ML17297B856

Revised Offsite Dose Calculation Manual

ML17297B856
Person / Time
Site:	Palo Verde
Issue date:	01/12/1982
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
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ML17297B855	List: ML17297B854 ML17297B856
References
PROC-820112, NUDOCS 8301130083
Download: ML17297B856 (119)

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OFFSITE DOSE CALCULATION HANUAL PALO VERDE NUCLEAR GENERATING STATIOiN UNIT 1/J'ev.0 1/12/82 8301130083 830iii PDR ADOCK 05000528 A PDR

~p-,>I C OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION TABLE OF CONTENTS Section

1.0 INTRODUCTION

Title~Pa e 2.0 GASEOUS EFFLUENT MONITOR SETPOINTS 2.1 Plant Stack-RU-143&144 4 3.0 4.0 2.2 Condenser Evacuation System-RU-141&142 2.3 Fuel Building Vent Exhaust-RU-145&RU-146 GASEOUS EFFLUENT DOSE RATE 3.1 Noble Gases 3.2 Radionuclides Other Than Noble Gases DOSE DUE TO GASEOUS EFFLUENT 4.1 Noble Gases 7/10 10 16 16 5.0 6.0 7.0 4.2 Iodine-131 Tritium and All Radionuclides in Particulate Form Other Than Noble Gases TOTAL DOSE OPERABILITY OF EQUIPMENT RADIOLOGICAL ENVIRONMENTAL PROGRAM 7.1 Radiological Environmental Monitoring Program 7.2 Census Program 17 36 39 40 40 APPENDIX A Sample Calculations 50 C~I E P~r OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNIT I List of Tables Table No.3-2 3-3 4-2 4-4 4-5 4-6 4-7 4-8 4-9 4-10 Title ANNUAL RADIOLOGICAL EFFLUENT OBJECTIVES AND STANDARDS 10CFR 20 MPC LIMITS DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS PALO VERDE NUCLEAR GENERATING STATION UNIT 1 DISPERSION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY P VALUES FOR THE PALO VERDE GENERATING STATION R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=: GROUND R VALUES FOR THE PALO VERDE NUCLEAR GENERATIiNG STATION PATHWAY=VEGET, AGE GROUP=ADULT R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=VEGET, AGE GROUP=TEEN'VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=VEGET, AGE GROUP=CHILD R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATkkWAY=MEAT, AGE GROUP=ADULT R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=MEAT, AGE GROUP=TEEN R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=MEAT, AGE GROUP=CHILD R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=: COW MILK, AGE GROUP=ADULT R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=COW MILK, AGE GPOUP=TEEN R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=COW MIKL, AGE GROUP~CHILD~Pa e 13 14 15 20 21 22 23 24 25 26 27 28 29

~l y l~E List of Tables (Continued)

Table No.4-11 4-12 4-13 4-14 Title R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATXON PATHWAY=COW MILK, AGE GROUP=INFANT R VALUES FOR THE PALO VERDE NUCLEAR GENERATXNG STATXON PATHWAY=INHAL, AGE GROUP=ADULT R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=INHAL, AGE GROUP=TEEN R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=INHAL, AGE GROUP=CHILD~Pa e 30 32 33 4-15 4-16 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY=INHAL, AGE GROUP=INFANT PALO VERDE NUCLEAR GENERATING STATION UNIT 1 DISPERSION

.35 PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST RESIDENCES RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION 43 LOCATXONS 7-2 7-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS-47 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGFAM 0~~I r

1.0 INTRODUCTION

The purpose of this manual is to provide the parameters and methodology to be used in calculating offsite doses and effluent monitor setpoints at.the Palo Verde Nuclear Power Plant, Unit 1.Included are methods for determining maximum individual, whole body, and organ doses due to gaseous effluents to assure compliance with the dose limitations in the Technical Specifications.

Hethods are included for performing dose projections to assure compliance with the gaseous treatment system operability sections of the Technical Specifications.

This manual includes the methods used for determining quarterly and monthly individual doses for inclusion in Effluent and Waste Disposal Semi-annual Reports.The dose models consider only one release mode-airborne.All/gaseous effluents are treated as ground level releases.Airborne releases are further subdividied into two subclasses:

a.Iodine-131 Tritium and Radionuclides in Particulate Form with Half-lives Greater than Ei ht Da s In this model, a critical location is identified for assessing the maximum exposure to an individual for the various pathways and to critical organs.Infant exposure occurs through inhalation and any actual milk pathway.Child, teenager and adult exposure derives from inhalation, consumed leafy vegetable and produce pathways, and any actual milk and meat pathways.Dose to each of the seven organs listed in Regulatory Guide 1.109 (bone, liver, total body, thyroid, kidney, lung and GI-LLI)are computed from individual nuclide contributions in each sector.The largest of the organ doses in any sector is compared to 10 CFR 50, Appendix I design objectives.

This dose calculation is performed monthly for all age groups.As necessary, the release rates of these nuclides will be converted to dose rates for comparison to the limits of 10 CFR 20.

Il s I OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNIT 1 List of Fi ures Fi ure No.6-1 Title Basic Flow Diagram Liquid Radwaste System Sheet 1 of 2~Pa e 39A 6-1 Flow Diagram Liquid Radwaste System Sheet 2 of 2 39B 6-2 6-3 Basic Flow Diagram Gaseous Radwaste System Basic Flow Diagram Solid Radwaste System Radiological Environmental Monitoring Program Sample Sites 39C 39D 42A I 1 s'r l b.Noble Gases Exposure to the beta and gamma radiations of the noble gases will result in a whole body and skin dose.The maximum whole body and skin doses for each offsite sector are determined from the individual nuclide.contributions and the maximum dose values are compared to the 10 CFR 50, Appendix I design objectives.

This calculation is performed monthly.As nece'ssary, the noble gas release rate will be converted to dose rates for comparison to the limits of 10 CFR 20.This manual discusses the methodology to be used in determining effluent monitor alarm/trip setpoints to be used to assure compliance with the instantaneous release rate limits in the Technical Specifications.

Hethods are'escribed for determining the annual cumulative dose to a real individual from gaseous effluents and direct radiation for critical organs to assure compliance with 40 CFR 190 limits.The calculational methodology for doses is based on models and data that make it unlikely to substantially underestimate the actual exposure of an individual through any of the appropriate pathways.The annual dose limits of 10 CFR 50, Appendix'I and 40 CFR 190 are summarized in Table 1-1.The Radiological Environmental Honitoring Program is described in this manual, also included is the Annual Land Use Census Survey.The ODCH will be maintained at the station for use as a document of acceptable methodologies and calculations to be used in implementing the Technical Specification.

Changes in the calculational methods or parameters will be incorporated into the 1'DCH in order to assure that the ODCH represents the present methodology.

