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{{#Wiki_filter:f.....DRAFT OF CRYSTAL RIVER - UtilT 3 0FFSITE DOSE CALCULATI0t1 fMfiUAL APRIL 19, 1979 (for use with Draft of Crystal River - Unit 3 Technical Specifications, April 19,1979, Based on NUREG-0472, Revision 2, February 1978)
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.e 853 221 7908290506
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..,'.TABLE OF CONTENTS 1.0 Introduction 2.0 Radioactive Liquid Effluent Instrumtr.t ? tion Setpoints (Speci fication 3.3.3.8) 3.0 Radioactive Gaseous Process and Effluent Instrumentation Setpoints (Specification 3.3.3.9) 4.0 Radioactive Liquid Effluent Releases and Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) 4.2 Radioactive Liquid Effluent Projected Dose (Specification 4.11.1.3) 5.0 Radioactive Gaseous Effluent Dose Caiculations 5.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1) 5.2 Radioactive Gaseous Effluent Other Than Noble Gas Dose Rate (Speci fIcation 4.11.2.1.4) 5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose (Speci fication 4.11.2.2) 5.4 Radioactive Gaseous Effluent Other Than Noble Gas Cumulative Dose (Specification 4.11.2.3) 5.5 Radioactive Gaseous Effluent Projected Dose (Speci fica tion 4.11.2.4.1) 6.0 Radiological Environnental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b) 7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports (Specification 6.9.1.9) 8.0 Revisions to the ODCM (Specification 6.14.2) 853 222  
        .
'.,', 1.0 Introduction This Offsite Dose Calculation Manual (0DCM) describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable Limiting Conditions for Operation (LCOs) contained in the Appendix A Technical Specifications for Crystal River Unit 3, 853 223  
DRAFT OF CRYSTAL RIVER - UtilT 3 0FFSITE DOSE CALCULATI0t1 fMfiUAL APRIL 19, 1979 (for use with Draft of Crystal River - Unit 3 Technical Specifications, April 19,1979, Based on NUREG-0472, Revision 2, February 1978)
**.,.2.0 Radficactive_ Liqui.d Ef fluent Instrumentation Setpoint Specification 3.3.3.G 3.0 Radoiactive Gaseous Process and Effluent Instrumentation Setpoints Specification 3.3.3.9)
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e 853   221 7908290506     ,
 
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TABLE OF CONTENTS 1.0 Introduction 2.0 Radioactive Liquid Effluent Instrumtr.t ? tion Setpoints (Speci fication 3.3.3.8) 3.0 Radioactive Gaseous Process and Effluent Instrumentation Setpoints (Specification 3.3.3.9) 4.0 Radioactive Liquid Effluent Releases and Dose Calculations 4.1   Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) 4.2 Radioactive Liquid Effluent Projected Dose (Specification 4.11.1.3) 5.0 Radioactive Gaseous Effluent Dose Caiculations 5.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1) 5.2 Radioactive Gaseous Effluent Other Than Noble Gas Dose Rate (Speci fIcation 4.11.2.1.4) 5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose (Speci fication 4.11.2.2) 5.4 Radioactive Gaseous Effluent Other Than Noble Gas Cumulative Dose (Specification 4.11.2.3) 5.5 Radioactive Gaseous Effluent Projected Dose (Speci fica tion 4.11.2.4.1) 6.0 Radiological Environnental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b) 7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports (Specification 6.9.1.9) 8.0 Revisions to the ODCM (Specification 6.14.2) 853   222
 
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1.0 Introduction This Offsite Dose Calculation Manual (0DCM) describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable Limiting Conditions for Operation (LCOs) contained in the Appendix A Technical Specifications for Crystal River Unit 3, 853     223
 
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2.0 Radficactive_ Liqui.d Ef fluent Instrumentation Setpoint Specification 3.3.3.G 3.0 Radoiactive Gaseous Process and Effluent Instrumentation Setpoints Specification 3.3.3.9)
The radiological effluent Technical Specifications require alann/ trip setpoints fer radiation monitors and flow measurement devices for each
The radiological effluent Technical Specifications require alann/ trip setpoints fer radiation monitors and flow measurement devices for each
~effinc ut line.
                                                            ~
Mpoint values are to be calculated to assure that alani and trip actions occur prior to exceeding the limits of 10 CFR 20 a? the release point to the unrestricted area.
effinc ut line. Mpoint values are to be calculated to assure that alani and trip actions occur prior to exceeding the limits of 10 CFR 20 a? the release point to the unrestricted area. The calculated alann and trip action setpoints to be specified in the ODCM for each radioactive liquid effluent line monitor and flow measurement device must satisfy the following equation:
The calculated alann and trip action setpoints to be specified in the ODCM for each radioactive liquid effluent line monitor and flow measurement device must satisfy the following equation:
cf Rf $ C where:
cf Rf $ C where: C=the cffluent concentration limit (Specification 3.11.1) implementing 10 CFR 20 for the site, in uCi/ml c=The setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentracion in the effluent line prior tc dilution and subsequent reiease; the setpoint, which is propo.-tional to the volumetric flow of the effluent line and inversely proportional to the volumetric flow of the dilution stream plus the effTuent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the unrestricted area f=the flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below F=the dilution water flow setpoint as measured prior to the release point, in volume.per unit time.(Note that if no dilution is pruided, c 1 C.
C=   the cffluent concentration limit (Specification 3.11.1) implementing 10 CFR 20 for the site, in uCi/ml c=   The setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentracion in the effluent line prior tc dilution and subsequent reiease; the setpoint, which is propo.-tional to the volumetric flow of the effluent line and inversely proportional to the volumetric flow of the dilution stream plus the effTuent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the unrestricted area f= the flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below F=   the dilution water flow setpoint as measured prior to the release point, in volume.per unit time.
Also, note that when (F) is large compared to (f), then F+f 2 F.)
(Note that if no dilution is pruided, c 1 C.     Also, note that when (F) is large compared to (f), then F+f 2 F.)
The equation is satisfied when the following alarm / trip setpoints are provided for each effluent line in the ODCM:
The equation is satisfied when the following alarm / trip setpoints are provided for each effluent line in the ODCM:
f 1[F_ (in ml/sec; for example), c F1 (in ml/sec; for example).
f 1[F_ (in ml/sec; for example),
cf (in uCi/ml; for example).
c F1       (in ml/sec; for example).
, Scme plants may be operated using a fixea value for or re of-,'these three variables, c, f or F.
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~,.853 224  
cf       (in uCi/ml; for example).
*.,-.Eg mple 1 By using a constant capacity radwaste system discharge pump (on the undiluted stream) the value of (f) is fixed; therefore, the setpoints to be given are:
      -  ,
f=ml/sec (fixed)
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F>ml/sec = cf/C c=xF uCi/ml I CF/f 6 If c = 3x10-8 pCi/ml, f = 4000 ml/sec and F > 4x10 ml/sec, the radiation monitor setpoint is calculated as follows:
Scme plants may be operated using a fixea value for or           re of these three variables, c, f or F.
c 1 CF/f ,(3x10-81F = 7.5x10-12F pCi/ml.
                    ~
4000-If F is measured at some value in excess of the limiting value (the 6 limiting value is 4x10 ml/sec in this exgmple), then c may be If F = 8x10 ml/sec, the alarm setpoint established proportionately.
                        ,                                                                 .
is: c = 7.5x10-12 (uCi/ml per ml/sec)(ml/sec)
853       224
F= 7.5x10-12.(8x106) = 6x10-5 pCi/ml.
 
