contributing to radioactivity in the dilution stream. f = the affluent discharge flowrate of release pathway r. r If the entire dilution stream contains detectable activity due to plant operations, whether or not its source is identified, f, = Fd' is the concentration in the total dilution system. This and Cir note does not apply: a) if the RDF of the planned release is 5 1; or b) if the release contributing radioactivity to the dilution stream has been accounted for by the assignment of an allocation factor. 2-24 Rev. 8, 1/94
. . . _ . . _ _ . , _ . . _ . _.. . - _ _ . - . _ . . _ _ . . < . - - ~- . ..-.-.--m ~ . .. . .~ .
4 I Hatch ODCM i i steo 5: Determine the maximum radioactivity monitor setpoint concentration. l ("~ Based on the values determined in previous steps, the radioactivity monitor setpoint for the planned release is calculated to ensure that the limits of j Section 2.1.2 will not be exceeded. Because the radioactivity monitor responds l primarily to gamma radiation, the monitor setpoint cp for release pathway p (in j pC1/mL) is based on the concentration of gamma emitters in the waste stream, as 1 i follows: 2 I j cp = Ap )[ Cg (2.9) E I i i where: l Ap = an adjustment factor which will allow the setpoint to be l - established in a practical manner to prevent spurious alarms while f a allowing a margin between -1asured concentrations and the limits l of section 2.1.2. l 1 ) Stoo 5.a. If the concentration of gamma emitters in the af fluent to ) s be released is suf ficient that the high alarm setpoint ; can be established at a level that will prevent spurious i
)
j alarms, Apshould be calculated as follows: j l I i i I 1 j Ap = x ADT ' RDT
} T (2.10) l , _dp RDT f ap j
t j where: the assured dilution factor. 1 ADF = f,p = the anticipated actual discharge flowrate for the i planned release (in gpm), a value less than f ,p. i The release must then be controlled so that the actual effluent discharge flowrate does not 4 exceed f,p at any time. Stoo 5.b. Alternatively, A pmay be calculated as follows: 2-25 Rev. 8, 1[94 I
n - - . - . . _ - . ._ -
- - . _ . - - .~. . - - . . - . . ~ . _ . _ . _ _ . . .-. . .
Hatch ODCM > W~ n7 Ap = (2.11) ( 7 sten 5.c. Evaluate the computed value of A p as follows: If A a 1, calculate the monitor setpoint, c. However, if cp is p p within about 10 percent of Cg , it may be inipractical to use this value of e. p This situation indicates that measured concentrations are approaching values which would cause the limits of Section 2.1.2 to be exceeded. Therefore, steps should be taken to reduce potential con-centrations at the point of discharge; these steps may include decreasing the planned effluent discharge flowrate, increasing the dilution stream flowrate, postponing simultaneous releases, and/or decreasing the af fluent concentrations by further processing the liquid planned for release. Alternatively, allocation factors ! for the active liquid release pathways may be reassigned. When one or more of these actions has been taken, repeat Steps 1-5 to calculate a new radioactivity monitor 3 setpoint. I Consider the If Ap < 1, the release may not be made as planned. alternatives discussed in the paragraph above, and l calculate a new setpoint based on the results of the j actions taken. l 1 2.3.2.3 Use of the Calculated Setpoint The monitor actually The setpoint calculated above is in the units yCi/mL. measures a count rate that includes background, so that the calculated setpoint must be converted accordingly: Ep +B p (2.Ta} ch = cp where: c = the monitor setpoint as a count rate. Ep = the monitor calibration factor, in count rate /(pci/mL). Monitor data for conversion between count rate and calibration operational data obtained from concentration may include 2-26 Rev. 8, 1/94
l l Hatch ODCM determining the monitor response to stream concentrations measured i [,, by liquid sample analysis. i l
\~s Sp a the monitor background count rate. In all cases, monitor
]
- background must be controlled so that the monitor is capable of (
4 responding to concentrations in the range of the setpoint value. The count rate units of c", Ep , and Bpin equation (2.7a) must be the same (cpm or eps). 2.3.3 setooints f or Monitors on Normally Low-Radioactivity Streams l Radioactivity in these streams (listed in Table 2-4 above) is expected to be at very low levels, generally below detection limits. Accordingly, the purpose of 4 these monitors is to alarm upon the occurrence of significant radioactivity in these streams, and to terminate or divert the release where this is possible. 2.3.3.1 Normal Conditions When radioactivity in one of these streams is at its normal low level, its radio-
~% activity monitor setpoint should be established as close to background as s, practical to prevent spurious alarms, and yet alarm should an inadvertent release occur.
l 2.3.3.2 Conditions Requiring an Elevated Setpoint 1 Under the following conditions, radionuclide concentrations must be determined and an elevated radioactivity monitor setpoint determined for these pathways: 4 e For streams that can be diverted or isolated, a new monitor setpoint must be established when it is desired to discharge the stream directly to the " dilution water even though the radioactivity in the stream exceeds the level which would normally be diverted or isolated. 1 e For streams that cannot be diverted or isolated, a new monitor setpoint must be established whenevert the radioactivity in the stream becomes detectable above the background levels of the applicable laboratory analyses; or the associated radioactivity monitor detects activity in the i stream at levels above the established alarm setpoint. When an elevated monitor setpoint is required for any of these ef fluent streams, 0 it should be determined in the same manner as described in section 2.3.2. Q 1 2-27 Rev. 8, 1/94 4
. _ . . . . _ . _ _ . _ . _ . _ . _ _ . . _ . _ . _ _ _ . _ . __ ._..__..__.__._..__.._.m. - _ . _ . _
i l Hatch OQqM I However, special consideration must be given to Step 3. An allocation factor must be assigned to the normally low-radioactivity release pathway under consideration, and allocation facters for other release pathways discharging simultaneously must be adjusted downward (if necessary) to ensure that the sum of the allocation factors does not exceed 1. Sampling and analysis of the normally low-radioactivity streams must be suf ficient to ensure that the liquid ef fluent dose limits specified in the controls of section 2.1.3 are not exceeded. i i I f 1 l i J' 4 3 i i i l l i o i 4 i l. d 4 4 2-28 Rev. 8, 1/94 i J 4 4
. . - . . . .- , _ . . . . - -- - _ _ . = . - - . .
l Hatch ODCM i l 2.4 LIQUID EFFLUENT DOSE CALCULATIONS
'O The following sub-sections present the methods required for ' 8 auid ef fluent dose calculations, in deepening levels of detail. Applicable ?4 < . pecific pathways
! and parameter values for the calculation of Dr ' Air, and a ire summarized in l l Table 2-5. a 4 2.4.1 Calculation of Dose , l The dose limits for a MEMBER OF THE'PUBLIC specified in Section 2.1.3 are on a j per-unit basis. Therefore, the doses calculated in accordance with this section f snust be determined and recorded on a per-unit basis, including apportionment of I releases shared between the two units. For the purpose cf implementing section 2.1.3, the dose to the maximum exposed individual due to radionuclides identified in liquid ef fluents released f rom 'each ! unit to UNRESTRICTED AREAS will be calculated as follows (equation from Ref-erence 1, page 15): m [ Ajy [ (Atf (2.12) ! D7 = Cfi T) f i . l= l b s ' where D7 = the cumulative dose commitment to the total body or to any organ f, in mrom, due to radioactivity in liquid effluents released during the total of the m time periods Atg. the site-related adult ingestion dose commitment factor, for the Air = total body or for any organ 7, due to identified radionuclide i, in (mree mL)/(h pCi). Methods for the calculation of Aj7 are presented below in Section 2.4.2. The values of Ajf to be used in dose calculations for releases from the plant site are listed in Table 2-8. Atg = the length of time period 1, over which C gi and Fg are averaged for liquid releases, in h. Cg= i the average concentration of radionuclide i in undiluted liquid effluent during time period 1, in pCi/mL. Only radionuclides 2-29 Rev. 8, 1/94
l l Hatch ODCM identified and detected above background in their respective (O samples should be included in the calculation. Fg = the near-field average dilution factor in the receiving water of l the UNRESTRICTED AREA: fg rf " (2.13) r, x z l wheres ; fg= the average undiluted liquid waste flowrate actually observed during the period of radioactivity release, in 9Pm. Fg= the average dilution stream flowrate actually observed during the period of radioactivity release, in gpm. Z= the applicable dilution factor for the receiving water l body, in the noar field of the discharge structure, during the period of radioactivity release, from ) Table 2-5. NOTE: In equation (2.13), the product (F x Z) is limited to 1000 cfs (= 448,000 gpm) or less. (Reference 1, Section 4.3.) 2.4.2 Calculation of Aj7 The site-related adult ingestion dose commitment factor, A ir, is calculatud as follows (equation adapted from Reference 1, page 16, by addition of the irrigated garden vegetation pathway): t 5 ,-A l 'w + #/ + uy crjy orir II*I'I Aj7 = 1.14 x 10 uf stfe where: 1.14 x 105 = a units conversion factor, determined by: 106 pCL/pci x 10 3 mL/L + 8'160 h/y. v 2-30 Rev. 8, 1/94
_- . _ . _ . . . ._m_____._ 4 I Hatch ODCM the adult drinking water consumption rate applicable to the plant 4 j Uw= i(_ site (L/y). 1
< D, = the dilution f actor from the near field of the discharge structure for the plant site to the potable water intake location.
l i = the decay constant for radionuclide 1 (h-I) . Values of i used in effluent calculations should be based on decay data from a ] recognized and current source, such as Reference 26. 1 i tw= the transit time from release to receptor for potable water f consumption (h). i the adult rate of fish consumption applicable to the plant site I
, Uf= 1 (k9 /y).
l l BF = the bioaccumulation factor for radionuclide i applicable to i, freshwater fish in the receiving water body for the plant site, in (pci/kg)/(pci/L) = (L/kg). For specific values applicable to the j i plant site, see Table 2-6. t tg = the transit time from release to receptor for fish consumption (h). Uy = the adult consumption rate for irrigated garden vegetation applicable to the plant site (kg/y). t ci'jy = the concentration factor for radionuclide i in irrigated garden ' vegetation, as applicable to the vicinity of the plant site, in (pci/kg)/(pci/L). Methods for calculation of CF y are presented i below in section 2.4.3. 1 DFj7 = the dose conversion factor for radionuclide i for adults, in j organ f (mrom/pci). For specific values, see Table 2-7. f I { 2.4.3 calculation of CFjy 1 The concentration f actor for radicauclide i in irrigated garden vegetation, CFjy 3 in (L/kg), is calculated as follows: 1 l i f Y 1 a 2-31 Rev. 8, 1/94 l; _____I
M Hatch ODCM 0 For radionuclides other than tritium (equation adapted from Reference 3, i equations A-8 and A-9):
-k; Ib l
= M*1
'I1~** Ei 'e , i Bgy f (1 - e y ,
e CTgy Yy AEl !Ai \ 0 For tritium (equation adapted from Reference 3, equations A-9 and A-10): I
- Ctry = #*L v (2.16) l i
I i i where: 1
. i i
M= the additional river dilution f actor from the near field of the j i discharge structure for the plant site to the point of irrigation
- water usage.
I= the average irrigation rate during the growing season (L)/(m2 .h). 4 i r= the fraction of irrigation-deposited activity retained on the 1 1 edible portions of leafy garden vegetation. Yy = the areal density (agricultural productivity) of leafy garden ] I i vegetation (kg/m 2) i fg = the fraction of the year that garden vegetation is irrigated. Bjy = the crop to soil concentration factor applicable to radionuclide i (pci/kg garden vegetation)/(pci/kg soil). 1 1 2 l P= the effective surface density of soil (kg/m 3, l lj = the decay constant f or radionuclide 1 (h"I) . Values of Aj used in effluent calculations should be based on' decay data from a recognized and current source, such as Reference 26. 4 1, = the rate constant for removal of activity f rom plant leaves by weathering (h-I). . O 2-32 Rev. 8, 1/94
l l l Hatch ODCM 1 l 1Ei = the effective removal rate for activity deposited on crop leaves D () ( h*I) calculated as: 1Ei " li+A w' j te= the period of leafy garden vegetation exposure during the growing ! season (h). l tb= the period of long-tarm buildup of activity in soil (h), th= the time between harvest of garden vegetation and human consumption (h). l Ly = the water content of leafy garden vegetation edible parts (L/kg). I
\
O . i l l I O . 1 2-33 Rev. 8, 1/94
._._._-_.__._-.._.__._____l 1
Match ODcM i l Table 2-5. Parameters for Calculation of Doses Due to Liquid Effluent Releases 1 s Dese calculation Receptor Incations: l j LLRh Vicinity of plant discharge i Drinkino Water: None + + l 1 Irriaated Garden Veoetation: None+ + l Numerical Parameters: } Parameter Value Keference ] ( Ref. 9, See. 5.1; Ref. 6, Sec. 3; l E 10 Ref. 21 [ U, O L/y (Pathway not applicable) l
- D, 1.0 + l 1
tw 12 h Ref. 3, Sec. A.2 l S 21 kg/y Ref. 3, Table E-5 l
- Ur
! tg 24 h Ref. 3, Sec. A.2 j Uy 0 kg/y (Pathway not applicable) i M 1.0 + f I No value ** i i r 0.25 Ref. 3, Table E-15 l Yy 2.0 kg/m2 Ref. 3, Table E-15 1 ) fg 1.0 +
! P 240 kg/m2 Ref. 3, Table E-15 kw 0.0021 h*I (i.e., half- Ref. 3, Table E-15 t life of 14 d) t, 1440 h (= 60 d) Ref. 3, Table E-15 tg 1.31 x 105 h (= 15 y) Ref. 3, Table E-15 24 h Ref. 3, Table E-15 th Ly 0.92 L/kg Based on Ref. 27, Table 5.16 (for lettuce, cabbage, etc.)
* - Because there is no known drinking water pathway or irrigated garden vegetation pathway downstream of the plant site, the parameters for these pathways are default values, and the usage factors.are set to 0.
+ - There is no established default value for this parameter. The most conservative physically realistic value is 1.0.
" - There is no established def ault value for this parameter. A value will be supplied if the pathway is ever observed.
++ - Confirmed during the annual river water use survey.
2-34 Rev. 9, 2/94
- . . - -- -. .- - .- - . = . . .- --
i Hatch ODCM Table 2-6. Element Transfer Factors } f_ ! I s ' Freshwater Fish ' Element , 1 H 9.0 E-01 5 C 4.6 E+03 Na 6.6 E+01 l $ P 2.5 E+04 Cr 1.5 E+02 Mn 8.9 E+01 - Fe 6.0 E+00 Co 1.7 E+02 4 Ni 1.0 E+02 Cu 4.4 E+01 Zn 2.9 E+02 Br 4.2 E+02 Rb 2.0 E+03 Sr 3.8 E+00 Y 2.5 E+01 Zr 1.9 E+02 Nb 4.1 E+01 Mo 1.8 E+02
' Tc 1.5 E+01 Ru 4.6 E+00 Rh 1.0 E+01 Ag 3.5 E+02 Sb 1.0 E+00 Te 4.0 E+02 I 4.3 E+01 Cs 5.8 E+02 Ba 5.0 E+00 La 2.5 E+01 Ce 8.4 E+01 Pr 2.5 E+01 Nd 4.6 E+01 W 1.2 E+03 Np 1.0 E+01
*- Bioaccumulation Factors for freshwater fish, in (pci/kg)/(pci/L).
They are obtained from Reference 9 (Appendix A, Table 2.3-1), except as follows: Reference 2 (Table A-8) for Sb.
\
I J 2-35 Rev. 8, 1/94 ! 1 1
I Hatch ODCM Table 2-7. Adult Ingestion Dose Factors _ ( T. Body Thyroid Kidney Lung GI-LLI Nuclide Bone Liver 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 H-3 No Data C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 l Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 No Data No Data 2.17E-05 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.66E'09 1.59E-09 5'.86E-10 3.53E-09 6.69E-07 l i Cr-51 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 . Mn-C4 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Mn-56 No Data 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 Fe-55 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 'f Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 No Data 1.88E-06 i Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data i Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 ! 1 7.10E-06 ! O V Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 ] s l ! Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 f ' No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 < Br-83 l No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 Br-84 No Data No Data 2.14E-09 No Data No Data No Data No Data Br-85 i 2.11E-05 9.83E-06 No Data No Data No Data 4.16E-06 j Rb-86 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 l Rb-88 No Data 1 ' Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 3.08E-04 No Data 8.84E-06 .No Data No Data No Data 4.94E-05 l Sr-89 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 l f l Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 ) ( 2 j They are obtained from All values are in (mram/pci ingested) . j Reference 3 (Table E-11), except as follows: Reference 2 (Table l A-3) for Rh-105, Sb-124, and Sb-125. t 4 2-36 Rev. 8, 1/94
Hatch ODCM Table 2-7 (contd). Adult Ingestion Dose Factors Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 4 Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 4 Y-93 2.6BE-09 No Data 7.40E-11 No Data No Data No Data 8.50E-05 3 Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 i < Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41E-05 Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 2.81E-06 5.30E-08 1.11E-06 6.79E-09 No Data 2.18E-06 7.95E-05 Sb-124 Sb-125 2.23E-06 2 40E-08 4.48E-07 1.98E-09 No Data 2.33E-04 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06F-07 1.09E-05 No Data 1.07E-05 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 4 Te-127m 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-127 5.79E-05 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 4 Te-129 ~ 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131m 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 Te-131 f% U 2-37 Rev. 8, 1/94
Hatch ODCM Table 2-7 (contd). Adult Ingestion Dose Factors v Bone Liver T. Body Thyroid Kidney Lung CI-LLI Nuclide I Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 f I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 l I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Co-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 ,
)
i Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 O V 2-38 Rev. 8, 1/94
Hatch ODCM Table 2-8. Site-Related Ingestion Dose Factors, A;, I V Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 c-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 Na-24 8.86E+01 8.86E+01 8.86E+01 8.86E+01 8.86E+01 8.86E+01 8.86E+01 P-32 1.10E+07 6.84E+05 4.25E+05 0.00 0.00 0.00 1.24E+06 Cr-51 0.00 0.00 9.32E-01 5.57E-01 2.05E-01 1.24E+00 2.34E+02 Hn-54 0.00 9.72E+02 1.85E+02 0.00 2.89E+02 0.00 2.98E+03 Mn-56 0.00 3.87E-02 6.86E-03 0.00 4.91E-02 0.00 1.23E+00 Fe-55 3.95E+01 2.73E+01 6.36E+00 0.00 0.00 1.52E+01 1.56E+01 Fe-59 6.14E+01 1.44E+02 5.53E+01 0.00 0.00 4.03E+01 4.81E+02 Co-58 0.00 3.00E+02 6.73E+02 0.00 0.00 0.00 6.09E+03 Co-60 0.00 8.71E+02 1.92E+03 0.00 0.00 0.00 1.64E+04
, Ni-63 3.11E+04 2.16E+03 1.04E+03 0.00 0.00 0.00 4.50E+02 Ni-65 1.72E-01 2.23E-02 1.02E-02 0.00 0.00 0.00 5.66E-01 Cu-64 0.00 2.37E+00 1.11E+00 0.00 5.97E+00 0.00 2.02E+02 Zn-65 3.35E+03 1.07E+04 4.82E+03 0.00 7.13E+03 0.00 6.72E+03 Zn-69 1.14E-07 2.19E-07 1.52E-nB 0.00 1.42E-07 0.00 3.28E-08 Br-83 0.00 0.00 3.83E-02 0.00 0.00 0.00 5.52E-02 Br-84 0.00 0.00 1.22E-12 0.00 0.00 0.00 9.61E-18 Br-85 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Rb-86 0.00 9.73E+04 4.53E+04 0.00 0.00 0.00 1.92E+04 Rb-88 0.00 1.29E-22 6.82E-23 0.00 0.00 0.00 1.78E-33 J Rb-89 0.00 1.61E-26 1.14E-26 0.00 0.00 0.00 0.00 Sr-89 2.76E+03 0.00 7.93E+01 0.00 0.00 0.00 4.43E+02 Sr-90 6.90E+04 0.00 1.69E+04 0.00 0.00 0.00 1.99E+03 Sr-91 8.95E+00 0.00 3.62E-01 0.00 0.00 0.00 4.26E+01 Sr-92 4.22E-02 0.00 1.83E-03 0.00 0.00 0.00 8.36E-01 Y-90 4.44E-01 0.00 1.19E-02 0.00 0.00 0.00 4.71E+03 Y-91m 1.04E-11 0.00 4.01E-13 0.00 0.00 0.00 3.04E-11 Y-91 8.34E+00 0.00 2.23E-01 0.00 0.00 0.00 4.59E+03 Y-92 4.60E-04 0.00 1.35E-05 0.00 0.00 0.00 8.06E+00 Y-93 3.09E-02 0.00 8.53E-04 0.00 0.00 0.00 9.80E+02 Er-95 1.37E+01 4.39E+00 2.97E+00 0.00 6.88E+00 0.00 1.39E+04 Zr-97 2.86E-01 5.76E-02 2.63E-02 0.00 8.70E-02 0.00 1.78E+04 Nb-95 5.99E-01 3.33E-01 1.79E-01 0.00 3.29E-01 0.00 2.02E+03 Mo-99 0.00 1.44E+03 2.75E+02 0.00 3.27E+03 0.00 3.35E+03 Te-99m 5.59E-04 1.58E-03 2.01E-02 0.00 2.40E-02 7.75E-04 9.36E-01 All values are in (mrem *mL)/(h pCi). They are calculated using equation (2.14), and data f rom Table 2-5, Table 2-6, and Table 2-7.
When "No Data" is shown for a radionuclide-organ combination in Table 2-7, Aj7 f actors in this table are presented as zero. O 2-39 Rev. 8, 1/94
Hatch ODCM Table 2-8 (contd). Site-Related Ingestion Dose Factors, Ag
- O Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI Tc-101 2.71E-33 3.91E-33 3.83E-32 0.00 7.03E-32 2.00E-33 0.00 Ru-103 2.OOE+00 0.00 8.62E-01 0.00 7.64E+00 0.00 2.34E+02 Ru-105 4.OOE-03 0.00 1.58E-03 0.00 5.17E-02 0.00 2.45E+00 Ru-106 3.02E+01 0.00 3.83E+00 0.00 5.84E+01 0.00 1.96E+03 l Rh-105 1.83E+00 1.33E+00 8.72E-01 0.00' 5.63E+00 0.00 2.11E+02 Ag-110m 1.34E+02 1.24E+02 7.34E+01 0.00 2.43E+02 0.00 5.05E+04 Sb-124 6.65E+00 1.25E-01 2.63E+00 1.61E-02 0.00 5.16E+00 1.88E+02 Sb-125 5.33E+00 5.74E-02 1.07E+00 4.74E-03 0.00 5.57E+02 4.71E+01 i Te-125m 2.54E+03 9.19E+02 3.40E+02 7.63E+02 1.03E+04 0.00 1.01E+04 Te-127m 6.44E+03 2.30E+03 7.85E+02 1.65E+03 2.62E+04 0.00 2.16E+04 Te-127 1.78E+01 6.38E+00 3.85E+00 1.32E+01 7.24E+01 0.00 1.40E+03 Te-129m 1.08E+04 4.02E+03 1.71E+03 3.71E+03 4.50E+04 0.00 5.43E+04 Te-129 1.78E-05 6.68E-06 4.33E-06 1.36E-05 7.47E-05 0.00 1.34E-05 f Te-131m 9.51E+02 4.65E+02 3.88E+02 7.37E+02 4.71E+03 0.00 4.62E+04 Te-131 8.64E-17 3.61E-17 2.73E-17 7.10E-17 3.78E-16 0.00 1.22E-17 Te-132 1.95E+03 1.26E+03 1.18E+03 1.39E+03 1.22E+04 0.00 5.97E+04 I-130 2.03E+01 5.98E+01 2.36E+01 5.06E+03 9.32E+01 0.00 5.14E+01 I-131 3.93E+02 5.62E+02 3.22E+02 1.84E+05 9.63E+02 0.00 1.48E+02 I-132 1.51E-02 4.04E-02 1.41E-02 1.41E+00 6.43E-02 0.00 7.59E-03 l ~s I-133 6.57E+01 1.14E+02 3.48E+01 1.68E+04 1.99E+02 0.00 1.03E+02
( I-134 6.26E-08 1.70E-07 6.09E-08 2.95E-06 2.71E-07 0.00 1.48E-10 q I-135 3.68E+00 9.64E+00 3.56E+00 6.36E+02 1.55E+01 0.00 1.09E+01 Cs-134 8.63E+04 2.05E+05 1.68E+05 0.00 6.64E+04 2.21E+04 3.59E+03 Cs-136 8.58E+03 3.39E+04 2.44E+04 0.00 1.88E+04 2.5BE+03 3.85E+03 Cs-137 1.11E+05 1.51E+05 9.91E+04 0.00 5.14E+04 1.71E+04 2.93E+03 Cs-138 2.64E-12 5.22E-12 2.59E-12 0.00 3.84E-12 3.79E-13 2.23E-17 Ba-139 7.05E-06 5.03E-09 2.07E-07 0.00 4.70E-09 2.85E-09 1.2SE-05 Ba-140 2.30E+02 2.89E-01 1.51E+01 0.00 9.83E-02 1.66E-01 4.74E+02 Ba-141 1.06E-24 8.00E-28 3.57E-26 0.00 7.44E-28 4.54E-28 4.99E-34 Ba-142 0.00 0.00 0.00 0.00 0.00 0.00 0.00 La-140 9.89E-02 4.99E-02 1.32E-02 0.00 0.00 0.00 3.66E+03 La-142 2.19E-07 9.96E-08 2.48E-08 0.00 0.00 0.00 7.27E-04 ] Ce-141 1.84E+00 1.25E+00 1.41E-01 0.00 5.79E-01 0.00 4.76E+03 Ce-143 2.OOE-01 1.48E+02 1.64E-02 0.00 6.52E-02 0.00 5.54E+03 f Ce-144 9.79E+01 4.09E+01 5.26E+00 0.00 2.43E+01 0.00 3.31E+04 l Pr-143 5.23E-01 2.10E-01 2.59E-02 0.00 1.21E-01 0.00 2.29E+03 Pr-144 1.48E-28 6.14E-29 7.51E-30 0.00 3.46E-29 0.00 2.13E-35 Nd-147 6.50E-01 7.52E-01 4.50E-02 0.00 4.39E-01 0.00 3.61E+03 W-187 1.47E+02 1.23E+02 4.30E+01 0.00 0.00 0.00 4.03E+04 Np-239 2.12E-02 2.09E-03 1.15E-03 0.00 6.51E-03 0.00 4.28E+02 O 2-40 Rev. 8, 1/94
- - . _ ~ . . - . . . . - . - - . - _ - _ . , ~ _= -.- - - . - . - ---. . _
l i Hatch ODCM 2.5 LIQUID EFFLUENT DOSE PROJECTIONS i 2.5.1 Thirty-One Day Dose Proiections 4 In order to meet the requirements for operation of the LIQUID RADWASTE TREATMENT I SYSTEM (see section 2.1.4), dose projections must be made at least once each 31 1 4 days; this applieu during periods in which a discharge to UNRESTRICTED AREAS of liquid ef fluents containing radioactive materials occurs or is expected. l l Projected 31-day doses to individuals due to liquid ef fluents may be determined as follows: A D rp = x 31 + D ra (2.17) l i 4 j i where: D 7p = the projected dose to the total body or organ 7, for the next 31 days of liquid releases. 1' the cumulative dose to the total body or organ r, for liquid l, Dg = releases that have occurred in the elapsed portion of the current j quarter, plus the release under consideration. I 1 I t = the number of whole or partial days elapsed into the current l l quarter, including the time to the end of the release under
- consideration (even if the release continues into the next quarter).
t I D ra = the anticipated dose contribution to the total body or any organ r, l due to any planned activities during the next 31-day period, if I those activities will result in liquid releases that are in addition to routine liquid effluents. If only routine liquid , effluents are anticipated, D , 7may be set to zero. i j
- 2.5.2 Dose Proiections for Specific Releases Dose projections may be performed for a particular release by performing a pre-release dose calculation assuming that the planned release will proceed as anticipated. For individual dose projections due to liquid releases, follow the
]
l methodology of Section 2.4, using sample analysis results for the source to be released, and parameter values expected to exist during the release period. 4 2-41 Rev. 8, 1/94 i s
. . _ _ . _ . _ _......_..______.m . _ _ . _ _ _ . - _ . . _ . _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ . _ _ _ _ _ _ . _
l Hatch ODcM 2.6 DEFINITIONS OF LIQUID EFFLUENT TERMS
- O The following . symbolic terms are used in the presentation of liquid of fluent I
calculations in the sub-sections above. section of Definition Initial Use Iggg a' Ap = the adjustment factor used in calculating the ] effluent monitor setpoint for liquid release pathway j p: the ratio of the assured dilution to t.5e required 2.3.2.2 . dilution (unitiess). 1 $ ADF = the assured dilution factor for a planned release 2.3.2.2 [unitiess). i AF p = the dilution allocation factor for liquid release l 2.3.2.2 pathway p (unitiess). the site-related adult ingestion dose commitment _ Air = ! f f actor, for the total body or for any organ 7, due to 1 identified radionuclide i [(mrem mL)/(h pci)J. The l 1 2.4.1 values of Air are listed in Table 2-8. B;y = the crop to soil concentration factor applicable to radionuclide i, {(pci/kg garden vegetation)/(pci/kg l 2.4.3 soil)). BFj= the bioaccumulation factor for radionuclide i for freshwater fish [(pci/kg)/(pci/L)). Values are listed 2.4.2 in Table'2-6. e= the setpoint of the radioactivity monitor measuring the concentration of radioactivity in the affluent line, prior to dilution and subsequent release (pci/mL). 2.3.2.1 the calculated effluent radioactivity monitor ep = setpoint for liquid release pathway p [pci/mL). 2.3.2.2 l c, = the gross concentration of alpha emitters in the liquid waste as measured in the applicable composite f 2.3.2.2 ! O sample (pci/mL). Q 2-42 Rev. 8, 1/94 l l 1 i
~, .._ . , . . - _ -- - . -
. . . ~ ._ _- . - . _ - _ . , _ .- - . - . . .~. . . -
i Hatch ODCM d Section of a Definition Initial Use Term the Ef fluent concentration Limit stated in 10 CFR 20, CECL = Appendix B, Table 2, Column 2 [pci/mL). 2.3.2.1 i i the concentration of Fe-55 in the liquid waste as j Cr = measured in the applicable composite sample j , [pci/mL). 2.3.2.2 C g= the concentration of gamma emitter g in the liquid ' waste as measured by gamma ray spectroscopy performed ; on the applicable pre-release waste sample [pci/mL). 2.3.2.2 J cj = the measured concentration of radionuclide i in a i sample of liquid effluent [pci/mL). 2.3.2.2 l l Cg= the average concentration of radionuclide i in i undiluted liquid effluent during time period 1 4 [pci/mL). 2.4.1 l lV Cir = the measured concentration of radionuclide i in release pathway r that is contributing to radio-activity in the dilution stream [pci/mL]. 2.3.2.2 j i Cs = the concentration of strontium radioisotope s (Sr-89 or Sr-90) in the liquid waste as measured in the applicable composite sample [pci/mL]. 2.3.2.2 1 Cg = the concentration of H-3 in the liquid waste as measured in the applicable composite sample [pci/mL). 2.3.2.2 CFjy = the concentration factor for radionuclide i in irrigated garden vegetation [(pci/kg)/(pci/L)). 2.4.2 Dw = the dilution factor from the near f ield of the discharge structure to the potable water intake 2.4.2 i location [unitiess). O V 2-43 Rev. 8, 1/94
1 1 Hatch ODCM Section of I
"~
Definition Initial Use ! O I,ggm D, = the cumulative dose commitment to the total body or to any organ 7, due to radioactivity in liquid affluents released during a given time period 2.4.1 (mrom). 1 j D ra = the anticipated dose contribution to the total body or any organ 7, due to any planned activities during the next 31-day period [mram). 2.5.1 D 7g = the cumulative dose to the total body or organ 7, for liquid releases that have occurred in the elapsed l portion of the current quarter, plus the release l I under consideration [ mrem). 2.5.1 I D,p = the projected dose to the total body or organ r, for the next'31 days of liquid releases [arem). 2.5.1 l l DF;7 = the dose conversion factor for radionuclide i for j adults, in organ v [ mrem /pci). Values are listed in ' 2.4.2 Table 2-7. l l ECLj = the liquid Effluent Concentration Limit for radio-nuclide i from 10 CFR Part 20, Appendix B, Table 2, Column 2 {pCi/mL). 2.3.2.2 l f= the affluent flowrate at the location of the radio- . 1 activity monitor (gpm). 2.3.2.1 f,p = the anticipated actual discharge flowrate for a planned release from liquid release pathway p (gpm]e 2.3.2.2 fg = the "raction f of the year that garden vegetation is irrigated (unitiess). 2.4.3 f,p = the maximum permissible af fluent discharge flowrate for release pathway p [gpm). 2.3.2.2 %) 2-44 Rev. 8, 1/94
i Hatch ODCM Section of 1' Initial Use Definition-4 ["'
\.
