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| gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 l
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| Title Revision No.
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| Offsite Dose Calculation Manual (ODCM) 17 Applicability /soope Calculate offsite doses due to radioactive msponsim office Effectwo Date effluents for demonstrating compilance with Site Technical Specifications 10 CFR 20 & 10 CFR 50 - Appendix l 6610 09/01/98 l
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| This document is within OA plan scope X Yes No Safety Reviews Required X Yes No List of Effective Pages
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| ,P_ age Revision Pace Revision Pace Revision Paos Revision 17 21.0 15 41.0 15 61.0 15 1.0 2.0 17 22.0 15 42.0 15 fog 62.0 15 23.0 15 43.0 15 f k 63.0 15 j 3.0 11 40 15 24.0 15 44.0 15p kl4 / 64.0 15 5.0 15 25.0 15 45.0 ($ p. "*!d 65.0 15 ,
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| jgggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Rowsion No.
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| Title 17 Offsite Dose Calculation Manual (ODCM)
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| List of Effective Pages (Cont'd) 1 Paae Revision Page Revision Pace Revision Paae Revision 121.0 12 161.0 16 81.0 15 122.0 12 162.0 12 82.0 15 123.0 12 163.0 12 83.0 15 124.0 12 164.0 12 84.0 15 125.0 12 165.0 12 85.0 15 I 126.0 12 166.0 12 86.0 15 I 127.0 12 167.0 16 87.0 15 128.0 12 168.0 16 (jpeg,,!!;
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| 105.0 16 145.0 % 'Ogi,12 !
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| e gggy TMI Radiological Controls Departmental Procedure Number Taue 6610-PLN-4200.01 l Revis6on No.
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| Offsita Dose Calculation Manual (ODCM) 11 INTRODUCTIOIS l The OFFSITE DOSE CALCU1.ATION MANUAL (ODCM) is a supporting document of the GPUNC Three Mlle Is N" clear Station (TMINS) Unit I and Unit 2 PDMS Technical Specifications and implements TML radiological l j controls. 7.ie ODCM contains the controls, bases, and survelliance requirements for liquid and gaseous l radiological effluents. In addition, the ODCM describes the methodology and parameters to be used in the calculation of off-stte doses due to radioactive liquid and gaseous effluents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring Instrumentation alarm / trip set points. Liquid and Gaseous Radwaste Treatment System configurations are also included.
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| 1 ge%
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| The ODCM also is used to define the requirements for the TMINS radiological envirpnmental monitoring pr (REMP) and contains a list and graphical description of the specific sample lo The ODCM la maintained at the Three Mile af Island (TMI) site for use a ence accepted methodologies and calculations. Changes in the calculation methdda.or, parameters guide and training docu will be incorporated into the ODCM to ensure the ODCM represents the present methodologyjrfill npplicable areas. GPUNC Initiated changes to the ODCM will be implemented in accordance with the TMI-J*. And TMI-2 PDMS Techrdcal ng The ODCM follows the methodology and models suggested bk NUREG-0133, and Regulatory Guide 1.109, Revision 1 for calculation of off-site doses due to plant effluentjeleases. Simplifying assumptions have been applied in this manual where applicable to provide a more MMable "
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| document for implementation of the Radiological Effluent Controls requirements. #l GPUN implements the TMI Radiological ENent C6r%#%
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| golsfrogram and Regulatory Guide 1.21, Revision 1 (Annual Radioactive Effluent Release Report) requirements by use'of a computerized system used to determine TMI effluent dosesgy/
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| releases and to update$cumulative effluen}%.
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| n ,.
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| a.vwon ce ONs!te Dose Calculation Manual (ODCM) 15 l
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| TABLE OF CONTENTS PARTI TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page I
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| 1.0 DEFINITIONS 15.0 l
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| )
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| Table 1-1, Frequency Notations 18.0 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES jf""%;. 21.0 ' '
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| 2.1 Radioactive Emuent Instrumentation f"' Iik g 21.0
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| %j 2.1.1 Radioactive Liquid Emuent Instrumentation '%g#" g #
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| *%gi h 21.0
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| 2.1.2 Radioactive Gaseous Process and Emuent Monitoring instrumentation 24.0 l
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| %;n %, I TaWe 2.11, Radioactive Uquid Emuent instrumentation 9,
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| !iji 22.0 h
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| TaWe 2.1-2, Radioactive Gaseous Process and Emuent Monitoring instrumentation 25.0
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| 2.2 Radiological Emuent Controls n
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| .s#jf!%jD
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| 2.2.1 IJguid Emuent Controls W,. 31.0
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| 2.2.2 Gaseous Emuent Controls
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| * A 34.0 j;gj mmd/
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| 2.2.3 Total Radioactive Emuent Controls 39.0 e~ m f ."wim 3.0 SURVEILLANCES g V 40.0 L."( % #)
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| 3.1 Radioactive Emueny' nstrumentation 40.0 41;ggF Mig 3.1.1 Radioactive Liquid Efiluent Instrumentation 40.0 m,
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| 3.1.2 Radioactive Gaseous Process and Emuont Monitoring Instrumentation 43.0 TaNe 3.1 1, Radioactive Liquid Emuent Monitoring instrumentation Surveillance Requirements 41.0 TaNe 3.1-2, Radioactive Gaseous Process and Emuent Monitoring Instrumentation 44.0 SurveRanoe Requirements 3.2 Radiological Effluents 49.0 3.2.1 Liquid Emuents 49.0 i
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| 3.2.2 Gaseous Efiluents 55.0 4.0 sm.
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| Numbw TMI Radiological Controls ME Departmental Procedure 6610-PLN-4200.01 Tlue Ravesson No.
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| Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS PARTI TMl-1 RADIOLOGICAL EFFLUENT CONTROLS i
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| Section Page i l
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| l Table 3.2-1, Radioactive Uquid Waste Sampling and Analysis Program 51.0 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 57.0 3.2.3 Total Radioactive Effluents /"*4 ;;3 il 62.0 k 't 4.0 PART 1 REFERENCES ./ 63.0 l
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| Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS (Cont'd)
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| PARTll TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINmONS 65.0 Table 1.1, Frequency Notation 67.0 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES f"*%k 68.0 2.1 Radioactive Emuent Instrumentation f iy, j 68.0
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| .% 21.0 een.n )k N j 2.1.2 Radioactive Gaseous Process and Efnuent Monitoring instrumentation 68.0 l % *%,
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| Table 2.1.2. Radioactive Gaseous Process and Elliuent Monitoririg;lnstrumentation 70.0 2.2 Radioactive Emuent Controls 71.0
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| 90 71.0 2.2.1 Liquid Emuent Controls $1
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| .g 2.2.2 Geseous Emuent Controls 73.0 g#%g% . v 2.2.3 77.0 Total Radioactive Emuent Controls ww /-
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| j 3.0 SURVEILLANCES g 4 79.0 l 4
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| # #% 79.0 3.1 Radioactive Emuent" instrumentation t %. %g#
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| 3.1.1 Radioactive Emuent instrumentation 79.0
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| % 7' %,;,
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| 3.1.2 RadioactivhGasacus Process and Emuents Monitoring instrumentation 79.0 Table 3.12, RadioactNo Gaseous Process and Emuent Monitoring instrumentation 80.0 SurveRance Requirements 3.2 Radiological Emuents 81.0 3.2.1 Uquid Effluents 81.0 3.2.2 Gaseous Emuents 83.0 Table 3.2-1. Radioactive Uquid Waste Sampling and Analysis Program 82.0 Table 3.2 2, RadioactNe Gaseous Weste Sampling and Analyals Program 84.0 3.2.3 Total Radioactive Emuents 87.0 6.0 m.
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| Ember gp TMI Radiologeal Controls Departmental Procedure 6610-PLN-4200.01 Tm. mn m.
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| Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS (Ccti)
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| PART11 TMI-2 RADIOLOGICAL EFFLUENT CONTROLC Secuan Page 4.0- PART 11 REFERENCES 88.0 gg;;mtitihig
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| Number J EE TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 T)de R*vesen No.
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| Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS PARTlli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Pace 1.0 LIQUID EFFLUENT MONITORS 90.0 1.1 TMI 1 and TMI-2 Uguld Radiation Monitor Set Points 90.0 1.2 TMI Liquid Release Points and Uguid Radiation Monitor Data is 91.0 h[N li 1.3 Control of Uquid Releases #
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| "[+d bp/
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| ,y 93.0 2.0 LIQUID EFFLUENT DOSE ASSESSMENT *(t.g.ill Mi g* 98.0 2.1 Uguid Emuents - 10 CFR 50 Appendix i g,+*% %g%@'''
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| , 96.0 49 11, 6
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| 2.2 TMl Uquid Redweste System Dose Colcs Once per Montis 100.0 I;
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| * 2.3 Altemative Dose Calculational Methodology 3 101.0 I
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| ;n.w j{m%
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| 3.0 LIQUID EFFLUENT WASTE TREATMENT SYSTEM 106.0
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| %gjnu 3.1 TMl-1 Uguld Emuent Waste Treatiher[ System 106.0 i! 4 3.2 Operability of TMI 1 g} %EfEmn(yyEste Treatment System107.0 3.3 TMI-2 Uguld Emuentyaste" Treatment System 107.0 if +rA 4.0 GASEOUS EFFLUENT < MONITORS 110.0 i
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| g Ni( *wf 4.1 TM1-1 Noble Gas Monitor Set Points 110.0
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| %!!;jf %4 4.2 TMI-1 Partye and Radiolodine Monitor Set Points 112.0 j
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| 4.3 TMI 2 Gaseous Radiation Monitor Set Points 113.0 4.4 TMI-1 Gaseous Emuent Release Points and Gaseous Radiation Monitor Data 114.0 4.5 TMI 2 Gaseous Emue t Release Pokits and Gaseous Radiation Monitor Data 116.0 4.6 Control of Gaseous Emuent Releases 117.0 8.0 smi
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| Number gp TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01
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| : m. n.v on so.
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| l Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS I
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| PARTlli EFFLUENT DATA AND CALCUL.ATIONAL METHODOLOGIES Section Page f
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| 5.0 GASEOUS EFFLUENT DOSE AS3ESSMENT 129.0 5.1 Gaseous Efluents - Dose Rate Umits 129.0 5.1.1 Noble Gases t'''"""4 129.0
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| : s. ?ll 5.1.1.1 Total Body N jp ' [%yg, 129.0 4.#
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| 5.1.1.2 Skin h% 4 g 130.0
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| %"le r.. A 5.1.2 lodines and Particulates dig, i[ar ~""* ' 131.0 NgSii .4 5.2 Gaseous Efluents - 10 CFR 50 Appendtx i 132.0 A
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| I?
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| 5.2.1 Noble Gases .wayk 132.0 pn %.
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| 5.2.2 lodines and Particulates 133.0
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| *#Q%
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| . .,. w
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| )r!Ii 5.3 Gaseous Radioactive System. Dose Calculations Once per Month 135.0 li! +
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| 5.4 Mtemative Dose CalculatidndMethcEologies 136.0 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 158.0
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| ; A%
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| 6.1 Description of the(TMl-1 Gaseous Radweste Treatment System 158.0 g,1( %#
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| 6.2 Operabtity of the TMI-1 Gaseous Radwaste Treatment System 158.0 yy m%,
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| 7.0 EFFLUENT TOTACDOSE ASSESSMENT 160.0 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 161.0 l 8.1 Monitoring Program Requirements 161.0 l
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| 8.2 land Use Census 163.0 8.3 Iraettaboratory Comparison Program 165.0 i
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| 9.0 PART 111 REFERENCES 182.0 9.0 rm.
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| i
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| r bmtlet ggy Ml Radiclogical Contrcis Departmental Procedure 6610-PLN-4200.01 Tm nww.n m.
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| Offsite Dose Calculation Manual (ODCM) 15 TAst.E OF CONTENTS (Cont'd)
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| PART HI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES TMI-1 L.lquid Release Point and Uquid Radiation Monitor Data 94.0 Table 1.1 TMI-2 Sump Capacities 95.0 Table 1.2 Ys/"*"*(
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| Table 2.1 Uquid Does Conversion Factors (DCF): DF, $p9/ k y, )s 102.0 Table 2.2 Bioaccumulation Factors, BF, \ 105.0 TM1-1 Geseous Release Point & Gaseous Radiation - 118.0 Table 4.1
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| '%g '4 119.0 Table 4.2 TMI-2 Gaseous Release Point & Gaseous Radiation Monhor Data I,
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| 120.0 Table 4.3 Dose Factors for Noble Genes ,#'g and Daughtersq%;a.
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| 121.0 Table 4.4 Atmospheric Dispersion Factors for gle f aland - Station Vent Atmospheric Dispersion Factorff5rh Mee taland Ground Release 122.0 Tabio 4.5 m ( "$
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| Dose Parameters for Radiolodinae and Radioactive Particulate, Gaseous, Etnuents 123.0 Table 4.6 '' I
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| # %g 137.0 Table 5.2.1 Pathway Dose Factors, R, "Infart, inhalation gA Table 5.2.2 Pathway Dose F(actors, fl,- Child, inhalation 138.0 gg w Table 5.2.3 Pathwa wg$
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| Fa tors, R Teen, inhalation 139.0 140.0 ;
| |
| Table 5.2.4 Pathway 65se Factors, R,- Adult, inhalation
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| )
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| 141.0 Table 5.3.1 Pathway Dose Factors. R, AR Age Groups Ground Piarm 142.0 Table 5.4.1 Pathway Dose Factors, R,-Infart, Grass-Cow-Mgk i
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| i43.0 Table 5.4.2 Pathway Dose Factors, R,- Child, Grass-Cow-MRk 144.0 Table 5.4.3 Pathway Dose Factors, R,- Teen, Grass-Cow-Mak 145.0 !
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| Table 5.4.4 Pathway Dose Factors, R,- Adult, Grass-Cow-Milk 146.0 Table 5.5.1 Pathway Dose Factors, R,-Infant, Grass-Goat Milk I
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| 10.0 nm.
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| ~ '- ~~
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| wnn r ggy TMI Radiological Controis Departmental Procedure 8810-PLN-4200.01 Ties Rodn No.
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| Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS (Cont'd)
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| PART Ill EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 8*ction Page TABLES Table 5.5.2 Pattway Dose Factors, R, Chtd, Grass-Goat Milk 147.0 Table 5.5.3 Pathway Dose Factors R,- Teen, Grass-Goet-Mik I!;;, 148.0 Table 5.5.4 Pathway Dose Factors R,- Adult, Grass-Goat-Milk f
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| # 149.0 j%fp, %.*
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| Table 5.6.1 Pathway Dose Factors, R, - Iriant, Grass <mMeat *4 q %g 150.0 )
| |
| Table 5.6.2 Pathway Dose Factors, R, Chid, Grass-Cow-Mont4!g$l*%lA tg
| |
| ' 151.0 Table 5.6.3 Pathway Dose Factors, R, - Teen, Grass-Cow 44est 4%4 152.0 k,
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| l Table 5.6.4 Pathway Dose Factors, R, Adult, GrassdCowy 153.0 pq '"If Table 5.7.1 Pathway Dose Factors, R, Infant., 154.0 j Table 5.7.2 Pathway Dose Factors, R, Chld[Vpdatation 155.0 l
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| E lh Table 5.7.3 156.0 Pathway Dose ,f Factorsg'g W-Taen yp0etation Table 5.7.4 Pathway Dose Factors, R,Mdult, Vegetation 157.0 Table 8.1
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| ( ..df%
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| l Sample Colection and W Requirements 106.0 (i!!ih IlN";;;;1r-Table 8.2 Reporting Lesels fAr RadioactMty Concentrations in Environmental Samples 171.0
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| %f %
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| Table 8.3 Detection C9blities for Environmental Sample Analysis 172.0 Table 8.4 TMINS REMP Station Locations - Air Particulate and Air lodine 174.0 Table 8.5 174.0 TMINS REMP Station Locations - Direct Radiation (TLD)
| |
| Table 8.6 TMINS REMP Station Locations - Surface Water 176.0 Table 8.7 TMINS REMP Station Locations - Aquatic Sedenent 176.0 Table 8.8 TMINS REMP Station Locations Mik 177.0 Table 8.9 TMINS REMP Station Locations Fish 177.0 Table 8.10 TMINS REMP Station Locations Food Products 178.0 11.0 o n.
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| L
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| r I
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| mmon l
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| gy WI Radiological Contrds C=; r . A Procedure Tise - 6610-PLN-4200.01 newwon M.
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| I Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS (Cont'd) l PARTlit EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section l
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| Page TABLES MAP 8.1 Three M8e Island Nuclear Station Locations of Radiological Environmental 179.0 Monitoring Program Stations wnhin 1 M5e of the Sh ;
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| .g i MAP 8.2 Three M8e Island Nuclear Station Locatiorn of Radio'ogical Envir 180.0
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| \
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| Monitoring Program Stations within 6 miles of the Site / , %e#)
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| l MAP 8.3 ha.d?
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| Three Mee Island Nuclear Station Locations of RadiologicdEnvironmental 181.0 {
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| ! Monitoring Program Stations Greater then 5 mfes fromp Sg,
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| * i FIGURES % ig, 41 rig (%.
| |
| Figure 1.1 TMI 1 Liquid Emuent Pathways h 96.0 Figure 1.2 TMi-2 Liquid EfHuent Pathways =%{%,
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| .cag 97.0 if.
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| Figure 3.1 TMI-1 Uguld Redweste
| |
| * M f;**%gf ** 108.0 l
| |
| Figure 3.2 TMl 1 Liquid Waste Evaporators }%g 109.0 Figure 4.1 TMi-1 Gaseous Effluent Peshwa%,); -
| |
| % ys 124.0 Figure 4.2 TMi-1 Aux 86ery &elW / ben 1
| |
| ,,, %# )ndling Buadings Effluent Pathways .125.0 Figure 4.3 TMI-1 Reacter Bulding 19Buent Pattmey 126.0 l lh Figure 4.4 TMI-1 Condens%,
| |
| er Ollgas Emuont Pathway
| |
| '%, 127.0 Figure 4.6 TMi-2 Gaseous Emuent F8tration System / Pathways 128.0 Figure 6.1 Waste Gas System 15g.0 l
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| 12.0 na
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| )
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| i )
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| r Number I
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| gp TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 I Ties Asviolon No.
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| l
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| , ONsite Dose Calculation Manual (ODCM) 15 TASLE OF CONTENTS ' (Cont'd)
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| PARTIV REPORTING REQUIREMENTS Section Pese 1.0 TMl ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 185.0 2.0 TMI ANNUAL RADIOACTWE EFFLUENT RELEASE REPORT 186.0 3.0 PART IV REPERENCES f"*"%i, 188.0 Ni lil
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| ' gr , nin n9r APPENDICES
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| % 'ihn Y gb dii%um%.."?'!s %-
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| A. Pathway Does Rate Parameter (P) 4. 'iig '"*
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| E1 1
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| %n,. 'lni B. Inhahstion Pathway Dose Factor (R) g % E21 lll C. Ground Plane Pathway Dome Factor (RJ4:wiy[ E3-1 g% 'i! ii, i D. Grass-Cow-Mik Pathway Dose Factor (Q E4-1 I yer Me ;
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| E5-1 l E. Cow-Meet Pathway Dose Fad @),. itq, e k l F. E6-1 Vegetation Pathway Doe.,s,i' Factor.=-(RJ' -
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| f APPENDIX A F REFERENCES kh E7-1 Ni,/
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| l Number jgdgy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tith Revision No.
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| Offsite Dose Calculation Manual (ODCM) 11 l
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| TMI-1 RADIOLOG4 CAL EFFLUENT CONTROLS s 'inig.
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| Number gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 TW Revision No.
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| Offsite Dose Calculation Manual (ODCM) 11 1.0 DEFINITIONS The h wing terms are defined for uniform interpretation of these controls and surveillances.
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| 1.1 Reactor Operating Conditions 1.1.1 Cold Shutdown The reactor is in the cold shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is no more than 200* F. Pressure is defined by Technical Specification 3.1.2.
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| if"%g%
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| 1.1.2 Hot Shutdown f" k,, [
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| %?
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| The reactor is in the hot shutdown condition when it'Is. s0$ critical by at least one percent I
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| * '"41*
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| delta k/k and Tavg is at or greater than ,5m
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| %(iiir 525' F.g;If%
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| dijg 1.1.3 Reactor Critical *%g ;.,\
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| The reactor is critical wh n the neutronhhain reaction is self-sustaining and Keff = 1.0.
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| 1.1.4 Hot Standby gg.4*adllilg The reactor is in the hot stanb Nlon when all of the following conditions exist: '
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| j''N %g
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| : a. Tavg is greater than 525; F b.
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| a? %
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| The reactot Is criticaIm/
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| in "%
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| : c. Indicdfed neutron power on the power range channels is less than two percent of A g), Wrated 6wer.lii Rated power is defined in Technical Specification Definitioj 1.1.5 - Power Okadan 9gjs- + )
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| The r$ctor is in a power operating condition when the indicated neutron power is above two percent of rated power as indicated on the power range channels. Rated power Is defined in Technical Specification Definition 1.1. {
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| l 1.1.6 Refueling Shutdown j i
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| The reactor is in the refueling shutdown condition when, even with all rods removed. the reactor would be suberttical by at least one percent de!!a k/k and the coolant temperature at
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| {
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| the decay heat removal pump suction is no more than 140' F. Pressure is defined by i Technical Specification 3.1.2. A refueling shutdown refers to a shutdown to replace or Y rearrange all or a portion of the fuel assemblies and/or controi rods. !
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| f-gggy TMl Radiological Controls Departmental Procedure Number
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| ! rm 6610-PLN-4200.01 l
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| % on uo. )
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| Offsite Dose Calculation Manual (ODCM) 11 1.1.7 Refueling Operation An operation involving a change in core geometry by manlpulation of fuel or control rods when the reactor vessel head is removed.
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| 1.1.8 Refueling Interval Time between normal refuelings of the reactor. This is defined as once per 24 months.
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| 1.1.9 Startup
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| ,p@g The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical.
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| g/ *lhn %/
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| 1.1.10 Tave
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| *g%,).f,[
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| Tle.
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| Tave is defined as the arithmetic average of the $ Orr'peratures in the hot and cold legs of the loop with the greater number of readtor hoolant pumps operating, if such a distinction of loops can be made. '!i;i.
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| li 1.1.11 Heatup - Cooldown Mode
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| .eQ*%
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| The heatup-cooldown modeiegn ly *ge d.mg of reactor coolant temperature greater than 200* F and less than 525' F.
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| s i ii g 1.2 Operable ,!.y' "%if %
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| A system, subsystem, trainihomp%;n onent or device shall be OPERABLE or have OPERABILITY when it is capable of performing,lts specified function (s) and when all necessary attendant instrumentation ,
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| controls, electrical p6werscooling or seal water, lubrication or other auxiliary equipment that are required for the systsrh7 subsystem, train, component, or device to perform its function (s) are also capable of performlhg%thefrelated jk support function (s).
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| 1.3 Instrument bhainel%
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| Mk An instrument etEnnel is the combination of sensor, wires, amplifiers, and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, control, and/or protection. An instrument channel may be either analog or d'gital. ,
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| 1.4 Instrumentation Survellance 1.4.1 Channel Test "
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| A CHANNEL TEST shall be the injection of a simulated signal into the channel as close to l
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| the sensor as practical to verify OPERABILITY, including alarm and/or trip functions.
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| ; 1.4.2 Channel Check A CHANNEL CHECK shall be the qualltative assessment of channot behavior during operation by observation. This determination shall include, where possible, comparison of 16.0 ,
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| Number M Radidogical Contrds GUClear Departmental Procedure 6610-PLN-4200.01 Tme Revision No.
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| Offsite Dose Calculation Manual (ODCM) 11 the channel Indication and/or status with other indications and/or status derived from j independent instrumentation channels measuring the same parameter, i 1.4.3 Source Check A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
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| 1.4.4 Channel Calibration An Instrument CHANNEL CAllBRATION is a test, and adjustment (ll that the channel output responds with acceptable range and secura'Onecessary),
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| y to known values of to es the parameter which the channel measures or an accurate sir'mdation of these values.
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| Calibration shall encompass the entire channel, includind e,quiprlieN actuation, alarm, or trip and shall be deemed to include the channel test.
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| *g%%
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| 1.5 Dose Equivalent 1-131 4
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| %(**bg The DOSE EQUIVALENT l-131 shall beil 131 that concentrationh..
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| (microcurle/ gram) whhh alone k, would produce the same thyroid dose as the qdantity and isotopic mixture of I-131,1132,1-133, 1-134, and 1135 actually present. The thyroid dose conversion factors used for this calculation shdi be those listed in Table ill of TID 14844, ".Calculiiton of Distance Factors for Power and Test Reactor i Sites". [Or in Table E-7 of NRC Regulatory #,%Guide 1.109, Revision 1, October 1977.]
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| 3 1.6 Offstte Dose Calculation Manual (06CM)%
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| ,. O I The OFFSITE DOSE CALCULATION, MANUAL (ODCM) contains the methodology and parameters used in the calculation of bffsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liq 0kl effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radidogical Environihental Monitoring Program. The ODCM also contains (1) the Radiological Effluent Contrds, y n Radiological Environmental Monitoring Program and (3) descriptions of the information thafehanid bilncluded in the Annual Radiological Environmental Operating and Annual Radioactiveffflyfielease
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| +
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| Reports.
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| 1.7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and Installed to reduce radioactive gaseous effluont by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
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| 1.8 Ventilation Exhaust Treatment System A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiolodine or radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing lodine or particulates from the gaseous exhaust system prior to the release to the environment.
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| Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS.
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| 17,0 tm
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| mmo.r gp TMl Radiological Controls Departmental Procedure ns. 6610 PLN-4200.01 bWon No.
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| OffsNe Dose Calculation Manual (ODCM) 15 f.9 Purge Purging PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure. humidity, concentration or other operating conditions in such a manner that replacement air or gas is required to purfy the confinement.
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| 1.10 Venting VENTING is the controlled process of discharging air as gas from a cordinement to rnalntain temperature, presm:re, humidty, concentration or other operating conditions in such a manner that replaooment air or gas is not provided. Vent used in system name doesnot imply a VENTING process.
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| $ li.
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| 1.11 Member (s) of the Public pki 4;( j **"""
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| MEMBER (S) OF THE PUBUC shall Indude all persons whb occupationally asstnted with the plant. TNs category does not include employees b,i tho'GPU System. GPU contractors or vendors. Also excluded from this category are persans b enter the site to service equipment or to make deliverles-sig~
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| * f 1.12 Site Boundary lh t
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| %Q The SITE BOUNDARY used as the basis for the' limits on the release of gaseous effluents is as defined in Section 2.1.z.2 and shown.oq Figure 2.1-3 of the TMI-1 FSAR. This boundary line includes portions of the Susquehanne River surface between the east bank of the rtver and Ttree Mle Island and between ThreeWisid6d and Shelley Island.
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| The SITE BOUNDARY undf he is for the limits on the release of liquid efAuents is as shown in Figure 1.1 in Part I of this"ODCM.
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| yn Mis 1.13 Frequency Notatiegf]
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| The FREQU N TA ON specified for the performance of SurveRance Requirements shall correspond to the intervals defined in Table 1 1. AB Survesance Requirements stel be performed within th51 epecified time interval with a maximum allowable extension not to exceed 25% of the surveillance' interval The 25% extension appines to at frequency intervals with the exception of "F.*
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| No extension is allowed for intervals designated *F.*
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| Table 11 Frequency Notation Notation Frequency S Shiftly (once per 12 hours)
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| D Daly (once per 24 hours)
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| W Weekly (once per 7 days)
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| M MontNy (once per 31 days) 1B 0 nm.
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| ._3. . . .
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| Number gggp TMI Radiological Controls Departmental Procedure 6610MLN-4200.01 True Ftevision No.
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| Offsite Dose Calculation Manual (ODCM) 11 Notation Frequency Q Quarterly (once per 92 days)
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| S/A Semi-Annually (once per 184 days)
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| R Refueling Interval (once per 24 months)
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| P S/U Prior to each reactor startup, if not done during the previous 7 days P
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| Completed prior to ea,ch release N/A (NA) Not applicable f
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| %/
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| E s Once per 18 montig%
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| F on.?%
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| Not to e,xceed 24' months Bases 4 lh Section 1.13 establishes the limit for which the specified, time interval for Survellance Requirements may be extr.ded. It permits an allowable extension of the.. normal surveillance interval to faclitate survellance sc,xduling and consideratlun of plant operating" con lditionsihat may not be sultable for conducting the surveillance; e.g., transient conditions or otheiong61ridsurveillance or maintenance activities. It also provides flexibility to accommodate the lerigth p a fuel cycle for surveillances that are specified to be performed at least once each REFUEUNQ INTEpVAL lt is not intended that this provision be used repeatedly as a convenience to extend survellartce intervals beyond that specified for survellances that are not performed once each REFUEUNC INTERVAL Ukewise, it is not the intent that REFUEUNG INTERVAL surveHlances be performed during powerpperation unless it is consistent with safe plant operation. The lim!!ation of Section 1,13 is bisodion engineering judgement and the recognition that the most prooable result of any particular survellfahce jbeing performed is the verification of conformance with the Surveillance Requirements. This prosisidhis" sufficient to ensure that the reliability ensured through surveillance activities is not significantly d dsd, that obtained from the specll led surveillance interval.
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| gy TMI Radiological Controls D.p-1,,,.ca.; Procedure Number noe 6610-PLN-4200.01
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| %viam No.
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| Offsite Dose CalculeSon Manual (ODCM) 15 2.0 _CONTnGLS AND RASE 8 2.1 Radioactbo Emuent instrumertation 2.1.1 RadioactNe Liquid Emuent instrumentation CONTROL:
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| The radicactke liquid eNuent monitoring instrumentation channels shown in Table 2.: t infl be OPERABLE with their alarm / trip setpoints set to ensure tfut the limits of Control 2.2.1.-
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| are not exceeded The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSfTE DOSE CALCULATION MANUAL (ODCM).
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| ,y ne w APPUCABluTY: At all tirms * .g. %f,
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| !;j ACTION: Q%dlh.ig "q 9 ! ;3L %;t a.
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| With a radioactive Nguld ofRuont monhorirh instrumentation channel alarm / trip setpoint less conservative than required'by the above control, iminediately suspend the release of radioactive liquid emuent montored by the affected channel or deciere the channel inoperable.
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| b.
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| f% "%
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| With less than thepinirnum number of radioactive liquid eMuent monitoring instrumentation.charmeis' OPERABLE, take the ACTION shown in Table 2.1 1. Exert best eftorts tohum the instrumentation to OPERABLE status within 30 days and, if unsuccesehA, explain in the next Annual Effluent Release Report why the inoperabity was pot corrected in a timely rnanner.
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| f %g
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| *g% For 5 84, and RM-LE, operabilty is not required when discharges are y (&.,#spositively 3 controlled through the doeure of WDL-V257.
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| 4 "% %# For RM-L12 and associated IWTS/lWFS Row interlocks, operability is not 7
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| .,e Ma 9 1i required when discharges are positively controlled through the dosure of
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| *lrig % IW-V72, 75 and IW-V280, 281.
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| i g*
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| For FT 146, operabuity is not required when discharges are positively controlled through the closure of WDL-V257, IW-V72, 75 and IW V280, 281. {
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| i BASES The radioactke liquid affluent instrumentation is provided to monitor and control, as l
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| applicable, the releases of radioactive materials in liquid effluent during actual or potential t releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding ten times the ofRuent concentrations of 10 CFR Part 20.
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| F Number gp TMl Radiologmal Controls Departrnental Procedure me 6610-PLN-4200.01 new on No.
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| Offsite Dose Calculation Manual (ODCM) 15 Ta ble 2.1-1 Radioactive Liquid EMuent instrumentation Minimum Channels instrument Operable ACTION
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| : 1. Gross Radioectivity Montors p Providing Automatic Terminetton of Release p ny f" %(
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| gj
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| : a. Unit 1 Liquid Radwaste Effluent 1 ' %f, %ndl18 Line (RMM) ,,,,["t ,, %g.
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| : b. IWTS/lWFS Discharge uno (RM-L12)
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| %'%O6 4
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| 1
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| *%sq 4 5, 20
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| : 2. Flow Rate Measurement Devices j
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| : a. Unit 1 Uquid Radwaste Etauent %g i I 21 Line (FT 84) '%
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| 4"j#Angmig
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| : b. Station Emuent Discharge if ' *,. 1 21 (FT 146) [ ' "4. %,
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| ',p 4"j{tig"%mnTable Notation ACTION 18 With the number af ehannelif 0PERABLE less than required by the Minimum Channels OPERABE g
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| requirement, emu
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| * 4nt releases may continue, provided that prior to initiating a release:
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| qi, p
| |
| : 1. At lobst bo kid $hendent samples are analyzed in accordance with SurvellencaQ.2.1.1.1 and 3.'2,$,112 and; 9;p ti %
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| : 2. At fiast two technically qualificd members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup.
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| : 3. Director Operations and Maintenance TMI shall approve each release.
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| Otherwise, suspend release of radioactNo emuents vis this pathway.
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| ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may commence or continue provided that grab samples are collected and analyzed for gross radioactivty (beta or gamma) at a Ilmit of detechon of at least 1x10' microcuries/ml, prior to initiating a release and at least once per 12 hours during release.
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| 22.0 nm.
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| 3 --
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| Number TMI Radiological Controls ME Departmental Procedure 6610-PLN-4200.01 Tme Revision No Offsite Dose Calculation Manual (ODCM) 15 Table 2.11 (Cont'd)
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| ACTION 21 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, radioactNo ofRuont releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate Row.
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| gp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 tes Ammon No.
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| Offsite Dose Calculation Manual (ODCM) 15 2.1.2 Radioactke Gaseous Process and Emuent Monkoring instrumentation CONTROL-The radioactke gaseous process and emuent monitoring instrumen'.ation channels shown in Table 2.12 shall be OPERABLE with their alarm / trip setpoirts set to ensure that the limks of Control 2.2.2.1 are not exceeded The alarm / trip setpoints of these channels shall be determined in accordance wth the OFFSITE DOSE CALCULAllON MANUAL (ODCM).
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| APPLICABILITY: As shown in Yable 2.1-2.
| |
| fn w j 7(wiw#}
| |
| ACTION: n
| |
| : a. With a radioactke gaseous process or emuent mohltoring instrumentation channel alarm / trip setpoint less conservatke than requirsd.by the above control, immediately suspend the release of radioactNe, effl0ent monkored by the affected channel or declare the channel inoperables g%
| |
| : b. With less than the minimtsu number of r$bicactNe gaseous process or effluent monitoring instrumentation ciennels OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to retum the instrumentation to OPERABLE status wthin 30 days and, if unsuccessful,, explairn in the next Annual Ef!Iuert Release Report why the inoperabiky was,lnot conected in a timely menner.
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| ym BASES f*"!!;[0liq, T
| |
| The sadioatJve gas *eous affluent instrumentation is provided to monitor and cortrol, as applicable, the releases of radioactNe materials in gaseous emuent during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance wth NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are withiri the lirnits soecified in 10 CFR 20.1301.
| |
| g, %g 4atir The tow'ranho condenser off0as noble gas activity monitors also provide data for deterinination of steam generator primary to secondary leakage rate. Channel operability requirements are based on an ASLB Order No. LBP-84 47 dated October 31,1964, and as cited in 20 NRC 1405 (1984).
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| | |
| Nwnber y TMI Radiological Contrds Departmental Procedure 6610-PLN-4200.01 Tm. n.- wo.
| |
| Offsite Dosa Calculat" tan Manual (ODCM) 15 Table 2.1-2 (Corn'J)
| |
| Table Notation At all times.
| |
| ** During waste gas holdup system operetlon.
| |
| *** Operabaty is not required when discharges are positively controncd through the closure of WDG-V47 and where RM-A8 (or RM-A4 and RM-A6), FT-149, and FT 150 are operable.
| |
| **** During Fuel Handling Bunding ESF Air Treatment System Operation.
| |
| # At all times during containment purging.
| |
| ## At all times when condenser vacuum is established. /y,'..
| |
| ### During operation of the ventBation system. 1 k "K)
| |
| / Nihyf ACTION 25 Wah the number of channels OPERABW less than fEquiried by the Minimum Channels OPERABW requirement, the cortents of the tank"msf be released tu the environment prwided that prior to initiating the reisese:. gmyg *
| |
| % 7;g
| |
| : 1. At least two independent samples of the tank's contents are analyzed in accordance wth Tabie 3.2-2, item A, and % '
| |
| I
| |
| : 2. At least two technica9y.quellfied members of the Unt staff independently verify the release rate calculations and worify the discharge valve lineup.
| |
| # Ui
| |
| : 3. des Malrtenance TMI, shall approve each release, The Directorf h'llpg, Otherwise, suspend releaseLof radioactive effluent via this pathway. ,
| |
| ACTION 26
| |
| / %%/
| |
| WRh the number #l channels OPERABW less than required by the Minimum Channels l
| |
| j OPERABLEmrequiromant, ofnuent releases via this pathway may continue provided the flow l rate is satimated at least once per 4 hours. I w y ACTION 27 With tbo .nUmbor of channels OPERABLE less than required by the Minimum Channels OPERABtf requirement, otRuent releassa via this pathway may continue provided Grab qk a$nplei are talon at least once per 12 hours and the intilal samples are analyzed for gross abtMty (gamma scan) wthin 24 hours after the channel has been declared inoperable. If RM-A9 is dedared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, item C.3.f.
| |
| ACTION 30 1. Wah the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable gas channel (s) at least once per 24 hours. With both channels inoperable, a grab sample shan be collected and anatyred for the Inoperable gas channel (s):
| |
| (a) at least once per 4 hours during dg.ssing operations.
| |
| (b) at least once per 24 hours 4Wa ciner operations (e.g. Feed and Bleod).
| |
| 29.0 m
| |
| | |
| 1
| |
| %mtper y TMl Radiological Controls Depenmental Procedure 661pLN 4200.01 rm. n m n rei.
| |
| Offsite Does Calculagon Manual (ODCM) 15 Table 2.1-2 (Cont'd)
| |
| : 2. If the inoperable gas channel (s) is not restored to service within 14 days, a special report shen be submitted to the Regional Administrator of the NRC Region 1 Omce and a copy to the Director, Office of inspection and Enforcement within 30 days of declaring the channel (s) inoperable. The report shall dowribe (a) 9m cause of the monitor inoperabity, (b) action being taken to restore the instrument to serv 6ce, and (c) action to be taken to prevent recunence.
| |
| ACTION 31 With the number of channels OPERABE less than required by the Minimum Channels OPERABE requirement, emuent releases via thii pathway may cortinue provided that within four hours eher the channel haE.been declared inopeiAde, samples are continuously collected with auxlied ,arnpling$quipment.
| |
| ACTION 32 With the number of channels OPERABE required by the Minimum
| |
| ~
| |
| Channels OPERABE requirement, ellluent release 6 via this pathway may continue for up to 28 days, provided that one OPL%ABLE bhannel remains in service or is placed in service within 1 hour. After (deye, or if one OPERABLE channel does not remain in service or le not pleoed in servloe within 1 hour, the prov6elone of Techn: col Speelllection 3.0.1 apply, se il thle Control were a Tech Spec IJmiting Condition' lor sOperation.
| |
| }"% %
| |
| ACTION 03 With the number of (:harojels OPERABE less than required by the Minimum Channels OPERASW.pequirWnent, either restore the Inoperable channel to OPERABE sisi0s WithiriJ days, or propero and submit a special report withat 30 days ouWrqin(the acdon(s) taken, the cause of the InoperabOty, and plaru and
| |
| ~
| |
| schedule for re"etoring the sywom to OPERABLE status.
| |
| pu%
| |
| e %g%g iwii!!' I Q,QJ \
| |
| sp; 9Iig l
| |
| l l
| |
| 30.0 nn.
| |
| l I
| |
| | |
| F 1 l
| |
| I
| |
| ! Number l gy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
| |
| ** nen No.
| |
| Offsite Dose Calculation Manual (ODCM) 15 2.2 Radioactive Effluent Controls l
| |
| 2.2.1 Uquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL: ,
| |
| I l The concentration of radioactive material reisesed at anytime from the unit to unrestricted areas shall be Ilmited to ten times the concentrations specNied in 10 CFR Part 20.1001-20.2401, Appendix B. Table 2, Colurnn 2 for radionudide&other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the* concentration shall be limbed to 3 x 10* uCl/cc total activity.
| |
| /"[% f %
| |
| APPUCABluTY: At all times %g% fi"4Og;4 ACTION: q *
| |
| * g, b Wth the concentration of radioactive material released from the unit to unrestricted areas i exceeding the above limts, immedist5fy restore concentrations within the above limits, i
| |
| %dli, ;
| |
| BASES g "g This control is provided IqM'INut'the concentration of radioactive materials released in liquid waste affluent from the_ unit to unrestricted areas wil be less than ten times the concentration levels specifiedJn 10 CFR Part 20.100120.2401. Appendix B, Table 2. This limitation provides"addllional. assurance that the levels of radioactbo materials in bodies of water outside thi*ste wil"not result in exposures with (1) the Section ll.A design objectives of Appendix is10 CPRfart 50, to a MEMBER OF THE PUBUC and (2) the limits of 10 CFR
| |
| , Part 20.1301 to the population The concentration limit for noble gases is based upon the assumptiori the XB-136 la the controlling radioisotope and its MPC in air (submersion) was i corWortid,to'an"squivalent concentration in water using the rnethods described in l
| |
| IntemellonelCommission on Radiological Protection (ICRP) Publication 2.
| |
| mgr 3;.-
| |
| 2.271.2 Uguid Effluent Dose CONTROL
| |
| ! The done or dose commitment to a MEMBER OF THE PUBUC from radioactive materials in l liquid effluents released from the unit to the SITE BOUNDARY shall be limited:
| |
| : a. During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or ectual to 5 mrom to any organ.
| |
| : b. During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrom to any organ.
| |
| APPUCABluTY: At all times 31.0 nm.
| |
| -- ~
| |
| | |
| Numbw TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 M8 Revee6on No.
| |
| Offsite Dose Celculation Manusi (ODCM) 15 ACTION:
| |
| : a. With the calculated does from the release of radioactivu rnatorials in liquid offluents exceeding any of the above limits, prepare and submit to the NRC Region i Administrator within 30 days, a Speclei Report which identlRes the cause(s) for exceeding the limit (s) and risAnos the corrective actions to be taken to reduce the rolesses of radioactive meterials in liquid alliuents during the remainder of the current calender quarter and during the d==1" ant 3 calender quarters so that the curnuletive does or does commkment to any individual from such releases during these four colonder quarters is wthin 3 mrom to the total body and 10 mrom to any organ. This Special Report shall also include (1) td req of radiological analyses of the drinidng water source, and (2) the radiologioel impeet on finished drinking water supplies with regard to the requirements *of 40 CRil41, Safe Drinidng Water Act.
| |
| %ig'f 4y.
| |
| k:k.
| |
| BASES q,q%2h%
| |
| 4it.
| |
| This control and associated action is provideItchement the requirements of Sections ll.A. Ill.A and IV.A of Appendtx 1,10 CFR Part 50 The Control implements the guides set forth in Section ll.A of Appendk I. The ACTION statements provide the required operating Sext Rky and at the same tirne implement the guides est forth in Section IV.A of Appendix i to assure that the rolesses of,sadioactive, material in liquid elliuents wIl be kept "as low as is reasonably achiewable". Ale 6, fo(fresh water elles with drinking water supplies which can be potentially allected by plant" operations, there is reasonable assurance that the operation of the incBty wlN not reendt in" enc 5enuclide concentrations in the finished drinidng water that are in excess of the reqtsromonts of to CFR 20. The dose calculations in the ODCM implomont The requiremente*in Section lit.A. of Appendix i that conformance with the guides of Appendix l is 16 lse shown'by calculational procedures based on modelo and data such that the actual esposurefist a MEMBER OF THE PUBUC through appropriate pathways is unlikely to be subistemeldy underestimated. The equations speclNed in the ODCM for ceictAating the dosee'elue'io the actual release rates of radioactive meterleis in liquid elliuents are con'letsit e whidhe methodology provided in Reguletory Guide 1.100, 'Calctdetion of Annual Dosesh 14sn from Rotaine Releases of Reactor Efiluents for the Purpose of Evaluating Compilence with 10 CFR Part 50, Appendk 1," Revision 1. October,197/, and Reguietory Guide 1.113, " Estimating Acrsatic Dispersion of ElRuents from Accidental and Routine Reactor Releases 8ar % t'urpose al implementing Appendix 1,* Aprg,1977. NUREG4133 .
| |
| provides methods for does calculations consletent with RegiAatory Guides 1.109 and 1.113. j 2.2.1.3 Liquid Radweste Treatment System COMROL:
| |
| The appropriate portiors of the liquid radweste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid ofnuent from the unit to unrestricted areas would exceed 0.06 mrom to the total body or 0.2 mrom to any organ in any calendar month APPUCABILITY: At all times 32.0 m ;
| |
| 4
| |
| -..5.. . . ._. .
| |
| | |
| Number
| |
| - gp TML Radlological Cortrols Depr.rtrnental Procedure 6610-PLN-4200.01 i
| |
| . . No.
| |
| Tite 15 Offsite Dose Calculation Manual (ODCM)
| |
| ACTION:
| |
| : a. With radioactive liquid weste being di:$erged without trestrnent and in excess of the above llrnits, prepare and submit to the NRC Region i Adminletrator within 30 days, a Special Report which includes the following information
| |
| : 1. Explanation of why liquid radwaste was being discharged without treatment, identlAcation of any (noperable equipment or subsystems, i
| |
| and the reason for inoperabilty, jar,,,
| |
| : 2. to OPERABLE Action (s) taken to restore the 1 status, and, / hy#
| |
| g Sl%f b
| |
| : 3. A summary description of action (s)*taken to prevent a recurrence
| |
| %%%4 ''
| |
| BASES *tg i4
| |
| 'gg%
| |
| The requirement that the appropriate portions of this system be used, when specthed, provides assurance that the releases of radiondive meterials in liquid almuents we be kept as"lowns is reasonably achievable. This cortrol implements the requirements 0010 CFR Part 50.36a, General Design Criterion 80 of Appendix A to 10 CFR Past 5G[and bio design otMe ghen in Section ll.D of Appendix ! to to CFR Part 50 Jhs lesent dSection ll.D. le to reducei 6". ue ts to as low as is reasonably, 'in a cost effective manner, This cortrol sehenes this intent by solablishing a doce limit which is a small fraction (.25%) of Section ll.A of Appendk I,10 CPR Part 50 does requirements. This mergin, a factor of 4, constitutes a reasonable reduction.
| |
| ,+ = ''g, 2.2.1g (M oidup Tanks l s.~s
| |
| ,% s' col 4 TROL 1 f%* I
| |
| 'k %
| |
| The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tr'tlum and dissolved or entrained noble gases. l
| |
| : a. Outside temporary tank APPUCA8luTY: At all times.
| |
| ACTION:
| |
| : a. With the quantsy of radicadive meterial in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank conterts to within the hmit.
| |
| em.
| |
| 33.0
| |
| | |
| Number ggy TMI Radiological Controls Departmental Procedure 6610-Pt.N-4200,01 Tese w nrm Offsite Dose Calculation Manuel (ODCM) 15 BASES Restricting the quantty of radioactive material contained in the spectied tanks .
| |
| I provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of to CFR Part 20.1001-20-20.2401. Appendtw B Table 2, Column 2, at the nearest potable water j supply and the nearest surface water supply in an unrestricted area. l 2.2.2 Gaseous EfRuent Controls 4
| |
| 2.2.2.1 Gaseous Erluent Dose Rate i[#_'lip CONTROL * [ 16,J The does rate due to radioactive materials release us affluent from the ske shall be limited to the following:
| |
| \ p\?! uua,b'. *
| |
| : a. For noble gases: less than or equal to' 600 mrom/yr to the total body and less than the skin, arb or equal to 3000 mrom/yr to,10,
| |
| : b. For 1-131,1133, trtium and alaradionuclides in particulate form with half lives greater than 8 days:, lees tharior equal to 1500 mrom/yr to any organ, g m APPUCABluTY: At au thW!
| |
| ACTION: .
| |
| g wg)g "
| |
| [ yl kin,/
| |
| Wth the release rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above lirnit(s).
| |
| kg'@%
| |
| BASESN .d
| |
| + "Q W TheMrdprovides reasonable assurance that the annual dose at the SmE BOUNDARY from. gaseous enluont from at unts on the site wig be within the annual dose limts of 10 .
| |
| I CFR fart 20 for unrestricied areas whBe providing sufficient operational flexibuty in establishing effluent montor setpoints. These gaseous release rates prcNide reasonable assurance that radioactive material discharged in gaseous ofnuent wRl not result in the exposure of a MEMBER OF THE PUBUC in an unrestricted area, ekher wthin or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B. Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBUC who may at times be within tne SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBUC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary The specined release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBUC at or beyond the SITE BOUNDARY to less than or equal to 500 mrom/ year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limtts also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year (NUREG 0133).
| |
| 34.0 p.
| |
| w ,e e me s . e gesymme a age n + eg =
| |
| * Numtw
| |
| -gy TML Radiological Controls Departmental Procedure 6610-PLN-4200.01 ns. nn np..
| |
| Offette Does nahdasaan Manuel (ODCM) 15 2.2.2.2 Gaseous Emuents Dose-Noble r W CONTROL-The air does due to noble games released in gaseous emuents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the followmg
| |
| : a. During any calendar quarter; less than or aquel to 6 mrad for gamma radiat8on and less then or equal to 10 mrad for beta radiation and,
| |
| : b. During any calendar year: less then or equal to 10 lor gammq radiation and less than or equal to 20 mrad for/beta radiativg yd f lj(%
| |
| APPUCABluTY: At en times. , %[
| |
| b ACTION:
| |
| %qymsh l
| |
| : a. With the calculated air Jose from radloectNo noble gases in gaseous emuents
| |
| =-ding any of the above, limits, propero and submit to the NRC Region i Adminletrator within 30 dayeYa Special Report which identmos the cause(s) for exceeding the ilmit(s) and eleAnos the corrective actions that have been taken to reduce the roleseos sht,the M corrective actions to be taken to assure that w*==4=nt release,s weite,in compilance with the above ilmas.
| |
| BASES f"*%
| |
| sY } lease of radioactNo motorials in geneous emuents from TMI to the re TNs cored g%"
| |
| This cormeFand aseeciated actlpn k provided to irnplement the requirements of Section 11.8, fil.A andlygd Wk I,10 CFR Port 50. The Control implements the guides set forth in Sectionll.Bfflppendk 1. The ACTION etatements provide the required operating fleulbuity andist the,same time implement the guides set forth in Section IV.A of Appendk I to aneure 4lithetths releemos of radioactive material in gaseous emuents wE be kept "as low as is reasonably achievable? The Surveillance Requirements implomont the requirements in Socilon Ill.A of Appendk i that conformance wth the guides of Appendk I be shown by ceiculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBUC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters aurahilahed in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous eNuents are conslatent with the methodology provided in Reguietory Guide 1.109,
| |
| " Calculation of Annual Doses to Man from Routine Release of Reactor Emuents for the Purpose of Evolusting Compliance wth 10 CFR Part 50. Appendk 1
| |
| * Revielon 1 October 1977 and Reg tatory Guide 1.111," Methods for Estimating Atmospheric Transport and j
| |
| Depersion of Gaseous Emuents in Routine Releases from Ught Water Cooled Reactors,"
| |
| I Revision 1. July 1977. The ODCM equations provided for rfetermining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
| |
| NUREG4133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
| |
| nm.
| |
| 35.0
| |
| ~
| |
| ).
| |
| 1
| |
| | |
| nantin TMl Radlological Controls gp Depenmental Procedure 6610-PLN-4200.01 m n.m onsste pose coloutanon Manual (oocu) is 2.2.2.3 Dose lodine 131, lodine-133, Tritium, and Radionuclides in Particulate Form CONTROL:
| |
| 1 The does to a MEMSER OF THE PUBUC from lodine-131, lodine-133, Tritium, and all !
| |
| radionuclides in particulate form with hell thes greater than 8 days, in gaseous alltuerfs l released froen the unit to areas et and beyond the SITE BOUNDARY shall be limited to the fokwing-
| |
| : a. During any calender quarter: less than or aquel to 7.5 prom to any organ, and
| |
| : b. During any calendar year: less than or equal to,15snrem to any organ.
| |
| / '%
| |
| t APPUCABluTY: At all times. % / wf ACTION: p%.$4 With the calculated dose from the release fod 131, lodine 133, Tritium, and radionuclides in particidate form wit 4helf lives gj ester than 8 days, in gaseous alguents exceeding any of the above limits, papero and submit to the NRC Region i Adminletrator within 30 days, a Special Reportwhich identmos the cause(s) for exceeding the limit and defines the corrective actions that have. boon taken to reduce the rolesses and the proposed conective actions to be talien tefassure that subsequent releases wW be in compliance with the above limits. %f' BASES jil lN[,%j%.
| |
| Q/
| |
| This control appNes to the release of radioactive meterials in gaseous elliuents from TMI-1, f4 '%ip This coritral anil..casociated action is provided to implement the requirements of Section ll.C.
| |
| Ill.A ampl IV.A g hppendk I,10 CFR Part 50. The Controls are the guides est forth in Se016pn tip $r Appendk 1. The ACTION statement provides the required operating flexibilty tan 4stil;4iname time implements the guides set forth in Section IV.A of Appendk i to asse thpt P4 teleases of radioactive meterials in gaseous ofRuants wpl be kept "as low as is dennably achievable
| |
| * The 00CM omloulational methods speelflod in the survetlance requirements implement the requirements in Section lil.A of Appendk I that conformance with the guides of Appendk I be shown by ceiculational procedures bened on models and data such that the actual exposure of a MEMSER OF THE PUBUC through appropriate pathways is unl5cely to be substantially underestimated The ODCM calculationet methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consletent with the methodology provided in Regulatory Guide 1.109,
| |
| " Calculation of Annual Doses to Men from Routine Releases of Reactor EfRuonts for the Purpose of Evaluating Compliance with to CFR Part 50, Appendk 1,* Revision 1. October, i 1977 and Regulatory Guide 1,111,
| |
| * Methods for Esemating Atmospheric Transport and )
| |
| Dispersion of naamma Efiluents in Routine Reisenes from Ught-Water-Cooled Reactors," l Revision 1, July,1977, These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, lodine 133, tettium and radionuclidos in particulate form with half lives greater than 8 days ;
| |
| are dependent upon the existing radionuclide pathways to men, in areas at and beyond the
| |
| . SITE BOUNDARY. The pathways that were examined in the development of these 36.0 m. I
| |
| -- -v
| |
| | |
| I l
| |
| I Number gp TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01
| |
| {
| |
| {
| |
| me n. mon No. )
| |
| Offsite' Dose Calculation Manual (ODCM) 15 I
| |
| calculations were: 1) Individual inhaintion of airbome radionudides,2) depostion of radionuclides orno green leafy vegetation wth subsequent consumption by man, 3) depoeltion onto grassy areas where mBk animals and meet producing animale graze wtth
| |
| {
| |
| consumption of the mIk and meet by man, and 4) deposition on the ground wth subesquent exposure of mort
| |
| )
| |
| 2.2.2.4 Gaseous Redweste Treatment System CONTROL The GASEOUS RADWASTE TREATMENT SYSTEM and the VkNTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE The approylele portidns of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to readcoltalinoctive materials in the gaseous weets prior to their discharge when the rnonthly $rojected Oaseous effluent air doses due to untreeded gaseous ellluont reiseses frem the unit would exceed 0.2 mrad for Damma radiation and 0.4 mrad for beta radistituwJ$b aswopriate portions of the VENTILATION EXHAUST TREATMENT SYETEWfshall IMused to reduce radioactive materials in Daseous weste prior to their discherpiwhen the montNy projected doses due to geneous ofnuant releases from stie would exceed 0,3 mrern to any orgart APPLif'ABiUTY: At aR times.