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Eg mple 1 By using a constant capacity radwaste system discharge pump (on the undiluted stream) the value of (f) is fixed; therefore, the setpoints to be given are:
f=                             ml/sec (fixed)
F>                             ml/sec = cf/C c=                             xF uCi/ml I CF/f If c = 3x10-8 pCi/ml, f = 4000 ml/sec and F > 4x106 ml/sec, the radiation monitor setpoint is calculated as follows:
c 1 CF/f
                    ,(3x10-81F = 7.5x10-12F pCi/ml.
4000-If F is measured at some value in excess of the limiting value (the 6
limiting value is 4x10 ml/sec in   this exgmple), then c may be established proportionately. If F = 8x10 ml/sec, the alarm setpoint is:
c = 7.5x10-12F (uCi/ml per ml/sec)(ml/sec)
                    = 7.5x10-12.(8x106) = 6x10-5 pCi/ml.
In this case, the alarm setpoint for the radioactive liquid effluent line nomitor can be established at 6x10-5 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:
In this case, the alarm setpoint for the radioactive liquid effluent line nomitor can be established at 6x10-5 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:
c/F < 7x5x10-12 pCi/ml per ml/sec.
c/F < 7x5x10-12 pCi/ml per ml/sec.
Example 2 By using a constant capacity dilution pump (on the dilution stream prior to a mixing box), the value of (F) is fixed; therefore, the setpoints to be given are:
Example 2 By using a constant capacity dilution pump (on the dilution stream prior to a mixing box), the value of (F) is fixed; therefore, the setpoints to be given are:
# <ml/sec = CF/c F=ml/sec (fixed) c=x (1/f)uCi/ml I CF/f 6 If C = 3x10-8 uCi/ml, F = 4x10 ml/sec and f < 4000 ml/sec, the radiation monitor setpoint is calculated as follows:
                  #<                           ml/sec = CF/c F=                           ml/sec (fixed) c=                           x (1/f)uCi/ml I CF/f If C = 3x10-8 uCi/ml, F = 4x106 ml/sec and f < 4000 ml/sec, the radiation monitor setpoint is calculated as follows:
c I CF/f= (3x10-8 6 x 4x10 1 = 0.12(1/f) uCi/ml.
c I CF/f
f 853 225  
                    = (3x10-8 x 4x106 1 = 0.12(1/f) uCi/ml.
*, , , If f is measured at some value less than the limiting value (the limiting salue is 4000 ml/sec in this example), then c may be establisned proportionately.
f 853   225
If f = 1000 ml/sec, the alarm setpoint is: c = 0.12(1/f)(uCi/sec)(sec/ml)
 
= 0.12 = 1.2x10-4 uCi/ml.
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If f is measured at some value less than the limiting value (the limiting salue is 4000 ml/sec in this example), then c may be establisned proportionately. If f = 1000 ml/sec, the alarm setpoint is:
c = 0.12(1/f)(uCi/sec)(sec/ml)
                  = 0.12 = 1.2x10-4 uCi/ml.
1000 In this case, the alarm setpont for the radioactive liquid effluent line monitor can be established at 1.2x10-4 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:
1000 In this case, the alarm setpont for the radioactive liquid effluent line monitor can be established at 1.2x10-4 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:
cf > 0.12 pCi/sec.
cf > 0.12 pCi/sec.
Value of c A detailed description of the ethod to be used to obtain the value of (c) should be provided.
Value of c A detailed description of the ethod to be used to obtain the value of (c) should be provided. Since (c) is dependent on the radionuclide distribution, yields, calibration and the monitor's parameters, each of these sariable: should be considered and the fixed or adjustable setpoint method o# determination described for each effuent monitor.
Since (c) is dependent on the radionuclide distribution, yields, calibration and the monitor's parameters, each of these sariable: should be considered and the fixed or adjustable setpoint method o# determination described for each effuent monitor.
This may be accomplished by tabulation.
This may be accomplished by tabulation.
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.,-, 4.0 Radioactive Liquid Effluent Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) m The dose contributions for the total time period I att shall be t=1 determined by calculation at least once per 31 days and a cumulative sumation of these total body and any organ doses shall be maintained for each calendar quarter. These dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression:
853     226
m C g Fr]Dt =I[Ait I att i i t=1 where: Dt = the cumulative dose or dose commitment to the total body or an organ t fran the liquid effluents for the total time period m I atg in mrem t=1 at = the length of the gth time period over which Cjg and Fg g are averaged for all liquid releases, in hours.
 
C g= the average concentration of radionuclide i in undiluted liquid i effluent during the time period att from any liquid release, in pCi/ml.Ait= the site related ingestion dose or dose cannitment factor to the total body or any organ t for each identified principal gamma and betta emitter listed in Table 4.1-1, in mrem-ml per hr-uCi .
      ,
Fr= the near field average dilution factor for Cig during any liquid effluent release.
  .
Defined as the ratio of the maximum undiluted liquid waste flow during release to the produce of the average flow from the site discharge structure to unrestricted receiving water times 1.0.
    -
For radionuclides not detennined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly canposite analyses.However, for reporting purposes, the calculated dose contributions shall be based on the actual canposite analyses.
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4.0 Radioactive Liquid Effluent Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) m The dose contributions for the total time period I att shall be t=1 determined by calculation at least once per 31 days and a cumulative sumation of these total body and any organ doses shall be maintained for each calendar quarter. These dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression:
m Dt =I[Ait I att   Ci g Fr]
i   t=1 where:
Dt = the cumulative dose or dose commitment to the total body or an organ t fran the liquid effluents for the total time period m
I atg in mrem t=1 at g= the length of the gth time period over which Cjg and Fg are averaged for all liquid releases, in hours.
Ci g= the average concentration of radionuclide i in undiluted liquid effluent during the time period att from any liquid release, in pCi/ml.
Ait= the site related ingestion dose or dose cannitment factor to the total body or any organ t for each identified principal gamma and betta emitter listed in Table 4.1-1, in mrem-ml per hr-uCi .
Fr= the near field average dilution factor for Cig during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the produce of the average flow from the site discharge structure to unrestricted receiving water times 1.0.
For radionuclides not detennined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly canposite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual canposite analyses.
The dose factor Ait for each nuclide, i, embodies the dose factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin.
The dose factor Ait for each nuclide, i, embodies the dose factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin.
The adult total body dose factor and the maximum adult organ dose factor for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109; thus the list contains critical organ dose factors for various organs.
The adult total body dose factor and the maximum adult organ dose factor for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109; thus the list contains critical organ dose factors for various organs. The dose factor is written:
The dose factor is written:
Ait = ko(Uw/Dw + UfBFi + UjBIj)DFj                         853 M
Ait = ko(Uw/Dw + UfBFi + UjBIj)DFj 853 M  
 