Iggs d f r
= the effluent discharge flowrate of release pathway r
] 2.3.2.2 (gpm). ft= the average undiluted liquid waste flowrate actually I observed during the period of a liquid release 2.4.1 l [gpm). l F= the dilution stream flowrate which can be assured prior to the release point to the UNRESTRICTED AREA 2.3.2.1 (gpm]. l rd = the entire assured dilution flowrate for the plant ; site during the release period (gpm). 2.3.2.2 F dp the dilution flowrate allocated to release pathway p
=
2.3.2.2 1 (gpm]. the near-field average dilution factor in the Fj = , receiving water of the UNRESTRICTED AREA 2.4.1 (unitless). the average dilution stream flowrate actually Fg= I observed during the period of a liquid release 2.4.1 [gpm]. I= the average irrigation rate during the growing season 2.4.3 (L/(m2 *h)]. Ly = the water content of leaty garden vegetation edible 2.4.3 parts (L/kg). M= the additional river dilution f actor from the near field of the discharge structure.for the plant site to the point of irrigation water usage (unitiess). 2.4.3 P= the ef f ective surf ace density of soil (kg/m 2) . 2.4.3 A 2-45 Rev. 8, 1/94
Hatch ODCM section of Initial Use Definition p Term ' r= the fraction of irrigation-deposited activity retained on the edible portions of leafy garden 2.4.3 vegetation. the minimum ratio by RDF = the required dilution factors which liquid ef fluent must be diluted before reaching the UNRESTRICTED AREA,, in order to ensure that the of Section 2.1.2 are not exceeded limits 2.3.2.2 (unitless). RDF = the RDF for a liquid release due only to its concen-7 2.3.2.2 tration of gamma-emitting radionuclides (unitiess) . RDF,7 = the RDF for a liquid release due only to its concen-tration of non-gamma-emitting radionuclides 2.3.2.2 [unitiess). selected to compensate for l SF = the safety factor ' statistical fluctuations and errors of measurement 2.3.2.2 [unitiess). , t= the number of whole or partial days elapsed into the current quarter, including the time to the end of the 2.5.1 release under consideration. tb= the period of long-term buildup of activity in soil 2.4.3 [h). i t* = the period of leafy garden vegetation exposure during 2.4.3 ; the growing season [h). . f tg = the transit time f rom release to receptor for fish 2.4.2 consumption (h). I the time between harvest of garden vegetation and th= 2.4.3 human consumption [h). tw = the transit time from release to receptor for potable 2.4.2 water consumption [h). Rev. 8, 1/94 2-46 l
-- ..~ _ .. . . . . . . .- . . - . - . ...- . . _ - . _. - .. -
Hatch ODCM Section of i Definition Initial Use l Iggg) O TF = the tolerance f actor selected to allow flexibility in the establishment of a practical monitor setpoint which could accommodate effluent releases at concentrations higher than the ECL values stated in , 10 CFR 20, Appendix B, Table 2, Column 2 [unitiess); the tolerance factor must not exceed a value of 10. 3.3.2.2 l the adult rate of fish consumption [kg/y). 2.4.2 Uf= Uy= the adult consumption rate for irrigated garden vegetation (kg/y). 2.4.2 1 U, = the adult drinking water consumption rate applicable to the plant site [L/y). 2.4.2 Yy = the areal density (agricultural productivity) of leafy garden vegetation [kg/m2 ). 2.4.3 the applicable dilution factor for the receiving O 2= water body, in the near field of the discharge j structure, during the period of radioactivity release 2.4.1 [unitiess). 1 Atg = the length of time period 1, over which C;g and Fg are
)
averaged for liquid releases [h). 2.4.1 the ef fective removal rate for activity deposited on 1Ei = crop leaves [h-I). 2.4.3 the decay constant for radionuclide 1 [h-I). 2.4.2 li= 1, = the rate constant for removal of activity from plant leaves by weathering [h-3 ) . 2.4.3 O v 2-47 Rev. 8, 1/94
~ _
Hatch ODCM CHAPTER 3 e GASEOUS EFFLUENTS 3.1 LIMITS OF OPERATION The following Limits of operation implement requirements established by Technical specifications section 5.0. Terms printed in all capital letters are defined in l Chapter 10. 3.1.1 Caseous Effluent Monitorino Instrumentation Control In accordance with Technical Specification 5.5.4.a., the radioactive gaseous l effluent monitoring instrumentation channels shown in Table 3-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of section 3.1.2.a are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with Section 3.3. 3.1.1.1 Applicability These limits apply as shown in Table 3-1. 3.1.1.2 Actions , With a radioactive gaseous of fluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive gaseous affluents monitored by the affected channel, declare the channel inoperable, or restore the setpoint to a value that will ensure that the limits of Section 3.1.2.a are met. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3-1. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS. When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 3-1 Rev. 10, 7/95
. - - . - . . - _ _ _ . - - - - _ - - - _ ~ .- -_ - - - _ . _ _ - - _ _ - _ _ . . . . .-
Hatch ODCM surveillance Requirements I 3.1.1.3 r i 4 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL l CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 3-2. 3.1.1.4 Basis The radioactive gaseous effluent . instrumentation is provided to monitor and ' control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous affluents. The ( Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in l accordance with the methodology and parameters in section 3.3 to ensure that the 4 alarm / trip will occur prior to exceeding the limits of section 3.1.2.a. The i OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CTR Part 50. 4 l 4 i j 4 1 4 4 i i a f e
\
3-2 Rev. 9, 2/94
-- -. - ~ - . . . . - -- .
l l Hatch ODCM l Table 3-1. Radioactive Gaseous Effluent Monitoring Instrumentation i Minimum " Channels Applica- l OPERABLE bility A:: TION Instrument
- 1. Reactor Building Vent Stack Monitoring System (Each Unit) f
- a. Noble Gas Activity MonitorC 1 (a) 105
]
- b. Iodine Sampler Cartridge 1 (a) 107
- c. Particulate Sampler Filter 1 (a) 107
- d. Effluent System Flowrate Measurement Device 1 (a) 104 j
' e. Sampler Flowrate Measurement 1 (a) 104 Device m-m e
- 2. Recombiner Building Ventilation Monitoring System
- a. Noble Gas Activity Monitor C 1 (a) 105 L
- b. Iodine Sampler Cartridge 1 (a) 107
- c. Particulate Sampler Filter 1 (a) 107 (a) 104
- d. Sampler Flowrate Monitor 1
- 3. Main Stack Monitoring System
- a. Noble Gas Activity Monitor e 1 (a) 105
( Iodine Sampler Cartridge 1 (a) 107 . b. Particulate Sampler Filter 1 (al 107 c.
- d. Effluent System Flowrate 1 (a) 104
- Measurement Device I
- e. Sampler Flowrate Measurement 104 i
Device 1 (a)
- 4. Condenser Offgas Pretreatment Monitor (Each Unit)
Noble Gas Activity Monitor 1 (b) 108 a. k I l
\
1 lO-3-3 Rev. 8, 1/94 l 4 i A
Hatch ODCM Table 3-1 (contd). Notation for Table 3-1
- a. During radioactive releases via this pathway.
- b. During operation of the main condenser air ejector,
- c. Monitor must be capable of responding to a MINIMUM DETECTABLE CONCENTRATION of 1 x 10d pCi/mL.
ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, af fluent releases via this pathy may continue provided the flowrate is estimated at least once per 4 hours. If the number of channels OPERABLE remains less than required by the minimum channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next Radioactive Effluent Release Report. ACTION 105 - With the nmber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fluent releases via this pathway may continue provided grab samples are taken daily andthe With these samples number are of main analyzed for gross activity within 24 hours. stack monitoring system channels OPERABLE less than required by the minimum channels OPERABLE requirement, immediately suspend drywell purge. If the number of channels OPERABLE remains less than required by the minimum channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next Radioactive Effluent Release Report. ACTION 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided samples are continuously collected with auxiliary equipment for periods on the order of 7 days and analyzed within 48 hours efter the end of the sampling period. If the number of channels OPERABLE remains less than required by the minimum channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next Radioactive Effluent Release Report. l ACTION 108 - With the number of channels OPERABLE less than required by the Minimum channels OPERABLE requirement, effluent releases via this pathway may continue for up to 72 hours, provided:
- a. The offgas treatment system is not bypassed; and
- b. The of fgas post-treatment monitor (Dil-K615 ) or the main stack monitor (D11-K600) is OPERABLE.
Otherwise, be in at least HOT STANDBY within 12 hours. If the number of channels OPERABLE remains less than required by the minimum channels OPERABLE requirement for over 30 days, an explanation of the circumstances l shall be included in the next Radioactive Effluent Release Report. O Rev. 10, 7/95 3-4
4 Hatch ODCH Table 3-2. Radioactive Gaseous Effluent Monitoring Instrumentation g
- Surveillance Requirements CHANNEL CHANNEL CHANNEL CALIBRA- FUNCTIONAL Instrument CHECK SOURCE CHECK TION TEST
- 1. Reactor Building Vent Stack Monitoring System (Esch Unit)
- a. Noble Gas Activity f Monitor Da M R QC j i b. Iodine Sampler Cartridge W"'d NA NA NA j
- c. Particulate Sampler ,d Filter g n n i
)
! d. Effluent System Flowrate Measuring Device D* NA R Q
- e. Sampler Flowrate Measuring Device D" NA R Q 1
- 2. Recombiner Building Ventilation Monitoring System
- a. Noble Gas Activity D* M R Q* Monitor ^
- b. Iodine Sampler Cartridge W NA NA
- _NA
- c. Particulate Sampler Filter W NA NA NA j
i^ d. Sampler Flowrate Measuring Device D* NA R Q j 4 3. Main Stack Monitoring System
- a. Noble Gas Activity , gc l
p Monitor
- b. Iodine Sampler ga,d NA NA NA
, Cartridge
- c. Particulate Sampler ga,d NA NA NA Filter :,
- d. Effluent Flowrate D, Monitor NA R Q l
i e. Sampler Flowrate , Monitor 9
- 4. Condenser Offgas Pretreatment Monitor (Each Unit)
- a. Noble Gas Activity Db 4
M R Q* Monitor 4 h l I l 9 l i i l O
- +
)
3-5 Rev. 8, 1/94 1 l l
.-~ .-. .~_ .- ----. .. . _ __- .._~ . _ -_. - _. .,
i
- Hatch ODCM i I
f i l Table 3-2 (contd). Notation for Table 3-2 1 a. Requirement applies during releases via this pathway.
- b. Requirement applies during operation of the main condenser air ejector.
- c. In addition to the basic functions of a CHANNEL FUNCTIONAL TEST (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate that control l room alarm annunciation occurs if any of the following conditions exists: !
\
(1) Instrument indicates measured levels above the alarm / trip setpoint. 4 I i (2) Circuit failure occurs. (3) Instrument indicates a downscale failure. l l
- d. The CHANNEL CHECK shall consist of verifying sampler flow and the presence of the collection device (i.e., particulate filter or charcoal cartridge, etc.) at the weekly changeout.
4 l
, J s
O . 3-6 Rev. 8, 1/94
.- _ ~ - - ~ .~ . - . - . . .. . . . .. - -
?. Hatch ODCM 3.1.2 caseous Effluent Dose Rate Control 1 In accordance with Technical specifications 5.5.4.c. and 5.5.4.g., the licensee l shall conduct operations so that the dose rates due to radioactive er.aterials I released in gaseous effluents from the site to areas at and beyond the SITE ! BOUNDARY (see Figure 10-1) are limited as follows: i a. For noble gases: Less than or equal to a dose rate of 500 mrom/y to the total body and less than or equal to a dose rate of 3000 mrom/y to the skin, and
- b. For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a does rate of 1500 mrom/y to any organ.
3.1.2.1 Applicability
\
This limit applies at all times.
)
3.1.2.2 Actions With a dose rate due to radioactive material released in gaseous affluente j Os exceeding the limit stated in Section 3.1.2, immediately decrease the release race to within the stated limit. When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 3.1.2.3 Surveillance Requirements The dose rates due to radioactive materials in areas at or beyond the SITE BOUNDARY due to releases of gaseous effluents shall be determined to be within the above limits, in accordance with the methods and procedures in Section 3.4.1, by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-3. 3.1.2.4 Basis This control is provided to ensure that gaseous effluent dose rates will be maintained within the limits that historically have provided reasonable assurance t that radioactive material discharged in gaseous effluents will not result in a 3-7 Rev. 10, 7/95
l Hatch ODCM dose to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside j the SITE BOUNDARY, exceeding the limits specified in Appendix I of 10 CFR Part [ For MEMBERS 50, while allowing operational flexibility for effluent releases. OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be suf ficiently low to compensate for any increase in l the atmospheric diffusion factor above that for the SITE BOUNDARY. The dose rate limit for Iodine-131, Iodine-133, tritium, and radionuclides in l l particulate form with half-lives greater than 8 days specifically applies to dose ! rates to a child via the inhalation pathway. j I l i l l l This control applies to the release of gaseous effluents from all reactors at the site. I ! \ l
)
l l O o 3-8 Rev. 8, 1/94
l Hatch ODCM Table 3-3. Radioactive Gaseous Waste Sampling and Analysis Program a i Sampling and Analysis Requirements MINIMUM DETECTAELE Minimum Type of CONCENTRA-Gaseous Release Sampling Analysis Activity TION (MDC) FREQUENCY Analysis (pCi/mL) Type FREQUENCY
' PRINCIPAL GAMMA 1 E-4 l Mc ge EMITTERS Grab Sample
- H-3 1 E-6 .
1 Wd I-131 1 E-12 Environmental Charcoal or CONTINUOUSe Silver I-133 1 E-10 Release Points Zeolite Sample .' 1. Main Stack Wd
- 2. Reactor PRINCIPAL GAMMA 1 E-11 CONTINUOUSe Particulate EMITTERS Building Vent Sample ;
(Each Unit) M ;
- 3. Recombine .
Gross Alpha 1 E-11 j Building Vent CONTINUOUS
- p i
Sample Y,/ Q - CONTINUOUS
- Sr-89, Sr-90 1 E-11 P e Sample O
3-9 Rev. 8, 1/94
. _ _ . _ _ = _ - - . _ . . . . _ . . - - . _ . - _- . . - _ . - _ _ . . --
Hatch ODCM
)
Table 3-3 (contd). Notation for Table 3-3
%J When
- a. Terms printed in all capital letters are defined in Chapter 10.
unusual circumstances result in a MINIMUM DETECTABLE CONCENTRATION higher l l than required, the reasons shall be documented in the next Radioactive l l l Effluent Release Report. } - b. The Recombiner Building Vent serves Unit 1. Sample analysis results and ! associated source terms must be assigned to Unit 1 for the purpose of
- release accountability and dose calculations.
t
- c. Sampling and analyses for PRINCIPAL GAMMA EMITTERS shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a one-hour period. The more frequent sampling and analysis requirement applies only if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main !
Stack Noble cas Activity Monitor reading have both increased by a factor of 3.
- d. Sampling shall be performed weekly, and analyses completed within 48 hours of changing (or after removal from sampler). Sampling shall also be performed once per 24 hours for 7 days following each shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a one-hour period, with analyses completed within 48 hours of changing.
When samples collected for 24 hours are analyzed, the corresponding MINIMUM DETECTABLE CONCENTRATIONS may be increased by a f actor of 10. The more frequent sampling and analysis requirement applies only if analysis l>
"i shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor reading have both increased (Q
j \ by a factor of 3.
- e. The ratio of the sample flowrate to the sampled stream flowrate shall be known for the time period covered by each dose or dose rate calculation made in accordance with controls specified in Sections 3.1.2, 3.1.3, and 3.1.4.
3 2 a O 3-10 Rev. 10, 7/95
= . . - . . _ . . , - - _ . . . . _- - -.. . - - - . -. . - - - -
Hatch ODCM 3.1.3 cameous Effluent Air Dese control O In accordance with Technical Specifications 5.5.4.e. and 5.5.4.h, the air dose l due to noble gases released in gaseous ef fluents, from each reactor unit, to I areas at and beyond the SITE BOUNDARY (see Figure 10-1) shall be limited to the following:
- a. During any calendar quarter Less than or equal to 5 mrad for gassoa radiation and less than or equal to 10 mrad for beta radiation, and i b. During any calendar years Less than or equal to 10 mrad for gasusa radiation and less than or equal to 20 mrad for beta radiation.
3.1.3.1 Applicability 1 This limit applies at all times. ) 3.1.3.2 Actions i With the calculated air dose from radioactive noble gases in gaseous affluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory ] Commission within 30 days a Special Report which identifies the cause(s) for l l i p 6 exceeding the limit (s); defines the corrective actions that have been taken to reduce the releases; and defines the proposed corrective actions to be taken to ) assure that subsequent releases of radioactive noble gases in gaseous affluents l will be in compliance with the limits of Section 3.1.3. 7 When the ACTION statement or other requirements of this control cannot be met, l steps need not be taken to change the Operational Mode of the unit. Entry into l an Operational Mode or other specified CONDITION may be made if, as a minimum, 4 the requirements of the ACTION statement are satisfied. l 4 3.1.3.3 Surveillance Requirements 4 4 ~ Cumulative air dose contributions from noble gas radionuclides released in gaseous affluents from each unit to areas at and beyond the SITE BOUNDARY, for the current calendar quarter and current calendar year, shall be determined in ! accordance with Section 3.4.2 at least once per 31 days. 1 iO 3-11 Rev. 10, 7/95
l Hatch ODCM l 3.1.3.4 Basis ; l This control is provided to implement the requirements of Sections II.8, III.A l and IV. A of Appendix I,10 CPR Part 50. Section 3.1.3 implements the guides set I forth in Section II.B of Appendix I. The ACTION statements in Section 3.1.3.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I, ast ring that the releases of l radioactive material in gaseous ef fluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance requirements in Section 3.1.3.3 implement the requirements in Section III. A of Appendix I, which require that conformance with the guides of Appendix I be shown by calculational ! procedures based on models and data such that the actual exposure of a MEMBER OF l THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in Section 3.4.2 for f calculating the doses due to the actual releases of noble gases in gaseous l ef fluents are consistent with the methodology provided in Regulatory Guide 1.109 f (Reference 3), and Regulatory Guide 1.111 (Reference 5). The equations in i Section 3.4.2 provided for determining the air doses at the SITE BOUNDARY are based upon the historical annual average atmospheric conditions. 1 l l l l l 1 l \ 3-12 Rev. 8, 1/94
i Hatch ODCM i 3.1.4 Centrol on Gaseous Effluent Dese to a M-her of the Public In accordance with Technical Specifications 5.5.4.e. and 5.5.4.1., che done to l a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and all ra?ionuclides in particulate form with half-lives granter than 8 days in gaseous effluents released, f rom each reactor unit, to areas at and beyond the SITE FOUNDARY (see l
; Figure 10-1) shall be limited to the following l l a. During any calendar quarter: Less than or equal to 7.5 mrom to any ergan, and ~
s
- b. During any calendar years Less than or equal to 15 mrom to any organ.
i !
- , 3.1.4.1 Applicability f
This limit applies at all times. 1 1 I 3.1.4.2 Actions With the calculated dose from the release of I-131, I-133, tritium, or radio-nuclides in particulate form with half-lives greater than 8 days, in gaseous l i j ef fluents exceeding any of the above limits, prepare and submit to the Nuclear j3 Regulatory Coanission within 30 days t Special Report which identifies the l cause(s) for exceeding the limit; defines the corrective actions that have been i taken to reduce the releases of radiciodines and radionuclides in particulate l ' form with half-lives greater than 8 days in gaseous effluents; and defines proposed corrective actions to assure that subsequent releases will be in compliance with the limits stated in Section 3.1.4. i i When the ACTION statement or other requirements of this control cannot be met,
! steps need not be taken to change the Operational Mode of the ur.it. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied.
i 3.1.4.3 Surveillance Requirements k cumulative organ dose contributions to a MEMBER OF THE PUBLIC from I-131, 2-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days released in gaseous ef fluents from each unit to areas at and beyond the SITE BOUNDARY, for the current calendar quarter and current calendar year, shall be determined in accordance with section 3.4.3 at least once per 31 days. 1
\
3-13 Rev. 10, ~1/95
i Hatch ODCM 3.1.4.4 Basis a \' This control is provided to implement the requirements of Section II.C, III. A and IV.A of Appendix I, 10 CFR Part 50. The limits stated in Section 3.1.4 are the guides set forth in Section II.C of Appendix 1. The ACTION statements in Section 3.1.4.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases i of radioactive materials in gaseous af fluents to UNRESTRICTED AREAS will be kept j
"as low as is reasonably achievable. " The calculational methods specified in the Surveillance Requirements of Section 3.1.4.3 implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The calculational methods in Section 3.4.3 for calculating the doses due to the actual releases of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109 (Reference 3), l I
and Regulatory Guide 1.111 (Reference 5). These equations provide for determining the actual doses based upon the historical annual average atmospheric ! conditions. The release specifications for radiciodines, radioactive materials f in particulate form and radionuclides other than noble gases are dependent on the l existing radionuclide pathways to man, in the areas at and beyond the SITE l BOUNDARY. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) ( deposition of radionuclides onto green leafy garden vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. l l O 3-14 Rev. 8, 1/94
t Hatch ODCM ] - 3.1.5 Cameous Radwaste Treatment System Control In accordance with Technical Specificrcion 5.5.4.f., the GASEOUS RADWASTE l i TREATMENT SYSTEM as described in Section 3.2 shall be in operation. 4 l 3.1.5.1 Applicability i Whenever the main condenser air ejector is in operation. l 3.1.5.2 Actions With gaseous radwaste from the main condenser air ejector system being discharged l without treatment for more than 7 days, prepara and submit to the Nuclear ! Regulatory Commission within 30 days a Special Report which includes the l following informations {
- a. Identification of the inoperable equipment or subsystem and the reason for inoperability,
- b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- c. Sununary description of action (s) taken to prevent a recurrence.
When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 3.3.5.3 Surveillance Requirements The GASEOUS RADWASTE TREATMENT SYSTEM shall be demonstrated to be OPERABLE by administrative controls which ensure that the offgas treatment system is not bypassed. 3.1.5.4 Basis The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous affluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous ef fluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 3-15 Rev. 10, 7/95
Hatch ODCM Part SO.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Sectior II.D of Appendix I to 10 CFR Part 50. The O specified limits governing the use of appropriate portions of the system were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. j This control applies to the release of radioactive materials in gaseous ef fluents from each unit at the site. For units with shared radwaste systems, the gaseous affluents from the shared system are proportioned among the units sharing that system. I 3.1.6 Maior Chances to Gaseous Radioactive Waste Trea&= ant Systems l Licensee initiated MAJOR CHANGES TO CASEOUS RADIOACTIVE WASTE TREATMENT SYSTEMS: l
- a. Shall be reported to the Nuclear Regulatory Commission in the Radioactive I Effluent Release Report for the period in which the change was implemented, in accordance with Section 7.2.2.7.
- b. Shall become ef fective upon review by the Plant Review Board and approval by the Nuclear Plant General Manager.
U i O 3-16 Rev. 10, 7/95
Hatch ODCM 3.2 GASEOUS RADWASTE TREATHENT SYSTEM
~~' At Plant Hatch, there are four points where radioactivity normally is released to the atmosphere in gaseous discharges. These four release pathways are the Unit 1 and Unit 2 reactor building vent stacks; the Unit 1 recombiner building vent; and the main stack, which serves both units. In addition, releases may be made from any of the building exhaust augmented ventilation systems that have been included in Table 3-1, Table 3-2, and Table 3-3.
The main stack serves as the discharge point from the following release sources from each unitt e Mechanical vacuum pumps; e offgas treatment system (see Figure 3-1); e Cland seal exhaust; and e Standby gas treatment system (through which drywell purges are discharged). In addition, the waste gas treatment building ventilation also discharges through the main stack. Each reactor building vent stack serves as the discharge point for the following ralease sources of its respective unit
- Reactor building; k) e Refueling floor ventilation; Turbine building; and e
e Radwaste building. The Unit 1 recombiner building vent discharges directly to the atmosphere. Releases from all of the above discharge points except the main stack are considered to be ground-level releases; releases from the main stack are considered to be elevated releases. Chapter 8 discusses the calculation of atmospheric dispersion parameters using the ground-level and elevated models. All release pathways are considered to be CONTINUOUS (as opposed to BATCH) in nature. O) t v 3-17 Rev. 8, 1/94
-- _. .. ._ . ~- .-. .. .._. . - - _ - . - .