| |
| Anah jnp$ \
| |
| ACTIO 9:
| |
| glin,.jfd %
| |
| : a. With the GASE D8h4DWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TPIEATMENT SYSTEM inoperable for more than a month or with gaseous waste hsng' discharged without treatment and in excess of the above limits, prepare and eLtsnit to tto NRC Region I Administrator within 30 days, a Special Report which includes the following infortnation:
| |
| (p n
| |
| %%ff'r%
| |
| ' %p[***Milication inoperabilty, of the inoperable equipment or subsystems a
| |
| % ibib Action (s) taken to restore the Inoperable equipment to OPERABLE stctus, g and
| |
| : 3. A surrs # wcription of action (s) taken to prevent a recurrence.
| |
| BASES The use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials Ir. gaseous ofnuents wil be kept 'as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36s, General Design Criterlon 60 of Appendix A to 10 CFR Part 50, and the desion objectives given in Section 11.D of Appendix 1 to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the systems were specahed as a.,sultable fraction of the guide set forth in Sections ll.B and II.C of Appwfix 1,10 CFR Part 50, for gaseous affluents. ,
| |
| 37.0 m l
| |
| L
| |
| | |
| Number gp TMI Radkiicslcel Controls Departmental Procedure 6610-PLN-4200.01 n.v on ee.
| |
| me 15 Offsite Dose Calculation Manual (OOCM) i 2.2.2.5 Explosive Gas Mixture CONTROL f
| |
| The concentration of oxygen in the Waste Gas Holdup System shall be limited to less than or aquel to 2% by vdume whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume.
| |
| AVAILABILITY: At all times.
| |
| ACTION:
| |
| ,q.
| |
| 4[*4%
| |
| &, jV Whenever the concentration of hydrogen in the Waste Gas Floidup' System is greater than or equal to 4% by volume, and; ,%gf
| |
| %4
| |
| : a. The concertration of oxygen in the Waste Gss Holdup System is greater than 2%
| |
| by vdume, but less than 4% by vdums}withoUt delay begin to reduce the oxygen conw eeks, to within its limit. i
| |
| %g%
| |
| g
| |
| : b. The concentration of oxyger(in the Waste Gas Holdup System is greater than or equal to 2% by vdume/immediately suspend additions of waste gas to the Waste Gas Holdup System and wthout delay begin to reduce the oxygen concentration to within its limt. 3, 9
| |
| BASES:
| |
| '# "% k,
| |
| # L .,
| |
| Based on experimental data (Reference 1), lower limits of flammobity for hydrogen is 5%
| |
| and for oxygin M 6% by volume. Therefore, if the concemration of either gas is kept below k lower limit! the other gas may be present in higher amounts wthout the danger of an exploeldsjnktise. "2M#g the concentrations of hydrogen and oxygen such that an exploelwe mbture does not occur in the waste gas holdup system provides assurance that the'telease 'of radioactive materials wil be controlled in conformance wth the requirements tof Seneral' Design Cetterlon 60 of Appendix A to 10 CFR 50.
| |
| R
| |
| * REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammabity of Gases and Vapors.
| |
| 2.2.2.6 Waste Gas Decay Tanks CONTROL-The quantty of radloactivty comained in each waste gas decay tank shall be limbed to less than or equel to 8800 curles noble gases (considered as Xe-133).
| |
| APPLICABILITY: At all times.
| |
| mu 38.0
| |
| | |
| I l I Number d TMl Radiological Controls 4 MI Departmental Procedure 6610-PLN-4200.01
| |
| . ton teo.
| |
| Trlie 1
| |
| 15 l Offsite Dose Calculation Manual (ODCM) 1 1
| |
| l ACTION:
| |
| : a. With the quantky of radioactNo material in any waste gas decay tank exceeding the l above limt. Immediately suspend all addhions of radioactNo rnatorial to the tank I
| |
| and wthin 48 hours reduce the tank contents to wthin the limit.
| |
| BASES Restricting the quantRy of radioactivty contained in each waste gas decay tank provides assurance that in the event of an uncontroRed release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBUC at the n$arest' exclusion area boundary wil not exceed 0.5 rom. This is consistent wth Standard Review Plan 15.7.1, " Waste Gas System Falure?
| |
| a f*!)
| |
| %g %
| |
| 2.2.3 Total Radioactke Efeuent Cortrols
| |
| %%%4 2.2.3.1 Total Dose % %
| |
| 41!;>W CONTROL:
| |
| 1 The annual (calendar year) dose"or ddse cornmtment to any MEMBER OF THE PUBUC, due to releases of radioactivitpand to udietion from uranium fuel cycle sources shall be limited to less than or aquel to 26,tnrem to the total body of any organ except the thy old, which shall be limtted }o less than or equal to 75 mrem.
| |
| p "% "%
| |
| APPUCABluTY: At ~ timesi
| |
| $ %f ACTION: Ng g
| |
| With the'ghcalctAsled dose trorn the release of radioective materials in liquid i
| |
| i sfRuente exopeding twice the limits of Controls 2.2.1.2.a. 2.2.1.2.b, 2.2.2.2.a. 2.2.2.2.b, l 2.213 der [2 2.2.3.b, calculations should be made including direct radiation contributions
| |
| <tromine unkt and from outside storage tanks to determine whether the above limits of Csntrol 2.2.3.1 have been exceeded. If such is the case, prepare and submk to the NRC l
| |
| Radion i Administrator within 30 days, a Specle! Report which defines the correctNe action I to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limts and indudes the schedule for achieving conformance wth the above limts. This Special Report, as defined in 10 CFR Part 20.2203(b), shaR include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBUC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that i Includes the release (s) covered by this report, it shall also describe levels of radiation and l l
| |
| ' concentrations of radioactke rnatorial involved, and the cause of the exposure levels or concentrations, if the estimated dose (s) exceed the above limits, and if the release l condtion resulting in violation of 40 CFR 190 has not already been corrected, the Special
| |
| (
| |
| Report shan include a request for a variance in accordance with the provisions of 40 CFR ,
| |
| l 190. Submittal of the report is considered a timely request, and a variance is granted untu I staff action on the request is complete.
| |
| un, 39.0 f
| |
| i 1
| |
| i
| |
| )
| |
| | |
| l TMI Radiologkal Controls p Departmental Procedure 6610-PLN-4200.01 me . u..
| |
| Offsite Dose Calculation Manual (ODCM) 15 BASES This control is provided to meet the does limitations of 40 CFR Part 100 that have been incorporated into 10 CFR Part 20.1301(d). This contrel requires the properation and submRtal of a Special Report whenever the calculated doses from plant generated radioactive emuents and direct radiation exceed 25 mrom to the total body or any organ, except the thyroid, whldt shal be limited to less then or equal to 75 rnrem. For altos containing up to 4 reactors, it is highly unlikely that the reedtant dose to a MEM8ER OF THE PUBUC we a=ceart the does limits of 40 CFR Part 190 if the individual reactors remain within twice the does design objectives of Appendix 1, and if direct radiation doess from the reactor units and outside storage tanks are kept small. The $$odial Report wil describe a coures of action that should result in the Rmitadon of the arstuel dose to a MEMBER OF THE PUBUC to within the 40 CFR Part 190 limits. FoptGpurposes[of the Special Report, it may be soeumed that the does commitment to thefnenter of the public from other uranium fuel cycle sources is negligible, with the a= cat *w) thg(dese contributions from other nuclear fuel cycle facIlties at the some sRe or within a fadiutpff km must be considered if the does to any member of the public is estimated to guceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release condalons resuhing in violation of 40 CFR Part 190 have not'eiready been corrected), in accordance with the provisions of 40 CFR Part 19h.11 and 10 CFR Part 20.2203(b), is conaldered to be a timely request and fulmis the requhements of 40 CFR Part 190 unti NRC staff action is cGe-f " The vartence only reistes td the limits of 40 CFR Part 190, and does not apply in any way to the other requiremesis for does limitation of to CFR Part 20, as addressed in Corytrols 2.2.1.1 and 2.2.2.13Ah Irisididual is not consulered a MEMBER OF THE PUBUC during any period in %%/she is engaged in carrying out any operation that is part of the p h W
| |
| %+,)
| |
| 3.0 SyRVEILLANCES 4(,k 3p 4 yp 3.1 Radioactive E mentation
| |
| + L %4 3.1.1 Radienctus Uquid Effluent instrumentation 41% [%g
| |
| * Requirements
| |
| $6pvoillance 3.1.1.1 Each radioactive liquid emuent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAUBRATION, AND CHANNEL TEST operations during the MODES and at the frequencies shown in Table 3.1 1.
| |
| 40.0 l
| |
| | |
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| |
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| |
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| |
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| |
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| |
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| |
| f L
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| | |
| Number gp TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01
| |
| : m. .1. _ {. No.
| |
| Offsite Dose Calculation Manual (ODCM) 15 Table 3.11 (Cont'd)
| |
| Table Notation The CHANNEL TEST sher also demonstrate that automatic isolation of this pattmey and control rJom alarm (1) annunciation occurs if the following condition exists:
| |
| : 1. Instrument Indicates menevred levels above the high alarm / trip setpoint. (includes - circuit failure)
| |
| : 2. Instrument indicates a down scale fature. (Alarm function only.) (includes - circuit failure) w Instrument controls moved from the operate mode (Alarm function o{nly).
| |
| : 3. !!i
| |
| / ,%iw/
| |
| lon shall be performed using (2)
| |
| The one orinitial more ofCHANNEL CAUBRATION the reference standards forNational certmed by the radioactivity Bureau a measurement ly(Standards or using s have been obtained from suppliers that pstticipated in measurespetageurance actMties with NBS. These standards should permit ceHbrating the system over its intended"mnge'of energy and measurement ren0s.
| |
| For subsequent CHANNEL CAUBRATION, sources that have tisan'related to the inittel celibration should be used. (Operating plants may substitute previously established cellbration procedures for this requirement)
| |
| M CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK (3) shal be made at leset once dasy on any da on which"sontinuous, periodic, or batch releases are mode.
| |
| $ )$nu,
| |
| ,(s v 4
| |
| CA;,ggf!
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| s s
| |
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| |
| k, 42.0 rim
| |
| | |
| Number gp TMi Radiological Controls Depanmental Procedure 6610-PLN-4200.01 Title Reve No.
| |
| Offsite Dose Calculation Manual (ODCM) 15 3.1.2 RadioactNo Gaseous Process and Efnuent Monitoring instrumentation SURVEILIANCE REQUIREMENTS 3.1.2.1 Each radioactNo gaseous process or enluont monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TE8!T operations at the frequencies shown in Table 3.12.
| |
| h;pa ggk lj.
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| TMl Radiological Controls I Departmental Procedure 6610-PLN-4200.01 Tm. nww.n No.
| |
| Offsite Oose Calculation Manual (ODCM) 15 Table 3.1-2 (Cont'd)
| |
| Table Notation At all times.
| |
| ** During weste gas holdup system operation.
| |
| *** Operabilty is not required when discharges are positively controlled through the closure of WDG V47, and where RM-AB (or RM-A4 t M RM-AS), FT-149, and FT-150 m operable.
| |
| **** During Fuel Handling Buliding ESF Air Treatment System Operation.
| |
| # At all time? during containment purging. pg
| |
| ## At aR times when condoneer vacuum is estabilshed. f 4
| |
| ### During operation of the ventembon system.
| |
| f p
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| |
| (1)
| |
| The CHANNEL TEST shat also demonstrate that automatic isolation of this pathway for the AuxElary and Fuel Handling Buuding ventiatbn System, the supplyventRatidn '
| |
| is isolated and control room alarm annunciation occurs if the following condition mgsuists:;g%
| |
| : 1. Instrument indicates measured levels above the hl0 h alarm / trip setpoint (Includes circut falure). h
| |
| .rPf, ig
| |
| : 2. Instrument indicates a down sceile failur% (Alarm function only) (includes circuit failure).
| |
| .e x
| |
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| |
| g m!{g, (2) The CHANNEL TEST shal[alsIo demonstrate that control room alarm annunciation occurs if any of the foRowing condtions amist: %#
| |
| : 1. Instruytsdicates measured levels above the alarm setpoint. (includes circut falure)
| |
| , Qf%
| |
| : 2. Instrursent Indicates a down scale faBure (includes circut fature).
| |
| 4 Mig "
| |
| : 3. Instrument controls moved from the operate mode.
| |
| The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be (3) performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppi'ers that participate in measurement assurance activities wth NBS. These standards should permit calt) rating the system over ks intenM range of energy and measurement range. For subsequent CHANNEL CAUBRATION sources that hc.9 been related to the initial calibration should be used. (Operating plants may sut stitute previously established callbration procedures for this requirement.)
| |
| The CHANNEL CAUBRATION shall include the use of standard gas samples containing a nominal:
| |
| ( (4)
| |
| : 1. One volume percent hydrogen. balance ntrogen, and
| |
| : 2. Four voluu percent hydrogen. balance nitrogen.
| |
| 47.0 vm
| |
| | |
| Numtw TMI Radiological Controls E Departmental Procedure 6610-PLN-4200.01 Revtsson No.
| |
| Tme Offsite Dose Calculation Manual (ODCM) 15 l
| |
| Table 3.1-2 (Cont'd)
| |
| The CHANNEL CALIBRATION shaR include the use of standard gas samples containing a nominal:
| |
| (5)
| |
| : 1. One volume percent oxygen, balance nitrogen, and
| |
| : 2. Four volume percent oxygen, botance nitrogen. g
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| --Qgy TMI Radiological Controis Departmental Procedure Tate 6610-PLN-4200.01 Reveon No Offsite Dose Calculation Manual (ODCM) 15 3.2 Radioactive Efiluents 3.2.1 Liquid Effluents SURVEll1ANCE REOUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivity content of each batch of radiomethre liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 3.21. The results of pre-release analyses shall be used wth the calculational methods in the OOCM to assure that the concentration at the point ofielease is maintained within the limits of Control 2.2.1.1. i;g/
| |
| 3.2.1.1.2 Post-release analysis of ammples, composted from batch releases shall be performed in accortlance withTable 3.21. The results of the previous post-release analysis-shall be used wth the caletdational methods in the ODCM to assure that the concentrations at the point of release were,fmaintained within the limits of Control 2.2.1.1.
| |
| ciaE!
| |
| 3.2.1.1.3 The radioactivky(oorwntration of liquids discharged from release polpts. shall be determined by collection and analysis of sarpplosin accordance with Table 3.21. The results of the analysis
| |
| ,shall be used with the calculational rnethods of the ODCM to assure (impfts at Control 2.2.1.1.that the concen: ration at tlie point of rele j%
| |
| fQ 3.2.1.2 Done,CalctAations
| |
| [ .s ;!%
| |
| s
| |
| : q. 311.2.1) Cumulative dose contributions from liquid effluents shall be
| |
| (% %# determined in accordance wth the Offsite Dose Calculation Manual
| |
| .%g p %,.(%
| |
| (ODCM) at least once a motth.
| |
| 3.2.'1;3, Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.
| |
| 49.0 n. .
| |
| ). _ _ _ . . ----- - . - - - - - -
| |
| | |
| l 1
| |
| 1 Number TMI Radkdogical Controls r Departrnented Procedure 6610-PLN-4200.01 Title Rwleton No.
| |
| Offalte Doao Calculation Manual (ODCM) 15 3.2.1.4 Uquid Holdup Tanks 3.2.1.4.1 The quaney d radioactive meterial cortained in each d the tanks specified in Control 2.2.1.4 shall be determined to be within the limt by anatyring a representative sample of the tank's content weeidy when radioactive materials are being added to the tank.
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| * Number TMI Radidogical Controls I Departmental Procedure 6610-PLN-4200.01 Tie. Rowmon No.
| |
| Offsite Dose Calculation Manual (ODCM) 15 Table 3.2-1 (Cont'd)
| |
| Table Notation ,
| |
| 1
| |
| : a. The Lt.D is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that wR yield a not count above system background that will be detected with 96% probab51ty with 5% probabilty of falsely conduding that a blank observation represents a " rear signal. ,
| |
| .'or a particular measurement system (which may indude radiochemical separation): !
| |
| LLD = 4.66 L 3 E x V x 2.22 x 10' x Y x exp (-A At) f ['%w/
| |
| # j%/
| |
| Where: %% ,
| |
| T"kadL."
| |
| i above (as microcurie per unit mass or LLD is volume), the "a priorr lower limit of detection as define (ig %
| |
| A s,is the standard deviation of the backgrourxi, counting rats or of the counting rate of a blank sample as appropriate (asf81g counts per minuto))%
| |
| j E is the counting efficiency (as counts per, disintegration), j me 5,.y i
| |
| .r'IME.E .
| |
| V is the sample size (in units:ci ma,ss$,.or,vdume).
| |
| l )
| |
| 2.22 x 10' is the numberh> djiinta0 rations per minute per microcurie, r %g Y is the fractional,radioche'liical r yield (when applicable),
| |
| kj#i 4 A is the radioactive decay constant for the particular radionuclide, and l q%g em,ha At is the,el,apted" time Detween midpoint of sample collection and time of counting.
| |
| y
| |
| * Typical values of E, V, Y and At shal be used in the calculation.
| |
| It should be recognized that the LLD is defined as an *a priorr (before the fact) limit represerWn0 the capabilty of a measurement system and not as an "a posteriorr (after the fact) limit for a particular measurement
| |
| : b. 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 which is representative of the liquids released,
| |
| : c. To be representative of the quantitles and concentrations of radioactive materials in liquid effluent, samples shall be cdlocted continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, au samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the affluent release.
| |
| 53 0 nm.
| |
| | |
| )
| |
| l Number ggy ,
| |
| TMI Reddogical Controls Departmental Procedure 6610-PLN-4200,01 inn - n. mon m.
| |
| Offatte Dose Calculation Manual (OOCM) 15 Tabic 3.2-1 (Cont'd)
| |
| : d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each tntch shall be isciated, and be thoroughly mixed, by a method described in the ODCM, to assure representative sempling.
| |
| i
| |
| : n. A continuous release is the discharge of Ilquid wastes of a non discrete volume; e.g., from a volume or system that has an input flow during the conthuous release.
| |
| : f. The principal gamma emitters for which the LLD speelRcation applies exclusively are the following radionudides: Mr> 54, Fe 59, Cn-58, Co40, Zn45, McF99, Co-134, Csl3RCo-141, and Ce-144.
| |
| This list does not mean that only these nuclides are to be considerid. Other gamma peaks that are identinable, together with those of the above nuclidos, shall aled'be snelyzed and reported in the
| |
| ~
| |
| Annual Radioactive Effluent Reisese Report pursuant to TS,6A4 j/*
| |
| bl33. M ii"
| |
| + $l?'"!msMj;,.
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| |
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| }
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| )
| |
| Number gp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
| |
| : m. mw n so Offette Dose Calculation Manual (ODCM) 15 3.2.2 Gsseous Efiluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The does rate due to noble Oases in gaseous eMuents shall be determined to be within the limts of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM.
| |
| 3.2.2.1.2 The dose rate of radioactive meterials/NNthan noble gases, in gaseous affluents shall be determined to be within the limits of Controt 2.2.2.1.b in accordance with methods'ind pr6cedures of the ODCM by obtalning representative samples"and performing analyses in accordance with the samplir@ and~enelysis program, specified in Table 3.2-2. gen %.'[g'i'
| |
| *as %
| |
| 3.2.2.2 Dose, Noble Gas '$ig 4 iP 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quadetand current calendar year shall be determined in accordanos wittitt3e OFFSITE DOSE CALCULATION MANUAL (ODOM) mo.ntNy..n m.,
| |
| . nM'*k #lill i
| |
| 3.2.2.3 Dose, lodined31',~10dinar 133. Tritium, and Radionuclides in Particulate Form 3 ,
| |
| 3.2.2.3/pIis ' Cumulative dose contributions from lodine-131, lodine-133, Tritium,
| |
| #" %g and radionuclides in particulate form with half lives Greater than 8 days for the current calendar quarter and current calendar year shall d
| |
| im
| |
| # f% be determined in accordance with the OFFSITE DOSE CALCULATION g%%;%g%
| |
| W / MANUAL (ODCM) monthly. l i
| |
| @%lil.2 2.4 %Giseous Waste Treatment k-I ha 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected montNy in accordance with the ODCM.
| |
| 3.2.2.5 Explosive Gas Mixture 3.2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be wkhin the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monhors covered in Table 2.12 of Control 2.1.2.
| |
| 55.0 nm.
| |
| | |
| Nurnbw A TMI Radiological Controls W I Departmental Procedure 6610 PLN4200.01 Ties NWon No.
| |
| 15 Offsite Dose Ca!!:ulation Manual (ODCM) 3.2.2.6 Wasta Gas Decay Tank 3.2.2.6.1 The concentration of radioactMty contained in the vent header shall be determined weeldy. If the concentration of the vont header exceeds 10.7 Cl/cc. dah samples shall be taken of each waste gas decay tank being added to, to determine if the tank (s) is less than or equal to 8800 O/ tank.
| |
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| mmber TMI Radiological Controls Depenmental Procedure 6610-PLN-4200.01 no. n *on 6.
| |
| ONefte Dose Calculation Manual (ODCM) 15 Table 3.2-2 (Cont'd)
| |
| Table Notation
| |
| : a. The LLD is defined, for purposes of this survellence, as the smalloot concentration of radioactive material in a sample that wSI yloid a not count above system background that wtl be detected with 95% probabity with 5% probabilty of falsely concluding that a blank observation represents a " rear signal.
| |
| For a parbcular measurement system (which may include radiochemical separation):
| |
| jm%:q LLD = 4 06 sL 5 x V x 2.22 x 10' x Y x exp (-A At) 4 p f Where q"ag !'hm [kwM T5%d, %;q,.
| |
| jy.
| |
| LLD is the "a priorf" lower IM of detection as defineel above (as' microcurie per unt mass or volume),
| |
| d!
| |
| '"%{li:
| |
| s,is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as cuunts per minima)hj, fHg 4.
| |
| 3 E is the counting emcloney (as couits gleintegration),
| |
| V la the sample stre (in units d volume),
| |
| # kb. .h 2.22 x 10' is the number of disintegrations per minute per microcurie, 7 "%
| |
| Y la the fractional at$ocherbical yleid (when applicable),
| |
| # ,iP A is the ry ,p kd constant for the particular radionuclide, and
| |
| : b. 'I%
| |
| At is the elapsed, time between midpoint of sample collection and time of counting, y
| |
| * Typical valuies of E, V, Y and at shall be used in the calculation.
| |
| It should be recognized that the LLD is defined as an "a priorr (before the fact) limit r.piM6i the capabilty of a measurement system and not as an "a posteriorr (after the fact) limit for a particular measurement.
| |
| : b. Sampling and analysis shal also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUlVALENT l-131 concentration in the primary coolant has not increased rnore than a factor of 3; and (2) the noble gas activity monitor shows that efRuont activity has not increased by more than a factor of 3.
| |
| : c. Tritium grab samples from the spent fuel pool area shall be taken at least once per 24 hours when the refueling canal is flooded.
| |
| 60.0 nm
| |
| | |
| Nweer TMl Radiological Controls y Departmental Procedure 6610-PLN-4200.01 Time nwn on No.
| |
| ONsite Dome Calculation Manual (ODCM) 15 Table 3.2-2 (Cont'd)
| |
| : d. Charcoal cartridges and particdote futers shal be changed at least once per 7 days and analyses shall be comple*ed within 48 hours after changing (or after removal from sampler),
| |
| : e. Tritium grab semples shal be taken weekly from the spent fuel pool ares whenever spent fuel is in the spent fuel pool.
| |
| i
| |
| : f. The reslo of the sample flow rate to the sempted stream flow rate shall be known for the time period i
| |
| coered by each does or dose rete omiculation made in accordance wy" Controls 2.2.2.1,2.2.2.2, and 2.2.2.3. f~ li h k excidelvely are the following
| |
| : g. The principal gamme emitters for which the L1D specification eh" tor gn radionudides: Kr-87, Kr-88, Xe 133, Xe-133m, Xe-136 andM ,,38 1 Fe-59, Co-68, Co40,2n-66 Mo40, Cs-137, Co 141 and Co.144 for particdato emloelons. This list does not mean that only these nuclides are to be corm!Other gamma peaks that are ,
| |
| l identulable, together with those of the above nuclides, shall alsh be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to yTS 6.9.4.
| |
| i '
| |
| : h. Applicable only when condenser vacuum is wahuahed Sampling and analysis shen also be performed followin0 shutdown, startup, er a3HERMAL POWER cher.Je exceeding 15 percent of RATED THERMAL POWER wa .hin one hour unless (1) analysis shows that the DOSE EQUfVALENT l l 131 concentration in the primaryfoolaint has not increased more than a factor of 3; and (2) the noble gas actMiy monitor shows tfiillMlluint activty has not increased by more then a factor of 3.
| |
| g g
| |
| : 1. Gross Alpha, Sree, and St to, analyloos do not apply to the Fuel Handling Building ESF Air j.
| |
| Treatment a System. gj(w$
| |
| If the Condonnerysnt,Sta i Continuous lodine Sampler is unevellable, then altamete sampilng equipment wIl he placed in service within 48 hours or a report wtl be prepared and submitted within
| |
| ~
| |
| 30 days frorithe tg#ie sampler is found or made inoperable which ide itlhes (a) the cause of h l inoperablitk(b) the action taken to restore representative sampling r apahuty, (c) the action taken to preventdeurrence, and (d) quantification of the release via the pathway during the period and comparfehn to the limits prescribed by Control 2.2.2.1.b.
| |
| g
| |
| : k. Applicable only when condenser vacuum is established.
| |
| : l. Applicable when liquid redweeta is moved or processed within the facility.
| |
| : m. Bodine semples only required in the Chemical Cleaning Building when TMI 1 liquid redweste is stored or processed in the facIlty.
| |
| 1 61.0 **
| |
| | |
| Wmber ggy TMI Radiological Controls Departmental Procedure 661HLN-4200.01 Tme Mmdekm No.
| |
| Offsite Dose Calculation Manual (ODCM) 15 3.2.3 Total Radioactive Effluents 3.2.3.1 ' Does Calculation 3.2.3.1.1 Cumulative annual dose contributions frorn liquid and gaseous ellluents shall be determined in awA>ce with SurveNances 3.2.1.2.1,3.2.2.2.1. and 3.2.2.3.1, including direct radhtlon contributions from the Unit and frorn outside storage tanks, and in accordance with the methodology contained in the ODCM.
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| 62.0 mm 4
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| | |
| Number I
| |
| gggp TMI Radiolo0lcal Controls Departmonal Procedure 6610 PLN-4200.01
| |
| ~
| |
| Revisnan No. I l
| |
| onsite cose calculation manual (oocu) 15 l
| |
| 4.0 PART I REFERENCES 4.1 Title 10, Code of Federal Regulations," Energy" l
| |
| l 4.2 Regulatory Guide 1.100 ' Calculation of Annual Donos to Man from Routing Releases of Reactor l' Emuents for the Purpose of Evaluating Compliance with 10 CFR Past 50, Appendix 1,
| |
| * Revision 1, October 1977 3 i
| |
| 4.3 TMi 1 Technicaf Speellications, attached to Facky Operating Ucense No. DPR-50 l 4.4 TMI-1 FSAR p,gn''illi p bg k h
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| j!l
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| Number TMl Radiological Controls g Departmental Procedure 6610-PLN-4200.01 wen No.
| |
| rm.
| |
| 15 Offsite Dose Calculation Manual (ODCM) p t::n, i' 4p ,
| |
| ! ai
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| .di Oh, M TMI-2 RADIOLOGICAL EFFLUENT CONTROLS
| |
| + w pNui$ lI 1.. ..npIbi;!
| |
| . uww m "sIl l]!'
| |
| k,% jaNig,!$
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| ''lig tow 64.0
| |
| | |
| m mter TMi Radiclopcal Controls I Departmental Procedure 6610-PLN-4200.01 T** nween No.
| |
| l Offsite Does Calculation Manual (ObCM) 15 I PART11 Definitione 1.0 DEPINITIONS
| |
| .QfFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part 11 of the ODCM.
| |
| g qf %g 1.2 Post-Defueling Montored Storage (PDMS) is that condtion 14 ng has boon aleen4Jp period has been shipped completed, off-site the core and the facility debris has been removed placed in a stable,from the reactor safe and'eec during_the,ise condition ACTION (T9llg'tg
| |
| %2h'#
| |
| ki 1.3 ACTION shall be those addtional requirements specified at corotary statements to each control and shall be part of the controls. ll ,
| |
| OPERABl.E - OPERASIUTY jn %id5: 3, 1.4 A system, +;":m, train, Nice shall be OPERABLE or have OPERABluTY when it is capable of performing ks spscent fdistion(s). Implicit in this definklon shall be the assumption that eN necessary atendant irstrumettation, controls, normal and emergency electrical power ,
| |
| sources, cooling or seeljditer71stylestion or other auuliary equipment, that are required for the l system, subsystem, train, component or device to gerform ks function (s), are also capable of l performing their related support function (s).
| |
| M E CAUBRA 6 .%( ,#% g/
| |
| 1.6 A CHANNE(CALIBRATION shall be the adjustment, as neccesary, of the channel output such that it responds"wth necesesry range and accuracy to known values of the parameter which the chamel monitors. The CHANfEL CALIBRATION sheH encompass the entire channel including the sensor and alarm and/or trip functions, and sher include the CHANNEL FUNCTIONAL TEST. CHANNEL CAUBRATION may be performed by any series of sequential, overlapping or total channel steps ,
| |
| such that the entire diennel is calibrated. I CHANNEL CHECK 1.6 A CHANNEL CHECK shall be the quahtative assessment of channel behavior during operation by observation. This determination shen include, where possible, comparison of the channel indication and/or status with other Indicattorr and/or status derived from independent instrument channels measurin0 the same parameter.
| |
| 65.0 om
| |
| | |
| Number gp' TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 T* w.on No.
| |
| ONsite Dose Calculation Menual (ODCM) 15 CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shal be:
| |
| : a. Analog channels - the injection of a slmtAated signal into the channel as close to the primary l sensor as practicable to verify OPERABlWTY including alarm and/or trip functions.
| |
| : b. Bistable channels - the injection of a simulated signal into the channel sensor to e h OPERABlUTY Including alarm and/or trip functions.
| |
| SOURCE CHECK )
| |
| {geg% 1 I
| |
| 1.8 A SOURCE CHECK shall be the qualitative assessment of char $ response % the channel sensor is exposed to a redlonctive source. / ,p *%#
| |
| eig%
| |
| NfE COMPOSITE SAMPLE
| |
| .97"%kb.4" 1.9 A ( OMPOSITE SAMPLE is a combination of Individusi samples obtained at regular intervals over a t
| |
| time period. Either the volume of each IndMdual sample is proportional to the flow rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the compoelte. $,
| |
| GRAB SAMPLR *%Q' %
| |
| j p#%g 1.10 A GRAB SAMPLE is an individg. Med in less than fifteen minutes.
| |
| BATCH RFI FASE (i; M d %wf A BATCH RELEASE is didischarge of fluid waste of a discrete volume.
| |
| 1 11 pn mis CONTINUOUS RELEASE
| |
| (#4g 1.12 A CONTIN MEL E is the discharge of fluid waste of a non-discrete volume. e.g., from a volume g ,that has an input flow during the CONTINUOUS RELEASE.
| |
| SITE BOUNDARY N-hi, i
| |
| 1.13 The SITE BOUNDARY used as the basis for the limits on the release of gaseous ernuents is as i defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI 1 FSAR. This boundary line includes portions of the Susquehanna Rher surface between the east bank of the river and Three Mlle Island and between Three Mle island and SheNey Island.
| |
| The SITE BOUNDARY used as the basis for the limits on the rolesse of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM. l FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION spedied for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time irderval with a maximum allowable extension not to exceed 25% of the sursellance interval.
| |
| i 66.C mu
| |
| | |
| 1 Number ggy WI Radiological Controls Departmental Procedure 6610+LN-4200.01 no. n.uon re.
| |
| Offsite Dose Calculation Manual (ODCM) 15 i
| |
| TABLE 1.1 Frequency Notation NOTATION FREQUENCY S (Shirliy) At least once per 12 hours.
| |
| /
| |
| D (Dely) At least once per 24 hours.
| |
| n W (Wooldy) At least once por 7 da .,w %Jilj M (Monthly) At least once perg31 da'ys,,/
| |
| "h f a,, %f Q (Quarterty) At least once per Rit..dnys.
| |
| . 4TPSib$h "
| |
| SA (SenAAnnuaNy) At least.once per 184 days.
| |
| 5 491 A (Annua 8y) ,At least once per 12 months.
| |
| lili E
| |
| %Jileast once per 18 months.
| |
| .pfy '%
| |
| N.A. 4i! jhi,3,,g;,Not applicable.
| |
| l .
| |
| i fra'... w;"? , '"!!n, t
| |
| j P i!,! Completed prior to each release p ,.
| |
| ,. ti
| |
| .Mt 'iii!!ngn!#
| |
| h, 2
| |
| giim4: '!!i4,
| |
| '!l gifiESiih Ylh T
| |
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| |
| % %s.
| |
| i ihi.qj;ing
| |
| .M Nhn 9:
| |
| ki, 4
| |
| l l
| |
| tim 67.0
| |
| | |
| m men, gy TMI Radiological coratois Departmental Procedure 6610-PLN-4200.01
| |
| : m. .s _ z m.
| |
| Offsite Dose Calculatkm Manual (ODCM) 15 l
| |
| 2.0 CONTROLS AND BASES 2.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control.
| |
| 2.0.2 Adherence to the requirements of the Control and/or associated ACTION within the specllied time interval shell constkute compliance wf.h %e control, in the event the Control is restored prior to expiration to the specified time interval, completion of the ACTION statement is not required 2.0.3 in the event the Control and associated ACTION requiremordI$$rmot be satisfied because of circumstances in excess of those addressed in the Conteol, inkisie appropriate actions to rectify the problem to the extent possible under the cinsUrnstancesfand submk a special report to the Commission pursuant to TMI-2 PDMS.Tichnical Specification (Tech.
| |
| Spec.) Section 6.8.2 within 30 days unless otherede T haQ*
| |
| 4li; kig 2.1 Radioactive Emuent instrumentation q A, 2.1.1 Radioactive Liquid Efiluent instrumentation 4 k
| |
| Redlonctive Liquid Efluent instrumentation is common between TMI-1 and TMI-2. Controls, appilcability, and actions are specifled lin ODCM Port 1, Control 2.1.1 Radioactive Geseous $ end Pmcess'jLn-Etnuent Monitoring instrumentation 2.1.2 )
| |
| g " 'g, g CONTROL: 1 j(44%af The radioactive gessous process and affluent monitoring instrumentation channels shown in Table 21(sher tdOPERABLE v.ith their alarm / trip setpoints set to ensure tw the limits of Control t.gJ. fare not exceeded The alarm / trip setpoints of these channels sheA be de pecordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
| |
| g PUCABILITY. As shown in Table 2.1-2.
| |
| ACT60N:
| |
| : a. Wah a radioactive gaseous process or effuent monitoring instrumentation channel elarm/ trip setpoint less consenettve than required by the above control, immediately suspend the release of radioactive elfluent montored by the affected channel or declare the channel Inoperable.
| |
| : b. With less than the minirnum numoer of radioactNe gaseous process or ofnuent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.12. Exert best efforts to retum the instrumentation to OPERABLE status within 30 devs and, N unsuccessful, explain in the next Annuel Emuent Release Report why the inoperab8Ry uns not corrected in a timely menner.
| |
| 68.0 m.
| |
| )
| |
| | |
| Number gp TMI Radiological Controls Departenental Procedure 6610-PLN-4200.01 Tise Revenson No.
| |
| Offsite Dose Calculation Manual (ODCM) 15 l
| |
| BASES The radioactive gaseous offluent instrumentation is provided to rnonitor and cor; trol, as applicable, the releases of radioactive materials in gaseous ofnuent during actual or potential rensases The alarm / trip setpoints for these instruments shall be calculated in acconiance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limts specified in 10 CFR 20.1301.
| |
| I p#io.ingI!!i. !
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| I .
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| n
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| b 4!h, E,ii jig;i kg, ''$ 4p
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| 41jo.
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| / ''ll;g %.s gydfii Ig
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| : s. s
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| ,N!!i. N its 4liig gi ig,
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| 'li!
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| lii I
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| I l
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| 69.0 sms
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| 7..;
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| t sIE l
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| I 8
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| i 3 .s d
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| gii,j,
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| 1 k }
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| *Q 2$
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| f 5 l
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| ft lllillillit 8a n a 3
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| Ra s a a 11 i:i a[ 1l I il it a o i s o -
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| I wumt.
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| -~gy TMI RadiologicalControls Departmental Procedure 6610-PLN 4200.01 f
| |
| nm n re. j Tme Onsite Dose Calculation Manual (ODCM) 15 2.2 Radioactive E%ent Controls i
| |
| 2.2.1 Uquid Efiluent Controis 2.2.1.1 Uguld Ef!Iuent Concentration CONTROL:
| |
| The concentration of radioacttve maternal released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendtz B, Table 2, Column 2. # ""%d
| |
| [
| |
| APPUCABluTY: At all times # hwM 9I
| |
| %f ACTION: % ig 9?%d,!N."h With the concentration of radioactive materialfeleased from the unit to unrestricted areas exceeding the above Emits, immediately restonconcentrations within the above limits.
| |
| BASES 4
| |
| %(
| |
| This control is provided to ensure that the concentration d radioactive materials released in liquid waste affluent from tis unl(to unrestricted areas will be less than ten times the concentration levels ad l$ 10"CFR Part 20.100120.2401, Appendix B, Table 2. These Controls permit flexibIlty undeI" unusual conditions, which may temporarily result in higher than normal roleeseelbut stil within ten times the concentrations, specified in 10 CFR 20. It is expected that by uilng this Sexibility under unusual condtions, and exerting every effort to keep levels of radloactive material in liquid wastes as low as practicable, the annual releases wRl not e*: sed.,a smsil fraction of the annual average concentrations specified in 10 CFR 20.
| |
| As a resill mthis Cortrol provides reasonable assurance that the resulting annual exposure to an indlwiduelg~ olf-site areas wIl not exceed the design ob}ectives of Section fl.A of Apdendis i to 10 CFR Part 50, which were established as requiremerts for the cleanup of g%ilrt% NRC's Statement of Policy of AprI 27,1981.
| |
| 21.i2 Uquid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBUC from radioactive materials in liquid effluerts released from the unit to the SITE BOUNDARY shall be timbed:
| |
| : a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.
| |
| : b. During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrem to any organ.
| |
| APPUCABluTY: At all times p.
| |
| 71.0
| |
| | |
| Numon TMl Radiological Controla y Departmental Procedure 6610-PLN-4200.01 RWon No.
| |
| noe 15 Offsite Dose Calculation Manual (ODCM)
| |
| ACTION:
| |
| : a. With the calculatetl does from the release of radioactbo materials in liquid erguents avana4g any of the above limits, propero and submit to the NRC Region f Administrator within 30 days, a Apar4al Report which IderMes the cause(s) for awrearting the limit (s) and delines the correctNo actions ' : be taken to reduce the rolesses of radioactive meterials in Ilquid emuents during c e remainder of the '
| |
| current calendar quarter and during the subsequert 3 calender quarters so that the ,
| |
| cumulative does or does commitment to any indNidual from such releases during I
| |
| thees four calender quarters is within 3 mrom to the total. body and 10 mrom to any organ. This Special Report shall also include (1) thd0ssLil,of radiologimi analyses of the drinidng water source, and (2) the radiolo water supplies with regard to the requiremente%gicil impact on f 401CFRif41, Safe Drinidng Water BASES mjh*
| |
| This Control requires that the does to offsite h be limited to the design objectNes of Appendk i of 10 CFR Part 50. This wHl assure this does received by the public during PDMS t is equNelent to or lees than that frorda normal operating reactor. The limits also assure that the erwironmental impacts are canaisient with those mah in NUREG4883, the TMI-2 Programmatic Erwironmentallenpact Susement (PElS). The ACTION statements provide the required flext Ilty un6er unusuel[ conditions and at the same time implement the guides set forth in Section IV.A of $ppendix IWassure that the reiseses of radioactNo meterial in liquid emuents wel be kept5 ladr ails c::- : y achievable". The dose ceiculations in the ODCM implement,thkrequirimerts in Section 111.A. of Appendix 1 that conformance with the guides of Appen$k i le to be shown by ceiculational procedures based on models and data such that the" actual =vpamme of a MEMBER OF THE PUBUC through appropriate pettways is unikely&be subsentially underestimated. The equations speclRed in the ODCM for calculating,.hf8t pees due to the actual reisess rates of radioactive materials in liquid empents erey cosibistent with the methodology provided in Regidatory Guide 1.109,
| |
| " Calculation of Annual Doses to Man from Routine Releases of Reactor EfRuonts for the Wurpose of Evolusting Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October, 1977, and Reguistory Guide 1.113, " Estimating Aquatic Dispersion of Emuents frorn Acdidental and Routine Reactor Relamaan for the Purpose of implementing Appendix f," Apri, 1977. NUREG-0133 provides methods for does calculations consistent with Regulatory Guides 1,109 and 1.113.
| |
| 2.2.1.3 Liquid Radweste Treatment System CONTROL:
| |
| The appropriate portions of the liquid redweste treatment system shall be used to reduce the radioactNe meterials in liquki wastes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrom to the total body or 0.2 mrom to any organ in any calendar month.
| |
| APPUCABluTY: At all times 72.0 m we +eme . = = -
| |
| ammans e , , ,
| |
| | |
| Numbw ggy TMt Radiological Controls Departmental Procedure 6610-PLN-4200.01 two n.m.n m.
| |
| Offsite Dose Calculation Manual (ODCM) 15 ACTION:
| |
| : a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region i Administrator within 30 days, a Special Report which Indudes the following information:
| |
| : 1. Explanation of why liquid redwaste was bein0 discharged without treatment, identincation of any inoperable equipment or subsystems, and the reason for inoperabuity, ja;g If '%
| |
| : 2. Action (s) taken to restore the Inoperable equipment to OPERABLE status, and, / %r,y#
| |
| . %,4
| |
| : 3. A summary description of actlim(s)itaken to prevent a recurrence
| |
| #Wmmfp*
| |
| BASES '!iti i
| |
| %.g*
| |
| The requirement that the appppriate portions of this system (shared with TMI-1) be used, when specined, provides assurance that the releases of radioactive materials in liquid ofRuonts wIl be itept sis low as is reasonably achievable This control implements the requirements of4$0 CFR Part 50.36a, General Design Criterion 80 of Appendix A to 10 CfH Pirt 50 and the design objecove given in Section 11.D of Appendk I to 10 CFR Part"56.' The intent of Section ILD. is to reduce sinuents to as low as is ressorsbl9 abhievable in a cost eMoctive manner This control satisfies this intent byhtablishing a dose limit which is a small fraction (25%) of Section ILA of Appentik 1,'"togCFR Part 50 dose requirements. This margin, a factor of 4, constitsia a reasonable reduction.
| |
| 9% *%,
| |
| 2.2.2 Gaseous EMluent Controls g *" g l 2.2.231 'hoseb6s EfRuont Dose Rate
| |
| .g gM4 4 CONtRob The dose rate due to radioactive materiais released in gaseous effluent from the site shall be l limited to the following.
| |
| : a. For noble gases: less than or equal to 500 mrom/yr to the total body and less than or equal to 3000 mrom/yr to the skin, and ;
| |
| : b. For tritium and al radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrom/yr to any organ.
| |
| APPLICABluTY: At all times.
| |
| ACTION:
| |
| With the release rate (s) exceeding the above lirnits, immediately decrease the retsase rate to comply with the above limit (s).
| |
| 73.0 m
| |
| | |
| Number TMl Radiological Controls
| |
| - I Departmental Procedure 6610-PLN-4200.01 TWe Revteson No.
| |
| Offsite Dose Calculatijn; Annual (ODCM) 15 BASES The control provides reasonable assurance that the annual dosa at the SITE BOUNDARY from gaseous alliuent from all unks on the she wRl be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. At the same time, these Controls permt flodbilty under unusual condtions, which may temporarly result in higher than the design objective levels, but stl4 wethin the dose limits speellied in 10 CFR 20 and within the design objectives of Appendh I to 10 CFR 50. It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive materlal in gaseous wastes as low as pra*ahia, the annual releases will not exceed a small fraction of the annual dose limits speellied in 10 CFR 20 and wE not restAt in doses which exceed'the design objectives of the cleanup of TMI-2 by the Appendk NRC's Statement I to of10Policy CFR 50,27,1981.These of Apri which weregas endorsed ous as limits Jor]ielease" rates provide reasonable assurance that radioactive material discharged"In gaseous effluent wil not result in the exposure of a MEMBEM OF THE PUBUC in ar(unrestricted area, other within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values speellied in Appendtx B, Table 2 of 10 CFR Part'20 FWMEMBERS OF THE PUBUC who may at times be wthin the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBUC wRl be suNicioney low to corppensate fofany increase in the atmospheric diffusion factor above that for the exclusion area boundary. The speelhed release rate limks restrict, at all times, the corresponding gamme and beta dose rates above background to a MEMBER OF THE PUBUC at,or beyondjhe SITE BOUNDARY to less than or equal to 500 mrom/ yew to the total bog [orfojess than or equal to 3000 mrem / year to the skin. The absence of iodine ensures that the c6rresponding thyroid dcee rate above background to an infant via the inhalatiorIpstlN)s less than or equal to 1500 mrem /yr (NUREG 0133), thus there is no need to speelly dose rate Ilmts for these nuclides.
| |
| j!f" %/
| |
| 2.2.2.2 Gase6idEffluents Dose-Noble Gases 94 '"%
| |
| 00 gf Thialr idh to noble gases released in gaseous efRuonts from the unit to areas at and ondp' SITE BOUNDARY shall be limited to the following:
| |
| gny%g
| |
| : a. During any calendar quarter: less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for t:ota radiation and,
| |
| : b. During any calendar year: less than os c qual to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
| |
| APPUCABluTY: At all times.
| |
| ACTION:
| |
| : a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region i Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding thu. .Jmit(s) and defines the c:Jective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases wHI be in compliance with the above lunits.
| |
| 74.0 un.
| |
| | |
| l i
| |
| Numter gg ml Radiological Contrds Departmental Procedure Ties 6610-PLN-4200.01 Revte6on No.
| |
| OffsNe Dose Calculation Manual (ODCM) 15 BASES This contrd applies to the release of radioactive materials in gaseous effluents from TMI-2.
| |
| This control and associated action is provided to implement the requirements d Section 11.8.
| |
| lil.A and N.A of Appendk 1,10 CFR Part 60. The Controlimplements the guides set forth in Section li.B of Appendk 1. The ACTION statements provide flexibilty under unusual conditions and at the same time implement the guidos set forth in Section IV.A of Appendix l to assure that the releases of radioactive anatorial in gaseous effluents wlN be kept "as low as is reasonably achievable.' The Survolliance Requirements irnplement the requirements in Section Ill.A of Appendk I that conformance with the guldepof Appendk i be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBUC through the appropriate pathways'is.unlikely to be substantially undersetimated. The does calcWation rnsthodology and. parameters established in the ODCM for calculating the doses due to the actual release . rates d radioactive noble gases in gaseous e9uents are consistent with w methodologl[provided in Regulatory Guide 1.109,
| |
| " Calculation of Annual Doses to Man from Routinepelease of Reactor EfRuonts for the Purpose of Evaluating Compliance with 10 CFR fad 50, Appendk 1,* Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmosphenc Transport arxf Diepersion of Gzoous Effloonts in Routine Releases from Ught-Water Cooled Reactors,'
| |
| Revision 1 July 1977. The ODCM eqastions provided for determining the air doses at and beyond the SITE BOUNDARYe are based upon the historical average atmospheric conditions.
| |
| NUREG4133 provides methods St dose calculations consistent with R*gulatory Guides 1.109 and 1.111. ""!G '"
| |
| [#hlig 'bly 2.2.2.3 Dose - lodm&131, '
| |
| lodine-133 Tritium, and Radionuclides in Particulate Form CONTROL: #(( %wn/
| |
| p %,
| |
| The dose jo a MEMBER OF THE PUBUC from Tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluerets released from the unit to areas at
| |
| .g andg% 4 *id 16e SITE BOUNDARY shall be limited to the following:
| |
| a."!if During any calendar quarter: less than or equal to 7.5 mrom to any organ, and
| |
| \
| |
| : b. ' During any calendar year: less than or equal to 15 mrom to any organ.
| |
| APPUCABluTY: At all times.
| |
| ACTION:
| |
| With the calculated dose from the release of Tritium and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region 1 Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
| |
| 75.0 m=
| |
| i r -
| |
| | |
| l l
| |
| l I
| |
| Number y TMI Radiological Controls l Departmental Procedure 6610-PLN-4200.01 !
| |
| T** W No. !
| |
| Offsite Dose Calculation Manual (ODCM) 15 BASES This control applies to the release of radioactive materials in gaseous offluents from TMI-2.
| |
| This control and associated action is prcrAded to implement the requirements of Section ll.C, Ill.A and IV.A of Appendk I,10 CFR Part 50. The Controls are the guides set forth in Section ll.C of Appendk 1. The ACTION statement provides flexabilty during unusual condklons and at the same time implements the guidos set forth in Section IV.A of Appendix i to assure that the releases of radioactive materials in gaseous effluerts wil be kept 'as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A c( Appendk i that confortnance l wth the guides of Appendk i be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OETHE PUBUC through appropriate pathways is unlikely to be substantially underestimatedyThe ODCM calculational methodology and parameters for calculating the doess due to the actual release rates of the subject rnatorials are consistent with the methodologp provided in Regulatory Guide 1.109.
| |
| * Calculation of Annual Doses to Man from Routina Releases of Reactor EfAuents for the Purpose of Evaluating Compliance wth 10 CFR Part 50. Appendbc I,' Rev6sion 1. October, 1977 and Reguistory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous EfRuonts in Routine Releases from Ught-Water-Cooled Reactors,"
| |
| Revision 1. July,1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for lodhe-131, iodine-133, tritium and radionuclides in particulate form wth half lives greater than 8 days are dependent upon the axisting rad 6nuclide pothways to man, in areas at and beyond the SITE BOUNDARY. Thiipathways that were examned in the dwelopment of these calculations wereg1)?lndMddal inhalation of airbome radionuclides,2) depostion of radionuclides ordo grden laafy vegetation with subsequent consumption by man, 3) deposition ont6 dressy areas where inilk animals and meet producing animals graze with j consumptionot the'"mik and meet by rnan, and 4) deposition on the ground with j subsequint suposure of man. The absence of lodines at the site eliminates the need to i specify.does limils for these nuclides.
| |
| %9w .
| |
| 2.2.2,4%Ventiation Exhaust Treatment System l yy % ;
| |
| CdfqROt.
| |
| The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive rnatorials in gaseous waste prior to their discharge when the monthly proiected doses due to gaseous ofnuent releases from the site would exceed 0.3 mram to any organ.
| |
| APPUCABluTY: At all times.
| |
| 76.0 sm.
| |
| | |
| mmmw gy TMI Radiological Controis Deputmental Procedure 6610-PLN-4200.01 T** n on m.
| |
| Offette Dose Calculation Manual (ODCM) 15 ACTION a With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a t month or with gaseous wests being discharged without treatment and in excess of l the above limits, propero and submit to the NRC Region 1 Administrator within 30 days, a Special Report which includes the following irdormation:
| |
| : 1. IdentNication of the inoperable equipment or subsystems and the reason for lrm ^9.
| |
| .AlllHEilhk
| |
| : 2. Action (s) taken to restore the Inoperable eqtdpmefgto OPERABLE status, and
| |
| /g (%dg 3.
| |
| A summary description of %action 4~
| |
| (s)(tahan to prevent a recurre BASES m qqlhp,mugjg' O!L The use of the VENTILATION EXHAUST TREATidENT SYSTEM onsures that gaseous efiluents are treated as appropetste pp to release to the erwironment The appropriate portions of this system provide reasonable assurance that the releases of radioactive materiais in gaseous entants wuwkept 'as low as is reasonably edievable
| |
| * This contre!
| |
| Implements the requirements ello CFR"Part 50.36s, General Design Crterion 60 of AppendtK A to 10 CFR Part So, aid Jhe design objectives given in Section 11.0 of Appendix i to 10 CPR Part 50. The,apesWid lipids govemmg the use of appropriate portions of the systems were specilisif as"s sUllable tramion of the guide 4 forth in Sections ll.B and ll.C 2.2.3 of Appendix g1,10 CF$*lis/Part 54, for gaseous alliuents.
| |
| Total Radioacne'9 Eluent Controls 9p% '!%
| |
| 2.2.3.1 TotalDoes
| |
| ,y w - p p %s
| |
| & gk
| |
| * Ths annual (calendar year) does or does commitment to any MEMBER OF THE PUBUC, dui;tp releases of radioactMiy and to radiation from uranium fuel cycle sources shen b limited to less than or equal to 25 mrom to the total body or any organ except the thyroid, I which shaN be limited to less than or equal to 75 mrem.
| |
| APPUCABluTY: At au times.
| |
| ACTION:
| |
| With the calculated dose from the release of radioactive materleis in liquid or pessous of9uents exceeding twice the limits of Controls 2.2.1.2.a. 2.2.1.2.b, 2.2.2.2.a. 2.2.2.2.b.
| |
| 2.2.2.3.a. or,2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the caser, prepare ord submit to the NRC Region i Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above 77.0 rm.
| |
| ~ . . . - . - , , '
| |
| | |
| gr g TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Me RMWon No.
| |
| ONsite Does Calculation Manual (ODCM) 15 limits and includes the schedule for achieving conformance with the above limits. This Special Report, as denned in to CFR Part 20.2203(b), shal include an analysis which estimates the radiation awfv=re (dose) to a MEMBER OF THE PUBUC from uranium fuel cycle sources, including all emuent pathways and direct radiation, for the calendar year that includes the release (s) owered by this report it shall also deoortbo levels of radiation and concentrations of ressosctrue material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceed the above limas, and if the release condtion resuting in violation of 40 CFR 100 has not already been corrected, the Special Report sher include a request for a variance in accordance with the provisions of 40 CFR 190. Submittel of the report is considered a timefy request, and e. variance is granted until staff action on the request is complete. / 1!y
| |
| & I u
| |
| BASES s# [!r4w# ;
| |
| g4%/ j This control is provided to meet the dose limhatione g( 46pFR Part 190 that have been incorponated into 10 CFR Part 20.1301(d). Thistente(39 quires the preparation and submittel of a Special Report whenever the egiculated doses from plant generated radionotive elRuents and direct radiation ave =a425 Inrem to the total body or any organ, except the thyroid, which shen be limped to less then or equel to 75 mrom. For stes containing up to 4 reactors, it is highij,unlikely that the resuhant does to a MEMBER OF THE PUBUC wBl exceed the does Nmts of 40 CPR Part 190 if the individual reactors remain within twice the does design pbl actives 1lf Appendu 1, and N direct radiation doses from the reactor unto and outside storage;tenks are kept small. The Special Report wul describe a course of action that shouldleeUlt 'irithe limitation of the annual does to a MEMBER OF CPS Part 190 limits. For the purposes of the Special Report, it THE may bePUBUC to withir)the%se assumed thatthe do commitment to the member of the public from o fuel cycle sourcesils M, with the amar innethat does contributions from other nuclear fuel cyde facultleiet the same alte or within a radius of 8 km must be conaldered. If the ;
| |
| dose to any membeIef the public is estinated to exceed the requirements of 40 CFR Part 190, the SpecialReport with a request for a variance (provided the rolesse conditions restating Iri%iation of 40 CFR Part 190 have not already been corrected), in accordance with b hemliel$w of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a tlmelyjeguset and fulfils the requirements of 40 CFR Part 190 unti NRC stall action is compisted. The verlance only relates to the lirnRs of 40 CFR Part 190, and does not apply in any'wsy to the other requeroments for does limitation of 10 CFR Part 20. as addressed in Controls 2.2.1.1 and 2.2.2.1. An indMdual is not considered a MEMSER OF THE PUBUC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
| |
| I i
| |
| 1 78.0 mu i .
| |
| | |
| Number TMI Radiological Controls EE Departmental Procedure 6610 PLN-4200.01 re. n onre.
| |
| Offsite Dose Calculation Manual (ODCM) 15 3.0 SURVEILIANCES 3.0.1 SurveWance Requirements shall be applicable during the condtions spectied for individual Controls unless otherwise stated in an indNidual Surveillance Requirernent. The Surveillance Requirements shall be performed to demonstrate compilance with the OPERABILITY requirements of the Control.
| |
| 3.0.2 Each Survellance Requirement shall be performed wthin the spectied time interval with a maximum allowable extension not to exceed 25% of the sug interval.
| |
| 3.0.3 FaRure to perform a Survemance Requirement within the tirr Int specWlod in Section 3.0.2 sher consttute non-compliance with OPERABly1Y requinpments for a Control Tne time limits of the ACTION requirements are applicenst the time it is identNied that a Survemance Requirement has not been performed 4The' ACTION requirements may be delayed for up to 24 hours to permit completiorg of IW:survellance when the allowable
| |
| ^
| |
| outage time limits of the ACTION requirements are..less than 24 hours. Surveillance Requirements do not have to be performed on' inoperable equipment.
| |
| g 3.1 Radioactive Effluent instrumentation h; 4d,tl 3.1.1 Radioactive Uquid Effluent Instrumentation d
| |
| Survellance Requiremarit,s *lig!gL,".
| |
| ~
| |
| ( n! g, Radioactive uguld ESuent instrumentation is common between TMI-1 ard TMI-2.
| |
| Survemances foribis lhotrumsntation are specified in ODCM Part 1, Surveillance 3.1.1.
| |
| p%
| |
| 3.1.2 Radioactke Gaseous ,ProcAs and Effluent Monitoring instrumentation
| |
| (...aa ?%
| |
| SURVEILLANCE REQUl8EMENJS ggw w.. s 3.t.2.14 Each rad!oactive gaseous process or effluent monitoring instrumentation channel shall be dersonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAUBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.12.
| |
| 79.0 m=
| |
| | |
| Y =
| |
| T n m.
| |
| u l 1 1 1 1 a
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| e5 1 B E E A T T E E m 6 C T T Un U O O O O Plee P N N N N Si P 1 v A se eR T
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| S E
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| L T s EL t
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| n NA A e NN M / A AO N M /
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| m HT I N e
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| i r
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| c aE n
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| e E h
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| G N %
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| r E
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| e 9 v
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| r LO EI T %~ w'M a u -
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| S NA NR E A A 3# R n / E /
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| it o AB HU N N .f 8f1 hiMy&F~ #
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| es CA n
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| e C m
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| u r
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| g#Vs#.(
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| t s ,_
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| n EK NC ,p[p g
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| o NE D W jr f e it n AH !
