ML17297B856
| ML17297B856 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/12/1982 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17297B855 | List: |
| 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 05000528 PDR ADOCK A PDR
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION TABLE OF CONTENTS Section Title ~Pa e
1.0 INTRODUCTION
2.0 GASEOUS EFFLUENT MONITOR SETPOINTS 4 2.1 Plant Stack RU-143 & 144 2.2 Condenser Evacuation System RU-141 & 142 2.3 Fuel Building Vent Exhaust RU-145 & RU-146 7/
3.0 GASEOUS EFFLUENT DOSE RATE 10 3.1 Noble Gases 10 3.2 Radionuclides Other Than Noble Gases 4.0 DOSE DUE TO GASEOUS EFFLUENT 16 4.1 Noble Gases 16 4.2 Iodine 131 Tritium and All Radionuclides in 17 Particulate Form Other Than Noble Gases 5.0 TOTAL DOSE 36 6.0 OPERABILITY OF EQUIPMENT 39 7.0 RADIOLOGICAL ENVIRONMENTAL PROGRAM 40 7.1 Radiological Environmental Monitoring Program 40 7.2 Census Program APPENDIX A Sample Calculations 50
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNIT I List of Tables Table No. Title ~Pa e ANNUAL RADIOLOGICAL EFFLUENT OBJECTIVES AND STANDARDS 10CFR 20 MPC LIMITS DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 13 3-2 PALO VERDE NUCLEAR GENERATING STATION UNIT 1 DISPERSION 14 PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY 3-3 P VALUES FOR THE PALO VERDE GENERATING STATION 15 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 20 PATHWAY =: GROUND 4-2 R VALUES FOR THE PALO VERDE NUCLEAR GENERATIiNG STATION 21 PATHWAY = VEGET, AGE GROUP = ADULT R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 22 PATHWAY = VEGET, AGE GROUP = TEEN 4-4 VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 23 PATHWAY = VEGET, AGE GROUP = CHILD 4-5 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 24 PATkkWAY = MEAT, AGE GROUP = ADULT 4-6 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 25 PATHWAY = MEAT, AGE GROUP = TEEN 4-7 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 26 PATHWAY = MEAT, AGE GROUP = CHILD 4-8 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 27 PATHWAY =: COW MILK, AGE GROUP = ADULT 4-9 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 28 PATHWAY = COW MILK, AGE GPOUP = TEEN 4-10 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 29 PATHWAY = COW MIKL, AGE GROUP ~ CHILD
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List of Tables (Continued)
Table No. Title ~Pa e 4-11 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATXON 30 PATHWAY = COW MILK, AGE GROUP = INFANT 4-12 R VALUES FOR THE PALO VERDE NUCLEAR GENERATXNG STATXON PATHWAY = INHAL, AGE GROUP = ADULT 4-13 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 32 PATHWAY = INHAL, AGE GROUP = TEEN 4-14 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 33 PATHWAY = INHAL, AGE GROUP = CHILD 4-15 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = INHAL, AGE GROUP = INFANT 4-16 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 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS -47 7-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGFAM
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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
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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.
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNIT 1 List of Fi ures Fi ure No. Title ~Pa e 6-1 Basic Flow Diagram Liquid Radwaste System 39A Sheet 1 of 2 6-1 Flow Diagram Liquid Radwaste System 39B Sheet 2 of 2 6-2 Basic Flow Diagram Gaseous Radwaste System 39C 6-3 Basic Flow Diagram Solid Radwaste System 39D Radiological Environmental Monitoring Program 42A Sample Sites
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- 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 in order to assure that the ODCH represents the present 1'DCH methodology.
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TABLE 1-1 ANNUAL RADIOLOGICAL EFFLUENT OBJECTIVES AND STANDARDS 10 CFR 50 APPENDIX I 40 CFR 190 DESIGN OBJECTIVES STANDARDS (PER REACTOR UNIT, (ALL REACTOR ABOVE BACKGROUND) UNITS COMBINED)
NOBLE GAS EFFLUENTS Gamma Dose in Air 10 MRAD Beta Dose in Air 20 MRAD Dose to total Body of an Individual 5 MREM Dose to Skin of an Individual 15 MREM RADIOIODINES AND PARTICULATES Dose to Any Organ from All Pathways 15 MREM TOTAL URANIUM FUEL CYCLE Dose to Whole Body from All Fuel Cycle Operations 25 MREM Dose to Thyroid from All Fuel Cycle Operations 75 MREM Dose to any Other Organ from All Fuel Cycle Operations 25 MREM TOTAL ANTITIES RELEASE Krypton-85 Released Per Gigawatt-Year 50,000 CURIES Iodine-129 Released Per Gigawatt-Year 5 MILLICURIES Combined Plutonium-239 and Other Alpha-emitting Radionuclides with Half Lives Greater than One Year Released per Gigawatt-Year .5 MILLICURIES
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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 3 , the highest annual average atmospheric dispersion parameter from Table 3-2.