I Hatch ODCM l ! l l l PROM CONDENSE R : V l l 7 itT ETAGE EACTOR 2 ist sTast iNTsRCoNoENSER 2ND STAGE EACTOR 2000 STAGE INTE RCONOENSER h =
.J j d 3RD STAGE EACTOR i
j r OPPG AS REMEATER j 2 4 1 1 i CATALYTicRECOMetNER l t It 3 OFD GAS CONDEISER l RADIAviON 4 } j MONITOR hs YvATER SEPARATOR e . N NOLDUP LINE I h/ J COOLE R CONDENSE R I 3
- ( i ; -
- edOISTURE STRIP l SEPARATOR HEATER l i I j
Y CMARCOAL FILTE Rg CHAmCOAL FILTE RS meLACES a cL u tsi
... 3 RAmiATiON
', MONITOR PROM l d
STANOSY l l oAs AFTER RADIATION TRgAftAENT i J FILTER 88088170R O SYST8M O ! u - ;":",0 ( SEALSysTSM i i I l Figure 3-1. Schematic Diagram of the Condenser of fgas Treatment System 3-18 Rev. 8, 1/94
Hatch ODCM 3.3 GASEOUS EFFLUENT MONITOR SETPOINTS Oi
- N ,Y 3.3.1 General Provisions Recardina Noble Gas Monitor Setooints Noble gas radioactivity monitor setpoints calculated in accordance with the methodology presented in this section are intended to ensure that the limits of f Section 3.1.2.a are not exceeded. They will be regarded as upper bounds for the actual high alarm setpoints. That is, a lower high alarm setpoint may be established or retained on the monitor, if desired. Intermediate level setpoints should be established at an appropriate level to give suf ficient warning prior i
to reaching the high alarm setpoint. If no release is planned for a given pathway, or if there is no detectable activity in the gaseous stream being evaluated for release, the setpoint should I be established as close to background as practical to prevent spurious alarms, and yet alarm should a significant inadvertent release occur. ) l As established in section 3.1.1, gaseous ef fluent monitor setpoints are reguired only for the noble gas monitors on the release streams listed above. However, Section 3.3.6 discusses setpoint methodologies for particulate and iodine l monitors on an information-only basis.
) Note: Section 3.3.3 is included for section numbering compatibility with the ODCMs of the other Southern company nuclear power plants. This section is not required by the existing release source and discharge point configuration of Plant Hatch.
4 4 i i i
, s 3-19 Rev. 8, 1/94
1 Hatch ODCM Table 3-4. Applicability of Gaseous Monitor Setpoint Methodologies
)
Final Release Pathways with no Monitored Source Streams Setpoint Method: Section 3.3.2 Release Type: CONTINUOUS Main Stack Release Elevation Elevated , Monitor: D11-K600 A and B Maximum Flowrate: 20,000 cfm (9.44 E+06 mL/s) Unit 1 or Unit 2 Reactor Buildino Vent Release Elevation Ground-level Monitor: D11-K619 A and B / 2Dil-K636 A and B Maximum Flowrate: 300,000 cfm (1.42 E+08 mL/s) Unit 1 Recombiner Buildino Vent Release Elevation: Ground-level Monitor: D11-P003 A and B Maximum Flowrate: 500 cfm (2.36 E+05 mL/s) Buildina Exhaust Auomented Ventilation The systems in this category are not currently vented to the atmosphere. Final Release Pathways with one or More Monitored Source Streams () Plant Hatch currer.tly has no release pathways in this category. l (176)vb Values for Use in Setpoint calculations 8.37 x 10 4 s/m 3 Ground-Level Releases: (ENE Sector] i Elevated Releases: 4.10 x 10*8 s/m3 (ENE Sector) l ( 3-20 Rev. 8, 1/94 ~-
Hatch ODCM 3.3.2 Setooint for the Final Noble Gas Monitor on Each Telease Pathway ( 3.3.2.1 overview of Method 1 Gaseous af fluent radioactivity monitors are intended to alarm prior to exceeding j the limits of Section 3.1.2.a. Therefore, their alarm setpoints are established to ensure compliance with the following equations o AG
- ST = X
- Rg e = the lesser of I*
where c= the setpoint, in pCi/mL, of the radioactivity monitor measuring the concentration of radioactivity in the effluent line prior to release. The setpoint represents a concentration which, if exceeded, could result in dose rates exceeding the limits of Section 3.1.2.a at or beyond the SITE BOUNDARY. AG = an administrative allocation f actor applied to divide the release limit among all the gaseous release pathways at the site. SF = the safety factor selected to compensate for statistical fluctuations and errors of measurement. X= the noble gas concentration for the release under consideration. Rt= the ratio of the dose rate limit for the total body, 500 mrem /y, to the dose rate to the total body for the conditions of the release under consideration. , Rk= the ratio of the dose rate limit for the skin, 3000 mrom/y, to the dose rate to the skin for the conditions of the release under consideration. Equation (3.1) shows the relationships of the critical parameters that determine the setpoint. However, in order to apply the methodology presented in the equation to a mixture of noble gas radionuclides, radionuclide-specific concentrations and dose factors must be taken into account under conditions of maximum flowrate for the release point and annual average meteorology. 3-21 Rev. 8, 1/94
1 Hatch ODCM The basic setpoint method presented below is appatcable to the radioactivity O t monitor nearest the point of release fer the release pathway. For monitors 4 measuring the radioactivity in source str9ams that merge with other streams prior to subsequent monitoring and release, the modifications presented ir. Section 3.3.3 must be applied. 7 3.3.2.2 Setpoint calculation Steps i
- Step 1
- Determine the concentration, X;y, of each noble gas radionuclide i in the gaseous stream v' being considered for release, in accordance with the sampling and analysis requirements of Section 3.1.2. Then i sum these concentrations to determine the total noble gas a
concentration, 2: Xjy. s I i j Step 2: Determine R t , the ratio of the dose rate limit for the total body, i 500 mrom/y, to the total body dose rate due to noble gases detected
- in the release under consideration, as follows,
, a. for release pathways for which the release elevation is ground-levels O ,, . (T[5)vb b (Ki*Ov) i (3.2) ! i 1 ,4
- b. for release pathways for which the release elevation is elevated:
1
=
500
' Rg (3.3)
[i [Vi Djyj i where: 500 = the dose rate limit for the total body, 500 mrem /y. ' (X/Q)vb = the highest annual average relative concentration at the SITE BOUNDARY for the discharge point of release pathway v. Table 3-4 includes an indication of what release elevation is applicable to i each release pathway; release elevation determines the appropriate value of (X/6)vb' a O V f 3-22 Rev. 8, 1/94
._. . -- . . -~. .~.. -- -- - . _ ~ . _ - - . .. _-.- , -
Hatch ODCM ) i Kg = the total-body dose factor due to gamma emissions from noble gas
' radionuclide 1, iu (mrem /y)/(pCi/m 3), from Table 3-5.
Qy = the release rate of noble gas radionuclide i from the release j i pathway under consideration, in pCi/s, calculated as the product of Xiy and f,y, where: 1 1 X;y = the concentration of noble gas radionuclide i for the particular release, in pci/mL. e 1 0 f,y = the maximum anticipated flowrate for release pathway v during the period of the release under consideration, in l mL/s. l
- 1 Vj = the elevated finite-plume total body dose factor due to gamma emissions from noble gas radionuclide i in af fluents released from i the main stack, in (mrom/y)/(pci/s), from Table 3-6. f M
sten 3: Determine R k , the ratio of the dote rate limit for the skin, 3000 fi mrem /y, to the skin dose rate due to noble gases detected in the i U release under consideration, as follows, i a. for release pathways for which the release elevation is 1 ground-levels i 3000 i (3*4) (X/D)vb i[ [(Li
- l'18 l i
- O v}
- b. for release pathways for which the release elevation is 4
elevated: i i 30
- y.
( * } i { Lj tyTC)vb
- l'13 ]/
- O iv
. i i
where: 4 3000 = the dose rate limit for the skin, 3000 mrem /y. O 3-23 Rev. 8, 1/94
i
)
Hatch ODCM Lj = the skin dose f actor due to beta emissions f rom noble gas ractio-I nuclide 1, in (mrent/y)/(pci/m 3), from Table 3-5. 1 l M; = the air dose factor due to gamma emissions from noble gas radio-nuclide i, in (mrad /y)/(pci/m 3), from Table 3-5. l 1.1 = the factor to convert air dose in mrad to skin dose in arem. Bj = the elevated finite-plume air dose factor due to gamma emissions from noble gas radionuclide i in affluents released from the main stack, in (mrad /y)/(yci/s), from Table 3-6. All other terms were defined previously. steo 4: Determine the maximum noble gas radioactivity monitor setpoint con-centration. Based on the values determined in previous steps, the radioactivity monitor setpoint for the planned release is calculated to ensure that the, limits of f Section 3.1.2.a will not be exceeded. Because the radioactivity monitor responds l primarily to radiation from noble gas radionuclides, the monitor setpoint c ay (in pCi/mL) is based on the concentration of all noble gases in the waste stream, as l follows: 1 AGy
- SF * [ Xgy *R g
- the lesser of (3.6) c,, y AG y
- SF* [Xjy* Rg 5
where i e ny = the calculated setpoint, in pCi/mL, for the noble gas moniteir serving gaseous release pathway v. AG y = the administrative allocation factor for gaseous release pathway v, applied to divide the release limit among all the gaseous release pathways at the site. The allocation factor may be assigned any value between 0 and 1, under the condition that the sum of the allocation factors for all simultaneously-active final release pathways at the entire plant site does not exceed 1. 3-24 Rev. 8, 1/94
- ..n .. .. . - . . - . . . . - . . . - . . ~ ~ , ~ . . ~ . - .-- - .. - - . . _ . . .. . . .
? t Hatch ODCM i s Alternative methods for determination of AG y are presented in Section 3.3.4. f-the safety factor selected to compensate for statistical SF = fluctuations and errors of measurement. The value for the safety
- factor must be between 0 and 1. A value of 0.5 is reasonable for gaseous releaness a more precise value may be developed if desired. <
i ) X;y = the measured concentration of noble gas radionuclide i in gaseous j l stream v, as defined in Step 1, in pci/mL. i 3 The values of R t and Rk to be used in the calculation are those which were
- determined in Steps 2 and 3 above.
i j steo 5: Determine whether the release is permissible, as follows: 5 z f xjy, the release is permissible. However, if'cov is within about If e nv i j 10 percent of E Xjy, it may be impractical to use this value of c,y. 8 s This situation indicates that measured concentrations are approaching values which would cause the limits of Section 3.1.2.a to be exceeded. Therefore, steps should be taken to reduce ( contributing source terms of gaseous radioactive material, or to e adjust the allocation of the limits among the active release
- points. The setpoint calculations (steps 1-4) must then be
! repeated with parameters that refleet the modified conditions. 1 consider the i If env < I Xjy, the release may not be made as planned. 1 alternatives discussed in the paragraph above, and calculate a new 5 setpoint based on the results of the actions taken.
' 3.3.2.3 Use of the calculated Setpoint 1
5 ( The setpoint calculated above is in the units pci/mL. The monitor actually measures a count rate that includes background, so that the calculated setpoint must be converted accordingly: ch - ( c,,y Ey) + B y (3*7) where 3-25 Rev. 8, 1/94
Hatch ODCM e, = the monitor setpoint as a count rate. O ' V Ey = the monitor calibration factor, in count rate /(pci/mL). Monitor data for conversion between count rate and calibration include operational data obtained from concentration may determining the monitor response to ef fluent stream concentrations measured by sample analysis. the monitor background count rate. In all cases, monitor i By = background must be controlled so that the monitor is capable of 4 responding to concentrations in the range of the setpoint value. contributions to the monitor background may include any or all of I the following f actors ambient background radiation, plant-related ! radiation levels at the monitor location (which may change between 1 ' shutdown and power conditions), and internal background due to contamination of the monitor's sample chamber. f l The count rate units for eny, Ey , and By in equation (3.7) must be the same, cpm 4 or eps.
! 3.3.3 Setooints for Noble Gas Monitors on Ef fluent Source Streams O
O The listing in Table 3-4 shows that Plant Hatch currently has no gaseous release pathways that meet the following criterias a setpoint is required for then under the offluent controls of this ODCM1 and they are monitored prior to merging with other streams, and passing a final radioactivity monitor. This section, which presents a setpoint methodology for such monitors, is included in the Plant Hatch ODCM for compatibility with the ODCMs of the other Southern Company nuclear power plants. 1 3.3.3.1 Setpoint of the Monitor on the Source Stream
.Steo 1: Determine the concentration X;g of each noble gas radionuclide i in source stream s (in pCi/mL) according to the results of its l required sample analyses (see Section 3.1.2).
1 Steo 2: Determine rt, the ratio of the dose rate limit for the total body, 500 mrem /y, to the total body dose rate due to noble gases detected in the source stream under consideration. Use the Jis values and the maximum anticipated source stream flow rate f as in equation 1 3-26 Rev. 8, 1/94
Hatch ODCM (3.2) (or in e,quation (3.3) if the release is elevated) to determine the total body dose rate for the source stream, substituting rg for R* t The SITE BOUNDARY relative dispersion value used in Steps 2 and 3 for the source stream is the same as the (i76)vb that applies to the respective merged stream. This is because the (176) value is determined by the meteorology of the plant site and the physical attributes of the release point, and is unaffected by whether or not a given source stream is operating. Steo 3: Determine rk, the ratio of the dose rate limit for the skin, 2000 mrem /y, to the skin dose rate due to noble gases detected in the ! source stream under consideration. Use the X;, values and the maximum anticipated source stream flow rate fas in equation (3.4) (or in equation (3.5) if the release is elevated) to determine the skin dose rate for the source stream, substituting rk for R
- k j l
Steo 4: Determine the maximum noble gas radioactivity monitor setpoint con-centration, as follows: Q AG,
- ST * [ X;,
- vg II'8) c ,,, = the lesser of <
AG,
- ST * [ Xg,
- ry i
where: c as = the calculated setpoint (in pCi/mL) for the noble gas monitor l serving gaseous source stream s. AG s = the administrative allocation factor applied to gaseous source stream s. For a given final release point v, the sum of all the AG, values for source streams contributing to the final release point must not exceed the release point's allocation factor AGy. Xg, = the measured concentration of noble gas radionuclide i in gaseous source stream s, as defined in Step 1, in pCi/mL. 3-27 Rev. 8, 1/94 l \ _ - _ _ _ _ _ - _ _
- . . __ _ - . _ . _ _ ~ _ _ _ _
Hatch ODCM The values of rg and rk to be used in the calculation are those which were ;
/N The safety factor, SF, was defined I determined in steps 2 and 3 above. l previously. !
Stoo 5: Determine whether the release is permissible, as follows:
> If e ns E EXis, the release is permissible. However, if c , is within about 10 percent of I X;,, it may be impractical to use this value of ens
- 1 This situation indicates that measured concentrations are approaching val,ues which would cause the limits of Section 3.1.2.a j to be exceeded. Therefore, steps should be taken to reduce contributing source terms of gaseous radioactive material, or to adjust the allocation of the limits among the active release l points. The setpoint calculations (steps 1-4) must then be repeated with parameters that reflect the modified conditions. l 1
If ens < E X;,, the release may not be made as planned. Consider the j I alternatives discussed in the paragraph above, and calculate a new setpoint based on the results of the actions taken. O( 3.3.3.2 Effect on the Setpoint of the Monitor on the Merged Stream r Before beginning a release from a monitored source stream, a setpoint must be determined for the source stream monitor as presented in Section 3.3.3.1. In addition, whether or not the source stream hts its own ef fluent monitor, the previously-determined maximum allowable setpoint f or the downstream final monitor on the merged stream must be redetermined. This is accomplished by repeating the steps of Section 3.3.2, with the following modifications. Modification 1: The new maximum anticipated flowrate of the merged stream is the sum of the old merged stream maximum flowrate, and the maximum flowrate of the source stream being l considered for release. l ( f ,y ) ,,, = (f ,y)old + f as (3*') l Modification 2: The new concentration of noble gas radionuclide i in the merged stream includes both the contribution of the V 3-28 Rev. 8, 1/94 I
l Hatch ODCM I merged stream without the source stream, and the source stream being considered for release. \ (favlog * (Xiv)og + far
- Xis (Xiv)nne
* (3.10) l (favinne 3.3.4 Determination of Allocation Factors, AG I
When simultaneous gaseous releases ate conducted, an administrative allocation factor must be applied to divide t'he release limit among the active gaseous l release pathways. This is to assure that the dose rate limit for areas at and beyond the SITE BOUNDARY (see Section 3.1.2) will not be exceeded by simultaneous releases. The allocation factor for any pathway may be assigned any value between 0 and 1, under the following two conditions:
- 1. The sum of the allocation factors for all simultaneously-active final release paths at the plant site may not exceed 1,
- 2. The sum of the allocation factors for all simultaneously-active source streams merging into a given final release pathway may not exceed the allocation factor of that final release pathway.
Any of the following three methods may be used to assign the allocation f actors to the active gaseous release pathways: l
- 1. For ease of implementation, AGy may be equal for all release pathways:
AG v = 1 (3.11) l N 1 i I where: ! N= the number of simultaneously ective gaseous release pathways.
- 2. AGy for a given release pathway may be selected based on an estimate of l 1
the portion of the total SITE BOUNDARY dose rate (from all simultaneous releases) that is contributed by the release pathway. During periods when a given building or release pathway is not subject to gaseous radioactive releases, it may be assigned an allocation factor of zero. l
- 3. AGy for a given release pathway may be selected based on a calculation of the portion of the total SITE BOUNDARY dose rate that is contributed by the release pathway, as follows, 3-29 Rev. 8, 1/94
Hatch ODCM
- a. for ground-lovel release points:
( M )vb [ (K IO ly) 5 AG y = N (3.12) { (Vf Oj,) + { . (F/g)rb E(Ki Dr) i i r=1 i
- b. for the elevated release point (main stack):
{ {Vg 0;,)
= I AG y N (3.13)
{ (Vg Oj,) + { i (YJD)rb b (Ki Dr) i r=1 i where: (X7Q)vb
= the annual average SITE BOUNDARY relative concentration applicable to the gaseous release pathway v for which the 3
allocation factor is being determined, in s/m . Kj = the total-body dose factor due to gamma emissions from noble gas radionuclide 1, in (mrem /y)/(pci/m ), from Table 3-5. 3 ( - Q;y = the release rate of noble gas radionuclide i from release pathway v, in pCi/s, calculated as the product of X,y and f,y, where Xjy = the concentration of noble gas radionuclide i applicable to the gaseous release pathway v for which the allocation factor is being determined, in pCi/mL. f,y = the discharge flowrate applicable to gaseous release pathway v for which the allocation factor is being determined, in mL/s. Note: As applied in equations (3.12) and (3.13), Qjy is restricted to ground-level release pathways. V; = the elevated finite-plume total body dose factor due to gamma emissions f rom noble gas radionuclide i in ef fluents released from 4 o the main stack, in (mrom/y)/(pci/s), from Table 3-6. 3-30 Rev. 8, 1/94
Hatch gggg ! Qj, = the release rate of noble gas radionuclide i from the maan ' stack, in pci/s, calculated as t.hA product of the Xjy and f,y values specific to the main stack. ' ~ (X/Q)g = the annual average SITE BOUNDARY relative concen-tration applicable to active gaseous release pathway r, in s/m 3. h i Qj, = the value of Qgy applicable to active release pathway r, in i pci/s. 4 N = the number of simultaneously active gaseous release pathways j (including pathway v that is of interest). A0TE: Although equations (3.11), (3.12), and (3.13) are written to j illustrate the assignment of the allocation factors for final l release pathways, they may also be used to assign allocation factors to the source streams that merge into a given final release j pathway. 3.3.5 Setooints for Noble Gas Monitors with Soeelal Reauirements 4 Unit 1 Condenser Offons Pretreatment Monitor Monitor: 1D11-K601 and 1D11-K602 4 Unit 2 Condenser Of fons Pretreatment Monitor Monitors 2D11-K601 and 2Dll-K602 For the purpose of implementing Section 3.1.1, the alarm setpoint level for these noble gas monitors will be calculated as follows:
= 2.40 x 10 5 c,,
E m *t w where: 2.40 x 105= the release rate limit for pretreatment condenser offgas as specified in Technical Specification 3.7.6 in pCi/s. c ,c, = the reading of the condenser of fgas pretreatment monitor at the alare setpoint, in mR/h. O 3-31 Rev. 10, 7/95 l
_ __ _, . = . ~ _ _ _ _ ._ _ . . . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _.. _ .. _ _ .-_ _ _. . _ . . . _ _ _ . 2 Hatch ODCM 3 1 fw= the condenser offgas flowrate, in efm. ; j Setooints for Particulate and Iodine Monitors
~ ; 3.3.6 2
4 In accordance with Section 5.1.1 of NRC NUREG-0133 (Reference 1), the affluent i
> controls of section 3.1.1 do not require that the ODCM establish setpoint j I
calculation methods for particulate and iodine monitors. j l 1 i I l 1 1
- i l
l l s l 1 l 2 l 4 . l s l l l l
}
'l l 3-32 Rev. 8, 1/94
--r -
~ . . . - - . . . . . - . . . _ _ . - . . . ~ _ _ , . . - _ . . - - . . - . . - _ ,
i a Hatch ODCM 3.4 GASEOUS EFFLUT.NT COMPLIANCE CALCULATIONS I5 3.4.1 Dose Rates at and Beyond the Site Boundary 1 Because the dose rate limits for areas at and beyond the SITE specified in f Section 3.1.2 are site limits applicable at any instant in time, the susunations
! extend over all simultaneously active gaseous final release pathways at the plant ! site. Table 3-4 identifies the gaseous final release pathways at the plant site, and indicates the (176)vb ICY (I7 Isb] value for each.
d 3.4.1.1 Dose Rates Due to Noble Cases i i j For the purpose of implementing the controls of Section 3.1.2.a, the dose rates due to noble gas radionuclides in areas at or beyond the SITE BOUNDARY, due to releases of gaseous effluents, shall be calculated as follows: ; j For total body dose rates: DR g = {v (R7D)g { {Kj Ojy]k + { (Fj Oj,) (3.15) 4 [ t i i l 'l For skin doss rates: , DRA
=
{v (176)4 { { (Lj + 1.1Mj) Ojyjf t j I (3.16)
+
[
,I (I75)sh Li* 1*181 Dsi where:
I DR = the total body dose rate at the time of the release, in mres/y. 4 DRk= the skin dose rate at the time of the release, in mrom/y. ' l Q,y = the release rate of noble gas radionuclide i, in pCi/s, equal to the product of fgy and Kiy, where: f gy = the actual average flowrate for release pathway v during the period of the release, in mL/s. l < 3-33 Rev. 8, 1/94
Hatch ODCM Notes For equations (3.15) and (3.16), the definition of Q,y, and the summations over v, are restricted to ground-level release pathways. Q;, = the release rate of noble gas radionuclide i from the main stack, I in pCi/s, equal to the product of the f gy and X;y values specific to the main stack. (This definition applies to both equations (3.15) and (3.16).) (176)sb = the value of (176)vb for the main stack; that is, the highest annual average relative concentration at the SITE BOUNDARY, for the main stack, in s/m3 . Table 3-4 includes the value of (176)sb' All other terms were defined previously. 3.4.1.2 Dose Rates Due to Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form with Half-Lives Greater than 8 Days For the purpose of implementing the controls of Section 3.1.2.b, the dose rates due to Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form
/
with half-lives greater than 8 days, in areas at or beyond the SITE BOUNDARY, due to releases of gaseous effluents, shall be calculated as follows: P io Ofy + (k7d)sh { Pjo 0,f, (3.17) f DR o = {v (Jigr@) p , [ i i i where DRo = the dose rate to organ o at the time of the release, in ares /y. I Pjo = the site-specific dose f actor for radionuclide i and organ o, in (mrem /y) / (gCi/m 3
) . Since the dose rate limits specified in Section 3.1.2.b apply only to the child age group exposed to the inhalation pathway, the values of Pjo may be obtained f rom Table 3-9, *R,jp j for Inhalation Pathway, Child Age Group."
Qjy= the release rat's of radionuelide i from gaseous release pathway v, in pCL/s. For the purpose of implementing the controls of Section 3.1.2.b, only I-131, I-133, tritium, and all radionuclides in O 3-34 Rev. 8, 1/94
. - - .. . _ - - -- - -. - ~ . . - . . - . - - . - . ~
l Hatch ODCM I particulate form with half-lives greater than 8 d ys should be O included in this calculation. V i All other terms were defined previously. 4 3.4.2 Noble Cas Air Dose at or Beyond Site Boundarv For the purpose of implementing the controls of Section 3.1.3, air doses in areas at or beyond the SITE BOUNDARY due to releases of noble gases f rom each unit shall be calculated as follows (adapted from Reference 1, page 28, by including only long-term releases): l 4 a j Dg = 3.17 x 10~8 {v (T[Q)rb [ (Ni
- d it')
i (3.18) (T[E)sh b (Ni* is) i 4 1 l Dy
- 3.17 x 10~8 {' (x/g)p3 { (M; djy)
,v i (3.19)
- + [ {B;
- 6;3h i
where: 7 3.17 x 10-8 = a units conversion f acter: 1 y/(3.15 x 10 s). Dg = the air dose due to beta emissions from noble gas radionuclides, 1 in mrad. D = the air dose due to gamma emissions from noble gas radionuclides, 7 j in mrad. N; = the air dose factor due to beta emissions f rom noble gas radio-nuclide i, in (mrad /y)/(pci/m ), 3 from Table 3-5.
)
3-35 Rev. 8, 1/94
I l I Hatch ODCM l l (I76),h = the value of (176)vb for the main stack; that is, the highest annual average relative concentration at the SITE BOUNDARY, for the l main stack, in s/m . Table 3-4 includes the value of (i]D)sb' I l M; = the air dose factor due to gamma emissions from noble gas radio- , 3 nuclide i, in (mrao/y)/(pci/m ), from Table 3-5. Bj = the elevated finite-plume air dose f actor due to gaerea emissions from noble gas radionuclide i in effluents released from the main stack, in (mrad /y)/(pci/s), from Table 3-6. 6;y = the cumulative release of noble gas radionuclide i from non-elevated reb >ase pathway v, in ci, during the period of interest. 6;, = the value of 6, ' ir the main stack; that is, the cumulative release of noble gas radionuclide i from the main stack, in uci, during the period of interest. and all other terms are as defined above.
"" " '"' ' " " " " ' ' ' ' - ' ' ' " ' ' - " " ' ' ' ' ' ' ' ' ' " " " " ~ ' ' ' " ' ' ' ' ' " '
(D~ over all gaseous final release pathways (other than the main stack, which'has its own tens) for a given unit. For a release pathway discharging materials originating in both reactor units, the activity discharged from the release point l may be apportioned to the two units in any reasonable manner, provided that all activity relaated via the particular shared release pathway is apportioned to one or the other unit. The gaswous final release pathways at the plant site, and the (17D)vb IC' C"' are identified in Table 3-4. O 3-36 Rev. 8, 1/94
Hatch ODCM i Table 3-5. Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases y - Body (K) $ - Skin (L) y - Air (M) $ - Air (N) j l (mrem /y) per (mrem /y) per (mrad /y) per (mrad /y) per ! ' (pci/m 3) (pci/m 3) (pci/m 3) (pci/m 3) l l Kr-83m 7.56 E-02 0.00 E+00 1.93 E+01 2.88 E+02 Kr-85m 1 17 E+03 1.46 E+03 1.23 E+03 1.97 E+03 , Kr-85 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03 Kr-87 5.92 E+03 9.73 E+03 6.17 E+03 1.03 E+04 Kr-88 1.47 E+04 2.37 E+03 1.52 E+04 2.93 E+03 Kr-89 1.66 E+04 1.01 E+04 1.73 E+04 1.06 E+04 Kr-90 1.56 E+04 7.29 E+03 1.63 E+04 7.83 E+03 Xe-131m 9.15 E+01 4.76 E+02 1.56 E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94 E+02 3.27 E+02 1.48 E+03 Xe-133 2.94 E+02 3.06 E+02 3.53 E+02 1.05 E+03 Xe-135m 3.12 E+03 7.11 E+02 3.36 E+03 7.39 E+02 Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 1.51 E+03 1.27 E+04 Os Xe-137 1.42 E+03 1.22 E+04 Xe-138 8.83 E+03 4.13 E+03 9.21 E+03 4.75 E+03 Ar-41 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E+03 All s a'ues in this table were obtained from Reference 3 (Table B-1), with units converted. gN 3-37 Rev. 8, 1/94
Hatch ODCM j Table 3-6. Dose Factors for Exposure to Direct Radiation f rom Noble Games in ( an Elevated Finite Plume-( y - Total Body (V) y - Air (B) Nuclide (mram/y) per (uci/s) (mrad /y) per (uci/s) Kr-83m 0.00 E-00 0.00 E-00 Kr-85m 8.25 E-05 8.69 E-05 ; 1.26 E-06 1.35 E-06 f Kr-85 Kr-87 4.40 E-04 4.59 E-04 l Kr-88 1.09 E-03 1.13 E-03 Kr-89 9.44 E-04 9.87 E-04 Kr-90 7.00 E-04 7.38 E-04 Xe-131m 1.68 E-06 1.76 E-06 Xe-133m 1.29 E-05 1.37 E-05 Xe-133 1.38 E-05 1.43 E-05 l Xe-135m 2.42 E-04 2.59 E-04 f Xe-135 1.33 E-04 1.42 E-04 Xe-137 9.55 E-05 1.02 E-04 l Xe-138 6.16 E-04 6.44 E-04 Ar-41 7.34 E-04 7.72 E-04 i l Values are as reported in Reference 24. They were calculated in accordance' with Ref erence 1 (Section 5.2.1) and Reference 3 ( Appendix F), using the meteorological joint frequency distributions presented in Reference 14. All values in this table are for the Site Boundary (1545 m) in the ENE sector. l l l
)
3-38 Rev. 8, 1/94
Hatch ODCM 3.4.3 Deze to a Member of the Public at or Beyond Site Boundary v The dose received by an individual due to gaseous releases from each reactor unit, to areas at or beyond the SITE BOUNDARY, depends on the individual's location, age group, and exposure pathways. The MEMBER OF THE PUBLIC expected to receive the highest dose in the plant vicinity is referred to as the controlling receptor. The dosimetrically-significant attributes of the currently-defined controlling receptor are presented in Table 3-7. Doses to a MEMBER OF THE PUBLIC due to gaseous releases of I-131, I-133, tritium, and all radionuclides in particulate form from each unit shall be calculated as follows (equation adapted from Reference 1, page 29, by considering only long-term releases): Dja
- 3.17 x 10-8 {< { R ap jj { W yfp *d (3.20) p i v i
where i Dja = the dose to organ j of an individual in age group a, due td gaseous I releases of I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in mrom. f 7 3.17 x 10-8 = a units conversion factor: 1 y/(3.15 x 10 s).