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TABLE 1-1 ANNUAL RADIOLOGICAL EFFLUENT OBJECTIVES AND STANDARDS NOBLE GAS EFFLUENTS 10 CFR 50 APPENDIX I DESIGN OBJECTIVES (PER REACTOR UNIT, ABOVE BACKGROUND) 40 CFR 190 STANDARD S (ALL REACTOR UNITS COMBINED)Gamma Dose in Air Beta Dose in Air----------Dose to total Body of an Individual Dose to Skin of an Individual 10 MRAD 20 MRAD 5 MREM 15 MREM RADIOIODINES AND PARTICULATES Dose to Any Organ from All Pathways TOTAL URANIUM FUEL CYCLE 15 MREM Dose to Cycle Dose to Cycle Dose to Cycle Whole Body from All Fuel Operations Thyroid from All Fuel Operations any Other Organ from All Fuel Operations 25 MREM 75 MREM 25 MREM TOTAL ANTITI ES RELEASE Krypton-85 Released Per Gigawatt-Year Iodine-129 Released Per Gigawatt-Year Combined Plutonium-239 and Other Alpha-emitting Radionuclides with Half Lives Greater than One Year Released per Gigawatt-Year 50,000 CURIES 5 MILLICURIES

.5 MILLICURIES gr'I i I

2.0 GASEOUS

EFFLUENT HONITOR SETPOINTS S ecification 3.3.3.10-The radioactive gaseous effluent.monitoring instrumentation channels shown in Table 3.3-12 of the Technical Specifications shall be operable with their alarm/trip setpoints set to ensure that the limits of specification 3.11.2.1 are not exceeded.The alarm/trip setpoints of these channels shall be determined in accordance with the methodology described in the ODCM.Setpoints are conservatively established for each effluent, monitor so that the instantaneous dose rates corresponding to 10 CFR 20 annual dose limits in unrestricted areas will not be exceeded Conservatism is to be incorporated into the determination of each setpoint to account for: P o All exposure pathways of significance at the critical receptor locations; o Dose contributions to critical receptors from multiple release points;and o Dose contributions from major radioisotopes expected to be present in gaseous effluents.

The general methodology for establishing plant gaseous effluent monitor setpoints is.based upon vent release concentrations (pCi/cc)derived from site-specific meteorological dispersion conditions, vent flow rates and the maximum permissible concentration (HPC)from 10 CFR Part 20 for the limiting radionuclide.

The HPC limits are tabulated in Table 2-1.Administrative values are used to reduce each setpoint to account for the potential activity in other releases.These administrative values shall be periodically reviewed based on actual release data and revised in accordance with the Unit Technical Specifications.

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2.1 Plant

Stack-RU-143&.144 For the purpose of implementation of Specification 3.3.3.10, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and meterorological dispersion factor.The setpoint for the detector is determined by using: C<(.5)(2120)MPC (2-1)(X/Q)S>(flow rate)Vhere: the instantaneous concentration at the detector in yCi/cc MPC the 10CFR Part 20 concentration for the limiting radionuclide present in sample analysis in yCi/cc (i.e., smallest MPC)from Table 2-1.flow rate=the plant vent flow rate in cfm 140,610 cfm (X/Q)S>=6.49 E-6 sec/m , the highest annual 3 average atmospheric dispersion parameter from Table 3-2.2120 conversion of cfm to m/sec 3-0.5 an administrative value used to account for potential activity from other gaseous release pathways.The alarm setting is determined by using the calibration curve for the applicable Plant Stack Airborne Monitor.

~M I l I II The alarm setpoint is the cpm value corresponding to the concentration, C, which is conservatively assumed to be the isotope of greatest sensitivity for the monitor.2.2 Condenser Evacuation S stem-RU-141 6 142 For the purpose of implementation of Specification 3.3.3.10, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and meteorological, dispersion factor.The setpoint for the detector is determined by using: C<(.3)(2120)MPC (X/Q)S~(flow rate)(2-2)'Where: the instantaneous concentration to the detector in pCi/cc.MPC the 10CFR Part 20 concentration for the limiting radionuclide present in sample.analysis in pCi/cc (i.e., smallest MPC)from Table 2-1.flow rate=the condenser evacuation system flow rate in cfm.2,960 cfm.(X/Q)S>=6.49 E-6 sec/m , annual highest average 3 atmospheric dispersion parameter from Table 3-2.

l J 2120 conversion of cfm to m/sec.3 0.3 an administrative value used to account for potential activity from other gaseous release pathways.The alarm setting is determined by using the calibration curve for the corresponding Condenser Evacuation System Monitor.The alarm setpoint is the cpm value corresponding to the concentration, C, which is conservatively assumed to be the isotope of greatest sensitivity for the monitor.2.3 Fuel Buildin Vent Exhaust-RU-145 6 RU-146 For the purpose of implementation of Specification 3.3.3.10, r P the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and meteorological dispersion factor.The setpoint for the detector is determined by using: C<(.2)(2120)MPC (X/Q)(flow rate)(2-3)Mhere: instantaneous concentration at the detector in yCi/cc.MPC the 10CFR Part 20 concentration for the limiting radionuclide present in sample analysis in pCi/cc (i.e., smallest MPC).flow rate=fuel building vent exhaust flow rate in cfm 55,500 cfm.

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(X/Q)SB the highest annual average dispersion parameter from Table 3-2.6.49E-6 sec/m 3 2120 conversion of cfm to m/sec.3 0.2 an administrative value used to account for potential activity from other gaseous release pathways.The alarm setting is determined by using the calibration curve for the applicable Plant Stack Airborne lionitor.The alarm setpoint is the cpm value coresponding to the concentration, C, which is conservatively assumed to be the isotope of greatest sensitivity for the monitor.

~(I C Table 2-1 10CFR20 MPC LIMITS (uCi'/cm3)

MJCLIDZ I'PC LIMIT (pCi/cm3)KR-83M KR-85M KR-85 IK-87 KR-88 KR-89 XE-131M XE-133iM XE-133 XE-135M XE-135 3P 137~138 BR-83 BR-84 BR-85 I-130 I-,131 I-132 I-133 I-134 I-135 CO-60 CO-58 FE-59~-54 CS-137 CS-134 SR-90 SR-89 H-3 C-14 AR-41': 3~8=3x10-8 3~~8" 1E-7 3E-7 2E-8 2E-8 3<8 4E-7 3<~7 3E-7 3E-8 1E-73~~8 3E-8 lE-10 3E-8 3E-8 1E-10 1E-10 3E-9 4E-10 6E-9 lE-9 3E-10 2E-9 2E-9 lE-9 5>~10 4E-10 3E-11 3E-10 2E-7 lE-7 4E-8

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3.0 GASEOUS

EFFLUENT DOSE RATE S ecification 3.11.2.1-The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a.Noble gases-Less than or*equal to SOO mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin.b.Iodine-131,tritium, and for all radionuclides in particulate form with half-lives greater than 8 days-Less than or equal to 1500 mrems/yr to any organ (inhalation pathway only).3.1 Noble Gases Noble gas activity monitor setpoints are established at.-release rates which permit some margin for corrective action to be taken before exceeding offsite dose rates corresponding to the 10 CFR 20 annual dose limits as described in Section 2.0.The methods for sampling and analysis of continuous ventilation releases are given in the applicable Plant Pro-cedures.The'dose rate in unrestricted areas due to radio-active materials released in gaseous effluents may be averaged over a 24-hour period and sha'll be determined by the following equation for whole body dose: D b=E.K.(X SB (3-1)and by the following equation for skin dose: D s I=Z.(L.+1.1H.)(X/Q)SB Q.(3-2)

E I Where: K.i the whole body dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrem/yr per pCi/m from 3 Table 3-1~Q.the release rate of radionuclide, i, yCi/sec.r (K/Q)SE the highest calculated annual average relative concentration for any area at the site boundary 6.49 E-6 sec/m from Table 3-2.D wb the annual whole body dose (mrem/yr).