3-2120 conversion of cfm to m /sec 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.
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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 (2-2)
(X/Q)S~ (flow rate)
'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 3 , annual highest average atmospheric dispersion parameter from Table 3-2.
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3 2120 conversion of cfm to m /sec.
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, P
r 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 3
2120 conversion of cfm to m /sec.
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.
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Table 2-1 10CFR20 MPC LIMITS (uCi'/cm3)
I'PC LIMIT MJCLIDZ (pCi/cm3)
KR-83M 3~~8 "
KR-85M 1E-7 KR-85 3E-7 IK-87 2E-8 KR-88 2E-8 KR-89 3< 8 XE-131M 4E-7 XE-133iM 3<~7 XE-133 3E-7 XE-135M 3E-8 XE-135 1E-7 3P 137 3~~8
~138 3E-8 BR-83 lE-10 BR-84 3E-8 BR-85 3E-8 I-130 1E-10 I-,131 1E-10 I-132 3E-9 I-133 4E-10 I-134 6E-9 I-135 lE-9 CO-60 3E-10 CO-58 2E-9 FE-59 2E-9
~-54 lE-9 CS-137 5>~10 CS-134 4E-10 SR-90 3E-11 SR-89 3E-10 H-3 2E-7 C-14 lE-7 AR-41 4E-8
': 3~8 = 3x10-8
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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 = E. K. (X (3-1) b SB and by the following equation for skin dose:
I D = Z. (L. + 1.1H.)(X/Q)SB Q. (3-2) s E
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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 3 from Table 3-1 ~
Q. the release rate of radionuclide, r
i, yCi/sec.
(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 3 from Table 3-1.
the air dose factor due to gamma emissions for each 'identified noble gas radionuclide, i, in mrad/yr per yCi/m3 from Table 3-1 (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
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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 3
(mrem/yr per pCi/ m ) from Table 3-3.
(X/Q)S> = the highest, calculated annual average dispersion parameter for estimating the dose to an individual from Table 3-2.
6.49 E-6 sec/m 3 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.
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TABLE 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Whole Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Ki Li Mi Nl Radionuclide (mrem/yr per pCi/m (mrem/yr per pCi/m (mrad/yr per pCi/m (mrad/yr per pCi/m Kr-83m 7.56E-02b 1.93E+Ol 2. 88E+02 Kr-85m 1. 17E+03 1.46E+03 1.23E+03 1.97E&3 Kr-8 5 l. 61E+01 1.34E+03 1.72E+01 1. 95E+03 Kr-8 7 5.92E&3 9.73E+03 6 ~ 17E+03 1.03E&4 Kr-58 1.4 7E+04 2.37E+03 l. 52E+04 2.93E+03 Kr-89 l. 66E+04 1. 01E+04 l. 73E+04 1.06E+04 Kr-9 0 l. 5 6E+04 7. 29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1. 11E+03 Xe-133m 2. 51E+0 2 9. 94E+02 3.27E+02 1. 48E+03 Xe-133 2.94E&2 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3. 12E+03 7. 1 lE+02 3.36E+03 7.39E+02 Xe-135 l. 81E&3 1.86E&3 1.92E+03 2.46E+03 Xe-13 7 1. 42E+03 l. 22E+04 1. 51E+03 1. 27E+04 Xe-138 8.83E+03 4. 13E& 3 9. 21K+03'. 4. 75E+03 Ar 141 8. 84E+03 2. 69E+03 30E+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.
b7 56E-02 = 7.56 x 10 2 i
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Table 3-2 Palo Verde Nuclear Generating Station Unit 1 Dispersion Parameters for long term releases at the Site 3oundarg Direction Distance X/G D/G (meters) (Sec/cub. meter) (per sq. meter)
N 1037. 6. 49E-06 1. 05E-08 NNE 1057. 4. 71E-06 1. 19E-08 NE 2206. 2. 81E-06 6. 60E-09 ENE 1967. 2. 96E-06 4. 74E-09 E 1927. 2. 98E-06 3. 54E-09 ESE 1967. 2. 57E-06 2. 57E-09 SE 2049. 3.34E-06 2. 30E-09 SSE 2730. 3. 58E-06 1. 48E-09 S 3006. 4. 49E-06 1. 55E-09 SSW 225S. 5:87E-06 2. 85E-09 SW 1487. 5. SBE-06 4. 37E-09 WSW 1251. 4. 41E-06 5. 41E-09 W 1225. 5. 43E-06 9. 13E-09 WNW 1244. 4. SOE-06 7. 59E-09 NW 1254. 4. 12E-06 6. 72E-09 NNW 1069. 4. 39E-06 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
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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 3 from Table 3-1.