= the site-specific dose factor for age group a, radionuclide 1, R,jpj expcsure pathway p, and organ j. For the purpose of implementing the controls of Section 3.1.4, the exposure pathways applicable to calculating the dose to the currently-defined controlling receptor are included in Table 3-7; values of Raipj for each exposure pathway and radionuclide applicable to calculations of dose to the controlling receptor are listed in Table 3-8 through Table 3-10.
A detailed discussion of the methods and parameters used for calculating R,;pj for the plant site is presented in Chapter 9. That information may be used for recalculating the R,jp j values if the underlying parameters change, or for calculating R,;p; values O 3-39 Rev. 8, 1/94
Hatch ODCM for special radionuclides and age groups when performing the
~
~
r ~ assessments discussed in'Section 3.4'.4 below. \ Wy ;p = the annual average relative dispersion or deposition at the location of the controlling receptor, for release pathway v, as appropriate to exposure pathway p and radionuclide 1. For all tritium pathways, and for the inhalation of any radio-nuclide: Wy ;p is (176)yp, the annual average relative dispersion factor for release pathway v, at the location of the controlling receptor (s/m 3). For the ground-plane exposure pathway, and for all ingestion-related pathways for radionuclides other than tritium: Wy ;p is (676)yp, the annual average relative deposition factor for release pathway v, at the location of the controlling receptor (m-2). Values of (176)yp and (676)yp for use in calculating the dose to the currently-defined controlling receptor are included in Table 3-7. 6ly= the cumulative release of radionuclide i from release pathway v, during the period of interest (pC1). For the purpose of implementing the controls of Section 3.1.4, only I-131, I-133, G tritium, and all radionuclides in particulate form with half-lives h greater than 8 days should be included in this calculation. In any dose assessment using the methods of this sub-section, only radio-nuclides detectable above background in their respective samples should be included in the calculation. Because the MEMBER OF THE PUBLIC dose limit is on a per-unit basis, the summations extend over all gaseous final release pathways for a given unit. For a release pathway discharging materials originating in both reactor units, the activity discharged f rom the release point may be apportioned between the two units in any reasonable manner, provided that all activity releasej from the plant site is apportioned to one or the other unit. The gaseous final release patnways at the plant site, and the release elevation for each, are identified in Table 3-4. e i V 3-40 Rev. 8, 1/94
Hatch ODCM ! l l Table 3-7. Attributes of the Controlling Receptor Os The locations of members of the public in the vicinity of the plant site, and the exposure pathways associated with those locaticas, were determined in the Annual Land Use census (Reference 12). Dispersion and deposition values were calculated based on site meteorological data collected for the period 1984 through 1986 (Reference 16). i Based on an analysis of this information, the current controlling receptor for l the HNP site is described as follows. l l Sector: Wsw Distance: 1.2 miles Ace GE222: Child Exoosure Pathways: Ground plane Inhalation Garden vegetation Dispersion Factors (X7Dl yp t 3.18 x 10 4 s/m3 ) Ground-Level: Elevated: 6.53 x 10 8 ,f,3 I Deoosition Factors (D76) : Ground-Level: 8 80 x 10~9 m*2
*2 Elevated: 1.37 x 10~9 m i
Elevated Plume Dose Fact 211 + Radionuclide Radionuclide (mrem /y)/(uci/s) (mrem /y)/(pci/s) Kr-85m 6.92 E-05 Xe-133m 1.07 E-05 Kr-85 9.95 E-07 Xe-133 1.23 E-05 Kr-87 3.36 E-04 Xe-135m 1.90 E-04 Kr-88 8.23 E-04 Xe-135 1.09 E-04 Kr-89 7.20 E-04 Xe-137 7.54 E-05 Kr-90 5.39 E-04 Xe-138 4.71 E-04 Xe-131m 1.42 E-06 l Ar-41 5.59 E-04
+ These values were calculated using the methods and data described in
- Reference 29. They are necessary when performing calculations for the purpose of demonstrating compliance with the limits of Section 5.1.
3-41 Rev. 8, 1/94
. - - - . . - . . - - . - - - . - ~ ~ . - - - . . - . . . - - - -
i Hatch ODcM I 3.4.4 E2pe calculations to Succort Other Raouirements i l Under 10 CFR 50.73, a radiological impact assessment may be )' case la l required to support evaluation of a reportable event. 1 i <
- Dose calculations may be performed using the equations in Section 3.4.3, with the substitution of the dispersion and deposition parameters [(X/Q) f and (D/Q)] for the period covered by the report, and using the appropriate pathway dose factors (R,j Methods for l p j) for the receptor of interest.
! calculating (x/Q) and (D/Q) from meteorological data are presented in Chapter 8. The values of R,;pj presented in Table 3-8 through Table 3-10 are applicable only to the currently-dsfined controlling receptor, so that when dose calculations must be performed for a different receptor, R ;p; values applicable to that receptor must first be calculated. Methods and parameters for calculating R,j p; for radionuclides and age groups other than those required in section 3.4.3 are presented in Chapter 9. When calculating R ;pj for evaluation of an event, pathway and usage factors specific to the receptor involved in the event may be used in place of the values in Chapter 9, if the specific values are known. O case 2: A dose calculation is required to evaluate the results of the Land Use Census, under the provisions of Section 4.1.2. In the event that the Land Use Census reveals that exposure pathways have changed at previously-identified locations, or if new locations are j identified, it may be necessary to calculate doses at two or more l locations to determine which should be designated as the controlling receptor. Such dose calculations may be performed using the equations in section 3.4.3, with the substitution of the annual average dispersion and deposition values [(K/6) and (67 )) for the locations of interest, and using the appropriate pathway dose factors (R,;pj) for the receptors of interest. Methods for calculating (X/Q) and (D/Q) from meteorological data are presented in Chapter 8. The values of R,;p; presented in Table 3-8 through i Table 3-10 are applicable only to the currently-defined controlling receptor, so that when dose calculations must be performed for a different receptor, R,p; values applicable to that receptor must first be calculated. O ; 3-42 Rev. 10, 7/95
._ - _ - - . . - . - - . . . .~. ~..-- __ . .-..~..._- --
a d J > 4 Hatch ODCM for radionuclides and age Methods and parameters for calculating Raipj f groups other than those required in section 3.4.3 are presented in Chapter 9. case 3: Under section 5.2, a dose calculation is required to support determination of total dose to a receptor of age group other than ; ' that currently defined as the controlling receptor. } Dose calculations shall be perf ormed using the equations in Section 3.4.3, I using the dispersion and deposition parameters defined in Table 3-7 for the controlling receptor, but substituting the appropriate pathway dose j factors (R,jpj) for the receptor age group of interest. 1 i The values of R ;pj presented in Table 3-6 through Table 3-10 are applicable ' only to the currently-defined controlling receptor, so that when dose l calculations must be performed f or a dif ferent receptor age group, R,;pj values applicable to that receptor must first be calculated. Methods and I parameters for calculating R,;pj for radionuclides and age groups other than those required in section 3.4.3 are presented in Chapter 9. I i 1 4 3-43 Rev. 10, 7/95
Hatch ODCM Table 3-8. Raipj for Ground Plane Pathway, All Age Groups Nuclide T. Body Skin H-3 0.00 0.00 C-14 0.00 0.00 ' P-32 0.00 0.00 Cr-51 4.66E+06 5.51E+06 Mn-54 1.39E+09 1.63E+09 Fe-55 0.00 0.00 Fe-59 2.73E+08 3.21E+08 Co-58 3.79E+08 4.44E+08 Co-60 2.15E+10 2.53E+10 Ni-63 0.00 0.00 Zn-65 7.47E+08 8.59E+08 Rb-86 8.99E+06 1.03E+07 i Sr-89 2.16E+04 2.51E+04 Sr-90 0.00 0.00 Y-91 1.07E+06 1.21E+06 Zr-95 2.45E+08 2.84E+08 Nb-95 1.37E+08 1.61E+08 Ru-103 1.08E+08 1.26E+08 Ru-106 4.22E+08 5.07E+08 Ag-110m 3.44E+09 4.01E+09 Sb-124 5.98E+08 6.90E+08 Os Sb-125 2.34E+09 2.64E+09 Te-125m 1.55E+06 2.13E+06 Te-127m 9.16E+04 1.08E+05 Te-129m 1.98E+07 2.31E+07 I-131 1.72E+07 2.09E+07 l I-133 2.45E+06 2.98E+06 Cs-134 6.86E+09 8.00E+09 Cs-136 1.51E+08 1.71E+08 Cs-137 1.03E+10 1.20E+10 Ba-140 2.05E+07 2.35E*07 Ce-141 1.37E+07 1.54E+07 Ce-144 6.95E+07 8.04E+07 Pr-143 0.00 0.00 Nd-147 8.39E+06 1.01E+07
- 1. Units are m 2-(mrem /yr)/(pCL/s).
- 2. The values in the Total Body column also apply to the Bone, Liver, Thyroid, Kidney, Lung, and GI-LLI organs.
- 3. This table also supports the calculations of Section 6.2.
O Rev. 8, 1/94 3-44
=_ . . . _ -- . .- . . . . . ---.
Hatch ODCM Table 3-9. R,jg for Inhalation Pathway, Child Age Group Bone Liver T. Sody Thyroid Kidney Lung GI-LLI Nuclide H-3 0.00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 3.59E+04 6.73E+03 6.73E+03 b 73E+03 6.73E+03 6.73E+03 6.73E+03 C-14 1.14E+05 9.88E+04 0.00 0.00 0.00 4.22E+04 P-32 2.60E+06 0.00 0.00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 ! cr-51 Mn-54 0.00 4.29E+04 9.51E+03 0.00 1.00E+04 1.58E+06 2.29E+04 Fe-55 4.74E+04 2.52E+04 7.77E+03 0.00 0.00 1.11E+05 2.87E+03 2.07E+04 3.34E+04 1.67E+04 0.00 0.00 1.27E+06 7.07E+04 Fe-59 Co-58 0.00 1.77E+03 3.16E+03 0.00 0.00 1.11E+06 3.44E+04 Co-60 0.00 1.31E+04 2.26E+04 0.00 0.00 7.07E+06 9.62E+04 i Ni-63 8.21E+05 4.63E+04 2.80E+04 0.00 0.00 2.75E+05 6.33E+03 Zn-65 4.26E+04 1.13E+05 7.03E+04 0.00 7.14E+04 9.95E+05 1.63E+04 1.98E+05 1.14E+05 0.00 0.00 0.00 7.99E+03 Rb-86 0.00 Sr-89 5.99E+05 0.00 1.72E+04 0.00 0.00 2.16E+06 1.67E+05 1.01E+08 0.00 6.44E+06 0.00 0.00 1.48E+07 3.43E+05 Sr-90 Y-91 9.14E+05 0.00 2.44E+04 0.00 0.00 2.63E+06 1.84E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 0.00 5.96E+04 2.23E+06 6.11E+04 Nb-95 2.35E+04 9.18E+03 6.55E+03 0.00 8.62E+03 6.14E+05 3.70E+04 0.00 1.07E+03 0.00 7.03E+03 6.62E+05 4.48E+04 Ru-103 2.79E+03 0.00 1.69E+04 0.00 1.84E+05 1.43E+07 4.29E+05 Ru-106 1.36E+05 o g Ag-110m 1.69E+04 1.14E+04 9.14E+03 Sb-124 Sb-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.12E+04 5.48E+06 1.OOE+05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 1.92E+03 0.00 4.77E+05 3.38E+04 Te-125m 6.73E+03 2.33E+03 9.14E+02 Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 J 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00 2.84E+03 l I-131 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00 5.48E+03 I-133 Cs-134 6.51E+05 1.01E+06 2.25E+05 0.00 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1.71E+05 1.16E+05 0.00 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 0.00 2.82E+05 1.04E+05 3.62E+03 Ba-140 7.40E+04 6.48E+01 4.33E+03 0.00 2.11E+01 1.74E+06 1.02E+05 Co-141 3.92E+04 1.95E+04 2.90E+03 0.00 8.55E+03 5.44E+05 5.66E+04 Ce-144 6.77E+06 2.12E+06 3.61E+05 0.00 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 0.00 3.00E+03 4.33E+05 9.73E+04 Nd-147 1.08E+04 8.73E+03 6.81E+02 0.00 4.81E+03 3.28E+05 8.21E+04
- 1. Units are (mrem /yr)/(pci/m 3
) for all radionuclides.
- 2. This table also supports the calculations of Section 6.2.
O 3-45 Rev. 8, 1/94
Hatch ODCM Table 3-10. R,;p; for Garden Vegetation Pathway, Child Age Group Liver T. Body Thyroid Kidney Lung GI-LLI Nuclide Bone H-3 0.00 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 0.00 0.00 0.00 9.31E+07 P-32 3.37E+09 1.58E+08 1.30E+08 cr-51 0.00 0.00 1.17E+05 6.50E+04 1.78E+04 1.19E+05 6.21E+06 0.00 6.65E+08 1.77E+08 0.00 1.86E+08 0.00 5.58E+08 ! Mn-54 ' 8.01E+08 4.25E+08 1.32E+0B 0.00 0.00 2.40E+08 7.87E+07 Fe-55 Fe-59 3.98E+08 6.43E+08 3.20E+08 0.00 0.00 1.86E+08 6.70E+08 0.00 6.44E+07 1.97E+08 0.00 0.00 0.00 3.76E+08 Co-58 0.00 3.78E+08 1.12E+09 0.00 0.00 0.00 2.10E+09 Co-60 3.95E+10 2.11E+09 1.34E+09 0.00 0.00 0.00 1.42E+08 Ni-63 8.13E+08 2.16E+09 1.35E+09 0.00 1.36E+09 0.00 3.80E+08 Zn-65 0.00 4.52E+08 2.78E+08 0.00 0.00 0.00 2.91E+07 Rb-86 0.00 1.03E+09 0.00 0.00 0.00 1.39E+09 Sr-89 3.6CE+10 0.00 3.15E+11 0.00 0.00 0.00 1.67E+10 Sr-90 1.24E+12 0.00 4.99E+05 0.00 0.00 0.00 2.48E+09 Y-91 1.86E+07 0.00 1.21E+06 0.00 8.85E+08 Zr-95 3.86E+06 8.48E+05 7.55E+05 0.00 1.50E+05 0.00 2.96E+08 Nb-95 4.10E+05 1.60E+05 1.14E+05 0.00 5.90E+06 0.00 3.86E+07 0.00 3.97E+08 Ru-103 1.53E+07 0.00 9.30E+07 0.00 1.01E+09 0.00 1.16E+10 Ru-106 7.45E+08 0.00 4.04E+07 0.00 2.58E+09 Ag-110m 3.21E+07 2.17E+07 1.73E+07 O' Sb-124 Sb-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00 0.00 3.38E+08 j Te-125m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00 1.07E+09 Te-127m 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 0.00 1.03E+09 Te-129m 0.00 1.28E+07 I-131 1.43E+08 1.44E+08 8.17E+07 4.75E+10 2.36E+08 3.53E+06 4.37E+06 1.65E+06 8.11E+08 7.28E+06 0.00 1.76E+06 I-133 Cs-134 1.60E+10 2.63E+10 5.55E+09 0.00 8.15E+09 2.93E+09 1.42E+08 Cs-136 8.24E+07 2.27E+08 1.47E+08 0.00 1.21E+08 1.80E+07 7.96E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 0.00 7.46E+09 2.68E+09 1.43E+08 Ba-140 2.77E+08 2.42E+05 1.61E+07 0.00 7.89E+04 1.45E+05 1.40E+08 Ce-141 6.56E+05 3.27E+05 4.86E+04 0.00 1.43E+05 0.00 4.08E+08 Ce-144 1.27E+08 3.98E+07 6.78E+06 0.00 2.21E+07 0.00 1.04E+10 Pr-143 1.46E+05 4.37E+04 7.23E+03 0.00 2.37E+04 0.00 1.57E+08 Nd-147 7.15E+04 5.79E+04 4.48E+03 0.00 3.18E+04 0.00 9.17E+07 Units are (mrem /yr)/(pci/m 3
) for tritium, and m 2-(mrem /yr)/(yci/s) for all other radionuclides.
O 3-46 Rev. 8, 1/94
Hatch ODCM 3.5 GASEOUS EFFLUENT DOSE PROJECTIONS i p iV I 3.5.1 Thirty-one Day Dose Proiections Because continuous operation of the gaseous radwaste treatment system is required (see section 3.1.5), routine 31-day dose projections are not required for effluent control compliance at Plant Hatch. However, whenever it is desired to perform such projections, projected 31-day air doses and doses to individuals due to gaseous effluents may be determined as follows: For air doses:
' Dge' Dgp
= x 31 +
Dg, i
'7' (3.21) I t 'o '
j D yp = x 31 + D ya ; I i For individual doses: D og = x 31 + D u (3.22) where the projected air dose due to beta emissions from noble gases, for . Dgp = the next 31 days of gaseous releases. Dge = the cumulative air dose due to beta emissions from noble gas 1 releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration. i Dg, = the anticipated air dose due to beta emissions f rom noble gas i releases, contributed by any planned activities during the next 31-day period, if those activities will result in gaseous releases that are in addition to routine gaseous ef fluents. If only routine gaseous ef fluents are anticipated, Dg, may be set to zero. a D = the projected air dose due to gamna emissions f rom noble gases for 9 the next 31 days of gaseous releases. t N 3-47 Rev. 8, 1/94 l
q l Hatch ODCM l l Dp = the cumulative air dose due to gamma emissions from noble gas l releases that have occurred in the elapsed portion of the current 4 quarter, plus the release under consideration. l l D,= y the anticipated air dose due to gamma emissions from noble gas releases, contributed by any planned activities during the next 31-day period, if those activities will result in gaseous releases that are in addition to routine gaseous effluents. If only routine gaseous affluents are anticipated, Dp may be set to zero. D op = the projected dose to the total body or organ o, due to releases of I-131, I-133, tritium, and particulates for the next 31 days of gaseous releases. Doe = the cumulative dose to the total body or organ o, due to releases of I-131, I-133, tritium, and particulates that have occurred in the elapsed portion of the current quarter, plus the release under consideration. D,= o the anticipated dose to the total body or organ o, due to releases f of I-131, I-133, tritium, and particulates, contributed by any I planned activities during the next 31-day period, if those I activities will result in gaseous releases that are in addition to routine gaseous effluents. If only routine gaseous effluents are anticipated, D o, may be set to zero. t= the number of whole or partial days elapsed into the current quarter, including the time to the end of the release under consideration (even if the release continues into the next quarter). 3.5.2 Dose Proisetions for Specific Releases Dose projections may be performed for a particular release by performing a pre- j release dose calculation assuming that the planned release will proceed as l l anticipated. For air dose and individual dose projections due to gaseous I effluent releases, fellow the methodology of Section 3.4, using sample analysis results for the gaseous stream to be released, and parameter values expected to exist during the release period. I O . 1 3-48 Rev. 8, 1/94
-. ~ ._ _ - . . - -- . . - - -
t Hatch ODCM l i I 3.6 DEFINITIONS OF GASEOUS EFFLUENT TERMS Section of l O I.EE3D Definition Initial Use I AG = the administrative allocation factor for gaseous l l streams, applied to divide the gaseous release limit among all the release pathways (unitiess). 3.3.2.2 AG, = the administrative allocation factor for gaseous source stream s, applied to divide the gaseous release limit among all the release pathways 3.3.3 (unitiess). AG y = the administrative allocation factor for gaseous ; l release pathway v, applied to divide the gaseous ) release limit among all the release pathways i i 3.3.2.2 (unitiess). Bj = the elevated finite plume air dose factor due to gamma emissions from noble gas radionuclide i in the effluents released from the main stack 3.3.2.2 ((mrad /y)/(pci/s)). c= the setpoint of the radioactivity monitor measuring the concentration of radioactivity in the ef fluent 3.3.2.1 line prior to release [pci/mL). c nco = the reading of the condenser offgas pretreatment monitor at the alarm setpoint (mR/h). 3.3.5 the calculated noble gas effluent monitor setpoint cns = 3.3.3 for gaseous source stream n (pci/mL). the calculated noble gas effluent monitor setpoint cav = for release pathway v (pci/mL). 3.3.2.2 Dj, = the dose to organ j of an individual in age group a, due to gaseous releases of I-131, I-133, tritium, and radionuclides in particulate form with half-lives 3.4.3 greater than 8 days (mrem). 3-49 Rev. 8, 1/94
. . - - - , _ . -~ _ ~_~ ~. _-
. Hatch ODCM ' Section of Definition Initial Use
/"~h It.Im i
' D,= o the anticipated dose to organ o due to releases of non-noble-gas radionuclides, contributed by any planned activities during the next 31-day period 3.5.1 (mrem). the cumulative dose to organ o due releases of non-Doe = noble-gas radionuclides that have occurred in the elapsed portion of the current quarter, plus the 3.5.1 release under consideration (mrom). a D op = the projected dose to organ o due the next 31 days of ganeous releases of non-noble-gas radionuclides 3.5.1 (mrom). Dg = the air dose due to beta emissions from noble gas , 3.4.2 radionuclides (mrad). Dg, = the anticipated air dose due to beta emissions from noble gas releases, contributed by any planned activities during the next 31-day period [ mrad). 3.5.1
)
Dge = the cumulative air dose due to beta emissions from noble gas releases that have occurred in the elapsed l portion of the current quarter, plus the release 3.5.1 under consideration (mrad]. i Dgp = the projected air dose due to beta emissions from noble gases, for the next 31 days of gaseous releases i 3.5.1 (mrad). Dy = the air dose due to gamma emissions from noble gas 3.4.2 radionuclides (mrad). D,= the anticipated air dose due to gamma emissions from y noble gas releases, contributed by any planned 3.5.1 activities during the next 31-day period [ mrad). 0 Rev. 8, 1/94 3-50
Hatch ODCM Section of Definition Initial Use Igg 3 the cumulative air dose due to gamna emissions f rom Dye = noble gas releases that have occurred in the elapsed portion of the current quarter, plus the release 3.5.1 under consideration (mrad). D7p = the projected air dose due to gamma emissions from noble gases, for the next 31 days of gaseous releases 3.5.1 (mrad). (D/D)yp = the annual average relative deposition factor for release pathway v, at the location of the controlling receptor, from Table 3-7 (m-2). 3.4.3 DRk= the skin dose rate at the time of the release 3.4.1.1 (mrom/y). DRo = the dose rate to organ o at the time of the release 3.4.1.2 (mrem /y). \ DRg= the total body dose rate at the time of the release 3.4.1.1 (mrem /y). E co = the calibration factor for the condenser offgas pretreatment monitor [(pci/s) per (cfm mR/h)]. 3.3.5 f,y = the maximum anticipated actual discharge flowrate for release pathway v during the period of the planned 3.3.2.2 release (mL/s). the condenser offgas flowrate (cfm). 3.3.5 feo = f ,, = the maximum anticipated actual discharge flowrate for gaseous source stream o during the period of the 3.3.3 planned release (mL/s). Kj = the total body dose factor due to gammaa emissions from noble gas radionuclide i, from Table 3-5 3.3.2.2 ((mrom/y)/(pci/m3 )). 3-51 Rev. 8, 1/94
Hatch ODCM Section of Definition Initial Use ( I.SJ3D
~,
L; = the skin dose f actor due to beta emissions from noble radionuclide 1, from Table 3-5 gas 3.3.2.2 ((arem/y)/(pC1/m3 )). M; = the air dose f actor due to gamma emissions from noble 1, from Table 3-5 gas radionuclide 3.4.2 ((mrad /y)/(pci/m3 )]. N= the number of simultaneously active gaseous release 3.3.4 pathways (unitiess). Nj = the air dose f actor due to beta emissions f rom noble 1, from Table 3-5 gas radionuclide 3.4.2 ((mrad /y)/(pci/m3 ) j. Pjo = the site-specific dose factor for radionuclide 1 (I-131, I-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days) t and organ o. The values of P;o are equal to the site- , presented in Table 3-9 spacific R,jp; values 3.4.1.2 [(mrom/y)/(pC1/m3 )) . Qy = the release rate of noble gas radionuclide i from i release pathway v during the period of interest 3.3.2.2 (pci/s). Qjy= the release rate of radionuclide 1 (I-131, I-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days) from gaseous release 3.4.1.2 pathway v during the period of interest (pci/s). 6,i = the cumulative release of noble , gas radionuclide i from the main stack during the period of interest 3.4.2 (pci). 6,y = the cumulative release of noble gas radionuclide i f rom release pathway v during the period of interest A 3.4.2 [pci). 3-52 Rev. 8, 1/94
- .- . . _ - _ . - - . . _ . . ... . . . . _ ~ . - . . . .
Hatch ODCM i
\
Section of Definition Initial Use IgIg1 i 6],w the cumulative release of non-noble-gas radionuclide i from release pathway v, during the period of interest [pci). 3.4.3 R ,jp ; = the site-specific dose f actor for age group a, radio-nuclide i, exposure pathway p, and organ j. Values and units of R,j jpfor each exposure pathway, age and radionuclide that may arise in group, calculations for implementing Section 3.1.4 are listed in Table 3-8 through Table 3-10. 3.4.3 Rk= the ratio of the skin dose rate limit for noble gases, to the skin dose rate due to noble gases in 3.3.2.1 the release under consideration (unitiess). l I Rg= the ratio of the total body dose rate. limit for noble gases, to the total body dose rate due to noble gases 3.3.2.1 in the release under consideration (unitiess). O . L) rk = the ratio of the skin dose rate limit for noble gases, to the skin dose rate due to noble gases in 3.3.3.1 the source stream under consideration (unitiess). rg = the ratio of the total body dose rate limit for noble gases, to the total body dose rate due to noble gases in the source stream under consideration 3.3.3.1 (unitiess). safety factor used in gaseous setpoint SF = the calculations to compensate for statistical 3.3.2.2 fluctuations and errors of measurement (unitles s ) . t= the number of whole or partial days elapsed in the current quarter, including the period of the release 3.5.1 under consideration. Vj = the elevated finite plume total body dose f actor due to gamma emissions from noble gas radionuclide i in b V. 3-53 Rev. 8, 1/94
- . - .- . - . . . . . - . . - . . . - . _ - - - . . - - . ~ - . - . . . - . . . - . .- ._.. -
1 1 j Hatch ODcM ,
- section of j Ings Definition Initial Use i
] _ _ . . _ . . , 1~ j the effluents released from the main stack [(aree/y)/(pci/s)). 3.3.2.2 W,;p = the annual average relative dispersion ((i?6)yp) or at the location - of the ] deposition [(576)yp) controlling receptor,, for release pathway v, as i appropriate to exposure pathway y and radio-nuclide 1. 3.4.3 f- , ! X= the noble gas concentration for the release under consideration [yci/mL). 3.3.2.1 the concentration of radionuclide i applicable to Xir = i active gaseous release pathway r [pci/mL). 3.3.4 i i i X;, = the esasured concentration of radionuclide i in $ gaseous source ntroam s [yci/mL). 3.3.3 ? f Xiy = the measured concentration of radionuclide i in gaseous stream v [pci/mL). "3.3.2.2 f 9 i (X/Q) = the highest relative concentration at any point at or l 3.3.2.1 j beyond the SITE BOUNDARY [ s / n:3') . l (I76)4 = the annual average SITE BOUNDARY relative concen-tration applicable to active gaseous release pathway l 3.3.4 , r (s/e 3), i (i]6),h = the highest annual average relative concentration at the SITE BOUNDARY for the main stack, from Table 3-4 l I 3 3.4.2 f (s/m ). i i 1 the highest annual average relative concentration at
~
l (176)vb = " the SITE BOUNDARY for the discharge point of release pathway v, from Table 3-4 (s/m3 ). 3.3.2.2 1 1 i 1 ?
