ML20138J335
| ML20138J335 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 12/19/1996 |
| From: | Diprofio W, Leland W, Litman R NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | |
| Shared Package | |
| ML20138H542 | List: |
| References | |
| PROC-961219, NUDOCS 9705080164 | |
| Download: ML20138J335 (385) | |
Text
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- OFFSITE DOSE CAIEULATION
- MANUAL
- 1 (ODCN) *
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O
*A DETERMINATION OF SAFETY EVALUATION APPLICABILITY:
Q Yv
- 1. Theindividualansweringthequestionsbelowshallhahohted
, 10 CFR 50.59 training.
- 2. Does this manual / manual revision:
- a. Make changes in the facility as described in h O Yes No UFSAR?
- b. Make changes in procedures as described in the UFSAR? O Yes do
- c. Involve tests or experiments not described in the O Yes Mo UFSAR?
- d. Require a change to the existing Operating License O Yes O (including the Technical Specifications) or are additional Operating License requirements needed?
- 3. If any of the above questions are answered yn, a safety evaluation per the Regulatory Compliance Manual (NARC) is required.
PREPARED BY: R. LITMAN, CHEMISTRY DEPARTMENT SUPERVISOR SUBMITTED BY: bS/-- /dhfhd W. B. LELAND, CHfMISTRY AND HEALTH PHYSICS MANAGER 'DAT5 SORC REVIEW COMPLETED DURING MEETING NUMB : kb'"//6 DATE: /c2/ fle APPROVED BY- b. o Y /9k
. A.' DIPR6Ff0,1 TATIO'N hfhECTOR DATE REVISION 16 -- EFFECTIVE: 12/19/96 O
North Atlantic Energy Service Corporation 97050B0164 970430 PDR ADOCK 05000443 R PDR ,
l l DISCIAIMER OF RESPONSIBILITY 1 1 l d 5 This document was prepared by Yankee Atomic Electric Company (" Yankee") . The use of information contained in this document by anyone other than Yankee, or the i Organization for which the document was prepared under contract, is not authorized i and, with remnact to any unauthorized use, neither Yankee nor its officers, ! directors, agents, or employees assume any obligation, responsibility, or liability ; or make any warranty or representation as to the accuracy or completeness of the ;
- material contained in this document. j i !
4 i 4 i l t- ) i . 1 i a 1 i I a i i i 1 i i 1 1 1 l i t i i i i s 1 i i i I i Page 1 of 1 ODCM Rev. 16 4
_ _ . . _ . _ . _._.____._______-__......__..___.___.__.m..._ _.._. _ 4 i ABSTRACT l The Offsite Dose Calculation Manual (ODCM) is divided into two parts: (1) the in-plant Radiological Effluent Monitoring Program requirements for liquid and gas sampling and analysis, along with the Radiological Environmental Monitoring Program requirements (Part A); and (2) approved methods to determine effluent monitor setpoint values and estimates of doses and radionuclide concentrations occurring beyond the boundaries of Seabrook Station resulting from normal Station operation (Part B). The sampling and analysis programs in Part A provide the inputs for the models of Part B in order to calculate offsite doses and radionuclide concentrations necessary to determine compliance with the dose and concentration requirements of the Station Technical Specification 3/4.11. The Radiological Environmental Monitoring Program required by Technical Specification 3/4.12 and outlined within this manual provides the means to determine that measurable concentrations of radioactive materials released as a result of the operation of Seabrook Station are . not significantly higher than expected. 1 O l 1 l l l O l Page 1 of 1 ODCM Rev. 16
1 $ i i 0FFSITE DOSE CAILU1ATION MANUAL (ODCM) i TABLE OF CONTENTS I CONTENT fAGE l l PART A: RADIDIDGICAL EFFIEENT MONITORING PROGRAMS , 1
1.0 INTRODUCTION
A.1-1 2.0 RESPONSIBILITIES FOR PART A A.2-1 3.0 LIQUID EFFLUENT SAMPLING AND ANALYSIS PROGRAM A.3-1 4.0 GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM A.4-1 5.0 RADIO 1DGICAL ENVIRONMENTAL MONITORING A.5-1 5.1 SAMPLING AND ANALYSIS PROGRAM A.5-1 5.2 IAND USE CENSUS A.5-1 PART 5: RADIOIDGICAL CAILUIATIONAL METHODS AND PARAMETERS
1.0 INTRODUCTION
B.1-1 1.1 RESPONSIBILITIES FOR PART B B.1-1 1.2
SUMMARY
OF METHODS, DOSE FACTORS, LIMITS, CONSTANTS, VARIABLES AND DEFINITIONS B.1-1 2.0 METHOD TO CALCUIATE OFF-SITE LIQUID CONCENTRATIONS B.2-1 2.1 METHOD TO DETERMINEt F " AND C'8 2 B.2-1 2.2 !sETHOD TO DETERMINE RADIONUCLIDE CONCENTRATION FOR EACH LIQUID EFFLUENT SOURCE B.2-2 2.2.1 Waste Test Tanks B.2-2 2.2.2 Turbine Building Sump B.2-3 2.2.3 Steam Generator Blowdown Flash Tank B.2-3 2.2.4 Primary Component Cooling Water (PCCW) System B.2-3 O Page 1 ODCM Rev. 16
TABLE OF CONTENTS CONTENT FAGE PART B: RADIDIDGICAL CAIEUIATIONAL METHODS AND PARAMETERS O 3.0 0FF-SITE DOSE CALCULATION METHODS B.3-1 3.1 INTRODUCTORY CONCEPTS B.3-2 3.2 METHOD TO CAlfUIATE TOTAL BODY DOSE FROM LIQUID RELEASES B.3-4 3.2.1 Method I B.3-4 3.2.2 Method II B.3-5 3.3 METHOD TO CALCUIATE MAXIMUM ORGAN DOSE FROM LIQUID RELEASES B.3 6 3.3.1 Method I B.3 6 3.3.2 Method II B.3 7 3.4 METHOD TO CALCUIATE THE TOTAL BODY DOSE RATE FROM NOBLE GASES B.3-8 3.4.1 Method I B.3-8 3.4.2 Method II B.3-10 3.5 METHOD TO CALCUIATE THE SKIN DOSE RATE FROM NOBLE GASES B.3-11 3.5.1 Method I B.3-11 j 3.5.2 Method II B.;s-14 3.6 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE RATE FROM IODINES, TRITIUM AND PARTICUIATES WITH Tu2 GREATER I THAN 8 DAYS B.3-15 3.6.1 Method I B.3-15 3.6.2 Method II B.3-18 3.7 KETHOD TO CALCULATE THE GAMMA AIR DOSE FROM NOBLE GASES B.3-19 I 3.7.1 Method I B.3 19 ; 3.7.2 Method II B.3-21 Page 2 ODCM Rev. 16 O l l
4 TABLE OF CONTENTS CONTENT FAQE : PART 5: RADIOIDGICAL CAIEUIATIONAL METHODS AND PARANETERS i 3 3.8 METHOD TO CALCULATE THE BETA AIR DOSE FROM NOBLE GASES B.3-22 3.8.1 Method I B.3-22 3.8.2 Method II B.3-24
- 3.9 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE FROM j IUDINES, TRITIUM AND PARTICUIATES B.3-25 ,
I 3.9.1 Method I B.3 25 , 3.9.2 Method II B.3-27 4 1 ] 3.10 METHOD TO CALCULATE DIRECT DOSE FROM PIANT OPERATION B.3-28 l ) 3.10.1 Method B.3-28 i
; 3.11 DOSE PROJECTIONS B.3-29 iO 1 3.11.1 Liquid Dose Projections B.3-29 l 3 3.11.2 Gaseous Dose Projections B.3-29 i
4.0 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM B.4-1 5.0 SETPOINT DETERMINATIONS B.5-1 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS B.5-1 l 1
- 5.1.1 Liquid Waste Test Tank Monitor (RM-6509) B.5-1
- 5.1.2 Turbine Building Drains Liquid Effluent Monitor (RM-6521) B.5-4 5.1.3 Steam Generator Blowdown Liquid Sample Monitor (RM-6519) B.5-5 5.1.4 PCCW Head Tank Rate-of-Change Alarm Setpoint B.5-5 5.1.5 PCCW Radiation Monitor B.5-6 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS B.5-7 i 5.2.1 Plant Vent Wide-Range Gas Monitors (RM-6528-1, 2 and 3) B.5-7 Page 3 ODCM Rev. 16 l
TABLE OF CONTENTS 1 CONTENT E691 ! PART B: RADIOIDGICAL CAIIDIATIONAL METHODS AND PARAMETERS O\ 5.2 GADEOUS EFFLUENT INSTRUMENTATION SETPOINTS 5.2.2 Waste Gas System Monitors (RM-6504 and RM-6503) B.5-10 5.2 3 Main Condenser Air Evacuation Monitor (RM-6505) B.5-10 6.0 LIQUID NID GASEOUS EFFLUENT STREAMS, RADIATION MONITORS AND RADWAST% TREATMENT SYSTEMS B.6-1 7.0 BASES FOR DOSE CALCUIATION METHODS B.7-1 7.1 LIQUID RELEASE DOSE CALCUIATIONS B.7-1 7.1.1 Dose to the Total Body B.7-4 7.1.2 Dose to the Critical Organ B.7-4 7.2 GASEOUS RELEASE DOSE CALCULATIONS B.7-7 7.2.1 Total Body Dose Rate From Noble Cases B.7-7 7.2.2 Skin Dose Rate From Noble Gases B.7 9 7 2.3 Critical Organ Dose Rate From Iodines, Tritium and Particulates With Half-Lives Greater Than Eight Days B.7-12 7.2.4 Gamma Dose to Air From Noble Cases B.7-14 7.2.5 Beta Dose to Air From Noble Cases B.7-16 7.2.6 Dose to Critical Organ From Iodines, Tritium and Particulates With Half-Lives Greater Than Eight Days B.7-18 7.2.7 Special Receptor Gaseous Release Dose Calculations B.7-20 7.3 RECEPTCE POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHWAYS B.7-34 7.3.1 Receptor Locations B.7-34 7.3.2 Seabrook Station Atmospheric Dispersion Model B.7-35 7.3.3 Average Atmospheric Dispersion Factors for Receptors B.7-35 8.0 BASES FOR LIQUID AND GASEOUS MONITOR SETPOINTS B.8-1 Page 4 ODCM Rev. 16 O
l l TABLE OF CONTENTS CONTENT Fffd Q) PART B: RADIOIDGICAL CAlfDIATIONAL METHODS AND PARAMETERS 8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT B.8-1 8.2 BASIS FOR THE PLANT VENT WIDE RANGE CAS MONITOR SETPOINTS B.8-5 8.3 BASIS FOR PCCW HEAD TANK RATE-OF-CRANGE AIARM SETPOINT B.8-10 l j 8.4 BASIS FOR WASTE GAS PROCESSING SYSTEM MONITORS (RM-6504 AND RM-6503) B.8-11 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT l (RM-6505) B.8-14 ! Il I 1 j 8.5.1 Example for the Air Evacuation Monitor Setpoint During j 3 Normal Operations B.8 14 8.5.2 Example for the Air Evacuation Monitor Setpoint During i Start Up (Hogging Mode) B.8-16 REFERENCES R-1 APPENDIX A: METHOD I DOSE CONVERSION FACTORS A-1 i a APPENDIX B: CONCENTRATIONS IN AIR AND WATER ABOVE NATUPJJ. BACKGROUND B-1 TAKEN FROM 10 CFR 20.1 20.602, APPENDIX B a APPENDIX C: EMS SOFTWARE DOCUMENTATION C-1 i APPENDIX X: CANCELLED APPENDIX Y: CANCELLED O Page 5 ODCM Rev. 16
l TABLE OF CONTENTS s l NUMBER LIST OF TABIES AND FIGURES FAEE PART A TABI25 A.3 1 Radioactive Liquid Waste Sampling and Analysis Program A.3-2 A.4-1 Radioactive Caseous Waste Sampling and Analysis Program A.4-2 j A.5-1 Radiological Environmental Monitoring Program A.5-3 A.5-2 Detection Capabilities for Environmental Sample Analysis A.5-7 A.5-3 Reporting Levels for Radioactivity Concentration in Environmental Samples A.5-10 PART B TAB 12S B,1-1 Suannary of Radiological Effluent Technical Specifications l and Imples=nting Equations B.1 3 ! 1 B.1-2 Summary of Method I Equations to Calculate Unrestricted B.1-6 Q Area Liquid Concentrations B.1-3 Summary of Method I Equations to Calculate Off-Site Doses from Liquid Releases B.1-7 B.1-4 Summary of Method I Equations to Calculate Dose Rates B.1-8 B.1-5 Summary of Method I Equations to Calculate Doses to Air from Noble Cases B.1-11 B.1-6 Summary of Method I Equations to Calculate Dose to an Individual from Tritium, Iodine and Particulates B.1 13 B.1-7 Summary of Methods for Serpoint Determinations B.1-14 B.1-8 Summary of Variables B.1-15 B.1-9 Definition of Terms B.1-22 O Page 6 ODCM Rev. 16 l I
TABLE OF CONTENTS i NUMBER LIST OF TABIE.S AND FIGURES FAgg FART B TAB 12S (Continued) B.1-10 Dose Factors Specific for Seabrook Station for Noble Gas Releases B.1-23 B.1-11 Dose Factors Specific for Seabrook Station for Liquid Releases B.1-24 B.1-12 Dose and Dose Rate Factors Specific for Seabrook Station ^ for Iodines, Tritium and Particulate Releases B.1-25 B.1-13 Combined Skin Dose Factors Specific for Seabrook Station ; Special Receptors for Noble Gas Release B.1-26 l B.1-14 Dose and Dose Rate Factors Specific for the Science and Nature Center for Iodine, Tritium, and Particulate Releases B.1-27 l B.1-15 Dose and Dose Rate Factors Specific for the " Rocks' for Iodine, Tritium, and Particulate Releases B.1-28 4 B.4-1 Radiological Environmental Monitoring Stations B.4-2 B.7-6 l B.7-1 Usage Factors for Various Liquid Pathways at Seabrook Station B.7-2 Environmental Parameters for Gaseous Effluents at Seabrook Station B.7-31 B.7-3 Usage Factors for Various Gaseous Pathways at Seabrook Station B.7-33 B.7 4 Seabrook Station Long-Term Average Dispersion Factors Primary Vent Stack B.7-38 B.7-5 Seabrook Station Long-Term Average Dispersion Factors for Special (On-Site) Receptors Primary Vent Stack B.7-39 i Page 7 ODCM Rev. 16 O
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TABLE OF CONTENTS l O. NUMBER LIST OF TABIE.S AND FIGURES E6gg l PART 5 TABIE.S (Continued) l l B.7-6 Seabrook Station Long-Tern Atmospheric Diffusion and Deposition Factors Ground-Level Release Pachway B.7-40 PART 5 FIGURES B.4-1 Radiological Environmental Monitoring Locations Within 4 kilometers of Seabrook Station B.4-5 B.4-2 Radiological Environmental Monitoring Locations Between 4 kilometers and 12 kilometers from Seabrook Station B.4 6 B.4-3 Radiological Environmental Monitoring Locations Outside 12 kilometers of Seabrook Station B.4-7 B.4-4 Direct Radiation Monitoring Locations Within 4 kilometers of Seabrook Station B.4-8 B.4-5 Direct Radiation Monitoring Locations Between 4 kilometers and 12 kilometers from Seabrook Station B.4 9 B.4-6 Direct Radiation Monitoring Locations outside 12 kilometers of Seabrook Station B.4-10 B.6-1 Liquid Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station B.6 2 B.6-2 Caseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station B.6-3 Page 8 ODCM Rev. 16 i l l
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1 LIST OF EFFECTIVE PACES M E E E E E 4 Cover 16 B.1-16 16 B.4-4 16 B.1-17 16 B.4-5 16 , Abstract 16 B.1-18 16 B.4-6 16 ! B.1-19 16 B.4-7 16 l l TOC 1 - 8 16 B.1-20 16 B.4-8 16 i B.1-21 16 B.4-9 16 ; ,j LOEP 1 & 2 16 B.1-22 16 B.4-10 16 I B.1-23 16 l i A.1-1 16 B.1-24 16 B.5-1 16 l 3 B.1-25 16 B.5-2 16 } A.2-1 16 B.1-26 16 B.5-3 16 B.1-27 16 B.5-4 16 j A.3-1 16 B.1-28 16 B.5-5 16 4 A.3-2 16 B.5-6 16 ! A.3-3 16 B.2-1 16 B.5-7 16 j A.3-4 16 B.2-2 16 B.5-8 16
< A.3-5 16 B.2-3 16 B.5-9 16 j A.3-6 16 B.5-10 16 A.3-7 16 B.3-1 16 B.5-11 16 B.3-2 16
- ' A.4-1 16 B.3-3 16 B.6-1 16 A.4-2 16 B.3 4 16 B.6-2 16
! A.4-3 16 B.3-5 16 B.6-3 16 A 4-4 16 B.3-6 16 I A.4-5 16 B.3 7 16 B 7-1 16 B.3 8 16 B.7-2 16 j A.5-1 16 B.3-9 16 B.7-3 16 A.5-2 16 B.3-10 16 B.7-4 16 j A.5-3 16 B.3-11 16 B.7-5 16 l A.5-4 16 B.3-12 16 B.7-6 16 A.5-5 16 B.3-13 16 B.7-7 16 y! B.3-14 B.7-8 16 A.5-6 16 16 l A.5-7 16 B.3-15 16 B.7-9 16 A.5-8 16 B.3-16 16 B.7-10 16 A.5-9 16 B.3-17 16 B.7-11 16 l j A.5-10 16 B.3-18 16 B.7-12 16 l B.3-19 16 B.7-13 16 B.1-0 16 B.3-20 16 B.7-14 16 B.1-1 16 B.3-21 16 B.7-15 16 3 B.1-2 16 B.3-22 16 B.7-16 16 B.1-3 16 B.3-23 16 B.7-17 16 i B.1-4 16 B.3-24 16 B.7-18 16 j B.1-5 16 B.3-25 16 B.7-19 16 B.1-6 16 B.3-26 16 B.7-20 16 i B.1-7 16 B.3-27 16 B.7-21 16
- B.1-8 16 B.3-28 16 B.7-22 16 1
B.1-9 16 B.3-29 16 B.7-23 16 B.1-10 16 B.3 30 16 B.7-24 16 B.1-11 16 B.3-31 16 B.7-25 16
) B.1-12 16 B.7 26 16 B.1-13 16 B.4-1 16 B.7-27 16 B.1-14 16 B.4-2 16 B.7-28 16 . B.1-15 16 B.4-3 16 B.7-29 16 Page 1 ODCM Rev. 16 i
i LIST OF EFFECTIVE PAGES EAGI BJil. IAGE REL. EMiE BIBL. B.7-30 16 B-1 16 B.7-31 16 B-2 16 B.7-32 16 B-3 16 B.7-33 16 B-4 16 B.7-34 16 B-5 16 B.7-35 16 E-6 16 B.7-36 16 B-7 16 B.7-37 16 B-8 16 B 7-38 16 B-9 16 B.7-39 16 B-10 16 B.7-40 16 B-11 16 B.8 1 16 C-1 16 B.8-2 16 C-2 16 i B.8-3 16 C-3 16 l B.8-4 16 C-4 16 l B.8-5 16 C-5 16 B.8-6 16 C6 16 B.8-7 16 B.8-8 16 i B.8-9 16 B.8-10 16 B.8 11 16 B.8-12 16 B.8-13 16 B.8-14 16 B.8-15 16 B.8 16 16 i B.8-17 16 B.8-18 16 B.8-19 16 R-1 16 A-1 16 A-2 16 A-3 16 A-4 16 A-5 16 A-6 16 A-7 16 A-8 16 A-9 16 A-10 16 A-11 16 A-12 16 A-13 16 A-14 16 A-15 16 A-16 16 A-17 16 A-18 16 A-19 16 Page 2 ODCM Rev. 16
PART A RAMOLDGICAL EFFIlJulT MONITORING PROGRAMS ; ( O
1.0 INTRODUCTION
The purpose of Part A of the ODCM (Off-Site Dose Calculation Manual) is to ; describe the sangling and analysis programs conducted by the Station, which provide 1 input to the models in Part B for calculating liquid and gaseous effluent concentrations, monitor setpoints, and off-site doses. The results of Part B calculations are used to determine compliance with the concentration and dose requirements of Technical Specification 3/4.11. The Radiological Environmental Monitoring Program required as a minimum to bs conducted (per Technical Specification 3/4.12) is described in Part A, with the identification of current locations of sampling stations being utilized to meet the l program requirements listed in Part B. The information obtained from the conduct of the Radiological Environmental Monitoring Program provides data on measurable levels of radiation and radioactive materials in the environment necessary to evaluate the i relationship between quantities of radioactive materials released in effluents and resultant radiation doses to individuals from principal pathways of exposure. The data developed in the surveillance and monitoring programs described in Part A to I the ODCM provide a means to confirm that measurable concentrations of radioactive materials released as a result of Seabrook Station operations are not significantly higher than expected based on the dose models in Part B. i l i l l O l A.1-1 ODCM Rev. 16
, 2.0 RESPONSIBILITIES FOR PART A 1
- All changes to Part A of the ODCM shall be reviewed and approved by the l Station Operation Review Committee (SORC) and the Nuclear Regulatory Commission ;
l prior to implementation. l It shall be the responsibility of the Station Director to ensure that the ODCM { 4 is used in the perfonssace of the surveillance requirements and administrative i controls of the appropriate portions of the Technical Specifications. I i t I i 3 4 i h 4 4 4 1 1 t i 4 1 y l 3 i. I 1 i ! 4 4 4 4 l e i A.2-1 ODCM Rev. 16 I
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u j 3.0 LIOUID EFTLUENT SAMPLING AND ANALYSIS PROGRAM i Radioactive liquid wastes shall be sampled and analyzed in accordance with the program specified in Table A.3-1 for Seabrook Unit 1. The results of the 'O radioactive analysis shall be used as appropriate with the methodolo5y of Part B of the ODCM to assure that the concentrations of liquid effluents at the point of } release from the multiport diffuser of the circulating Water System are maintained ' within the limits of Technical Specification 3.11.1.1 for Unit 1. ! Radioactive affluent information for liquids obtained from this sampling and i analysis program shall also be used in conjunction with the methodologies in Part B
- to demonstrate compliance with the dose objectives and surveillance requirements of j Technical Specifications 3/4.11.1.2, 3/4.11.1.3, and 3/4.11.4.
i 1 O
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O ! A.3-1 ODCM Rev. 16 j
TABil A. 3-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD) (1) l l Liquid Release Type Frequency Frequency Analysis (uci/ml) A. Liquid Principal Gamma Radwaste Test p p Emitters (3) 5x10-7 Tanks Each Batch Each Batch I-131 1x10-8 (Batch Release)(2) Dissolved and P lx10-5 M Entrained Cases One Batch /M (Gamma Emitters) p gt43 H-3 1x10-5 Each Batch Composite Gross Alpha lx10-7 Sr-89, Sr-90 5x10-s p qts: Each Batch Composite Fe-55 1x10-s B. Turbine Principal Gamma 5x10., W Em' ters;3g Building Sump g - Effluent (8) Grab Sample I-i 1x10-s (Continuous Dissolved and Release)(3) M Entrained Gases 1x10-5 Grab Sample (Gamma Emieters) , A.3-2 ODCM Rev. 16 O O O
O O O TABLE A.3-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM ~ (Continued) Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD) (1) Liquid Release Type Frequency Frequency Analysis (uci/ml) H-3 1x10-3 B. (Continued) y M Grab Sample Gross Alpha 1x10-7 g Sr-89, Sr-90 5x10-a l Grab Sample Q (9) 1X10-s Fe-55 C. Steam Generator Principal Camma 5x10-7 ! Blowdown Flash W g Emitters (33 Tanktsus Grab Sample I-131 lx10-s t (Continuous Dissolved and Release)(3) M Entrained Cases lx10-3 Gr b Sample (Camma Emitters) I g H-3 lx10-3 M Grab Sample Cross Alpha 1x10-7
~.
Sr-89, Sr-90 5x10-e g l Grab Sample Q(9) Fe-55 1x10-s l l A.3-3 ODCM Rev. 16
TABLE A.3-1 RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued) Lower Limit Minimum of Detection Sampling Analysis Type of Activity (LLD) (1) Liquid Release Type Frequency Frequency Analysis (uci/al) D. Service Principal Gamma 5x10-7 Water (73 W g Emitters (33 Grab Sample I-131 1x10-8 Dissolved and M Entrained Cases 1x10-3 C ab le (Gamma Emitters) y H-3 1x10-5 M Grab Sample Gross Alpha 1x10-7 g Sr-89, Sr-90 5x10-8 Q Grab Sample Fe-55 1x10-s P - Prior to Discharge W - Weekly M - Monthly Q - Quarterly A.3-4 ODCM Rev. 16 O O e - -
TABLE A.3-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued) Notations m The 122 is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system backgrot nd, 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 radiochemical separation: LLD - 4.66 s3 E x V x 2.22 x 10' x Y x exp (-AAt) Where: LLO - the "a priori" lower limit of detection (microcurie per unit mass or volume), sb - the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), O E - the counting efficient y (counts per disintegration), O V - the sample size (units of mass or volume), 2.22 x los - the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A - the radioactive decay constant for the particular radionuclide (s*1) , and at - the elapsed time between the midpoint of sample collection and the time of counting (s). Typical values of E, V, Y, and at should be used in the calculation. It should be recognized that the LLD is defined as an A priori (before the fact) limit representing the capability of a measurement system and not as an A nosteriori (after the fact) limit for a particular measurement. m A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling. O A.3-5 ODCM Rev. 16
i TABLE A.3-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANA1YSIS PROCRAM (Continued) Hatations (Continued) 9il D) The principal gamma emitters for which the LLD specification applies include l the following radionuclides: Kn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these l nuclides are to be considered. Other gamma peaks that are identifiable, ' together with those of the above nuclides, shall also be analyzed and reported , l in the Annual Radioactive Effluent Release Report in accordance with Technical l Specification 6.8.1.4. Isotopes which are not detected should be reported as l "not detected." Values determined to be below detectable levels are not u ed ; in dose calculations. (') A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. U) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.
") Sampling and analysis is only required when Steam Generator Blowdown is directed to the discharge transition structure.
(7) Principal gamma emitters shall be analfzed weekly in Service Water. Sample and analysis requirements for dissolved and entrained gases, tritium, gross alpha, strontium 89 and 90, and Iron 55 shall only be required when analysis for principal gamma emitters exceeds the LLD. The following are additional sampling and analysis requirements:
- a. PCCW sampled and analyzed weekly for principal gamma emitters,
- b. Sample Service Water System (SUS) daily for principal gamma emitters whenever primary component cooling water (PC'N) activity exceeds lx10-3 uC/cc.
- c. With the PCCW System radiation monitor inoperable, sample PCCW and SWS daily for principal gamma emitters.
- d. With a confirmed PCCW/SWS leak and PCCW activity in excess of 1x10-'
uC/ce, sample SUS every 12 hours for principal gamma emitters.
- e. The setpoint on the PCCW head tank liquid rate-of-change alarm will be set to ensure that its sensitivity to detect a PCCW/SWS leak is equal to or greater than that of an SWS radiation monitor, located in the unit's combined SWS discharge, with an LLD of 1x10-s uC/cc. If this sensitivity cannot be achieved, the SUS will be sampled once every 12 hours.
(e) If the Turbine Building Sump (Steam Generator Blowdown Flash Tank) isolate due to high concentration of radioactivity, that liquid stream will be sampled and analyzed for Iodine-131 and principal gamma emitters prior to release. A.3 6 ODCM Rev. 16
TABLE A.3-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued) Notations (Continued) (8) Quarterly composite analysis requirements shall only be required when analysis for principal gamma emitters indicate positive radioactivity. l l l A.3-7 ODCM Rev. 16 i
4.0 GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM Radioactive gaseous wastes shall be sampled and analyzeil in accordance with O the program specified in Table A.4-1 for Seabrook Unit 1. T'a results of the radioactive analyses shall be used as appropriate with the methodologies of Part B of the ODCM to assure that the dose rates due to radioactive materials released in i gaseous effluents from the site to areas at and beyond the site boundary are within ' i the limits of Technical Specification 3.11.2.1 for Unit 1. l
- I I
Radioactive effluent information for gaseous wastes obtained from this
- sampling and analysis program shall also be used in conjunction with the l l methodologies in Part B to demonstrate compliance with the dose objectives and !
surveillance requirements of Technical Specifications 3/4.11.2.2, 3/4.11.2.3, 1
- 3/4.11.2.4, and 3/4.11.4.
i 1 l 1 O lU i k i i i 4 i f
\
i A.4 1 ODCM Rev. 16 4
TABLE A.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Activity Detection (ll Gaseous Release Type Frequency Frequency Analysis (LLD) (uci/cc)
- 1. Plant Vent Principal Gamma 1x10..
M(3)(4) g Emitterst2) Grab Sample H-3 lx10-8 Continuous (58
- Charcoal Sample W(53 Principal Gamma Continuous (5) Particulate Emitterst2) lx10-11 Sample M Gross Alpha Continuous (5) lx10-11 p g ,
Sample Q Sr-89, Sr-90 Continuous (5) lx10-11 p , Sample
- 2. Condenser Air Principal Gamma 1x10-4 Removal Exhaust gt?) cy3 Emitters Grab Sample H-3 lx10-s A.4-2 ODCM Rev. 16 O O O
O O O TABLE A.4-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROCRAM (Continued) Minimum Iower Limit of Sampling Analysis Type of Activity Detection") Gaseous Release Type Frequency Frequency Analysis (LLD) (uC1/cc)
- 3. Cland Steam W Principal Gamma Packing Exhauster Continuous Particulate Emitterstz) 1x10-11 Sample Continuous 1x10-12 Ga a Sa le M Gross Alpha ,
1x10~11 Continuous p Sample Q Sr-89, Sr-90
*
- lx O'11 Continuous p y te l
Sampla ts
- 4. Containment Purge pts Principal Gamma 1x10
Each Purge Grab Each Purge Sample H-3 (oxide) 1x10-8 [ A.4-3 ODCM Rev. 16
TABLE A.4-1 RADIOACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Continued) Notations O m The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, 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 radiochemical separation: 4.66 s 3 E x V x 2.22 x 10' x Y x exp (-Aat) Where: I LLD - the "a priori" lower limit of detection (microcurie per unit i mass or volume), sb - the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E - the counting efficiency (counts per disintegration), V - the sample size (units of mass or volume), l 2.22 x los - the number of disintegrations per minute per microcurie, Y - the fractional radiochemical yield, when applicable, A - the radioactive decay constant for the particular radionuclide (s4), and At - the elapsed time between the midpoint of sample collection and the time of counting (s). Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LID is defined as an A oriori (before the fact) limit representing the capability of a measurement system and not as an A nosteriori (after the fact) limit for a particular measurement. O A.4-4 ODCM Rev. 16
J l TABLE A 4-1
- RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS. PROGRAM (Continued) i" Notations (Continued) t (2) The principal gamma emitters for which the LLD specification applies include the following radionuclides
- Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and l Xe-138 in noble gas releases and Mn-54, Fe-59, co-58, C2-60 Zn-65, Mo-99, i 1-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases.
- This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides,
; l shall also be analyzed and reported in the annual Radioactive Effluent Release i Report in accordance with Technical Specification 6.8.1.4. Isotopes which are 4 not detected should be reported as "not detected." Values determined to be below detectable levels are not used in dose calculations. ,
l (8) Sampling and analysis shall also be performed following shutdown, startup, or ;
- a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a >
l one hour period unless; 1) analysis shows that the DOSE EQUIVALENT I-131 j concentrations in the primary coolant has not increased more than a factor of
- 3; 2) the noble gas activity monitor for the plant vent has not increased by
! more than a factor of 3. For containment purge, requirements apply only when purge is in operation.
I
") Tritium grab samples shall be taken at least once per 24 hours when the ^
! refueling canal is flooded. (5) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made
- in accordance with Technical Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3. j
{ (s) Samples shall be changed at least once per seven (7) days and analyses shall ;
- be completed within 48 hours after changing, or after removal from sampler. '
, Sampling shall also be performed at least once per 24 hours for at least seven i (7) days following each shutdown, startup, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one-hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This ! requirement does not apply if 1) analysis shows that the DOSE EQUIVALENT I-131 i concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not l l increased more than a factor of 3. ,
") Samples shall be taken prior to start-up of condenser air removal system when j there have been indications of a primary to secondary leak. L
<s) Quarterly composite analysis requirements shall only be required when analysis l for principal gamma emitters indicate positive radioactivity.
i
?
!O
- A.4-5 ODCM Rev. 16 1
- ~ . - - - . . _ - - - . __ - - . - _ -
5.0 RADIOIDGICAL ENVIRONMENTAL MONITORING 5.1 SAMPLING AND ANALYSIS PROGRAM The Radiological Environmental Monitoring Program (REMP) provides representative measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of members of the public resulting from station operation. This monitoring program is required by Technical Specification 3.12.1. The monitoring program implements Section IV.B.2 of Appendix I to 10CFR, Part 50, and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of effluent measurements and the modeling of the environmental exposure pathways which have been incorporated into Part B of the ODCM. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience. In accordance with Technical Specification surveillance requirements, 4.12.1, sampling and analyses shall be conducted as specified in Table A.5-1 for locations shown in Section 4 of Part B to the ODCM. Detection capability requirements, and reporting levels for radioactivity concentrations in environmental samples are shown on Tables A.5-2 and A.5-3, respectively. It should be noted that Technical Specification 3.12.1.C reqaires that if milk or fresh leafy vegetable samples are unavailable from one or more sample locations required by the REMP, new specific locations for obtaining replacement samples (if available) shall be added to the REMP within 30 days, and the specific locations from which the samples are unavailable may then be deleted from the monitoring O program. In this context, the term unavailable means that samples are no longer available to be collected now or in the future for reasons such as the permission from the owner to collect the samples has been withdrawn or he has gone out of business, thus causing the permanent loss of the sample location. 5.2 LAND USE CENSUS As part of the Radiological Environmental Monitoring Program, Technical Specification 3/4.12.2 requires that a land use census be conducted annually during growing season to identify within a distance of 8 km the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50 m8 producing broad leaf vegetation. The land use census ensures that changes in the use of area beyond the site boundary are identified, and appropriate modifications to the monitoring program and dose assessment models are made, if necessary. This census satisfies the requirements of Section IV.3.3 of Appendix I to 10CFR Part 50. For the purpose of conducting the land use census as required by Technical Specification 4.12.2, station personnel should determine what survey methods will provide the necessary results considering the type of information to be collected and the use to which it will be put, such as the location of potential milk animal pathway for use in routine dose calculations. Land use census results shall be obtained by using a survey method, or combination of methods, which may include, but are not limited to, door-to-door surveys (i.e., roadside identification of A locations), aerial surveys, or by consulting local agricultural authorities. A.5-1 ODCM Rev. 16
1 l l 5.2 LAND USE CENSUS (Ccntinusd) l Technical Specification 3.12.2.b requires that new locations identified from l the census that yield a calculated dose of dose commitment 20 percent greater than ct a location from which samples are currently being obtained be added within 30 days to the REMP. These new locations required to be added to the sampling program thall only be those from which permission from the owner to collect samples can be obtained and sufficient sample volume is available. l l l l l l i l O O A.5-2 ODCM Rev. 16
m Cs% Om U TABLE A.5-1 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Number of Representative Samples Sampling and Type and Frequency of Sample and Sample Locations
- Collection Frequency Analysis
- 1. DIRECT RADIATIONb 40 routine monitoring stations with Quarterly. Gamma dose quarterly, s .tse or more dosimeters placed as follows:
An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; An outer ring of statiens, one in each meteorological sect.or, Senerally in the 6 to 0-km range from the site; The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and control locations.
- 2. AIRBORNE Radiolodine ard Samples from five locationsd : Continuous sampler Radioiodine Canister:
Particulates operation with Three samples from close to the sample collection I-131 analysis weekly. three SITE BOUNDARY locations, in weekly, or more different sectors, of high frequently if Particulate Sampler: calculated long-term aversge required by dust ground-level D/Q. loading. Gross beta radioactivity analysis following filter One sample from the vicinity of a change'; community having the highest Gamma isotopic analysis" calculated long-term average of composite (by ground-level D/Q. location) quarterly. A.5-3 ODCM Rev. 16
TABLE A.5-1 RADEOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) Exposure Pathway and/or Number of Representstive Samples Sampling and Type and Frequency of Sample and Sample Locations
- Collection Frequency Analysis
- 2. (Continued) One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.
- 3. WATERBORNE
- a. Surface One sample in the discharge area. Monthly grab sample. Gamma isotopic analysis
- One sample from a control location. monthly. Composite for tritium analysis quarterly.
- b. Sediment from One sample from area with existing Semiannually. Gamma isotopic analysis' shorelinc or potential recreational value. ramiannually.
- 4. INGESTION
- a. Milk Samples from milking animals in Semimonthly when Gamma isotopic
- and I-131 three locations within 5 km milking animals are analysis on ecch sample.
distance having the highest dose on pasture, monthly potential. If there are none, at other times. then, one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 arem per yr.' One sample from milking animals at a control location, as for example, 15-30 km distant and in the least prevalent wind direction. A.5-4 ODCM Rev. 16 O O O
O O O TABLE A.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) Exposure Pathway and/or Number of Representative Samples Sampling and Type and Frequency of Sample and Sample Locations
- Collection Frequency Analysis
- 4. (Continued) ' One sample of each of three Sample in season, or Gamma isotopic analysis *
~
commercially and recreationally semiannually if they on edible portions.
- b. Fish and important species in vicinity of are not seasonal.
Invertebrates plcnt discharge area. One sample of similar species in areas not influenced by plant discharge.
- c. Food Products Samples of three (if practical) Monthly, when Gamma isotopic
- and I-131 different kinds of broad leaf available, analysis, vegetation 8 grown nearest each of two different off-site locations of highest predicted long-term average ground-level D/Q if milk sampling is not performed.
One sample of each of the similar Monthly, when Gamma isotopic" and I-131 broad leaf vegetations grown at a available. analysis. control location, as for example 15-30 km distant in the least prevalent wind direction, if milk sampling is not performed. t A.5-5 ODCM Rev. 16
TABLE A.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Continued) Table Notation
- a. Specific parameters of distance and direction sector from the centerline of the Unit I reactor, and additional description where pertinent, shall be provided for each and every sample location in Table B.4-1 in the ODCM, Part B. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location (s), if available, for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
- b. A thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
- c. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
- d. Optimal air sampling locations are based not only on D/Q but on factors such as population in the area, year-round access to the site, and availability of power.
- e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility,
- f. The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM, Part B.
- g. If broad leaf vegetation is unavailable, other vegetation will be sampled.
A.5-6 ODCM Rev. 16 O O O
O O O TABLE A.5-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS =.t.s Lower Limit of Detection (LLD)b Fish and WatetN !'"9 Airborne Particulate Invertebrates Milk Food Products Sediment Analysis (pC1/htg) or Cas (pCi/m )3 (pC1/kg wet) (pC1/kg) (pCi/kg, wet) (pC1/kg dry) Gross Beta 4 0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15* I-131 15 0.07 1 60* Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15* * ' 15* d A.5-7 ODCM Rev. 16
TABLE A.5-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS **f'8 (Continued) Table Notation
- c. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report,
- b. The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation: g, 4.66 s3 E V 2.22 Y exp (-Aat) Where: LLD is the "a priori" lower limit of detection as defined above, as picoeuries per unit mass or volume; 4.66 is a constant derived from the K.ig, and K 3,s values for the 95% confidence level; s3 is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute; E is the counting efficiency, as counts per disintegration; V is the sample size in units of mass or volume; 2.22 is the number of disintegrations per minute per picoeurie; Y is the fractional radiochemical ' eld, when applicable; A is the radioactive decay constant for the particular radionuclide as per second; and at for environmental samples is the elapsed time between sample collection and time of counting, as seconds. Typical values of E, V, Y, and At should be used in the calculation. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., Potassium-40 in milk samples). O A.5-8 ODCM Rev. 16
_ . . _ _ . _ _ . . _ _ _ _ _ _ _ . . . _ _ _. .. _ ___ _ . ~ . . _ . _ _ _ . _ _ _ _ . _ _ _ _ - _ _ . _ . _ - t 1
- TABLE A.5-2
' DETECTION CAPABILITIES FOR ENVTRONMENTAL SAMPLE ANALYSISe,f.s (Continued) ! Table Notation $ (Continued) ! It should be recognized that the LLD is defined as an a criori (before the fact) limit representing the capability of a measurement system and not as an A nosteriori (after the fact) limit for a particular measurement. This does 4 not preclude the calculation of an a nosteriori LLD for a particular
- measurement based upon the actual parameters for the sample in question and I
appropriate decay correction parameters such as decay while sampling and l during analysis. Analyses shall be performed in such a manner that the stated j LLDs will be achieved under routine conditions. Occasionally background 1 fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and l described in the Annual Radiological Environmental Operating Report, i
- c. Parent only,
- d. The Ba-140 LLD and concentration can be determined by the analysis of its short-lived daughter product u-140 subsequent to an eight-day period followin5 collection. The calculation shall be predicated on the normal ingrowth equations for a parent-daughter situation and the assumption that any unsupported La-140 in the sample would have decayed to an insignificant amount (at least 3.6% of its original value). The ingrowth equations will assume that the supported La-140 activity at the time of collection is zero.
l
- e. Broad leaf vegetation only.
- f. If the measured concentration minus the three standard deviation uncertainty j is found to exceed the specified LLD, the sample does not have to be analyzed l to meet the specified LLD.
- g. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance .with recommendations of Regulatory Guide 4.13, Revision 1, July 1977. l a
l l i i 1 I A.5-9 ODCM Rev. 16 j
TABLE A.5-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Fish and Water Airborne Particulate or Invertebrates Milk Food Prouucts Analysis (pci/kg) Gas (pCi/kg, wet) (pC1/kg, wet) (pCi/kg) (pCi/kg, wet) H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58, 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400* I-131 100 0.9 3 100** Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200* 300*
- Parent only.
- Broad leaf vegetation only.
A.5-10 ODCM Rev. 16 O O e_ - -
t i l i [ } i ? !G i 4 4 i a i c , a : l 1 t I i SEABROOK STATION vDCN l ! l PMT B 4 t t i I RADIOIDGICAL CALCUIATIONAL METHODS AND PARAMETERS i 4 i l O q ., B.1-0 ODCM Rev. 16
- - - - - - . _ - - - -----.---- ---_-~_- .--
i
-i
1.0 INTRODUCTION
j l Part B of the ODCM (Off-Site Dose Calculat.sn Manual) provides formal and i approved methods for the calculation of off-site concentration, off-site doses and effluent monitor setpoints, and indicates the locations of environmental monitoring stations in order to comply with the Seabrook Station Radiological Effluent , Technical Specifications (RETS), Sections 3/4.3.3.9, 3/4.3.3.10, and 3/4.11, as well , as the REMP detailed in Part A of the manual. The ODCK forms the basis for station j procedures which document the off-site doses due to station operation which are used j to show compliance with the numerical guides for design objectives of Section II of i Appendix I to 10CPR Part 50. The methods contained herein follow accepted NRC ! guidance, unless otherwise noted in the text. l l 1.l' RESPONSIBILITIES POR PART B l All changes to Part B of the ODCM shall be reviewed and approved by the i
. Station Operation Review Committee (SORC) in accordance with Technical Specification l 6.13 prior to implementation. Changes made to Part B shall be submitted to the i l
Commission for their information in the Annual Radioactive Effluent Release Report l for the period in which the change (s) was made effective. ! l It shall be the responsibility of the Station Director to ensure that the ODCM l is used in the performance of in-plant surveillance requirements and administrative l l controls of the appropriate portions of the Technical Specifications, and Effluent { Control Program detailed in Part A of the manual. The Executive Director of Nuclear ' Production shall be responsible to ensure that the Radiological Environmental Monitoring Program described in Section 4 of Part B is implemented in accordance I with Technical Specification 3/4.12 and Part A of this manual. In addition to off-site dose calculations for the demonstration of compliance with Technical Specification dose limits at and beyond the site boundary, 10CFR20.1302 requires that compliance with the dose limits for individual members of the public (100 mres/yr total effective dose equivalent) be demonstrated in controlled areas on site. Demonstration of compliance with the dose limits to members of the public in controlled areas is implemented per Health Physics Department Procedures, and is outside the scope of the ODCK. However, calculations performed in accordance with the ODCK can be used as one indicator of the need to perform an assessment of exposure to members of the public within the site boundary. Since external direct exposure pathways are already subject to routine exposure rate surveys and measurements, only the inhalation pathway need be assessed. The accumulated critical organ dose at the site boundary, as calculated per ODCM Sections 3.9 and 3.11, can be used as an indicator of when additional assessments of on-site exposure to members of the public is advisable (see Section 3.11.2). Off-site critical organ dos,es from station effluents should not, however, be the only indicator of potential on-site doses. 1.2
SUMMARY
OF METHODS, DOSE FACTORS, LIMITS, CONSTANTS, VARIABLES AND DEFINITIONS This section summarizes the Method I dose equations which are used as the primary means of demonstrating compliance with RETS. The concentration and setpoint methods are identified in Table 3.12 through Table 5.1-7. Appendix C providas documentation for an alternate computerized option, designated as Method 1A in the ODCM, for calculating doses necessary to demonstrate compliance with RETS. The 1 Effluent Management System (EMS) software package used for this purpose is provided l by Canberra Industries, Inc. Where more refined dose calculations are needed, the l ' use of Method II dose determinations are described in Sections 3.2 through 3.9 and j 3.11. The dose factors used in the equations are in Tables B.1-10 through B.1-14 l and the Regulatory Limits are summarized in Table B.1-1. 1 B.1-1 ODCM Rev. 16
1.2
SUMMARY
OF METHODS, DOSE FACTORS, LIMITS, CONSTANTS, VARIABLES AND DEFINITIONS (Centinuod) The variables and special definitions used in this ODCM, Part B, are in Tables B.1-8 and B.1-9. l l I 1 l l O O B.1 2 ODCM Rev. 16
D (G TABLE B.1-1
SUMMARY
OF RADIOIDCICAL EFFLUENT TECHNICAL SPECIFICATIONS AND IMPLEMENTING EOUATIONS
-(U Catemory Method I T1=it Technical Snecification 3.11.1.1 Liquid Effluent Total Fraction of Eq. 2-1 s 1.0 Concentration MPC Excluding Noble cases Total Noble Gas Eq. 2-2 $ 2 x 10 pC1/ml Concentration 3.11.1.2 Liquid Effluent Total Body Dose Eq. 3-1 5 1.5 aren in a qtr.
Dose s 3.0 mrea in a yr. Organ Dose Eq. 3-2 s 5 area in a qtr. s 10 mren in a yr. 3.11.1.3 Liquid Radwaste Total Body Dose Eq. 3-1 5 0.06 area in a no. Treatment Operability Organ Dose Eq. 3-2 s 0.2 area in a mo. Total Body Dose Rate Eq. 3-3 $ 500 mres/yr. 3.11.2.1 Caseous Effluents Dose Rate from Noble Cases Skin Dose Rate Eq. 3-4 5 3000 mres/yr. from Noble Gases Organ Dose Rate Eq. 3-5 5 1500 aren/yr. from I-131, I-133, Tritium and Particulates with Tuz > 8 Days B.1-3 ODCM Rev. 16
TABLE B.1-1
SUMMARY
OF RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS AND IMPLEMENTING EOUATIONS (Continued) m Technical Specification Category Method I L1=fr 3.11.2.2 Gaseous Effluents Gamma Air Dose from Eq. 3-6 $ 5 mrad in a qtr. Dose from Noble Noble Cases Gases s 10 mrad in a yr. Beta Air Dose from Eq. 3-7 s 10 mrad in a qtr. Noble Cases s 20 mrad in a yr. 3.11.2.3 Gaseous Effluents Organ Do:e from Eq. 3-8 $ 7.5 area in a qtr. Dose from T 1_31, Iodines, Tritium and I-133. Tritium, Particulates with < 15 mrem in a yr. and Particulates Tuz > 8 Days 3.11.2.4 Ventilation Organ Dose Eq. 3-8 s 0.3 arem in a mo. Exhaust Treatment 3.11.4 Total Dose (from Total Body Dose Footnote (2). s 25 arem in a yr. All Sources) Organ Dose $ 25 mrem in a yr. Thyroid Dose $ 75 mrem in a yr. 3.3.3.9 Liquid Effluent Monitor Setpoint Liquid Waste Test Alarm Setpoint Eq. 5-1 T.S. 3.11.1.1 Tank Monitor 1.1-4 ODCM Rev. 16 O O O
J TABLE B.1-1 SUIGIARY OF RADIOiDGICAL EFFLUENT TECHNICAL SPECIFICATIONS AND TMPIRNKNTING EDUATIONS (Continued) (1) Technical Snecification Catestory Method I Tf=lt 3.3.3.10 Gaseous Effluent Monitor Setpoint Plant Vent Alarm / Trip Setpoint Eq. 5-9 T.S. 3.11.2.1 Wide Range Gas for Total Body Dose (Total Body) Monitors Rate Alarm / Trip Setpoint Eq. 5-10 T.S. 3.11.2.1 for Skin Dose Rate (SMn) (1) More accurate methods may be available (see subsequent chapters). I (2) Technical Specification 3.11.4.a requires this evaluation only if twice the limit of equations 3-1, 3-2, 3-12, 3-15 or 3-18 is reached. If this occurs a Method II calculation, using actual release point , parameters with annual average or concurrent meteorology and identified pathways for a real individual, shall be made. i f l r t B.1-5 ODCM Rev. 16 i _ __ - - . , _ . . . _ _ _ , - _ _ . . . _ . . . _ _ . _ , . ~ _ . . _ - _ . . . _ . . . _ . . ~ . . _
TABLE B.1 2 j
SUMMARY
OF METHOD I EOUATIONS TO CALCUIATE UNRESTRICTED AREA LIOUID CONCENTRATIQH1 Equation 0' Number Category Equation I 2-1 Total Fraction of MPC in Liquids. Except Noble cases N F -(( s1 2-2 Total Activity of Dissolved
' = { Cf and Entrained Noble Gases from all Station Sources Cf a s 2E-04 l
l O l l l
.1-6 ODCM Rev. 16
_ . . . .. _ _ m m. . . _ . _ . . _ _ . _ _ . . _ _ _ _ , . _ . . . _ . ~ . _ . _ . . . _ _ _ _ _ _ . . . . _ _ _ . . . _ . . _ _ _ _ . _ _ . . . . _ . . _ _ i i TABLE B.1-3 '
SUMMARY
OF METHOD I EOUATIONS TO CALCUIATE [ i OFF-SITE DOSES FROM LIOUID nFTFASES l Equation N'i-her Catemorv Eauntion l l : l 3-1 Total Body D tb(area) -kEQg DE ith Dose i i 3-2 Maximum Organ Dose D,,(area) - k E Q g DEg ,,
- i ,
r r i l l i B.1-7 ODCM Rev. 16
~
TABLE B.1-4
SUMMARY
OF METHOD I EOUATIONS TO CALCUIATE DOSE RATES Equation Receptor Release Caterory Number Location
- Heightb Eaustion Total Body Dose Rate From Noble 3-3a OS E bag,, = 0.85 * (Qi
- DFBg )
Cases 3-3b OS G bag,3 = 3.4 * (Qi e DFBi ) 3-3c EC E bagg,,= 0.0015 * (Qi
- DFBg )
3-3d EC G b.e bets) = 0.0074 * (Qi e DFB3 ) 3-3e R E Dag,3= 0.038 * (Qi
- DFBi )
3-3f R G bag,3 = 0. 2 * (Qi e DFBi )
*05 - Off-Site, EC - Science & Nature Center, formally the Education Center, R - The " Rocks" bE = Elevated, G - Ground B.1-8 ODCM Rev. 16 O O O
O O TABLE B.1-4
SUMMARY
OF METHOD I EOUATIONS TO CAlfUIATE DOSE RATES (Continued) Equation Receptor Release Catemory N= d er location
- Heirhtb Eaustion Skin Dese Rate From 3-4a OS E Noble Gases 6*ki"(* 3 = (Qi
- DF' 1(*3) 3-4b OS G 6,gg,,,3 - (Q3
- DF' ig,3) 3-4c EC E 6,,ggg,3 = 0.0014 * (Q,
- DF'inces) 3.4d EC G 6,gigg,3 - 0.0014 * { (Qi
- DF' ,,g,3) 1 3-4e R E b,,,gg,3 = 0.0076 * (Qg
- DF' gag,3) 3-4f R G bekiets) = 0.0076 * (Qg
- DF' gag,3)
- 0S - Off-Site, EC - Science & Nature Center, formally the Education Center, R - The " Rocks" bE - Elevated, G = Ground B.1-9 ODCM Rev. 16
TABLE B.1-4
SUMMARY
OF METHOD I EOUATIONS TO CALCUIATE DOSE RATES (Continued) Equation Receptor Release Category Number Iecation" Helehtb Ecuation Critical Organ Dose Rate From I-131, b,,g,3 - (Qi*DFG*g.c.3) I-133, H-3, and 3.5a OS E Particulate With T1/2 >8 Days 3.5b OS G 6,,g,3 = (Qg
- DFG' g g,3) 3.5c EC E b eort.) = 0.0014 * (Qg
- DFG" seert.1) 3.5d EC G 6eor(s) = 0.0014 * (Qg
- DFG' teerts))
3.5e R E 6,,ag,3 - 0.0076 * (Qg
- DFC' teonc.3) 3.5f R G 6,,ag,3- 0.0076 * (Qg
- DFG' g .ag,3)
"OS - Off-Site, EC - Science & Nature Center, formally the Education Center, R - The " Rocks" bE - Elevated, G = Ground B.1-10 ODCM Rev. 16 O O O
I. 1 TABLE B.1-5 SL"^*Y OF METHOD I EOUATIONS TO CAlfUIATE DOSES TO AIR FROM NOBLE GASES ;
}
Equation Receptor Release Category Number beation' Helmht6 Eauation I
", - "gi: , ; e^ " 3.6a oS E D:,..., = 3.2E-07 . t-o.=>>
. p (Q, . DF:) j I
i 3.6b OS C D!g,g,3 = 1.6E-06
- t-8 2'3 * { (Qi
- DFl) !
1 I i 3.6c EC E Dlg,gg,3 = 4.9E-10
- t-o.25: . p (q, . DF ) l 1 ,
3.6d EC G D!ser(s) = 4.4E-09 + t-o.szt . (q, . 3p7) l 3.6e R E Dlgreg., - 5.1E-09
- t-8 155 * (Qg
- DFl) 3.6f R G D!trats) = 4.1E-08
- t-o.2o4 *
(Qi
- DFl)
E 'OS - Off-Site, EC - Science & Nature Center, formally the Education Center, R - The " Rocks" ; bE - Elevated, G - Ground B.1-11 ODCM Rev. 16
TABLE B.1-5
SUMMARY
OF METHOD I EOUATIONS TO CALCUIATE DOSES TO AIR IROM NOBLE GASES (Continued) Equation Receptor Release Caterory Number Location
- Heirhtb Eaustion 3.7a OS E D# irg,3 = 4.1E-07
- t-8 3 * (Qi
- DET)
Fr No e a 3.7b OS G D# ,g,3 - 6.0E-06
- t-o.sts .
i (q, pyj) 3.7c EC E D# irgg.3 = 1.8E-09
- t-8 33 * { (Qi
- Dfi) i 3.7d EC G D# irgc,3 = 2.4E-08
- t-8 3*F * (Qi
- dei) 3.7e R E D trat.) = 3.9E-08
- t-8 2'8 * (Qi*DET) 3.7f R G D# trats) = 4.6E-07
- t-o.asr . (q,.ppf)
"0S - Off-Site, EC .'lence & Nature Center, formally the Education Center, R - The " Rocks" bE - Elevated, G - Grcund B.1-12 ODCM Rev. 16 O O O
,. _ .- - - - - - ~ .~. . _ . .. _ . . . .
O O O ! TABI.E B.1-6
SUMMARY
OF METHOD I EDUATIONS TO CAILULATE DOSE TO AN INDIVIDUAL FROM TRITIUM. IODIFE AND PARTICUIATES Equation Receptor Release Category Number Location" Heimhtb Eaustion i Dose to Critical Organ From Iodines, 3.8a OS E D,,,,3 - 14. 8
- t-o.as7 , (qt DFG3 ,,g,3)
Tritium, and Particulates 3.8b OS G D,,g,3 = 17. 7
- t 318 + (Qg
- DFG3 ,,g,3) i 3
3.8c EC E D,,gg,3 = 3. 3E-02
- t-8 * { (Qg
- DEUgeogg,3) 1 !
l i 3.8d EC G D ,gg,3 = 3. 3E-2
- t-8 3*7 * [ (Qi
- DFG i.,gg,3) 1 3.8e R E Decat.) = 7.3E-02
- t-o.zas * { (Qi
- DFGienat.1) i t
3.8f R G D, ag,3 = 8. 6E-02
- t-o.as? , (q,,om )
i i l
*0S - Off-Site, EC - Science & Nature Center, formally the Education Center, R - The " Rocks" bE - Elevated, G = Ground B.1-13 ODCM Rev. 16
TABLE B.1-7 i
SUMMARY
OF METHOUS FOR l SETPOINT DETERMINATIONS Equation Ntunbe r Catamorv Eaustion 5-1 Liould Effluents: Liquid Waste Test DZ_ Tank Monitor R setpoint ( S "1
)~ fl DF"i" 1
$1 (RM-6509) 5-23 PCCW Rate-of- 8 SWF 1
Change Alarm RCset(gph) - 1x10 I Gaseous Effluents; Plant Vent Wide Range Cas Monitors (RM 6528-1, 2, 3) I 5-5 Total Body R - 588 tb (pci/sec) DFB 5-6 Skin R - 3000 1 skin (pCi/sec) DF', 9 O B.1-14 ODCM Rev. 16 k
. . _ . . . . ~ .