L.i the skin dose factor due to the beta emissions for each identified noble gas radionuclide, i, in mrem/yr per pCi/m from Table 3-1.3 the air dose factor due to gamma emissions for each'identified noble gas radionuclide, i, in mrad/yr per yCi/m from Table 3-1 3 (conversion constant of 1.1 converts air dose-mrad to skin dose-mrem).

D the annual skin dose (mrem/yr).

3.2 Radionuclides

Other Than Noble Gases The methods for sampling and analysis of continuous-ventilation releases for radioiodines, radioactive particulates and other radionuclides except noble gases, are given in the applicable Plant Procedures.

Additional monthly and quarterly analyses shall be performed in accordance with Table 4.11.-2 of the PVNGS Technical Specifications.

The dose rate in unrestricted areas due to radioactive materials

~~~l released in gaseous effluents may be averaged over a 24-hour period and shall be determined by the following equation for any critical organ dose: D 0 E.(P.)(X/Q)SB (Q.)(3-3)Mhere: P.i the dose parameter for radionuclide, i," other than noble gases for the inhalation pathway (mrem/yr per pCi/m)from Table 3-3.3 (X/Q)S>=the highest, calculated annual average dispersion parameter for estimating the dose to an individual from Table 3-2.3 6.49 E-6 sec/m for the inhalation pathway The location is at the site boundary in the N sector.Q the release rate of radionuclide (i)(pCi/sec)in gaseous effluents.

D 0 the annual organ dose (mrem/yr).

Sample calculations for determing doses to critical organs from radionuclides other than noble gases released from PVNGS are given in Appendix A.

5 t I TABLE 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Radionuclide Whole Body Dose Factor Ki (mrem/yr per pCi/m Skin Dose Factor Li (mrem/yr per pCi/m Gamma Air Dose Factor Mi (mrad/yr per pCi/m Beta Air Dose Factor Nl (mrad/yr per pCi/m Kr-83m Kr-85m Kr-8 5 Kr-8 7 Kr-58 Kr-89 Kr-9 0 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-13 7 Xe-138 Ar 141 7.56E-02b 1.17E+03 l.61E+01 5.92E&3 1.4 7E+04 l.66E+04 l.5 6E+04 9.15E+01 2.51E+0 2 2.94E&2 3.12E+03 l.81E&3 1.42E+03 8.83E+03 8.84E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.1 lE+02 1.86E&3 l.22E+04 4.13E&3 2.69E+03 1.93E+Ol 1.23E+03 1.72E+01 6~17E+03 l.52E+04 l.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51E+03 9.21K+03'.30E+03 2.88E+02 1.97E&3 1.95E+03 1.03E&4 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03 The listed dose factors are for radionuclides that may be detected in gaseous effluents and derived from Table B-1 in Reg.Guide 1.109.i b7 56E-02=7.56 x 10 2 W I~t'C Table 3-2 Palo Verde Nuclear Generating Station Unit 1 Dispersion Parameters for long term releases at the Site 3oundarg Direction Distance X/G (meters)(Sec/cub.meter)D/G (per sq.meter)N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1037.1057.2206.1967.1927.1967.2049.2730.3006.225S.1487.1251.1225.1244.1254.1069.6.49E-06 4.71E-06 2.81E-06 2.96E-06 2.98E-06 2.57E-06 3.34E-06 3.58E-06 4.49E-06 5:87E-06 5.SBE-06 4.41E-06 5.43E-06 4.SOE-06 4.12E-06 4.39E-06 1.05E-08 1.19E-08 6.60E-09 4.74E-09 3.54E-09 2.57E-09 2.30E-09 1.48E-09 1.55E-09 2.85E-09 4.37E-09 5.41E-09 9.13E-09 7.59E-09 6.72E-09 S.26E-09 t

TABLE 3-3 P Values for the Palo Verde Nuclear Generating Station-child-inhalation pathway TO BE SUPPLIED BY N.U.S.CORPORATION

~+l I t I I 4.0 DOSE DUE TO GASEOUS EFFLUENT 4.1 Noble Gases S ecification 3.11.2.2-The air dose due to noble gases released in gaseous effluents, from each reactor unit to areas at and beyond the SITE BOUNDARY shall be, limited to the following:

a.During any calendar quarter.-Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation.

b.During any calendar year-Less than or-.equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

The air dose in unrestricted areas beyond the site boundary due to noble gases released in gaseous effluents from the site shall be determined by the following equation for gamma radiation during any specific time period: 3.17 x 10 E.M.(X/Q)SBQ.(4-1)and by the following equation for beta radiation during any specified time period: 3.17 x 10 Z.N.(X/Q)SBQi (4"2)Where: M, the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per pCi/m from Table 3-1.3 the air dose factor due to beta emissions for each identified noble gas radionuclide, i, in mrad/yr per yCi/m from Table 3-1.3 I C E l i

(~/0)SB the highest calculated annual average relative concentration for any area at the site boundary (sec/m)from Table 3.2.3 the total gamma air dose from gaseous effluents for a specified time period (mrad).~.the total beta air dose for gaseous effluents for a specified time period (mrad).the integrated release of each identified noble gas radionuclide, i, in gaseous effluents for a specified time period-(yCi).

3.17 x 10 the inverse of seconds in a year (yr/sec).The cumulative gamma air dose and beta air dose for a quarterly or annual evaluation shall be based on the calculated dose contribution from each specified time period occurring during the reporting time period.A discussion of the method used to calculate the individual dose from gaseous effluents is given in Appendix A.Also, sample calculations for determining gamma and beta air doses from noble gas radionuclides released from the PVNGS are given there.4.2 Iodine-131 Tritium and All Radionuclides in Particulate Form Other than Noble Gases Specification 3.11.2.3-The dose to a HENBER OF THE PUBLIC from iodine-131, tritium and all radionuclides in particulate form with half-lives greater than 8 days at or beyond the SITE BOUNDARY shall be limited to the following:

a.During any calendar quarter-Less than or equal to 7.5 mrems to any organ.

r I 1 l~t I b.During any c'alendar year-Less than or equal to 15 mrems to any organ.The dose to a realistic individual from radioiodines, radioactive materials in particulate form and all rdionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to unrestricted areas is'I calculated using the following expressions:

D=3.17 x 10 E.o0 1"k"Pko'(4-3)Mhere: D 0 the total projected dose from gaseous effluents to an individual, in mrem, at the, nearest residence in Sector, 0.the amount of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days, i, released in gaseous effluents in pCi.R.ik the dose factor for each identified radionuclide, i, for pathway k (for the inhalation pathway in mrem/yr per yCi/m and 3 for the food and ground plane pathways in m 2 mrem/yr per yCi/sec)at the controlling location.The R.k's for each age group are ik given in Tables 4-1 through 4-15.V Vk0=the annual average dispersion parameter for estimating the dose to an individual at the closest residence in Sector, 0, and for pathway, k.

~~I 3.17 x 10 (X/Q)for the inhalation pathway in sec/m 3 The (X/Q)for the nearest residence in Sector, 8, is given in Tables 4-16.(D/Q)for the food and ground plane pathways in-2 m.The (D/Q)for the nearest residence in Sector 8 is given in Table 4-16.the inverse of seconds per" year (yr/sec).In order to provide a conservative estimate of the doses, each of the nearest residences is assume to have a milk animal, a meat animal and a vegetable garden.The'y provide the maximally-exposed individual with 100%of his dietary intake.The R.values were calculated in accordance with i the methodologies in NUREG-0133 and generated using the GASPAR code.The following site specific information was used to calculate them: Value fraction of year milk animals and beef animals are on pasture 0.75 fraction of daily intake of milk animals and beef animals derived from pasture while on pasture 0.35 fraction of year vegetables are grown 0.667 absolute humidity (g/m)over the 3 growing season These site specific values are from the PVNGS Environ-mental Report, Section 2 and Appendix B-7.The long-term meterological dispersion parameters were obtained from the Section 2.3 of the PVYGS ER-OL.

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TABLES 4-1-4-15 R Values for the Palo Verde Nuclear Generating Station TO BE SUPPLIED BY N.U.S.CORPORATION Pages 20-34 S~3 I~f 1 (

Table 4-16 Palo Verde Nuclear Generating Station Unit 1 Dispersion Parameters

%or long term releases at the Nearest residences Direction Distance (meters3 X/8 (Sec/cub.meter 3 D/G (per sq.meter)N NNE NE ENE E ESE SSE$$4t SW NW fwNW 2300.2900.3000.4300.5100.5700.7300.7200.5500.6800.3600.3700.3.92E-06 2.12E-06 i.98E-06 i.27E-06 9.63E-07 b.59E-07 i.25E-06 2.35E-06 2.97E-06 i.86E-06 i.69E-06 i.57E-06 3.60E-09 2.82E-09 3.87E-09 i.21E-09 6.02E-10 3.19E-10 2.60E-10 4.39E-10 7.48E-10 4.61E-10 i.41E-09 i.38E-09

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5.0 TOTAL

DOSE S ecification 3.11.4-The annual calendar year dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to 1'ess than or equal to 75 mrems.The cumulative dose to any member of the public due to" radioactive releases from the PVNGS site is determined by summing the calculated doses to critical organs from the previously-discussed effluent sources.The annual dose to critical organs of a real individual for the noble gases released in the gaseous effluents is determined by using.D=3.17 x 10 E.wb i K (X/Q)Q.

(5-2)ii'here: K.i the whole body dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrem/yr per pCi/m from Table 3-1.Q.the release rate of radionuclide, i.the highest calculated annual average relative concentration for the nearest residence in Sector, 0, in sec/m from Table 4-16.3 D wb the annual whole body dose (mrem/yr)due to gamma emmissions.

,~I L.i the skin dose factor due to the beta emissions for each identified noble gas radionuclide, i, in mrem/yr per pCi/m from Table 3-1.3 the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per pCi/m from Table 3-1 3 1 (conversion constant of 1.1 converts air dose-mrad to skin dose-mrem).

D s the annual skin dose (mrem/yr).

The annual dose to critical organs of a real individual for the radionuclides other than noble gases released in the gaseous effluents is determined by using: D=317x10 E.o8 i"k RiA8)Qi (4-3)Mhere: D 8 the total projected dose from gaseous effluents to an individual, in mrem, at the nearest residence in Sector, 8.Q the amount of radioiodines, radioactive materials in particulate form and rdionuclides other than noble gases with half lives greater than eight days, i, released in gaseous effluents in pCi R k the dose factor for each identified radionuclide, i, for pathway k (for the inhalation pathway in mrem/yr per pCi/m and 3 for the food and ground plane pathways in 2 m-mrem/yr per yCi/sec)at the controlling location.The R.k's for each age group are ik given in Tables 4-1 through 4-15.

