ML17299A668
| ML17299A668 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/20/1985 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17299A667 | List: |
| References | |
| PROC-850920, NUDOCS 8510160118 | |
| Download: ML17299A668 (140) | |
Text
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 TABLE OF CONTENTS SECTION 1IILE PAGE
1.0 INTRODUCTION
l-l 1.1 Liquid Effluents 1-1 1.2 Gaseous Effluents ,.1-3 1.3 Nuisance Pathways 1-4 2.0 GASEOUS EFFLUENT MONITOR SETPOINTS 2-1 2.1 Equivalent Dose Factor Determination 2-2 2.2 Site Release Rate Limit 2-3 2.3 Unit Release Rate Limits 2-5 2.4, Setpoint Determination 2-6 2.5 Monitor Calibration 2-8 3.0 GASEOUS EFFLUENT DOSE RATE 3-1 3.1 Noble Gases 3-1 3.2 Radionuclides Other Than Noble Gases 3-3 4.0 DOSE DUE TO GASEOUS EFFLUENT 4-1 4.1 Noble Gases 4-1 4.2 Iodine-131, Iodine-133, Tritium, and All 4-3 Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 4.3 Dose Projection 4-6 5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE 5-1 5.1 Technical Specification 3.11.4 5-1 5.2 Dose to Public Onsite 5-4 6.0 OPERABILITY OF EQUIPMENT 6-1 7.0 RADIOLOGICAL ENVIRONMENTAL PROGRAM 7-1 7.1 Radiological Environmental Monitoring Program 7-1 7.2 Land Use Census 7-2 7.3 Interlaboratory Comparison Program 7-3 APPENDIX A DETERMINATION OF CONTROLLING'OCATION A-1 Rev. 1 09/20/85
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OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Tables TABLE TITLE PAGE NUISANCE PATHWAYS 1-5 3-1 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 3-4 3-2 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY (3 SHEETS) 3-5 3-3 Pi VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION 4-1 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY GROUND 4-10 4-2 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY VEGET, AGE GROUP ~ ADULT 4-11 4-3 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY VEGET, AGE GROUP ~ TEEN 4-12 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY VEGET, AGE GROUP ~ CHILD 4-13 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ MEAT, AGE GROUP ~ ADULT 4-14 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ MEAT, AGE GROUP ~ TEEN 4-15 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ MEAT, AGE GROUP ~ CHILD 4-16 4-8 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ COW MILK, AGE GROUP ~ ADULT 4-17 a R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ COW MILK, AGE GROUP ~ TEEN 4-18 4-10 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ COW MILK, AGE GROUP ~ CHILD 4-19
-ii-Rev. 1 09/20/85
OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Tables (Continued) TABLE TITLE PAGE 4-11 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ COW MILK, AGE GROUP INFANT 4-20 4-12 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY ~ INHAL, AGE GROUP ~ ADULT 4-21 4-13 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = INHAL, AGE GROUP ~ TEEN 4-22 4-14 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = INHAL, AGE GROUP CHILD 4-23 4-15 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION PATHWAY = INHAL, AGE GROUP INFANT 4-24 4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS (3 SHEETS) 4-25 4 7-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE
'COLLECTION LOCATIONS (4 SHEETS) 7-4 7-2 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (2 SHEETS) 7-8 7-3 .RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 7-10 A-1 EXPOSURE PATHWAY LOCATIONS (3 SHEETS) A-2
-iii-Rev. 1 09/20/85
OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1 2 AND 3 List of Fi ures FIGURE TITLE PAGE 2-1 Calibration Curve for PVNGS Effluent Monitors RU-141, RU-143, and RU-145. Response to Noble Gas. II 2-9 2-2 Initial Calibration Curve for PVNGS Monitor RU-12. Response to Kr-85 Gas. 2-10 6-1 Process Flow Diagram Liquid Radwaste System (Sheet 1 of 2) 6-2 6-1 Process Flow Diagram Liquid Radwaste System (Sheet 2 of 2) 6-3 6-2 Basic Flow Diagram Gaseous Radwaste System 6-4 6-3 Basic Flow Diagram Solid Radwaste System 6-5 7-1 Radiological Environmental Monitoring Program Sample Sites, 0 to 5 miles 7-11 7-2 Radiological Environmental Monitoring Program Sample Sites, beyond 5 miles 7-12
-iv-Rev. 1 09/20/85
1.0 INTRODUCTION
The purpose of the Offsite Dose Calculation Manual (ODCM) is to provide the parameters and methodology to be used in calculating offsite doses and effluent monitor setpoints at the Palo Verde Nuclear Generating Station (PVNGS) for Unit 1, Unit 2, and Unit 3. Included are methods for determining air dose from beta and gamma radiation, and organ dose at the controlling location due to plant effluents, to assure compliance with the dose limitations in the Technical Specifications. Methods are included for performing dose projections to assure compliance with the gaseous treatment system operability sections of the Technical Specifications. This manual, in addition to Regulatory Guide 1.109, includes the methods used for determining quarterly individual doses for inclusion in Semiannual Radioactive Effluent Release Reports. 1.1 Li uid Effluents Dose calculation methodology for liquid effluents is not included in this manual because of the desert location of the plant and the hydrology of the area. PVNGS is located in the drainage basin of the Centennial Wash, which flows southeasterly into the Gila River. Surface water flows near the site area are intermittent and of short duration because the flows are caused by storm runoff, usually occurring in August and September and from December to April. Surface water bodies, such as ponds, lakes, and marshes, are not present in the area offsite because of the arid climate, the geological character of surficial materials, and the high potential evaporation rate. The groundwater in the site area consists of an extensive regional aquifer and a local perched-water zone. The regional aquifer extends to over 400 square miles. The primary recharge source to the regional aquifer is underflow from the Upper Hassayampa Valley to the north. The general flow direction is Rev. 1 09/20/85
north to south. Infiltration of precipitation, surface runoff, and return flow from irrigation constitute a small portion of the total recharge of the aquifer. Discharge of the aquifer 1 occurs as underflow to Arlington Valley to the, south and pumpage from irrigation wells (the major use of groundwater in the area). Contaminated water, if accidentally spilled during plant operation, may seep through the ground surface. For this postulated occurrence, the contaminated water will infiltrate downward through the unsaturated soil and reach the perched water table about 40 feet below the land surface. It will then disperse into the perched groundwater. Further downward movement of water from the base of the perched water zone is restricted due to the presence of the Palo Verde Clay layer about 200 feet below the ground surface. Two aquifer systems have been analyzed for the possible effect of a contaminated water spill: the perched water zone and the underlying regional aquifer. The impact of such postulated accidental seepages on the groundwater system, and in particular on the existing wells located in the 5-mile zone around the site area has been calculated and analyzed in Section 2.4.13.3 of the 'VNGS FSAR. It is shown that the resultant concentrations of the refueling water tank source-term radionuclides are well below the MPC w values listed in 10 CFR 20, Appendix B, Table II. Therefore, no methods for calculating doses due to the liquid have been included. If geological I conditions, surface, or groundwater sources change in the future', or if plant operating conditions become such that the likelihood of a liquid effluent pathway increases, then dose calculation methodology for this pathway will be added to this manual. 1-2 Rev. 1 09/20/85
1.2 Gaseous Effluents All gaseous effluents are treated as ground level releases and are considered to be "long-term" as discussed in NUREG-0133', Section 3.3, page 8. This includes'the containment purge and gaseous decay tank releases as well as the normal ventilation system and condenser vacuum exhaust releases. All releases are either greater than 500 hours in duration or are made at random, not depending upon atmospheric conditions or time of day. The releases are lumped together and calculated as an entity. The historical annual average X/g is therefore used throughout this manual for all gaseous effluent set-point and dose calculations. Airborne releases are further subdivided into two subclasses: 1.2.1 Iodine 131 Iodine 133 Tritium and Radionuclides in Particulate Form with Half-lives Greater than Ei ht
'~Da s In this model, a controlling location is identified for assessing the maximum exposure to a MEMBER OF THE PUBLIC 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 vegetation 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. The release rates of these nuclides will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20. 1-3 Rev. 1 09/20/85
0 1.2.2 Noble Gases The air dose from both the beta and gamma radiation component of the noble gases will be assessed and compared to the 10 CFR 50, Appendix I design The noble gas release rate will be'bjectives. converted to instantaneous 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 of Technical Specification 3.11.2.1. Methods are described for determining the annual cumulative dose to a MEMBER OF THE PUBLIC, from gaseous effluents and direct radiation for critical organs, to assure compliance with Technical Specification 3.11.4. The Radiological Environmental Monitoring Program is described in this manual; also included is the Annual Iand Use Census Survey. The ODCM will be maintained for use as a document of acceptable methodologies and calculations to be used in implementing the Technical Specifications. Changes will be incorporated into the ODCM in accordance with Technical Specification 6.14. 1.3 Nuisance Pathwa s This section addresses the potential release pathways which should not contribute more than lOX of the doses evaluated in this manual. Table 1-1 identifies these potential release pathways which would occur primarily due to operation with, primary to secondary leakage. The doses from these nuisance pathways'will periodically be evaluated to ensure that they do not contribute more than lOX of the doses evaluated in this manual. If any nuisance pathway exceeds this limit then the ODCM methodology for calculation of doses will be applied to each applicable release pathway. Rev. 1 09/20/85
0 TABLE l-l NUISANCE PATHWAYS Evaporation Pond Cooling Towers Laundry Building Exhaust Unmonitored Secondary System Steam Vents/Reliefs Turbine Building Ventilation Exhaust Unmonitored Tank Atmospheric Vents 1-5 Rev. 1 09/20/85
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2.0 GASEOUS EFFLUENT MONITOR SETPOINTS Technical S ecification 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 [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 and adjusted in accordance with the methodology and parameters in the ODCM. The general methodology for establishing low range gaseous effluent monitor setpoints is based upon a site release rate limit in uCi/sec derived from site specific meteorological dispersion conditions, radioisotopic distribution, and whole body and skin dose factors. The high alarm of the low range monitors will alarm/trip when the release rate from an individual vent will result in exceeding Technical Specification 3.11.2.1. 80X of Technical Specification 3.11.2.1 limits is considered to be the site release rate limit. The site release rate limit will be allocated among the licensed units'elease points. The unit release. rate limit will then be utilized for the determination of gaseous effluent monitor setpoints. A fraction of the unit
/
release rate limit is then allotted to each release point and its monitor alert setpoint (PCi/cc) is derived using actual or fan design flow rates. Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be reviewed based on actual release data. For the purpose of implementation of Technical Specification 3.3.3.9, the alarm setpoint levels for low range effluent noble gas monitors are established to ensure that personnel are alerted when the noble gas releases approach the total body dose rate of 500 mrem/yr and 3000 mrem/yr skin dose (Technical Spec'ification 3'11.2 1). The equations in Section 3.0 of this manual provide the methodology for calculating the gaseous effluent dose rate. 2-1 Rev. 1 09/20/85
The evaluation of doses due to releases of radioactive material can be simplified by the use of equivalent dose factors as defined in Section 2.1. The equivalent dose factors will be evaluated periodically to assure that the best information on isotopic distribution is being used for the dose equivalent value. 2.1 uivalent Dose Factor Determination The equivalent whole body dose factor is calculated as follows: eq Where: K the equivalent whole body dose factor weighted eq by historical radionuclide distribution in releases. the whole body dose factor due to gamma emissions for'each identified noble gas radionuclide i, in mrem/yr per p Ci/m3 from Table 3-1. the fraction of noble gas radionuclide i in the total noble gas radionuclide mix. The equivalent skin dose factor is calculated as follows: (Z+l.m)eq - Z [(L + l.m )(f )] (2-2) 2-2 Rev. 1 09/20/85
l 1 i e l l Il
Where: (I,+l.m)eq the equivalent skin dose factor due to beta and gamma emissions from all noble gases released, weighted by the historical radionuclide distribution in releases. Li 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 3 i, in mrad/yr per PCi/m from Table 3-1. the fraction of noble gas radionuclide i in the total noble gas radionuclide mix. 2.2 Site Release Rate Limit (Q ) The release rates corresponding to 80X of the whole body (QWB) and skin (QS<) dose rate limits are calculated using the equivalent dose factors defined in Section 2.1. QSITE is the lower f WB The site release rate limit or QSK, thus assuring that the more restrictive dose rate limit will not be exceeded. The QSITE is established as follows: (D ) QSITE, WB WB (0.8) (2-3) X QSBW 2-3 Rev. 1 09/20/85
0 0
Where: QSITE,WB the site release rate, in pCi/sec, that would deliver a dose rate 80X of the whole body dose rate limit, DWB. WB whole body dose'rate limit of 500 mrem/yr. K eq equivalent whole body dose factor, in mrem/yr per pCi/m 3 weighted by the historical radionuclide distribution.
-6 (X/Q) ~
8.91X10, the highest calculated annual 3 average dispersion parameter, in sec/m , at the Site Boundary for any of the 3 units, from Table 3-2. 0.8 administrative factor to provide conservatism to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded. Q , ( SK) (0.8) SITE> SK L+1 e 1M eq X Q (2-4 ) Where: QSITE,SK the site release rate limit, in p Ci/sec, that would deliver a dose rate 80% of the skin dose rate limit, D SK skin dose rate limit of 3000 mrem/yr. 2-4 Rev. 1 09/20/85
~ i 0 0
(L+l.m)eq equivalent skin dose factor, in mrem/yr per 3 p Ci/m , weighted by the radionuclide distribution.
-6 'X /Q)SBW 8.91X10 , the highest calculated annual average dispersion parameter, in sec/m 3 , at the Site Boundary for any of the three units, from Table 3-2.
0.8 administrative factor to provide conservatism to compensate for any unexpected variability
.,in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.
After determination of the Q whole body and skin dose rates SITE (equations 2-3 and 2-4, respectively), the most conservative result will be used as QSITE, the site release rate limit. 2.3 Unit Release Rate Limits ( ) NIT-Typically Q will be divided equally among operating units. If operational history dictates a larger fraction of the QSITE be assigned to a specific unit then a weighted average 'of each unit's contribution to the QSZ will be utilized to determine the QUNIT. UNIT UNIT QSITE (2-5) where: unit release rate limit, in u Ci/sec. Rev. 1 09/20/85
I UNIT the fraction ( < 1) of noble gas historically released from a specific operating unit to the total of all noble gas released from the site.
~SEE the site release rate limit, in p Ci/sec determined in section 2-2 of this manual.
2.4 Set oint Determination To comply with Technical Specification 3.3.3.9, the alarm/trip setpoints can now be established using the unit release rate limit (JUNKET) to ensure that the noble gas releases do not exceed the dose rate limits. To allow for multiple sources of releases from different or common release points, the effluent monitor setpoint includes an administrative factor which allocates a percentage of the unit release rate limit to each of the release sources. Monitor setpoints will also be adjusted in accordance with Station Manual Procedures to account for monitor-specific characteristics. 2.4.1 Monitors RU-141 RU-143 and RU-145 The alarm/trip setpoint for Monitors RU-141, RU-143, and RU-145 is calculated as follows: 0 Monitor Setpoint (pCi/cc) < llNITi~~.12x10 ~ (Flow Rate) cfm )
)(
(2-6) Mhere: Monitor Setpoint the setpoint for the effluent monitor, in pCi/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded. 2-6 Rev. 1 09/20/85
QUNIT unit release rate limit, in P Ci/sec, as determined in Section 2.3. Flow Rate ~ t'e flow rate, in cfm, from flow rate monitors or the fan design flow rate for the release source under consideration. 2.12X10 conversion factor, cubic feet/minute per cubic centimeter/second. fraction of QUNIT allocated for a specific release point. The sum of these administrative values will be less than or equal to one. 2.4.2 Monitor RU-12 The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows:
-3 cfm )
Monitor Setpoint (u Ci/cc) < [(QUNIT) (2.12x10 cc/sec) (0.9) (a) 1 where: Monitor Setpoint ~ the setpoint for the monitor, in pCi/cc at STP, which provides a safe margin of assurance that the allowable dose, rate limits wi'll not be exceeded. QUNIT- unit release rate limit, in uCi/sec, as determined in Section 2.3. Flow Rate flow rate, in cfm at STP at which the tank will be released. 2-7 Rev. 1 09/20/85
0 fraction of Q allocated for a specific release point. This administrative value should be equal to or less than the administrative value used for the Plant Vent. 0.9 an administrative value to account for potential increases in activity from other contributors to the same release point.