. _ - - . - - - - - - . - . . - - . , - . . . - - . - . - - . . ~ - - - - - . - . . ,
4 ' TABLE B.1-8 ApMMARY OF VARIABLES . t
) Variable Definition Units
] i
= Concentration at point of discharge and Ci/ml
- CE[ entrained noble gas "i" in liquid pathways from all station sources l - Total activity of all dissolved and pCi j Cf entrained noble gases in if quid pathways I '
, from all station sources Cai
- Concentration of radionuclide "i" at the yCi l
- point of liquid discharge al C3 - Concentration of radionuclida "i" pCi/ml I C,3 - Concentration, exclusive of noble gases, of pCi l radionuclide "i" from tank "p" at point of "A discharge
- Cg - Concentration of radionuclide "i" in pCi/ml 4 mixture at the monitor i
- Off-site beta dose to air due to noble mrad D{tec.) gases in elevated release
- Off-site beta dose to air due to noble gas arad D{ tins) in ground level release j
- Beta dose to air at Science & Nature Center mrad Dbrec.) due to noble gases in elevated release ;
- Beta dose to air at Science & Nature Center arad f D{irt(s) due to noble gases in ground level release ,
- Beta dose to air at " Rocks" due to noble mrad Dbrat.) gases in elevated release 1
- Beta dose to air at " Rocks" due to noble mrad D{trats) gases in ground level release j
- Off-site gamma dose to air due to noble mrad D ir(*) Eases in elevated release
- Off-site gamma dose to air due to noble mrad D inds) Bases in ground level release
- Gamma dose to air at Science & Nature mrad i DIirst.) Center due to noble gases in elevated release
- Gamma dose to air at Science & Nature mrad D!arrts) Conter due to noble gases in ground level release i
Gamma dose to air at " Rocks" due to noble arad ' O D}trat.) gases in elevated release B.1-15 ODCM Rev. 16 l l 1
l TABLE B.1-8
SUMMARY
OF VARILLES l ( (Continued) Variable Definition Units
- Gamma dose to air at " Rocks" due to noble mrad 4 D!irats) gases in ground level release D .g,3 - Critical organ dose from an elevated mrem l l
release to an off-site receptor D,,c,3 - Critical organ dose from a ground level mrem l release to an off-site receptor i D. gg,3 - Critical organ dose from an elevated mrem release to a receptor at the Science & l Nature Center Deor(s)
- Critical organ dose from a ground level mrem release to a receptor at the Science &
Nature Center Dcoat.) - Critical organ dose from an elevated mrem release to a receptor at the " Rocks" Deon(s)
- Critical organ dose from a ground level arem l release to a receptor at the " Rocks" l Da
- Direct dose mrem l
- Gamma dose to air, corrected for finite mrad l
D}intt.. cloud l l D., - Dose to the maximum organ mrem Ds - Dose to skin from beta and gamma mrem Dr.b
- Dose to the total body arem DF - Dilution factor ratio DF.3, - Minimum allowable dilution factor ratio
- Composite skin dose factor for off-site mrem-sec/pci-yr DF i receptor
- Composite skin dose factor for Science & mrem-sec/pci-yr DFiz Nature Center
- Composite skin dose factor for the " Rocks" mrem-sec/pci-yr DFig DFB i - Total body gamma dose factor for nuclide mrem 3 "i" (Table B.1-10) pCi-yr DFB, - Composite total body dose factor 3 pCi-yr l
O B.1-16 ODCM Rev. 16
1 I TABLE B.1-8
SUMMARY
OF VARIABLES l 1 (Continued) 1 I J J j Variable Definition gnig l l DFLi a - Site-specific, total body dose factor for a
"#** I liquid release of nuclide "i" (Table B.1-N l 11) l DFL t - Site-specific, maximum organ dose factor area i for a liquid release of nuclide "i" (Table B.1-11) N 1 4
- Site-specific, critical organ dose factor ares /pci
- DFBt ..c.3 for an elevated gaseous release of nuclide j "i" (Table B.1-12)
} DFGi ..c,3 - Site-specific critical organ dose factor area /pci for a ground level release of nuclide "i" (Table 5.1-12) ! DFGi ..gr.3 - Science & Nature Center-specific critical area /pci organ dose factor for an elevated release
- of nuclide "i" (Table 5.1-14)
DFCs..gc,3 - Science & Nature Center-specific critical area /pCi
- organ dose factor for a ground level i release of nuclide "i" (Table B.1 14) i i DFG icaa( ) - The " Rocks"-specific critical organ dose arem/pCi 4
factor for an elevated release of nuclide !. "i" (Table B.1-15) l DFGi .ac,3 - The " Rocks"-specific critical dose factor arem/pci j for a ground level release of nuclide "i"
- (Table B.1-15) ,
1 1 1
- Site-specific critical organ dose rate l factor for an elevated gaseous release of arem-see l DFGie .c.3 i
nuclide "i" (Table B.1-12) *Ci~7# l - Site-specific critical organ dose rate arem-sec
- DFUse.cs) factor for a ground level release of nuclide "i" (Table B.1-12) #C1~7' j
l ,
= Science & Nature Center-specific critical arem-sec DFG ie .st.)
organ dose rate factor for an elevated
#Ci~7#
l release of nuclide "i" (Table B.1-14)
- Science & Nature Center-specific critical j' DFG icorts) organ dose rate factor for a ground level arem-seg i release of nuclide "i" (Table B.1-14) #Cl-7I
- The " Rocks"-specific critical organ dose "#*"~***
i DFC ie ac.) rate factor for an elevated release of ci-yr i nuclide "i" (Table B.1-15) !o B.1-17 ODCM Rev. 16
TABI.E B.1-8 l
SUMMARY
OF VARIABLES (Continued) Variable Definition Units 1
- The " Rocks"-specific critical organ dose arem-sec 1
DFGieon(s) rate factor for a ground level release of nuclide "i" (Table B.1-15) # i-7# C DFS 3 - Beta skin dose factor for nuclide "i" arem-m3 (Table B.1-10) pCi-yr DF' g - Combined skin dose factor for nuclide "i" mrem-m3 (Table B.1-10) pCi-yr
- Gamma air dose factor for nuclide "i" mrad-m8 DF t (Table B.1-10) pGi-yr
- Beta air dose factor for nuclide "i" mrad-m8 DFf (Table B.1-10) pGi-yr
- Critical organ dose rate to an off-site D eo (.) receptor due to elevated release of iodines , tritium, and particulates 7#
- Critical organ dose rate to an off. site "#*"
D (s) eo receptor due to ground level release of iodines, tritium, and particulates 7#
- Critical organ dose rate to a receptor at "#**
D coE(e) the Science & Nature Center due to an olevated release of iodines, tritium, and 7# particulates
- Critical organ dose rate to a receptor at "#**
Deor(s) the Science & Nature Center due to a ground 7# 1evel release of iodines , tritium, and particulates
- Critical organ dose rate to a receptor at D n(.)
eo the " Rocks" due to an elevated release of iodines, tritium, and particulates 7#
= Critical or5an dose rate to a receptor at Decats) the " Rocks" due to a ground level release of iodines, tritium, and particulates 7#
- Skin dose rate to an off-site receptor due Dninte) to noble gases in an elevated release yr f O B.1-18 ODCM Rev. 16
j TABLE B.1-8
SUMMARY
OF VARIABLES (Continued) O Variable Definition Units
- Skin dose rate to an off-site receptor due Dato(s) to noble gases in a ground level release yr
- Skin dose rate to a receptor at the Science Daint(e) & Nature Center due to noble gases in an elevated release 7#
= Skin dose rate to a eceptor at the Science
& Nature Center due to noble gases in a ****
Datar(s) ground level release Y# 1
, - Skin dose rate to a receptor at the " Rocks" Datnat.) due to noble gases in an elevated release 1 yr 1'
- Skin dose rate to a receptor at the " Rocks" Daina(s) due to noble gases in a ground level release 7#
' - Total body dose rate to an off-site d "#**
Dac.) receptor due to noble gases in an elevated release 7#
, Ob
- Total body dose rate to an off-site Da(s) receptor due to noble gases in a ground l 1evel release 7#
2 - Total body dose rate to a receptor at the Dest.) Science & Nature Center due to noble gases in an elevated release 7#
= Total body dose rate to a receptor at the f Darts) Science & Nature Center due to noble gases in a ground level release 7#
- Total body dose rate to a receptor at the
', Danc.) " Rocks" due to noble gases in an elevated "#** l release 7# l l
= Total body dose rate to a receptor at the "#**
Dants) " Rocks" due to noble gases in a ground 1evel release 7# d D/Q - Deposition factor for dry deposition of elemental radiciodines and other ," ] particulates i Fe
- Flow rate out of discharge tunnel gpm or ft 8 /sec F. - Flow rate past liquid waste test tank gpm monitor O
i B.1-19 ODCM Rev. 16
TABLE B.1-8
SUMMARY
OF VARIABilS (Continued) Variable Definition Units F - Flow rate past plant vent monitor cc see f;f1 t 2 fs;
- Fraction of total MPC associated with Paths Dimensionless
- f. 1, 2, 3, and 4
- Total fraction of MPC in liquid pathways Dimensionless @ (excluding noble gases)
MPC i - Maximum permissible concentration for yCi radionuclide "i" (10CFR20 Appendix B, CC Table 2, Column 2) Qi - Release to the environment for radionuclide curies, or l I
"i" pcuries
- Release rate to the environment for pCi/see Di radionuclide "i" R .t,,tos - Liquid monitor response for the limiting pCi/ml concentration at the point of discharge Rm. - Response of the noble gas monitor to epm, or pCi/sec limiting total body dose rate Re - Response of the noble gas monitor to cpm, or pCi/sec limiting total body dose rate Sr - Shielding factor Dimensionless l S'
- Detector counting efficiency from the gas c mR r monitor calibration g{Pm or e
S,i - Detector counting efficiency for noble gas pCL-cc pCi/cc l St - Detector countins efficiency from the I liquid monitor calibration CP8 l pCi/ml l Sti - Detector counting efficiency for cps radionuclide "i. pCi/ml l X/Q - Average long-term undepleted atmospheric sec i dispersion factor (" ables B.7-4, B.7-5, and m B.7-6) [X/Q)r - Effective long-term average gamma sec i atmospheric dispersion factor (Tables B.7-4, B.7-5, and B.7-6) m3 ) O' B.1-20 ODCM Rev. 16 l 1
i i TABLE B.1-8
SUMMARY
OF VARIABLES I (Continued) !O a Variable Definition Units I
- i SWF - Service Wster System flow rate gph
} PCC - Primary component cooling water measured pCi/ml (decay corrected) gross radioactivity concentration j t-* - Unitiess factor which adjusts the value of Dimensionless
- atmospheric dispersion factors for elevated
- or ground-level releases with a total release duration of t hours 4
I 4 I a r i l 1 i g 4 i 3 i 4 i 1 1 a t.
, ' % ,1
.p e i
f a 4 i h w i i B.1-21 ODCM Rev. 16
TABLE B.1 9 DEFINITION OF TEMS Critical Recentor - A hypothetical or real individual whose location and behavior cause him or her to receive a dose greater than any other possible real individual. Dose - As used in Regulatory Guide 1.109, the term " dose," when applied to individuals, is used instead of the more precise term "dore equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When cpplied to the evaluation of internal deposition or radioactivity, the term " dose," cs used here , includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. Thvi dose commitment is evaluated over a period of 50 years. The dose is measured in trem to tissue or mrad to air. Dose Rate - The rate for a specific averaging time (i.e., exposure period) of dose cccumulation. Liould Redwaste Treatment System - The components or subsystems which comprise the cvailable treatment system as shown in Figure B.6-1. O l l l l O B.1-22 ODCM Rev. 16
l h r (" b TABLE B.1-10 DOSE FACTORS SPECIFIC FOR SFAnanOK STATION FOR NOBLE GAS RFi n sES Combined Skin Combined Skin Gamma Total Dose Factor for Dose Factor for Body Dose Beta Skin Dose Elevated Release Ground Level Beta Air Dose Gamma Air Factor Factor Points Release Points Factor Dose Factor
. g y.
Radio- py,* garem-s*) "~"' ("I*"-**#) ~**C DF
- g *, ( p"**c*i-yr ) ( pci "I'd'" ) d ('pCi-yr ) E8d"*
PC1 yr Drs8 ( "p*c*i-yr ) DFg (e) pci.yr yr nuclide Ar-41 8.84E-03 2.69E-03 1.09E-02 6.22E-02 3.28E-03 9.30E-03 Kr-83m 7.56E-08 ----- 1.81E-05 7.33E-05 2.88E-04 1.93E-05 Kr-85m 1.17E-03 1.46E-03 2.35E-03 1.93E-02 1.97E-03 1.23E-03 Kr-85 1.61E-05 1.34E-03 1.11E-03 1.35E-02 1.95E-03 1.72E-05 Kr-87 5.92E-03 9.73E-03 1.38E-02 1.21E-01 1.03E-02 6.17E-03 Kr-88 1.47E-02 2.37E-03 1.62E-02 8.15E-02 2.93E-03 1.52E-02 Kr-89 1.66E-02 1.01E-02 2.45E-02 1.67E-01 1.06E-02 1.73E-02 Kr-90 1.56E-02 7.29E-03 2.13E-02 1.35E-01 7.83E-03 1.63E-02 Xe-131m 9.15E-05 4.76E-04 5.37E-04 5.35E-03 1.11E-03 1.56E-04 Xe-133m 2.51E-04 9.94E-04 1.12E-03 1.12E-02 1.48E-03 3.27E-04 Xe-133 2.94E 04 3.06E-04 5.83E-04 4.40E-03 1.05E-03 3.53E-04 Xe-135m 3.12E-03 7.11E-04 3.74E-03 1.99E-02 7.39E-04 3.36E-03 Xe-135 1.81E-03 1.86E-03 3.33E-03 2.59E-02 2.46E-03 1.92E-03 Xe-137 1.42E-03 1.22E-02 1.14E-02 1.28E-01 1.27E-02 1.51E-03 Xe-138 8.83E-03 4.13E-03 1.20E-02 7.63E-02 4.75E-03 9.21E-03 8.84E 8.84 x 10-3 B.1-23 ODCM Rev. 16
TABLE B.1-11 DOSE FACTORS SPECIFIC FOR SEABROOK STATION IDE LIOUID RELEASES Total Body Maximum Organ Dose Factor Dose Factor DFbu, I ch D% ( c Radionuclide H-3 3.02E-13 3.02E-13 Na-24 1.38E-10 1.42E-10 Cr-51 1.83E-11 1.48E-09 Mn-54 5.15E-09 2.68E 08 Fe 55 1.26E-08 7.67E-08 Fe 59 8.74E-08 6.66E 07 Co-58 2.46E-09 1.40E-08 Co 60 6.15E-08 9.22E-08 Zn 65 2.73E-07 5.49E-07 Br-83 1.30E-14 1.89E-14 Rb 86 4.18E-10 6.96E-10 Sr-89 2.17E-10 7.59E 09 Sr-90 3.22E-08 1.31E-07 Nb 95 5.25E-10 1.58E-06 Mo-99 3.72E-11 2.67E-10 Tc-99m 5.22E-13 1.95E-12 Ag-110m 1.01E 08 6,40E-07 Sb-124 1.71E-09 9.89E-09 Sb-125 6.28E-09 8.31E-09 Te-127m 7.07E-08 1.81E-06 Te-127 3.53E-10 9.54E-08 Te-129m 1.54E-07 3.46E-06 Te-129 7.02E-14 1.05E-13 Te-131m 3.16E-08 2.94E 06 Te-132 9.06E-08 3.80E-06 , I-130 2.75E-11 3.17E 09 I I-131 2.30E-10 1.00E-07 I 132 6.28E-11 6.36E-11 i I-133 3.85E-11 1.15E-08 I I-134 1.19E-12 1.41E-12 I-135 5.33E-11 4.69E-10 Cs-134 3.24E-08 3.56E-08 Cs-136 2.47E-09 3.27E-09 Cs-137 3.58E-08 4.03E-08 Ba-140 1.70E-10 3.49E-09 La 140 1.07E-10 4.14E-08 Ce-141 3.85E 11 9.31E-09 Ce-144 1 '96E-10 6.46E-08 Other* 3.12E-08 1.58E-06*
- Dose factors to be used in Method I calculation for any "other" detected gamma emitting radionuclide which is not included in the above list.
l 0 B.1-24 ODCM Rev. 16
TABLE B.1-12 DOSE AND DOSE RATE FACTORS SPECIFIC FOR SEABROOK STATION l , ros p IODINES. TRITIUM AND PARTICtRATE PRT FASES iV Critical Organ Critical Organ Critical Organ Dose Critical Organ Doea Factor Dose Factor for Rate Factor for Dose Rate Factor ' for Elevated Ground Level Elevated Release for Ground Level Release Point Release Point Point Release Point Radio pm,,,, g ey) om,,, g ey) pm;,,,,,gmem;see) p m ,,, g.m em-see) H-3 3.08E-10 3.76E-09 9.71E 03 1.19E-01 Cr-51 8.28E-09 2.89E 08 2.91E-01 1.01E+00 l I Mn-54 1.11E 06 3.79E-06 4.38E+01 1.50E+02 , 1 Fe-59 1.06E-06 3.65E 06 3.53E+01 1.21E+02 Co-58 5.56E-07 1.91E-06 2.00E+01 6.88E+01 i Co-60 1.21E-05 4.12E-05 5.42E+02 1.85E+03 i Zn-65 2.33E-06 7.93E-06 7.82E+01 2.66E+02 ; Sr-89 1.98E-05 6.73E-05 6.24E+02 2.12E+03 Sr-90 7.21E-04 2.47E-03 2.27E+04 7.79E+04 Zr-95 1.10E-06 3.77E-06 3.63E&O1 1.24E+02 , Nb-95 2.01E 06 6.86E-06 6.40E+01 2.20E+02 O ( Mo 99 1.63E 08 1.10E 07 5.39E-01 3.56E+00 Ru-103 3.03E-06 1.04E-05 9.62E+01 3.31E+02 Ag-110m 5.02E-06 1.72E-05 1.80E+02 6.15E+02 Sb-124 1.83E-06 6.28E-06 6.15E+01 2.11E+02 1 1-131 1.47E-04 5.04E-04 4.64E+03 1.59E+04 l l I-133 1.45E-06 5.72E-06 4.57E+01 1.80E+02 1 , Cs-134 5.62E-05 1.91E-04 1.81E+03 6.18E+03 l Cs-137 5.47E-05 1.86E-04 1.79E+03 6.09E+03 Ba-140 1.55E-07 6.39E-07 5.01E+00 2.06E+01 Ce-141 2.65E-07 9.28E-07 8.45E400 2.96E+01 Co-144 6.09E-06 2.09E-05 1.93E+02 6.62E+02 Other* 4.09E-06 1.39E-05 1.29E+02 4.38E+02
- Dose factors to be used in Method I calculations for any "other" detected gamma emitting radionuclide which is not included in the above list.
k B.1-25 ODCM Rev. 16
TABLE B.1-13 COMBINED SKIN DOSE RATE FACTORS SPECIFIC FOR SEABROOK STATION SPECIAL RECEPTORSm FOR NOBLE CAS RELEASE Science & Nature Science & Nature Center Center The " Rocks" Combined Skin Combined Skin The " Rocks" Combined Skin Dose Rate Factor Dose Rate Factor Combined Skin Dose Rate Factor for Elevated for Dose Rate Factor for Release Ground Level for Elevated Ground Level Release Point Release Point Release Point Point Radio- ~** py**' 4 mrem-see) pci yr DF'**' ( "*p *c*i-yr ) D P'** ' ( "#pci-yr
*" ~ * * ) DF**O ( mr em-see Ci-yr )
nuclide Ar-41 1.57E-02 1.17E-01 9.73E 02 6.99E-01 Kr-83m 2.35E-05 1.13E-04 1.07E 04 5.58E-04 Kr-85m 3.84E-03 4.08E-02 3.16E-02 2.69E-01 ! Kr-85 2.16E-03 3.09E-02 2.29E-02 2.15E-01 Kr-87 2.31E-02 2.60E-01 2.00E-01 1.74E+00 Kr-88 2.23E-02 1.44E-01 1.25E-01 8.18E-01 l Kr-89 3.73E-02 3.34E-01 2.68E 01 2.12E+00 Kr-90 3.15E-02 2.64E-01 2.14E-01 1.64E+00 Xe-131m 9.52E-04 1.19E-02 8.96E-03 8.07E-02 Xe-133m 1.99E-03 2.48E-02 1.87E-02 1.68E-01 Xe-133 9.20E-04 9.11E-03 7.16E-03 5.92E-02 Xe-135m 5.24E-03 3.61E-02 3.07E-02 2.11E 01 Xe-135 5.32E-03 5.41E 02 4.23E-02 3.53E-01 Xe-137 2.14E-02 2.89E 01 2.16E-01 2.00E+00 Xe-138 1.78E-02 1.49E 01 1.21E-01 9.27E-01 m See Seabrook Station Technical Specification Figure 5.1-1. O B.1-26 ODCM Rev. 16
TABLE B.1-14 DOSE AND DOSE RATE FACTORS SPECIFIC FOR THE SCIENCE & NATURE CENTER ; FOR IODINE. TRITIUM. AND PARTICUT. ATE RELEASES !
';itical Organ Critical Or5an' Dose Factor for Critical Or6e Dose Critical Organ Dose Dose Factor for Ground level Rate Factor for Rate Factor for Elevated Release Elevated Release Ground 14 vel Release Release Point Point Point Point DMs ac. ("c7) DM aste (7e7) t DM'se.s c.: ( ", $ #) D M's sic ( % y )
H-3 6.45E-11 9.27E-10 2.03E-03 2.92E 02 Cr-51 4.98E-09 2.88E-08 2.12E-01 1.11E+00 Mn-54 1.39E-06 5.71E-06 6.24E+01 2.39E+02 Fe-59 3.09E-07 1.89E-06 1.29E+01 7.16E+01 Co-58 3.89E 07 2.10E-06 1.72E+01 8.26E+01 Co-60 2.17E-05 8.03E-05 9.87E+02 3.63E+03 Zn-65 7.34E-07 3.19E-06 3.31E+01 1.33E+02 Sr-89 1.15E-07 1.61E-06 3.63E+00 5.08E+01 Sr-90 5.14E-06 7.19E 05 1.62E+02 2.27E+03 7r-95 3.38E-07 2.57E-06 1.35E+01 9.15E+01 Nb-95 1.53E-07 9.35E-07 6.43E+00 3.53E+01 Mo-99 1.62E-08 1.92E-07 5.58E-01 6.21E+00 l Ru-103 1.30E-07 8.64E-07 5.33E+00 3.19E+01 Ag-110m 3.43E-06 1.54E-05 1.55E+02 6.34E+02 Sb-124 6.96E-07 4.46E-06 2.89E+01 1.67E+02 1-131 7.79E-07 1.08E-05 2.47E+01 3.41E+02 I-133 1.84E 07 2.56E-06 5.83E+00 8.11E+01 Cs-134 6.83E-06 2.53E-05 3.08E+02 1.14E+03 Cs-137 1.03E-05 3.81E 05 4.64E+02 1.72E+03 Ba-140 , 1.14E-07 1.42E 06 3.85E+00 4.54E+01
^
Ce-141 4.09E-08 4.51E 07 1.45E+00 1.48E+01 Co-144 6.95E-07 9.11E 06 2.27E+01 2.90E+02 Other* 2.26E-06 9.24E-06 1.02E(02 3.91E+02
- Dose factors to be used in Method I calculations for any "other" detected gamma emitting radionuclide which is not included in the above list.
l O B.1-27 ODCM Rev. 16
TABLE E.1-15 DOSE AND DOSE RATE FACTORS SPECIFIC FOR THE " ROCKS" FOR IODINE. TRITIUM. AND PARTICUIATE RELEASES Critical Organ Critical Organ Critical Organ Dose Critical Organ Dose Dose Factor Dose Factor for Rate Factor for kate Factor for for Elevated Ground Level Elevated Release Ground Level Release Point Release Point Point Release Point me-Ra o- om,,,,,,, ( mre) Dmt , ( gy) DM's.,,,,,("{,lc) p m ,,,,, m 4 e c3 H-3 6.85E-10 6.45E-09 2.16E-02 2.03E-01 Cr-51 2.68E-08 1.75E-07 1.07E+00 6.53E+00 Kn-54 5.84E-06 3.18E-05 2.55E+02 1.31E+03 Fe-59 1.74E-06 1.17E-05 6.78E+01 4.29E+02 Co-58 2.01E-06 1.25E 05 8.11E+01 4.79E+02 Co-60 8.83E-05 4.09E-04 3.97E+03 1.85E+04 Zn-65 3.23E-06 1.80E-05 1.37E+02 7.29E+02 Sr-89 1.23E-06 1.15E-05 3.88E401 3.63E+02 Sr-90 5.48E-05 5.14E 04 1.73E+03 1.62E+04 Zr-95 2.22E-06 1.6BE-05 8.14E+01 5.83E+02 Nb-95 8.59E 07 5.79E 06 3.37E+01 2.13E+02 Mo 99 1.50E-07 1.34E-06 4.92E+00 4.32E+01 Ru-103 7.74E-07 5.47E-06 2.95E+01 1.96E+02 Ag-110m 1.54E-05 8.77E-05 6.47E+02 3.53E+03 Sb-124 4.04E 06 2.80E-05 1.56E+02 1.01E+03 I-131 8.27E-06 7.73E-05 2.01E+02 2.44E+03 I-133 1.95E 06 1.83E-05 6.18E+01 5.77E+02 Cs-134 2.78E-05 1.292-04 1.25E+03 5.80E+03 Cs-137 4.19E-05 1.94E-04 1.89E+03 8.77E+03 Ba-140 1.10E-06 9.99E-06 3.56E+01 3.19E+02 Ce-141 3.59E 07 3.14E-06 1.20E+01 1.02E+02 Ce-144 7.02E 06 6.46E-05 2.25E+02 2.05E+03 Other* 9.56E-06 5.09E-05 4.16E+02 2.12E+03
- Dose factors to be used in Method I calculations for any "other" detected gamma emitting radionuclide which is not included in the above list.
O B.1-28 ODCM Rev. 16
_. _. _ . _ _ .-~ - 2.0 METHOD TO CALCUIATE OFF-SITE LIOUID CONCENTRATIONS Chapter 2 contains the basis for station procedures used to demonstrate compliance with Technical Specification 3.11.1.1, which limits the total fraction of MPC in liquid pathways, other than noble gases (denoted here ast F ") at the point i of discharge from the station to the environment (see Figure B.6-1). Ft " is l limited to less than or equal to one, i.e., I i 4 F s 1. { The total concentration of all dissolved and entrained noble gases at the point of discharge from the.multiport diffuser from all station sources combined,
! denoted C t ", is limited to 2E 04 pCi/m1, i.e. ,
l Ct " $ 2E-04 pCi/ml. Appendix C Attachments 3 and 4, provide the option and bases for the use of the EMS determination of liquid concentration limits for plant discharges to the i environment. l 2.1 METHOD TO DETERMINE2 F " AND C2 " ! First, determine the total fraction of MPC (excluding noble gases), at the i point of discharge from the station from all significant liquid sources denoted FtN; and then separately determine the total concentration at the point of l discharge of all dissolved and entrained noble gases from all station sources,
- denoted Ct ", as follows
O ENG Fi - E E .MFC 21 s 1. (2-1) p i i uCi/a1 Ipci/al) i j and: NC NG .' Cy - E Cig s 2E304 (2-2) i (pCi/al) (p.Ci/ml) (pci/ml) i where: F - Total fraction of MPC in liquids, excluding noble 1 gases, at the point of discharge from the multiport diffuser. 2 ( B.2-1 ODCM Rev. 16 a I
2.1 METHOD TO DETERMINE 2 F r" AND2 C " (C ntinusd) C,i - Concentration at point of discharge from the multiport diffuser of radionuclide "i", except for dissolved and entrained noble gases, from all tanks and other significant sources, p, from , which a discharge may be made (including the waste test tanks and < any other significant source from which a dischar6e can be made). C,3 is determined by dividing the product of the measured radionuclide concentration in liquid waste test tanks, PCCW, steam generator blowdown, or other effluent streams times their discharge flow rate by the total available dilution water flow rate of circulating and service water at the time of release (pCi/ml). l MPC t - Maximum permissible concentration of radionuclide "i" except for I dissolved and entrained noble gases from 10CFR20, Appendix B. ( Table II, Column 2 (pCi/ml). See Appendix B for a list of MPC values. l C"t
- Total concentration at point of discharge of all dissolved and entrained noble gases in liquids from all station sources (pci/ml)
Cu" - Concentration at point of discharge of dissolved and entrained noble gas "i" in liquids from all station sources (pCi/ml) 2.2 METHOD TO DETERMINE RADIONUCLIDE CONCENTRATION FOR EACH LIQUID EFFLUENT SOURCE 2.2.1 Waste Test Tanks C,i is determined for each radionuclide detected from the activity in a representative grab sample of any of the waste test tanks and the predicted flow at the point of discharge. The batch releases are normally made from two 25,000-gallon capacity waste test tanks. These tanks normally hold liquid waste evaporator distillate. The vaste test tanks can also contain other waste such as liquid taken directly from the floor drain tanks when that liquid does not require processing in the evaporator, distillate from the boron recovery evaporator when the BRS evaporator is cubstituting for the waste evaporator, and distillate from the Steam Generator Blowdown System evaporators and flash steam condensers when that system must discharge liquid off-site. If testing indicates that purification of the waste test tank contents is required prior to release, the liquid can be circulated through the waste demineralizer and filter. The contents of the wasto test tank may be reused in the Nuclear System if the sample test meets the purity requirements. Prior to discharge, each vaste test tank is analyzed for principal gamma emitters in accordance with the liquid sample and analysis program cutlined in Part A to the ODCM. O B.2-2 ODCM Rev. 16
2.2 METHOD TO DETERMINE RADIONUCLIDE CONCENTRATION FOR EACH LIQUID EFFLUENT SOURCE i 2.2.2 Turbine Buildirug Sumo [
\s,- The Turbine Building sump collects leakage from the Turbine Building floor drains and discharges the liquid unprocessed to the circulating water system.
Sampling of this potential source is normally done once per week for determining the radioactivity released to the environment (see Table A.3-1). 2.2.3 Steam Generator Blowdown Flash TADh The steam generator blowdown evaporators normally process the liquid from the I steam generator blowdown flash tank when there is primary to secondary leakage. ' Distillate from the evaporators can be sent to the vaste test tanks or recycled to the condensate system. When there is no primary to secondary laakage, flash tank liquid is processed through the staan generator blowdown domineralizers and returned to the secondary side. Steam generator blowdown is only subject to sampling and analysis when all or part of the blowdown liquid is being discharged to the environment instead of the normal recycling process (see Table A.31). I 2.2.4 Primary Connonent Cooline Water (PCCW) System I The PCCW System is used to cool selected primary components. The system is normally sampled weekly to determine if there is any radwaste in-leakage. If leakage has been determined, the Service Water System is saapied to determine if any release to the environment has occurred. ( b9., R i f lk B.2-3 ODCM Rev. 16
3.0 QEE-SITE DOSE CALCUIATION METHODE Chapter 3 provides the basis for station procedures required to meet the Radiological Effluent Technical Specifications (RETS) dose and dose rate {ss ,)T requirements contained in Section 3/4.11 of the station operating Technical Specifications. A simple, conservative method (called Method I) is listed in Tables B.1-2 to B.1-7 for each of the requirem.ints of the RETS. Each of the Method I ! equations is presented in Sections 3.2 through 3.9. As an alternate to Method I, the EMS computer program documented in Appendix C can be used to determine regulatory compliance for effluent doses and dose rates. The use of the EMS software is designated as Method IA in Chapter 3. In addition, those sections . include more sophisticated methods (called Method II) for use when more refined results are needed. This chapter providas the methods, data, and reference material with which the operator can calculate the needed doses, dose rates and setpoints. For the requirements to demonstrate compliance with Technical Specification off-site dose limits, the contribution from all measured ground level releases must be added to the calculated contribution from the vent stack to determine the Station's total radiological impact. The bases for the dose and dose rate equations are given in Chapter 7.0. Method IA bases and software verification documentation are contained in Appendix C. l The Annual Radioactive Effluent Release Report, to be filed after January 1 each year per Technical Specification 6.8.1.4, requiras that meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, be used for determining the gaseous pathway doses. For continuous release sources (i.e., plant vent, condenser air removal exhaust, and gland steam packing exhauster), concurrent quarterly average meteorology will be used in the dose calculations along with the quarterly total radioactivity released. For batch releases or identifiable 7s operational activities (i.e. , containment purge or venting to atmosphere of the Waste Gas System), concurrent meteorology during the period of release will be used to determine dose if the total noble gas or iodine and particulates released in the batch exceeds five percent of the total quarterly radioactivity released from the unit; otherwise quarterly average meteorology will be applied. Quarterly average meteorology vill also be applied to batch releases if the hourly met data for the period of batch release is unavailable. l Annual dose assessment reports prepared in accordance with the requirements of the ODCM will include a statement indicating that the appropriate portions of Regulatory Guide 1.109 (as identified in the individual subsections of the ODCM for each class of effluent exposure) have been used to determine dose impact from statica releases. Any deviation from the methodology, assumptions, or parameters given in Regulatory cuide 1.109, and not already identified in the bases of the ODCM, will be explicitly described in the effluent report, along with the bases for the naviation. O B.3-1 ODCM Rev. 16
3.1 INTRODUCTORY CONCEPTS In part, the Radiological Effluent Technical Specifications (RETS) limit dose
- or dose rate. The term " dose" for ingested or inhaled radioactivity means the dose commitment, measured in arem, which results from the exposure to radioactive l
materials that, because of uptake and deposition in the body, will continue to expose the body to radiation for some period of time after the source of radioactivity is stopped. The time frame over which the dose commitment is evaluated is 50 years. The phrases " annual dose" or " dose in one year" then refers to the 50-year dose commitment resulting from exposure to one year's worth of releases. " Dose in a quarter" similarly means the 50-year dose commitment resulting from exposure to one quarter's releases. The term " dose," with respect to external sxposures, such as to noble gas clouds, refers only to the doses received during the cetual time period of exposure to the radioactivity released from the plant. Once i the source of the radioactivity is removed, there is no longer any additional cccumulation to the dose commitment.
" Dose rate" is the total dose or dose commitment divided by exposure period.
l For example, an individual who is exposed via the ingestion of milk for one year to l radioactivity from plant gaseous effluents and receives a 50-year dose commitment of , 10 mrem is said to have been exposed to a dose rate of 10 mrem / year, even though the l cetual dose received in the year of exposure may be less than 10 mrem. In addition to limits on dose commitment, gaseous effluents from the station cre also controlled so that the maximum or peak dose rates at the site boundary at cny time are limited to the equivalent annual dose limits of 10CFR, Part 20 to unrestricted areas (if it were essumed that the peak dose rates continued for one year). These dose rate limits provide reasonable assurance that members of the public, either inside or outside the site boundary, will not be exposed to annual l cveraged concentrations exceeding the limits specified in Appendix B, Table II of l 10CFR, Part 20 (10CFR20.106(a)). See Appendix B for a listing of these i concentration limits. The quantities AD and b are introduced to provide calculable quantities, related to off-site doses or dose rates that demonstrate compliance with the RETS. I Delta D, denoted AD, is the quantity calculated by the Chapter 3, Method I dose equations. It represents the conservative increment in dose. The AD calculated by Method I equations is not necessarily the actual dose received by a real individual, but usually provides an upper bound for a given release because of the conservative margin built into the dose factors and the selection and definition l of critical receptors. The radionuclide specific dose factors in each Method I dose l oquation represent the greatest dose to any organ of any age group. (Organ dose is a function of age because organ mass and intake are functions of age.) The critical receptor assumed by " Method I" equations is then generally a hypothetical individual whose behavior - in terms of location and intake - results in a dose which is higher than any real individual is likaly to receive. Method IA dose calculations using the EMS software evaluate each age group and organ combination to determine the maximum organ dose for each mix of radionuclides specified in a release period. Method II also allows for a more exact dose calculation for each individual if necessary. 1 O B.3-2 ODCM Rev. 16
3.1 INTRODUCTORY CONCEPTS (C ntinusd) i D dot, denoted 6, is the quantity calculated in the Chapter 3 dose nr.g 1 equations. It is calculated using the station's effluent monitoring system reading
- and an annual or long-term average atmospheric dispersion factor. b predicts the 3 maximum off-sita annual dose if the peak obsarved radioactivity release rate from '
the plant stack continued for one entire year. Since peak release rates, or resulting dose rates, are usually of short time duration on the order of an hour or less, this approach then provides assurance that 10CFR20.106 limits will be met. j Each of the methods to calculate dose or dose rate are presented in the following subsections. Each dose type has two levels of complexity. Method I is the simplest and contains many conservative factors. As an alternate to Method I the EMS computer program documented in Appendix C can be used to determine
- l. regulatory compliance for effluent doses and dose rates. The use of the EMS system j is designated as Method IA in Chapter 3.
Method II is a more realistic analysis which makes use of the models in i
- Regulatory Guide 1.109 (Revision 1), as noted in each subsection of Chapter 3 for i the various exposure types. A detailed description of the methodology, assumptions, and input parameters to the dose models that are applied in each Method II
- calculation, if not already explicitly described in the ODCM, shall be documented 1
and provided when this option is used for NRC reporting and Technical Specification dose compliance. 1 ) I 1 '; O a l O B.3-3 ODCM Rev. 16
3.2 METHOD TO CALCULATE THE TOTAL BODY DOSE FROM LIQUID RELEASES Technical Specification 3.11.1.2 limits the total body dose commitment to a member of the public from radioactive material in liquid effluents to 1.5 mrem per quarter and 3 mrom per year per unit. Technical Specification 3.11.1.3 requires liquid radwaste treatment when the total body dose estimate exceeds 0.06 mrem in any 31-day period. Technical Specification 3.11.4 limits the total body dose commitment to any real member of the public from all station sources (including liquids) to 25 area in a year. l Use Method I or Method IA first to calculate the maximum total body dose from o liquid release from the station as it is simpler to execute and more conservative than Method II. Use Method II if a more refined calculation of total body dose is needed, l 1.e. , Method I or Method IA indicates the dose might be greater than the Technical Specification limits. To evaluate the total body dose, use Equation 3.1 to estimate the dose from the planned release and add this to the total body dose accumulated from prior releases during the month. See Section 7.1.1 for basis. 3.2.1 Method I The increment in total body dose from a liquid release is: Du, = k Qi DFLau (3-1) (mrem) = ( ) (pCi) where DFLi u, - Site-specific total body dose factor (arem/pCi) for a liquid release. It is the highest of the four age groups. See Table B.1-11. 03 - Total activity (pCi) released for radionuclide "ia. (For strontiums, use the most recent measurement available.) K- 918/F4 ; where Fa is the average (typically monthly average) dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 8/sec) . For normal operations with a cooling water flow of 918 ft8 /sec, K is equal to 1. Equation 3-1 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Liquid releases via the multiport diffuser to unrestricted areas (at the edge of the initial mixing or prompt dilution zone that corresponds to a factor of 10 dilution), and
- 2. Any continuous or batch release over any time period.
B.3-4 ODCM Rev. 16
3.2 METHOD TO CALCUIATE THE TOTAL BODY DOSE FROM LIQUID RELEASES i
,_ 3.2.1 Method I (Continued) f Method IA is implemented by the EMS software as described in Appendix C.
Liquid release models are detailed in sections 2.1 - 2.6 of the EMS Technical Reference Manual (Attachment 4 of Appendix C). 3.2.2 Method II Method II consists of the models, input data and assumptions (bioaccumulation factors, shore-width factor, dose conversion factors, and transport and buildup
- times) in Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or assumptions have been identified in the ODCM. The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and used its the derivation of the simplified Method I approach as described in the Bases section, are also applied to Method II assessments, except that doses calculated to the whole body from radioactive effluents are evaluated for each of the four age groups to determine the maximum whole body dose of an age-dependent individual via all existing exposure 4 pathways. Table B.7-1 lists the usage factors of Method II calculations. As noted in Section B.7.1, the mixing ratio associated with the edge of the l'F surface isotherm above the multiport diffuser may be used in Method II calculations for the l shoreline exposure pathway. Aquatic food ingestion pathways shall limit credit i taken for mixing zone dilution to the same value assumed in Method I (M, - 0.10) .
1 .i i t j 4 O B.3-5 ODCM Rev. 16
I 3.3 METHOD TO CALCUIATE MAXIMUM ORGAN DOSE FROM LIQUID RELEASES Technical Specification 3.11.1.2 limits the maximum organ dose commitment to a Member of the Public from radioactive material in liquid effluents to 5 mrem per quarter and 10 mrem per year per unit. Technical Specification 3.11.1.3 requires liquid radwaste treatment when the maximum organ dose projected exceeds 0.2 mrem in cny 31 days (see Subsection 3.11 for dose projections). Technical Specification 3.11.4 limits the maximum organ dose commitment to any real member of the public from all station sources (including liquids) to 25 mrem in a year except for the thyroid, which is limited to 75 arem in a year. l Use Method I or Method IA first to calculate the maximum organ dose from a liquid release to unrestricted areas (see Figure B.6-1) as it is simpler to execute end more conservative than Method II. Use Method II if a more refined calculation of organ dose is needed, l 1.e. , Method I or Method IA indicates the dosc. may be greater than the limit. Use Equation 3-2 to estimate the maximum organ dose from individual or combined liquid releases. See Section 7.1.2 for basis. 3.3.1 Method I The increment in maximum organ dose from a liquid release is: D =k Q DFL% i (3-2) (mrem) = ( ) (pCi) where DFL .i
- Site-specific maximum organ dose factor (arem/pCi) for a liquid release. It is the highest of the four age groups. See Table B.1-11.
Qi - Total activity (pC1) released for radionuclide "i". (For strontiums, use the most recent measurement available.) K- 918/Fd ; where F4 is the average (typically monthly average) dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft /sec). 3 For normal operations with a cooling water flow of 918 ft /sec, K is equal to 1. 3 i Equation 3-2 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Liquid releases via the multiport diffuser to unrestricted areas (at the edge of the initial mixing or prompt dilution zone that corresponds to a factor of 10 dilution), and
- 2. Any continuous or batch release over any time period.
O B.3-6 ODCM Rev. 16
3.3 METHOD TO CALCUIATE MAXIMUM ORGAN DOSE FROM I.IQUID RELEASES 3.3.1 Method I (Continued) Method IA is implemented by the EMS software as described in Appendix C. Liquid release models are detailed in sections 2.1 - 2.6 of the EMS Technical Reference Manual (Attachment 4 of Appendix C). 3.3.2 Method II Method II consists of the models, input data and assumptions (bioaccumulation factors, shore-width factor, dose coaversion factors, and transport and buildup times) in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or assumptions have been identified in the ODCM. The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases section, are also applied to Method II assessments, except that doses calculated to critical organs from radioactive effluents are evaluated for each of the four age groups to determine the maximum critical organ of an age-dependent individual via all existing exposure pathways. Table B.7-1 lists the usage factors for Method II calculations. As noted in Section B.7.1, the mixing ratio associated with the edge of the l'F surface isotherm above the multiport diffuser may be used in Method II calculations for the shoreline exposure pathway. Aquatic food ingestion pathways shall limit credit taken for mixing zone dilution to the same value assumed in Method I (M, - 0.10) . o O B.3-7 ODCM Rev. 16
3.4 METHOD TO CALCUIATE THE TOTAL BODY DOSE RATE FROM NOBLE GASES Technical Specification 3.11.2.1 limits the dose rate at any time to the total body from noble gases at any location at or beyond the site boundary to 500 mrea/ year. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued release at the peak rate. By limiting ba to a rate equivalent to no more than 500 mrem / year, we assure that the total body dose accrued in any one year by any member of the general public is less than 500 mrem. l Use Method I or Method IA first to calculate the Total Body Dose Rate from the peak release rate via the station vents or ground level effluent release points. Method I applies at all release rates. Use Method II if a more refined calculation of Da is desired by the station (i.e. , use of actual release point parameters with annual or actual meteorology to l cbtain release-specific X/Qs) or if Method I or Method IA predicts a dose rate greater than the Technical Specification limit to determine if it had actually been exceeded during a short time interval. See Section 7.2.1 for basis. Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant vent noble gas activity ronitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site dose rate limit, or a value below it. Determinations of dose rate for compliance with Technical Specifications are performed when the effluent monitor alarm setpoint ir exceeded, or as required by the Action Statement (Technical Specification 3.3.3.10 Table 3.3-10) when the monitor is inoperable. 3.4.1 Method I The Total Body Dose Rate to an off-site receptor due to noble gases in , effluents released via the plant vent can be determined as follows: bag,3 = 0.85 * ('Qi
- DFB )i (3-3a) mrem , 'pci-see' 'pCi ' mrem-m' 8
yr 3 p ,pci yr, pCi-m , ,s e c, where i ba - The off-site total body dose rate (mrem /yr) due to noble gases in elevated effluent releases. Qi - the release rate at the station vents (pCi/sec), for each noble gas radionuclide, "i", shown in Table B.1-10, and DFBi- total body gamma dose factor (see Table B.1-10). The Total Body Dose Rate (to an off-site receptor) due to noble gas in ground level effluent releases can be determined as follows: O B.3-8 ODCM Rev. 16
3.4 METHOD TO CALCULATE THE TOTAL BODY DOSE RATE FROM NOBLE GASES i 7- 3.4.1 Method I (Continued) ( 34
- DFB3 )
b ats) " *h(91 (3-3b) ares ,'pci-sec' 'pci 'arem-m' 3
,p ,
yr , pCi-m ,3
,s e e, ,
pci-yr, where Da - The total off-site body dose rate (arem/yr) due to noble gases in elevated effluent releases, and Qi and DFBi are as defined for Equation 3-3a. For the special on-site receptor locations, the Science & Nature Center and the " Rocks," the total body dose rates due to noble gases in effluent discharges can be determined as follows: For the Science & Nature Center, elevated effluent release: bart.) - 0.0015 * (Qi e DFBg) (3-3c) For the Science & Nature Center, ground level efflue.nt release: ; O ! d bagg,3 - 0.0074 * { (Qi* DFBi ) (3-3d) 1 For the " Rocks," elevated effluent release: banc,3 - 0.038 * { (Qi
- DFBi ) (3-3e)
For the " Rocks," ground level effluent release: bam(s) - 0.2 * {i (Qi e DFBi ) (3-3f) where Darc.). Oasts). Dam (.), and ban - The total body dose rate (arem/yr) at the Science & Nature Center and the " Rocks," respectively, due to noble gases in Baseous discharges from elevated (e) and ground level (g) release points, and l l Qi and DFB are as defined previously, i j Equations 3 3a through 3-3f can be applied under the following conditions l (otherwise, justify Method I or consider Method II): ( B.3-9 ODCM Rev. 16 1
- 1
I 3.4 METHOD TO CALCUIATE THE TOTAL BODY DOSE RATE FROM NOBLE GASES i ! 3.4.1 Method I (Continued)
- 1. Normal operations (nonemergency event), and
- 2. Noble gas rel' eases via any station vent to the atmosphere.
Method IA is implemented by the EMS software as described in Appendix C. l Gaseous release models are detailed in Section 6.7.3 of the EMS Software Requirements Specification (Attachment 3 of Appendix C). 3.4.2 Method II Method II consists of the model and input data (whole body dose factors) in l Regulatory Guide 1.109, Rev. 1 (Reference A), except where site +apecific data or ; cssumptions have been identified in the ODCM. The general equation (B-8) taken from ; Regulatory Guide 1.109, and used in the derivation of the simplified Method I i cpproach as described in the Bases section, is also applied to a Method II 1 cssessment. No credit for a shielding factor (Sr) associated with residential structures is assumed. Concurrent meteorology with the release period may be ; utilized for the gamma atmospheric dispersion factor identified in ODCM Equation 7-3 (Section 7.2.1), and determined as indicated in Section 7.3.2 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. l i J O l l l i l O B.3-10 ODCM Rev. 16
3.5 HF.THOD TO CALCULATE THE SKIN DOSE RATE FROM NOBLE GASES Technical Specification 3.11.2.1 limits the dose rate at any time to the .
/] skin from noble gases at any location at or beyond the site boundary to 3,000 ares / year. The Technical Specification indirectly limits peak release rates V by limiting the dosa rate that is predicted from continued release at the peak rate.
I By limiting be m to a rate equivalent to no more than 3,000 aren/ year, we assure that the skin dose accrued in any one year by any member of the general public is less than 3,000 mram. Since it can be expected that the peak release rate on which ! baa is deriv 9d would not be exceeded without corrective action being taken to ! lower it, tha resultant average release rate over the year is expected to be considerably less than the peak release rate. l l l Un Method I or Method IA first to calculate the Skin Dose Rate from peak j roles:;. rate via station vents. Method I applies at all release rates. l ; Use Method II if a more refined calculation of baa is desired by the station ! use of actual release point parameters with annual or actual meteorology to i.e., l o(btain release-specific X/Qs) or if Method I or Method IA predicts a dose rate , greater than the Technical Specification limit to determine if it had actually been I exceeded during a short time interval. See Section 7.2.2 for basis. , 1 Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant vent noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site dose rate limit, or a value below it. Determinations of dose rate for compliance with Technical Specifications are performed when the effluent monitor alarm setpoint is exceeded. 3.5.1 Method I For an off-site receptor and elevated effluent release, the Skin Dose Rate due to noble gases is: Deinc.)" (Qi
- DF'ig.3 )
(3-4a) arem , p 901 arem-see yr ,s e c, , pci-yr , where bgag,3 - the off-site skin dose rate (ares /yr) due to noble gases in an effluent discharge from an elevated release point, Q3
- as defined previously, and D6c.3 - the combined skin dose factor for elevated discharges (see j Table B.1-10).
O l B.3-11 ODCM Rev. 16
3.5 METHOD TO CALCUIATE THE SKIN DOSE RATE FROM NOBLE GASES 3.5.1 Method I (Continued) For an off-site receptor and ground level release, the skin dose rate due to noble gases is: 0, kin (s)~h(Di eDIgg,3) (3-4b) where 6,ging,3 - The off-site skin dose rate (arem/yr) due to noble gases in an effluent discharge from a ground level release point, Qi - as defined previously, and DI ig,3 - The combined skin dose factor for ground level discharges (see Table B.1-10). For an on-site receptor at the Science & Nature Center and elevated release conditions, the skin dose race due to noble gases is: 0,gigg,3 - 0.0014 * (Qi*DIgt3) i (3-4c) where b aktarc.) - The skin dose rate (arem/yr) at the Science & Nature Center due to noble gases in an elevated release, Qi - as defined previously, and DIgg,3 i
- the combined skin dose factor for elevated discharges (see Table B.1-13).
For an on-site receptor at the Science & Nature Center and ground level release conditions, the skin dose rate due to noble gases is: 6,rinzg,3 - 0.0014 * (Qi
- DIz(s))
t (3-4d) there 0,gingg,3 - the skin dose rate (arem/yr) at the Science & Nature Center due to noble gases in a ground level release, Qi - as definet, previously, and DIggg,3 - The combined skin dose factor for ground level discharges (see Table B.1-13). O B.3 12 ODCM Rev. 16
3.5 METHOD TO CALCULATE THE SKIN DOSE RATE FROM NOBLE CASES 3.5.1 Method I (Continued) For an on-site receptor at the " Rocks" and elevated release conditions, the ; skin dose rate due to noble gases is: Dainac.3 - 0.0076 * (Qi
- DIgg,3) i (3-4e) where baigg,3 - the skin dose rate at the " Rocks" due to noble gases in an elevated release, Qi - as defined previously, and DIgg,3 i
- The combined skin dose factor for elevated discharges (see Table B.1-13).
For an on-site receptor at the " Rocks" and ground level release conditions, the skin dose rate due to noble gases is: Daigg 3 - 0.0076 e (Q + DIa(s)) i t (3-4f) i where baigt,3 - the skin dose rate (area /yr) at the " Rocks" due to noble gases in ph a ground level release, Qi - as defined previously, and dini (s) - the combined skin dose factor for ground level discharges (see Table B.1-13). Equations 3-4a through 3 4f can be applied under the following conditions (otherwise, justify Method I or consider Method II).
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via any station vent to the atmosphere.
Method IA is implemented by the EMS software as described in Appendix C. Caseous release models are detailed in Section 6.7.3 of the EMS Software Requirements Specification (Attachment 3 of Appendix C). O B.3-13 ODCM Rev. 16
3.5 METHOD TO CALCUIATE THE SKIN DOSE RATE FROM NOBLE GASES 3.5.2 Method II Method II consists of the model and input data (skin dose factors) in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or essumptions have been identified in the ODCM. The general equation (B-9) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I cpproach as described in the Bases section, is also applied to a Methed II cssessment, no credit for a shielding factor (Sr) associated with residential structures is assumed. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispersion factor and undepleted atmospheric dispersion factor identified in ODCM Equation 7-8 (Section 7.2.2), and determined as indicted in Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. 1 9l l l l l l l B.3-14 ODCM Rev. 16
1 3.6 METHOD TO CAlfUIATE THE CRITICAL ORGAN DOSE RATE FROM IODINES, TRITIUM j AND PARTICUIATES WITH Tgf CREATER THAN 8 DAYS a Technical Specification 3.11.2.1 limits the dose rate at any time to any organ from 1811, issy, sH and radionuclides in particulate form with half lives greater j than 8 days to 1500 aren/ year to any organ. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued i release at the peak rate. By limiting b,, to a rate equivalent to no more than 2 1500 area / year, we assure that the critical organ dose accrued in any one year by any member of the general public is less than 1500 area. l Use Method I or Method IA first to calculate the Critical Organ Dose Rate from ]
; the peak release rate via the station vents. Method I applies at all release rates.
1 ! Use Method II if a more refined calculation of 6,, is desired by the station (i.e. , use of actual release point parameters with annual or actual meteorology to i l obtain release-specific X/Qs) or if Method I or Method 'IA predicts a dose rate j greater than the Technical Specification 1imit to determine if it had actually been
- exceeded during a short time interval. See Section 7.2.3 for basis.
i 3.6.1 Method I The Critical Organ Dose Rate to an off-site receptor and elevated release condities can be determined as follows: N D,,c.) - (4
- DFGge,(,))
( area)yr
,g 4 pCi) see
, (arem-sec) pCL-yr where j b,,c,3 - The off-site critical organ dose rate (mrem /yr) due to iodine, tritium, and particulates in an elevated release, Qi
- the activity release rate at the station vents of radionuclide "i" in pCi/sec (i.e., total activity measured of radionuclide "i" averaged over the time period for which the filter / charcoal sample collector was in the effluent stream. For 1 - Sr89 or Sr90, use the best estimates, such as most recent measurements),
and Df 7 3 g ,3 = the site specific critical organ dose rate factor ( arem-sec) for an elevated gaseous release (see Table B.1-12) . pci-yr O B.3-15 ODCM Rev. 16
l 3.6 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE RATE FROM 10 DINES, TRITIUM AND PARTICULATES WITH Tua CREATER THAN 8 DAYS 3.6.1 Method I (Continued) For an off-site receptor and ground level release, the critical orSan dose rate can be determined as follows: 6,,c,3- (Qi DFG'i .c,3) (3-5b) where 6,,c,3 - the off-site critical organ dose rate (mrem /yr) due to iodine, tritium, and particulates in a ground level release, Qi - as defined previously, and DFG[,,g,3- the site-specific critical organ dose rate factor for a ground level gaseous discharge (see Table B.1-12). For an on-site receptor at the Science & Nature Center cnd elevated release conditions, the critical organ dose rate can be determined as follows: I beor< ) - 0.0014 * { (Qi DFG1,gg,3) (3-Sc) l where 1 6,,gg,3 - The critical organ dose rate (mrem /yr) to a receptor at the 1 Science & Nature Center due to iodine, tritium, and particulates in an elevated release, Qi
- as defined previously, and DFG'seort ) - the Science & Nature Center-specific critical organ dose rate I factor for an elevated discharge (see Table B.1-14). l
\
I 1 l l l
@1 B.3-16 ODCM Rev. 16 l l
l l
- - . - . .- -_, _ -_ .- .- - _~ . . - _.
I 3.6 METHOD TO CALCULATE THE CRITICAL ORGAN DOSE RATE FROM 10 DINES TRITIUM AND FARTICUIATES WITH Tu2 GREATER THAN 8 DAYS 3.6.1 Method I (Continued) For an on-site receptor at the Science & Nature Center and ground level release conditions, the critical orSan dose rate is: b,,gg,3 - 0.0014 (Qi
- DFGleor(s)) (3-5d) where 6,,gg,3 - the critical organ dose rate (area /yr) to a receptor at the Science & Nature Center due to iodine, tritium, and particulates in a ground level release.
Qi - as defined previously, and DFGleor(s) - the Science & Nature Center-specific critical organ dose rate factor for a ground level discharge (see Table B.1-14) . For an on-site receptor at the " Rocks" and elevated release conditions, the critical organ dose rate is: Decat.)= 0.0076 * (Qi
- DFGleont.)) (3-Se) where 0,g g,3 - The critical or8an dose rate (area /yr) to a receptor at the j
" Rocks" due to iodine, tritium, and particulates in an elevated release.
Qi - as defined previeusly, and DFGleont.) - the " Rocks"-specific critical organ dose rate factor for an elevated discharge (see Table B.1-15). For an on-site receptor at the " Rocks" and ground level release conditions, the critical organ dose rate is: Dcom(s) - 0.0076 * (Qi
- DFGleac,3) (3-Sf) where bn ee and Qi - are as defined previously, and DFC coa (s) - the " Rocks"-specific critical organ dose rate factor for a ground level discharge (see Table B.1-15).
A B.3-17 ODCM Rev. 16
3.6 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE RATE FROM IODINES, TRITIUM AND PARTICUIATES WITH Tu2 GREATER THAN 8 DAYS 3.6.1 Method I (Continued) Equations 3-Sa through 3-5f can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency event), and
- 2. Tritium, I-131 and particulate releases via monitored station vents to the atmosphere.
Method IA is implemented by the EMS software as described in Appendix C. Caseous release models are detailed in Section 6.7.3 of the EMS Software Requirements Specification (Attachment 3 of Appendix C). 3.6.2 Method II Method II consists of the models, input data and assumptions in Appendix C of Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or cssumptions have been identified in the ODCM (see Tables B.7-2 and B.7-3). The critical organ dose rate will be determined based on the location (site boundary, nearest resident, or farm) of receptor pathways as identified in the most recent ennual land use census, or by conservatively assuming the existence of all pathways (ground plane, inhalation, ingestion of stored and leafy vegetables, milk, and meat) ct an off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance with Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. The maximum critical organ dose rates will consider the four age groups independently, < cnd take no credit for a shielding factor (S F) associated with residential atructures. j 1 l l l 9 B.3-18 ODCM Rev. 16
3.7 METHOD TO CALCULATE THE GAMMA AIR DOSE FROM NOBLE GASES Technical Specification 3.11.2.2 limits the gamma dose to air from noble gases at any location at or beyond the site boundary to 5 mrad in any quarter and 10 mrad b in any year per unit. Dose evaluation is required at least once per 31 days. l Use Method I or Method IA first to calculate the gamma air dose from the station gaseous effluent releases during the period. Use Method II if a more refined calculation is needed (i.e. , use of actual release point parameter with annual or actual meteorology to obte,in release-specific l X/Qs), or if Method I or Method IA predicts a dose greater than the Technical Specification limit to determine if it had actually been exceeded. See Section 7.2.4 for basis. l 3.7.1 Method I The general form of the gamma air dose equation is: D!i, - 3.17E-02 * [X/Q]b * (3-6) t-* * { (Qi
- DFi)
PCi-yr 's e c' * ( mrad-mi (arad) = , ) * { (pCi) p
,Gi-sec, ,pCi-yr, where D',1, is the gamma air dose.