.,-.where: Ait = composite dose parameter for the total body or critical organ of an adult for nuclide, i, for all appropriate pathways, mrem /hr per pCi/ml.
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3 k = units conversion factor,1.14x105 = 106 o pCi/uCi x 10 ml/kg +
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    -
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where:
Ait = composite dose parameter for the total body or critical organ of an adult for nuclide, i, for all appropriate pathways, mrem /hr per pCi/ml.
ko= units conversion factor,1.14x105 = 106 pCi/uCi x 10 3ml/kg +
8750 hr/yr.
8750 hr/yr.
U = 730 kg/hr, adult water consumption (fresh water cite only).
Uw = 730 kg/hr, adult water consumption (fresh water cite only).
w.Vf = 21 kg/hr, adult fish consumption (all sites).
      .
Vf = 21 kg/hr, adult fish consumption (all sites).
Uj = 5 kg/yr, adult invertebrate consumption (salt water site only).
Uj = 5 kg/yr, adult invertebrate consumption (salt water site only).
BFj = Bioaccumulation factor for nuclide, i, in fish (fresh or salt water site, as applicable), pCi/kg per Ci/1, from Table A-1 of Regulatory Guide 1.109 (Rev.1,10/77).
BFj = Bioaccumulation factor for nuclide, i, in fish (fresh or salt water site, as applicable), pCi/kg per Ci/1, from Table A-1 of Regulatory Guide 1.109 (Rev.1,10/77).
BIj = Bioaccumulation factor for nuclide, i, in invertebrates (salt water only), pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109 (Rev. 1, 10/77).
BIj = Bioaccumulation factor for nuclide, i, in invertebrates (salt water only), pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109 (Rev. 1, 10/77).
DFj = Dose conversion factor for nuclide, i, for adults in pre-selected organ, t, in mrem /pCi, from Table E-11 of Regulatory Guide 1.109 (Rev. 1, 10/77).
DFj = Dose conversion factor for nuclide, i, for adults in pre-selected organ, t, in mrem /pCi, from Table E-11 of Regulatory Guide 1.109 (Rev. 1, 10/77).
Dilution factor from the near field area within one-quarter mile D=w of the release point (s) to the potable water intake for the adult water consumption (fresh water site only).
Dw =  Dilution factor from the near field area within one-quarter mile of the release point (s) to the potable water intake for the adult water consumption (fresh water site only).
Inserting the usage factors of Regulatory Guide 1.109 (Rev.1,10/77) as appropriate into the equation gives the following expression:
Inserting the usage factors of Regulatory Guide 1.109 (Rev.1,10/77) as appropriate into the equation gives the following expression:
5 Ait = 1.14x10 (21BFj + 5BI )DFj j.853 228  
Ait = 1.14x10 5(21BFj + 5BI j)DFj
..~Table 4.1-1
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.LIQUID EFFLUENT INGESTION DOSE FACTORS Ait Dose or Dose Conmitnent Factors BF BI Critical DF (mrem-ml per br-pCi)
853     228
Radionuclide (t/kg)(t/kg)Orga n (mrem /pCi)
 