-3 =
2.12X10 conversion factor, cubic feet/minute per cubic centimeter/second. If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms, and yet assure an alarm should an inadvertent release occur. 2.5 Monitor Calibration The calibration factor for each monitor is entered into the Radiation Monitoring System Database and may change whenever the monitor is calibrated. Calibration is performed in accordance with Station Manual Procedures. The calibration factor may vary with detector age and equipment changes. The typical calibration conversion factor for the Plant Vent Airborne Monitor (RU-143), Condenser Evacuation Monitor
.(RU-141), and Fuel Building Vent Exhaust (RU-145) is based on the detector energy response curve (Figure 2-1) and the FSAR source term.
The typical calibration conversion factor for the Haste Gas Decay Tank Monitor (RU-12) is based on Kr-85 calibration as indicated on Figure 2-2. 2-8 Rev. 1 09/20/85
10 I
~ \ 2 E
CJ E p 10 t 0 0
'g 0 S
UJ 10' i S i ~ ~ I 7 I I 10 Maximum Beta Energy (Mev) FIGURE 2-1 CALIBRATION CURVE FOR PVNGS EFFLUENT MONITORS RU-14lp RU-143, AND RU-145. RESPONSE TO NOBLE GAS
Reference:
Kaman Instrumentation Corporation Calibration Report K-82-50-U(R) Rev. 1 09/20/85
10 10 10 tzl Kr-85: 1.22(10') cpm 10" per pci/cc o CO E 10 10 10 10 10 10-'0'CTIVITY CONCENTRATION ( >Ci/cc) FIGURE.2-2 INITIAL CALIBRATION CURVE FOR PVNGS MONITOR RU-12 RESPONSE to Kr-85 GAS
Reference:
Kaman Instrumentation Corporation Calibration Report K-83-30-V(R) 2-10 Rev. 1 09/20/85
3.0 GASEOUS EFFLUENT DOSE HATE Technical S ecification 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site (see [Technical Specification] Figures 5.1-1 and 5.1-3) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For I-131 and I-133, for 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.
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 and batch effluent releases are given in the Station Manual Procedures. The dose rate in unrestricted areas shall be determined using the following equations. I For whole body dose rate: WB i <<<i) (X/Q)SBW (Qi)i (3-1) For skin dose rate: DSK
- ~i ((Li + 1.1Mi) (X/Q)SBg (Qi)] (3-2) 3-1 Rev. 1 09/20/85
Where: K the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per p Ci/m3 from Table 3-1. Qi the release rate of radionuclide i, in p Ci/sec.
-6
( ~Q)SBW 8.91x10 , the highest calculated annual average dispersion parameter, in sec/m 3 , for any of the three units, from Table 3-2. WB the annual whole body dose rate (mrem/yr.). Li the skin dose factor due to the beta emissions for each identified noble gas radionuclide 3 i, in mrem/yr per 9 Ci/m from Table 3-1. the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr perP Ci/m3 from Table 3-1 (conversion constant of 1.1 converts, air dose-mrad to skin dose-mrem). SK the annual skin dose rate (mrem/yr). 3-2 Rev. 1 09/20/85
0 3.2 Radionuclides Other Than Noble Gases The methods for, sampling and analysis of continuous and batch releases for I-131, I-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, 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 total organ dose rate in"unrestricted areas shall be determined by the following equation: Do ~i [(Pi)(X/Q)SBW (Qi)l (3-3) Where.' 3 m the dose factor, in mrem/yr per PCi/m, for radionuclide i, for the child inhalation pathway, from Table 3-3.'
-6 ,(X/Q)SBW 8.91xXO , the highest calculated annual average dispersion parameter, in sec/m 3 , at the Site Boundary, for any of the three units, the release rate of radionuclide i, in PCi/sec D
0 the total organ dose rate (mrem/yr). 3-3 Rev. 1 09/20/85
t 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 Ni Radionuclide (mrem/yr per liCi/m ) (mrem/yr per PCi/m3) (mrad/yr per PCi/m3) (mrad/yr per NCi/m3) Kr-83m 7 56E-02(b) 1.93E+01 2.88E+02 Kr&5m 1.17E&3 1.46E+03 1.23E+03 1.97E+03 Kr-85 l. 61E&1 l. 34E&3 l. 72E&1 1.95E+03 Kr&7 5.92EK3 9.73E&3 6.17E&3 1.03E&4 Kr-88 Kr-89 1.47EK4 2.37E&3 l. 52E+04 2. 93E&3 1.66E&4 1. 01E+04 1.73E+04 1.06E+04 Kr-90 l. 56EK4 7.29E+03 1.63E+04 7.83K+03 Xe-.131m 9.15E+01 4.76E&2 1.56E+02 1.11E&3 Xe-133m 2. 51E&2 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E&2 3.06E&2 3.53E+02 1.05E&3 Xe-135m 3.12EK3 7. 11E&2 3. 36E&3 7.39E+02 Xe-135 1. 81E&3 1.86E&3 1.92E+03 2.46E&3 Xe-137 1.42EK3 l. 22E+04 1.51E+03 1. 27E&4 Xe-138 8.83E&3 4.13E+03 9. 21E&3 4.75E&3 Ar&1 8. 84E+03 2. 69E&3 9.30E&3 3.28E+03 a The listed dose factors are for noble gases that may be detected in gaseous effluents. Og (>>7.56E02 Mm 7.56 x 10 2. N~ O CO
Reference:
Regulatory Guide 1.109, Table B-l.
l
,I 0
TABLE 3-2 (Sheet 1 of 3) PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY CENTERED ON UNIT 1 DISTANCE x/q D/g DIRECTION (METERS) (SEC/m3) (m ~) N 1037 4.93 E&6(a) 9.24 E&9 NNE 1057 4.14 E-06 1.19 E NE 2206 2.84 E-06 6.84 E&9 ENE 1967 2.51 E&6 4.43 E-09 E 192? 2.56 E-06 3.24 E9 ESE 1967 2.61 E-06 2.46 E-09 SE 2049 3.56 E-06 2.36 E&9 SSE 2730 3.80 E&6 1.58 E&9 S 3006 5.07 E-06 1.78 E&9 SSW 2258 6.52 E&6 3.20 E-09 SW 1487 7.47 E&6 5.65 E9 WSW 1251 4.52 E6 5.93 E-09 W 1225 4.73 E-06 9.49 E&9 WNW 1244 3.76 E-06 6.76 E-09 NW 1254 3.43 E 5.87 E&9 NNW 1069 3.70 E-06 7.26 E-09 (a) 4.93 E6 4.93 X 10 6
Reference:
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985. 3-5 Rev. 1 09/20/85
TABLE 3-2 (Sheet 2 of 3) PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR IONG TERM RELEASES AT THE SITE BOUNDARY CENTERED ON UNIT 2 DISTANCE x/q D/q DIRECTION (METERS) (SEC/m3) (m ~) N 1318 3.85 E-06 6.17 E-09 NNE 1342 3.18 E&6 7.93 E&9 NE 2545 2.42 E-06 5.34 E-09 ENE 2206 2.22 E-06 3.64 E&9 E 2163 2.27 E-06 2.66 E-09 ESE 2067 2.32 E-06 2.11 E&9 SE 2101 3.47 E-06 2.26 E9 SSE 3026 3.43 E-06 1.32 E9 S 2699 5.16 E-06, 1.97 E-09 SSW 1836 7.90 E-06 4.56 E&9 SW 1208 7. 72 E6 6.88 E-09 WSW 1014 5.55 E-06 8.44 E-09 W 993 5.86 E-06 1.34 E8 WNW 1010 4.67 E&6 9.60 E&9 NW 1191 3.62 E-06 6.40 E-09 NNW 1342 2.85 E-06 4.87 E&9
Reference:
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985. 3-6 Rev. 1 09/20/85
TABLE 3-2 (Sheet 3 of 3) PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY CENTERED ON UNIT 3 DISTANCE X/Q D/Q . DIRECTION (METERS) ( SEC/m3) (m ~) N 1661 3.54 E6 4.86 E-09 NNE 1693 2.86 E-06 6.23 E&9 NE 2756 2.21 E-06 4.65 E&9 ENE 2337 2.08 E-06 3.30 E&9 E 2290 2.14 E-06 2.41 E&9 ESE 2023 2.37 E-06 2.10 E&9 SE 2256 3.24 E-06 2.00 E-09 SSE 2786 3.72 E-06 1.52 E&9 S 2346 5.90 E&6 2.51 E9 SSW 1607 8.91 E-06 5.73 E&9 SW 1057 8.68 E-06 8.61 E-09 WSW 889 5.34 E-06 8.83 E9 W 871 6.72 E-06 1.67'E-08 WNW 885 5.37 E-06 1.19 E&8 NW 1045 4.17 E&6 7.98 E&9 NNW 1561 2.93 E-06 4.58 E&9
Reference:
Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a'eptember, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985. 3-7 Rev. 1 09/20/85
I TABLE 3-3 Pi Values for the Palo Verde Nuclear Generating Station Inhalation Pathway (a)
~Isoto e (mrem/ r/WCi/m3)
H 3 le12EW3(b) Cr 51 1.70E+04 Mn 54 1.57E+06 Fe 59 1.27E+06 Co 58 l. 10EK6 Co 60 7. 06E+06 Zn 65 9.94E&5 Sr 89 2.15E+06 Sr 90 1. 01E&8 Zr 95 2.23E+06 Sb 124 3 '4E+06 I 131 1.62E+07 I 133 3.84E&6 Cs 134 1. 01E+06 Cs 137 8.24E+05 Ba 140 1. 74E+06 Ce 141 5.43E&5 Ce 144 1.19E+07 (a) Child receptor
) le12E&3 ~ 1.12 x 103
References:
NUREG133, Section 5.2.1.1 (Calculation of Pi (inhalation)) Regulatory Guide 1.109, Table E-5, Table E-9. NUS Corporation letter NUS-ANPP-1385, dated 9/26/85. 3-8 Rev. 1 09/20/85
0 4.0 DOSE DUE TO GASEOUS EFFLUENT 4.1 Noble Gases Technical 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 (see [Technical Specification] Figures 5.1-1 and 5.1-3) 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 and,
- 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 each unit during any specified time period shall be determined by the following equations: For gamma wadiation: D yu (3.17 x 10-8) Z i [(Mi) ( X Q)SBu(Qi)~ For beta radiation: D Where: 8u (3."17 x 10-8) E i [(Ni) ( ~Q)SBu(Qi) (4-2) the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per P Ci/m3 from Table 3-1. 4-1 Rev. 1 09/20/85
0 0 0
N i the air dose factor due to beta emissions for each identified noble gas radionuclide i, in 3 mrad/yr per p Ci/m from Table 3-1. 5 /g)SB the highest calculated annual average dispersion parameter, in sec/m 3 , at the site boundary for the particular unit, from Table 3-2. 7.47X10 from Unit 1 7.90X10 from Unit 2 8.91X10 from Unit 3 D Yu the total gamma air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY. Dg the total beta air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY. the integrated release, from the particular unit, in u Ci, of each identified noble gas radionuclide i, in gaseous effluents for a specified time period. 3.17 K 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. 4-2 Rev. 1 09/20/85
0 0
4.2 Iodine 131 Iodine-133 Tritium and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Da s Technical S ecification 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see [Technical Specification] Figures 5.1-1 and 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
The organ dose to an individual from I-131, I-133, tritium, and all radionuclides in particulate form, with half-lives greater than eight days, in gaseous effluents released to unrestricted areas from each reactor unit is calculated using the following expressions: Dou (3.17 x 10 ) Q (E k (Rik Wk) (Qi)] Where: D ou the total accumulated organ dose from gaseous effluents for a particular unit, to a MEMBER OF THE PUBLIC, in mrem, at the SITE BOUNDARY or at the controlling location. Q a the quantity of radionuclide i, in'i, released in gaseous effluents from a particular unit. Rev. 1 09/20/85
ik the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mrem/yr per li Ci/m3 and for the food and ground plane pathways in m 2 mrem/yr per 9 Ci/sec) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15.
-8 3.17X10 the inverse of seconds per year (yr/sec).
Wk the highest annual average dispersion or deposition parameter for the particular unit, used for estimating the dose at the site boundary or to a MEMBER OF THE PUBLIC at the controlling location for the particular unit. ( X/Q) , in sec/m 3 for the inhalation pathway and for all tritium calculations, for organ dose at the site boundary, from Table 3-2.
~ 7.47X10 -6 from Unit 1 7.90X10 from Unit 2 8.91X10 from Unit 3 3
( X/Q)RU, in sec/m for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16.
= 2.92X10 -6 from Unit 1 2.19X10 from Unit 2 2.31X10 from Unit 3 Rev. 1 09/20/85
i ( D/g) in m-2 for the food and ground plane pathways, for organ dose at the site boundary, from Table 3-2. 1.19X10 from Unit 1
-8 1.34X10 from Unit 2
-8
= 1.67X10 from Unit 3
( D/q)RU'n m ', for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16. 3.25X10 from Unit 1
-10,'from Unit 3.88X10 2
-10
~ 4.21X10 from Unit 3 Residences, vegetable gar'dens and meat and milch animals located within 5 miles of the site will be identified during the annual land use census. The controlling pathway and location will be identified and will be used for all MENBER OF THE PUBLIC dose evaluations.
in with the The R i values were calculated accordance methodologies in NUREG-0133 and generated using the GASPAR . code. The following site specific information was used to calculate Ri: Value fraction of year milch animals and beef animals are on pasture, fP 0.75 fraction of daily intake of milch animals and beef animals derived from pasture while on pasture, f 0.35 4-5 Rev. 1 09/20/85
1 0 0
fraction of year vegetables are grown, fl, approximation 0.667 absolute humidity (g/m 3 ) over the growing season, H These site specific values are from the PVNGS Environmental Report, Section 2 and Appendix 5-B. Technical S ecification 3.11.2.4 The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see [Technical Specification] Figures 5.1-1 and 5.1-3) when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor uPt, to areas at and beyond the SITE BOUNDARY (see [Technical pecification] Figures 5.1-1 and 5.'1-3) when averaged over 31 d's would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. Where possible, consideration for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections. 4.3.1 - Noble Gas Dose Pro ection For the purpose of satisfying requirements of Technical Specification'.11.2.4, the air dose at the site boundary due to noble gases released in gaseous effluents from a particular unit is projected at least once per 31 days. 4-6 Rev. 1 09/20/85
The air dose, in mrads for the current quarter is determined using the methodology described in Section 4.1 of this manual. This information is used to determine an air dose projection for the next 31 days using the following equations: Por gamma e radiation: 31 day y ~ (D qtr/Tqtr) 31 + CD (4-4) y y Por beta radiation: 31 day < (D < qtr/Tqtr) 31 + CD where: D y qtr ~ the total gamma air dose due to noble gases released in gaseous effluents for the current quarter, in mrads, at the site boundary. D g qtr the total beta air dose due to noble gases released in gaseous effluents for the current quarter, in mrads, at the site boundary.
' in Tqtr the time period, days, over which P qtr and Dg qtr were integrated.
31 the number of days over which the dose projections are, made. 4-7 Rev. 1 09/20/85
'll 0'
31 dayy the 31 day projected gamma air dose due to noble gases released in gaseous effluents, in mrads, at the site boundary. 31 day g the 31 day projected beta air dose due to noble gases released in gaseous effluents, in mrads, at the site boundary.