3.17E-02 is the number of pCi per pCi divided by the number of second (/ per year, [X/Q]b is the 1-hour gamma atmospheric dispersion factor, t-* is a unitiess factor which adjusts the 1-hour (X/Q]7 value for a release with a total duration of t hours, Qi is the total activity in pCi of each radionuclide ai" released to the atmosphere from the station gaseous effluent release point during the period of interest, and DF1 1 is the gamma dose factor to air for radionuclide "i" (see Table B.1-10). Incorporating receptor location-specific atmospheric dispersion factors ([X/Q]'), adjustment factors (t**) for elevated and ground level effluent release conditions, and occupancy factors when applicable (see Section 7.2.7), yields a series of equations by which the gamma air dose can be determined.
- a. Maximum off-site receptor location, elevated release conditions:
(3-6a) D!irc,3 = 3. 2E-07
- t-o.275 (q . 9 77)
O Ci-yr' *( mrad-m' 8 (b (arad) = P
,pci-m ,3
) * { (pC1)
,PCi-yr, B.3-19 ODCM Rev. 16
3.7 METHOD TO CALCUZATE THE CAMMA AIR DOSE FROM NOBLE GASES 3.7.1 Method I (Continued)
- b. Maximum off-site receptor location, ground-level release conditions:
(3-6b) D!irg,3 = 1. 6E-06
- t-o. ass . (qt , p77) mrad-m8, (arad) . PCi-yr 3
*( ) * { (pci) ,PCi-yr,
,pci-m ,
- c. Science & Nature Center receptor; elevated release conditions:
D!i,gg,3 = 4. 9E-10
- t-o.252 * (Qi
- DFI) (3-6c)
Ci-yr (arad) = ( PpCi-m3 ) * ( ) { (pci * "f*d~"8PCi-yr )
- d. Science & Nature Center receptor; ground-level release conditions:
Dji,gg,3 = 4.4E-09
- t-o.321 * { (Qi
- DFI) (3-6d) 3 (mrad) = ( PCi-yr) 3
*( ) { (pci
- mrad-m )
pCi-m P C L-yr
- e. Receptor at the " Rocks"; elevated release conditions:
Djirac 3 = 5.lE-09
- t-8153 * (Qi
- DFI) (3-6e) 8 Ci-yr ) { (pci
- mrad-m )
(mrad) = ( PpCi-m3 ) * ( pCi-yr I
- f. Receptor at the " Rocks"; ground-level release conditions:
DIirats) = 4. lE-08
- t-o.20' * { {Qi
- DFI) (3-6f) 3 (arad) = ( P C i-yr) * (
3
){ (pCie mrad-m )
pCi-m PCi-yr Equations 3-6a through 3-6f can be applied under the following conditions (otherwise justify Method I or consider Method II):
- 1. Normal. operations (nonemergency event), and
- 2. Noble gas releases via station vents to the atmosphere.
O I B.3-20 ODCM Rev. 16
3.7 METHOD TO CALCUMTE THE GAMMA AIR DOSE FROM NOBLE GASES 3.7.1 Method I (Continued) Method IA is implemented by the EMS sof tware as described in Appendix C. Caseous release models are detailed in Section 6.7.3 of the EMS Sof tware Requirements Specification (Attachment 3 of Appendix C). 3.7.2 ggghod II Method II consists of the models, input data (dose factors) and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or assumptions have been identified in the ODCd. The general equations (B-4 and B 5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section 7.2.4 are also applied to Method II assessments. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispersion factor identified in ODCK Equation 7-14, and determined as indicated in Section 7.3.2 for the release point (either ground level l or vent stack) from which recorded effluents have been discharged. ' l I (~~) V i l l l O V B.3-21 ODCM Rev. 16
3.8 METHOD TO CALCUIATE THE BETA AIR DOSE FROM NOBLE CASES Technical Specification 3.11.2.2 limits the beta dose to air from noble gases et any location at or beyond the site boundary to 10 mrad in any quarter and 20 mrad i in any year per unit. Dose evaluation is required at least once per 31 days. l Use Method I or Method IA first to calculate the beta air dose from gaseous l offluent releases during the period. Method I applies at all dose levels. { i I Use Method II if a more refined calculation is needed (i.e. , use of actual release point parameters with annual or actual meteorology to obtain l release-specific X/Qs) or if Method I or Method IA predicts a dose greater than the i Technical Specification limit to determine if it had actually been exceeded. See i Section 7.2.5 for basis. 1 3.8.1 Method I The general form of the beta air dose equation is: D{i,= 3.17E-02 * (X/Q)iu
- t-* * { (Q
- DF{)
i (3-7) l Ci-yr ' 's ec' f (mrad) = p P
,ci-sec,
~iT
* ( )e pCi* mrad-m pci-yr, where D8 i, is the beta air dose, 1
3.17E-02 is the number of pCi per pCi divided by the number of seconds l per year, 4 (X/Q)iu is the 1-hour undepleted atmospheric dispersion factor, t-* is a unitiess factor which adjusts the 1-hour X/Q value for a release with a total duration of t hours, l l Qi is the total activity (pCi) of each radionuclide "i" released to the atmosphere during the period of interest, and DF{ is the beta dose factor to air for radionuclide "i" (see Table B.1-10). Incorporating receptor location-specific atmospheric dispersion factor (X/Q), adjustment factors (t-*) for elevated and ground-level effluent release conditions, and occupancy factors when applicable (see Section 7.2.7) yields a series of equations by which the Beta Air Dose can be determined. l
- a. Maximum off-site receptor location, elevated release conditions:
D{3,g,3 = 4.1E-7
- t-0 3 * { (Qi
- DF{} (3-7a) 3 (mrad) = ( CP i-yr) *( ) { (pCi e mrad-m )
pCi-m 3 PCi yr l B.3-22 ODCM Rev. 16 l
4 3.8 METHOD TO CALCUIATE THE BETA AIR DOSE FROM NOBLE GASES , 3.8.1 Method I (Continued)
- b. Maximman off-site receptor location, ground-level release conditions:
DE,c 3 = 6.0E-06
- t-o.sts . (qt , pg) (3,73)
Ci-yr (arad) = ( PpCi-m3 ) * ( ) ( Ci * "Y*d~"8pCi-yr ) l : 1
- c. Science & Nature Center receptor; elevated release conditions:
l f D{i,gc.3 = 1.8E-09
- t-8 85 * { (Qi
- Dd) (3-7e) a
. J 3 (arad) = ( pCi-yr) *( ) (pCi
- arad-m )
l pCi-m 3 pCi-yr i l d. Science & Nature Center receptor; ground level release conditions: D{irr(s) = 2.4E-08
- t-8 8'? * (Qg
- DF{} (3-7d)
I h 8 Ci-yr j (arad) = ( PpCi-m 3 ) * ( ) { ( Ci
- mrad-m PCi-yr )
- e. Receptor at the " Rocks"; elevated release conditions:
D{ ira (*) = 3.9E-08
- t-o.24e , { (qt , ppf) (3 7 )
A U 8 (arad) = (PCi-yr) 3
*( ) (pCi e arad-m )
l pCi-m pCi yr l
- f. Receptor at the " Rocks"; ground-level release conditions:
i D{i,mg,3 = 4. 6E-07
- t-o.2er . (q, , pq) (3 7f) 8 Ci-yr ) { (pci
- mrad-m )
(arad) = ( PpCi-m3 ) * ( pC1-yr 4
)
N 4 B.3-23 ODCM Rev. 16
l 3.8 METHOD TO CALCULATE THE BETA AIR DOSE FROM NOBII GASES i ( 3.8.1 Method I (Continued) \ l Equations 3-7a through 3-7f can be applied under the following conditions l (otherwise justify Method I or consider Method II):
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via station vents to the atmosphere.
Method IA is implemented by the EKS software as described in Appendix C. Gaseous release models are detailed in Section 6.7.3 of the EMS Software Requirements Specification (Attachment 3 of Appendix C). 3.8.2 Method II Method II consists of the models, input data (dose factors) and assumptions in Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or cssumptions have been identified in the ODCM. The general equations (B-4 and B-5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section 7.2.5, are also applied to Method II assessments. Concurrent meteorology with the release period may be utilized for the atmospheric dispersion factor identified in ODCM Equotion 7-15, and i determined, as indicated in Sections 7.3.2 and 7.3.3 for the release point (either l ground level or vent stack) from which recorded effluents have been discharged. l l l O!l 1 I i
)
)
)
I l B.3-24 ODCM Rev. 16
i 3.9 METHOD TO CAlfUIATE THE CRITICAL ORGAN DOSE FROM IODINES, TRITIUM AND PARTICULATES O V Technical Specification 3.11.2.3 limits the critical organ dose to a member of the public from radioactive iodines, tritium, and particulates with half-lives greater than 8 days in gaseous effluents to 7.5 arem per quarter and 15 arem per year per unit. Technical Specification 3.11.4 limits the total body and organ dose 4 to any real member of the public from all station sources (including gaseous effluents) to 25 mrem in a year except for the thyroid, which is limited to 75 arem in a year. ! l Use Method I or Method IA first to calculate the critice.1 organ dose from ! gaseous effluent releases as it is simpler to execute and more conservative than Method II. Use Method II if a more refined calculation of critical organ doise is needed l (i.e. , Method I or Method IA indicates the dose is greater than the limit) . See Section 7.2.6 for basis. 3.9.1 Method I D, = (X/Q)$1/(X/Q)$P1
- t** * (Qi
- DFGi ,) (3-8)
(arem) = ( sec)f( sec) * ( ) * { (pci) * ( ) where [ D., is the critical organ dose from iodines, tritium, and particulates, (X/Q)@l is the 1-hour depleted atmospheric dispersion factor. l (X/Q)$P1 is the annual average depleted atmospheric dispersion. t** is a unitiess adjustment factor to account for a release with a total duration of t hours, Qi is the total activity in pCi of radionuclide "i" released to the atmosphere during the period of interest (for strontiums, use the most recent measurement), and 4 DFG i is the site-specific critical organ dose factor for radionuclide "ia, see Tables 3.1-12, B.1-14, and B.1-15. (For each radionuclide, it is the age group and organ with the lar8est dose factor.) 7 Incorporating receptor location specific atmospheric dispersica factors ((X/Q)@l and (X/Q)$P1) and adjustment factors (t**) for elevated and ground-level release conditions, and incorporating occupancy factors when applicable (see Section 7.2.7), yields a series of equations by which the critical organ dose can be determined. B.3-25 ODCM Rev. 16
3.9 METHOD TO CA14ULATE THE CRITICAL ORGAN DOSE FROM 10 DINES, TRITIUM AND PARTICUIATES 3.9.1 Method I (Continued)
- a. Maximum off-site receptor location, elevated release conditions:
D,,c,3 = 14. 8
- t-c.2s7 * { (Qi
- DFG 3,,g,3) (3-Ba)
(mrem) = ( )*( ) { (pCi * )
- b. Maximum off-site receptor location, ground-level release conditions:
D,,c,3 = 17.7
- t-0 *818 * { (Qi* DFG3,,g,3) (3-8b)
(arem) = ( )*( ) { (pCi * )
- c. Science & Nature Center receptor; elevated release conditions:
Dcorte) = 3. 3E-02
- t*0 8'8 * { (Qi e DFGicotte)) (3-8c)
(arem) = ( )*( ){ (pCi* )
- d. Science & Nature Center receptor; ground-level release conditions:
D.,gg,3 = 3. 3E-02
- t-0 847 * { (Q *i DFG ,ogg,3) 3 (3-8d)
(arem) = ( )*( ){ (pCi* ) O
- e. Receptor at the " Rocks"; elevated release conditions:
Deon(*) = 7. 3E-02
- t-o.zas * (Qi
- DFG ,ogg,3) (3 8e)
(mrem) = ( )*( ){ (pCi* )
- f. Receptor at the " Rocks"; ground-level release conditions:
Decats) = 8.6E-02
- t-o.2s7 * { (Q *i DFG ,ogg,3) 3 (3-8f)
(area) = ( )*( ){ (pci* ) Equations 3-8a through 3-8f can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (nonemergency event),
- 2. 'odine, tritium, and particulate releases via station vents to the atmosphere, and
- 3. Any continuous or batch release over any time period.
B.3-26 ODCM Rev. 16
3.9 METHOD TO CALCUIATE THE CRITICAL ORGAN DOSE FROM IODINES, TRITIUM AND PARTICUlATES 3.9.1 Method I (Continued) Method 1A is implemented by the EMS software as described in Appendix C. Caseous release models are detailed in Section 6.7.3 of the EMS Software Requirements Specification (Attachment 3 of Appendix C). 3.9.2 Method II Method II consists of the models, input data and assumptions in Appendix C of Regulatory Guide 1.109. Rev. 1 (Reference A), except where site-specific data or assumptions have been identified in the ODCM (see Tables B.7-2 and B.7-3) . The critical organ dose will be determined based on the location (site boundary, nearest resident, or farn) of receptor pathways, as identified in the most recent annual land use census, or by conservatively assuming the existence of all pathways (ground plane, inhalation, ingestion of stored and leafy vegetables, milk and meat) at an off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance with Sections 7.3.2 and 7.3.3 for the release point (either ground level or vent stack) from which recorded effluents have been discharged. The maximum critical organ dose vill consider the four age groups independently, and use a shielding factor (S )F of 0.7 associated with residential structures. O b A i i O B.3-27 ODCM Rev. 16 l l
3.10 METHOD TO CALCUIATE DIRECT DOSE FROM PLANT OPERATION Technical Specification 3.11.4 restricts the dose to the whole body or any organ to any member of the public from all uranium fuel cycle sources (including direct radiation from station facilities) to 25 mrem in a calendar year (except the thyroid, which is limited to 75 mrem). It should be noted that since there are no uranium fuel cycle facilities within 5 miles of the station, only station sources need be considered for determining compliance with Technical Specification 3.11.4. 3.10.1 Method The direct dose from the station will be determined by obtaining the dose from TLD locations situated on-site near potential sources of direct radiation, as well as those TLDs near the site boundary which are part of the environmental monitoring program, and subtracting out the dose contribution from background. Additional methods to calculate the direct dose may also be used to supplement the TLD information, such as high pressure ion chamber measurements, or analytical design calculations of direct dose from identified sources (such as solid waste storage facilities). The dose determined from direct measurements or calc'*1ations will be related to the nearest real person off-site, as well as those individuals on-site involved in activities at either the Education Center or the Rocks boat landing, to assess the contribution of direct radiation to the total dose limits of Technical Specification 3.11.4 in conjunction with liquid and gaseous effluents. 1 O l O B.3-28 ODCM Rev. 16
3.11 DOSE PROJECTIONS Technical Specifications 3.11.1.3 and 3.11.2.4 require that appropriate O portions of liquid and gaseous radwaste treatment systems, respectively, be used to reduce radioactive effluents when it is projected that the resulting dose (s) would exceed limits which represent small fractions of the *as low as reasonably achievable" criteria of Appendix I to 10CFR Part %. The surveillance requirements l of these Technical Specifications state that dose projections be performed at least once per 31 days when the liquid radwaste treatment systems or gaseous radwaste treatment systems are not being fully utilized. Since dose assessments are routinely performed at least once per 31 days to account for actual releases, the projected doses shall be determined by comparing I the calculated dose from the last (typical of expected operations) completed 31-day period to the appropriate dose limit for use of radwaste equipment, adjusted if appropriate for known or expected differences between past operational parameters and those anticipated for the next 31 days. 3.11.1 Liould Dose Projections The 31-day liquid dose projections are calculated by the following:
- a. Determine the total body Da and organ dose D. (Equations 3-1 and 3-2, respectively) for the last typical completed 31-day period. The last )
typical 31-day period should be one without significant identified I operational differences from the period being projected to, such as full l power operation vs. periods when the plant is shut down. < 1
- b. Calculate the ratio (R 3) of the total estimated volume of batch releases )
expected to be released for the projected period to that actually ' V released in the reference period. 1
- c. Calculate the ratio (R 2 ) of the estimated gross primary coolant activity for the projected period to the average value in the reference period.
Use the most recent value of primary coolant activity as the projected value if no trend in decreasing or increasing levels can be determined.
- d. Determine the projected dose from:
Total Body: Da ,,- Da . R3 .R Max. Organ: D ,,,- D. . R 3 .R The ENS, software can also be used to perform monthly projected dose calculations W described in Appendix C. The methodology applied by EPJi in projecting lignid doses is outlined in Section 2.7 of Attachment 4 to Appendix C (EMS Technic d Reference Manual). 3.11.2 Gaseous Dose Proiections For the gaseous radwaste treatment system, the 31-day dose projections are calculated by the following:
- a. Determine the gamma air dose D L (Equation 3-6a), and the beta air dose 08 ,
(Equation 3-7a) from the last typical 31-day oper.ating period. B.3-29 ODCM Rev. 16
i 3.11 DOSE PROJECTIONS ; l 3.11.2 Gaseous Dose Proiections
- b. Calculate the ratio (R 3) of anticipated number of curies of noble gas to '
be released from the hydrogen surge tank to the atmosphere over the next 31 days to the number of curies released in the reference period on . which the gamma and beta air doses are based. If no differences between ! the reference period and the next 31 days can be identified, set R3 to 1. I
- c. Determine the projected dose from:
Gamma Air: D!g, ,, = Dig, . R 3 ; Beta Air: D{t, ,, = D{g, . R 3 ) For the ventilation exhaust treatment system, the critical organ dose from iodines, tritium, and particulates are projected for the next 31 days by the following:
- a. Determine the critical organ dose D e, (Equation 3-8a) from the last typical 31-day operating period. (If the limit of Technical Specification 3.11.2.4.c. (i.e. , 0.3 mrem in 31 days) is exceeded, the projected controlled area annual total effective dose equivalent from all station sources should be assessed to assure that the 10CFR20.1301 dose limits to members of the public are not exceeded.)*
- b. Calculate the ratio (R )4of anticipated primary coolant dose equivalent I-131 for the next 31 days to the average dose equivalent I-131 level during the reference period. Use the most current determination of DE '
I-131 as the projected value if no trend can be determined,
- c. Calculate the ratio (R 3 ) of anticipated primary system leakage rate to the average leakage rate durin5 the reference period. Use the current value of the system leakage as an estimate of the anticipated rate for the next 31 days if no trend can be determined.
- d. Determine the projected dose from:
Critical Organ: D., ,, - D , . R 4 . R$ The EMS software can also be used to perform monthly projected dose calculations as described in Appendix C. The methodology applied by EMS in projecting gaseous dose is outlined in Section 3.8 of Attachment 4 to Appendix C (EMS Technical Reference Manual). O B.3-30 ODCM Rev. 16
3.11 DOSE PROJECTIONS 3.11.2 Casaous Dosa Proiactions (Continued) l Note: This action is based on the assumption that tritium is the controlling nuclide for whole body exposures through the inhalation pathway. Maximum annual average on-site X/Q's for station effluent release points are approximately 100 times the values used for the site boundary dose calculations. However, i che site boundary doses calculated by the ODCM for iodines, tritium, and particulates with half lives greater than 8 days, includes all potential j off-site exposure pathways. For tritium, the inhalation pathway only accounts - for 10% of the total dose contribution being calculated. As a result, if the . monthly calculation indicates that the site boundary maximum organ dose reached 0.3 area, the on-site maximum dose due to inhalation would be i approximately 3.0 mrea for this period. If this were projected to continue j for a year with a 2000 hour occupancy factor applied, the projected inhalation f whole body dose would be approximately 8 area, or 81 of the 10CFR20.1301 j limit. This is a reasonable tri5 ger value for the need to consider the dose
- contribution from all station sources to members of the public in controlled
- areas.
a i i i lO i l l i J O B.3-31 ODCM Rev. 16
- _ - _ _ ~ - _ . -- - _ _ - . . - - _ . . - .. - ____ . - _ _ - -.
a 0 i 4.0 RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAN ! The radiological environmental monitoring stations are listed in Table B.4-1. The locations of the stations with respect to the Seabrook Station are shown on the 4 maps in Figures B.4-1 to B.4-6. i Direct radiation measurements are analyzed at the station. All other l radiological analyses for environmental samples are performed at the Yankee l Environmental Laboratory. The Yankee Environmental laboratory participates in the
- U.S. Environmental Protection Agency's Environmental Intercomparison Studies Program j for all relevant species in an aqueous (water) matrix. An independent vendor (Analytics) supplies the remaining cross check samples. These samples are presented on an air filter and in milk and water matrices.
i
- Pursuant to Specification 4.12.2, the land use census will be conducted l 'during the growing season" at least once per 12 months. The growing season is defined, for the purposes of the land use census, as the period from June 1 to October 1. The method to be used for conducting the census will consist of one or more of the following, as appropriate
- door-to-door survey, visual inspection from roadside, serial survey, or consulting with local agricultural authorities.
Technical Specification 6.8.1.3 requires that the results of the Radiological Environmental Monitoring Program be summarized in the Annual Radiological Environmental Operating Report 'in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, 1979." The general table format will be used with one exception and one clarification, as follows. The mean and range values will be based not upon detectable measurements only, as specified in the NRC Branch Technical Position, but upon all measurements. This will prevent the positive bias associated with the calculation of the mean and range based upon detectable measurements only. Secondly, the Lower Limit of Detection column will specify the LLD required by ODCM Table A.5-2 for that radionuclide and sample medium. l l l 1 EI 4 i
)
l l l O B.4-1 ODGM Rev. 16
TABLE B.4-1 RADIOLOGICAL ENVIRONMENTAL MONITORING STATIONj(f Distance From Exposure Pathway Sample Location Unit 1 Direction From and/or Sample and Desirnated Code Containment (km) the Plant l 1. AIRBORNE (Particulate and Radiciodine) ) AP/CF-01 PSNH Barge 2.7 ESE Landing Area l AP/CF-02 Harbor Road 2.7 E AP/CF-03 SW Boundary 0.8 SW AP/CF-04 W. Boundary 1.0 W AP/CF-05 Winnacunnet H.S.(b3 4.0 NNE AP/CF-06 Georgetown 24.0 SSW i Substation (Control) l i
- 2. WATERBORNE
- a. Surface US-01 Hampton-Discharge Area 5.3 E WS 51 Ipswich Bay (Control) 16.9 SSE
- b. Sediment SE-02 Hampton-Discharge Area tb) 5.3 E l SE-07 Hampton Beach (b) 3.1 E i SE-08 Seabrook Beach 3.2 ESE l SE-52 Ipswich Bay (Control)(b) 16.9 SSE SE-57 Plum Island Beach 15.9 SSE (Control)(b)
- 3. INGESTION
- a. Milk TM-04 Salisbury, MA 5.2 SW l TM-09 Hampton, NH 5.5 NNW TM-15 Hampton Falls, NH 7.0 NW TM-16 Kensington, NH(b) 7.7 WNW l TM-20 Rowley, MA (Control) 16.3 S
- b. Fish and Invertebrates (*)
FH-03 Hampton - Discharge 4.5 ESE Area FH-53 Ipswich Bay (Control) 16.4 SSE HA-04 Hampton - Discharge 5.5 E Area HA-54 Ipswich Bay (Control) 17.2 SSE MU-06 Hampton - Discharge 5.2 E Area MU-56 Ipswich Bay (Control) 17.4 SSE O B.4-2 ODCM Rev. 16
. . _ _ _ . . . _ . _ _ . . _ . . _ . _ _ _ _ m _ . _ . . _ . _ . _ _ _ _ _ _ _ _ _ _ . _ - _ . . . . _ _ _ . _ .m i
A i j TABLE B.4-1
] RADIOIDGICAL ENVIRONMENTAL MONITORING STATIONSW (Continued) ;
1 e l Exposure Distance From Direction From Pathway and/or Sample Location Unit 1 Direction From ! 1 M mad Damirnated C & Containment (km) the Plant ;
- 4. DIRECT RADIATION j TL-1 Brimmer's Lane, 1.1 N j 1 Hampton Falls i 1 TL-2 Landing Rd., Hampton 3.2 NNE )
3 TL 3 Glade Path, Hampton 3.1 NE j Beach } TL 4 Island Path, Hampton 2.4 ENE (
- Beach ;
TL-5 Harbor Rd., Hampton 2.7 E ; Beach j ' PSNH Barge Landing 2.7 TL-6 ESE Area , e TL Cross Rd. , Seabrook 2.6 SE i ! Beach l TL-8 Fara Lane, Seabrook 1.1 SSE l TL-9 Farm Lane, Seabrook 1.1 S
- TL-10 Site Boundary Fence 1.0 SSW ,
l TL-11 Site Boundary Fence 1.0 SW TL-12 Site Boundary Fence 1.0 WSW TL-13 Insida Site Boundary 0.8 W 1.1 TL-14 Trailer Park, Seabrook WNW , ] 4 TL-15 Brimmer's Lane, 1.4 NW ^ l Hampton Falls j TL-16 Brimmer's Lane, 1.1 NNW i Hampton Falls l TL-17 South Rd., N. Hampton 7.9 N TL-18 Mill Rd., N. Hampton 7.6 NNE TL-19 Appledore Ave., 7.9 NE $ N. Hampton i TL-20 Ashworth Ave., 3.4 ENE
' Hampton Beach i TL-21 Route 1A, Seabrook 2.7 SE
- Beach
! TL-22 Cable Ave., 7.6 SSE ) g Salisbury Beach J ;' TL-23 Ferry Rd. , Salisbury 8.1 S l TL-24 Ferry Lots Lane, 7.2 SSW i Salisbury TL-25 Elm St. , Amesbury 7.6 SW ), TL-26 Route 107A, Amesbury 8.1 WSW i l J l B.4-3 ODCM Rev. 16
TABLE B.4-1 RADIOM)GICAL ENVIRONMENTAL MONITORING STATIONS ta) (Continued) Exposure Distance From Direction From Pathway and/or Sample Location Unit 1 Direction From Sample and Designated Code Containment (km) the Plant TL-27 Highland St., 7.6 W S. Hampton TL-28 Route 150, Kensington 7.9 WNW TL-29 Frying Pan Lane, 7.4 NW Hampton Falls l T1-30 Route 27, Hampton 7.9 NNW TL-31 Alumni Drive, Hampton 4.0 NNE TL-32 Seabrook Elementary School 1.9 S TL-33 Dock Area, Newburyport 9.7 S TL-34 Bow St., Exeter 12.1 NW TL-35 Lincoln Ackerman School 2.4 NNW TL-36 Route 97, Georgetown 22.0 SSW (Control) TL-37 Plaistow, NH (Control) 26.0 USW TL-38 Hampstead, NH (Control) 29.0 W TL-39 Fremont, NH (Control) 27.0 WNW TL-40 Newmarket, NH (Control) 24.0 NNU TL-41 Portsmouth, NH 21.0 NNE (Control)(b) TL-42 Ipswich, MA (Control) 27.0 SSE (a) Sample locations are shown en Figures B.4-1 to B.4-6. (b) This sample location is not required by monitoring program defined in Part A of ODCM; program requirements specified in Part A do not apply to samples taken at this location. (c) Samples will be collected pursuant to ODCM Table A.5-1. Samples are not required from all stations listed during any sampling interval (FH - Fish; l HA - lobsters; MU - Mussels). Table A.5-1 specifies that "one sample of three commercially and recreationally important species" be collected in the vicinity of the plant discharge area, with similar species being collected at a control location. (This wording is consistent with the NRC Final Environmental Statement for Seabrook Station.) Since the discharge area is off-shore, there is a great number of fish species that could be considered commercially or recreationally important. Some are migratory (such as striped bass), making them less desirable as an indicator of plant-related radioactivity. Some pelagic species (such as herring and mackerel) tend to school and wander throughout a large area, sometimes making catches of significant size difficult to obtain. Since the collection of all species would be difficult or impossible, and would provide unnecessary redundancy in terms of monitoring important pathways to man, three fish and invertebrate species have been specified as a minimum requirement. Samples may include marine fauna such as lobsters, clams, mussels, and bottom-dwelling fish, such l as flounder or hake. Several similar species may be grouped together into one j sample if sufficient sample mass for a single species is not available after a ! reasonable effort has been made (e.g., yellowtail flounder and winter flounder). ! B.4-4 ODCM Rev. 16
l FIGURE 5.4-1 RADTOTACICAT. ENVIRONMDrrAY. MONITORING TACATIONS ' WITHIN 4 KITAMET m OF SEARROOK STATION I I i r 1 i N \ 4 4 h
\
\
i j \ i b~p ) '%., ,
\
( 3 RIVER 1 i ' ) , l , SEAgno0K % L STATION g L a n( AP/cF42 A AP/CF43 A 4 I ( . t AP/CF-01'A i # sE-08 A
/
5 5 \ y 5' 4
\
i-8 \ i 1 M N k 0 500 1000
#4 g
\ METERS ff N ! i D J O B.4-5 ODCM Rev. 16 i 4
FIGURE B .40 2 RADIOLOGTCAL ENVIRONMENTAL MONITORING IDCATIOh3 BETVEEN 4 KITRETERS AND 12 KIlfMETERS FROM SEABROOK STATION O
$ 0 5 KILOMETERS E
N 5 8 N RYE BEACH l TM-09 A .- TM-15 A SEE ENLARGEMENT IN FIGURE B.4-1 % A AP/CF-05
. t - - - - -
t I l Tu . t A
. {
e d li : u - IWIPTON BEACH
! lASE-07 SEAEROoK S ATION e A& DISCHARGE SITE WS-01 l SE-02 m-06
- e
', ~FM-03 HA-04
$ u Rooc s uCH s.4 ,
; s, ,' ;
~~~, ,.- - - _%,/- a .
TM-04 A SAL'SBURY I BEACl! O MAC @ t O ATLANTIC OCEAN ) B.4-6 ODCM Rev. 16 O
FIGURE B.4-3 RADIOIDGICAL ENVIRONMENTAL MONITORING IDCATIONS 4 OUTSIDE 12 KIIBMETm OF SEABROOK STATION i O b \. f 0 5 10 15 l - KILOMETERS - i a YORK l OURHAM e
.\ UVQ NEWMARKET e 80RT5 MOUTH e _.g j
i RAYMOND EPPING \.
. s,
.I I +\,h ____g.__________ , ee J J l . aErER SEE ENLARGEMENT IN FIGURE : i J l 8.4-2 ' WPTM , i e , I , j 8 SEA 8R00K STATION g ' : 4 KINGSTON e I + M ON M R I T i f I I SEA 8R00K ,e I r l DISCHARGE SITE
', s. .
. SAU58URY f i j
, ,-lAME18vRre i
, i etAISTow e . i ' i
/ I
' / .-.,f.ij M Myg. .NEWSURYPORT e . 8 ATLANTIC OCEAN
.i __________---- _-_ t I HAVERMILLe , j ,
SE-57 I
' " ' 'j TM-20 I , . PLUM ISLAND FM-53 AP/CF-06 A A SE-52 METHUEN e A WS-51 e LAWRENCE !*SWICH 8AY [ '
IP5WICH e A MU-56 MA-54 I l GLOUCESTER
- O J
B.4-7 ODCM Rev. 16 A
FIGURE B.4-4 DIRECT RADIATION MONITORING IACATIONS VITHIN 4 KIIAMETERS OF SEABROOK STATION N NNE O' NNW _ -- A TL-2 NE NJ b
\
l 5
-- N-35A TL i A TL-3 ,
J A TL-4 ENE e gn ^ I18 A TL-1
'4 Sp WNW TL-14 A yg se % E W TL-13 A h k TL-5 4 HAMPTON HMtSOR TL-12 A y TL-11 A H S IS , CREEK
( A N TL-10 A TL-8
]- ~
A A ESE g TL-g
- E ATL-7 h
gj TL-32 A ==
*s su q
s 2 u 1 f 0 500 1000 3; { f METERS 4 N j ssw s ssE sE B.4-8 ODCM Rev. 16 O i
. .~ .. - - _ - . . . . . _ _ - ~ .. _ . ~ . - . . . . . . - . . - . . _ . . . . - . . . . . . . . - . - . . .
FICURE R.4-5 DIRECT RADIATION MONITORING IDCATIONS BEIVEEN 4 KIIDMETFRM AND 12 KIIDMETERE FROM SEABROOK STATION
=,NNW N NNE j
)J 2 0 w 5
=i - -
KLCMETERS ] o ] M i NW I
- & NE 4
A TL-34 N
! Miles \ J "A RTE BEACH
'A TL-17 A TL-30 TL-18 A TL-19
[ l WNW , A TL-2sg
\
h - ENE i SEE ENLARGEMEIT IN FIGURE B.4-4
/
A TL-28 _ h _ A I.'-3 Li i
/ / asa -
n / ! SEA 8200K STATION s I W A TL-17 DISCHARGE SITE l -
. . .. : j N.'
, SEA 8R00X SEACM
- - i /
TL-26 i N , i
,,,. 8 - - - N, -
- WsW
' 7\k 5 58URY LEACH
' TL-24 A it-zz A) N O ~A
- o l #Darme. Wit L SE 7'-33 A l
) ATLANTIC ocean SW 1
SSW 3
\ SSE \
iO B.4 9 ODCM Rev. 16 4
. .- . - - - . - . _. _ = . .-. 1 FICURE B.4-6 l DIRECT RADIATION MONITORING IACATIONS OUTSIDE i 12 KIIDMETERS OF SEABROOK STATION NNW NiI NNE O o 5 10 ~15 gf j gy KILONETERS YORX
\ CURHAM e s e
NE
\ s TL -40 A 41
\ NE'4 MARKET e CRTSNOUTHe ' .g
"':ca on.
e N 10 1 tat - s gg i
\.$
i i Y \' GE FREMONT g i TL-394 e
' N e crita SEE BLAAGDIST IN FIGunt l J 8.4-5 e- -
l l 5tA8R00K STATI l W KINGSTCNe l sana 00x e I l OtsCuasi stir r E g
/rt.3, i . g;_,, fXn..
PtAISTFJ e. , i TL-37 A *
/ ' 8 ESE I
NWMU . I ATLANTIC OC DN WSW { KAVERHILLe I
,...j . PLUM !stANO ETHUEN . TL-36 A
.__ _T ,,
tPsvIcx e grt-4 l l 3 sW J ssu s sss&e\stouctsTE B.4-10 ODCM Rev. 16 O
?
I 5.0 SETPOINT DETERMINATIONS Chapter 5 contains the methodology for the calculation of effluent monitor l l setpoints to implement the requirements of the radioactive effluent monitoring i systems Technical Specifications 3.3.3.9 and 3.3.3.10 for liquids gases, . , respectively. Example setpoint calculations are provided for each of the required effluent i monitors. , j 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS , 4 i Technical Specification 3.3.3.9 requires that the radioactive liquid effluent l instrumentation in Table 3.3-12 of the Technical Specifications have alarm setpoints ! in order to ensure that Technical Specification 3.11.1.1 is not exceeded. Technical 1 Specification 3.11.1.1 limits the activity concentration in liquid effluents to the , appropriate MPCs in 10CFR20 and a total noble gas MPC. ; i 5.1.1 Liauid Waste Test Tank Monitor (RM-6509) t The ligt id waste test tank effluent monitor provides alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 to the environment. It is also used to monitor discharges from various waste sumps to the environment. p 5.1.1.1. Method to Determine the Setnoint of the Liould Waste Test Tank Monitor ) (RM-6509) : I The instrument response (pCi/al) for the limiting concentration at the point of discharge is the setpoint, denoted R .sptos, and is determined as follows: l O R .tyg,e - ft Ct (5-1) i (pCi/ml) ( ) ( ) ( ) where: F DF -
- Dilution factor (dimensionless) (5-2)
F. - Flow rate past monitor (gpa) F4
- Flow rate out of discharge tunnel (gpa)
DF,n - Minimum allowable dilution factor (dimensionless) ft - 1 - (f + f3 + f ); where ft is the fraction of the total contribution of MPC at the discharge point to be associated with the test tank effluent pathway and, fa, f 3 , and f. are the similar fractions for Turbine Building sump, steam generator blowdown, and primary component cooling pathways, respectively: (fg + f + f3 + f. 5 1) . O ! B.5-1 ODCM Rev. 16
l 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS 5.1.1.1. Method to Determine the Setroint of the Liould Waste Test Tank Monitor (RM-6509) (Continued) DF,i, = (5-3) O MPCs
- MPC for radionuclide "i" from 10CFR20, Appendix B Table II, Column 2 (pCi/al). In the event that no activity is expected to be discharged, or can be measured in the system, the liquid monitor setpoint should be based on the most restrictive MPC for an " unidentified" mixture given in 10CFR20, Appendix B, notes, qu - Activity concentration of radionuclide "i" in mixture at the monitor (pCi/al).
5.1.1.2. Licuid Waste Test Tank Monitor Setroint Ex==nle The activity concentration of each radionuclide, C,i, in the waste test tank is determined by analysis of a representative grab sample obtained at the radwaste sample sink. This setpoint example is based on the following data: i C ,1 (pci/ml) MPCs (pCi/ml) Cs-134 2.15E-05 9E-06 Cs-137 7.48E-05 2E-05 Co-60 2.56E-05 3E-05
}l C,a - 2.15E-05 + 7.48E-05 + 2. 56E 1.22E-04 a
pCi (pCi) (pC1) (pCi) (isT) m1 al al l I 1 i i l l I B.5-2 ODCM Rev. 16 l l 1
- __ ~ -.-. .. ._ = . . _ . - . . - ... . - . _ . .. ... . -- - _ . -
5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS t 5.1.1.2. Liould Umste Test Tank Monitor Setcoint Examnle (Continued) j O DFe, = c_ , (pCi-al) al-pci
; , 2.15E-05 , 7.48E-05 , 2.56E-05 9E-06 2E-05 3E-05 (yCi-al) pCi-al (pCi-al) al pci (int"RI) al pci DFm - 7 i
' l 4 4 1 The minimum dilution factor, DFgo, needed to discharge the mixture of radionuclides in this example is 7. The release rate of the waste test tank is between 10 and 150 gpa. The circulating water discharge flow can vary from 10,500 to 412,000 gpm of dilution water. With the dilution flow taken as 412,000 gpm and the release rate from the waste test tank taken as 150 gpm, ! the DF is: DF - 4 4 (gpm) l (Spa) (5-4) i
, 412,000 gpm 150 gpm ,
~~
- 2750 1
J , 4 i B.5-3 ODCM Rev. 16
5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS 5.1.1.2. Liould Waste Test Tank Monitor Setooint Examnle (Continued) Under these conditions, and with the fraction f3 of total MPC to be associated with the test tank selected as 0.6, the setpoint of the liquid radwaste discharge monitor . is: R,.spoios - fg pC at pCi ihT ( )( ) (uci) iiT (5-1)
- 0. 6 2750 1.22E-04 7
( )( ) (pCi) mL
- 2.87E-02 pCi/ml or pCi/cc In this example, the alarm of the liquid radwaste discharge monitor should be set at 2.87E-02 pCi/cc above background.
5.1.2 Turbine Buildine Drains Liould Effluent Monitor (RM-6521) The Turbine Building drains liquid effluent monitor continuously monitors the O Turbine Building sump effluent line. The only sources to the Sump Effluent System are from the secondary steam system. Activity is expected in the Turbine Building Sump Effluent System only if a significant primary-to-secondary leak is present. If a primary-to-secondary leak is present, the activity in the sump effluent system would be comprised of only those radionuclides found in the secondary system, with reduced activity from decay and dilution. l The Turbine Building drains liquid effluent monitor provides alarm and automatic termination of release prior to exceeding the concentration limits I specified in 10CFR20, Appendix B, Table II, Column 2 to the environment. The alarm setpoint for this monitor will be determined using the same method as that of the liquid waste test tank monitor if the total sump activity is greater than 10 percent of MPC, as determined by the most recent grab sample isotopic analysis. If the total activity is less than 10 percent of MPC, the serpoints of RM-6521 are calculated as follows: High Trip Monitor Setpoint (pCi/ml) - fa (DF*) (1.0E-07 pCi/ml) (5-21) where: pp. _ Circulating water flow rate (gpm) Flow rate pass-monitor (gpm) O' B.5-4 ODCM Rev. 16 I 1
. _ _ . . . .- . - - _ . .--- . _ - , ~. -- .
I i 5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS j 5.1.2 Turbine Buildine Drains Liould Effluent Monitor (RM-6521) (Continued) 1.0E-07 pCi/ml - most restrictive NPC value for an unidentified . mixture given in 10CFR20, Appendix B, Note 3b. '
- f: - 1 - (fg + fa + f.); where the f values are l l described above. l j In addition, a warning alarm setpoint can be determined by multiplying the high trip alarm point by an administrative 1y selected fraction (as an example, 0.25). l l
l Warnfng Alarm - High Trip (5-22) ! Monitor Setpoint ) Mon (itor Setpoint(0.25) l (pci/ml) j 5.1.3 Steam Generator Blowdown Liould S==nle Monitor (RM 6519) The steam generator blowdown liquid sample monitor is used to detect abnormal I activity concentrations in the steam generator blowdown flash tank liquid discharge. The alarm setpoint for the steam generator blowdown liquid sample monitor, when liquid is to be discharged from the site, will be determined using the same approach as the Turbine Building drains liquid effluent monitor. i For any liquid monitor, in the event that no activity is expected to be
- discharged, or can be measured in the system, the liquid monitor setpoint should be based on the most restrictive MPC for an " unidentified" mixture given in 10CFR20,
,/ Appendix B notes.
5.1.4 PCCW Head Tank Rate-of-Chanre Alarm Setnoint
- \
A rate-of-change alarm on the liquid level in the Primary Component Cooling i Water (PCCW) head tank will work in conjunction with the PCCW radiation monitor to l j alert the operator in the Main Control Room of a leak to the Service Water System ) from the PCCW System. For the rate of-change alarm, a setpoint is selected based on :
- detection of an activity level equivalent to 10-e pCi/ml in the discharge of the ,
l Service Water System. The activity in the PCCW is determined in accordance with the l liquid sampling and analysis program described in Part A. Table A.3-1 of the ODCM l and is used to determine the setpoint. l The rate-of-change alarm setpoint is calculated from: , I RC,,, - 1x10'S e SWF * (5-23) ' mi ( hr Eal) . ('pCi) TmT (Lal) hr (WI) where: RC .t - The setpoint for the PCCW head tank rate-of-change alarm (in gallons per hour). lx10-8 - The minimum detectable activity level in the Service Water System due to a PCCW to SWS leak (p qi/ml). B.5-5 ODCM Rev. 16
5.1 LIQUID EFFLUENT INSTRUMENTATION SETPOINTS l 5.1.4 PCCW Head Tank Rate-of-Change Alarm Setooint (Continued) SWF = Service Water System flow rate (in gallons per hour). PCC - Primary Component Cooling Water measured (decay corrected) gross radioactivity level (pci/ml). As an example, assume a PCCW activity concentration of 1x10-5 pCi/ml with a service water flow rate of only 80 percent of the normal flow of 21,000 gpm. The rate-of-change setpoint is then: RC ,g - 1x10-s pCi e 1,0x108 gph (1/1x10 3 pCi) al al RC,,g - 1000 gph As a result, for other PCCW activities, the RC,,s which would also relate to a detection of a minimum service water concentration of 1x10-s pCi/ml can be found from: 1x10-5 e pCi/ml 1000 gph (5-24) l RC,*s PCC 5.1.5 PCCW Radiation Monitor The PCCW radiation monitor will alert the operator in the Main Control Room of a leak to the PCCW System from a radioactively contaminated system. l The PCCW radiation monitor alarm is based on a trend of radiation levels in I the PCCW System. The background radiation of the PCCW is determined by evaluating the radiation levels over a finite time period. The alert alarm setpoint is set at 1.5 x background, and the high alarm setpoint is set at 2 x background, per Technical Specification Table 3.3-6. O B.5-6 ODCM Rev. 16 i i
5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS Technical Specification 3.3.3.10 requires that the radioactive gaseous O effluent instrumentation in Table 3.3-13 of the Technical Specifications have their b alarm setpoints set to insure that Technical Specification 3.11.2.1 is not exceeded. 5.2.1 Plant Va=* Vide Ranre Cas Monitors (RM-6528-1.2 and 3) The plant vent wide-range gas monitors are shown on Figure B.6-2. 5.2.1.1. Method to Determine the Setooint of the Plant Vent Wide Rance Gas Monitors (RM-6528-1.2 and 3) The maximum allowable setpoint for the plant vent wide-range gas monitor (readout response in Ci/sec) is set by limiting the off-site noble gas dose rate to the total body or to the skin, and is denoted R .spios. R,.tygos is the lesser of: Ru,= 588 (5-5) 8 pCi/see - ( arem-gCi-m ) ( pCi-yr) 3 yr-pci-sec arem-m and: Rai, - 3,000 (5-6) pCi-yr pCi/sec - ("#*") ( arem-see) (S yr where: Ro, - Response of the monitor at the limiting total body dose rate (pCi/sec) s 500 (mrem-pCi-m ) 588 - (1E+06) (8.5E-07) yr-pci-sec 500 - Limiting total body dose rate (area /yr) 1E+06 - Number of pCi per pCi (pCi/pCi) 8.5E-07 - [X/Q)1, maximum off-site long-term average gamma atmospheric dispersion factor for primary vent stack releases (sec/m a) Dk - Composite total body dose factor (arem-m8 /pCi-yr) h E4i DFB i
- (5-7)
EDs a Qi - The release rate of noble gas a i in the mixture, for each noble gas identified in the off-gas (pCi/sec) DFB, - Total body dose factor (see Table B.1-10) (mrem-m8 /pCi-yr) O B.5-7 ODCM Rev. 16
5.2 GASEOUS EFFWENT INSTRUMENTATION SETPOINTS 5.2.1.1. Method to Determine the Setroint of the Plant Vent Wide Range Gas Monitors (RM 6528-1.2 and 3) (Continued) R,gt, - Response of the monitor at the limiting skin dose rate (pci/sec) 3,000 - Limiting skin dose rate (mres/yr) . DF', - Composite skin dose factor (arem-sec/pci yr) EQsDF'i
- 1 (5-8)
(Da DF's - Combined skin dose factor (see Table B.1-10) (arem-sec/pci-yr) The following setpoint example for the plant vent wide range gas monitors demonstrates the use of equations 5-5 and 5 6 for determining setpoints. This setpoint example is based on the following data (see Table B.1-10 for DFBt and DF~i): Qi DFB i DF's 3 (pCi) ( mrem-m ) (mrem-sec) g sec pCi-yr pC1-yr Xe-138 1.03E+04 8.83E-03 1.20E-02 Kr-87 4.73E+02 5.92E-03 1.38E-02 Kr-88 2.57E+02 1.47E-02 1.62E-02 Kr-85m 1.20EM2 1.17E-03 2.35E-03 Xe-135 3.70E+02 1.81E-03 3.33E-03 Xe-133 1.97E+01 2.94E-04 5.83E-04 EQi DFB i DFB, - ' (5-7) ks Qi DFB i - (1.03E+04)(8.83E-03) + (4.73E+02)(5.92E-03)
+ (2.57E+02)(1.47E-02) + (1,20E+02)(1.17E-03)
+ (3.70EM2)(1.81E 03) + (1.97E41)(2.94E-04)
- 9.83E+01 (pCi-arem-m8 /see-pCi-yr)
B.5-8 ODCM Rev. 16
l, 5.2 GASEOUS EFFLUENT INSTRUMENTATION SETPOINTS j
!. 5.2.1.2. Plant Vant Vide Ranne Gas Monitor Setooint Examnle O Qg
- 1.03E+04 + 4.73E+02 + 2.57E+02
+ 1.20E+02 + 3.70E+02 + 1.97E+01
- 1.15E+04 pCi/see i'
- 9.83E+01 DFB*
1.15E+04
- 8.52E-03 (arem m 3/pci-yr) 1 I4b - 588 (5-5) 399 1 .
~( )
(5.5ZE-037 i l - 6.90E+04 pCi/sec
- and next
l x })D iDF~g I DF",- * (5-8) I 1)ki 1 i . ]Qt DF*, - (1.03E+04)(1.20E-02) + (4.73E+02)(1.38E-02) j + (2.57E+02)(1.62E-02) + (1.20E+02)(2.35E-03) i
+ (3.70E+02)(3.33E-03) + (1.97E+01)(6.83E-04) 4
- 1.38E+02 (pci-arem sec/sec-pCi yr) l pp.1L,1.36E+02
, -1.15E+04
%ll T W 1.18E-02 (arem-sec/pci-yr) l (5-6) l Ret, - 3,000 yp,_
't i O , B.5 9 ODCM Rev. 16 1
I 1 5.2 CASEOUS EFFLUENT INSTRUMENTATION SETPOINTS 5.2.1.2. Plant Vent Wide Ranne Gas Monitor Setooint Examole (Continued) 1
- (3,000)
((l l6E-02))
- 2.54E+05 pCi/sec The setpoint, R., ,,ta, is the lesser of Ro and Rouo. For the noble gas I cixture in this example Ra is less than Rsun, indicating that the total body dose l rate is more restrictive. Therefore, in this example the plant vent wide-range gas conitors should each be set at no more than 6.90E+04 pCi/sec above background, or at i some administrative fraction of the above value.
l In the event that no activity is expected to be released, or can be reasured in the system to be vented, the gaseous monitor setpoint should be based on Xe-133. l 5.2.2 Waste Gas System Monitors (RM-6504 and RM-6503) Process radiation monitors in the waste gas system provide operational information en the performance of the system before its discharge is combined and diluted with other gas flows routed to the plant vent for release to the environment. The setpoints for the waste gas system monitors are administrative 1y set as small l I multiples of the expected activity concentration to provide operational control over unexpected changes in gas discharges from the system. Typically, the alert alarm cetpoint for both monitors is placed at 1.5 times the expected activity concentration passing the monitor, with the high alarm trip set at 2 times the expected concentration flow. Under all conditions, the maximum allowabie alarm trip shall not exceed a concentration equivalent to 62.5 uCi/cm8 . This concentration limit, based on system design flow of 1.2 cfm, assures that any release from the waste gas system to the plant vent will not exceed the site boundary dose rate limits of Technical Specification 3.11.2.1.a. l 5.2.3 Main Condenser Air Evacuation Monitor (RM-6505) The process radiation monitor on the main condenser air evacuation system provides operational information about the air being discharged. The discharge occurs either directly from the turbine building during start up (hogging mode) or through the plant vent during normal operations. This process monitor is also used as an indicator of potential releases from the Turbine Gland Seal Condenser exhaust. Early indications of a potential release (i.e., monitor count rate at twice the normal background) should be evaluated by collecting a grab sample of the exhausts from both the main condenser and the Turbine Gland Seal Condenser. The operational setpoints for the air evacuation monitor are administrative 1y set as small multiples of the expected background response of the detector to provide operational control over unexpected changes in the activity discharged from the system. Typically, the alert setpoint is 1.5 times background, with the high alarm set at 2 times background. O B.5-10 ODCM Rev. 16
l 5.2.3 Main condertser Air Evacuation Monitor (RM-6505) (Continu2d) Maximum allowab*4e setpoint determinations assure that the site boundary dose rate limits of Tochttcal Specification 3.11.2.1.a will not be exceeded. For a typical Os air evacuation detector efficiency of 6.0E+05 cpm-cm 8/pci, flow rates of 10 and 10,000 cfm for the normal and hogging modes of operation, respectively, and assuming that all the response is due to the most restrictive noble gas (Kr-89), the difference between the stack release and ground level release pathway setpoints for 1 the two modes of operation (normal power and startup, respectively) are seen to be ! about three orders of magnitude. This example also assumes 670 lbs/ hour of steam ! flow through the Turbine Gland Seal Eystem,1.5E+07 lbs/ hour of steam flow to the ; main condenser, and that the Turbine Cland Seal Condenser exhaust flow rate of 1,800 l efs goes directly to the Turbine Building Vents (does not directly pass RM-6505). For these conditions, the maximum allowable alarm should not exceed 3.2E+06 cpm when exhausting to the plant vent (assumes an administrative limit of 70% of the calculated value to account for potential contributions from the Turbine Gland Seal Condenser exhaust). Under hogging mode operations, the maximum allowable alarm should not exceed 1.4E+02 cpm (assumes an administrative limit of 15% of the calculated value to account for potential contributions form the plant vent). The maximum allowable setpoints during startup and normal power operations may be recalculated based on identified changes in detector efficiency, discharge flow rate, rad!onuclide mix distribution, or administrative apportionment of potential contributions from the plant vent and ground level release points following the methods identified in $8.5 O l I i l l O B.5-11 ODCM Rev. 16
6.0 LIOUID AND CASEOUS EFFIEENT STREAMS. RADIATION MONITORS AND RADVASTE TREATMENT SYSTEMS i 4 Pg Figure 8.6-1 shows the liquid effluent streams, radiation monitors and the V appropriate Liquid Radwaste Treatment System. Figure B.6-2 shows the gaseous effluent streams, radiation monitors and the appropriate Gaseous Radvaste Treatment 4 Sycten. For more detailed information concerning the above, refer to the Seabrook Station Final Safety Analysis Report, Sections 11.2 (Liquid Waste System), 11.3 l (Gaseous Waste System) and 11.5 (Process and Effluent Radiological Monitoring and Sampling System). The turbine gland seal condenser exhaust is an unmonitored release path. The iodine and particulate gaseous releases will be determined by continuously sampling the turbine gland seal condenser exhaust. The noble gas releases will be determined by the noble gas released via the main condenser air evacuation exhaust and ratioing them to the turbine gland seal condenser exhaust by use of the flow rates. l I l l l I F y B.6-1 ODCM Rev. 16
l l l FIGURE B.6-1 l L70UID EFFLUENT STREAMS. RADIATION MONITORS. AND RADVASTE TREATMENT SYSTEM AT SEABROOK STATION i O1 o o l MAKEUP STORAGE UNIT TANK PAS g l edk_E a p"e l 1
< EI:,"
i ans.eeie
=
l
,1 1
4 l r_- lr l =
~~
al,
~"'"
- l
~# O 8
i i 3 1 , i n G i _"\
= 0 c- ; > = l 8
1 t 4 i GE> """ e ,,_
,._- _ e--- "- .:::"._=,,g g G -= ~ O ~ ~--
B.6-2 ODCM Rev. 16
~ _ . . . _ - - . ~ . - - . - - . - _ . . - . - - . . ~ . - . . . - . . . . _ . . ~ . - . _ - . - . . . . . . . . . - - - . - . . . - - . -
l i
- FIGURE B.6 2 I I GASEOUS. EFFLUENT STREAMS. R4pIATION MONITORS. AND 1
- RADWASTE TREATMENT SYSTEM AT SEABROOK STATIQN i l
anm.o wooosso l 1 CONTAINMENT e== = 1 asons omty j BUILDING VENTEAtoms Tunese yngyy,, { i nzw eue.soi ii ,uo, mmf ,' JttacTuft N vacyyg
~
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, couTAse.
.~ A g=
ment _ FLASH TANK ,,
~
mg tassous WASTE .motessee6 systtu W
.g- ._ == a_.== m - I m u .