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| E W 0 H C_ 0 M o C 8
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| n
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| /)figsV n w
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| a P i ) H 5 (2 2 /*
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| - R- a m
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| s P ) P )
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| 2 5
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| (2 9
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| 1 2-e t
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| s y
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| e T t
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| s r R- e r R s v N y o P t
| |
| s o -
| |
| d
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| - it S t y it P e n
| |
| i
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| - c E g H S n H r a M n o 2 o o io (
| |
| g (2 n M M it d U ir r r n a R o y e i r y e o R T it n
| |
| t lp o t lp m S
| |
| N o Mt m it n M t m e I
| |
| M c a o c) a h e A S M AA S t .
| |
| s s19 f
| |
| g a t e n e o r
| |
| u G l a io a2 G-t a n P u t e R lu o .
| |
| u le c it s le- P ic it a
| |
| r b t b
| |
| e o r a n oH t
| |
| a r r e _
| |
| m N P e N (2 p n v P o
| |
| - i a n g _
| |
| t o ,.
| |
| n i t in -
| |
| o .
| |
| a r u
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| C a b
| |
| t S a b
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| D S
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| E
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| . T O
| |
| 1 2
| |
| N 1
| |
| .s 1i
| |
| | |
| Number jgp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Ties Reneen No.
| |
| ONsite Dose Calculation Manual (ODCM) 15 3.2 Radioactive E!:uents 3.2.1 Liquid Effluents SURVEILI.ANCE REOUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactMty content d each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with ,
| |
| Table 3.21. The restits d analyses shall bdused with the '
| |
| calculational methods in the ODCM tou assurd that the concentration at the point of release is mainta wfin the'lirnits of Control 2.2.1.1.
| |
| 3.2.1.1.2 w %$
| |
| Analysis of samples composited_from batch releases shah be performed in accordancelwith Table"3.2-1. The results of the analysis shed be used with the"~ o alculational methods in the ODCM to assure <
| |
| that the concentrations it,$he* point of release were maintained within l the limks of Control 2.2.1.1' l v -
| |
| 3.2.1.1.3 The radioact concentration of liquida discharged from continuous release,. points shall be determined by collection and analysis of samples inlaccordance with Table 3.2-1. The results of the analysis shan tid 10Esed%th the calculational methods of the ODCM to assure athat Ihe concentration at the point of release is maintained within the
| |
| . ! limits al Control 2.2.1.1.
| |
| / Nilwd #
| |
| 3.2.1.2 Dose Cisbulations ja ll;;r 3.2.1,2.19 Cumulative dose contributions from liquid affluents shall be determined in accordance wkh the Offsite Dose Calculation Manual
| |
| %g%'"'"*%d/
| |
| li4,.
| |
| (ODCM) at least once a month.
| |
| .y )Q?iv 3 Dose Projections 3.2.{g 3.2.1.3.1 Doses due to liquid releases shaR be projected at least once a month, in accordance with the ODCM.
| |
| 81.0 mm.
| |
| | |
| Number
| |
| -ggy TMI Radiological Controls Departmental Pirw Nre
| |
| : m. 6610 PLN-4200.01 ewww.
| |
| Offsite Dose Calculation Manual (ODCM) 15 TABLE 3.2-1 Radioactive Liquid Weste Sampling and Analyste (4,5)
| |
| A. Uauld Releases Type of Detectable Sampling Frequency ActMty Analysis Concentration (3)
| |
| P IndMdual Gamma Each Batch SE-7 pCi/mi-(2)g H-3 1E-5 pC(I/rni /y O Gross Alpha 1EqpCl/mi' Ouarterly Compoche (1)
| |
| *h "%
| |
| St-90 emmSE4 pC1/ml NOTES:
| |
| %- 4 (1) A COMPOSITE SAMPLE is one in which the quantky of liquid sampled is proportional to the quantky of liquid waste discharged from the plant. 4 %'{ .
| |
| y% '%;w (2) For certain mixtures of gamma emitters, k may nG(be possible to measure radionuclides la concentrations naar this sanskMiy limit when oth6r nuclides are present in the sample in much greater concentrations.
| |
| Under these circumstances, k will be more' appropriate to calculate the concentrations of such radionudides using measured ratios with those radioimucNded:which are routinely identified and measured.
| |
| (3)
| |
| ./ %/
| |
| The detectabilay firnats for radioectlWy analysis are based on the technical feasibilty and on the potential signincance in the environmort of the"quantitles released. For some nuclidos, lower detection limits may be randGy achievable and when v nuedidos are measured below the stated limits, they should also be reported.
| |
| y 3 (4) The results of these ad sh00ld be used as the basis for recording and reporting the quantkles of redlonctive material released"In liquid effluents during the sampling period. In estimating releases for a period when anal ses%eranot performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the ofEuent records and reports; however, they should be cleady identiheci as estimates, and the method used to obtain these data should be described (S) Deviations from the sampling / analysis regime will be noted in the report specified in ODCM Part IV.
| |
| 81.0 nm.
| |
| | |
| tbmber gp TMl Radiological Controis Departmental Procedure 6610-PLN-4200.01 me awson No.
| |
| Offsite Dose Calculation Manual (ODCM) 15 3.2.2 Gaseous Effluents SURVEILI.ANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determhed to be within the limits d Control 2.2.2.1.a in accordance with the rrethods and procedures of the ODCM.
| |
| ,ieg 3.2.2.1.2 The dose rate of radioactive materials /other Jhan noble gases, in gaseous affluents shall be determined to be yrithin the limits of Control 2.2.2.1.b in accc,d.r.ce with mptfids"And pfocedures of the ODCM by obtaining representative samples'and performing analyses in accordance wth the sampling and' analysis program, specified in Table 3.2 2. Q%dsg "
| |
| 1 *ig 3.2.2.2 Dose, Noble Gas 4g4!;q,, "iin d I 3.2.2.2.1 Cumulative does contributions from noble gas effluents for the current ,
| |
| calendar quarte ('and current calendar year shall be determined in )
| |
| accordance with the OFFSITE DOSE CALCULATION MANUAL i (ODCN,iq) -% mbath.ly.
| |
| 3.2.2.3 Dose.TrtiumNRabpr nuclides in Particulate Form 3.2.2.3.38 Eum Ivo dose contributions from Tritium and radionuclides in
| |
| # kib particulate form with half lives greater than 8 days for the current j F4 '% calendar quarter and current calerdar year shall be determined in
| |
| !!gi;gf] accordance with the OFFSITE DOSE CALCULATION MANUAL l (ODN) mNy.
| |
| a %n. iw/ j
| |
| ''% 'A 42.2.4%gVentilation w;f Exhaust Treatment Sa 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM.
| |
| 83.0 nm.
| |
| 4 9
| |
| | |
| Numba SEF TMl Radiolo01 cal Cortrols Departmental Procedure 6610-PLN-4200.01 Tm mm Offsite Dosa Calculation Manual (ODCM) 15 TABE 3.2-2 Radioactive Gaseous Weste Sampling and Analysis (3)
| |
| SAMPLE SAMPUNG TYPE OF DETECTABLE SAMPl.E POINT TYPE FREOUENCY ACTIVITY ANALYSIS CONCENTRATION (1)(a)
| |
| Reactor Building Purge Releases Gas P H-3 1E 6 pCl/cc Each Purge IndMdual Gamma Emitters *'"*. 1E4 pCl/cc (2)
| |
| Unt Exhaust Vent Release Poires Gas M H-3 p i!!!,. 166 pCl/cc MontNy IndMdual.g3 /
| |
| Gamma Emiters 1E4 pCl/cc (2)
| |
| W IndMdual.(b)..
| |
| Particulates Wealdy Gamme Emhters 1E-10 pCl/cc (2)
| |
| M, %
| |
| Monthly St90 1E-11 pCl/cc Compoalte f% M % Gross Alpha e MontNy Emkters 1E-11 pCl/cc
| |
| .an[ (ComMRe
| |
| ' Reactor Building Breather Pasticulates h '"' SA Indv. Gamma 1E-10 pCi/cc (2)
| |
| [Yit%, SemihnuaHy Emitters (b)
| |
| 'if * "h ,, St-90 1E-11 pCl/cc g%'
| |
| g
| |
| / "..
| |
| kiwi;ii l!
| |
| Gross Alpha Emitters tE-11 pCl/cc
| |
| '"!!h "'!Ei
| |
| % AlYN, (1) The above detectablity lirslts are based on technical feasibility and on the potential significance in the erwironment of the"duantties released. For some nuclidos, lower dettetion limits may be readdy achievable and when nuclides are measured below the stated limits, they should also be reported.
| |
| (2) For certain mixtures of Gamma emhters, it may be possible to measure radionuclides at levels near their sensitivky limts when other nuclides are present in the sample at much higher levels. Under these circumstances, it wlR be more appropriate to calculate the levels of such radionuclides using observed ratios in the Oaseous component in the reactor coolent for those radionuclides which are measurable.
| |
| 1 (3) Deviations from the sampling and analysis regime wul be noted in the report specified in ODCM Part IV.
| |
| l 84.0 nm.
| |
| | |
| Sksmber I TMI Radiological Controis Departmental Procedure 6610-PLN-4200.01 Rwmon No.
| |
| Offsite Dose Calculation Manual (ODCM) 16 TABLE 3.2-2 (CorW'd)
| |
| Radiomative Gaseous Weste Sampling and Analysis Program l
| |
| Table Notation l
| |
| a.
| |
| The LLD is the smallest concentration of radioactive material in a sample that WNI be detected with 95% !
| |
| probabilty with 6% probabity of falsely concluding that a blank observation represents a "real* signal.
| |
| .,p For a particular measurement system (which may include radiochemical separa%tior$
| |
| ,p? Y
| |
| , 4.66 Sy *h f" Q g j E V 2.22 Y
| |
| * exp (-Aat) k%
| |
| Where . 9*5%UA>4
| |
| \.h LLD is the lower limit of detection as defined pbove (as picoeurie per unit mass or volume). ,
| |
| 1 S, is the standani deviation d the backgroundjpounting rate or of the counting rate of a blank sample as appropriate (as counts perjninute). 'h.
| |
| E is the counting efficiencyd.... (as cou[rts.per liahsformation),
| |
| s..
| |
| jpF"%pg V la the sample size (in units of massipt volume),
| |
| / iku$
| |
| 2.22 is the number of transformations per minute per picocurie, pm "%g Y is the fractional #adlochemical yield (when appilcable),
| |
| ,y w g A is the radloectbe decayconstant for the particular radionuclide, and
| |
| .,,, )h. '%
| |
| At is the e' lapsedlime between midpoint of sample collection and time of counting (for plant effluents, nottonvironmental samples).
| |
| The value of S, used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma. ray spectrornetry, the background shaR Include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and At shall be used in the calculation. The background count rate is calculated from the J background counts that are determined to be with t one FWHM (fun-Width-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that radionuclide.
| |
| 85.0 on.
| |
| | |
| Pennber TMl Radiological Controls EI Departmortal Procedure 6610-PLN-4200.01
| |
| % n=en m.
| |
| Offalte Dose Calculation Manual (ODCM) 15 TABLE 3.2-2 (Cort'd)
| |
| : b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: hW54, Fe-53, Co-58 Co40 Zn45, Mo-99, Cs-134, Cs 137, Co-141 and Co 144 for particulate emissions This list does not mean that only these nuolides are to be detected and reported Other peaks which are measurable and identifiable, together wtth the above nudidos, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as less than' the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The less than* values shall not be used in the required does calculations.
| |
| , p5*%j Si.
| |
| r 1,,/
| |
| 'k, db ii:g k
| |
| , N! h lb
| |
| %ig%
| |
| 's p ik
| |
| 'b%uijn g'lijg "4 pg{gpm ip Nib I
| |
| f s'i, p g!!jg *II' !md 4
| |
| 9 dENI' II lh pi;!['
| |
| "Ilj
| |
| @s+~J l!!bi!g Ilig 86.0 *"k
| |
| | |
| Number TM! Radiological Controls
| |
| - !EE Departmental Procedure 6610 PLN-4200.01 !
| |
| : a. w n m. 1 Offatte Dose Calculation Manual (ODCM) 15 l
| |
| 3.2.3 Total Radioactive Emuents <
| |
| i 3.2.3.1 Dose Calculation 3.2 A 1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordince with Survemances 3.2.1.2.1,3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.
| |
| i
| |
| .f cilia,,.
| |
| t f, n- e a all -
| |
| 'i!'i NHi!
| |
| ~
| |
| g kwpgg!f
| |
| $ljn Ni :
| |
| hg',
| |
| %;$"iE!!h:g Tig. 'h,
| |
| ' !P k.
| |
| d!Ninliij-al !,f",
| |
| .m,p%;! n N ,,f"tui, 1
| |
| gis#"2%
| |
| r !B, ii . .yOl b,!?
| |
| H#p %,J!!!yinnif i t !i
| |
| - I l'i.i n, juMg, II h
| |
| %u.,u'iOIk
| |
| .: k
| |
| .g gj 4; !;; d!!!nli 90,. e b ,
| |
| iii i.
| |
| Nji, 87.0 rm.
| |
| -- - - - ~ ~
| |
| | |
| mmna g gy TMI Radiological Controis Departmental Procedure 6610-PLN-4200.01 l D MOft No.
| |
| Offsite Dose Calculation Manual (ODCM) 15 1
| |
| 4.0 PART 11 REFERENCES I 4.1 NUREG4883, " Final Programmatic Environmental Impact Statement related to decontamination and !
| |
| disposal of radioactNo wastes resulting from March 28,1979, aceksent Three M8e Island Nuclear Station, Unit 2,* March 1981, and Rs supplements.
| |
| 4.2 TMi-2 PDMS Technical Specifications, attached to Facity Ikonse No. DPR-73 4.3 Title 10 Code of Federal Regulations
| |
| * Energy" l
| |
| .p% g 4.4 ' Statement of Policy Relative to the NRC Programmatic Environmental impact Statement on the Cleanup of Three MRe Island Unit 2,* dated Apri 27,1981 p lij;q j
| |
| ,/p ,,, i%; p l 4.5 Regulatory Guide 1.109,
| |
| * Calculation of Annual Doses to Man'from Routine Releases of Reactor P
| |
| Effluents October 1977 for the Purpose of Evaluating Compliance with 10 Cfflg, ad 50, Appe di![%% .
| |
| 4.6 DOE / TIC-27001, Atmospheric Science and Power Re beti !
| |
| s 4.7 TMl-1 Technical Specifications, attached to F Nity Operating License No. DPR-50 !
| |
| 4.8 PDMS SAR feiji, mak l l
| |
| ni siigr
| |
| ,y')%
| |
| cpiMUiliipa d t Ni g' 'lji4 !!
| |
| .# h. .I ji@4t l 't$!Pk piih li- Ng I
| |
| f A, I(g;;;lis" Nm !!!i 44L{p!lP!!g,,. w
| |
| 'i iig i
| |
| i 88 0 sm.
| |
| | |
| 1 Number EE TMI Radiological Controls Departmental Procedure 6610-PLN4200.01 m Amneson No.
| |
| _ Offsite Dose Calculation Manual (ODCM) 1.2 l
| |
| l 1
| |
| l psuiw ill bli, p'' i
| |
| ,q)b hh,.
| |
| nnu -s,(
| |
| %.,e".
| |
| /
| |
| *h.w 'Iy,'!,_ r lf, fL
| |
| ..i HI!!Hilb[!iht.
| |
| %,3.%,b
| |
| - hh
| |
| ,, ll
| |
| ''i' h
| |
| j;!Miq, 4%4 '9ijp 4pr tif
| |
| %,,!1/PART lil p ' % 'uis ify y}, s
| |
| '80:
| |
| 'l ! l (l!
| |
| atY l'T . f EFFLUENT.+ DATA w AND CALCULATIONAL METHODOLOGIES g";dU!!!N' !hjp s%, Ifgg;!;# ll I
| |
| i i!h nirildy i
| |
| 4
| |
| 'ip
| |
| ..'4Ily .ner l
| |
| ! MpF'n,p$
| |
| 'N(jj' 4 g
| |
| i I
| |
| l i
| |
| I i
| |
| i 89.0 nm l 1
| |
| - . . - . . . . . .__ _ . _ , . l J
| |
| | |
| 1 gg I TMI Radiological Controls Departmental Procedure Number Tiite 6610-PLN-4200.01 Revia 6on No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 1.0 LIQUID EFFLUENT MONITORS 1.1 TMl 1 ard TM12 Uauid Radiation Monitor Set Points The liquid effluent off-line monitors are set such that the concentration (s) of radionucildes in the liquid effluents will not exceed ten times the concentrations specified in 10 CFR 20, Appendix B Table 2, Col 2. Table 1.1 lists the Uquid Effluent Release Points and their parameters; Figure 1.1 provides a Uquid Release Pathway Diagram.
| |
| i To meet the above lindt, the alarm / trip set points for liquid effluent monitors ard flow measuring I devices are set in accordance with the following equation:
| |
| $p"9gy j c
| |
| * f _< O j/* hiig j'i' l
| |
| (eq 1.1)
| |
| F+f 4f
| |
| %g V .
| |
| * l 95m! l#
| |
| C- 4. "%
| |
| ten times the effluent concentration of 10 CFR RfoF the site, in pCl/mi.
| |
| c=
| |
| the set point, in pCl/ml, of the liquid effluent monitor rneasuring the radioactivity concentration in the effluent line prio(iciidilution and release. The set point is inversely proportional to the maximum volumetrDqw of the effluent line and proportional to the minimal volumetric flow of thgdllugn stream plus the effluent stream. The alert set point value is set to ensure that advance waming occurs prior to exceeding any limits. The high alarm set point value is pucffthai(It were exceeded, it would result in concentrations 0 CFil 20 concentrations for the unrestricted area.
| |
| exceeding ten / times ghe)%$
| |
| f- flow set point as fnessured at the radiation monitor location, in volume per unit time, but in the same unity as F below.
| |
| II .,#%
| |
| F= flow rate of dru,tionfrater measured prior to the release point, in volume per unit time.
| |
| .g %g eer The set polot coriicenstion is reduced such that concentration contributions from multiple release points wouliflhoicobine to exceed ten times 10 CFR 20 concentrations. The set point concentration l$ converted to set point scale units using appropriate radlation monitor calibration factors.
| |
| This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Uguld Waste procedure.
| |
| s 90,0 mm
| |
| | |
| jggy TMI Radiological Controls Departmental Procedure Number Tme 6610 PLN-4200.01
| |
| % mon No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 1.2
| |
| _TMl Liould Effluent Release Points and Uould Radiation Monitor Data
| |
| \
| |
| TMl-1 has two required liquid radiation monitors. These are RM-LS and RM-L12. These liquid release point radiation monitors and sample points are shown in Table 1.1. (The TMI outfall radiation monitor, RM-L7, is also listed for information only.) l TMI-2 does not have any required liquid radiation monitors, but does utDize RM-L12, and RM-L7 for release of liquid waste.
| |
| 1.2.1 RM-L6
| |
| ("%g l RM-ta is an offline system, monitoring radioactive batch discharges from the TMI-t liquid radwaste system (see Figure 1.1). These batch releasesdire sampled and analyzed per site procedures prior to release. The release rate is based" {
| |
| Evaporator Condensate Storage Tanks (WECST) at hless which wil add fl%pn releasing than 10%, of one of two W ten times the 10 CFR 20 concentrations to radionuclidiconcentrations in the unrestricted area, including conservative default values Yl' ,
| |
| u fory$krg$iM and Fe-55.
| |
| The release flow rate used is the most restrictive $f th ee flow rates calculated fo batch release. Der the approved plant kocedure, i
| |
| i
| |
| "%d Three DRution Factors (DF) are calcuieted to ultimately calculate the batch release flow rate.
| |
| l These three DF's are calculated 1
| |
| *todi ) insure each radionuclide released to the unrestricte '
| |
| area is less than 10 percent,or tpn'tiEnes the 10CFR20 radionuclide concentrations, 2) ensure ;
| |
| each liquid batch release bortgcogeentration to the river wHl not exceed 0.7 ppm, and 3),
| |
| ensure ten times the 10CFR20 concentration for Coslum-137 (IE-5 pCl/ml) will not be exceeded based ortthe balculstbd high alarm set point and the expected response of RM-Lfi to this concentrationW Cs-137. ;
| |
| I f4 \%
| |
| The maximum release flow rate is then calculated by dividing the most restrictive (largest)
| |
| DF into 90 p$rdsnt of the current dRution flow rate of the Mechanical Draft Cooling Tower (MDCT)'JigThis cbrdervative flow rate is then multiplied by 0.9 for the allowable flow rate.
| |
| e A%
| |
| kg;%iCalc0lation of 10 percent 10% of ten times the 10CFR20 DF, = E (SA) + (10% of ten times the 10CFR20 concentration)
| |
| SA = Specific Activity of each identified radionuclide o Calculation of Boron DF:
| |
| DF, = Actual Tank Boron Concentration + 0.7.
| |
| * Calculation of Cs-137 Limit:
| |
| DF, = High Alarm Set Point + (1E-5 pCl/mi
| |
| * 1.05E8 cpm per pCi/ml) e Maximum release flow rate calculation:
| |
| Max Flow = ((MDCT flow gpm
| |
| * 0.9) + (Most Rettrictive DF)]
| |
| * 0.9 91.0 mm
| |
| * . = =
| |
| | |
| Number gp TMI Radiological Controfs Departmental Procedure Tme 6610-PLN-4200.01 Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 The dilution flow rate used is the current flow rate at the site. The minimum dilution flo is 5000 gpm per the TMl-1 FSAR. This ensures this batch release will meet the following equation.
| |
| E(C/X,) 1 0.10, (eq 1.2) where: Ci = diluted concentration of the 1* radionuclide, X, =
| |
| Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B, Table 2, Col. 2). A value of 3E-3 pCl/ml for dissolved and entrained noble gases shall be used jF%4 f
| |
| The set points for RM-L6 are set for each release itor m basect,on response tothe each mon $
| |
| radionuclide identified in the gamma scan sample results as folldws:
| |
| (1.5)* [Il(pCl/cc),*(CPM /pCl/cc)J .
| |
| ,= + ( Ph8h)e%* ALERT CP (2.0)* [Il (pCl/cc), (CPM /pCl/cc)J +*(CPM,,,) = HIGH ALARM CPM
| |
| 't where: (pCl/cc), = positivelyldentified radionuclides
| |
| ! mumb (CPM /pCl/cc), = RM-L6. sensitivity to radionuclide 1.
| |
| y m (CPM ) = "RMidbackground prior to batch release l
| |
| p*"%{"li!g A high alarm on RM-LS bill close valve WDL-V-257 and terminate any WECST releases to
| |
| $4F%li y/
| |
| environment.
| |
| 1.2.2 RM-L12 %;g
| |
| $g,.sA RM-L12 isAn"eff-lineIsystem, monitoring periodic combined releases from the industrial Waste Treatmert 8 stem / industrial Waste Filtration System 7'vTS/lWFS). The input to IWTS/lWPS odginates in TMI-2 surnps. (see Figures 1.1 and 1.2) and the TMI-1 Turbine Buildingsuriip (see Figure 1.1). The set points are based on the maximum rel ease rate fram both IWIS and IWFS simultaneously, (see Figure 1.1) a minimum dilution flow rate, and 50%
| |
| of ten tirries the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1E-5 pCl/rnt These inputs are used in equation 1.1 to determine the RM-L12 High Alarm set point for all radionuclides being released. A high alarm on RM-L12 will close IWTS and IWFS release valves and trip release pumps to stop the reloase.
| |
| 1.2.3 RM-L10 RM-L10 was a Nal detector submerged in the TMl-1 Turbine Building Sump. This detector has been removed from service.
| |
| l l 1.2.4 _RML7 RM-L7 is not an ODCM required liquid radiation monitc,r. RM-L7 is an off-line system, monhoring the TMINS outfall to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMl-1 and TMI-2 normal liquid effluent releases.
| |
| 92.0 mm I _. . _
| |
| l
| |
| | |
| i l
| |
| (ggy TMI Radiological Controis Departmental Procedure Number Title 6610 PLN 4230.01
| |
| % won No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 1.3 Control of Uould Releases i i
| |
| TMI liquid effluent releases are controlled to less than ten times the 10CFR20 cr'rcentratio limiting the percentage of this Ilmit allowable from the two TMl liquid release points. RM-L6, and effluent sampling limits batch releases to less than or equal to 10% for all radlonuclidea, and RM-1.12, and effluent sampling, limits releases from TMl 1 and TMI-2 to less than or equal to 50%
| |
| Cs-137. l j
| |
| These radiation monitor set points also include bulf* in meter error factors to further ensure that TMil liquid effluent releases are less than ten times the 10CFR20 concentrations to the environment, jeENilig.
| |
| The radioactivity content of each batch of radioactive liquid waste is[ determined prior to rele sampling and analysis in accordance with ODCM Part i Table q,2-1 br.ODCM Part it, Table 3.2-1.
| |
| }
| |
| The results of analyses are used with the calculational methodtirlfecti6ri 1.1, to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part il Control 2.2.1.1.
| |
| 4..%
| |
| %yg "'&
| |
| Post-release analysis of samples composited from batchgefenses are performed in accordance with ODCM Part i Table 3.2-1 or ODCM Part il Table 3.2-1. Thitesults of the previous post-release analysis shall be used with the calculational mehods in the CDCM to assure that the concentrations at the point of release were maintained within tlse ODCM Part i Control 2.2.1.1, and ODCM Part il )
| |
| Control 2.2.1.1. l jlg.'ji "*ig The radioactivity concentration of liqOlds;dr2:har9ed from continuous release points are determined by collection and analysis of samples hi accordance with ODCM Part 1 Table 3.2-1, or ODCM Part ll Table 3.21. The results of the analysis $re used with the cafculational methods of the ODCM to assure that the concentratioriatie polht of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part WCoprol 2.2.1.1.
| |
| qpe *lig m;ii![
| |
| (QJ sfe k 93.0 mm
| |
| ..w.
| |
| | |
| gggy TMI Radiological Controls Departmental Procedure Number Tme 6610-PLN 4200.01 Revle6on No.
| |
| Offatte Dose Calculation Manual (ODCM) 12 i
| |
| TABLE 1.1 '
| |
| TMl Uquid Release Point and Liquid Rediation Monitor Data UQUID RELEASE L)OUlD RELEASE TERMINATION RADIATION POINT DISCHARGE INTERLOCK MONITOR (Maximum FLOW (YES/NO)
| |
| (DETECTOR) LOCATION Volume) RECORDER
| |
| _ VALVES YES.
| |
| WQL-V257:
| |
| 281' Devation WECST Batch RM La TML1 Auxiliary Releases #j >iig ki' (Nal) Bido (8000 gal.) FT44
| |
| ..,, E"t"#,j
| |
| * Station s RM.L7 Discharge 91 V'"f YES
| |
| 'WDL-\257 (Nat) South end of TM1-1 and l **
| |
| TML 1 MDCT TMI2,
| |
| $4hn:nq j; y 4 1311 4 FT 146
| |
| 'g 'w YES IWTS/lWFS IW-V/3 Continuous 1 fW-P16.17.18 Releases l RM-L12 IWFS Building (3QQ.600/""!;i FT 342/ IW.V279, (Nr.1) NW Comer 80.000 gal.)
| |
| * FT.373 IW-P29.30
| |
| * WDL-R 1311 has been flanged off as a TML2 liquid outfaygg.g%"e ow 8'RM-L7 le not an ODCM required liquid radiation monhof, ghi l, lig,
| |
| /' lgv. 1 A.;[. l glil$!II' Ii(h I i;lill ;
| |
| A"!!$,, l/
| |
| D h*
| |
| iggg% %g1 l
| |
| %!g 94.0 me
| |
| | |
| I t
| |
| Number ggy l TMl Radidogical Contrds l Departmental Procedure 6610-PLN4200.01 Tia. mn uo.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 1.2 TMI-2 Sump Capacities Total Capacity Gallons Sump Gallons per Irch Turbine Building Sump 1346 g a 22.43 l
| |
| Circulating Water Pump House Sump 572,.k ll: 10.59 Control Building Area Sump 7[5 #
| |
| * 9.96 Tendon Access Galley Sump *$3tih 9.96 Control to Service Buiding Sump '9;[*415A[
| |
| 1 4 22.43 i
| |
| Contaminated Drain Tank Room Sump ., #"% 135 3.80 CNorinator House Sump .,,, $L Water Treatment Sump" 8
| |
| .# "%lk N 1615 22.43 Air intake Tunnel Normal Sump m h/***"' 700 -
| |
| Air intake Tunnel Emergency Sump ( lj; '"' 100000 766.00 Condensate Polisher Sump * /k. ***# 2617 62.31 Sludge Cdlection Sump *y** "% 1106 26.33
| |
| *#" .,,)
| |
| Heater Drain Sump 4..
| |
| Sdid Waste Staging MacilkSump 1476 24.00 Auxiliary BuildingM J0102 202.00 Decay Heat Vault Sump 479 10.00 Building Spray Vault Sump 479 10.00
| |
| * Condensate Pdisher Sump is deact!vated and in PDMS condition. !
| |
| ** The Water Treatment and Sludge Cdlection Sumps will be deactivated for PDMS. l i
| |
| I i
| |
| l 95.0 mm l '
| |
| i L
| |
| | |
| r o
| |
| a_$
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| g g _
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| i i
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| n oS i
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| t cP gm e m e t n
| |
| e e* uk i
| |
| s in l tte j Na n l
| |
| gl8 S l
| |
| D o" sate ET 0M 1
| |
| 5 bN : %wg aey r
| |
| 4l
| |
| =
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| n .
| |
| t.
| |
| 1
| |
| = ' i s
| |
| o*.s p' o G u .
| |
| m2s o".i p 0 2 l t
| |
| e
| |
| 'n ' "
| |
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| |
| dm e e s o
| |
| " n
| |
| &t s cp t g ds i,~
| |
| t
| |
| 'r_
| |
| g .,:- r r PS 1
| |
| 4 nme ou i",r, ,, tt t, o i
| |
| l r
| |
| c d S e r
| |
| mt
| |
| ,sy e, S m
| |
| e t'* e 6'JT '
| |
| "w,u g i R
| |
| d' l
| |
| h wA" s
| |
| ,' m'enl''j S d _
| |
| y m _
| |
| d i 'n g* {
| |
| 'n iu ,F l
| |
| S o 'e j- J"* , '-
| |
| T-s xs 2 .^e
| |
| #j g
| |
| #insd
| |
| *y r
| |
| taeT t
| |
| 1 M2 a e n T I -
| |
| M 1 ..e n s o 4 e
| |
| g at ma n y el x e "
| |
| * SWa uS l
| |
| l a SM y a de s ws 4 wm d p eY\-
| |
| h w PV oe ou P B=- (j# '
| |
| t a # 5g~V y i r
| |
| e z
| |
| P l
| |
| s dgt a r
| |
| p? V::"#+
| |
| l ,,iI
| |
| 'I. k t
| |
| 3 e u e n t f
| |
| a n
| |
| _ SgNT a r r n l De w e y w o egn lao l
| |
| u l r
| |
| a ir iew d nip id bl m i e ta s
| |
| n ing cT an1
| |
| : 1. Ef f xio uol ABB l
| |
| I ,1 ri uuu TBS deT gcl*na*
| |
| o hl i coI -
| |
| c oM
| |
| - MCT =
| |
| 1 eid -
| |
| " t r tt oa s a ne u u r r q g
| |
| - t eoegB as pd a a nrk on l _
| |
| n - p vot t gi p WECST a n 1 emu i l n -
| |
| L -
| |
| e m e E
| |
| i !
| |
| n a F ol e a u M t
| |
| iC t
| |
| a d
| |
| laS i iS deg t >
| |
| n ogT 1 r )
| |
| - eg n rt n
| |
| e la2 c(s ' t oa s pi r min
| |
| - mi t a ne mlote pi i
| |
| Omn r dt r dt s r
| |
| eo e gA M e - es h a i
| |
| t elis nBE ua t el u e t s pd a nrk ooa InBW a a v ot on a CCW t
| |
| PCB I T WECST _
| |
| go =
| |
| 1 !l -l j i -
| |
| \
| |
| | |
| F M10-PL.N4200.01 FIGURE 1.2 Revision 12 TMI.2 Lkysid Efiluent Pathways -
| |
| CONTROL CONTROL &
| |
| BUILDING #4 SERVICE SUMP AREA SUMP TURBINE TENDON BUILDING >< ACCESS SUMP
| |
| /',GkLLENY
| |
| %,,,,,s"' SUMP
| |
| ~~
| |
| 1L. lp'"
| |
| y (p, 3y ei. 97.,,,4
| |
| * o, 3biip t
| |
| IWTWtSUMP w
| |
| %gpu i ~%' . "i ig i !
| |
| j jil!! gIII!a!!!!!
| |
| , (,,,./* lNDUSTRIAL WASTE g % w} TREATMENT SYSTEM
| |
| .,%/h,,, ,%
| |
| e NI g r
| |
| RML-12 v
| |
| C (RML-7 C - COMPOSITE SAMPLER v
| |
| 97.0 me.
| |
| | |
| l Gualeer ' "'''d***'' oa""'''
| |
| Departmental Procedure 6610 PLN-4200.01 Tise l Redman No.
| |
| Offette Does Calculation Manuel (ODCM) 14 2.0 LNMalD EPPLAMffT D(ME ASSF,SSMENT 2.1 8O N% - 10 CPR 80 #=- A 1 The dose from liquid enluente reedts from the consumption of floh and drinking water. The loostion of the nearest potable water intake le PP&l. Brunner leiend Steam Beatric Station W downstream of TM. The use of the Gow of the Susquehenns River se the duution flow is lustined bened on the complete mixing in the Hvor prior to the first potable water supply, adequately demonstrated by nume tracer die studies and addnional liquid emuent ruleses studies conducted using actual TM.1 tettlum rolesses. Other pathways contribute nodigibly at Three M5e leiend. The does contrtsution from all radionudidos in liquid amuents rolessed to the. unrestricted area is ceiculated using the fotowing expreselon li;
| |
| [ jfk%,#
| |
| Dose j = th t) X (Cg ) X M,3 X --- t; h X~X {eq2.1) 19 where
| |
| $4l%90l N
| |
| %h!b igg I
| |
| Does l = the cumdative de o . to the total body or any orgen, j, from the liquid elRuents for the toted time parlod.lin mrom.
| |
| _pwy %
| |
| At = the length of the time"perhed of actual rulemeos, over which C $
| |
| and f are averaged for su liquid reissess, ipW4,%
| |
| y g C=
| |
| j the everageg goneentration of radionuotido, I, h undIuted liquid eleuent during time period A}Wom erff Ng61d release, in pCl/ml.
| |
| h!M For 45S(Sr.asf St-GO, prior to hatch releases conservative conoemiration values wE be used in the initial does calculation bened si simisipast plant concNtions. LLD values are not used in does colindstions, f= undluted liquid weste flow, ir* gpm.
| |
| FD = plant dilution water Rowrote during the period of rolesse, in gpm FR = actual river Rowrote during the period of rolesse or everage river Sowrr*e for the month the rolesse is occurring, in Opm.
| |
| DF = dIution factor as a resWt of mbdng elfocts in th6 near field of the discharge structure of 0.2 (NUREG 0133) or taken to be 5 bened on the Irworse of 0.2.
| |
| f AWq and AFq = the alte roisted ingestion does commitment factor to the total body or any orgen, l. for sech identuled principle gamme and beta emitter, in mrom/hr por pCl/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway.
| |
| 98.0 mm
| |
| | |
| gggy TMl Radiological Controls Departmental Procedure Number Tita 6610 PLN-4200.01 Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 Values for AW, are determined by the following equation:
| |
| AW, = (1.14E5) x (U,) x (DF,) (eq 2.2) where:
| |
| 1.14E5 = (1.0E6 pCl/pCi) x (1.0E3 rnl/kg) + (5780 hr/yr)
| |
| U, = Water consumption rate for adult is 730 kg/yr (Reg. Guide 1.109, Rev.1).
| |
| DF, - ingestion dose conversion factor for radionuclide, I, for adON total body and for ' worst case' organ, J, in mrem /pCI, from Table 2.1 (Reg. Guide}'"1.109)}
| |
| /
| |
| Values for AF, are determined by the following equation: ( ~
| |
| *%l%[ 4m/
| |
| AF, = (1.14E5) x (U,) x (DF) x (BF,) 4pg]! % (eq 2.2.2) s A.
| |
| where: '0 .%
| |
| 4'" 5119 i 1.14E5 - defined above
| |
| %mh
| |
| (
| |
| U, -
| |
| adult fish consumption, asgurned tok 21 kg/yr (Reg. Guide 1.109, Rev.1). i DF, = ingestion dose convers la$ lor radionuclide, I, for adult total body and for " worst case" organ, j, in mpns/pCj,%om Table 2.1 (Reg. Guide 1.109, Rev.1).
| |
| k I {
| |
| BF, - Bloaccumulatlod<factogpr radionuclide, I, in fish, in pCl/kg per pCl/L from Table 2.2 {
| |
| (Reg. Guide..f.109, Rev.1). ]
| |
| greii. 14 m/ l 9ya
| |
| $.h llll Ili
| |
| ,s 99.0 mm
| |
| | |
| 1 I
| |
| gggp TMi Radiological Controls Departmental Procedure Number Title 6610-PLN-4200.01 Revistori No.
| |
| Offatte Dose Calculation Manual (ODCM) 12 2.2 TMI Llould Radwaste System Dose Cales Once/ Month ODCM Part i Control 2.2.1.3 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 requires that ap portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent 4 I
| |
| releases from each unft to unrestricted areas would exceed 0.06 mrem to the tota! body or 0.2 m to thisany doseorgan in any calendar month. The following calculational method is provided for performi projection.
| |
| At least once per month, the total dose from all liquid releases for the quarter-to4 ate will be divided by the number of days into the quarter and multiplied by 31. Also, this" dose projection shall include the estimated dose due to any anticipated unusual releases during t@ period for which the projection is made, if this projected dose exceeds 0.06 mrem t,otal bodyg0.2 mrem any orDan, appropriate portions of the Liquid Radwaste Treatment SystenCasdefined in Section 3.1. shall be used to reduce radioactivity levels prior to release. i
| |
| *!!!g %
| |
| <ienn h" {'
| |
| At the discretion of Radiological Engineering, time perjodslotM, Fthan the current quarter-to-date m be used to project doses if the dose per day in the cusantfhuarter-to4 ate is not believed to be representative of the dose per day projected for the next month. ;
| |
| i
| |
| 'Miluitin; "h,.
| |
| jim 1
| |
| ,,)%w je"En {liig n l ll
| |
| /g'f.
| |
| ''4
| |
| (%,/
| |
| \
| |
| pi!4 ljji.
| |
| . ngpliY j M
| |
| %g,.. Ad g,hj gh 4
| |
| 'k!;f 4 Nig 100.0 nm
| |
| | |
| l ggy TMl Radiological Controls Departmental Procedure Nwnber j
| |
| I f E' 6610-PLN-4200.01 l Revision No.
| |
| l Offsite Dose Calculation Manual (ODCM) 12 l
| |
| 2.3 Altemative Liould Dose Calculational Methodoloov l i l
| |
| i As an altemative, models in, or based upon, those presented in Regulatory Guide 1.109 (Rev.! '
| |
| be used to make a comprehensive dose assessment. Default parameter values from Reg.
| |
| Guide 1.109 (Rev.1) and/or actual site specific data are used where applicable.
| |
| i I As an attemative dose calculational methodology GPU Nuclear calculates doses using SEEDS (simplified environmental effluent dosimetry system). !
| |
| The onsite and SEEDS calculational models use actual liquid release data with actual monthly
| |
| ! Susquehanna River flow data to assess the dispersion of effluents in fb" river.
| |
| li. A l
| |
| .p[ %,ge
| |
| % 'llik,,'Q ff-kg qi,.
| |
| Tgimacgjhp 4,j! h.
| |
| %g. '"%
| |
| M) i!
| |
| Albih41 il' png I
| |
| % gp!*$i il:sinr f
| |
| gil id*lm Nh,ga l g
| |
| / (/
| |
| ./ 4.;
| |
| ,fn% IQp p4f l l
| |
| ' ,kiig 3
| |
| #'"4 4,.eucl 4l; ;ll 4 4
| |
| 'in 101.0 mm
| |
| (
| |
| l i -
| |
| l
| |
| | |
| I l
| |
| ' Number
| |
| , MI TMI Radiological Controls Departmenta) Procedure I
| |
| ittle 6610-FLN-4200.01 Fhvision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 2.1 Liquid Dose Converebn Factors (DCF): DF, Page 1 of 3 Ingestion Dose Factors for AdtAts*
| |
| (MREM Per PCIIngested)
| |
| NUCLIDE BONE _ LIVER T. BODY THYROID KfDNEY%g _ LUNG GI-LLI H 3 NO DATA 1.05E47 1.05E-07
| |
| .. I lh 1.05E-07 p5E-07 1.05E-07 C 14 2.84E46 5.68E47 5.68E-07 "5,66E47 ,/1.05E47 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 5.68E 07 1.70E-06 1.70E 06 1.70E46
| |
| *(17DE46 CR 51 NO DATA MN 54 NO DATA 2.66E-09 1.59E49 hN 4 1.
| |
| * 3.53E-09 6.69E47 NO DATA 4.57E46 8.72E47 NO DATA *. "T86E w -b1.36E 06 10 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 'fNO DATA 1.46E-07 NO DATA 3.67E 06 FE 55 2.75E-06 1.90E-06 4.43E 07 FE 59 .,g N O DATA NO DATA 1.06E46 1.09E 06 4.34E 06 1.02E-05 3.91E46.3g NQDATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 CO 60 1.67$Y4NO DATA NO DATA NO DATA 1.51E45 NO DATA 2.14E46 37pE46( NO DATA NO DATA NO DATA 4.02E-05 N! 63 1.30E-04 9.01E 06 , $.36E-06 ~ NO DATA NO DATA NO DATA 1.88E-06 i Mi 65 5.28E-07 6.86E-08/S!!g 3.I5Eh NO DATA NO DATA CU 64 NO DATA 1.74E46
| |
| ' NO DATA B.33E OS 9 3.91E48 NO DATA 2.10E.07 NO DATA 7.10E 06 ZN 65 4.B4E-06 NO DATA 1.54E-05am:li w 6.96E-06 1.03E-05 NO DATA 9.70E 06
| |
| ! ZN 69 1.03E-08 M 57E-08 1.37E 09 NO DATA 1.28E-08 NO DATA 2.96E49 BR 83 NO DATA NODATA 4.02E48 NO DATA NO DATA NO DATA 5.79E48 RR 84 NO DATA bilmifNCfDATA 5.21E 08 NO DATA l
| |
| NO DATA NO DATA 4.09E-13 '
| |
| l ?"L - -
| |
| BR 85 NO DATA NO DATA 2.14E49 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E 08 3.21 E-08 NO DATA l
| |
| NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E 08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 108E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR' 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E44 .
| |
| SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E 05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04
| |
| ~
| |
| t- .
| |
| 102.0 mm l . . _ _ . . _ . .
| |
| t
| |
| | |
| e g gy TMt Radiological Controls Departrnental Procedure Wmber Title 6610-PLN-4200.01 AeWeson No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 2.1 (Cont'd)
| |
| Liquid Dose Conversion Factors (DCF): DF, Page 2 of 3 Ingestion Dose Factors for Adults *
| |
| (MREM Per PCI ingested)
| |
| NUCUDE BONE fq3_,, T. BODY _ THYROID _ LUNG GI-LU Y
| |
| Y 91M 91 9.09E-11 1.41 E-07 NO DATA NO DATA 3.52E-12 NO DATA _ KIDNEY %,$
| |
| ,f "
| |
| NO. D6TA NO DATA 2.67E-10 Y
| |
| 3.77E49 NO DATA 92 8.45E-10 NO DATA NO DATQ NO DATA 7.76E 05 2.47E-11 NO DATA
| |
| --- -- NOAATA ~ NO DATA 1.48E45 Y 93 2.68E49 NO DATA 7.40E-11
| |
| %lQ ZR 95 NO DATA % MO DATA NO DATA 8.50E 05 3.04E-08 9.75E-09 6.60E-09 ZR 97 1.68E 09 3.39E-10 NO DATA %l *T.53E 08 NO DATA 3.09E45 1.55E-10 NO DATA '"%5.12E-10 NO DATA 1.05E44 NB 95 6.22E49 3.46E49 1.86E-09 hODATA 3.42E-09 MO 99 NO DATA NO DATA 2.10E-05 4.31E-06 8.20E-07 g TC 99M 9.76E 06 NO DATA 9.99E 06 2.47E-10 6.98E-10 8.89E-Oh, NQDATA j0 DATA 1.06E48 3.42E-10 4.13E-07 TC 101 2.54E 10 3.66E-10 RU 103 1.85E47 NO DATA 3.59dM['"**NO DATA 6.59E-09 1.87E 10 1.10E.21 RU 105 1.54E-08 397E48g', NO DATA 7.06E-07 NO DATA 2.16E-05 NO DATA 5.08E-09 NO DATA
| |
| .* lg . t 1.99E-07 NO DATA 9.42E 06 RU 106 2.75E-06 NO DATAk 3.255$7 NO DATA 5.31 E-06 NO DATA AG 110M 1.60E-07 1.48E 07 ' 8,79E-08 1.78E-04 SB 125 NO DATA 2.91E47 NO DATA 6.04E-05 1.79E-06 2.00E 06 gg 4.26E-07 TE 125M 1.82E49 0.0 1.38E-06 1.97E 05 2.68E46
| |
| , 9J1E47...
| |
| s . r$ 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E45 TE 127M 6.77E46 142ki-06 8.25E-07 TE 127 1.73E-06 2.75E45 NO DATA 2.27E-05 1.10E-07 3.95E 08 2.38E-08 8.15E48 TE 129M 1.15E-05 k[44.29E 06 1.82E 06 3.95E46 4.48E-07 4.00E45 NO DATA NO DATA 8.68E-06 5.79E-05 TE 129 3.14E48 1.18E-00 7.65E-09 TE 131M 2.41E 08 1.32E-07 NO DATA 2.37E-08 1.73E 06 8.46E-07 7.05E-07 TE 131 1.34E46 8.57E-06 NO DATA 8.40E-05 1.97E-08 8.23E 09 6 22E49 1.62E-08 8.63E 08 NO DATA 2.79E49 TE 132 2.52E-06 1.63E 06 1.53E-06 1.80E-06 1.57E45 NO DATA 1 130 7.56E-07 2.23E-06 7.71E45 8.80E 07 1.89E-04 3.48E46 1 131 4.16E-06 NO DATA 1.92E-06 5.95E 06 3.41E46 1.95E-03 1.02E-05 NO DATA 1.57E-06
| |
| ! 132 2.03E-07 5.43E-07 1.90E-07 1.90E45 1 133 8.65E 07 NO DATA 1.02E-07 1.42E-06 2.47E-06 7.53E-07 3.63E 04 4.31 E-06 NO DATA 1 134 1.06E47 2.88E47 2.22E-06 1.03E47 4.99E-06 4.58E-07 NO DATA 2.51E-10 1030 me.
| |
| | |
| I l l
| |
| Number Nuclear ' aad* coa"*
| |
| Departmental Procedure 6610-PLN-4200.01 Tstl* Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 i
| |
| TABLE 2.1 (Cont'd) I Liquid Dose Conversion Factors (DCF): DF, Page 3 of 3 Ingestion Dose Factors for Adults *
| |
| (MREM Per PCI Ingested)
| |
| NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG Ci-LLI
| |
| . p%
| |
| i 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E kNO DATA 1.31E46 !
| |
| CS 134 6.22E-05 1.48E44 1.21 E-04 NO DATA 4 79E-66,"/1.59E-05 2.59E-06 CS 136 6.51 E-06 2.57E-05 1.85E-05 NO DATA 143E45 1.96E-06 2.92E46 n..,f .
| |
| CS 137 7.97E 05 1.00E-04 7.14E45 NO DATA33 ,g'3.70E 05 1.23E 05 2.11E 06 CS 138 5.52E 08 1.09E-07 5.40E48 NO DATAig. 8.01E-08 7.91 E-09 4.65E-13 BA 139 9.70E48 6.91E 11 2.84E-09 NO DATAx '%6.46E-11 3.92E-11 1.72E-07 w
| |
| BA 140 2.03E C5 2.55E 08 1.33E-06 NO DATA 8.67E 1.46E-08 4.18E-05 BA 141 4.71 E-08 3.56E-11 1.SSE49 NO DATA 3.31E 11 2.02E-11 2.22E-17 BA 142 2.13E 08 2.19E 11 1.34E-09ng.,em,,MQ, 1.85E-11 DATA 1.24E.11 3.00E-26 LA 140 2.50E-09 1.26E49 3.335$9 **NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.2SE 10 5.82E-11 ) 45E 11 %3, NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 .18E-10 NO DATA 2.94E49 NO DATA 2.42E45
| |
| -- - l, {' .,._l
| |
| ~
| |
| CE 143 1.65E 09 1.3' E 10 5 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.8BE-07 1.22E 060gf 2.04E 07 2 .62E.38 NO DATA 1.21 E-07 NO DATA 1.65E-04 PR 143 9.20E49 3.69Ep%g 4.56E-10 NO DATA 2.13E49 NO DATA 4.03E45 PR 144 3.01 E-11 %.5Ed 1.53E 12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 7 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 6.29E-09 1.03E-07 .g%j 8.61E.27E49 08 3.01 E-08 NO DATA NO DATA NO DATA 2.82E45 NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E 05
| |
| * Dose factors of internal exposure are for continuous intake over a one-year porlod and include the dose commrtrnent over a 50-year period; from Reg. Guide 1.109 (Rev.1). Additional dose factora, for nuclides not included in this table may be obtained from NUREG-0172.
| |
| l l 104.0 mm
| |
| | |
| 1 Number
| |
| - gggp TMl Radiological Controls Departmental Procedure l Tsue 6610-PLN-4200.01 nedmon No.
| |
| ONshe Dose Calculation Manual (ODCM) 16 l
| |
| TABLE 2.2 Bloaccumulation Factors, BF, Blosccumulation Factors to be Used in the Absence of Site Specific Data *
| |
| (pCl/kg per pCl/ liter)
| |
| FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E-01 9.0E41 '4-C 4.6E + 03 9.1E403 NA 1.0E + 02 h
| |
| 2.0E 02 w #
| |
| CR 2.0E + 02 2.0E"tiO3 MN 4.0E + 02 ,he.0 Ego 4 FE 1.0E + 02 twup3.2E 403 C0 5.0E + 01 $
| |
| "%4 2.0E + 02 !
| |
| NI 1.0E + O2 "
| |
| CU Sig*"," 1.0E + 02 i 5.0E+0h 4.0E + 02 i 2N 2.0E + 03]j, 1.0E + 04 BR 3.3E + 02 4.2E4022ll RB 2.0E+03 h h. 1.0E + 03 SR f~3.0l!4,01, 1.0E + 02 j
| |
| Y 2.8E + 01 1.0E + 03 ZR NB
| |
| [#.1 i
| |
| "ta.5E+ 00 6.7E + 00 10E + 04 1.0E + 02 MO .f 5%ril.0E + 01 l
| |
| TC # ((4 1.5E + 01 1.0E + 01 5.0E + 00 t
| |
| RUf*d' 4 1.0E + 01 3.0E + O2 RHi,,g*"- 1.0E + 01 3.0E + 02
| |
| ***AG1 110rg/ 2.30E + 1 7.70E + 2
| |
| "?!S83,. " 1.0E + 00 1.0E + 00 4 /TE i lg
| |
| * 4.0E + 02 0.1E+ 03 1.5E + 01 5.0E + 00
| |
| ! %CS 2.0E+ 03 1.0E + 03 BA 4.0E + 00 2.0E + 02 1.A 2.5E + 01 1.0E + 03 CE 1.0E + 00 1.0E + 03 PR 2.5E 4 01 1.0E + 03 ND 2.5E + 01 1.0E + 03 W 1.2E + 03 1.0E + 01 NP 1.0E + 01 4.0E + 02 1
| |
| Bloaccumulation factor values are taken from Reg. Guide 1.109 (Rev.1), Table A 1).
| |
| Sb bloeccumulation factor value is taken from EPRI NP-3840.
| |
| Ag bloaccumulation factor value is taken from Reg. Guide 1.109 (Rev. 0), Table A-8.
| |
| 105.0 mm l
| |
| | |
| I Number GUCIS8r TMl Radiological Controls l Departmental Procedure Tm 6610-PLN-4200.01 l %. ion No.
| |
| l l Offsite Dose Calculation Manual (ODCM) i 12 3.0 TMl LIQUID EFFLUENT WASTE TREATMENT SYSTEMS 3.1 TMI-1 Liould Effluent Waste Treatment System 3.1.1 Description of the uguld Radioactive Waste Treatment System (see Figure 3.1)
| |
| Reactor Coolant Train a.