'I CD y any current or projected gamma air dose, in mrads, due to noble gases released in gaseous effluents, which could have a significant impact on 31 day ~
CD g ~ any current or projected beta air dose, in mrads, due to noble gases released in gaseous effluents, which could have a significant impact on 31 day g 4.3.2 Or an Dose Pro ection For the purpose of satisfying requirements of Technical Specification 3.11.2.4 for a particular unit, the organ dose, in mrem, for the current quarter is determined using the methodology described in Section 4.2 of this manual. This information is used to determine an organ dose projection for the next 31 days using the following equation: 31day ~ (D qtr/Tqtr)31 + CD 0 0 0 4-8 Rev. 1 09/20/85
where: D 0'nit qtr the total due organ dose from a particular to I-131, I-133, tritium, and radionuclides in particulate form with all half-lives greater than eight days, released in gaseous effluents for the current quarter, in mrem. Tqtr the time period, in days, over which D 0 qtr was integrated. 31 the number of days over which the dose projections are made. 31 day ~ the 31 day projected organ dose, in mrem, from a particular ungt. CD 0 any current or projected organ dose for a particular unit, in mrem, which could have a significant impact on 31 day . 0 4-9 Rev. 1 09/20/85
e TABLE 4-1 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION( PATIMAY = GROUND
-----t----xd NUCLIDE
!Io 54 T. BODY GI-TRACT BONE
-+
LIVER
-------- +
KIDHEY
+
THYROID
+
LUNG
+
SKIN
+
i 1.38E+09 f+ 1.38E+09 i 1.38E+09 i 1.38E+09 i 1.38Et09 1.38E+09 1.38E+09 1.62E+09
+ - t + +
(
+
i
+
J
+ - +
[ Cr 51 i 4.65Et06 i 4.65E+06 i 4.65E+06 i 4.65E+06 4.65E+06 i 4.65E+06 4.65E+06 i 5.49E+06 i
+ + + + t) +
)
+ + - " +
F 59 f 272EOB 272EOB [ 272E08 272EOB 272 08 2.72E+08 272EO 20
+ +
)
+
)
+ t] )
+
I
+
I
+
I
+
Co 58 I 3.79E+08 3.79Et08 [ 3.79E+08 [ 3.79E+08 ] 3.79E+08 f 3 79E+08 3 79E+08 4'44E+08
+
f
+ + + +
)
+
f
--+- ------+I Co 60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 f 2 15E+10 2 15E+10 ] 2 15E+10 2 ~ 52E+10 I
---------+) ----- +
(
------- +----------+--
f (
--- - +- )
+ +
(
+ ~ +
Zo 65 7.44E+08 7.44Et08 7.44E+08 7 .44E+08 7.44Et08 / 7.44E+08 ] 7 .44E+08 8.56E+08 I + (
+
f f
+
f [
+ ------+-----
f
-+[
CD Sr 89 ] 2. 16E+04 f 2. 16E+04 ] 2. 16E+04 f 2. 16Et04 ] 2. 16E+04 [ 2. 16Et04 ) 2. 16E+04 f 2.50E+04 ) Zr 95 2.45E+08 2.45E+08 2.45E+08 2.45E+08 [ 2 '5E+08 ) 2 '5E+08 ] 2 45E+08 [ 2 84E+08 I t[ + f [
+ t f
+ + + + +
Sb124 f 5.98E+08 5.98E+08 [ 5.98E+08 f 5.98E+08 5 ~ 98E+08 f 5 ~ 98E 08 f 5 ~ 98E 08 [ 6 ~ 91E+08 I
)
+ t +
)
+ + + +
I 131 i 1.72E+07 i 1.72E+07 i 1.72E+07 i 1.72E+07 ) 1.72E+07 ) 1.72E+07 i 1.72E+07 i 2.09E+07 )
+ + + + + + + + +
I 133 i 2.45E+06 i 2.45Et06 i 2.45E+06 i 2.45E+06 ) 2.45E+06 i 2.45E+06 i 2.45E+06 ) 2.98E+06 i
+ + + + + + + + +
Cs134 [ 6.82E+09 ) 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 7.96E+09
+ +
)
+
)
-+- ---+--
) (
+
)
+
)
+ - )
+
Cs137 1.03E+10 1.03E+10 1.03E+10 / 1.03E+10 f 1.03E+10 f 1.03E+10 ] 1.03E+10 ] 1.20E+10
+
f
------+----------t---
f )
------t----------t----------t----------t----------t----------t J Ba140 2.05Et07 2.05Et07 2.05E+07 2.05Et07 2 '5E+07 f 2.05E+07 2.05E+07 ] 2.34E+07 OQ
)
t )
+
)
+ t
)
+
)
+
)
+ +
)
+
c) m Ce141 1.36E+07 1.36E+07 1 ~ 36Et07 1.36Et07 1.36E+07 1.36E+07 1.36E+07 1.54E+07 W( + f f
+
)
+
)
+ +
)
t
) f
+
f
+
f
+
C) Ce144 J 6.95E+07 ) 6.95E+07 f 6.95E+07 ) 6.95E+07 ( 6.95E+07 ) 6.95E+07 f 6.95E+07 ] 8.03E+07 [
+ + + + + + + +
co (a) R values are in units of m2-mrem/yr per >Ci/sec. (b) 1.38E+09 = 1.38 X 10 . Reference': NUREG-0133; NUS 'Corporation letter NUS-ANPP-1385, dated 9/26/85.
STATION(a) TABLE 4 2 R VALUES POR THE PALO VERDE NUCLEAR GENERATING PATINAY ~ VEGET AGE GROUP = ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+b + + -+-- - ---- +-------- -+ + +
H 3 4.34E+OP't 4.34E~03 ) O.OOE-OI ) 4.34E+03 ) 4.34E+03 4.34E+03 4.34E+03 4.34E+03
)
+ +
)
+
)
+ t) )
+
Hn 54 5.65E~07 9.07E+08 O.OOE-OI 2.96E+08 8.81E+07 O.OOE-01 ) O.OOE-Ol ) 0 ~ OOE-01
) ) ) ) ) )
+ + + + + +
. Cr 51 3.99E+04 )
1.006+07 ) O.OOE-01 ) O.OOE-OI ) 8.79E+03 ) 2.38E+04 ) 5.29E+04 ) O.OOE-OI
)
+ + + + +
Fe 59 ) 1.02E+08 ) 8.91E+08 )
- l. 14E+08 )
2.67E+08 ) O.OOE-01 ) O.OOE-Ol ) 7 .47E+07 ) O.OOE-OI
- )
+ + + + + + +
Co 58 6.38E+07 5.77E+08 O.OOE-OI 2.85E+07 O.OOE-OI O.OOE-01 0 OOE-01
~ O.OOE-01 )
) ) ) ) ) ) ) )
+ + + +- + +
Co 60 3.51E<08 2.99Et09 O.OOE-Ol 1.59E+08 O.OOE-OI O.OOE-01 O.OOE-01 O.OOE-OI ) t) } j +
) )
+
)
+
)
+ -+) -+
Zn 65 4.3IE~08 6.01E+08 3 DOE+08 9 ~ 54E+08 6 38E+08 0 OOE 01 0 OOE 01 0 OOE 01 I
) ) ) ) ) ) ) )
+ + + + + + + + +
Sr 89 2.60E+08 1.45E+09 9.06E+09 ) O.OOE-01 O.OOE-01 O.OOE-01 ) O.OOE-01 ) 0 ~ OOE-01 ) (
) ) )
+
)
) + + + +
Sr 90 1.41E+11 1.66E+10 5.76E+11 O.OOE-OI O.OOE-OI O.OOE-01 O.OOE-OI ) O.OOE-OI )
) ) ) ) ) ) )
+ + + + + + + + +
Zr 95 2.35E+05 1.10E+09 1.08E+06 3.47E+05 5.45E+05 O.OOE-OI O.OOE-OI ) O.OOE-01
+
)
+
)
+
) )
+- +
) )
+
)
+ -+)
Sbl24 3.7SEi07 2.71E+09 9.53E+07 1.80E+06 O.OOE-OI 2.31E+05 ) 7.42E+07 ) O.OOE-OI
) ) ) ) ) )
+ + + + + -+
I 131 ) 4.49E+07 ) 2.07E+07 ) 5 47E+07 ) 7.83E+07 ) 1 34E+08 ) 2 57E+10 ) 0 OOE 01 ) 0 OOE 01 I
+ + + + + +
I 133 7.35E+05 2.17E+06 I 39E+06 ) 2 ~ 41E+06 ) 4 21E+06 ) 3 54E 08 ) 0 ~ OOE 01 ) O.OOE 01 I
+
) )
+
)
+ + + -+--- + +
Cs134 ) 8.62E+09 ) 1.85E+08 ) 4.43E+09 ) 1.05E+10 ) 3.41E+09 ) O.OOE-OI ) 1.13E+09 ) O.OOE-01 )
+ + + + + + +
Cs137 5.42E~09 1 6OE+08 6 05E 09 8 28E 09 I 2 BIE 09 ) O.OOE 01 ) 9 34E+08 ) 0 OOE 01 I
) ) ) )
+ + + + + + +
Ba140 6.17E+06 1.94E+08 9.42E+07 1.18E+05 4.03E+04 O.OOE-OI 6.78E+04 O.OOE-OI omm5 ) )
+
)
+
)
+
)
+
)
+
)
+
)
+
WC h) ~ Ce141 ) 1.33E+04 ) 4 ~ 47E+08 ) 1 73E+05 ) 1.17E+05 I 5'43E+04 ) 0 OOE Ol ) 0 ~ OOE Ol ) 0 OOE Ol l
+ + + + + + +
CO Ce144 ) 1.67E+06 ) 1 05E+10 ) 3 IIE 07 ) I 30E 07 I
'72E+06 ) 0 ~ OOE 01 ) 0 OOE 01 ) 0 OOE 01 I co + + + + + + +
Ln (a) R values are in units of mrem/yr per pCi/m3 for tritium, and in units of m2-mrem/yr per )LCi/sec for all others. (b) 4.34E+03 = 4.34 X 103.
1 TABLE 4-3 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PATH'r(AY = VEGET AGE GROUP "- TEEN HUCLIDE T.BODY. GI-TRACT BDWE LIVER KIDNEY THYROID LUNG SKIN
---------+--------vrf- + -+ + --+- + +
H 3 5.08E<OS 'f 5.08E+03 0.00E-OI 5 .OBE+03 5.08E+03 5.08E+03 5.08E+03 5.08E+03 l. ( ( ( (
+ +- + -+ +
(
-+- +----------+ - -- --+(
( ( Hn 54 8.72E+07 9.02E+08 O.OOE-OI 4.40E<08 1.31E+08 O.OOE-01 O.OOE-OI O.OOE-DI
--+--------
( ( ( ( ( ( ( ( Cr 51 ( 5.58E+04 9.37E+06 O.OOE-OI O.OOE-OI 1.22E+04 3. IOE+04 ( 7.96E+04 O.OOE-DI ( (
+ + +- +
(
- -- +---
( (
+ - -+--- (
+
(
+
Fe 59 1.52E+08 9.28E<08 1.68E+08 3.92E+08 O.OOE-OI O.OOE-OI 1.24E+08 O.OOE-OI (
+ +
(
-- (
+ --- +( ( (
+ +
(
-+- -
( (
+
C 58 9'60E+07 ( 5 74E+08 0 OOE 01 ( 4 17E 07 0 OOE 01 0'OOE 01 ( 0 OOE 01 I 0 00 -01 ( ( t ---+ --- ----+----- ---+ ---------+---- ---+ ---------+------ -+----- ( ( (
+
C 60 I 5'44E 08 ( 3'14E+09 0 OOE 01 2 41E+08 0 OOE 01 ( 0 OOE 01 0 OOE 01 ( 0'OOE 01 I
+
(
+- +
(
------+ z
(
+ ---+(
+ +
Zn 65 6.64E+08 6.03E+08 ( 4. IOE+08 1.42E+09 ( 9. 11E+DB O.OOE-Ol O.OOE-OI ( O.OOE-01 (
+ -----+----- -- +--- ------+-- ------t----------+- - ---+-- -------+----------+
( ( ( ( Sr 89 4.09E+08 1.70E+09 ( 1.43E+10 ( O.OOE-OI O.OOE-Ol ( O.OOE-DI O.OOE-01 O.OOE-01 I
+ ---
( ( (
+ ( (
+ + +- + + +
Sr 90 1 BOE+11 ( 2 05E+10 7 29E+11 ( 0 OOE 01 0 OOE 01 ( 0 OOE 01 ( 0 OOE Ol I 0.0o -01 I.
+ ---
( ~
+ ---
( ~ (
+ +- + + + + +
Zr 95 ( 3.56E+05 (
- 1. 19E+09 1.64E+06 5 18E+05 7 .60E 05 0 OOE 01 O.OOE 01 0.00 -01
( ( ( I I
+ + + +
(
+ - (
+ + +
24 I 5'E+0 I 2 96E+09 1 47E+08 2 70E+06 0 OOE 01 3 33E+05 I I 28E+08
+ +
(
+ +
(
----+-
(
-------+-
(
------+------ ---+- I
---+I I 131 (
3.97E+07 ( 1.46E+07 ( 5.28E+07 7.40E+07 1.27E+08 2. 16E+10 O.OOE-OI O.OOE-DI (
+ + +- + - (
+
(
+
(
+
(
+ ----+
I 133 (
+
6.66E+05 (
+
1.65E+06 (
+
1.29E+06
+
( 2.18E+06 ( 3.83E+06 ( 3.05E+08 ( O.OOE-OI I
-+-
. E- '
+ + + +
Cs134 I 7'52E~09 2.02EIOB 6,89E+09 1.62E+10 5.15E+09 O.OOE-01 1.97E+09 O.OOE-01
+
(
+ -- (
+ +
( (
+
(
+
(
+-- (
+
Cs137 4.56E+09 1.86E+08 9.84E+09 1.31E+10 4.46E+09 O.OOE-OI 1.73E+09 O.OOE-01 (
+ --- (
+
(
+ - +
( (
+
(
+
(
+
(
+ - (
+
Ba140 ( 6.87E+06 1.65E+08 1.07E+08 1.31E+05 4.43E+04 O.OOE-01 8.79E+04 O.OOE-01 (.
+ - (
+
(
+ -- +
( (
-+
(
+ t
( (
+ - +
Ce141 2.DOE+04 4.97E+08 2.60E+05 1.74E+05 8.18E+04 O.OOE-OI O.OOE-DI O.OOE-Ol (
+
(
+
(
+ -- +
( (
+
(
+
(
+
(
+
(
+
Ce144 j 2.74E+06 ( 1.28E+10 ( 5.11E+07 ( 2 ~ 11E+07 ( 1.26E+07 ( O.OOE-01 ( O.OOE-OI ( O.OOE-DI (
+ + + + + + + + +
(a) R values are in units of mrem/yr per p Ci/m3 for tritium, and in units of m2-mrem/yr per p Ci/sec for all others. (b) 5.08E&3 = 5.08 X 10
1 TABLE 4-4 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(<) PAT)MAY = VEGET AGE GROUP = CHILD NUCLIDE T. BODY GI-TRACT LI VER SKIN
---t---KIDNEY BONE THYROID LUNG
---------t--------qgj----------t-------- t - ---- + + -+
I 7 91E'03 1 7 91E+03 I o OOE-OI ( 7.91E+03 7.91E'03 I 7 91E+03 I 7 91E'03 7 91E'0
- I I I
+ + + + + + + +
~ )to 54 (
1.73E+08 ( 5.44E+08 ( O.OOE-OI ( 6.48E+08 ( 1.82E+08 ( O.OOE-OI ( O.OOE-01 ( O.OOE-OI ( Cr 51 ( 1.08E+DS 5.73E+06 O.OOE-01 O.OOE-OI 1.64E+04 6.DOE+04 1.09E+05 O.OOE-01 ( (
+ + -+( +
(
+
(
+
(
+
( (
+
F 59 ( 3.04E 08 6.36E+08 3 78E 08 6.11E 08 O.OOE 01 0 OOE 01 1 77Et08 0 OOE 01
+ +
( (
+
(
+
(
+
( ( t ( I
+
Co 58 1 90E+08 3 63E+08 0 OOE 01 6 22E 07 0 OOE 01 0 OOE Ol 0 OOE 01 0 OOE 0 I
+
( ( (
+ ---t>---------t----------t-( ( ~
( ( I
+
Co 60 '( 1.09E+09 2.05E+09 O.OOE-01 3.70E+08 O.OOE-01 O.OOE-01 O.OOE-OI O.OOE-01
+ +
( t ( (
+
(
+
(
+ t
( t ( ( Z" 6 ( I 31E+09 3.70E+08 7 92E 08 2 IIE 09 1 33E+09 0 ~ OOE Ol O.OOE 01 0 OOE 01 I
----+- +
( (
+ t
( (
+
(
+ t
( (
+ +
Sr 89 ( 9.DOE+08 ( 1.33E+09 3.43E+10 O.OOE-OI O.OOE-01 O.OOE-OI O.OOE-01 O.OOE-OI
+ +
(
+
(
+ t
( (
+
(
+
(
+ +
Sr 90 3.08E+11 1.64E+10 1.22E+12 O.OOE-01 O.OOE-OI O.OOE-01 O.OOE-OI O.OOE-01 (
+ +
(
-------+ ----- -+----------+-
( ( ( ( (
+-
(
---+ - - - +
Zr 95 7 27Et05 8.52E+08 3.72E+06 8-17E+05 1 17E+06 0 OOE 01 0 OOE 01 O.OOE 01 I t (
+
( (
-+--- ---- t - -----+-----
( ( (
+----
~
---+- - ----+-
( (
----- --+
Sbl24 1. 19E+08 2. 12E+09 3.38E+08 4.39E+06 O.OOE-01 7 ~ 47E+05 1.88E+08 O.OOE.-OI
) ) (
-----t( ( ( (
+- (
+
(
+
I 131 5.67E+07 8.89E+06 9.92E+07 9.98E+07 1.64E+08 3 ~ 30E+10 O.OOE-DI O.OOE-DI (
+
(
+ t( (
+- t
( (
+ ----- (
+- (
+ +.