.- u. _
euAfe EW ' l i, l
._ i i
= -
CMAACOALEWS ' l l
, _.._ l _
I j fas Als
""' - @l b l l
hi b h
)5 gt ll*,,,, - -
L, v , Anasunar sumasasverram " L8GSS . L M .npa stigt " " C. CDeAngeAL PL1WL Res. AActAft01s tseIWTOR B.6-3 ODCM Rev. 16
1 ! i i 7.0 EASES FOR DOSE CALCULATION METHODS ! i 7.1 LIQUID RELEASE DOSE CALCULATIONS I 4 l This section serves: (1) to document the development and conservative nature j of Method I equations to provide background information to Method I users, and (2) , to identify the general equations, parameters and approaches to Method II-type dose l { assessments. Appendix C provides the bases for the EMS sof tware which is used to i ! implement the dose and dose rate calculations indicated as Method IA. ? I Method I may be used to show that the Technical Specifications which limit i off-site total body dose from liquids (3.11.1.2 and 3.11.1.3) have been met for i releases over the appropriate periods. The quarterly and annual dose limits in l j Technical Specification 3.11.1.2 are based on the ALARA design objectives in i
- 10CFR50, Appendix I Subsection II A. The minimum dose values noted in Technical
! Specification 3.11.1.3 are " appropriate fractions," an determined by the NRC, of the i j design objective to ensure that radwaste equipment is used as required to keep ; 4 off-site doses ALARA. ! l 1 Method I was developed such that "the actual exposure of an individual ... is 1 l unlikely to be substantially underestimated" (10CFR50, Appendix I). The definition,
- below, of a single " critical receptor" (a hypothetical or real individual whose behavior results in a maximum potential dose) provides part of the conservative !
margin to the calculation of total body dose in Method I. Method II allows that actual individuals, associated with identifiable exposure pathways, be taken into account for any given rLlease. In fact, Method I was based on a Method II analysis for a critical receptor assuming all principal pathways present instead cf any real individual. That analysis was called the " base case;" it was then reduced to form j Method I. The general equations used in the base case analysis are also used as the starting point in Method II evaluations. The base case, the method of reduction, and the assumptions and data used are presented below. The steps performed in the Method I derivation follow. First, the dose impact to the critical receptor (in the form of dose factors DFLn3 (mren/pCi)] for a unit activit, telease of each radioisotope in liquid effluents was derived. The base case analysis uses the general equations, methods, data and assumptions in Regulatory Guide 1.109 (Equations A-3 and A-7, Reference A). The liquid pathways contributing to an individual dose are due to consumption of fish and invertebrates, shoreline activities, and swimming and boating near the discharge point. A normal operating plant discharge flow rate of 918 ft /see 3 was used with a mixing ratio of 0.10. The mixing ratio of 0.10 corresponds to the minimum expected prompt dilution or near-field mixing zone created at the ocean surface directly above the multiport diffusers. (Credit for additional dilution to the outer edge of the prompt mixing zone which corresponds to the l'F surface isotherm (mixing ratio .025) can be applied in the Method II calculation for shoreline exposures only cince the edge of this isotherm typically does not reach the shoreline receptor poirts during the tidal cycle. The mixing ratio for equatic food pathways in Method II assessments shall be limited to the same value (0.10) as applied in Method I for near-field mixing, or prompt dilution only. S B.7 1 ODCM Rev. 16
7.1 LIQUID RELEASE DOSE CALCUIATIONS (Continu:d) l 1 The requirements for the determination of radiological impacts resulting from l releases in liquid effluents is derived from 10CFR50, Appendix 1. Section III.A.2 , of Appendix I indicates that in making the assessment of doses to hypothetical l receptors, -The Applicant may take account of any real phenomenon or factors j cetually affecting the estimate of radiation exposure, including the characteristics l of the plant, modas of discharge of radioactive materials, physical processes l tending to attenuate the quantity of radioactive material to which an individual l would be exposed, and the effects of averaging exposures over time during which l determining factors may fluctuate." In accessing the liquid exposure pathways that characterize Seabrook Station, the design and physical location of the Circulating Water Discharge System needs to be considered within the scope of Appendix I. Seabrook utilizes an offshore submerged multiport diffuser discharger for rapid dissipation and mixing of thermal effluents in the ocean environment. The 22 port diffuser section of the Discharge System is located in approximately 50 to 60 feet of water with each nozzle 7 to 10 feet above the sea floor. Water is i discharged in a generally eastward direction away from the shoreline through the multiport diffuser, beginning at a location over one mile due east of Hampton Harbor inlet. This arrangement effectively prevents the discharge plume (at least to the 1 degree or 40 to 1 dilution isopleth) from impacting the shoreline over the tidal cycle. 1 Eleven riser shafts with two diffuser nozzles each form the diffuser and are epaced about 100 feet apart over a distance of about 1,000 feet. The diffusers are designed to maintain a high exit velocity of about 7.5 feet per second during power cperations. Each nozzle is angled approximately 20 degrees up from the horizontal plane to prevent bottom scour. These high velocity jets passively entrain about ten volumes of fresh ocean water into the near field jet mixing region before the plume 1 reaches the water surface. This factor of 10 mixing occurs in a very narrow zone of i less than 300 feet from the diffuser by the time the thermally buoyant plume reaches i the ocean surface. This high rate of dilution occurs within about 70 seconds of I discharge from the diffuser nozzles. The design of the multiport diffuser to achieve a 10 to 1 dilution in the near field jet plume, and a 40 to 1 dilution in the near mixing zone associated with the 1 degree isotherm, has been verified by physical model tests (referen c
" Hydrothermal Studies of Bifurcated Diffuser Nozzles and Thermal Backwashing -
Seabrook Station," Alden Research Lnoratories, July 1977). During shutdown periods, when the plant only requires service water cooling flow, the high velocity jet mixing created by the normal circulating water flow at the diffuser nozzles is reduced. However, mixing within the discharge tunnel water volume is significantly increased (factor of about 5) due to the long transit time (approximately 50 hours) for batch waste discharged from the plant to travel the three miles through the 19-foot diameter tunnels to the diffuser nozzles. Additional mixing of the thermally buoyant effluent in the near field mixing zone assures that an equivalent overall 10 to 1 dilution occurs by the time the plume reaches the ocean surface. O B.7-2 ODCM Rev. 16
7.1 LIQUID REIZASE DOSE CALCULATIONS (Centinued) The dose assessment models utilized in the ODCM are taken from NRC Regulatory (] Cuide 1.109. The liquid pathway equations include a parameter (M,) to account for (/ the mixing ratio (reciprocal of the dilution factor) of effluents in the environment at the point of exposure. Table 1, in Regulatory Guide 1.109, defines the point of exposure to be the location that is anticipated to be occupied during plant lifetime, or have potential land and water urage and food pathways as could actually exist during the term of plant operation. For Seabrook, the potable water and land irrigation pathways do not exist since saltwater is used as the receiving water body for the circulating water discharge. The three pathways that have been factored into the assessment models are shoreline exposures, ingestion of invertebrates, and fish ingestion. With respect to shoreline exposures, both the mixing ratios of 0.1 and 0.025 are extremely conservative since the effluent plume which is discharged over one mile offshore never reaches the beach where this type of exposure could occur. Similarly, bottom dwelling invertebrates, either taken from mud flats near the shoreline or from the area of diffuser, are not exposed to the undiluted effluent plume. The shore area is beyond the reach of the surface plume of the discharge, and the design of the upward directed discharge nozzles along with the thermal buoyancy of the effluent, force the plume to quickly rise to the surface without affecting bottom organisms. Consequentially, the only assumed exposure pathway which might be impacted by the near field plume of the circulating water discharge is finfish. However, the mixing ratio of 0.1 is very conservative because fish will avoid both the high exit velocity provided by the discharge nozzles and the high thermal temperature difference between the water discharged from the diffuser and the ambient water O temperature in the near field. In addition, the dilution factor of 10 is achieved within 70 seconds of discharge and confined to a very small area, thus prohibiting any significant quantity of fish from reaching equilibrium conditions with radioactivity concentrations created in the water environment. The mixing ratio of 0.025, which corresponds to the 1 degree thermal near field mixing zone, is a more realistic assessment of the dilution to which finfish might be exposed. However, even this dilution credit is conservative since it neglects the plant's operational design which discharges radioactivity by batch mode. Batch discharges are on the order of only a few hours in duration several times per week and, thus, the maximum discharge concentrations are not maintained in the environment long enough to allow fish to reach equilibrium uptake concentrations as assumed in the dose assessment modeling. Not withstanding the above expected dilution credit afforded at the 1 degree isotherm, all Method II aquatic food pathway dose calculations shall conservatively assume credit for prompt dilution only with an N, - 0.10. When dose impacts from the fish and invertebrate pathways are then added to the conservative dose impacts derived for shoreline exposures, the total calculated dose is very unlikely to have underestimated the exposure to any real individual. The recommended value for dilution of 1.0 given in NUREG-0133 is a simplistic assumption provided so that a single model could be used with any plant design and physical discharge arrangement. For plants that utilize a surface canal-type discharge structure where little entrainment mixing in the environment occurs, a dilution factor of 1.0 is a reasonable assumption. However, in keeping with the guidance provided in Appendix I to 10CFR50, Seabrook has determine site-specific p mixing ratios which factor in its plant desi n. 5 b B.7-3 ODCM Rev. 16
l
\
l 7.1 LIQUID RELEASE DOSE CALCUIATIONS (C:ntinued) The transit time used for the aquatic food pathway was 24 hours, and for choreline activity 0.0 hours. Table B.7-1 outlines the human consumption and use i factors used in the analysis. The resulting, site-specific, total body dose factors cppear in Table B.1-11. Appendix A provides an example of the development of a Method I liquid dose conversion factor for site-specific conditions at Seabrook. 7.1.1 Dose to the Total Body For any liquid release, during any period, the increment in total body dose from radionuclide "i" is: ADa - k Qi DFLn , (mrem) () (pC1) pCi (7-1) where: DFiga - Site-specific total body dose factor (arem/pC1) for a liquid release. It is the highest of the four age groups. See Table B.1-11. Qi - Total activity (pC1) released for radionuclide ai". K = 918/F, (dimensionless); where Fe is the average dilution flow of the Circulating Water System at the point of discharge from the multiport diffuser (in ft 3/sec). Method I is more conservative than Method II in the reS ion of the Technical Specification limits because the dose factors DFL a used in Method I were chosen for the base case to be the highest of the four age groups (adult, teen, child and l infant) for that radionuclide. In effect each radionuclide is conservatively l represented by its own critical age group. ) 7.1.2 Dose to the Critical Orran The methods to calculate maximum organ dose parallel to the total body dose methods (see Section 7.1.1). 1 1 I O B.7-4 ODCM Rev. 16
. . . _ _ _ _ _ _ _ . . . . . _ _ _ . _. . _ . _ _ _ _ . _ . _ . _ . - . - _. _ . _ __ _ . . _ _ _ >_. _ .m. _.
N 4 7.1 LIQUID RELEASE DOSE CALCU1ATIONS (Continu1d) ! 7.1.2 Dose to the critical Orman (Continued) , For each radionuclide, a dose factor (aren/pci) was determined for each of
, seven organs and four age groups. The largest of these was chosen to be the maximum organ dose factor (DFLw) for that radionuclide. DFL also includes the external dose contribution to the critical organ.
l For any liquid release, during any period, the increment in dose from radionuclide "i" to the maximum organ is:
- j AD, = k Qi DFLi ,
I
.nren. (7-2) 1 (mres) () (801) 1 pCi j l
4 where: i } D% - Site-specific maximum organ dose factor (ares / Ci) for a liquid i release. See Table B.1-ll. Qi - Total activity (pCi) released for radionuclide "ia. 1 l K - 918/Fe (dimensionless); where Fa is the average dilution flow of j the Circulating Water System at the point of discharge from the i multiport diffuser (in ft 8/sec). i i 4 i i I I J j I i l l t i I 2 4 i
)
1 i B.7-5 ODCM Rev. 16
TABLE B.7-1 USAGE FACTORS FOR VARIOUS LIOUID PATHWAYS AT SEABROOK STATION (From Reference A, Table E-5*, except as noted. Zero where no pathway exists) AGE VEG. LEAFY MIIX MEAT FISH INVERT. POTABLE SHORELINE SWIMMING ** BOATING ** VEG. WATER (KG/YR) (KG/YR) (LITER /YR) (KG/YR) (KG/YR) (KG/YR) (LITER /YR) (HR/YR) (HR/YR) (HR/YR) Adult 0.00 0.00 0.00 0.00 21.00 5.00 0.00 334.00*** 8.00 52.00 Teen 0.00 0.00 0.00 0.00 16.00 3.80 0.00 67.00 45.00 52.00 Ghild 0.00 0.00 0.00 0.00 6.90 1.70 0.00 14.00 28.00 29.00 Infant 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- Regulatory Guide 1.109.
- HERMES; "A Digital Computer Code for Estimating Regional Radiological Effects from Nuclear Power Industry,"
HEDL, December 19/1. Note, for Method II analyses, these pathways need not be evaluated since they represent only a small fraction of the total dose contribution associated with the other pathways. t
- Regional shoreline use associated with mudflats - Maine Yankee Atomic Power Station Environmental Report.
B.7-6 ODCM Rev. 16 O O O
- . ~~ . .... .-._ - -- - . _ - - . - . _~ .- - - _-._ _ .~.. - -
i i I 7.2 GASEOUS RELEASE DOSE CALCUIATIONS i 7.2.1 Total Body Dose Rate From Noble Cases 1 I This section serves: (1) to document the development of the Method I equation, (2) to provide background information to Method I users, and (3) to identify the general equations, parameters and approaches to Method II-type dose rate assessments. Method I may be used to show that the Technical Specification which limits j total body dose rate from noble gases released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak noble gas release rate. l i Method I was derived from general equation B-8 in Regulatory Guide 1.109 as ! follows: a i > 8, = IE46 [X/Q]Y t Q, DFB i (7-3) i I < i . . , ! ' ares' .
'pci' sec 'pCi ' aree-e 3 '
i yr pCi m3 sec pCi-yr { 4 (~') v t j where: i ! [X/Q]1 - Maximum off-site receptor location long-term average gamma i atmospheric dispersion factor. 1 i l Qi - Release rate to the environment of noble gas "i" (pCi/sec). DFB t - Gamma total body dose factor, aremM . See Table B.1-10. pCi-yr . (Regulatory Guide 1.109. Table B-1) . I i Elevated and ground level gaseous effluent release points are addressed . 1 separately through the use of specific (X/Q] y. For an elevated gaseous effluent release point and off-site receptor, Equation 7-3 takes the form: ] O ! B.7-7 ODCM Rev. 16 i
7.2 CASEOUS RELEASE DOSE CALCUIATIONS 7.2.1 Total Body Dose Rate From Noble Gases (Continued) O 6 tbc .) = (IE+06) + (8.5E-07) * { (4, DFB,) i 3
' mrem' , 'pp' ,
sec , pCi , mrem-m yr pCi m 3 sec pCi-yr which reduces to: 6 tbce) = 0.85 . { (Q, . DFBi ) i 1 3
' mrem' ,
pCi-sec 'gC i ' , mrem-m yr gC1-m3 , sec pCi-yr For a ground level gaseous effluent release point and off-site receptor, Equation 7-3 takes the form: 6,3c,3 = (IE+06) (3.4E-06) + { (Q i. DFB i ) I which reduces to: 6,w,3 = 3.4 + { (Q i* OFB,) i 3
' mrem' ,
pCi-sec 'gC i ' mrem-m yr yt.,3 , sec pCi-yr The selection of critical receptor, outlined in Section 7.3 is inherent in the derived Method I, since the maximum expected off-site long-term average atmospheric dispersion factor is used. The sum of doses from both plant vent stack and ground level releases must be considered for determination of Technical Specification compliance. All noble gases in Table B.1-10 should be considered. O B.7-8 ODCM Rev. 16
. . - - - . _ - - . . . ~. . ._
i 7.2 GASEOUS RELEASE DOSE CAIEUIATIONS 7.2.1 Total Body Dose Rate From Noble Gases (Continued) A Method II analysis could include the use of actual concurrent meteorology to assess the dose rates as the result of a specific release. 7.2.2 Skin Dose Rate From Noble Gaggg This section serves: (1) to document the development of the Method I J equation, (2) to provide background information to Method I users, and (3) to identify the general equations parameters and approaches to Method II-type dose rate assessments. The methods to calculate skin dose rate parallel the total body dose i rate methods in Section 7.2.1. Only the differences are presented here. ; . Method I may be used to show that the Technical Specification which limits
- skin dose rate from noble gases released to the atmosphere (Technical Specification l 3.11.2.1) has been met for the peak noble gas release rate. l 1
l The annual skin dose limit is 3,000 area (from NBS Handbook 69, Reference D, l pages 5 and 6, is 30 rem /10). The factor of 10 reduction is to account for l l nonoccupational dose limits. It is the skin dose commitment to the critical, or most limiting, off-site receptor assuming long-term site average meteorology and that the release ra' i reading remains constant over the entire year. ) i Method I was derived from the general equation B-9 in Regulatory Gade 1.109 as follows. j l S D - 1.11 DIir + 3.17E44 Qi [X/Q] DFS, (7-4) 3
' mrem' ' mrem' ' mrad' 'pCi -yr' Ci sec mrem-fn
- =
l yr mrad yr Ci-sec yr m3 , PCi -yr where:
- 1.11 - Average ratio of tissue to air absorption coefficients (will convert arad in air to mrem in tissue). j l DFS 3 - Beta skin dose factor for a semi-infinite cloud of radionuclide "i" which includes the attenuation by the outer " dead" layer of the skin. j l
l
\
i i B.7-9 ODCM Rev. 16
7.2 GASEOUS RELEASE DOSE CALCULATIONS 7.2.2 Skin Dose Rate From Noble Cases (Continued) D!i, - 3.17E44 { Q [X/Q) i DF Y i (7-5) { i
' mrad' 'pC i -yr' mrad-a3
=
(Ci) ( sec) y yr , Ci-sec yr pCi-yr DFI - camma air dose factor for a uniform semi-infinite cloud of radionuclide "i". Now it is assumed for the definition of (X/Q7) from Reference 8 that: J l l i Djinit, - D!i, [X/Q]Y/[X/Q) (7-6) . \ 3
' mrad' ' mrad' sec m 4
yr yr d sec and Qi = 31.54 Q i 4
'C i ' 'Ci -sec' 'gCi'
- = -
yr , pCi-yr ,sec , so: 7 (7-8) b,gi, - 1.11 1E+06 [X/Q]S Qi
- DF i
'arem' ,
"arem' 'pci' 's e c' ' sci 'arad-m'3
, yr , , mrad, M, ,7, ,s e c, ,
pGi-yr,
+1E+06 X/Q Qi DFS i 3,
pCi see pCi mrem-m
,M 7.ss e e. ,pGi yr.
O B.7-10 ODCM Rev. 16
7.2 CASECUS RELEASE DOSE CALCUIATIONS _. 7.2.2 Skin Dose Rate From Noble Cases (Continued) Substituting atmospheric dispersion factors for an elevated gaseous effluent j release point, Equation 7-8 takes the following form: i
- baiot 3 - [1.11 e 1E+06
- 8.5E-07 * { (Qi
- DFi)] + [1E+06
- 8.2E-07 * { (Qi
- DFS )] i j
j which yields: I 1
- Dai,c,3 = [0.94 { (Qi
- DF])] + [0.82 { (Q
- DFSi )] i (7-9a) i i i 'aren' ,
'pci-sec-aren' { [pCi , arem-m8' 4 pCi-see p 'pci , mrem-m3 '
1 , yr , , pCi-m3 -arad , (sec pGi-yr, pCi-m 3 ,sec pGi-yr, l defining: 4 . DF[g,3 = 0.94 DFI + 0.82 DFS i (7-10a)
\
j Then the off-site skin dose rate equation for an elevated gaseous effluent release point is: I O Dai,c,3 = { Q i* DF[g,3 (3-4a) i ,
, mrem
,p pCi , arem-sec 7
, yr , ,s e c pGi-yr ,
For an off-site receptor and a ground level gaseous effluent release point, Equation 7-8 becomes: bagog,3 = [1.11*1E+06 *3.4E-06 *{ (Qi +DF])] + [1E+06 *1.0E-05 *{ (Q i+DFSi )] A which yields: 6,gi,g,3 = [3.8 { (Qi
- DFj)] + [10 { (Qi
- DFS )] (7-9b) i
= { Qi [3.8 DFI + 10 DFSi ]
l l B.7-11 ODCM Rev. 16 l l
7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.2 Skin Dose Rate From Noble Cases (Continued) d fining: DF[g,3 = 3.8 DFl + 10 DFS i (7-10b) Then the off-site skin dose rate equation for ground level gaseous effluent release points is: D. kin (s) " b Qi
- DF[g,3 (3-4b)
I 1 The selection of critical receptor, outlined in Section 7.3, is inherent in the derived Method I, as it is based on the determined maximum expected off-site ctmospheric dispersion factors. All noble gases in Table B.1-10 must be considered. 7.2.3 Critical Organ Dose Rate From ' Iodines. Tritium and Particulates With Half-Lives Greater Than Eirht Days This section serves: (1) to document the development of the Method I equation, (2) to provide background information to Method I users, and (3) to identify the general equation's parameters and approached to Method II type dose rate assessments. The methods to calculate skin dose rate parallel the total body dose rate methods in Section 7.2.1. Method I may be used to show that the Technical Specification which limits crgan dose rate from iodines, tritium and radionuclides in particulate form with half lives greater than 8 days released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak above-mentioned release rates. The annual organ dose limit is 1500 mrem (from NBS Handbook 69, Reference D, pages 5 and 6). It is evaluated by looking at the critical organ dose comunitment to the most limiting off-site receptor assuming long-term site average meteorology. The equation for 0,, is derived from a form of Equation 3-8 in Section 3.9 by cpplying the conversion factor, 3.154E+07 (sec/yr) and converting Q to Q in pCL/see: O B.7-12 ODCM Rev. 16
-. - - , . - ~ - . - . ~ _ . . ~ . . - . . . - . ...- - . ...--.....- .-..-.- .-.- - ..
) ,
- 7.2 GASEOUS REl. EASE DOSE CALCUIATIONS I
7.2.3 Critical Orean Dose Rate From Iodines. Tritium and Particulates With , h) 2
- \
r gglf-Lives Creater Than Eirht Days (Continued) ' 6,, = 3 15E+07 * (Qi
- DFG .) i (7-12) arem sec pCi aren p ,
W
, 7Y . 7f. .s e c, , ,
Equation 7-12 is rewritten in the form: 6,,= (Qi
- DFC',,) i (7-12a)
'pci 'arem-sec'
' ares'
, yr ,
,p ,s e c, pci-yr ,
where: DFG'e, = 3.154E+07
- DFG4 ,, (7-13) i arem-sec , sec , arem ci-yr , ,yr, W The dose conversion factor, DFGi .., has been developed for both elevated O gaseous effluent release points and ground level gaseous effluent release points (DFG ..c 3 and DFG i i ..c 3), respectively. These dose factors are used to determine accumulated doses over extended periods and have been calculated with the Shielding Factor (SF) for ground plane exposure set equal to 0.7, as referenced in Regulatory Guide 1.109. In the case of the dose rate conversion factors (DFG' g .c 3 and DFG' t .c,3), the dose conversion factors from which they were derived were calculated l with the Shielding Factor (SF) for ground plane exposure set equal to 1.0.
For an off-site receptor and elevated effluent release point, the critical organ dose rate equation is: ! b,,c 3 = (Qi
- DFG' i,.c 3) (3-Sa)
' ares' ,p 'pci , erem-sec'
, yr , ,s ec pci-yr ,
For an off-site receptor and ground level effluent release point, the critical organ dose rate equation is: ( ( B.7-13 ODCM Rev. 16
7.2 CASEOUS RELEASE DOSE CALCUIATIONS 7.2.3 Critical Orran Dose Rate From Iodines. Tritium and Particulates With Half-Lives Greater Than Eirht Days (Continued) 6,,c,3 = { (Qi
- DFG' g,,c,3) (3-5b)
O mrem
,y pCi , arem-sec
, yr , ,s ec pci-yr ,
The selection of critical receptor, outlined in Section 7.3 is inherent in Method I, as are the expected atmospheric dispersion factors. In accordance with the Basis Statement 3/4.11.2.1 in NUREG-0472, and the base's section for the organ dose rate limit given for Technical Specification 3.11.2.1, a Method II dose rate calculation, for compliance purposes, can be based en restricting the inhalation pathway to a child's thyroid to less than or equal to 1,500 mrem /yr. Concurrent meteorology with time of release may also be used to essess compliance for a Method II calculation. 7.2.4 Gm== Dose to Air From Noble Cases This section serves: (1j to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) ! to identify the general equations, parameters and approaches to Method II-type dose essessments. I Method I may be used to show that the Technical Specification 3.11.2.2 which limits off-site gamma air dose from gaseous effluents has been met for releases over cppropriate periods. This Technical Specification is based on the objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated gamma air dose in off-site unrestricted areas. NUREG/CR-2919 presents a methodology for determining atmospheric dispersion factors (CHI /Q values) for intermittent releases at user specified receptor locations (intermittent releases being defined as releases with durations between 1 cnd 8,760 hours).. The CHI /Q values for intermittent releases are determined by linearly interpolating (on a log-log basis) between an hourly 15-percentile CHI /Q value and an annual average CHI /Q value as a function of release duration. This : methodology has been adopted to produce a set of time-dependent atmospheric dispersion factors for Method I calculations. For any noble gas release, in any period, the increment in dose is taken from Equations B-4 and 5-5 of Regulatory Guide 1.109 with the added assumption that D7giott, - D1 [X/Q]T/[K/Q]: 1 O B.7-14 ODCM Rev. 16
7.2 CASEOUS RELEASE DOSE CALCULATIONS 7.2.4 C--- Dose to Air From Noble Cases ADjg, - 3.17E+4 [X/Q]1 { Qi DFj (7-14) PCi-yr' 'sec' #8d'" (arad) - (C1) ,"pci-yr
,Gi-sec, {
where: 3.17E+04 - Number of pCi per Ci divided by the number of seconds per year. [X/Q]7 - Annual average gamma atmospheric dispersion factor for the receptor location of interest. Qi - Number of curies of noble gas "i" released. DF15
- Gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i".
Incorporating a unitiess release duration adjustment term t-* (where "a" is a constant and "t" is the total release duration in hours), and the conversion factor for Ci to pCi (to accommodate the use of a release rate Q in pCi), and substituting the 1 hour gamma atmospheric dispersion factor in place of the annual average gamma atmospheric dispersion factor in Equation ?-14 leads to: (3-6) D!i, - 3.17E-02 * [X/Q)'a,
- t-* *
(Qi
- DFI)
P Ci-yr ' 8
'sec'
[ *{ (mrad) . , uCi
- arad-m '
,ci-sec, p ,
pGi-yr, For an elevated release, the equation used for an off-site receptor is: p {g, pp D,d(,) - 3.17E-02 * [1.0E-05)
- t-o.an n
U B.7-15 ODCM Rev. 16
7.2 GASEOUS RELEASE DOSE CAIEUIATIONS l 7.2.4 G=== Dose to Air From Noble Cases l which leads to: Dji,c.3 - 3.2E-07 + t-o.275 . p (q, . pp7) (3-6a)
'PCi-yr' arad-af (mrad) .
- Ci e
,pCi-m', PCi-yr, For a ground-level release, the equation used for an off-site receptor is:
4 D,g}(g) - 3.17E-02 + [4.9E-05]
- t-o.2es . (q , pp which leads to:
(3-6b) D!i,g,3 - 1.6E-06 e t-o.2s3 . { (qt , pp7) Ci-yr' Ci e arad-mi (mrad) . P
,pCi-m* ,
*{ PCL-yr, The major difference between Method I and Method II is that Method II would use actual or concurrent meteorology with a specific noble gas release spectrum to determine [X/Q)? rather than use the site's long-term average meteorological dispersion values.
7.2.5 Beta Dose to Air From Noble Cases This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose assessments. Method I may be used to show that Technical Specification 3.11.2.2, which limits off-site beta air dose from gaseous effluents, has been met for releases over apprcpriate periods. This Technical Specification is based on the objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated beta air dose in off-site unrestricted area locations. For any noble gas release, in any period, the increment in dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109: 1 l
@:I B.7-16 ODCM Rev. 16
. = _ _ - .-- - - _ _ _ _ . .. - . . - . _ - . . .- ._.---..- .- - .
4 i l ( ! 7.2 CASEOUS RELEASE DOSE CALCULATIONS i l 7.2.5 Beta Dose to Air From Noble Cases (Continued) AD!,, - 3.17E-02 X/Q { Qi DF{ (7-15) i r , , , PCi-yr sec mrad-m3 (arad) - iT (pCi)
,pCi-yr, pci-sec,
! where: DF# 3
- Beta air dose factors for a uniform semi-infinite cloud of radionuclide "ia.
Incorporating the term t-* into Equation 7-15 leads to: D{1, - 3.17E-02
- X/Q
- t-* * { (Qi
- Dd) (3-7)
A 8, pCi-yr sec gCi
- mrad-m m, *()*{
(mrad) - , PCi-yr,
, pCi-sec, 3 Where X/Q = average 1-hour undepleted atmospheric dispersion factor.
For an elevated release, the equation used for an off-site receptor is: D{i,c,3 - 3.17E-02
- 1. 3E-05
- t-0 8 * (Qi
- Dd) 8, pCi-yr sec pCi
- arad-m (arad) - ,
*()*{ pCi-yr;
,pci-sec, "ET ,
which leads to: D{i,<.3 - 4.1E-07
- t-0 8 * { (Qi
- Dd) (3-7a)
'PCi-yr'
*()* arad-af (arad) . pCi e PCi yr,
,pci-m 3, For a ground-level release, the equation used for an off-site receptor is:
B.7-17 ODCM Rev. 16
7.2 CASEOUS RELEASE DOSE CALCULATIONS 7.2.5 Beta Dose to Air From Noble Cases (Continued) D{3,g,3 - 3.17E-02 e 1.9E-04
- t-0 828 * (Q*Dd) i
, 1 3,
(arad) - P Ci-yr * *()* gCi* mrad-m l
,ci-sec, p ,m , ,
PCi-yr, r which leads to: l (3-7b) 1 D{3,c,3 - 6. 0E-06
- t-0 318 * (Qi
- DF{f I l
l Ci-yr' 3* ' (mrad) - P
,pCi-m 3,
*()*{ ,
Ci
- arad-m PCi-yr, 7.2.6 Dose to Critical Ornan From Iodines. Tritium and Particulates With Half-Lives Greater Than Einht Days This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose assessments.
1 Method I may be used to show that the Technical Specifications which limit off-site organ dose from gases (3.11.2.3 and 3.11.4) have been met for releases over the appropriate periods. Technical Specification 3.11.2.3 is based on the AIARA objectives in 10CFR50, Appendix I, Subsection II C. Technical Specification 3.11.4 ; is based on Environmental Standards for Uranium Fuel Cycle in 40CFR190, which applies to direct radiation as well as liquid and gaseous effluents. These methods apply only to iodine, tritium, and particulates in gaseous effluent contribution. Method I was developed such that "the actual exposure of an individual ... is unlikely to be substantially underestimated" (10CFR50, Appendix I) . The use below of a single " critical receptor" provides part of the conservative margin to the calculation of critical organ dose in Method I. Method II allows that actual individuals, associated with identifiable exposure pathways, be taken into account for any given release. In fact, Method I was based on a Method II analysis of a critical receptor assuming all pathways present. That analysis was called the " base case"; it was then reduced to form Method I. The base case, the method of reduction, and the assumptions and data used are presented below. O B.7-18 ODCM Rev. 16
7.2 CASEOUS RELEASE DOSE CALCULATIONS 7.2.6 Dose to critical Orran From Todines. Tritium and Particulates With 4 Half-Lives Creater Than Eirht Days The steps performed in the Method I derivation follow. First, the dose impact to the critical receptor [in the form of dose factors DFG1 , (arem/pci)] for a unit activity release of each iodine, tritium, and particulate radionuclide with half lives greater than eight days to gaseous effluents was derived. Six exposure pathways (ground plane, inhalation, stored vegetables, leafy vegetables, milk, and i meat ingestion) were assumed to exist at the site boundary (not over water or marsh j areas) which exhibited the highest long-term X/Q. Doses were then calculated to six organs (bone, liver, kidney, lung, GI-LLI, and thyroid), as well as for the whole 1 body and skin for four age groups (adult, teenager, child, and infant) due to the seven combined exposure pathways. For each radionuclide, the highest dose per unit activity release for any organ (or whole body) and age group was then selected to become the Method I site-specific dose factors. The base case, or Method I analysis, uses the general equations methods, data, and assumptions in Regulatory Guide 1.109 (Equation C-2 for doses resulting from direct exposure to contaminated i ground plane; Equation C-4 for doses associated with inhalation of all radionuclides 4 to different organs of individuals of different age groups; and Equation C-13 for I doses to organs of individuals in different age groups resulting from ingestion of l radionuclides in produce, milk, meat, and leafy vegetables in Reference A). Tables B.7-2 and B.7-3 outline human consumption and environmental parameters used in the
- analysis. It is conservatively assumed that the critical receptor lives at the
" maximum off-site atmospheric dispersion factor location" as defined in Section 7.3.
l The resulting site-specific dose factors are for the maximum organ which l combine the limiting age group with the highest dose factor for any organ with each f 5 nuclide. These critical organ, critical age dose factors are given in Table B.1-12. Appendix A provides an example of the development of Method I gaseous dose conversion factor for site-specific conditions at Seabrook. For any iodine, tritium, and particulate gas release, during any period, the increment in dose from radionuclide "i" is: ADi . - Q1DFGi ,, (7-16) where DFCs., is the critical dose factor for radionuclide "i" and Qi is the activity of radionuclide "i" released in microcuries. Applying this information, it follows that the general form for the critical organ dose equation is: l O B.7-19 ODCM Rev. 16
7.3 CASEOUS RELEASE DOSE CALCUIATIONS 7,2.6 Dose to Critical Organ From Iodines. Tritium and Particulates With Half-Lives creater Than Eirht Days (Continued) O D., - (X/Q)M/(X/Q)df
- t** *
(Qi
- DFG..)
i (3-8) arem - 'see' / sec' * () * { uCi
- arem' 7.
Substituting specific values associated with the maximum off-site receptor location and elevated release condition yields: D.,c,3 - (1.12E-05)/(7.55E-07)
- t-o.2s? , (qt , pp g ,(,,)
which reduces to: D,,c,3 - 14. 8
- t-o.2e7 * (Q
- DFG ) (3-8a)
For the maximum off-site receptor location and ground-level release conditions, the equation is: D,,c,3 - (1.71E-04)/(9.64E-06)
- t-o.32s . (q, , pyg,,,(,,)
which reduces to: D, c,3 - 17. 7
- t-0 318 e h (Q
- DFGug) i (3-8b) 7.2.7 Snecial Recentor Caseous Release Dose Calculations 1 Technical Specification 6.8.1.4 requires that the doses to individuals l involved in recreational activities within the site boundary are to be determined and reported in the Annual Radioactive Effluent Release Report.
1 The gaseous dose calculations for the special receptors parallel the bases of ' the gaseous dose rates and doses in Sections 7.2.1 through 7.2.5. Only the differences are presented here. The special receptor XQs are given in Table B.7-5. i 7.2.7.1 Total Body Dose Rate From Noble Cases l Method I was derived from Regulatory Guide 1.109 as follows: 1 O B.7-20 ODCM Rev. 16
7.2 GASEOUS RELEASE DOSE CALCU1ATIONS 7.2.7.1 Total Rody Dose Rate From Noble Gases (Continued) e be,- 1E+06 [X/Q)? Qi DFB i (7-3) General Equation (7-3) is then multiplied by an Occupancy Factor (OF) to account for the time an individual will be at the on-site receptor locations during ; the year. There are two special receptor locations on-site. The " Rocks" is a boat j landing area which provides access to Browns River and Hampton Harbor. The Seabrook Station UFSAR, Chapter 2.1, indicates little boating activity in either Browns River l or nearby Hunts Island Creek has been observed upon which to determine maximum or - conservative usage factors for this on-site shoreline location. As a result, a default value for shoreline activity as provided in Regulatory Guida 1.109, Table j E-5, for maximum individuals was utilized for determining the " Rocks" occupancy ! factor. The 67 hours / year corresponds to the usage factor for a teenager involved j in shoreline recreation. This is the highest usage factor of all four age groups } listed in Regulatory Guide 1.109, and has been used in the ODCM to reflect the ! maximum usage level irrespective of age. ! Regulatory Guide 1.109 does not provide a maximum individual usage factor for activities similar to those which would be associated with the Seabrook Station ! Science & Nature Center. Therefore, the usage factor used in the ODCM for the i Science & Nature Center reflects the observed usage patterns of visitors to the facility. Individuals in the public who walk in to look at the exhibits on display { and pick up availtble information stay approximately 1.5 hours each. Tour groups j who schedule visits to the facility stay approximately 2.5 hours. For conservatism, it was assumed that an individual in a tour group would return five times in a year, and stay 2.5 hours on each visit. These assumptions, when multiplied together, ; O provide the occupancy factor of 12.5 hours / year used in the ODCM for public activities associated with the Science & Nature Center. > For the Science & Nature Center, and the " Rocks", the occupancy factors , (OFs) are: Science & Nature Center - 12.5 hrs /yr
- 0.0014 5760 hrs /yr The " Rocks" - 57 hrs /yrm - 0.0076 5760 hrs /yr O m Taken from Seabrook Station Technical Specifications (Figure 5.1-1) .
B.7-21 ODCM Rev. 16
7.2 GASEOUS RELEASE DOSE CAlfUIATIONS 7.2.7.1 Total Body Dose Rate From Noble Cases (Continued) substituting in the annual average gamma X/Qs: [X/Q)? - 1.1E-06 sec/m3 (Science & Nature Center) for primary vent stack releases.
- 5.3E-06 seem 8 (Science & Nature Center) for ground level releases.
- 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases.
- 2.6E-05 sec/m3 (The " Rocks") for ground level releases.
cnd multiplying by: OF - 0.0014 (Science & Nature Center)
- 0.0076 (The " Rocks")
gives: bagc,3 = 0.0015 * (Qi
- DFBi ) -(arem/yr) (3-3c) bar(s) = 0.0074 * (Qi
- DFBi ) (ares /yr) (3-3d) bagt,3 = 0.038 * (Qi
- DFBi ) (arem/yr) (3-3e) l 1
bants) = 0.2 * {s (Qi
- DFB ) i (mrem /yr) (3-3f) l 1
where: Narc.). barts). banc.), and 6aa(s) - total body dose rates to an individual ( at the Science & Nature Center and the
" Rocks" (recre#tional site),
respectively, due to noble gases in an elevated (e) and ground level (g) release, Qi and DF5s are as defined previously. 7.2.7.2 Skin Dome late From Noble Gases 1 1 Method I was derived from Equation (7-8): l bag - 1.111E+06 [X/Q)7 { Q DF] + i (7-8) I 1E+06 X/Q { Q3 DFS i O 1 B.7-22 ODCM Rev. 16 j i l l
i 2 7.2 CASEOUS RELEASE DOSE CALCUIATIONS I i 7.2.7.2 Skin Dose Rate From Noble Cases (Continued) 0 l substituting in the annual average gamma X/Qs: l [X/Q]1 - 1.1E-06 sec/m3 (Science & Nature Center) for primary vent stack releases. 1 ' 3
- 5.3E-06 sec/m (Science & Nature Center) for ground level release points.
i l 3
- 5.0E-06 sec/m (The " Rocks") for primary vent stack releases.
- 2.6E-05 sec/m 8 (The " Rocks") for ground level release points. !
and the annual average undepleted X/Qs-i j X/Q - 1.6E-06 sec/m 3 (Science & Nature Center) for primary vent stack releases. ! l
- 2.3E-05 sec/m3 (Science & Nature Center) for ground level release points.
- 1.7E-05 sec/m 8 (The " Rocks") for primary vent stack releases.
l
- 1.6E-04 sec/m 8 (The " Rocks") for ground level release points. l
} and multiplying by: i 0F - 0.0014 (Science & Nature Center)
- 0.0076 (The " Rocks")
4 gives: bainst.) = 0.0014 { Qi [1.22 DFj + 1.60 DFSi ] for an elevated release point. 1 i bai,gg,3 = 0.0014 { Qi [5.88 DFJ + 23 DFS i ) for a ground level release point. )
- i bg wg.3 = 0.0076 Qi [5.55 DFJ + 17.0 DFS i ) for an elanted release point.
bainacs) = 0.0076 Qi [28.9 DF] + 160 DFSi ) for a ground level release point. and the equations can be written: i bai,gg,3 = 0.0014 * { (Q *i DF[gg.3) (3-4c) 8 l 1 Ov B.7-23 ODCM Rev. 16
l 7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.7.2 Skin Dose Rate From Noble Cases (Continued) Ddidcs) = 0.0014 * { (Qi
- DFar(s)) (3 4d)
Daist,3 - 0.0076 * { (Qi
- DFag.3) (3-4e)
Dead (s) = 0.0076 * { (Qi
- DFag,3) (3-4f) where:
beanst.). b n int (s>' b
- i d (.), and 6gigg,3 = the skin dose rate (mrem /yr) to an individual at the Science &
Nature Center and the " Rocks", respectively, due to noble gases in an elevated (e) and ground level (g) release, Qi - defined previously, and DFisc.), DIgg,3, i Diag,3and t Diag,3 - the combined skin dose factors for radionuclide "i" for the Science & Nature Center and the " Rocks", respectively, for elevated (e) and ground level (g) release points (see Table B.1-13). 7.2.7.3 Critical Orean Dose Rate From Iodines. Tritium and Particulates With Half-Lives Greater Than Einht Days The equations for be , are derived in the same manner as in Section 7.2.2, except that the occupancy factors are also included. Thercfore: Deorg,3 = 0.0014 * { (Qi
- DFGl..gg.3) for an elevated release. (3-Sc) i Dcor(s) = 0.0014 * (Qi
- DFGi ogg,3) for a ground level release. (3-5d)
Dcoat.) = 0.0076 * (Qi
- DFGl.ac.3) for an elevated release. (3-Se)
O B.7-24 ODCM Rev. 16
I 7.2 CASEOUS RELEASE DOSE CA14UIATIONS ;
'f 7.2.7.3 Critical Orean Dose Rate From Iodines. Tritium and Particulates With f s Half-Lives Creater Than Eirht Days (Continued) !
besa(s) = 0.0076 * (Qi
- DFGicam(s)) for a ground level release. (3 - 5 f) where: !
I D .sg.3, D..gc,3, Deance). and D eem(s) - the critical organ dose rates i (area /yr) to an individual at the ! Science & Nature Center and the ,
" Rocks", respectively, due to iodine, tritium, and particulates in elevated (e) and ground level (g) releases, .
Qi - as defined previously, and
)
DFG[cosc 3, DFGie s(s), DFC$ coat.), and DFC com(*) - the critical organ dose rate I factors for radionuclide "i" for i the Science & Nature Center and I the " Rocks", respectively, for ! elevated (e) and ground level (g) ; release points (see Tables B.1-14 ! and B.1-15). [ 7.2.7.4 0 - - Dose to Air From Noble Cases \ Method I was derived from Equation (3-6): DL - 3.17E-02 * [X/Q)6
- t** * { (Qi
- DFI) (3-6) i where all terms of the equation are as defined previously.
Incorporating the specific 0F and the atmospheric dispersion factor, the gamma air dose equation for the Science & Nature Center for elevated releases: Dhsc.3 - 3.17E-02 e 1.1E-05 t-o.as
- 0.0014 * (Q,
- DFI) which reduces to:
O B.7-25 ODCM Rev. 16
7.2 CASEOUS RELEASE DOSE CALCULATIONS 7.2.7.4 C=-== Dose to Air From Noble Cases (Continued) D!i,gg,3 = 4. 9E-10
- t-0 252 * (Qi
- DFI) (3-6c)
"PC i-yr' Ci e arad-m' 8
(mrad) - * ( )*{
,pci-m 3, PCi-yr, For ground-level releases, the gamma air dose equation for the Science & Nature Center becomes:
1 D!i,cgc,3 - 3.17E-02 e 1.0E-04 t-o.szt
- 0.0014 * { (Qi
- DFI) which reduces to:
i Djirr(s) = 4.4E-09
- t-o.321 * { (Q
- DFI) i (3-6d)
A 3, Ci-yr' (mrad) . P 3 * ( )*{ uCi
- mrad-m PCi-yr
.pCi-m . - -
Incorporating the specific 0F and atmospheric dispersion factors for the
" Rocks" yields the gamma air dose equation for elevated releases:
D!irag 3 - 3.17E-02
- 2.1E-05
- t-0155
- 0.0076 * { (Qi e DFI) which reduces to:
Djirate) " 5.1E-09
- t-0 155 * (Qi
- DFJ) (3-6e)
(arad) . P Ci-yr' mrad-m3, 3 * ( )*{ uCi e P Ci-yr,
,9Ci-m , ,
For ground-level releases, the gamma air dose equation for the " Rocks" becomes: D!i,ac,3 - 3.17E-02
- 1.7E-04 t-o.20'
- 0.0076 * { (Q e DFI) i which reduces to:
O B.7-26 ODCM R2v. 16
I 7.2 CASEOUS RELEASE DOSE CALCUIATIONS 7.2.7.4 C=== Dose to Air From Noble Cases (Continued) s D irats) = 4.1E-08
- t-o.20' *' { (Qi *DFI) (3-6f) i l
(arad) -
'pci-yr' Ci
- aradM
* ( )*{ Pci-yr i pCi-m3 ,
7.2.7.5 Beta Dose to Air From Noble Cases Method I was derived as described in Section 7.2.5. The general form of the dose equation is: D{i, - 3.17E-02
- X/Q$** t-* * (Q1
- DFf) (3-7) ,
where all terms in the equation are as defined in Section 7.2.5. Incorporating the specific OF and atmospheric dispersion factor for k elevated releases into Equation 3-7 yields the following beta dose equation for the Science & Nature Center: D{3,gg,3 - 3.17E-02
- 4.0E-05
- t-0 85
- 0.0014 * { (Qi
- DFf)
A which reduces to: D{3,gg 3 - 1.8E-09 + t-0 85 * { (Qi
- DIT) (3-7c) s 3,
(arad) - 'PCi-yr' 3 * ( )*{ pCi
- mrad-m Pci-yr pCi-m , ,
For ground-level releases, the beta air dose equation for the Science & Nature Center becomes: D{i,sc,3 - 3.17E-02
- 5.5E-04
- t-0 3'7
- 0.0014 * { (Qi
- DET) 1 l
which reduces to: B.7-27 ODCM Rev. 16
7.2 GASEOUS RELEASE DOSE CALCULATIONS i l 7.2.7.5 Beta Dose to Air From Noble Gases (Continued) l D{1,,c,3 - 2.4E-08
- t-0 8'?
- E (Qi
- Dd) (3-7d)
(arad) =
'PCi-yr'
* ( )*{ Ci , arad-af
,pci-m3, PCi-yr, Incorporating the specific 0F and atmospheric dispersion factors for the
" Rocks" yields the beta air dose equation for elevated releases: D{irag.3 - 3.17E-02
- 1.6E-04
- t-o.24s e 0.0076 * (Q
- DF{)
i which reduces to: 1 Dfirac.) - 3.9E-08 + t-o.zas . { (q, . pp{) (3 7.) 8, Ci-yr' (arad) - P
* ( )*{ aci
- mrad-m PCi-yr s
pCi-m' . - < For ground-level releases, the beta air dose equation for the " Rocks" becomes: D{irats) - 3.17E-02
- 1.9E-03
- t-o.2s7
- 0.0076 * (Qi
- DF{}
which reduces to: D{irac,3 - 4. 6E-07
- t-o.2s7 (q , pq) ( 3.,7 f) l Ci-yr' arad-m3, (arad) . P
* ( )*{ uCi e PG1-yr ,
pci-m', , 7.2.7.6 Critical Orean Dose From Iodines. Tritium and Particulates With Half-Lives Greater Than Eight Days Method I was derived as described in Section 7.2.3. The Critical Organ Dose equations for receptors at the Science & Nature Center and the " Rocks" were derived from Equation 3-8. The following general equation incorporates (i) a B.7-28 ODCM Rev. 16
7.2 GASEOUS RELEASE DOSE CALCUIATIONS 7.2.7.6 Critical Orran Dose From Iodines. Tritium and Particulates With Half-Lives Greater Than Eirht Days (Continued) I ratio of the average 1-hour depleted atmospheric dispersion factor to the average annual depleted atmospheric dispersion factor, (ii) the unitiess t-* term, and (iii) , the OF: D , - (X/Q){*.6/(X/Q)d*P1
- t-*
- OF * { (Q
- DFG3 ,,)
i 1 (area) - / *( )*( )*{ pCi
- Applying the Science & Nature Center-specific factors for elevated release conditions produces the equation:
Decr(*) - (3.72E-05)/(1.56E-06)
- t-0 3'8
- 0.0014 * { (Q e DFG i i c,3) 1 l which reduces to:
D,,gg,3 - 3. 3E-02
- t-0 8'8 * { (Qi
- DFG i g,3) (3-8c) o (arem) - ( )*( )*{ gCi
- i For a ground-level release, the equation for a receptor at the Science & Nature Center is:
0,,gg,3 - (5.21E-04)/(2.23E-05)
- t-0 3'7
- 0.0014 * { (Qi
- DFG .,c,3)i j which reduces to:
D,,gg,3 - 3.3E-02
- t-0 847 * { (Qi
- DFGi . c,3) (3-8d) l l
- (area) = ( )*( )*{ uCi e i The specific Critical Organ Dose equation for a receptor at the " Rocks" under elevated release conditions is
B.7-29 ODCM Rev. 16
l 7.2 GASEOUS RELEASE DOSE CAlfU1ATIONS ! 7.2.7.6 Critical Orran Dose From Todines. Tritium and Particulates With Half-Lives Greater Than Eirht Days (Continued) D,ac,3 - (1.54E-04)/(1.61E-05)
- t-o.zas
- 0.0076 * (Qi e DFG3 ,,g,3)
O l I which reduces to: D,ag,3 - 7.3E-02
- t-o.zas * (Qi
- DFG.g,3) i (3-Se)
(area) - ( )*( )*{ uCi
- For a ground-level release, the equation for a receptor at the " Rocks" is:
D,ag,3 - (1.80E-03)/(1.59E-04) e t-o.zsr = 0.0076 * { (Qi
- DFGi ,c,3) which reduces to:
D,ag,3 - 8.6E-02
- t-8 287 * (Qi
- DFG i c,3) (3-8f)
(area) - ( )*( )*{ Ci e The special receptor equations can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (nonemergency event).
- 2. Applicable radionuclide releases via the station vents to the atmosphere.
If Methad I cannot be applied, or if the Method I dose exceeds this limit, or if a more refined calculation is required, then Method II may be applied. O B.7-30 ODCM Rev. 16
O~ v V TABLE B.7-2 ENVIRONMENTAL PARAMETERS FOR GASEOUS EFFLUENTS AT SEABROOK STATICN (Derived from Reference A)* Vegetables Cow Milk Coat Milk Meat Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored YV Agricultural Productivity (Kg/M2 ) 2. 2. 0.70 2. 0.70 2. 0.70 2. P Soil Surface Density (Kg/M2 ) 240, 240. 240. 240. 240. 240. 240. 240. T Transport Time to User (HRS) 48. 48. 48, 48. 480. 480. TB Soil Exposure Time m (HRS) 131400. 131400. 131400. 131400. 131400. 131400. 131400. 131400. TF Crop Exposure Time to Plume (HRS) 1440. 1440. 720. 1440. 710. 1440. 720. 1440. TH Holdup After Harvest (HRS) 1440. 24. O. 2160. O. 2160. O. 2160. Animals Daily Feed (Kg/ DAY) 50. 50. 6. 6. 50. 50. QF FP Fraction of Year on Pasture tz) 0.50 0.50 0.50 FS Fraction Pasture when on 1. 1. 1. Pasture (33 FG Fraction of . Stored Veg. Grown in 0.76 Garden FL Fraction of Leafy Veg. Grown in 1.0 Garden FI Fraction Elemental Iodine - 0.5 H Absolute Humidity - 5.60"3 (gm/m3 )
- Regulatory Guide 1.109, Rev. 1 B.7-31 ODCM Rev. 16
TABLE B.7-2 ENVIRONMENTAL PARAMETERS R)R GASEOUS EFFLUENTS AT SEABROOK STATION (Continued) N:tes: (1) For Method II dose / dose rate analyses of identified radioactivity releases of less than one year, the soil exposure time for that release may be set at 8760 hours (1 year) for all pathways. (2) For Method II dose / dose rate analyses performed for releases occurring during the first or fourth calendar quarters, the fraction of time animals are assumed to be on pasture is zero (nongrowing season). For the second and third calendar quarters, the fraction of time on pasture (FP) will be set at 1.0. FP may also be adjusted for specific farm locations if this information is so identified and reported as part of the land use census. (3) For Method II analyses, the fraction of pasture feed while on pasture may be set to lese than 1.0 for specific farm locations if this information is so identified and reported as part of the land use census. For all Method II analyses, an absolute humidity value equal to 5.6 (ga/m3 ) shall be used to reflect conditions (4) in the Northeast (
Reference:
Health Physics Journe , Vol. 39 (August), 1980; Page 318-320, Pergammon Press). B.7-32 ODCM Rev. 16 O O O
1 I TABLE B.7-3 l USAGE FACTORS FOR VARIOUS GASEOUS PATHWAYS AT SEABROOK STATTON (from Reference A, Table E-5)* I Maximum Receptor: Age Leafy ; 4 Groun Venetables Venetables Hilk HRA1 Inhalation (kg/yr) (kg/yr) (1/yr) (kg/yr) (m8 /yr) ! 1 Adult 520.00 64,00 310.00 110.00 8000.00 l Teen 630.00 42.00 400.00 65.00 8000.00 i Child $20.00 26.00 330.00 41.00 3700.00 l Infant 0.00 0.00 330.00 0.00 1400.00 j i i The " Rocks" and Science & Nature Center: Age leafy GI2gg Venetables Venetablar gilk gggg Inhalation (m3 /yr)
; (kg/yr) (kg/yr) (1/yr) (kg/yr) l Adult 0.00 0.00 0.00 0.00 8000.00 l Teen 0.00 0.00 0.00 0.00 8000.00 l l Child 0.00 0.00 0.00 0.00 3700.00 l Infant 0.00 0.00 0.00 0.00 1400.00 s.
l
- Regulatory Guide 1.109 l l
B.7-33 ODCM Rev. 16
7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHWAYS The gaseous effluent dose equations (Method I) have been simplified by cssuming an individual whose behavior and living habits inevitably lead to a higher dose than anyone else. The following exposure pathways to gaseous effluents listed in Regulatory Guide 1.109 (Reference A) have been considered:
- 1. Direct exposure to contaminated air;
- 2. Direct exposure to contaminated ground;
- 3. Inhalation of air;
- 4. Ingestion of vegetables;
- 5. Ingestion of goat's milk; and
- 6. Ingestion of meat.
Section 7.3.1 details the selection of important off-site and on-site locations and receptors. Section 7.3.2 describes the atmospheric model used to convert meteorological data into atmospheric dispersion factors. Section 7.3.3 presents the maximum atmospheric dispersion factors calculated at each of the off-site receptor locations. 7.3.1 Receptor Locati2B1 The most limiting site boundary location in which individuals are. or likely to be located as a place of residence was assumed to te the receptor for all the gaseous pathways considered. This provides a conservative estimate of the dose to an individual from existing and potential gaseous pathways for the Method I analysis. This point is the west sector, 974 meters from the center of the reactor units for undepleted, depleted, and gamma X/Q calculations, and the northwest section, 914 meters for calculations with D/Q the dispersion parameter. The site boundary in the NNE through SE sectors is located over tidal marsh (e.g., over water), and consequently are not used as locations for determining maximum off-site receptors (Reference NUREG 0133). O B.7-34 ODCM Rev. 16
7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHUAYS 7.3.1 Receptor Incations (continued) Two other locations (on-site) were analyzed for direct ground plane exposure l and inhalation only. They are the " Rocks" (recreational site) and the Education Center shown on Figure 5.1-1 of the Technical Specifications. l 7.3.2 Seabrook Station Atmosnherie Disnersion Model i The time average atmospheric dispersion factors for use in both Method I and Method II are computed for routine releases using the AEOLUS-2 Computer Code (Reference B). AEOLUS-2 produces the following average atmospheric dispersion factors for each location: I
- 1. Undepleted X/Q dispersion factors for evaluating ground level l concentrations of noble gases;
- 2. Depleted X/Q dispersion factors for evaluating ground level l concentrations of iodines and particulates;
- 3. Gamma X/Q dispersion factors for evaluating gamma dose rates from a '
sector averaged finite noble gas cloud (multiple energy undepleted ; source); and 4 D/Q deposition factors for evaluating dry deposition of elemental ; radiciodines and other particulates. Gamma dose rate is calculated throughout this ODCM using the finite cloud model presented in " Meteorology and Atomic Energy - 1968" (Reference E, Section 7-5.2.5). That model is implemented through the definition of an effective gamma atmospheric dispersion factor, [X/Q1) (Reference B, Section 6), and the replacement of X/Q in iaSmite cloud dose equations by the [X/Q'). t 7.3.3 gyar-- amanharie Dinnersion Factors for Recentors The calculation of Method I and Method II atmospheric diffusion factors (undepleted CHI /Q, depleted CHI /Q, D/Q, and gamma CHI /Q values) utilize a methodology generally consistent with US NRC Regulatory Guide 1.111 (Revision 1) criteria and the methodology for calculating routine release diffusion factors as represented by the XOQD0Q computer code (NUREG/CR-2919), The primary vent stack is treated as a " mixed-mode" release, as defined in Regulatory Guide 1.111. Effluents O are considered to be part-time ground B.7-35 ODCK Rev. 16
l 7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHWAYS 7.3.3 Averare Ae=nscheric Dispersion Factors for Receptors (Continued) I level /part-time elevated releases depending on the ratio of the primary vent stack effluent exit velocity relative to the speed of the prevailing wind. All other release points (e.g., Turbine Building and Chemistry lab hoods) are considered ground-level releases, i In addition, Regulatory Guide 1.111 discusses the concept that constant mean wind direction models like AEOLUS-2 do not describe spatial and temporal variations in airflow such as the recirculation of airflow which can occur during prolonged periods of atmospheric stagnation. For sites near large bodies of water like Seabrook, the onset and decay of sea breezes can also result in airflow reversals and curved trajectories. Consequently, Regulatory Guide 1.111 states that adjustments to constant mean wind direction model outputs may be necessary to account for such spatial and temporal variations in air flow trajectories. Recirculation correction factors have been applied to the diffusion factors. The recirculation correction factors used are compatible to the " default open terrain" recirculation correction factors used by the XOQDOQ computer code. The relative deposition rates, D/Q values, were derived using the relative deposition rate curves presented in Regulatory Guide 1.111 (Revision 1). These curves provide estimates of deposition rates as a function of plume height, stability class, and plume travel distance. Recentor Locations For ground-level releases, the downwind location of "The Rocks" (244m NE/ENE) and the Science & Nature Center (406m SW) were taken as the distance from the nearest point on the Unit 1 Administrative Building / Turbine Building complex. For the site boundary, the minimum distances from the nearest point on the ! Administration Building / Turbine Building complex to the site boundary within a j 45-degree sector centered on the compass direction of interest as measured from i UFSAR Figure 2.1-4A were used (with the exception that the NNE-NE-ENE-E-ESE-SE site . boundary sectors were not evaluated because of their over-water locations). I i For primary vent stack releases, the distances from the Unit 1 primary vent l i stack to "The Rocks" (244m NE) and the Science & Nature Center (488m SW) as measured from a recent site aerial photograph were used. For the site boundary, the minimum distances frem the Unit 1 primary vent stack to the site boundary within a 45-degree sector centered on the compass direction of interest as measured from UFSAR Figure 2.1-4A were used (with the exception that the B.7-36 ODCM Rev. 16 l
7.3 RECEPTOR POINTS AND AVERAGE ATMOSPHERIC DISPERSION FACTORS FOR IMPORTANT EXPOSURE PATHWAYS 7.3.3 Averara Awanharie Disnersion Factors for Recentors (Continued) NNE-NE-ENE-E-ESE-SE site boundary sectors were not evaluated because of their over-water locations). Meteoro1orical Data Bases For "The Rocks" and Science & Nature Center receptors, the diffusion factors represent six-year averages during the time period January 1980 through December 1983 and January 1987 through December 1988 (with the exception that, because of low data recovery, April 1979 and May 1979 were substituted for April 1980 and May 1980). For the site boundary receptors, both six-year average growing season (April through September) and year-round (January through December) diffusion factors were generated, with the higher of the two chosen to represent the ; site boundary. The meteorological diffusion factor used in the development of the ODCM Method I dose models are summarized on Tables B.7-4 through B 7-6. O O B.7-37 ODCM Rev. 16
TABLE B.7-4 SEABROOK STATION IDNG-TERM AVERAGE DISPERSION FACTORS
- PRIMARY VENT STACK O
Dose Rate to Individual Dose to Air Dose to Critical Organ Total Skin Critical Gamma Beta Thyroid Body Organ
- - - 7.5E-07 X/Q depleted
- - - 8.2E-07 -
X/Q undepleted
- - 1. 5 E-08" - - 1.5E-08
'l D/Q
.P.
s e c' 8 R -07 8.5E-07 - 8.5E-07 - - X/Q, 7 O
- Wst site boundary, 974 meters from Containment Building
- Northwest site boundary, 914 meters from Containment Building B.7-38 ODCM Rev. 16
d [ TABLE B.7-5 SEABROOK STATION IDNG-TERM AVERAGE DISPERSION FACTORS
- p FOR SPECIAL (ON-SITE) RECEPTORS ;
PRIMARY VENT STACK
\
j Dose to Critical Dose Rate to Individual Dose to Air Organ Total Skin Critical Gamma Beta Thyroid Body Organ Education Center: (SW - 488 meters)
's e c'
- - 1.5E-06 - -
1.5E-06 X/Q depleted 7
, , c' - 1.6E-06 - -
1.6E-06 - X/Q undepieted
'1' - -
2.7E-08 - - - i D/Q p
, 's e c' 1.1E-06 1.1E-06 -
1.1E-06 - -
? \
The " Rocks =: (ENE - 244 meters) l l
'sec' - -
1.6E-05 - - 1.6E-05 X/Q depleted
,, e' - 1.7E-05 - -
1.7E-05 - X/Q undepleted s .