| |
| Water Sources - (3) Reactor Coolant Bleed Tanks (RCBT)
| |
| - (1) Reactor Coolant Drain f Tank (RCDT)%.,
| |
| b.
| |
| Liquid Processing - Reactor Coolant Waste Evaporatpr igure 3 2) (seefl Domineralizers prior to releaseI "(,g c.
| |
| 'No /
| |
| Liquid Effluent for Release - (2) Waste Evap6 tats Condensate Storage Tanks (WECST) q,g m [ d'i' d.
| |
| gy 5
| |
| Dilution Mechanical
| |
| - River Flow (2E7 gpm Draft Cooling average) '"!i! TowerJ >-38k gpm)
| |
| Miscellaneous Waste Train
| |
| 'If
| |
| .,m%
| |
| : a. Water sources: -/[pgugley Building Sump ReactorBuGding Sump M
| |
| f#D iscellaneous Waste Storage Tank
| |
| . f Laundry Waste Storage Tank
| |
| /[%gy4g- Neutralizer Feed Tank 4y Neutralizer Mixing Tank hlib. - Used Precoat Tank i* jA pas, - Borated Water Tank Tunnel Sump 4 I - Heat Exchanger Vault Sump i % g% W - Tendon Access Galley Sump l ..rs 4 l
| |
| - Spent Fuel Pool Room Sump
| |
| % 4 TMI-2 Miscellaneous Waste Holdup Tank b.
| |
| 4 [h Uguld Processing Miscellaneous Waste Evaporator, MWE (see Figure 3.2)
| |
| Demineralizers prior to release
| |
| : c. Liquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST)
| |
| : d. Dilution - Mechanical Draft Cooling Tower (0-38k gpm)
| |
| - River Flow (2E7 gpm average) 106.0 mer j _ _ _ . . . , _ - . . .
| |
| L
| |
| | |
| (
| |
| i gggy TM1 Radiological Controls Departrnental Procedure Numbw f T** 6610-PLN-4200.01 HeWon No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 3.2 Operabaity of the TMI-1 Liould Effluent Waste Treatment System 3.2.1 The TM1-1 Uquid Waste Treatment System as described in Section 11 of the TMl-1 Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is avalable to perform its intended function:
| |
| a) Miscellaneous Waste Evaporator (WDL-21B) or Reactor Coolant Evaporator (WDL-Z1A) b) Waste Evaporator Condensate Domineralizer (WDL-K3 A.or B) oF%
| |
| c)
| |
| Waste Evaporator Condensate1 AStorage i o(B) if Tank (WDL-Tp,%
| |
| d) Evaporattv Condensate Pumps (WDL-P 14 A oh[B)# nyf
| |
| , 3.2.2 %y "Q TMl 1 Representative Sampling Prior. tosgDischarge k e
| |
| yaw,.4 kjp NI-All liquid releases from the TMI-1 Uquid Waste Treaiment System are made through the Waste Evaporator Condensa e Storage. Tanks. Tciprovide thorough mixing and a
| |
| ! representative sample, the contents of the tank are recirculated using one of the Waste Evaporator Condensate Transfer Pump {
| |
| 3.3 es '%
| |
| .TMI-2 Uould Effluent Waste Treatment:Sys% tem gg a.:g;w 3.3.1 Description of the TM1-4LG0ldpad.loactivo Waste Treatment System
| |
| ,i 1 The TMl-2 Uquid Radioadeyaste Treatment System has been out of service since the TMI-2 Accident in1979. TM12 Uguld Radloactive Waste is processed by the TMI-1 system described in Sectin 3.p prior to release. In addition, TMl-2 releases water from various sumps and tsnks:tofbe river (see Figures 1.1 and 1.2). These processes are governed by plant proceddis that encompass proper sampling, sample analysis, and radiation monitoringlochn%0es.
| |
| t yj?Nis ifg; l
| |
| l i
| |
| 107.0 222k I
| |
| | |
| i i
| |
| TM) Radiological Cottrols y Departmernal Procedure 6610-PLN-4200.01 l m %.on No.
| |
| Wisite Dose Calculation Manual (ODCM) 12 l FIGURE 3.1 mi-1 uguid Redweste
| |
| ' ac
| |
| ~"
| |
| B. A. MU-Vs 4 -r L RC DRAIN SWST' SUMP ----+
| |
| RB S.F. SUMP
| |
| * [ (g SUMP TEND. GAL.
| |
| # f i -e Suue y geLE 4 unsC. oRaw g %# ==
| |
| AuxstDo 4 SUMP -
| |
| & REUEF
| |
| ,, ,,, r % . a"t1,%. ,v-l
| |
| 'r ,rv + ^ 4 ,s ,g 4 4 Rest A %e "RCar s RCsTc Tj$ ----+ 'u"$7 I e[t i I h
| |
| I h J
| |
| .p;;rr j,
| |
| 'p"''
| |
| $:4 4 h ,h 9, 1r qr
| |
| 'F 'F ..
| |
| iki) +g' u l
| |
| ,p@i'luliq,. $ v' i li 31 CATION p PRECOATp Jf
| |
| , on, DEMIN FILTER PRECOAT #,CATIONm & MAKE UP 4 FILTER - DE' MAN TO MU-V9
| |
| !# ' (1 OF;.2)
| |
| ( 1 OF 2) gil igg!' '" ")
| |
| J
| |
| " b ,,
| |
| r'%rv, . RC WASTE j
| |
| " MISC. WASTE EsTiu. ATE EVAR 4!!!igi$ ib[ EVAR II I DISTILLATE 3r ill:;g, U
| |
| 'P 4 +
| |
| M AT CWST 4_,,_ ggy ,,,,,,
| |
| (1 O F 2)
| |
| (1 O F 2) gg awam.
| |
| h b h MDCT k
| |
| * HITTMAN 2 9P + E.FFLUENT -i BUILDING ' U WECST I COND.
| |
| RECLAIM (1 O F 2)
| |
| DEMIN WATER , DEMIN 4_,,
| |
| WATER STOR TANK ! (1 CF 2)
| |
| RECLAIMED WATER SYSTEM 108.0 .
| |
| | |
| Number EE TMl Radiologeal Controls Departmersal Pr~ wiure !
| |
| 6610-PLN4200.01 Amneon te.
| |
| Offsite Dose Calculation Manual (ODCM) 12 FIGURE 3.2 TMI-1 Liquid Weste Evaporators 450J gw 0 '
| |
| g8 '
| |
| u9
| |
| ^
| |
| ' l
| |
| ~ z o
| |
| ud.5:mz gr pmg I ,$.
| |
| e p ,4!
| |
| >( W b.
| |
| p k
| |
| , , ' h; p, l l
| |
| - .ao. *+$ (%;P "*
| |
| j g ("g, W w 3
| |
| b q r ^$ '
| |
| < a s 0 ,, g%
| |
| a ,
| |
| q> 759 mea .. i s j u
| |
| .Ih j, '!"g g gh i >
| |
| $o e # v
| |
| / f%~ gg) ,"tl~ <_A is - c mit e
| |
| 4h k ~4 -, =
| |
| g 4 (
| |
| 1*~ '
| |
| 9 f* 2[f#9 ..
| |
| r E
| |
| .g D
| |
| l ;.::A4 ._-
| |
| J, g
| |
| 6 Af,ig lis ,yg,, 4 k e
| |
| :gh o +en . . -
| |
| i !
| |
| y&g jg g n 8
| |
| 'V i 3 8 .
| |
| < . .. y-=
| |
| .g E 1: 1: 1: o 4' ;Y e se oi g
| |
| 109.0 **
| |
| ' ' ~ ~ **
| |
| | |
| F l
| |
| Number ggp TMl Radiological Controls Departmental Procedure l True 6610-PLN-4200.01 n.vson No.
| |
| l Offsite Dose Calculation Manual (ODCM) 12 4.0 GASEOUS EFFLUENT MONITORS l
| |
| 4.1 TMI-1 Noble Gas Monitor Set Points The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in ODCM Part i Control 2.2.2.1. Table 4.1 lists Gaseous Effluent Release Points and their associated l
| |
| parameters; Figure 4.1 provides a Gaseous Effluent Release Pathway Diagram.
| |
| The set points are established to satisfy the more restrictive set point concentration in the following two equations:
| |
| #""""l
| |
| $ ig}E 500 > I(c)(F)(Kj(Dv) 1
| |
| (/
| |
| in f 1
| |
| / (eg 4.1.1) i and
| |
| , '(yg
| |
| %"+
| |
| w 3000 > E (c)(L, + 1.1 Mj(Dv)(F) qtg,%, (eg 4.1.2) l g% '
| |
| l
| |
| 't where:
| |
| %,j c, = set point concentration M>n 3 equivalent, in pCl/cc g
| |
| F= gaseous effluent flowMs s$genn the monitor, in cc/sec
| |
| ~
| |
| ,k ll j
| |
| K= total body dose fact 4'"1n, mrem /yr per pCl/m' from Table 4.3 flig l i
| |
| Dv = highest sector ann,ual average gaseous atmospheric dispersion factor (X/Q) at or beyond.themunrestricted area boundary, in sec/m', from Table 4.4 for station vent releane5% Tible 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releasseh. Msdmum values presently used are 7.17E-7 sec/m8 at sector NNE for st 4,g. gnent, and 1.16E-5 sec/m' at sectors N and WNW for all other releases.
| |
| l, = skdose factor due to beta emissions from radionuclide I, in mrem /yr per pCl/m' from Table 4.3.
| |
| M= air dose factor due to gamma emissions from radionuclide I, in mrad /yr per pCl/m' from Table 4.3.
| |
| 1.1 = mrc,m skin dose per mrad air dose.
| |
| 500 = annual whole body dose rate limit for unrestricted areas, in mrem /yr.
| |
| 3000 = annual skin dose rate limit for unrestricted areas, in mrem /yr.
| |
| The set point concentration is further reduced such that the concentration contributions from multiple release points would not combine to exceed ODCM Control limits.
| |
| The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.
| |
| 110.0 mie 1
| |
| L
| |
| | |
| I, Number E Nuclear True m' a dio'ooicai coarroie Departmental Procedure 6610-PLN-4200.01 l Revisiori No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 l
| |
| This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste. ;
| |
| l vilgenm!,n,,
| |
| w.
| |
| 'i1, l4
| |
| # N). '
| |
| l 1
| |
| % jiik 'ii%gnsi fit. b! k
| |
| '*lg 'j'tj;,,
| |
| i
| |
| . N'I'USch !$jn. -
| |
| l l '! iip!!g44 3
| |
| m ,,'If:l':.
| |
| 94
| |
| ! ti:mim,("%
| |
| f "!! !!!,
| |
| :til- tH
| |
| \ jdIIrHT4; iip EE p# k\;e,. m;s,
| |
| ./ $k%rr.,e l
| |
| ",p :g'+4e l
| |
| l peg 'H!lg IS
| |
| % ;qgi/
| |
| g;,, 'll g %#)l'l i
| |
| 4!! nij:
| |
| g jil?g'igt #
| |
| 11 , 4 l Mg f
| |
| l l
| |
| t I
| |
| i 111.0 n, 1
| |
| | |
| i Number gggy TMI Radiologicc.l Controls Departmental Procedure 6610 PLN-4200.01
| |
| ]
| |
| 1 Title Revision No. I Offsite Dose Calculation Manual (ODCM) 12 4.2 TMl-1 Particulate and Radioiodine Monitor Set Points Set points for monitoia which detect radionucides other than noble gases are also established to assure that concentrations of these radionuclides in Gaseous effluents do not exceed the limits of ,
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| ODCM Part i Control 2.2.2.1. l l
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| Set points are established so as to satisfy the following equations:
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| l 1
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| 1500 > Z(c)(F)(Pj(Dv)
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| (eg 4.2)
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| I ,
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| pm*%
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| where: fq3 c, = /,i.nCi/Sc%j p
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| set point concentration based on *lg1-131 equivalent (91L ,
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| F= gaseous affluent flow rate at the monitor, inicc/sec 4 o l
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| 9g "<4 >
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| P, - pathway dose parameter, in mrem /yr per M/m' for the inhalation pathway from Table 4.6. The dose factors are based on tlis actual Individual organ and most restrictive age group (child) (NUREG-0133).
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| .%.3
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| .cNOTE %
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| Appendix A co_nlaN' Pi,;i! Tg.g. calculational methodology.
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| $ g*
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| 1500 - annual dose rate limit to any organ from particulates and radiolodines and radionuclideslother"thafinoble gases) with half lives greater than eight days in mrem /yr g ,[ %!
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| Dv = highpsfesakannual averags gaseous dispersion factor (X/O or D/Q) at or beyond the unrestricted area boundary from Table 4.4 for releases from the station vent and
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| %!yalues TaSof5Jor all other releases. X/Q is used for the inhalation pathway. Maximum of X/O presently used are 7.17E-7 sec/m' for station vent, at sector SE, and 146E-5 sec/m' for all other releases, at sectors N and WNW.
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| m The set point concentration is further reduced such that concentration contributions from multiple release points would not combine to exceed ODCM Control limits.
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| The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.
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| This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.
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| * 112.0 mm
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| Number
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| - gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 It6e Revision No.
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| Offsite Dose Calculation Manual (ODCM) 12 ;
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| I l
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| 4.3 TMI-2 Gaseous Radiation Monitor Set Points I TMI 2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 1101-2.1.
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| Figure 4.5 provides a gaseous effluent release pathway diagram. Table 4.2 provides TMI-2 Radiation Monitor Data.
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| These set points are set in accordance with the Controls delineated in Part II of this ODCM.
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| .pmus .
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| i.
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| .# Y iijo .i!
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| I
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| .f'i' .. Hahm;;#
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| ''9,j, . "ili,q .
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| U5$ii ljn. ~
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| *%3 ,,,l"%g3,
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| , s Isi!h n
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| e .W1 l f
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| jf!!;;-
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| k l s ,p m
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| !!if#E_ lli:n. ' lith.
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| !h
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| ! 'h "lij;t
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| .y @s I
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| ,;(, %#'
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| g;pihijg. ig 31;N
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| ,L
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| ~
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| qg 3rg dmdf i
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| ''Ilj ll0 '1ij 3 b l
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| l 113.0 222k
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| I l
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| l l
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| l Number I" UClear i Radiological Controls Departmental Procedure 6610-PLN-4200.01 !
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| me wWon No.
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| Offsite Dose Calculation Manual (ODCM) 12 1
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| 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radration Monitor Data l
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| TMI-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-AS, i RM-AIS, RM-AS, RM-A7, RM-A8, RM A9, RM-A14, ALC-RMI-18, WHP-RIT-1, and RLM-RM-1. These I gaseous release points, radiation monitors, and sample points are shown in Tatje 4.1.
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| 4.4.1 RM-A4/RM-A6 Fuel Handlino and Auxiiary Boudino Exhaust i l
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| RM-A4 is the particulate, radiolodine and gaseous radiation monitor for the TMI-1 Fuel Handling Buuding Ventilation (see Figures 4.1 and 4.2). RS -A6 is the parthulate, .
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| radiolodine, and ga*eous radiation monitor for the TMI 1 Malliar9 Bulding Ventilation (see l Figures 4.1 and 4.2). Kgh alarms on RM-A4 or RM-A6 noble 7 gar channels will Initiate l shutdown of the related building ventilation air supply system'.41gesi two radiation monitors concurrently will satisfy requirements for the Station Vent release poht in place of RM-AB. l 4.4.2 RM-A8 Station Ventilation Exhaust
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| \Y
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| ,,g.ju[4
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| .g 3("N RM-A8 is the particulate, radiolodine and gaseo'Og radiation monitor for the TMI 1 Station Ventuation (see Figures 4.1 and 4.2). This in plani"isftluent radiation monitor also has an associated sampling panel with samplith lines located before the sample filters. High alarm on RM-A8 noble gas low channel wiu,. initiate shutdown of the Sta' on Ventilation air supply systems. (The Fuel Handling and(uxRIAnf, Building Ventilation). This rad!ation monitor satisfies requirements for the, Station Vent release point in place of RM-A4 and RM-A6.
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| yy%
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| 4.4.3 RM-AS/Rh/ %15 CondensefUff das_ Exhaust i E i RM-A5 is the gaseods radiatlorimonitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4"4ptRM-A15 is the back up gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15 ribble gas channels will initiate the MAP-5 Radioiodine Processor Station. These two radiatlog monhors together satisfy requirements for the Condenser Off Gas release point. hr-g3-t #1,Ih ''
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| 4.4.4 RM-A7 Waste,. Gas Decay Tank Exhaust RM-A7 is the gaseous radiation monitor for the TMI-1 Waste Gas Decay tanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampilng panel. High alarm on RM-A7 noble gas channel will Initiate shutdown of the Waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point.
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| 4.4.5 RM-A9 Reactor Buildina Purae Exhaust RM-A9 is the particulate, radiolodine and gaseous radiation monitor for the TM1-1 Reactor Building Purge system (see Figures 4.1 and 4.3). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters.
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| High alarm on RM-A9 noble gas low channc! will initiate shutdown of the Reactor Building Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge System release point.
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| 114.0 mm
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| Number gggy TM1 Radiological Controls Departmental Procedure Title 6610-PLN-4200.01 Revision No.
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| Offsite Dose Calculation Manual (ODCM) 12 4.4.6 RM-A14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMI-1 Emergency Safeguards Features (ESF) Fuel Hand!Ing Building Exhaust system (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sampler filters. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF Fuel Handling Bulding Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling Building Exhaust System release point.
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| 4.4.7 ALC-RMI-18 Chemical Cleanina Facility (CCF) VentBation Exhaust pm%g ALC-RMI-18 is an Victoreen particulate, radiolodine, and gase,ous radiation monitor for the Chemical Cleaning building exhaust. This monitor is located"In.the Chemical Cleaning bulding on the ground floor, and has an associated sampf paw Sampling for particulate actMty is performed off of the monnor.
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| ''%fis 4.4.8 m. . l\ %
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| WHP-RIT-1 Waste Handlina and Packaalna Facility [MfPF) Exhaust ig, . *!g, WHP-RIT-1 is an Eberline AMS 3 particulate radiation monitcr for the TMl WHPF. The monitor is located in the Mechanical E(ulpment Room in the WHPF. Sampling for particulate actMty is performed off ofjhe monitor. A high alarm will initiate shutdown of the ventilation air exhaust system.%g .
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| ph 4.4.9 RLM-RM-1 Reso!rator Cleanir$xandDiundry Maintenance (RLM) FacNity RLM-RM-1 is an EbertinAlF% *;;,
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| /.MS-3,. particulate radiation monitor for the TMI RLM Facility. The monitor is located inihe*.dechanical Equipment Room in the RLM. Sampling for particulate activity is performed off of the monitor.
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| 9% %
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| \
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| hd 1;, 94 hsf 0 i!
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| ai;Y L
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| 115.0 m=
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| jggy TMI Radiological Controis Departmental Procedure Number Tme 6610-PLN-4200.01 Revision No.
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| Offsite Dose Calculation Manual (ODCM) 12 4.5 TMI-2 GP,eous Effluent Release Points and Gaseous Radiation Monitor Data TMI 2 has three (3) regulatory required gaseous effluent radiation mor* ors. These are HP-R 219.
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| HP-R-219A and HP-R-225. These gaseous release points, radiation monitors, and sample points are shown in Table 4.2, and various gaseous effluent pathways are depicted in Figure 4.5.
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| 4.5.1 HP-R-219 Station Ventila+ ion Exhaust HP-R-219 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328 foot elevatfors and has an associated sample panel. g!!#%rm O!
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| 4.5.2 HP-R-219A Station Ventilation Exhaust j# $!;q,, ,.,,[4 g%. 34 HP-R-219A is a Victoreen particulate and gaseous rddiation!? monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor ja located in the TMI-2 Auxiliary Building 328 foot elevation. f"ig *"di
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| ..g%g9th 4.5.3 HP-R-225 Reactor Buildina Purae Air Exhaust Duci*A" HP-R-225 is a Victoreen particulate and baseous radiation monitor for the TMI-2 Reactor Building Purge Air Exhaust System. This'in TMl-2 Auxiliary Building 328' eldatibn area'.'.-plant effluent radiation monitor is located in the gp%
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| p*% iiq
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| # 'l .Jf pl ''iitsnif jm 3;,,
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| kw$ .
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| j 4:#
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| ; g%"'!gg%
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| i t
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| ,ri;4: iirjf%.+ ik i,y, k
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| 116.0 nm
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| -- - -- ~ --
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| \
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| I
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| )
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| I Number l
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| $tIClear TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01 D8 Revislort No.
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| Offsite Dose Calculation Manual (ODCM) 12 4.6 Control of Gaseous Effluent Releases TMl Daseous effluent combined releases are controlled (per ODCM Part I for TMI 1 and ODCM Part 11 for TMI-2) by effluent sampilng and radiation monitor set points. These measures assure that releases from the various vents do not combine to produce dose rates at the site boundary exceeding the most restrictive of 500 mrem per year to the total body or 3000 mrom per year to the skin, and 1500 mrom per year to the thyrold. This is done by restricting simultaneous releases and by limiting the dose rates that may be contributed by the various vents at any time. The various vent radiation monitor sot points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2#%egactual set points are then listed in TMl-1 Operations Procedure 1101-2.1. 0 $
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| ji* i
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| ,lr The radioactive content of each batch of gaseous waste is detaf hl r to release by sampilng and analyses in accordance with ODCM Part I for TMl-1 and ODCM Part 11 for TM!-2. The results of pre-release analyses are used with the calculational methods _intSestions 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained belodthi!!rhlts in ODCM Part I for TMI-1 and ODCM Part 11 for TMI-2.
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| 'lig $4
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| , +
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| Post-release analyses of samples composited from batch and continuous releases are performed in accordance with ODCM Part i for TMI-1 and ODCM Part il for TMI-2. The results of the analyses are used to assure that the dose rates at the. site $6bndary are maintained within the limits of ODCM Part I for TMI 1 and ODCM Part 11 for.TMI-2 Si3 ,p.%
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| #Niin kni.
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| o
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| 'ij %
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| j kgg gif %
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| ppl$Isi m
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| !gsi gw 4Iiggil ip g
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| 117.0 me.
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| Number gggy TMt Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tme R. vision No.
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| Offsite Dose Calculation Manual (ODCM) 12 TABLE 4.1 TMl-1 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION GASEOUS (F) INTERLOCK MONITOR RELEASE FLOW (YES/NO)
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| (DETECTOR) LOCATION POINT RECORDER VALVES YES ..,
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| AH-E;10"%
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| Fuel Hand. AH-D420 o 306' Bevation Building AH-Dk21 E RM-A4 AuxlNary Bldg. Exhaust FR 14g j!'%H-@1221'"
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| Auxiliary l;, ''il!l[
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| 306' Bevation Sullding % YES RM-A8 Auxiliary Bldg. Extaust FR.15bh %IME.11 Ml!;n,. , YES MI!;m WDG-V47 r AH-E-10 AH-E 11 RMA-8/9 Bldg. 't!!!% 1. Starts MAP 4 Near BWST Stajiertj;. '"!!fR-14g Radiolodine RM-A8 Exhaust Vent J & FR-150 Sampler
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| .. %f YES 322' ElevatAE donnnser Starts MAP 4 Second Floor Off;faas Radioiodine RM A5 TurbimeI Blds... Enfinust FR.1113 Sampler
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| ## YES
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| '(
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| .+ 322' Elevbn Condenser Starts MAP-5
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| ( Seenrad Floor RM-A15 % Turbise Bldg.
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| Off Gas Exhaust FR 1113 Fladiolodine Sampler gj, m. uw g,,,, g,, j 306' Bevatior. Decay Tanks YES l
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| ,gS!;fWl-A73.,aE!!g AuxlEary Bldg.' (A,B.C) FR 123 WDG-V47 i it YES AH-V-1A/B/C/D Reactor WDG-534/535 Building Starts MAP 4 RMA-8/9 Bldg. Purge FRSO9/ Radiciodine RM-A9 Near BWST Exhaust FR 148 Sampler j 331' Bevation l
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| ESF FHB ESF Fuel j Outs 6de Handling NO Chem. Building Manual RM-A14 Addition Bldg. Exhaust FR-1104A/B Actions )
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| i 118.0 mm
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| gggy TMI Radiological Controls Departmental Procedure Number Title 6610-PLN-4200.01 Revislor No.
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| Offene Dose Calculation Manual (ODCM) 12 TABLE 4.1 (Cont'd) f TMl-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RELEASE RADIATION GASEOUS TERMINATION MONtTOR RELEASE INTERLOCK (DETECTOR) LOCATION POINT (fES/NO) VALVES Chemical Cleanlrig CCB Exhaust ALC RML18 Bidg. 304* Elevation System NONE en YESjE k, WHPF Mechanical WHPF Exhaust WHP-RIT 1 Equipment Room System WHPFyentation f ji'Tr!pe %ff!w RLMMechanical RLM Exhaust g %WF RLM RM 1 Equipment Room System
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| '"%NONE
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| , m.m, TABLE 4.2 *%;. 314+..
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| yig,.
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| TMI-2 Gaseous Release Point and Gaseous RadiItion Monitor Data i Ill
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| .e.. '"ilb RELEASE GASEOUS RADIATION JFl TERMINATION 4Eh /M w GASEOUS INTERLOCK MONITOR gag k! RELEASE (YES/NO)
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| (DETECTOR) LOCATION (4POINT VALVES 328 Eleva Station gg,y , tion *mm!*4 Vent HP-4219 Building Exhaust NONE
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| [ .. 846' Elevation
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| ,1 4!i1#s AuNiliary Station Vent HP.R 219A aullding Exhaust NONE jdh,94
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| '4 9:;j f"' Reactor Bldg g,;g 328' Elevation Auxiliary Purge Exhaust HP4225 Building Duct 'A' NONE l
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| I l
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| l l
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| 119.0 mm e
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| l ggy Ml Radiological Controls Departmental Procedure Number l Tethe 6610 PLN-4200.01 Fievision No.
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| 1 Offsite Dose Calculation Manual (ODCM) 12 TABt.E 4.3 A
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| Dose Factors for Noble Geses and Daughters
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| * Gamma Beta Total Body Skin Dose Gamma Air Beta Air Dose Factor (a) Factor (b) Dose Factor K, Dose Factor t, M, Radh (mrem /yr per (mrem /yr per N,
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| nuclide (mrad /yr per "*"% (mrad /yr per yCl/m') pCl/m') 1 pCl/m') I. 1 pCl/m')
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| Kr-83m 7.56E-02" -
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| 1.93E + 01"' #
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| 2.88E + 02 Kr-85m 1.17E + 03 1.46E + 03 1.23E203 54 1.97E + 03 Kr-85 1.61E + 01 1.34E + 03 4j2E/df* 1.95E + 03 Kr-87 5.92E + 03 9.73E + 03 6.UEfb3 1.03E + 04 Kr 88 1.47E+ 04 2.37E + 03 1.52E+ 04 2.93E + 03 Kr-89 1.66E + 04 1.ot E t 04,. ' 4 1.73E + 04 i
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| 1.06E + 04 Kr-90 1.56E + 04 7.295+0$4 1.63E + 04 7.83E + 03 Xe-131m 9.15E+ 01 /E70$ td2- 1.56E 4 02 1.11E + 03 Xe-133m #
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| 2.51E + 02 9.94E802 3.27E + 02 1.48E+ 03 Xe-133 2.94E + 02[f *( 3.06E + 02 3.53E + O2 1.05E + 03 Xe-135m #
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| 3.12E + 53# 7.11E + 02 3.36E + 03 7.39E4 02 Xe-135 1.81E703 # 1.86E + 03 1.92E + 03 2.46E + 03 Xe-137 4.4$5703 1 1.22E + 04 1.51 E + 03 1.27E + 04 Xe-138 8.85E4 03 4.13E + 03 9.21 E + 03 4.75E + 03 Ar-41 8.84E + 03 2.69E + 03 9.30E + 03 3.28E + 03
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| * Dose factors are for immersion exposure in uniform semi-infin!!e cloud of nobte gas radionuclides detected ingaseous effluents. Dose factor values are taken from Regulatory Guide 1.109 (Rev.1), Table
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| **7.56E42 - 7.56 x 10-2,
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| (:) Total body dose factor for gamma penetration depth of 5 cm into the body.
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| l l
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| (b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm'.
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| 120.0 nm.
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| )
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| l t
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| Number gggy TMI Radiological Controls Departmental Procedure Tu 6610-PLN-4200.01 Revision No.
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| Offsite Dose Calculation Manual (ODCM) 12 TABLE 4 4 Atmospheric Dispersion Factors for 1hree Mile island 0 STATION VENT DISTANCE o SECTOR AVERAGE X/O (fN SEC/M3) (IN METERS) SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 58315 72405 N 1.18E 07 5.32E& 2.95E-07 1.93E-07 1.39E 07 5.52E48 1.91E 08 5.02E 09 1.88E-09 1.00E-09 NNE 1.70E-07 7.17E47 3.45E 07 2.00E47 1.30E-07 5.58E-08 1.70E-08 4.77E49 1.98E49 9.69E 10 NE 1.12E-07 1.75E-07 3.26E.07 1.86E-07 1.21E-07 5.00E 08 1.67E-08 4.67E 09 1.85E 09 9.93E-10 ENE 1.09E-07 2.13E47 2.67E 07 1.53E 07 1.05E-07 4.31E-08 1.42E 08 A42E49 1.59E49 8.64E-10 E 2.31E47 1.71E-07 1.52E 07 1.49E 07 1.06E47 4.63E48 1.52E-08 15.19E 00 2.48E-09 150E 09 ESE 3.50EW 2.12E 07 2.50E47 1.48E-07 9.48E-08 3.98E48 1.505-08 't.a2E49 2.92E49 1.93E49 SE 4.19E-07 3.79E-07 2.53E47 1.55E 07 1.11E 07 4.82E 08 1.81E48 d
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| 6.84E49 3.30E49 2.22E49 SSE 2.90E47 3.62E 07 2.55E47 1.49E-07 1.11E-07 5.02E-08 1.00E 081 6.97E 00 2.94E49 1.70E 09 S 1.87E 07 6.47E 08 2.18E 07 1.30E47 8.65E48 4.00E48
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| * E1;40E48 4.96E-09 1.99E 09 1.04E 09 SSW 613E 08 4.18E 08 1.56E 07 1.03E-07 6.81E-08 2.72E40% 0.74E 09 3.01E 09 1.50E-09 8.23E-10 SW 5.76E-08 1.14E 07 1.70E47 1.05E47 6.93E 06 4 2.51E48 8.34E49 2.72E-09 1.33E49 8.33E-10 WSW 8.52E48 3.75E-07 2.14E47 1.26E47 7.74E48 h 3.08E48 1.02E-08 3.28E49 1.39E49 9.69E-10 W 1.15E 07 5.80E-07 2.88E 07 1.83E47 1.18E4P IE.23E48 1.72E48 5.06E 09 1.98E49 1.25E49 WNW 1.41E-07 6.28E 07 3.30E47 2.19E 07 J.'48E47 5.68E46 1.95E-08 6.32E49 2.16E49 1.34E49 NW 1.42E 07 5.67E 07 3.17E-07 1.93E 07.. "I 30E 07" 5.67E-08 2.06E 08 5.90E49 2.70E 09 1.45E 09 NNW 1.00E47 5.77E 07 3.18E47 1.80E47 7 27E 07 5.20E-08 i
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| 1J7E-08 4.82E49 2.01E49 1.22E49 o STATION VENT o SECTOR AVERAGE D/O (IN M-2) skq[ \.g'(dSTANCE IN METERS)
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| SEASON. ANNUAL SECTOR 610 2413 4022 4 5681 7240 12067 24135 40225 56315 72405 N 2.51L 09 8.72E-10 4.84E 10@ +R.98E-10 2.50E 10 8.57E 11 2.51E.11 4.98E-12 1.57E 12 7.84E-13 NNE 3.89E49 1.98E49 9.54E 1Gr 4 4.99E 10 3.38E 10 1.10E 10 2.89E-11 6.06E-12 2.10E-12 8.89E 13 NE* 2.58E-09 6.70E 10 ;9,13E40 4.91E 10 2.97E-10 1.04E 10 2.87E 11 6.01E 12 1.99E-12 9.23E-13 ENE 2.15E49 5.85E '10s 5.54E 10 3.06E 10 2.08E 10 8.30E 11 2.32E 11 5.41E 12 1.63E 12 7.64E 13 E 5.54E-09 1.23E 09 !;.6.17E 10 4.59E-10 3 63E-10 1.34E-10 3.66E.11 9.44E-12 3.77E-12 1.97E-12 ESE 9.17E49 2.05E 09 1.51E 09 8.66E 10 5.11E 10 1.82E-10 5.77E 11 1
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| 1.72E-11 7.07E 12 4.07E 12 SE 1.22E48 2.88E49 1.84E 09 1.02E 09 6.85E 10 2.80E-10 8.30E-11 2.34E 11 9.42E-12 5.51 E-12 SSE 7.50E-09 1.62E-09 1.08E 09 5.89E 10 4.49E-10 1.87E 10 6.16E-11 1.61E 11 5.67E 12 2.83E-12 6 3.86E 09 6.53E 10 6 27E-10 3.59E 10 2.32E-10 1.06E-10 3.05E 11 8.10E 12 2.73E 12 1.23E 12 SSW 1.13E-00 2.94E-10 4.19E-10 2.53E-10 1.56E-10 5.38E 11 1.68E 11 3.91E 12 1.64E-12 7.84E 13 l SW 1.19E-09 3.84E-10 4.96E 10 2.80E 10 1.70E-10 5.24E 11 1.65E-11 3.62E-12 1.49E 12 8.12E 13 WSW 1.77E49 8.31 E-10 6.49E-10 3.50E 10 199E 10 6.73E 11 1.89E 11 4.58E-12 1.63E-12 9.90E 13 W 2.41E 09 1.29E 09 6 81E 10 3.65E-10 2 96E-10 1.1 3 -10 3.11E-11 6.90E-12 2.26E 12 1.25E-12 WNW 3.20E 09 1.39E-09 7.73E-10 5.91E-10 3.66E-10 1.19E-10 3.43E-11 8.36E 12 2.39E-12 1.29E 12 NW 3.25E49 1.23E49 7.39E 10 4.22E 10 2.77E 10 1.14E-10 7.2SE 11 7.61E 12 2.92E 12 1.36E-12 NNW 1.98E-09 9.88E 10 5.71E-10 3.05E 10 2.23E-10 8.21E-11 1 2.41E 11 4.93E-12 1.72E 12 9.03E 13 DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS 121.0 mm
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| ~' - -
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| ~ *
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| * Number jggp TMI Radl0 logical Controls Departmental Procedure 6610-PLN-4200 01 Tme Revision No.
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| Offsite Dose Calculation Manual (ODCM) 12 TABLE 4.5 Atmospheric Dispersion Factors for 'three Mlle Island o GAOUND RELEASE DISTANCE o SECTOR AVERAGE X/Q ON SEC/M3) (IN METERS) SEASON ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.16E 05 1.13E46 5.94E47 3.80E 07 2.38E 07 0.74E48 3.45E 08 9.28E-09 3.52E 09 2.05E49 NNE 1.08E 05 1.10E 06 5.66E 07 3.41E47 2.38E 07 9.55E46 3.11E48 8.94E 09 3.74E49 1.84E 09 NE 7.02E-06 9.81EW 5.42E47 3.17E47 2.10E-07 9 01E48 3.10E-08 8.87E-09 3.54E-09 1.91E-09 ENE 7.14E46 9 64E 07 4.92E47 2 85E 07 1.97E-07 7.82E 06 2.64E-08 .,8.38E49 3.04E-09 1.66E49 E 8.49E-08 1.00E-06 5.48E47 2.91E-07 1.87E-07 8.40E48 2.82E48 9.85E-09 4.75E 00 2.87E 09 ESE 6.91E46 9.02E 07 4.49E47 2.57E47 1.67E 07 7.20E48 2.77E46 412E48 5.54E-09 3.68E 09 SE 6.70E 06 9.00E-07 4.53E47 2.81E& 2.03E47 8.94E-08 3.33E48" 1.28E 08 6.19E 09 4.18E 09 SSE 7.26E-06 9 25E47 4.91E 07 2.87E 07 2.08E 07 9.18E-08 3.72E-08.,. 1.32E-08 5.62E 09 326E49 S 8.70E46 9.08E 07 3.90E47 2.41E-07 1.61E47 7.3115481 "2EE48 9.23E 09 3.74E 09 1.95E-09 SSW 6.05E 06 7.01E 07 2.75E-07 1.86E-07 1.24E47 5.06E 08, '1.82E-08 5.71E49 2.87E 09 1.58E 09 SW 5.94E46 5.71E 07 286E 07 1.81E47 1.22E-07 4.50E 08 :P1.72E 08 5.12E-09 2.53E49 1.59E 09 WSW 8.00E46 7.02E47 3.60E47 2.15E47 1.34E47 5.50E 08 1.87E.08 6.12E49 2.62E 09 1.83E-09 W 1.02E45 1.07E-06 5.30E-07 3.02E 07 2.05E-07* 19.31E-08 3.15E48 9.48E-09 3.74E49 2.38E 09 WNW 1.1EE 05 1.13E 06 5 98E47 3.67E 07 4 2.53E 07 1.00E47 3.56E48 1.18E-08 4.07E49 2.54E 09 NW 1.13E45 1.08E46 5.70E47 3.53ER *2.40E 07* 1.02E47 3.82E 08 1.11E 08 514E-00 2.h'E49 NNW 1.08E45 1.04E 06 5.72E47 3.27E 07 12.22E 07 9 06E48 3.20E-08 8.89E-09 3.75E-09 2.29E49 cGROUND RELEASE o SECTOR AVERAGE D/O (AN M-2)
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| /.[% \wg (IN STANCEMETERS) SEASON ANNUAL SECTOR 610 2413 402P 1 Seal 7240 12067 24135 40225 56315 72405 N 2.30E-08 1.88E49 ; 8:93Gio ! 4.82E-10 2.70E 10 8.96E-11 2.53E 11 4.96E 12 1.57E 12 7.84E-13 NNE 2.66E 06 225E 09a 't06E4ef 5 42E-10 3.38E-10 1.10E-10 2.89E-11 6.06E 12 2.10E-12 8.89E 13 NE 1.75E48 2.00E 00s 11.01E-09 5.04E-10 2.98 E-10 1.04E-10 2.88E 11 6.01E-12 1.99E 12 9.23E 13 ENE 1.88E48 1.85E49 845E-10 4.28E 10 2.65E-10 8.57E-11 2.33E-11 5.41E 12 1.63E-12 7.64E-13 E 2.88E46 2.90E 00 1.39E49 6.34E-10 3.67E-10 1.35E-10 3.68E 11 9.42E-12 3.77E-12 1.97E-12 ESE 3 59E 08 3.80E 09 1.77E 09 8.79E-10 5.15E 10 1.83E-10 5.78E-11 1.71E 11 7.06E-12 4.06E-12 SE 4.12E 08 4.55E-09 2.13F 09 1.15E 09 7.50E-10 2.72E 10 8.31E 11 2.34E-11 9.42E 12 5.50E 12 SSE 3.12E 06 3.23C-09 1.59E 09 8.00E 10 5.20E-10 1.88E 10 6.18E-11 1.61E 11 5.66E 12 2.83E 12 S 2.65E48 2.21E49 9.07E-10 4.75E-10 2.86E-10 1.07E-10 3.06E 11 8.10E 12 2.73E 12 1.23E-12 SSW 1.45E 08 1.30E 09 4.80E-10 2.82E-10 1.70E 10 5.71E 11 1.89E-11 3.91E-12 1.64E 12 7.84E-13 SW 1.42E48 1.10E 09 5.15E 10 2.82E-10 1.71E-10 6.24E-11 1.65E 11 3.62E 12 1.49E 12 8.12E 13 WSW 2.01E 08 1.41E49 6.82E 10 3.54E-10 2.00E 10 6.76E-11 1.89E-11 4.58E 12 1.63E-12 9.90E 13 W 2 55E 08 2.16E-00 1.00E 09 4.91E-10 3.01 E-10 1.12E 10 311E 11 6.90E 12 2.27E 12 1.25E-12 WNW 2.88E 08 2.30E49 1.13E49 5.93E-10 3.67E 10 1.19E 10 3.43E-11 8.36E-12 2.39E 12 129E 12 NW 2.78E-06 2.15E49 1.00E-09 5.58E 10 3 41E 10 1.19E-10 3.57E 11 7.61E 12 2 92E 12 1.36E 12 NNW 2.17E 08 1.75E-09 8.75E 10 424E 10 2.57E-10 8.55E 11 2.42E-11 4.93E 12 1.72E 12 9 03E-13 DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS I 122.0 mm
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| | |
| Number TMI Radiological Controls N MI Departmental Procedure 6610-PLN-4200.01 Rowston No.
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| Tsue 12 Offsite Dose Calculation Manual (ODCM)
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| TABLE 4.6 Dose Parameters for Radiolodines and Radioactive Particulate in Gaseous Effluents
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| * CRITICAL ORGAN CRITICAL ORGAN ORGAN FACTOR Pl* *
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| * NUCUDE ORGAN FACTOR Pl***
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| NUCUDE 1.12E + 03 RU-103 LUNG 1.79E-04 6.62E + 05 H-3 *
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| * TOTAL BODY 3.04E-07 3.59E + 04 RU-105 GI-LU 2.69E-05 9.95E + 04 C-14 BONE 9.70E-06 1.61E + 04 RU-106 LUNG 3.87E-03 1.43E + 07 NA-24 TOTAL BODY 4.35E-06 7.04E-04 2.60E 4 06 AG 110M LUNG 1.48E43 5.48E+06 P-32 BONE 1.29E-04 4.77E + 05 CR-51 LUNG 4.59E-06 1.70E + 04 TE-125M LUNG /#"h 2.32E + 06 MN-54 LUNG 4.26E44 1.58E + 06 SB-125 LUNG $.27E-04 MN-SS GI-LU 3.33E-05 1.23E + 05 TE 127M LUNG * $$t!
| |
| 100E-04 1.48E 4 06 5.62E + 04 LUNG 3.00E-05 1.11E+ 05 TE-127 Gl4.1.1 g 1.52E 05 FE-55 1.27E + 06 TE-129M LUNGT 4.76E-04 1.76E + 06 FE-59 LUNG 3.43E-04 CO-58 LUNG 2.99E44 1.11E + 06 TE-129 GI-tu k 6.89E-06 2.55E + 04 7.07E + 06 TE 131M #km'GDLU+ 8.32E-05 3.08E + 05 CO-60 LUNG 1.91E-03 5.55E 07 2.05E + 03 NI43 BONE 2.22E-04 8.21E + 05 TE-131 TE-132
| |
| %*LUNG LUNG 1.02E-04 3.77E+ 05 N145 GI-LU 2.27E-05 8.40E + 04 3.67E + 04 th30 TYHROID 4.99E-04 1.85E + 06 CU-64 GI-LU 9.92E-06 2.69E-04 9.95E + 05 ,13 31 THYROlD 4.39E43 1.62E + 07 ZN45 LUNG 1.94E + 05 GI-LU 2.75E-06 1.02E +04 4 32 THYROlD 5.23E-05 ZN-69 4.74EIOS l 13$ THYROID 1.04E-03 3.85E + 06 BR43 TOTAL BODY 1.28E-07 THYROID 1.37E45 5.07E + 04 BR44 TOTAL BODY 1.48E-07 5.48Ep 02' l-134 l-135 THYROID 2.14E-04 7.92E + 05 BR-85 TOTAL BODY 6.84E49 s233EIDI CS-134 UVER 2.74E-04 1.01 E + 06 RB-86 UVER 5.36E-05 1.98E) 05 LIVER 1.52E-07
| |
| %62E+ 02 CS-136 UVER 4.62E45 1.71E + 05 RB-88 3ASE + 02 CS-137 BONE 2.45E-04 9.07E + 05 RB49 UVER 9.33E45L 8.40E+ 02 5.89E-04 4 . 2.16E + 06 CS-138 UVER 2.27E-07 SF % LUNG 5.77E 4 04 2.73E 02 " 1.01E + 08 BA-139 GI4.LI 1.56E-05 SR-90 BONE 1.74E + 05 BA-140 LUNG 4.71 E-04 1.74E + 06 SR-91 GI-LU L 4.70E-06 BA-141 LUNG 7.89E-07 2.92E 4 03 SR-92 Gl-LLI %. *6.55E-05 2.42E + 05 2.68E4 05 BA-142 LONG 4.44E-07 1.64E + 03 ;
| |
| Y-90 GI-LU 47224E45 2.26E + 05 Y-91M LUNG 4Y "7.60E-07 2.81E 4 03 LA-140 GI-LLI 6.10E-05 l 7.59E + 04 Y 91 LUNG % 7.10E-04 2.63E + 06 LA-142 GI-LU 2.05E 05 1.47E-04 5.44E + 05 l
| |
| i Y-92 Gl-LU 6.46E-05 2.39E+ 05 CE-141 LUNG 3.89E + 05 CE 143 GI-LLI 3.44E-05 1.27E + 05 Y-93 GI-LU 1.05E-04 CE 144 LUNG 3.23E-03 1.20E + 07 ZR-95 LUNG 6.03E44 2.23E + 06 3.51 E + 05 PR-143 LUNG 1.17E-04 4.33E + 05 ZR-97 GI-LU 9.49E-05 6.14E + 05 PR-144 LUNG 4.23E-07 1.57E + 03 NB-95 LUNG 1.66E-04 1.35E 4 05 ND-147 LUNG 8.87E-05 3.28E + 05 MO-99 LUNG 3.66E-05 4.81 E + 03 W-187 GI-LU 2.46E-05 9.10E + 04 l TC-99M GI-LLI 1.30E-06 5.85E + 02 NP-239 GI-LU 1.73E-05 6.40E + 04 l TC-101 LUNG 1.58E-07 l
| |
| ' The listed dose parame:ers are for rad onuclides, other than noble Oases that may be detected in gaseous effluents. Pi factors include all nonatmospheric pathway transport parameters. the receptor's usage of pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG4133.
| |
| ** Tritium cose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin.
| |
| *** mrem / year per pCl/m'.
| |
| 123.0 me
| |
| | |
| c Number TMl Radiological Controls I, Departmental Procedure 6610-PLN-4200.01 rise ammen m ,
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| 1 ONsite Dose Calculation Manual (ODCM) 12 FIGURE 4.1 TMl-1 Gaseous Effluent Pathways .
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| $b, ,hi.
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| s
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| DUespg 124.0 ma
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| Dee Nuclear " " * =' *
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| * Departmental Procedure Wmber 6610-PLN-4200.01 Monsson No, Offsite Dose Calculation Manual (ODCM) 12 FIGURE 4.2 TMI-1 Auxillery and Fuel HendNng Buudings Ef8uent Pathways 4
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| 'Mgp TMl Radiological Controls Departmermal Procedure
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| ** 6610-PLN-4200.01 weien No.
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| Offsite Dose Calculation Manual (ODCM) 12 FIGURE 4.3 TMI 1 Reactor Building Efnuent Pathway jiii'E*ilijg, l
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| -ggy TMl Radiological Controls Departmortal Procedurs 6610-PLN-4200.01 Thie Rr 'mion No.
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| Offsite Dose Calculation Manual (ODCM) 12 FIGURE 4.4 1MI-1 Condeneer OMges Emuent Pathway p !aii,3 i
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| CONDENSER lii %
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| 3 CONDENSEttpFF GAS 115 as EXHAUST *g..%4 FEET RADIATION,hDNITORS ANDijpATLING STATIONS w *
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| gggp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 me %. ion no. l Offsite Dose Calculation Manual (ODCM) 12 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents Instantaneous Release Limits 5.1.1 Noble Gases ,
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| 1 For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary:
| |
| 5.1.1.1 Total Body Dose Rate. = I(K) x (Dv) x (Q) llI,siskliin,.]j (eg 5.1.1.1)
| |
| I .# kis J where: (I e g %!P"'
| |
| w %iit Dose Rate,, = instantaneous total body dose rrate lim.it,"at the site boundary, in mrem /yr. j
| |
| ' i!;; %Wim K, - total body dose factor due to ga{mma emissions for each ident gas radionuclide, in mrem /yr per pCl/m8 from Table 4.3.
| |
| DV -
| |
| I l I
| |
| highest sector anoudaverage gaseous dispersion factor (X/0) at or beyond the unrestricted, area boundary, in sec/m', from Table 4.4 for station vent' releases; and Table 4.5 for all other releases (Condenser Off Gas, ESE PHBlisfircund releases). Maximum values presently in use are pi7E%sec/m' at sector NNE for station vent, and 1.16E-5 spc/m' for all otherteleases, at sectors N and WNW.
| |
| 0, = #g "IIbiun/
| |
| Release rate of radionuclide, I, in pCl/sec as determined by sampling and ai;F* an5!ysis. Calculated using the concentration of noble gas radionuclide,l.
| |
| ii i
| |
| % [gi+# n pCi/cc, times the release pathway flow rate, in ec/second.
| |
| iy, N!! ( 4:iff; .
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| 'mn. naa.
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| 4g %;[ l w
| |
| 129.0 me
| |
| | |
| ( Number jggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 f
| |
| Tit
| |
| * w on m.
| |
| Offsite Dose Calculation Manual (ODCM) 12 l 5.1.1.2 Skin '
| |
| Dose Rate = I(( + 1.1 M) X (Dv) X (Q) (eq 5.1.1.2) l .
| |
| l I
| |
| where:
| |
| Dose Rate. - Instantaneous mrem / year skin dose rate limit, at the site boundary, in mrem /yr.
| |
| (- skin dose factor due to bota emissions for eactildentified noble gas radionuclide, in mrem /yr per pCl/m' from Table 4.3, M, - air dose factor due to gamma / emissionsfor eac$l identified nobl
| |
| 'Hl6,,
| |
| radionuclide, in mrad /yr per pCl/rrfJrorrtTable 4.3.
| |
| e,y,f4,e 'E 1.1 = mrem skin dose per mrad alt dosa. " Converts air dose to skin dose.
| |
| i'( "9 4, O= release rate of radionuclide, l, inMI/sec, as determined by sampling and analysis. Calculated tising the concentration of noble gas radionuclide,1, in pCl/cc, times thyepse pathway flow rate, in ec/second. j jng '93 Dv = highest sector'angual average gaseous dispersion factor (X/0) at or beyond the utirostricted area boundary, in sec/m', from Table 4.4 for stationyentWleases; and Table 4.5 for all other releases (Condenser Off Gas ESF FHB and ground releaseu). Maximum values presently in use ar(7.17Eit4c;/m' at sector NNE for ststion vent, and 1.16E-5 sec/m' foll all'bther releases, at sectors N and WNW.
| |
| p!4 '%
| |
| , ihl!
| |
| a if,4.,, ll:4
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| 130.0 mm l
| |
| l
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| _ --y , . . . ,4g.,, m. e *" ** *** **** N l
| |
| | |
| Number ggy TMt Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No.