Total Body Critical Or9ans H-3 9.0E-01 9.3E-01 All 1.05E-07 2.80E-01 2.80E-01 Na-24 6.7E-02 1.9E-01 All 1.70E-06 4.60E-01 4.60E-01 P-32 2.9E+04 3.0E+04 Bone 1.93E-04 6.45E+05 1.67E+07 C r-51 4.0E+02 2.0e+03 GI-LLI 6.69E-07 5.58E+00 1.40E+03 Mn-54 5.5E+02 4.0E+02 GI-LLI 1.40E-05 1.35E+03 2.16E+04 Fe-55 3.0E+03 2.0E+04 Bone 2.75E-06 8.23E+03 5.llE+04 Fe-59 3.0E+0i 2.0E+04 GI-LLI 3.40E-05 7.27E404 6.32E+05 Co-58 1.0E+02 1.0E+03 GI-LLI 1.51E-05 1.35E+03 1.22E+04 Co-60 1.0E+02 1.0E+03 GI-LLI 4.02E-05 3.82E+05 3.25E+04 Zn-65 2.0E+03 5.0E+04 Liver 1.54E-05 2.32E+05 5.13E+05 Sr-89 2.0E+00 2.0E+01 Bone 3.08E-04 1.43E+02 4.99E+03 S r-90 2.0E+00 2.0E+01 Bone 7.58E-03 3.01E+04 1.23E+05 Zr-95 2.0E+02 8.0E+01 GI-LLI 3.09E-05 3.50E+00 1.62E+04 Nb-95 3.0E+04 1.0Et02 GI-LLI 2.10E-05 1.34E+02 1.51E+06 f50-99 1.0E+01 1.0E+01 GI-LLI 9.99E-06 2.43E+01 2.96E+02 Tc-99M 1.0E+01 5.0E+01 GI-LLI 4.13E-07 5.00E-01 2.17E401 Ag-llOn GI-LLI 6.04E-05 2.55E-01 1.75E+02 I-131 1.0E+01 5.0E+01 Thyroid 1.95E-03 1.79E+02 1.02E+05 I-132 1.0E+01 5.0E+01 Thyroid 1.90E-05 1.00E+01 9.96E+02 1-133 1.0E+01 5.0E+01 Thyroid 3.63E-04 3.95E+01 1.90E+04 I-135 1.0E+01 5.0E+01 Thyroid 7.65E-05 2.24E+01 4.01E+03 Cs-134 4.0E+01 2.5E+01 Liver 1.48E-04 1.33E+04 1.63E+04 Cs-137 4.0E+01 2.5E+01 Liver 1.09E-04 7.85E+03 1.20E+04 Ba-140 1.0E+01 1.0E402 GI-LLI 4.18E-05 1.08E+02 3.38E+03 La-140 2.5E+01 1.0E+03 GI-LLI 9.25E-05 2.00E-01 5.83E+04 cy3 t;, Ce-141 1.0E+01 6.0E+02 GI-LLI 2.42E-05 3.00E-01 8.86E+03 tsa Ce-144 1.0E+01 6.0E+02 GI-LLI 1.65E-04 9.60E+00 6.04E+04 Np-239 1.0E+01 1.0E+01 GI-LLI 2.40E-05 1.91E-03 7.llE+02 N N 4  
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**..-.4.2 Radioactive Liquid Effluent Projected Dose (Soecification 4.11.1.3) 853 230  
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'*., 5.0 Radioactive Gaseous Effluent Dose Calculations 6.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1) a.Release rate limit for noble gases:
                                                                                                        ~
E [Kj (x/Q) Qj] < 500 mrem /yr, and i.I [(Lj + 1.1 Mj)(x/Q) Qj)] < 3000 mrem /yr i mrem /yr where: Kj = The total body dose factor due to gamma emissions for eqch identified noble gas radionuclide, in mrem /yr per uCi/m .
Table 4.1-1
o Lj = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3, iij = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 (unit conversion constant of 1.1 mrem / mrad converts air dose to skin dose).
                                                                                                            .
Qi = The release rate of radionuclides, i, add in gaseous effluent from ail release points at the site in pCi/sec.(x/Q) =sec/m3 The highest calculated annual average relative concentration for any area at or bayond the exclusion area bounda ry.
LIQUID EFFLUENT INGESTION DOSE FACTORS Ait Dose or Dose Conmitnent Factors BF     BI     Critical         DF                   (mrem-ml per br-pCi)
Radionuclide (t/kg) (t/kg)     Orga n       (mrem /pCi)     Total Body         Critical Or9ans H-3       9.0E-01 9.3E-01     All           1.05E-07       2.80E-01           2.80E-01 Na-24     6.7E-02 1.9E-01     All           1.70E-06       4.60E-01           4.60E-01 P-32     2.9E+04 3.0E+04     Bone         1.93E-04       6.45E+05           1.67E+07 C r-51     4.0E+02 2.0e+03     GI-LLI       6.69E-07       5.58E+00           1.40E+03 Mn-54     5.5E+02 4.0E+02     GI-LLI       1.40E-05       1.35E+03           2.16E+04 Fe-55     3.0E+03 2.0E+04     Bone         2.75E-06       8.23E+03           5.llE+04 Fe-59     3.0E+0i 2.0E+04     GI-LLI       3.40E-05       7.27E404           6.32E+05 Co-58     1.0E+02 1.0E+03     GI-LLI       1.51E-05       1.35E+03           1.22E+04 Co-60     1.0E+02 1.0E+03     GI-LLI       4.02E-05       3.82E+05           3.25E+04 Zn-65     2.0E+03 5.0E+04     Liver         1.54E-05       2.32E+05           5.13E+05 Sr-89     2.0E+00 2.0E+01     Bone         3.08E-04       1.43E+02           4.99E+03 S r-90     2.0E+00 2.0E+01     Bone         7.58E-03       3.01E+04           1.23E+05 Zr-95     2.0E+02 8.0E+01     GI-LLI       3.09E-05       3.50E+00           1.62E+04 Nb-95     3.0E+04 1.0Et02     GI-LLI       2.10E-05       1.34E+02           1.51E+06 f50-99     1.0E+01 1.0E+01     GI-LLI       9.99E-06       2.43E+01           2.96E+02 Tc-99M     1.0E+01 5.0E+01     GI-LLI       4.13E-07       5.00E-01           2.17E401 Ag-llOn                       GI-LLI       6.04E-05       2.55E-01           1.75E+02 I-131     1.0E+01 5.0E+01     Thyroid       1.95E-03       1.79E+02           1.02E+05 I-132     1.0E+01 5.0E+01     Thyroid       1.90E-05       1.00E+01           9.96E+02 1-133     1.0E+01 5.0E+01     Thyroid       3.63E-04       3.95E+01           1.90E+04 I-135     1.0E+01 5.0E+01     Thyroid       7.65E-05       2.24E+01           4.01E+03 Cs-134     4.0E+01 2.5E+01     Liver         1.48E-04       1.33E+04           1.63E+04 Cs-137     4.0E+01 2.5E+01     Liver         1.09E-04       7.85E+03           1.20E+04 Ba-140     1.0E+01 1.0E402     GI-LLI       4.18E-05       1.08E+02           3.38E+03 cy3  La-140     2.5E+01 1.0E+03     GI-LLI       9.25E-05       2.00E-01           5.83E+04 t;,   Ce-141     1.0E+01 6.0E+02     GI-LLI       2.42E-05       3.00E-01           8.86E+03 tsa   Ce-144     1.0E+01 6.0E+02     GI-LLI       1.65E-04       9.60E+00           6.04E+04 Np-239     1.0E+01 1.0E+01     GI-LLI       2.40E-05       1.91E-03           7.llE+02 N
N 4
 
  *     *
          .
    .
      -
.
4.2 Radioactive Liquid Effluent Projected Dose (Soecification 4.11.1.3) 853 230
 