't'
- - 1.1E-07 - - -
D/Q p ,
.. e' 5.0E-06 5.0E-06 -
5.0E-06 - - X/Q, 7 B.7-39 ODCM Rev. 16
l TABLE B.7-6 SEABROOK STATION LONC-TERM ATMOSPHERIC DIFFUSION AND DEPOSITION FACTORS CROUND-LEVEL RELEASE PATHVAY R E C E P T O R(*) Diffusion Factor The Rocks Science & Nature Off-Site Center Undepleted CHI /Q 1.6 x 10-* 2.3 x 10-5 1.0 x 10-5 3 sec/m (244m ENE) (406m SW) (823m W) Depleted CHI /Q, 1.5 x 10-* 2.1 x 10-5 9.4 x 10-8 3 sec/m (244m ENE) (406m SW) (823m W) D/Q, m-2 5.1 x 10-7 1.0 x 10-7 5.1 x 10-e (244m ENE) (406m SW) (823m W) Camma CHI /Q, sec/m3 2.6 x 10-5 5.3 x 10-8 3.4 x 10-5 (244m ENE) (406m SW) (823m W) O l l l l l l (*) The highest site boundary diffusion and deposition factors occurred during the April through September growing season. Note that for the primary vent stack release pathway, none of the off-site receptor diffusion and deposition factors (located at 0.25-mile increments beyond the site boundary) exceeded j the site boundary diffusion and deposition factors. l B.7-40 ODCM Rev. 16 1
i 8.0 BASES FOR LIQUID AND GASEOUS MONITOR SETPOINTS 8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT The liquid waste test tank monitor setpoint must ensure that Specification . 3.3.3.9 is not exceeded for the appropriate in-plant pathways. The liquid waste test tank monitor is placed upstream of the major source of dilution flow. l The derivation of Equation 5-1 begins with the general equation for the response of a radiation monitor: i ] R = { C,i S,i 4 i (8-1) (cps)= (pCi) ( cps-el)
- ml pCi 1
i j where: l R - Response of the monitor (cps) l Sit - Detector counting efficiency for radionuclide "i" (eps/(pci/ml)) C ,1 - Activity concentration of radionuclide "i" in mixture at the monitor (pCi/ml) f~s The detector calibration procedure for the liquid waste test tank monitor at i ( , Seabrook Station establishes a counting efficiency by use of a known calibration
- source standard and a linearity response check. Therefore, in Equation 8-1 one may substitute St for Sti , where S t is the detector counting efficiency determined from f the calibration procedure. Therefore, Equation 8-1 becomes:
1 i 4 R= Sg {Ci at (8-2) i 1 (cps) = ( cps-el) (pCi)
- pCi al I
8 I J
- O B.8-1 ODCM Rev. 16
- f
8,1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOIN* (C2ntinurd) The KPC for a given radionuclide must not be exceeded at the point of discharge. When a mixture of radionuclides is present, 10CFR20 specifies that the concentration at the point of discharge shall be limited as follows: C'd s1 {'MPC, (8-3) i ( pCi-sl ) mi-pCi where: Cat
- Activity concentro don of radionuclide "i" in the mixture at the point of discharge s 11/ml)
MPCs - MPC for radionuclide 1" from 10CFR20. Appendix B, Table II, Column 2 (pCi/ml) The activity concentration of radionuclide "i" at the point of discharge is related to the activity concentration of radionuclide "i" at the monitor as follows: F C,i - C, 2 (8 4) F, pCi) , pCi) ( gpm) ml ml gpm where: Cat - Activity concentration of radienuclide "i" in the mixture at the point of discharge (pci/ml) F. - Flow rate past monitor (gpm) F4 - Flow rate out of discharge tunnel (gpm) B.8-2 ODCM Rev. 16 elI i
8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT (Centinusd) Substituting the right half of Equation 8-4 for Cet in Equation 8-3 and solving for p) F4 /F, yields the minimum dilution factor needed to comply with Equation 8-3. ; j F DF in 5 2 E ,C"' (8-5) (gps) (pCi-el y gpm al-sci where: F4 - Flow rate out of discharge tunnel (gpa) F. - Flow rate past monitor (gpt) l 1 C.i - Activity concentration cf radlinuclide "i" in mixture at the monitor (pCi/ml) , I MPCs - MPC for radionuclide "i" from 10CFR20, Appendix B. Table II, Column I 2 (pci/al) If F 4 /F, is less than DF.in, then the tank may not be discharged until either F4 or F or both are adjusted such that: 1 1 F 2 DF,in (8 5) l (9Pm) gpm Usually F 4/F, is greater than DF.1, (i.e., there is more dilution than necessary to comply with Equation 8-3). The response of the liquid waste test tank monitor at the setpoint is therefore: DF R,,,,in, = fg S Cat (8-6) DF,in i al
.( )( ) (cpsel) (8C1) pCi al O ODCM Rev. 16 B.8 3
8.1 BASIS FOR THE LIQUID WASTE TEST TANK MONITOR SETPOINT (Ctntinund) where ft is equal to the fraction of the total contribution of MPC at the discharge point to the environment to be associated with the test tank effluent pathway, such that the total sum of the fractions for the four liquid discharge pathways is equal to or less than one (fx + f + f + f4 5 1). The monitoring system is designed to incorporate the detector efficiency, S ,t into its software. This results in an automatic readout in pCi/cc or pCi/ml for the tonitor response. Since this procedure for converting eps to pCi/ml is inherently done by the system software, the monitor response setpoint can be calculated in terms of the total waste test tank activity concentration in pCi/ml determined by the laboratory analysis. Therefore, the setpoint calculation for the liquid waste test tank is: DF R,,, gin, - f t C,, (5 1) DF,in i ( ml ) ( )( ) ( ml ) O l B.8 4 ODCM Rev. 16 O
-i - 8.2 BASIS FOR THE PIANT VENT WIDE RANGE CAS MONITOR SETPOINTS The setpoints of the plant vent wide range gas monitors must ensure that j'~' Technical Specification 3.11.2.1.a is not exceeded. Sections 3.4 and 3.5 show that
! Equations 3-3 and 3-4 are acceptable methods for determining compliance with that
- Technical Specification. Which equatien (i.e., dose to total body or skin) is more
'; limiting depends on the noble gas mixture. Therefore, each equation must be considered separately. The derivations of Equations 5-5 and 5-6 begin with the general equation for the response R of a radiation monitor: I R- S,, C,i (3,7) i i 3 1 (cpm)= ( cpm-cm ) (pCi) pCi cm 3 l where: 1 ! R - Response of the instrument (cpm) S,1 - Detector counting efficiency for noble gas "i" (epa /(pci/cm 8)) i Ce - Activity concentration of noble gas "i" in the mixture at the noble
- gas activity monitor (pCi/cm 8) 1 C.1, the activity concentration of noble gas "i" at the noble gas activity monitor, may be expressed in terms of hg by dividing by F, the appropriate j flow rate. In the case of the plant vent noble gas activity monitors the appropriate flow rate is the plant vent flow rate.
C,i = Qi (8-8) g pCi) , yCi) sec) 3 59C 3 I c'4 cm where: ] di - The release rate of noble gas "i" in the mixture, for each
; noble gas listed in Table B.1-10.
) F - Appropriate flow rate (cm 8/sec) I ' Substituting the right half of Equation 8-8 into Equation 8-7 for C 3 yields: R- S,i Qi (3,9) 3 (cpm)= ( cpm-cm ) (pCi) ( sec) pCi sec 3 ( cm B.8-5 ODCM Rev. 16 I
8.2 BASIS FOR THE PLANT VENT WIDE RANGE GAS MONITOR SETPOINTS (C:ntinusd) , As in the case before, for the liquid waste test tank monitor, the plant vent ! wide range gas monitor establishes the detector counting efficiency by use of a calibration source. Therefore, S, can be substituted for S,3 in Equation 8-9, where S, is the detector counting efficiency determined from the calibration procedure. Therefore, Equation 8-9 becomes: 8 i (8-10) 3 (cpm)= ( cpm-cm ) ( sec) (#Ci) pCi cm 3 see The total body dose rate due to noble gases is determined with Equation 3-3: 0,3- 0.85 . EL(R) . Q, DFB' (3-3) 3 mrem) , pCi-sec) ) yCi) mrem-m ) yr pCi-m3 sec pCi-yr I where: 6 tb - total body dose rate (arem/yr) 0.85 - (1.0E+06) x (8.5E 07) (pci-sec/pci-m 8) 1E+06 - number of pCi per pCi (pci/pci) l 8.5E-07 - [X/Q]1, maximum off-site average gamma atmospheric dispersion l 3 factor (sec/m ) for primary vent stack releases EL(R) - Release point correction factor - 1.0 for primary vent stack 4g - As defined above. DFB i = total body dose factor (see Table B.1-10) (arem-m8 /pci-yr) 3.8-6 ODCM Rev. 16
. - - . - . . - - . - . . _ - . _ . ~ . . _. . -- _. - - -_ _ . _ _ > l J l l
8.2 BASIS FOR THE PIANT VENT WIDE RANGE CAS MONITOR SETPOINTS (Continuad)
- A composite total body gamma dose factor, DFB , may be defined such that
Q DFBe { 4, = { Q, DFB I (8-11) i i 3 3 j mree-m pCi) , pCi) { mrem-m ) ' pCi-yr see sec pCi-yr 1 4 Solving Equation 8-11 for DFB, yields: 4 l
; { Q, DFB,
' (5-7)
DFB, = bh i i Technical Specification 3.11.2.1.a limits the dose rate to the total body from i noble gases at any location at or beyond the site boundary to 500 mrem /yr. By setting 6 tb equal to 500 mrea/yr and substituting DFB, for DFB i l 4 l in Equation 3-3, one may solve for [ h, at the limiting whole body noble f gas dose rate: i l O V 1 [k i i= 588 DFB, (8-12) 3 i pCi ) , mrem-pCi-m) pCi-yr )
- sec yr-pCi-sec mrem-m 3
i Substituting this result for [ Q, in Equation 8-10 yields Ru>. the response i of the monitor at the limiting noble gas total body dose rate: 1 1 R. - 588 S s F DFB, (8-13) PCi-yr (cpm)=("#*"yr-pCi-sec ) (' pCi cm
) ( **"3 ) ( mrem-m )
3 e i U f 3 B.8-7 ODCM Rev. 16 a
8.2 BASIS FOR THE PIANT VENT WIDE RANGE GAS MONITOR SETPOINTS (czntinuad) The skin dose rate due to noble gases is determined with Equation 3-4: 6,,,,= EL(R) . [ Q, DF', (3-4) I mrem) , ) (8C1) mrem-sec gCi-yr
)
yr sec where: EL(R) - 1.0 for primary vent stack release (dimensionless) skin
- Skin dose rate (mrem /yr) hg - As defined above.
DF'i - combined skin dose factor (see Table B.1-10) (arem-sec/pci-yr) A composite combined skin dose factor, DF',, may be defined such that: DF ', [Qi i
=
Ei Q, DF'i (8-14) mrem-sec) gCi) , pCi) mrem-sec ) gCi-yr sec sec pCi-yr 1 Solving Equation 8-14 for DF', yields: E Q, DF'i DF ', = (5-8) bk i t B.8-8 ODCM Rev. 16 O
8.2 BASIS FOR THE PIANT VENT VIDE RANGE GAS MONITOR SETPOINTS (Continu2d) Technical Specification 3.11.2.1.a limits the dose rate to the skin from noble s gases at any location at or beyond the site boundary to 3,000 arem/yr. By setting D,gg, equal to 3,000 aren/yr and substituting DF' for DF~t in Equation 3-4 one may solve for [ Qi at the limiting skin noble gas dose rate: I i I [ D =i 3,000 i DF ,* (8 15) (pCl) arem) #Ci-yr ) i sec yr prem-sec i Substituting this result for [ kg in Equation 8-10 yields Rato, the t response of the monitor at the limiting noble gas skin dose rate: I 1 1 R*ki" = 3,000 S' F DF', (cpm) ("I'") (cpe d ) (sec) { yWyr ) yr pCi cm 3 mrem-sec (8-16) As with the liquid monitoring system, the gaseous monitoring system is also designed to incorporate the detector efficiency, S., into its software. The monitor also converts the response output to a release rate (pci/sec) by using a real time stack flow rate measurement input. Therefore, multiplyin5 by the stack flow rate l measurement (F), the Equations 8-13 and 8-16 become: 1 R3= 588 (5-5) DFB, 3 ( pC1 ) ^- (aree-pCi-m ) ( pCi-yr ) sec yr-pCi-sec mrem-e 3 1 R, gin = 3000 (5-6) DF ,, ( pCi) = ( mrem) ( #Ci-yr ) sec yr mrem-sec B.8-9 ODCM Rev. 16
- n. ._
8.3 BASIS FOR PCCW HEAD TANK RATE-OF-CHANGE ALARM SETPOINT The FCCW head tank rate-of-change alarm will work in conjunction with the PCCW radiation monitor to alert the operator in the Main Control Room of a leak to the Service Water System from the PCCW System. For the rate-of-change alarm, a setpoint based on detection of an activity level of 10-'pci/cc in the discharge of the Service Water System has been selected. This activity level was chosen because it is the minimum detectable level of a service water monitor if such a monitor were installed. The use of rate-of-change alarm with information obtained from the liquid sampling and analysis commitments described in Table A.3-1 of Part A ensure that potential releases from the Service Water System are known. Sampling and cnalysis requirements for the Service Water System extend over various operating ranges with increased sampling and analysis at times when leakage from the FCCW to the service water is occurring and/or the activity level in the FCCW is high. O B.8-10 ODCM Rev. 16 O
i l l l 8.4 BASIS FDR WASTE CAS PROCESSING SYSTEM MONITORS (RM-6504 AND RM-6503) The maximum allowable setpoint for the waste gas system monitors (response in 1 uCi/cm3 ) can be determined by equating the limiting off-site noble gas dose rate I from the plant vent to the total body or skin dose rate limits of Technical specification 3.11.2.1.a, assuming that all the activity detected by the vent wide-range gas monitors is due to waste gas system discharges. By evaluating the noble gas radionuclide with the most limitin5 dose factor as given on Table B.1-10, a conservative activity release rate from the plant vent for both whole body and skin dose rate conditions can be calculated. From Tai:n B.1-10, ' Kr-89 is seen to be the most restrictive noble gas if it were present in he effluent discharge. Applying plant vent seepoint equttion 5-5 for the whole body, and equation 5-6 for the skin, the maximum allowable stack release rate can be calculated as follows: Ru, - 588 1/DFB, (5-5) where: Ru> Pl ant vent maximum release rate (uci/sec) based on the whole body does rate limit of 500 mrem /yr DFB, - 1.66E-02 (arem-m 3
/pci-yr), whole body dose factor for Kr-89
( 588 - conversion factor (arem-uCi m 3 /yr-pCi-sec) Therefore: ; Rtb - 588 1/1.66E 02 l
- 35,421 uCi/see maximum release rate at plant vent Next, the skin dose rate limit is evaluated from equation 5-6 in a similar fashion
)
as follows: Rea, .- 3000 1/DF', (5-6) 1 where: l Rea, - plant vent maximum release rate (uCi/sec) based on skin dose i rate limit of 3000 mrem /yr. I DF', - 2.45E-02 mrem-sec/uci-yr skin dose factor for Kr*89 1 /"') 3000 - Site boundary skin dose rate limit (mrem /yr) 's_ / B.8-11 ODCM Rev. 16 1 l
l l l 8.4 BASIS FOR WASTE GAS PROCESSING SYSTEM MONITORS (RM-6504 AND RM 6503) (C:ntinued) l therefore: Raa - 3000(arep/yr) 1/2.45E-02(arem-sec/uci-yr)
- 122,449 uCi/sec from the plant vent !
comparing the release rate limit for the whole body to that for the sk.in (i.e. , 35,421 uCi/see vs 122,449 uCi/see, respectively) it is determined that the release rate for the whole body is limiting. Next, to get the maximum plant vent release rate from the waste gas system discharge, equate the plant vent nutximum releasa rate limit for the whole body equal to the vaste gas system activity concentration times its flow rate to the plant vent, i.e.: I
] Ra - 35,421(uci/sec) -
R,,,(uci/cm3 ) F,,,(cm8 /sec) or solving for R,,,: R,,,(uci/cm8 ) - 35,421(uci/sec) / F ,,(cm3/s ec) where: O! R,,, - maxinram concentration (setpoint limit) at the waste gas system monitors F,,, - wast.e gas design flow of 566.4 cm8 /sec (1.2 cfm) ) therefore: 1 R,,,(uCi/cm )8 - 35,421(uci/sec) / 566.4(cm 3/sec) 62.5 uCi/cm 8 This represents the maximum vaste gas discharge concentration which would equal the site boundary whole body dose rate limit for plant veut releases. Administrative controls may set alert alarm and high alarm (vaste gas isolation) setpoints on the waste gas monitors as some multiple of expected activity concentration, such as 1.5 and 2 times, respectively, as long, as the maximum setpoint does not exceed 62.5 uC1/cm 8
. This provides operational controls to be exercised before any waste gas discharges could equate to the Technical )
Specification limits of 3.11.2.1.a. ODCM Rev. 16 O E.8-12 ;
8.4 BASIS FOR WASTE GAS PROCESSING SYSTEM MONITORS (RM-6504 AND RM-6503)
; (Continued) '
J _ \d Q The primary process moniter noted in Technical Specification 3.3.3.10 is RM-6504, which is downstream of the waste gas discharge compressor at the end of the i process system. Monitor RM-6503 is on the inlet side of the compressor downstream ) of the charcoal delay beds, and is considered as an alternate monitor if RM 6504 is inoperable. For the purpose of setting the maximum discharge setpoint. RM 6503 is j treated the same as RM-6504, which assumes no additional source reduction before j discharge to the plant vent. 4 i I i l i l !O j
$ l l
J
' .I '
f ( t,_ B.8-13 ODCM Rev. 16
l 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) The maximum allowable setpoint for the main condenser air evacuation monitor must be evaluated for two modes of operation. For normal operations the monitor is responding to a low flow rate that is released through the plant vent stack. During start-up (hogging mode), the monitor response must be related to a high flow rate thac is being released from the turbine building which is considered a ground level release. In both instances, the setpoint can be determined by equating the limiting off-site noble gas dose rate from the release point to the total body or skin dose rates of Technical Specification 3.11.2.1.a. In a manner similar to that for the waste gas monitoring system in $8.4 the most restrictive radionuclide in Table B.1-10, Kr-89, can be used to calculate a conservative activity release rate condition for both total body and skin dose rates. More realistic or actual radionuclide distributions in condenser air can be used to calculate the maximum allowable alarm setpoint. In addition to monitoring the main condenser air, the air evacuation monitor response is also used as an indicator for Turbine Cland Seal Condenser exhaust. Since this is a potential release pathway during both the normal and the hogging modes of operation, the impact is considered in the setpoint calculations. l 8.5.1 Exa2nole for the Air Evacuation Monitor Servoint Durine Normal Operations l During normal power operation the maximum allowable setpoint for the air evacuation j monitor is detertained by applying plant vent setpoint equation 8-13 for the total I body, and equation 8-16 for the skin. Therefore, the maximum allowable stack release rate can be calculated as follows: l Re - (588) (S ) (1/F) (1/DFB,) (8-13) l l (cpm) - (mrem-pCi m*/yr-pCi-sec) (cpm-cm8 /pC1) (sec/cm3 )(pci-yr/ mrem-m3 ) l l l where: Ra - count rate (cpm) for the plant vent maximum release rate based on the total body dose rate limit of 500 mrem /yr , 1 588 - conversion factor (mrem-pCi-m /yr-pCi-sec) 3
$, - the detector response efficiency (cpm cm8 /pCi) as determined from monitor calibration. For the air evacuation monitor, a typical value is 6.0E+05 cpm cm3 / Ci.
F - release flow rate. During normal operations, a typical flow value is 4.72E+03 cc/sec (10 cfm) for the air evacuation pathway. DFB, - the composite total body dose factor, For Kr-89 alone, the value is 1.66E-02 (arem m 8
/pCi-yr) . For different gas mixes, the composite can be found from:
l DFB, - [kg DFB; / { 6, (5-7) i i B.8-14 ODCM Rev. 16
l 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) l 8.5.1 Example for the Air Evacuation Monitor Setooint Durine Normal Ooerations
/' % (Continued)
- l Therefore, l Ro, - 588 6.0E+05 (1/4.72E+03) (1/1.66E-02) I - 4.50E+06 cpm detector count rate for a maximum release rate at the plant vent based on the total body dose rate. Next, the off-site skin dose rate limit is evaluated from equation 8-16 in a similar i fashion as follows: l R,gi, - 3000 S (1/F) (1/DF'.) (8-16) i j l (cpa) - (area /yr) (cpa-cm3 /pCi) (sec/cm3 ) (pci-yr/arem-sec) 4 l where: R,gt, - count rate (cpm) for a plant vent maximum release rate based on the j skin dose rate limit of 300 area /yr DF', - the olevated release . skin dose factor for Kr-89 of 2.45E-02 (arem- l sec/pci-yr). ' l l Therefore, O R,gt, - 2000 6.0E+05 (1/4.72E+03) (1/2.45E-02)
- 1.56E+07 cpm detector count rate for a maximum release rate at the plant vent based on the skin dose rate. l l
Comparing the release rate limit for the total body to that of the skin (i.e. , l 4.50E+06 cpm versus 1.56E+07 cpa, respectively) it is determined that the release i rate for the total body is limiting in this case. I Since during normal operations the Turbine Gland Seal Condenser exhaust has the potential to be a minor additional contribution to the plant vent release, the effective contribution from the main cuadenser exhaust must be limited to some fraction of the calculated value. The contribution from the Turbine Gland Seal Condenser exhaust is expected to be minor because this system handles only 670 lbs/ hour of steam which is a very small fraction of the 1.5E+07 lbs/ hour of 4 secondary side steam that the main condenser handles. Therefore, the maximum alarm is set at 3.2E+06 cym, which is 70% of the calculated value, to ensure that the contribution of the two does not exceed the dose rate limit of Technical Specifications 3.11.2.1.a. During normal operations, this would represent the maximum allowable count rate on the air evacuation monitor that would equate to the site boundary total body dose rate limit or less. i B.8-15 ODCM Rev. 16
8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) 8.5.2 Evannie for the Air Evacuation Monitor Setnoint During Start Up Worrine Mode) During start up (hogging mode), the determination of the air evacuation setpoint must take into account a larger air flow rate that is also released as a ground level ef'.luent. The flow rate must also include the contribution from the Turbine Clard Seal Condenser exhaust, which is a potential release pathway which the air evacuation monitor response must also take into account. For ground releases, the general equation 8-10 is used to represent the monitor count rate. l R - (S ) (1/F) [ 4, (8-10) t (cpm) - (cpm-cm 3
/pci) (sec/cm3 ) (pCi/sec) where:
R - detector count rate (cpa) S, - the detector efficiency (cpm-cm 3/pci) F - release flow rate (cm 3/sec) l l Di - the release rate of noble gas "i" in the mixture, for each noble gas listed in Table B.1-10. For a ground release, the off-site total body dose rate is based on: I l tb(s) = 3.4 [ (Q ei DFB ) g (3-3b) i A composite total body dose factor, DFB, can be defined such that: l DFB, [hg = [(kg DFB )g (8-11) i i B.8-16 ODCM Rev. 16 O
. -.. - ..~_-_ - . . . . . - - . . - -. . .. - . . . _ . . . .
. l j l l 8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) l 8.5.2 Fv==le for the Air Evacuation Monitor Setuoint Durine Start Up (Horrine Mode) O U (Continued) i j l By substituting 8-11 into 3-3b and rearranging to solve for [D i the following i ~ l equation is obtained: l [h i (b(tb(s) / 3.4) (1/DFB,) l 2 i 1 By inserting a limiting value of 500 mrea/yr as 8tb(s) this simplifies to: i i 1 l 4 l [Qi i
- 147 (1/DFB,)
l l Insertion of this equation into equation 8-10 yields: l R.t hts) I47 S(s) (1/F) (1/DFB,) l (cpm) - (arem pCi-m3 /yr-pCi-sec) (cpa-cm3 /pci) (sec/cm )3 (pCi-yr/ mrem-m3 ) i
- \ where
1 i Rac,3 - count rate (cpm) for the maximum ground release rate based on the i total body dose rate limit of 500 are/yr. l 147 - conversion factor (aren-pci-m 3/yr-pCi-sec) S, k- the detector response efficiency for the air evacuation monitor (a typical value of 6.0E+05 cpm-cm 3/pCf. is applied in this example). O B.8 17 ODCM Rev. 16 , l
8.5 BASIS FOR THE MAIN CONDENSEE AIR EVACUATION MONITOR SETPOINT (RM-6505) 8.5.2 Ex== ale for the Air Evacuation Monitor Setooint Durine Start Un (Horrine Mode) (Ct.ntinued) F - release flow rate. During the hogging mode of operation, a value of 5.57E+06 cm3 /sec (1.18E+04 cfm) is assumed. This value represents the sum of the 1.0E+04 cfm from the main condenser discharge and the 1.8E+03 cfm exhaust rate from the Turbine Gland Seal Condenser. Both discharges are to the Turbine Building roof. Lin e
- the total body dose factor from Table B.1-10. For Kr-89, this factor is 1.66E-02 (arem-m /pCi-yr) .
8 l Therefore R ag,3 - 147 6.0E+05 (1/5.57E+06) (1/1.66E-02)
- 9.54E+02 cpm detector count rate for a maximum ground release rate based on the total body dose rate.
Next, the off-site skin dose rate limit for a ground release is evaluated from equati>n 3-4b in a similar fashion as follows: l 6 stin<s) - { @, DF,c,3) (3-4b) 1 l A composite skin dose factor, DF',c,3 can be defined such that: l DF',c,3 [Qg - [(kg DF ic,3) (8-17) I i l By substituting 8-17 into 3-4b and rearranging to solve for [kg the t l following equation is obtained: I bhi 1
- b etings) (1/DF',g,3) l By inserting a limiting value of 3000 mrem /yr as ,ging,3 this simplifies to:
B.8-18 ODCM Rev. 16 O
8.5 BASIS FOR THE MAIN CONDENSER AIR EVACUATION MONITOR SETPOINT (RM-6505) 8.5.2 Fv-la for the Air Evacuation Monitor Setooint Durine Start Up (Horrine Mode) ] (Continued) l [hg - 3000' (1/DF',c,3) i l l l Insertion of this equation into equation 8-10 yields: l R*ki" - 3000 S. (1/F) (1/DF',c,3) l (cpm) - (aren/yr) (cpm cm8 /pci) (sec/ca )s (pCi-yr/arem-sec) i , l where: l i l l R, ming,3 - Count rate (cpm) for the maximum ground release rate based on , the skin dose rate limit of 3000 arem/yr. DF',g,3 - the ground release skin dose factor from Table 3.1-10. For
- Kr-89, this factor is 1.67E-01 (arem-sec/ /Ci-yr).
Therefore: O R,gt c,3 - 3000 6.0E+05 (1/5.57E+06) (1/1.67E-01) 1.94E+03 cpm detector count rate for a maximum ground release rate based on the skin dose rate. Comparing the release rate limit for the total body to that of the skin (i.e. , 9.54E+02 cpm versus 1.94E+03 cpa, respectively) it is determined that the release rate for the total body is limiting in this case. During start up (hogging mode), this represents as a 5round level release the maximum allowable count rate on the ; air evacuation monitor tha* would equate to the site boundary total body dose rate ! limit. Since during startup, the plant vent still constitutes a primary release pathway, the effective contribution from the hogging exhaust must be limited to some fraction of the calculated value to ensure that the combination of all gaseous releases from the station do not exceed the dose rate limits of Technical Specification'3.11.2.1.a. In this example, the maximum alarm point is set at 15% of the calculated value, or 1.4E+02 eps. l l l B.8-19 ODCM Rev. 16
4 4 REFERENCES A. Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases.of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", U.S. Nuclear Regulatory Commission, Revision 1, October 1977. B. Hamawi, J. N. , "AEOLUS A Computer Code for the Determination of Continuous 4 and Intermittent-Release Atmospheric Dispersion and Deposition of Nuclear Power Plant Effluents in Open-Terrain Sites, Coastal Sites, and Deep-R;,er Valleys for Assessment of Ensuing Doses and Finite-Cloud Gamma Radiation Exposures,* Entech Engineering, Inc., March 1988. 1 C. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Caseous Effluents in Routine Releases From Light-Water Cooled Reactors", U.S. Nuclear Regulatory Commission, March 1976. D. National Bureau of Standards, " Maximum Permissible Body Burdens and Maximum , Permissible Concentrations of Radionuclides in Air and in Water for - Occupational Exposure", Handbook 69, June 5, 1959. E. Slade, D. H., " Meteorology and Atomic Energy - 1968", USAEC, July 1968. j F. Seabrook Station Technical Specifications. i f i _ a 4 l R-1 ODCM Rev. 16
I 8 i i AFFENDIX A I I 1 i 1 i i 1 1 a i 1 4 J ,i .i
)
1 1 J a J 6 5 DOSE CONVERSION FACTORS 1 I l i ; 1 l A l 1 'l e
^*1 ODCM Rev. 16
I APPENDIX A j METHOD I DOSE CONVERSION FACTORS I
- 1. LIQUID PATHWAYS - SEABROOK SITE SPECIFIC DCF'S The models used to assess doses resulting from effluents into liquids is derived from Appendix A of Reg. Guide 1.109. Since Seabrook is a salt water site, the assumed pathways of exposure taken from Reg Guide 1.109 are Aquatic foods -
fish; Aquatic foods -invertebrates; and dose from shoreline deposits (direct dose). No drinking water or irrigation pathways exist because of the salt water environment. In addition, exposures resulting from boating and swimming activities have been included for key radionuclides even though Reg. Guide 1.109 identifies these pathways as not contributing any significant contribution to the total dose, and therefore does not provide dose equations for them. For completeness, the swimming and boating pathways have been included using the dose models from the HERMES code (HEDL-TME-71-168, Dec. 1971) section G, Water Immersion. The Method I dose conversion factors are derived by calculating the dose impact to individuals via the site specific pathways for a unit activity release (1 curie per nuclide). For each pathway, doses by radionuclide are calculated for each of the 7 organs (including whole body) for each of the four age groups (adult, teen, child, and infant). The Method I dose factor for each nuclide is then selected by taking the highest factor for any organ in any of the age groups for all the exposure pathways combined. The list of dose factors in the ODCM then represents a combination of different limitin5 organs and age groups which, when used to calculate a done impact from a mix of radionuclides released in liquid effluents, gives a conservative dose since it combines the exposure to different organs and age groups as if there was a single critical organ-age group. As an example of how the liquid dose conversion factors are developed, the following calculation for Co-60 is shown. The critical organ / age group is selected based on the full assessment of all organs and age groups. Factor for fish Ingestion: The 5eneral equation for ingestion doses in RG 1.109 is eq. A-3. 1119.7
- Qi *Bip *D.,,3 e e*'
The full assessment for the ODCM dose factors indicated that for 1 - Co-60, the maximum dose (arem/yr) is to the GI LLI of an adult as the target organ and age group., therefere: A-2 ODCM Rev. 16 O
U,, :- 21 kg/yt cdult useg2 fceter for fich l M, :- 0.1 mixing ratio for near field dilution provided by () submerged multiport diffuser. F := 918 cu. ft./sec effluent flow rate for circulating water system Qi :- 1.0 curies / year released of co-60 assumed B,3
- - 100 equilibrium bicaccumulation factor for CO-60 in salt water fish, in liters /kg D.i,3 :- 4.02
- 10-5 area /pci. adult GI-LLI ingestion dose factor from RG-1.109, table E-11.
A :- 1.501
- 10-8 decay constant for Co-60 in 1/ hrs.
t, :- 24 time between release and ingestion, in hrs. 1119.7 is the factor to convert from Ci/yr per ft3/see to pCi/ liter. Note that RG 1.109 uses 1100 as a rounded approximation. O Therefore the dose from fish to adult GI-LLI is (arem/yr): l 1119.7 * *
- Qi
- B,,
- D,,,; e e-**b = 0. 0103 i
Factor for invertebrate ingestion: Next, the dose from invertebrates to the adult GI-LLI is given by the same general equation but with the folicwing variables changed: O A-3 ODCM Rev. 16
1 l l U:, :- 5 kg/yr ur ga fcetar I B,3
- - 1000 1/kg bicaccumulation factor j
all other variables the same as above l ! therefore the dose from invertebrates is (arem/yr): I 1119.7
' . Q, B,, *D,ipj ee -**** - 0. 0 2 4 5 Factor for shoreline direct dose:
The general equation for direct dose from shoreline deposits is taken from equation A-7 in RG-1.109 as (arem/yr): U* M'* W 111970 . Q, +T +Dg e e '* *** B* ~* **
- It is assumed that all internal organ doses also receive exposure from direct external sources, therefore each organ dose due to ingestion must have an external component added. For the above equation, the site specific variables for an adult exposure to a 1 curie per year release of CO-60 are:
U,, :- 334 hrs / year usage factor used for assumed shoreline l activities at Seabrook. M, :- 0.1 mixing ratio for near field dilution provided by the submerged multiport diffuser and assume to be extended to the beach continuously. W :- 0.5 shorevidth factor for ocean sites, dimensionless A-4 ODCM Rev. 16 O
T :- 1.923*108 redictetivo hnif life in d:ya for CO 60 D,3,3 :- 1.70*10-8 dose factor for Co-60 due to deposits in O. sediments, units of (area /hr)/(pci/m2) t, :- 0.0 transit time to point of exposure, hrs t3 := 131400 period that sediment is assumed to be exposed to water contamination for long term buildup, set at 15 years for Method I DCF's Q3 :- 1.0 curies per year, Co-60 assumed 111970 conversion factor to convert (Ci/yr)/(ft3/sec) to pCi/ liter and account for the proportionality constant used in sediment model Therefore the dose to the whole body and each organ due to direct exposure to the shoreline (area /yr) is: 111970 + . Qi *T D,i,j e e'*"* * ,1 -e-*% =0.0573 o V Direct dose due to Swimming: The dose due to immersion in water (swimming) is taken from the HERMES computer code. The original ODCM calculation was based on some preliminary dilution assumptions which gave a near field prompt dilution factor for the multiport diffuser of 8. For single unit operation with both service water and circulating water flow (412,000 gpa), a value of 10 is more realistic. This surface area of the plume is restricted to a small area over the diffuser and does not touch the shoreline approx. 1 mile away. Since the over all impact from swimming is small when compared to the other exposure pathways, the original conservatism on dilution are kept here. O O A-5 ODCM Rev. 16
Tha doca from cvimming is giv:n by tha following equatien: 1.0 1012 , , Qi *DFi , (arem/yr) Where: U, :- 45 hrs /yr, usage factor for swimming for maximum age group (teen) from HERMES. F. :- 6.56*1011 liters /yr, estimated annual dilution effluent flow in multiport diffuser Qi :- 1.0 Curies /yr, assumed release rate of nuclide i. DFi , :- 4.6*10-8 mrem-liters per hrs-pci, dose factor for Co-60 for water immersion taken from HERMES. 1.0*1012 constant for pCi/Ci Therefore the swimming dose for a 1 curie release of Co-60 is (arem/yr): 1.0 10 12 eU+p + Qi eDFi ,- 3.155 10 4 O As can be seen, the contribution of the swimming dose is only about one 30000ths of the total of the RG 1.109 pathways, and can be ignored in the case of Co-60. Similarly, the boating dose as given in HERMES is taken as half of the swimming dose, (and corrected for change in usage assumptions). The resulting dose is found to be less than the swimming dose and can also therefore be discounted in this case. A-6 ODCM Rev. 16 O
, Totc1 liquid Pathw y deso: ,
, The sum of the above liquid pathway doses can now be added to give the total maximum individual dose to the critical organ (adult-GI-LLI) for Co-60. This gives: l 0.0103 + 0.0245 + 0.0573 - 0.0921 ares /yr i l Since the internal doses given by the RG-1.109 methods actually are 50 yr dose , commitments resulting from one year exposure to the quantity of activity ;
' assumed to be released into the water, and the direct dose represents the dose received for the period assumed to be exposed to the pathway, and the activity l l
l release was taken as a unit quantity (i.e. Q - 1 Ci), the above total liquid pathway dose can be stated as site specific committed dose fac*ar in arem/Ci l I released. For Method I in the ODCM, the critical organ dose fe :or is seen to be 0.0921 aren/Ci, as shown above. The value reported on Table B.1-11 (9.22 ' E-08 ares /pci) was generated by a computational routine which gives rise to l the round-off difference between it and the above example. The whole body ! site specific dose factor for the ODCM was calculated in the same way treating the whole body as a separate organ. A-7 ODCM Rev. 16 l
II. CASEOUS PATHWAYS - SEABROOK SITE SPECIFIC DCF'S The models used to assess doses resulting from gaseous effluents in the form of iodines, tritium, and particulates are derived from Appendix C of Reg. Guide 1.109. For Seabrook, it is assumed that at the off site location which exhibits minimum atmospheric dilution for plant releases the following exposure pathways exist: inhalation, ground plane, ingestion of goats milk, meat, stored vegetables, and leafy vegetables. The Method I dose and dose rate factors are derived by calculating the dose impact to all age group individuals via the site specific pathways for a unit activity release (1 curie per nuclide). For each pathway, doses by nuclide are calculated for each of 7 organs (including the whole body) for each of the 4 age groups. The Method I dose factor for each nuclide is then selected by taking the highest factor for any organ in any of the age groups for all exposure pathways combined. The list of dose factors in the ODCM then represents a combination of different limiting organs and age groups which, when used to calculate the dose impact from a mix of racionuclides released into the atmosphere, gives a conservative dose since it combines the exposure to different organs and age groups as if they were for all the came critical organ-age group. As an example of how the gaseous particulate dose factors are developed, the following calculation for Mn-54 is shown. The critical organ / age grcup for Mn-54 was selected based on a full assessment of all organ and age group combinations. For elevated releases from the plant vent stack to the maximum site boundary (max. dose point due to meteorology), the critical organ and age group for Mn-54 was I determined to be the CI-LLI for the adult. PART A: INHA1ATION DOSE CONTRIBUTION The general equations for inhalation doses in RG 1.109 are eq. C-3, and C-4 which together give: 3.17 10' R,* 5 + [ Q i*DFA,;, = Dj , 0 I Where for the case of Mn-54 releases, the variables above are defined as: 3.17*10' is the number of pCi/Ci divided by the number of second per year A-8 ODCM Rev. 16
.-. . - _ _ . .- .- , _ - _ . _ - - . -. .- -_- - =. _ . . . .
- R.
- - 8000 the broething rato for egs group e (cdults) in e-3
- /yr.
1 X
-. :- 7.5
- 10~7 the long term average depleted atmospheric 0 dispersion factor, in sec/m a 3, at the maximum exposure point off site (S.B.)
i Qi :- 1 the release rate of nuclide i to the atmosphere in ] Ci/yr DFA 33 :- 9.67*10-s the inhalation dose factor for nuclide 1 (Mn-54), organ j (GI-LLI), and age group a (adult) taken from RG 1.109, table E-7, in area /pci inhaled. l Therefore, the inhalation dose to the maximum potential off site individual is given : 4 as:
)
3.17 10'*R,
- 3 . eQ, *DFA,3, = 0.00184 mrem /yr per Ci '
Q l PART B: GROUND PLANE DIRECT DOSE CONTRIBUTION The general equations for ground plane external direct dose in RG 1.109 are equations C-1 and C-2 which together give the dose DG as: 8760 1.0 10'2.S,e * [ Q, e eDFG ij 0 I Al ' Where for the case of Mn-54 releases, the variables in the above equation are ! defined as: l I l l O A-9 ODCM Rev. 16
1.0*1012 io tha nuabar cf pCi p:r ci Sr :- 0.7 the shielding factor provided by residential structures (dimensionless) for use in calculation accumulated doses over time. Note that for determination of dose rate factors (i.e. instantaneous dose rates) the shielding factor is set equal to 1.0, or in affect no credit for dose reduction is taken for determination of dose rates at points in time. D
- :- 1. 5*10-e the long term average relative deposition factor at l
0 the maximum site boundary location, in 1/m^2 l Ai :- 0.8105 is the radiological decay constant for Mn-54 (nuclide i in this case) in 1/yr. t, :- 15 is the time in years over which accumulation is evaluated (approx. midpoint of plant operating life) DFGy :- 5.80*10-8 external dose factor to the whole body, or any internal organ j, for standing on contaminated ground from Mn-54 (RG 1.109 l Table E-6) in mrem /hr per pCi/m-2 Qi :- 1.0 is the unit release quantity assumed for each nuclide i, in Ci/yr. 8760 is the number of hours in a year Therefore, the contribution to the total dose made by exposure to the ground plane at the maximum off site exposure location for Mn 54 is given as: 8760 1.0 1012 .S, . .Qi + *DFGy = 0.658 mrem per yr per ci
- 0. A1 l
A-10 ODCM Rev. 16 O
PART C: INCESTION DOSE CONTRIBUTION: As an initial step to determining the dose contribution from ingestion of milk, meat, stored vegetables, and leafy vegetables, we must first calculate the radionuclide concentration in forage, produce, and leafy vegetables resulting from j atmospheric tranfers of the activity to the surface of the vegetation and onto the l soil for root uptake. For all radioiodines and particulate nuclides (except tritium , and C-14), the concentration of nuclide i in and on the vegetation at a point of interest can be calculated using R.C.1.109 equations C-5 and C-6, which combined gives: i T i 1 1.14 10s , "_D ~, Q, e r+ 1 -e * "- + B,
- 1 -e ~h ** * .e -z .c a j _Q ,
Y,
- Ag P
- A, s
) PART C.1: Concentration in Produce (stored veretablesl i For the case of Mn 54 released in air emissions to the maximum site boundary, the (]/
/
concentration of Mn in produce grown in the hypothetical garden at that location can j be calculated from the above equation where the variables are defined as: i
. 1 1 1.14*10e is the number of pCi per Ci divided by the number of '
hours in a year (8760). i i l E=1.510 4 is the relative deposition factor, in 1/m2, at the I O maximum exposure point off site (S. B.) l Qi := 1 the release rate of nuclide i to the atmosphere in Ci/yr r :- 0.2 fraction of deposited activity retained on crops, leafy vegetables, or pasture grass (1.0 for iodines) A-11 ODCM Rev. 16
Agi :- 0.00219 sffcetiva rcmoval rcta esnaccnt for Mn-54 frca crcpc due to decay and weathering, in hr-1 j t3 :- 131400 soil exposure time to deposition, in (equal to 15 yrs, or mid plant life) ) i Y, :- 2.0 agricultural productivity (yield) for produce, in l kg/m-2 B, 3 :- 2.9*10-2 concentration factor for uptake of Mn-54 from soil by edible parts of crops in pCi/kg (wet weight) per pCi/kg dry soil Ai :- 9.252*10-5 radioactive decay constant for Mn-54, in hrs-1 P := 240 effective surface density of soil, in kg/m2 tg := 1440 crop holdup time after harvest and before ingestion, in hrs t, := 1440 crop exposure time to plume, in hrs Therefore, the concentration of Mn-54 in stored vegetables produced at the location of maximum deposition for a unit activity release is given as: p 11-a, .t* -
- z .t '
1.14 10s , , g, , p, +B,e i . e -A *** - 67.379 pCi/kg _Q . Y*A v ri P+A i PART C.2: Leafy Veretable Concentration For leafy vegetables, the above equation is repeated with the value for t.h, crop holdup time after harvest is chan5ed from 1440 hrs to 24 hrs, i.e.: A-12 ODCM Rev. 16
tg :- 24 crep holdup time efter htrvast, in hrs. Therefore the concentration of Mn.54 in leafy vegetables at the maximum deposition point due to a unit activity release is given as: 11-a, et* I * -4 .t* 1.14+10s , ! - , g, , p, + B,, *e -6 *** - 76.811 pci/kg Q Y, + A,, P + A, PART C.3.a: 6Dimal Feed concentration (nasture): C, Next, we can repeat the above calculation to determine the concentration of Mn-54 in pasture grass used as animal feed. This will allow for the determination of dose , contribution from milk and meat. Fcr pasture grass, all the above variables remain the same except for: 1
> :- 0.70 for agricultural productivity of pasture grasses, p kg/m2 G
l t, :- 720 for grass exposure time to plume, hrs l th :- 0.0 for holdup time after harvest Using these variables in the above equation gives the concentration in pasture grass as: 1 1.14 10s , ~p ' , g, , n . I M "" +B,, I* *e-A *** - 179.227 pci/kg Q YA y gi P*A
.. , i_
I A-13 ODCM Rev. 16
PART C.3.b: Animal Feed Concentration (stored feed): C, For stored feed that would be given to goats, or meat animals, the average concentration would be calculated by changing the following variables in the above calculation to: Y, :- 2.0 agricultural productivity for stored feed t, :- 1440 feed crop exposure time to plume in hrs th :- 2160 feed crop holdup time after harvest, hrs l Putting these values back into the above equation gives the concentration in stored animal feed (goat and meat animal) of Mn-54 for a unit activity release to the maximum exposure point. 1 1.14 10s , p r
- I * -2, ,e*
- 4 .t * +e -A *** - 63.037 pCi/kg Q.i + B,, e
_ Q. Y,
- As, P + A, l
PART C.3.c.: Concentration in Goat's Milk: C, . The Mn-54 concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentration in milk is estimated from RG 1.109 general equation C-10 as: F,*C, Q,ee-A "' - cone, in milk, pCi/ liter A-14 ODCM Rev. 16
s wharo ths varicbica era definsd cc:
- 2. 5*10-' average fraction of animal's daily intake of Mn-54
-b) g F. :-
which appears in each liter of milk, in days / liter Q, :- 6.0 amount of feed consumed by a goat per day, in kg/ day (50 kE /d for seat) tg :- 2.0 average transport time of activity from feed into milk and to receptor, in days. Ai := 2.22*10-8 decay constant of Kn-54, in days-1 i In addition, the C, term for the concentration of a nuclide in the animal's feed is given from RG 1.109 general equation C-11 as: C, - f, e f, *C, + (1 -f,] *C, + f, * [1 -f,] *C, where the following equals: f, :- 0.5 fraction of the year that animals graze on pasture
- f. :- 1.0 fraction of daily feed that is pasture grass when the animal grazes on pasture C,
- =' 179.227 concentration of Mn.54 in pasture grass as calculated from above, pCi/kg i
C, :- 63.037 concentration of Mn-54 in stored feed as calculated from above, in pCi/kg Therefore, the concentration in the total animal's feed is estimated to be: A-15 ODCM Rev. 16 1
l f, of, eC, + (1-f,] eC, + f, e [1-f,] eC, - 121.132 pCi/kg When this value of 121.132 is put back into the above general equation for nuclide l concentration in milk, we get: [ C, :- 121.132 pci/kg ) l cnd F, C, Q,ee4 "' = 0.181 pci/ liter of Mn-54 in goats milk PART C.3.d.: concentration in Meat: Cr Similar to milk, the concentration of the nuclide in animal meat is calculated. RG 1.109 general equation C-12 is given as: C,- F, C, Q,ee 4 "* !!ere the variables are set as: Fr :- 8 . 0*10-* fraction of animals daily intake of Mn-54 which appears in each kg of flesh, in days /kg Qr :- 50.0 animal's daily feed intake, in kg/ day t, :- 20.0 average time from slaughter to consumption, in days C, :- 121.132 concentration on Kn-54 in animal's feed, same as calculated above for goat, in pci/kg Therefore, the concentration of Mn-54 in animal meat is calculated to be: A-16 ODCM Rev. 16 O
__ _ _ - . . _ _ _ _ _ _ . _ _ . _ _ _ ~. . _ . . ._ _ _ _ . i i F, +C y .Q, ee4 "* - 4.635 pCi/kg in meat for Mn-54 O 1 PART D: DOSE FROM INGESTION OF FOODS PRODUCED AT MAXIMUM IhCATION Now that we have calculated the concentration of Mn-54 in milk, meat, leafy vegetables, and stored vegetables produced at a location of maximum air deposition, the resulting dose to any organ j and age group a can be calculated from the following general equation C-15 taken from RG 1.109: I I [ DFl ,y * [ U ,y ef, et +y U,, *C, + U,, C, + U , e f,
- C ] t t i
for Mn-54 set equal to 1, we find that from the evaluation of all organs for all age groups for combination of all exposure pathways, the adults GI-LLI is the critical age group / organ. Therefore, the variables in the above dose equation can be defined as: DFIu. :- 1.40*10-S ingestion dose factor for adults /GI-LLI for Mn-54, in ares /pci ingested (RG 1.109, Table E-11) U,. :- 520.0 vegetable ingestion rates for adults, kg/yr f, := 0.76 fraction of stored vegetables grown in the garden ft := 1.0 fraction of leafy vegetables grown in the garden U, :- 310.0 milk ingestion rate for adults, liter /yr i I i O . A-17 ODCM Rev. 16 l l
1 Ura :- 110.0 ment ingsstien rota for cdults, kg/yr i U. t :- 64.0 leafy vegetable ingestion rate for adults, kg/yr Cy :- 67.379 concentration of Mn-54 in stored vegetables, in pCi/kg (from above) C, :- 0.181 concentration of Mn-54 in milk, in pCi/ liter (from above) Ce :- 4.635 concentration of Mn-54 in meat, in pCi/kg (from above) Cn :- 76.811 concentration of Mn-54 in leafy vegetables, in pCi/kg (from above) The dose from the combination of ingestion pathways for this example is calculated by substituting the above listed variables back into the ingestion does equation: O DFI,*[U,,ef,eC g + U,, y
- C, + V,,
- C, + U , te f, *C ] = 0. 4495 t
mrem-/yr per Ci By breaking the above dose equation down into the different pathways which combine to give the total ingestion dose, we can see the individual dose contribution made by each exposure pathway. Therefore, we have: Dose for ingestion DFIy *Uy.
- f,
- Cy - 0.373 of stored vegetables Dose for ingestion DFIy *U., *C, - 7. 8 5 5 *10
of goat's milk l A-18 ODCM Rev. 16 O'
I l Daco for ingsstien DFIy, *Ure *Cr - 0.00714 ) of meat l Dose for ingestion DFIo,*U,. t *f t *C ,t - 0. 06 8 8 l of leafy vegetables i PART E: TOTAL DOSE FROM ALL EXPOSURE PATlWAY j The total dose from all exposure pathways assumed to be present at the maximum receptor location can be found by simply adding the individual pathway doses calculated above. Since all the calculations above assumed a unit activity release from the plant vent stack, the combined dose can be stated as dose factor per unit activity released. This then demonstrates the development of the Seabrook ODCM Method I dose factors for gaseous release of particulates from the vent stack.
/
I Inhalation dose (Part A) 0.00184 area /yr per Ci Ground plane dose (Part B) 0.658 area /yr per Ci I Ingestion dose total (Part D) 0.449 arem/yr per Ci Total dose all pathways 1.11 aren/yr per Ci (critical organ is GI.LLI of an adult for Mn-54) 1 1 O A-19 ODCM Rev. 16 i
3 i . i APPENDIX B 1 i. ?{ . i i 1 i j_ : i l i I l i i l i C014CENTRATIONS IN AIR AND VATER ABOVE NATURAL BACKGROUND l TAKEN FROM i i 10 CFR 20.1-20.602, APPENDIX B i f ! I
$) I 1
i 1 l i l i
'4 i
l i 1 I i 51 ODCM Rev. 16 ;
l l 1 1 APPENDIX B TO (( 20.1-20.6024NCENTRATIONS IN AUR AND WATER ABOVE NATURAL. BACKGROUND (See footnotes at and of Ag2penttu 01 isotope
- Tatne 4 Tatse 11 Em (stomse riumber) g , ,,,g Col. 2- g , _g, Col. 2-O'G4 mQ b* *O C mg i
Acuruum (09) Ac 227- S 2 x 10"' 6 x 10-* 8 x 10-" 2 x 10-* 8 3 x 10-" 9 x 10-8 9 x 10- ** 3 x 10-
- Ac 22f - .