- 3-54 Rev. 8, 1/94 i
1 5
,m m. ~ --
l Hatch ODCM l Section of Definition Inittal Use Iggi (17h)yp = annual average relative dispersion f actor for release f at the -location of the controlling pathway v, l 3.4.3 receptor, from Table 3-7 (s/m3 ). , I li l l l J l l l 1
)
l 1 l l I J l l l 3-55 Rev. 8, 1/94 l
I 4 Hatch ODCM L 4 CHAPTER 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 LIMITS OF OPERATION 1 The following limits are the sama for both units at the site. Thus, a single program' including monitoring, land use survey, and quality assurance serves both units. 4.1.1 Radioloaical Environmental Monitorino i TheRadiologicalEnvironmentalMonitoringProgram(REMP)-shallbeconductedasl specified in Table 4-1. 4.1.1.1 Applicability This control applies at all times. i 4.1.1.2 Actions 4.1.1.2.1 With the REMP not being conducted as specified in Table 4-1, submit O to the Nuclear Regulatory Commission (NRC), in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting l the program as required and the plans for preventing a recurrence. Deviations f rom the required sampling schedule are permitted if specimens are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction, or other just reasons. If deviations are due to equipment malfunction, efforts shall be made to complete corrective action prior to the end of the next sampling period. 4.1.1.2.2 With the confirmed' measured level of radioactivity as a result of I plant effluents in an environmental sampling medium specified in Table 4-1 exceeding the reporting levels of Table 4-2 when averaged over any calendar quarter, submit within 30 days a Special Report to the NRC. The Special Report shall identify the cause(s) for exceeding the limit (s) and define the corrective action (s) to be taken to reduce radioactive af fluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of sections 2.1.3, 3.1.3, and 3.1.4. The methodology and parameters used to 4
' Defined as confirmed by reanalysis of the original sample, or analysis of a duplicate or new sample, as appropriate. The results of the confirm-O V
atory analysis shall be completed at the earliest time consistent with the analysis. 4-1 Rev. 10, 7/95
. . . . - - - .. . .. -..-.-. . - - _ - _ - .-. - - ~ _ - . - .
Hatch M estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in the special Report. l When more than one of the radiom.-lides in Table 4-2 are detected in the sampling l medium, this report shall be submitted ifs ; 1 concentration (1) co.;contration (2)
, +...k 1.0 (4.1) reporting level (1) repo.-ting !evel (2)
When radionuclides other than those in' Table 4-2 are detected and are the result of plant effluents, this special Report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits stated in sections 2.1. 3, 3.1. 3, and 3.1. 4. This special Report is i not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be described in the Annual Radiological Environmental Operating Report. Thelevelsofnaturally-l occurring radionuclides which are not included in the plant's effluent releases ; need not be roported. 4.1.1.2.3 If adequate samples of milk, or during the growing season, grass or leafy vegetation, can no longer be obtained from one or more of the sample locations required by Table 4-1, or if the availability is frequently or persistently wanting, ef forts shall be made: to identify specific locations for l ' obtaining suitable replacement samples; and to add any replacement locations to the REMP given in the ODCM within 30 days. The specific locations from which i samples became unavailable may be deleted from the REMP. Pursuant to Technical , specification 5.5.1, documentation shall be submitted in the next Radioactive l Effluent Release Report for the chanp(s) in the ODCM, including revised figure (s) and table (s) reflecting the changes to the location (s), with supporting information identifying the cause of the unavailability of samples and justifying the sele tion of any new location (s). When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be stade if, as a minimum, the requirements of the ACTION statement are satisfied. l l l IO 4-2 Rev. 10, 7/95 l
Hatch ODcM 4.1.1.3 surveillance Requirements ( The REMP samples shall be collected pursuant to Table 4-1 from the locations ( described in section 4.2, and shall be analyzed pursuant to the requirements of Table 4-1 and Table 4-3. Required detsetion capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the i recommendations of Regulatory Guide 4.13. Program changes may be initiated based ; on operational experience. Analyses shall be performed in such a manner that the stated MINIMUM DETECTABLE CONCENTRATIONS (MDCs) will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering radionuclides, or other uncontrollable circumstances may render these MDCs unachievable. In euch cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report. l 4.1.1.4 Basis The REMP required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways, and for those radionuclides, which lead to the highest poter al radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant operation. The REMP implements Section ) IV.B.2, Appendix I,10 CFR 50, and thereby supplements the radiological effluent monitoring program by measuring concentrations of radioactive materials and l levels of radiation, which may then be compared with those expected on the basis l l of the ef fluent measurements and modeling of the environmental exposure pathways. The detection capabilities required by Table 4-3 are within state-of-the-art for routine environmental measurements in industrial laboratories. l l i l l O 4-3 Rev. 10, 7/95
f~ b)v 4 Approximate y Exposure Pathway Number of Sampling and Type of Analysis and Frequency
- and/or Sample Sample Collection Frequency w I.ocations' --
- 1. AIRBORNE w Continuous operation Radiolodine canister. 1-131 weekly, c.
Radioiodines and 6 of sampler with sample E . Particulates Particulats sampler. Analyze for collection weekly. { o gross beta radioactivity not less than 23 houra following filter change and E anaP;t: for I-131 weekly. Perform $ gamma is7 topic analysis on affected sample whwn gross beta activity is 10 7 times the yes:1y mean of control $ samples. Composite (by location) for n O gamma isotopic analysis quarterly. 1
- s
- 2. DIRECT RADIATION et Quarterly. Cama dose quarterly. E Direct Radiation 37
- 3. INGESTION g 4h Bi-weekly. Gamma isotopic and I-131 analyses bi- g Milk weekly. n Semi-annually. Canna isotopic analysis on edible E FishC or clams 2 portions semi-annually. ,
n Grass or Leafy 3 Monthly during growing Gamma isotopic analysis monthly.d M season. Vegetation "$
- 4. WATERBORNE 2 Composite" sample Gama isotopic analysis monthly.
surface collected monthly. Composite (by location) for tritium analysis quarterly. e Semiannually Gamma isotopic analysis yearly. l Sediment 2
? ~
8 o t. 6 X
- . . . ~ _ , ._
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h e b a Approximate
- Number of Sampling and f b Fgm g
Exposure Pathway Sample collection Frequency and/or Sample o Locations" S I-131 analysis on each sample when bi- S Drinking WaterI4 From each of River Water collected weekly collections are required. - the one to near the intake will cross beta and ganuna isotopic analyses three nearest be a composite sample; water supplies the finished water on each sample; composite (by will be a grab sample. Location) for tritium quarterly. , which could be e affected by HNP These samples will be S discharge one collected monthly o sample of river unless the calculated o water near the dose due to consumption of the intake and one y ' sample of water is greater than w finished water. 1 mrem / year; then the n collections will be v, bi-weekly. The r- , collection may revert 8 to monthly should the 3
- g calculated doses 6 become less than 1 $
mrem / year. b x o h 8
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O O O H CT TABIE NOTATIONS e
- a. Sample locations are shown in Table 4-4, and in Figure 4-1 through Figure 4-5.
- b. Up to three sampling locations within 5 miles and in different sectors will be used as O available. In addition, one or more control locations beyond 10 miles will be used. ?s Clams will be sampled if n
- c. Ccamercially or recreationally important fish may be sampled. 7 difficulties are encountered in obtaining sufficient fish samples.
- d. If gamma isotopic analysis is not sensitive enough to meet the required MINIMUM DETECTABLE CONCENTRATION (MDC), a separate analysis for I-131 may be performed. W D
at intervals not exceeding a n
- e. Composite samples shall be collected by collecting an aliquot o few hours. o C
f. If it is found that river water downstream of HNP is used for drinking, water samples will n be collected and analyzed as specified herein. E A survey shall be conducted annually at least 50 river miles downstream of HNP to identify n
- g. g those who use the Altamaha River water for drinking.
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Hatch ODCM 4.1.2 Land Use census A land use census shall be conducted and shall identify the locations of the l followings the nearest MILK ANIMAL' and the nearest permanent residence in each of the 16 meteorological sectors within a distance of 5 miles; and all MILK ANIMALS within a distance of 3 miles. 4.1.2.1 Applicability This control applies at all times. 4.1.2.2 Actions 4.1.2.2.1 With a land use' census identifying a location (s) which yields a calculated dose or dose conunitment greater than values currently being calculated in accordance with Section 3.4.3, identify the new location (s) in the next Radioactive Effluent Release Report. l 4.1.2.2.2 With a land use census identifying a location (s) which yielos a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 4.1.1, add the new location (s) to the REMP within 30 days if samples are available. The sampling location, excluding control station location (s), having the lowest calculated dose or dose comunitment (via the same exposure pathway) may be deleted from the REMP if new sampling locations are added. Pursuant to Technical Specification 5.5.1 submit in the next Radioactive l Effluent Release Report any change (s) in the ODCM, including the revised figure (s) and table (s) reflecting any new location (s) and information supporting the change (s). When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 4.1.2.3 Surveillance Requirements The land use census shall be conducted annually, using that information which will provide good results, such as a door-to-door census, a visual census from automobile or aircraft, consultation with local agriculture authorities, or some f ' Defined as a cow or goat that is producing milk for human consumption. 4-9 Rev. 10, 7/95
--. -- . . -. .. .. .- .. _ . _ _ - . . . = - - . . - - -.
l l Hatch ODCM combination of these methods, as fossible. Results of the land use census shall be included in the Annual Radiological Environmental Operating Report. l 4.1.2.4 Basis l This control is provided to ensure that changes in the use of UNRESTRICTED AREAS l are identified and that modifications to the REMP are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 l of Appendix I to 10 CFR Part 50. I a l 1 1 1 I N i
~
4-10 Rev. 10, 7/95
I i i Hatch ODCN f 4.1.3 Interlaboratory Comoarison Proaram I ! O of an V Analyses shall be performed on radioactive materials supplied as part Interlaboratory Comparison Program which satisfies the requirements of Regulatory Guide 4.15 Revision 1, February, 1979. 4.1.3.1 Applicability l This control applies at all times. 4.1.3.2 Actions With analyses not being performed as required by section 4.1.3, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Operating Report. When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry i.ta an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 4.1.3.3 Surveillance Requirements ( A summary of the results obtained as part of the required Interlaboratory l Comparison Program shall be included in the Annual Radiological Environmental l Operating Report. 4.1.3.4 Basis The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2, Appendix I, 10 CFR 50. lO I Rev. 11, 12/96 4-11
- . . . ~ .= ..- - . - ~ . - - - . . . . . . ~ . . . . . - . . . . = . . , - . . - . - ... - - ...-. .. . . . - . - .
Hatch ODCM 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS i Table 4-4, and Figure 4-1 through Figure 4-5 specify the locations at which the > l measurements and samples are taken for the REMP required by Section 4.1.1. . l > I
- l l
l l l l i
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i I I l i I 1 I 4-12 Rev. 8, 1/94
Hatch ODCM l Table 4-4. Radi>1ogical Environmental Monitoring Locations I ( Distance Sampi,e Location Descriptive Location Direction Number (miles) Type 064 Roadside park WNW O.8 D Inner ring N 1.9 D 101 Inner ring NNE 2.5 D 102 Inner ring NE 1.8 AD 103 Inner ring ENE 1.6 D 104 Inner ring E 3.7 D 105 Inner ring ESE 1.1 DV 106 Inner ring SE 1.2 AD 107 Inner ring SSE 1.6 D 108 109 Inner ring S 0.9 D l 1 110 Inner ring SSW 1.0 D 111 Inner ring SW O.9 D 1 Inner ring Wsw 1.0 ADV 112 Inner ring W 1.1 D 113 D V 114 Inner ring WNW 1.2 Inner ring NW 1.1 D 115 Inner ring NNW 1.6 AD 116 WNW ** R 170 Upriver
** R 172 Downriver E Outer ring N 5.0 D 201 outer ring NNE 4.9 D 202 Outer ring NE 5.0 D 203 Outer ring ENE 5.0 D 204 Outer ring E 7.2 D 205 Outer ring ESE 4.8 D 206 Outer ring SE 4.3 D 207 Outer ring SSE 4.8 D 208 Outer ring S 4.4 D 209 Outer ring ssW 4.3 D 210 l
l i i I LJ 4-13 Rev. 8, 1/94
Hatch ODCM Table 4-4 (contd). Radiological Environmental Monitoring Locations l is
" Uistan l Descriptive Location Direction g,g s) 211 outer ring SW 4.7 D i
212 outer ring WSW 4.4 D 213 Outer ring W 4.3 D 214 Outer ring WNW 5.4 D 215 outer ring NW 4.4 D , l 216 outer ring NNW 4.8 D 301 Toombs Central School N 8.0 D 304 State Prison ENE 11.2 AD l 304 State Prison ENE 10.3 M 309 Baxley substation S 10.0 AD j 416 Emergency News Center NNW 21.0 DV
- Sample Types:
A - Airborne Radioactivity l fg ! D - Direct radiation i (Ns) M - Milk R - River (fish or clams, shoreline sediment, and surface water) V - Vegetation
** Station 170 is located at approximately 0.6 river miles upstream of the intake structure for river water, 1.1 river miles f or sediment and clams, and 1.5 river miles for fish.
Station 172 is located at approximately 3.0 river miles downstream of the discharge structure for river water, sediment, and clams, and 1.7 river miles for fish. The location f rom which river water and sediment may be taken can be rather precisely defined, often, the sampling locations for clams have to be extended over a wide area to obtain a suf ficient quantity. High water adds to the dif ficulty in obtaining clam samples; high water might also make an otherwise suitable location for sediment sampling unavaila.ble. A stretch of the river on the order of a few miles or so is gwderally needed to obtain adequate fish samples. The mile locations given above represent approximations of the locations about which the catches are taken. i 4-14 Rev. 8, 1/94
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J Hatch ODcM CHAPTER S TOTAL DOSE DETERMINATIOE1 1 5.1 LIMIT OF OPERATION In accordance with Technical Specification 5.5.4 3., the dose or dose cossaitment l to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radio- " activity and to radiation from uranium fuel cycle sources, shall be limited to I less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrom. 5.1.1 Aeolicability This limit applies at all times. l l 5.1.2 Actions < e { With the calculated doses f rom the release of radioactive materials in liquid or i gaseous affluents exceeding twice the limits of Section 2.1.3, 3.1.3, or 3.1.4, ' calculations shall be made according to Section 5.2 methods to determine whether
- the limits of Section 5.1 have been exceeded. If these limits have been exceeded, prepare and submit a Special Report to the Nuclear Regulatory
] Commission within 30 days, which defines the corrective actions to be taken to l l reduce subsequent releases to prevent recurrence of exceeding the limits of section 5.1 and includes the schedule for achieving conformance with the limits of Section 5.1. This Special Report, as defined in 10 CFR 20.2203, shall also j include an analysis which estimates the radiation exposure (dose) to a MEMBER OF j THE PUBLIC from uranium fuel cycle sources (including all effluent pathways and i direct radiation) for the calendar year that includes the release (s) covered by this report. This Special Report shall also describe the levels of radiation and l concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the limits of Section 5.1, and if the release condition resulting in violation of the provisions of 40 i CFR 190 has not already been corrected, the Special Report shall include a request for variance in accordance with the provisions of 40 CFR 190 and Submittal of the report including the specified information of 40 CFR 190.11(b). i is considered a timely request, and a variance is granted until staff action on the request is complete. 4 When the ACTION statement or other requirements of this control cannot be met,
! steps need not be taken to change the Operational Mode of the unit. Entry into 1
i 5-1 Rev. 10, 7/95
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]
Hatch ODCM 5.2 DEMONSTRATION OF COMPLIANCE l
- There are no other uranium fuel cycle facilities within 5 miles of the plant. j site. Therefore, for the purpose of demonstrating compliance with the limits of j section 5.1, the total dose to a MEMBER OF THE PUBLIC in the vicinity of the plant site due to uranium fuel cycle sources shall be determined as follows:
Dyk = DL*Da+Dp+Dy (5.1} I ! ! . i where Dg = the total dose or dose cosusitment to the total body or organ k, in area. DL= the dose to the same organ due to radioactivity discharged from the plant site in liquid effluents, calculated in accordance with
~
Section 2.4.1, in arem. Do = the dose to the same organ due to non-noble-gas radionuclides discharged from the plant site in gaseous ef fluents, calculated for l- the controlling receptor in accordance with section 3.4.3, in arem. !
)
I DD= the direct radiation dose to the whole body of an individual at the ; controlling receptor location, due to radioactive materials l retained within the plant site, in mrom. Values of direct f radiation dose may~be determined by measurement, calculation, or , a combination of the two. DN= the external whole body dose to an individual at the controlling receptor location, due to ganuna ray emissions f rom noble gas radio- I nuclides discharged from the plant site in gaseous effluents, in arem. Dg is calculated as follows (equation adapted from Reference 1, page 22, by re-casting in cumulative dose form): Dy = 3.17 x 10~I (YTC), { (Kg + Cfy) + [ (Vf
- d i,) (5.2)
{v , i i where: l 5-3 Rev. 8, 1/94 I _ _. ._ _ .-. , n._
Hatch ODCM 3.17 x 10~8 = a units conversion f actor: 1 y/(3.15 x 10 7 m). l ! /' 6;y = the cumulative release of noble gas radionuclide i from non-elevated release pathway v (pci), during the period of interest. 6;, = the value of 6;y for the main stack; that is, the cumulative release of noble gas radionuclide i from the main stack ( C1), during the period of interest. Kg = the total-body dose f actor due to gamma emissions from noble gas radionuclide 1 (mrom/y)/(pci/m 3), from Table 3-5. Vj = the elevated finite-plume total-body dose factor at the controlling receptor location, due to gamma emissions from noble gas radionuclide i in effluents released from the main stack (mrom/y)/(pci/s), from Table 3-7. (X/6)yp = annual average relative dispersion f actor for release pathway v, at the location of the controlling receptor, O from Table 3-7 (s/m3 ). As defined above, DL and Dg are for dif ferent age groups, while DD and Dy are not age group specific. When a more precise determination of Dn is desired, values of Dt and Do may be calculated for all four age groups, and those values used in equation (5.1) to determine age group specific values of Dn; the largest value of Dn for any age group may then be compared to the limits of Section 5.1. i l i l 5-4 Rev. 8, 1/94
Hatch ODCM i , CMAPTER 6
/ POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO V THEIR ACTIVITIES INSIDE THE SITE BOUNDARY i
1 6.1 REQUIREMENT FOR CALCULATION To support the reporting requirements of Section 7.2.2.3, an assessment of the , radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE f l PUB! 'C due to their activities inside the SITE BOUNDARY (Figure 10-1) shall be l performed as specified in Section 6.2, at least once per calendar year. l l l 6.2 CALCULATIONAL METHOD For t!.a purpose of performing the calculations required in Section 6.1, the dose i to a member of the public inside the SITE BOUNDARY shall be determined at the ! locations, and for the receptor age groups, defined in Table 6-1. The dose to j such a receptor at any one of the defined locations shall be determined as ) i follows: l [ To (6.1) l \ Dlk * [Dg+DS+Dpj a where: Dg = the total dose to the total body or organ k, in mram. DA= the dose to the same organ due to inhalation of non-noble-gas radionuclides discharged f rom the plant site in gaseous ef fluents, calculated in accordance with Section 3.4.3, in mrom. The (I~/6) value to be used is given for each receptor location in Table 6-1; depleted (176) values may be used in calculations for non-noble-gas radionuclides. D3= the dose to the same organ due to around clane deoosition of non- . 1 nobin-gas radionuclides discharged f rom the plant site in gaseous effluents, calculated in accordance with section 3.4.3, in mrom. { The (676) value to be used is given for each receptor location in j Table 6-1. l O 6-1 Rev. 8, 1/94
. _ - _ . _. _ _ . . . __ _ . __ _ _ _ _ ._. ~ _
Hatch ODCM Dp = the external whole body dose due to ganna ray emissions from noble 3 gas radionuclides discharged from the plant site in gaseous i effluents, calculated using equation (5.2), in mrom. The values of (X7D) and Vg that are to be used are given for each receptor location in Table 6-1. 1 Fo= the occupancy f actor for the given location, which is the fraction of the year that one individual MEMBER OF THE PUBLIC is assumed to be present at the receptor location [unitiess). Values of F o for each receptor location are included in Table 6-1. ,
\.
i l 6-2 Rev. 8, 1/94
I Hatch ODCM ) Table 6-1. Attributes of Member of the Public Receptor Locations Inside the ; l SITE BOUNDARY l Location: Roadside Park, WWW st 1182 meters Age Grount Child Occucanev Factors 2.28x 10 (based on 2 hours per year) Dispersion and Deposition Parameters Parameter Ground-Level Elevated Undepleted (176), s/m3 7.83 E-6 2.42 E-8 Depleted (i76) , s/m3 7.00 E-6 2.37 E-8 l 1 (D76) , m*2 2.01 E-8 1.29 E-9 Elevated Plume Dose Factors + v; v3
-- Radionuclide Radionuclide (mrom/y)/(uci/s) (mrom/y)/(uci/s)
[N Kr-85m 8.39 E-05 Xe-133m 1.32 E-05 Kr-85 1.31 E-06 Xe-133 1.37 E-05 Kr-87 4.60 E-04 Xe-135m 2.51 E-04 Kr-88 1.14 E-03 Xe-135 1.37 E-04 Kr-89 9.89 E-04 Xe-137 9.91 E-05 Kr-90 7.32 E-04 Xe-138 6.45 E-04 Xe-131m 1.70 E-06 Ar-41 7.69 E-04
- Values from Reference 16.
+ See footnotes to Table 3-6.
i 6-3 Rev. 8, 1/94
I l I Hatch ODCM Table 6-1 (contd). Attributes of Member of the Public Receptor Locations Inside the SITE BOUNDARY r g Locations Camping Area, WNW at 1274 meters Ace Groupt Child j occucanev Factor 5.48 x 10'3 (based on 48 hours per year) Dispersion and Decosition Parameters: d Parameter Ground-Level Elevated Undepleted (i76), s/m3 7.03 E-6 2.38 E-8 Depleted (176), s/m 3 6.27 E-6 2.33 E-8 (D76), m-2 1.80 E-8 1.21 E-9 Elevated Plume Dose Factors:+ 2 V; Vj Radionuclide Radionuclide O
\
Kr-85m (mrom/y)/(uci/s) 7.84 E-05 Xe-133m (mrem /y)/(uci/s) 1.24 E-05 Kr-85 1.22 E-06 Xe-133 1.28 E-05 4.28 E-04 Xe-135m 2.34 E-04 Kr-87 Kr-89 1.06 E-03 Xe-135 1.27 E-04 9.19 E-04 Xe-137 9.23 E-05 Kr-89 a Kr-90 6.80 E-04 Xe-138 5.99 E-04 1.59 E-06 Ar-41 7.14 E-04 Xe-131m 1 4 4 4
'
- Values from Reference IS.
+ See footnotes to Table 3-6.
i 1 i i
'N ' 6-4 Rev. 8, 1/94 i
1 1 Hatet ODCM Table 6-1 (contd). Attributes of Member of the Public Receptor Locations Inside the SITE BOUNDARY O Locations Recreation Area, SSE at 1030 meters Ace Groues child I Occupancy Factors 2.37 x 10~2 (based on 208 hours per year) Disoersion and Deposition Par'ameterst .i Parameter Ground-Level Elevated Undepleted (176), s/m 3 6.42 E-6 3.30 E-8 Depleted (i?6), s/m3 5.73 E-6 3.21 E-8 (676), m"2 2.36 E-8 1.56 E-9 i Elevated Plume Dose Factorst+ V Vj
/" Radionuclide Radionuclide (mrem /y)/(uci/s)
( (mrem /y)/(uci/s) Xe-133m 1.14 E-05 Kr-85m 7.21 E-05 J Kr-85 1.13 E-06 Xe-133 1.17 E-05 l Kr-87 3.99 E-04 Xe-135m 2.17 E-04 Kr-88 9.90 E-04 Xe-135 1.18 E-04 Kr-89 8.57 E-04 Xe-137 8.57 E-05 Kr-90 6.34 E-04 Xe-138 5.58 E-04 I l Xe-131m 1.46 E-06 Ar-41 6.66 E-04
- Values from Reference 16.
+ See footnotes to Table 3-6.
i 6-5 Rev. 8, 1/94 l l
- . . _ . - - .. - _ _ . ~ _ - . ~ . - - . - . . . . - . . . - . _ - . . _ . - . . . -. - _
Hatch ODCM Table 6-1 (contd). Attributes of Member of the Public Receptor Locations Inside the SITE SOUNDARY i Location: Visitors conter, Wsw at 694 meters ] Ace Groups Child Occupancy Factors 4.57 x 10 4 (based on 4 hours per year) Discersion and Deoosition Par'ametgI.3: 1 4 0 Parameter Ground-Level Elevated Undepleted (i"/6), s/m3 1.87 E-5 5.00 E-8 j 1.72 E-5 4.97 E-8 Depleted (i~/6), s/m3 l ' (6'/6) , m-2 5.47 E-8 2.26 E-9 I Elevated Plume Dose Factors:+ l v; v; Radionuclide Radionuclide (mrem /y)/(uci/s) (mrom/y)/(uci/s) k 1.47 E-04 Xe-133m 2.34 E-05 Kr-85m Kr-85 2.34 E-06 Xe-133 2.36 E-05 8.27 E-04 Xe-135m 4.49 E-04 Kr-87 2.06 E-03 Xe-135 2.42 E-04 Kr-88 1.78 E-03 Xe-137 1.77 E-04 Kr-89 1.31 E-03 Xe-138 1.16 E-03 Kr-90 2.98 E-06 Ar-41 1.38 E-03 Xe-131m
- Values from Reference 16.
+ See footnotes to Table 3-6.
5 Rev. 8, 1/94 6-6
. . _ - - . - - _ _ _ --- . . _ - - - - . - - _ _ . - - .... . . - .- . ~ . _ __ .. - - . .
Hatch ODCM i 4' CHAPTER 7 REPORTS 4 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l 4 7.1.1 Reauirement for Reoort i In accordance with Technical specification 5.6.2, the Annual Radiological Environmental Operating Report covering the REMP activities during the previous l (A single report } calendar year shall be submitted by May 15 of each year. fulfills the requirements for both units. ) The material provided shall be ! consistent with the objectives outlined in Section 4.1 and Section 7.1.2 of the ODCM, and in Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. ! 7.1.2 Reoort Contents The materials specified in the following sub-sections shall be included in each 1 j Annual Radiological Environmental Operating Reports l i ! 7.1.2.1 Data The report shall include sunraarized and tabulated results of all REMP samples f required by Table 4-1 taken during the report period, in a format similar to that contained in Table 3 of the Radiological Assessment Branch Technical Position i 1 (Reference 18); the results for any additional samples shall also be reported. In the event that some results are not available for inclusion with the report, ,' the report shall be submitted noting and exp5.aining the reasons for the missing j results; the missing data shall be submitted as soon as possible in a supplementary report. The results for naturally-occurring radionuclides not il included in plant effluents need not be reported. l 7.1.2.2 Evaluations Interpretations and analyses of trends of the results shall be included in the l (as appropriate) comparisons with pre-report, including the followings operational controls, and previous environmental l operational studies, l surveillance reports; and an assessment of any observed impacts of the plant operation on the environment. If the measured level of radioactivity in an j environmental sampling medium exceeding the reporting levels of Table 4-2 is not
' the result of plant affluents, the condition shall be described as required by Section 4.1.1.2.2.
~ 7-1 Rev. 10, 7/95 i
___._..m._ . . . .. . . . . _ _ _ - m_ _ . . _ . _ . . . _ . .- l Match ODCM 1 7.1.2.3 Programmatic Information j
\s_/ Also to be included in each report are the following: a summary description of I
the REMP: a map (s) of all sampling locations keyed to a table giving distances and directions from the main stack; the results of land use censuses required by l l Section 4.1.2: and the results of licensee participation in the Interlaboratory 3 Comparison Program required by Section 4.1.3. l ; I 7.1.2.4 Descriptions of Program Deviations . ~ Discussions of deviations from the established program must be included in each
)
j report, as follows: i If the REMP is not conducted as required in Table 4-1, a 7.1.2.4.1 description of the reasons for not conducting the program as required, and the plans for preventing a recurrence, must be included in the report. J, If the MDCs required by Table 4-3 are not achieved, the l 7.1.2.4.2 4 l 4 contributing factors must be identified and described in the report. t 7.1.2.4.3 If Interlaboratory Comparison Program analyses are not performed as required by Section 4.1.3, the corrective actions taken to prevent a recurrence must be included in the report.