      '
  *
    .
,
5.0 Radioactive Gaseous Effluent Dose Calculations 6.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1)
: a. Release rate limit for noble gases:
E [Kj (x/Q) Qj] < 500 mrem /yr, and i                         .
I [(Lj + 1.1 Mj)(x/Q) Qj)] < 3000 mrem /yr i                             mrem /yr where:
Kj = The total body dose factor due to gamma emissions for eqch identified noble gas radionuclide, in mrem /yr per uCi/mo.
Lj = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3, iij = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 (unit conversion constant of 1.1 mrem / mrad converts air dose to skin dose).
Qi = The release rate of radionuclides, i, add in gaseous effluent from ail release points at the site in pCi/sec.
(x/Q) =         sec/m3     The highest calculated annual average relative concentration for any area at or bayond the exclusion area bounda ry.
5.2 Gaseous Effluents Other than Noble Gas Dose Rate (Specification 4.11.2.1.4)
5.2 Gaseous Effluents Other than Noble Gas Dose Rate (Specification 4.11.2.1.4)
Release rate limit for all radionuclides and radioactive materials in particulate fonn and radionuclides other than noble gases:
Release rate limit for all radionuclides and radioactive materials in particulate fonn and radionuclides other than noble gases:
I Pj [W Qj] < 1500 mrem /yr i where: Pj = The dose factor for radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases the food and ground plane pathways in m2 (mrem /m3 and for for the inhalation pathway, in mrem /yr oer aCi
I Pj [W Qj] < 1500 mrem /yr i
/yr) per pCi/sec from Tchle 4.11-4.
where:
The dose factors are based on the critical individual organ and most restrictive age group (i nfa nt) .
Pj = The dose factor for radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases for the inhalation pathway, in mrem /yr oer aCi the food and ground plane pathways in /yr)         m2 (mrem per     /m3 and fo pCi/sec from Tchle 4.11-4.     The dose factors are based on the critical individual organ and most restrictive age group (i nfa nt) .
W=The high calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location: W=sec/m3, for the inhalation pathway.
W= The high calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location:
The location is the exclusion area boundary in the sector.853 231  
W=           sec/m3, for the inhalation pathway. The location is the exclusion area boundary in the                 sector.
.-.W=meter-2, for th- food and ground plant pathways.
853     231
The location is the exclusion area boundary in the sector..Qj = The release rate of radionuclides, i, add in gaseous effluent from all release points at the site in uCi/sec.
 
853 232  
    .
*.SPECIAL NOTES:
  -
(1) In all cases, the tritium relgases use the first W parameter, based on relative concentration (sec/m ).
.
(2) All radio-iodines are assumed to be released in elemental form.
W=       meter-2, for th- food and ground plant pathways.
If analysis includes the capability of detemining elemental and nonelemental foms in all releases, the food pathway rarameter may be adjusted accordi ngly.
The location is the exclusion area boundary in the sector.
      .
Qj = The release rate of radionuclides, i, add in gaseous effluent from all release points at the site in uCi/sec.
853   232
 
  *
.
SPECIAL NOTES:     (1) In all cases, the tritium relgases use the first W parameter, based on relative concentration (sec/m ). (2) All radio-iodines are assumed to be released in elemental form. If analysis includes the capability of detemining elemental and nonelemental foms in all releases, the food pathway rarameter may be adjusted accordi ngly.
The dose rate from the ith radionuclide (except tritium) is:
The dose rate from the ith radionuclide (except tritium) is:
Pj(inhalation)(x/Q) Q + [Pj(food) + Pj(ground plant)] (F/iJ) Q (mrem /yr) and for tritium, is:
Pj(inhalation)(x/Q) Q + [Pj(food) + Pj(ground plant)] (F/iJ) Q (mrem /yr) and for tritium, is:
3 P (inhalation)(x/Q) Q + P (food)(x/Q) Q = 3.0 x 10 (x/Q) Q (mrem /yr) j j Calculation of P4 (Inhalation) 3 Pj = K'(BR) DFAj (mrem /yr per pCi/m )
Pj (inhalation)(x/Q) Q + P j(food)(x/Q) Q = 3.0 x 10 (x/Q) 3    Q (mrem /yr)
where: K' = a constant of unit conversion,106 pCi/pCi.3 BR = the breathing rate of the infant age group, in m /yr.
Calculation of P4 (Inhalation)
DFAj = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide, in mrem /pCi.
Pj = K'(BR) DFAj (mrem /yr per pCi/m3) where:
The total body is considered as an organ in the selection of DFA .
K' = a constant of unit conversion,106 pCi/pCi.
j The age group considereg/yr from Table E-5 of Regulatory Guide 1.109 is the infant group.
BR = the breathing rate of the infant age group, in m /yr.3 DFAj = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide, in mrem /pCi. The total body is considered as an organ in the selection of DFA j.
The infant's breathing rate is taken as 1400 m (Rev. 1, 10/77).
is the infant group. The infant's breathing The   age group considereg/yr rate is taken as 1400 m            from   Table E-5 of Regulatory Guide 1.109 (Rev. 1, 10/77). The inhalation dose factors for the infant, DFAj are presented in Table E-10 of Regulatory Guide 1.109, in units of mrem /pC1.
The inhalation dose factors for the infant, DFAj are presented in Table E-10 of Regulatory Guide 1.109, in units of mrem /pC1.
Resolution of the units yields:
Resolution of the units yields:
Pj (inhalation) = 1.4 x 109 DFAj Calculation of Pi (Ground Plane) 2 Pj = K'K"DFGj (1-e-A t)Aj (m . mrem /yr per pCi/sec) i where: K' = a constant of unit conversion,106 pCi/pCi.K" = a constant of unit conversion, 8760 hr/ year.
Pj (inhalation) = 1.4 x 109   DFAj Calculation of Pi (Ground Plane)
Aj = the decay constant for the ith radionculide, sec -1 7 t = the exposure period, 3.15 x 10 sec (1 year).
Pj = K'K"DFGj (1-e-Ai t)Aj (m2 . mrem /yr per pCi/sec) where:
K' = a constant of unit conversion,106 pCi/pCi.
K" = a constant of unit conversion, 8760 hr/ year.
Aj = the decay constant for the ith radionculide, sec -1 t = the exposure period, 3.15 x 10 sec7  (1 year).
DFGj = the ground plane dose conversica factor for the ith radionculide (mrem /hr per pCi/m').
DFGj = the ground plane dose conversica factor for the ith radionculide (mrem /hr per pCi/m').
853 233  
853     233
*.The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for the ith radionuclide, DFG-are presented in Table E-6 of Regulatory Guide 1.109 (Rev.1,10/7f),, 2 in units of mrem /hr per pCi/m ).
 