- 8 x 10-8 3 x 10- 8 3 x 10-
- 9 x 10- 8 1 2x 10*
- 3 x 10-8 6 x 10- " 9 x 10-
- Amruum (95) Am 241 S 6 x 10- 58 1 x 10" 2 x to"* 4 x 10-8 1 1 x 10-" 8 x 10" e x 10* " 3 x 10-*
Am 242m S 6 x 10-" 1 x 10" 2 x 10- ** 4 x 10** I 3 x 10-" 3 x 10-8 9 x 10-" 9 x 10-* Am 242 S 4 x 10-* 4 x 10-s 4 x 10" 1 x 10" l 5 x 10*
- 4 x 10-8 2 x 10" 1 x 10" A;a243 S 6 x 10-'8 1 x 10-
- 2 x 10-" 4 x 10-*
1 1 x 10*" 0 x 10-* 4 x 10-'8 3 x 10*
- Am 244 S 4 x 10-* 1 x 10-8 1 x 10" 5 x 10-8 1 2x10-8 1x?T' 8x1C" 5 x 10" Atibmony _ Sb 122 S 2 x 10-' 6 x 10-* 6 x 10** 3 x 10*
- 1 1x10" 8 x 10" 5x10"* 3 x 10-8
$b 124 S 2 x 10-' 7x10" 5 x10*
- 7 x t1" l 2 x 10** 7 x 10-* 7x10-" t a, ta" Sb125 S 5x10-' 3 x 10-8 2x10" 1 x 10" l 3 x 10*
- 3 x 10-8 9 x 10* " 1 x 10" Argon (18) A 37- Sub' 6 x 10-8, 1 x to" ,
A 41 - _ Sub 2 x 10** 4 x 10-8 Arsenc (33) As 73 S 2x10" 1 x10-8 7 x to" 5 x10" 1 4 x 10" 1 x 10-8 1 x1G"* 5 x 10" AS 74 S 3 x 10-* 2 x10-8 1 x10" 5 x 10-* I t x10-' 2 x10-s 4 x 10" 5 x10-s
. l /4 76 S 1 x 10-' 6 x 10" 4 x 10" 2 x 10" i 1 x 10-' 6 x 10-* CX10" 2 x 10-*
As 77 S 5 x 10-' 2 x10*
- 2 x10-8 8 x 10-8 1 4 x 10" 2 x 10-8 1x10-8 8 x 10-8 Astatirte (65) At 211 S 7 x10** 5 x t,4fe 2 x10* " 2 x 10-*
1 3 x10** 7 x 10" 1 x10" 7 x 10*
- Barum (56) Ba 131 . S 1 x to-* f.x 10-8 4 x 10'-* 2 x 10" 1 4 x 10-' d x 10-8 1 x10" 2 x 10" 1 Ba140 S 1 x 10" 8 x 10" 4 x10" 3 x 10-8 1 4 x 10-8 7 x 10" 1 x 10** 2 x 10" Berkelium (97) Bk 249- S 9 x 10-" 2 x10-8 3 x 10-" 6 x 10-
- 1 1xF0" 2 x 10-' 4 x 10" 6 x 10" Bk 250 S 1 x 10" 6 x10-8 5 x 10" 2 x 10" 1 1 x 10-* 6 x 10-s 4 x 10*
- 2 x 10-
- 06tWum (4) Se 7 S 6 x10-* 5 x 10-' 2 x 10" 2 x 10" 1 1 x 10-* 5 x 10-8 4 x 10-* 2 x 10* a Bismuth (83) .- 8:206 S 2 x 10" 1x10" 6 x 10" 4 x to-
- I 1 x 10-' 1 x 10*
- 5 x 10" 4 x 10-*
8: 207 - . . . ..S 2 x 10" 2x108 6 x ?" 6 x 10*
- 1 1 x 10-* 2 x 10-s 5 x 10*
- 6 x 10" 8 2io.. S 6 x 10" 1 x 10" 2x10-" 4 x 10*
- O B-2 ODCM Rev. 16
Nuclxr R:gulottry Commiz23:n Pt. 20 [@@ 20.1-20.102], App. B APPENotX G TO gg 20.1-20.602-CONCENTRAtlONS IN AIR AND WATER AeovE NATURAL BACKGROUND--Continued (See footrees at end of Appenduc B) a i Isotope
- Tause 1 7able 11 '
Elemera (some number) Col. W Col. 2- Col 1. -h Col. 2-4 WCumi) [Cs)mo b.C./mq ya;w l 6 x 10" 1 x 10 *
- 2 x t0* d 4 x 10" l Bi 212 S 1 x 10" 1x10" 3 x 10" 4 x 10" '
1 2 x 10-' 1 x 10-' 7x10-' 4 x 10-* stomine (35) Br 82_ S 1 x 10-8 8 x 10" 4 x 10-' '3 x 10" ; I 2 x 10" 1 x 10*
- 6 x 10*' 4 x 10" Cadmnem (48) -
Cd 109 S 5 x 10" 5 x 10" 2 x 10-6 2 x 10" 1 7 x 10" 5 x to-* 3 x 10-' 2 x 10" Cd 115m S 4 x 10*
- 7x10" 1 x to" 3 x 10" 1 4 x 10" 7 x 10" 1 x 10-' 3 x 10*
- l Cd 115 - S 2 x 10- ' 1 x 10*
- 6 x 10
- 3 x 10" f s 2 x10" 1 x 10" 6 x 10" 4x10" '
f%rme (20) Ca 45 S 3x 104 3 x 10" 1x10" 9 x 10-8 8 1 x10" 5 x 10-s a x io
- 2 x 10" Ca 47 S 2x 10" 1 x 10* 8 6 x 10-
- 5 x 10" 1 2 x 10-' 1 x 10-s 6 x 10" 3 x 10" Caplomann (96)__ Q 249 S 2 x 10- 1 x t0-* 5 x 10-" 4 x to" I 1x10* 7x10" 3 x 10-" 2 x 10*
- O 250 S 5 x 10-" 4 x 10" 2x10"' 1 x 10" 1 1 x 10*" 7 x 10" . 3 x 10"' 3 x10" l 0 251 S 2x10-" 1 x 10" 6 x 10-" 4 x t o-*
- 1 1 x 10*
- 8 x 10" 3 x 10"' 3 x 10" 2 0 252 S 6 x 10* *' 2 x 10" 2 x 10"* 7x104
' 1 3 x10"a 2 x10" 1 x 10"' 7 x 10-*
0 253 S 8 x10-" 4 x 10" 3 x 10"' 1 x 10" i 8 x10-" 4 x10-s 3 x 10-" 1 x10" Q 254 S E x10-'8 4x10" 2 x10-u g xion f g Carten (6) C 14 I S 5 x 10-" 4 x 10" 4 x 10** 2 x10" 2x10"8 1 x 10-' 1 x10-' 8 x 10-* j N (CO ) See 5 x10" . 1 x 10*
- t Car 4sm (58) Ce 141 S 4x10" 3x10" 2 x 10" 9 x iO-* l l 2x10" 3 x 10" 5 x 10*' 9 x10" Ce 143 S 3x10"' l x 10-8 9x104 4 x 10" 1 2x10" 1 x 10** 7 x 10-' 4 x 10" Ce 144 S 1 x 10** 3 x 10" 3 x 10-
- 1 x16" 1 6 x 10-* 3 x 10" 2 x 10-" 1 x 10-8 i Ceanan (66) _
Cs 131 0 1 x10-8 7x to-8 4 x 10-' 2x 10-8 ; I 3 x10** 3 x10-8 1 x 10" 9 x10" Cs 134m . S 4s;;10 " 2 x10" 1 x 10-* 6x10-8 I 8x10** 3 x 10-8 2 x 10-' 1 x10" Cli 134 S 4 x 10-8 3 x10" 1 x 10-* 9 x 10*
- 1 1 x 10-8 1 x 10" 4 x10-" 4 x 10*
- Ca 135 6 5x10" 3 x 10-8 2 x 10" 1 x 10-*
I 9x10-8 7 x10" 3 x10" 2x10" Cs 138 S 4 x '40* ' 2 x 10-* 1 x 10-* 9 x10-8 1 2 x 10-' 2 x10-8 8 x 10-8 6 x 10-8 Co 137 $ ex10" 4 x 10" 2 x10" ' 2 x 10*
- T I 1 x10*
- 1 x 10* 8 6 x 10-" 4 x10-6 CNorirse(1F 0 38 -
S 4 x 10-' 2x to-8 1 x 10" 8 x 10**
!- 1 2 x 10-* 2 x10*8 8 x 10*
- 8 x10-5 0 34 S 3 x10-* 1 r.10" 9 x 10-* 4 x 10" 1 2 x10-' 1 x 10-8 7 x 10-' 4 x 10" Ovomasm (24) _ Cr 51__ _ S 1 x 10** 5 x 10-8 4 x 10-' 2x10" I 2x10" 5x10" 8 x 10-* 2 x 10-8 Cobalt (27) Co 57 S 3 x 10*
- 2 x 10" 1 x 10-8 5 x 10" I 2 x 10-' 1 x 10-8 6 x 10" 4 x to" Co $8m ,- < $ 2xt0" 8 x 10*
- 6 x 10-' 3 x 10-8 1 9 x ta-* 6 x 10-8 3 x 10-' 2 x 10-8 Co 68 S 8 x 10" 4 x *0-8 3 x 10" 1x10" 1 5 x 10*
- 3 x 10** 2 x 10*
- 9 x 10-*
Co 60 S 3 x 10-' 1 x 10" 1 x 10-8 5 x 10" l 1 9 x 10" 1 x 10*8 3 x 10-
- 3 x 10*
- Cooper (29) . . . . . . . Cu 64 S 2 x 10" 1 x 10-' 7x50" 3 x 10"
] Cunum (96) - . - . - ... . Cm 2*2 i
S 1 x 10-* 1x10"' e7x10" 4 x 10-* x 10" l4 x 10" 2 x 10" 2 x 50" B-3 ODCM Rev. 16
Pt. 20 [(( 20.1-20.602], App. B 10 CFR Ch.1 (1-1-93 Editirri) APPENDIX B TO {f 20.1-20.602--CONCENTRATIONS IN AIR AND WATER AeOvE NATURAL BACKGROUND-Continued (See tootnotes at end of Appenda 81 esotope
- Table i TatHe it Element (atomic number) Col 1-Ar Col. 2- g , _4,, Cot 2-b (pC i) W #I ( Ci f)
I 2 x 10-" 7 x 10" 6 x 10-" 2 x 10" Cm 243 S 6x10"' 1 x 10" 2 x 10- " 5 x 10" i 1 x 10-" 7 x 10" 3 x 10* " 2 x 10" Cm 244 S 9 x 10- u 2x10" 3 x 10-" 7 x 10*
- 1 1x10*" 8x10" 3 x 10"8 3 x 10-*
Cm 245 - S 5x10*" 1 x 10" 2 x 10-" 4 x 10" I 1 x 10 '* 8 x 10" 4 x 10-" 3 x 10" Cm 246 S 5 x 10* " 1 x 10*
- 2x10"* 4 x 10-8 1 1x10-" 8 x 10" 4 x 10-" 3 x 10" Cm 247 S 5 x 10-" 1 x 10" 2 x 10-" 4x10-*
1 1 x 10- " 6 x 10" 4 x 10* " 2 x 10" Cm 248 S 6 x 10* ** 1 x 10" 2 x 10*" 4 x 10-' i 1 x 10* " 4 x 10*
- 4 x 10-" 1 x 10-*
Cm 249 S 1 x 10-8 6 x 10" 4 x 10" 2 x 10" i 1 x 10" 6 x 10-8 4 x 10" 2 x 10- 8 Dysprueum (66)_ Dy 165 S 3 x to-* 1 x 10* 8 9 x 10" 4x10" 1 2 x 10-* 1 x 10-8 7 x 10" 4 x to" Dy 166 S 2 x 10-' 1 x 10" 8 x to" 4 x 10" I 2 x 10*' 1 x 10- 7 x 10" 4 x 10-8 Einstenum (99) Es 253 S 8 x t o-" 7xto" 3 x 10-" 2 x 10" l 6 x 10* " 7 x 10" 2 x 10* " 2 x 10-s Es 254m S 5 x 10-' 5x10" 2 x 10- " 2 x 10" 1 6 x10-' 5 x 10" 2 x 10-" 2 x 10" Es 254 S 2 x 10-" 4 x 10-* 6 x 10-u 1 x 10-* 1 1 x 10-" 4 x 10*
- 4 x 10* " 1 x 10" Es 255 S 5 x 10-" 8 x 10" 2 x 10-" 3 x 10- 8 :
I 4 x 10* " 8 x 10-* 1 x 10- " 3 x 10-e Erbium (68) Er169 $ 6 x10" 3 x10.s 2 x 10" 9 x 10-* I 4 x 10*' 3 x 10-8 1 x 10" 9 x 10*
- I Er 171 S 7x 10" 3 x 10-8 2 x10" 1 x to" 1 6x10" 3 x 10*
- 2 x10-e j x 30" Etropum (63) Eu 152 S 4 x t o-' 2 x10" 1 x 10-* 6 x 10" (T/2-9.2 ivs) _ I 3 x10" 2 x 10-8 1 x 10-8 6 x 10-8 Eu 152 S 1 x 10-8 2 x 10- 4 x 10-" 8 x 10- *
(T/2=13 yrs) 1 2 x 10-8 2 x 10-8 6 x 10-" 6 x 10-8 Eu 154 S 4x10" 6 x 10" 1 x 10-" 2 x 10" l 7 x 10*' 6 x 10-* 2 x 10-" 2 x 10*
- 1 Eu 155 S 9 x10-8 6 x 10-8 3 x 10-' 2x10" l l 7x10-8 6 x10- 3 x 10" 2x10" i Fermium (100) Fm 254 S 6 x10-8 4 x 10-* 2 x10" 1 x 10-*
I 7 X 10*
- 4 x 10*
- 2 x 10" 1 x 10*
- Fm 255 S 2 x 10*
- 1 x 10-8 6 x 10-" 3 x 10-8 1 1 x 10-8 1 x 10-8 4 x 10- " 3 x 10" l Fm 256 S 3 x 10-* 3 x10" 1 x 10-
- 9 x10" ;
I 2 x 10-' 3 x10-8 6 x 10- " 9x10" Fluonne (8) F 16 S 5 x10-* 2x10-8 2 x 10" 8 x 10-* I 3 x 10-* 1 x 10*
- 9 x10" 5 x 10" Gadoinum gaa? Gd 153 S 2 x 10*' 8 x 10-e 8 x 10" 2 x to-*
I 9 x 10*
- 6 x 10- 3 x 10-' 2 x 10" Gd 159 S 5 x 10-' 2x to-8 2 x to" 8 x 10-8 1 4 x10-? 2 x 10" 1 x 10" 8 x 10-*
Galbum (21) Ga 72 S 2 x 10" 1 x 10-e 8 x 10" 4 x 10-
- I 2 x.10-' 1 x 10- e 6 x 10" 4 x 10" Germanum (32) Ge 71 S 1 x 10" 5 x 10" 4 x 10" 2 x 10- 8 ;
I 6 x 10-* 5 x 10-8 2 x 10-' 2 x 10- 8 Go6d (79) Au 196 S 1 x to" 5 x to- 4 x 10" 2xto" 1 6 x 10-' 4 x 10- 8 2 x 10*
- 1 x 10-
- Au 198 S 3 x 10" 2 x 10" 1x10" 5xio" I 2 x 10-' 1 x 10- 8 8 x 10-
- 5 x 10*
- At.199. - S 1 x 10-* 5 x 10-8 4 x to" 2 x 10" 1 8 x 10-' 4 x 10-
- 3 x 10' 2 x 10" Matruum (72).- . . . . Mf181- S 4x10" 2 x 10- 8 1 x 10" 7x10" l 7 x 10" 2 x 10" 3 x 10" 7 x 10" Holmium (67) ... . . . . . Ho 166 - S 2 x to-* 9 x to" 7 x 10" 3 x 10 a B-4 ODCM Rev. 16
.~ - - . - . . . _ --- - - .. .- -
Nuclear Ret;ulatary C mmissian Pt. 20 [{) 20.1-20402], App. 8 APPENDIX 8 TO $$ 20.1-20.602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUNO-Contirtued ( (See footnotes at end of Appendai 81 Isotope
- Tatse i Table it Element (atome number) Cod.1-4 Col. 2- g i_g Col 2-
@@*0 (pd/m0 4Ci/m0 4[f,n l I l t 2 x 10-' 9xto" 6 x 10*' 3 x 10" '
I Hyarogen (1) H3 . _.. . ... S 5 x to" 1 x 10" 2 x 10" 3 x 10- 8 4 5 x 10*
- 1 x 10*
- 2 x 10* ' 3 x Jo*
- Sub 2 x 10-8 4 x 10"
$ndaum (49) in 113m S 8 x 10" 4 x 10-' 3 x to" 1 x to-8 1 7 x 10-* 4 x 10* 8 2 x 10* ' 1 x 10- 8 in 114m S 1 x 10-' 5 x 10" 4 x t o" 2 x 10" i 2 x 10-8 5 x 10" 7 x 10- " 2 x 10" in 115m - S 2 x 10** 1 x 10" 8 x 10*
- 4xto" i 2 x 10'* 1 x 10* 6 x 10*
- 4 x 10*
- In 115 S 2 x 10* ' 3 x 10.'a 9 x 10" 9 x 10*
- 1 3 x 10-* 3 x 10.s 1 x 10** 9 x 10" iodine (53) i125 S 5 x 10" 4 x 10" 8 x 10-" 2 x to-'
I 2 x 10-' 6 x 10-s 6 x 10*
- 2 x 10*
- 1126 S 8 x 10-' 5 x 10-* 9 x 10-" 3 x 10* '
I 3 x 10-' 3 x 10-s 1 x 10*
- 9 x 10*
- 1129 S 2 x 10*' 1 x 10*
- 2 x 10* " 6 x 10-'
I 7 x 10" 6 x 10-8 2 x 10" 2 x 10-* 1131 S 9 x 10-' 6 x 10*
- 1 x 10* " 3 x 10* '
i 3 x 10-' 2 x 10-8 1 x 10** 6 x 10*
- t132 S 2 x 10*' 2 x 10-s 3 x10** 8 x 10-*
I 9 x 10" 5 x 10" 3 x10" 2 x 10-* 1133 $ 3xto" 2 x 10" 4 x 10*
- 1 x 10" 1 2 x 10-' 1x10" 7 x 10" 4 x 10" 1134 S 5x10" 4 x 10-8 6 x 10" 2 x 10-*
1 3 x10** 2 x 10-8 1 x10" 6 x 10" 1135_ S 1 x 10-' 7 x10" 1 x 10" 4 x 10*
- i I 4 x 10-' 2 x10-s g xion 7xion j 2 x10" andium (77) ir 190 . S 1 x 10** 6 x 10-s 4 x 10*
- 1 4 x 10-' 5 x 10-s 1 x10" 2 x10" Ir 192 S 1 x10-' 1 x10-8 4 x 10" 4 x 10" l 3 x 10*
- 1 x10-s g x go- = 4xto-a ir 194 S 2x 10*' 1 x 10-8 8x10" 3 x 10*
- 1 2 x 10-' 9x10" 5 x 10" 3 x 10-8 tron (26) Fe 55 S 9 x 10-' 2 x10-8 3 x10" 8 x 10" i 1 x 10** 7 x 10* 8 3 x 10*
- 2 x 10-8 Fe 59, S 1 xio-' 2 x 10-8 5 x10" 6 x 10" i 5 x 10-8 2 x 10-8 2x10" 5 x 10-8 Kr%Aonm Kt$5m Sub 6 x 10-* 1 x 10-'
Kr 88 Sub 1 x 10-* 3 x10" Kr 87 Sub 1 x 10-* 2 x10*
- Kr SS Sub 1 x 10** 2x10" Lar8iemsm(57) La 140 S 2 x 10-' 7 x10" 5 x 10*
- 2 x 10*
- i 1 x10-' 7x10" 4 x10" 2 x10.s Lead (Se Pb 203 $ 3 x to-* 1 x 10-8 9 x to" 4 x 10" i 2 x10-8 1 x10-8 6x10" 4 x10"
,,, Pb 210 S 1 x 10-" 4 x 10-* 4 x 10"8 1 x 10-'
M i 2 x10*
- E x10-s e xgons 2 x10" Pb212 S 2 x10** 6 x10" 6 x 10* " 2 x 10**
I 2 x10-* Ex10" 7 x 10* " 2 x 10-* tamalhen (P4 Lu 177 - S 6 x 10-' 3 x 10-s. 2 x10" 1 x10" 8 5 x10*' 3 x 10" 2 x10" 1 x 10** Mengenese (35) Mn 52 S 2 x 10-' 1 x 10* 8 7 x 10" 3 x 10" 1 1x10-' 9 x 10-* 5 x 10-' 3 x 10" Mn 54 S 4 x 10-' 4 x 10-8 1 x 10-8 1 x to" l 4 x10-8 3 x 10-s 1 x 10" 1 x 10*
- Mn 56 S 8x10" 4 x 10-8 3 x 10-' 1xto" l 5 x 10*' 3 x 10-8 2 x 10-8 1 x to" Mercury (80) Hg 197m S 7 x 10*' 6 x 10*
- 3 x 10*
- 2xto" 1 8x10*' 5 x 10*
- 3 x 10*
- 2 x 10" Hg 197 S 1 x 10** 9 x 10-s 4 x 10" 3 x 10" I 3 x10-* 1 x 10-s 9 x 10" 5 x 10" Hg 203 S 7 x 10-' 5x10" 2 x 10" 2x10" O
l ' t 1 x 10-' 3 x 10-8 4 x 10-' 1 x 10-- B-5 ODCM Rev. 16
Pt. 20 [{ 20.1-20.602), App. B 10 CFR Ch. I (1-1-93 Edition) APPENOlX B TO $9 20.1-20.602--CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-Continued (See footnotes at end of Appenden B1 Isotope
- Table i Table n Element (stom*c numoer) g% Col. 2- g% Col. 2-(pCum0 9Ng 4Cs/m0 h*f[n Molybdenum (42). . . . Mo 99 S 7 x 10" 5 x 10- 8 3 x 10" 2 x 10" 1 2x10" 1 x 10" 7 x 10" 4 x 10" Neodymsum (60) Nd 144 S 8 x 10-" 2 x 10" 3 x 10"' 7 x to" 4 3 x 10* " 2 x 10" 1 x 10* " 8 x 10" Nd147- S 4 x 10" 2 x 10- s 1 x 10" 6 x 10" 8 2 x 10-' 2 x 10- 8 8 x 10" 6 x 10" Nd 149 S 2 x 10-8 8 x 10' 6 x 10*
- 3 x 10" I 1 x 10-* 8x10-8 5 x 10" 3 x 10" Neptumum (93) Np 237 S 4 x 10"' 9 x 10-8 1 x 10"8 3 x 10-
- 1 1 x 10"' 9 x to-* 4 x 10" 3 x 10" No 239 S 8 x 10" 4 x to- 8 3 x 10" 1 x 10" l 7 x 10*' 4 x 10- 8 2 x 10-' 1 x 10-
- Nschef (28) Ni59 S 5 x 10*' 6 x to-8 2 x 10" 2 x 10" l 8 x 10*' 6 x 10* 8 3 x 10*
- 2 x 10*
- Ni 63 S 8x10-8 8 x 10*
- 2 x 10*
- 3 x 10*
- 1 3 x 10-' 2 x 10-8 1 x 10*
- 7 x 10-
- te 65 S 9 x 10*' 4 x 10-8 3 x 10-' 1 x 10-
- I 5x10" 3 x to-8 2 x 10" 1 x 10" Neubsum (Colur9bsum) (41) Nb 93m S 1 x 10*' 1 x 10*' 4 x 10" 4 x 10" 1 2 x 10-' 1 x 10- 8 5 x 10-' 4 x 10-*
ND 95. S 5 x 10-' 3 x 10- 8 2 x10-* 1 x 10*
- 1 1 x 10" 3 x 10*
- 3 x 10" 1x10" Nb97 S 6 x 10** 3 x 10-8 2 x 10" 9 x 10" 1 5 x 10-* 3 x 10-8 2 x 10" 9x10" Osmium (78) Os 185 f 5 x 10-' 2 x 10-8 2 x to" 7 x to" i 5 x10" 2 x 10-s 2 x 10-' 7 x 10" Os 191m S 2 x 10-8 7 x 108 6 x 10" 3 x 10- 8 8 9 x 10** 7 x 10-8 3 x 10-' 2 x 10- 8 Os 191 S 1 x10" 5 x 10-8 4 x 10** 2 x 10" i I 4 x 10" 5 x 10-8 1 x 10" 2 x 10- 8 Os 193 S 4 x10-' 2 x 10" 1 x 10" 6 x 10" 1 3 x10-' 2x 10-8 9 x 10*' 5 x 10" Penedium (46) Pd 103 S 1 x 10-* 1 x 10" 5 x10" 3 x 10" l 7 x 10-' 8 x 10-8 3 x 10-e 3 x ton Pd 109 S 6 x 10-' 3 x 10-8 2 x 10*
- 9 x 10*
- I 4 x 10-' 2 x 10- 8 1 x 10*
- 7 x 10" Phosphorus (15) P 32 S 7 x 10-8 5 x10" 2 x 10" 2 x to-
- I 8 x 10-* 7x10" 3 x 10" 2 x 10-8 Platrusn (78) Pt 191 S 8 x 10-' 4 x 10-8 3 x10" 1 x 10" l 6 x 10*' 3 x10-8 2x10" 1x10" Pt 193m S T x10-* 3 x10" 2 x10" 1 x 10-8 1 5 x10-* 3 x 10-' 2 x 10-' 1 x 10* 8 Pt 193 S 1 x t o-* 3 x 10-8 4 x 10-8 9 x 10" 1 3 x 10-' 5 x10-8 1 x 10** 2 x 10-
- Pt 197m S 6 x 10** 3 x 10-8 2 x 10" 1 x 10- 8 1 5 x10** 3 x10" 2 x 10" 9 x 10" Pt197 S 8 x10-' 4 xio-8 3 x 10" 1 x 10" 1 6 x 10*' 3 x10-8 2 x 10-* 1 x 10-
- Pluunnan (94) Pu 238 S 2 x to-58 1x10" 7 x 10-" 5 x 10*
- I 3 x10* H 8 x 10" 1x10"8 3 x 10-8 Pu 239 S 2x10"8 1 x to-* 6 x 10"* 5 x 10*
- 1 4 x 10-" 8 x 10-* 1 x 10"8 3 x 10" Pu 240 S 2 x 10-'8 1 x 10" 6 x 10-" 5 x 10*
- I 4 x to-u 8 x 10" 1x10-" 3 x 10" Pu 241 S 9 x 10-" 7 x 10-a 3 x 10- ** 2 x 10" 1 4 x 10-8 4 x 10- 8 1 x 10-* 1 x 10" Pu 242. - S 2 x 10-'8 1 x to" 6 x to"* 5x10" 1 4 x 10-" 9 x 10" 1 x 10"' 3 x 10" Pu 243 S 2 x to" 1 x 10-8 6 x 10" 3xto" 1 2 x 10*
- 1 x 10-' 8 x 10*
- 3 x 10" Pu 244. S 2 x 10"' 1x10" 6 x 10- " 4 x 10" 1 3 x 10- " 3 x 10" 1 x 10"8 1 x 10" Po6onasm (64 Po 210.. S 5 x 10-" 2 x 10-
- 2xto "l 7 x 10" t 2 x 10- 8 x 10" 7 x 10"' I 3 x 10" B-6 ODCM Rev. 16
- - -_- , . . _ - _ _ . -~ - __ - - -,- - . - _ - - - _ -
Nuclear Regulatory Commission Pt. 20 [ff 20.1-20.602], App. 8 APPENOtX B TO $9 20.1-20.602---CONCENTRATIONS IN AIR AND WATER AsOVE NATURAL s BACKGROUNO--Continued (See footnotes at end of Appendes B) ' isotope ' Tab 6e 1 l Tause u Ematomic numW Cd t-4 Cd 2- g , _u Cd 2-(uC.M) g,Ci$) (uCe/my da;e Potassaum (19). . . . . . . . . . x 42 .. S 2 x 10 *
- 9 x 10 *
- 7 x 10 *
- 3 x 10' I 1 x 10* ' 6 x 10*
- 4x10** 2 u t0*
- Praseodymus (59)... Pr 142.. $ 2 x 10' 9 x 10" 7 x 10 *
- 3 x 10 *
- I 2 x 10' 9 x 10" 5k10** 3 x 10 *
- Pr 143. S 3 x 10" 1 x t0" 1 x to" 5 x 10" l 2 x 10' 1 u 10' 6 x 10*
- 5 x 10 *
- Promethium (61) . Pm 14 7... . . . . . . . . S 6 x 10" 6 x 10" 2 x 10" 2 x 10" i 1 x 10" 6 x 10 *
- 3 x 10* ' 2 x 10* *
- Pm 149 - S 3xt0" t u to" 1 x 10" 4 x 10" '
1 2 x 10" 1 x 10*
- 8 x 10 * ' 4 x 10" Protosetatwum (91) Pa 230 - S 2 x 10" 7 x 10' 6 x to"' 2 x 10" l 8 x 10*
- 7 x 10*
- 3x10"' 2 x 10*
- Pa 231-- S 1 x 10"' 3 x 10" 4 x 10"* 9 x 10" 1 1 x t0*
- 8 x 10*
- 4 x 10"' 2 x 10*
- l Pa 233 - S 6x10" 4 x 10" 2 x 10" 1 x 10" I
2 x 10" 3 x 10" 6 x 10" 1 x 10" Radium (88) -- Ra 223 $ 2 x 10" 2x10" 6 x 10"' 7 x 10' i 2 x 10"* 1 x 10" 8 x 10"' 4 x 10*
- Ra 224 S 5 x 10*
- 7 x 10" 2 x 10* " 2 x 10*
- I 7 x 10*
- 2 x 10*
- 2 x 10* " 5 x 10**
Ra 226 S 3 x 10*" 4 x 10" 3 x 10"' 3 x 10" 1 5 x t0* " 9 x 10" 2 x ' C "' 3 x 10" Ra 228 S 7 x 10*" 8 x 10" 2 x 10"' 3 x 10" l 4 x 10*" 7 x 10" 1 x t0"' 3 x 10" Redon (88) An 220 S 3 x 10" 1 x to" Rn 222 8 3 x to" 3 x 10" j R%ruum (75) . Pt 183 . S 3 x to" 2 x 10" 9 x 10" 6 x to" 1 2 x 10" 8 x 10" 5 x 10" 3 x 10" 4 Re 186 S 6 x 10" 3 x 10" 2 x 10" 9 x 10" I 2 x10" 1 x 10*
- 8 x 10" 5 x 10" Re 187 S 9 x 10*
- 7 x 10** 3 x 10" 3 x 10*
- I 5 x 10*' 4 x 10*' 2 x 10*
- 2 x 10*
- Re 188 S 4 x 10*' 2 x 10- 1 x 10*
- 6 x 10* *
. I 2 x 10-' 9 x 10*
- 6 x 10*' 3 x 10*
- Rhodasm (45! Rh 103m S 4 x 10** 4 x to" 3 x 10" 1 x 10" 1 6 x10" 3 x 10*
- 2 x 10*
- 1 x 10* '
Rh 105 S 8xto" 4 x 10" 3 x 10" *1 x to" 1 5x10" 3 x 10** 2 x 10" tx10" Rutmeum (37) Rti86 - S 3 x10" 2 x10-: i x 30-e 7 x 10" 4 7x10" 7 x 10" 2 x10" 2 x 10" Rti87 S 5 x 10-' 3 x 10-8 2 x 10*
- 1 x10" ;
I 7 x 10*
- 5 x 10" 2x10" 2 x10" )
Rulhennsm (44) Ru87 8 2 x10*
- 1 x 10* 8 8 x 10*
- 4 x 10" j 1 2 x10** 1 x 10-s 4 x10*
- 3 x 10** !
, Ru 103 S 5x10" 2 x 10*
- 2x 10" 8 x 10*
- C g,, I 8 x10" 2 x10-s 3 x 10*' 8 x 10* * ,
i Ru 105 S 7 x 10*' 3x10" 2 x 10*
- 1 x 10" j t*; I 5 x10" 3 x 10-8 2 x 10*
- 1 x 10" Ru 108 . S 8 x 10*
- 4 x 10*
- 3 x 10" 1x10**
I 8 x 10** 3 x 10" 2 x 10* " 1 x 10*
- 5reMum 188) Sm 147 S 7 x 10*" 2 x 10" 2 x 10"' 6 x 10" 1 3 x 10*" 2 x 10*
- 9 x 10* " 7 x 10*
- Sm 151 S 6 x 10*
- 1 x 10** 2 x 10-' 4 x 10" l i 1 x 10" 1 x 10" 5 x 10*
- 4 x 10" j Sm 153 S 1 se 0" 2 x 10" 2 x 10" 8 x 10" I 2 x 10*
- 1 x 10*
- 8 x 10*
- Scandium (21) Sc 46 - S <x10'}
' " " 1 x 10" M10-a 8 x 10" 8 x 10 *
- 4 x 10" 4 x 10*
- 1 2=
Sc 47 S 6 x 10 - J x 10*
- 2 x t0** 9 x 10*
- 1 5 x 10" 3 x 10" 2 x 10" 9 x 10" Sc 48 S 2 x 10* ' 8 x 10*
- 6 x 10*' 3 x 10*
- 1 1 x 10" 8 x t *J" 5 x t0" 3xt0" Seien.um 341 s. 75 _ . . . . . S 1 x 10- *
- x 5 0" 4 x 50"
- i i x io" 8 x iO" 4x10-* 3 xx io-3 10".
B7 ODCM Rev. 16
i l l Pt,20 ((( 20.1-20.602], App. B 10 CFR Ch.1 (1-1-93 Editi n) APPENOtX D TO $$ 20.1-20.602-CONCENTRATIONS 8N AIR AND WATER ABOVE NATURAL BACKGROUNO--Continued (See footnotes at end of Appens: 8) isotope ' Table 1 l Tacae si Element (atome number) Cot 1--A, M 2- Col 1 -An l " #~~ (eOW) ([ofmn baOW l[h S.6an (14) . . . Sa31 S 6 x 10" 3 x 10-' 2 x 13- ' 9 x 10' 1 1 x 10-* 6 x 10-' 3 x 10" 2 x 10" Sdver (47) - . . . A0105 5 6 x 10" 3xto" 2 x 10" 1 x 10" l 8 x 10-* 3 x 10 ' 3 x 10" l 1 x 10
- Ag 110m . ... S 2 x 10" 9 x 10" 7 x 10" l 3 x 10'
- 1 1x10-* 9 x 10-
- 3 x 10*
- 3 x 10-
- Ag 111 S 3 x 10" 1 x 10*
- i x 10" 4 x 10" i 2 x 10 ' 1x10-8 41 x 10 ' 4 x 10-
- Sodium (11) . . . . . . . Na 22 S 2 x 10" 1 x 10- 8 ' 6 x 10" 4 x 10-
- 1 i
8 9 x 10" 9 x 10" 3 x 10 " 3 x 11- 6 N4 24 - S 1 x 10
- 6 x 10 8 4 x 10 ' 2 x 10*
- I 1 x 10-' 8 x 10 *
- 5 x 10-* 3 x 10*
- Stronvum (38) .. Sr 85m . S 4 x 10*
- 2xto" 1 x 10
- 7 x 10" l 3 x 10-
- 2 x 10" 1 x 10" 7 x 10 8 Sr95 S 2 x 10" 3 x 10- 8 8 x 10" 1 x 10" 1 1 x 10-' 5 x 10" 4 x 10" 2 x 10" Se es. S 3x10* 3 x 10-
- 3 x 10-" 3 x 10**
I 4 x 10*
- 8 x 10-
- 1 x 10" 3 x 10-
- Sr90. S 1 x 10-' 1 x 10" 3 x 10 " 3x10" i 1 5 x 10" 1 x 10" 2 x 10-" 4 x 10" l Sr 91 S 4 x 10" 2 x 10" 2 x 10" 7 x 10- 8 l l 3 x 10" 1x10" 9 x 10" 5 < 10-8 l Sr 92 S 4x10" 2 x 10-8 2 x 10" 7 x 10" l 1 3 x 10*' 2 x 10" 1 x 10" 6 x 10" Suttur (16) S 35 S 3xto" 2 x 10" 9 x to" 6 x 10" 1 3 x 10-' 8 x 10- 8 9 x 10" 3 x 10-* '
Tantalum (73) Ta 182 S 4 x 10-8 1 x 10-s 1 x 10" 4 x 10" l 1 2 x 10" 1 x 10*
- 7 x 10
- 4 x 10" I Technetium (43) Tc 96m S 8 x 10" 4x10" 3 x to" 1 x 10" l l 3 x 10-8 3 x 10* ' 1 x 10** 1 x 10*'
Tc 96 S 6 x 10-' 3 x 10- s 2 x 10" 1 x 10" I 2 x 10" 1 x 10" 8 x 10" 5 x 10" Tc S7m- S 2 x 10" 1 x 10" 6x10" 4 x 10" I 2 x 10-' 5 x 10- 8 5 x 10*' 2 x 10-* Tc g7 S 1 x 10" 5 x 10-s .sx10" 2 x 10* 8 1 3 x 10*' 2 x 10-' 1 x 10" 8 x 10-* Tc 99m S 4 x 10" 2 x 10" 1 x 10-* 6 x 10- 8 1 1 x 10*
- 8 x 10-' 5 x 10-' 3 x 10-8 Tc 99 S 2 x 10" 1 x 10-s 7 x 10" 3 x 10'
- I 6 x 10*
- 5 x 10- 8 2 x 10-' 2 x 10-*
Teilunum (52) To 125m S 4 x 10" 5xti? 1 x 10" 2 x10" I l i 1 x 10*' 3 x 10-a 4 x 10" 1 x 10" To 127m $ 1 x to" 2 x to" 5 x 10" 6 x to" l 4x10" 2 x 10" 1 x 10" 5 x 10" To 127 S 2 x 10-* 8 x 10-8 6 x 10" 3 x t 0* * . I 9 x10" 5 x 10" 3 x 10" 2 x 10" l To 129m S 8 x 10" 1 x 10- s 3 xico 3xico l t 3 x10*
- 6 x 10*
- 1 x 10-' 2 x 10*
- To 129 S 5 x 10-8 2 x 10- 8 2 x 10-' 8 x 10*
- 1 4 x 10-e 2 x 10- 8 1 x 10-' 8 x 10**
To 131m. S 4 x 10" 2 x 10" 1 x 10" 6 x 10" 8 2 x 10" 1 x 10-a 6 x 10*
- 4 x 10*
- l Te 132 ? 2 x10" 9 x 10*
- 7 x 10" 3 x 10" i i 1 x 10" 6 x 10*
- 4 x 10" 2 x 10" l Tertnum (65) Tb 160 S 1x10" 1xto' 3 x 10-' 4 x 10" l 3 x 10-8 1 x 10*
- 1 x 10-' 4 x 10- *
.... Ti200 S 3 x 10" 1 x 10' 9 x 10" 4 x 10" Thallnam (81)
I 1 x 10-* 7 x 10 8 4 x 10" 2 x 10" TI201 S 2 x 10" 9 x 10" 7 x 10" 3 x 10" l 9 x 10-' 5 x 10* 8 3 x 10" 2 x 10' T1202 . S 8 x 10 ' 4 x 10*
- 3 x 10" 1 x 10-
- I 2 x 10" 2 x 10- 8 6x10" 7 x 10" T1204.. . . . - . . S 6 x 10" 3x10-' 2 x 10" t x 10
- i 3 x 80" 2x10-' 9 x 10-
- I 6 w 10" i
B-8 ODCM Rev, 16
r Nucteer Regulatory Commission Pt. 20 [9) 20.1-20 502], App. B p APPENOlX B TO (( 20.1-20.602-CONCENTRATIONS IN A1R AND WATER Aeo E NATURAL ( BACKGROUNOMf'1tif1U6d (See tootnotes at end of Appends 8) Isotope ' Tatue f 't . bie H Dement (stome number) C t 2- Cd 2-Cd 14 cg g,,,u 4 mi) N*9 ( ,
)
Thonum (90) Th 227-... .. S 3 x 10* " 5 x 10" 1 x 10'" 2 x 10
- I 2x1C-" 5 x 10" 6 x 10* " 2 x 10" Th 228- S 9 x 10* *s 2 x 10" 3 x 10"' 7 x 10*
- I 6 x 10* " 4 x 10" 2 x 10"' 1 x 10 *
- Th 230 S 2x t0*" 5x10" 8 x 10"* 2 x 10**
1 1 x 10* " 9 x 10" 3 x 10 * " 3 x 10*
- Th 231 - S 1 x 10** 7 x 10*
- 5 x 10*' 2 x 10* '
i 1 x 10** 7 x 10- 8 4 x 10*
- 2 x 10*
- Th 232 S 3 x 10*" 5 x 10" 1 x 10* " 2 x 10" 1 3 x 10* " 1 x 10*
- 1 x 10"' 4 x 10" Th natural S 6 x 10* " 6 x 10" 2 x 10"' 2 x 10" 1 6 x 10"" 6 x 10" 2 x 10* " 2 x 10" Th 234 . . . S 6 x 10" 5x10" 2 x 10" 2 x 10" l 3 x 10*
- 5 x 10*
- 1 x 10*
- 2 x 10*
- Thulum (89) Tm 170 S 4 x 10" 1 x 10" 1 x to" 5 x 10**
1 3 x 10*
- 1 x10 s ixio-. 5 x 10*
- Tm 171. S 1 x 10* ' 1 x 10*
- 4 x 10** 5 x 10*
- I 2 x 10*' 1 x 10*' 8 x 10" 5 x 10" T'wi (50) Sn 113 S 4 x 10** 2x10-a 1 x 10" 9 x 10" 8 5 x 10" 2 x 10*
- 2 x 10" 8 x 10*
- Sn 125 S 1 x 10** 5 x 10" 4 x 10" 2 x 10" l 8 x 10*
- 5 x10" 3 x 10*
- 2 x 10" Tungsten (WeeranQ (74) W 181 S 2 x 10** 1 x 10*' 8 x 10*
- 4x10" 1 1 x 10*' 1 x 10-a e x ion 3 x ion W 185 S 8 x 10*' 4 x10-s 3x10" 1 x 10" 1 1 x 10*' 3 x10-s 4 x 10" 1x10" W 187 S 4 x 10" 2x 10*a 2 x 10" 7x 10" 3 x10" 1 x 10" 6 x 10" 1 2 x 10*
- Uraruumamm U 230 S 3 x 10*" 1x10" 1 x t o"" 5 x 10" i 1 x 10*" 1x10" 4 x 10* " 5 x 10*
- Um S 1 x10*
- 8 x10" 3 x 10"' 3 x 10" l 3 x10*" 8 x10" 8 x 10"8 3 x 10*
- U 233 S 5 x 10*" 9x10" 2 x 10*" 3 x 10" 1 1 x 10*" 9x10" 4 x 10* " 3x10" U 234_ S* 6 x10*" 9 x10" 2 x 10* " 3 x10" 1 1 x 10*" 9x10" 4x10"' 3 x 10*
- U 235 S* 5 x 10*" 8 x10" 2 x 10*" 3 x10" 1 1 x 10*
- 8 x10" 4 x 10* " 3 x 10*
- U 236 S 6 x 10*" 1 x10*
- 2 x 10* " 3 x 10" 1 1 x 10*" 1 x10" 4 x 10* " 3 x 10".
I U 238 S* 7 x10*" 1 x10-s 3 x10"' 4 x 10" i 1 x10*
- 1x10-s 5 x 10"' 4 x 10*
- U 240 S 2 x10" 1 x 10** 8 x 10** 3 x10" 1 2 x 10-' 1 x10-s 6 x 10" 3 x10" 7 U. natural S* 1 x10*" 1 x10*8 5x10"8 3 x10" A,- i 1 x 10*" 1 x 10*
- 5 x 10* 3 x10**
Venmean & V 48 S 2 x 10" 9 x10** 6 x 10** 3 x 10" 4.* ~ l 6 x 10** 8 x 10** 2 x 10** 3 x 10" Xenon "a Xe 131m Sub 2 x 10** 4 x 10" Xe 133 Se 1x10** 3 x 10* ' Xe 133m Sub 1 x10" 3xto" . Xe 135 Se 4 x 10** 1 x 10*' Yttertmwn (70) Yb 175-- S 7 x 10" 3 x10" 2 x to" 1 x 10" l 6 x 10*' 3 x 10*
- 2 x 10" 1 x 10" Yttrium (38) Y 90 S 1 x 10*' 6 x 10" 4 x 10" 2 x 10*
- 1 1x10" 6 x 10" 3 x 10" 2 x 10" Y 91m. S 2 x 10** 1x10" 8x10" 3 x 10" 1 2 x 10*
- 1 x 10* ' 6 x 10" 3 x 10*
- Y 91.. S 4 x 10*
- 8 x 10*
- 1 x 10" 3 x 10" t 3 x 10*
- 8 x 10** 1 x 10*' 3 x 10*
- Y 92.. S 4 x 10* ' 2 x 10*
- 1 x 10*
- 6 x 10" O Y 93 ...
1 S i 3 x 10*' 2 x 10" 1 x iO" 2 x 10-8 8 x to" 8 x io" 1 x 10*' 6 x 10" 5x10" 6 x 10*
- 3 x 10" 300" B-9 ODCM Rev. 16
Pt. 20 [{@ 20.1-20.602L App. B 10 CFR Ch.1 (1-1-93 Editian) APPENOfX B TO {$ 20.1-20 602-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUNO-Continued (See footnotes at end of Apperidra 8) Isotope ' Tabie i Table 11 Elemens (atome numbed Col 1.-An Col 2- Co 1 -A, Col 2-4G/mt) [C. mi) 4 ""U WC. 4 Zme (30) ... . . . . . Zn 65. S 1x10" 3 x 10" 4 x 10" 1 x to-
- I 6 x 10- 8 5 x t0** 2 r 10 2 x 10' Zn 69m .. S 4x10" 2 x 10" 1 x 10" 7xto" 1 3 x 10* ' 2 x t0 1 x 10" 6 x 10-
- 2n 69. S 7 x 10*
- 5 x t0" 2 x 10" 2 x 10- 8 1 9 x 10*
- 5 x 10* 8 3 x 10* ' 2 x 10 '
2rcoruum (40).. . _ . . . . Zr 93.- 5 1 x 10" 2 x 10" d x 10" 8 x 10' l 3xt0" 2 x 10- 8 1 x 10" 8 x 10" 2r 95. S 1 x 10" 2 x t0" 4 x 10-' 6 x 10" 1 3 x 10-
- 2 x 10 s 1 x 10*
- 6 x 10" Zr 97 ... S 1 x 10" 5 x 10" 4 x 10" 2 x 10" l 9 x 10-8 5 x 10*
- 3 x 10-' 2 x 10*
- Any sogle ramonuchde not hsted above Sub 1 x 10" 3 x 10" with decay rnode other than alpha emssason or soontaneous fisson and with radcactrve half.iife less than 2 hours.
Any eengle radenuclide rot ksted above 3 x 10" 9 x 10" 1 x 10-" 3 x 10-
- with decay mode other than alpha etruseson or spontaneous hsson and with redwtrve half-life greater than 2 hours.
Any omgle radorwha not ksted 6 x 10"' 4 x 10" 2 x 10-" 3 x 10" above, which decays by alpha errus. aion or spontaneous sneen.
'Sobhie (Sh insokhle (1). '"Sub" means that values given are for submerson in a senusphencat in6nine doud of arbome matenal 'These redon concentrahons are appropriate for protectson from rados corremed with as shor14ved daughters Anemeevely, wie weius in Table I may be replaced by one-thrd (%) "wortang loveL" (A "wortung levef" e defmed as any comtunaton of short4rved radorw222 daughters, poloruum-218, lead-214, tus. nut >214 and poioruum-214, in one hter of an.
wWuh4 regard to the degree of equihbnunt that wsB result in the tdtsmate omsseen of t 3x108 MeV of alpha particle energy.) The Table 11 value may be rarw=d by one-thr1seth (%e) of a "wortdng levoL" The Irrut on redor>222 concentratorts e restricted areae may be based on an annual average.
'For nok26e matures of U-236 U-234 and U-235 in air chemcal tonicity may be the brrutng factor. If the percent by weight-ennchmtnt) of U-235 m lese than 5, the concentraten value for a 404 tour woricweek Tatse 4 as 0.2 truikgrams uratuurn per cienc rneter of er average. For any enrichment the product of the everage concentraten and trne of exposure durmg a 404 tour woricweek shaa tot exceed 8x10-s SA pO-hr/ml, where SA is sie specshe acervity of the uraruurn mhaled. The concenesten vetue for Table it as 0.007 rndhgrarns uraruum per cieic meter of er. The specific actmey for natural uratuum is 6.77x10" cunes per gram U. The speedc actmty for other mertures of U-238, LM35 and U-234, d not knowrt shali be:
SAw3.6x to"cunes/grarn U U<depteted SA=(0.4+0.38 [+0.0034 E i 10-8 E E0.72 where E is the percentage by weighg of U-235, expressed as percent Nott in any caos where there is a murture m er or water of more than one redenuc6de, the kmrting values for purposes of Inn Apperurm shouid to deiermned as tonows-t, a vie idenser and conoontremon of endi redenuchde in ene vruxture are known, the amieng values should be denved as 8that Decomurse, for each redsonuchde in the truxture, Wie raiso between tie quenley present in the murture and the hmet oeherwise emessesmed in Appenda B tor the speedic radionuchde when tot in a markse. The sum of suoi rates for att the redenutidos et Ste mense may not exceed *1" (ie "urutM Exaaert.c W semenusedes A, B, and C are present in concentramons C C., and Cc, and if the anre*= MPC s, are MPC., and IMCe, and hW'Cr , -- Oi, then the concentrations shell be lutuand so that the lo660wng relationship easts: (C./MPC.)+(C,/MPC.)+(Cc/MPCc) 31
- 2. If either sie adenemy or the concentratson of any radonucisse in the motture as not knowet the limstmg values for purposes of Appenda B shes be-a For purposes of Tabte t. Col 1-6 x 10"'
- b. For purposes of Tatne 1. Col. 2-4 x 10"
- c. For purposes of Table ti. Col 1-2 x 10'"
- d. For purposes of Tab 6e 6t, Col 2-3 x 10"
- 3. If any of the conditions s>eefed below are met. the corresponding values spearfied be4ow may be used an lieu of those specified m paragraph 2 tibows,
- a. If the udentity ot each radenuclade m the r urture is knowm but the concentraten of one or more of the ra&onuchdes m the truxture is not known tne concentraton hat for the mrture es the hrrut specified in Appen&x 'B" tor the ra&onuchoe m the muture having the lowest concentraton hat, or
- b. af the esentity of each raconuchoe m the mrture as not known, but it as known that Cenam radenucides specAed en hpen&n "B" are not present m the nature. tne concentration hmet for the murture es the tr= west concentraten hat speed.ed e > Appendia "S" tor any racionuchoe wn.cn es not knowe to be absent from the murture; or B-10 ODCM Rev, 16
i A
- U Nuclear Regulatory Commission Pt. 20 [@{ 20.1-20.602], App. C l Tao = i j Tabie u
.'C,','-
1 e oemem mom.c numon) and isoiope Coi 2- Cet 1- cot 2-water Ar(,G/ Water I "O# 4G/m4 rrv) 4G/mi) I tf a m known that Sr 90, i 125. I 126. I 129. I 131 (t 133. Tatde a onsy). Pb l 210. Po 210. At 218. Aa 223. Aa 224. Am 226. Ac 227. Ra 228. Th 230. Pa 231. Th 232. Theat. Cm 248. Cf 254. and Fm 256 are not present. 9 x 10 -
- 3 x 10** .
W d a known that Sr 90. I 125. I 126. I 129 (i 131, i 133. Tenie u only). Pb I 210. Po 2 0. Aa 223. Ra 226. Ra 228. Pa 231. Thet. Cm 248. Cl 254 and Fm 256 are not present.. 6 x 10" . 2 x 10** H a a known that Sr *S I 129 (1 125. I 126. I 131. tao 6e il onsy). Pb 210. Ra 226. Ra 228. Cm 2ee, end Cf 254 are not preson' - 2 w 10" . 6 x 10* ' N a m known that (I 129, Taow al ordy). Ra 226. and Ra 228 are not presord 3 x 10 1 x 10* ' W R s known that aspha+rurters and Sr 90. I 129. PD 210. Ac 227. Ra 228. Ps 230, Pu 241, and Bk 249 are not present 3 x 10" 1 x 10"* N N is known that alpha 4mrrters and PD 210. Ac 227. Ra 228. and Pu 241 are not psesent 3 x 10 * ** . I x 10 * " if R es known Wnat alpha 4mmers and Ac 227 are not present 3 x 10 * " . - 1x10*" If a is known that Ac 227. Th 230. Pa 231. Pu 238. Pu 239. Pu 240. Pu 242. Pu 244. Cm 248. Cf 249 and Cf 251 are not present 3 x to-" , . . - . . . 1 x 10* " _
- 4. If a matere of radionuckles conosts of uraruum and Rs daughters ki ore duet pnor to chemaal separaten of the uranum troni the ore, wie values specrried be60w may be used for uratuurn and us daughters through radium 226. mstead of annee trorn paragraphs 1. 2. or 3 above.
a For purposes of Tatue 1. Cot 1-1 x10** pG/mi groes alpha acerwity; or 5x10*" eG/mi natural uraruum or 75 A numoyams por cubic meter of ar deatural urarwum. I v) b. F f Tatde I
- or purposes o.c m e, of ama,I.
ura ,. Co_t.1-3 x10"* pO/mi groes alpha actmey; 2x10* ** pG/mi naturat uratuum; or 3 trucr
$. For purposes of the note. a radionuckle may be conentered as'not present m a marture N (a) the ratso of the concereremon of that radionuchde n the mature (C.) to wie concerarehon knut for that radionuchos specified in Tabte 5 of Appendu *11" (AdPC.) ooes not exceed %e (te. C./MPC.51/10) and (b) the sum of such rates for se the radem consulared as not present at the murture ooes not escoed % Le.
(C./AdPC.+ C./MFC + 5 %). x 4; b d B-11 ODCM Rev. 16
, APPENDIX C i i I f .i I 'i e i 1 a EMS SOFIVARE DOCUMENTATION i 4 i I C-1 ODCM Rev. 16
APPENDIX C EMS SOFIVARE DOCUMENTATION TABLE OF CONTENTS CONTENTS PAGES Effluent Management System Software Test Report for C-3 Seabrook Station, May 1994 Cover 11 1-11 Resolutions of EMS Software Test Report Discrepancies C-4 1-2 Software Requirements Specification for North Atlantic C-5 Energy Service Corporation, Seabrook Station, 1-35 Effluent Management Systems, Revision 04, FP 75486 Technical Reference Manual, Effluent Management System C-6 Southern Nuclear Operating Company, January 1993, 36-92 FP 75486 O O C-2 ODCM Rev. 16
_.m...._ . _ _ . . 1 i 1 i APPENDIX C: EMS SOFTWARE DOCUMENTATION 1 4 i i i I' i l f d l 1 i ATTACHMENT 1: EFFLUENT MANAGEMENT SYSTEM SOFTWARE TEST REPORT FOR SEABROOK STATION, MAY 1994 1 l l l l 1 C-3 ODCM Rev. 16
EFFLUENT MANAGEMENT SYSTEM: ' SOFTWARE TEST REPORT FOR SEABROOK STATION MAY 1994 l i 1 a
- 1 Prepared by a J!E/9f4
/ Iface ne<L A b & -/ 5% 7/99 Reviewed by -
_ _> . 3/ - 7 Approved by / ! ' ' l Date l w l l Yankee Atomic Electric Company Nuclear Services Division 580 Main Street Bolton, Massachusetts 01740 O V j
Table of Contents
1.0 INTRODUCTION
. . . . . . . . . . . . . . . . . . . . . . . . 1 O
1.1 Background . . . .. . . . . . . . . . . . . . . . . . . . . . 1 1.2 Acceptance Criteria . . . . . . . . . . . . . . . . . . . . . . 1 2.0 SUHHARY OF FINDINGS . . .. . . . . . . . . . . . . . . . . . . . . . 2 2.1 EMS Dose and Dose Rate Conversion Factors . . . . . . . . . . . 2 2.2 Liquid Release Testing . . . . . . . . . . . . . . . . . . . . 4 2.3 Caseous Release Testing . . . . . . . . . . . . . . . . . . . . 4 3.0 TEST CONCLUSIONS . .. .. . . . . . . . . . . . . . . . . . . . . . 7 4.0
SUMMARY
OF DISCRIPANCIES . . . . . . . . . . . . . . . . . . . . . . 9 References . .. . . .. . .. . . . . . . . . . . . . . . . . . . . . . '11 1 O l l l i
l l Q
1.0 INTRODUCTION
Software testing as described in Reference [1] has been conducted for the l Seabrook Station version of the Canberra Effluent Management System (EMS). The
]
results and conclusions are presented in this report. l 1.1 Background I l " l Canberra Industries Inc. developed the EMS software to assist nuclear power plant personnel track effluent emissions and perform associated dose calculations. North Atlantic Energy Service Corporation purchased a Seabrook-specific version the Canberra EMS software which must meet specific requirements and incorporate site-specific information provided in the Offsite Dose 1 Calculation Manual (ODCM) [2]. Software testing was conducted to provide 1 assurances that the Seabrook EMS program produces results which are consistent i with current ODCM assumptions and methods. All executions of the EMS program 1 i q vere performed at Seabrook Station on the target software. All executions of l Q ODCM Method II were conducted at Yankee Atomic Electric Company in Bolton, 4 Massachusetts, i l 1.2 Acceptance Criteria 1 The operability of the EMS software will be accepted if (i) information J contained in the EMS data files is consistant with the CDCM, (ii) test results I from the EMS pro 5 ram are consistent with results from ODCM methods, (iii) Technical Specifications requirements are met by the EMS software, and (iv) the EMS software meets design specifications.
- Final user (Seabrook) acceptance is contingent on Seabrook approval of verification testing results and criteria established by user needs.
q 2.0
SUMMARY
OF OBSERVATIONS The EMS software testing included (i) identifying appropriste meteorological set up data, (ii) review of dose and dose rate conversion factor development, (iii) assessments for liquid releases, and (iv) assessments for gaseous releases. ODCM Method I was used initially to confira dose results from the EMS program. However, the simplified nature of ODCM Method I made it difficult to change the values of various parameters or obtain meaningful comparisons (other than " bottom line" comparisons). The more adaptable ODCM method, Method II, was then used to confirm EMS doses. Observations made during the sof tware testing are summarized below. 2.1 EMS Dose and Dose Rate Conversion Factors The EMS software uses precalculated conversion factors which are contained in a data file. The dose conversion factors for both liquid and gaseous effluent releases were developed for four age groups (adult, teen, child and infant), and for specific organs (bone, liver, total body, kidney, lun5, CI tract and skin). The liquid release dose conversion factors in the EMS program are the summation of the components for water recreation and ingestion of aquatic foods. The gaseous release dose conversion factors are exposure pathway-specific (e.g., inhalation, ground plane, milk ingestion, etc.). Dose conversion factors are provided in the EMS program for all exposure pathways addressed in the ODCM. The development of all dose conversion factors in the EMS program followed the pathway-specific equations in the Effluent Manarement System Technical Reference Manual [3] . The EMS conversion factors for several radionuclides were examined to determined that the development process was consistent to the Technical Reference Manual and the ODCM. O
2.1.1 Liquid Relean.e Dose Conversion Factors-Although the individual components for the ingestion of aquatic foods were found to be consistent with the ODCM, a discrepancy was discovered in the water recreation component. The mixing ratio for shoreline activity used in the development of the EMS dose factors is equal to 0.025. While this value is inconsistent with ODCM Method I (which employs a mixing ratio of 0.1), it is consistant with ODCM Method II. It is identified as a discrepancy because it is unclear which set of ODCK assumptions (those for Method I or those for Method II) the EMS program is expected to adopt. 2.1.2 Caseous Release Dose Conversion Factors The EMS program uses dose conversion factors from Regulatory Guide 1.109 l for assessment of noble gas releases. The dose factors in the EMS program were l verified against and found to be consistent with Table B-1 of Regulatory Guide 1 1.109 [4). The development methods for the other gaseous dose factors (i.e., for I inhalation, ground plane, milk ingestion, meat ingestion, and ingestion of vegetables) were reviewed against applicable equations in the Technical Reference Manual and information in the ODCM. It is noted that the dose factors for ingestion of milk and meat are based on the fraction of year that animals are allowed to graze on pasture land (Fp) equal to 1.0. This is not consistent with the ODCM which calls for the use of an Fp value equal to 0.5. The dose conversion factors in the EMS program for gaseous releases incorporate a shielding factor (SF) equal to 1.0. The EMS program is designed with a way of changing the value of SF (via use of the Options Table), but the factor is applied uniformly to both doses and dose rates. In contrast, the ODCK calls for the use of different values for SF in the calculations for doses and 3 ,
dose rates. 2.2 Liquid B.elease Testing Dose estimates from the EMS program for hypothetical liquid effluent discharges (containing single nuclide and radionuclide mixtures) are nearly identical to results from ODCM Method II when input data are based on the same mixing ratio value, indicating that the calculation method used in the EMS program is consistent with the ODCK. Additionally, the EMS routine (s) responsible for liquid effluent concentrations comparisons to MPC values and monitor set point determinations was observed to be operating properly. 1 2.3 Caseous Release Testing The agreement between estimates for total body dose rates, skin dose rates, and air (gamma and beta) doses due to emission of noble gases from the ODCM methods and the EMS program is excellent, indicating that the EMS calculation method is consistent with the ODCM. There is also excellent agreement between inhalation doses from the EMS program and ODCM Method II indicating that, for the inhalation pathway, the calculational method and assun:ptions in the EMS program are consistent with those in the ODCM. The evaluation of the dose estimates via inhalation pathway included both long and short release durations for an elevated (mixed mode) and a ground level release point. The excellent agreement between the EMS and ODCM Method II also confirms that the release duration adjustment ters, t**, is applied properly in the EMS program. However, an incorrect receptor location was reported on the EMS printout in the tests (D-2c and D-2d) in which the Plant Vent was changed to be recognized as a ground level release point. Also noted during testing was that the EMS routine (s) responsible for calculating effluent concentration-to-MPC ratios and radionuclide release rates S
. - - - . -. - _ - . . . . . _ - - . . . - - - ~ , . - . - . - - . _. --- 1 I i l appeaxs to be operating properly for gaseous ' releases. The EMS program incorporates the assumption that the fraction of elemencal iodine is equal to 1.0 (consistent with NUREG 0133 [5]). In contrast, the fraction of elemental iodine is assumed equal to 0.5 in the ODCM methods l (consistent with Regulatory Guide 1.109) . Consequently, the EMS program produces i l dose estimates due to radiciodine that are at least a factor of two greater than doses from the ODCM methods. This difference increases to about a factor of 4 when the current values for Fp and SF assumed in the EMS program and ODCM methods are used in the dose calculations. The different assumptions for elemental iodine fractions should not present a problem because each program is based on NRC guidance: the EMS is based on NUREG-0133, the ODCM methods are based on Regulatory Cuide 1.109. The EMS program takes the more conservative approach for determining doses from radiciodine. Making appropriate adjustments for Fp, SF, and the fraction of elemental iodine (when radioiodine input was used) and comparing results for organ doses due to I131. H3, Co60 and Cs137 revealed that the calculational methods used in the EMS program are consistent with the ODCM for all exposure pathways (i.e., ground plane, inhalation, milk ingestion, meat ingestion, and vegetables ingestion). Technical Specification 3.11.2.1 and the ODCM require the calculation of organ dose rates due to effluent discharges of 1131,1133, H3 and particulates
, with a half-life greater than 8 days. However, in all test cases involving these types of nuclidas, organ dose rate information did not appear a Page 4 of the EMS printout. Instead, the message "No calculations performed - check Sample &
Receptors" appeared. The EMS set up data and input were reviewed with no apparent error identified. Since the test cases included Cs137, Co60,1131, and 5
H3, the missing dose rate information was unexpected. It is noted that organ dose rate information was provided on Page 4 of the EMS printout during a ] demonstration of the EMS program prior to testing. l t O S
3.0 TEST CONCLUSIONS U Although the dose conversion factors are based on information which is not completely consistent with the assumptions in the ODCM, the calculational methods used to determine doses from liquid and gaseous effluent discharges are consistent with the ODCM methods. Other conclusions are:
- 1. As stated in Section 2.1.1, the development of the EMS liquid effluent dose factors is consistent with ODCM Method II, but not with Method I due to the mixing ratio value. If the EMS program is intended to be a hybrid method, the dose factors are consistent with the ODCM and are acceptable.
On the other hand, if the EMS program is intended to provide automated ODCM Method I calculations, then the dose factor should be recalculated using a mixing ratio for shoreline activity equal to 0.1.
- 2. Since the EMS program is not designed to support the use of two O
\ shielding factors ' (one for dose rates and one for doses), use of a shielding factor equal to 1.0 is acceptable with the understanding that, ,
I although the dose rates produced by the EMS program will be consistent with the ODCM, the doses from the EMS program will be based on a more conservative assumption than doses from the ODCM methods.
- 3. Under the normal ODCM assumption for elemental iodine, the results from the EMS program will be at least a factor of two greater than results from the ODCM methods. The different assumptions regarding the elemental iodine fraction do not present a problem because each pro 5 ram is based on NRC guidance: the EMS program is based on NUREG-0133, and the ODCM is based on Regulatory Guide 1.109. Of the two methods, the EMS program takes the more conservative approach toward estimating doser from O 7 O
i l radioiodine in gaseous effluent. 4 The radiation monitor set point determination method for liquid releases produces a set point value that is consistent the ODCM set point method.