1 WkO=the annual average dispersion parameter for estimating the dose to an individual at the closest residence in Sector, O, and for pathway, k.(X/Q)for the inhalation pathway in sec/m 3 The (X/Q)for the nearest residence in Sector I 0, is given in Table 4-16.(D/Q)for the food and ground plane pathways in-2 m The (D/Q)for the nearest residence in Sector 6 is given in Tables 4-16.For all dose calculations from gaseous effluents, the annual/average relative concentration or relative deposition rate.used in the analysis should be at the receptor location of the individual being evaluated, the nearest residence in each sector.These annual average dispersion parameters are given in Table 4-16.The direct radiation from the site should be determined from the environmental monitoring program's direct radiation (TLD)monitors'ince all other uranium fuel cycle sources are greater than 20 miles away, only the PVNGS site need be considered as a uranium fuel cycle source for meeting the EPA regulations.

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6.0 OPERABILITY

OF E UIPlfENT The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous, and solid waste management systems are shown in Figures 6-1 through 6-3.

1 i't~:i~,'

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7.0 RADIOLOGICAL

ENVIRONHENTAL PROGRAH 7.1 Radiolo ical Environmental Honitorin Pro ram S ecification 4.12.1.1-The radiological environmental moni-toring samples shall be collected pursuant to Table 3.12-1 of the Technical Specifications from the specific locations given in the table and figure(s)in the ODCH, and shall be analyzed pursuant to the requirements of Table 3.12-1, and the detec-tion capabilities required by Table 4.12-1 of the Technical Specifications.

Environmental samples will be collected at..locations shown in Figure 7-1 and described in Table 7-1.Analytical techniques used will ensure that the detection capabilities in Table 7-2 t are achieved.Environmental samples will be collected and analyzed according to Table 7-3.The results of the radiological environmental monitoring pro-gram are intended to supplement the results of the radiologi-cal effluent monitoring by verifying that the measurable con-centrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure path-ways.Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionu-clides which lead to the highest potential radiation exposures of individuals resulting from station operation.

The initial radiological environmental-monitoring program will be con-ducted for the first three years of commercial operation of Unit 1.Following this period, program changes may be pro-posed based on operational experience.

Deviations are per-mitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavaila-bility, malfunction of automatic sampling equipment and other legitimate reasons.

• re' If specimens are unobtainable due to sampling equipment malfunction, an effort shall be made to complete corrective action prior to the end of the next sampling period.All deviations from the sampling schedule shall be documented in the annual report.Specification 3.12.2-A land use census shall be conducted and shall identify within a distance of 8 km (5 miles)the loation in each of the 16 meterological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m (500 ft)producing broad-leaf 2 2 vegetation.

A land use census will be conducted to identify the location of the nearest milk animal and the nearest residence in.each of the 16 meteorological sectors within a distance of five miles.Vhen a land use census identifies a location(s) which yields a calclated dose or dose commitment greater than the values calculated from current sample lcoations, appropriate changes in the'ample locations will be made.If a land use census identifies a location(s) with a higher average annual deposition rate (D/Q)than a current indicator location, the following shall apply: l.If the D/Q is at least 20%greater than a previously high D/Q, one of the existing sample locations may be replaced after an evaluation with a new one within 60 days.Evaluation will be based on past, history of the location, availability of sample, milk production history and other environmental conditions.

0 0

'P~2.If the D/Q is not 20/greater than the previously highest, D/Q, distance and D/Q will be considered in deciding whether to replace one of the existing sample locations.

If applicable, replacement shall be within 30 days.A land use census will be conducted at least once per calendar year by a door-to-door or aerial survey, by consulting local agricultural authorities or by any combination of these methods.

I}S Ie t'i I/~W 3 I 1 N~'!JO~I~~W Vffet~SAIK S<SV>>t OO<<O<<I<<S}ttl II 1~(N+ee IA>>tA'N~IC el el N s~~~~ee ee JI I>><1~<>>e>>sr OONP s\~~~/~'s;s~Ol<<se IW sr>>I,~<1}V I s I~+'OA/}44!s~e NI IS N>>t}S~rr~/<>>/: s'./!iPfpr./L",~Ie Ie<<K~I N l(eo>Y" r/5!1~/Nr Ss'N N I~)K//r s r/s 4 r j>>/A//r'~4NWI SS r}~, 4'-l~,.f.J N~~Qs/'J~I//O O I)I I<s/'!/N/4 s"-I te js.~I 4}'<<e tv le>>I 35"'N W tet I sle I Q I 5~.'aff f>>1'~~I~>>'s Sr ON, 1>>ON I N~I e I I 1 3 AJ<<N~~~el e le N J APSO es>>3 I I 3>>.e~I l5sl~J 10>>~'Y~s\, 50 I ls I Ne 5 I3 I 35~~Iy Psb Vst<!e I<<st}sot Contest>>13 ltl>>s 7+<~>>~~~~<O~N 1~55 hl~25 2,~I IS r'/ts'N eo I}IC".Irl/s I ON IN<e ss'r>>~3 O I~I~J.e<ito ceo+>>I f 5.I/1/,t/l I'/NIONS (~IN A>>r I>>I Ie~~51~.j!I I" vA n t<K~~~>>fs">>r ,er>-.'f ttaSs>>A tsee 0<<NO NNOOO 4 1 I>>ffs~~~,'k I~N O'I>>N>>>>O s 10~~>>I N te~~~J set.~)~~l I>>I e el~Il SAON<<>>~~>>'s~~~)I Sb N ff e, A s~Y l h<<YAN ffe'>>5 0<<~~t s.}>>r~*h/~'~~AIO<<le IS~It J~II:,JN e:.5 S<<l lOKI~~~N~N>>Q<Ne N~<<~fe~~}I<<N b.>>I~fj~~A<<s~~>>ttl<<<<ro s~It>>r I/~I 1st I~g r O s It L41Y~l>>~sso N Ct'~g~A>>}I l rr I>>el N I 0>>eo~NS~~OO>>I~~I~~3~>>}I C 4~r~<4~'~~e 55 II5I 5~'~OAAC~~I~~~J 4>>~sv H e 0 e~I N N I N~I Y Palo Verde Nuclear Generating Station RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE SITES Figure 7-j.-.42A I r N Page 1 of 4 TABLE 7-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SAt%'LE COLLECTION LOCATIONS SAMPLE SiQPLE SITE TYPE LOCATION DESIGNATION LOCATION DESCRIPTION 1 TLD, Air 2-TLD 3 TLD E30 ENE24 H25 APS Goodyear Office Scott-Libby School Liberty School 10 12 13 14 14A 16 TLD, Air TLD TLD p Air TLD,'b'i TLD TLD TLD TLD TLD TLD Ai TLD Ai TLD E20 ESE15 SSE35 SE8 SSE5 S5 SE5 ESE5 E5 Nl NNE2 NNE2 ENE2 APS Buckeye Office Palo Verde APS Gila Bend Substation Arlington School Corner of 363rd Ave.&SPP Rd.Corner of 371st Ave.&SPP Rd.Corner of 355th Ave.&Ward Rd.Corner of 339th Ave.&Dobbins Rd Corner of 339th Ave.&B-S Rd.N Site Boundary NNE Site Boundary Buckeye-Salome Rd.&371st Ave.NE Site Boundary ENE Site Boundary