  *
.
The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for the ith radionuclide, DFG-are presented in Table E-6 of Regulatory Guide 1.109 (Rev.1,10/7f),,
in units of mrem /hr per pCi/m2 ).
Resolution of the units yields:
Resolution of the units yields:
Pj (Ground) = 8.76 x 199 DFGj (1-e-A t)f39, i Calculation of P4 (Food)
Pj (Ground) = 8.76 x 199 DFGj (1-e-Ai t)f39, Calculation of P4 (Food)
P j = K ' r _F(Vap)
Q P j = K ' r _F(Vap)   F 0Fl i [e-A tif
Q i [e-A t ] y2. mrem /yr per uCi/sec)
                                                    ] y2. mrem /yr per uCi/sec)
F 0Fl if Y TAj+A ) m p w where: K' = a constant of unit conversion 106 pCi/uCi.QF = the cow's consumption rate, in kg/ day (wet weight).
Yp TAj+Aw ) m where:
K' = a constant of unit conversion 106 pCi/uCi.
QF = the cow's consumption rate, in kg/ day (wet weight).
Uap = The infant's milk consumption rate, in liters /yr.
Uap = The infant's milk consumption rate, in liters /yr.
2 Yp = the agricultural productivity by unit ared, in kg/m , F = the stable element transfer coefficients, in days / liter, m r = fraction of deposited activity retained on cow's feed grass.
Yp = the agricultural productivity by unit ared, in kg/m2 ,
Fm = the stable element transfer coefficients, in days / liter, r = fraction of deposited activity retained on cow's feed grass.
DFLj = the maximum organ ingestion dose factor for the ith radionuclide, in mrem /pCi.
DFLj = the maximum organ ingestion dose factor for the ith radionuclide, in mrem /pCi.
Aj = the decay constant for the ith radionuclide, in sec -1 Aw = the dacay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-time), tf = the transport time from pasture to cow, to milk, to infant, in sec.A fraction of the airborne deposition is captured by the ground plant vegetation cover.
Aj = the decay constant for the ith radionuclide, in sec -1 Aw = the dacay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-time),
The captured material is removed from the vegetation (grass) by both radiological decay and weathering p rocesses.
tf = the transport time from pasture to cow, to milk, to infant, in sec.
The values of QF, V o, and Y are provided in Regulatory Guide 1.109 a (Rev.1,10/77), Tables E-3,pE-5, and E-15, as 50 kg/ day, 330 liters / day and 0.7 kg/m2 respectively.
A fraction of the airborne deposition is captured by the ground plant vegetation cover.       The captured material is removed from the vegetation (grass) by both radiological decay and weathering p rocesses.
The value tf is provided in Regulatory Guide 1.109 (Rev.1,10/77), Table E-15, as 2 days (1.73 x 10 seconds).
The values of QF, Va o, and Y are provided in Regulatory Guide 1.109 (Rev.1,10/77), Tables E-3,pE-5, and E-15, as 50 kg/ day, 330 liters / day and 0.7 kg/m2 respectively. The value tf is provided in Regulatory Guide 1.109 (Rev.1,10/77), Table E-15, as 2 days (1.73 x 10 seconds). The fraction, r, has a value of 1.0 for radiciodines and o.2 for particulates, as presented in Regulatory Guide 1.109, (Rev. 1, 10/77), Table E-15.
The fraction, r, has a value of 1.0 for radiciodines and o.2 for particulates, as presented in Regulatory Guide 1.109, (Rev. 1, 10/77), Table E-15.
853 234
853 234  
 
-., Table E-1 of Regulatory Guide 1.109 (Rel,10/77) provides the stable element transfer coefficients, F , and Table E-14 provides the ingestion m dose factors, DFLj , for the infant's organs.
  -
The organ with the maximum value of DFLj is to be used.
    .
,
Table E-1 of Regulatory Guide 1.109 (Rel,10/77) provides the stable element transfer coefficients, F m, and Table E-14 provides the ingestion dose factors, DFLj , for the infant's organs. The organ with the maximum value of DFLj is to be used.
Resolut. ion of the units yields:
Resolut. ion of the units yields:
10 % DFLj[e-A t ](m . mrem /yr per uCi/sec) if 2 Pj (food) = 2.4 x 10 A 'A i w f;r all radionuclides, except tritium.
Pj (food) = 2.4 x 10 10 % DFLj[e-A if t ](m . 2mrem /yr per uCi/sec)
A i 'A w f;r all radionuclides, except tritium.
The concentration of tritium in milk is based on its airborne concentration rather than the deposition rate.
The concentration of tritium in milk is based on its airborne concentration rather than the deposition rate.
3 Pj = K'K"F 0 Um F apDFLj [0.75(0.5/H)] (mrem /yr per pCi/m )
Pj = K'K"F 0 Um F apDFLj [0.75(0.5/H)] (mrem /yr per pCi/m3 )
where: K'"= a constant of unit conversion,103 gm/kg.3 H = absolute humidity of the atmosphere, in gm/m , 0.75 = the fraction of total feed that is water.
where:
K'" = a constant of unit conversion,103 gm/kg.
H = absolute humidity of the atmosphere, in gm/m3 ,
0.75 = the fraction of total feed that is water.
0.5 = the ration of the specific activity of the feed fass water to the atmospheric water.
0.5 = the ration of the specific activity of the feed fass water to the atmospheric water.
From Table E-1 and E-14 of Regulatory Guide 1.lg9 (Rev.1,10/77), the values of F and DFLj for tritium are 1.0 x 10- day / liter and 3.08 x m 10-7 mrem per pC , respectively.
From Table E-1 and E-14 of Regulatory Guide 1.lg9 (Rev.1,10/77), the values of Fm and DFLj for tritium are 1.0 x 10- day / liter and 3.08 x 10-7 mrem per pC , respectively. Assuming an average ab. solute humidity of 8 grams / meter {, the resolution of units yields:
Assuming an average ab. solute humidity of 8 grams / meter {, the resolution of units yields:
Pi (food) = 2.4 x 103 mrem /yr per uCi/m3 for tritium, only.
Pi (food) = 2.4 x 103 mrem /yr per uCi/m3 for tritium, only.
853 235  
853     235
*..''5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose (Specification 4.11.2.2)
 