- 5. The EMS routine that is responsible for comparison of liquid effluent concentrations and MPC values is operating properly.
- 6. The release duration adjustment term, t**, is used consistent 1*, ta the ODCM.
O i l l Gi i
4.0 SUMwJLRY OF DISCREPANCIES l N Discrepancy Area of Impact Potential Solution (s) Mixing ratio for Doses associated with Clarify whether the EMS shoreline activity liquid effluent program is expected to used in EMS discharges. follow ODCM assumptions program. for Method I or Method II. If determined to follow Method I, recalculate dose I factors for liquid releases. EMS dose factors Doses due to ingestion of Recalculate EMS dose based on Fp value milk and meat. factors for milk and meat , which is not ingestion pathways to consistent with incorporate Fp value ODCM. consistent with the ODCM. Accept added conservatism in EMS in calculations of doses via milk and meat ingestion pathways. Shielding factor Doses associated with Accept use of SF - 1.0 and (SF) applied gaseous effluent the added conservatism for
. uniformly to dose discharges. doses.
g races and doses in EMS program. Modify EMS software to accommodate use of two values for SF (one for dose rates and one for doses). Incorrect receptor Potential assignment of Discuss with Canberra, location doses to the wrong identified on EMS receptor. printout for ground level release point. Assumed fraction Dose estimates due to Accept added conservatism of elemental iodine in gaseous in doses due to iodine. iodine used in EMS effluents.
- program differs Modify EMS software to use from ODCM methods, fraction for elemental iodine that is consistent with ODCM.
O O '
Discrepancy Area of Impact Potential Solution (s) Missing organ dose Technical Specification Discuss with Canberra. ! rate information required dose rate not on dis printout calculated. [ for effluent discharges containing 1131, 1133. H3, and particulates. O 10
5 References.
- 1. Yankee Atomic Electric Company, Effluent Monitorine System Software Test Plan for Seabrook Station, May, 1994
- 2. NAESC, Station offsite Dose calculation Manual, Rev 13, 9/24/93. ,
- 3. Southern Nuclear Ooeratine Comoany Effluent Macarement System Technical Reference Manum 1 (07-0545), January 1993.
4 NRC Regulatory Guide 1.109, Calculation of Annum 1 Doses to Man from Routine Releases of Reactor Effluents for the Purnoses of Evaluatine Compliar;;:e with 10CFR Part 50. Accendix I, Revision I, October 1977. . 5. NRC NUREG-0133, Precaration of Radiolorical Effluent Technical i Soecifications for Nuclear Power Plants, October 1978. i 1 I 1 I 11 l l l
APPENDIX Cf EMS SOFTWARE DOCUMENTATION I I T ATTACHMENT 2: RESOLUTIONS OF EMS SOFIVARE TEST REPORT DISCREPANCIES l .i A ( ~ 1 2 1 } O C-4 ODCM Rev. 16
l Attechment 2 l 2. Resolution of EMS _ Software Test Reoort Discrepancies v The following discrepancy resolutions apply to the findings contained in the
" Effluent Management System Test Report for Seabrook Station, May 1994= as noted on pages 9 and 10 (see Attachment #1 of Appendix C of the ODCM). With the poritive !
resolution of the discrepancies iden~.ified in the EMS dose code, use sf EMS as a 1 computerized alternative approach (desigrated as Method IA in the ODC't; to determine l compliance with the radioactive effluent dose and dose rate limits is acceptable j since the results are comparable with the currently approved dose methods. j i 1 l Discrepanev: Mixing ratio for shoreline activity used in Ei1S Program not equal to the value used in the ODCM Method I (Mp - 1.0) . l Resolutforp The mixing ratio for the shoreline activity pathway in the EMS is consistent with the ODCM Method II approved value of 0.025, and therefore does provide for a calculated dose that is within the parameters elready approved in the ODCM. Tbf. use of the EMS code (ODCM Method IA) for calculating liquid doses is acceptable for determining compliance with the dose limits of the Technical Specifications without the need to modify the assumption used for the shoreline mixing ratio. l ( l Discrecanev: D EMS dose factors based on Fp (fraction of year animals are on pasture) value which is not consistent with ODCM. l Resolutinn: 09CM Method I assumes that the pe.sture season in the North East is 6 months long each year (Fp + 0.5). Method II allows for the pasture fraction to be set equal to 0.0 for the first and fourth quarters which equates the non-growing period of the year. The second and third quarters correspond to the growing season where the pasture fraction is assumed to be 1.0. The EMS software assumes an Fp value of 1.0 for animal grazing (meat and milk pathways) for all conditions. This is a moderstely conservative approach compared to Method I and the off grazing season condicions modeled in Method II. It is equal to the grazing season assumptions of Methed II as applied in the second and third quarters. As a result, the added conservatism in the EMS calculations for doses via milk and meat pathways a;a within acceptable margins and guidance provided in NRC NURE6'-0133 for demonstrating compliance with Technical Specification dose limits. No changes to the EMS software are necessary. l Discrecana: l Shielding factors (SF) applied uniformly to dose rates and doses in the EMS program. U 1
l 1 l Attrchnery 2 l l 2. Resolution of EMS Software Test Reoort Discrecaqqig} (Continued) Ol l Resolution: The EMS program for gaseous releases incorporates a shisiding factor (SF) equal to 1.0 for both dose rate and total dose determinations. In contra.st, both Method I and II use a SF value of 1.0 instantaneous dose rate calculations, but a value of 0.7 for integrated doses based on assumptions in NRC Reg. Guide 1.109. The use of a SF equal to 1.0 for fJie external ground plane exposure pathway for both dose rate and total dose is a moderately conservativa assumption that is within the bounds already assumed in the ODCM dose modeling. As a <ssult, no modification co the EMS code as an acceptable approach (Method IA) for deaonstrating compliance with Technical Specification dose / dose rate limits is required for SF. l Discrengngy; Incorrect receptor location identified on EMS printout for ground level release point. l Resolution: Incorrect name is identified on report with no impact on dose or dose rate calculations which were verified to be correct. l Discrepanev: Assumed fraction of elemental iodine used in EMS program differs from ODCM Methods I and II. l Resolution: 1 For ODCM Methods I and II, the fraction of elemental iodine assumed for gaseous i releases in 0.5 based on the guidance in NRC Reg. Guide 1.109. The EMS code assumes l an elemental iodine fraction of 1.0 based on the guidance in NUPEG-0133. Consequently, the EMS program (Method IA) will produce a moderately conservative estimate of dose impact (factor of 2) for iodine radionuclides if present in the release estimations when compared to existing approved methods. As a result, no modification to the EMS code is necessary for use in the ODCM for determining ' compliance with Technical Specification dose limits. l Discreoancy: Missing organ dome rate information on EMS printout for effluent discharges containing I-131, I-133, H-3, and particulates. l Resolution: 1 This required information is easily obtainable from the permit closure process with flashing indication if any dose or dose rate limits are exceeded. l i O 2
1 1 4 5 APPENDIX C: EMS SOFTWARE DOCUMENTATION l l 4 s $ r i i I A . I i . 1 l 1 1 i i ! i, a i i i ATTACHMENT 3: SOFTWARE REQUIREMENTS SPECIFICATION FOR NORTH ATIANTIC 2 ENERGY SERVICE CORPORATION, SEABROOK STATION, , EFFLUENT MANAGEMENT SYSTEMS, REVISION 04, FP 75486 i i > i 1 1 i d 1 i l I i I C-5 ODCM Rev. 16 1
Software Requirements Specification for North Atlantic Energy Services Corporation Seabrook Station Effluent Management Systems 48-8448 Revision 04 Nuclear Data Systems Division Software Product O Originator: . ma : //#f5 ) Approved: Date: I-78 Engineering (Cl/NDS) Approved: N
/ Date: 9o J QuaBty Mnager(CL/NDS)
Approved: hv Date: /0 if 73 Pro'je@4idinager (I seabrook Station) l
Scftware R:quirem3nt3 Specificatlan RS-6448-04 Revision Historv In M Revision Data Desertp6on H 00 2/26/93 W8al e DJH 01 3/22/93 Updated incorrect dose equabon DJH 02 4/30/93 Updated toinclude all dose and dose rate equations DJH 03 8/3/93 Updated baaed on modifications to software and customer's requested modification to the use of the default nuclide for gaseous P M proosas M . DJH 04 9/14/93 Updated based on customer's request to remove trML,.ei to the default nuclide for 9aseous permit process 4 I O
Software Requirerrcnt3 Specificati:n RS-8448-04 O 1. Scope P.agt 1
- 2. Applicable Documents 1
- 3. Interfaces 1 3.1 Hardware 1 3.2 Software 1 3.3 Human 2 3.4 Packaging 2
- 4. Definitions 2
- 5. Principal Changes from Existing Packages 2
- 6. EMS Functionality 4
. 6.1 Database Maintenance Transactions 4 6.2 Editing Values through INGRES QBF 7 6.3 Uquid Pre-Release Processing 8 6.3.1 Userinterface and Functionality 8 6.3.2 Associated Reports 9 6.3.3 Undertying Cahda'ians 10 6.4 Uquid Post-Release Processing 11 6.4.1 Userinterface and Functionality 11 6.4.2 A==aalaw Repos's 12 6.4.3 Undertying Cahdations 12 6.5 Uquid Permit Editirig 13 6.5.1 User interisce and Fur ~ra,rs.;ny 13 6.5.2 A==aalaw Reports 13 O
6.5.3 Undestying Calculations 13 6.6 Uquid Permit Deletion 13 6.7 Gaseous Pre-Release Processing 14 6.7.1 UserIntertaos and Functionality 14 6.7.2 Associated Reports 15 6.7.3 UndertiJ 'alculations 15 6.8 Gaseous Pos.14eiease Processing 21 6.8.1 User intertaos and Functionality 21 6.8.2 Aaantuaw Reports 21 6.8.3 Undertying nahdations ~22 , 6.9 Gaseous Permit Editing 27 6.9.1 User interface and Fur #m,r.e:ty 27 6.9.2 A==aalaw Reports 27 6.8.3 Underlying Calculations 27 6.10 Geseous Permit Deletion 27 6.11 Semi Annual Reporting 28 6.11.1 User Interface and Functionality 28 6.11.2 EMS Trond Plots 30 6.12 End-of-the-YearData Archiving 30 6.12.1 User Interisce and Functionality 30 O w3
Software Requirements Specificati:n RS *tiSO4
- 1. Scope This document estabishes the software requirements for the Effluent Management System (EMS) software to be installed at North Atlantic Energy Services Corporation's Seabrook Station.
l 2. Applicable Documents 2.1 The following two documents are included as part of this SRS, and this SRS l refers to specific sections of them: 2.1.1 " Southern Nuclear Operating Company Effluent Management System i Operator's Manual" (07-0544), Version 1, January 1993. 2.1.2 " Southern Nuclear Operating Company Efftpent Management System Technican Reference Manual" (07 0545), Version 2, January 1993. 1 Note: The above documents contain material (including screens and report formats) imported from final manuals for other EMS packages. Utility and i plant names shown on screens and reports in these manuals are not significant, since they are determined by database data that will be i customized to fit the Seabrook Station's usage. 2.2 The following document is a reference source for calculation rr.ethods of the EMS , software This SRS may roter to specific sections. 2.2.1 *3eabrook Station Offsite Dose Calculation Manual," Revision 12. O January 1993.
- 3. Interfaces ;
I ! 3.1 Hardware ! The EMS software shall run on the following CPU model: DEC Microvax 3100, Model 80. 3.2 Software l The software shau be written under VMS version 5.4-2 or later, using INGRES version 6.4 or later. It shall be written in VAX/ FORTRAN or VAX-DCL Utility programs provided by INGRES that are installed on the hardware configuration may be used if app 5 cable. 4 s W O
-_._ - - ~_.. .__. - _-. - - - .. - .... - . . - _.. _ -..-.- - _ _.. . ._ .. - .__ - - _ - -
l 1 1 Software Requirementa Specification RS 8448-04 a 0 N 3.3 Human 1
- The user may be expected to have received operator training from the system manager,
- Canberra /NDS, or the plant training department prior to using any part of the EMS j software. Knowledge of INGRES or VMS shall not be assumed. The menus of operations are intended to be self-explanatory, but an Operator's Manual shall be developed.
i j-
' The user may be expected to have enough knowledge of USNRC-regulated nuclear power plant effluent management to provide accurate and appropriate inputs, and to determine j the valdity of the software's results.
i. ) 3.4 Packaging i l A distribubon kit will be produced for the customer. Any removable medium supported by j the operating hardware delivered to the Seabrook Station is an acceptable distribution j medium. l j 4. Definitions i i EMS- Effluent Management System. Software for determining effluent monitor setpoints, i tracking activity releases and dose impacts of individual releases, and generating semi- ! annual release reports. SRS - Software Requirements Specification. j SNC - Southem Nuclear Operating Company i
- 5. Principal Changes from Existing Package
! The fol6owing paragraphs summarize the principal changes to the existing software that are j required for the Seabrook Station system, and are intended only as introductory material. ; Specifics of the required Seabrook Station EMS functionality are presented in the following ' i sec$ons. i
- 1 1
! 5.1 The EMS software will be developed by customizing the generic EMS package. l in general, the most important changes from previous versions are as follows: 1
- 5.1.1 ModiScation to Gaseous Permit Processing to allow scaling of nuclides for Plant Vent Spike release point.
i 5.1.2 Modification of noble gas dose rate and dose calculation methods to use i a third set of X/O values. !O wg I 1
Software Requir ments Cpecificatlin RS-8448-04 5.1.3 Modification of noble gas dose rate and dose calculation methods to multiply X/O and D/O values by a factor depending on the release duration. 5.1.4 Modification to setpoint calculations to calculate setpoints for low gamma concentration releases. 5.1.5 Modification of Permit Processing to automatically correct the expected j waste flow if it is greater than the calculated maximum waste flow. l 5.1.6 Modification of Liquid Permit Processing to determine dilution flow rate based on the number of pumps operating. 5.1.7 Modification of the permit reports to include Month-to-Date Cumulative Doses and Alert Setpoints. 5.1.8 Modification of Post-Release Permit Processing to update the monitor l response. 5.1.9 Addition of data to database to support and control the above operations. O i l l l i 1 l
i Software Requirements Specificati n RS-844H4 1 i i
- 6. EMS Furictionality 4
6.1 Database Maintenance Transactions
- The functionality of the EMS Database Maintenance transactions shall be described in j section 2 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions:
l ! 6.1.1 On the Release Point Setpoint transaction [EM DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following j parameter shall be added to the list of those which can be entered, stored, and j which appear on the printed report for these transactions: } } SCAL _NUC: For a gaseous release, a flag to denote that this release point will ] have nuclide concentrations scaled so that the total concentration matches a j value entered by the user. l 6.1.2 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)] and the i Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following ! parameter shall be added to the list of those which can be entered, stored, and j which appear on the printed report for these transactions: {
- DILOOKUP: For a liquid release, a flag to denote that permits for this release
! point will have a selection screen appear for the user to select the proper dilution j flow for the release based on the number of pumps operating. l 6.1.3 On the Release Point Setpoint transaction [EM-DM RP (Form 2)], and the j Discharge Point Setpoint transaction [EM-DM-DP (Form 2)], the following i parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:
- DEF NUC: For a liquid or gaseous release, this parameter will contain the default i nuclide that will be used in setpoint calculations for low gamma concentration i releases. This parameter is used in conjunction with the DEF CONC parameter.
J . 6.1.4 On the Release Point Setpoint transaction (EM-DM RP (Form 2)], and the 1 l Discharge Point Setpoint transaction (EM-DM-DP (Form 2)], the following l l paramotor shall be added to the list of those which can be entered, stored, and ' i whloh appear on the printed report for these transactions: ; i DEF._ CONC: For a liquid or gaseous release, this parameter will contain the defr4t concentration that will be used in setpoint calculations for low gamma conoontration releases. This parameter is used in conjunction with the DEF_,NUC j Parameter. 1
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4 Software Requirements Specificati:n RS-8448-04 i 6.1.5 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)], and the Discharge Point Setpoint transaction [EM DM-DP (Form 2)], the following parameter shall be added to the list of those which can be entered, stored, and which appear on the printed report for these transactions:
+ DEF_, TYPE: For a liquid or gaseous release, this parameter will contain the i default nuclide type that will be used in setpoint calculations for low gamma
, concentration releases. This parameter is used in conjunction with the DEF_NUC and DEF_ CONC parameters. (Note: For a gaseous release, the default nuclide type shall determine which monitor setpoint should t.s ) the default nuclide and ~ concentration.) 6.1.6 On the Release Point Setpoint transaction [EM-DM-RP (Form 2)], and the Discharge Point Setpoint transaction (EM-DM-DP (Form 2)], the following ps.rameter shall be added to the list of those which can be entered, stored, and , which appear on the printed report for these transactions: 4 + ALRT SET: For a liquid or gaseous release, this parameter will contain the multiplier to be used in the calculation of Alert Alarm Setpoints for permit reports. 6.1.7 On the Release Point transaction [EM-DM RP (Form 1)], the meaning of the Response Option will change. When set to "Y", this option will denote the display of a Monitor Response window during the Post-Release Permit Processing, rather than during the Pre-Release Permit Processing. The Response Option
- parameter, itself, will remain unchanged for this transaction, but the response entered should include the monitor background values.
6.1.8 On the Dilution Streams transaction [EM-DM-ov the fogowing parameters will be i removed: the number of extra dilution flow rate And the four dilution flow rates. These parameters will be replaced with two column fields. One column will contain the dilution flow rate, while another will contain the pump configuration description (such as " Jockey Pump
- or '5"). In this transaction, the dilution flow rate for particular pump configuration can be added.
6.1.9 On the Meteorological Data transaction (EM-DM-ME (Form 1)], several menu options will added to the ist of MET DATA TABLES. These addtional menu items-are as follows: X/O - Noble Gases (Gamma) i "a" Factor - D/O-Part/lodines
- 'a' Factor- Noble Gases "a* Factor - X/O-Part/lodines "a" Factor - Gamma Noble Gases
.s. M O
t Software Requirements Specification RS-8448-04 6.1.10 On the Meteorological Data transaction [EM DM-ME (Form 1)], the following menu items will be used to store short-term (1 hour) D/O and X/O values. ; D/Q - Partics/Radiciodines X/Q - Partics/Radioiodines X/Q - Decayed Noble Gases X/Q - Noble Gases (Gamma) Note: This specification item only denotes a change in the meaning for the values on this transaction and requires no further changes to the software. 6.1.11 On the Meteorological Data transaction [EM-DM-ME (Form 1)), the X/Q, D/Q, and "a" Factor values are defined for various elevations, distances, ' and directions from the plant vent or stack. This combination with the
" mode of release" parameter on the Release Point transaction (EM-DM- '
RP (Form 1)], and the receptor definition on the Gas Receptors transaction [EM-DM-GR), allow the X/Q, D/O, and "a" factors to be different for each receptor and/or release point. Note: This specification item is only for clarification and no additional code changes need to be made to this transaction. O
+
49 %
Software R;quirements Specificati:n RS-8448-04 6.2 Editing Values through INGRES OBF in addition to the interactive forms based EMS Database Maintenance transactions, O certain flags and values must be edited through INGRES OBF on the database tables which contain data not accessible through the forms-based transactions. 6.2.1 Some colurans of the Quarterly Dilution Volume table (ODVOL), which has no other use in the Seabrook Station version of EMS, will be used for recording monthly dilution volume for use in semi-annual reports. Once per month, an authorized user will use OBF to append a record to the ODVOL table as follows: sampleid (sample ID) 0 [not used] dvdate (dilution volume date) The first day of the month to which the volume applies (time not regired). tvol (total volume) Dilution volume for the month, in user units. aflow (average flowrate) 0 [not used) O
.,. f4 0 G
i Software Requ!rements Specificati:n RS-8448-04 6.3 Liquid Pie-Release Processing l 6.3.1 User interface and Functionality j i i Liquid Pre-Release Processing functionality for the EMS software shall be as ! described in section 3 of the EMS Operator's Manual (Reference 2.1.1), with the I
. following revisions:
6.3.1.1 On the Uquid Permit DeAnition Screen (Screen 3.04): , Upon entering the permit de6nition screen, if the DILOOKUP parameteris set to "Y" for t!ie release point associated with the current permit being processed, the Dilution Flow Rate parameter will default to zero. If a user uses the " Tab' or " Return" key to exit the Dilution Flow Rate i parameter on the Permit DeAnttion Screen and the Dilution Flow Rate parameter has a value of zero, a selection screen with two columns of ) data will appear. One column will contain the pump configuration I description, while the other will contain the dilution flow rate for each , asetxWed pump con 6guration. Upon selection of the Dilution Flow Rate, the selection screen will disappear and the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen. The cursor will then automatically advance to the Dilution Volume Parameter. 6.3.1.2 On the Liquid Permit De6nition Scroon (Screen 3.04): When a " Fill" (F14) or a "Save" (F10) without a " Fill' is executed, if the DILOOKUP parameter is set to "Y" for the release point associated with the current permit being processed and the Dilution Flow Rate parameter is set to zero, a selection screen, as described above will appear. Once a selection of the Dilution Flow Rate is complete, the selectior, screen will disappear and the " Fill" operation will continue. Upon completion, the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit DeAnttion Screen. If the Dilution Flow Rate parameter on the Permit Definition Screen is not set to zero and the DILOOKUP parameter is set to "Y", the fill will ' proceed as normal without the dilution flow rate selection screen appearing. O moA\
\
S:ftware Requirements Specificati n RS-8448-04 i S.3.1.3 Prior to entering the Liquid Permit Approval Screen (Screen 3.09): J If it is determined that the computed maximum waste flow is less than the anticipated waste flow, the anticipated waste flow will be changed to have the value of the computed maximum waste flow. If the anticipated waste flow is modified, setpoint, dose, and dose rate values will be recalculated 4 based on the new value. i 6.3.1.4 For releases with low or zero gamma emitter concentrations that result in a pre-diluted MPC ratio less than 10%, a default concentration will be used for setpoint calculations. This default concentration will not be used for updating curie, dose rates, or dose totals. The default nuclide will be attained from the DEF_NUC parameter. The default concentration for this nuclide will be attained from the DEF CONC parameter. The default type for this nuclide should be attained from the DEF TYPE parameter. 6.3.1.5 The Monitor Response Screens for Release Points and Discharge Points (Screen 3.08) will no longer appear while processing a Pre-Release ! Permit when the Response Option is set to "Y" on the Release Point transaction [EM-DM-RP (Form 1)). t 6.3.2 Associated Reports Liquid Pre-Release Permit Reports shall be as described in section 3 (pages 3 53 through 3-58) of the EMS Operator's Manual (Reference 2.1.1), with the following l revisions: 6.3.2.1 On the Pre-Release Permit Report (3.01), the Cumulative Month-to-Date Doses will appear on the page with the report category of Cumulative Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of i the doses for all "Open" and " Closed" permits including the permit for i which the report is being generate <t. These dose values will appear immodately below the "This Release' row of doses. 6.3.2.2 On the Pre-Release Permit Report (3.01), an Alert Alarm Setpoint will appear below the Max Monitor Setpoint Value. The Alert Alarm Setpoint will be calculated by using the multiplying the release point setpoint value by a multiplier specified with the ALRT_ SET parameter menboned above. 6.3.2.3 On the Liquid Special Report (3.02), e Alert Alarm Setpoint will appear below the Release Point and Dischtarge Point Setpoint values in the Radiation Monitor (s) portion of the repert. 1 9
4 d Software Requ!rements Specificati n RS-8448-04 1 i 6.3.2.4 On the Pre-Release Permit Report (3.01), the calculation of setpoint data for addibonal dilution flow rates (under Pre-Release Calculations) will use dilution flow rate values from the Dilution Streams transaction [EM-DM-DS) for a specific dilution stream. Up to four dilution flow rates which are Igr]33r than the dilution flow rate parameter entered on the Liquid Permit Definition Screen (3.06) will be used. ? I 6.3.3 Underlying' Calculations The calculations performed by the EMS software for Liquid Pre-Release Permits shall produce the same results as those described in Chapter 2 (sections 2.1-2.6) of the EMS Technical Reference Manual (Refenmco 2.1.2), with no revisions. O 1 I O I Software Requirement] Specificati:n RS-8448-04 6.4 Liquid Post-Release Processing 6.4.1 User interface and Functionality Liquid Post-Release Processing functionality for tne EMS software shall be as described in section 3 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: l 6.4.1.1 On the Uquid Permit Definition Screen (Screen 3.13): If the DILOOKUP parameter is set to "Y" for the release point and a user uses the " Tab' or " Return" key to exit the Dilution Flow Rate parameter on the Permit Definition Screen and the Dilution Flow Rate parameter has a value of zero, a selection screen with two columns of data will appear. One column will contain the pump configuration description, while the other will contain the dilution flow rate for each associated pump configuration. Upon selection of the Dilution Flow Rate, the selection screen will disappear and the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen. The cursor will then automatically advance to the Dilution Volume Parameter. 6.4.1.2 On the Uquid Permit Definition Screen (Screen 3.13): When a " Fill" (F14) or a "Save" (F10) without a " Fill" is executed, if the DILOOKUP parameter is set to "Y" for the release point associated with the current permit being processed and the Dilution Flow Rate parameter is set to zero, a selection screen, as described above will appear. Once a selection of the Dilution Flow Rate is complete, the selection screen will disappear and the " Fill' operation will continue. Upon comps?Jon, the selected dilution flow rate will appear in the Dilution Flow Rate parameter on the Permit Definition Screen. If the Dilution Flow Rate parameter on the Permit Definition Screen is not set to zero and the DILOOKUP parameter is set to "Y", the fill will proceed as normal without the dilution flow rate selection screen appearing. 6.4.1.3 (item removed since actual waste flow is known at time of post release processing.) _ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . ~ . _ . - _ _ . . _ _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ j Software Requirements Specification RS-8448 04 1 i i ' 6.4.1.4 The Monitor Response Screens for Release Points and Discharge Points
; (Screen 3.08) will appear while processing a Post-Release Permit when i the Response Option is set to "Y" on the Release Point transaction [EM- } DM-RP (Form 1)]. These screens will appear following the Nuclide
- Concentration Screen (Screen 3.15). The monitor response values entered should include the monitor background values.
l 6.4.2 Associated Reports t Uquid Post-Release Permit Report shall be as described in sec, tion 3 (pages 3-59 : j through 3-62 of the EMS Operator's Manual (Reference 2.1.1), with the following ' l revisions: ! 6.4.2.1 On the Post-Release Permit Report (3.03), the Cumulative Month-to-Date Doses will appear on the page with the report category of Cumulative
- Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summaticn of l the doses for all "Open" and " Closed" permits including the permit for l which the report is being generated. These dose values will appear j immediately below the "This Release' row of doses.
i j 6.4.3 Underlying Calculations ! The calculabons performed by the EMS software for Liquid Post-Release Parmits
- shall produce the same results as those described in Chapter 2 (sechon 2.7) of i the EMS Technical Reference Manual (Reference 2.1.2), with no revisions.
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., . . , , . - - . ~ - .-
Software Requir;ments Specificati:n RS-8448-04 6.5 Liquid Permit Editing 6.5.1 User inte1 ace and Functionality ) Functionality for editing liquid permits through the EMS software shall be as described in section 3 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: The appearance and functionality of the liquid permit definition screen and the monitor response screen shall be modified as described for the Pre-Release stage in sections 6.3.1 and 6.4.1 above. 6.5.2 Associated Reports The permit report format and contents for edited open and closed liquid permits shall be as specified above for original permit toports, in sections 6.3.2 and 6.4.2. respectively. 6.5.3 Underlying Calculations . The calculation methods for editing open and closed liquid permits shall be n specified above for original calculations, in sections 6.3.3 and 6.4.3, respectively. 6.6 Liquid Permit D61stion Functionality for deleting liquid permits through the EMS software shall be described section 3 or the EMS operator's Manual (Reference 2.1.1).
.I
l 1 j Software Requirements Specificati:n RS-8448-04 6.7 Gaseous Pre-Release Processing 4 l 6.7.1 User interface and Functionality Gaseous Pre-Release Processing functionality for the EMS software shall be as 4
- described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions
6.7.1.1 On the Gaseous Permit Definition Screen (Screen 4.05): a j The initial Pressure and Final Pressure parameters shall be deleted. l 6.7.1.2 On the Gaseous Nuclide Concentration Screen (Screen 4.06): 1 l If the SCAL _NUC parameteris set to "Y", when exiting the Concentration 4 Screen by hitting " Process" (Do), the user will be prompted for the total 3 nuclide concentration of permit. The concentrations are then ' scaled
- j and then stored intomally. As a result, the concentrations displayed on the screen will remain unchanged. (See the Underlying Calculations section for Pre-Release Permit Processing for an explanation of the
' scaling' of concentrallons.)
NOTE: ~This method requires the VAX_GSP (F12) file transfer has occurred bringing the representative nuclide concentration values to the O screen pr'or to "Save" of data. 6.7.1.3 For releases with low or zero gamma emitter concentrations that result in a pre-diluted MPC ratio less than 10%, a default concentration will be used for setpoint calculations. This default concentration will not be used for updating curie, dose rates, or dose totals. The default nuclide will be attained from the DEF_NUC parameter. The default concentration for this nuclide will be attained from the DEF_ CONC parameter.' The defau!t type for the default nuclide should be attained from the DEF_ TYPE parameter. 6.7.1.4 The Monitor Response Screens for Release Points and Discharge Points
., (Screen 4.08) will no longer appear while processing a Pre-Release Permit when the Responso Option is set to "Y" on the Release Point transaction [EM-DM-RP (Form 1)).
6.7.1.5 Prior to entering the Gaseous Permit Approval Screen (Screen 4.09): If it is determined that the computed maximum waste flow is less than the anticipated waste flow, the anticipated waste flow will be changed to have the value of the computed maximum waste flow. If the anticipated waste flow is modified, setpoint, dose, and dose rate values will be recalculated based on the new value. O
.w 9p\7
Software Requirements Specificati:n RS-8448-04 6.7.2 Associated Reports Gaseous Pre-Release Permit Reports shall be as described in section 4 (pages 4-49 through 4-58) of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: 6.7.2.1 Ori the Pre-Release Permit Report (4.01), the Cumulative Month-to-Date Doses will appear on the pages with the report category of Cumulative Dose at Site Boundary and Cumulative Maximum Individual Dose for Controlling Age Group at Controlling Location. The Month-to-Date dose values will contain the summation of the doses for all"Open" and
" Closed" permits including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" row of doses.
6.7.2.2 On the Pre-Release Permit Report (4.01), the " scaled" noble gas concentrations shall appear on the isotopic identification page of the report if the SCAL _,NUC parameter is set to "Y" for the release point where the releaseis being made. 6.7.2.3 On the Pre-Release Permit Report (4.01), the Noble Gas Alert Alarm Setpoint will appear below the Max Monitor Setpoint values. The Alert Alarm Setpoint will be calculated by multiplying the noble gas monitor setpoint value by a multiplier specified with the ALRT SET parameter mentioned above. 6.7.2.4 On the Gaseous Special Report (4.02), the Noble Gas Alert Alarm Setpoint will appear below the Release Point and Discharge Point Setpoint values in the Radiation Monitor (s) portion of the report. It will be calculated as mentioned above. 6.7.2.5 On the Pre-Release Permit Report (4.01), the initial and Final Pressure parameters will be removed from the Pre-Release Data section of page one of the report. 6.7.3 Underlying Calculations The calculations performed by the EMS software for Gaseous Pre-Release Permits shall produce the same results as those described in Chapter 3 (section 3.1-3.6) of the EMS Technical Reference Manual (Reference 2.1.2), with the following revisions and clarifications: i Software Requirem:nts Specificati:n RS 8448-04 i O 6.7.3.1 Dose Calculations will appear in the site specific technical reference manualas follows: For Noble Gas Total Body Dose Rate (for vents or stacks < 80 meters): Dt = shf X/Q g 8760-a po I (K;
- QRgy) where Dt = the total body dose rate due to gamma emissions by noble gas relamaan from vent v (mrom/yr) shf = shieldng factor (dmensionless)
Q Rgy = release rate of noble gas radionuclides,I,in gaseous effluents from vent or stack v ( pCi/sec). Fo = occupancy factor defined for the receptor at the given j locahon (dimensionless) i Ki
= total body dose factor due to gamma emissions for noble gas radionuclide I (mrom/yr per pCL/m3) ;
X/Q g = highest value of the noble gas 1-hour X/O for gamma radiation for vent or stack y at the site boundary, (sec/m3 ) 8760-a = adjustment factor used to convert the 1-hour X/O value to an average 1 year X/O value (dimensionless) where 8760 = number of hours in a year
.a = "a" factor for gamma noble gas X/Q
. For Noble Gas Total Body Dose (for vents or stacks < 80 meters):
shf. Fa I(K; Orgy) X/Qg t-a
=
De 5 (5.256 + 10 / dur) where De. = total body dose from gaseous effluents (mrom) 5.256 10 =5 number of minutes in a year dur = duration of the release (minutes) O -1 s-gW
.. . . _. - - _ - _ _ . . . .. . ~_~ -- =_ _ . _ . .
Software Requirements Specificatten RS-8448-04 t-a = adjustment factor to convert the 1-hour X/O value to the short term X/Q value for the release (dimensioniess) , where t = duration of release (hours) l l a = "a* factor for gamma noble gas X/O l For Noble Gas Skin Dose Rate (for vents or stacks < 80 meters): D= s shf a Fo I QRiy + [(Lg + X/O 87604) + (1.11M;
- X/Qg 8760-a))
where Ds = skin dose rate from gaseous effluents (mrom/yr) X/O = highest value of the noble gas 1-hour X/O for vent or stack v atthe site boundary (sec/m3) M; = air dose factor due to gamma emissions for noble gas radionucide I(mradlyr per pCl/m3) l l 1.11 = conversion factor from mrad to mrom l Li
= skin dose factor due to beta emissions for noble gas radionucide I (mrem /yr per pCL/m3) b = "a" factor for noble gas X/O For Noble Gas Skin Dose (for vents or stacks < 80 meters):
shf F o I QRjy -[(L X/O i + t% + (1.11Mg a X/Qg t-a)) Dak (5.256 105/ dur) where Dsk
= total skin dose from gaseous effluents (mrem)
Oh
Software Requir;ments Specificati:n RS-8448-04
- For Noble Gas Air Dose due to gamma radiation (for vents or stacks < 80 meters):
Dy = (3.17 10-8). X/Qg t-a . Fo a I Mg . Qiy where Dy = total gamma air dose from gaseous effluents (mrad) ! 3.17 + 104 = inverse of number of seconds in a year O-y = release of noble gas radionuclides, I, in gaseous effluents from vent or stack v (gCl) Q;y = ORjy + dur
- 60 l where l
60 = number of seconds in a minute For Noble Gas Air Dose due to beta radiation (for vents or stacks < 80 meters): Dp = (3.17 10-8). X/O
- t*
- Fo
- I N i
- Oiy where Dp = total beta air dose from gaseous effluents (mrad)
Ng = air dose factor due to beta emissions for noble gas radionucBdeI(mrad /yrperpCi/m3 )
+
For Critical Organ Dose Rate-Inhalation Pathway and all Pathways ; for H-3, C-14 (for vents or stacks < 80 meters): DRTa = X/Or 8780* I PipTa . Orgy where DRTa = dose rate for age group a and organ T from iodines and particulates with half lives greater than 8 days in gaseous effluents (mrom/yr) P ipra = dose factor for each radionuclide i, pathway p, organ T, and age group a (mrom/yr per pCl/m ) O gM
Software R quir;ments Specificatlin RS-8448-04 X/O r = highest value of the radiolodine/ particulate 1-hour X/O for vent or stack v at the site boundary (sec/m3 ) c = "a* factor for Radioiodine/ Particulate X/O Note: Itis assumed P ipta will not contain long term X/O or D/O values. For Critical Organ Dose Rate--Ground and Food Pathways (for vents or stacks < 80 meters): DRra - D/O =87604 IR pra ORjy where D/O = highest distance ofvalue the siteof the 1-hour boundary (1/m dep)osition factor at the d = "a" factor for D/O R ipta = dose factor for each radionuclide I, pathway p, organ r, and age group a (m2
- mromfyr per pCl/sec)
Note: it is assumed R ipta will not contain long term X/O or D/O values. For Critical Organ Dose-Inhalation Pathway and all Pathways for H 3, C-14 (for vents or stacks < 80 meters): D ra = (3.17 + 10-8) . X/Or t* + F o I P ipta Ojy where D ra = dose for age group a and organ i from lodines and particulates with half lives greater than 8 days in gaseous affluents (mrom) Note: It is assumed P ipta will not contain long term X/O or D/O values.
~h
Softwarv Requirements Specification RS 8448-04 For Critical Organ Dose-Ground and Food Pathways (for vents or stacks < 80 meters): j D Ta = (3.17 10-8) . D/O + td+F+IRipra o
- Oiv Note: it is assumed R ipta will not contain long term X/O or D/O values.
6.7.3.2 On the Nuclide Concentration Screen (Screen 4.06), nuclide ! concentrations will be " scaled" if the SCAL _NUC parameter is set l property for a Release Point. This "scaing"is desenbod as follows: Cinew = (t / s)
- Ci f
where
'Cinow = concentration (after"scaing") of nucBdei ,
s = sum of all nuclide concentrations on the Nuclide l Concentration Screen. l t = total nucide concentration entered by the user Cg = concentation (before 'scaing") of nucideg
.- - .. - _ . - _ _~ . . . - . ____ - - - -
l Software Requirsments Specificati:n RS-8448-04 6.8 Gaseous Post-Release Processing 6.8.1 User interface and Functionality Gaseous Post-Release Processing functionality for the EMS software shall be as
- described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the 1
following revisions: 6.8.1.1 On the Gaseous Permit Definition Screen (Screen 4.14): The initial Pressure and Final Pressure parameters shall be deleted. 6.8.1.2 On the Gaseous Nuclide Concentration Screen (Screen 4.15):
- If the SCAL NUC parameter is set to "Y", when exiting the i
' Concentration Screen by hitting " Process" (Do), the user will be prompted for the total nuclide concentration of permit. The value entered for the total nuclide concentration while opening the permit shall be displayed as a default value which can be modified. Once the value is entered / accepted the concentrations are then " scaled" and then stored , intomally. As a result, the concentrations displayed on the screen will j remain unchanged. (See the Undertying Calculations section for Post-Release Permit Processing for an explanation of the ' scaling" of i concentrations.) NOTE: This method requires the VAX_GSP (F12) file transfer has occurred bringing the representative nuclide concentration values to the screen prior to "Save" of data. 6.8.1.3 The Monitor Response Screens for Release Points and Discharge Points (Screen 4.08) will appear while processing a Post Release Permit when the Response Option is set to 'Y' on the Release Point transaction [EM-DM RP (Form 1)]. These screens will appear following the Nuclide Concentration Screen (Screen 4.15). The monitor response values should include the monitor background values. 6.8.1.4 (ltem removed. since actual waste flow is known at time of post release Processing.) 6.8.2 Associated Reports Gaseous Post Release Permit Reports shall be as described in section 4 (pages 4-58 through 4-63) of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: 21-
1 i i Software Requirements Specification RS-844604 !O t 8'.8.2.1 On the Post-Release Permit Report (4.03), the Cumulative Month-to-Date Doses will appear on the pages with the report category of Cumulative l Dose at Site Boundary and Cumulative Maximum Individual Dose for ControlHng Age Group at Controlung Location. The Month-to-Date dose values will contain the summation of the doses for all"Open" and i " Closed" permits including the permit for which the report is being generated. These dose values will appear immediately below the "This Release" row of doses. 6.8.2.2 On the Post Release Permit Report (4.03), the ' scaled" noble gas concentrations shall appear on the isotopic Identification page of the report if the SCAL NUC parameter is set to "Y" for the release point ' where the release is being modo. i 6.8.2.3 On the Post-Release Permit Report (4.03), the initial and Final Pressure i parameters will be removed fmm the Pre-Release Data section of page one of the report. 6.8.3 Underlying Calculations The calculations performed by the EMS software for Gaseous Post-Release Permits shall produce the same results as those described in Chapter 3 (section 3.7) of the EMS Technical Reference Manual (Reference 2.1.2), with the following revisions and clattfications: ; 6.8.3.1 Dose Calculations will appear in the site specific technica .eference manual as follows: For Noble Gas Total Body Dose Rate (for vents or stacks < 80 i meters) l Dt = shf
- X/Qg
- 8700-a . po. I (Kg
- QRjy) where Dt = the total body dose rate due to gamma emissions by ne'ole gas releases from vent v (mrom/yr) shf = shieldng factor (dimensionless)
ORiy = release rate of noble gas radionuclides, I, in gaseous effluents from vont or stack v ( pCi/sec). Fo = occupancy factor defined for the receptor at the given location (dimensionless) Kg = total body dose factor due to gamma emissions for noble gas radionuclide I (mrom/yr per pCl/m3) 22 #po
\ 9 35
Software Requirements Specificatlin RS-8448-04 X/Q g = highest value of the noble gas 1-hour X/O for gamma radiation for vent or stack V at the site boundary, (sec/m3 ) 8760-a = adjustment factor used to convert the 1-hour X/O value to an average 1 year X/O value (dimensionless) where 8760 = number of hours in a year a = "a" factor for gamma noble gas X/O 1
+ For Noble Gas Total Body Dose (for vents or stacks < 80 meters):
shf = Fo I(Kg ORiv) X/Qg t-a D tb " 5 (5.256 10 / dur) l where Dtb
= total body dose from gaseous effluents (mrom) 5.256 10 =5 number of minutes in a year dur -
duration of the release (minutes) t-a = adjustment factor to convert the 1-hour X/O value to the short term X/O value for the release (dimensionless) where t = duration of release (hours) a r. "a" factor for gamma noble gas X/O
+ For Noble Gas Skin Dose Rate (for vents or stacks < 80 meters):
D= s shf Fo I QRgy. [(Q + X/Q 8760-b) + (1.11Mg X/Qg 8760-a)) where Ds = skin dose rate from gaseous effluents (mrem /yr) X/O = highest value of the noble gas 1-hour X/O for vent or stack V at the site boundary (sec/m3) 23
~
l - . 1
; Softwere Requirements Specification RS-8448-04 i
, Mg =
- air dose factor radionuclide I(mrad /yr due to gamma g) missions for noble g por pCi/m i
i 1.11 = conversion factor from mrad to mrom I j L; = skin dose factor due to beta emissions for noble gas , radionuclide I(mrom/yr per pCi/m3) b = "a" factor for noble gas X/Q l
. For Noble Gas Skin Dose (for vents or stacks < 80 motors):
l shf
- Fo + I QRiy.[(L i+ X/Q th + (1.11Mi X/Q g t-ay)
{ Dg = 5 j (5.256 10 /dur) where Dsk
= total skin dose from gaseous effluents (mrom) i For Noble Gas Air Dose due to gamma radiation (for vents or stacks < 80
, meters):
'D y = (3.17 + 104 ) a X/Q a t4* F aI M
- Q g o i iy 4
I where Dy ) 4
= total gamma air dose from gaseous effluents (mrad) 3.17 a 104 = inverse of number of seconds in a year l 09 = release of noble gas radionuchdes, I, in gaseous effluents j from vent or stack y (pCI)
'/ Qgy = Orgy a dur
- 80 l j where i 60 = number of seconds in a minute
}
! l 1
j k k l - 27 l 5" i i
i . Software Requirements Cpecificati:n RS-6448-04
+
For Noble Gas Air Dose due to beta radiation (for vents or stacks < ] 80 meters): Dp = (3.17 a 10-8) X/O t-b , op . I N; 0;y where Dp = total beta air dose from gaseous effluents (mrad) N3
= air dose factor due to beta emissions for noble gas radionuclide I(mrad /yr per pCl/m3 )
For Critical Organ Dose Rate-Inhalation Pathway and all Pathways for H-3, C-14 (for vents or stacks < 80 meters): DRta = X/Or
- 8760*
- I Pipta
- Q R;y where DRia = dose rate for age group a and organ i from iodines and particulates with half lives greater than 8 days in gaseous effluents (mromfyr) l l pathway p, organ r, P;pra = doseand agefactor group a for eachperradionuclide I,3)
(mrom/yr pC1/m X/O r = highest value of the radioiodine/ particulate 1-hour X/O for 3 vent or stack v at the site boundarf (sec/m ) c = *a" factor for Radiciodine/ Particulate X/O Note: It is assumed P ipta will not contain long term X/O or D/O values. i 4 - For Critical Organ Dose Rate-Ground and Food Pathways (for vents or stacks < 80 meters): DRra - D/O + 8760d*IRipta OR y I where I D/O = l highest distance ofvalue the site of the 1-hour boundary (1/m deg)osition factor at the d = *a* factor for D/O
.,.s. W *
. - . _ . _ _ . - ~ . _ _ _ . _ _ _ _ _ . - _ _ _ . _ _ . - - . . _...___ _ _ _ . _ _._... _.__._ - .
Softwere Requirements Opecificatirn RS4448-04 R ipra = dose factor for each radionuclide I, pathway p, organ r,
- and age group a (m2* mrom/yr per pCi/sec) t Note
- It is assumed R ipta will not contain long terrh X/O or D/O
{ values.
+
i For Critical Organ Dose-Inhalation Pathway and all Pathways for H-3, i C-14 (for vents or stacks < 80 motors): D ra = (3.17 104)
- X/Or a t* Fo I Pipta*Oiv j where 4
j D, y = dose for age group a and organ i from lodines and j particulates with half lives greater than 8 days in gaseous effluents (mrom) Note: It is assumed Pipy, will not contain long term X/O or D/O values. For Critical Organ Dose-Ground and Food Pathways (for vents or stacks < 80 meters): D ra = 4 (3.17 a 10 )
- D/Q
- td*Fo IRipt a
- Oiv Note: It is assumed R ipta will not contain long term X/O or D/O values.
6.8.3.2 On the Nuclide Concentration Screen (Screen 4.15), nuclide concentrations will be " scaled" if the SCAL _NUC parameter is set property for a Release Point. This "scaing" is described as follows: Cinew = (t / s) + C; it: where 3 Cinew = concentration (after"scaNng") of nucEdei s = sum of all nuclide concentrations on the Nuclide Concentration Screen, t = total nuclide concentration entered by the user C; = concentration (before 'scaing") of nucEde; y l
Software Requirements Specificatl2n RS-8448-04 6.9 Gaseous Permit Editing 6.9.1 User Interface and Functionality , 9 Functionality for editing gaseous permits through the EMS software shall be described in section 4 of the EMS Operator's Manual (Reference 2.1.1), with the following revisions: The appearance and functionality of the gaseous permit definition screen, the monitor response screen, and nuclide concentration sitall be modified as described for the Pre- and Post-Release stages in sections 6.7.1 and 6.8.1 above. 6.9.2 Associated Reports The permit report format and contents for edited open and closed gaseous permits shall be as specified above for original permit reports, in sections 6.7.2 and 6.8.2, respectively. 6.9.3 Underlying Calculations The calculation methods for editing open and closed gaseous permits shall be specified for original calculations, in sections 6.7.3 and 6.8.3, respectively. 6.10 Gaseous Permit Deletion Functionality for deleting gaseous permits through the EMS software shall be described section 4 or the EMS operator's M.anual (Reference 2.1.1).
I ) Software Requirements Specification RS-8448-04 O 6.11 Semi-Annual Reporting 6.11.1 User interface and Functionality Semi-Annual Reporting functionality for the EMS software shall be as described in section 5 of the EMS Opomtor's Manual (Reference 2.1.1), with the following revisions: 6.11.1.1 On Report 5.01 (Gaseous Summation of All Releases):
+
Compute each value on line A.3 of the report by taking 9"" 100 D /Q where D ag = the gamma air dose in the applicable quarter at the site boundary receptor due to noble gas emissions (mrom) D ab = the beta air dose in the applicable quarter at the site boundary due to noble gaa emissions (mrom) QLar. a the quarterly limit on Dag (mrom)[usually 5] OLab = the quarterly limit on Dab (mrom)[usually 10] A note will be made at the bottom of the report stating whether the beta air dose and its associated limit or gamma air dose and its associated limit were used for the Percent of Applicable Limit of Fission and Acthration Products..
+
The values on lines B.3, C.3, and D.3 will be the equivalent. They will be e=Ma'm1 as follows: 5 the greatest (overD of 100 + (I D i,T) / QLrp O Software Requir:ments Specificatl*n RS-8448-04 where Di ,T = the dose to organ T of the controllirig receptor, in the applicable quarter, due to gaseous emissions of radionucEde I(mrom) The summation is over all non-noble gas radionuclides with half-lives greater than 8 days, including radioiodines, particulates and tritium. OLrp = the quarterly limit on the controlling receptor organ dose due to gaseous effluents (mrum) [ususily 7.5] 6.11.1.2 On Report 5.02 (Uquid Summation of All Releases): a , For each quarter q in the report, calculate the reportable dilution volume ' (DVrg, in liters) for the portion of the quarter that is within the report 4 dates, it is the sum of the reportable monthly dilution volumes (DVg) in user units for all the months in the quarter that are within the report dates: DVrq = 28.31685 sd_lvolf I DVrm
'The values DVrm are from the column tvol of the ODVOL table. The value DV rq is included in the report on line F, and is used in the calculations below.' *sd_lvolf" should be the user unit conversion factor to convert from user units to ~ft3 . 28.31685 is a unit conversion factor from ft3to liters.
For each space on a line titled " AVERAGE DILUTED CONCENTRATION 1 DURING PERIOD", the average concentration (Cq, in pCl/ml) for the respective quarter is computed as follows (where i ranges over only the nucDdes in the category): l Cq= I C;q = I [Actq / (1000
- DV,q)]
1 where Actiq = total activity of nuclide i released during the portion of the quarter q that is within the period (pCI)
- DVrq = reportable dilution flow for the portion of quarter q that is within the report period (Eters), as calculated above.
Compute each value on line A.3 and B.3 of the report by taking the greater of Dit/ OLit 100
- D;o / QL;o 1
7 Software Requirements Specificati n RS-8448-04
- o f
I, Da
=
the liquid total body dose in the applicable quarter at the site boundary receptor (mrom)
= the liquid maximum organ dose in the applicable quarter at Dio i the site boundary (mrom) i
{ OLg = the quarterly limit on D g(mrem) [usually 1.5] OLin = the quarterty Emit on Dio (mrem)[usually 5) i 1 A note will be made at the bottom of the report stating whether the liquid total body dose and its associated Nmit or maximum organ dose and its d associated Smit were used for the Percent of Applicable Limit. Compute each value on Ene C.3 of the report as follows: Pq= 100 Cq/ L dg where } Cq = sum of noble gas concentrations Pq = Percentage appHcable to a given quarter for dissolved and ! entrained gases Ldg = Liquid dissolved gas limit (pCl/ml) [usually 2.0E-04) 6.11.2 EMS Trond Plots i Trend Plotting functionality for the EMS software shall be described in section 5 of j the EMS Operators Manual (Reference 2.1.1) with no revisions. l -I 1 6.12 End-of-the-Year Data Archiving l N 6.13,8;JJoer interface and Functionality
.g n
{ [End-of-the-Year Data Archiving functionality for the EMS software shall be
- described in section 6 of the EMS Operators Manual (Reference 2.1.1) with no revisions.
l Documentation Review Report Document Reviewed hkS $EA3/toeK. YAT)eA) $N$ k]-$hh$~0h Does the document meet the requirements or No is the document approved? or No if not pleasr, state the exceptions: 1 O Signature: 6fW Date: /I"Y3 3 34 m,n O
1, lj a 1 5 I 1 , l J
,R .
Documentation Review Report 1 Document Reviewed 6E3 [ O - N N
- O'I Ser a off 6 e ft.J i -
Does the document most the requirementsdecor No l 18 the document appnpved?h or No a
- u not please simie the emopsons
i < 1 e 4 } i ) 3 4 ? i I
- i i
- l
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- s. y.. +
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- i f
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I
@Amo_ MM , , u-i
_ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ . . _ . . . . . . _ . . _ . _ . _ _ _ _ _ _ _ . _ _ . _ _ _ _ . . . _ _ . _ _ _ ______.__m ___.__.__________._s .s s 4 APPENDIX C: EMS SOFNARE DOCUMENTATION a 5 1 1 t ; i ' 4 1 4 t 4 I 4 1 \ b i I ATTACHMENT 4: TECHNICAL REFERENCE MANUAL, EFFLUENT MANAGEMENT SYSTEM l SOUTHERN NUCLEAR OPERATING COMPANY. JANUARY 1993, FP 75486 I i 1 l l l 4
.9. ,
C-6 ODCM Rer, 16
\ -
- 3 i
n 4 j . i Canberra Nuclear t Nuclear Data Systems Division i 150 Spring Lake Drive s , Itasca, Illinois 60143-2096 4 = 1 i 7
- January 1993 l
l l 1 4 t 1 1 1 J i Southern Nuclear i Operating Company ] Effluent Management System ' , Technical Reference Manual
- 07-0545-02 ..
3 i i 4 i 1 i Copyright C 1993, Canberra Industries Inc. Printed in U.S.A.
. ..-- f
i O TABLE OF CONTENTS Page . a CHAPTER 1 INTRODUCTION .............'............................ 1-1 4 ,--
~,
1.1 SETPOINT CALCULATIONS .................................. 1-2 1.2 RELEASE PROCESSING ..................................... 1-3 1.3 COMPOSITE NUCLIDES ..................................... 1-3 CHAPTER 2 LIQUID RELEASE CALCULATIONS .......................... 2-1 , 2.1 LIQUID PRE-RELEASE PERMIT .............................. 2-1 2.2 10CFR20 COMPLIANCE ..................................... 2-1 Dissolved and Entrained Gases ...................... 2-4 2.3 MAXIMUM WASTE FLOW ..................................... 2-4 2.4 MINIMUM DILUTION FLOW RATE ............................. 2-5 2.5 SETPOINT CALCULATIONS .................................. 2-5 ; Recommended Setpoint ............................... 2-8 Setpoint in pCi/ml ................................. 2-8 Reconnended Setpoint in User Units (e.g. cpm) ..... 2-10 Setpoint for Discharge Point ...................... 2-11 2.6 DOSE CALCULATIONS FOR LIQUID RELEASES ................. 2-12 2.7 31 DAY PROJECTED DOSE CALCULATIONS . . . . . . . . . . . . . . . . . . . . . 2-14 ! 2.8 POST-RELEASE PROCESSING ............................... 2-14 l CHAPTER 3 GASEOUS RELEASE CALCULATIONS ......................... 3-1 3.1 GAS PRE-RELEASE PEPMIT ................................. 3-1 '
?3.2 RADIONUCLIDE ACTIVITIE3 AND COMPOSITE VALUES ........... 3-1 Activity ReleVsed .................................. 3-2 l 3.3 10CFR20 COMPLIANCE ..................................... 3-2 l 3.3a COMPLIANCE WITH OLD 10CFR20 ............................ 3-3
- 3.3b COMPLIANCE WITH NEW 10CFR20 ............................ 3-5 ,
.Y3.4 SETPOINT DETERMINATION FROM NEW/OLD 10CFR2 0 . . . . . . . . . . . . 3-6 l J3.4a NEW 10CFR2O NRATIO .................................... 3-6 3.4b OLD 10CFR20 NRATIO .................................... 3-11 Noble Gases ....................................... 3-11 Radiciodines and Particulates . . . . . . . . . . . . . . . . . . . . . 3-11 3.4c SETPOINTS ............................................. 3-12 3.4d REPORTED SETPOINTS .................................... 3-15 3.5 MAXIMUM WASTE FLOW .................................... 3-16 3.6 DOSE RATE AND CUMULATIVE DOSE CALCULATIONS ............ 3-17 Noble Gas Total Body Dose Rate Calculations ....... 3-17 Noble Gas Dose Calculations ....................... 3-18 Organ Dose Calculations ........................... 3-20 3.7 RESOLVING DOUBLE-COUNTING OF DOSE AND ACTIVITY. . . . . . . . . 2-21 3.8 31 DAY PROJECTED DOSE CALCULATIONS..................... 3-22 3.9 GAS POST-RELEASE PROCESSING ........................... 3-22 fy37
a I g CHAPTER 4 LIQUID DOSE FACTOR EQUATIONS ......................... 4-1 4.1 POTABLE WATER .......................................... 4-2 4.2 AQUATIC FOODS PATHWAYS ................................. 4-2 4.3 SHORELINE RECREATION PATHWAY ........................... 4-3 4.4 IRRIGATED VEGETABLE PATHWAY ............................ 4-4 4.5 REDUCTION TO NUREG-0133 EQUATIONS .. ... ................ 4-5 . CHAPTER 5 GAS DOSE FACTOR CALCULATIONS ......................... 5-1
. 5.1 INHALATION PATHWAY ..................................... 5-1
~-
-- 5.2 GROUND PLANE PATHWAY ................................... 5-2 ,
5.3 HI LK P ATHWAY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 l Carbon-14 in Milk .................................. 5-4 Tritium in Milk .................................... 5-4 5.4 HEAT PATHWAY ........................................... 5-5 Carbon-14 in Meat ......................~............ 5-5 Tritium in Heat .................................... 5-6 l 5.5 VEGETABLE PATHWAY'...................................... 5-6 Carbon-14 in Vegetables ............................ 5-7 Tritium in Vegetables .............................. 5-7 5.6 REDUCTION TO NUREG-0133 EQUATIONS .......... ............ 5-7 I APPENDIX A REFERENCES .......................................... A-1 (' i . i
\
.h .
o y* e (~ . - 3g 11
i i e CHAPTER 1 INTRODUCTION The Effluent Management System (EMS ) Software implements the . requirements for determining limits ,and doses for the routine liquid and gaseous releases from nuclear power plants. The calculations
,. and methodology are based on those described in U. S. Nuclear 2 Regulatory Commission Regulatory Guide 1.109 and references described taerein. These equations reduce to those described in NUREG-0133 by proper selection of parameters.
This manual describes the calculations used in the LRW/GRN program for handling liquid and gaseous releases anc. preparing the semi- l annual report, and the equations used in the DFP option for ' calculating- the relevant dose f actors. This manual describes the new 10CFR20 (1992) as well as old 10CFR20 requirements. - For a nuclear power plant, the Off-Site Dose Calculation Manual (ODCM) describes the methods used at that plant for complying with O
- the effluent release portions of the technical specifications and the requirements of 10CFR20 and Appendix I of 10CFR50.
The concentration and dose limits that are required to be met are: - o For radioactive liquid effluents, the concentrations released to areas beyond the site boundary are limited to:
.s .