%I Page 2 of 4 TABLE 7-1 S&PLE SAP LE SITE TYPE LOCATION DESIGNATION LOCATION DESCRIPTION 17 TLD 17A 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Air TLD.TLD TLD TLD , Air TLD TLD TLD, Water (b)TLD TLD, Water (b)TLD TLD(b), Air TLD TU'" E2 E4 ESE2 SE2 SSE2 S3 SSM3 M5 SW5 WSW5 SSW5 MSW1 Wl E Site Boundary 351st Ave., 1 mi.S of B-S Rd.ESE Site Boundary SE Site Boundary SSE Site Boundary S Site Boundary SSW Site Boundary Benchmark at Baseline Ward Rd.8 Mell 18bbb Ward Rd.8 DF Well 2 Rd.Well 21 Cbb2 SM Site Boundary WSW Site Boundary W Site Boundary WNW Site Boundary NW Site Boundary g~ll I~~l Page 3 of 4.TABLE 7-1 S&PLE SAMPLE SITE TYPE LOCATION DESIGNATION LOCATION DESCRIPTION 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 TLD TLD TLD, Air TLD(b)TLD TLD TLD TLD(b), Air , Water (b)TLD TLD TLD TLD(b), Air TLD Water (b)NNW9 N5 NNE5 NE5 ENE5 WNW20 N8 N45 ENE35 ENE50 NNW9 NNW Site Boundary Yuma Rd.1/2 mi.W.of Belmont Rd.Corner Belmont Rd.&Van Buren Rd.Tonopah, Palo Verde'Inn Fire Station Corner of Wintersburg Rd.&Van Buren Corner of 363rd Ave'.&Van Buren Corner of 355th Ave.&Yuma Rd.343rd Ave., 1/2 mi.S.of L.Buckeye Trailer Park;Water at Red Quail Str.Harquahala Valley School Ruth Fisher School Vulture Mine Rd.School, Wickenburg APS El Mirage Office (Sun City)APS Headquarters (Phoenix)McArthur's Farm, Tonopah (4 (tt l r I Page 4 of 4 TABLE 7-1 S&FLE SAMPLE SITE TYPE LOCATION DESIGNATION LOCATION DESCRIPTION 47 48 49 50 51 52 53 54 55 56 Water Water (b)Water (b)Milk (b)Veg.Vegetation (b)Milk Milk Milk NNW6 SSE4 ESE4 NE7 E15 E15 E20 E25 E25 E50 Winter's Wells Well 14dbb Glover Residence, 351st Ave.&Dobbins Baisley Dairy, 331st Ave.&'Van Buren i Butler Dairy, P.Ver'de Rd.&Southern Cambron Farm, Miller Rd.&Broadway Kerr Dairy, Dean&Buckeye Rds.Skousen Dairy, Airport&Dobbins Lueck Dairy, Jackrabbit

&Hazen Rds.Paxton Dairy, Mcgueen&Ryan Rds.(a)Table J-l, NUREG-0654; distances are from centerline of Unit 2 containment.

'I (b)These samples fulfill the requirements of the NRC Technical Specifications; the other samples fulfill PVNGS station requirements.

I~l~t I I Page 1 of 2 TABLE 7-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSES Lower Limit of Detection (LLD)Analysis Water (pci/1)Airborne Particulate or Gas (pci/m3)Milk (pCi/1)Food Products (pCi/kg, wet)gross beta H-3 2000b 1 x 10-2, Mn-54 Fe-59 Co-58 Co&0 Zn-65 Z r-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 15 30 15 15 30 30 15 15 18 60 15 7 x 10 2 5 x 10 2 6 x 10-2 15 60 15 60 60 80 r I~~(I h 1 I Page 2 of 2 TABLE 7-2 aThe LLD is the smallest concentration of radioactive material in a sample that will be detected with 95%probability and with 5%probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

LLD=4.66s 2.22 EVY exp-AAt Where: LLD is the"a priori" lower limit of detection as defined above (as pCi per unit mass or volume)~Sb is the standard deviation of the backgound counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)E is the counting efficiency (as counts per transformation)

V is the sample size (in units of mass or volume)y'.22 is the number of disintegrations per minute per picocurie Y is the fractional radiochemical yield (when applicable) gis the radioactive decay constant for theparticular radionuclide, and At is the elapsed time between sample collection (or end of the sample collection period)and time of counting.In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background should include the contributions of other radionuclides normally present in the samples (e.g., potassium-40 milk samples).Typical Values for E, V, Y, and t should be used in the calculations.

It should be recognized the the LLD is defined as a~riorf, (before the fact)limit representing the capability of a measurement system and not as a 2osteriori (after the fact)limit for a particular measurement.

bLLD for drinking water.

I C<f~(

TABLE 7-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pa thway and/or Sample Sampling and Co 1 lee t ion Frequency Type and Frequency of Analysis Sampling Locations(a)

Airborne radioiodine Continuous sampling and particulates collected weekly Gross beta weekly;I-131 weekly;gamma spectrum monthly;composite of filters Twelve locations as listed in Table 7-1 Direct radiation TL dosimeters at location changed quarterly and annually Gamma dose quarterly and annually 45 locations (Nos.1-45)as described in Table 7-1 Waterborne Surface Ground Monthly Composite of weekly grab sample Quarterly grab sample Gamma spectrum monthly;tritium quarterly Tritium and gamma spectrums quarterly On-site reservoir and evaporation pond/On-site well Nos.34abb, 27ddc.Drinking (well)Composite sample one~onth period Gross beta and gamma spectrums monthly;tritium quarterly 24, 46, 49 Ingestion Milk Food products Semimonthly for.animals on pasture, other-wise monthly Monthly when available Gamma spectrum and radioiodine semi-monthly or monthly Gamma