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| Offsite Dose Calculation Manual (ODCM) 12 l
| |
| 5.1.2 lodine-131. lodine-133. Trtium and Radionuc!! des in Particulate Form. wkh Half-Lives Greater than 8 Davs 1 1
| |
| For 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies:
| |
| Dose Rate, = E (P,) (Ov) (Q,) (eq 5.1.2)
| |
| I j l
| |
| where:
| |
| .pl%
| |
| Dose Rate, = mrem / year organ dose rate.
| |
| j#
| |
| ffi!Lu,m]j P- dose parameter for 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8'daysyfor the inhalation pathway, in n
| |
| mrem /yr per pCl/m', from Table g The dose factors are based on the critical individual organ and most restrictive age group (child).
| |
| *%, Tlg Dv = highest sector annual average gaseous dispersion factor (X/O or D/0) at or beyond the unrestricted area boundary, in sec/m', from Table 4.4 for the station vent releasss and Table 4.5 for all other releases. X/O is used for the inhalation pattEJay, Maximum values of X/O presently used are 7.17E-7 sec/ rep fo[ station vent, at sector NNE, and 1.16E-S sec/m' for all other releases; et sectors N and WNW.
| |
| ;?""u%lq, Q, - release rate of each radionuclide, i, in pCl/sec. Calculated using the concentratiori"of each radionuclide, I, in pCi/ce, times the release pathway sflokrate, in oc/second.
| |
| . pie "'"uig,
| |
| . 4 er# $
| |
| (9N!;g
| |
| * ital!*$
| |
| '4!gjdi
| |
| 'iq.)
| |
| 131.0 mm
| |
| | |
| E ;
| |
| 1I Number gggy TMI Radiological Contrds Departmental Procedure 6610-PLN-4200.01 M'
| |
| Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 5.2 _ Gaseous Effluents - 10 CFR 50 Appendix l 5.2.1 Noble Gases The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions:
| |
| Dose r = (3.17E-8) x E (K) x (Dv) x (Qi) (eg 5.2.1)
| |
| I and
| |
| #"annity Dose p = (3.17E-8) x I(N,) x (Dv) x (Oi) N (eg 5.2.2)
| |
| I k i j[ nine[
| |
| 4 where: g 'pi:lsi!
| |
| Dose r -
| |
| een% h4 mrad gamma air dose due to gammd" emissions from noble gas radionuclides. '"4 '*Ini, 9g, ~
| |
| Dose p - mrad beta air dose due to beta emissions from noble Das radionuclides. l
| |
| *nund M, - air dose facto (due to gamma emissions for each identified noble gas radionuclidyIn mrad -a
| |
| /.yr per pCl/m', from Table 4.3.
| |
| vi.s
| |
| ..s.. s.
| |
| N, = Jir dor,e factor due to beta emissions for each identified noble gas !
| |
| radionuclide, in mrad /yr per pCl/m', from Table 4.3. l df Ni,i,n/ ;
| |
| Dv - + highest sector annual average gaseous dispersion factor, X/O, at or I ilgie beyondfrom jpinterpolated the unrestricted Table area 4.4 for releases fromboundary, the station ventinand sec/m'. Values may be Table 4.5 di! fofall other releases. Maximum values of X/Q presently used are 7.17E-7 1,g%g[""sec/m'
| |
| % for station vent at sector NNE, and 1.16E-5 sec/m' for all other 4Adpiin"g4 9 releases at sectors N or WNW.
| |
| m hi,0, = release of noble gas radionucilde, I, in pCl, over the specified time period,
| |
| ( Cl/second
| |
| * seconds).
| |
| 3.17E-8 = inverse of the number of seconds in a year.
| |
| NOTE If the methodology in this section is used in determining dose to an indMdual, rather than air dose due to noble gases, substitute KI, from Table 4.3, for Mi, and (Li + 1.1 Ml) for N1.
| |
| l l
| |
| 132.0 nm 1
| |
| | |
| i l
| |
| Number i 1
| |
| I Radiological Contrds
| |
| -GUClear Departmental Procedure 6610-PLN-4200.01 j Tstle Revision No.
| |
| Offstte Dose Calculation Manual (ODCM) 17 5 2.2 lodine-131. lodine-133. Tritium and Radionuclides in Particulate Form with Half-Uves Greater than 8 Days l The dose to an individual from I-131,1133, Tritium and Radionuclides in Particulate Form l with half-lives greater than 8 days in gaseous effluents released from the site to an l unrestricted area is determined by solving the following expression: l Dose, = Z(3.17E-8) x I (R,) (Dv) (Q,) (eq 5.2.2) i 1 where: ,.p:g, l f %
| |
| Dose, - dose to all real pathways, p, to organ.,o, of.an individual in age group, a.
| |
| from I-131,1-133, Tritium and Radions.lides Iri Particulate Form, with half- l lives greater than 8 days, in mremeddrind any desired time period.
| |
| R, = the dose factor for each identb lide, I, pathway, p, age group, a, 2
| |
| and organ, o, in mrem /yr per pCf/q1' for the Inhalation pathway and m -
| |
| mrem /yr per pCl/segfor other" pathways, from Tables 5.2 to 5.7. i Y l NOTE 4 jirig 1!g, Since there is minimal or no elemental iodine released from the condenser off-gas air ejectoQsei NUREG4017) att todine R, values for all pathways, except thdnhalatinpathway, are considered to be zero when performing dose balculations for releases from the condenser off-gas air ejectorf Only" calculate the dose due to the inhalation pathway for condenser.offgs air ejector lodines.
| |
| r m,,
| |
| t '""""*d NOTE
| |
| #f
| |
| %g %gg Tritiumt H-3't dose factor is mrem / year per pCl/m' for all pathways.
| |
| 4;
| |
| % Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m', for the inhalation pathway, and D/O, in m', for other pathways. Table 4.4 is used to derive the values for station vent releases and Table 4.5 is used to derive the values for all other releases. The values used to calculate site boundary and critical receptor doses are as follows:
| |
| Statlon Vent Releases Boundary inhalation X/O 7.17 E-7 1.22 E4 Ground D/O 1.22 E-8 Meat D/O Vegetation D/O 1.22 E-8 Cow / Milk / infant D/O 1.22 E 8 Station Vent Releases - Critical Receptor Inhalation X/Q 7.2 E-7 4 6 E-9 Ground D/O 7.8 E-9 Meat D/O 3.1 E-9 Vegetation D/O 8.9 E-9 Cow / Milk / infant D/O 22m 133.0 l
| |
| l
| |
| | |
| Number Nuclear ' "^d'd*a' co**
| |
| Departmental Procedure 6610-PLN-4200.01 M'
| |
| Asvisen No.
| |
| Offsite Dose Calculation Manual (ODCM) 17 Ground or Other Rieases - Boundary inhalation X/O 1.16 E-5 Meat D/Q 4.12 E-8 Ground D/O 4.12 E 8 Cow /Mllk/ infant D/O 4.12 E-8 Vegetation D/O 4.12 E-8 Ground or Other Rleases - Critical Receptor Inhalation X/O 1.2 E-5 Meat D/O 9.2 E-9 Ground D/O 3.0 E-8
| |
| * Cow /Mllk/ infant D/O 6.3 E-9 Vegetation D/O 2.6 E-8 Dv(H 3) - In the case of H-3 only the X/Q's above are used for all pathways.
| |
| Q, - f4lis_
| |
| release of I-131,1133. Tritium and Radionuclides,' in Particulate Form with half-lives greater than 8 days, in pCl, cumuditive ov(er the specifie period (pCl/second
| |
| * seconds). 4![ , f ""*"""
| |
| 3.17E $k '!!k inverse of the number of seconds i.n a year.
| |
| , $p%iiir 911;g "4;, '
| |
| M;g l
| |
| hi
| |
| %uQ'% ,
| |
| jMni ii siiw l
| |
| % p!%arai,-
| |
| ii pdHNI4ty,
| |
| ., ,g
| |
| ,it , w
| |
| , t
| |
| /(5!;g kigep'"
| |
| pg '!::g, p
| |
| l l!and#.ji; "lih .t!! '
| |
| i dI'Hi!I i
| |
| 99,. 9ih 1!q; gif'llg" "lig i
| |
| l 134.0 mm l
| |
| l l
| |
| | |
| i gggy TMI Radiological Controls Departmental Procedure Number Title 6610-PLN-4200.01 Revteson No.
| |
| Of 'stte Dose Calculation Manual (ODCM) 12 5.3 Gaseous Radioactive Svstem Dose Calculations Once oer Month ODCM Part I Control 2.2.2.4 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shtll be used to reduce the radioactive l
| |
| materials in gaseous waste prior to their discharge. When the monthly projected doses due to the gaseous effluent releases from the site would exceed:
| |
| 0.2 mrad to air from gamma radiation; or 1
| |
| 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ.
| |
| fm%g l The following calculational method is provided for performing this dose projection.
| |
| j
| |
| .,/* *1!
| |
| i At least once per month the gamma air dose, beta air dose and the' maximum organ dose for the quarter to date will be divided by the number of days into the.. quarter and multiplied by 31. Also, this dose pojection shall include the estimated dose due to any ahticipated unusual release during the period nr which the projection is made. If these projected'ddses exceed any of the values listed i
| |
| above, apprcpriate portions of the TMI-1 Gaseous Waste, Treatment System, as defined in l
| |
| Section 6.0, or itppropriate portions of the TMi-2 GaseouiEfiluent Filtration System as shown on Figure 4.5, shall t,s used to reduce radioactivitilevels prior to release.
| |
| . . . l!!:
| |
| At the discretion of RadiolNkal Engineering,'likperiods other than the current quarter-to-date may er day in the current quarter-todato is not believed to be l
| |
| be used oftotheproject representative dose per daypr doses if the dNe p$ ped for the next tri-Ah.
| |
| g""wigmg, 4
| |
| "I
| |
| [g'4!g. kique/'
| |
| .s e 9e k .jg;tN
| |
| % e r
| |
| j dl [!!!$
| |
| kn, 'i;h l
| |
| A gj;iifi!q.3 # '
| |
| 9j;..
| |
| ']j:
| |
| l l
| |
| 135.0 me L
| |
| | |
| gggy TM1 Radiological Controls Departmental Procedure Numt:Dr Tme 6610-PLN-4200.01 Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 5.4 Altemative Dose Cafculational Methodolooles for Gaseous Effluents As an altemacive to the methods described above, the models in/or based upon, those presented in Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default parameter where values from Regulatory Guide 1.109 (Rev.1) and/or actual site specific data can be used applicable.
| |
| The onsite, on-line computerized system for tracking gaseous effluent dose uses annual avera gaseous dispersion factors. As an altemative dose calculational methodology. GPU Nuclear calculates doses using an advanced class "A" dispersion model called SEEDS (simplified '
| |
| environmental effluent dosimetry system).
| |
| f"'"'"'*t;g
| |
| ., ik In This rnodel incorporates the guidelines and methodology set foph in'USN.8C Regulatory Guide 1.109, and uses actual hourfy meteorologicalinformation matched to thd time of releases to more accurately assess the dispersion of effluents in the atmosphere." Combining this assessment of dispersion with TMINS effluent data for each unit, postulated Maxlrdum hypothetical doses to the public are calculated.
| |
| g %.[''""*
| |
| '%g #4 Tim
| |
| , h l w 4illiiii:[;j:
| |
| jag b g l
| |
| ,, g;!
| |
| l pl%gi['h, '"Lik g vg @
| |
| l f
| |
| # '''i(
| |
| inge!
| |
| l' 'g 9;;!!'
| |
| h) l i
| |
| f ,
| |
| l l
| |
| 136.0 mm
| |
| . i
| |
| | |
| l l
| |
| -- gggy TMI Radiological Controls Departmental Procedure Number Tme 6610-PLN-4200.01
| |
| > Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.2.1 Pathway Dose Factors, RI AGE GROUP: INFANT PATHWAY: INHALATION NUCL1DE ----------_---- ORGAN - - - - - -DOSE
| |
| . . - - - . FACTORS;
| |
| . . - . . . . _ . . _mrem
| |
| . . . . . ./.. .year
| |
| _ _ . .per
| |
| . pCI/m'....._.......___
| |
| BONE
| |
| ................ ....== - UVER = _ _
| |
| T. BODY THYROID KI
| |
| .. . ... . . . . .. .... . _. ... .D N. EY .. .....____
| |
| LUNG GI
| |
| _ ___..-LLI H-3 ...
| |
| C-14 0.00E + 00 6.47E + 02 6.47E + 02 6.47E + 02 6.47E + 02 6.47E + 02 6.47E + 02 CR-51 2.65E + 04 5.31E + 03 5.31E + 03 5.31 E + 03 5.31E + 03 i!WE + 03 5.31 E + 03 0.00E + 00 0.00E + 00 8.95E + 0
| |
| ._.... ... ..__....._... ....1 5.75E + 01 1.32E +011g 1.28E)04 3.57E + 02 MN-54 0.00E + 00 2.53E + 04 4.98E + 03 0.00E + 00 4.08E403, t00E + 06 7.06E+ 03 FE-55 FE-59 1.97E + 04 1.17E + 04 3.33E + 03 0.00E + 00 0.00E(00' 8.69E + 04 1.09E + 03 '
| |
| ~ ~ 1.36E
| |
| ~ ~~~ + 04 2.35E + 04 9.48E + 03 0.00E + 00
| |
| ~~
| |
| 0.00E.+ 00, 1.02E + 06 2.48E + 04 Cd-58 0d'~E+00 O 1.22E + 03 1.82E +0.00E+00.. 03 "Q.00EV00 7.77E+ 05 1.11E+ 0i CO-60 NI63 0.00E + 00 8.02E + 03 1.18E + 04 0.00E + 00%D.00E+ 00 4.51 E + 06 3.19E + 04
| |
| ._.3.39E
| |
| .. . ._+_. 05. .. 2.04E 4 04 1.16E + 04
| |
| . .... . . . . . . _ _ ._ _ 0.00E + 00 b.00E + 00
| |
| .,....__........____.. ..-2.09E + 05 2.42E + 03 ZN-65 _=__......
| |
| RB-86 1.93E +04 6.26E + 04 3.11E + 04 0.00E + 00 3.25E + 04 6.47E + 05 5.14E + 04 SR 0.00E + 00 1.90E + 05 8.82E + 04
| |
| * 0.00E + 00 0.00E + 00 0.00E + 00 3.04E + 03
| |
| . __-89 3.98E + 05 0.00E + 00 1.14E +
| |
| ____..__........- - - - _ _._ .... 04_0.00E .. _.. +...
| |
| 0.00E 4 00 00 .....___. 2.03E + 06 6.40E + 04 SR-90 Y-91 4.09E + 07 0.00E + 00 2.59E106*D.00E + 00 0.00E + 00 1.12E + 07 1.31 E + 05 ZR45 5.88E + 05 0 00E + 00 157E/04. 0.00E + 00 0.00E + 00 2.45E + 06 7.03E + 04
| |
| . .-- 1.15E + 05=__...... ==..._ 2.03E40#
| |
| 2.79E( + 040.00E + 00 3.11 E + 04 1.75E + 06 2.17E + 04 NB-95 1.57E + 04 6.43E +,03 -___
| |
| 3.78E#03 0.00E + 00 4.72E + 03 4.798E + 05 1.27E+ 04 RU-103 RU-106 2.02E + 03 0.00EI00 4 6.79E + 02 0.00E + 00 4.24E + 03 5.52E + 05 1.61E + 04
| |
| -.._ __ _.. . ..8.68E
| |
| . .. .. .+...
| |
| 04...
| |
| 0.00E + 00 09E + 04 0.00E + 00 1.07E + 05 1.16E + 07 1.64E + 05
| |
| ,.. .._N_ .___.=-
| |
| AG-110M .=_... _________.___.__ __.... ..........
| |
| TE-125M 9.98E + 03 722ET03 5.00E + 03 0.00E + 00 1.09E + 04 3.67E + 06 3.30E + 04 TE 127M 4.76E+03%1.99E 1.67E + 04 f 03 6.58E + 02 1.62E + 03 0.00E + 00 4.47E + 05 1.29E + 04
| |
| ..._h.690E + 03 2.07E + 03 4.87E + 03 3.7 1.31E + 06 2.73E + 04 TE-129M
| |
| __.. ........._.. ......_...5E+04 _ _ . . . . - --- =---..___
| |
| l131 1.41Et04 "B.09E + 03 2.23E + 03 5.47E + 03 3.18E + 04 1.60E + 06 6.90E + 04 l-133 3.79E 404 4.44E4 04 1.96E + 04 1.48E + 07 5.18E + 04 0.00E + 00 1.06E + 03 1.32E + 0[ 1.92E + 04 5.60E + 03 3.56 CS-134
| |
| _.............._........_.._.._..E+06 ....
| |
| 2.24E + 04 0.00E + 00 2.16E + 03 CS-136 3.96E + 05 7.03E + 05 7.45E + 04 0.00E + 00 1.90E 4 05 7.97E+ 04 1.33E + 03 CS 137 4.83E + 04 1.35E + 05 5.29E + 04 0.00E + 00 5.64E + 04 1.18E + 04 1.43E + 03
| |
| .......................___...__04 BA-140 5.49E + 05 6.12E + 05 4.55E + 0.00E+00 1.72E+05
| |
| . ......... .....=-__ 7.13.E+ 04 1.03E + 03 5.60E + 04 5.60E + 01 2.90E + 03 0.00E + 00 1.34E + 01 1.60E + 06 3.84E + 04 CE-141 CE-144 2.77E + 04 1.67E + 04 1.99E4 03 0.00E 4 00 5.25E + 03 5.17E 4 05 2.16E + 04 3.19E + 06 1.21E + 06 1.76E + 05 0.00E + 00 5.38E + 05 9.84E + 06 1.48E + 05
| |
| - - = _ _
| |
| PR-143
| |
| =...... ........__ .....__. ..........
| |
| ! 1.40E + 04 5.24E + 03 6.99E 4 02 0.00E + 00 1.97E + 03 4.33E + 05 3.72E + 04 ND-147
| |
| ................_..........-.....E+00 7.94E + 03 8.13E + 03 5.00E + O2 0.00 3.15E + 03 3.22E + 05 3.12E + 04 137.0 nm l .
| |
| I f
| |
| L
| |
| | |
| ( Number l '
| |
| (MOlear m Rami eai 9 Connois Departmental Procedure 6610-PLN-4200.01 Title Revisson No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 6.2.2 Pathway Dose Factors, RI AGE GHOUP: CHILD PATHWAY: INHALATION ORGAN DOSE FACTORS: mrem / year per pCl/m' NUCUDE -----------------------..---------..---- - - - - - - - - - - - - - - - - - - - - - - - - - - - -
| |
| BONE UVER T. BODY THYROID KIDNEY LUNG GI
| |
| _ ..__-LU ___
| |
| H-3 0.00E + 00 1.12E + 03 1.12E + 03 1.12E + 03 1.12E+03 A12E,+03 1.12E + 03 C-14 3.59E + 04 6.73E + 03 6.73E + 03 6.73E + 03 6.73E+03 (6.73E)03 6.73E + 03 CR 51 0.00E 4 00 0.00E + 00 1.54E + 02 8.55E + 01
| |
| ........_..__......____..____ ...._____ ..____- 2.43Et_.01 9M.. ..._
| |
| . , , . 0E.iO4 1.08E + 03 MN 54 0.00E + 00 4.29E + 04 9.51 E + 03 0.00E + 00 1.00E +04' 1.S8E + 06 2.29E + 04 FE-55 4.74E + 04 2.52E + 04 7.77E + 03 0.00E + 00 0.00E + 00.. 1.11E + 05 2.87E + 03 2.07E + 04 3.34E + 04 1.67E 4 04 0.00E+00 TD.00E FE..-59
| |
| . ....__ . . .. _ _ _ . _ _ ... . .. ._ _ _ _ . ...._ _ _ . __ _ _ _ . ._ _ _ _l D0" 1. 2 7 7.07E E + +06 04 CO-58 CO-60 0.00E + 00 1.77E + 03 3.16E + 03 0.00E + 00%'0.00E + 00 1.11E + 06 3.44E + 04 0.00E + 00 1.31E + 04 2.26E + 04 0.00E + 00 O.00E + 00 7.07E + 06 9 62E + 04 NI63 8.21 E + 05 4.63E + 04 2.80E + 04 0.00E + 00 0.00E + 00 2.75E + 05 6.33E + 03 ZN45 4.26E + 04 1.13E + 05 7.03E + 04 e n.00E + 00 7.14E + 04 9.95E + 05 1.63E + 04 RB-86 0.00E + 00 1.98E + 05 1.14E+054 0.00E+00 0.00E + 00 0.00E + 00 7.99E + 03 SR 5.99E + 05 0.00E + 00 1.72ET04d!
| |
| ..__-89 _ ,...._ _ _ _. .. . ._ _.__ _ _..__.. . . . L.O.. .00E + 00 0.00E
| |
| ... ..__....._ ___.___..+ 00.___......
| |
| 2.16E + 06 1.67E + 05 SR-90 1.01 E + 08 0.00E + 00 6.44Ef06 0.00E + 00 0.00E + 00 1.48E + 07 3.43E + 05 Y-91 9.14E + 05 0.00E+00 (2.44ETC(" 0.00E+00 0.00E + 00 2.63E + 06 1.84E + 05 ZR 1.90E + 05 4.18E + 04 9 0.00E + 00 5.96E + 04 2.23E + 06 6.11 E + 04
| |
| ..-95..... ......... .._..,,,.. 3.70.E/04 u. + - ....... ......... .........-..__......
| |
| NS-95 2.35E + 04 9.18E403s 6.55E + 03 0.00E + 00 8.62E + 03 6.14E + 05 3.70E + 04 RU-103 2.79E + 03 0.00E + 00 %1.07E + 03 0.00E + 00 7.03E + 03 6.62E + 05 4.48E + 04 RU 106 1.36E+ .05 (O
| |
| .... ....____. ..DE400 . . . 1.69E
| |
| . _ . . .4. 04
| |
| . . _0.00E
| |
| - - . . .+. 00
| |
| . . .1.84
| |
| . . . E_ .+ 05
| |
| . . _ .1.43E
| |
| - - _ _ _+_ 07. 4.29E
| |
| .......+ . 05 AG-110M 1.69E + 04 % .14E+04 9.14E + 03 0.00E + 00 2.12E + 04 5.48E+06 1.00E + 05 TE-125M 6.73E + 03 .33E+03 9.14E + O2 1.92E + 03 0.00E + 00 4.77E + 05 3.38E + 04 TE _. ...______. 2.49E + 0_(y'_4_55E3.02E + 034 03 6.07E + 03 6.36E + 04 1.48E + 06 7.14E + 04
| |
| ._-127M _ ._ ..__... ...... ...___...___. ....____. .........___........ l TE-129M 1.92E 404 6.85E + 03 3.04 E + 03 6.33E + 03 5.03E + 04 1.76E + 06 1.82E + 05 l-131 4.81E + 0i 4.81 E + 04 2.73E + 04 1.62E + 07 7.8BE + 04 0.00E + 00 2.84E + 03 l-133 1.66E + 04 2.03E + 04 7.70E + 03 3.85E + 06 3.38E + 04 0.00E + 00 5.48E + 03
| |
| ~ ~'~~ ~~ ~~
| |
| ~CS~l34 6 51E + 05 101545 hI25E+b5 U.~00El00 3.30E + 05 3.~21 E + 05 35IE303~~
| |
| CS-136 6.51 E + 04 1.71 E + 05 1.16E + 05 0.00E + 00 9.55E + 04 1.45E + 04 4.18E + 03 CS 137 9.07E + 05 8.2SE + 05 1.28E + 05 0.00E + 00 2.82E + 05 1.04E + 05 3.62E + 03 BA-140 -7.40E + 04 6.48E + 01 4.33E + 03 0.00E + 00 2.11E + 01 1.74E + 06 1.02E + 05 CE-141 3.92E + 04 1.95E + 04 2.90E + 03 0.00E + 00 8.55E + 03 5.44E + 05 5.66E + 04 CE-144 6.77E+ 06 2.12E + 06 3.61E+ 05 0. 00 E + 00 1.17E + 06 1.20E + 07 3
| |
| ...... .. . . _ __. .. _ _ . ... . .._ _ _ _. .. ._ _ . _ _ _ _ _ __ . . . . . . ._ _ ... _ _ _._ _89 E__..... +05 PR-143 1.85E + 04 3.55E + 03 9.14E + O2 0.00E + 00 3.00E + 03 4.33E + 05 9.73E + 04 l ND 147 1.08E 4 04 8.73E + 03 6.81 E + 02 0.00E + 00 4.01E + 03 3.2BE + 05 8.21E + 04
| |
| .__.....__ ...__....._____._... ........._...._____ ..... ..__.........-_....___ . l 138.0 m* i l
| |
| l b
| |
| | |
| Number WI Raddogical Conads GUClear Departmental Procedure 6610-PLN-4200.01 TrDe Hevision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.2.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: INHALATION ORGAN DOSE FACTORS; mrom/ year per pCl/m' NUCLIDE - - - - = = = - - - - - - = - - = - - - - - - - - . . - - - - - - - - - - - - - - - - - = - = = = - ---------
| |
| BONE LIVER T. BODY THYROtD KIDNEY LUNG GI
| |
| . .._ .............__..._____..._____.............___.___....._______......-LLI ...
| |
| H-3 0.00E + 00 1.27E + 03 1.27E + 03 1.27E + 03 1.27E + 03 1.27E + 03 1.27E + 03 C-14 2.60E + 04 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 4.87E g + 03 4.87E + 03 j CR-51 0.00E + 00 0.00E + 00 1.35E + O2 7.50E + 01 3.07E+01 f 2.10El04 3.00E 4 03 l
| |
| ~'~~ ~~ ~ ~~ ~
| |
| 55I3 5 b.~00E +bo~5.11E + O4~~~~"~~ 8 5E + b~3~b5E b'0~I.~27h4 . iMb~6~b5E+Y FE-55 3.34E + 04 2.38E + 04 5.54E + 03 0.00E + 00 0.00E400 ! 1.24E + 05 6.39E + 03 FE-59 1.59E 4 04 3.70E + 04 1.43E + 04 0.00E + 00 0.00Eq 00 1 1.53E + 06 1.78E + 05 _
| |
| CO-58 0.00E + 00 2.07E + 03 2.78E + 03 0,00E+00 1.34E + 06 9.52E + 04 CO-60 0.00E + 00 1.51 E + 04 1.98E + 04 0.00E 0.00E + 00 + 00,%p.00E8.72E + 00+ 06 2.59E + 05 NI63 5.80E + 05 4.34E + 04 1.98E + 04 0.00E + 00 0.
| |
| . . - _ - _ _ = = . . . _ _ . . . _ _ . .. _ _. .____.. _0_0 E + 00 3.07E + 05 1.42E 4 04 ZN45 3.86E + 04 1.34E + 05 6.24E + 04 0.00E + 00 8.64E + 04 1.24E + 06 4.66E + 04 RB-86 0.00E + 00 1.90E + 05 8.40E4 04 4 0.00E+00 0.00E + 00 0.00E + 00 1.77E + 04 SR-89 4.34E + 05 0.00E + 00 1.25E+04% 0.00E+ 00 0.00E + 00 2.42E + 06 3.71~'~~ E + 05 SR-90 1.08E + 08 0.00E + 00 6.68E i O6 Ro.00E + 00 0.00E + 00 165E307 7.65E+b5 Y-91 6.61E + 05 0.00E + 00 L77E t04, 0.00E + 00 0.00E + 00 2.94E + 08 4.09E + 05 l ZR 1.46E + 05 4.5BE 4 04 ji15EiO4* 0.00E+00 6.74E + 04 2.69E + 06 1.49E + 05
| |
| ..-95--- ..._____ ..... __ .. ____.._....._______..__.... ....___.____. _....__
| |
| NS-95 1.86E + 04 1.03E + 04 166E+03 0.00E 4 00 1.00E + 04 7.51 E + 05 9.68E + 04 RU 103 2.10E + 03 0.00E400s 8.96E+02 0.00E + 00 7.43E + 03 7.83E + 05 1.09E + 05 RU 106 9.84E + 04 0.00E + 00311.24E + 04 0.00E + 00 1.90E + 05 1.61E + 07 9.60E + 05 AG-110M 1.38E +04, i.31E"+ 04 7.99E + 03 0.00E + 00 2.50E + 04 6.75E+ 06 2.73E + 05 l TE.125M 4.88E + 03 92.24Ed3 6.67E + 02 1.40E + 03 0.00E + 00 5.36E+05 7.50E + 04 TE
| |
| _ 127M 1.80.E
| |
| ... ... +u 0h ...836..E
| |
| ....__..... + 03 2.18E + 03 4.38E
| |
| ...-...___... .........+ 03 6.54E + 04 1.66E + 06 1.59E + 05 TE-129M 1.39E404 '6.58E + 03 2.25E + 03 4.58E + 03 5.19E + 04 1.98E + 06 4.05E + 05 l131 3.54E A04, 4.91 E + 04 2.64E + 04 1.46E + 07 8.40E + 04 0.00E + 00 6.49E + 03 1133 1.22E + 04 2.05E + 04 6.22E + 03 2.92E + 06 3.59E + 04 0.00E+ 00 1.03E + 04 CS-134 5.02E + 05 1.13E + 06 5.49E + 05 0.00E + 00 3.75E + 05 1.46E + 05 9.76E + 03 CS-136 5.15E + 04 1.94E + 05 1.37E + 05 0.00E + 00 1.10E + 05 1.78E + 04 1.09E + 04 CS-137 6.70E + 05 8.48E + 05 3.11 E + 05 0.00E 4 00 3.04E + 05 1.21 E + 05 8.48E + 03 BA-140 5.47E + 04 6.70E + 01 3.52E + 03 0.00E + 00 2.28E + 01 2.03E + 06 2.29E + 05 CE-141 2.84E + 04 1.90E + 04 2.17E 4 03 0.00E + 00 8.88E + 03 6.14E + 05 1.26E + 05 CE
| |
| ....-144 4.89E + 06 2.02E 4 06 2.62E + 05 0.00E + 00 1.21 E + 06 1.34E + 07 8.64E + 05 PR-143 1.34E + 04 5.31 E + 03 6.62E + 02 0.00E + 00 3.09E + 03 4.83E + 05 2.14E + 05 ND-147
| |
| ..=__
| |
| 7.86E + 03 8.56E + 03 5.13E+O2 0.00E + 00 5.02E + 03 3.72E 4 05 1.82E + 05
| |
| .-_ - _==...
| |
| I I
| |
| l 139.0 mm
| |
| | |
| Numbw J n TMI Radiological Controls EUU598F o,p.,tmentai procedur. 6610-PLN 4200.01 Tate Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.2.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: INHALATION
| |
| .=
| |
| ........___.___....____..__..... .....___.____......_..____ _. . . _ _- __=
| |
| ORGAN DOSE FACTORC; mrem / year per pCl/m' NUCLIDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- ----- - - - - - - - - - - - - - - - - - - - - - - - - -
| |
| ~~
| |
| BONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LU
| |
| ~ ~ ~ ~
| |
| H-3 U.50E 00~~i.~26Eib3~~IE 3 Ub~~i.~26E b3~~i.~26E b3~~I.26E+b3 f.~2E+~bb~
| |
| C-14 1.82E + 04 3.41 E + 03 3.41E + 03 3.41 E + 03 3.41 E + 03 3.41E + 03 3.41 E + 03 CR-51 0.00E + 00 0.00E + 00 1.00E + 02 5.95E + 01 2.28E + 01 jf M4E + 04 3.32E + 03 MN-54 0.00E + 00 3.96E + 04 6.30E + 03 0.00E + 00 9.84E+03 h.40E406 7.74E + 04 FE-55 2.46E + 04 1.70E + 04 3.94E + 03 0.00E + 00 0.00E +60,, 7.21EIO4 6.03E + 03 FE 1.18E + 04 2.78E + 04 1.06E + 04 0.00E + 00 0.00E + 00
| |
| ____-59 ......__...__... ... __... ....... . ...___... ........ _"._.....__1.025 + 06 1.88E + 05 CO-58 0.00E + 00 1.58E + 03 2.07E + 03 0.00E + 00 #000E+00!iF 9.28E+05 1.06E + 05 3
| |
| CO-60 0.00E + 00 1.15E + 04 1.48E + 04 0.00E + 00 0 5.97E+06 2.85E + 05 N143 4.32E + 05 3.14E + 04 1.45E + 04 0.00E+00$ .00E+00
| |
| ._ _ _... ..__ _ _ ___ ... __.. ...__ t.o. 00E .......+ 00 1.78E +_ 05
| |
| ...__. 1.34E + 04 ZN-65 3.24E + 04 1.03E + 05 4.66E + 04 0.00E + 00 6.90E + 04 8.64E + 05 5.34E + 04 RB-86 0.00E + 00 1.35E + 05 5.90E + 04 0.00E + 00 0.00E + 00 0.00E + 00 1.66E + 04 SR 89 3.04E + 05 0.00E + 00 8.72E+03 40.00E4 00 0.00E + 00 1.40E + 06 3.50E + 05
| |
| - =..._ .....____.__.......
| |
| SR-90 9.92E + 07 0.00E + 00 6.10Ep06]l 0.00E 4 00 0.00E + 00 9.60E + 06 7.22E + 05 Y 91 4.62E + 05 0.00E + 00 1.24E'+ 0F 0.00E + 00 0.00E + 00 1.70E + 06 3.85E + 05 ZR 1.07E + 05 3.44E + 04
| |
| ....-95 . _........_ __........_,,2. 33E + k. 0.00E + 00 5.42E + 04 1.77E + 06 1.50E + 05 NB-95 1.41 E + 04 7.82E+01 (4.21E+p3 0.00E + 00 7.74E + 03 5.05E + 05 1.04E + 05 RU 103 1.53E + 03 0.00E +00 6.68E(02 0.00E + 00 5.83E + 03 5.05E + 05 1.10E + 05 RU 106 6.91 E + 04 0.00ETOOx 8.72E+03 0.00E + 00 1.34E + 05 9.36E + 06 9.12E + 05
| |
| ........ ........_ .. ___. __...... .__...... ..__..... =...... ...._____.
| |
| AG-110M 1.08E + 04 LOOE+ 04 '5.94E + 03 0.00E + 00 1.97E + 04 4.63E + 06 3.02E + 05 TE-125M 3.42E + 03 g f.68E"IO3 4.67E + 02 1.05E + 03 1.24E + 04 3.14E + 05 7.06E + 04 TE-127M 1.26E+04 t5.77E+03 1.57E + 03 3.29E + 03 4.58E + 04 9.60E + 05 1.50E+ 05 TE-129M 9.76E + 03# 3467E + 03 1.58E + 03 3.44E 4 03 3.66E + 04 1.16E + 06 3.83E + 05 l131 2f>2E%04 3.58E + 04 2.05E + 04 1.19E + 07 6.13E + 04 0.00E + 00 6.28E + 03 8.64E(0
| |
| + 04 4.52E + 03 2.15E + 06 2.5 . . . . _ _ _0.00E 1-133 + 00 8.88E + 03
| |
| -- .....__...__ ...% ___1.48E _...._.__..___..........___.8E+04 . . . _ _ _ . . - - - - _ . __
| |
| CS-134 3.73E + 05 8.48E + 05 7.28E + 05 0.00E + 00 2.87E + 05 9.76E + 04 1.04E + 04 CS-136 3.90E + 04 1.46E + 05 1.10E + 05 0.00E + 00 8.56E + 04 1.20E + 04 1.17E + 04 CS 137 4.78E + 05 6.21 E + 05 4.28E + 05 0.00E + 00 2.22E + 05 7.52E + 04 8.40E + 03 BA-140 3.90E + 04 4.90E + 01 2.57E + 03 0.00E + 00 1.67E + 01 1.27E + 06 2.18E + 05 CE-141 1.99E + 04 1.35E+ 04 1.53E + 03 0.00E + 00 6.26E + 03 3.62E + 05 1.20E + 05 CE 144 3.43E + 06 1.43E + 06 1.84E + 05 0.00E + 00 8.4 7.78E + 06 8.16E + 05 j ....... ...............__..........-........._...8E+05 ..... .... - .-_
| |
| l PR-143 9.36E + 03 3.75E + 03 4.64E + 02 0.00E + 00 2.16E + 03 2.81 E + 05 2.00E + 05 ND 147 5.27E + 03 6.10E + 03 3.65E + 02 0.00E + 00 3.56E + 03 2.21 E + 05 1.73E + 05 f 140.0 me<
| |
| i-
| |
| | |
| gggy TMl Radiological Controls Departmental Procedure Number
| |
| : w. 6610-PLN-4200.01 Hovision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5 3.1 Pathway Dose Factors, Ri
| |
| __ ._________...___. . AGE GROUP: ALL PATHWAY: GRO PLANE v..__.__.. ..__ ________..___....UND ....., ..____ -- __ .____.___...
| |
| ORGAN DOSE FACTORS
| |
| * i fNUCUDE T. BODY SKIN i 4
| |
| p__.......
| |
| 4
| |
| ' H-3 0.00E + 00 0.00E + 00 ,
| |
| l C-14 0.00E + 00 0.00E + 00 l
| |
| p.. CR.51 j MN-54
| |
| ___. 4.65E + 06 5.50E + 06
| |
| ___..__q y
| |
| [" "4.gt 1.39E + 09 1.62E+09 j p '!!i j l FE-55 ' '
| |
| ! FE .59p.. ...._2.73E+
| |
| 0.00E + 00 08 0.00E 4007 3.21 E + 08' hi#
| |
| : f. W*'/ !
| |
| .___.... .....__. q CO-58 3.79E + 08 4.44EgD8 h . q4 C040 2.15E + 10 I N143 0.00E + 00 0.00E(+ 00 e2,53E 10j"
| |
| * b- 4 ZN-65 7.47E + 08 8.59E408 !
| |
| RB-86 8.97E + 06 1.03E + 07 I SR-89 2.18E + 04 2.51E + 04 ;
| |
| F 1 l SR-90 .p.00E+00 " 0.00E+00 '
| |
| !Y-91 %.07E406 1.21 E + 06
| |
| !Z p_R. .95 p 2.84E + 0 l
| |
| ... %.. 2i45..E 4 .....___.8;
| |
| __ 08____ ..
| |
| {,37E + 08 ' ;
| |
| NB 95 q.. 1.61 E + 08 RUy03 4!igj1.08E + 08 1.26E + 08 RO2106 4.22E + 08 5.06E + 08 l p ~
| |
| _=.__.. 4 RAG 110M9 3.44E + 09 4.01 E + 09 kJEtT2SM 1.55E + 06 2.13E + 06 T
| |
| 4g'p.E.427M 9.17E + 04 t,g%. ___.__ ...._
| |
| 1.08E + 05
| |
| __...__...y s 1.98E + 07 2.31E+07 L iigid q%.'lTE.129M N,,i
| |
| ' t.131 1.72E + 07 2.09E+ 07 '
| |
| ""!il 1-133 2.45E + 06 2.98E + 06 l 4 p 4
| |
| CS-134 6.86E + 09 8.00E + 09 CS-136 1.51 E + 08 1.71 E + 08 CS-137 1.03E + 10 1.20E + 10 l F 4 BA-140 2.06E4 07 2.36E + 07 CE.141 1.37E + 07 1.54E + 07 CE.144 6.r6E+07 8.05E + 07 i p _...
| |
| .._____..........l PR-143 0 00E + 00 0.00E + 00 J
| |
| !' ND 147 c.__...... .. . 8.39E + 06 1.01E + 07 I
| |
| .. _ _ .___.....a
| |
| * m' . rarem/ year per pCl/sec.
| |
| 14 f.0 mm
| |
| (
| |
| | |
| Number
| |
| - itAClear m Ram i 9a Connois Departmental Procedure 6610-PLN-4200.01
| |
| : m. n. con No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.4.1 Pathway Dose Factors, RI AGE GROUP: INFANT PATHWAY: GRASS COW MILK ORGAN DOSE FACTORS; m2 . mrem / year per pCl/sec NUCUDE - - - - - - - - --. -- - . . ~ . - - - - . . . . . . . . - - - - - - - - - - . - - - - - - - - - - - . . - - - -
| |
| BONE UVER T. BODY THYROID KIDNEY LUNG GI-LU
| |
| ~ ~ ~~"~~ ~~~~ ~ ~ '~~
| |
| E3 d.~00E + b0 d.38E4 03 2.38E+b5~E.~38E+b3 d.38E+03 5.38E +b3~E.3E+~b5~
| |
| C-14 2.34E + 09 5.00E + 08 5.00E + 08 5.00E 4 08 5.00E + 08 5.00E + 08 5.00E + 0B CR-51 0.00E + 00 0.00E + 00 1.61 E + 05 1.05E + 05 2.30E + ;2.b5Et_05 4.70E + 06
| |
| .._..........__..___.___......--- .. .. ______.04 .. ..___ ...______.....
| |
| MN-54 0.00E + 00 3.91E + 07 8.85E + 06 0.00E +00 8.65E+06 I!;0.00Ejo0 1.43E + 07 FE-55 1.35E + 08 8.74E + 07 2.34E + 07 0.00E + 00 0.00(+00 4 . 4:27E+07 1.11 E + 07 2.25E + 08 3.93E + 08 1.55E + 08 0.00E + 00 0.00E400 1.16E + 08 1.88E + 08 4
| |
| FE-59 CO-58 0.00E + 00 2.43E + 07 6.06E + 07 0.00E+00 A00E+004 0.00E+00 6.05E + 07 CO-60 0.00E + 00 8.83E + 07 2.08E + 08 0.00E + 00, 0,00E +00 0.00E + 00 2.10E + 08 N143 3.50E + 10 2.16E + 09 1.21 E + 09 0.00E + 00k0.00 0.00E + 00 1.08E + 08
| |
| - ___. ... ....__ .. _......______...-.....E.+.00 _ _ _ _ _ _ =.......
| |
| ZN-65 5.56E + 09 1.91 E + 10 8.79E + 09 0.00E + 00 9.24E + 09 0.00E + 00 1.61 E + 10 RB-86 0.00E + 00 2.23E + 10 1.10E + 10 0.00E + 00 0.00E + 00 0.00E + 00 5.70E + 08 SR-89 1.26E 410 0.00E + 00 3.62E + 08 *0.00E + 00 0.00E + 00 0.00E + 00 2.09E + 08 SR-90 1.22E + 11 0.00E + 00 3.10Efl0]i 0.00E400 0.00E + 00 0.00E + 00 1.52E + 09 Y-91 7.34E + 04 0.00E + 00 1.95EkO3*D.00E + 00 0.00E + 00 0.00E + 00 5.26E+06 ZR-95 6.81 E + 03 1.66E + 03 :1418E+#1 0.00E + 00 1.79E + 03 0.00E + 00 8.27E + 05
| |
| .__.. .__.......______...._ u..... . ......... .....__.._.. ........_.........
| |
| NB-95 5.94E + 05 2.45E+05. !!1.41E+105 0.00E + 00 1.75E + 05 0.00E + 00 2.07E + 08 RU 103 8.68ti+ 03 0.00E+d f.90E#03 0.00E + 00 1.81 E + 04 0.00E 4 00 1.06E + 05 RU 106 1.91 E + 05 0.00E%. 2.38E + 04 0.00E + 00 2.25E + 05 0.00E + 00 1.45E + 06
| |
| ......___. ..._______.__. .....u___. ._____.. . __........___.__.._______ _._
| |
| AG-110M 3.86E + 08 2.82E+ 07, '1.87E + 08 0.00E + 00 4.03E + 08 0.00E + 00 1.46E + 10 TE-125M 1.51 E + 08 g d.06E407 2.04E 4 07 5.08E + 07 0.00E + 00 0.00E + 00 7.19E + 07 TE-127M 1.22E + 1.04E + 09 0.00E + 00 1.70E .____ + 08
| |
| -... . .. . 4.22E .. + 08 %. 40E+DS
| |
| ....- 5.10E + 0_7.__.._____....08 . _ _ _ _ _ . . . _ . . _ _ . . . . . -
| |
| TE-129M 5.58E + 06%1.91E + 08 8.59E + 07 2.14E + 08 1.39E + 09 0.00E + 00 3.33E + 08 l-131 2.72Ep) 121E+09 1.41E + 09 1.05E + 12 3.75E + 09 0.00E + 00 1.15E 4 08 l-133
| |
| ..__.....__ _3.63E __ +___..L_.5.29E O
| |
| + 07 1.55E + 07 9.62E + 09.._______
| |
| ........ ___...._________________....... 6.22E +..._______ 07 0.00E + 00 8.96E + 06 CS-134 3.65E + 10 6.81 E + 10 6.88E + 09 0.00E + 00 1.75E + 10 7.19E + 09 1.85E + 08 CS-136 1.98E + 09 5.83E + 09 2.18E + 09 0.00E 4 00 2.32E + 09 4.75E + 08 8.85E + 07 CS-137 5.15E + 10 6.03E + 10 4.27E + 09 0.00E + 00 1.62E + 10 6.55E + 09 1.89E + 08 l
| |
| BA 140 e.42E + 08 2.42E + 05 1.25E + 07 0.00E + 00 5.75E + 04 1.49E + 05 5.94E + 07 CE 141 4.34E + 04 2.65E + 04 3,12E + 03 0.00E 4 00 8.17F + 03 0.00E + 00 1.37E + 07 i CE 144 2.33E + 06 9.53E + 05 1.30E + 05 0.00E ..-
| |
| + 00 3.85E + 05 0.00E + 00 1.34E
| |
| + 08 i
| |
| PR-143 1.49E + 03 5.56E + O2 7.37E + 01 0.0CE + 00 2.07E + 02 0.00E 4 00 7.84E + 05 r
| |
| ND-147 8.83E + O2 9.07E + 02 5.55E 4 01 0.00E + 00 3.50E + 02 0.00E + =- 00..5.75E + 05
| |
| , .... .. ......_. ..........____...... .......- = = _ _ . . . . _ . . ._.....
| |
| l
| |
| )
| |
| 1 142.0 mm i
| |
| | |
| f Number TMI Radiological Controls l
| |
| I gdgy Departmental Procedure 6610-PLN.4200.01 Revinson No.
| |
| Trt6e Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.4.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS
| |
| .....______.....__..._____..._........._______.__..-COW-MILK __.______.__....______.__._
| |
| ORGAN DOSE FACTORS; m' mrem
| |
| ----------_-------.------------.------../ year per pCl/sec - - - - . - - - - - - . -
| |
| NUCLIDE LUNG GI BONE UVER T. BODY THYROID KIDNEY
| |
| .....___......__.._____________________........_......._____..__....______-LLI___
| |
| H-3 0.00E + 00 1.57E + 03 1.57E + 03 1.57E + 03 1.57E + 03 1.57E + 03 1.57E + 03
| |
| ~
| |
| C-14 1.20E + 09 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 CR-51 0.00E + 00 0.00E + 00 1.02E + 05 5.65E + 04 1.54E +04 ji".03E+ 05 5.40E ~~~~~
| |
| 4 06
| |
| ~~ ~ ~
| |
| MN-54 055Ub~b.~10d+~bi~559[ b6 b.Ed bb~~5Ed h6}bEUbb~1.76EIbi~ ,
| |
| l FE-55 1.12E + 08 5.94E + 07 1.84E + 07 0.00E + 00 0.00EiOO,. '3 36Ei07 1.10E + 07 j
| |
| FE-59 1.20E + 08 1.95E + 08 9.70E + 0 " 0.00E + 00 0.00E400 5.65E + 07 2.03E + 08 CO-58 0.00E + 00 1.21E + 07 3.72E + 07 0.00E + 00 gp.00E(00> 0.00E+00 7.08E + 07 C040 0.00E + 00 4.32E + 07 1.27E + 08 0.00E + 00 *0.00E +00 0.00E + 00 2.39E + 08 l
| |
| NI-63 2.97E +10 1.59E + 09 1.01E + 09 0.00E+0h0.00E + 00 0.00E = = = _ _
| |
| + 00 1.07E
| |
| . ____.__.. + 08
| |
| ____.-- 1 l
| |
| ZN-65 4.14E + 09 1.10E + 10 6.86E + 09 0.00E + 00 6.95E + 09 0.00E + 00 1.94E + 09 RB-86 0.00E + 00 8.78E + 09 5.40E + 09 0.00E + 00 0.00E + 03 0.00E + 00 5.65E + 08 SR-89 6.63E~~
| |
| + 09 0.00E + 00 1.89E + C 3 0'h 40E + 00 0.00E + 00 0.00E + 00 2.57E + 08
| |
| ~
| |
| ~b~R-90 f.~12dI11 bbd+"00 bkb$h ~bEk+'b~0 b5E [b.00d+'b I.515 b9 Y-91 3.91E + 04 0.00E + 00 1.05'Ei Di"o.00E+00 0.00E + 00 0.00E + 00 5.21E + 06 ,
| |
| 1 ZR-95 3.84E + 03 8.43E+O2 ,m731ES02 0.00E + 00 1.21E + 03 0.00E + 00 8.80E + 05 1 l
| |
| NS-95 3.18E + 05 1.24E+05 %8.86EiO4 0.00E + 00 1.16E + 05 0.00E + 00 2.29E+ 08 I
| |
| RU-103 4.29E4 03 0.00E4bo 'Y.66EIO3 0.00E + 00 1.08E + 04 0.00E + 00 1.11 E + 05 l RU 106 9.25E + 04 0.00E + bC
| |
| ___._-.. ........ . ...._ _L 1.15E n -___. + 04 0.00E + 00 1.25E + 05
| |
| -..._____....._.........-..=_- - 0.00E =..-_.--.
| |
| + 00 1.44E + 06 ?
| |
| l AG-110M 2.09E + 08 p.4]E408 "1.13E+08 0.00E + 00 2.63E + 08 0.00E 4 00 1.68E + 10 TE-125M 7.39E+ 07m 2.00E+b7 9.85E + 06 2.07E + 07 0.00E + 00 0.00E + 00 7.13E + 07 l TE 127M 2.08E + 2.47E + 07 4.98E + 07 5.94E + 08 0.00E.__.+ 00__.____..__
| |
| 1.69E + 08
| |
| .....___.____ _____.08%_5.81ET
| |
| _ .......________... 07..___.- =- ..______....
| |
| i TE 129M 2.72E 08(7.59E+07 4.22E +07 8.76E + 07 7.98E + 08 0.00E + 00 3.31E4 08 l 1-131 1.31E{3 09 "1.31 E + 09 7.46E + 08 4.34E + 11 2.16E + 09 0.00E + 00 1.17E + 08 l-133 1.72E #07 2.13E + 07 8.05E + 06 3.95E + 09 3.55E + 07 0.00E + 00 8.58E + 06 l
| |
| CS-134 2.27E + 10 3.72E+ 10 7.85E + 09 0.00E + 00 1.15E + 10 4.14E + 09 2.01 E + 08 '
| |
| CS-136 1.01 E + 09 2.79E + 09 1.80E + 09 0.00E + 00 1.49E + 09 2.21E + 08 9.80E + 07 CS-137 3.23E + 10 3.09E + 10 4.56E + 09 0.00E + 00 1.01E + 10 3.62E + 09 1.93E + 08 BA-140 1.18E + 08 1.03E + 05 6.86E + 06 0.00E + 00 3.35E + 04 6.14E + 04 5.96E + 07 CE-141 2.19E + 04 1.09E + 04 1.62E + 03 0.00E + 00 4.79E + 03 0.00E + 00 1.36E + 07 C5 144 1.63E + 06 5.09E + 05 8.67E + 04 0.00E + 00 2.82E + 05 0.00E= =+= 00 = 1.33E + 08 PR-143 7.18E + O2 2.16E + 02 3.56E + 01 0.00E + 00 1.17E + O2 0.00E + 00 7.75E + 05 ND 147 4.45E + O2 3.61E 4 -.,..._.....
| |
| 02 a.79E + 01 0.00E + 00 1.98E
| |
| ......... + O2 0.00E + 00 5.71E
| |
| .........-......... ....... + 05 ..
| |
| - . - ___...._-_=-_
| |
| 1 l
| |
| 143.0 me
| |
| | |
| Number gggy TMI Radiological Controls Departmental Procedure 6610.PLN-4200.01 htD Hovision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.4.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY:
| |
| === -- ......_....__. GRASS ._. COW-MILK ORGAN DOSE FACTORS; m' mrem /--year - .per_... pCl/.sec NUCUDE - - - - - - - - - - - - - - - - . - - . - . - . - - - .-. - .
| |
| BONE UVER T. BODY THYROID KIDNEY LUNG GI-LU
| |
| ~ ~~' ~ '
| |
| 5-3 UE0i[+~00~553E+02 hdE+02 ~~~ 53E+[2 9 ~ EE+T22
| |
| : 9. 9.93E + 02~~~553Ii+~i2~
| |
| C-14 4.86E + 08 9.73E + 07 9.73E + 07 9.73E + 07 9.73E + 07 9.73E + 07 9.73E + 07 CR-51 0.00E + 00 0.00E + 00 4.99E + 04 2.77E + 04 1.09E + 04 AT3E+04 8.39E + 06 MN-54 0.00E + 00 1.40E + 07 2.78E + 06 0.00E + 00 4.19E+06 10.00E j 00 2.88E + 07 FE-55 4.46E + 07 3.16E + 07 7.37E + 06 0.00E + 00 0.00E+00,.101E407 1.37E + 07 FE 5.19E + 07 1.21 E + 08 4.68E + 07 0.00E + 00 0.00Et00 3.82E + 07 2.86E4 08
| |
| ____-59_......__........_. __.=- _____...________.... ... ..w _" __...._____...__. __. s CO-58 0.00E + 00 7.94E + 06 1.83E + 07 0.00E + 00# 0;00Et004 0.00E+00 1.10E + 08 j
| |
| ; CO-60 0.00E + 00 2.78E + 07 6.27E + 07 0.00E + 00 '0,00E +00 0.00E + 00 3.62E 4 08 i j
| |
| i Ni63 1.18E + 10 8.36E + 08 4.01 ...___0.00E
| |
| - - E_ +- 08 +004!
| |
| __...__._L_O;00E + 00 0.00E + 00 1.33E + 08 i .....___ ..__.....___ ___....- - _.. ..____..____..__......__.
| |
| 4 ZN45 2.11 E + 09 7.32E + 09 3.42E + 09 0.00E + 00 4.69E + 09 0.00E+ 00 3.10E + 09 I RB-86 0.00E + 00 4.73E + 09 2.22E + 09 0.00E + 00 0.00E + 00 0.00E + 00 7.00E + 08 y SR-89 2.68E + 09 0.00E + 00 7.67E + 07 +0.00E + 00 0.00E + 00 0.00E + 00 3.19E + 08 SR-90 6.62E+10 0.00E + 00 1.63E/1Oj 0.00E400 0.00E + 00 0.00E + 00 1.86E + 09 l
| |
| ! Y-91 1.58E + 04 0.00E + 00 4.24E t.02MO.00E + 00 0.00E + 00 0.00E + 00 6.48E + 06 l ZR 1.65E + 03 5.21E +02 1 ....-95 .....__ _ _ ___.....__... _ __ _ _.3.5BE/02 0.00E + 00 7.65E + 02 0.00E + 00 1.20E + 06 NB-95 1.41E + 05 D4 0.00E + 00 7.58E+ 04 0.00E + 00 3.34E + 08 l
| |
| t RU-103 1.81 E + 03 7.82E+04 0.00E '7J5E. (4.30E{f 0.00E02 + 00 6.39E + 03 0.00E + 00 1.51 E + 05 l
| |
| RU-106 3.76E + 04 0.00d+0060.g 4.73E + 03 0.00E + 00 7.24E + 04 0.00E 4 00 1.80E + 0 AG-110M 9.64 E + 07 9."12E 1 07 'S.55E+07 0.00E + 00 1.74Ed 08 0.00E + 00 2.56E + 10 TE-125M 3.01E+07.g 108E+ p7 4.02E+ 06 8.40E + 06 0.00E + 00 0.00E + 00 8.87E+07 TE 8.45E + 0
| |
| __..-127M
| |
| _. _..___...7.%3 00E407
| |
| .. ...___ 1.00E + 07 2.01E
| |
| ___..________... __... 4 07 3.42E + 08 0.00E
| |
| .....________...... .... + 00 2.11
| |
| __.__ E + 08 TE-129M 1.10E + 06 V09E + 07 1.74E + 07 3.56E + 07 4.61 E + 08 0.00E + 00 4.14E + 08 l-131 5.38Et08 7.53E + 08 4.05E + 08 2.20E + 11 1.30E + 09 0.00E + 00 1.49E + 03 1.20E + 07 3.66E + 06 1.68E4 09 2.11E + 07 0.00E + 00 9.09E,03 1133
| |
| .____ ...._........6 7.08E + 0 CS-134 9.83E + 09 2.31 E + 10 1.07E + 10 0.00E + 00 7.35E + 09 2.81E + 09 2.88E + 08 i
| |
| CS-136 4.49E + 08 1.77E + 09 1.19E + 09 0.00E + 00 9.63E + 08 1.52E + 08 1.42E + 08 CS 137 1.34E + 10 1.78E + 10 6.21 E + 09 0.00E
| |
| - ==.=-
| |
| + 00 6.06E + 09 2.36E + 09
| |
| ____.....____.__.==- _-_ .
| |
| 2.54E + 08
| |
| .___.......__....__.. ...___.==
| |
| BA-140 4.87E + 07 5.97E + 04 3.14E + 06 0.00E + 00 . 2.02E + 04 4.01 E + 04 7.51 E + 07 CE-141 8.89E + 03 5.94E+03 6.82E + O2 0.00E + 00 2.80E + 03 0.00E + 00 1.70E + 07
| |
| . ..d.## ...__.6,,59E 2.73E 05 3.54E 04,, ,,3 ,,,,g,00E p0,,3 ,,,,,,1 g ,E ,,,,,g,
| |
| ,3,05,,,_,,,,,3 , , 1 ,0500E,,3,00,,,,,g,,3,08 1 E PR 143 2.90E + 02 1.16E + 02 1.44E + 01 0.00E + 00 6.73E + 01 0.00E + 00 9.55E + 05 ND 147 1.81E + 02 1.97E + 02 1.18E + 01 0.00E + 00 1.16E + O2 0.00E + 00 7.12E + 05 144.0 222=
| |
| ~
| |
| | |
| F l
| |
| Number l p
| |
| EEl Nuclear
| |
| , ,g
| |
| * "ad w a "
| |
| Departmental Procedure 6610-PLN-4200.01 l TO Revision No. I l
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.4.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW MILK t ORGAN DOSE FACTORS; m' - mrem / year per pCl/sec l NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - - - - - - - - - - - - - - - - - -
| |
| l BONE UVER T. BODY THYROID KIDNEY LUNG GI
| |
| _ .....-LU...
| |
| t l
| |
| H-3 0.00E + 00 7.62E + O2 7.62E + O2 7.62E + O2 7.62E + O2 7.62E + 02 7.62E + 02 l
| |
| C-14 2.63E + 08 5.26E + 07 5.2GE + 07 5.26E + 07 5.26E + 07 5.26E + 07 5.26E + 07 CR 0.00E + 00 0.00E + 00 2.85E + 04 1.70E + 04 6.28E+03 j3f78Et04 7.17E + 06
| |
| _.-51 MN-54 0.00E + 00 8.40E + 06 1.60E + 06 0.00E + 00 2.50E+06 (0.00E100 2.57E + 07 l
| |
| FE-55 2.51E + 07 1.73E + 07 4.04E + 06 0.00E + 00 0.00E +00dg 9.66EiiO6 9.93E + 06 FE-59 2.97E + 07 6.97E + 07 2.67E + 07 ' O.00E + 00 0.00E400 1.95E + 07 2.32E + 08 l
| |
| ... . . . . . . . . . . _ . . - . ..._ ........._... .. . i CO-58 0.00E + 00 4.71E + 06 1.05E + 07 0.00E + 00#0.00E+30& 0.00E+00 9.54E + 07 l CO-60 0.00E + 00 1.64E + 07 3.61 E + 07 0.00E + 00,. '0.00E + 00 0.00E + 00 3.08E + 08 l NI43 6.72E + 09 4.65E 4 08 2.25E+ 08 0.00E + 00%0.'00E + 00 0.00E + 00 9.71 E + 07
| |
| , ~
| |
| ; ZN-65 1.37E + 09 4.36E + 09 1.97E + 09 0.00E + 00 2.91 E + 09 0.00E + 00 2.74E + 09 RB-86 0.00E + 00 2.59E+ 09 1.21 E + 09 0.00E +00 0.00E + 00 0.00E + 00 5.10E+08 1.45E + 09 0.00E + 00 4.16E + 07 eO.dDE +00 0.00E + 00 0.00E + 00 2.32E + 08 SR..-89. . . . . . . - - . . _ _ _... ......... .... . . . . . . . . . _ . . - . ..........