I 133 ( 1.10E+06 ( 1.17E+06 ( 2.35E+06 ( 2.90E+06 ( 4.84E+06 ( 5.39E+08 O.OOE-01 O.OOE-01 ( ( (
+ + + + + + + + +
Csl34 ( 5.42E+09 ( 1.39E+08 ( 1.57E+10 ( 2.57E+10 ( 7.96E+09 O.OOE-01 2.86E+09 O.OOE-01 ( ( ( (
+ + + + + + + +
Cs137 3.31E+09 1.40E+08 2.34E+10 2.24E+10 7.30E+09 O.OOE-01 2.63E+09 O.OOE-01 Og Mm (
+
(
+ +
( (
+ t
( (
+- --- (
+- (
+ +
B 140 I 1 28E+07 1 IIE+08 2 20E 08 I 93Et05 6'2 +04 O.OOE-OI 1.15E+05 O.OOE-01 N~ ( ( ( ( (
-+-------
l. ( ( O + + + + + + + - + Ce141 ( 4.54E+04 ( 3.82E+08 ( 6.14E+05 ( 3.06E+05 ( 1.34E+05 O.OOE-01 ( O.OOE-01 O.OOE-OI co + (
+
C 144 ( 6 61E 06 ( 1'01E+10 ( 1 24Et08 ( 3 89E 07 I 2'15E 0 O.OOE-01 ( O.OOE-01 ( O.OOE-01
+ + + + + --+
(a) R values are in units of mrem/yr per PCi/m3 for tritium, and in units of m2-mrem/yr per )LCi/sec for all others. (b) 7.91E+03 = 7.91 X 103.
0 TABLE 4-5 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PATtMAY
- HEAT AGE GROUP = ADULT NUCLIDE T. BODY GI-TRACT BOttE LIVER KIDttEY THYROID LUNG SKIN
---+----- Tgg
-- -- +-------- -+- -+ -+-- -+--- +
N 3 I 6.55E+02 I 6.55E+02 O.OOE-OI i 6.55Et02 I 6.55E+02 6.55E+02 i 6.55E+02 6.55E+02
+ + t
(
+ +
(
+ +
J
+
)
+
Hn 54 i 8.29E+05 1.33E+07 i O.OOE-OI i 4.34E+06 i 1.29E+06 O.OOE-OI i O.OOE-OI i O.OOE-01
+ t
/
---+- +
)
+ + + - - +
Cr 51 2.04E+03 5.12E+05 i O.OOE-01 O.OOE-01 4.48E+02 i 1.22E+03 2.70E+03 O.OOE-01 i
+
( t J
+
J
+
i
+ +
J
+ -t i
+
Fe 59 7.78Et07 6.77E+08 ( 8.64E+07 2.03E+08 O.OOE-OI i O.OOE-01 i 5.67E+07 O.OOE-01 ti ------ -+] ---------+- - )
+ --- -----t---~- ---+-
i
+
/
+ +
Co 58 i 1.51Et07 1.37E+08 O.OOE-OI 6.74Et06 O.OOE-OI O,OOE-01 O.OOE-01 O.OOE-01
+ f f ) f ) ) ) f Co 60 i 8.49E+07 7.23E+08 i O.OOE-OI 3.85E+07 i O.OOE-OI i O.OOE-OI O.OOE-01 O.OOE-OI
+
i
+ ------+-- )
+ t t J i
+ t J
Z" 65 i 2 36E+08 I 3.29E+08 i 1 64E 08 i 5 23E 08 i 3 50E+08 i 0 ~ OOE 01 i 0 OOE 01 i O.OOE 01 I
+ + + + + + + + +
Sr 89 i 2.91E+06 1.63E+07 j 1.02E+08 i O.OOE-OI i O.OOE-01 i O.OOE-01 i O.OOE-01 J O.OOE-OI i
+
i
+ + -+- t----------i- t + +
Sr 90 I'58E 09 1'86E+08 6 45E 09 ) 0 OOE 01
/ 0 OOE 01 i 0 OOE 01 I 0 OOE 01 i 'OOE Ol 1
=
+
i J
+
/
+ ----t- + + t + +
Zr 95 1.46E+05 i 6 85E+08 I 4E 05 ) 2'16E 05 i 3 39E 05 i 0 OOE 01 I OOE 01 I J
+ + + -------+ + +
I
+
Sbl24 2.78E+06 1.99E+08 7.DIE+06 1.32Et05 i O.OOE-OI 1.70E+04 5.45E+06 O.OOE-OI I
) / J
+
i
----- --t-- -- -f-J i ) )
131 2.31E+06 i 1.06E+06 i 2 ~ 81E+06 i 4.03E+06 i 6.90E+06 i 1.32E+09 i 0.00E-OI i 0.00E-OI
+
J
+ -----t----------t------- - t----------+----------+
I 133 5. 14E 02 I 1 52E 01 I 9 69E 02 i I 69E 01 i 2.94E-OI i 2 '8E 01 i 0 OOE 01 i 0 OOE 01 i
) -e-Cs134 i 6.39E+08 i 1.37E+07 i 3.28E+08 i 7.81Et08 i 2.53E+08 i O.OOE-OI 8.39E+07 i O.OOE-OI
+ ---+- + + + +
J Cs137 4.05E+08 1.20E+07 4.52E+08 i 6.18E+08 2.10E+08 i O.OOE-OI 6.98E+07 O.OOE-01 o8 M0
+
i i
+
/
+ + +
i
+
J
+
I
+
I B>140 i 4.97E+05 i 1.56Et07 [ 7.59E+06 i 9.54E+03 i 3.24E+03 i 0.00E-DI i 5.46Et03 i O.OOE-01 h) O
~ t + +-------- -+ + + -+
Cel41 i 3.23E+02 i 1.09E+07 i 4.21E+03 i 2.85E+03 i 1.32E+03 i O.OOE-01 j O.OOE-OI i O.OOE-Ol i co Ln
+ + + + + + + t +
Ce144 3.67E+04 i 2.31E+08 6.84E+05 j 2.86E+05 i 1.70E+05 O.OOE-OI i O.OOE-OI O.OOE-01
+
)
+ +
)
t + + i
+ tJ
+
i (a) R values are in units of mrem/yr per )LCi/m for tritium, and in units of m2-mrem/yr per pCi/sec for all others. (b) 6.55E+02 = 6.55 X 102
~ .
p
TABLE 4-6 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PATIMAY ~ HEAT AGE GROUP = TEEtt ttUCLIDE T. BODY GI-TRACT BONE LI VER KIDttEY THYROID LUtlG SKI tt
--------+ + + +- --- -+
H 3 i 3.91E+02 f 3.91E+02 i O.ODE-OI i 3.91E+02 i 3.91E+02 i 3.91E+02 i 3.91E+02 i 3.91E+02 i
+ -+ + + + + + + +
th 54 i 6.57E+05 6.79E+06 i O.OOE-01 3.31E+06 9.88E+05 i a.aOE-al i O.OOE-al i a.OaE-OI 'j
-- + ----
) ) )
+ + + + + + + +
, Cr 51 1.63E+03 2.74E+05 O.OOE-DI O.OOE-OI / 3.57E+02 i 9.04E+02 2.32E+03 O.OOE-DI
+
( (
+
(
+
/
+- - -- -- + +
/
+
i
+ +
Fe 59 6.22E+07 3.81E+08 6.91E+07 1.61E+08 O.OOE-OI O.OOE-DI i 5.08E+D7 O.OOE-OI
+
)
---- ---+ ----- ---+ ---- ---+------
J / J i
-+------ +--- - ---+----------+
[ J
+
Co 58 i 1.20E+07 i 7.16E+07 i O.OOE-OI i 5.19E+06 / O.OOE-Ol i O.OOE-DI i O.OOE-OI i O.OOE-OI f Co 60 I 6.72E 07 I 3.89E+08 O.ODE-OI 2.99E+07 O.OOE-01 O.OOE-01 O.OOE-OI I - O.OOE-01
+ + --+I )
+
I
--+< --------+-
J I
+ -+- +
I Zn 65 1.87E+08 1.70E+08 1.15E+08 i 4.DIE+08 i 2.57E+08 i O.OOE-DI i O.ODE-DI ) O.OOE-DI
-ti /
+
/
+ + -- + t- + + +
i Sr 89 i 2.45E+06 j 1.02E+07 i 8.57E+07 O.DOE-DI i O.OOE-DI i O.OOE-DI O.OOE-DI O.OOE-DI
+ +
)
+ + +
)
+
/
+ - +
Sr 90 i 1.03E+09 i 1.17E+08 i 4.17E+09--+----------+- O.OOE-ol j O.ODE-01 'j O.ODE-01 i O.OOE-Ol / O.ODE-01 1
+ + +
)
--- --4-- ---- -+- ---- -+----------+
Zr 95 1.17E+05 3.93E+08 i 5.40E+05 1.70E+05 2.50E+05 i 0 OOE 01 i 0 OOE 01 I O.ODE 01 J J
+ ----- --+ i
+-
/
+ + + + +
Sb124 ) 2.23E+06 ) 1.15E+08 ) 5.72E+06 i 1.05E+05 i 0.00E-01 1.30E+04 i 5.DOE+06 i O.DDE-DI
+ + -+- + + +
J
+ + - +
I 131 1.76E+06 6.48E+05 2.34E+06 i 3.27E+06 5.64E+06 9.56E+08 0.00E-DI i O.ODE-DI
+
I
--- --+ J
-------+J
-- - +------ - J
+ ---- ---+--- -- ---+- -----
/ i
-+------ -+
/
I 133 i 4.19E-02 1.04E-01 f 8.11E-02 i 1.38E-01 2.41E-01 f 1.92E+01 f O.OOE-ol f O.OOE-01
+ +
)
+ - +
)
+ + + -+- - - ----+
2.85E+08 7.64E%6 i 2.61E+08 6.14E+08 1.95E+08 7.45E+07 Cs134
+
i J i J J O.OOE-DI
) )
O.OOE-OI i Cs137 i 1.74E+08 i 7.11E+06 3.75E+08 4.99E+08 f 1.70E+08 i O.OOE-DI / 6.60E+07 i O.OOE-DI
-+ + +
)
+
)
- + +- + + +
Be140 ) 4.04E+05 i 9.68E+06 i 6.28E+06 I 7.69E+03 i 2.6IE<03 i 0.00E-DI i 5.17E 03 I O.OOE-DI
+ + + - + + - + + + -+
Ce141 ) 2.71E+02 6.75E+06 ) 3.53E+03 ) 2.36E 03 ) 1.11E+03 ) D.ODE-DI ) D.DDE-DI i 0.00E-01 )
+ +
)
- + -+ + -+ +- + +
Ce144 3.10E+04 1.45E+08 5.76E+05 i 2.38E+05 I-42E+05 i O.OOE-DI O.OOE-01 O.DOE-Ol i
+
i
-- +
/
t)
- t t[ +
i
+- +
i
+
(a) R values are in units of mrem/yr per ItCi/m3 for. tritium, and in units of m2-mrem/yr per ItCi/sec for all others. (b) 3.91E+02 = 3.91 X 102.
I TABLE 4-7 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PATNAY = HEAT AGE GROUP > CHILD tlUCLIDE H 3 T. BODY
-+-- - -7H'-+ ---------t-GI-TRACT 4.72Et02 I 4.72E+02 BOttE O.OOE-DI LIVER 4.72E+02
+
KIDtlEY 4.72E+02
+-
THYROID 4.72Et02 LUltG 4.72E+02 SKIH 4.72E+02
+
(
+ +
(
-------+----
(
- +
( (
+- ( (
+
(
+
Hn 54 ( 1.DIE+06 ( 3.18E+06 ( 0.00E-01 ( 3.79E+06 ( 1.06E+06 0.00E-DI O.OOE-OI I O.OOE-OI ( I I
+ + + + + + +
. Cr 51 (
2.54E+03 1.35E+05 O.OOE-DI O.OOE-DI 3.85Et02 1.41E+03 2.57Et03 O.OOE-OI ( ( ( ( ( I I
+ I
+ + + + + +
Fe 59 ( 9.87E+07 ( 2.06E+08 ( 1.22E+08 1.98Et08 O.OOE-01 O.OOE-OI 5.74E+07 O.OOE-OI (
+ + + +
(
+
(
+ +---
( (
-+- ---- +
Co 58 ( 1.86E+07 3.54E+07 O.OOE-01 6.07E+06 O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI l.--------t----------tt ( ( (
+ + + +
(
+
(
+ t
( (
+
Co 60 ( 1.05E+08 ( 1.96E+08 ( O.OOE-DI 3.54E+07 (,O.OOE-OI ( O.OOE-DI O.OOE-OI I O.OOE-01.
+ + --+-
(
--+ I Zn 65 2.87E+08 8.11E+07 1.73E+08 4.62E+08 2.91E+08 Q.OOE-OI O.OOE-OI I O.OOE-OI t(
t--- (
- ---t-(
- -- +
(
---- - +---
(
- -- (
+
I
+ +-- I
+
Sr 89 ( 4.63E+06 ( 6 '8E+06 ( 1.62E+08 ( O.OOE-OI ( O.OOE-OI ( O.OOE-DI O.OOE-OI O.OOE-OI 1 1 1 Sr 90 1.37E+09 7.26Et07 5.39E+09 O.OOE-01 O.OOE-01 O.OOE-OI O.OOE-OI O.OOE-01 t (
---+--
( ( (
-+
(
- -----+( ( (
+ +
Zr 95 ( 1.88E+05 ( 2.20E+08 ( 9.59E+05 (
- 2. IIEt05 (
3.02E+05 ( O.OOE-01 ( O.OOE-OI ( O.OOE-OI
+ + + + + + + + +
Sbl24 ( 3.63Et06 ( 6.47E+07 1.04E+07 ( 1.34Et05 O.OOE-OI 2.28E+04 5.74E+06 O.OOE-01
+ +
(
+ +
(
+ t
(
+
( (
+
(
+
I 131 ( 2:48E+06 ( 3.88E+05 4.34Et06 ( 4.36E+06 7.16E+06 1.44Et09 O.OOE-OI I O.OOE-01
+
(
+ -+- (
+ --+---
( tI + I
+
I 133 7.05E-02 7.50E-02 1.51E-OI 1.86E-OI 3. IOE-01 3.46E+01 O.OOE-OI O.OOE-01 ( t ( ( ( (
---------t----------t l.
( (
+ +
Cs134 ( 1.59Et08 ( 4.07E+06 ( 4.60E+08 ( 7.55Et08 ( 2.34E+08 ( O.OOE-01 8.40E+07 O.OOE-Ol (
+ + +
Cs137 9.77E+07 4.14Et06 6.91E+08 6.62Et08 i 2.16E+08 0.00E-OI 7.76E+07 O.OOE-OI
+
( (
+ t
( ( (
+ +
( ( BaI40 ( 6.76Et05 ( 5.87Et06 ( 1.16E+07 ( 1.01Et04 ( 3.30Et03 ( O.OOE-DI 6.05E+03 O.OOE-DI
- l. ------t----------t
( (
+ + + + + + + +
Ce141 4.93Et02 4.14E+06 6.66Et03 3.32E+03 1.46Et03 O.OOE-OI O.OOE-OI I O.OOE-01 t ( (
+
( (
+
(
+ ) I Ce144 5.80Et04 8.88Et07 1.09E+06 3.41E+05 1.89E+05 O.OOE-Ol O.OOE-01 O.OOE-OI
(
+
(
+
(
+ t-(
---- (
+
( (
+- - -- (
+ - ------+
(a) R values are in units of mrem/yr per HCi/m3 for tritium, and in units of m -mrem/yr per ItCi/sec for all others. (b) 4.72E+02 = 4.72 X 102
y t ~ ' I t il 4 4
TABLE 4-8 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PATIQAY = COM HILK AGE GROUP = ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
-----+-- + + -+ + +
H 3 1.54E+03 f 1.54E+03 O.OOE-01 1.54E+03 i 1.54E+03 1.54E+03 1.54E+03 1.54E+03
---t(
+
i
-t-i
+
i
+
J
--+f +
i Hn 54 J 7.60Et05 ) 1.22E%7 J O.OOE-OI 3.98E+06 f 1.18E+06 O.OOE-OI / O.OOE-01 O.OOE-OI J f Cr 51 8.26E+03 2.08E+06 O.OOE-01 O.OOE-OI / 1.82E+03 4.94E+03
-- -----+) 1.