- J- 1 J
4 I . <- 1 l l l l O Rev. 11, 12/96 72
,l Hatch ODCM ,
1
- 7.2 RADIOACTIVE EFFLUENT RELEASE REPORT l i
1 e 7.2.1 Reauirement for Renort .I In accordance with Technical specification 5.6.3, the Radioactive Effluent l , l Release Report covering the operation of the units during the previous calendar j
- l. year of operation shall be submitted in accordance with 10 CFR 50.36.a.l '
l (A single submittal may be made for Units 1 and 2. However, the submittal shall specify the releases of radioactive material in liquid and gaseous effluents from l each unit and solid radioactive waste from the site.) The report shall include : l j a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with , the objectives outlined throughout this ODCM and the Process Control Program l ! 3 (PCP) and in conformance with 10 CFR Part 50.36a and section IV.B.1 of Appendix a i I to 10 CFR Part 50. i j 7.2.2 Renort Contents , t 1 F The materials specified in the following sub-sections shall be included in each l Radioactive Effluent Release Reports I 4' 7.2.2.1 Quan*.ities of Radioactive Materials Released ! The report shall include a summary of the quantities of radioactive liquid and 4 gaseous ef fluents and solid waste released from the units as outlined in NRC [. l Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in s j solid Wastes and Releases of Radioactive . Materials in Liquid and Gaseous Ef fluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with liquid and gaseous ef fluent data susunarized on a quarterly basis and solid f radioactive waste data sununarized on a semiannual basis following the format of i t Appendix B thereof. The report shall include documentation of quantities of j radioactive materials in unplanned releases of gaseous and liquid effluents from j j the site to UNRESTRICTED AREAS, tabulated either by quarter or by event, provided 1 such liquid releases exceeded 1 C1, excluding tritium and dissolved or f thats l entrained noble gases; or such gaseous releases exceeded 150 Ci of noble gases i f or 0.02 Ci of radiciodines. For ganuma emitters released in liquid and gaseous f j effluents, in addition to the principal gamma emitters for which MDCs are other peaks which are
- specifically established in Table 2-3 and Table 3-3, 4
i measurable and identifiable also shall be identified and reported. l , i i ! 4 .i j Rev. 10, 7/95 7-3 4 J
_ . - _ _ _ _ _ _ . _ _ . . . . _ _ . _ _ . __ _ _.. . - _ _ _ _ = _ _ _ _ _ _ _ . Hatch ODCM 7.2.2.2 Meteorological Data 4 j The report shall include an annual summary of hourly meteorological data 1 collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction', and atmospheric 3 stability, and precipitation (if measured) on magnetic taper or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radioactive Ef fluent Release Report, l ' the licensee has Cae option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request. 7.2.2.3 Dose Assessments i ' l 4 l The report shall include an assessment of the radiation doses due to the l radioactive liquid and gaseous effluents released from each unit during the ) ] Historical annual average meteorology or the
- previous calendar year.
meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway dose. This f assessment of radiation doses shall be performed in accordance with Sections j 2.1.3, 2.4, 3.1.3, 3.1.4, 3.4.2, 3.4.3, 5.1, and 5.2. If a determinstion is required by Section 5.1.2, the report shall also include an assesament of radiation doses to the likely most exposed MEMBER OF THE PUBLIC } from roactor releases and other nearby uranium fuel cycle sources (including j j doses from primary ef fluent pathways and direct radiation) for the previous j calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation; thic dose assessment must be , 1 j performed in accordance with Chapter 5. The report shall also include an j i assessment of the radiation doses from radioactive liquid and gaseous effluents j l to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 10-1) during the report period; this assessment must be performed in accordance with Chapter 6. 7.2.2.4 Solid Radwaste Data i For each type of solid waste shipped offsite during the report period, the following information shall be included: 1
- a. Container volume,
- b. Total curie quantity (specify whether determined by measurement of
~ ''
O 7-4 Rev. 10, 7/95 L______ _ ____ _ - _- _ - _ _ _ ___ _ .-.
Hatch ODCM 2
- c. Principal radionuclides (specify whether determined by measurement or estimate),
[ (e.g., spent resin, compacted dry waste, evaporator
- d. Type of waste l
bottoms),
), and
- e. Type of container (e.g., LSA, Type A, Type B, Large Quanti
- Solidification agent (e.g., cement, urea formaldehyde.)
f. 7.2.2.5 Licensee Initiated Document Changes Licensee initiated changes shall be submitted to the Nuclear Regulatory l i commission as a part of or concurrent with the Radioactive Effluent Release l Report for the period in which any changes were made. Such changes to the ODCM shall be submitted pursuant to Technical Specification 5.5.1. Thisrequirementl l l includes: f l 7.2.2.5.1 Any changes to the sampling locations in the radiological environmental monitoring program, including any changes made pursuant to section 4.1.1.2.3. Documentation of changes made pursuant to Section 4.1.1.2.3 shall l include supporting information identifying the cause of the unavailability of samples. 7.2.2.5.2 Any changes to dose calculation locations or pathways, including any changes made pursuant to Section 4.1.2.2.2. Q t' Descriptions of Program Deviations 4 7.2.2.6 Discussions of deviations from the established program shall be included in each 4
- report, as follows:
7.2.2.6.1 The report shall include deviations from MINIMUM DETECTABLE ' CONCENTRATION (MDC) requirements included in Table 3-3. 7.2.2.6.2 The report shall include deviations from the liquid and gaseous of fluent monitoring instrumentation OPERABILITY requirements included in Sections 2.1.1 and 3.1.1, respectively. The report shall include an explanation as to why i the inoperability of the liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement. (This requirement does , I l not include the Service Water System to Closed cooling Water System Dif ferential s Pressure channel.) 7.2.2.6.3 The report shall include notification if the contents within any outside temporary tank exceed the limits of Technical Specification 5.5.8.b. l l n 7-5 Rev. 10, 7/95 4
Hatch ODcM ii 7.2.2.7 Major Changes to Radioactive Waste Treatment Systems i- As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the f i Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering l the period in which the change was reviewed and accepted for implementation.'
- The discussion of each change shall contains 2
- a. A sumunary of the evaluation that led to the determination that the t change could be made in accordance with 10 CFR Part 50.59; i
f b. Sufficient detailed information to totally support the reason for the ' change without benefit of additional or supplemental information; ' c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; i
- d. An evaluation of the change, which shows the predicted releases of
,i radioactive materials in liquid and gaseous effluents that differ from 1 - those previously predicted in the license application and amendments 1 4 thereto; i 4 4 $ e. An evaluation of the change, which shows the expected maximum exposures I to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general 1 population that differ from those previously estimated in the license ! application and amendments thereto; ] I
- f. A comparison of the predicted releases of radioactive materit.ls, in liquid and gaseous affluents, to the actual releases for the period j prior to when the changes are to be made; I
i g. An estimate of the exposure to plant operating personnel as a result l l of the change; and l! ) Documentation of the fact that the change was reviewed and found h. { ! acceptable by the Plant Review Board. l 1 ) i 4 l
' In lieu of inclusion in the Radioactive Ef fluent Release Report, this same l j information may be submitted as part of the annual FSAR update.
I i 4 7-6 Rev. 10, 7/95
. _ . _ __ ._. . _ _ .- ._ . _ . . _ . . ___m. _ _ _ . _ . _ . _ _ _ . . _ . . . . .
l i Hatch ODCM 7.3 MONTMLY OPERATING REPORT ) l i 4 ! This ODCM establishes no requirements pertaining to the Monthly Operating Report. i 7.4 SPECIAL REPORTS f special Reports shall be submitted to the Nuclear Regulatory Ccounission, as required by sections 2.1. 3. 2, 2.1. 4. 2, 3.1. 3. 2, 3.1. 4.2, 3.1. 5. 2, 4.1.1.2. 2, and 5.1.2. l i i i 1 1 1 l 1 1
- , J 4
1 i i i i i 1 t i 1 i i i i 4
\
7-7 Rev. 10, 7/95 8
l Hatch O M 4 CHAPTER 8 METEOROLOGICAL MODELS The models presented in this chapter are those which were used to compute the specific values of meteorology-related parameters that are referenced throughout this ODCM. These models should also be used whenever it is necessary to l calculate values of these parameters for new locations of interest. Note la When calculating values of annual average parameters for new locations, ) use the joint frequency meteorological data precented in Reference 28. Those are the data which were used to compute the specific values of f 4 meteorology-related parameters that are referenced throughout this ODCM. Note 2 Although Plant Hatch has no mixed-mode releases, the sections on mixed-l mode calculations (8.1.3 and 8.2.3) are included to preserve section number compatibility with the ODCMs of the other Southern Company nuclear power plants. i i 8.1 ATMOSPHERIC DISPERSION l Atmospheric dispersion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous release elevations may be considered to be either at ground-level, elevated, or mixed-mode. Facility release elevations for each gaseous release point are as indicated in Table 3-4. i j 8.1.1 Ground-Level Releases Relative concentration calculatione for ground-level releases, or for thu ground-level portion of mixed-mode releases, shall be made as follows: 2.032 5 K # njk (x/0)c = E (8.1) N r jk Uj E9 - where: (X/Q)g = the ground-level sector-averaged relative concentratzen for a given wind direction (sector) and distance (s/m3 ). I 2.032 = (2/st)I/2 divided by the width in radians of a 22.5* sector, which is 0.3927 radians. 8-1 Rev. 8, 1/94
Hatch ODCM 6= the plume depletion factor for all radionuclides other than noble gases at a distance r shown in Figure 8-3. For noble gases, the depletion f actor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by radioactive decay would be of little significance at the distances considered. Kr = the terrain recirculation f actor corresponding to a distance r, taken from Figure 8-2. njk = the number of hours that wind of wind speed class j is directed into the given sector during the time atmospheric stability category k existed. i N= the total hours of valid meteorological data recorded throughout the period of interest for all sectors, wind speed classes, and stability categories. uj = the wind speed (mid-point of wind speed class j) at ground level (m/s). r= the distance from release point to location of interest (m). O the vertical standard deviation of the plume concentration Ed= distribution considering the initial dispersion within the building wake, calculated as follows: 2 b2 'l/2 s b*E W Eg = the lesser of s og
, (#d) og = the vertical standard deviation of the plume concentration distribution (m) for a given distance and stability category k as shown in Figure 8-1. The stability category is determined by the vertical temperature gradient AT/A: ('C/100 m).
n= 3.1416 g b= the maximum height of adjacent plant structure (47 m). f 8-2 Rev. 8, 1/94
Hatch ODCM 8.1.2 Elevated Releases O d Relative dispersion calculations for elevated releases, or for the elevated portion of mixed-mode releases, shall be made as follows: I l , , l A
-h l 2.032 K r 6A njk exP 2 (a.3)
(X/0)E "
# # b s 2 og, jk Uj *$
t where: l j (X/Q)E = the elevated release sector-averaged relative concentration for 3 l l a given wind direction (sector) and distance (s/m ). ) j l 5k= the plume depletion f actor for all radionuclides other than noble 0 gases at a distance r for elevated releases, as shown in l Figure 8-4, Figure 8-5, and Figure 8-6. For an elevated release, ; this f actor is stability dependent. For noble gases, the depletion s factor is unity. If an undepleted relative concentration is
, Only depletion by
- desired, the depletion factor is unity.
deposition is considered since depletion by radioactive decay would l be of little significance at the distances considered. l 1 the number of hours that wind of wind speed class j is directed njk = I into the given sector during the time atmospheric stability category k existed. the wind speed (mid-point of wind speed class j) at the effective
- uj =
release height h (m/s). i h= the ef f ective height of the release (m), which is calculated as follows:I i j h=h y -h, (8) J I Effective release height may be further adjusted for plume rise in l accordance with Section E.4.3.2 of Appendix E to Reference 7.
, y 8-3 Rev. 8, 1/94
_ - . - . _ = . - . ~ - . . . _ _ _ - . . . _ - - -. - . - . --. - ... . , f Hatch ODCM hy = the height of the release point (m), which is the height of the !' b main stack, 120 m. d - hg= the maximum terrain height between the release point and the point I of interest (m), from Figure 2.3-12 of Reference 8. 1 i All other symbols are as previously defined in Section 8.1.1. 8.1.3 Mixed-Mode Releases ' Relative dispersion calculations for mixed-mode releases shall be made as follows: 4 i
- (X/0)y * (1 -E) * (X/0)E
- E ' (X/0)G (s.5)
I where: I (X/Q)M = the mixed-mode release sector-averaged relative concentration for 3 i a given wind direction (sector) and distance (s/m 3, 7 l E= the fraction of hours during which releases are considered as i ground-level release.s, calculated as follows: w 1.0 for d s 1.0 Uj l V# W 3 2.58 - 1.58 - _ f or 1. 0 < # 51.5
. Uj. Uj i'
E = (s.s) W# W i O.3 - 0.06
- for 1. 5 < _# 55.0 r Uj. Uj w
0 f or _# > 5. 0 Uj All other symbols are as previously defined. O Rev. 8, 1/94 8-4
Hatch ODCM 8.2 RELATIVE DEPOSITION ' s Plume depletion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous release elevations may be considered to be either at ground-level, elevated, or mixed-mode. Facility release elevations for each gaseous release points are as indicated in Table 3-4. 8.2.1 Ground-Level Releases Relative deposition calculations for ground-level releases, or for the ground-level portion of mixed-mode releases, shall be made as follows: , l 2.55 D g Kr (D/0)G " Ey nk (8.7) l N r where: (D/Q)G = the ground-level sector-averaged relative deposition for a given wind direction (secto..) and distance. (m-2 ) . 2.55 = the inverse of the number of radians in a 22.5* sector (= (2 n/16)-I) . Dg = the deposition rate at distance r, taken from Figure 8-7 for ground-level releases (m-I) . nk = the number of hours in which the wind is directed into the sector of interest, and during wnich stability category k exists. All other symbols are as defined previously in Section 8.1. 8.2.2 Elevated Releases Relative deposition calculations for elevated releases, or for the elevated portion of mixed-mode releases, shall be made as follows: 2.55 K (D/0)E
- b (Ak Dek) (8.8)
N r g where 8-5 Rev. 8, 1/94 4
Hatch ODCM (D/Q)E = the elevated-plume sector-averaged relative deposition for a given wind direction (sector) and cistance (m-2). Dd= the elevated plume deposition rate at distance r, taken from Figure 8-8, Figure 8-9, or Figure 8-10, as appropriate to the plume ' effective release height h defined in Section 8.1.2, for stability class k (m-I) . ; l All other symbols are as defined previously. 8.2.3 Mixed-Mode Releases f Relative deposition calculations for mixed-mode releases shall be made as ! follows: (D/0) Af
=
(1 -E) * (D/0)E
- E * (D/0)G (8 9) where:
(D/Q)M = the mixed-mode release sector-averaged relative deposition for a given wind direction (sector) and distance (m-23 , E= the f raction of hours during which releases are considered as ground-level releases, defined in section 8.1.3. All other symbols are as previously defined.
)
8-6 Rev. 8, 1/94
.- , . . . , . - , - - ~ - - - - . ~ . . - - ~ .-. - - .~ .- . . . . . - .
1 Hatch ODCM i I 8.3 ELEVATED PLUME DOSE FACTORS Certain gaseous af fluent dose calculations require the use of the elevated-plume j noble gas dose parameters Bj orj V , which are first defined in Section 3.4. These parameters are calculated as follows: a njg A,g
- p a, E,
- Ig, ( r) (4.10)
Bf = y [ "j rN J,k,e 1 l 1 2 ~ 5 l njk
- A,g p a, E, Ika (r) -{p T, d) 1,1 g [ "j e rN j,k,e i
i 4 wheres d, N K= a numerical constant representing the aggregated numerical 4 constants and unit conversions, 2.1 x 10 . 1 l
\ A,; = the number of photons in energy group e emitted per transformation of radionuclide 1 (number / decay).
): 1 j p a, = the air energy absorption coefficient for photons in energy group , I t e (m-I). E, = the photon energy assigned to energy group e (MeV). a
- Ike(r) = the (dimensionless) result of integrating the emission and attenuation of photons of energy group c, over the entire spatial activity distribution of a plume that has spread under atmospheric
- stability classification k, for a dose receptor at downwind 4
distance r (see below for calculational method). ( 1.1 = the average ratio of the photon energy absorption coefficient for tissue to that of air over the energy range of interest. This j ratio converts air dose (rad) to dose equivalent (rem). i 8-7 Rev. 8, 1/94 i
- ~ - - - . . _ . . - . _ - . - . . - - - - . . -. ._- -
Hatch ODCM ? pT g = the tissue energy absorption coefficient for photons in energy O group a (cm 2/g). d= the tissue density thickness taken to represent the depth at which total body dose is received (5.0 g/cm2 ). All other symbols are as previously defined. For a sector-averaged plume model like that described in Section b.1, the dose integral Ike ( r ) is calculated as follows: oo ao k, r) u A(p ,g R) x L dL dz Igg (r) = 2 1 9 0 0 llB g(p ,pa ,R) x G(s g g o gg,ggy where: L= the upwind or downwind distance from the differential volume element of the plume to the dose receptor point. z= the vertical distance from the differential volume element of the plume to the dose receptor point. v the total distance from the differential volume element of the R= plume to the dose receptor points R - h2.,2 B g= the air dose buildup factor through a thickness R of airs xR B = 1+ E pae y, = the total photon attenuation coefficient in air, for energy group I a (m-I). G= the function describing the vertical distribution of activity in i a plume that has travelled downwind a distance r f rom the point of emission, at an ef fective height h, under stability classification f ks 8-8 Rev. 8, 1/94 l j
,. - ... -_ - .__-..~ - .. , . ~ . - - . . . . . . -- . . . - - . - . _ - - . . _ i Hatch ODCM G = exp - (s-h)2 + exp - (s +h)2 ' 2 2 2 og 2 og j A= the attenuation and geometric loss factor for photons in energy group e, for the distance R from the differential plume volume element to the dose receptor points ;
)
exp[p,RJ j R1 2w L dL dz = the volume of the differential plume element. (When the 2n is f actored out into the constants in equations (8.10), (8.11), and (8.12), only L dL dz is left.) All other symbols are as previously defined. A derivation of the model describing the gamma dose rate f rom an elevated finite plume is found in Chapter 7 of Reference 19. Numerical methods for evaluating the dose integral are found in Appendix F of Reference 3. Details of the numerical methods used there may be found in Reference 20. l l O Rev. 8, 1/94 8-9
j ,j Hatch ODCM ) Table 8-1. Terrain Elevation Above Plant Site Grade 4 .I
,1 a
1 i l 1
+
5 4 i l 1 l t l 4 i i 4 i, ' l 1 i ! l 4 i I l , 1 1 4
- This table intentionally left blank. l 6
i 6 i J c 4 l 1 l. i I a 3 i 1 } f a i i a d 4 1 i4 8-10 Rev. 8, 1/94 1 4 i
Hatch ODcM I i ! / 1 J , a a /i x' i; iI I b
/ / e / e9 6 / ! /e i / * !t
/ 6/ I I I f i 6 i.-
/ / I i i / I I ./'l
/ /, I / if
/ /
l , ,,, - - 100 4
/ .
/ .,
' /
,' , , f ,
e f V ,F ) / */ h
/ .f o. / / af I / '
-' +
_. i / / 7 / / I. . . I i _ -
$ / / s
' of/l /'I M j /// . /1/l4,d
T
\ l
/ /
,~
// / / a/,/ // p'/ l
\
,e ' '
,' , ,' ., w
,'/r / l , , , , s .
/ / / s- . . s a
/ / / I i I
/1 / l I
- I l
/
' o,i 1.0 to 100 PLUME TRAVEL OtSTANCE (KILOMETERS)
Range of Vertical Range of Vertical category Temperature Gradient Temperature Gradient (*c/100 mi (*F/100 ft) A AT/AZ < -1.9 AT/AZ < -1.0 8 -1.9 s AT/AZ < -1.7 -1.0 s AT/AZ < -0.9 c -1.7 s AT/AZ < -1.5 -0.9 s AT/AZ < -0.8 l D -1.5 s AT/AZ < -0.5 -0.8 s AT/AZ < -0.3 j l E -0.5 s AT/AZ < 1.5 -0. 3 s AT/AZ < 0.8 F 1.5 s AT/AZ < 4.0 0.8 s AT/AZ < 2.2 G 4.0 s AT/AZ 2.2 s AT/AZ i s This graph is reproduced f rom Reference 5 (Figure 1) . I Figure 8-1. Vertical Standard Deviation of Material an a Plume (og) 8-11 Rev. 8, 1/94
_. _. . . . . . _ . . . . _ . . _ . - _ ~ _ . _ . _ . - _ _ _ _ _ _ _ _ _ - . - - _ . . - . _ _ _ - . - . . - _ i j Hatch ODCM f 4 A i i a I 3 } l i e 10
. . , ,i.
. .. i.isi i.ii..is i iiie i~
i ii t i t il n i4 ieillt i i I 4 1 l I l l l I ll \l l 1 l l llll l l l l 5 I II IIIII \I I IIIII I I . g N \ a a % ] gg I G i I . . . . . . . . . . . ieii i . . . . I g . . . . . . . . . ..i,. . .i W . t i i i i i ll I 1 1 4 4 64It il i ti i ! ! I I l l l 111 l I I i 1llll i l li\ i l l I lllllli ' l I I llllll l l lll i l l -- 0.1 < , 0.1 1.0 18 15
- DISTAleCE IKtLORAETEftSi I
i i i i f i a i 4 This graph is reproduced from Reference 4. Figure 4-2. Terrain Recirculation Factor (Kr) a l B-12 Rev. 8, 1/94 4
. _ . _ . ._ . ... _ . _ , _ _ _ _ _ _ _ _ . _ . ~ . . _ . . - m .._ . . _ _ _ . _ _ _ . . . ___.___ - _ _ _ _ _ . _
Maten ODCM f 4 l l f
! lf is '
O.9 i e
! i llll M JI !I j Ii . !a 0.7 I I l iil ' l N \ i 0.8 -
I l f' ' ' E O.5 ' ( i % b_ i N 0.4 ! l l \ m i i e l I III I I i N . 0.2 i 0.1 I i
' l iIjl lll l l* l 1 I -
0.1 1.2 10J 100.8 2004 j l PluteE TRAVEL CISTANCE IKELot4ETERS) i I
, i f i < l l
} i ; i i i l 1
-s This graph is reproduced from Reference 5 (Figure 2).
^
Figure d-3. Pluse Depletion Effect for Ground Level Releases 8-13 Rev. 8, 1/94
Hatch ODCM I l t I i l l 1.0 NE RA ( E.F,0) O.B kh 1 ,,, . 0 Il ^ % \ i, l aAu, J S$%-
- i: , ,
t rg
- g., , '
3 c.4 i oJ
- ' II \\
I I c.2 I g,3 I i t I 0.1 1A ISA 100A' 2084 PLUME TRAVEL DISTANCE (KILOMETERS)
, This graph is reproduced from Reference 5 (Figure 3).
Figure 8-4. Plume Depletion Effect for 30-Meter Releases 8-14 Rev. 8, 1/94
Hatch ODCM t'% J E 't 1.0 . STABLE', o.s w o.
! ,1 1 ! Ill l I i30s jl l l PJr&"g I
N s s o.5 \ . s I ill i s' U- 9" o.3 c., I! II II l \ o.1 i I lil ' I l lll i 6 i I 01 1A to,e look assa l PLUME TRAVEL DISTANCE (KILOMETERS) 4 i l l l i This graph is reproduced from Reference 5 (Figure 4). Figure 8-5. Plume Depletion Effect for 60-Meter Releases I + 8-15 Rev. 8, 1/94
Hatch ODCM [ N. .i 's .) l 1 I l 1.0
~ -
s ~~s% gNEWR AL (D) c3 % i '% g K w c.: 5 ! i UNSTABLE
*3
\
N- l
! o.7
~
STASLE (E.F,01 \
" \
c.s f'0" A j (FRACTION REMAININ0 = 1 Al
\
\
\ l i os P- 6 l b
s ~ os \ ( l \\
' c3 0.2 o.1 i
l l l o.1 1.o toA looA 2cos PLUME TRAVEL Ot3TANCE (KILOe4ETERS) This graph is reproduced from Reference 5 (Figure 5). Figure 8-6. Plume Depletion Effect for 100-Meter Releases 8-16 Rev. 8, 1/94
Hatch ODCM J 1d I I a t J J i 10-4 - ! s 2 w
$ t
- y ' N J e %<
E T
; \
- N 4
e s%
$ 104
\ s 4 G \
2 x g t i
. (w w 2
g 3 E \( d c 104 s x 1 l l 10-7 0.1 1.0 10A 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) i This graph is reproduced from Reference 5 (Figure 6). Figure 8-7. Relative Deposition for Ground-Level Releases 8-17 Rev. 8, 1/94 4
)
l Hatch ODCM l l b I 104 4 1 I UNSTABLE (A,B.C) 104 sN ' ' ' ' i h / s
> / 't h.
m 's l g / 'h , y [ \\ NEUTRAL i w
> \\N (
c 2 I NEUTRAL (D)
^
(gg h 104 l' k STABLE i;; i u s -m O I v i i A / /s X h J J V ' u lm f w / / A'N \ l ! h / [ \ k 2
/ / N % '
h STABLE (E,F,G) 104
- I l I 1 i I
i
/
10-7 0.1 1.0 10A 100A 200A i PLUME TRAVEL DISTANCE (KILOMETERS) i This graph is reproduced from Reference 5 (Figure 7).
; Figure 8-8. Relative Deposition f or 30-Meter Releases 8-18 Rev. 8, 1/94
Hatch ODCM i [~T, kj ] 104 l t
/ ==
% UNSTABLE (A,B,C)
( \ \
/ N f%
10-6 / NEUTRAL (D) hv l l , . .
;w
' A
' &w / I I A i ! i i t Y
>= / / I I NA
\ N A
$ / I i UNSTABLE I
e / ' l l \ X I
! l N'EUTRAL \ \
3 / N N 5 is
/
%- ~
U [ ' l / C) ! / /
> f }
j { d a 10-7 / STABLE (E.F.G) I n I I s s 1 I i 4 . e 6 f I I I i i i i I , I ll l l / I 1H i 0.1 1.0 104 100.0 200A PLUME TRAVEL DISTANCE IKILOMETERS) 1 r This graph is reproduced f rom Reference 5 (Figure 8) . ( rigure 4-9. Relative Deposition for 60-Meter Releases 8-19 Rev. 8, 1/94
Hatch ODCM 104 h UNSTABLE (A.8,C)
/
\ \
10-6 , j ,-4 l 1 '; , l % ; , a i 1 w . g f f NEUTRAL (D) ii xg-y / / I \ *w ' J e > I / N - s.
/ / N N3 s
j 10-6 , . E 2 I l f
} i i E / J
=
2 I / l 4 E }, d STABLE (E.F,G) l NO DEPLETION 10-7 I ' I j
, .l , , , ,
1 i , i < l t !
/ I I f i I
/ I ,
i 10-8 0.i 1.o 1om 100.o 2004 PLUME TRAVTL DISTANCE (KILOMETERS) f s This graph is reproduced from Reference 5 (Figure 9). k Figure 8-10. Relative Deposition for 100-Meter (or Greater) Releases 8-20 Rev. 8, 1/94
-. . - .. - ._ - - . - -- . - . - - ~ _ ._ -. . ~ _ . .
I ' Hatch ODCM i CHAPTER 9 !, METHODS AND PARAMETERS FOR CALCULATION OF N GASEOUS EFFLUFNT PATHWAY DOSE FACTORS. R,jp j
~
i
' 4.1 INHALATION PATHWAY FACTOR 3
j ror the inhalation pathway, R,jp j in (mrom/y) per (pci/m ) is calculated as , ! follows (Reference 1, Section 5.3.1.1): R aipj " K1 * (BR),* (DTA)ay (9.1) I { where Kg = the units conversion factor 100 pCi/pci. , (BR), = the breathing rate of receptor age group a, in m3 /y, from I Table 9-5. j the inhalation dose factor for receptor age group a, .
} (DFA),;j = ' radionuclide i, and organ j, in mrem /pci, from Table 9-7
) through Table 9-10. l
\
9-1 Rev. 8, 1/94
l l Hatch ODCM l l 9.2 GROUND PLANE PATHWAY FACTOR 2 For the ground plane external exposure pathway, R,;pj in (m *mrom/y) per (pci/s) is calculated as follows (Reference 1, Section 5.3.1.2): j s T
-k;
' ~* (9*2) R ap j; = Kg K2 * (SHF) * (DTG);;
- s s s where:
i the units conversion factor: 106 pCi/pci. j Kg = K2u the units conversion factor: 8760 h/y. 3 (SHF) = the shielding factor due to structure (dimensionless). The value used for (SHF) is 0.7, f rom (Ref erence 3, Table E-15). (DFG);j = the ground plane dose f actor for radionuclide i and organ j 2 from Table 9-15. Dose j, in (mrom/h) per (pci/m ),
' factors are the same for all age groups, and those for the total body also apply to all organs other than skin.
1; = the radioactive decay constant for radionuclide i, in f s-I. Values of Ag used in ef fluent calculations should be based on decay data f rom a recognized and current source, such as Reference 26. I t= the exposure time, in s. The value used for t is 4.73 x 10 8 m (= 15 y), from (Reference 1, Section 5.3.1.2). l l O U 9-2 Rev. 8, 1/94
Hatch ODcM 9.3 GARDEN VEGETATION PATHWAY FACTOR 1 \ For radionuclides other than tritium in the garden vegetation consumption pathway, R,jp j in (m 2* mrem /y) per (pci/s) is calculated as follows (Reference 1, Section 5.3. l.5 ): 4 1 Rapj ) = Kg
- Y ( Aj + A ) * (DTL)a;;
. y w 1 (9.3) i L y,g Ug fLe , g g ,% % h i wh.rei a Kg = the units conversion factor: 106 pCi/pci. j i r= the fraction of deposited activity retained on the edible parts of garden vegetation (dimensionless). The value I used for r is 1.0 for radiciodines and 0.2 for
- - particulates, f rom (Ref erence 3, Table E-1) .