| |
| j SR-90 4.67E + 10 0.00E + 00 1.15Ep10j 0.00E400 0.00E + 00 0.00E + 00 1.35E + 09 Y-91 8.57E + 03 0.00E + 00 2.29EkD2MO.00E + 00 0.00E + 00 0.00E + 00 4.72E + 06 i ZR 9.41 E + O2 3.02E + O2 2.04E i
| |
| _. -95 ........ ... ..-......f 02 0.00E + 00 4.74E
| |
| .. ......... + O2 0.00E
| |
| .........-....... + 00 9.57E + 05 NB-95 8.24E + 04 4.58E+0$ !l2.46E(D4 0.00E + 00 4.53E + 04 0.00E + 00 2.78E + 08 l
| |
| RU-103 1.02E +03 0.00E +00 W.38E#02 0.00E + 00 3.88E + 03 0.00E + 00 1.19E+ 05 i
| |
| RU-106 2.04E + 04 0.00ET60x 2.58E+03 0.00E + 00 3.93E + 04 0.00E + 00 1.32E + 06
| |
| ... ........ ......... ......... .................... 1 AG-110M 5.81 E + 07 5.38E + 07 '3.19E + 07 0.00E + 00 1.06E + 08 0.00E + 00. 2.19E + 10 l
| |
| TE.125M 1.63E + 07 4 $.89ETD6 2.18E + 06 4.89E + 06 6.61 E + 07 0.00E + 00 6.49E + 07 TE-127M 4.57E + 0 l
| |
| ......... .........? M........
| |
| 63E+07..... 5.57E..+ 06 1.17E +........
| |
| ......... 07 1.86E. +...... 08 0.00E + 00 1.53E + 08 TE-129M 6.01E + 07%2.24E + 07 9.51 E + 06 2.06E + 07 2.51 E + 08 0.00E + 00 3.02E + 08 l-131 2.96E +s08 4.23E + 08 2.42E + 08 1.39E + 11 7.25E + 08 0.00E + 00 1.12E + 08 l133
| |
| .......... .......3.87E 6 6.73E +0
| |
| + 06 __ 2.05E + 06 9.88E
| |
| ..._......... + 0B 1.17E
| |
| ......... + 07 0.00E + -..........
| |
| ........._......... 00 6.04E + 06 CS-134 5.64E + 09 1.34E + 10 1.10E + 10 0.00E + 00 4.34E + 09 1.44E + 09 2.35E + 08 CS-136 2.63E + 08 1.04E + 09 7.48E + 08 0.00E + 00 5.78E + 08 7.92E 4 07 1.18E + 08 7.37E + 09 1.01E + 10 6.60E4 09 0.00E + 00 3.42E + 09 1.14E + 09 1.95E + 08 l CS .137 ..... ......... ....... .... _. .... .... ......... ........._.. .......
| |
| BA-140 2.69E + 07 3.38E 4 04 1.76E + 06 0.00E + 00 1.15E + 04 1.94E + 04 5.54E + 07 l CE-141 4.84E + 03 3.27E + 03 3.71 E + O2 0.00E + 00 1.52E + 03 0.00E + 00 1.25E + 07
| |
| _ Ej33,,,_,3J,7E 95,.1 ,,,149E + 05_,1p1E194 _ 0 00E + 00 8pXtp4 0.pqE1pp,,,11E198, C ,, , _, _, ,
| |
| 1 PR-143 1.57E + O2 6.32E + 01 7.81 E + 00 0.00E + 00 3.65E + 01 0.00E + 00 6.90E + 05 ND-147 9.40E + 01 1.09E + O2 6.50E + 00 0.00E + 00 6.35E + 01 0.00E + 00 5.22E + 05 1
| |
| l l
| |
| 145.0 mm l
| |
| | |
| I l
| |
| ; l l I r i gggy Numt:Or TMI Radiological Controls l
| |
| Departmental Procedure 6610-PLN-4200.01 1m.
| |
| Rowsion No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.5.1 !
| |
| Pathway Dose Factors, RI i
| |
| AGE GR PATHWAY: GRASS-GOAT-MILK
| |
| ---........ .. . . . .. .. - -.. .O U P: . INFANT NUCLlDE - - - - - - - - - - - - - - - - - - - - - - - - - - - -
| |
| BONE LIVER
| |
| -..................-_......._......ODY H-3 T.B THYROID
| |
| .--.........-.........................-LLI KIDNEY LUNG GI 0.00E + 00 4.86E + 03 4.86E + 03 4.86E + 03 4.86E + 03 4.86E+ 03 4.86E + 03 C-14 2.34E + 09 5.00E + 08 5.00E + 08 5.00E + 08 5.00E + 08 5.00E + 08 5.00E + 08 <
| |
| .CR .51 0.00E + 00 0.00E + 00 1.94E + 04 1.26E + 04 2.76E + 03 5.64E + 05 MN-54
| |
| _ .. . . .. . ... .. .. . .... . ..-. .. ... . .._. ... .... . f 23 6E
| |
| + 04 0 00E + 00 4.68E + 06 1.06E + 06 0.00E + 00 1.04E +p6 0.00E;4 00 1.72E + 06 FE-55 1.76E + 06 1.14E + 06 3.03E + 05 0.00E + 00 0.00E4 00,('5.56E1.44E + 05
| |
| + 05 FE-59 2.92E + 06
| |
| .... . .........-.5.10E+06 . . ......
| |
| 2.01 E + 06
| |
| ........--.0.00E + 00........ 0.00.,E*
| |
| .. 00' .1.51
| |
| .... E + 06 2.44E + 06 CO-58 0.00E + 00 2.91E + 06 7.26E + 06 00Et002 0.00E + 00 7.25E + 06 CO-60 NI63 0.00E + 00 1.06E + 07 2.50E + 07 0.00E 0.00E+00
| |
| + 00 A'0.00E+00 0.00E + 00 2.52E + 07 4.19E + 09 2.59E
| |
| ... .... ......... ... ..... .......08
| |
| + 08 1.46E + 1.29E 0.00E
| |
| + 07 ZN.65
| |
| . ........ -.olDO.E+000.00E . . .+. .00h
| |
| . . . ...= -....
| |
| - = + 00 6.67E + 08 2.29E + 09 1.05E+ 09 0.00E + 00 1:11E + 09 0.00E + 00 1.93E + 09 RB-86 0.00E + 00 2.67E + 09 1.32E + 09 0.bOE+ 00 0.00E + 00 0.00E + 00 6.83E + 07 SR-89 2.65E + 10 0.00E + 00 7.59E+ 08 co.00E + 00 0.00E+ 00 0.00E + 00 5.44E+08
| |
| =.... .........-..........
| |
| SR-90 2.55E + 11 0.00E + 00 6.50Ef10j 0.00E'+ 00 0.00E + 00 0.00E+ 00 3.19E + 09 Y-91 ZR-95 8.80E + 03 0.00E + 00 2.34EkOMO.00E + 00 0.00E + 00 0.00E + 00 6.31E + 05 8.17E + 02 1.99E + 02 1.41Ef02 0.00E + 00 2.15E + 02 0.00E+ 00 9.91E + 04 NB-95 7.13E + 04 2.93E + 04 [1.70E 404 " 0.00E+00 2.10E+ 04 0.00E + 00 2.48E + 07 RU-103 1.04E + 03 0.00Et 00 '348E402 0.00E + 00 2.17E + 03 0.00E+ 00 1.27E + 04 RU-106 2.28E + 04 0.00E400., 2.85E + 03 0.00E + 00 2.70E + 04 0.00E + 00 1.73E + 05 I
| |
| ~~~~kOM AG 1 4.63E + 07 3.38E.+ 07 N2.24E+07 0.00E + 00 4.84E + 07 0.00E + 00 1.75E+ 09 TE 125M 1.81E + 07 8.0SEV06 2.45E + 06 6.09E 4 06 0.00E + 00 0.00E + 00 8.62E + 06 TE 5.06E+
| |
| ..-127M
| |
| .... .07%1. 66.E.i.07 6.12E + 06.........
| |
| 1.46E + 07 1.24E + 08 0.00E + 00 2.04E + 07
| |
| .....=_ . =........
| |
| TE-129M 2
| |
| 6.69E + Opq .29E + 07--= 1.03E + 07 2.57E + 07 1.67E + 08 0.00E + 00 3.99E + 07 l-131 3 27E109 3.85E + 09 1.69E + 09 1.27E + 12 4.50E + 09 0.00E + 00 1.37E + 08 l-133 4.36E #07 6.35E + 07 1.86E + 07 1.15E + 10 7.46E + 07 0.00E + 00 1.07E + 07
| |
| = = = = -
| |
| CS 134 _......._......... .... ...-..........
| |
| 1.09E + 11 2.04E + 11 2.06E + 10 0.00E+ 00 5.26E+10 2.15E + 10 5.55E + 08 CS 136 i 5.94E t 09 1.75E + 10 6.52E + 09 0.00E + 00 6.96E + 09 1.42E + 09 2.65E + 08 CS-137 1.54E + 11 1.81E + 11 1.28E ,10 0.00E + 00 4. s BA-140
| |
| ...............................-....85E+10 .===--- -
| |
| 1.96E + 10 5.65E + 08 2.90E + 07 2.90E + 04 1.50E + 06 0.00E + 00 6.89E + 03 1.7Ed + 04 7.13E + 06 l CE-141 5.21E + 03 3.18E + 03 3.74E + 02 0.00E + 00 9.79E + 02 0.00E + 00 1.64E + 06 l CE
| |
| ....-144 PR-143 _....................-....................................--......07--
| |
| 2.79E + 05 1.14E + 05 1.56E + 04 0.00E + 00 4.62E + 04 0.00E + 00 1.60E +
| |
| 1.78E + 02 6.66E + 01 8.83E + 00 0.00E + 00 2.48E + 01 0.00E + 00 9.40'I+ 04 ND-147 1.06E + O2 1.09E + 02 6.66E + 00 0.00E + 00 4.19E + 01 0.00E + 00 6 89E + 04
| |
| == = _ =-__.. ..........
| |
| I 146.0 mm I
| |
| I
| |
| | |
| l l Number M Radiological Cmtrols l
| |
| GUClear Departmental Procedure 6610-PLN.4200.01 j j Title Revision No.
| |
| l l
| |
| Offsite Dose Calculation Manual (ODCM) 12 l i i I TABLE 5.5.2 Pathway Dose Factors, Ri j
| |
| .. . . ... ...AGE
| |
| . ...GROUP: .,.. . .. . . .PATHWAY:
| |
| .. .. . _. .CHILD . ... . . _. ..GRASS
| |
| -G O AT _M
| |
| ...... I LK ORGAN DOSE FACTORS; m' mrem / year per pCl/.sec NUCUDE ------------ - ---- . . - . . . _ . . . . - - - . . _ . . . - - - - - - . . - . . . . . . -
| |
| BONE UVER --.-- . TBODY KIDNEY
| |
| _................................._......-LLI....
| |
| THYROID LUNG GI
| |
| ...........-........_.......=
| |
| H-3 0.00E + 00 3.20E + 03 3.20E + 03 3.20E + 03 3.20E + 03 3.20E + 03 3.20E + 03 C-14 1.20E + 09 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 l CR 51 0.00E + 00 0.00E + 00 1.22E + 04 6.78E + 03 1.85E + 03 6.48E + 05 )
| |
| . . ........._......._ _ _ = ... .. .... .. . ....... ...#..tl24E + 04 MN-54 0.00E + 00 2.52E + 06 6.71 E + 05 0.00E + 00 7.06E p5li 0.00E)00 2.11E + 06 FE-55 1.45E + 06 7.71E +05 2.39E + 05 0.00E + 00 0.00E ' 00. 4,3eE + 05 1.43E + 05 FE 1.56E +06 2.53E + 06 1.26E + 06 0,
| |
| . 59 .. . . . . . . . . _ . . _ _ . . . . - - ..00Et00 7.34E + 05 2.64E + 06 0.00E + 00........ , ..
| |
| I CO-58 0.00E + 00 1.46E + 06 4.46E + 06 0.00E + 00pp.00E t 00 0.00E + 00 8.49E + 06 CO40 0.00E + 00 5.18E + 06 1.53E 4 07 0.00E+00 400E+00 0.00E + 00 2.87E + 07 NI-63 3.56E + 09 1.91E + 08 1.21 E + 08.... 0.00E + 00 0 +.... 0.00E + 00 1.28E + 07
| |
| - - . . - _ - .-- - ____... - - ....... ... 4y:.00.E 00 ......... ..........
| |
| ZN-65 4.96E + 08 1.32E + 09 8.22E + 08 0.00E + 00 8.33E + 08 0.00E + 00 2.32E4 08 RB-86 0.00E + 00 1.05E + 09 6.47E + 08 OBOE + 00 0.00E 4 00 C.00E + 00 6.77E + 07 SR 89 1.39E + 10 0.00E + 00 3.97E + 0840.00E + 00 0.00E + 00 0.00E + 00 5.39E + 08 )
| |
| SR-90 2.35E + 11 0.00E + 00 5.95EF100 0.00E+00 0.00E + 00 0.00E + 00 3.16E + 09 Y-91 4.69E + 03 0.00E + 00 1.25E + O2 4 .00E 0 + 00 0.00E + 00 0.00E + 00 e24E+05 ZR-95 4.60E + 02 1.01E+ O2 a
| |
| .........a ........ ==
| |
| 0.00ETD1 0.00E + 00 1.45E + 02 0.00E + 00 1.05E + 05 NB-95 3.82E + 04 1.06E)D4 0.00E + 00 1.40E + 04 0.00E + 00 2.75E + 07 RU-103 5.14E + 02 1.49E +04 0.00EfD0 1 (9 .90E4020.00E + 00 1.29E + 03 0.00E + 00 1.33E + 04 RU-106 1.11 E + 04 0.00E700 1.38E + 03 0.00E + 00 1.50E + 04 0.00E + 00 1.73E + 05 ]
| |
| i l AG-110M 2.51E+ 07 jf.'69E+ 07
| |
| * 1.35E+ 07 0.00E + 00 3.15E + 07 0.00E + 00 2.01E + 09 TE-125M 8.86E + 06 62.40EYD6 1.18E + 06 2.49E + 06 0.00E + 00 0.00E + 00 8.55E + 06 '
| |
| TE-127M 2.96E + 06 5.97E + 06 7.12E + 07 0.00E + 00 2.02E + 07
| |
| ...... 2.50.E t.D7%6.72E$06 TE 129M 3.26E;p7g 9.10E+06 5.06E + 06 1.05E + 07 9.56E + 07 0.00E + 00 3.97E + 07 l-131 1.57E409 41.57E + 09 8.95E + 08 5.21 E + 11 2.58E + 09 0.00E + 00 1.40E + 08 l133 2.06EIO7--
| |
| 2.55E + 07 9.66E + 06 4.74E + 09 4.25E + 07 0.00E + 00 1.03E + 07
| |
| -......._____ =_... ..... ..._......... ......... ..........
| |
| CS-134 6.00E + 10 1.12E + 11 2.35E + 10 0.00E + 00 3.46E + 10 1.24E + 10 6.01 E + 08 i l
| |
| CS-1?6 3.04E + 09 8.36E + 09 5.41 E + 09 0.00E + 00 4.45E + 09 6.64E + 08 2.94E + 08 CS-137 9.68E + 10 9.26E + 10 1.37E + 10 0.00E + 00 3.02E + 10 1.09E + 10 5.80E + 08 i
| |
| I I
| |
| BA-140 1.41 E + 07 1.24E + 04 8.23E + 05 0.00E + 00 4.02E + 03 7.37E + 03 7.15E + 06 l CE-141 2.63E + 03 1.31 E + 03 1.95E + O2 0.00E + 00 5.74E + O2 0.00E + 00 1.63E 4 06 CE 144 1.95E + 05. 6.11E + 04 1.04E + 04 0.00E
| |
| + 00 3.38E + 04 0.00E + 00 1.59D 07.
| |
| PR 143 8.61E + 01 2.59E + 01 4.27E + 00 0.00E + 00 1.40E + 01 0.00E + 00 9.29E + 04 .
| |
| ND-147 5.34E + 01 4.33E + 01 3.35E + 00 0.00E + 00 2.37E+ 01 0.00E + 00 6.85E + 04 l
| |
| 147.0 mm l
| |
| l 1
| |
| | |
| f Numbu glgg TMI Radiological Controls Departmental Procedure 6610.PLN.4200.01 j im. n. vision No. l l Ottsite Dose Calculation Manual (ODCM) 12 l
| |
| i l TABLE 5.5.3 Pathway Dose Factors, Ri l
| |
| AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK NUCUDE - - - - - - - - - - - - - - = - - - - - - - - - - - - - = = = - - - - - - - - - - - - . - - - - - . - - - - - - . - - - -
| |
| BONE UVER T. BODY THYROID
| |
| ..........._......._........___..........___.....___,...............__.....__..-LU KIDNEY LUNG GI H-3 0.00E + 00 2.04E + 03 2.04E + 03 2.04E + 03 2.04E + 03 2.04E + 03 2.04E + 03 C-14 4.86E + 08 9.72E + 07 9.72E + 07 9.72E + 07 9.72E + 07 S.72E + 07 9.72E + 07 CR-51 0.00E + 00 0.00E + 00 5.99E + 03 3.33E + 03 1.31E + 03 ; 8 SSE + 03 1.01 E + 06 MN-54 0.00E + 00 1.68E + 06 3.34E + 05 0.00E + 00 5.02E+05 i(,0.00Ep00 ! 3.45E + 06 FE-55 5.79E + 05 4.11 E + 05 9.58E + 04 0.00E + 00 0.00E4 00, 2.61E+05 1.78E 4 05 FE-59 6.74E + 05 1.57E + 06 6.08E 4 05 0.00E + 00 0.00E400" 4.96E + 05 3.72E + 06 CO-58 0.00E + 00 9.53E + 05 2.20E + 06 0.00E + 00 p 0.00Et001 0.00E + 00 1.31 E + 07 )
| |
| CO-60 0.00E + 00 3.34E + 06 7.52E + 06 0.00E+00, *0;00E400 0.00E + 00 4.35E + 07 i NI-63 1.42E + 09 1.00E + 08 4.81E + 07 0.00E + 009lb 0.00E + 00 0.00E + 00 1.60E + 07 !
| |
| ZN 65 2.53E + 08 8.78E + b8 4.10E + 08 0.00E + 00 5.62E + 08 0.00E + 00 3.72E + 08 RB-86 l 0.00E + 00 5.67E + 08 2.67E + 08 0 00E + 00 0.00E + 00 0.00E +00 8.40E + 07 l SR..-89 5.62E + 09 0.00E + 00 1.61 E + 08 co.00E + 00 0.00E + 00 0.00E + 00 6.69E + 08 SR-90 1.39E + 11 0.00E + 00 3.43Es10 0.00E400 0.00E + 00 0.00E+ 00 3.90E + 09 5.09E401M] O.00E+00 Y-91 1.90E + 03 0.00E + 00 0.00E + 00 0.00E+ 00 7.78E+ 05 l ZR 1.98E + O2 9.1
| |
| ..-95
| |
| ._ ____ . .. ...... 6....--
| |
| 25E + 01 ....
| |
| 4.30E +01 0.00E + 00 ... 8E...__.__........-..._____..
| |
| .. ....... + 01 0.00E + 00 1.44E + 05 I NB-95
| |
| ' 1.69E + 04 9.38E + 03 f5.16E 403 0.00E + 00 9.09E + 03 0.00E + 00 4.01 E + 07 l RU-103 2.17E + O2 0.00Et0d "9.29E/01 0.00E + 00 7.66E + O2 0.00E + 00 1.82E + 04 l RU 106 4.50E + 03 0.00E400 q
| |
| ...._...._-_ __ _. ..... . .... . _ .. 1 5. 68 ....- E + O2 0.00E _ _ . . . .+ 00
| |
| . . . . 8.69E
| |
| . - _ . . .+ 03
| |
| . . . . 0.00E
| |
| . - . . . .+ 00
| |
| . _ . _ 2.16E
| |
| . - . . . .+ 05 AG 110M 1.16E + 07 009Et07 '6.65E+06 0.00E + 00 2.09E + 07 0.00E + 00 3.07E + 09 TE-125M 3.61E + 06 L30E706 4.82E + 05 1.01 E + 06 0.00E + 00 0.00E + 00 1.06E + 07 4
| |
| TE 1.01E+07 %3.59E+06 1.20E + 06 2.41 E + 06 4.11 E + 07 0.00E + 00 2.52E + 07
| |
| ....-127M TE-129M 1.32E + OR4.90E + 06 2.09E + 06 4.26E + 06 5.53E + 07 0.00E + 00 4.96E 4 07 l-131 6 45E+08 3.03E + 08 4.85E + 08 2.64E + 11 1.56E 4 09 0.00E + 00 1.79E + 08 l133 8.49El06 1.44E + 07 4.40E + _06
| |
| ' 2.01 E + 09 2.53E + 07 0.00E + 00 1.09E + 07
| |
| . . . . . . . . . _ _ _ . . . . . . . _ _ _ _ _ _ _ . . . = - _ . . . . . - .. ._......... ......- .........
| |
| CS-134 2.95E + 10 6.93E + 10 3.22E + 10 0.00E + 00 2.20E + 10 8.41 E + 09 8.62E + 08 CS-136 1.35E+ 09 5.30E + 09 3.56E + 09 0.00E + 00 2.89E + 09 4.55E + 08 4.27E + 08 CS 137 4.02E + 10 5.34E + 1 1.86E + 10 0.00E + 00 1.82E + 10 7.07E + 09 7.60E + 08
| |
| ........_......... ........0 .__..___... .. .. .__...... ...._____________ ..
| |
| BA 140 5.84E + 06 7.1GE + 03 3.76E + 05 0.00E + 00 2.43E + 03 4.81 E + 03 9.01 E + 06
| |
| : l. CE-141 1.07E + 03 7.12E + 02 8.18E + 01 0.00E + 00 3.35E + 02 0.00E + 00 2.04E + 06 l CE 144 7.90E 4 04 3.27E + 04 4.2SE + 03 0.00E + 00 1.95E + 04 0.00E + 00 1.99E + 07
| |
| _-.....-._........ ......- ======.. .... .....
| |
| ; PR-143 3.48E + 01 1.39E + 01 1.73E + 00 0.00E + 00 8.08E + 00 0.00E4 00 1.15E + 05 l ND 147 2.18E + 01 2.37E + 01 1.42E 4 00 0.00E + 00 1.39E + 01 0.00E + 03 8.54E + 04 148.0 na t
| |
| | |
| 7_
| |
| jggy TMI Radiological Controls Departmental Procedure Number f Tme 6610 PLN-4200.01 Revision No.
| |
| Offshe Dose Calculation Manual (ODCM) 12 TABLE 5.5.4 Pathway Dose Factors, RI l
| |
| AGE GROUP: ADULT PATHWAY: GRASS-GOAT-MILK NUCUDE ----= -- - ORGAN DOSE ------.'.----
| |
| .-.-------.------ FACTORS; m/ mrem year per pCi/sec BONE ----------------------------
| |
| ......... ....... .. ..... LIVER T. BODY THYROlD
| |
| .. .. __ _ _..__ ...__..._ _... KIDNEY LUNG GI H3 .
| |
| .. .... .. ._ _ _ _ . . ...-Lil ...
| |
| C-14 0.00E + 00 1.56E + 03 1.56E + 03 1.56E + 03 1.56E + 03 1.56E + 03 1.56E + 03 CR 2.64E 0.0 + 08 5.27E + 07 5.27E+07 5.27E + 07 5.27E + 07 5.27E + 07 5.27E 4 07
| |
| ..___51 .. . __.0E+00 .__ . . 0.00E + 00 3.43E + 03
| |
| ........ .... ....____2.05E + 03
| |
| . ....... 7.56E
| |
| .__. ..._ _ +#,,..L55E 02 + 03 8.63E + 05 MN-54 0.00E + 00 1.01E + 06 . . . . . _ . . . . . . _ _ - .
| |
| FE-55 1.93E+ 05 0.00E + 00 3.01E+05 %0.00E400 3.10E + 06 FE 3.27E + 05 2.26E + 05 5.26E + 04 0.00E + 00 0.0054,00,126E + 05 1.30E + 05
| |
| -..-59 ...... __ . 3.87E
| |
| .. _. . ..+ __..
| |
| 05 9.0 l
| |
| l 9E.....
| |
| + 05......_3.48E + 05 0.00E + 00 CO-58 _ _ ..... .. _0.00E4'__. 00... 2.54E + 05 3.03E +__..
| |
| __ ....___..... 06 l CO.00 0.00E + 00 5.66E + 05 1.27E 406 0.00E + 00 .e0,00E+00> 0.00E + 00 1.15E +07 Nt63 0.00E + 00 1.97E + 06 4.35E + 06 0.00E+00, 'O.00ET00 0.00E + 00 3.70E + 07 8.08E + 08 5.
| |
| ...... ........__..60E+07 2.71 E+ 07 0.00E + 0
| |
| ...__. . .. .. _ _. ......_ _.0 %__0.00E + 00. . ....__0.00E + 00 1.17E + 07 ZN-65 .
| |
| ........ __...__ .. i 3
| |
| RB.86 1.65E + 08 5.24E + 08 2.37E + 08 0.00E + 00 3.51 E + 08 0.00E + 00 3.30E + 08 -
| |
| SR 0.00E 3.05E + 09 + 00 3.12E + 08 1.45E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.14E + 07 0.00E + 00
| |
| __.-89...... ........ ..... ... 0.76E + 07 +0.00E
| |
| ..... ., +
| |
| ... 00 0.00E + 00 0.00E + 00 4.89E + 08 SR-90 -= -_-_-_.._______
| |
| l Y-91 9.84E + 10 0.00E + 00 2.41E 1010.00E400 0.00E + 00 0.00E+00 2.84E+ 09 l ZR-95 1.03E + 03 0.00E +200 2.76E 0_0)J4 .00E+00 0.00E + 00 0.00E+ 00 5 68E + 05 '
| |
| NB 95
| |
| ........___.........01 1.13E + 02 3.63E +
| |
| 48
| |
| ___E.+ 01 0.00E 4 00_ .. .......... 0.00E + 00 1.15E++ 01........
| |
| ........ 5.70E ... ....
| |
| 05 9.92E + 03 5.52E+ 03 j2.97E +p3 0.00E + 00 5.45E+ 03 0.00E + 00 3.35E + 07 RU-103 RU 106 1.22E 03 2.45E+ + 02 0.00E+00I $47Ef 01 0.00E4 00 4.67E4 02 0.00E + 00 1.43E + 04
| |
| .........__ __... .._....0.00 .E4 .00.. .. 3.10E
| |
| .. . . _ +_ O2 0.00E + 00 4.
| |
| ... _...... .. . . . 73 E...- + 03 0.00E '
| |
| AG-110M - =+ 00 1.59E + 05 6.99E + 06 6,47E+ 06 ''3.84E+ 06 0.00E + 00 1.27E + 07 0.00E+ 00 2.64E + 09 TE-125M TE 1.96E 5.50E + 06 7'.09EIO5 2.62E +
| |
| + 0%J.,.97E.t._D_B 05 5.89E + 05 7.96E + 06 0.00E + 00 7.81 E + 06
| |
| ..127M
| |
| .. ... .. ....6 6.70E + 05 1.41 2.23E + 07 0.00 TE.129M
| |
| _ ._ . . .. .. _ _ . ..E ...
| |
| + 06 .___.. ..... . . . ...E 4....
| |
| 00 1.84E + 07 7.23E + 06p l131 3.56E 08' p.70E+06 1.14E + 06 2.48E + 06 3.02E4 07 0.00E + 00 3.64E + 07 t
| |
| l133 5D9E +08 2.92E+ 08 1.67E + 11 8.73E + 08 0.00E + 00 1.34E + 08
| |
| ....__..___.....6,4.65E + 0
| |
| ___...8.10E.. + 06 2.47E
| |
| .... + 06 1.19
| |
| .... .....E+09.... 1.41 E + 07 0.00E + 00 7.28E + 06 CS-134 =
| |
| CS 136 1.70E + 10 4.04E + 10 3.30E + 10 0.00E + 00 1.31 E + 10 4.34E7.07E+ + 09 08 7.92E +
| |
| 2.22E+ 1008 3.03.13E + 1.99E 09 2.25E + 09 0.00E + 00 1.74E + 09 2.38E + 08 3.55E + 08
| |
| _CS .137
| |
| __. ..... ......_____..3E+10 + 10 0.00E + 00 3.42E + 09 5.87E +
| |
| BA-140
| |
| .. . ..._ _ .. . _ _ _ _ . .__ _ _ _.. . _1.03 _... E ___+ 10 .........._____...08 ...
| |
| I CE-141 3.24E4 06 4.07E + 03 2.12E + 05 0.00E + 00 1.38E + 03 2.33E+03 6.67E + 06 CE-144 5.82E 4.30E + 04 + 02 1.83.94E + O2 4.47E + 01 0.00E400 1.83E4 02 0.00E + 00 t.51E + 06
| |
| ...... .. . .. ..... . . . . 0E +....._. 04 2.31 E + 03 0.00E + 00
| |
| ....... .....__..__.07E+04 1. 0.00E + 00 1.45E + 07 PR-143 . L90E + 01 7.60E + 00 ..__.. ......... ..........
| |
| 9.40e-01 ND 147 1.13E + 01 1.31E +
| |
| 0.00E+ 00 4.39E + 00 0.00E 4 00 8.30E + 04
| |
| ........ ......... .......01.........__..........E+00 7.82e 01 0.00E + 00 7.65 0.00E 4 00 6.28E + 04
| |
| .... ......... -==....
| |
| 149 0 me t - - . - - -. -.
| |
| 1
| |
| [
| |
| | |
| c Number
| |
| 'juClear M Radidogd Connds Departmental Procedure 6610-PLN-4200.01 Me F4evision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.6.1 Pathway Dose Factors, RI AG
| |
| .__..___... -_......_ _E _G. ROUP:
| |
| . . . .. INFANT PATHWAY:__GRASS . .. COW ._
| |
| . . .MEAT NUCUDE
| |
| - - - -BONE UVER T.80DY THYROID KIDNEY LUNG
| |
| ~~ GhLU 53 C-14 b E d+~bb~b 5d+~0b b 5d+~b'O~ bed +~b0 b.00E+~0b b 5d ~0b b 5 d CR-51 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 #0.00E4 00 0.00E + 00 MN-54 FE-55 0.00E + 00 0 DOE + 00 0.00E+ 00 0.00E + 00 0.00E+00 i!!(0.00E$00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E400g ~0.00E + 00 0.00E + 00 FE-59 j
| |
| ~~
| |
| 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E400 0.00E + 00 0.00E + 00
| |
| ~
| |
| ~bi5~58 UEd+~0b UIO0E4bb~b.50E+000 00E + 00 .0.00Et.00% 0.00E + 00 0.00E+ 00 CO-60 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E+ 00, 'O.00E+00 0.00E + 00 0.00E + 00 NI63
| |
| .....___...__0.00E + 00 0.00E + 00 0.00E + 00 _ _ . . . _ _ _ _ 0.00 0.00E +
| |
| ZN-65 ...___ _ ___ _..__ _..__...... _ __0.00 E + 00 %_0. 00E + 00___ ... .... E + 00
| |
| .___.....00__
| |
| RB46 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E + 00 0.00E + 00 SR49 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E 4 00 0.0
| |
| ..... ....__...___..__ __.... .. _ _ _0E + 00 4 0.00.E
| |
| _... - ... +..__
| |
| 00 0.00E + 00 0.00E+ 00
| |
| ....._____.......... .......... 0.00E+ 00 SR-90 0.00E + 00 0.00E + 00 0.00Ef 00j 0.00E400 0.00E + 00 0.00E + 00 0.00E + 00 Y 91 ZR-95 0.00E+ 00 0.00E+ 00 0.00E(0 PAG.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00
| |
| ~~~ 0.00E + 00 0.00E ~~
| |
| + 00 0,00Ef00,. 0.00E ~
| |
| + 00 0.00E + 00 0.00E + 00 0.00E+ 00 5B-95 ~
| |
| RU 103 UEd+~00~~b5E+0b~~hEdkO~b.~00EIb0 b E d+~bb b.E EIbb ~ b.~00EIbb~
| |
| 0.00E + 00 0.00E + 00' 0,00Ef00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 RU-106 0.00E + 00 0.00E+00. 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 AG-110M 0.00E + 00 0,.00E+ 00 "0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 TE-125M TE.127M 0.00E + 00 0.00ETOO 0.00E + 00 0.00E + 00 0.00E + 00 0.00E 4 00 0.00E + 00 0.00E + 00 %D.00E *00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 iE.129M~b55 I-131 bOh5d ~00~~b5d bb b50E+~00~~b50E+~b~0~b5d~00~~b50E b~
| |
| 1-133 0.00Et D0 D.00E +00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00, 0.00E + 00 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E4 00
| |
| ~ ~
| |
| ~b'SSI'34'~~~b50E+~0b~bE0E+b'O CS-136
| |
| ~ bed b~0 b.~00E+~5 BIO 0E+00 bE bb~ be CS 137 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0. 0.00E + 00.<....._..
| |
| 0.00E + 00.........
| |
| 0.00E + 00 0.00E
| |
| ....... ... . .. ... . . ._.. . .. ... _ ._00 E......
| |
| + 00 ......... ......+.00 BA-140 ..
| |
| CE-141 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CE-144 0.00E + 00 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 PR-143 ND-147 0.00E + 00 0.00E b0 0.00I+~bb bed bb~b50EIbb~550dIbb bed bb 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 150.0 me
| |
| | |
| Number (ggy TMl Radiological Controls Departmental Procedure M8 6610-PLN-4200.01 Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.6.2 Pathway Dose Factors, R1 AGE CHILD PATHWAY: GRA
| |
| ........... ..._ _..... .G R. OU .... .P:.____ __ _... .._. .__ __... .S S.__ COW-M EAT NUCUDE ----- -----.- ORGAN - - - DOSE
| |
| - - - . - -FACTORS;
| |
| . . . . . . - - . . m'.
| |
| . . -mrem-........_...
| |
| / year per pCl/.sec ..... - .........
| |
| BONE UVER T H-3 BODY THYROID K!DNEY
| |
| .......___.....__.......,__..____.....__-LU LUNG GI C-14 0.00E + 00 2.34E + O2 2.34E + O2 2.34E + O2 2.34E + O2 2.34E + 02 2.34E + 02 CR 51 3.84E + 08 7.67E+ 07 7.67E + 07 7.67E + 07 7.67E + 07 7.67E + 07 7.67E + 07 0.00E 4 0
| |
| ..__...___..__.0 0.00E + 00 8.78E + 03 4.88E +
| |
| ........._......___ __....... 03 _1.33E + 03 4 8.90E + 03 4.66E + 05 MN-54 FE-55 0.00E + 00 8.01E + 06 2.13E + 06 0.00E + 00 2.25E+,06 ii(~0.00E)00 6.73E + 06 4.57E + 08 2.43E + 08 7.52E + 07 0.00E + 00 0.00E (00, 1.37E + 08 4.49E + 07 FE-59 3.77E + 08 6.10E + L'
| |
| ~ ~ ~" 3.04E + 08 0.00E + 00 0.00E+00 1.77E + 08 6.35E + 08
| |
| ~~ ~
| |
| Ci558 b50E+~00 C040 N163 0.00E + 00 2.91E + 10 1 EE + 0E'5.03E+"0E~b 6.93E + 07 2.04E + 08 0.00E + 00, 0.00E +~00E+~Ib]A00E 00 3.84E + 08 +
| |
| ...__. . ........ 1.56E + 09........ 9.91 E + 08........_.0.00E ........ + 00%.___.__...
| |
| ....... 0 00E + 00 0.00E + 00 1.05E + 08 ZN-65 3.76E + 08 1.00E + 09 6.22E + 08 000E+00 6.3:E+08 0.00E + 00 1.76E + 08 '
| |
| RB46 0.00E + 00 5.76E + 08 3.54E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.71E + 07 SR-89 4.82E + 08 0.00E + 00 1.38E+ 07 e
| |
| .. ....... . . . . .. .. . . .. .... .. . . . . . . .. n.0.00.E .. + 00 ....0.00E
| |
| ... ..... + 00 -- 0.00E
| |
| _---- .+ 00 1.87E + 07
| |
| .. ...... i SR-90 1.04E + 10 0.00E + 00 2.64E7 09j 0.00E400 0.00E + 00 0.00E + 00 1.40E + 08 Y-91 )
| |
| 1.80E + 06 0.00E + 00 4.82E40Pa00E4 00 0.00E + 00 0.00E + 00 2.40E + 08 ZR 2.66E + 06 5.86E + 05
| |
| - -.-95 ...... ....... ........_ _. 5 21....... E.4 05 0.00E 4 00 8.38E + 05 0.00E + 00 6.11E + 08 NB-95 3.10E + 06 1.21 E + 06. [B.63E + 05 0.00E + 00 1.13E + 06 0.00E + 00 2.23E + 09
| |
| )
| |
| RU-103 1.55E + 08 0.00E +gD0 5.96E#07 0.00E + 00 3.90E + 08 0.00E + 00 4.01E + 09 RU-106 4.44E + 09 0.00
| |
| ...._..__ __....___...E4 00m. ..... 5.54E 4___......_
| |
| ......__ 08 0.00E __...... + 00 6.00E .___+ ....
| |
| 09 0.00E+
| |
| .......... 00 6.91 E + 10 AG-110M 8.39E + 06 5.67E + 06 +4.53E + 06 0.00E+ 00 1.06E + 07 0.00E + 00 6.74E + 08 TE 125M 5.69E + 08 iS4EYOB 7.59E + 07 1.60E + 08 0.00E + 00 0.00E + 00 5.49E+08 TE-127M 1.78E + 0
| |
| __....__...... 9 %A . ..78.E.tn8 2.11 E + 08 4.25E + 08 5.06E + 09 0.00E + 00 1.44E + 09
| |
| __ __....... ......_.. ....._..= - - - - = =.....
| |
| TE-129M 1.795 + 09A,5.00E+ 08 2.78E + 08 5.77E + 08 5.26E + 09 0.00E + 00 2.18E + 09 l131 1.66Et07 167E +07 9.48E + 06 5.52E + 09 2.74E + 07 0.00E + 00 1.48E + 06 l133 2.68e 01
| |
| ....... .._. 5.72eb1 CS-134
| |
| .__..__..........___..........................5e.01
| |
| ....... . 7.08e .01 1.31 E + 02 1.18E + 00 0.00E + 00 2.8 9.23E + 08 1.51E + 09 3.19E + 08 0.00E + 00 4.69E + 08 1.68E + 08 8.16E + 06 CS-136 1.63E + 07 4.48E+ 07 2.90E4 07 0.00E + 00 2.39E + 07 3.56E + 06 1.57E + 06 CS 137 1.33E + 09 1.28E + 09 1.89E + 0
| |
| .___......__...............__........8 0.00
| |
| . .....E + 00 4.16E
| |
| ..._ + 08 1.50E
| |
| ___...- - _.+ 08 8.00E......___+ 06 BA-140 4.42E + 07 3.87E + 04 2.58E + 06 0.00E + 00 1.26E + 04 2.31 E + 04 2.24E + 07 CE-141 2.22E + 04 1.11E + 04 1.65E + 03 0.00E + 00 4.86E + 03 0.00E + 00 1.38E 4 07 l CE-144 2.32E + 06 7.26E 4 05 1.24E+ 05 0.00E + 00 4.02E + 05 0.00E + 00 1.89E + 08
| |
| ~ ~ ~
| |
| Eik~3
| |
| ~
| |
| 5.53E b4~~EE 1 + b~4~~'ESE+~b'3~b.~00EIbb~5.~42E+~b'3~b5E 1 bb~5560E+0E l ND-147 1.17E + 04 9.48E + 03 7.34E + 02 0.00E + 00 5.
| |
| ...........__.............___...._____.........____20E+03 0.00E + 00 1.50E + 07
| |
| ...... __ ....= ...__..
| |
| 151.0 mm
| |
| | |
| I gggy TMI Radiological Controls Departmental Procedure Number True 6610-PLN.4200.01 nem.on re.
| |
| Offstte Dose Calculation Manual (ODCM) 12 TABLE 5.6.3 Pathway Dose Factors, R1
| |
| ........__........___ AGE GROUP:
| |
| ___=
| |
| TEEN PATHWAY: GRASS COW-MEAT ORGAN DOSE FAC NUCUDE ---------------------..--.--. TORS; m'.. mrem / year per pCl/_sec BONE UVER KIDNEY
| |
| . . . . .. . _ _ ... _ _.. . . . . .T..... B O ._.......-
| |
| DY THYROtD LUNG GI H-3 ....__.__.__....__......-LLI .__
| |
| C 14 0.00E + 00 1.93E + 02 1.93E + 02 1.93E + 02 1.93E + 02 1.93E + 02 1.93E + 02 CR-51 2.04E + 08 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07
| |
| ~ ~~ 0.00E + 00 0.00E~~+ 00 5.63E
| |
| ~~ + 03 3.13E ~~ + 03 1.23E+ 03 / 8.03E+ 03 9.46E + 05 5t 54 ~' ~ ~~ '~~~~~'
| |
| FE-55 UEE+ 00 FEE + i[~I.~39E75~b 5E + 05~~2.bE{b~63~ BIO 0El+ ib~~
| |
| 2.38E + 08 1.69E + 08 3.94E+ 07 0.00E + 00 0.00E 40Q, '1.07E + 08 7.31 E + 07 FE-59 2.12E + 0B 4.95E + 08 1.91E + 08 0.00E + 00 0.00E4 00 1.56E + 08 1.17E + 09 CO 58 0.00E + 00 1.40E + 07 3.24 E + 07 0.00E + 00 9 .,00Et 0 00 0.00E 4 00 1.94E + 08 CO 60 s 0.00E 1.
| |
| 4 00 5.83E + 07 1.31 E + 08 0.00E + 00 " 0.00E400 0.00E + 00 7.60E + 08 1.
| |
| NI63........ ____52E + 10.__..___ __07E 0.00E + +09____
| |
| 00M.00E ._
| |
| ~.....__5.15E
| |
| + 00 0.00E +
| |
| .__.___.. 4 0008__..___.
| |
| 1.71 E + 08 ZN45 RB 80 2.50E + 08 8.68E + 08 4.05E + 08 0 00E+00 S.56E + 08 0.00E + 00 3.68E +08 S 0.00E + 00 4.06E + 08 1.91E + 08 0.'00E + 00 0.00E + 00 0.00E + 00 6.00E + 07
| |
| ...R..89... 2.55E 408 0.00E + 00 7.29E + 06 *0.00 E + 00 0.00E + 00 0.00E + 00 3.03E + 07 SR-90 Y-91 8.04E + 09 0.00E + 00 1.99Ef09) 0.00E400 0.00E + 00 0.00E+ 00 2.26E4 08 9.54E + 05 0.00E + 00 2.56Et 04Wo40E+00 0.00E+ 00 0.00E + 00 3.91E + 08
| |
| .ZR-95 1.50E + 06 4.73E + 05 3.25
| |
| __.......___.............____...E/05. . . 0.00E + 00........ 6.95
| |
| .....E405 0.00E + 0
| |
| ______...... 0 1.09E + 09 NB-95 RU-103 1.79E + 06 9.95E+05 (5.48E@5 0.00E + 00 9.64E + 05 C.00E + 00 4.25E + 09 RU-106 8.56E + 07 0.00E t 00 '3.66Eio7 0.00E4 00 3.02E + 08 0.00E + 00 7.15E + 09
| |
| ........ ._____... 2.36E +0.00E4 09 00s,.2.97E + 08 0.00E + 00 4.54E + 09 0.00E + 00 1.13E + 11 AG-110M ......__ ....__... ........__..___.... ..........
| |
| TE 125M 5.06E+06 4.78E106 *2.91E+06 0.00E + 00 9.13E + 06 0.00E + 00 1.34E + 09 TE 3.03E + 08 LOSEV06 4.05E4 07 8.46E + 07 0.00E + 00 0.00E + 00 8.94E + 08 9.41E +
| |
| ....-127M
| |
| ......__...... 08 %3.34.E.t
| |
| -. 081,12E + 08 2.24E
| |
| ..___..__... ......... + 08 3.81 E + 09 0.00E + 0
| |
| ....__.___ ..... .0 2.35E + 09 TE 129M 9.49E+ 08A 3.52E + 08 1.50E + 08 3.06E+ 08 3.97E + 09 0.00E + 00 3.56E + 09 l-131 8.93EtD6' '"i.25E+07 6.72E + 06 3.65E + 09 2.15E + 07 0.00E + 00 2.47E + 06 l133 3.00e!0
| |
| .............1.
| |
| CS-134
| |
| -...............41 5.228 01 1.59e 7.29E + 01 9.16e 01 0.00E + 00
| |
| . . - . . . . . . . . . . . . . . . . . . . . . . . . . . . = = 3.950-01
| |
| - ==
| |
| CS-136 5.23E + 08 1.23E + 09 5.71E + 08 0.00E + 00 3.91 E + 08 1.49E + 08 1.53E + 07 CS 137 9.43E + 06 3.71E + 07 2.49E + 07 0.00E + 00 2.02E + 07 3.18E + 06 2.99E + 06 7.24E 4 08 9.63E + 08 3.35E + 08 0.00E + 0 3.28E + 08 1.27E + 08 1.37E + 07
| |
| ___......................-. =-- .. ____....0 ....__...-......... ....___...
| |
| BA-140 2.39E + 07 2.93E + 04 1.54E + 06 0.00E 4 00 9.94E + 03 1.97E ,04 3.69E + 07 CE 141 1.18E + 04 7.87E + 03 9.05E4 02 0.00E + 00 3.71E + 03 0.00E+ 00 2.25E4 07 CE 144 1.23E + 06 5.0BE + 05 6.60E + 04 0.00E + 00 3.03E + 05 0.00E + 00 3.09E + 08 PR 143 1.76E + 04 7.03E + 03 8.76E + 02 0.00E + 00 4.08E + 03 0.00E + 00 5.79E + 07 ND 147
| |
| . . . . . . . . . .6.23E
| |
| . . . . . .+-03
| |
| - . .6.78E
| |
| . . . . .+. _03_ 4.06E
| |
| .- + O2 0.00E + 00 3.98E + 03 0.00E + 00 2.44E+ 07 152.0 mm l
| |
| I
| |
| | |
| Number
| |
| -(UOleer M Radiological Controls Departmental Procadm 6610-PLN_4200.01 hue Hovtsson No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.6.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS
| |
| __..........__....___..__....__.............___.._.__-COW-MEAT _...____..._____________ _
| |
| NUCUDE ------------- ORGAN DOSE FACTORS; m' --mrem=/ -year per pCl/sec l
| |
| BONE
| |
| ..........................._................_.............UNG__
| |
| H-3 LIVER T. BODY THYROID KIDNEY L GI
| |
| _ _ _ ....-LLI 0.00E + 00 3.24E + 02 3.24E + 02 3.24E + 02 3.24E + 02 3.24E + 02 3.24E 4 02 C-14 2.42E + 08 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 CR 51 0.00E + 00 0.00E + 00 7.04E + 03 4.21 E + 03 1.55E + 03 j B'.35E+ 03 1.77E + 06 MN-54 0.00E + 00 9.18E + 06 1.75E + 06 0.00E + 00 2.73E4 06 il 0.00Eg 00 2.81 E + 07 FE-55 2.93E + 08 2.03E + 08 4.73E + 07 0.00E + 00 0.00E+ 00,1!'13E+ 08 1.16E + 08 FE -59
| |
| . ..__ 2.66E .._____ + 08 6.25E +
| |
| .._____.. 08 2.39E + 08 0.00E... +
| |
| ........._______. 00 0.00.E40.0
| |
| .. ,__..___... ..__...... 1.75E + 08 2.08E + 09 ;
| |
| CO-58 0.00E + 00 1.82E + 07 4.09E + 07 0.00E + 00 #000Et004 0.00E+00 3.70E + 08 j CO-60 0.00E + 00 7.52E + 07 1.66E + 08 0.00E+00 "D.00E400 0.00E + 00 1.41 E + 09 Nl.63 1.89E + 10 1.31 E + 09 6.33E + 08 0.00E+ 00%0.00E+ 00 0.00E ~~+ 00 2.73E + 08
| |
| ~ ~~ ~ ~~ ~~~~ ~~ '
| |
| ~Ei[b~5 3.5iEi+~b'8 1.13E + 09 5.12E + 08 b.00Elbb~~f."S7E+b~8~b5E+bb f.13E+b8 RB-86 0.00E + 00 4.87E + 08 2.27E + 08 0.00E + 00 0.00E + 00 0.00E + 00 9.59E + 07 ;
| |
| SR-89 3.02E + 08 0.00E + 00 8.66E + 06 4 0.00E + 00 0.00E + 00 0.00E + 00 4.84E + 07 I
| |
| ~
| |
| l SR 90 1.24E + 10 0.00E + 00 3.05Ef 09 0.00E400 0.00E + 00 0.00E + 00 3.60E + 08 3.03E 404]RO.00E 0.00E ++00 Y-91 1.13E + 06 0.00E + 00 00 0.00E + 00 6.24E + 08 ZR-95 1.87E + 06 6.01 E + 05
| |
| ..__..._____......_ 4. 07E e.06
| |
| .... . 0.00E + 00 9.43E
| |
| ....... + 05 0.00E
| |
| _==....- + 00
| |
| _....... 1.90E + 09 NB-95 -.30E+06 2 1.28E + 06 !6.87E + 05 0.00E + 00 1.26E + OS 0.00E+00 7.76E + 09 RU-103 1.05E + 08 0.00E 4 00" 153E407 0.00E + 00 4.02E + 08 0.00E + 00 1.23E + 10 RU 106 2.80E + 09 0.00Ef00, 3.54E 4 08 5.41 E + 09 0.00E + 00 1.81 E + 11
| |
| ... ..____... _ _. .._ _.. ._ _... . . . .. _ _ . .. 0.00 E + 00 AG-110M 6.68E + 06 6.18Etp6 "3.67E + 06 0.0CE + 00 1.22E + 07 0.00E + 00 2.52E + 09 TE.125M 3 59E + 08 C30E708 4.81 E + 07 '08E+08 1.46E + 09 0.00E + 00 1.43E + 09 i TE-127M 1.12E + 00. $3_,99E r.08 1.36E + 08 2.85E + 08 4.53E + 09 0.00E + 00 3.74E + 09 I TE-129M 1.13E+ 09)y.23E+ 08 1.79E + 08 3.89E+ 08 4.73E + 09 0.00E + 00 5.71 E + 09 l l-131 1.08Eic7 IiS4E + 07 8.82E + 06 5.04E + 09 2.64E + 07 0.00E + 00 4.06E + 06 l133 3.68e 1.958 9.42E + 01 1.12E + 00 0.00E + 00 5 76e 01
| |
| .......... .......h..-_ _6.41 e 01_......____...-01 .. ..____... ......... __-_..._... ___._
| |
| CS-134 6.58E + 08 1.57E + 09 1.28E + 09 0.00E + 00 5.07E + 08 1.68E + 08 2.74E + 07 ,
| |
| CS-136 1.21 E + 07 4.78E + 07 3.44E + 07 0.00E + 00 2.66E + 07 3.65E + 06 5.43E + 06 CS 137 8.72E + 08 1.19E + 09 7.82E + 08 0.00E + 00 4.05E 4 08 1.35E + 08 2.31E + 07
| |
| =.... - .._ _- _ .._______
| |
| BA-140 2.90E + 07 3.64E + 04 1.90E + 06 0.00E + 00 1.24E + 04 2.08E + 04 5.96E + 07 CE-141 1.41 E + 04 9.51E + 03 1.08E + 03 0.00E + 00 4.42E + 03 0.00E + 00 3.64E + 07 CE 144 1.46E + 06 6.10E + 05 7.83E + 04 0.00E +
| |
| ...... __. .....___......___.__....____ .......00 3.62E + 05 0.00E + 00 4.93E + 08 PR-143 2.09E + 04 8.40E + 03 1.04E + 03 0.00E+ 00 4.85E+ 03 0.00E + 00 9.17E + 07 ND..- 147 7.08E + 03 8.18E + 03 4.90E + 02 0.00E + 00 4.78E + 03 0.00E + 00 3.93E + 07 l
| |
| 153.0 me i -- .. ., . . .
| |
| | |
| 1 Numtm
| |
| -gdgy TMI Radiological Controls Departmental Procedure I htle 6610-PLN-4200.01 Hovision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.7.1 Pathway Dose Factors, RI
| |
| _...____.. AGE GROUP:
| |
| INFANT PATHWAY: VEGETATION NUCUDE BONE UV
| |
| ............._______.......ER T. BODY THYROID
| |
| .__....__...__......._...........__ KIDNEY LUNG G1-LLI H-3 ...._.
| |
| C-14 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 0.00E 00 - _- ....
| |
| + 00 CR-51 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 MN-54 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 $00Et00 0.00E + 00 FE-55 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 N0.00EJ00 0.00E + 00 '
| |
| 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E(00p 0:00E+00 0.00E + 00 FE..-59 0.00E + 00 0.00E + 00 0.00E + 00 0 00E+ 00 0.0 CO-58
| |
| __.______....._........___........... ...__..___._0.E%0_0 0.00E +
| |
| ... _____...._ ..00 0.00E + 00 CO-60 0.00E + 00 0.00E + 00 0.00E + 00 0.00E #+ 00 0.00E+00& 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00, 'O.00El 00 0.00E + 00 0.00E + 00 l NI.63 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 %D.00E+ 00 0.00E 4 00 0.00E + 00 ZN-65 RB-86 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 SR-89 0.00E4 0.00E + 00 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00
| |
| ____........_........,.-.....E+00 0.00E + 00 0 00E+00 40.00 0.00E + 00 0.00E + 00 0.00E + 00 SR-90 0.00E + 00 0.00E + 00 Y-91 0.00E400 0.00E + 00 0.00E + 00 0.00E 4 00 ZR-95 0.00E + 00 0.00E + 00 0.00E(90 0.00E400}F0.00E+00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E t 00 r, 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 NB-95 0.00E + 00 0.00E + 00, D.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E + 00 RU-103 RU-106 0.00E + 00 0.00E + 00' O.00E4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 I 0.00E + 00 0.00E400 AG-110M
| |
| ........._w__.......0.00E + 00
| |
| ............................0E+00 0.00E + 00 0.00E+ 00 0.00E + 00 0.0 TE-125M 0.00E + 00 0.00E+ 00 ' O.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 O!
| |
| 0.00E + 00 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 TE-127M 0.00E+00 0 00Et064 .00EiOO00.E + 00 0.00E + 00 0.00
| |
| _ _ . . . . . . . . . . . . . . . . . . . . _ _ . . . . .0......._._....___.....E+00 0.00E + 00 0.00E + 00 TE-129M ... .___......._.......__.
| |
| 0.00Eb 00)0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 l-131 l 1-133 0.00E+ 00" 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 !
| |
| 0.00E + 00 0.00E +______.... 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +
| |
| ..__....__........__..............__00..