/ i 10E+04 i O.OOE-OI
+
(
+ --+ - ------+ J
+
i
+- ---- ---+-- +
Fe 59 8.7IEi06 7.57E+07 9.67E+06 2.27E~07 O.OOE-01 6.35E+06 (
+
J
+
( ( J i O.OOE-01 ) ) O.OOE-OI
+ + + + + + +
Co 58 i 3.90E+06 / 3.53E+07 i O.OOE-OI / 1.74E+06 O.OOE-OI I O.OOE-01 O.OOE-OI O.OOE-OI I
+ + + + t J I
+
I
+ --------+
Co 60 1.85E+07 1.58E+08 0.00E-01 8.39E+06 0.00E-01 i i
-+-------- -+---------q+
i i O.OOE-OI i O.OOE-01 i O.OOE-Ol
+
( J
+------- +- +---- - +
)
Zn 65 9. 11E+08 1.27E+09 6.33E+08 2.02E+09 1.35E+09 j O.OOE"01 J O.OOE-OI i O.OOE-OI
-+[ ] ] ] [
Sr 89 Sr 90
+
i
/
1.40E+07 5.95E 09 i
+
/
7.84E+07 7.01E+08
+
J
+
2.43E+10
+
---------+-0.00E-01 4.89E+08 J
+
i 0.00E-01 O.OOE-OI / O.OOE-01 l.
+- -
O.OOE-01 O.OOE-OI
--+---
/ O.OOE-01 O.OOE-01
+
/ O.OOE-01 O.OOE-OI
+
/
+---- ---+- /
+
/
+ +
)
+
f
+
/
--------+
Zr 95 f 7.37E+01 3.45E+05 3.39E+02 1.09E+02 1.71E+02 O.OOE-OI O.OOE-01 O.OOE-01
+
)
+
[
+
)
+
)
+ +-- -------+-- -
I I i
+- - - +
Sb124 3.61E+06 2.59E+08 9.11E+06 1.72E+05 0.00E-01 2.21E+04 7.09E+06 O.OOE.-OI
+
i i
+ ---t-i ----- )
-+- i
+
i
+ -+-
J
--+-------
i
--{.
I 131 6.36E+07 i 2.93E+07 i 7.76E+07 ) 1.11E+08 i 1.90E+08 3.64E+10 ( O.OOE-01 i O.OOE-01
-+-----
i
+ + + + + +
I 133 5.39E+05 1.59E+06 1.02E+06 1.77E406 3.08E406 2.60E+08 i 0.00E-01 O.OOE-DI
-+------
f f
+- )
+
[
---+- f J
+ + +
I
+
I Cs134 i 5.49E+09 i 1.18E+08 i 2.82E+09 i 6.72E+09 i 2.17E<09 ] O.OOE-OI 7.2IE~OB f O.OOE-01
+ + + + + +
[
-+-- +------- +
Cs137 3.43E+09 1.01E+08 3.83Et09 i 5.23E+09 i 1.78Et09 i O.OOE-OI 5.91E+08
+
i J i
---+- J i O.OOE-OI
+ + + + + + +
Ba140 f 4.65E+05 f 1.46E+07 7.10E+06 ) 8.92E+03 f 3.03E+03 O.OOE-01 5.11E+03 O.OOE-01 J J f )
+ + + + + + + + +
Ce141 f 6.68E+02 f 2.25E+07 J 8.71E+03 ) 5.89E+03 f 2.74E+03 i O.OOE-OI O.OOE-01 f O.OOE-OI J
+ + + + + + + +
144 5 41E 04 3 40E+08 DIE+06 21E+0 I 2.50E+05 I O.OOE-01 I O.OOE-01 I O.OOE-OI C [ J ) 1 ~ f 4 I
+ + + + + + + +
(a) R values are in units of mrem/yr per PCi/m3 for tritium, and in units of m2-mrem/yr per ~Ci/sec for all others. (b) 1.54E+03 = 1.54 X 103.
~ ' TABLE 4-9 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PAIIQAY
- CIM HILK AGE GROUP = TEEN T. BODY
-----+-----TCP-GI -TRACT NUCLIDE BOtlE
+
LI VER
+
KIDNEY
+
TIIYROID
+
LUttG
+
SKltt
+
H 3 ) 2.DOE+03 ) 2 AB ODE+03 O.OOE-01 2.DOE+03 2 ~ OOE+03 2.DOE+03 2.DOE+03 2.DOE+03
+
)
-----+ ) ) ) ) )
+- - -- +)
Hn 54 1.32E+06 1.36E+07 O.OOE-OI 6.63E406 1.98E+06 O.OOE-Ol O.OOE-01 O.OOE-OI t) ) )
+ +
) )
---------t----------F-
) ) )
--------4 Cr 51 1.44E+04 2.42E+06 O.OOE-01 O.OOE-DI 3. 16E+03 8.DIE+03 2.06E+04 O.OOE-01
)
t) )
+
)
+ +
)
+
)
t) )
+
)
+
Fe 59 ) 1.52E+07 ) 9.31E+07 ) 1.69E+07 3.94E407 O.OOE-01 O.OOE-01 1.24E+07 O.OOE-OI
) ) ) ) )
+ + + + + + +
Co 58 ) 6.75E+06 ) 4.04E~07 ) O.OOE-01 2.93E+06 O.OOE-01 O.OOE-OI O.OOE-01 O.OOE-OI
+ + +
)
+ ---+) )
+ - ------+-
)
-----4----------4
) )
Co 60 3.20E+07 1-.85E+08 O.OOE-01 1.42E~07 O.OOE-OI O.OOE-01 O.OOE-01 O.OOE-01 t
) ) ) ) ) ) ) ) )
Zo 65 1.58E+09 1.43E<09 9.73E+08 3.38E+09 2.16E+09 O.OOE-DI O.OOE-OI O.OOE-01
--+) ---- -- +---- ---
) )
+
)
+
) )
+ t)
----+)
-----+
Sr 89 2.58E+07
-----+) ----- -+- 1.07E+08
) )
9.01E+08 ) O.OOE-01 ) O.OOE-01 ) O.OOE-01 ) O.OOE-01 ) O.OOE-01 Sr 90 8.46E+09 9.62E+08 3.43E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-OI
)
+
)
+
)
+ -+) +
)
-- )
+ +
) )
+
Zr 95 ) 1.29E+02 ) 4.32E+05 ) 5.93E+02 ) 1.87E+02 ) 2,75E+02 O.OOE-01 ) 0 OOE-01
~ O.OOE-01 t ---+ -- - +- --------+ --- +)
)
+ + + --+
Sbl24
--f 6.34E+06
) ) 3.27E+08
-- - ---t-- - )
4 1.62E+07
-- ---4) 2.99E+05 ) 0.00E-01
-- - -- ) 3.68E+04 ) 1.42E+07 )
0.00E-OI I 131 ). 1.06E+08 3.90E+07 ) 1.41E+08 ) 1.97E+08 ) 3.39E+08 5.75E+10 0.00E-01 I 0.00E-DI
+ ---------+- - -+ ---- - +----------+)
)
+- )
t + I 133 9.60E+05 ) 2.38E<06 1.86E+06 ) 3.15E+06 5.52E+06 ) 4.40E+08 ) O.OOE-01 ) O.OOE-01
)
-+- -+ ---------+- )
+--- +-- ------+
)
----+- +---- -+
Cs134 5.35E+09 ) 1.43E~OB ) 4 90E+09 ) 1.15E+10
~ 3.66E+09 O.OOE-DI 1.40E+09 O.OOE-01
-------+ ---- -+------ -+
)
+- -- -- -+--- --- --+
) ) )
+---- ---- +)
)
Cs137 3.22Et09 1.3IE~OB 6.94E+09 9.23E+09 3. 14E+09 O.OOE-01 1.22E+09 O.OOE-01
) )
+ --- - )
+- )
+ +
) )
+
)
+ --+) --- -+)
Be140 8.26E+05 1.98E+07 1.28E+07 1.57E+04 5,33E+03 O.OOE-01 1.06E+04 O.OOE-01 t
)
+
) )
+
)
+ +---
)
- - -+-) )
+
)
+ +
Ce141 ) 1.23E+03 ) 3.05E+07-) 1.60E+04 ) 1.07E+04 ) 5.02E+03 ) O.OOE-OI O.OOE-DI ) O.OOE-01 )
+- )
Ce144 9.96E+04 4.66E+08 ) 1.85E+06 7.67E+05 4.58E+05 O.OOE-OI O.OOE-01 O.OOE-01
-----i----------+----------+----------+----------+----------+----------4-------
) ) ) ) ) )
--+----------+
) )
(a) R values are in units of mrem/yr per It Ci/m3 for tritium, and in units of m2-mrem/yr per It Ci/sec for all others. (b) 2.00E+03 = 2.00 X 10
0 TABLE 4-10 R VALUES POR THE PALO VERDE NUCLEAR GENERATING STATION(a) PATIMAY ~ COM HILK AGE GROUP -" CHILD ltUCLIDE T. BODY GI-TRACT BOttE LIVER KIDttEY THYROID LUNG SKItt
+ )gal- -- -+ + + ---------+------ --+- ---- --+-- --- +
3 3.17E+09 f 3.17E<03 i O.OOE-OI i 3.17E+03 i 3.17E+03 i 3.17EK3 i 3.17E+03 ( 3.17E+03 i H (
--------t------ +--- + + +
Hn 54
/
2.64E+06 / 8.33E+06 / O.OOE-OI 9.92E+06 2.78E+06 O.OOE-01 O.OOE-OI / O.OOE-OI
-+- +
)
+- +
/ )
+ +
/
+ +
. Cr 51 ) 2.94E+04 1.56E+06 O.OOE-OI O.OOE-OI 4.46E+03 1.63E+04 2.98E+04 O.OOE-OI J / /
+ + +
J
+ +
J
+ +
( (
+-- --- - (
+
Fe 59 / 3.15E<07 / 6.59E+07 j 3.91E+07 6.33E+07 O.OOE-OI O.OOE-01 1.84E+07 O.OOE-OI /
+-- + +
)
+ +
/
----+/ +
/ /
+ +
Co 58 i 1.37E+07 2.61E+07 / O.OOE-OI / 4.48E+06 O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI J ) / J / Co 60 6.51E+07 1.22E+08 O.OOE-OI 2.21E+07 O.OOE-OI O.OOE-01 i i i O.OOE-01 O.OOE-01
+
J
-+- J i
----+-- -----
J
+- --+------
)
-+
Zn 65 / 3. 16E+09 ( 8.93E+08 ( 1.9IE~09 / 5.0BE+09 / 3.20E+09 O.OOE-OI O.OOE-OI O.OOE-OI f
/ ( /
+ + + + + + + + +
Sr 89 6.37E+07-J 8.63E+07 2.23E+09 / O.OOE-01 / O.OOE-01 O.OOE-OI / O.OOE-DI / O.OOE-OI f
+
[
+ --+--
J
--- + -- -- +------ -+----------+
J Sr 90 / 1.47E+10 7.80E+08 / 5.79E+10 / O.OOE-Ol / O.OOE-OI O.OOE-OI O.OOE-OI O.OOE-OI
+
J
+ + --+-- +
/
+ -------+-
/ /
+
)
+
Zr 95 [ 2.70E+02 3.16E+05 1.38E+03 3.03E+02 4.34E+02 O.OOE-01 O.OOE-Ol 0.00E-01
+---- ---+--- -
)
--+] -- )
+-- +------
) f
---+-- ---- --+f J
+
]
+
Sb124 1'35E+07 2'40E+08 I 3'84E+07 f 4'99E+05 / 0'OOE 01 / 8'48E+04 2 13E+07 0'OOE 01
+
J )
+ -+-- [
-+- --+--------
/
+
I 131 [ 1.95E+08 f 3.06E~07 / 3.42E+08 / 3.44E+08 / 5.64E+08 1. 14E+11 O.OOE-01 O.OOE-OI
+ f / / J
+ + + + + + +
I 133 i 2.11E+06 i 2.25E+06 i 4.51E+06 5.58E<06 i 9.29E+06 1.04E+09 O.OOE-OI O.OOE-OI
+ + +
i
+ + --- i
+----------+- i i
--------+----------4 Cs134 3.91E+09 I.DOE+08 i 1. 13E+10 i 1.85E+10 i 5.75E+09 J /
--+ ---- ---+- i O.OOE-OI i 2.06E+09 i 0.00E-01
+ + + + + + ---+
Cs137 2.36E+09 1.DOE+08 / 1.67E+10 / 1.60E+10 i / i 5.21E+09 i O.OOE-01 i 1.88E+09 O.OOE-01
+ + + + + + -+-- -
( )
+
Be140 1.81E+06 [ 1.57E+07 3.09E+07 2.71E+04 8.82E+03 O.OOE-OI 1.62E+04 0.00E-01
---+ ---------+
(
-+-- ---
J /
+
) /
+- ---- --+-
/ )
+ -------+
Ce141 2.91E+03 2.45E+07 3.93E+04 1.96E+04 8.60E+03 O.OOE-OI 0:OOE-01 J
+
/
+ +
/ / ) / / / O.OOE-OI )
+ + + +
Ce144 2.44E+05 3.73E+08 4.57E+06 1.43E+06 7.93E+05 f f ( f / / O.OOE-OI / O.OOE-01 ) O.OOE-DI /
+ + + + + + + + +
(a) R values are in units of mrem/yr per It Ci/m for tritium, and in units of m -mrem/yr per It Ci/sec for all others. (b) 3.17EK3 = 3.17 X 10
TABLE 4-11 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION~a) PATIMAY = COW HILK AGE GROUP - INFANT NUCLIDE T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
- -------+--------wgt- + + + + + +
H 3 4.80E+09 4.80E403 O.ODE-DI 4.80E<03 4.80E+03 4.80E+03 4.80E+03 4.80E+03
+
) S
+ +
) )
+
)
+
)
+- ------ -+ ) )
+ +
)
Yn 54 4.18E+06 6.78E+06 O.OOE-01 1.85E+07 4.09E+06 i O.OOE-OI O.OOE-OI O.OOE-OI
-+----------+----------4----------4--------- ) ) ) ) )
-------4----------+- ) )
+ f Cr 51 4 ~ 66E+04 1.36E+06 O.OOE-OI O.OOE-OI 6.64E+03 3.04E+04 5.92E404 O.OOE-OI
)
+ t
)
+
) )
+
)
+ +
)
+
) )
+ $
Fe 59 ) 5.03E<07 ) 6.09E+07 ) 7.30E+D7 ) 1.28E+08 ) O.OOE-01 ) O.OOE-OI ) 3.77E+07 ) O.OOE-OI
+ + + + + + - + + +
Co 58 ) 2.23E+07 ) 2.23E+07 ) O.OOE-DI ) 8.96E 06 ) 0.00E-01 ) 0.00E-01 ) 0.00E-01 O.OOE-01
+ $ j Co 60 1.06E+08 1.07E+08 O.OOE-01 4.51E+07 O.OOE-OI O.OOE-Q1 O.OOE-Q1 O.OOE-01 f $ f ) ) ) ) )
-+)
Zo 65 ) 4.05E+09 ) 7.42E+09 ) 2.56E+09 ) 8.79E<09 ) 4.26E+09 ) O.OOE-01 ) O.OOE-Ol ) O.OOE-OI
+ + + + + + + + +
5r 89 ) I 22E+08 ) 8 71E+07 ) 4 24E~09 ) 0 OOE Ol ) 0 OOE 01 ) 0 OOE Ol ) 0 OOE 01 I O'OOE Ol
+ + + + + + +
Sr 90 1.60E+10 7.87E+08 6.30E+10 O.OOE-01 0.00E-Ol D.OOE-Ol D.OOE-D1 0.00E-01
-+--- - ---+ --- --
) )
+
)
--- - -- +--- ---
) )
-+ - -- +
)
-- --+---
) )
--+ )
+
Zr 95 4.23E+02 2.97E+05 2.45E+03 5.97E+02 ) 6.43E+02 O.OOE-01 O.OOE-01 ) O.ODE-01 )
) ) ) ) ) )
-+-- + + -+ + + +
Sbl24 2.30E+07 2.29E+D8 7.41Ei07 1.09E406 O.ODE-01 1.97E+05 4.64E+07 O.OOE-01
) )
+--- -- +
) )
+
)
+ j) -+) )
+ +
I 131 ) 3.69EK8 ) 3.DDE+07 ) 7.13E+08 ) 8.40E+08 ) 9.81E+08 ) 2.76E+11 ) 0.00E-OI ) 0.00E-DI
+ + + + + + + +
I 133 4.06Et06 2.35E+06 9.52E+06 1.39E>07 1.63E<07 2.52E+09 O.OOE-OI O.OOE-DI
) )
-+ +
)
+
) )
--+~- - --- +
)
-+)
---- -+---- - --+
)
Csl34 3.43E+09 9.23E+07 1.82E+10 3.40E+10 8.74E+09 O.OOE-OI 3.58E+09 O.OOE-01
) +
) ) ) )
) J j )
Cs137 ) 2.21E+09 ) 9.76E+07 ) 2.67E+10 ) 3.12E+10 ) 8.38E+09 ) O.OOE-OI ) 3.39E+09 ) 0.00E-DI )
+ + + + + + +
Ba140 3.28E+06 1.56E+07 6.37Et07 6.37E<04 1.51E+04 D.OOE-DI 3.91E+04 0.00E-DI ).