spectrum and radioiodine monthly 50, 51, 53-56 46, 51,52 I<V~r I APPENDIX A SAMPLE CALCULATIONS A.l GASEOUS EFFLUENT MONITOR SETPOINTS The monitor setpoints are calculated using the isotope of greatest s sensitivity for the monitor, Kr-85, and equations 2-1, 2-2, and 2-3.The MPC limit for Kr-85 is given in Table 2-1 and is 3.0 E-7 pCi/cm.The highest annual average atmospheric dispersion parameter at the site boundary occurs in the north sector and is 6.49 E-6 sec/m , and is found in Table 3-2.3 A.l.1 Plant Stack C<(0.5)(2120)MPC (X/Q)SE (flow rate)cfm 0<(0.5)(2120 m3/sec)(3.0 E 701/cm3)-(6.49 E-6 sec/m)(140,610 cfm)C<3.48 E-4 pCi/cm A.l.2 Condenser Evacuation System The setpoint for these monitors will be calculated by the method described in Section 2.23 and equation 2-2.The flow rate of this system is 2,960 cfm.cfm 0<(0.3)(2120 m/sec)(EPC)X/Q SE (flow rate tf~I~'J'I cfm 0<(0.3)(2120 m3/sec)(3.0 E 7-Ci/cm3)(6.49 E-6 sec/m3)(2,960 cfm)C<9.93 E-3 pCi/cm 3 This alarm setpoint is the cpm value corresponding to the setpoint concentration, C.This cpm value, will be determined during the calibration of these monitors.A.1.3 Fuel Building Vent Exhaust The setpoint for these monitors will be calculated by the method described in Section 2.3 and equation 2-3.The flow rate for this vent is 55,500 cfm.cfm 0<(0.2)(2120 m3/sec)(HPC)(X/A)SB flow rate (2-3)cfm C<(0~2)(2120 m3/sec)(3.0 E 70i/cm3)-(6.49 E-6 sec/m)(55,000 c f m)C~<3.53 E-4 pCi/cm 3 This alarm setpoint is the cpm value corresponding to the setpoint concentration, C.This cpm value will be determined during the calibration of these monitors.

C('I A.2 GASEOUS EFFLUENT DOSE RATE A.2.1 Noble Gases The methods used to calculate the annual whole body or skin dose rates are discussed in Section 3.1 of the text.The dose factors (K., L., M., N.')for noble gases and their daughters are r I.3.l.taken from Table 3-1.The highest annual average dispersion parameter at the site boundary occurs in the north sector and the value is taken from Table 3-2.Assuming a noble gas release rate of 279pCi/sec of Xe-133, and 634pCi/sec of Kr-85, the whole body is to be calculated, using equations 3-1, as follows: Dwb=Xi K'X/Q)SE Q'here: Ki 1.61 E+1~for Er-85 pci/m3 2.94 E+1~for Xe-133 pCi/m3 (X/Q)SE=6.49 E-6 sec/m Qi=279 pCi/sec for Xe-133=634 pCi/sec for Kr-85 D b=(1.61 E+1)(6.49 E-6 sec/m)(634 pCi/sec)+pci/m3 t (2.94 E+2~)(6.49 8-6 sec/m3)(279 pCi/sec)j pCi/m Dwb=0.60 mrem/yr from Kr-85 and Xe-133

~(I The skin dose is to be calculated using equation 3-2 as follows: Ds=Xi (Li+1.1Mi)(X/Q)SS Qi (3-2)Where: Li 1.34 E+3~fo K-85 pci/rn3 3.06 E+2~for Xe-133 pCi/m3 Mi 1.72 E+1~for Kr-85 pci/m 3.53 E+2~for Xe-133 pCi/m3 (X/Q)Sg=6.49 E-6 sec/m I Qi=634 pCi/sec for Kr-85=279 pCi/sec for Xe-133 D s=[(1;34 E+3~)pCi/m3 ([(3.06 E+2~~)pci/m3+1~1(1 72 E+1~)j (6.49 E-6 sec/m)(634 pCi/sec))+

pCi/m3+1.1(3.53 E-2Žad~3)j (6.49 E-6 sec/m3)(279 pCi/sec))pci/rn3 Ds=6.15 mrem/yr from Kr-85 and Xe-133

A.2.2 Radionuclides Other'Ihan Noble Gases The methods used to calculate the annual critical organ dose rate is discussed in Section 3.2 of the text.The dose parameter, P., is taken from Table 3-3.The highe'st annual average dispersion parameter at the site boundary occurs in the north sector and the value taken from Table 3-2.Assuming a release rate of 5.31 E-4 pCi/sec of I-131, 2.54 E-1 pCi/sec of C-14, 2.54 E-5 pCi/sec of Cs-137 and 3.17 E+1 pCi/sec of H-3, the critical organ annual dose rate is calculated, using equation 3-3, as follows: Do=~i Pi (X/Q)SB Qi Where: Pi 1.62 E+7~for 1-131 pCi/m3 3.59 E+4~fo 0-14 pci/m3 9.07 E+5-3 for Co-137 pCi/m3 1.12 E+3~~for 11-3 pCi/m3 (X/Q)SB=6.49 E-6 sec/m 3 I Qi=5.31 E-4 pCi/sec for I-131=2.54 E-1 pCi/sec for C-14=2.54 E-5 pCi/sec for Cs-137=3.17 E+1 pCi/sec for H-3 r 1~I I Do t (1.62 E+7 r (3.59 E+4 t (9.07 E+5~mrem/r3 pci/m3~mram/p Ci/m3~mrem/r~pCi/m3~mrem/r pCi/m3 (6.49 E-6 sec/m3)(5.31 E-4 pCi/sec)+(6.49 E-6 sec/m)(2.54 E-1 pCi/sec)+(6.49 E-6 sec/m)(2.54 E-5 pCi/sec)+(6.49 E-6 sec/m3)(3.17 E+1 pCi/sec)Do=0.35 mrem/yr A.3 DOSE DUE TO GASEOUS EFFLUENT A.3.1 Noble Gases The methods used to calculate the beta and gamma air doses are discussed in Section 4.1 of the text.'Ihe dose factors, M.and N., for noble gases and their daughters are taken 3.from Table 3-1.The highest annual average dispersion parameter at the site boundary occurs in the north sector and the value as taken from Table 3-2.Assuming an annual release of 8.8 E+9 pCi Xe-133 and,2.0 E+10 pCi Kr-85, the gamma air dose is calculated as follows using equation 4-1.Dy~3.17 x 10 Xi Mi (X/Q)SE Qi Where: M.1.72 E+1~mrad/r for Kr-85 pCi/m3=3.53 E+2~for Ke-133 pci/m 3

[I ll'I'N (X/Q)SE=6.49 E-6 sec/m3 Qi=2.0 E+10 pCi/yr for Kr-85=8.8 E+9 pCi/yr for Xe-133 0=(3~17 E-8 yr/sec)l(1..72'E+1~)(6.49 8-6 sec/m3)(2.0 E+10 poi/yr)+Y L pCi/m3 (3.53 E+2~)(6.49 E-6 sec/m3),(8.8 E+9 pCi/yr)]pci/m3=0.71 mrad/yr The annual beta air dose is calculated as follows using equation 4-2:=3.17 E-8 Zi Ni~(X/Q)8E Qi Where: Ni 1.95 E+3~for Er-85 pci/m3 1.05 E+3-3 for Ee-133 pci/m3 (X/Q)8E=6.49 E-6 sec/m Qi 2.0 E+10 pCi/yr for Kr-85=8.8 E+9 pCi/yr for Xe-133