  *
        .
    .
      '
5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose
'
(Specification 4.11.2.2)
The air dose due to noble gases released in gaseous effluents from the site shall be limited during any calendar quarter to the following expressions:
The air dose due to noble gases released in gaseous effluents from the site shall be limited during any calendar quarter to the following expressions:
For gamma radiation:
For gamma radiation:
3.17 x 10-8 EMj ((x/Q) Qj + (x/q) gj) 15 mrad, and i for beta radiation:
3.17 x 10-8 EMj ((x/Q) Qj + (x/q) gj) 15 mrad, and i
3.17 x 10-8 I Nj ((x/Q) Qj + (x/q) gj) i 10 mrad i where: 3.17 x 10-8 = The inverse of the number of seconds in a year.
for beta radiation:
M j = The air dose factor due to gamma emissions for eagh identi-fied noble gas radionuclide, in mrad /yr per uCi/m f rom Table 4.11-3.Nj = The air dose factor due to beta emissions fog from Table each identified noble gas radionuclide, in mrad /yr per pCi/m 4.11-3.3 x/Q =sec/m .The highest calculated annual average relative concentration for any area at or beyond the exclusion area boundary for long term releases (greater than 500 hrs / year).
3.17 x 10-8 I Nj ((x/Q) Qj + (x/q) gj) i 10 mrad i
3 x/q =sec/m .The relative concentration for any area at or beyond the exclusion area boundary for short term releases (equal to or less than 500 hrs /yr).
where:
Qj = The release of noble gas radionuclides, i, in gaseous effluents, for long term releases (greater than 500 hrs /yr), in pCi.Releases shall be cumulative over the calendar qua rte r.
3.17 x 10-8 = The inverse of the number of seconds in a year.
M j = The air dose factor due to gamma emissions for eagh identi-fied noble gas radionuclide, in mrad /yr per uCi/m f rom Table 4.11-3.
each identified Nj = The nobleairgas dose factor due in radionuclide,  to mrad beta emissions   fog from Table
                                                                /yr per pCi/m 4.11-3.
x/Q =         sec/m3 . The highest calculated annual average relative concentration for any area at or beyond the exclusion area boundary for long term releases (greater than 500 hrs / year).
x/q =           sec/m3 . The relative concentration for any area at or beyond the exclusion area boundary for short term releases (equal to or less than 500 hrs /yr).
Qj = The release of noble gas radionuclides, i, in gaseous effluents, for long term releases (greater than 500 hrs /yr),
in pCi. Releases shall be cumulative over the calendar qua rte r.
qj = The release of noble gas radionuclides, i, in gaseous effluents, fer short term releases (equal to or less than 500 hrs /yr), in uCi. Releases shall be cumulative over the calendar quarter.
qj = The release of noble gas radionuclides, i, in gaseous effluents, fer short term releases (equal to or less than 500 hrs /yr), in uCi. Releases shall be cumulative over the calendar quarter.
853 236  
853       236
'5.4 Radioactive Gaseous Effluent Other than Noble Gas Cumulative Dose
 
*Specification 4.11.2.3)
  '
* 5.4 Radioactive Gaseous Effluent Other than Noble Gas Cumulative Dose Specification 4.11.2.3)
The dose to an individual from radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases in gaseous effluents released to unrestricted areas shall be limited during any calendar year to the following expression:
The dose to an individual from radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases in gaseous effluents released to unrestricted areas shall be limited during any calendar year to the following expression:
3.17 x 10-8 I Rj (W Qj + w gj ) f 7.5 mrem, and i where: 3.17 x 10-8 = The inverse of the number of seconds in a year.
3.17 x 10-8 I Rj (W Qj + w gj ) f 7.5 mrem, and i
Qj = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs /yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate, qj = The release of radiciodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for short tenn releases (equal to or less than 500 hrs /yr), in pCi .
where:
Releases shall be cumulative aver the calendar quarter or year as appropriate.
3.17 x 10-8 = The inverse of the number of seconds in a year.
Qj = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs /yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate, qj = The release of radiciodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for short tenn releases (equal to or less than 500 hrs /yr), in pCi . Releases shall be cumulative aver the calendar quarter or year as appropriate.
W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long tena releases (greater than 500 hrs /yr):
W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long tena releases (greater than 500 hrs /yr):
W=x/Q for the inhalation pathway, in sec/m3 f rom Table 4.11-6a.W=D/Q for the food and ground plane pathways, in meters-2 f rom Table 4.11-6b.
W= x/Q for the inhalation pathway, in sec/m3 f rom Table 4.11-6a.
w=The dispersion parameter for estimating the dose to at the controlling location for short term releases less than 500 hrs /yr):
W= D/Q for the food and ground plane pathways, in meters-2 f rom Table 4.11-6b.
w=x/q for the inhalation pathway, in sec/m3 from Table 4.11-6c.
w=   The dispersion parameter for estimating the dose to at the controlling location for short term releases less than 500 hrs /yr):
w=D/q for the food and ground plane pathway, in meters-2 from Table 4.11-6d.
w=   x/q for the inhalation pathway, in sec/m3 from Table 4.11-6c.
w=     D/q for the food and ground plane pathway, in meters-2 from Table 4.11-6d.
2 Rj = The dose factor for each identified radigriuclide, i, in m mrem /yr per uCi/sec or mrem /yr per pCi/m f rom Table 4/11-7.
2 Rj = The dose factor for each identified radigriuclide, i, in m mrem /yr per uCi/sec or mrem /yr per pCi/m f rom Table 4/11-7.
The dose factors are based on the most critical individual organ and most restrictive age group from historical dose calculations.
The dose factors are based on the most critical individual organ and most restrictive age group from historical dose calculations.
853 237  
853   237
..'For the direction sectors with existing pathways within 5 miles from
 
*the unit, use the values of Rj for these pathways.
  .   .
If no real pathway exists within 5 miles from the center of the building complex, use the cow-milk Rj assuming that this pathway exists at the 4.5 to 5.0 mile distance in the worst sector.
    '
If the Rj for an existing pathway within 5 miles is less than a cow-milk R at 4.5 to 5.0 miles, then use the 3 value of the cow-milk Rj at 4.5 to 5.0 miles. The values used for calculating dose contributions shall be consistent with the results of the land use census performed pursuant to Specification 3.12.2.
* For the direction sectors with existing pathways within 5 miles from the unit, use the values of Rj for these pathways. If no real pathway exists within 5 miles from the center of the building complex, use the cow-milk Rj assuming that this pathway exists at the 4.5 to 5.0 mile distance in the worst sector. If the Rj for an existing pathway within 5 miles is less than a cow-milk R at 4.5 to 5.0 miles, then use the 3
The controlling value for each radionuclide of Table 4.11-7 shall be determined and made effective within 30 days after the completion of each required land use census.
value of the cow-milk Rj at 4.5 to 5.0 miles. The values used for calculating dose contributions shall be consistent with the results of the land use census performed pursuant to Specification 3.12.2. The controlling value for each radionuclide of Table 4.11-7 shall be determined and made effective within 30 days after the completion of each required land use census.       The parameters W and w shall correspond to the applicable Rj for the same sector, pathway and location con <li ti on.
The parameters W and w shall correspond to the applicable Rj for the same sector, pathway and location con <li ti on.
SPECIAL NOTES:       (1) In all cases, the tritium mleases use the first W or w parameter, based on relative concentration (sec/m3 ). (2) All radiciodines are assumed to be released in elemental form. If analysis includes the capabiity of determining the elemental and nonelemental forms in all releases, the food pathway parameters may be adjusted accordingly.
SPECIAL NOTES:
In developing the Rj values, separate expressions are written for each of the potential pathways. These expressions are similar to those d veloped Rg[D/Q], R [x/Q], CR [D/Q], R',[D/Q] and RY[D/Q , where then Section 5.2 of gh
(1) In all cases, the tritium mleases use the first W 3 or w parameter, based on relative concentration (sec/m ).
: 1.                     1         1           1 superscripts G, I, C, M, and V refer to ground plane, inhalation, cow's milk, meat and vegetation, espectively. The ' argument' notation, [ ],
(2) All radiciodines are assumed to be released in elemental form.
indicates the appropriate dispersion parameter, W, to be applied with the Ri factor. Note that the argument is not included in the following expressions. In the case of tritium, the dispersion parameter, W, is always taken as (x/Q). The Rj parameter is independent of long-term or short-tenn releases.
If analysis includes the capabiity of determining the elemental and nonelemental forms in all releases, the food pathway parameters may be adjusted accordingly.
Inhalation Pathway Factor, RI [x/Q]
In developing the Rj values, separate expressions are written for each of the potential pathways.
1 RI [x/Q] = K'(BR)a (DFAj)a (mrem /yr per uCi/m3 )
These expressions are similar to those d veloped Rg[D/Q], R [x/Q], R [D/Q], R',[D/Q] and RY[D/Q , where then Section 5.2 of ghis manual for P , wl are denoted by C 1.1 1 1 superscripts G, I, C, M, and V refer to ground plane, inhalation, cow's milk, meat and vegetation, espectively.
1 where:
The ' argument' notation, [ ], indicates the appropriate dispersion parameter, W, to be applied with the Ri factor.
K' = a constant of unit conversion,10 6pCi/pCi.
Note that the argument is not included in the following expressions.
(BR)a = tge breathing rate of the receptor of age group (a), in m jyr.
In the case of tritium, the dispersion parameter, W, is always taken as (x/Q).
(DFA j )a = the maximum organ inhalation dose factor for the receptor of age group (a) for the ith radionuclide, in mrem /pCi. The total body is considered as an organ in the selection of (DFAj)a.
The Rj parameter is independent of long-term or short-tenn releases.
853     238
I Inhalation Pathway Factor, R [x/Q]
 