the air dose factor due to beta emissions for each identified noble gas radionuclide, i, in mrad/yr per yCi/m3 from Table 3-1.
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(~/0)SB the highest calculated annual average relative concentration for any area at the site boundary 3
(sec/m ) from Table 3.2.
the total gamma air dose from gaseous effluents for a specified time period (mrad).
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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.
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- 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 o0 3.17 x 10 E.
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/m3 and 2
for the food and ground plane pathways in m mrem/yr per yCi/sec) at the controlling ik for each age group are location. The R.k's 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.
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(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.
3.17 x 10 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 3 ) over the 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
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Table 4-16 Palo Verde Nuclear Generating Station Unit 1 Dispersion Parameters
%or long term releases at the Nearest residences Direction Distance X/8 D/G (meters3 (Sec/cub. meter 3 (per sq. meter)
N 2300. 3. 92E-06 3.60E-09 NNE 2900. 2. 12E-06 2. 82E-09 NE 3000. i. 98E-06 3. 87E-09 ENE 4300. i. 27E-06 i. 21E-09 E 5100. 9. 63E-07 6. 02E-10 ESE 5700. b. 59E-07 3. 19E-10 SSE 7300. i. 25E-06 2. 60E-10 7200. 2. 35E-06 4.39E-10
$ $ 4t 5500. 2. 97E-06 7. 48E-10 SW 6800. i. 86E-06 4.61E-10 NW 3600. i. 69E-06 i. 41E-09 fwNW 3700. i. 57E-06 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 than or equal to 75 mrems. 1'ess 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 wb 3.17 x 10 i
E. K (X/Q)< Q (5-1)
D = 3.17 x 10 E. (L. + 1.1M.)(X/Q)>Q. (5-2) k 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 3 from Table 4-16.
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 3 from Table 3-1.
the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per pCi/m 3 from Table 3-1 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 o8
= 317x10 i "k RiA8) Qi E. (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 3 and for the food and ground plane pathways in 2
m -mrem/yr per yCi/sec) at the controlling location. The R.k'sik for each age group are given in Tables 4-1 through 4-15.
1
= the annual average dispersion parameter WkO 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.
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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 2 (500 ft2 ) producing broad-leaf 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 N I ! JO ~W ' I ~ Ie 1 ~ ~ 3 OO <<O<<I <<S}ttl 1 ~ II ' el N (N + IA>>tA ee ee Vffet~ SAIK S<SV>>t ee / ~ <>> t'i I/W~ ~ IC JI I>><1 N ~ Ol W tet I sle IQ \ >> -.'f ttaSs>>A tsee ~ ~ ~ ~ ~ Y l el e <<se I s s ~ 's; s h<<YAN ffe >>sr OONP IW ~}4.} q-,q I 'aff f 5 ~ > ~ ~ 1 0 ~ ~ ~ ~ '>> 5 1>> I ~ ~ . ' >> 's >> I 4 <<NO NNOOO }>>r t s. 0 << ON 1 ON, Sr ~
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Page 1 of 4 TABLE 7-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SAt%'LE COLLECTION LOCATIONS SAMPLE SiQPLE LOCATION SITE TYPE DESIGNATION LOCATION DESCRIPTION 1 TLD, Air E30 APS Goodyear Office 2
TLD ENE24 Scott-Libby School 3 TLD H25 Liberty School TLD, Air E20 APS Buckeye Office TLD ESE15 Palo Verde TLDp Air SSE35 APS Gila Bend Substation TLD,'b'i SE8 Arlington School TLD SSE5 Corner of 363rd Ave. & SPP Rd.
TLD S5 Corner of 371st Ave. & SPP Rd.
10 SE5 Corner of 355th Ave. & Ward Rd.
TLD ESE5 Corner of 339th Ave. & Dobbins Rd 12 TLD E5 Corner of 339th Ave. & B-S Rd.