| |
| CS 134 CS-136 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CS 137 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00......- 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00 BA-140
| |
| ....._.........-.........---E+00_ ---
| |
| CE-141 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E4 00 0.00E4 00 0.00E+ 00 CE-144 0.00E + 00 0.00E + 00 0.00E 4 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 PR-143 ND-147 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E 4 00 154.0 mm 9
| |
| e=>* gies.m.e .e. 6
| |
| **4*4 - *'$*
| |
| | |
| r gggp TMl Radiological Controls Departmental Procedure Number Titie 6610-PLN-4200.01 aman No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.7.2 Pathway Dose Factors, RI
| |
| -__ ...... .......... ...AGE ROUP;G CHILD
| |
| . PATHWAY: VEGETATION NUCUDE
| |
| - - - -BONE
| |
| - - - - - - - - -LfVER
| |
| ...- _... T. BODY THYR KIDNEY LUNG H-3
| |
| .....-........._......OtD......................__......LLI G1-C-14 0.00E + 00 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 8.89E + 08 1.78E + 08 1.78E + 08 1.78E + 08 1.78E 4 08 1,78E + 08 1.78E + 08 CR-51 0.00E + 00 0.00E + 00 1.17E + 05 6.49E + 04 1.77E+04 /13BE+05 6.20E + 06 MN-54 FE-55 0.00E + 00 6.65E + 08 1.77E + 08 0.00E + 00 1.86E+p8 (0.00E400 5.58E + 08 FE- 8.01E+ 08 4.25E + 08 1.32E + 08 0.00E + 00 0.0054003 2.40E + 08 7.87E + 07
| |
| -_.59 3.98E + 08 6.44E + 08
| |
| ...... . .. . .. .. . .. . _ _... . _ __213. E + 08 0.00E + 00 0.00E4
| |
| ..........________.._.0,0 1.87E + 08 6.71 E + 08 CO-58 0.00E + 00 6.44E + 07 1.97E + 08 0.00E + 00 ,0.00E+:000 0.00E+00 3.76E + 08 CO-60 NI63 0.00E + 00 3.78E + 08 1.12E + 09 0.00E+00 'O.00E400 0.00E + 00 2.10E + 09 3.95E + 10 2.11E + 09 0.00E + 00
| |
| ....._ __.. ... . _ _ _ . . ..._ _ _ _ .1.34....__. E + 09 ....__..._\0 00E + 00 0.00E+ 00 1.42E + 08 7N-65 . _ _ _ . . _ _ _ . . . . . . _ - _ _ _ - - - -
| |
| RB-86 8.12E + 08 2.16E + 09 1.35E + 09 0 00E + 00 1236E + 09 0.00E + 00 3.80E + 08 SR-89 0.00E + 00 4.51E + 08 2.77E + 08 0.00E+ 00 0.00E+ 00 0.00E + 00 2.90E + 07 3.60E + 10 0.00E + 00 1.03E+09 *0.00E+ 00 0.00E===+ 00 0.00E+ 00 1.39E+ 09 SR-90 ....__ ........
| |
| 1.24E + 12 0.00E + 00 Y-91 3.15E. 11 0.00E400 0.00E + 00 0.00E + 00 1.67E + 10 ZR 1.87E + 07 0.00E + 00 4.99E . 05]"#0.00E 0.00E + + 00 00 0.00E + 00 2.49E + 09
| |
| ....-95 3.86E 4 06 8.48E + 05 0.00E + 00 1.21E + 06 0.00E + 00 8.85E + 0 NB-95
| |
| ...... . ..__. ___....__... .L.55E. .f..b6._ . . . . ...__... . .......__... ...
| |
| 4.11 E + 05 1.60E + 05 $.14E+p5 0.00E + 00 1.50E+ 05 0.00E + 00 2.96E+ 08
| |
| ........8 .
| |
| RU-103 1.53E + 07 0.00E +po# 5.90Et06 0.00E + 00 3.86E + 07 0.00E + 00 3.97E + 08 RU-106 7.45E + 08 0.00E400w 9.30E+07 0.00E + 00 1.01 E + 09 ~~~
| |
| 0.00E + 00 1.16E + 10 AG-110M ~' ~~
| |
| TE 125M 3.21E + 07 217E s + 07 *1.73E+07 0.00E + 00 4.04E + 07~b.~00E [2.58E 09 TE-127M 3.51E 1.32
| |
| + 08 9.50Eib7 4.67E + 07 9.84E+07 0.00E + 00 0.00E+ 00 3.38E + 08
| |
| .. ..__..._.__..E + 09. %356E.+.
| |
| .... ... 1.57E 08 + 08 3.16E + 08 3.77E+ 09 1.07E+ 0 TE-129M . __ . _ _ _. .. . .. . ... . _ _ _.. .. . _ _. . . 0.00E + 00.__....___.......9 l-131 8.40E + 08N.35E + 08 1.30E + 08 2.71 E + 08 2.47E + 09 0.00E + 00 1.02E + 09.
| |
| l133 1.43E + 08" t44E+08 8.18E4 07 4.76E + 10 2.36E + 08 0.00E + 00 1.28E + 07 3.53E +6.,0 4.37E + 06
| |
| ..... ... .. .....1.65E
| |
| ... ...+ ....
| |
| 06 8.12E + 08 7.28 E + 06........ 0.00E + 00 1.76E + 06 CS-134 ........-....._...
| |
| I CS-136 1.60E + 10 2.63E + 10 5.55E + 09 0.00E + 00 8.15E + 09 2.93E + 09 1.42E + 08 ;
| |
| 8.28E 2.
| |
| + 07 2.28E + 08 1.47E + 08 0.00E + 00 1.21E + 08 1.81E + 07 8.00E + 06 2.29E + 10 3.38 CS 137..._._..
| |
| BA-140
| |
| ..............__.._.E+09
| |
| .39E+10 0.00E + 00 7.46E + 09 2.68E + 09 1.43E +
| |
| ... .-__......__........ .........._.... ..08 ..
| |
| CE-141 2.79E + 08 2.44E + 05 1.63E + 07 0.00E4 00 7.96E + 04 1.46E + 05 1.41 E+ 08 \
| |
| i CE 144 6.57E + 05 3.28E + 05 4.86E + 04 0.00E + 00 1.44E + 05 0.00E 4 00 4.09E + 08 1.27E + 08 3.99E + 07 6.7
| |
| ........ . ....... ....__...__..9E+06 0.00E + 00 2.21 E + 07 0.00E + 00 1.04E + 10
| |
| ..... . ....... . ........_.......- ........ l PR-143 ,
| |
| ND 147 1.45E + 05 4.36E + 04 7.21E + 03 0.00E + 00 2.36E 4 04 0.00E + 00 1.57E + 08 '
| |
| ..........._.........7.15E + 04....-- 5.79E + 04 4.49E + 03 0.00E + 00 3.18E + 04 0.00E + 00 9.18E + 07
| |
| _ ........._......... ......... ... )
| |
| l l
| |
| I i
| |
| 155.0 mm
| |
| | |
| F l
| |
| Numtcr f
| |
| l GUOle8r TMI Radiological Controls Departmental Procedure 6610~PLN.4200.01 Title Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 TABLE 3.7.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: VEGETATION NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - = = = - = - - . - - - - - - _ - - - - - - - -
| |
| BONE LIVER T. BODY THYROID KIDNEY LUNG GI
| |
| .__...__... . ___... ... .._________.._______...__......__..._________.....-LLI .__
| |
| H-3 0.00E + 00 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 C-14 3.69E + 08 7.38E + 07 7.38E + 07 7.38E + 07 7.38E + 07 7.38E + 07 7.38E + 07 ~
| |
| CR 51 0.00E + 00 0.00E + 00 6.16E + 04 1.35E + 04
| |
| _ . _ _ _... . . . . ... .___.. .. . _ __ _ _ _.3. .. 42 E +_04
| |
| ._ __ ___. . _ _.. 38.79E + 04 1.03 ....___
| |
| . . . . . , . . . E + 07 MN-54 0.00E + 00 4.54E + 08 9.01 E + 07 0.00E + 00 1.36E+98 i[p.00E}00 9.32E + 08 FE-55 3.26E + 08 2.31 E + 08 5.39E + 07 0.00E + 00 0.00F,+ 00 1!47E+ 08 1.00E + 08 dy FE 1.80E + 08 4.19E + 08 1.62E + 08 0.00E + 00 0.00E4 1.32E + 08 9.91 E + 08
| |
| : __..-59.......---..._____.............______.....___...__00 ..__..... ...__ ....
| |
| CO-58 0.00E + 00 4.36E v07 1.01 E + 08 0.00E 4 00#0 700E+00& 0.00E+00 6.01 E + 08 CO-60 0.00E + 00 2.49E + 08 5.60E + 08 0.00E 4 00. ~ 0 00E+ 00 0.00E 4 00 3.24E + 09 NI-63 1.61E + 10 = ....__.. ..... +0.00E + 06% , ..___.
| |
| - ___._......... 1.13E + 09 5.45E 0B ___...... .D 00E + 00 0.00E........
| |
| ..__...____ + 00 1.81 E + 08 ZN-65 4.24E + 08 1.47E + 09 6.86E + 08 0.QOE + 00 9'~42E + 08 0.00E + 00 6.23E + 06 .
| |
| RB-86 0.00E + 00 2.73E + 08 1.28E + 08 0.00E .e 00 0.00E + 00 0.00E + 00 4.04E + 07 SR-89 1.52E + 10 0.00E '+ 00 4.34E + 08 +0.00E + 00 0.00E + 00 0.00E + 00 1.80E + 09 5 90 7.51E 11~'~b5'E'+ 00 1.85E :11? 0.00E+00 0.00E + 00 0.00E + 00 2.11 E + 10 I
| |
| Y 91 7.84E + 06 0.00E + 00 2.10E p5ka.00E+ 00 0.00E + 00 0.00E + 00 3.22E + 09 i ZR-95 1.72E + 06 5.43E + 05 3.73E.(.06..........
| |
| .. . 0.00E+00 ._. .1.98E. .. 0.00E+ 05
| |
| + 00.......
| |
| ........ 1.25E .. + 09 l
| |
| \
| |
| l NS-95 1.92E + 05 1.07E + 05 $.87E + 04 ' O.00E + 00 1.03E + 05 0.00E + 00 4.56E + 08 '
| |
| RU-103 6.82E + 06 0.00E + 00 2.92E #06 0.00E + 00 2.41 E + 07 0.00E + 00 5.70E + 08 RU-106 3.09E + 08 0.00E500s 3.90E+07 0.00E + 00 5.97E + 08 0.00E + 00 1.48E + 10 i AG 110M 1.52E + 07 1,43Et 07 *8.72E + 06 0.00E + 00 2.74E + 07 0.00E + 00 4.03E + 09 i TE 125M 1.48E+08,. SL34E707 1.98E + 07 4.14E + 07 0.00E + 00 0.00E + 00 4.37E + 08 TE 127M 5.52E+0
| |
| .__....... ..___... 8 M_ 96E ._ ..__ t.08.. 6.56E + 07 1.31E + 08 2.24E + 09
| |
| .........._....- - - _ . 0.00E
| |
| ==______... 4 00 1.37E + 09 TE-129M 3.61E + 08%1.34E + 08 5.72E + 07 1.17E + 08 1.51 E + 09 0.00E + 00 1.36E + 09 l l131 7.69Evo7 108E+08 5.78E + 07 3.14E + 10 1.85E+08 0.00E + 00 2.13E + 07 l l133 1.94E +D6, 3.29E + 06 1.00E + 06 4.59E + 08 5.77E + 06 0.00E + 00 2.49E + 06 CS-134 7.10E 4 09 1.67E + 10 7.75E + 09 0.00E + 00 5.31E + 09 2.03E + 09 2.08E + 08 i CS-136 4.39E + 07 1.73E 4 08 1.16E + 08 0.00E + 00 9.41 E + 07 1.48E + 07 1.39E + 07 CS-137 1.01 E + 10 1.35E + 10 4.69E + 09 0.00E + 00 4.SSE + 09 1.78E + 09 1.92E + 08 BA-140 1.39E + 08 1.71 E + 05 8.97E + 06 0.00E + 00 5.78E + 04 1.15E + 05 2.15E + 08 CE-141 2.83E + 05 1.89E + 05 2.17E + 04 0 00E + 00 8.90E + 04 0.00E + 00 5.41E + 08 CE-144 5.28E + 07 2.18E + 07 2.83E + 06 0.00E + 00 1.30E + 07 0.00E + 00 1.33E + 10 PR-143 6.99E + 04 2.79E + 04 3.48E + 03 0.00E + 00 1.62E + 04 0.00E + 00 2.30E + 08 ND 147 3.62E + 04 3.94E + 04 2.36E + 03 0.00E + 00 2.31 E + 04 0.00E + 00 1.42E + 08 156.0 mu
| |
| | |
| Number GMClear M Radidogical Conuds Departmental Procedure Tme 6610-PLN.4200.01 Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 l l
| |
| 1 TABLE 5.7.4 Pathway Dose Factors, Ri A
| |
| . ..... ... ......._.. GE .GROUP:
| |
| . . . . . . _ . _ADULT
| |
| . . . _ = _ _ _ _PATHWAY:
| |
| VEGETATION NUCUDE ------------- ORGAN DOSE FACTORS; m' - mrem / year per pCl/sec l BONE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -=-- - - (
| |
| .. .. ... LIVER . _ _ . . T. BODY THYR
| |
| .._ __.. .. ..... KIDNEY H.3 . ...... . . ... ..OID LUNG
| |
| ... _ _ _ _ _ _. ._ ___ _ __ _ _. . . . .____. . . . .GI-LLI t
| |
| C-14 0.00E + 00 2.26E + 03 2.26E + 03 2.26E + 03 2.26E + 03 2.26E+ 03 2.26E +
| |
| CR 51 2.28E 0.00
| |
| ....E+00
| |
| + 0.00E 08 4.55E + 00 4.64E + 07 + 4.55E + 07 4.55E + 07 4.55E + 07 4.55E + 07 4.55E ) !
| |
| MN-54
| |
| .. . .... ... .......04. .....__..__
| |
| 2.77E + 04 1.02E + 04
| |
| _......../.SI15E ...+_..
| |
| 1.17E+ 07 04 ....__.__.
| |
| FE-55 0.00E + 00 3.13E + 08 5.97E+07 0.00E + 00 9.31E 9.58E + 08 2.10E+ 08 1.45E + 08 3.58E +07 0.00E + 00 0.002"+407h.0.00li+ 00. '"8.08E+07 8.31 E +00 1
| |
| FE-59 07 CO-58 1.26E + 08 2.97E + 08 1.14E +08 0.00E + 00 0.00E+00 = . .....
| |
| 8.29E + 07 9.89E + 0 0.00E+ 00 3.07E + 07 6.89E + 07 CO-60 0.00E+
| |
| NI.63 0.00E + 00 1.67E + 08 3.69E + 08 0.00E + 00 00,46:0,00E+00 0.00E+00 6.23E + 08 00EiOO 0.00E+ 00 3.14E + 09 1.04
| |
| -.. ... ... .. . .E +....
| |
| 10 .... 7.21_E_+ .08 3.49E + 08
| |
| ........___0. ..00E ZN-65 3.17E +08
| |
| + 00%
| |
| ..... 0100.E
| |
| ... .... ......0.00E+00 00 1 .......
| |
| +...___.50E+08 RB 86 1.01E + 09 4.56E+ 08 0,00E + 00 6:75E +08 0.00E +00 6.36E + 08 SR 89 0.00E + 00 2.19E + 08 1.02E + 08 0.'00E + 00 0.00E + 00 0.00E+ 00 4.32E + 0 9.98E +09 0.00E + 00 2.86E + 08 tD.
| |
| SR-90 _ _ ...... _... . _. . . ..__ _ _ __ _ . _ _ .00..E
| |
| ; +0.00E 00 + 00 0.00E + 0 _...__.....
| |
| ...........__.......__0 1.60E + 09 Y-91 6.05E + 11 0.00E + 00 1.48Ep11j 0.00E"+00 0.00E + 00 0.00E + 00 1.75E + 10 ZR 5.12E+ 06 0.00E + 00 1.37EgD5%Da0E+00 0.00E + 00 0.00E + 00 2.82E + 09
| |
| ... -95 1.t 7E + 06 3.77E + 2.55 ;.. . ...E+00 0.00
| |
| __....__...____.._________05 __.#...E.105 5.91E + 05 0.00E + 00 NS-95 1.42E +05 7.92E + 04 4.26 Esp 4
| |
| . .. . ......... ......... 1.19E + 09 _________
| |
| RU-103 4.77E + 06 0.00E t 0d ['2,ppEf06~ 0.00E 4 00 7.83E t 04 0.00E + 00 4.81 E + 08 R 0. 0.00E + 00 1.82E + 07 0.00E4 00 5.57E + 08
| |
| _U .106_ ...1.93E + 0
| |
| ._.........8 .._00E.*. _. 00 2.44E + 07 0.00E + 00 j AG.110M __m _ _. . .... . . ........ 3.72 E + 08... ...... 0.00E
| |
| ... +__. 00 __......
| |
| 1.25E + 10 '
| |
| I TE-125M 1.05E + 07 9.75E + 06 '5.79E + 06 0.00E + 00 1.92E + 07 0.00E + 00 3.98E + 09 TE
| |
| ....-127M 9.66E 3.49E + 08 + 07 @0E407 1.29E + 07 2.90E + 07 3.93E + 08 0.00E + 00 3.86E+ 0 TE.129M
| |
| .__.__....%1.25.E OB. _i_.. .........__......__.....00 4.26E + 1.42E 07........_.8.93E
| |
| + 09 0.00E + +1.17E 07 + 09 l-131 2.51E 8.08Eg97+ 08M.37E 4
| |
| + 07 3.97E + 07 8 63E + 07 1.05E + 09 0.00E + 00 1.26E + 09 1133 2.09E + 0 "1 16E + 08 6.62E + 07 3.79E + 10 1.98E + 08 0.00E + 00 3.05E + 07
| |
| ............__._6 3.63E+ 06 1.11E +
| |
| __....______.......06 6.
| |
| .-.5 34E+ 08. ...... . 33E 0. + 06.. __. .. 00E + 00 3.26E+ 06 CS-134 4.67E + 09 1.11 E+ 10 .... . __........
| |
| CS-136 9.08E+ 09 0.00E + 00 3.59E + 09 1.19E + 09 1.94E + 08 CS-137 4.28E + 07 1.69E + 08 1.22E + 08 0.00E + 00 9.41E + 07 1.29E + 07 1.92E + 07 l BA-140 6.36E + 09 8.70E + 09 5.70E + 09 0.00E + 00 2.95E + 09 9.81E + 08 1.68E + 08 1.29E + 08 CE-141 1.62E+ 05 8.47E + 06 0.00E + 00 5.52E + 04 9.29E + 04 2.66E + 08 CE 144 1.97E + 05 1.33E + 05 1.51E + 04 0.00E + 00 6.20E + 04 0.00E + 00 5.10E+ 08 5 I43 3.29E + 07 1.38E
| |
| ' ~ ~~ ~ + 07 1.77E + 06 0.00E + 00 8.16E + 06 0.00E + 00 1.11E + 10
| |
| ~ ~ ~~ ~
| |
| ND 147 U.~255 3.34E+ 04 3. b~4~~5.~51EIO4 3.10EIO3 b5E Ob"'I.~45EIO4~~h5E +b
| |
| .__....... .. ....... .. 85E.... + 04. 2.31 E + 03 0.00E +
| |
| .__...... .......00. ... 2.25E + 04 0.00E + 00 1.8
| |
| _ __. .. . ... .. .. . . . _ _5 E + 0 8 ___...
| |
| 157.0 ma
| |
| | |
| usmbe
| |
| $UOle8r i Radidogical Contrds Departmental Procedure
| |
| : m. 6610-PLN-4200.01 Revis6on No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 6.0 TMl-1 GASEOUS WASTE TREATMENT SYSTEM 6.1 Descriptbn of the TMi-1 Gaseous Radwaste Treatment System (see Ficure 61) 6.1.1 Waste Gas System
| |
| : a. Reactor BuRding:
| |
| - Reactor Coolant Drain Tank (RCDT) header
| |
| : b. Auxilary Bullding: f%g Vent Header from h k l 1.
| |
| / %,g ,gE Miscellaneous Waste Storage Tank (MWST)?
| |
| 2.
| |
| Three (3) Reactor Coolant Bleed Tanks (RCBT)
| |
| - Waste Gas Delay Tank 4 q,,,3 Two (2) Waste Gas Compressors 4 %,]' g *
| |
| - Three (3) Waste Gas Decay Tanks (WGD1)4 c.
| |
| FRtration and dilution provided by the Station Ventuation System.
| |
| 6.2 Operability 4.7". Ei g h 1 ii3 '
| |
| Operability of the Gaseous Waste Tr$tadrit"$ypem is defined as the abRity to remove gas from the e vent header / tank gas spaces aruf More'it under a higher pressure in the Waste Gas Decay Tanks for suDsequent release.
| |
| 9 }~
| |
| of N Except for initiating the make pp %,l tank sample and waste gas venting and the recycle or disposal of compressed waste ganas stored.in the waste gas decay tanks, the operation of the waste gas system is entirely automade. One waste gas comprossor comes on automatically, removing gases from the vent headerWstem as required, to maintain the pressure in the system at a maximum of about 16.4 pslah '% "#
| |
| b _*
| |
| % j "%
| |
| 3it l
| |
| l 158.0 mm
| |
| )
| |
| | |
| ~
| |
| kmber TMt Radsological Controls Departmental Procedure 6610-PLN-4200.01 nos a m.
| |
| Offsite Dose Calculation Manual (ODCM) 12 FIGURE 8.1 Waste Gas System
| |
| _ p%
| |
| esasemn.esnams e
| |
| eassue at j 0;,
| |
| i e s. iu *
| |
| $gE gest mages ,8,,. g~'NA 8 1P 1 P 4 6 afs'esle n s == == == eis ir T l iip;Il![ir
| |
| = a b 1P "e"s I *hph a >
| |
| t ir < , h. b
| |
| ,,,,,,d,.
| |
| sans i esesses a m eans aseans l g*8,8,8,, esassa tasse seass l d , y. 'yp
| |
| &&. = - == = =8 hp y 6 eens,une sesessmasus s - .
| |
| %ngijIIl:.,- esaaesans MmM 95sW N
| |
| , jf ,tig 'uv
| |
| , y ase,,m f jgn;g
| |
| 'af3 % 'iae g
| |
| asses ..%s,'ll; ) meses ens g
| |
| ml _, gas ,se 0l!l ' T!gg 0]h,se 01l=
| |
| t .a i, y
| |
| 46 T gegu gag
| |
| . <i t anages gg ,g4 mens esas esem sans omstems seem esas I
| |
| * gggg ih ' :$a 8 8 i
| |
| g 1
| |
| ,, n .., ,,: 9.. = )mlb- --' y Jo : -
| |
| - e 4-
| |
| : l. 0 ''
| |
| )
| |
| 1590 "'
| |
| .i
| |
| | |
| T 1
| |
| Number jggy TMI Radiological Controls Departmental Procedure l
| |
| 6610-PLN-4200.01 ino i
| |
| : n. mion No. l i
| |
| Offsite Dose Calculation Manual (ODCM) 12 '
| |
| 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 1
| |
| 7.1 Total Dose Calculation The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactMty and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrom. This controlis provided in order to meet the dose limitations of 40 CFR 190.
| |
| The total dose from TMI 1 and TMI 2 (uranium fuel cycle facilities within 8 kilometers) is calculated by summing the calculated annual doses to critical organs of a real lydlWiual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 aryd 5.2.2;tnetixxiology, and the direct radiation from the site from the environmental monitoring progregt's direct radiation (TLD) monitors. "
| |
| e, (i,#. f kg if f4hWuakihp.
| |
| O!qq. Ilvp.
| |
| m,g sp:
| |
| ~%g, NiihiigNkj ;.
| |
| j$" hip irm DpE iAYkhj 0; y 'h lthun0 i f Mig,,
| |
| g png p Nikj,
| |
| _ , g$ Af; ili4 it!'
| |
| i g Ny,, bd
| |
| $t gli i, 4
| |
| N:l; I
| |
| l I
| |
| i l 160.0 mm I
| |
| | |
| I l
| |
| 1 Number ggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Time AnytWon No.
| |
| ONsite Dose Calculation Manual (ODCM) 16 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) l 8.1 Monitorina Prooram Raouirements l I
| |
| 8.1.1 Controls in accor6ance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., the radiological envirorwental monitoring program shall be conducted as specified in Table 8.1.
| |
| 8.1.2 AgrAicability I l
| |
| ,,pm%4 At all times. p 44 l f '!j .!if i 8.1.3 Action ,!jf p *d l
| |
| %w NY I
| |
| : a. With the radiological environmental monitoring pJogram pot being conducted as specified in I Table 8.1, prepara and submit to the Commlssion irithe Annual F.adiological Environmental l Operating Report, a description of the reasons"for nelconducting the program as required j and the plans for preventing a recurrence. %g, l
| |
| : b. With the level of radioactivity as thalestdt of plant ofRuants in an environmental sampling medium exceeding the reporting,levelibifable 8.2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a special rehort that identifies the cause(s) for exceeding the lirnit(s) and .
| |
| defines the corrective actio6s to Q taken to reduce radioactive efRuents so that the potential I annual dose
| |
| * to a member of tly public is less than the calendar year limits of ODCM Part i Controls 2.2.1.2,2,;2.2.2 and22.2.3 and ODCM Part 11 Controls 2.2.1.2,2.2.2.2 and 2.2.2.3.
| |
| When more than tine of theTadionuclides in Table 8.2 are detected as the result of plant effluents in the samplirsg medium, this report shall be submitted If:
| |
| concentra + concentration (2) + . = 1.0 reporting level (1) reporting level (2) l 4 A4 WhEn hio$uclides other than those in Table 8.2 are detected and are the result of plant effluenta,this report shall be submitted if the potential annual dose
| |
| * to a member of the pubilc is equal to or greater than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part 11, Controls 2.2.1.2,2.2.2.2 and 2.2.2.3. This report is not required ll the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shan be reported and described in the Annual Radiological Environmental Operating Report.
| |
| * The methodology and parameters used to estimate the potential annual doss to a member of the pubile shall be indicated in this report.
| |
| 161.0 me.
| |
| | |
| i Number jggy' TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No, i
| |
| l l
| |
| Offsite Dose Calculation Manual (ODCM) 12 -
| |
| l l
| |
| : c. With mik or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 8.1, identify specific locations for obtalning replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to TMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table for the ODCM reflecting the new location (s) with supporting Information Identifying the cause of the unavalabilty of samples and justifying the selection of the new location (s) for obtaining samples.
| |
| p%
| |
| 8.1.4 Bases ik
| |
| [f %,,
| |
| The radiological monitoring program required by this control provkles representative measurements of radiation and of radioactfve materials in those exposure pathwaps and for those radionucildes j
| |
| which lead to the highest potential radiation exposures ofzmembers'of the general pubtle resulting i from the station oporation. This monitoring program impferns$ti Section IV B.2 of Appendix ! to 10CFR50 and thereby supplements the radiological effisant inonitoring program by verifying that the measurable concentrations of radioactive materlats and lents of radiation are not higher than expected on the basis of the effluent measuretrients and modeling of the environmental exposure pathways. Guidance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operationa(experience.
| |
| ~.
| |
| 9y 8.1.5 Surveillance Reauirements /" *ilj[%,
| |
| l lf The radiological environment $1 monitoring samples shall be collected pursuant to 10ble 8.1, from the specific locations given in" Tables 8.4 through 8.10 and Maps 8.1 through 8.3, and shall be analyzed i pursuant to the requirements of Table 8.1 and the detection capabilities required by Table 8.3.
| |
| (gf}
| |
| . s y es h } h, hij 9
| |
| 162.0 mm
| |
| | |
| Number ggy TML Radiological Controls Departmental Procedure 6610-PLN-4200,01 T rtle Fievision No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 l
| |
| 8.2 land Use Census 8.2.1 Controls in accordance with the TMI-1 Tech. Specs and TMI-2 PDMS Tech. Specs., a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden
| |
| * of greater than 50 m' (500 ft') producing broad leaf vegetation.
| |
| 8.2.2 Aoolicabilty pm%
| |
| At all times. %
| |
| # fl i
| |
| /
| |
| tf 8.2.3 Action 9%{p
| |
| : a. With a Land Use Census identifying a location (s) thathlds a calculated dose or dose commitment greater than the values currently being calculated in ODCM Part i Surveillance 3 2.2.3.1, pursuant to ODCM, Part IV Section 2.0, identify the new location (s) in the next Annual Radioactive Effluent Release Report. %
| |
| : b. With a Land Use Census identifying a l$ cation (s) that yields a calculated dose or dose commitment (vla the same exposure pathway) 20% greater than at a location from which samples are currently being obtalred in accordance with Table 8.1, add the new location (s) within 30 days to the Radlological ErWironmental Monttoring Program given in the ODCM.
| |
| The sampling location (s[saluding the contrel station location, having the lowest calculated dose or dose commitment (s),$la the same exposure pathway, may be deleted from this monitoring progres aftsr 0o 6ber 31 of the year in which this Land Use Census was 4
| |
| conducted. Puriusnt to TMl-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report dccumentation for a change in the ODCM inclu ling a, revised figure (s) and table (s) for the ODCM reflecting the new location (s) with i atiggsupporting the change in sampling locations.
| |
| 8.2.4 Bases % hk i
| |
| This Control ibprovided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial surveys, or consulting with local agricultural authorttles shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix i to 10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 m') provides assurance that significant exposure pathways via leafy vegetables wi!L be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used.1) that 20% of the garden was used for growing broad leaf vegetation (i e., slmlar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
| |
| * Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different sectors wtth the highest predicted D/Os in lieu of the garden census.
| |
| Requirements for broad leaf sampling in Table 8.1 shall be followed, including analysis of control samples.
| |
| l mm 163.0 j
| |
| | |
| e Number
| |
| --glgy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
| |
| ! 1m. Naion No.
| |
| I l Offsite Dose Calculation Manual (ODCM) 12 l
| |
| l 8.2.5 SurveWance Reaulrements 1
| |
| The Land Use Census shall be conducted during the growing season at least once per 12 months, using that information that will provide the best results, such as by a door-todoor survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part IV, Section 1.0. )
| |
| gismMijy )
| |
| E j.f v ik g 1;ig!","
| |
| I iig '51
| |
| . prmst;;;; g -
| |
| l
| |
| .s 4 9
| |
| kn, llj, 1
| |
| 9j;
| |
| : 5. i miQ.
| |
| N.ii j g"'$g
| |
| % . #6%
| |
| 3 j
| |
| Tj$tnig4Sysj 1pr ,
| |
| j? p. . .a
| |
| )
| |
| #sw'''i::g. 1 9 ;g, !
| |
| ,pde
| |
| [g!. !!
| |
| s 0; tyN4;;3 N. 4:ss9 iltr pi! iig, lin@.
| |
| l l
| |
| l l
| |
| l 164.0 mm 1
| |
| .g. m agy,gg >g gg ,a es* @ ***ND Y
| |
| | |
| l ggy TMl Radiological Controls Departmental Procedure Number I Tmo 6610-PLN-4200.01 novisen No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 8.3 Interlaboratory Comparison Prooram 8.3.1 Controls in accordance with the TMI 1 Tech. Specs. and TMI-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and anal'yses which are required by Table 8.1 shall be performed.
| |
| 8.3.2 Acolicability At all times.
| |
| jMuly f4
| |
| ,/. . %m,ud"
| |
| }
| |
| 8.3.3 Action ti f gAf t..
| |
| t y With analysis not being performed as required above, report tha c%onective action taken to prevent a recurrence to the Commission in the Annual Radiological EnW6rsnental Operating Report.
| |
| 8.3.4 Bases Mhs '4 k,:
| |
| The requirement for participation in an approved [lntedaboratory Comparison Program is provided to ensure that independent checks on preclakv1 and accuracy of the measurements of radioactive materialin environmental sample mat,ridhsjre. performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, B.2 of AppendlQ tq,10 CFR 50.
| |
| $ 1 8.3.5 Surveillance Reautrements $ 0
| |
| [*4g iing/
| |
| A summary of the interfaboratory,. Comparison Program results shall be included in the Annual l Radiological Environmerdal Operating Report.
| |
| g w y s % sd
| |
| ' lip Oigjf )lig%
| |
| ili
| |
| !!g 1 165.0 mm
| |
| | |
| l ggggy TMl Radiological Controls Departmental Procedure Number Title 6610-PLN-4200.01 Revisbn No, Offsite Dose Calculation Manual (ODCM) 12 i TABLE 8.1 Sa'nple Collection and Analysic Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations' Collection Frequency" of Analys!s"
| |
| : 1. Alitxxne
| |
| .,g imiqi Radiolodine and Samples from 5 locations I ut Continuous sampfer g Rahiolodine Canistg; Particulates from Table 8.4. operation with sampis(p j
| |
| * Analyze weekly for 1-131.
| |
| collection weeldy, or;tnore, Particulate Filter:
| |
| frequently if required by, dust Analyze for gross beta loading. radioactMty following h '"$[""*Ellie iig,, ig filter change'. Perform N;g ~ gamma isotopic analysis'
| |
| ( on composite (by location) sample 5,,,l7"..."*%
| |
| ih quarterly.
| |
| 3*+
| |
| 93
| |
| : 2. Direct Samples from 40 ,,ym *S$mdiQuarterfy Analyze for gamma dose Radiatlorf locations from Table 8.5 (using ehher 2 f( k{% quarterly.
| |
| y F
| |
| dosimeters or at least timm Instrument for# '
| |
| continuousifineas%, uring and recordingdone rate at each" location)/
| |
| .Miin, %
| |
| , hgf' 'ilip "k
| |
| !!jg,
| |
| :y.
| |
| 166.0 n.*
| |
| | |
| Number ggy TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revieson No.
| |
| Offsite Dose Calculation Manual (ODCM) 16 TABLE 8.1 (Cont'd)
| |
| Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample locations' Collection Frequencyb of Analysis'
| |
| : 3. Waterbome
| |
| $j.y l
| |
| bli
| |
| : a. Surface' Samples from 2 locations Composite
| |
| * sample ovy 1 ill3,, @rform gamma Isotopic from Table 8.6. montNy period. m analysis' montNy.
| |
| /4 /p %
| |
| 1 Composite for trttlum e 1 sample from 4'"g,,141:g.
| |
| ,. analysis quarterfy.
| |
| downstream (Indicator) .9 location % j%@4~,.
| |
| %s Mg 3 e 1 sample from upstream
| |
| * 4 (control) location (or location not influenced by **d'ik the station discharge) "ig *4
| |
| : b. Drinking Samples from 2 locationsgComposite'%, sample over 1 Perform gross beta and from Table 8.6. ##%g# -li."*monthly period. gamma isotopic analysis' l!I montNy Perform Sr-90 e 1 sample at thilo*ostion analysis if gross beta of 1
| |
| '""f of the nearest 4ater montNy composite >10 i supply that.could k times control. composite {
| |
| affected by*the station for tritium analy,.1 ;
| |
| dischargs? " J quarterly. l g g 4#
| |
| .g o 1 Antrfe from a c'ontrol IocsOon.+
| |
| : c. Sediment from Sa$ples from 2 locations Shoreline (1 Control and 1 Indicator) Sample twice per year Perform gamma isotopic from Table 8.7. (Spring and Fall) analysis' on each sample.
| |
| 167.0 mm
| |
| | |
| Number
| |
| - ggy TMl Radiological Controls Departmental Procedure i Title 6610-PLN-4200.01 1 Reviolon No.
| |
| Offsite Dose Calculation Manual (ODCM) 16 TABLE 8.1 (Cont'd) l Sample Collection and Analysis Requirements Number of Samples l Exposure Pathway and Sampilng and i and/or Sample Type and Frequency !
| |
| Sample Locations
| |
| * Collection Frequency" of Analysis
| |
| * I
| |
| : 4. Ingestion g
| |
| : j. g%. ,
| |
| I
| |
| : a. Milk Samples from 4 locations Sample semimonthly when i!!4 P from Table 8.8. animals are on pasturpf j " maerform nalysis' and gamma 1-131 Isotopic monthly at other times?%f analysis on each sample.
| |
| *%. '!!:ig Composite for Sr-90
| |
| . *$m.nra.,y4.~ analysis quarter 1y.
| |
| N
| |
| *it;p,ig;. ig O it,h
| |
| : b. Fish Samples from 2 locations Sample twice per'9 ear Perform gamma Isotopic' from Table 8.9. (Sprindand Fall). and Sr-90 analys!s on e 1 sample of egd edible portions, "jg, recreationally important . d*. *. %,
| |
| bottom feeders and 1 !/
| |
| sample of recreationall[y.,' .-s ""!W, important predators in Cji '
| |
| l the vicinity of the"statidny discharge. # "%..
| |
| gn;aus '*g3, e 1 sampIe of*
| |
| recreatloriall{lm%
| |
| bottorp, feed. ors and I portant sample'ci, recreationally i important" redators from an area not influenced I by the station discharoe. !
| |
| l 1
| |
| l l
| |
| 168.0 mm
| |
| | |
| F Nurnber glgg TMI Radiological Controls Departmenta! Procedure Tme 6610-PLN-4200.01 RevWon No.
| |
| Offsite Dose Calculation Manual (ODCM) 16 I
| |
| TABLE 8.1 (Cont'd) '
| |
| Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and and/or Sample Type and Frequency Sample Locations' Collection Frequency
| |
| * of Analysis'
| |
| : c. Food Samples from 2 locations Sample at tirne of harvest, w.. Perform gamma isotopic',
| |
| Products from Table 8.10 (when
| |
| : j. .
| |
| i 1-131, and Sr-90 analysis avaRable) p k!;;, onydible portions.
| |
| * 1 sample of green leafy fN .,,3.
| |
| m.m#
| |
| %. %f*
| |
| vegetables or leafy % 'h r ia,,.
| |
| vegetation at a location in T"h ki,, '
| |
| the immediate vicinity of the station. (indicator) %e..
| |
| '41!!g. '(*.
| |
| y g
| |
| e 1 sample of same lh species or group from a location not influenced by "*%!!!;4 .
| |
| d"*i!g the station discharde. f .!ib"a-rw (
| |
| 0 4
| |
| $ iijk
| |
| %%r#a pa, %g
| |
| , ,p;;!!
| |
| g w,N;g %n0I,!
| |
| li:q., 9kl .
| |
| $q ji i! N!4
| |
| 'T,g-169.0 mm
| |
| . . + - . . _ . ._ - .-- - - . - . - - -. --
| |
| | |
| i l
| |
| Number l
| |
| Nuclear = a^did aa'ca' c an'
| |
| * Departmental Procedure 6610-PLN-4200.01 Iltl* Fhision No.
| |
| l l Offsite Dose Calculation Manual (ODCM) 12 TABLE 8.1 (Cont'd) l Sample Collection and Analysis Requirements Table Notation l i
| |
| : a. Sampling locations are provided in Tables 8A through 8.10. They are depicted in Maps 8.1 through 8.3.
| |
| I Deviations are permitted frum the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the samp!!ng schedde shall be explained in the Annual Radiological Env!ronmental Operating Report. / %g b.
| |
| .L $
| |
| Frequency notation: weeldy (7 days), semimonthly (15 days), monthly (31' days)tand quarterly (92 days).
| |
| All surveillance requirements shall be performed within the specified time ir}terval with a maximum allowable extension not to exceed 25% of the surveillance Interval. A total maximdm consecutive tests shall not exceed 3.25 times the specified collectior) dan; combined alysis interval. inter q mv
| |
| : c. One or more instruments, such as a pressurized io.'. chamber fdpdasuring and recording dose rate continuously, may be used in place of, or in addition to, integratinddosimeters. For the purpose of this table, a thermoluminescent dosimeter (TLD) is consider 5d to be one phosphor; two or more phosphors in a packet are corssidered as two or more dosimeters. jar { badges shall not be used as dosimeters for measuring direct radiation. jag k
| |
| : d. Airborne particulate sample filters shall be an e EEboss beta radioactivity 24 hours or more after sampilng to allow for radon and thoron daughter' decay. If gross beta activity in an air particulate sample (s) is grerter than ten times the calendar, year mean of control samples, Sr-90 and gamma isotopic analysis shall be performed on the individu(tarnple(s)/
| |
| 4" Rg
| |
| : e. Gamma isotopic analysis means the idIntification and quantification of gamma-emitting radionucIldes that may be attributable to the effluents'from the facility.
| |
| gv )
| |
| : f. The
| |
| * upstream sampleith$ belnilen at a distance beyond significant influence of the discharge. The
| |
| ~
| |
| " downstream sample's% be- taken in an area beyond but near the mixing zone.
| |
| w ]
| |
| : g. Composite sample alkhbots shall be collected at time intervals that are short (e.g., hourly) relative to the !
| |
| compositing period (e.g., monthly) in order to assure obtaining a representative sample.
| |
| I 170.0 mm L.__.__.____._______-___----_________
| |
| | |
| jggy TMI Radiological Controls Departmental Procedure Number Title 6610-PLN-4200.01 Revision No.
| |
| I Offsite Dose Calculation Manual (ODCM) 12 l TABLE 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples
| |
| {
| |
| l I
| |
| Airborne Particulate Water or gas Fish Analysis Milk Food Products (pCl/L) (pCl/m') (pCl/kg, wet) (pCl/L) (pCl/kg, wet)
| |
| HG 20,000*
| |
| [ k !
| |
| Mn-64 1000 .
| |
| 30,000 '"i #ps
| |
| [ .o '6ih.
| |
| Fe-59 400 10,000 *ilik k Co-58 1000 30,000 ,
| |
| * l,[*"*D '
| |
| Co40 300 10,000 "
| |
| Zn45 300 20",000 Sr 90 8 0.1 .,, 100s 8 100 Zr-Nb-95 400 4 .$ %
| |
| l-131 2 0.9f * 'is 3 100 Cs-134 30 #10liit. I 1000 60 1000 Cs 137 50 # '20 2000 70 2000 Ba-La-140 200 ijf jmi . tt 300
| |
| * N!! s gg#
| |
| '"tijn. 'A
| |
| *For drinking water samples. Jhls is 40 CFR Part 141 value.
| |
| "{;' '
| |
| I f
| |
| i I 171.0 mm
| |
| 'w gyp + y hg<M q @ N" 8MN M%O *
| |
| : m. w N
| |
| * Number ggy TMI Radiological Controls Departmental Procedure Title 6610-PLN-4200.01 Reyte,on No.
| |
| Offalte Dose Calculation Manual (ODCM) 16 TABLE 8.3 s
| |
| Detection Capabilities for Enviror: mental Sample Analysis
| |
| * Lower Limit of Detection (LLD)"
| |
| Alrbome Particulate Fish Food Sediment Water or Gas (pCl/kg, Mik Products
| |
| * i. (pCi/kg, Analysis (pCl/L) (pCl/m') wet) (pCl/L) (pCl/kg, Wet) 4 dry)
| |
| Gross Beta 4 0.01 [ ,,5 %w H-3 2000 941 Mn44 15 130 .m N ""4"E'l"'
| |
| Fe-59 30 260 4
| |
| * Co-58, 60 '
| |
| 15 130 I Zn-65 30 z260 *"' t,.
| |
| Zr-95 30 "gb #n2w Sr90 2 9 # 2 0.01 4 % 10 10 Nb-95 15 d #
| |
| ik J I e
| |
| I-131 1 8
| |
| . .,, 0.U73 1 60 Cs-134 15 I d Yl.05#
| |
| 130 15 60 150 Cs-137 la 'i "*"#b.06 150 18 80 180
| |
| ... m .
| |
| Ba 140 ts B0 ""' 60 La 140 'l$ 15 172.0 me.
| |
| | |
| 'ggy TMl Radiological Contrds Departmental Procedure Number Title 6610-PLN-4200.01 Revis#0n No.
| |
| Offsite Dese Calculation Manual (ODCM) 12 TABLE 8.3 (Cont'd)
| |
| Detection Capabilities for Environmental Sample Analysis' Table Notation a.
| |
| This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyz and reported in the Annual Radiological Environmental Operating Report.
| |
| t, Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Rev.1).
| |
| : c. {p %*(b The LLD la defined, for purposes of these contrds, as the smallest concentration of radioactive material in a sample that will yloid a net count, above system background, that wHl b6 detected %ith 95% probablity with only 5% probability of falsely concluding that a blank observation represents a "reaf* signal.
| |
| gg For a particular rneasurement system (which may include radiocftemic heehration):
| |
| 4.66 S3 Sq% b E V
| |
| * 2.22 Y exp (-Aat)
| |
| * Where: $
| |
| #wd l pq '%
| |
| LLD is the "a priorf lower limit of detection asMefirWKi above, as picocuries per unit mass or volume.
| |
| pg -
| |
| s,is the standard deviation of the backgr60[O 'cohnting rate or of the counting rate of a blank sample as appropriate, as counts per minute, ,$ $
| |
| f%
| |
| E is the counting efficiency, as counts per dis) integration,
| |
| .a m 9 V ls the sample size M units 6i mass or vblume, ik
| |
| )
| |
| 2.22 is the number of disintegratioris per minute per picoeurie,
| |
| < M3 %
| |
| Y is the fractional rad 600hemical yleid (when appik:able),
| |
| wg A is the radioactive deca / constant for the particular radionuclide and at for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting.
| |
| Typical values of E, V, Y and at should be used in the calculation.
| |
| It should be recognl:ed that the LLD is defined as an *a priorr (before the fact) limit representing the capabiltty of a measurement system and not as an "a posteriorr (after the fact) limit for a particular measurement Analyses shall be performed in such a manner Inat the stated LLDs will be achieved undor routine conditions. Occasionally background fluctuations, unavoidable small samples 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 described in the Annual Radiological Environmental Operating Report.
| |
| : d. LLD for drinking water.
| |
| 173.0 mm Owy
| |
| | |
| p Number gggy TMI Radiological Controls Departmental Procedure
| |
| )
| |
| l Th 6610 PLN-4200 01 na. Lsn No.
| |
| l Offalte Dose Calculation Manual (ODCM) 16 i TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air lodine
| |
| _ Station Code Distance (mles) Azimuth (*) Man No.
| |
| B1-4 0.8 28 60 El-2 0.4 95 2 F1-3 0.6 105 70 G2-1 1.4 125 74 M2-1 1.3 A3-1 2.6 253 f% 3 358 H31 2.3 f % 4 ;
| |
| 04-1 15 %'""""#/ 5 1 Q15-1 3.5 13.5 32(9//"
| |
| 61 3059'8 8
| |
| % ig, ;
| |
| TABLE 8.5 N% %,
| |
| TMINS REMP Station Location w $ Direct Radiation (TLD)
| |
| Station Code Distance (miles) y *k g Arlmuth (*) Mao No. l p
| |
| A1-4 0.3 k g S 9 B11 0.6%q \[****' 25 10 l
| |
| B12 i 0.4 h* 26 11
| |
| #A/ig[0.0.(./
| |
| C1-2 l 54 13 i D11 2 74 14 El 2 p, ~%D 4 95 2 l
| |
| .gf*#ahl El-4 0.2 98 N 16 F1-2 0.2 109 17 G1-3 9% *hd 0.3
| |
| %g 129 18 H11 dti "% 0.5 167 J1-1 k. rf g% 0.8 184 19 21 J1-3 q%g 0.3 109 22 K1-4 0.2 g 208 24 L11 l 0.1 235 26 M1 1 0.1 249 27 N13 0.1 270 28 P1 1 0.4 293 29 P1-2 0.2 290 30 l
| |
| i 174.0 m.
| |
| | |
| Nurnber 3 TM1 Radiological Controls
| |
| ..w ME Departmental Procedure 6610-PLN-4200.01 Title Revis6on No.
| |
| Offette Dose Calculation Manual (ODCM) 16 TABLE 8.5 (Cont'd)
| |
| TMINS REMP Station Locations-Direct Radiation (TLD)
| |
| Station Code Distance (miles) Azimuth M Manno.
| |
| 01-2 0.2 318 31 R1-1 0.2 335 32 C2-1 1.6 48 33 K2-1 1.1 200 34 M2-1 1.3 253 ,pm%.. 3 A3-1 2.6 358 !!" 1. 4 H31 2.3 159 f ki,, / 5 R3-1 2.6 .
| |
| 't"""" 35 B5-1 C5-1 4.8 4.5 338*S [e
| |
| *18 y 36 37 ES 1 4.6 g '"(, 81"diw
| |
| ,, 42g % 38 F5-1 4.7 39 GS-1 4.8 .
| |
| Nig'"(107 131 40 H5-1 4.1 j! 157 41 JS-1 4.9 .,ggj:lj 182 42 K5-1 5.0 k' 200 43 Im 228 44 LS-1 MS-1 4.1 ,;;g /).
| |
| 4.3 ' %! *4" 249 45 268 46 NS-1 j dM"1;;3% 285 47 PS-1 . d 4.9 k 05-1 318 48 RS-1
| |
| #[Sig4.9' 5.0j'Y 339 49 1
| |
| y % 5.2 65 50 D6-1 E7-1 (;r4eg gs 6.8 86 51 09-1 8.5 308 52 "iin B10-1 ( l';
| |
| ' *# r 9.4 21 53 G10-1 9.8 127 6 G15-1 te%g%;;b 14.4 124 54 J15-1 % 12.6 180 7 Q15-1 13.5 305 8 i
| |
| 1 i
| |
| 175.0 me l l i
| |
| I l
| |
| ['
| |
| | |
| I ggy TMI Radiological Controls Departmental Procedure Number Talo 6610-PLN-4200.01 Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 16 1
| |
| TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code Distance (miles) _ Azimuth (*) MaoNo.
| |
| J12 (R) 0.5 188 57 A3-? (R) 2.5 355 59 09-1 (F) 8.5 308 52 09-1 (R) 8.5 308 52 G15-2 (F) 13.6 G154 (F) 14.8 128 f"'%g 62 124 g! } 63 F15-1 (R) 12.6 122f % / "
| |
| 65 (R) = Raw Water Q (F) - Finished Water g 's1l;;%
| |
| *Pl.%uus;;,
| |
| ,. 3h TABLE 4.7 iip %
| |
| TMINS REMP Station Locatkms-Aquatic Sediment mg Station Code Distance (mites ["$ Azimuth (*) MacNo.
| |
| A1-3
| |
| %.ph % .
| |
| G11 0.5% 'A* 0 67
| |
| ' 0.3 137 K13 68 J2-1 f [0.3 1.5"j}e 202 69 l 1 l
| |
| J12 182 58 p[#iim.'hiip.5 188
| |
| {' 57
| |
| .ju 4s##lit9 j
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| |
| h,. T
| |
| %gg;# %
| |
| T4s.
| |
| 4 I
| |
| I l
| |
| l 176.0 mm
| |
| | |
| Number ggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No.
| |
| Offsite Dose Calculation Manual (ODCM) 16 TABLES.s TMINS REMP Station Locations-Milk Station Code Distance (miles) Azimuth (*) MapNo.
| |
| D2-1 1.1 65 72 E2-2 1.1 93 73 G2-1 1.4 125 74 P7-1 6.7 293 77 K15-2 12.8 208 jamh 78 i
| |
| m:.
| |
| 'l;ei.
| |
| u.
| |
| ,ffY myy. mis
| |
| $ii , 3in, TABLE 8.9
| |
| . T s'."'Nced.. i'*!p ;l
| |
| * k
| |
| +a .
| |
| m TMiNS REMP Station Locationt-Fish tiig '"
| |
| 9P Station Code Stat Location p% "'%
| |
| IND Downstream of Station Discharge BKG Udi4resiiri"of Stat!on Discharge p%%
| |
| 1;, 't" f
| |
| M its
| |
| %vn"Y,J
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| *4l
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| 4
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| *% 't:L Il;-ig kag,,pj!s w
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| ligg 177.0 mm
| |
| --. - -- - - ~
| |
| l
| |
| | |
| Number Nuclear ' "ad'd**' o ""d' Departmental Procedure 6610-PLN-4200.01 noe n.vWon No.
| |
| Offsite Dose Calculation Manual (ODCM) 16 TABLE s.10 TMINS REMP Station Locations-Food Products Station Code Distance (miles) Azimuth M Map No.
| |
| D1-3 0.5 65 79 E1-2 0.4 95 2 F1-1 0.5 117 80 A15-1 10.5 10 85 B10-2 10.1 28 .p " ,,, ,
| |
| 55 g m.
| |
| .lir ill,
| |
| }E fi , j p kyrg'ensI' iiqq fiI
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| ,Sy3:na.
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| -4ip,!pe h.4I4 j!!!:p ty mv. ,
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| :!j 'l!lg dili ;tlff h, 'lin 4llyf f~%g ' *
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| '*g 178 0 222 6 L
| |
| | |
| Number MI TMI Radiological Controls Departmental Procedure Titae 6610-PLN-4200.01 Rowsion No.
| |
| Offsite Dose Calculation Manual (ODCM) 16 MAP 3.1 l
| |
| THREE MILE ISLAND NUCLEAR STATION i
| |
| LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM !
| |
| STATIONS WITHIN 1 MILE OF THE SITE '
| |
| O
| |
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| s..w i ikw l i
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| : 7. .
| |
| i NJmber 1
| |
| TMI Radiological Controls i
| |
| l g EI Departmental Procedure 6610-PLN-4200.01 i
| |
| Revision No.
| |
| Tttle Ottsite Dose Calculation Manual (ODCM) 16 MAP 8.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE SITE I
| |
| igii, O )l 3,3 ti,w g# ;%d k[g, f arm l}
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| mm a "ib#.,,,
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| i ! 9,.