)
+
)
+
)
+
)
+
)
+
)
+
)
+----- ---+
)
Cel41 5.60E+03 2 '6E+07 7.80E+04 4.76E+04 1.47Ei04 O.OOE-OI O.OOE-OI O.OOE-OI
+
)
-- - -+--)
-- -+) +
)
+
)
t ) t) )
--+)
Ce144 3.67E+05 3.76E+08 6.54E+06 2.68E+06 I.OBE+06 O.OOE-OI O.OOE-01 O.OOE-01 t) +
)
t)
+
) )
+
)
+
)
+
)
+
)
(a) R values are in units of mrem/yr per P Ci/m3 for tritium, and in units of m -mrem/yr per p Ci/sec for all others. (b) 4.80E&3 = 4.80 X 10 .
0 0'
TABLE 4-12 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PATIIMAY I ItlHAL AGE GROUP = ADULT HUCLIDE T. BODY GI-TRACT LIVER KIDllEY SKIH
---------t--------rtt----------t- BOflE + + +
THYROID
--+
LUNG
+----------+
H 3 ) 1.26Et00 I 1.26E+03 ) O.OOE-OI ) 1.26E+03 ) 1.26Et03 ) 1.26Et03 ) 1.26E+03 ) 1.26E+03 )
+ + + + + + + + +
Hn 54 6.29E+03 7.72E+04 O.OOE-DI 3.95E+04 9.83Et03 O.OOE-01 1.40E+06 O.OOE-01
)
+
)
+
)
+
)
+
)
+
)
+
)
+ t
) )
+
Cr 51 9.99E+01 3.32E+03 O.OOE-01 O.OOE-01 2.28E+01 5.94Et01 1.44Et04 O.OOE-01
)
+
)
+
)
+
)
+ -+) )
+
)
+ t
)
+
Fe 59 I.OSEt04 I.BBEt05 1.17E+04 2.77E+04 O.OOE-OI O.OOE-OI 1.DIE+06 O.OOE-OI t) ) t )
+
)
+
)
+ t
) )
+
)
+
)
+
Co 58
)
2.07Et03 ) 1.06E+05 ) O.OOE-OI ) 1.58E+03 ) O.OOE-OI ) O.OOE-OI ) 9.27E+05 ) O.OOE-OI )
+ + + + + + + +
Co 60 1.48Et04 2.84E+05 O.OOE-OI 1.15E+04 O.OOE-01 O.OOE-Ol 5.96Et06 O.OOE-OI
)
t
) )
+
)
+
)
+
)
+ -------t---
) )
+ +
Zn 65 ) 4.65Et04 ) 5 ~ 34E+04 ) 3.24E+04 ) 1.03E+05 ) 6.89E+04 ) 0.00E-01 I 8.63E+05 I 0.00E-OI I
+ + + + + + + + +
Sr 89 ) 8.71E+03 ) 3.49E+05 ) 3.04Et05 ) O.OOE-01 O.OOE-OI O.OOE-OI 1.40E+06 ) O.OOE-OI
)
+ )
Sr 90 ) 6.09E+06 ) 7.21E+05 ) 9.91E+07 ) O.OOE-01 ) O.OOE-OI ) O.OOE-OI ) 9.59E+06 ) 0.00E-DI
+ + + + + + + + +
Zr 95 2.32E+04 1.50E+05 1.07E+05 3.44E+04 5.41E+04 O.OOE-OI 1.77E+06 O.OOE-01
)
+
)
+
)
+
)
+
)
+
)
+ +
)
--------+-
)
+
Sb124 ) 1.24Et04 ) 4.06E+05 )
- 3. 12Et04 )
5.88E+02 ) O.OOE-OI ) 7.54E+01 ) 2.48E+06 ) O.OOE-OI
+ + + + + + + +
I 131 2.05E+04 6.27E+03 2.52E+04 3.57E+04 6.12E+04 1.19E+07 O.OOE-OI O.OOE-Ol
)
+
)
+
)
+
)
+ t
) )
+ +
) )
+
I 133 ) 4.51E+03 ) 8.87E+03 ) 8.63E+03 ) 1.48E+04 ) 2.58E+04 ) 2.15E+06 ) O.OOE-OI ) O.OOE-OI
+ + + + . + + + +
Cs134 ) 7.27E+05 ) 1.04E+04 ) 3.72E+05 ) 8.47E+DS ) 2.87E+05 ) O.OOE-OI ) 9.75E+04 ) 0.00E-OI )
+ + + + + + + + +
CsI37 4.27E+05 8.39Et03 4.78E+05 6.20E+05 2 22E 05 0 OOE 01 ) 7 ~ 51E 04 0 OOE Ol
--+--------+--------
) )
+) -- w- )
--- --+----------e---
) )
- --t--- ---t----------+I
)
Ba140 ) 2.56E+03 ) 2.18E+05 ) 3.90E+04 ) 4.90E+01 ) 1.67E+01 ) O.OOE-OI ) 1.27E+06 ) O.OOE-OI
+ + + + + + + + +
Ce141 ) 1.53E+03 ) 1.20E+05 ) 1.99E+04 ) 1.35E+04 ) 6.25E+03 ) O.OOE-OI ) 3.61E+05 ) O.OOE-01
+ + + + + + + +
Ce144 ) 1.84E+05 ) 8.15E+05 ) 3.43E+06 ) 1.43E+06 ) 8.47Et05 ) O.OOE-OI 7.76Et06 ) O.OOE-OI )
+ + + + + -+- +
)
+ +
(a) R values are in units of mrem/yr per Il Ci/m3. (b) 1.26E+03 1.26 X 10
TABLE 4-13 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PATIMAY ~ IHHAL AGE GROUP R TEEM HUCLIDf T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIH
---------t--------rent----------t- ---------+- + + +
H 3 i 1.27ft05 $ 1.27E+03 i O.OOE-OI i 1.27E+03 i 1.27E+03 1.27E+03 i 1.27E+03 i 1.27E+03
--+- + ---+- +
i
-+ ------ + -- i
+
Mn 54 8.39E+03 / 6.67ft04 / O.OOE-01 / 5. IOE+04 1.27E+04 O.OOE-DI 1.98E+06 O.OOE-OI J
--+/ -+--
/ ( /
+ +
Cr 51 1.35E+02 3.00Et03 O.OOE-01 O.OOE-01 3.07E+01 7.49E+01 2.09E+04 O.OOE-OI
/ /
+ + +
/ /
+ +
/
--t---
/ /
---+- ---+----------+/
/
Fe 59 ) 1.43E+04 / 1.78E+05 / 1.59E+04 3.69E+04 O.OOE-01 O.OOE-OI 1.53E+06 O.OOE-OI /
/ / / / /
+ + + + + T T T Co 58 (
2.77Et03 9.51E+04 O.OOE-OI 2.07E+03 0 ~ OOE 01 0 ~ OOE Ol / 1 34E 06 0 ~ OOE Ol I
+ +
J t) t
/ I
+
/
+ +
~
/
+ +
Co 60 1.98E+04 2.59E+05 O.OOE-01 1.51E+04 i O.OOE-Ol i O.OOE-OI 8.71E+06 i i ti i
------ / i O.OOE-01 i
+ + + + +- + +
Zn 65 6.23E+04 4.66E+04 3.85E+04 1.33E+05 8.63E+04 0.00E-OI 1.24E+06 0.00E-DI tf
---+ ----
J /
+- / / f
+
/
+
/
+
)
+
Sr 89 1.25E+04 3.71E+05 4.34E+05 0.00E-DI O.OOE-DI 0.00E-01 2.41E+06 0.00E-OI
--+f /
+
f
-------+/ - -------t----------t----------+-
/ / f
+---------
/
t Sr 90 ) 6.67E+06 / 7.64E+05 / 1.08E+08 / 0.00E-OI 0.00E-01 / 0.00E-01 1.65E+07 O.OOE-DI [
/ / [
+ + + + + + + +
Zr 95 3.15E+04 1,49E+05 1.45E+05 4.58E+04 6.73E+04 0.00f-01 2.68E+06 O.OOE-01 t f t f
+
J f
+ +
]
t f t f t f
+
Sbl24 1.68E+04 3.98Et05 i 4.30E+04 i 7.92E+02 i O.OOE-01 9.75E+01 i 3'.84E+06 i 0.00E-OI
+
i )
+ + + + t
(
+ +- - -----t I 131 2.64f+04 6.48E+03 3.54E+04 4.90E+04 8.39f+04 1.46E+07 0.00E-OI 0.00E-OI
/
---+---
/
----+) )
+
/ (
+ - /
+
[
+
f
+
I 133 6.21E+03 1.03E+04 21E+04 / 2.05E+04 3.59E+04 2.92E+06 0.00E-DI
--------t-D.OOE-DI 1 ~
t/ f
+
/
+ + ----+/ - )
+- f )
+ +
Cs134 5.48E+05 9.75E+03 5.02E+05 1.13E+06 3.75E+05 O.OOE-DI i 1.46E+05
+
i )
----+ i i i i i O.OOE-01
+ + + + + + +
CsI37 ] 3.11E+05 f 8.47E+03 6.6'9E+05 ] 8.47E+05 3.04E+05 O.OOE-OI [ 1.21E+05 O.OOE-OI )
+ + +
J
+
[
-+---- +----------+-
) J
+ +
Ba140 3.51E+03 / 2.28Et05 5.46Et04 6.69E+01 2.28E+01 0.00E-DI 2.03E+06 0.00E-01 ].
----+) - ---+-- --+-----
) f
+ +
J /
+
[
+
J
+ - +
Ce141 2.16E+03 1.26Et05 2 ~ 84E+04 1.89E+04 8.87E+03 0.00E-01 6.13E+05 0.00E-OI f f
+ +
)
t
]
-- ---t----------t- - ----+-
) / J )
+ - )
+
Ce144 ( 2.62E+05 f 8.63E+05 / 4.88E+06 f 2.02E+06 1.21E+06 0.00E-01 1.33E+07 0.00E-01
+ / / J ( )
+ + + + + + + +
(a) R values are in units of mrem/yr per p Ci/m3. (b) 1.27EK3 = 1.27 X 10
TABLE 4-14 R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(<) PATlfAAY "- IHIIAL AGE GROUP = CHILD HUCLIDE T. BODY GI-TRACT BOHE LIVER KIDHEY THYROID LUHG SKIH
+ + + + + +
H 3 ) 1.12E<03 1.12E+03 f O.OOE-OI f 1.12E+03 1.12E+03 1.12E+03 f 1.12E+03 1.12E+03 J ( J ] f
+ + + + + + + + +
!4l 54 /
9.SUE+03 f 2.29E+04 / O.OOE-01 / 4.29E404 / 1.DOE+04 f O.OOE-OI / 1.57E+06 j O.OOE-OI
+ + +
Cr 51 / 1.54E+02 / I.OBE+03 J 0.00E-DI J 0.00E-OI J 2.43E+01 / 8.53E+01 / 1.70E+04 J 0.00E-DI
+ + + + + + + +
Fe 59 1.67E+04 7.06E+04 2.07E+04 3.34E+04 0.00E-OI 0.00E-01 1.27E+06 0.00E-OI
/
+ --------+-
)
------+- -
[
+------ ---+-----
) / /
+- --- -- -+-
/ /
+
/
Co 58 f 3.16E+03 i 3.43E+04 J 0.00E-01 J 1.77E+03 J
.O.OOE-OI i O.OOE-DI i 1.10E+06 i 0.00E-OI i Co 60 2.26E+04 9.61E+04 O.OOE-01 1.31E+04 [.O.OOE-OI O.OOE-OI 7.06E+06 O.OOE-DI t
I )
+
/
+
/
+ +
/
+ +
/ /
+
Zn 65 / 7.02E+04 ] 1.63E<04 / 4.25E<04 J 1.13E+05 [ 7.13E+04 / O.OOE-01 / 9.94E+05 / O.OOE-01 /
+ + + + + + +
Sr 89 t 1.72E+04 1.67E+05 f 5.99E+05 O.OOE-OI 0 OOE-01 / O.OOE-Ol
~ 2.15E+06 O.OOE-OI
+
)
+ +
f
+
f
+ +
) J
+ -+]
Sr 90 / 6.43E+06 / 3.43E+05 J I.DIE<08 J O.OOE-01 J O.OOE-OI / O.OOE-OI / 1.47E+07 / O.OOE-OI
+ + + + + + + + +
Zr 95 3.69E+04 / 6.10E+04 j 1.90E+05 / 4.17E+04 / 5.95E+04 O.OOE-OI 2.23E+06 / O.OOE-Ol l.