2 Yy = the areal density (agricultural productivity) of < growing i leafy garden vegetation, in kg/m2 , from Table 9-1. , 1; = the radioactive decay constant for radionuclide 1, in s ~I. Values of 1; used in ef fluent calculations should be $ based on decay data f rom a recognized and current source, 1 4 such as Reference 26. I 1, = the rate constant for removal of activity on leaf and i plant surfaces by weathering, in s~I, f rom Table 9-1. 4 ) (DFL),;; = the ingestion dose factor for receptor age group a, j radionuclide i, and organ j, in arem/pci, f rom Table 9-11 through Table 9-14. l the consumption rate of fresh leafy garden vegetation by 1 U,L =
' a receptor in age group a, in kg/y, f rom Table 9-5. l l
i l lO 9-3 Rev. 8, 1/94 !
Hatch ODCH U,3 = the consumption rate of stored garden vegetation by a receptor in age group a, in kg/y, from Table 9-5. the fraction of the annual intake of fresh leafy garden ft= vegetation that is grown locally (dimensionless), from ; Table 9-1. I J f = the fraction of the annual intake of stored garden g i vegetation that is grown locally (dimensionless), from Table 9-1. the average time between harvest of fresh leafy garden tt= vegetation and its consumption, in s, from Table 9-1. 4 l the average time between harvest of stored garden ! thy = I vegetation and its consumption, in s, from Table 9-1, j I H l For tritium in the garden vegetation consumption pathway, R,jg in (mram/y) per (pci/m3 ) is calculated as follows (Reference 1, Section. 5. 3.1. 5 ) , based on the concentration in air rather than deposition onto the ground: f- g V aaq,j = xn x3 - (ort >ay - ( u a t it + v as is ) 0 's - '*L' (s s> 1 Ht i
- I where
the units conversion factor: 103 g/kg. i K3= H= the absolute humidity of atmospheric air, in g/m ,3 from 4 Table 9-1. l 0.75 = the fraction of the mass of total garden vegetacion that j is water (dimensionless). 0.5 = the ratio of the specific activity of tritium in garden vegetation water to that in atmospheric water 2 (dimensionless). and other parameters are as defined above. d 2 9-4 Rev. 8, 1/94 4
m .m___ Hatch ODCM l Table 9-1. Miscellaneous Parameters for the Garden Vegetation Pathway s The following parameter values are for use in calculating Rgipj for the garden vegetation pathway only. The terms themselves are defined in Section 9.3. 5 Parameter Value Reference 4 Yy 2.0 kg/m2 Ref. 3, Table E-15 4 1, 5.73 x 10*7 s *I Ref. 1, page 33 (14-day half-life) i .
1.0 Ref. 1, page 36 l
4 fL fg 0.76 Ref. 1, page 33 1 tg 8.6 x 104 s Ref. 3, Table E-15 (1 day) i 6 Ref. 3, Table E-15 t hv 5.18 x 10 s j i (60 days) H 8 g/m 3 Ref. 3 i 4 l I 4 a 1 } O 9-5 Rev. 8, 1/94
__ . _. .__ . . . . m.. . _ . _ . . . _ _ . _ . . . _ . . Hatch ODCM 9.4 GRASS-COW-MILK PATHWAY FACTOR O For radionuclides other than tritium in the grass-cow-milk pathway, R.;p; in (m2 . mrem /y) per (pci/s) is calculated as follows (Reference 1, Section 5.3.1.3)s R aipj
- Kg * *Oy U ap *Tmi ' (D F L)a;;
(Al
- Aw)
(
-k /'hm fp f, . (1 - f pf,) e . , -k; sj Yp Ys i
a where Kg = the units conversion factor: 100 pci/pci. r= the f raction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radiciodines and 0.2 f or particulates, from p (Reference 3, Table E-1). 1; = the radioactive decay constant for radionue..de i, in s ~I. Values of 1; used in ef fluent calculations should be based on decay data from a recognized and current source, such as Reference 26. 1 I 1, = the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-I, from Table 9-2. Op = the cow's consumption rate of feed, in kg/d, from i Table 9-2. U,p = the consumption rate of cow milk by a receptor in age group a, in L/y, from Table 9-5. Fini = the stable element transfer coefficient applicable to radionuclide 1, for cow's milk, in d/L, from Table 9-6. 1
\
9-6 Rev. 8, 1/94
. _ _ . _ _ _.._m _ _.._ _ _ _ - ___..._.m_._ - _ _._. - _ _ _ _ m . ..m m _. _. _. _
.m_.~_____.
Hatch ODCM ; ) (DFL),;j = the ingestion dose f actor for receptor age group a, radionuclide i, and organ j, in arem/pci, f rom Table 9-11 i through Table 9-14. f = the fraction of the year that the cow is on pasture p i 1 (dimensionless), from Table 9-2. j f, = ' the fraction of the cow's feed that is pasture grass i ! while the cow is on pasture (dimensionless), from Table 9-2. ! f J Yp = the areal density (agricultural productivity) of growing j ] pasture feed grass, in kg/m2, from Table 9-2. r i Y, = the areal density (agricultural productivity) of growing 4 stored feed, in kg/m 2, from Table 9-2. i i l I tg = the transport time f tom harvest of stored feed to its ] j consumption by the cow, in s, from Table 9-2. I l tg = the transport time from consumption of feed by the cow, l l l \ to consumption of milk by the receptor, in s, from I j !
- Table 9-2.
3
. For tritium in the grass-cow-milk pathway, R,;pj in (mram/y) per (pCi/m )
i is calculated as follows (Reference 1, Section 5.3.1.5), based on the
- concentration in air rather than deposition onto the grounds 1
R aip) "Kl*K3
- Q-
- Uap
- Tmi * ( M l aij
- O * ' 5 * ( (***)
a where: a the units conversion factor: 103 g/kg. K3= H= the absolute humidity sf atmospheric air, in g/m ,3 from ] i Table 9-2. ! 5
)
l 9-7 Rev. 8, 1/94 l 1 i
)
4
. - . ~ . . . . - . - . . _ . , . . . . - .~ -. . - . . . . . - . - _ . - - . . . . . - . . .
4 i I 1
' Hatch ODCM i4 0.75 = the fraction of the mass of total vegetation that is J
water (dimensionless). 0.5 = the ratio of the specific activity of tritium in 4 vegetation water to that in atmospheric water i I (dimensionless). 5 and other parameters are as defined above. 1 ( i i 4 5 i i 3 s A d i 1 1 3 l i 1 1 i i i j i f i l 1 ? l i i V 9-8 Rev. 8, 1/94 3
Hatch ODCM Table 9-2. Miscellaneous Parametero for the Grass-Cow-Milk Pathway i V The following parameter values are for use in calculating R,;pj for the grass-cow-milk pathway only. The terms themselves are defined in Section 9.4. 4 Parameter Value Reference ) 1, 5.73 x 10'2 s *I Ref. 1, page 33 (14-day half-life) d Op 50 kg/d Ref. 3, Table E-3 f 1.0 Ref. 1, page 33 p f, 1.0 Ref. 1, page 33 Yp O.7 kg/m 2 Ref. 3, Table E-15 l i Y, 2.0 kg/m2 Ref. 3, Table E-15 7.78 x 106 s 4 Ref. 3, Table E-15 thm (90 days) tg 1.73 x 105 s Ref. 3, Table E-15 (2 days) H 8 g/m 3 Ref. 3 i 4 1 l N 9-9 Rev. 8, 1/94
. . . - - . - - . - . - - , - , ~ . - . . - . - - . . . . - . . .- . . - . . . , ~ . _ ~ - .
Hatch ODcM 9.5 GRASS-GOAT-MILK PATHWAY FACTOR b U For radionuclides other than tritium in the grass-goat-milk pathway, R,ipj in (m2.mrom/y) per (pci/s) is calculated as follows (Reference 1, Section l 5.3.1.3): i Raip)
- Kg * *Op*Uap *Tmi * (DFLlaij (1/ + Aw)
_xj gg (9*7) fp f, + (1 - fp f,) e e -k; if Yp Ys where Kg = the units conversion factor: 100 pCL/pci. r= the fraction of deposited activity retained on the edible parts of vegetation (dimensionless) . The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1). 1j= the radioactive decay constant for radionuclide 1, in s -I. Values of A used in ef fluent calculations should be g based on decay data from a recognized and current source, such as Reference 26.
+ 1, = the rate constant for removal of activity on leaf and plant surfaces by weathering, in s~I, from Table 9-3.
l Op = the goat *s consumption rate of feed, in kg/d, from Table 9-3. U,p = the consumption rate of goat milk by a receptor in age group a, in L/y, from Table 9-5. Fg = the stable element transfer coef ficient applicable to radionuclide 1, f or goat
- s milk, in d/L, from Table 9-6.
O 9-10 Rev. 8, 1/94
_ . _ .._.. _ _._ .. _ _ _ _ . _ _ _. _ . _ ._..... _ .... ._. .. _ ___.. . _ .m _ _ ... ~ .m . . _ _ _ _ _ . l 4 Hatch ODCM 4 (DFL).jj = the ingestion dose f actor for receptor age group a, radionuclide i, and organ j, in eres/pci, from Table 9-11. 4 1~( ' through Table 9-14. , i
- f = the fraction of.the year that the goat is on pasture p
$ (dimensionless), from Table 9-3. 4 l L f, = ' the fraction of the goat's feed that is pasture grass } l while the goat is on pasture (dimensionless), from j Table 9-3. Y p= the areal density (agricultural productivity) of growing ) f pasture feed grass, in kg/m2, from Table 9-3. i j Y, = the areal density (agricultural productivity) of growing ! stored feed, in kg/m 2, from Table 9-3. i, j tg = the transport time f rom harvest of stored feed to its consumption by the goat, in s, from Table 9-3. i ; 4 tr = the transport time from consumption of feed by the goat, to consumption of milk by the receptor, in s, from j i Table 9-3. l l 3 For tritium in the grass-goat-milk pathway, Raip; in (mrem /y) per (pC1/m ) is calculated as follows (Reference 1, Section 5.3.1.5), based on the f concentration in air rather than deposition onto the ground: l-O l R aipj = Kg K3
- Oy
- Uap *T mi * ( DFL } a;;
- 0. 7 5 * (9.8}
4 1 I where: the units conversion factors 103g /)rg . K3= 1 H= the absolute humidity of atmospheric air, in g/m3, from Table 9-3. 4
;0 9-11 Rev. 8, 1/94 W
f
.. .. . . . . . . - . . _ . - . - - - . . . _ - - . - -.- . . . . . . . . . . . - . - . - ~ . . - . . . - . . . . - . . .
] 1 Hatch ODCM 5 4 0.75 = the fraction of the mass of total vegetation that is j 'l j water (dimensionless). ! 0.5 = the ratio of the specific activity of tritium in vegetation water to that in atmospheric water 4
, (dimensionlees).
and other parameters are as defined above. a i i
)
9-12 Rev. 8, 1/94 l
1 Hatch ODCM d Table 9-3. Miscellaneous Parameters for the Grass-Goat-Milk Pathway V The following parameter values are for use in calculating R,jp; for the s grass-goat-milk pathway only. The terms themselves are defined in Section 9.5. 4 Parameter Value Reference 1, 5.73 x 10~7 s *I Ref. 1, page 33
- (14-day half-life)
Qp 6 kg/d Ref. 3, Table E-3 f 1.0 Ref. 1, page 33 p f, 1.0 Ref. 1, page 33 Y 0.7 kg/m2 Ref. 3, Table E-15 i p Ys 2.0 kg/m2 Ref. 3, Table E-15 tg 7.78 x 106 s Ref. 3, Table E-15 [b (90 days) l tg 1.73 x 105 s Ref. 3 Table E-15 4 (2 days) H 8 g/m 3 Ref. 3 l 1 1 5 [ ( 9-13 Rev. 8, 1/94
-. . .- . . . ~. ..__.- . . . . . . . - - - - . ~ . - ~ - - . . -. . . . - - -
Hatch ODCM 9.6 GRASS-COW-MEAT PATHWAY FACTOR For radionuclides other than tritium in the grass-cow-meat pathway, R,jjp in (mL,. rem /y) per (pci/s) is calculated as follows (Reference 1, Section 5.3.1.4): i
- v ap * !)1 * (DTL)ay R apj;
= Kg
- Oy (Ai+Aw)
(9.9)
~hi ihm fp f, . (1 - f pf,) e ., -kg tf
-d Yp Is i i 3 whore: f Kg = the units conversion factor: 100 pCi/pci. r= the fractic,n of deposited activity retained on the edible parts of vegotation (dimensionless) . The value used for r is 1.0 f or radioiodines and 0.2 f or particulates, from (Reference 3, Table E-1). the radioretive decay constant for radionuclide 1, in l lj = i s -I. Valet m of 1; used in ef fluent calculations should be i based on decay data from a recognized and current source, such as Reference 26. 4 1, = the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-I, from Table 9-4. 1 J Op = the cow's consumption rate of feed, in kg/d, from l Table 9-4.
- U,p = the consumption rate of, meat by a receptor in age group a, in kg/y, from Table 9-5.
1 Fg; a the stable element transfer coefficient applicable to radionuclide i, for meat, i., d/kg, from Table 9-6. 3 . ( i' 9-14 Rev. 8, 1/94 l
Hatch ODCH
= the ingestion dose factor for receptor age group a, (DFL),jJ radionuclide i, and organ j , in mrem /pci, f rom Table 9-11 through Table 9-14.
f = the fraction of the year that th6 cow is on pasture p (dimensionless), from Table 9-4. f, = the fraction of the cow's feed that is pasture grass I while the cow is on pasture (dimensionless), from 1 Table 9-4. Y p= the areal density (agricultural productivity) of growing j pasture feed grass, in kg/m 2, from Table 9-4. Y, = tt< areal density (agricultural productivity) of growing stored feed, Ln kg/m 2, from Table 9-4. a tg = the transport time from harvest of stored feed to its ! consumption by the cow, in s, from Table 9-4. tg = the transport time f rom consumption of f eed by the cow, j < to consumption of meat by the receptor, in s, from Table 9-4. I 3 For tritium in the granc-cc,w-meat pathway, R aipj in (mrem /y) per (pCi/m ) is calculated as follows (Reference 1, Section 5.3.1.4), based on the concentration in air rather than deposition onto the ground: J R aipj = Kg K3
- Oy ' Upp
- Tjj = (DFL)ag;
- O.75 ' (9.10}
where the unite conversion factor: 103 g/kg. K3= 1 H= the absolute humidity of atmospheric air, in g/m3 , from f Table 9-4. O LJ 9-15 Rev. 8, 1/94
- --~ . . - - . _ - _ . - . . _ _ - _ . . _ . - _ , , _ . .
Hatch ODCM j 0.75 = the fraction of the mass of total vegetation that is
~
water (dimensionless). 1 0.5 = the ratio of the specific activity of tritium in , vegetation water to that in atmospheric water I (dimensionless). i and other parameters are as defined above. i i
)
A U 9-16 Rev. 8, 1/94 l
f I 1 Hatch ODCM Table 9-4. Miscellaneous Parameters for the Grass-Cow-Meat Pathway 1
, \s_/
i The following parameter values are for use in calculating ap Rjj for the ' grass-cow-meat pathway only. The terms themselves are defined in Section 9.6. 1 Parameter Value Reference 1, 5.73 x 10*7 s *I Ref. 1, page 33 4 (14-day half-life) 50 kg/d Ref. 3, Table E-3 Qp i f 1.0 Ref. 1, page 33 f p f, 1.0 Ref. 1, page 33 Y 0.7 kg/n3 Ref. 3, Table E-15 p Y, 2.0 kg/n3 Ref. 3, Table E-15 thm 7.78 x 106 s Ref. 3, Table E-15 (90 days) l tf 1.73 x 106 s Ref. 3, Table E-15 (20 days) H 8 g/m 3 Ref. 3 i l l 4 O 9-17 Rev. 8, 1/94
. .. - - - . . _ _ . . - _ . _ _ . _ . _ . . . . - . . -. -.= . ' Hatch ODCM Table 9-5. Individual Usage Factors b
V Receptor Age Group Usage Factor Infant Child Teenager Adult Hilk Consumption Rate, U,p 1 (L/Y) Meat Consumption Rate, U,p (kg/y) Fresh Leafy Garden Vegetation Consumption Rate, Ual O 26 42 64 . (kg/y) Stored Garden Vegetation Consumption Rate, UaS O 520 630 520 (kg/y) Breathing Rate, (BR), 1400 3700 8000 8000 (m 3 /y) O All values are from Reference 3, Table E-5. O 9-18 Rev. 8, 1/94
Hatch ODCM Table 9-6. Stable Element Transfer Data Cow Milk Goat Milk Meat { 4 Element Fr (d/kg) F ,(d/L) Tm (d/L)+ l H 1.0 E-02 1.7 E-01 1.2 E-02 c 1.2 E-02 1.0 E-01 3.1 E-02 t Na 4.0 E-02 4.0 E-02 3.0 E-02 P 2.5 E-02 2.5 E-01 4.6 E-02 Cr 2.2 E-03 2.2 E-03 2.4 E-03 i Mn 2.5 E-04 2.5 E-04 8.0 E-04 Fe 1.2 E-03 1.3 E-04 4.0 E-02 Co 1.0 E-03 1.0 E-03 1.3 E-02 Ni 6.7 E-03 6.7 E-03 5.3 E-02 , Cu 1.4 E-02 1.3 E-02 8.0 E-03 l Zn 3.9 E-02 3.9 E-02 3.0 E-02 Br 5.0 E-02 5.0 E-02 2.6 E-02 Rb 3.0 E-02 3.0 E-02 3.1 E-02 Sr 8.0 E-04 1.4 E-02 6.0 E-04 Y 1.0 E-05 1.0 E-05 4.6 E-03 Zr 5.0 E-06 5.0 E-06 3.4 E-02 Nb 2.5 E-03 2.5 E-03 2.8 E-01 Mo 7.5 E-03 7.5 E-03 8.0 E-03 Tc 2.5 E-02 2.5 E-02 4.0 E-01 (] Ru 1.0 E-06 1.0 E-06 4.0 E-01 () Rh 1.0 E-02 1.0 E-02 1.5 E-03 Ag 5.0 E-02 5.0 E-02 1.7 E-02 Sb 1.5 E-03 1.5 E-03 4.0 E-03 Te 1.0 E-03 1.0 E-03 7.7 E-02 I 6.0 E-03 6.0 E-02 2.9 E-03 Cs 1.2 E-02 3.0 E-01 4.0 E-03
- Ba 4.0 E-04 4.0 E-04 3.2 E-03 La 5.0 E-06 5.0 E-06 2.0 E-04 Ce 1.0 E-04 1.0 E-04 1.2 E-03 Pr 5.0 E-06 5.0 E-06 4.7 E-03 Nd 5.0 E-06 5.0 E-06 3.3 E-03 W 5.0 E-04 5.0 E-04 1.3 E-03 Np 5.0 E-06 5.0 E-06 2.0 E-04
* - Values f rom Ref erence 3 (Table E-1) except as follows:
Reference 2 (Table C-5) for Br and Sb.
+ - Values from Reference 3, Table E-2 for H, C, P, Fe, Cu, Sr, I, and Cs in goat milk, and Table E-1 for all other elements in cow milk, except as follows:
Reference 2 (Table C-5) for Br and Sb in cow milk. O 9-19 Rev. 8, 1/94 1
Hatch ODCM Table 9-7. Inhalation Dose Factors for the Inf ant Age Group Liver T. Body Thyroid Kidney Lung GI-LLI Nuclide Bone H-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4 4 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05 P-32 1 No Data No Data 6.39E-08 4.11E-08 9. 4 5E-09 9.17E-06 2.55E-07 < Cr-51 I Mn-54 No Data 1.81E-05 3.56E-06 No Data 3. 5 6E-06 7.14E-04 5.04E-06 Mn-56 No Data 1.10E-09 1.58E-10 No Data 7 . 86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data No Data 5.80E-06 3.58E-05 2.84E-09 6.64E-06 1.07E-05 ( Cu-64 No Data 1.34E-09 5.53E-10 No Data Zn-65 1.3BE-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 No Data No Data 2.72E-07 No Data No Data No Data No Data Br-83 No Data 2.86E-07 No Data No Data No Data No Data Br-84 No Data No Data 1.46E-08 No Data No Data No Data No Data Br-85 No Data Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 l Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E 05 3 Sr-90 2.92E-02 No Data 1.8bE-03 No Data No Data 8.03E-03 9.36E-05 Sr-91 6.83E-08 No Data 2.47E-09 No Data ' No Data 3.76E-05 5.24E-05 All values are in (mrem /pci inhaled). They are obtained from Reference 3 (Table E-10). Neither Reference 2 nor Reference 3 4 contains data for Rh-105, Sb-124, or Sb-125. ( 9-20 Rev. 8, 1/94
Hatch ODCM Table 9-7 (contd). Inhalation Dose Factors for the Infant Age Group O Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI l Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 i Y-91m 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Y-93 1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 2r-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 , 1 Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.9BE-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 v 9-21 Rev. 8, 1/94
Hatch ODCM Table 9-7 (contd). Inhalation Dose Factors for the Inf ant Age Group A b Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Te-132 2.66E-07 1.69E-07 ).26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05
- I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 2
I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 No Data 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-07 I-135 2.76E-06 5.43E-06 1.9BE-06 4.97E-04 6.05E-06 No Data 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05 t Ba-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 V Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 No Data No Data 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05 Co-144 2.28E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Np-2 39 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 O 9-22 Rev. 8, 1/94
Hatch ODCM Table 9-8. Inhalation Dose Factors for the Child Age Group p) t Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 Mn-56 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 No Data No Data 3.43E-04 1.91E-05 l Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 ] Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71E-06 8.08E-10 7.99E-11 4.44E-11 No Data No Data 2.21E-06 2.27E-05 I Ni-65 (- Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E-06 Br-83 No Data No Data 1.28E-07 No Data No Data No Data No Data Br-84 No Data No Data 1.48E-07 No Data No Data No Data No Data l Br-85 No Data No Data 6.84E-09 No Data No Data No Data No Data Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.11E-10 Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 All values are in (mrom/pci inhaled). They are obtained from Reference 3 (Table E-9). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-124, or Sb-125. O . 9-23 Rev. 8, 1/94
Hatch ODCM Table 9-8 (contd). Inhalation Dose Factors for the Child Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 } 7.07E-05 7.24E-05 < Y-90 1.11E-06 No Data 2.99E-08 No Data No Data Y-91m 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05 Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 4 Nb-95 6.35E-06 2.4BE-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05 I n l I I 1 Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 No Data No Data No Data No Data No Data Rh-105 No Data No Data Ag-110m 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 No Data No Data No Data No Data No Data Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 1.93E-05 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 ~ Te-129 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 s Te-131 O 9-24 Rev. 8, 1/94 )
Hatch ODCM 4 Table 9-8 (contd). Inhalation Dose Factors for the Child Age Group v Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 No Data 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 No Data 1.20E-06
! Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 No Data 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 No Data 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 q
Ba-142 1.35E-11 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 e La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 i La-142 3.50E-10 1.11E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05 2.31E-06 1.47E-04 1.53E-05 4 Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 a Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 b 9-25 Rev. 8, 1/94
l Hatch ODCM f Table 9-9. Inhalation Dose Factors for the Teenager Age Group m + V Nuclide Bone Live. I T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 2 P-32 2.36E-04 1.37E-08 8.95E-06 No Data No Data No Data 1.16E-05 4 Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 i I Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06 j Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data . E-05 7.99E-07 , l 4 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E-05 l Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.19E-05 j l Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 5 Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06
'N Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 l \ Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data No Data 4
Br-84 No Data No Data 5.41E-08 No Data No Data No Data No Data Br-85 No Data No Data 2.29E-09 No Data No Data No Data No Data Rb-86 No Data 2.38E-05 1.05E-05 No Data No Data No Data 2.21E-06 Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 No Data 4.40E-08 2.91E-08 No Data No Data No Data 4.22E-17 Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05 Sr-91 1.10E-08 No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05 All values are in (mrem /pCi inhaled). They are obtained from Reference 3 (Table 'E-8) . Neither Reference 2 nor Reference 3 contains data for Rh' 105, Sb-124, or Sb-125. O 9-26 Rev. 8, 1/94
4 l l Hatch ODCM Table 9-9 (contd). Inhalation Dose Factors for the Teenager Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 1.19E-09 No Data 5.08E-11 No Data No Data 3.43E-06 1.49E-05 Y-90 3.73E-07 No Data 1.00E-08 No Data No Data 3.66E-05 6.99E-05 I l Y-91m 4.63E-11 No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 ) Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05 Y-92 1.84E-09 No Data 5.36E-11 No Data No Data 3.35E-06 2.06E-05 Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 1 a Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 . Mo-99 No Data 2.11E-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 j Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 ku-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05 ~ Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 4 Rh-105 No Data No Data No Data No Data No Data No Data No Data l Ag-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 s Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 I l Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 1 2.32E-07 1.89E-09 O 9-27 Rev. 8, 1/94
Hatch ODCM Table 9-9 (contd). Inhalation Dose Factors for the Teenager Age Group [ Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 I-135 4.62E-Ci7 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 4 Cs-134 6.28E-OS 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3. BOE-0 5 1.51E-05 1.06E-06 Co-138 5.82E-08 1.07E-07 5.5BE-OB No Data 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-OS m j Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.11E-0 6 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.OBE-08 1.63E-05 3.19E-05 Co-144 6.11E-04 2.53E-04 3.28E-OS No Data 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 1 Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 No Data 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 No Data No Data 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 No Data 1. 25E-08 8.11E-06 1.65E-05 i i ks 9-28 Rev. 8, 1/94
. - . _ . - ~_ -. - . _ . - - _ -
l Hatch ODCM Table 9-10. Inhalation Dose Factors for the Adult Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 3-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 4 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 4 Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-56 No Data 1.55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01E-06 7.54E-07 1 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 i ! Co-60 No :)ata 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 h Ni-63 5.40E-05 3.93E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.00E-07 1.54E-06 i Cu-64 No Data 1.83E-10 7.69E-11 No Data 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8. 62E-0 6 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 5 Br-84 No Data No Data 3.91E-08 No Data No Data No Data 2.05E-13 i' Br-85 No Data No Data 1.60E-09 No sata No Data No Data No Data Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 1.24E-02 No Data No Data .20E-03 9.02E-05 Sr-90 7.62E-Of No Data Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 All values are in (mrem /pci inhaled). They are obtained from Reference 3 (Table E-7), except as follows: Reference 2 (Table C-1) for Rh-105, Sb-124, and Sb-125. O Rev. 8, 1/94 9-29
Hatch ODCM i Table 9-10 (contd). Innalation Dose Factors for the Adult Age Group
- Vn.