13 TLD Nl N Site Boundary 14 TLD NNE2 NNE Site Boundary 14A Ai NNE2 Buckeye-Salome Rd. & 371st Ave.
TLD Ai NE Site Boundary 16 TLD ENE2 ENE Site Boundary
%I Page 2 of 4 TABLE 7-1 S&PLE SAP LE LOCATION SITE TYPE DESIGNATION LOCATION DESCRIPTION 17 TLD E2 E Site Boundary 17A Air E4 351st Ave., 1 mi. S of B-S Rd.
18 TLD . ESE2 ESE Site Boundary 19 TLD SE2 SE Site Boundary 20 TLD SSE2 SSE Site Boundary 21 TLD , Air S3 S Site Boundary 22 TLD SSM3 SSW Site Boundary 23 TLD M5 Benchmark at Baseline 24 TLD,(b) Water SW5 Ward Rd. 8 Mell 18bbb 25 TLD WSW5 Ward Rd. 8 DF Well 2 Rd.
26 TLD,(b) Water SSW5 Well 21 Cbb2 27 TLD SM Site Boundary 28 TLD(b) MSW1 WSW Site Boundary 29 , Air Wl W Site Boundary 30 TLD WNW Site Boundary 31 TU '" NW Site Boundary
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. TABLE 7-1 S&PLE SAMPLE LOCATION SITE TYPE DESIGNATION LOCATION DESCRIPTION 32 TLD NNW Site Boundary 33 TLD Yuma Rd. 1/2 mi. W. of Belmont Rd.
34 Corner Belmont Rd. & Van Buren Rd.
35 TLD, Air NNW9 Tonopah, Palo Verde 'Inn Fire Station 36 TLD(b) N5 Corner of Wintersburg Rd. & Van Buren 37 TLD NNE5 Corner of 363rd Ave'. & Van Buren 38 TLD NE5 Corner of 355th Ave. & Yuma Rd.
39 TLD ENE5 343rd Ave., 1/2 mi. S. of L. Buckeye 40 TLD(b),
Air(b) , Water Trailer Park; Water at Red Quail Str.
41 TLD WNW20 Harquahala Valley School 42 TLD N8 Ruth Fisher School 43 TLD N45 Vulture Mine Rd. School, Wickenburg 44 TLD(b), Air ENE35 APS El Mirage Office (Sun City) 45 TLD ENE50 APS Headquarters (Phoenix) 46 Water (b) NNW9 McArthur's Farm, Tonopah
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Page 4 of 4 TABLE 7-1 S&FLE SAMPLE LOCATION SITE TYPE DESIGNATION LOCATION DESCRIPTION 47 Water NNW6 Winter's Wells 48 Water (b) SSE4 Well 14dbb 49 Water (b) ESE4 Glover Residence, 351st Ave. & Dobbins 50 Milk NE7 Baisley Dairy, 331st Ave. &'Van Buren 51 i Veg.
(b) E15 Butler Dairy, P. Ver'de Rd. & Southern 52 Vegetation (b) E15 Cambron Farm, Miller Rd. & Broadway 53 Milk E20 Kerr Dairy, Dean & Buckeye Rds.
54 Milk E25 Skousen Dairy, Airport & Dobbins 55 E25 Lueck Dairy, Jackrabbit & Hazen Rds.
56 Milk E50 Paxton Dairy, Mcgueen & Ryan Rds.
(a) Table J-l, NUREG-0654; distances are from centerline of Unit
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(b) These samples fulfillthe requirements of the NRC Technical Specifications; the other samples fulfill PVNGS station requirements.
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Page 1 of 2 TABLE 7-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSES Lower Limit of Detection (LLD)
Airborne Particulate Water or Gas Milk Food Products Analysis (pci/1) (pci/m3) (pCi/1) (pCi/kg, wet) gross beta 1 x 10-2, H-3 2000b Mn-54 15 Fe-59 30 Co-58 15 Co&0 15 Zn-65 30 Z r-95 30 Nb-95 15 I-131 7 x 10 2 60 Cs-134 15 5 x 10 2 15 60 Cs-137 18 6 x 10-2 80 Ba-140 60 60 La-140 15 15
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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) is the number of disintegrations per minute per picocurie y'.22 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
<f ~
(
C
TABLE 7-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pa thway Sampling and Type and Frequency and/or Sample Co 1 lee t ion Frequency of Analysis Sampling Locations(a)
Airborne radioiodine Continuous sampling Gross beta weekly; Twelve locations as and particulates collected weekly I-131 weekly; gamma listed in Table 7-1 spectrum monthly; composite of filters Direct radiation TL dosimeters at Gamma dose quarterly 45 locations (Nos. 1-45) location changed and annually as described in Table 7-1 quarterly and annually Waterborne Monthly Composite of Gamma spectrum monthly; On-site reservoir and Surface weekly grab sample tritium quarterly evaporation pond
/
Ground Quarterly grab Tritium and gamma On-site well Nos. 34abb, sample spectrums quarterly 27ddc.