) / )
+ + + + + + + +
SbI24 2.DOE+04 1.64E+05 / 5.73E+04 / 7.39E<02 / 0.00E-OI ] 1.26E+02 / 3.24E+06 0.00E-01
) J
+
I 131 2.72E+04 2.84E+03 4.80E+04 4.80E+04 7.87E+04 1.62E+07 0.00E-DI D.OOE-OI
)
+
f
+
)
+ +----
) )
+ --+-----
)
-----+-
f
- - --+--- ------+
J I 133 i 7.68E+03 5.47E+03 1.66E+04 2.03E+04 3.37E+04 3.84E+06 0.00E-OI D.OOE-01
+
i
+
i
+ t J )
+
)
+
i
+
J
+ +
Cs134 i 2.24E+05 i 3.84E+03 i 6.50E+05 I.DIE~06 3.30E+05 i O.OOE-OI 1.21E+05 i O.OOE-OI
+ + t )
+
)
+ + +
i
+ +
J Cs137 1.28E+05 3.61E%3 9.05E+05 i 8.24E+05 i 2.82E+05 0.00E-01 1.04E+05 0.00E-OI t
) i
+
i
+ + +
i
+ +
J i
+ +
Bal40 4.32E+03 1.02E+05 7.39E+04 6.47E+01 2.11E+01 / O.OOE-OI / 1.74E+06 O.OOE-OI
---+-- -- ----+----
f / /
-+---- f
+ - - t-
/
+ +
/
+
f
+
Ce141 2.89E+03 5.65E+04 3.92E+04 1.95E+04 8.53E+03 O.OOE-OI / 5.43E+05 O.OOE-OI
) -----4----------+----------+--------- [ / f / f /
+
)
+
Cel44 J 3.61E%5 J 3.88Ei05 ] 6.76E+06-) 2.1IEt06 [ 1.17E+06 f O.OOE-OI J 1.19E+07 f O.OOE-DI ]
+ + + + + + + + +
(a) R values are in units of mrem/yr per P Ci/m . (b) 1.12E+03 = 1.12 X 10
0 I J 0
TABLE 4-15 - R VALUES FOR THE PALO VERDE NUCLEAR GENERATING STATION(a) PAIHWAY
- INttAL AGE GROUP = INFAttT NUCLIDE T.BODY GI-TRACT BONE LI VER KIDNEY THYROID LUNG SKIN
-+------ -gg -- <<---+----- + ---------+------ -- t----------+ -- --+ -------+
H 3 ) 6.46Et02 $ 6.46Et02 ( 0.00E-OI 6.46E+02 6.46E+02 6.46E+02 6.46E+02 6.46E+02
+ +
( )
+---
)
- - --+-)
------ +
(
- --- + )
Hn 54 4.98E+03 7.05Et03 O.OOE-01 2.53E+04 4.98E+03 O.OOE-OI 9.98E+05 O.OOE-OI t( ) (
+
(
+ +
)
+
) )
-+- )
+- - +
( Cr 51 ) 8.93E+01 ( 3.56gt02 ( O.OOE-OI ) O.OOE-OI ) 1.32E+01 ( 5.75E+01 1.28E+04 O.OOE-OI
-+)
(
+ + + + + + +
9.46E+03 2.47E+04 1.35E+04 2.35E+04 O.OOE-OI O.OOE-OI 1.01E+06 O.OOE-OI
+
) )
+ - )
+
(
+ +
)
+
)
- +
(
+
)
- +
Co 58 1.82E+03 1.11E+04 O.OOE-OI I 22E+03 0'OOE Ol 0 Ol 7'76E+05 0 01 t( (
-+)
+
I ( OOE
+----------+-
) )
OOE
-- +
Co 60 1.18Et04 3.19E+04 O.OOE-OI 8.DIE+03 O.OOE-OI O.OOE-OI 4.50E+06 I O.OOE-OI
)
+
)
-+- )
+ +
I I
+----
I I t + I Zn 65 3.10Et04 5.13Et04 1.93E+04 6.25E+04 3.24E+04 O.OOE-OI 6.46E+05 O.OOE-OI
)
+
(
+
)
+ +
)
--- -+---
) (
+
)
+ +
(
+
Sr 89 1.14E+04 6 ~ 39E+04 3.97E+05 O.OOE-01 O.OOE-OI O.OOE-OI 2.03E+06 O.OOE-Ol
--+( ---- ---+ (
----- (
+ +
) (
+
(
+
)
+ +
)
+
Sr 90 2.59E+06 1.31E+05 4.08E+07 O.OOE-OI O.OOE-01 O.OOE-01 1.12E+07 O.OOE-OI (
----+- --
( (
+ +
) )
+
( t----------t----------t ( ( ( Zr 95 ( 2.03E+04 (
- 2. 17Et04 1.15Et05 2.78E+04 3.10E+04 O.OOE-OI 1.75E+06 O.OOE-OI
( ( ) ) ( (
+ + + + + + -+
Sb124 1.20E+04 5.90E+04 3.79E+04 5.55E+02 O.OOE-01 1.DOE+02 2.64E+06 O.OOE-OI
) ------t----------t-
) (
+
( )
+
(
+
(
+ +
( )
+
I 131 1.96E+04 1.06E+03 3.79E+04 4.43E+04 5.17E+04 1.48E+07 O.OOE-OI O.OOE-OI
)
+ ---+( ---+) +
) )
+
) (
---+) ---- --+
I 133 5.59E+03 2. 15Et03 1.32E+04 1.92Et04 2.24E+04 3.55E+06 O.OOE-OI O.OOE-OI ( ( (
+
) (
---+----------+-
) )
+
)
+
Cs134 ) 7.44E+04 ( 1.33E+03 ) 3.96E+05 7.02E+05 1.90E+05 O.OOE-01 7.95E+04 O.OOE-OI
+ + +
( ( ( (
+--------- t(
)
C 137 4 '4E+04 1 ~ 33E+03 48E 05 I 6. IIE+05 1.72E+05 0.00E-OI ( 7 . 12E+04 0.00E-OI (
+ t
( I
+ +
(
+- (
-+- ----- -+--- -----+(
( Ba140 2.89E+03 3.83E+04 5.59Et04 5.59E+01 1.34E+01 O.OOE-OI 1.59E+06 O.OOE-01 t (
----+( (
--+- -+
( ( (
+
(
-+------ )
--+--------- )
Ce141 1.99E+03 2. 15E+04 2.77E+04 1.66E+04 5.24E+03 O.OOE-OI 5.16E+05 O.OOE-OI
)
+ t
( I
+ tI ( (
+
I
+
)
---------+(
Cel44 1.76E+05 1.48Et05 3. 19E+06 1.21E+06 5.37E+05 O.OOE-OI 9.83E+06 O.OOE-OI (
+--- ----- )
+ - (
-+- +
( (
+
)
+ t
(
+
)
+
( (a) R values are in units of mrem/yr per It Ci/m3. (b) 6.46E+02 = 6.46 X 102.
0 TABLE 4-16 (Sheet 1 of 3) PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR I,ONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 1 DIRECTION X /Q (Sec/m3) RESIDENCE(c) D/g (m >)
., X/Q (Sec/m3)
GARDEN(c) D/Q (m ~) X/Q (Sec/m3) MILK(c) D/Q (m ~) N 2.92Z6(b) 3.25E-09 2.92E6 3.25E&9 7.03E-07(a) 3.48E-1O(a) NNE 1.81E-06 2.88E&9 4.7OE-O7(a) 4. O4E-1O <<) 4.70E-O7(a) 4.04E-10<<) NE 1.95E<6 3.85E-09 1.76E&6 3.29E&9 5.77E-O7(a) 6.51z-lo(a) ENE 1.03E-06 1.08E9 1.03E&6 1.08E&9 3.86E-07(a~ 2.86E-10(a) E 9.39E7 6.68E-10 3. 71E-07<<) 1.87E-lO(a) 3.71E-07(a) 1.87E-10( ESE 6. 37E-07 2.84E-10 4.12E-07 1.60E-10 4.12E&7 1.60E-10 SE 8.83E7 2.61E-10 8.83E-07 2.61E-10 5.84E-O7<<) 1.52E-10( ) SSE 1.27E6 2.61E-10 1.09E6(a) 2.15E-10(a) 1. 09E-O6 <<) 2.15z-lo(a) S 2.58E6 4.85E-10 2.09E-06 3.59E-10 2.13E&6 3.71z-lo SSW 3.26E&6 8.26E-10 2.28E6(a) 4.53E-lO(a) 2.28E-06(a) 4.53E-1O(a) SW 2.80E<6 9.10E-10 1.58E-06(a) 3.56E-10(a) 1.58E-06(a) 3.56E-10(a) WSW 1.95E6 1.09E&9 8.55E-O7 a 3.18E-10 a 8.5SZ-O7 a W 7.54E-O7(a) 4.44E-1O(a) 7.54E&7 a 4.44E-10 a 7.54E&7 a 4.44Z-10 a WNW 6.03E7(a) 3.25E-10<<) 6.O3E-O7(a) 3.25E-lO(a) 6.O3E-O7(a) 3.25E-10(a) NW 8.24E-07 5.25E-10 7.55E&7 4.61z-lo 6.O2E-O7(a) 3.27E-10(a) NNW 1.46E&6 1.47z-09 5.20E&7<<) 3.04E-10(a) 5.20E-07(a) 3.O4E-1O(a) 5-mile value used since there is no pathway located within the sector up to five miles. 2.92E6 = 2.92 x 10 6 Locations of these residences, gardens and milch animals are given in Table A-l, sheet 1. Controlling locations are discussed in Appendix A.
References:
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
TABLE 4-16 (Sheet 2 of 3) PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2 RESIDENCE(c) GARDEN(c) MILK(c) DIRECTION x/Q D/g x/Q D/g x/Q D/Q (Sec/m3) (m ~) (Sec/m3) (m ~) (Sec/m3) (m ) N 2.73E-06(b) 2.92E-09 2.39E&6 2.35E&9 7.03E-07(a) 3.48E-lo <<) NNE 2.20E-06 3.87E-09 2.20E6 3.87E9 4.70E-07(a) 4.04E-10(a) NE 1.85E-06 3.55E-09 1.57E&6 2.78E-09 5.77E-07<<) 6.51E-10(a) ENE 1.03E-06 1.08E-09 1.03E6 l. 08E9 <<) 3.86E-07(a) 2.86E-10( E 8.80E-07
- 6. 25E7 6.06E-10 2.76E-10 3.71E-07(a) l. 87E-10 3. 71E&7 <<) 1.87E-lo(a)
ESE 3.96E-07 1.51E-10 3.96E-07 1.51E-10 SE 9.06E7 2.72E-10 9.06E7 2.72E-10 5.84E-07(a) 1.52E-10(a) SSE 1.34E&6 2.81E-10 1.09E6(a) 2.15E-10<<) 1.09E6(a) 2.15E-10(a) S 2. 63E6 5.01E-10 2.19E-06 3.88E-10 2.19E-06 3.88E-10 SSW 3.48E-06 9.19E-10 ,2.28E6( ) 4.53E-10(a) 2.28E&6( 4.53E-10(a) SW 2.93E6 9.75E-10 1.58E-06(a) 3.56E-10(a) 1.58E-06(a) 3.56E-10(a) WSW 2. 01E&6 1.16E-09 3.18E-10(a) 8.55E&7 a 3.18E-10 a W 7.54E-07(a) 4.44E-10<<) 7.54E7 a 4.44E-10<<> 7 54E 07 a 4.44E-10 a WNW 6.03E-07(a) 3.25E-10(a) 6. 03E7 (a) 3.25E-10(a) 6.03E&7(a) 3.25E-10<<) NW 7.84E-07 4.88E-10 7.84E&7 4.88E-10 6.02E&7(a) 3.27E-10(a) NNW 1.46E&6 1.47E&9 5.20E&7 3.04E-10 5.20E&7(a) 3.04E-10(a) 5~ile value used since there is no pathway located within the sector up to five miles. (b) 2.73E-06 = 2.73 x 10 6 O P$ MQ & ~ Locations of these residences, gardens and milch animals are given in Table A-l, sheet 2. CD = Controlling locations are discussed in Appendix A. CO Ln
References:
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
TABLE 4-16 (Sheet 3 of 3) PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PAKQKTERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 RESIDENCE(c) GARDEN(c) MILK(c) DIRECTION X/Q D/g X/Q D/g X/Q D/g (Sec/m3) (m 2) (Sec/m3) (m ) (Sec/m3) (m ~) N 2.58E6(b) 2.47E-09 2.42E-06 2.22E&9 7.03E7(a) 3.48E-10 <<) NNE 1.85E-06 2.97E-09 l. 85E&6 2.97E-09 4.?OE&7(a) 4.04E-10(a) NE 1. 66E6 3.00E-09 1.48E-06 2.54E&9 5.77E-07(a) 6. 51E-10 <<) ENE 8.75E-07 8.86E-10 8.75E&7 8.86E-10 3.86E-07(a) 2.86E-10(a) E 8.90E-07 6.17E-10 4.06E-07 2.15E-10 4.25E-07 2.31E-10 ESE 6.3?E-07 2.84E-10 5.80E-07 2.46E-10 3.73E&7(a) 1.37E-10 <<) SE 5.84E-07(a) 1.52E-10(a) 5.84E&7(a) 1.52E-10(a) 5.84E&7(a) 1.52E 10(a) SSE 1.36E&6 2.88E-10 1.09E&6(a) 2.15E-10(a) 1.09E-06(a) 2.15E-10( S 2.65E&6 5.25E-10 2. 25E&6 4.06E-10 2.31E-06 4.21E-10 SSW 3.64E6 9.82E-lo 2.28E&6(a) 4.53E-10(a) 2.28E&6(a) 4.53E-10(a) SW 3.19E6 1.11E-09 1.58E-06(a) 3.56E-10(a) 1.58E-06(a) 3.56E-10(a) WSW 2. 12E6 1.26E-09 8 55E-07 a 3.18E-10 a 8.55EW? a 3.18E-10 a W 7. 54E-07 <<) 4.44E 10(a) 7.54E&7 a 4.44E-10 a 7.54E-10 a 4.44E-10 a WNW 6.03E-07(a) 3.25E-10(a) 6.03E&7(a) 3.25E-10(a) 6.03E-07(a) 3.25E-10(a) NW 6.83E&7 4.05E-10 6.82E-07 4.05E-10 6.02E&7<<) 3.27E-lo(a) NNW 1.34E6 1.26E-09 5. 16E&7 3.01E-10 5.20E&7<<) 3.04E-10(a) 4 5-mile value used since there is no pathway located within the sector up to five miles. (b) 2.58E-06 2.58 x 10-6 Mg O m Locations of these residences, gardens and milch animals are given in Table A-l, sheet 3. h) O
~ Controlling locations are discussed in Appendix A.
CO Ln
References:
1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.
5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE 0 5.1 Technical 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 less than or equal to 75 mrems. Since all other uranium fuel cycle sources are greater than 20 miles away, only the PVNGS site need be considered. The total dose to any MEMBER OF THE PUBLIC will be determined based on a sum of the doses from all three units'eleases and doses from direct radiation from PVNGS. This dose evaluation is done annually and submitted with the 4 Semiannual Radioactive Effluent Release Report for July through December to assure compliance with 40CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. This dose evaluation will also be performed whenever calculated doses associated with effluent releases exceed twice the limits of any one of the Technical Specifications 3.11.2.2 or 3.11.2.3. 5.1.1 Doses from Releases The annual whole body dose accumulated by a MEMBER OF THE PUBLIC for the noble gases released in gaseous effluents is determined by using the following equation: I (3.17 x 10-8) Z i f(Ki) (X/Q)RU (Q 5-1 Rev. 1 09/20/85
1 i 1" t tl I tI
Where: Ki the whole body dose factor due .to gamma emissions for each identified noble gas radionuclide i, in mrem/yr peru Ci/m3 from Table 3-1. the integrated release of radionuclide i, inP Ci for the previous calendar year. ( ~~)RU the highept calculated annual average dispersion parameter, in sec/m 3 , for a particular unit, at the controlling location, from Table 4-16, or concurrent meteorological data if available.
~ -6 2.92x10 from Unit 1 2.19x10 from Unit 2
~ 2.31xl0 from Unit 3 WB the annual whole body dose in mrem to a MEMBER OF THE PUBLIC at the controlling location due to noble gases released in gaseous effluents.
The annual dose to any organ accumulated by a MEMBER OF THE PUBLIC for iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents is determined by using the following equation: Do (3.17 x 10-8) g i [ Z k(RikWk )(gi)J (4-3) Where: D 0 the total annual organ dose from gaseous effluents to a MEMBER OF THE PUBLIC, in mrem, at the controlling location. 5-2 Rev. 1 09/20/85
0 0
the integrated release of radionuclide i, in
'PCi, for the previous calendar year.
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 m 2 -mrem/yr per PCi/sec) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15. the highest annual average dispersion or deposition parameter for the particular unit, used for estimating the total annual organ dose to a MEMBER OF THE PUBLIC at the controlling location for the particular unit. ( X/Q)RU, in sec/m 3 for the inhalation pathway.and for all tritium calculations, for organ dose at the controlling location, from Table 4-16 or concurrent meteorological data if available. ~ 2.92xl0 from Unit 1 2.19x10 from Unit 2 ~ 2.31xl0 from Unit 3
-2 (D/Q)RU, in m, for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16 or concurrent meteorological data if available.
~ -9 3.25x10 from Unit 1 ~ 3.88xl0 -10 from Unit 2 ~ 4.21x10 -10 from Unit 3 Rev. 1 09/20/85
0 t, ~ ~ ji, 0
5.1.2 Dose Due to Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be evaluated by first determining the direct radiation dose at the site boundary in each sector, and then extrapolating the site boundary dose to the controlling location by the inverse square law of distance. 5.2 Dose to Public Onsite Technical S ecification 6.9.1.8 For the purpose of evaluating the dose to MEMBERS OF THE PUBLIC due to their activities within the SITE BOUNDARY the following methodology will be used. These activities have been determined to be limited to the vicinity of the Visitor Center located inside the SITE BOUNDARY west of Unit l. An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location. A X/Q, determined for the Visitor Center, will be used for this assessment. Equations 5-1 and 4-3 in Sections 5.1.1 and 5.1.2 should be used for this assessment. Qi should be the integrated release of. radionuclide i, in P Ci, for 8 hours (determined from the yearly Q ). 5-4 Rev. 1 09/20/85
6.0 OPERABILITY OF E UIPMENT The flow diagrams defining the treatment paths and the components of the liquid, gaseous, and solid radioactive waste systems are shown in Figures 6-1 through 6-3, respectively. 6-1 Rev. 1 09/20/85
LRS, TURB. BLDG. AUX. STEAM LRS RECY. ABSOR. BED SUMPS COND EN. MONITOR. TANK TANK H Pd o A CHEM. Ch CONT. LO V/. T DS AUX. BLDG. RADV/ASTE VIASTE Co H NEUT. RADVIASTE HOLDUP SUMPS BLDG. TANK SUMPS TANK SUMPS 0 0 FUEL BLDG. CHEM. SPENT EVAP. FLUSH SUMPS DRAIN RESIN VIATER TANKS TANKS CAUSTIC ACID BATCH TANK BATCH TANK lV ~ CO CO Ln HIGH TDS HOLDUP TANKS
LRS BAC HOLDUP COIIDEN. ION TANKS EXCHGR. LRS EVAP-ORATOR C H 0 0 LRS MIXED t7 BED ION A EXCHGR. C BORIC ACID LRS LRS ION CONCEN- CONC EN. EXCHANGER 0 P3 TRATOR thONITOR. C4 t7 (BAC) TANK PREFILTER I LRS RECY,. DECONTAMINATION A thONITOR. BUILDING TANK (UNIT 1 ONLY) CONDEN- SPENT REACTOR LOW TDS SATE FUEL thAKEUP WATER HOLDUP TANK POOL TANK TANK SOLID RAD WASTE S YSTEth
CQ CO
~O N Oh O ~
O~ OO W ~O ~ OOO ~ ON l V W'ON
~ ~ ~ NO MNO ON
~
~ ~
N N NNN OWN ro-No N w o ~
~O h O rl ON N NNWN 'O hhl ~ ~
N- l OO ~ Wl ~ NO I H C> A g) NN WWO hl Qc O H g) CO W Wlhh
~ O NN ~ l r N ~
WNO
VI I 0 I k t
'I 1
I' NM4 ~ ~ N
~ W ~
S Af \
~ 4 S ~
~ .S
~ W\ \IS 8 a S>>W ~ 1
~ ~ SS I I I
I JI I I I II I I I I Iv I I ~s 1 I I I I IS I!II
)
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7.0 RADIOLOGICAL ENVIRONMENTAL PROGRAM 7.1 Radiolo ical Environmental Monitoring Pro ram Technical S ecification 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1 [of the Technical Specifications]. Samples shall be collected as specified in Table 3.12-1 [of the Technical Specifications] and from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1, and the detection capabilities required by Table 4.12-1 [of the Technical Specifications]. Environmental samples are collected at locations shown in Figures 7-1 and 7-2 and described in Table 7-1. Analytical techniques used ensure that the detection capabilities in Table 7-2 are achieved. Environmental samples are collected II and analyzed according to Table 7-3. The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected based on the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental I monitoring program provides measurements of radiation and of I radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals resulting from station operation. The initial radiological environmental monitoring program will be conducted for the first three years of commercial operation of Unit 1. Following this period, program changes may be proposed based on operational experience. Deviations are 7-1 Rev. 1 09/20/85
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permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, an effort is made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule are documented in the annual report. 7.2 Land Use Census Technical S ecification 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m 2 (500 ft2 ) producing broad leaf vegetation. A land use census is conducted in accordance with Technical Specification 3.12.2. When a land use census identifies a location(s) which yields a calculated dose or dose commitment greater than the values calculated from current sample locations, appropriate changes in the sample locations are 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 applies:
- 1. If the D/Q is at least 20X greater than a previously high D/Q, one of the existing sample locations may be replaced after an evaluation with a new one within 30 days. The 7-2 Rev. 1 09/20/85
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evaluation is based on past history of the location, availability of sample, milk production history, and other environmental conditions.