Bone Liver T. Body Thyroid Kidney Lung GI-LLI Nuclide Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 J Y-90 2.61E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 Y-91m 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.L6E-10 Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81E-05 Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 1 Y-93 1.18E-08 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 i 4 Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05 i Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 a' Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 I l Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1. 35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05 9.88E-11 No Data 3.89E-11 No Data 1.27E-10 1.37E-06 6.02E-06 Ru-105 (
% 1.67E-05 1.17E-03 1.14E-04
- j Ru-106 8.64E-06 No Data 1.09E-06 No Data l
9.24E-10 6.73E-10 4.43E-10 No Data 2.86E-09 2.41E-06 1.09E-05 l Rh-105 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Ag-110m d 3.90E-06 7.36E-08 1.55E-06 9.44E-09 No Data 3.10E-04 5.08E-05 Sb-124 8.26E-06 8.91E-08 1.66E-06 7.34E-09 No Data 2.75E-04 1.26E-05 Sb-125 I 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06
! Ta-125m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127m 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-1C 8.14E-07 7.17E-06 Te-127 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129m Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 i Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 1
9-30 Rev. 8, 1/94
.. .~
i Hatch ODCM Table 9-10 (contd). Inhalation Dose Factors for the Adult Age Group
- .O Nuclide Bone Liver T. Body Tnyroid Kidney Lung CI-LLI 1
Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-06 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 3 Data 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 - I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 i I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 i Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.7BE-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 4 Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Da-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 i La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07 i Ce-141 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05 o co-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05 ! Co-144 4.29E-04 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.39E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data S.75E-09 4.70E-06 1.49E-05 i 9-31 Rev. 8, 1/94 2
4 _ Hatch ODCM l Table 9-11. Ingestion Dose Factors for the Inf ant Age Group I l Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI 4 H-3 No Data 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.0BE-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 i P-32 1.70E-03 1.00E-04 6.59E-05 No Data No Data No Data 2.30E-05 Cr-51 No Data No Data 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Hn-54 No Data 1.99E-05 4.51E-06 No Data 4.41E-06 No Data 7.31E-06 f Mn-56 No Data 8.18E-07 1.41E-07 No Data 7.03E-07 No Data 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 No Data No Data 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 No Data No Data 1.59E-05 2.57E-05 4 Co-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06 Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 No Data No Data No Data 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 No Data No Data No Data 4.05E-05 Cu-64 No Data 6.09E-07 2.82E-07 No Data 1. 03E-0 6 No Data 1.25E-05
Zn-65 1.84E-05 6.31E-05 2.91E-05 No Data 3.06E-05 No Data 5.33E-05 1
Zn-69 9.33E-08 1.68E-07 1.2SE-08 No Data 6.98E-08 No Data 1.37E-05 i Br-83 No Data No Data 3.63E-07 No Data No Data No Data No Data i Br-84 No Data No Data 3.82E-07 No Data No Data No Data No Data Br-85 No Data No Data 1.94E-08 No Data No Data No Data No Data Rb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06 Rb-88 No Data 4.98E-07 2.73E-07 No Data No Data No Data 4.85E-07 Rb-89 No Data 2.86E-07 1.97E-07 No Data No Data No Data 9.74E-08 l i Sr-89 2.51E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05 1 l Sr-90 1.85E-02 No Data 4.71E-03 No Data No Data No Data 2.31E-04 4 Sr-91 5.00E-05 No Data 1.81E-06 No Data No Data No Data 5.92E-05 l All values are in (mrem /pci ingested) . They are obtained from Reference 3 (Table E-14). Neither Reference 2 nor Reference 3 contains data for Rh-105, sb-124, or Sb-125. l l
- O Rev. 8, 1/94 9-32
s j ' Hatch ODCM Table 9-11 (contd). Ingestion Dose Factors for ths Inf ant Age Group j f Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI Sr-92 1.92E-05 No Data 7.13E-07 No Data No Data No Deta 2.07E-04 , l 3 Y-90 8.69E-08 No Data 2.33E-09 No Data No Data No Data 1.20E-04 . Y-91m 8.10E-10 No Data 2.76E-11 No Data No Data No Data 2.70E-06 i l Y-91 1.13E-06 No Data 3.01E-Od No Data No Data No Data 8.10E-05 I i Y-92 7.65E-09 No Data 2.15E-10 No Data No Data No Data 1.46E-04 i l Y-93 2.43E-08 No Data 6.62E-10 No Data No Data No Data 1.92E-04 l Zr-95 2.06E-07 5.02E-08 3.56E-08 No Data 5.41E-08 No Data 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 No Data 2.56E-09 No Data 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 No Data 1.24E-08 No Data 1.46E-05 Mo-99 No Data 3.40E-05 6.63E-06 No Data 5.08E-05 No Data 1.12E-05 4 Tc-99m 1.92E-09 3.96E-09 5.10E-08 No Data 4.26E-08 2.07E-09 1.15E-06 i i Tc-101 2.27E-09 2.86E-09 2.83E-08 No Data 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.80E-05 , 1 Ru-105 1.36E-07 No Data 4.58E-08 No Data 1.00E-06 No Data 5.41E-05 Ru-106 2.41E-05 No Data 3.01E-06 No Data 2.85E-05 No Data 1.83E-04 i Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 9.96E-07 7.27E-07 4.81E-07 No Data 1.0(E-06 No Data 3.77E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data i ( a Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 No Data 2.36E-05 ! 4 70-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 No Data 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-05 Te-131m 1.52E-05 6.12E~06 5.05E-06 1.24E-05 4.21E-05 No Data 1.03E-04 ~ Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.11E-06 O Rev. 8, 1/94 9-33
- . . - - _ _ _ . _ . . - _ . , . . . - . . .~. --. . ~ _ . - ,
I Hatch ODCM i Table ~9-11 (contd). Ingestion Dose Factors for the Infant Age Group ("% I IF
- Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI i Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 No Data 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 No Data 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 No Data 1.51E-06 4 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 No Data 2.73E-06 -
l I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 No Data 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 No Data 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 No Data 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 No Data 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91E-06 ) Cs-138 4.81E-07 7.82E-07 3.79E-07 No Data 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 No Data 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 No Data 4.06E-08 1.05E-07 4.20E-05 j Ba-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 No Data 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 No Data No Data No Data 9.77E-05 l La-142 1.10E-09 4.04E-10 9.67E-11 No Data No Data No Data 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 No Data 1.4BE-08 No Data 2.48E-05 Co-143 1.48E-08 9.82E-06 1.12E-09 No Data 2.86E-09 No Data 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 No Data 4.93E-07 No Data 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 No Data 1.13E-08 No Data 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 No Data 3.84E-11 No Data 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 No Data 2.19E-08 No Data 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 No Data No Data No Data 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 No Data 1.9BE-09 No Data 2.87E-05 9-34 Rev. 8, 1/94
_ . . - - _ . . - . . . - ~ - - . . , ..-. - - . - -
- .- . _. . . _ _ . . _ _ - . .~
l l l 1 Hatch ODCM Table 9-12. Ingestion Dose Factors for the Child Age Group j
/ l , \
Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI H-3 No Data 2.33E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 C-14 I Ha-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 No Data No Data No Data 2.28E-05 a J Cr-51 No Data No Data 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 No Data 1.07E-05 2.85E-06 No Data 3.00E-06 No Data 8.98E-06 Mn-56 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data 4.84E-05 i Fe-55 1.15E-05 6.10E-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06 . i Fe-59 1.65E-05 2.67E-05 1.33E-05 No Data No Data 7.74E-06 2.78E-05 1
- Co-58 No Data 1.80E-06 5.51E-06 No Data No Data No Data 1.05E-05 Co-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 No Data No Data No Data 1.94E-06 1
Ni-65 2.22E-06 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-05 i 4 Cu-64 No Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data 1.15E-05 i Zn-65 1.37E-05 3.65E-05 2.27E-05 No Data 2. 30E-C5 No Data 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 No Data 3.84L-08 To Data 3.99E-06 2 Br-83 No Data No Data 1.71E-07 No Data No Data No Data No Data i Br-84 No Data No Data 1.98E-07 No Data No Data No Data No Data Br-85 No Data No Data 9.12E-09 No Data No Data No Data No Data 4 s Rb-86 No Data 6.70E-05 4.12E-05 No Data No Data No Data 4.31E-06 Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09 I Rb-89 No Data 1.17E-07 1.04E-07 No Data No Data No Data 1.02E-09 Sr-89 1.32E-03 No Data 3.77E-05 No Da;a No Data No Data 5.11E-05 , Sr-90 1.70E-02 No Data 4.31E-03 No Data No Data No Data 2.29E-04 Sr-91 2.40E-05 No Data 9.06E-07 No Data No Data No Data 5.30E-05 i All values are in (mrem /pci ingested). They are obtained from Reference 3 (Table E-13). Neither Reference 2 nor Reference 3 contains data for Rh-105, sb-124, or Sb-125.
\
9-35 Rev. 8, 1/94 o
Y Hatch ODCM 4 Table 9-12 (contd). Ingestion Dose Factors for the Child Age Group i Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71E-04 Y-90 4.11E-08 No Data 1.10E-09 No Data No Data No Data 1.17E-04 l Y-91m 3.82E-10 No Data 1.39E-11 No Data No Data No Data 7.48E-07 Y-91 6.02E-07 No Data 1.61E-08 No Data No Data No Data 8.02E-05 Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04 i Y-93 1.14E-08 No Data 3.13E-10 No Data No Data No Data 1.70E-04 l Zr-95 1.16E-07 2.55E-08 2.27E-08 No Data 3.65E-08 No Data 2.66E-05 : I Zr-97 6.99E-09 1.01E-09 5.96E-10 No Data 1.45E-09 No Data 1.53E-04 l t Nb-95 2.25E-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-05 Mo-99 No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.10E-05 Tc-99m 9.23E-10 1.81E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06
- Tc-101 1.07E-09 1.12E-09 1.42E-08 No Data 1.91E-08 5.92E-10 3.56E-09 i
- Ru-103 7.31E-07 No Data 2.81E-07 No Data 1.84E-06! No Data 1.89E-05 Ru-105 6.45E-08 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05 j Ru-106 1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 I 1
4 Rh-105 No Data No Data No Data No Data No Data No Data No Data ! Ag-110m 5.39E-07 3.64E-07 2.91E-07 No Data 6.78E-07 No Data 4.33E-05 4 Sb-124 No Data No Data No Data No Data No Data No Data No Data < Sb-125 No Data No Data No Data No Data . ata No Data No Data k 1.10E-05 4 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data 2.34E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No Data Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05 i Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 '. 1.01E-04 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 Te-131m No Data Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-07 J 4 s 9-36 Rev. 8, 1/94
1 Hatch ODCM Table 9-12 (contd). Ingestion Dose Factors for the Child Age Group I Nuclide Bone Liver T. Body Thyroid Kidney L ng CI-LLI 4 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2.76E-06 I-131 1.72E-05 1.73E-05 9. 83E -06 5.{EE-03 2.84E-05 No Data 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 No Data 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 No Data 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06 5 Cs-134 2.34E-04 3.84E-04 8.10E-05 No Data 1.19E-01 4.27E-05 2.07E-06 ~ Cs-136 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 l i Cs-138 2.28E-07 3.17E-07 2.01E-07 No Data 2.23E-07 2.40E-08 1.46E-07 i Ba-139 4.14E-07 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05 I Ba-140 8.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05
' Ba-141 2.00E-07 1.12E-10 6.51E-C9 No Data S.69E-11 6.58E-10 1.14E-07 f
Ba-142 8.74E-08 6.29E-11 4.8BE-09 No Data 5.09E-11 3.70E-11 1.14E-09 l l La-140 1.01E-08 3.53E-09 1.19E-09 No Data No Data No Data 9.84E-05 l t La-142 5.24E-10 1.67E-10 5.23E-11 No Data No Dats No Data 3.31E-05 Co-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 1 1 Co-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 No Data 3.GIE-07 No Data 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 No Data 6.39E-09 No Data 4.24E-05 i Pr-144 1.29E-10 3.99E-11 6.49E-12 No Data 2.11E-11 No Data 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 4.29E-07 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05 [ W-187 Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 1 i 9-37 Rev. 8, 1/94 i e
l l ] Hatch ODCH Table 9-13. Ingestion Dose Factors for the Teenager Age Group
) \j Kidney Lung GI-LLI
, Nuclide Bone Liver T. Body Thyroid H-3 No Data 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 n C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 l 1 P-32 2.76E-04 1.71E-05 1.07E-05 No Data No Data No Data 2.32E-05 ! Cr-51 No Data No Data 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Kn-54 No Data 5.90E-06 1.17E-06 No Data 1.76E-06 No Data 1.21E-05 i l Mn-56 No Data 1.58E-07 2.81E-08 No Data 2.00E-07 No Data 1.04E-05 l Fe-55 3.78E-06 2.68E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 I Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 i Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 2 Co-60 No Data 2.81E-06 6.33E-06 No Data No Data No Data 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 No Data No Data No Data 1.99E-06 1 i Ni-65 7.43E-07 9.57E-08 4.36E-08 No Data No Data No Data 5.19E-06 Cu-64 No Data 1.15E-07 5.41E-08 No Data 2.91E-07 No Data 8.92E-06 1 , Zn-65 5.76E-06 2.00E-05 9.33E-06 No Data 1.28E-05 No Data 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 No Data 1.83E-08 No Data 5.16E-08 l Br-83 No Data No Data 5.74E-08 No Data No Data No Data No Data l Br-84 No Data No Data 7.22E-08 No Data No Data No Data No Data j Br-85 No Data No Data 3.05E-09 No Data No Data No Data No Data Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41E-06 Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-08 3.89E-08 No Data No Data No Data 8.43E-17 l Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 i St-90 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04 Sr-91 8.07E-06 No Data 3.21E-07 No Data No Data No Data 3.66E-05 A'.1 values are in (mrem /pti ingested). They are obtained from i
- Tieference 3 (Table E-12). Neither Reference 2 nor Reference 3 contains data for Rh-105, S b- 12 4 , or Sb-125.
iO - ' 9-38 Rev. 8, 1/94 )
a l Hatch ODCH 4 Table 9-13 (contd). Ingestion Dose Factors for the Teenager Age Group j
\n) v Lung l
Nuclide Bone Liver T. Body Thyroid Kidney CI-LLI Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05 Y-90 1.37E-08 No Data 3.69E-10 No Data No Data No Data 1.13E-04 J Y-91m 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09 2 Y-91 2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 Y-92 1.21E-09 No Data 3.50E-11 No Data No Data No Data 3.32E-05 Y-93 3.33E-09 No Data 1.05E-10 No Data No Data No Data 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 No Data 1.91E-08 No Data 3.00E-05 Er-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.11E-10 No Data 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 No Data 4.42E-09 No Data 1.95E-05 Mo-99 No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 No Data 1.3BE-08 5.14E-10 6.08E-07 1 Tc-101 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 i Ru-103 2.55E-07 No Data 1.09E-07 No Data 8.99E-07 No Data 2.13E-05
)
8.46E-09 2.75E-07 No Data 1.76E-05 [ Ru-105 2.18E-08 No Data No Data
\ 7.56E-06 1.88E-04 Ru-106 3.92E-06 No Data 4.94E-07 No Data No Data Rh-105 No Data No Data No Data No Data No Data No Data No Data t
Ag-110m 2.05E-07 1.94E-07 1.18E-07 No Data 3.70E-07 No Data 5.45E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data 6 sb-125 No Data No Data No Data No Data No Data No Data No Data 1 4 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 No Data No Data 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 No Data 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 No Data 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 No Data 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1. 22 E-07 No Data 2.29E-09 s 9-39 Rev. 8, 1/94
Hatch ODCM Table 9-13 (contd). Ingestion Dose Factors for the Teenager Age Group. V Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Te-132 3.49E-06 2.212-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No Data 2.29E-06 4 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 No Data 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 ?.46E-05 1.15E-06 No Data 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E 06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 t'o Data 5.10E-09 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data I-135 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06 l 1 Cs-136 8.59E-06 3.38E-05 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 1.10E-07 1.28E-08 4 Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 No Data 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05 l Ba-141 6.71E-08 5.01E-11 2.24E-09 No Data 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 No Data 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Data 9.82E-05 4 La-142 1.79E-10 7.95E-11 1.98E-11 No Data No Data No Data 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-09 No Data 2.54E-05 Co-143 2.35E-09 1.71E-06 1.91E-10 No Data 7.67E-10 No Data 5.14E-05 l Ce-144 6.96E-07 2.8BE-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 No Data 1.01E-11 No Data 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 No Data 5.99E-09 No Data 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 No Data No Data No Data 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-05 9 do Rev. 8, 1/94
Hatch ODCM i Table 9-14. Ingestion Dose Factore for the Adult Age Group i T. Body Thyroid Kidney Lung GI-LLI ( Nuclide Bone Liver H-3 No Data 1.05E-07 1.05E ~7 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 J P-32 ) Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 l l
- Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 1
Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 l i a l Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2 .10E-07 No Data 7.10E-06
' En-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 i
En-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 { ' Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 No Data 2.14E-03 No Data No Data No Data No Data Br-85 No Data
- Rb-86 No Data 2.11E-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05
? All values are in (mram/pci ingested) . They are obtained from
' Reference 3 (Table E-11), except as follows: Reference 2 (Table ' A-3) for Rh-105, Sb-124, and Sb-125.
9-41 Rev. 8, 1/94 4 I
Hatch ODCM i Table 9-14 (contd). Ingestion Dose Factors for the Adult A9e Group j b Nuclide Bone Liver T. Body Thyroid Kidney Lun9 GI-LLI Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 ; Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 l l Y -9 3 2.68E-09 No Data 7.40E-11 No Data No Data No Data 8.50E-05 l l , Er-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 i Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 i l Hb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-99 No Data 4.31E-06,8.20E-07 No Data 9.76E-06 No Data 9.99E-06 i Tc-99m 2.47E-10 6.98E .10 .sE-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 i ' Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 l 1 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 \ Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41E-05 l Ag-110m 1.60E-01 1.48E-07 8.79E-08 No Data 2.93E-07 No Data 6.04E-05 f Sb-124 2.81E-06 5.30E-08 1.11E-06 6.79E-09 No Data 2.18E-06 7.95E-05 l Sb-125 2.23E-06 2.40E-08 4.48E-07 1.98E-09 No Data 2.33E-04 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 j Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 i Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05 ) Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 i Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 i O 9-42 Rev. 8, 1/94 W
.. . . - . _ _ . . - . . . ~ . . - . . . - . - -.- . - . _ - . _ . . _ - .=
Hatch ODCM 4 j Table 9-14 (contd). ' Ingestion Dose Factors for the Adult Age Group
- O Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI
- Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 l I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 l I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-07 i 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 k I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 7
Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 1 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 - Co-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05
' 3.31E-11 2.22E-17 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 2 . 02 E.- 11 l Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Co-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.03E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11l No Data 3.65E-10 No Data 2.40E-05 9-43 Rev. 8, 1/94
4 J, Hatch ODCM i i Table 9-15. External Dose Factors for Standing on Contaminated Ground J , ( i Nuclide T. Body Skin Nuclide T. Body Skin H-3 0.00 0.00 Sr-91 7.10E-09 8.30E-09 l C-14 0.00 0.00 Sr-92 9.00E-09 1.00E-06 Na-24 2.50E-08 2.90E-08 Y-90 2.20E-12 2.60E-12 a P-32 0.00 0.00 Y-91m 3.80E-09 4.40E-09 Cr-51 2.20E-10 2.60E-10 Y-91 2.40E-11 2.70E-11 . Mn-54 5.80E-09 6.80E-09 Y-92 1.60E-09 1.90E-09 , ) ~ Mn-56 1.10E-08 1.30E-08 Y-93 5.70E-10 7.80E-10 l j Fe-55 0.00 0.00 Zr-95 5.00E-09 5.80E-09 Fe-59 8.00E-09 9.40E-09 Zr-97 5.50E-09 6.40E-09 f Co-58 7.00E-09 8.20E-09 Nb-95 5.10E-09 6.00E-09 ' Co-60 1.70E-08 2.00E-08 M0-99 1.90E-09 2.20E-09 Ni-63 0.00 0.00 Tc-99m 9.60E-10 1.10E-09 Ni-65 3.70E-09 4.30E-09 Tc-101 2.70E-09 3.00E-09 ) Cu-64 1.50E-09 1.70E-09 Ru-103 3.60E-09 4.20E-09 Zn-65 4.00E-09 4.60E-09 Ru-105 4.50E-09 5.10E-09 Zn-69 0.00 0.00 Ru-106 1.50E-09 1.80E-09 Br-83 6.40E-11 9.30E-11 Rh-105 6.60E-10 7.70E-10 'l ! Br-84 1.20E-08 1.40E-08 Ag-110m 1.80E-08 2.10E-08 Br-85 0.00 0.00 Sb-124 1.30E-08 1.50E-08 Rb-86 6.30E-10 7.20E-10 Sb-125 3.10E-09 3.50E-09 j kb-88 3.50E-09 4.00E-09 Te-125m 3.50E-11 4.80E-11 Rb-89 1.50E-08 1.80E-08 Te-127m 1.10E-12 1.30E-12 Sr-89 5.60E-13 6.50E-13 Te-127 1.00E-11 1.10E-11 j Sr-90 0.00 0.00 Te-129m 7.70E-10 9.00E-10 4 l i 2 They are obtained from ] All values are in (mres/h) per (pci/m ). j Reference 3 (Table E-6), except as follows: Reference 2 (Table A-7) ' for Rh-105, Sb-124, and Sb-125. E d 4 i 9-44 Rev. 8, 1/94
Hatch ODCM l Table 9-15 (contd). External Dose Factors for standing on contaminated cround rN U Nuclide T. Body Skin Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 ) , Te-131 2.20E-09 2.60E-06 j Te-132 1.70E-09 2.OOE-09 i I-130 1.40E-08 1.70E-08 j I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.OOE-08 { j I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 i Cs-134 1.20E-08 1.40E-08 ) Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 co-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.00 0.00 1 Pr-144 2.OOE-10 2.30E-10 Nd-14's 1.00E-09 1.20E-09 K-187 3.10E-09 3.60E-09 Np"239 9.50E-10 1.10E-09 9-45 Rev. 8, 1/94
. _ . _ . _ _ _ _ _ _ . _ _ _ _ . . _ _ _ ..__ _ _ ._ _ . m .._ . - . _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ . - _ _ _ _ .
i Hatch ODCM CHAPTER 10 DEFINITIONS OF EFFLUENT CONTROL TERMS ' The terme defined in this chapter are used in the presentation of the above
- chapters. These terms are shown in all capital letters to indicate that they are specifically defined.
10.1 TERMS SPECIFIC TO THE ODCM f i The following terms are used in the ODCM, but are not found in the Technical i Specifications: l BATCH RELEASE A BATCH RELEASE is the discharge of wastes of e discrete volume. Prior to i sampling for analyses, each liquid batch shall be isolated and then ' thoroughly mixed by a method described in the ODCM to assure j representative sampling.
- i 4
! COMPOSITE SAMPLE ' A COMPOSITE SAMPLE is one which contains material from multiple waste i 1 releases, in which the quantity of sample is proportional to the quantity I - of waste discharged, and in which the method of sampling employed results ~ in a specimen that is representative of the wastes released. Prior to analyses, all liquid samples that are to be aliquotted for a COMPOSITE l I SAMPLE shall be mixed thoroughly, in order for the COMPOSITE SAMPLE to be 4 representative of the effluent release. ) i When assessing the consequences of a waste release at the pre-release or post-release stage, the most recent available COMPOSITE SAMPLE results for the applicable release pathway may be used. CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of wastes of a non-discrete volume, e.g., from a volume within a system that has an input flow during the CONTINUOUS RELEASE. FREQUENCY NOTATION Tl.a FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined below, with a maximum allowable extension not to exceed 25% of the surveillance interval. O 10-1 Rev. 10, 7/95
_. ~ . . . - _ - . - - . . _ _ . _ . . _ _ . - - _ _-.- - - . . - - - - . ~ . . _ - . . . _ _ _ . - - - . - - - . ] Hatch ODCM i i NOTATION FREQUENCY 8 (Once per shift) At least once per 12 hours. t D (Daily) At least once per 24 hours. 3 W (Weekly) At least once per 7 days. M (Monthly) At least once per 31 days. Q (Quarterly) At least once per 92 days. SA (Semi-annually) At least once per 184 days, t R (Refueling) At least once per 18 months. j ~ S/U (Startup) Prior to each reactor startup. NA Not applicable.
- P (Prior) Completed prior to each release.
l GASEOUS RADWASTE TREATMENT SYSTEM ,i. The CASEOUS RADWASTE TREATMENT SYSTEM is the of fgas holdup system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for 4 delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. i LIOUID RADWASTE TREATMENT SYSTEM l A LIQUID RADWASTE TREATMENT SYSTEM is any system designed and installed to l { reduce radioactive materials in liquid affluents by systematic collection, retention, and processing through filtration, evaporation, f i separation and/or ion exchange treatment. This system consists of at i least one collection tank, one evaporator or dominera11ser system, one l post-treatment tank and associated components providing for treatment flow ! and functional control. I j MAJOR CHANCES TO RADIOACTIVE WASTE TREATMENT SYSTEMS i For the purposes of the OOCM, MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS include the following changes to such systems: l (1) Major changes in process equipeent, components, structures, or effluent monitoring instrumentation as described in the Final Safety Analysis Report (FSAR) or as evaluated in the Nuclear l Regulatory Coaunission staf f's Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of domineralizers); i I (2) Changes in the design of radwaste treatment systass that could significantly increase quantities of effluents released from those ) previously considered in the FSAA and SER; l !O 1 10-2 Rev. 10, 7/95 4 )
. _ _ _ . ____. _ . ___..m _ - .__ _. . . _ _ . _ __ _ __. _ .. _ .._ . _ . . . - _
? Hatch ODCM { i ! (3) Changes in system design which may invalidate the accident analysis as described in the SER (e.g., changes in tank capacity that would ! alter the curies released); or 4 (4) Changes in system design that could potentially result in a f i significant increase in occupat. anal exposure of operating j personnel (e.g., use of temporary equipment without adequate shielding provisions). MEMBERfS1 OF THE PUBLIC' i A MEMBER OF THE PUBLIC shall be an individual in a controlled area or an UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC j during any period in which the individual receives an occupational dose. $ This category may include persons who use portions of the site for j recreational, occupational, or other purposes not associated with the j plant. i MILK ANIMAL l
- A MILK ANIMAL is a cow or goat that is producing milk for human consumption.
w MINIMUM DETECTABLE CONCENTRATION The MINIMUM DETECTABLE CONCENTRATION (MDC) is defined, for purposes of the controls in this ODCM, as the smallest concentration of radioactive material in a sample that will yield a not count above system background and that will be detected with 95-percent probability, with only 5-percent probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochastical l separation, the MDC for a given radionuclide le determined as follows l (Reference 17):
- 3*29 E *
(10.1) g $
..C .
4 E
- V 2.22 x 108 Y*e
' The italicised terms in this definition, which are not otherwise used in this ODCM, shall have the definitions assigned to them by 10 CFR 20.2003.
E 10-3 Rev. 10, 7/95
I i Hatch ODCM l where: i MDC = the a priori MINIMUM DETECTABLE CONCENTRATION (pCi per unit mass or volume). - R. = the background counting rate, or the counting rate of a I blank sample, as appropriate (counts per minute).
- t, = the length of the sample counting period (minutes).
- t. = the length of the background counting period (minutes).
E = the counting ef ficiency (counts per disintegration) i V = the sample size (units of mass or volume). J 4 2.22 x 10' = the number of disintegrations per minute per pC1. i Y = the fractional radiochemical yield, when applicable. I 1 = the radioactive decay constant for the given radionuclide ( h-8 ) . Values of A used in effluent calculations should 1 l ' be based on decay data from a recognized and current l } ' source, such as Reference 26. 3 At = for effluent samples, the elapsed time between the i midpoint of sample collection and the time of counting l (h); for environmental samples, the elapsed time between l the end of sample collection and the time of couating j
- (h).
1 Typical values of E, V, Y, and At should be used in the calculation. It V should be recognized that the MDC is defined as an a priori (before the fact) limit representing the capability of a measurement system, and not as an a posteriori (after the fact) limit for a particular measurement. PRINCIPAL CAMMA EMITTERS for which the MINIMUM DETECTABLE The PRINCIPAL GAMMA EMITTERS CONCENTRATION (MDC) limit applies include exclusively the following radio-nuclides:
- For liquid radioactive ef fluents: Mn-54, Fe-59, Co-58, Co-60, En-65, Mo-99, Co-134, co-137, and Co-141. Co-144 shall also be measured, but with an MDC of 5 x 10d pCi/mL.
- For gaseous radioactive affluents: In noble gas releases, Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138; and in particulate releases, Mn-54, Fe-59, Co-58, co-60, En-65, Mo-99, Cs-134, co-137, Co-141, and Co-144. f
- For environmental media: The gamsa emitters specifically listed in Tabla 4-3. l
( i Rev. 10, 7/95 l 10-4 l l i
J l' Match ODCM These lists do not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above l j nuclides, shall also be analyzed and reported in the Radioactive Effluent i Release Report, the Annual Radiological Environmental Operating Report, or a j other applicable report (s). i OPERATIONAL CONDITION An OPERATIONAL CONDITION shall be any one inclusive combination of Mode Switch position and average reactor coolant temperature, as defined in { Table 1.1-1 of the Technical Specifications. ) j REACTOR MODE l The REACTOR MODE is established by the Mode Switch position. The four ! Mode Switch positions are REFUEL, SHUTDOWN, START E HOT STANDBY, and RUN.
- (See Technical Specifications Table 1.1-1 for definitions of these MODES.)
j SITE BOUNDARY
- - The SITE BOUNDARY shall be that line beyond which the land is not owned, I leased or otherwise controlled by Georgia Power Company as shown in j Figure 10-1.
i j SOURCE CHECK I l A SOURCE CHECK shall be the qualitative assessment of channel response l when the channel sensor is exposed to a source of increased radioactivity. i UNRESTRICTED AREA l' The UNRESTRICTED AREA shall be any area access to which is neither limited i nor controlled by the licensee, or any area within the SITE BOUNDARY used ' for residential quarters or for industrial, cosusercial, institutional, and/or recreational purposes. i. i i i l i i ) i ! 10-5 Rev. 10, 7/95 1 ) l r
j Hatch ODcM 1 10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATION 3 i j O The following terms are defined in the Technical specifications, section 1.1. l Because they are used throughout the Limits of Operation sections of the ODCH, i they are presented here for convenience. In the event of discrepancies between the definitions below and those in the Technical Specifications, the Technical ; l Specifications definitions shall take precedence, j i l ACTIDMA i ACTIONS shall La that part of a specification that prescribes Required l Actions to be taken under designated Conditions within specified ; ! Completion Times. I ! i J CHANNEL CALIBRATION ' A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the { channel output such that it responds within the necessary range and l accuracy to known values of the parameter that the channel monitors. The i CHANNEL CALIBRATION shall encompass the entire channel, including the l required sensor, alarm, display, and trip functions, and shall include the
- CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with
- resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable Javices in the channel. The
{' i CHANNEL CALIBRATION may be performed by means of any series of sequential, l overlapping, or total channel steps so that the entire channel is calibrated. l 1 CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, j where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels 1 measuring the same parameter. l l ! CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual f i signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip i functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be j performed by means of any series of sequential, overlapping, or total
! channel steps so that the entire channel is tested.
!O J 10-6 Rev. 10, 7/95 l i 1
Hatch ODCM DOSE EQUIVALENT I-131 I DOSE EQUIVALENT I-131 shall be that concentration of I-131
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(microcuries/ gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962,
" Calculation of Distance Factors for Power and Test Reactor Sites;" l Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977; or ICRP 30, supplement to Part 1, page 192-212, Table titled, " Committed Dose Equivalent in Target organs or Tissues per Intake of Unit Activity."
OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety , function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function (s) are also capable of performing their related support function (s). j RATED THERMAL POWER I RATED THERMAL POWER shall be a total reactor core heat transfer rate to O the reactor coolant of 2436 MWt. , l THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. 10-7 Rev. 10, 7/95
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