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| R 10$ii 338 25' 4, k* j $8,, % 33 W
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| |
| 180.0 mm f l
| |
| 1 a
| |
| | |
| r Number i
| |
| TMt Radiological Controls g MF Departmental Procedure 6610-PLN-4200.01 l Tai. n.vi.i.n so.
| |
| Offsite Dose Calculation Manual (ODCM) 16 l l MAP 8.3 4 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE l
| |
| !i o
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| /
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| e te g 95 .1 s
| |
| # e ,/ i \ a j 123.75*
| |
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| |
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| |
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| i 191 25' J 188.W 181.0 me.
| |
| | |
| Numt>et biOSF TMl Radiological Controls Departmentai Procedure 6610 PLN-4200.01 Title Revmon No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 9.0 PART HI REFERENCES
| |
| : 1. EPRI NP-3840, RP 1560-3 Final Report, " Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985
| |
| : 2. " Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendix 1," Nuclear Safety Associates, May 1976
| |
| : 3. TMl-1 Final Safety Analysis Report (FSAR)
| |
| : 4. TMl-2 Final Safety Analysis Report (FSAR) f*%g k
| |
| : 5. MeteorologicalInformation and Dose Assessment System (MIDAS) $g)y !
| |
| ,a p
| |
| : 6. NUREG-0017,' Calculation of Releases of Radioactive Material [In[baseous and Liquid Effluents from PWR," Revision 1,1985 %
| |
| g.
| |
| : 7. NUREG-0133, " Preparation of Radiological Effluent Technic &l Specifications for Nuclear Power Plants," October 1978 % l j
| |
| h
| |
| : 8. NUREG-0172, ' Age-Specific Radiation Dose.Qmitment Factors For A One-Year Chronic Intake,"
| |
| November 1977 4 gng th
| |
| : 9. Regulatory Guide 1.21, "Measurings NIard Reporting RadioactMty in Solid Wastes and Releases of Radioactive Materials"in" Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1 Jyns 1974 ];
| |
| 10.
| |
| l %)
| |
| Regulatory Guide 1.109,4* Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of EUeluating Compilance with 10 CFR 50, Appendix 1," Revision 1, ;
| |
| October 1977 flyp2!
| |
| : 11. Simplified Errdro f ffluent Dosimetry System (SEEDS)
| |
| %ARtig *
| |
| : 12. TMI Recirculation Factor Memos, April 12,1988 and March 17,1988
| |
| : 13. TMI-1 Operations Procedure, 1101-2.1, " Radiation Monitor Set Points"
| |
| : 14. Title 10. Code of Federal Regulations
| |
| * Energy"
| |
| : 15. TMI-1 Technical Specifications, attached to Faculty Operating License No. DPR-50
| |
| : 16. Regulatory Guide 1.111,
| |
| * Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluent i in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977
| |
| : 17. TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73
| |
| : 18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, l November 1979
| |
| : 19. Title 40, Code of Federal Regulations,
| |
| * Protection of Environment" l 182.0 mm
| |
| | |
| I l
| |
| Numb 2r l
| |
| jggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 l
| |
| Tme Revia. A No.
| |
| l l
| |
| Offsite Dose Calculation Manual (ODCM) 12
| |
| : 20. Regulatory Guide 4.13, " Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications,' Revision 1 July 1977
| |
| : 21. Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR)
| |
| .inib ll gt, i i I
| |
| (h 3 l
| |
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| |
| h.5111 .ill'
| |
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| |
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| |
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| |
| il
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| |
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| |
| )I . Ib iig
| |
| .hg;fF NI4 sin Ng i
| |
| i 183.0 mm 1
| |
| | |
| Number
| |
| ..gdgy TMI Radiological Controls Departmental Procedure Ttte 6610-PLN-4200.01 Revision No, Offsite Dose Calculation Manual (ODCM) 12
| |
| ,1) pan,,%
| |
| ,,p sgs J
| |
| '44q":#F' ti!( ' . :3
| |
| +i. "*4iq[']I''
| |
| '"4 3 '%4 T!* n%diji,.
| |
| % %q'i!n
| |
| 'i;}g '
| |
| t di#
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| |
| en;aiirg(l!4
| |
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| |
| PAR
| |
| ,gy T,+IV,,
| |
| ,1(
| |
| Sj:I!; N!!
| |
| : n. iii 1
| |
| REPORTING REQUIREMENTS jewr "%g\(,
| |
| gi'Nki r
| |
| .gl % wasp iii Ii d,hi hs %
| |
| $ggk i 'n4l Iih.g:
| |
| 0 184.0 mm
| |
| | |
| p Number l
| |
| $UClear M Radiological Controls Departmental Procedure 6610-PLN-4200.01 a wan re.
| |
| Offsite Dose Calculation Manual (ODCM) 12 PART IV Reporting Requirements 1.0 i TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ** !
| |
| 1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year.
| |
| 1.2 !
| |
| The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, j and an analysis of trends of the results of the radiological environment $l" monitoring activities for the report period, including a comparison with pre-operational ctudies, pith operational controls as appropriate, and with previous environrnental monitoring reportsfand an assessment of the observed impacts of the plant operation on the environment. The fe results of 1.and Use Censuses required by Part 111 Section 8.2 "% ports shall also include the 1.3
| |
| %dA 4 The Annual Radiological Environmental Operating Reports shsllfriclude the summarized tabulated j
| |
| results of analysis of all radiological erwironmental sarhbles"nnd environmental radiation measurements required by Part 111 Table 8.1 taken duringihe period pursuant to the locations specified in the tables and figures in this ODChl, as well as summarized and tabulated results of these analyses and measurements in a fortnatjimilar to the table in the Radiological Assessment Branch Technical Position, Revision 1.J4ovemberJ979. In the event that some individud results are {
| |
| not avalable for inclusion with the report.,the report shall be submitted explaining the reasons for the missing results. The missing data'shall bhubmitted as soon as possible in a supplementary report. p"""1 "g, 1.4 The reports shall also includ$ t ijoll ing: a summary description of the radiological environments
| |
| ~
| |
| monitoring program; a m5dts) of all sampling locations keyed to a table giving distances and directions from a point:that Ishtidway between the Reactor Buildings of TMI-1 and TMI-2; the results }
| |
| I of licensee participation in the Interlaboratory Comparison Program, required by Part lli, Section 8 3; l discussion of all devlidions from the sampling schedule of Part lil, Table 8.1; discussion of all the required analyses la.which the LLD required by Part 111, Table 8.3 was not achievable.
| |
| igg b ig i
| |
| l
| |
| **A single submittal may be made for the station.
| |
| !' 185.0 1 mm
| |
| | |
| Number
| |
| {
| |
| GUCIO8r i RadblogW Controls Departmental Procedure 6610 PLN-4200.01 ime se m6on ta i
| |
| _ Offsite Dose Calculation Manual (ODCM) 17 2.0 TMl ANNUAL. RADIOACTIVE EFFLUENT RELEASE REPORT 1
| |
| ~
| |
| NOTE A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station -
| |
| however, for units with separate redwaste systems, the submittal shall specify the release of radioactive material from each unit.
| |
| 2.1 Routine Radioactive Effluent Release Reports covering the operations of.the unit during the previous
| |
| . 12 months of operation shall be subm!!!ed prior to May 1 for TMI-1 aiG TMb2.
| |
| m k3 k i 2.2 The following information shall be included in both Radioact!ve bluent Balease Reports to be submitted each year; b
| |
| i[
| |
| ig
| |
| % '"4 The Radioactive Effluent 3elease Reports shall include a pummary of the quantities of raioactive liquid and gaseous effluents and solid waste released from@ unit as outlined in Reg. Guide 1.21, Rev.1, with data summarized on a quarterly basis following'the format of Appendix B thereof. l 2.3 The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report pahod
| |
| : a. container volume. (,pj g.,
| |
| : b. total curie quantity (s k er determined by measurement or estimate),
| |
| .h
| |
| : c. principal radionuciides (specif whether determined by measurement or estimate),
| |
| Niqh.
| |
| : d. type of was}e (s g., spent resin, compacted dry waste, evaporator bottoms),
| |
| : e. type oghgmen((e)!g., LSA, Type A. Type B) and K"
| |
| : f. solidificatlorg % agent (e g., cement).
| |
| 2.4 The RadioacthEffluent Release Reports shall include a summary of unplanned releases from site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.
| |
| 2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part til Section 8.2.
| |
| 2.6 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1b and 2.1.2b, and ODCM Part ll Control 2.1.2b.
| |
| 1860 me b
| |
| | |
| namb., l TMl Radiological Controls ;
| |
| Mgp Departmental Procedure 6610-PLN-4200.01 i bision No.
| |
| h 12 OffsNe Dose Calculation Manual (ODCM) 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be alther in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stabRity, and precipitation l (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stabRy.
| |
| 2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to MEMBERS OF THE PUBUC due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The meteorologfcal conditions concurrent with the l
| |
| {
| |
| time of release of radioactive materials in Gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shat! be performed in accordance fwith this%fODCM. {% ,
| |
| The Radioactive Effluent Release Report shall include an asseshnent bl thd radiation doses from f 2.9 l radioactive liquid and Daseous effluents to MEMBERS OF THE PUBUC due to their activities inside the SITE BOUNDARY during the report period, to verify < corp' pliande with the limits of f 10CFR20.1301(a)(1). All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these" reports.
| |
| '4 2.10 The Radioactive Effluent Release Report shall $1so include an assessment of radiation doses to the likely most exposed real individual from reacto{ releases and other nearby uranium fuel cycle sources including doses from primarypffluent pathways and direct radiation for the previous 12 consecutive months to show conformancepith 40 CFA 190
| |
| * Environmental Radiation Protection Standards for Nuclear Power Operati6n?" Acesplable methods for calculating the dose contributions from liquid and geseous effluentialei given in Regulatory Guide 1.109, Rev.1.
| |
| # %d h
| |
| #_k g"h f.m ig gpfi Nh
| |
| % ),
| |
| h ii g ht!F 1r j k '*
| |
| hg i
| |
| l me 187.0 l
| |
| | |
| l Number l gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 l
| |
| Title beson No.
| |
| Offsite Dose Calculation Manual (ODCM) 12 30 PART IV REFERENCES 3.1 Radiological Assessment Branch Technical Position, Revision 1, November 1979 3.2 Regulatory Guide 1.21, " Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Ught-Water-Cooled Nuclear Power Plants,' Revision 1, June 1974 3.3 TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-60 3.4 Title 40, Code of Federal Regulations, " Protection of Environment * #%
| |
| 3.5 Regulatory Guide 1,109, " Calculation of Annual Doses to Man from Rh[ in Q }
| |
| Effluents for the Purpose of Evaluating Compilance with 10 CF(Part 50," Appendix 1,* Revision 1 October 1977 'ig M; 3.6 Title 10, Code of Federal Regulations "Er ergy* Y"gb;g q'%;w ^%
| |
| 3.7 Regulatory Guide 1.111," Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Qooled Reactors," Revision 1, July 1977 emw3; 3.8 Regulatory Guide 1.112, " Calculation of, Releases of Radioactive Materials in Gaseous and Liquid Effluents from Ught-Water-Cooled Power R5 actors,* Revision 0-R, April 1976 "g j e n.
| |
| 3.9 Regulatory Guide 1.113, *EstimatfridAqbatJp Dispersion of Effluents from Accidental and Routine Reactor Releases for the Pu of lyementlog Appendix 1," Revision 1, April 1977 4 v Oa ll
| |
| .pn4 Niijp lhlis
| |
| ,y. 4 .s Hhn. 3Uin.
| |
| ( j!!Ni',ig
| |
| * My{g 188.0 mm 1
| |
| l L
| |
| | |
| T Number 4MCIS8r WI RadiologM Controls Departmental Procedure ime 6610-PLN-4200.01
| |
| %sion No.
| |
| Offsite Dose Calculation Manual (ODCM) 17 APPENDIX A P,- Pathway Dose Rate Parameter P,(inhalation) = k' (BR) DFA, (Eq A.1)
| |
| Where:
| |
| P, = the pathway dose rate parameter for radionuclide, I, (other than not/e gases) for the inhalation pathway, in mrom/yr per nicrocurie/m'. The dose factors are based on the critical indMdual organ for the child age Group.
| |
| k' = conversion factor, IES pCl/ microcurie / f(y%g,h f BR =
| |
| 3700 m*/yr, breathing rate for child (Reg. Guide 1.109, Rev.1 Table E4)
| |
| .em "% %
| |
| DFA, = the maximum organ Inhalation dose factor for the infant age, group lfor the Ith rad Values are taken from Table E-10, Reg. Guide 1.109 (Rev.1),*or NUREG-0172.
| |
| Resolution of the units yields: (ODCM Part 111 Table 4.(
| |
| .au s P, (inhaletion) = 3.7E9 DFA, (mrom/yr per pCl/m') f g "*%ig i (Eq A-2) f 3
| |
| {a,a% rg 4 9E The latest NRC Guidance has deleted the requirement to determine P, -
| |
| (ground plane) ang. $ (fo$d)$ addition, the critical age group has been changed from intant to chlid.
| |
| qq,1!( %# pr , gf"%
| |
| 8
| |
| % pi ij i
| |
| E t-1 mm
| |
| | |
| F Number GUOlear M Radidogical Contrds Departrnental Procedure 6610-PLN-4200.01 1me s.v,.,on w
| |
| _ Offsite Dose Calculation Manual (ODCM) 17 APPENDIX B RI- Inhalation Pathway Dose Factor R, a k' (BR) (DFA ) (mrem /yr per microcurle/m') (Eq B-1)
| |
| Where:
| |
| k' = conversion factor, IES pCl/ microcurie BR = breathing rate, 1400, 3700, 8000, 8000 m'/yr for infant, chRd, teenager;ard adult age groups, respecthrely. (Reg. Guide 1.109 Rev.1. Table E-5) li sp '1{ 3 4n._,f.4 DFAa,= the inhalation dose factor for organ, o, of the receptor of a givert age grollp, a, and for the ith radlonuclide, in mrem /pCl. Tha total body is considered as an organ in the selection of DFAa ,
| |
| Values are taken from Tables E 7 through E-10, Reg. Guided.109.(Rev.1), or NUREG 0172.
| |
| ,,g % nem Resolutions of the units yields: ii (1!gN ,,.
| |
| Ri - u (1.4E9) (DFA ) Infant (ODCMalihth Part til Table 5.2.h: I Ri = [hi! ;g (3.7E9) (DFAu ,) child (ODCM Part til Tatdag.2.
| |
| RI =
| |
| d' Ji' . , .
| |
| (8.0E9) (DFA,,,) teen and adult (ODCM Part il1 Tables 5.2.3 and 5.2.4) n pu,,!jg ;u!O l .,/' li' 4'i!:*a#[
| |
| j!(
| |
| 4
| |
| ,I Mi:h
| |
| .dilf4 ip, gjjil !
| |
| % f! y 4: U; had liggli !!!!
| |
| m
| |
| '41 E2-1 an*
| |
| | |
| Number gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tatie Revision No.
| |
| Offstte Dose Calculation Manual (ODCM) 17 APPENDIX C Ri- Ground Plane Pathway Dose Factor R, a k' k' (SF) (DFG,) [(1-e T)/A,] (Eq C-1)
| |
| Where:
| |
| k' - conve slon factor,1E6 pCl/ microcurie k" a conversion factor, 8760 hr/yr ,s.mH .
| |
| fl g"s J, + decay constant for the l* radionuclide, sec '
| |
| j#f iis" gE
| |
| , %ga
| |
| ** h. . .eb t- the exposure time (this calculation assumes that decay is the only, operating removal mechanism) 4.73 x 10'sec. (15 yrs), Reg. Guide 1.109 (Rev.1), Apperd!x C
| |
| .g
| |
| , sy
| |
| ,%g. %
| |
| l'%
| |
| DFG,- the ground plane dose conversion factor for the i* radionucildelmrem/hr per pCl/m'). Values are taken from Table E 6, Reg. Guide 1.109 (Rev.1), or NUREG 0172. These values apolv to all aae aroups.
| |
| I SF = 0.7, shielding factor, from Table E 15 Reg. Guide 4jo9 (Rev.1) q ny$lg, Reference ODCM Part til Table 5.3.1 #gliiIIII' I
| |
| N 4!ip ,.f%
| |
| :if.pWHII:ika,i:I!lp
| |
| 'i %
| |
| Jh II[:n;gflI
| |
| $ *Q l
| |
| .g2[r IIIg
| |
| ]
| |
| r"Iln. ;;;Y >h
| |
| # ;;g@'
| |
| j !
| |
| i qN !!i.,, 'I);;.
| |
| ! i
| |
| !jj ijnlinilg[N
| |
| :- ,b im,.
| |
| llp E3-1 mm j
| |
| | |
| F Number gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Teile Revistori No.
| |
| Offsite Dose Calculation Manual (ODCM) 17 APPENDIX D RI- Grass Cow-Milk Pathway Dose Factor R. = c k' [(Q, x U-.) / (2, A.,' ;] a (i,p x tr) x (DFV x
| |
| (((f, x f.)/Y,) + ((I-f, x f,) e Th)/YJ eTf (Eq D-1)
| |
| Where.
| |
| k' - conversion factor,1EG picocurie / microcurie (r Ol/pci) y%
| |
| 0, - cow consumption rate,50 kg/ day, (Reg. Gd a 1.109. Rev.1) li goat consumption rate,6 kg/ day, (Reg. Gwse 1,109, Rev.1, Table Eg y},
| |
| %1 U, = Receptor's milk consumption rate; 330, 330, 400, 310 liters /yr for [nfant, child, teenager, and adult age groups, respectively (Reg Guide 1.109, Rev.1)
| |
| ,,,, , m. %,, NF g, e,-
| |
| Y, - agricultural productMty by unit area of pasture feed grass,0.7 kg/m' (NUREG4133)
| |
| Y, - agricultural productMty by unit area of stored feed,2.0 kg/m' (NUREG-0133)
| |
| %}
| |
| F, - stable element transfer coefficient (Table E;1,Rev.1)
| |
| Guide 1.109, Rd)g3 r- traction of deposited activity retaine chs feed grass, 0.2 for particulates,1.0 for radiolodine (Table E 15, Reg Guide 1.109. Be@1),)"ijn, DF( = the ingestion dose factor for, organ o/and k ) the Ith radionuclide for each respective age group, a g
| |
| (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1), or NUREG 0172.
| |
| ,p4 "uis A, - decay constant for the,s"illfradionuclide, m, sec' a g J, - decay constanhoIwo$thfring,5.73 x 10'sec' (NUREG-0133); based on a 14 day half life t, = 1,73 x 10'%. jhhin,?
| |
| seclthe transpo t time from pasture to cow to milk to receptor (Table E-15. Reg Guide 1.109, Rev 1), or 2 days t, = 7.78 x 10'sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev.1), or 90 days I, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture E4-1 nm
| |
| | |
| Number gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01
| |
| : 3. n vm on No.
| |
| Offsite Dose Calculation Manual (ODCM) 17 APPENDIX D (Cont'd)
| |
| The concentration of tritium in ml!k is based on the airborne concentration rather than the deposition. Therefore. R, is based on (X/0):
| |
| 1 R',, = k*k"' F,,, 0, U,DF(,, (.75 [.5/H]) (Eq D-2) l Where: >
| |
| l 1
| |
| k'" - 1E3 grams /kg g Ali,,.
| |
| H= 8 grams /m', absolute humidity of the atmosphere ll[ 9it
| |
| .75 = fraction of the total feed grass mass that is water (/ %
| |
| .5 a ratio of the specific activity of the feed grass water to the atypospheric water (NUREG4133) sg wa,q,ip 4,,
| |
| DF( ,= the ingestion dose factor for tritium and organ, o, for eac%.h' respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1), or NUREG 0172. '"%,
| |
| ff A!! other parameters and values are as given above. .w;d
| |
| ,ss, 4 g,m. a.
| |
| 4!
| |
| [
| |
| Goat-mak pathway facth,$[l"be computed using the cow-milk pathway factor equatioq,3 F Reg. Guide 1.1094ev.1h, # factor for goat-mlik will be from Table E-2 A
| |
| | |
| ==Reference:==
| |
| ODCM Part ll! Tables 5I.. I to 5.4"4 l
| |
| , 4. %#;~"@ik kii!@ l
| |
| 'llgku lj,%
| |
| l
| |
| '% 9l? Q;g
| |
| !!j E4 2 mm em n. gem Ne. sp-g 'w,w = + eman dhe Qa
| |
| . Ops > e
| |
| | |
| Numbet gggy TM! Radiological Controls Departmental Procedure 6610-PLN-4200.01 im. Moon No.
| |
| Offsite Dose Calculation Manual (ODCM) 17 APPENDIX E RI - Cow-Meet Pathway Dose Factor R, = k' ((Q, x U,) / (A, + A,)] x (F,) x (r) x (DFLa ) x
| |
| (((f, X I,)/Y,) + ((I-f,f,) e 'Th)/Y,] x o'8 1'f (Eq E-1)
| |
| Where:
| |
| k' - convers!on factor,1E6 picoeurle/ microcurie (pCi/pci) pLq Q, - cow consumption rate. 50 kg/ day, (Reg. Guide 1.109, Rev.1) 'l
| |
| [% $
| |
| U,, - Receptor's meat consumption rate; 0,41,65,110 kg/yr for infant .cb;lidtte$nahr, and adu respectively (Reg. Guide 1.109, Rev.1) *ig,f%j[
| |
| F, = the stable element transfer coefficients, days /kg (Table E[hdhd 1.109, Rev.1)
| |
| "% 14 r= fraction of deposited activity retained in cow's feed grass,0 2 for particulates,1.0 for radiolodine (Table E-15 Reg. Sulde 1.109, Rev.1)
| |
| % d) ;
| |
| DFLa., - the ingostion dose factor for organ, o, and Jhe 8th radionuclide for each respecthie age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Sev. h, or NOREG 0172.
| |
| 1g,j %
| |
| A, - decay constant for the radionuclide/EO$ 4 l k $
| |
| A, - decay constant for weatherin .73110 Hec' (NUREG4133), based on a 14 day half life
| |
| " j lia .
| |
| t, = 1.73 x 10'sec, the transport time from pasture to receptor (NUREG4133)
| |
| ,, k,#*
| |
| t, a 7.78 x 10'sec, the transpogdji e from crop to receptor (NUREG4133)
| |
| \% 4 Y, = agricultural productMty b/y' unit area of pasture feed grass,0.7 kg/m' (NUREG4133) y Y, - agricultural produdtMty by unit area of stored feed. 2 0 kg/m' (NUREG4133) f, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture The concentration of tritium in meat is based on the airborne concentration rather than the deposition. Therefore, R,is based on (X/Q):
| |
| (Eq E-2)
| |
| R,,, = k'k"' F, Q, U, (DFV x 0.75 x (0.5/H])
| |
| Where:
| |
| All terms are as defined above and in Appendix D.
| |
| | |
| ==Reference:==
| |
| ODCM Part lit, Tables 5.6.1 to 5.6.4 ES-1 mm
| |
| | |
| g gy TMl Radiological Controls Departmental Procedure Number Tate 6610-PLN-4200.01 Revieson No.
| |
| Offsite Dose Calculation Manual (ODCM) 11 APPEN0lkr RL - Vegetation Pathway Dose Factor R, = L k' x [r/ (Y, (A, + J,,))] x (DFly x [(U ) f, e4L + U', f, e'I'h] (Eq F-1)
| |
| Where:
| |
| k' - 1ES picocurle/ microcurie (pCl/pci)
| |
| U\ = the consumption rate of fresh leafy vegetation,0,26,42. 64 kg/yr for infanCYhud, teenager, or adult groups, respectively (Reg. Guide 1.109, Rev.1)
| |
| / (%nedy D', = the consumption rate of stored vegetation,0,520,630. 520 kg/yr fAr liiant, child, teenager, or adult t groups respectively (Rig. Guide 1.109, Rev.1)
| |
| "ig]Ni -
| |
| f, - <W the fraction of the annual intake ofifly,"fresh leafy vegetation grow
| |
| = 1.0 (NUREG4133)
| |
| >t,ty. %
| |
| f, = the fraction of the stored vegetation grown locally ,. 0.76 (NUREG4133) t, = the average time between harves of leafy vegetatioh@ nd its consumption 8.6 x 10 secondI 4 4
| |
| [ Table E-15, Reg. Guide 1.109 Rev 1 (24 hrs)} si,.
| |
| t, = the average time between harvest of sto hhybgetation and its consumption,5.18 x 10' seconds, (Table E-15, Reg. Guide 1.109, Rev. 9(60"da a))
| |
| L t y, - the vegetation area densfry,2.0Jh/ 8 (Tat #e E 15, Reg. Guide 1.109, Rev.1) y% ;
| |
| All other parameters are as previously defined. hilt, l
| |
| (!L #
| |
| The concentration of tritium ""#
| |
| in vegetation %ibased on the airborne concentration ra Therefore, R,is based on (X/0)g, %(.,
| |
| -Q lYN\y e Fi R , = k'k'" (Ui f, + 0', ff,q%s,) (.75 [.5/H]) (Eq F-2) 1 l
| |
| Where; ,
| |
| l All terms are as defined above and in Appendix D.
| |
| t
| |
| | |
| ==Reference:==
| |
| ODCM Part III, Tables 5.7.1 to 5.7.4 I
| |
| E6-1 m=
| |
| mm
| |
| -mirW
| |
| | |
| (
| |
| ( Number l
| |
| ' ggy TMi Radiotoolcal Controls Departrnental Procedure 6610-PLN-4200.01 Tette Revisaon No.
| |
| Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 1 of 4)
| |
| Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G.1.109 NUREGg133 Specific I
| |
| '" For P, "* { }
| |
| ,( j *ca" DFA Each radionuclide E-9 Note 1 BR 3700 m'/yr (child) E-5 (*%g.
| |
| ,v( .no
| |
| '*iin. i
| |
| "*For R1 (Vegetation)"* , '%
| |
| r Each element type ,, (E1 Y, 2.0 kg/m' f 9
| |
| 'E:15 Aw 5.73 E 7 sec' , '%g "4im' 5.3.1.3 DFI, Each age group and radbnuclide ' E-11 thru E-14 Note 1 U,' Each age group jj; %# E-5
| |
| : f. 1.0 ,pq %;i;i, 5.3.1.5 t, E 15 8.6 E + 4 seconds Ji U,' Each age lgr6bp, E-5 l
| |
| +
| |
| f, 5.3.1.5 0.76 9llll{
| |
| : t. 5.18 E + 6 seconds E 15 H 8.0 grams /kg 5.2.1.3
| |
| ***For R1 (Inhalation)***
| |
| BR Each age group E-5 DFA Each age group and E-7 thru E-10 Note 1 nuclide l
| |
| l l
| |
| i l E7-1 mm
| |
| | |
| Number gdgp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 TO Aemion No.
| |
| Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A F REFERENCES (Page 2 of 4)
| |
| Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G.1.109 Specific NUREGp133
| |
| *" For R, (Ground Plane) '" ,
| |
| j j SF 0.7 E 15 (" j '"*ne"""
| |
| DFG, Each radic,nuclide E-6 *
| |
| ., Nirg i 4.73 E + 8 sec '""
| |
| 5.3.1.2 ev.. "%S
| |
| *g
| |
| *" For Ri (Grass / Animal / Meet) *** (
| |
| Q,(Cow) 50 kg/ day ftg '%E-3 0, (Goat) 6kg/ day ,, %.g /"' %' E-3 Ref. Only U, Each age group
| |
| [ ''g
| |
| * E-5 Aw 5.73 E-7 soc' j g{ %# 5.3.1.3 F, (Both) Each element pu %;p, E-1 r Each element,typeSi""' J E 15 DFL, Each age group"and nuclide
| |
| .g E-11 thru E 14 Note 1 tl 55kt f, 1.0
| |
| * 5.3.1.3 Note 2
| |
| *lh.{
| |
| f, 1.0 5.3.1.3 Note 2 Y, 0.7 kg/m' E-15 1, 7.78 E + 6 see E 15 Y, 2.0 kg/m' E-15 t, 1.73 E + 6 see E-15 H 8.0 grams /kg 5.2.1.3 E7-2 m=
| |
| | |
| r Number 2 mE TMl Radiological Controls
| |
| - WUWEI Departmental Procedure 6610-PLN-4200.01 1,e.
| |
| twen No.
| |
| Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 3 of 4)
| |
| Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Sito-Parameter value R.G.1.109 NUREG-0,133 SpeFb
| |
| *** For R, (Gross / Cow / Milk) *** ., t[ }
| |
| 0, 50 kg/ day E-3
| |
| #[ f '"'
| |
| U, Each age group E-5 "%g %;p Aw 5.73 E-7 sec' 4tt 14 '""' 5.3.1.3 F,, Each element E-1 '"'!!i;,,
| |
| r Each element type Ik E-15 DFL, Each age group and nuclide jr .i, E-11 thru E-14 e
| |
| Note 1 Y, 0.7 kg/m' "hg '"5
| |
| * E 15 t, 7.78 E + 6 sec g "g E-15 Y, 2.0 kg/m' # Tiinis,/ E-15
| |
| +b t, 1.73 E + 5 secg "%, E-15 f, 1.0 ,g,
| |
| %#" Ji 5.3.1.3 f, 1.0 '!( ""g[ 5.3.1.3 H 8.0 giams/kg4 5.2.1.3 o
| |
| E7-3 rum
| |
| | |
| Wmber
| |
| -gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tsee Amnion res.
| |
| Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 4 of 4)
| |
| NOTES
| |
| : 1. Inhalation and ingestion dose factors were taken from the inoicated source. For each age group, for each nuclide, the orge.n dose factor used was the highest dose factor for that nuclide and age group in the referenced table. -
| |
| : 2. Typically beef cattle are raised all year on pasture. Annualland surveys have: Indicated that the small number of goats raised within 5 miles typica.Ily are used for grass control arx(not fodd or mlX.
| |
| Nevertheless, the Goats can be treated as full meat sources where prssert despitg me fact that their numbers cannot sustain the meat consumption rates of Table E-5, NUREG-0133?'
| |
| "g, i![
| |
| 4!!cyg h BEFERENCES 4 "i ""*
| |
| : 1. ReQuiatory Guide 1.109, " Calculation of Annual Doses to Man frordRoutine Releases of Reactor Effluents for the Purpose of Evaluating Compilance with 10 CFR Par (50, Appendix 1," Revision 1, October 1977.
| |
| "%.h
| |
| : 8. TMl-1 Technical SpecNications, attached to Facpypperating Ucense No. DPR-50.
| |
| 4 A.,, .
| |
| : 3. NUREG 0133, " Preparation of Radiological Effluerst Technical Specifications for Nuclear Power Plants,"
| |
| October 1978. "t;p, gf'"" ""3l[lt b l f(p V'% d n
| |
| 3,.
| |
| JiNIF p, g;pi" f d;j g %,4 %! 1" F
| |
| 1in,,
| |
| 4ihlis%ig[""I!bi.
| |
| 4 914 E7-4 me.
| |
| | |
| l
| |
| .\
| |
| Enclosure 2 -
| |
| I 1 8 Annual Radioactive Effluent Releases Repon for TMI I
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| . Procedure Change Request (PCR) 1-RC-98-0033 to the ODCM,6610-PLN-4200.01 -
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| 1 i
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| 1001A FIGURE 1 Revision 25 b0
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| .E PASSWWE 954sEE Meutsi Pcm Refer to instrucWons and guidennes in AP 1001A when nomoteting thus form.
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| : 1. I.,l. l o -Pt.e4 - 4 Zoo . cl IL 6DCM ""
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| Procedure No. Present b. No. True 2 '" Cheeps: e include peGe numbers, paragraph numbers, and sanot wutng of roommmended chan08
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| . Am.e ade.on.i. nee. n n -
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| bt.% l.0 3 1**.G .0 3 A9b 16(e.O As stADicATED ed ATrACHED HAR VED L/P copy . Aos,, ws si.1, ca..i, c3 , c4-i, c4 3 , goo gg _ g ,
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| : 3. nuesen for chasse: e is this onan0e part t,f the B onruel Bocedure Revow?
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| Include l&E Butetins, TSCR d T. S. Amendmect . ...
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| *!l;;.gf
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| ..Yes e, Moenostion No a,Xeuh, . k . . .
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| s
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| ''E B e674 D A R,Y O M SPEcePy //g's Amp D/g/s OSCD To pggpeg Aup cetTecAL RECEPTot.
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| * DOSES 'Tb PEgg geltz FoEMA4
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| ' Doc.5)ME9tATho J AMD 4'od rftoL OF TME,SEE,jACCES Nai, Dio h batccT TYPod.C.A1%c.AL. E.Pto%S l o u " Proc 16(..c I
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| Dd 0; h MDO REFERz4CE To NG
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| * f$$'*%
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| quid %g %li ink '
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| : 4. (a) Does Revision replace a TCN7 . . . .J!( 2.i #,( ..... . . . .., , , , ..... ,,, . Yes No 1 (b) N "yes', indicate the TCN Number, .w % N avillable 4 b ..
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| 5 Is procedure within OA Plan Scope? kof."* . . . . . . . , , , , , , , , .. , , ......... , Yes X No 6 Change Recommended By: R f:' t TT" ,DateJ ]lL/#A 1
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| y g n.w e6-ws.:
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| : 7. Precedure owner Concurmnae
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| : s. naponsibie omoe Conourrenos JW stu-om a o. m . cr+tio6e>4M/e / v l 9 Iesponetble Technical Reviewer Concurrence M #beLIM*C - Date *80
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| * h_
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| : 10. independent sesmy Review n/r /FM 4' ''[/NV Date _
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| P. Appsesel signeewest (Por'AP 1001 A) [
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| lCA/h & A^. .T a o o J b- fM = 9 Y~U*
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| s.On.ium
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| ,7 Deio
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| : n. Cnane.ensor.d Th I'& De e Rev. No.-
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| l'1 E101 tith L '
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| l .. . _, -. . , . .
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| 1001A Revision 35 FIGURE 4 THREE MILE ISt.AND l SAFETY DETERMINATION TNs deterrnination is required for all documents wrtNn 1001 A applicability / scope.
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| N.w e,oe.du,e_ _ _ . _ _ _ _ _ reN . .
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| @ Pcn _). - $. C. @.E .Q.Q _& Sie - -
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| (,(,I o -Pt.4 -4 2.oo . o l w
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| : 1. Is ths a substantive change 7 Indicate "YES* for new procedures and STP's jwy, Yes X No 3 $
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| if Box 1 is *No', sign and date tNs form. The remainder of the form need not be completedJ p n p
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| .s #
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| % b it
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| : 2. Does this change involve any non-radiological environmental impact? 9'ly'"%dqh' # Yes No X (Refer to Definitions Section of tNs procedure.) !
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| "4;3,, '(w q.
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| e if "Yes', complete Figure 9 and ensure the change is submitted to En0konmental Affairs for review, o Comp 6ete the remainder of tNs form. jj al g#"h ,ig l!!i ,.i ,
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| ~l;g(g Anite -
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| thp*! ltia'h %
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| iiii jfik/i,*illmrnHN[
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| : 3. Does this change have the potential ,to adversely affect nuclear safety or safe plant operations? Yes No k (aefer to Paragraph 4.2.2) #
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| #4 '%
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| ik ,ad@i;
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| : 4. Does tNs make changes in the NOlity es described in the safety analysis report? Yes No X 4;4 '94 nir#F
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| : 5. Does tNs ma,ke changes in One kocedures as described in the safety analysis report? Yes No )(
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| gg %Ii,
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| : 6. Are tests or expenments"bonducted wNch are not described in the safety analysis report? Yes No X
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| : 7. Does tNs change conflict with the requirements of the plant Techrucal Spec!fications? Yes No N If AfD' of the answers to 3,4, 5,6 OR 7 are XES. you must fill out Figure 5 AN,Q provide a written safety evaluation Sign and date this form, if the answers to 3,4,5,6 AND 7 are ek(liq, tNs precludes the existence of an Unreviewed Safety Question or Techrscat Specification change.
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| Provide the basis for the answers to each of the questions (3,4,5,6,7) on one or more separate sheets.
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| Sign and date tNs form. l 1
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| Propered By: averr- Date: kl 6 ara sy: a m5 8AeA Date: 6Je-n E131
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| SAFETY CETERMINATION FOR PCR to 6610-PLN-4200.01 Page 2 of 2 Description of the Chegg This PCR is being submitted to identify the specific values of the maximum average annual X/Q's and D/Q's used to estimate offsite doses at the site boundary and at critical receptors on a monthly basis. Doses reported to the NRC in the Annual Effluent Report do not utilire these values. Real time meteorology is used to determine actual X/Q's and D/Q's to calculate these doses. Historically Tables 4.4 and 4.5 of the O!X'M were used to identify the maximum annual average site boundary X/Q's and D/Q's to be used for monthly done calculations. These tables were also used in conjunction with the results of the Annual Land Use Census to extrapolate X/Q's and D/Q's at critical receptors. These numbers were transmitted by calculation, but were never formally identified in the ODCM. This PCR will incorporate the specific values to be used to make these dose estimates, improving their documentation, review, and control. The values included in this PCR for the site boundary are directly read from Tables 4.4 and 4.5 of the ODCM.
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| Environmental Controls Calculation 6510-98-003 calculated the X/Q's and D/Q's for the critical locations identified by the land use census.
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| p%
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| : 3. Does thk change have thepotential to adversely afect nuclear safety or sqlTeplant operations?
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| / %. 1 No. Specifying the X/Q and D/Q values in the ODCM will improye their documentation, review, and control. As a result, this change enhances nuclear safety and safe plant operations.
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| ""('%g
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| : 4. Does nk make changes in thefacility as described inAlie sep(ny analysk reportt 14 '('
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| No. This change does not make any changes to the facilitg.
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| * 6 L Does thh make changes in theprocedures an described in the safety analysk report?
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| t%l No Maximum annual average dispedi5n and position coefficients are not specified in the SAR.
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| *( f%r
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| : 6. Are tests or experimena consuennd inhlch are aet describedin the safety analysk reporti g %,
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| No special tests or experiments are jerformed.
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| ,pq w&
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| \ 7.
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| Does thh chang conflict G the requirements of theplant technicalspecyications!
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| W ..s%
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| No. Efiluent controis are contained in the ODCM.
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| + % w?
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| 1 h!g, }b Safety Analyth Revert Document Sections Reviewed i w Technical Specifbtion 6.8.4.b FSAR Chapter 1I Signature B. A. Parfitt Date 4/16/98 y
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| : e. , . . - .
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| Number ggp TMl Radiological Contrds Departmental Procedure ,
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| h 6610 PLN-4200.01 l Aews.on No.
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| Offsite Dose Calculation Manual (ODCM) 16 Appuoebuny/ - = ce#e oNsas doses due to radioactive Aespaamb6* Omos Wcm* Date effluents for demonstrating compliance with Sao Technical Spec #ications 10 CFR 20 & 10 CFR 50 Appendtr i 6610 06/30/97 TNs document is within QA plan scope X Yes No i
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| l Safety Reviews Required X Yes No l
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| l Ust of Effective Pages '
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| fagg Revision fa,gg Revision Ep.gg ELv,iaB29 Pace Revision 1.0 16 21.0 15 41.0 15 61.0 15 2.0 16 22.0 15 42.0 155g
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| *E"%g. 62.0 15 3.0 11 23.0 15 43.0 15 h 63.0 15 4.0 15 24.0 15 44.0 5.0 15 25.0 15 45.0
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| #1 dg*'"'/ 64.0 15 15 65.0 15 6.0 15 26.0 15 46.0 ' ,q[M5 66.0 15 7.0 15 27.0 15 47.0 <>g% '15 67.0 15 8.0 15 28.0 15 48.0 Tf"9""dG!b15 68.0 15 9.0 15 29.0 15 49'.'O r ha 15 69 0 15 10.0 15 30.0 15 15 70.0 11.0 15 31.0 15 50.0 %*
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| * 15 15 71.0 15 12.0 13.0 15 15 32.0 33.0 15 15 il 51.0
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| #%?. 53.0 52.0 15 15 72.0 15 73.0 15 14.0 15.0 11 34.0 15f"g % 54.0 15 74.0 15 11 35.0 15 pg, 55.0 15 75.0 15 16.0 11 36.0 56 0 l
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| 15 76.0 15 17.0 11 37.0 # 45,if15[k% 57.0 15 77.0 15 18.0 ,!
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| 38.0 I 19.0 ,(1 N, 1 39.0d(g q
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| %15)'
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| 15 58.0 59.0 15 15 78.0 79.0 15 15 ig N, 20.0 15 \ 40.0 ig 15 60.0 15 80.0 GPUN .
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| j-ggp TMI P=*R-$2 Controls Departmental Procedure 6610-PLN-4200.01 T** a on m Offsite Dose Calculation Manual (ODCM) 12 5.2.2 lodine-131. lodine-133. Trttlum and Radionu6das in Particulate Forrn. with Half-l.Nes Greater than 8 Days The dose to an indNidual from I 131,1433. Tritium and Radionuclides in Particulate Form wth half 4Nes greater than 8 days in gaseous affluents released from the site to an unrestricted area is determined by solving the following expression:
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| Dome, = Z(3.17E-4) x I (R,) (Dv) (Q,) (og 5.2.2) i i
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| ,pa"%g where: { }
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| Dose =
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| / %f #
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| does to all real pathways, p, to orgar)fo, of an individual in age group, a, from I-131.1133. Trttium and Radeonuc! ides in Particulate Form, with half-inr lives greater than 8 days, wiig.
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| 4,8h h,qy *em.,during any desired time period l h R, = the dose factor for each"identfiled radionuclide,1, pathway, p, age group, a, and organ, o. In mrem /yr per.pCi/m3 for the inhalation pathway and m 2 mrem /yr per qsee for other pathways, from Tables 5.2 to 5,7.
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| m j/Mg NOTE, i
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| Since there is minimal ofno.eMiriental iodine released from the condenser off-gas air s}ects (see NUREGJ)017) all lodine R, values for all pathways, except the inhalation pathway, are considered to be zero when performing dose caldulations for rolesses from the condenser off-gas air eN. ONp"selculate the dose due to '.he inhalation pathway for condenser off-gas air ejector lodines.
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| t .am.
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| % .aii' NOTE
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| ,y %g %#
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| TMurhH-3, dose factor is mrem / year per pCl/m3 for all pathways.
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| %!!k "ai;t si sector annual average gaseous dispersion factor ).ever 3
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| nrsn Wn.; a1 6 /;..,, r, -
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| the inhalation pathway, and m 2, for other patt Table 4.4 is usMor station vent releases and Ta 5 for all r releases. Maximum values of X/O ;
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| presently used are 7.17E-7 for station vent at sector NNE and l T.lte. s sec/mhor all relekseig at sectors N and WNW. Maximum values of D/Q in m.2 r station ventil%22E-8/m 2at sector SE, ard for ground releasey .12E.8/m 2for sector S n .. w f
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| - ~ - _ . - ...
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| n vent releases and Table 4.5 for all other A REPt. ACE p t ra ATTACA4ED 1330 mm
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| Dv= highest sector annual average gaseous dispersion fator (X/Q) at or beyond the unrestricted area boundary, in sec/m', for the inhalation pathway, and D/Q, in m-8, for other pathways.
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| Table 4.4 is used to derive the values for statien vent releases and Table 4.5 is used to derive the values for all other releases. The values used to calculate site boundary red critical receptor doses are a follows:
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| Station Vent Releases- Boundary inhalation X/Q 7.17 E -7 Meat D/Q l .22 E -8 Ground D/Q l.22 E -8 Cow / Milk / Infant D/Q l.22 E-8 Vegetation D/Q l.22 E-8 Station Vent Releases - Critical Receptor Inhalation X/Q 7.2 E -7 Meat D/Q 4.6 E -9 Ground D/Q 7.8 E -9 Cow / Milk / infant D/Q 3.1 E -9 Vegetation D/Q 8.9 E -9 Ground or Other Releases - Boundary inhalation X/Q 1.16 E 5 f%.,.
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| Meat D/Q 4.12 E-8 Ground D/Q f 4.12 E-8 Cow / Milk / Infant D/Q 4.12 E 8 Vegetation D/Q g*4.12.E-8 Ground or Other Releases - Critical Receptor / n#
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| Inhalation X/Q 1.2 E 5 .im.M/p.
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| i Meat D/Q 9.2 E -9 Ground D/QA 3.0 E -8 Cow / Milk / Infant D/Q 6.3 E -9 V
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| .i% yetatus
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| * D/Q 2.6 E-8 DY(ll 3) = In the case of11-3 only the X/Q's above are used fhall thways.
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| 4 sge "4
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| . il" .111 jiFiciiii,iic
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| ;$in!"E4 kg,.
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| 4
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| ,4!B4
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| </s %)
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| ljg, t
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| 14p1'8 i d!j 1!g 'lniiliNy i
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| "lli llI! I lg
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| 'N]g i
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| Numes r TMI Radiologiced Controls F Depenmental Procedure 6610-PLN-4200.01 nm. n visen %.
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| Offsite Dose Calculation Manual (ODCM) 12 2.0 TMI ANNUAL RADIOACTWE EFFLUENT RFa sAas IEEPORT NOTE A singe submittal rney be made for the station. The subm8 tat should combine those sections that are common to both units at the station however, for units with esperate redneste systems, the submittal shun specify the release of radioactive matenal from each unit.
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| 2.1 Routine Radioactive Effluent Release Reports covering the operatieri[$f.the unit during the previous and Tbil-2.
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| 12 months of operation shall be submined / prior to May 1 for TMiy% )
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| 2.2 The following irWormation shall be included in both RadioacIhre Emuent Reisese Reports to be submitted each year: % 't emne,. h(4 The Raceoactive Effluent Release Reports shall include a Emmary of the quantfties of radioactive liquid and gaseous alltuents and solid waste releases (trom the unit as oulioned in Reg. Guide 1.21, Rev.1, with data surnmartred on a quart basis foGeging the format of Appendix B thereof.
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| 2.3 The Radioactive ESuent Release Reports shot include the fo8cming infortnation for each type of solid woole shipped offsas during the reptst penod gug wu.
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| : a. container volume, f pe,4,,
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| sm%
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| : b. total curie guaretty spec whether determined by measurement or estimate),
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| : c. pnncipal redsettuclidee$pecify whether determined by measurement or estimate),
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| p 3
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| : d. type of wiste (e.gI" spent resin, compacted dry waste, evaporator bottoms),
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| e.
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| ($?%
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| ship (e.g , LSA, Type A, Type B) and k +
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| f.
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| qi,Wsolltfissation
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| + agent (e.g., cement).
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| w 2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned rolesses from the site to unrestricted areas of radioective meterials in gaseous and liquid ofRuonts made during the reporting period 2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting penod to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calcu'ations and/or errvirorwa moratonng identifed by the land use census pursuant to Part til Section 8.2.
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| 2.6 The Radioactive EfRuont Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1b and e:e:4b, and ODCM Dart la Control 44+.b.
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| At*
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| : a. i. 2.
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| i i
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| 186 0 a i, l
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| 4 w e4gh e 4-p MW e BG = . # eg W Ww qq gg
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| . N wnber
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| ' y TMl Radiological Cortrois Departmortal Procedure 6610-PLN-4200.01 Tie.
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| nma n %.
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| Offette Dose Calculation Manual (ODCM) 11 APPENDOC A P,- Pethway Does Rete Parameter P, (ethelauen) = k' (BR) DFA (Eq A-1)
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| Where:
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| P3 - the pettmey does sate parameter for radionudide, i. (other than noble gEsas) for the inhalation pathway, in mrom/yr per microcurie /m*. The done factors are beood on the critical indMdual organ for the child age ,
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| group.
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| tr/ %pHib h
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| #/
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| E k' - conversson tector,1E6 pCi/mcrocurie 4,{h{
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| 8 % *j.
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| BR = 3700 m /yr, breettung rute for chid (Reg. Guide 1.109; %.1. Jab 6e E-5)
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| *ll i DFA,= the rnaxenum organ inhalation dose facsor for the inkra, age group for the kh radionudde (mrem /pCi).
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| Values are taken from Table E 10, Reg. Guide 1.109 (Reut), or MultE(s -0572 Il ,.
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| Resolution of the unas yisids; (ODCM Pari,mwys Table 4.6) 8
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| ,u"; "'
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| P, (enhalation) = 3.7E9 DFA; (mrom/yr per M,,./m ) (Eq A 5)
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| % ,,f+tt u
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| ["Mt Tgg NOTE Pi j!
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| The latest .NR6 Guidance has deleted the requirement to determine P 6 (groured ' plane) suf Pj (lood). In addition, the creical age group has beer) changed from irtint to chki.
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| (jf # *
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| ''$'h .1 '
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| ig ; UliullII 9k N.
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| I
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| -p yiprg?""Q t
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| 4 El 1 ==
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| i
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| r
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| (
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| 1 L
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| . kamtMrf l
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| 'gr WI Rad & pent Controls Departmortal Procedure 6610-PLN-4200.01 no. w m.
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| l Offsite Dose Calculation Manual (ODCM) 11 APPENDIX 5 Ri- InheisHon Pathway Dose Factor ,
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| l R3 = k'(BR) (DFAw) (mrom/yr per microcurie /m') . (Eq B-1)
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| ~ ,
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| k' = corwersion lector,1E6 pCl/ microcurie p$% 9,
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| . . W ?it i 8 l
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| BR = brosshmg rate, 1400,3700,8000,8000 m /yr for intent, ded}leenager, arut adult age gw, respectwely. (Reg. Guide 1.109, Rev.1 Table E-5) [ ,.'"%+"
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| * %f" DFAg= the inhalebon does tactor kr orgart, o, of the receptorm of e.ghn age group, s. and for the 8th l
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| radonudide, it) mrom/pCL The total body is conneleted.as an organ in the selection of DF6, I
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| i Values are taken from Tables E-7 through E-10. Reg. Gukle 1.109 (Rev.1)3of* NUEEG on 7, I iqn g, Resoluuons of the unhs yields: ''db *
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| $,i ..
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| Ri =, (1.409) (DFAy infant (ODCM Rar Table 5.2.1)
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| \ .n. . in l R1 = (3.7E9) (DF6) cnid (ODCM fort 111 Table 5.2.2) l % /%:Le l
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| Ri = (8.DE9) (DFA i d teen ard eduft (ODCM Part ill Tabloc 5.2.3 and 5.2.4) g g s, e
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| .ol!'s r"4hmm!
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| /"' jI M s i hi giGr %j,p 3;jil 4ir jn I Q. ,' Yilli$V
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| '4ik , }y%*
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| ilh' N.
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| * 4
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| ! NF Ng. ' 5ft l!! gob l
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| 5' E21
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| l l
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| l
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| ~
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| p TMl RadknogcolControis Departmental Procedure 6610-PLN-4200.01 Ties Ammon No.
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| Offsite Dose Calculation Manual (ODCM) 11 APPENDIX C Mi. Ground Plane Pe#moy Does Factor
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| ' % '= k' k* (SF) (DFG,) [(14 4)/JJ (Eq C-1)
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| * whwe k' = conversion tector,1E6 pCl/microcune pg, s'
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| 2 10 .
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| ii k= conversion tector, s7ao hr/yr - jn
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| (%s- -
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| y .
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| 2, = decay oorstent for the P radionudde, see -' . '%,f,,,
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| : q. g i= the aposure time (ths cweuhman assunes that deany & tts ork operating removal mechanism) 4.73 x 10' e c. (15 yrs). Reg. Guide 1.109 (Rev.1). AppendixC"'"'""*
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| - '"l!ij DFG = 3 the ground plane does coreversion factor for(mrom/hr the f N,. per%
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| pCi/ma). Values are taken from Tabie E4. Reg. Guide 1.109 (Rev.1)j Thear values aoniv to all ane aroups
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| ,..... y H Ut-E G. Ot3 2 SF = 0.7. shiekkng factor, from Table E-15 [Lgg."Gude 1.100 (Rev.1)
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| Reference ODCM Part til Table 5.34 g;!!:;q::g, sm,n % lim
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| ,p Nwd
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| ,n g
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| w, g ;!!! al
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| $j ,, { $111lf
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| ~ lll l} f!
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| thy G.
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| E31 m*
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| - ~ ~
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| l
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| . Numtw d TMI Radiologksi Controls W EI Departmertal Procedure 6610-PLN-4200.01 rn h= on No.
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| OffaMe Dose Calculation Manual (ODCM) 3 APPENDIX D RI . Groes Cow 4411k Pethuey Dose Factor R, = k' ((Q, a U,) / (4 + J,,)] x (F ,) x (r) x W s l((f. A f.)/Y.) + (lbf, x f,) e Th)/YJ eTf (Eq D-1)
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| Where:
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| # l k' = cortversion factor,1ES picoeurte/truerocurie (pci/gi) f '"% l
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| -h 'li Q, - cow consumption rate, 50 kg/ day, (Reg. Guide 1.109. Aev.1) . f goet consumption ruta, 6 kg/ day. (Reg. Guide 1.109, pop 1, Table E-2)
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| ,%. y U, = Receptor's mik consumption rate; 330, 330,400, 310 leers /yr for Want, chld, teenager, and adult age groups, respectWy (Reg, Guide 1.100. Rep 1)dh. " l
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| +it w l Y, = agr6 cultural prodt.s:tMey by unt area of pasti$e feb grass. 0.7 kg/m' (NUREG 0133)
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| Y, = agrictAural producsMty by una area',of stored seed,2.0 kg/m' (NUREG4133)
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| F. = stable element transfer c F E-1, Reg. Guide 1.100. Rev.1) r= traction of deposr.ed actMy retained in cow's toed grass. 0.2 for particulates,1.0 for radioiodine Fable E 15. Reg Guide 1.109, Rei.^1) y my_3 DFL = the ingestion done betor for organ, o, and the kh radionuclide for each respectow age group, a i Fables E 11 to E-142,gGuide 1.109. Rev.1)g NoEE(. o'tt on t j J, = condanilor the th radionuclide, sec' decay $"""",, %
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| j 4 = decay constatq for weathenng,5.73 x 10'sec'' (NUREG 0133); based on a 14 day half life ;
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| t, = 0 kNf the transport time from pasture to cow to mDk to receptor Fabie E 15, Reg.
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| .g Guide 1.109, Rev.1), or 2 days l N;p "ip l t, = "7.78 x to'sec, the transport time from pasture to harvest to mw to milk to receptor Uable E-15.
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| Reg. Guide 1.109, Rev.1), or 90 days ,
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| f, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture E4-1 m
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| | |
| E l
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| _ #6 ,nter g UI TMl Radiologicsd Cornrds Depenmermd Procedure 6610-PLN-4200.01 no. a==r, ate.
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| Offsite Dose Calcmalation Manual (ODCM) 11 APPENDDC D (Cortd)
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| The cor%WM of trtkJm in mik is based on the airbome conconmuuon rather than the depostion Therefore. R i is based on (X/Q): -
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| R8 = k'k" F, Q, U,D( (.75 [.5/H]) (Eq D-2)
| |
| Where:
| |
| d, p*i g_ i k" = 1E3 grams /kg *
| |
| ,e .{ e$
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| a
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| ,,N 8 ' !h : !..<uth H= 8 grams /m , absolute humdiry of the annosphere 4!(pP".f i
| |
| 4>g wil
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| .75 = fractson of the total feed grass mees that is water .. Sig 31g
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| *Q"%Jb
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| .5 = ratio of the specMc ac Mry of the feed grass wueer to'the atmospheric water (NUREG.0133)
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| ,-(wry <
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| D( = the ingeston dose factor for tritium and Orgen, o, for each respedive age group, a (Tables E-11 to E 14, Reg. Gude 1.109, Rev.1),or MucEG ps7 2 ,,
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| , %uuj All other pararneters andn values are as gy#stpy.)'dg. i NDTE jfg\.f%f"h, Gost-rm palhuey tector. R,. wel be computed using the cow rnuk ,
| |
| pathway tector equemon. F lector for goet-mak we be from Table E-2 l
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| Reg.,.Guille 1.109, Rev.1.
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| l p% %, I
| |
| | |
| ==Reference:==
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| | |
| ODOM Part lilJab,les 5.4.110.5.4.4
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| 'Ilb. w .th liii di airi#
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| (i. g k ""' i fglh ygf 'itja, v
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| ' 'igiijg 9
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| E4-2 ::.
| |
| | |
| I l qqclggy wt Radwogwcontras \
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| Departmental Procedure 6610-PLN-4200.01
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| 're.. s on %
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| 1 I
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| Offstie Dose Calculation Manual (ODCM) 11 '
| |
| APPENDIX E l
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| Ri- Cow 44est Pathway Dose Factor l
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| R= l 3
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| k' l((f,((Q, x U,)
| |
| I f)/Y,) / Q +e J,)]Th)/Y ] x e#fx (F,) x (r) x (Dy x
| |
| + (M,f.) , (Eq E-1). {
| |
| Where; j
| |
| fi i i
| |
| k' = conversion factor,1E6 picoeuria/ microcurie (pCi/pci)J
| |
| [
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| I
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| *{ l Q, = cow cortsumpuon rate. 50 kg/ day, (Reg. Guide 1.'109, Revq p **
| |
| : g. y j U, = Receptors mest consumption rate; 0, 41, SS,110 l'g/yr for.indant, child, teenager, and adutt age groups. '
| |
| respectively (Reg. Guide 1.109, Rev.1) , '" 7' Q lg.
| |
| % *!L F, = the stable elemert trartster coefficients, days /kg (TatSe E4, Reg. Guitte 1.109 Rev.1) r= ained r' i chs feed grgss, 0.2 for particulstes,1.0 for radiciodine traction (Table E 15,of deposhed Reg. Guide 1.109,actMty
| |
| . g{ re'.Rev 1) j
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| .,n - % l DFQ = the mgestion dose tactor for orgah, 0; and the Ith radionuclide for each respecthe age group, a (Tables E-11 to E-14, Reg. Guide,1109?Rev.1),or NUEGG 0172-3 p%?%
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| * A, = decay constars for the radenucNde I,"sec4
| |
| $% N J,, = decay consiant foy weathering; 5.73 x 10# seed (NUREG 0133), based on a 14 day half life t, = 1.73 x 10' x.ithe transport time trorn pasture to receptor (NUREG4133) - l ff .e %
| |
| I t,=
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| i 7.78 x 1dsedhe t$tnsport time from crop to receptor (NUREG4133) g gg niew Y, = agrictitdalpAxiuctutry by unit area of pasture feed omss 0.7 kg/m (NUREG4133) 2
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| %f %
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| Y, = agriSUltural productwky by una area of stored femi,2.0 kg/m2 (NUREG4133) f, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, t'he tracDon of the cow feed that is pasture grass while the cow is on pasture The concentration of tntium in mest is based on the airbome concentration rather than the deporAon. Therefore, R,is based on (X/Q)-
| |
| R m a k*k"* F, Q, U, (DFQ) x 0.75 x (0.5/H]) (Eq E 2)
| |
| Where:
| |
| M terms are as defined above ard in Appendix D.
| |
| , Reference- ODCM Part 111. Tables 5 6.1 to 5.6.4 ES-1 =6
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| _ - - - , - - . - - - - - - - - , . . - - - - - -}}
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