- 2. If the D/Q is not 20X greater than the previously highest D/Q, distance and D/Q are considered in deciding whether to replace one of the existing sample locations. If applicable, replacement is made within 30 days.
A land use census is 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. 7.3 Interlaborator Com arison Pro ram Technical S ecification 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission that correspond to samples required by [Technical Specification] Table 3.12-1. PVNGS laboratories or contract laboratories which perform analyses for the Radiological Environmental Monitoring Program participate in the Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program. This participation includes all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program. The results of analyses of these crosscheck samples are included in the annual report. 7-3 Rev. 1 09/20/85
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TABLE 7-1 (Sheet 1 of 4) RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS SAI1PLE SAMPLE LOCATION SITE TYPE DESIGNATION( LOCATION DESCRIPTION TLD, Air E30 APS Goodyear Office 2 TLD ENE24 Scott-Libby School TLD E25 Liberty School TLD, Air E20 APS Buckeye Office TLD ESE15 Palo Verde, AZ TLD, Air (Control)(b) SSE35 APS Gila Bend Substation TLD, SE7 Old U.S. 85 and Arlington School Road 7A Air SE8 Arlington School TLD SSE5 Corner of 363rd Ave. & Southern Pacific Pipeline Rd. TLD S5 Corner of 371st Ave. & Southern Pacific Pipeline Rd. 10 TLD SE5 Corner of 355th Ave. & Ward Rd. TLD ESE5 Corner of 339th Ave. & Dobbins Rd. 12 TLD E5 Corner of 339th Ave. & Buckeye-Salome Rd. 13 TLD Nl N Site Boundary 14 NNE2 -NNE Site Boundary 14A .(') NNE3 Buckeye-Salome Rd. & 371st Ave. 15 TLD(b) Ai (b) NE2 NE Site Boundary O Pd Mm N ~ 16 TLD ENE2 ENE Site Boundary <D CO 17 TLD E2 E Site Boundary Ln
0 TABLE 7-1 (Sheet 2 of 4) SAMPLE SAMPLE LOCATION SITE TYPE DESIGNATION LOCATION DESCRIPTION 17A Air E4 351st Ave., 1 mi. S of Buckeye Salome Rd. 18 TLD ESE2 ESE Site Boundary 19 TLD SE2 SE Site Boundary 20 TLD(b) 'SSE2'3 SSE Site Boundary 21 TLD Ai S Site Boundary 22 TLD SSW3 SSW Site Boundary 23 TLD(b) W5 2 miXes N. of Ward Rd., 3 miles W. of Wintersburg Rd. 24 TLD SW4 Ward Rd. at Desert Farms 25 TZ D(b) WSW5 Ward Rd. at Cattle Guard 4 26 TLD SSW5 Shepard Farm 27 T~(b) SW2 SW Site Boundary 28 TLD( ) WSW1 WSW Site Boundary 29 TLD , Air Wl W Site Boundary 30 TLD( ) WNW Site Boundary 31 TLD NW Site Boundary 32 TLD NNW Site Boundary
'33 TLD(b) Yuma Rd., 1/2 mile W.of Belmont Rd.
O5 'c) m 34 TLD Corner of Belmont Rd. & Van Buren Rd. t4 ~ 35 O Tonopah, Palo Verde Inn Pire Station CO tn 36 TLD Corner of Wintersburg Rd. & Van Buren Rd. 37 TLD Corner of 363rd Ave. & Van Buren Rd.
0 TABLE 7-1 (Sheet 3 of 4) SAMPLE SAMPLE LOCATION SITE TYPE DESIGNATION LOCATION DESCRIPTION 38 TLD NE5 Corner of 355th Ave. & Yuma Rd. 39 TLD") 343rd Ave., 1/2 mi. South of Lower Buckeye Rd. 40 TLD Ai N3 Wintersburg, AZ 41 TLD WNW20 Harquahala Valley School 42 TLD(b) N8 Ruth Fisher School 43 TLD(b) N45 Vulture Peak School (Wickenburg, AZ) 44 TLD( ) Ai APS El Mirage Office (Sun City, AZ)) (b) (Control) \ 45 TLD E20 REMP Lab. (Buckeye, AZ) (Iead PIG) 46 Water (b) (Control) McArthur's Farm (Tonopah, AZ)) 47 Vegetation (b) NE3 Adams Residence 48 Water (b) SW5 Desert Farms 49 Water (b) ESE4 Wedgeworth Residence, 351st Ave. & Dobbins Milk( ) 50 Baisley Dairy, 331st Ave. & Van Buren Rd. 51 Milk(b) Vegetation Ell Butler Dairy, Palo Verde Rd. & Southern Ave. 52 Vegetation (b) E15 Cambron Farm, Miller Rd. & Broadway Rd. 53 E26 Kerr Dairy, Dean & Buckeye Rds. 54 Milk E27 Skousen Dairy, Airport & Dobbins Rd. O P$ 'Cl lD 55 Milk E28 Lueck Dairy, Jackrabbit & Hazen Rds. M Milk(b) (Control)
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56 E75 Hamstra Dairy 82, McQueen & Ryan Rds. Water (b) CO Ln 57 Onsite Well 27ddc 58 Water Onsite Well 34abb
a TABLE 7-1 (Sheet 4 of 4) SAMPLE SAMPLE LOCATION SETE 1YPE DESIGNATION LOCATION DESCRIPTION 59 Surface Water (b) Onsite PVNGS Evaporation Pond 60 Surface Water (b) Onsite PVNGS Reservoir 61 Citrus (Control) E80 Cooley Farms, Inc. (Higley, Arizona) 62 Vegetation(b) E60 AJM Farms, Inc., Chandler Industrial Park (Control) (a) Location Designation based on Sector and Zone Nomenclature from Table J-l, NUREG-0654. Distances are from the centerline of UnitI 2 containment. (b) These samples fulfillthe requirements of the PVNGS Technical Specifications. (c) Refer to Figures 7-1 and 7-2 for relative locations of Sample sites. 'V I
TABLE 7-2 (Sheet 1 of 2) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Lover Limit of Detection (LLD)(a) Airborne Particulate Mater or Gas Milk Food Products Analysis (pCi/1) (pCi/m3) (pci/1) (pCi/kg, wet) Gross Beta 4 1 x 10-2 H-3 2000(b) Mn-54 Fe-59 30 Co-58 15 Co-60 15 Zn-65 , 30 Zr-95 30 Nb-95 15 I-131 7 K 10-2 60 O M0 P1 Cs-134 15 5x102 60 h) ~ O CO Cs-137 18 6xl02 18 80 Ln Ba-140 60 60 La-140 15
TABLE 7-2 (Sheet 2 of 2) (a) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95X 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): 4.66S LLD = 2.22 EVY exp (-XAt 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), 2.22 is the number of disintegrations per minute per picocurie, E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), Y is the fractional radiochemical yield (when applicable), his the radioactive decay constant for the particuar 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 It should the fact) ( )LLD be limit for for drinking water. a recognized that the LID particular
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is defined measurement. in the samples (e.g., potassium-40 milk samples). Typical values for E, V, Y, and t should be used in the calculations. as a yrdord r " (before the fact) M limit
0 TABLE 7-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PVNGS Exposure Pathway Sampling and Type and Frequency and/or Sample Collection Frequency of Analysis Sampling Locations r Airborne radioiodine Continuous sampling Gross beta weekly; Six locations as and particulates collected weekly I-131, weekly; gamma listed in Table 7-1. spectrum monthly; Control locations are 6 composite of filters and 44 (alternate). Direct radiation TL dosimeters at Gamma dose:quarterly Forty locations as location changed listed in Table 7-1. quarterly Control locations are 43 and 44. Waterborne: Surface Monthly Composite of Gamma spectrum monthly; On-site reservoir and weekly grab sample tritium quarterly evaporation pond (sample locations 59 and 60). Ground arterly grab Tritium and.gamma On-site well Nos. 34abb and sample spectrums quarterly 27ddc (sample locations 57 and 58). Drinking (Well) Composite or grab Gross beta and gamma Locations 46, 48 & 49. sample one-month spectrums monthly; Control location is 46. period tritium quarterly OQ Ingestion: Semimonthly for Gamma spectrum and Locations 50, 51, 53 and M m Milk animals on ~ radioiodine semi- 56. Control location is h) ~ pasture, other- monthly or monthly 56. Co wise monthly 'Ln Food Products Once per harvest Gamma spectrum and Locations 47, 52 and 62. radioiodine per sample
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APPENDIX A DETERMINATION OF CONTROLLING LOCATION The controlling location is the location of the MEMBER OF THE PUBLIC who receives the highest doses. The determination of a controlling location for implementation of 10CFR50 for radioiodines and particulates is known to be a function of: (1) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptor's age , The incorporation of these parameters into Equation 4-3 results in the respective equations at the controlling location. The isotopic release rates are based upon the source terms calculated using the PVNGS Environmental Report, Operating License Stage, Table 3.5-12, without carbon. All of the locations and exposure pathways, identified in the 1984 Land Use Census, have been evaluated. -These include cow milk ingestion, goat milk ingestion, vegetable ingestion, inhalation, and ground plane exposure. An infant is assumed to be present at all milk pathway locations. A child is assumed to be present at all vegetable garden locations. The ground plane exposure pathway is only considered to be present where an infant is not present. Naturally, inhalation is present everywhere an individual is present. For the determination of the controlling locations, the highest X/Q and D/Q values, based on the 9 year meteorological data base, for the vegetable garden, cow milk, and goat milk pathways,, are selected for each unit. The receptor organ doses have been calculated at each of these locations. Based upon these calculations, it is determined that the controlling receptor pathway is a function of unit location. For Unit 1, the controlling receptor is a garden-child pathway; for releases from Unit 2 and Unit 3 the controlling receptor is a cow milk-infant pathway. These determinations are based upon Table 4-16 which, in turn, is based upon the 1984 Land Use Census. Locations of the nearest residences, gardens and milch animals, as determined in the 1984 Land Use Census, are given in Table A-l. A-1 Rev. 1 09/20/85
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TABLE A-.l (Sheet 1 of 3) EXPOSURE PATHWAY I,OCATIONS NEAREST TO PVNGS UNIT 1 Nearest Nearest I,ocation Nearest Location Milch Location Residence Designator Garden Designator Animal Designator Animal Sector Distance (b) Distance (b) Distance (b) Type Desi ator(a) Miles(a) Miles(a) Miles(a) N 1.4 3 1.4 (c) NNE 1.8 20 (c) (c) NE '1.9 4 2;1 (c) ENE 2.7 6 2.7 (c) E 2.8 9 (c) (c) ESE 3.7 8 4.6 9 4.6 . Goat SE 4.1 10 'l 4.1 10 (c) SSE . 4.7 (c) (c) S 4.6 19 5.2 12 5.1 12 . Cow SSW 3.5 13 (c) (c) SW 2.9 14 (c) (c) WSW 2.6 15 (c)~ (c) W (c) (c) (c) WNW (c) (c) (c) NW 3.8 21 4.1 16 (c) NNW 2.0 17 (c) (c) (a) Sector designators and distances derive from the 1984 Land Use Census (letter ANPM-21221-JRM/LEB), and are specific to the subject PVNGS unit. Og (b) Location designators, and animal types at locations indicated, are from the 1984 Land Use Census (letter Mm ANPM-21221-JRM/LEB). CO (c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified. no pathway (residence, Ln garden or milch animal as appropriate) within the sector and within 5 miles.
5Ti<,BLE A-1 (Shel;.. 2 of 3) EXPOSURE PATHWAY LOCATIA S NEAREST TO PUNGS UNIT 2 F Nearest Nearest Location Nearest Location Milch Location Residence Designator Garden Designator Animal~ Designator Animal Sector Distance (b) Distance
~ (b) Distance (b) Type Desi nator(a) Miles(a) Miles(a) Miles(a)
N 1.5 1 1.7 2 (c) NNE 1.5 3 1.5 3- (c) NE 2.0 4 2.3 5 (c) ENE 2.7 6 2.7 6 (c) E 3.0 7 (c) (c)'.7 ESE 3.7 8 4.7 9 Goat SE - 4.0 10 4.0 .10 (c) SSE 4.5 11 (c) (c) S 4.5 19 5.0 12 5.0 12 Cow SSW 3.2 13 (c) (c) SW 2.7 14 (c) (c) WSW 2.5 15 (c) (c) W (c) (c) (c) WNW (c) (c) (c) NW 4.0 16 4.0 16 (c) NNW 2.0 17 5.0 18 (c) (a) Sector designators and distances derive from the 1984 Land Use Census (letter ANPM-21221-JRM/LEB), and are specific to the subject PUNGS unit. O g 'c) m tO ~ (b) Location designators, and animal types at locations indicated, are from the 1984 Land Use Census (letter O ANPM-21221-JRM/LEB) ~ CO Ln (c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified no pathway (residence, garden or milch animal as appropriate) within the sector and within 5 miles.
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TABLE A-1 (Sheet 3 of 3) EXPOSURE PATHWAY LOCATIONS NEAREST TO PVNGS UNIT 3 Nearest Nearest Location Nearest Location Milch Location Residence Designator 'arden Designator Animal Designator Animal Sector Distance (b) Distance (b) Distance (b) Type Desi nator(a) Miles(a) exiles(a) Miles(a) N 1.8 1 1.9 (c) NNE 1.7 3 1.7 3 (c) NE 2.2 2.4 5 (c) ENE 2.9 6 2.9 6 (c) E 3.0 7 4.6 9 4.5 Goat ESE 3.7 8 4.0 10 (c) SE (c) (c) (c) SSE S 4.4 4.2 ll 19 (c) 4.9 12 (c) 4.8 12 Cow SSW 3.1 13 (c) (c) SW 2.5 14 (c) (c) WSW 2.4 15 (c) (c) W (c) (c) (c) WNW (c) (c) (c) NW 4.3 16 4.3 16 (c) NNW 2.2 17 5.0 18 (c) (a) Sector designators and distances derive from the 1984 Land Use Census (letter ANPM-21221-JRl9'LEB), and are specific to the subject PVNGS unit. Mg O lb N~ (b) Location designators, and animal types at locations indicated; are from the 1984 Land Use Census (letter. ANPM-21221-JRM/LEB). CO (c) Postulated to be at 5 mile distance since the 1984 Land Use Census identified no pathway (residence, garden or milch animal as appropriate) within the sector and within 5 miles.
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