Drinking (well) Composite sample Gross beta and gamma 24, 46, 49 one~onth period spectrums monthly; tritium quarterly Ingestion Semimonthly for Gamma spectrum and 50, 51, 53-56 Milk .animals on radioiodine semi-pasture, other- monthly or monthly wise monthly Food products Monthly when Gamma spectrum and 46, 51,52 available radioiodine monthly
I rI
<V ~
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 3
6.49 E-6 sec/m , and is found in Table 3-2.
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) 3 C < 9.93 E-3 pCi/cm 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) (2-3)
(X/A)SB flow rate cfm C < (0 2) (2120 m3/sec) (3.0 E 70i/cm3)-
~
(6. 49 E-6 sec/m ) (55,000 c fm) 3 C~<3.53 E-4 pCi/cm 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 N.') for noble gases and their daughters are r L.,
(K., I.
M.,
- 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 Ki 1. 61 E+1 2.94 E+1
~
~
pci/m3 Q'here:
for Er-85 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 ~)
pCi/m (6.49 8-6 sec/m3) (279 pCi/sec)j 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 ~
~
pci/rn3 fo K -85 3.06 E+2 for Xe-133 pCi/m3 Mi 1.72 E+1 3.53 E+2
~
~
pci/m for Kr-85 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 Ds = [(1;34 E+3 ~)
pCi/m3
+ 1 ~ 1(1 72 E+1 ~)j pCi/m3 (6.49 E-6 sec/m ) (634 pCi/sec))+
([(3.06 E+2 ~~)
pci/m3
+ 1.1(3.53 E-2 'ad~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 3.59 E+4
~
~
pCi/m3 for fo 1-131 0-14 pci/m3 9.07 E+5 pCi/m33 for Co-137 1.12 E+3 ~~
pCi/m3 for 11-3 3
(X/Q)SB = 6.49 E-6 sec/m Qi I
= 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
~
I 1
I
~mrem/ r3 (6.49 E-6 sec/m3)
Do t (1.62 E+7 pci/m3 (5.31 E-4 pCi/sec) +
~mram/
(3.59 E+4 (6.49 E-6 sec/m ) (2.54 E-1 pCi/sec) +
r p Ci/m3 E+5 ~mrem/ r~ (6.49 E-6 sec/m ) (2.54 E-5 pCi/sec) t(9.07 pCi/m3
+
~mrem/ r (6.49 E-6 sec/m3) (3.17 E+1 pCi/sec) pCi/m3 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
Y
= (3 ~ 17 E-8 yr/sec) l(1..72 'E+1 ~) (6.49 8-6 sec/m3) (2.0 E+10 poi/yr) +
~)
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 1.05 E+3
~
pci/m3 for Er-85 for Ee-133 pci/m33 (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 1
/II
e 3.17 E-8 (1.95 E+3 ) (6.49 E-6 sec/m3) (2.0 E+10 pCi/yr) +
(1.06 E+3 ~)
pci/m3 pci/m3 (6.49 E-6 eec/m8) (8.8 E+9 pCi/Ec)]
= 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
X/Q for the inhalation pathway, 3.92 E-6 ke 3 sec/m from Table 4-16.
D/Q for the food and ground plane pathways, 3.60 2
E-9/m, 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 (3.6 E-9/m2) + (3.3 E+10 m2 mrem/ r ) (3.6 E-9/m2) +
C (1.32 E+9 m2 mrem r ) (3.6 E-9/m ) +
C
+
m2 mrem/ r ) (3.6 E-9/m 2)
C (1.62 E+7 66E m mrem/ r
) (3.92 E-6 sec/m3)j 1.77 mrem/yr to the thyroid from I-131
= (3.17 E-8 yr/sec) (8.0 E+2 pCi/yr) (1.04 E+10) (3.6 E-9)
Dthyroid Cs-137
= 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 (3.17 E-8) (1.0 E+9 pCi/yr) [(7.92 E+3) (3.92 E-6) +
thyroid, H-3 (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 from 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) (4.8 E+3) (3.92 E-6) +
(6.46 E+2) (3.92 E-6)
= 0.68 mrem/yr from H-3 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.
J Qrs
~ ~
~ I 4 H, ~ ~=