MPC values given in old 10CFR20, Appendix B, Table 11. OR ECL values given in new 10CFR20, Appendix B, Table 2. [. where ECL values are effluent concentration limit values. o, For radioactive liquid effluents, the maximum dose to any member of the public will be less than the limits given in 10CFR50, Appendix I. o For gaseous effluents, the old 10CFR20 requires that the dose rate at any location beyond the site boundary will be limited to the annual dose limits given in the Technical Specifications and corresponding to the concentrations in Appendix B of the old 10CFR20, while the new 10CFR20 requirement is that the diluted concentration at the site O boundary be less than the ECL values given in the new 10CFR20, Appendix B, Table 2, 1-1 9
o for gaseous effluents, the maximum dose to any member of the public will be less than the limits given in 10CFR50, Appendix I. o The maximum dose to any member of the public will not exceed the limits given in 40CFR190. , . The equations employed for calculating the dose and dose factors are taken from NUREG-0133 1 and Regulatory Guide 1.109.2
~~
For a particular nuclear plant, the ODCM describes the physical configuration of release sources and release points-for routine and non-routine liquid and gaseous effluents, the monitor setpoint calculations, dose, and dose rate calculations. - l l 1.1 SETPOINT CALCULATIONS I l 1 I Calculations are made for the radiation monitors to determine the alarm / trip setpoint so that 10CFR20 compliance is met. For the old 10CFR20 compliance, liquid calculations use the maximum permissible ; concentrations from 10CFR20 App. B, Table 2, column 2, and the more conservative value (smaller) of the soluble and insoluble values while gas calculations use dose rate equations and limits from NUREG-0133. To comply with the new 10CFR20 requirements, the
~ effluent concentration limits are used for both liquid and gaseous calculations.
In the terminology of EMS,' individual sources of radiation, such as storage tanks, the containment building, etc., are defined as
" release points." Several release points may lead to the same
.'" discharge point."
'Setpoint calculations produce monitor limiting values in activity units (FCi/ml or pCi/cc) . These are then converted to user units, e.g. counts per minute (cpm).
EMS allows setpoints to be set for both the release points and the discharge points. In the case that the release point and the discharge point are the same, or use the same physical monitor, the same discharge setpoint value is reported for both. This use of the same discharge setpoint value can be disabled. EMS has a "nuclide specific" option. In this option only the nuclides listed in the monitor slope table are used in the setpoint
. calculations.
b2 q
s I 1.2 RELEASE PROCESSING For batch releases, the processing of releases consists of sampling 4 the tank or volume of air, analyzing the radionuclide content, then . using the radionuclide concentrations and estimated release flows, i volumes, etc. and calculating the d'oses and setpoints, comparing to j ,, the 10CFR20 limits, and comparing to the 10CFR50 limits. If the
~
j limits are not exceeded, the pre-release permit is signed off and j ! the release can occur. After the release, post-release processing performs the same calculations (except the setpoints are not needed) .! and the database is updated with the actual values for the release.
- For continuous releases, many installations prefer not to generate an actual pre-release permit, but for the sake of analogous ;
operation', pre-release calculations must still be made in EMS. After review, the post-release calculations are made to update the database. l EMS does not allow more that one open release at a time for a single release point. However, multiple re. leases may be open for one ] discharge point. Also, for discharge points, the setpoint is ~ O calculated by summing over all open releases f or the time period involved.
, 1.3 COMPOSITE NUCLIDES ,
' 'Ihe standard radionuclide ' analysis, with high-resolution germanium detectors, quantifies the gamma-emitting radionuclides. Pure beta
, emitters, nuclides that decay by K-capture, and alpi.a emitters are
- handled with other detection mechanisms. These are usually not
,l'. . tracked individually by sample, but as a composite of many samples Jover a month or quarter period. The concentrations of the composite nuclides are combined with the concentrations of the individual nuclides determined from gama analysis for each sample.
For liquid releases, the composite nuclides are generally H-3, Fe-55, Sr-89, Sr-90, and gross alpha. For gaseous releases, Fe-55 is generally not included. In EMS, these are contained in an editable file designated by the composite ID number. Each release point definition specifies which composite ID is used with the release point. These can be the composite nuclides, or any other nuclides desis.ed. U .<** 1-3
Composite samples produced by taking portions of the samples from individual releases are analyzed after the releases are over. Since these generally do not vary much from one period to the nert, it is common to use the most recent values. However, EMS provides the option of updating the composite values for the proper time period and recalculating the activity and dose values in the database. For the setting of flags to control; options in the EMS code, see the EMS Operator's Manual. L-O O e 4 1-4
a
~- / CHAPTER 2 LIQUID RELEASE CALCULATIONS !
l l 2 2.1 LIQUID PRE-RELEASE PERMIT A liquid pre-release permit is generated with a program that uses the nuclide activities to determine the radiation monitor setpoint 3 (for 10CFR20 compliance) and the potential doses for 10CFR50 compliance.
- Continuous releases are treated similarly.
4 O
, 2.2 10CFR20 COMPLIANCE 2
10CFR20 compliance calculations are broken down into two paths. The ! l ) ..first path calculates compliance with the old 10CFR20 i'n which the 3, calculations are based on Maximum Permissible Concentrations. The
- second path complies with the new 10CFR20 and is Effluent Concentration Limits based.
510CFR20 requires that the sum of concentrations divided by MPC
I (old i
. 10CFR20) or ECL (new 10CFR20) values must not exceed unity:
OLD 10CFR20 1 NEW 10CFR20 S=I g Cg /MPC s1 S=I g Cg /ECL g s1
- OF.
for concentrations Cg released from the site. MPCi is the maximum permissible concentration f rom the old 10CFR20, Appendix B, Table II, Column 2, for nuclide i and ECL i is the effluent concentration limit from the new 10CFR20, Appendix B, Table 2, Column 2, for nuclide 1.
,_, 3
If the summation is greater than unity, dilution is required. The i required dilution f actor is: i If the 10CFR20 option is OLD: C i I, i i D = ,, req f *R
.. max where D req = Total required dilution factor l
Ci = Concentration of nuclide i in pCi/mL MPC{ = Maximum permissible concentration of nuclide i in pC1/mL f = Release point setpoint safety factor (usually equal to 0.5) from the release point definition. Pmx = The marimum MPC ratio from the release point setpoint , definition, j If the 10CTR20 option is NEW: C - 1
. I -
- ECL 1.g i D =
req,g f*R C
,',. 3 i=ng i
ECL i
- f. p , j req,ng i*R D = D req req,g + Dreq,ng where D req,g a Required dilution f actor for gamma-emitters D reg,ng = Required dilution factor for non-gamma-emitters ECL i = Effluent concentration limit of nuclide i in pCi/mL qL h
l I i e and the sums extend over gamma-emitters (g) and non-gamma-emitters (ng), respectively. Any nuclides with MPCis 0 are ercluded from the sum. Any nuclides with ECL i s 0 are ercluded from the sum. l L l
- The available dilution flow is the minimum dilution stream, flow that can be ensured for the period of t'he release, corrected for other
,, releases in process and any activity in the dilution stream, and
- "J reduced by a safety factur.
i 3 F,V,iy =F ant f
~
i i I I i where C1- = Concentration (FCi/ml) for nuclide i for the dilution
- stream sample XXXi= MPCi or ECLi ff = Flow safety factor, in percent F ant = Anticipated dilution flow rate for the release The anticipated dilution factor is then .
D = {F waste +f 3 1 ant alloc Favail)/Fwaste l where i J waste = waste, flow anticipated for this release
*,- F i .>:
I F = available dilution flow 4 avail 4 i l f d& = fra tion of available dilution stream flow allocated to this release O i y5 L
)
Dissolved and Entrained Gases To implement '9CFR20, it is also required that the total concentration of dissolved and entrained gases in liquid effluents be less than a specified value (normally, 2 E-04 pCi/mL under OLD 10CTR20, or 1 E-04 pCi/mL under NEW 10CFR20). EMS stores this limit , in the Activity Limits transaction, checks this limit for each liquid permit, and indicates on the permit approval screen whether or not it is exceeded. To include dissolved noble gases in the D reg
-- calculation, the database must also contain the same limiting value, as the liquid MPC or ECL for each gas.
2.3 MAXIMUM WASTE FLOW . The maximum waste flow calculation is based on the setting of the SET _ OPT option in the WFLOW M class of options in the Release Point Setpoint definition. This option can take on four values: NONE, NO_ WASTE, CALC or DOSE. For liquid releases, NONE, NO_ WASTE, and CALC are allowed. For liquid releases, Wmax = the =4n4="= of Pm and R ewmax Wmax = Maximum permissible waste flow rate for this release Rwmax = Release point maximum waste flow rate, as set in the release point definition If the SET _ OPT option = NONE: R cwmax = waste flow rate for the sample, Fwaste If the required dilution f actor, Dreq - (section 2.2) for the sample is greater than 1, Rewmax becomes: Favail
- falloc Rcwmax "
D req - 1.0 If the SET _ OPT option = CALC Fay,41
- falloc + Fwaste Rcwmax "
D reg
..-+--
2-4 h ___________a
If the SET _ OPT option = NO_ WASTE F,y,11 = falloc Rcwma:. " D req
- 2.4 MINIMUM DILUTION FLOW RATE If D req > 1, .the minimum dilution flow rate is determined as follows:
If the SET _ OPT option is NO_ WASTE: Fwaste
- D req min _dflow =
C' falloc * (ff / 100) * [l-{ ] i where XXXg is MPCi under OLD 10CFR20, and is ECLi under NEW 10CFR20. lO . If the SET _ OPT option is other than NO_ WASTE: Twaste * (D req - 1. 0) min _dflow = falloc
- Iff / 100) *
[l-If )
. XXX g
.,Otherwise :
, min _dflow = 0.0 2.5 SETPOINT CALCULATIONS Setpoints are calculated for individual release points, and for the discharge point that may combine several release points.
A setpoint adjustment factor, Sadj is determined from the value of D req-O -.-.-. W] l l 1
If Dreq > 1 or the di.lution factor option is N, and the setpoint equation is set to STD: Sadj = Dant /D req If the dilution factor option is Y, no credit is taken for dilution (setpoint equation is set.to NO_DILUT), and the setpoint adjustment factor is: E- Sadj = 1/Dreq . If neither of these conditions is true, Sadj = 0. After the above tests, further tests are made based on the setting of the setpoint equation option, SETP_EQN. These may change Sadj as follows: If'the SETP_ EON is set to STD, and the SET _ OPT option is set to NO_ WASTE, and Fwaste > 0, then: falloc
- F ,ygiy S adj "
Fwaste
- D req Otherwise, if the SETP_EQN option is set to STD, and the SET _ OPT option is set to other than NO_ WASTE, and Fwaste > 0, then: l l
(falloc
- Favail) +F waste S
adj " Fwaste *D req Otherwise, if the SETP_EQN option is set to LOW ACT, and the SET _ OPT option is set to NO_ WASTE, and Fwaste > 0, then: I (falloc
- Favail)
-D reg,ng S I adj "
D reg,g l
.-2" *
~ pp g !
l
_. - - . - - - . - . _ . - - _ - . - . _ . _ ~ _ _ - - . . . - . _ . . - . . - - . . - . - . . . - j . 1 s i e 1 \ - 4 Otherwise, if the SETP_EQN option is set to LOW ACT, and the SET _ OPT _ l option is set to other than NO_ WASTE, and Fwaste > 0, than: j
; (falloc
- ravail) +F waste j ~D req,ng -
i F waste e S adj " D req,g j Otherwise, S adj is unchanged. I The setpoint adjustment factor is further tested against a limiting ) value (Sadj lim which is set using the Release Point transaction in 4 Database Maintenance). 4 If Sadj > 3adj,11x th*" 3adj " Sadj,lia - e i All of this leads to the maximum setpoint value, S,,x, based on the j gamma-emitting 'radionuclide mix: I i S (pci/ml) =S max adj.I Ci f where the sum extends over all gamma-emitting nuclides (nuclides of 3 1 type other than O) in which their concentrations are greater than O.
- .In user units (cpm or other as set in the N1ow Monitor Parameters i
transaction in Database Maintenance), the maximum setpoint is: I
?. (cpm) =S -
adj (R'mon - B) +B S 3 max ll where ] _,3 ' . B = monitor background (cpm) R,,, = monitor response (cpm)
- offset + slope
- I Ct + quad * (I C t)2 + 3 where offset, slope, and quad are the coefficients in a quadratic fit to the monitor response to nuclide activity.
4 4 !O .. i i
\9 a
EMS provides an option to calculate nuclide specific responses so that Rmon is the sum of responses for each nuclide, rather than the sum of the nuclide concentrations, as shown above. In the nuclide-specific case, R =I [ offset + slope
- Cy + quadg * (C ) ] +B where the sum ertends over all nuclides which have response factors
}~. stored in the database for the monitor of interest. Recommended Setnoint The setpoint recommended for actual use is based on a comparison of the setpoint calculated as above and default values determined by the user. The default setpoint in user units (e.g. cpm) can be defined with or without background included. If the cunitnopt parameter (defined in the release point and discharge point tables) equals 0, the default value does not include background; and the current background is added to the def ault value. Otherwise, the current background is not added to the default value. Setooint in uCi/ml A candidate setpoint is calculated based on the erpected response S =f IC erp tol i . where
/, f g y = setpoint tolerance f actor (can be set f or the d' release point using QBF)
= 2 if not specified by the user Now compare the S,xp value to the def ault table value Sdef:
1 l
-+
,., p go 9
4 J i d
' If Sexp < S max 1
j and if 1 'I S <S .and 5 sS exp def def max ,
- then use S def Case 1 .
1 I
".~. Otherwise use S Case 2,5 .! exP.
4 If S,xp 1S m use S m. Case 3 ) 1 If S m = 0, use S def Case 4 .
- 1 a
Case 4 occurs if no , activity is detectable in the sample (Sadj = 0). i i Case 1 Case 2 Case 3 Case'4 Case 5 s S,,p- - Sde f ~~ i !+ Sm ---- S ---- Sm ---- Sm --- I S ,p - - S.,p---
- ( l
., 3def~~~ 3def" - 3def~~~~ 3de f ~~
. 1 1 .
3 . S .,p--- J
. O o --- o ._ o --- 0 --
i Use S def Use S,,p Use Sm Use Sdef Use S,,p Schematic of Liquid Setpoints (FCi/ml) l ( 2-9 _pp. 5
O Recommended Setroint in User Units (e.a. epm) The candidate setpoint based on expected monitor response is , calculated as follows: '5 S (cpm) = f * (R - B) +f Btol where fatol = background tolerance factor (set using QBF on the releasept table) If the def ault setpoint value includes background: B rp =0 If the default setpoint value does not include background: B rp =B where B is the monitor background count rate and Brp is used below. If Sexp (cpm) <S ma:: (CP")
- and if -
S exp (cpm) <Sdef (cpm) +B rp and l (cpm) def (CPS) +B rp s Sm !
, S j i
then use Sdef (cpm) +B rp Case 1 Case 2, 5 Otherwise, use S,xp (cpm) If S exp (cpm) >S m (epm) use S max (cpm) Case 3 I I 2-10 I
1 l l If S . (cpm) =0, use S def +B rp Case 4 i NOTE: S ax is due to concentration only (i.e., excludes background) for Case 4 .
~E Setooint for Discharae Point For the discharge point, the total MPC/ECL fraction is:
( I C /MPC ) *F + ( I C /MPC ) *F F +F l o OR ( I C g/ECLg) *F + ( Z C g/ECLg) *F F +F o where (I Ci /MPCi )o= total MPC fraction for existing concurrent , releases for this discharge point excluding this additional release. I C i/MPCi= total.MPC fraction for the new release (I C1/ECLi )o= total ECL f raction f or existing concurrent
., releases for this discharge point excluding
, this additional release.
I Cg/ECLi= total ECL fraction for the new release To= discharge point waste flow excluding new the release point waste flow to be added. l l F= projected waste flow for the new release point to be ad.ied i i O 2-11
l The radiation monitor for the discharge point has setpoint equations identical to those presented above, except for the nuclide-specific response. For the nuclide-specific response, the concentrations are modified as in: CfE=Cg (F/(F + F )] R = [I (offsetg+ slope
- C P + quad * (Cdp)2 ] +R dpmen where CpP = the discharge point isotope concentration from this release point R dpmon = the discharge monitor response in user units R
dpmono= the discharge monitor response before the current release is added including the background For non-isotope specific response: R dpmon d + quad *
= [ offset + slope
- C P (Cd p)2 ) ,Rdpmon g where cdp = [ I C i] [F/ (F+F o) )
J.6 DOSE CALCULATIONS FOR LIQUID RELEASES ~*The EMS software calculates and stores the dose for each receptor, for each nuclide, and for each organ. The dose is the total over
.all pathways which apply to that receptor. A receptor is defined by
,(receptor ID, age group (infant, child, teen, or adult), sector, and ,J : distance from the plant. The equation used in the liquid permit processing to calculate the dose received by receptor r from a released nuclide i is: D =A I At C F iTr iTr s is sr where: l DiTr = the cumulative dose or dose commitment to the total body or an organ T by nuclide i for receptor r from the liquid effluents for the total time period of the release, in mrem. ! l
. :E" 2-12 gg ;
1 1
i l t Alfr = site-related ingestion dose or dose commitment factor for receptor r to the total body or organ 7 for radionuclide i, in mrem /hr per pCi/ml. At s = length of time period s, over which the concentration and F value are averaged, for all liquid releases, in . hours. , Cis = the average concentration of radionuclide i in undiluted liquid effluent during, time period At, from any liquid release, in pCi/ml. T sr = the near field average dilution factor for receptor r
, during any liquid effluent release.
If the denom_typ option from the Options Table is 1, then: F sr = F,
- Raix otherwise, if denom_typ is 2, then:
F-o otherwise: r sr mir
'. F sr " F +F mix
.' F, = flow rate of undiluted waste effluent Fdil = flow rate of the dilution flow
? #
,4 Raix = mixing ratio = fraction of the release that reaches.
the receptor. Separate mixing ratios are stored for each pathway for each receptor. A mixing ratio of zero for a pathway receptor indicates that the pathway is not present for the receptor. The first non-zero value is used in the dose calculation. The different mixing ratios for the pathways are incorporated into the composite At factors calculated by the dose factor processing (DFP) program. Also, the sum extends over all time periods s. 2-13 _ bunn r u-
Alfr is available as an editable table, but can be recalculated m1.th different parameters and pathways with the Dose Factor Procs .1g (DFP) option. The equations used are presented in Chapter 4 of a's manual. 2.7 31 DAY PROJECTED DOSE CALCULATIONS
.- The 31 Day Projected Dose values appear on the Standard and Special # Permit Reports. The Projected Dose values are calculated as follows:
D pg = (D 7
- p) +D at where:
D py '=the 31 Day Projected Dose by organ T DT = sum of all open release points in mrem / day by organ T when an answer of "Y" is specified for the " Update , Totals" field on the release point definition screen. f p =the Projection Factor which is the result of 31 divided by the number of days from start of the quarter to the l
' end of the release.
D at = Additional Anticipated Dose for liquid releases by organ - 7 and quarter of release. NOTE: The 31 day dose projections on the Approval /Results screen f include additional
- d'oses -for all units. l l
)
l 2.8 POST-RELEASE PROCESSING l
.After the release is made, actual concentrations are used to check 10CFR20 limits, and the actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.
For batch releases, the duration is determined from the start and end dates and times, and is used with the volume input to calculate the release rate. Dose calculations are the same as for the pre-release, but with actual release flow rates and rel' ease duration. Setpoint calculations are not performed at the post-release stage. 2-14 h j
G
*. ~ .
CHAPTER 3 GASEOUS RELEASE CALCULATIONS The " annual average X/Q" method is used, in which fixed X/Q and D/Q values are used for each receptor for all dose calculations, regardless of actual wind direction and speed prevailing during a given release. Doses are calculated for each receptor location and age group specified in the Gas Receptors transaction. The controlling individual is the age group and location which receives the maximum organ dose. 3.1 GAS PRE-RELEASE PERMIT
. The pre-release permit.is produced by a program that uses user-entered estimates of flow rates and release times to calculate doses and activities. The dose rate from the potential release is added
, .to the
==v4 ="= dose rate occurring f or all other releases during the J, duration of this release for "old" 10CFR20 compliance. The noble
<> {. g a s or air doses and the organ doses are checked against the corresponding limits for 10CFR50 compliance.
3.2 RADIONUCLIDE ACTIVITIES AND COMPOSITE VALUES The radionuclide results are read from one set of composite activity database records, and from three spectrum analysis result files, and saved in an activity array. If a nuclide appears in more than one spectrum, only the last value read for that nuclide is used. In case of duplication, the one not desired should be edited out of the nuclide list. The samples are read in the following order: 3-1
- 1. Composite Records ;
- 2. Particulate File
- 3. Radiciodine File
- 4. Noble Gas File The activity (01 ) and the activity release rate (Q t) are calculated for each nuclide i.
- -- ~ .
Activity Released For the plant stack and turbine building vent: Og = Ci *Vf
- duration of release (min)
- 28316.85
- U p l l
(pCi) =(pci/ml) (cubic feet / min) (min) (ml/ cubic feet) 1 where: vf = vent flow rate in user units (usually CFM) C t = concentration in FCi/ml Up = the flow-rate units conversion factor which converts from user units to CFM
'The activity release rate in #Ci/sec is 01=Ci *V f a 28316. 85
- Up/ 60 i
For containment purge: 28316.85
- Uy/60 Qi=Ci
- pump release rate (CFM)
- i t-Og=hg a duration of release (min)
- 60 3.3 10CFR20 COMPLIANCE The maximum dose rate during the release is determined by summing together the dose rates for this release, with all concurrent releases in the database for the time of the release.
The database contains all releases for which both pre- gad post-release reports have been made (the post-release program enters the data into the cumulative totals) . Pre-releases that have not been completed, and which occur during the release under consideration, .
J d 4
~
4
- s -
are also added into the maximum dose rate to account for releaser l not yet added to the cumulative totals. 3 j q 3.3a COMPLIANCE WITH OLD 10CFR20 . j The three dose rates (whole body, 's kin , organ) are compared to the j , , , old ;OCTR20 limits (old and new 10CFR20 are described below) as ; a l defined in the Dose Limits transaction in Database Maintenance. The sose rate at or beyond the site boundary due to gaseous t effluents from the site is limited to: '. (a) Release rate limit for noble gases: d 1 j IKi i shf Iv [ (X/Q)vr Qiv) < 500 mrem /yr a f *f alloc s 3 OR I shf I 4 v (vir Qiv] < 500 mrem /yr a f *f alloc s } Elevated Stack a 80m 1 i 3 Ei shf (L + 1.1M i) I v ( (X/Q)vr h)iv< 3000 mrem /yr
- f alloc s
*f i
- .$ . OR i .
i
. Zy shf I g[(Lg (X/Q { + 1.1Bh) Oh] < 3000 mrem /yr a f *f, g
l :
' Elevated Stack a 80m j .>.
1 where the terms are defined below, i ~, (b) Release rate limit for all radionuclides and radioactiv? materials in particulate form, with ha.lf lives greater than i days:
- Ii Ip Iv [fp Pip mvW h ).< 1500 mrem /yr
- f alloc*fs i
where.
~
, ss
.3
l 4 i= index over all radienuclides O' v= index over all vents or stacks for the unit p= index over all pathways . r= index for receptor loc'ations 5- Ki= the total body dose factor due to gamma emissions for noble gas radionuclide i, in mrem /yr per pCi/m 3, Li= the skin dose factor due to beta emissions for noble gas radionuclide i, in mrem /yr per pCi/m 3. vir - the elevated plume gamma total body dose factor for nuclide i at receptor location r, in mrem /yr per pCi/sec. Mi= the air dose factor due to gamma emissions for noble gas radionuclide 1, in mrad /yr per pCi/m 3. Bir = the elevated plume gamma skin dose factor for nuclide i at receptor location r, in mead /yr per pCi/sec. 1.1 = mrad to mrem conversion factor in mrem / mrad Pgp = the dose factor for the critical organ for nuclides other than noble gases for the inhalation pathway (in units of mrem /yr per pCi/m3 ) and for ground plane and food pathways (in units of m2 (mrem /yr per pCi/sec)) . The most restrictive age group is used. l
* =
. fp factor to select which pathways are included in the
- h, calculation. Factor = 1 t'o include a pathway, O to exclude.
W ,y = (M) ,, for tritium and the inhalation pathway and = (D/Q) ,y for other nuclides and pathways. I 1 (X/Q)ve = the highest value of the annual average atmospheric dispersion factor at the site boundary, for all sectors, in sec/93 (X/Q)mv = the highest value of the annual average atmospheric dispsrsion factor at the distance of the site beandary, for aJ1 sectors, in sec/m 3, 3-4 y
._ 1
1 \ (D/Q)mv = the highest value of the annual average deposition factor at the distance of the site boundary, for all l sectors, in m-2 Qiy = the average releasei rate of nuclide i in gaseous
"~
effluent from release point v, in pCi/sec. Noble
.- gases may be averaged over a period of 1 hour, and any other nuclides may be averaged over a period of 1 week.
500 = site dose rate limit for whole body in mrom/ year. 3000 = site dose rate limit for skin in mrem / year 1500 = site dose rate limit for any organ in mrem / year shf = noble gas dose shielding factor fa gine= fraction of the dose limit allocated to this release -
- g. point f, = safety factor for the ' release point -
-3.3b COMPLIANCE WITH NEW 10CFR20
..-T h e diluted site boundary ECL ratio is compared to the limiting
.,value permitted by Tech Spec:
k[,
-4 - -
Ciy - = 4.72
- 10 ,f* (X/Q) v , , ,
- limit, for gansna-emitters rp_utocl_ng = undiluted total fraction of the effluent limit, for non-ganna-emitters Pm= the maximum MPC ratio from the release point setpoint definition ECL4= effluent concentration limit of nuclide i in pCi/mL and the sums extend over gamma-emittert (g) and non-gamma-emitters (ng), respectively.
. r.. . Onm o 3-7 A
(X/Q) , is the noble gas X/Q for the distance which matches the site boundary OI distance, in sec/m3 The table used (ground-level, mixed-mode, er elevated) is specified in the release point . definition. rp_wflow is the effluent flow rate for the ' 4- release point, in CFM l units is the units conversion factor i units = (1 m3 /35.31 ft3) . (1 min /60 sec) = 4.72 E-04 The total fraction of effluent concentration limit for the sampled mix of isotopes for the specified discharge point is given by: dp_teci = units - (X/Q) , dp_wflow
- dp_utsel l
l dp_utecl_g l dp_tecl_lo = ' fs
- f alloc '
units - (X/Q)y dp_wflow where: dp_tecl_hi i s ,t,h e diluted total fraction of the l effluent concentration limit for the ' discharge point, at the site boundary, for use in the high-gamma-activity case. dp_,tecl_lo is the diluted total fraction of the i effluent concentration limit for the discharge point, at the site boundary, for use in the low-gaarna-activity case. . dp_uteci is the undiluted total fraction of the effluent concentration limit for the discharge point. [ [rp_utecl_g y rp_wflowy} dp uteci g = dp_wflow
~~~
3-8
d 4 1 "I e p trp_utecl_ngy rp_wflow y] dp uteci - ng = dp_,wflow dp_uteci = dp_utecl_g + dp uteci ng where: i dp_utecl_g is the undiluted total ECL fraction ) f or gamma-erlitters for the designated discharge point. dp_utecl_ng is the undiluted total.ECL fraction for non gamma-emitters for the designated discharge point. , dp_utecl_g y is the undiluted total ECL fraction for gamma-emitters for the designated point v, as calculated above. dp_utecl_ng y is the undiluted total ECL fraction ; for gamma-emitters for the designated { point v, as calculated above. ' l
' I rp_wflow y is the waste flow for release point v.
dp_wflow is the waste flow for the discharge point: the sum of the waste flows for all open release points on the discharge point. I and the sums ext'end over all open release points v on the discharge point. (X/Q) , is the noble gas X/Q for the distance which matches the site boundary distance, in sec/m 3. The table used (ground-level, uixed-mode, or elevated) is specified by the discharge point definition. units is the units conversion factor units = (1 m3 /35.31 ft 3) - (1 min /60 see) = 4.72E-04 btnQ-3-9 \ S
I Noble Gases For the release point: If the release point setpoint equation is set to LOW ACT, then: . nratio = 1 / rp_tecl_lo
- L' -
Otherwise:
. nratio = 1 / rp_tecl_hi For the discharge point:
If the discharge point setpoint equation is set to LOW ACT, then nratio = 1 / rp_tecl_lo Otherwise: nratio = 1 / rp_tecl_hi Radioiodines and Particulates j l For the release point: If the release point setpoint equation is set to LOW ACT,_ then: rpratio = 1 / rp_tecl_lo
','. Othe rwis e :
rpratio = 1 / rp_tecl_hi For the discharge point: If the discharge point setpoint equation is set to LOW ACT,_ then rpratio = 1 / dp_tecl_lo Otherwise: rpratio = 1 / dp_tecl_hi _lhea g- h
~~
3-10
1 9 O 3.4b OLD 10CTR20 NRATIO The ratio of dose rate limit to dose rate for a single release point is given below for these three cases: Noble Gases 4 l ,, nratio = rg = lesser of the ratios l (total body dose rate limit / total body dose rate) and (skin dose rate limit / skin dose rate) ' i 4
. = for a vent release, lesser of 500 mrem /yr 1
shf Ig K
- Q *
- iv (X/Q) my i
l and i 4 l 3000 mrem /yr a 4 f shf I (L + 1.1M g) *Q h (X/Q)
= for an Elevated Stack e 80m, lesser of I
3 500 mrem /yr 1 -
, shi I V *Q i '
ir a ] ud
~,
3000 mrem /yr i , shf I [ L (X/Q) r + 1'1Bh] 01 i Radiciodines and Particulates 2 In these cases, the ratio is obtained by summing over the j appropriate nuclide indices:
- 1500 mrem /yr rpratio = , = maximum organ dose rate IPi*Qiy *W mv O +
j o 3-11 -g 3-(o 7 4 e i 4
l When the sum is over nuclides and the inhalation, ground plane and cow's milk pathways are all turned on. 3.4c SETPOINTS . Setpoints are determined for radiation monitors on i$tdividual release points, and also for radiation monitors at the discharge L- points that may combine the effluent from several release points. Calculations for the monitor response are made for noble gases, radioiodines, and particulates. For a release point, the expected monitor response co a given nuclide concentration is: - Rmon = monitor response (cpm) +B
= offset + [ slope *IC]i + (quad * ( I Cg)2) + B l
where offset, slope, and quad are the coefficients in a quadratic ! fit to the monitor response to nuclide activity, and B is the ) monitor background. i EMS provides an option to calculate nuclide specific responses so
-that Rmon is determined from the response for each nuclide, rather than the sum of the nuclide concentrations, as shown above. In that
..cas e ,
Rmon =I ( offsett+ (slopet
- C i] + (quadi* ( C1)2]) +B
',I'..
'The expected response for discharge points is based on the sum of
'the expected response for releases already in progress plus the expected response due to release point being considered.
dp (Cdp)2 ) R dpmen" dpmon o
** i+ 'l E*i C + quad *
~
3-12
1 J where C P = C. * (F /Fdp) i i rp 4
= concentration for the release point C1 ,
F rp = flow rate for the release point
.~.
I
~
F dp = flow rate for the discharge point j R dpmon = discharge point monitor response for the release in progress R dpmon = the discharge monitor response before the current o release is added including the background 4 and offsett, slopei and quadi are the quadratic response coefficients of the discharge point monitor. - l j Non-isotop'e specific response: (3
%_) ($n= offset + slope * (ICfP) + quad * (ICf)2+Rdpmen o a ' All other equations are the same as for the individual release point, but use the discharge point monitor response and the discharge point allocation f actor and safety factors.
l EMS allows for setpoint calculations based on the standard or .
,: ' response method. Thus, each release point will have associated with
. it, a setpoint equation: STD or RESP. This can.be set in the Release Point (Setpoint) transaction of ' Database Maintenance.
~
If the release point setooint ecuation =.STD : The limiting setpoint for the monitor (in pCi/ml) is given by: S ,,;; = f,
- falloc
- ratio a SUM The limiting setpoint for the monitor (in user units, e . g . , cpm) is given by:
d .:. 3-13
SU m = f,
- failee a ratio * (Ptton - B) +B where offset = 1. noble gas offset factor
- 2. radioiodine offse,t factor
- 3. particulate offset factor
.~. ~
slope = 1. noble gas slope factor
- 2. radiciodine slope factor
- 3. particulate slope f actor quad = 1. noble gas quadratic factor
- 2. radiciodine quadratic factor
- 3. particulate quadratic factor i
fs = safety factor for the release point falloc = dose rate allocation f actor for the release point ratio = 1. nratio for noble gases
- 2. rpratio for radiciodines
- 3. rpratio for particulates SUM = 1. I noble gas concentrations, for noble gases
- 2. I radioiodine concentrations, for radiciodines
- 3. I particulate concentrations, for particulates P
hn
=
- 1. noble gas, monitor response
- 2. radiolo' dine monitor response
~
- 3. particulate monitor response B = 1. observed backcround response for the noble gas monitor
. 2. . observed background response for the radioiodine monitor
- 3. observed background response for the particulate monitor NOTE : Separate calculations are made for noble gases, radiciodine, and particulates The limiting setpoint for gaseous releases is determined separately for noble gases, radiciodines, and particulates for each release point and discharge point.
~
y
- - _ _ - . ~ . - . . . - . . - . . . - - . - . - - . . _ _ . - - . . - - . . . .
O If the release point setpoint ecuation = RESP : ) a The reported setpoint for the monitor (in pCi/ml) now becomes: j S m = [mrtol * (SUM - B)} + (mrtolb = B) , i 4 The limiting setpoint for the monitor (in user units, e.g., cpm) now j , , , becomes: ] SUmax = [mrtel * (Rmon - B)) + (mrtolb
- B) j where i
! mrtol = 1. monitor response tolerance factor (noble gas)
- 2. monitor response tolerance factor (radiciodine)
! 3. monitor response tolerance factor (particulate) i i SUM = as defined above 1 B = as defined above i mrtolb = 1. monitor tolerance background factor (noble gas)
- 2. monitor tolerance background factor
' (radioiodine)
- 3. monitor tolerance background factor (particulate)
' Rmon = as defined above 3.4d REPORTED SETPOINTS If the release point setpoint equation is STD, then the maximum j setpoint is compared with the response and default setpoints.
NOTE :The response setpoint as defined in this section is not ' necessarily the same as the maximum setpoint based on the RESP setpoint equation, as defined in the previous section. l S response is defined below. ! I 3 1s y 7/ I
1 i l The reported setpoint is as follows:
- 1. Reported = S response if Sresponse < Smax < Sdefault OR if S default <Sresponse < S max .
j
- 2. Reported = S max if Sresponse 1 S max l
~ 1
- 3. Reported = Sdefault l if Sresponse < Sdefault < S max where 1
S max
- = as defined in the previous section r mrtol
- SUM (FCi/ml]
S response " 5 L (mrtol * (Rmon - B)) + (mrtolb
- B) ['
Units] ) S default
= normal setpoint defined for the release point in units of (FCi/ml] and (User Units).
NOTE : Separate checks are made for each !.etpoint in (FCi/ml] and (User Units) for the noble gas, radioiodine, and particulate monitors. I l I 3.5 MAXIMUM WASTE FLOW
',('The maximum waste flow calculation is based on what the WFLOW M
'coption (release point setpoint calculation option) is set to. This option can take on one of three values: NONE, DOSE, and CALC.
Gaseous release point setpoint WFLOW M can be set to either NONE or DOSE. For gaseous relrap.s, Wmax = the minimum of Pm and R cwmax where R. = Release point maximum waste flow rate as stored in the release point definition 3-16
. . _ . _ _ . . __ _ _ . . .. . _ . . _ _ . ~ _ _ _ . . _ _ _ _ _ . . _ _ . . _ . _ . _ _ _ _ . . _ _ __..._m.____
I 4 If WFLOW M option = NONE R eymax = waste flow rate fo2. the sample, Vf If WFLOW M option = DOSE fs * "*"tiO *V f R ewmax " F,,gge i where f, = Safety factor for the release point i i nratio = nratio as described in section 3.4 (i . e . , 3.4a & 3.4b) Vf = Waste flow rate for the release (sample). l T wsfac = Waste flow rate DOSE setpoint safety factor i i I I 3.6 DOSE RATE AND CUMULATIVE DOSE CALCULATIONS Noble Gas Total Body Dose Rate Calculations
*The total body dose rate due to gamma emissions by noble gas releases from vent v is calculated by using the following Jexpressions:
Dt = 1.14
- 10-4 ' (shf) (X/Q)y I (K t*by) l Vent < 80m i
Dt = 1.14
- 10-4 (shf) I (vi
- Ogy) Elevated Stack a 80m i
where: Dt= the total body dose rate due to gamma emissions by noble gas releases from vent v, in mrem /h. 1.14
- 10-4 = inverse of the number of hours in a year.
\ . .,..-
y 73
~ Noble Gas Dose Calculations The dose contribution due to noble gases in gaseous effluents is calculated using the fellowing expressions: For any time period, for air dose due to gamma radiation:
~
D, = 3.17 + 10 IM y * (X/Q)
- O Vent < 80m h
OR
~
D = 3.17 e 10 ZB h
- Oh Elevated Stack a 80m and for air dose due to beta radiation:
~
Dg = 3.17
- 10 IN g *
(X/Q)y
- O Vent < 80m h
OR
~
D = 3.17
- 10
- IN *
(X/Q)v
- Qiv Elevated Stack a 80m i p i l and for total body dose:
shf
- fo
- I Ki* (X/Q)y *Qy i Dt= Vent < 80m (5.256E+05/ duration)
OR shf
- foe I vir
- Oiv Elevated Stack a 80m Dt=
. s '.
(5.256E+05/ duration) 4 l and for skin doses shf a f*I o (Li + 1.1M i)
=
(X/Q)y *Qiy Ds = Vent < 8.0m (5.256E+05/ duration) OR shf
- f o
- I ( (Li* (X/Q)y) + 1.1Bir)I
- iv Ds = Elevated (5.256E+05/ duration) Stack a 80m 3- S
-pge 74 i
.-.-l l
.~ .
1 where: 1 D y= the total gamma air dose from gaseous effluents, in I mrad. I
\
Dp = the total beta air dose from gaseous effluents, in 4 4 mrad. 1 Dt= the total body dose from gaseous effluents, in mrem. Ds = the total skin dose from gaseous effluents, in mrem. 3 .1~1
- 10-8 = inverse of number of seconds in a year 4
j 5.256E+05 = number of minutes in a year fo= The occupancy factor defined for the receptor at the 1 given location, a dimensionless number s 1.0 . l Ki = the total body dose f' actor due to gamma emissions for i noble gas radionuclide i, in mrem /yr per pCi/m3 . Li = the skin dose f actor due to bets emissions for noble gas radionuclide i, in mrem /yr per pCi/m3 . ' O Mi = the air doge f actor due to gamma emissions for noble gas radionuclide i, in mrad /yr per FCi/m 3,
/,
#' Ni =
the air dose factor duft to beta emissions for noble gas radionuclide i, in mrad /yr per FCi/m 3, vi = the gamma total body dose factor for nuclide i at receptor location r, in mrem /yr per pCi/sec. Bi = the gamma skin dose faci.or for nuclide i at receptor location r, in mrem /yr par Ci/sec. (X/Q)y = the highest value of the annual average atmospheric dispersion factor for vent or stack v at the site boundary, for all sectors, in sec/m 3. l O :-
, __ u 75
1
- l Qy = the release of noble gas radionuclides, i, in gaseous i
effluents from vent or stack v in pCi. Releases are i cumulative over the time period selected f or the l report. l Ogy - the release rate of noble gas radionuclides, i, in gaseous effluents from vent or stack v in pCi/sec. Release rates are cumulative over the time period selected for the report. duration = the duration of the release in minutes Orean Dose Calculations ; For any time period, organ doses from particulates and iodines are: D Ta = 3.17
- 10-8
- fo e IRipy,* Wpy *Qyi where:
3.17
- 10-8 = inverse of number of seconds in a year DTa = the cumulative dose for age group a and organ 7 from iodines and particulates with half lives greater than ,
8 days in gaseous effluents, in mrem. R ipta = the dose factor for each radionuclide i, pathway p, organ T, and age group a, in m2 (mrem /yr) per pCi/sec l or mrem /yr per pCi/m3 l 1 Wpy = the annual average dispersion parameter for estimating the dose to an individual at the critical
' g. location, as appropriate to pathway p and release point v, is shown below:
. 1) (X/Q), in sec/m 3 , for the inhalation pathway and for tritium and C-14 in all pathways. ,
1
- 2) (D/Q) for the food and ground plane pathways, in j meters 3, Oty = the release of nuclide i in gaseous effluents from release point v. Releases are cumulative over the time period selected for the report. Only tritium, I-131, I-133, and radiciodines in particulate form with half-lives greater than 8 days are included.
3-20 % 1 4
I The maximum exposed individual is determined by the maximum dose received by any organ. The summation extends over all applicable I nuclides and pathways. I ]; 3.7 RESOLVING DOUBLE-COUNTING OF DOSE AND ACTIVITY , Gaseous release points fall into three categories for double-l counting of dose and activity. One, a release point will not have 4 activity sampled twice. Two, a release point can have activity that { is sampled again downstream and would be double-counted if no corrections were applied. Three, a release point can have samples i containing activity already sampled once upstream which would be double-counted if no corrections were applied. The last two l
- categories can be called the "CAUSE" release point and the "EFFECT" release point, respectively.
To avoid double-counting dose and activity, only the "EFFECT" i release point will have its activity and concentrations corrected as l
- follows. Corrected activity is calculated as follows:
5 Acei " Aei - Aci where: A egi =the corrected "EFFECT" release point activity for nuclide i which defaults to zero if its value is less than zero. A,1 =the initial""sFFECTd release point activity for nuclide , i l i Act =the "CAUSE" release point activity for nuclide i
'5- '
JCorrected concentrations are calculated as follows: C e ,i = (Ae i / V,)
- 35.315 where:
C e ,1 -the corrected "EFFECT" release point concentrations for nuclide i V, = the waste volume for the "EFFECT" release point 35.315 = conversion factor from Ci/ft3 to uCi/ml (Ci/ft 3
- 1 O 3 3 3 ft /1728 in 3
- in /16. 3 87 cm )
3-21 NIO rn 77 B e - r- . - -
1 3.B 31 DAY PROJECTED DOSE CALCULATIONS O 1 The 31 Day Projected Dose values appear on the Standard and Special ! Permit Reports. The Projected Dose values are calculated as follows: D pg = (Dr
- p) +D at where:
Dpr =the 31 Day Projected Dose by organ T ] Dr = sum of all open release points in mrem / day by organ T l when an answer of "Y" is specified for the " Update l Totals" field 'on the release point definition screen. 1 p =the Projection Factor which is the result of 31 divided by the number of days from the start of the quarter to the end of the release. l Dar = Additional Anticipated Dose for gaseous releases by I organ T and quarter of release.
~
NOTE: The 31 day dose projections on the Approval /Results screen include additional doses for all units. 73.9 GAS POST-RELEASE PROCESSING After a pre-release permit has been approved, the post-release program is run to:
, (, o Enter actual release start and stop times, flow rates, etc.
o Check 10CFR20 limits o Check 10CFR50 limits o Add the dose and activity data into the cumulative totals. Compliance with 10CFR20 limits is checked in the same way as described for the pre-release program. Dose rates are calculated and compared to 10CFR20 limits. Monitor setpoints are not calculated at the post release stage. 3-22 .J l 1
-- _. .. . _ . -- . . - - _ _ . _ . .. . ,_. _ ~ . . . - - .-- .-. -_ . . - - . - _ _ . _ _ . . - - _ _
4 i 1 1 f~% , .i i 3 . i $ *-- ~ . CHAPTER 4 LIQUID DOSE FACTOR EQUATIONS i i } The DFP option is used to calculate the liquid dose factors described previously. Dose f actors are calculated separately for ] each nuclide, organ, and age group. The age group, applied to a l specific receptor's dose calculations, is part of the receptor specification. For a particular receptor, the total dose factor (Alfr) is a sum
- over each pathway p with its specific mixing ratio:
i 1 4 l A = IR.m ,r,p A iTr iT, r, p g ~
; mix,r 3.where ,
1 . i
,:, Air,r,p = the dose factor for nuclide i, organ T, recept;or age
>- l group r, end pathway p '
! Raix,r,p = mixing ratio for the pathway ] } Rmix,r = mixing ratio for the receptor, which is the first I j non-zero value of Rmix,r,p encountered during the 4 calculation 2 The user specifies which pathways are included by setting the mixing } ratios for the pathways desired to the correct non-zero value. If the receptor mixing ratio for a given pathway is zero, that term is 4 not included in the sum. 4
....~-- hO.
4-1 S i t
~
i The DFP option of EMS uses a more expanded form for liquid dose factors than is given in NUREG-0133. These equations are taken from R.G. 1.109, and account for nuclide decay as well as shoreline doses. If desired, parameters may be selected to reduce the calculations to match NUREG-0133 exactly. Four different forms of equations are used for the dose factors.
~~.
4.1 POTABLE WATER The dose f actor f or potable water is: ) l AiT,r,p = k o * (Ur ,p /dw) *Ni
- DFif,r * 'I~A tip) where -
Air,r,p = dose parameter f or organ 7, for the receptor age group r, for nuclide i, due to exposure pathway p, in mrem /hr per #Ci/ml ko = units conversion factor, = 1.142E5 = lE6 (pCi/pC1)
- 1000 (ml/Kg)/ 8760 hr/yr Ur ,p = usage factor for pathway p and age group r dw = additional dilution factor for potable water Ni = fraction of the radionuclide activity released to 3 the water
- discharge path that reaches a specific receptor.
.* DFir,r = ingestion dose conversion factor for nuclide i for receptor age group r in organ T, in mrem /pci (Tables E-7 to E-ll of R.G. 1.109)
At= decay constant for nuclide i tp= average transit time in seconds 4.2 AQUATIC FOODS PATHWAYS The liquid dose factor is A it,r,p = k o
- Ur ,p
- BFi,p
- Ni
- DFif,r * * *P ( ~ i tp) w so
.-2
( ( where BFi,p= bioaccumulation factor for pathway p and nuclide i (from Reg. Guide 1.109, Table A-1). Other variables are as defined on the previous page. ,
'..~.
4.3 SHORELINE RECREATION PATHWAY The pathway-specific dose factors for shoreline deposition are given by:
~
1-e ib ~ A if,r,p
=k W N U s s e i sd DFG i f,r,p y if i
where Ws = shoreline width factor ks = conversion factor = ko *k e
- mtv/3600 ke = water to sediment transfer coefficient in L/kg hr mtv = Mass density of sediment in kg/m 2, 40 kg/m2
?" 3600 = Seconds per hour units conversion 4: factor tb = length of time sediment is exposed '
to ; t contaminated water, 4.716E8 sec t sd = transit time to deposit activity on shoreline DFGit = the dose conversion factor for standing on ground contaminated with nuclide i, in mrem /hr per pCi/m2 4-3 &f
i 4.4 IRRIGATED VEGETABLE PATHWAY i A = 1.14 + 10
- U CF - DF
! it,r,p f,r,p iv it, r where: 1.14
- 105 = a units conversicn factor 7
' ~ CFiy = the concentration f actor for radionuclide i in irrigated vegetables, as applicable to the vicinity of the plant site (pCi/kg) / (pCi/L) . Calculation of the Concentration Factor The calcuiation of the concentration factor for radionuclide i in irrigated vegetables, CFiy as used in the equation for Air, is calculated as follows for all radionuclides other than Tritium:
-A t ib
~* ~
CFiy =N
- H* I r (1 - e *) I iv ,
i v Ei' i - For Tritium, the equation is as follows:
- I CFly =
Ni*M*L y where 1 M = the additional dilution factor from the near l
'3, field'of the discharge structure to the point ef irrigation water usage.
I = the average irrigation rate during the growi.ng season (L/m2 h).
- r = the fraction of irrigation-deposited activity retained on the edible portions of leafy vegetables. There are separate values available for radioiodines and particulates.
Yy = the agricultural productivity of irrigated leafy vegetables (kg/m 2), i w 4,4
, . = . - _ _ - - . _ _ _ . - _ _ . _ _ _ _ - - . _ , . _ - - - _ - . _ - - _ . ~ - _ _ _ - _ - - _ _ .
.e .- - U fy = the fraction of the year that vegetables are irrigated. B iy = the crop to soil concentration factor applicable to radionuclide 1 (pCi/kg vegetables) / (pCi/kg soil) . . i P = the effective ' surf ace density of soil' (kg/m 2) , the decay constant for radionuclide 1 (h-1) . A = i i AEi = the effective removal rate for activity 4 deposited on crop leaves (h-1), calculated as j AEi " di+A w I A, = the rate constant for removal of activity from plant leaves by weathering (h-1). i t, = the period of leafy vegetable exposure during the growing season (h). I tb = the period of long-term buildup of activity in soil (h). O f th = the time between harvest of vegetable and human consumption (h).
'- Ly =
j the water content of leafy vegetable edible ! parts (L/kg). 4.5 REDUCTION TO NUREG-0133 EQUATIONS
,NUREG-0133 does not have shoreline deposit equations, which can be
'}<' eliminated by setting the Water Recreation Mixing Ratio to zero in the Liquid Receptor Transaction definition under EMS.
For the other equations, reduction to NUREG-0133 is obtained by setting: Ni= 1 (this can be set in the definition of Fraction of Activity Reaching Receptor in DFP) average transit time t = 0 (t his can be set in the definition of Dose C$1culation Parameters in DFP) l 4-S ' I
a , O'
' -~ .
CHAPTER S GAS DOSE FACTOR CALCULATIONS The DFP option is used to calculate the gas dose f actors described previously. Dose factors are calculated separately for each nuclide, organ, and age group. The age group, applied to a specific receptor's dose calculations, is part of the receptor specification. The same gas dose factors are used for both the site boundary dose rate calculations and for the maximum individual controlling location dose calculation. The dose factor for each particulate or iodine nuclide i (or tritium) is given Delow. It is a function of pathway, organ, and age group. The pathways considered are:
- 1. Inhalation
- 2. Ground
'., 3. Milk (Cow or Goat)
- 4. Heat
- 5. Vegetable 5.1 INEALATION PATHWAY Pita = K' (BR) a (DFAiT) a (mrem /yr per #Ci/m3)
K' = 1E6 pCi/pCi
)
. l l
l 1 i (BR), = breathing rate for age group a, in cubic m/yr (DFAlt)a = inhalation dose factor for organ T, for age group ! a, for nuclide i, in mrem /pci , 7 5.2 GROUND PLANE PATHWAY RiT a = K' K" (SF) DFG ir [(1 - eN)/Ai) (m2 -mrem /yr per pCi/sec) where K' = 1E6'pCi/pCi K" = 8760 hr/yr At= decay constant for nuclide 1, in see-1 t= exposure time (sec) = 4.73E8 (15 years)
. DFGiT = ground plane conversion f actor for nuclide i, organT (The same DFGit factors apply to all age groups. Tne factors labelled tot al body in the database are applied to all other organs)
SF = shielding fa or
'h'.
'5.3
; MILK PATHWAY
- t ig y n .
Rif a = K' (DFLiTIa
' ~ '
r (1-e"( i w'*e) (1 - e i b) ff + B Ps iv y {j ,;) O . . :- 5-2
f
~ ~ ^ '
4 r (1-e i w' e) (1 - e i b)
+ (1-fpsf ) e ih +B iv 7, (; +; ) p; i
~
(m2 - mrem /yr per pCi/sec) where 1 *: K' = lE6 pCi/pCi
- Op = feed consumption rate by the milk animal (cow or goat)
(Kg/ day) , U ap - age group a milk consumption (cow or goat) Yp = agricultural productivity by unit area of pasture feed grass, in Kg/sq. m Ys = agricultural productivity by unit area of stored feed, in Kg/sq. m Fmi = stable element transfer coefficient for nuclide 1, frein feed to milk, in days / liter B iy m factor for uptake of radionuclides from soil by crops r= fraction of deposited activity retained on animal feed grass (cow or milk). Separate values are used for radioiodines'than all other particulates. (DFL iT I.a = ingestion dose f actor for organ T, for nuclide 1, for [ receptor in age group a, in mrem /pCi At= decay constant for nuclide i Aw = decay constant for removal of activity on leaf and plant surfaces by weathering, in sec~1 tg = transport time from pasture to cow or goat to milk to receptor, in sec. th= transport time from pasture to harvest to cow or goat to milk to receptor, in sec. l t,= seasonal crop exposure time, in sec. l fp = fraction of year that animal is on pasture l 5-3
- . _ .. = . . _ - _ - - _ . . . ..__. - _ - . _ _ . -. .. . . - . . .- .
1 1 j , f, = fraction of animal feed that is pasture grass while 1 animal is on pasture , l Carbon-14 in Milk
* - A t'g Rit a = K' K"' Fmi k Ump (DFLiTl a Pc (0.11/0.16) e i l (m2 -mrem /yr per pC1/sec) !
where K"' = lE3 gm/Kg i . ! pe = fractional equilibrium ratio 0.11 = fraction of total plant mass that is natural carbon } 0.16 = concentration of nut ral carbon in the atmosphere (g/m3) and'all other parameters as defined above i i . I { Only Op and U,p depend on cow or goat. L Tritium in Milk 5 RiT a = K' K"' F d OF Uap (DFLiTl a * (0.75) (0.5/B) e if t (m2 -mren/yr per FCi/sec) , where . K"' = lE3 gm/Kg H= absolute humidity, gei/ cubic meter 1 0.75 = fraction of total feed that is water l l 0.5 = ratio of specific activity of feed grass water to the l atmospheric water ; l i and all other parameters as defined ab i
.r.~--
5-4
Only 07 and U,p depend on cow or goat. 5.4 !E.AT PATHWAY , t
,, Rif a = P' (DFLif) a , igg y y .
'r (1-e ~I i w e)
# ~ ~
1-e ib ff +B Y p (Ai + A,) P At .
' ~ '
~
r ( 1-e" i w e) 1-e ib
+ (1-f f )e ih +B Ps Y, (Ag + A ) pA g ,
where Fgi a stable element transfer coefficient for nuclide i, from feed meat, in days /Kg U ap = receptor's meat consunption (Kg/yr) th= transport time from crop field to receptor, in see tg= t,-
- nsport time f: pasture to receptor, in sec
, ano . . nther factors are as described for the cow-
'.,,, milk pata, v ,
Carbon-14 in Meat Ri t a = K' K"' Fgg Op U,p (DFLiTl a Pe (0.11/0.16) e -A ii t (m2 -mrem /yr per pCi/sec) where all terms are as defined above. r;;-
. .-2 ~
5-5
- = - . . ~ . . . - . - . _ . . . . _ _ - . - ... . . . . _ . _
i 1 Tritium in Heat Rif a = K' K"' ~ Fgg Qp Uap (DFLiTl a * (0.75) (0.5/B) e -E if t (m2 -mrem /yr per pCi/see) I where all terms are as defined above. ) l E- l
~
5.5 VEGETABLE PATHWAY
~
R = K' Ua fL e iL
- iTa (DFLif)a i
' r (1-e" i w I e) B iv (1-e ~t) ib Y
v (Ai + Aw) pA i - 8 '
+0 f e ia
- a g 1
'r (1-e
~ ~ '
. i w e) 3 iv (1-e i b) *
- sv (Ai + Aw) pA Y
i - (m2 mram/yr per #Ci/sec)
,'whe re Uh = consumption rate of fresh leafy vegetation for age group a, in Kg/yr Ul= consumption rate of stored vegetation for age group a, in Kg/yr f3= fraction of annual intake of leafy vegetation grown locally fg =* fraction of annual intake of stored vegetation grown locally O . .-
,, gf
l l tg= average time between harvest of leafy vegetation and consumption, in sec. , l t s= average time between harvest of stored vegetation and consumptien, in sec. tb= long term sediment exposure time, in see. t,= seasonal crop exposure time, in sec. Yy = vegetation areal density, in Kg/m2 Y sv
= stored vegstation areal density, in KG/m2 p= effective soil surface density Biy. = soil to vegetation transfer factor for nuclide i Ali other factors are as defined above.
Carbon-14 in Vecetables RiT a = K' K"' (Uk+Uf) (DFLiT)'a pc (0.11/0.16) e -A if t (m2 -mrem /yr per pCi/sec) where al.7. variables are as defined earlier. Tritium in Veoetables Rit a = K' K"' \+Uf) (DFLiTl a * (0.75) (0.5/B) e -Ai ty (m2 -mrem /yr per pCi/sec) where all variables are as defined earlier. 5.6 REDUCTION TO NUREG-0133 EQUATIONS Inhalation a7d ground plane pathways are the same in R.G. 1.109 and NUREG-0133. For the other pathways (milk, meat, and vegetable), these eq ations reduce to the NUREG-0133 values by setting: tb=0
. .- F
O t, = 9.999E19 l tg = 0 (in tritium equations only) i There are no C-14 equations in NUREG-0133, which can be obtained by setting pe = 0. 4 1 1 e e i d l A U 0 J , e I
"ED,g**
5-8 1 i
1 1
,~
O 7 APPENDIX A q REFERENCES 9
- 1. Boegl.1, J.S., R.R. Bellamy, W.L. Britz, and R.L.
Waterfield, " Preparation of Radiological Effluent Technical Specifications for Nuclea'r Power Plants, "NUREG-0133" (October 1978) .
- 2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the ~/urpose of Evaluating Compliance with 10CFR Part 50, Appee. dix I, U.S. NRC Regulatory Guide 1.109, Rev. 1 (October 3377).
. . .: .. cp y A-1 f
1 l e l l l )
' 1 d
i d ! i 2 l 3 l 1 1 1 i i i I i APPENDIX X: j J j t 4 i 4
- 4 1
a i i j i 4 l l i
, i a
i l , i l ) 1 DELETED l t 1 i i 1 q 1 1 4 i 4 1 4 4 i f i i 4 ,i X1 CDCM Rev. 16
4 f I 1 i 4 i i s 1 1 4 , APPENDIX Y: i i . 1 4 4 4 J j DELETED 1 i 4 i, e 1 i 4 4 i < 1 9 l t 4 3 i 4, f. 4 4 1 3 ,1 1 4 4 1 Y-1 ODCM Rev. 16
4 i l
- 4 l
APPENDIX B 4 ? 4 Process Control Prontam Reauirement: Technical Specification 6.12.2.a requires that licensee initiated changes to the 4 Process Control Program be submitted to the Commission in the Annual i Radioactive Effluent Release Report for the period in which the change (s) were d made. i Resnonse: During 1996, Seabrook Station implemented a change to their PCP. A PCP that ] covers the Dewatering of Resins and process filters was developed. 1 i ! . This document (PCP) was presented to and approved by the Stations' SORC on j April 1,1996. This document is attached.
- This is a change to the previously approved PCP.
1 i 1' i i $ 1 l l I
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