/II 1 e 3.17 E-8 (1.95 E+3)(6.49 E-6 sec/m3)(2.0 E+10 pCi/yr)+pci/m3 (1.06 E+3~)(6.49 E-6 eec/m8)(8.8 E+9 pCi/Ec)]pci/m3=9.92 mrad/yr A.3.2 Radionuclides Other Than Noble Gases The methods used to calculate the critical organ dose from actual releases received by real members of the public is discussed in Section 4.2 of the text.These doses are calculated at the nearest residence with the highest annual average atmospheric dispersion parameter, 2300 meters north, and the values are taken from Table 4-16.The dose factor, I R.is taken from Tables 4-1 through 4-15.The ik'oses are calculated for the child and infant age groups using the appropriate exposure pathways.Assuming an annual release of 8.1 E+4 pCi/yr of I-131, 8.0 E+2 pCi of Cs-137, 8.0 E+6 pCi/yr of C-14, and 1.0 E+9 pCi/yr of H-3, the critical organ dose is calculated as follows using equation 4-2.The critical organs used are thyroid, bone and total body.Dog=(3.17 E-8 yr/sec)Z i Q (Q Rik Wkg)(4-3)Wher e: Q 8.1 E+4 pCi/yr for I-131 8.0 E+2 pCi/yr for Cs-137 8.0 E+6 pCi/yr for C-14 1.0 E+9 pCi/yr for H-3 l

ke X/Q for sec/m 3 D/Q for E-9/m, 2 the inhalation pathway, 3.92 E-6 from Table 4-16.the food and ground plane pathways, 3.60 from Table 4-16.ik from tables 4-1, 4-4, 4-7, 4-10, and 4-14 for the child pathway.from Tables 4-1, 4-11, and 4-15 for the infant pathway The doses to the child from the ground, vegetable, meat, milk, and inhalation pathways are: THYROID, CHILD: thyroid, I-131 m2 mrem/r (3.6 E-9/m2)+(3.3 E+10 C)(3.6 E-9/m2)+m2 mrem r (1.32 E+9 C)(3.6 E-9/m)+m2 mrem/r+C)(3.6 E-9/m 2)m mrem/r (1.62 E+7-66E)(3.92 E-6 sec/m3)j 1.77 mrem/yr to the thyroid from I-131 Dthyroid Cs-137=(3.17 E-8 yr/sec)(8.0 E+2 pCi/yr)(1.04 E+10)(3.6 E-9)=9.49 E-4 mrem/yr from Cs-137

/L

~h 1 thyroid, C-14 (3.17 E-8)(8.0 E+6 pCi/yr)[(6.92 E+5)(3.6 E-9)+(1~07 E+5)(3.6 E-9)+(3.32 E+5)(3.6 E-9)j=1.03 E-3 mrem/yr from C-14 thyroid, H-3 (3.17 E-8)(1.0 E+9 pCi/yr)[(7.92 E+3)(3.92 E-6)+(4.72 E+2)(3.92 E-6)+(3.17 E+3)(3.92 E-6)+(1.12 E+3)(3.92 E-6)j 1.58 mrem/yr from H-3 thyroid, total=1.77 mrem/yr+9.49 E-4 mrem/yr+1.03 E-3 mrem/yr+1.58 mrem/yr=3.35 mrem/yr from I-131, Cs-137, C-14 and H-3.BONE, CHILD: DZ 131~(3~17 E-8)(8~1 E+4)[(1.72 E+7)'(3~6 E-9)+(9.92 E+7)(3.6 E-9)+(3.98 E+6)(3.6 E-9)+(3.13 E+8)(3.6 E-9)+(4.8 E+4)(3.92 E-6)]=4.50 E-3 mrem/yr from I-131 DCs 137=(3.17 E-8)(8.0 E+2)[(1.04 E+10)(3.6 E-9)+(2.45 E+10)(3.6 E-9)+(6.62 E+8)(3.6 E-9)+(1.53 E+10)(3.6 E-9)+(9.05 E+5)(3.'92 E-6)j I=4.70 E-3 mrem/yr from Cs-137-5 9-

~~l f I I DC 14=(3.17 E-8)(8.0 E+6)[(3.46 E+6)(3.6 E-9)+(5.33 E+5)(3.6 E-9)+(1.66 E+6)(3.6 E-9)j=5.16 E-3 mrem/yr from C-14 Dbpne t'pre 1 1~43 E 2 mrem/yr f rom I-1 31, Cs-137, H-3 and C-14 TOTAL BODY j CHILD: DZ 13]=(3.17 E-8)(8.1 E+4)[(1.72 E+7)(3.6 E-9)+(5.67 E+7)(3.6 E-9)+(2.27 E+6)(3.6 E-9)+(1.79 E+8)(3.6 E-9)+(2.72 E+4)(3.92 E-6)j=2.63 E-3 mrem/yr from I-131 I DCs 137=(3.17 E-8)(8.0 E+2)[(1.04 E+10)(3.6 E-9)+-(3.46 E+9)(3.6 E-9)+(8.78 E+7)(3.6 E-9)+(2.2 E+9)(3.6 E-9)+(1.28 E+5)(3.92 E-6)j=1.48 E-3 mrem/yr from Cs-137 DC 14=(3.17 E-8)(8.0 E+6)[(6.92 E+5)(3.6 E-9)+(1.07 E+5)(3.6 E-9)+(3.32 E+5)(3.6 E-9)j=1.03 E-3 mrem/yr from C-14 t:hyrozd H-3=(3~17 E-8)(1~0 E+9)[(7'92 E+3)(3 92 E-6)+(4.72 E+2)(3.92 E-6)+(3.17 E+3)(3.92 E-6)+(1.12 E+3)(3.92 E-6)j 1.58 mrem/yr from H-3

a~~Dtotal body child=(2.63 E-3+1.48 E-3+1.03 E-3+1.58)mrem/yr=1.58 mrem/yr from I-131, Cs-137, C-14 and H-3 Doses to the infant by critical organ via the ground, milk and inhalation pathways are: THYROID, INFANT: DZ 131=(3.17 E-8)(8~1 E+4)(1~72 E+7)(3.6 E-9)+I (2.53 E+11)(3.6 E-9)+(1.48 E+7)(3.92 E-6)=2.49 mrem/yr from I-131 DCs-137=(3.17 E-8)(8.0 E+2)(1.04 E+10)(3.6 E-9)=9.5 E-4 mrem/yr from Cs-137 DC 14=(3.17 E-S)(8.0 E+6)(6.94 E+5)(3.6 E-9)=6.33 E-4 mrem/yr from C-14 DH 3 (3.17 E-8)(1.0 E+9)(6.46 E+2)(3.92 E-6)=0.68 mrem/yr from H-3 (4.8 E+3)(3.92 E-6)+Dthyroid (0.68+6.33 E-4+9~5 E-4+2.49)mrem/yr 3.17 mrem/yr from I-131, Cs-137, C-14 and H-3.

0 BONE, INFANT: DZ 13].=(3.17 E-8)(8.1 E+4)(1.72 E+7)(3.6 E-9)+(6.54 E+8)(3.6 E-9)+(3.79 E+4)(3.92 E-6)=6.59 E-3 mrem/yr from I-131 DCs 137=(3.17 E-8)(8.0 E+2)(1.04 E+10)(3.6 E-9)+(2.4 E+10)(3.6 E-9)+(5.48 E+5)(3.92 E-6)=3.19 E-3 mrem/yr from Csl37 DC 14=(3.17 E-8)(8.0 E+6)(3.25 E+6)(3.6 E-9)=2.97 E-3 mrem/yr from C-14 DH 3-no dos e contribution from H-3 Dbone infant 1.28 E-2 mrem/yr from I-131, Cs137, C-14 and H-3 TOTAL BODY, INFANT: DZ 131=(3.17 E-8)(8.1 E+4)(1.72 E+7)(3.6 E-9)+(3.39 E+8)(3.6 E-9)+(1.96 E+4)(3.92 E-6)=3.49 E-3 mrem/yr from I-131 DCs 137=(3 17 E 8)(8~0 E+2)(1 04 E+10)(3~6 E 9)+(1.99 E+9)(3.6 E-9)+(4.54 E+4)(3.92 E-6)=1.14 E-3 mrem/yr from Cs-137

~/I ,1 DC 14=(3'17 E-8)(8.0 E+6)(6.94 E+5)(3.6 E-9)=6.34 E-4 mrem/yr from C-14 (3.17 E-8)(1.0 E+9)(4.80 E+3)(3.92 E-6)+(6.49 E+2)(3.92 E-6)6.77 E-1 mrem/yr from H-3 total body infant=(3.49 E-3+1.14 E-3~+6.34 E-4+6.77 E-1)mrem/yr=0.68 mrem/yr from"I-131, Cs-137, C-14 and H-3 A.4 TOTAL DOSE This dose is calculated to the nearest real resident.Use the X/Q and D/Q from Table 4-16.The maximally exposed resident is iri the north sector at 2,300 meters.A.4.1 Noble Gases wb=3.17 x 10~iKi (/Q)'Qi (5-1)D k=3.17 x 10 X (L+1.1 M)(X/Q)Q.(5-2)If the source term is: 8.8 E+9 pCi Xe-133 2.0 E+10 pCi Kr-85 lh en: D=3.17 x 10 (1.61 E+1)(3.92 E-6)(8.8 E+9)+(2.49 E+2)(3.92 E-6)(8.8 E+9)=0.29 mrem/yr (Ij~l I D xE=3.17 x 10 8([(3~06 E+2)+(1~1)(3~53 8+2)j (3.92 E-6)(8.8 8+9))+[(1.34 E+3)+1.1 (1~72'E+1))(3.92 E-6)(2~0 E+10))=4.14 mrem/yr A.4.2 Radionuclides Other Than Noble Gases Since all other uranium fuel cycle sources are greater than 20 miles away, only PVNGS Unit'~1 needs to be considered for meeting the EPA regulation, 40CFR190.The total dose to an individual from radionuclides other than noble gases can be calculated in the same manner as Section A'3.2 of this Appendix.A.4.3 Direct Radiation The direct radiation to any member of the public due to operations at PVNGS should be determined from the results of the environmental monitgring program.

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