1 I 3 R [x/Q] = K'(BR)a (DFAj)a (mrem /yr per uCi/m )
  .
1 where: 6 K' = a constant of unit conversion,10 pCi/pCi.(BR)a = tge breathing rate of the receptor of age group (a), in m jyr.(DFA )a = the maximum organ inhalation dose factor for the receptor of j age group (a) for the ith radionuclide, in mrem /pCi.
-
The total body is considered as an organ in the selection of (DFAj)a.853 238  
* The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of Regulatory Guide 1.109 (Rev.1,10/77).
.The breathing rates (BR)a for the various age groups are tabulated below,*-as given in Table E-5 of Regulatory Guide 1.109 (Rev.1,10/77).
Age Group (a)             Breathing Rate (m3/yr)
Age Group (a)
Infant                           1400 Child                             3700 Teen                             8000 Adult                             8000 Inhalation dose factors (DFAj)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 (Rev.1,10/77).
Breathing Rate (m3/yr)
Ground Plane Pathway Factor, RG [D/Q]
Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAj)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 (Rev.1,10/77).
1 RG [D/Q] = K'K"(SF)DFGj[1-e-Ait)/Aj] (m2. mrem /yr per uCi/sec) 1 where:
G Ground Plane Pathway Factor, R [D/Q]
K' = a constant of unit conversion,106 pCi/uCi.
1 R [D/Q] = K'K"(SF)DFGj[1-e-Ait)/Aj] (m2. mrem /yr per uCi/sec)
G 1 where: K' = a constant of unit conversion,106 pCi/uCi.
X" = a constant of unit conversion, 8760 hr/ year.
X" = a constant of unit conversion, 8760 hr/ year.
Aj = the decay constant for the ith radionuclide, sec-1 t = the exposure tim, 4.73 x 108 sec (15 years).
Aj = the decay constant for the ith radionuclide, sec-1 t = the exposure tim, 4.73 x 108 sec (15 years).
Line 198: Line 307:
SF = the shielding factor (dimensionless).
SF = the shielding factor (dimensionless).
A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109 (Rev. I 10/77). A tabulation of DFGj values is presented in Table E-6 of Regulatory Guide 1.109.
A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109 (Rev. I 10/77). A tabulation of DFGj values is presented in Table E-6 of Regulatory Guide 1.109.
C Gra ss-Cow-M1i s Pathway Factor, R [D/Q]
Gra ss-Cow-M1i s Pathway Factor, RC [D/Q]
1 f fs (1-f fs)e-Ajt -
1 Q (Vap)                    f pfs (1-f pfs)e-Ajt i-C                      Fm( r)(DFLj )a                            e -Ajtf R [D/Q] = K'   F 1
Q (Vap)i p p C R [D/Q] = K' F Fm( r)(DFLj )a e -Ajtf 1 Aj+Aw Y Ys p (m2.;nrem/yr per pCi/sec)
Aj+Aw                         Yp          Ys
.where: K' = a constant unit conversion,106 pCi/pCi.
                                                          .
(m2.;nrem/yr per pCi/sec) where:
K' = a constant unit conversion,106 pCi/pCi.
QF = the cow's consumption rate, in kg/ day (wet weight).
QF = the cow's consumption rate, in kg/ day (wet weight).
Vap = the receptor's milk consumption rate for age (a), in liters /yr.
Vap = the receptor's milk consumption rate for age (a), in liters /yr.
Yp = the agricultural productivity by unit area of pasture feed grass, in kg/m2 Ys = the agricultural productivity by unit area of stored feed, in kg/m2 853 239  
Yp = the agricultural productivity by unit area of pasture feed grass, in kg/m2 Ys = the agricultural productivity by unit area of stored feed, in kg/m2 853       239
'F = tne stable element transfer ccefficients, in days / liter.
 
'm r = fraction of deposited activity retained on cow's feed grass.(DFLj)a = the maximum organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem /pCi.
  '
'
Fm= tne stable element transfer ccefficients, in days / liter.
r = fraction of deposited activity retained on cow's feed grass.
(DFLj)a = the maximum organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem /pCi.
Aj = the decay constant for the ith radionuclide, in sec-1 Aw = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec-1 (corresponding to a 14 day half-life).
Aj = the decay constant for the ith radionuclide, in sec-1 Aw = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec-1 (corresponding to a 14 day half-life).
tf = the transport time from pasture to cow, to milk, to mceptor, in sec.th = the transport time from pasture, to harvest, to cow, to milk, to receptor, in sec.
tf = the transport time from pasture to cow, to milk, to mceptor, in sec.
f = fraction of the year that the cow is on pasture p (dimensionless).
th = the transport time from pasture, to harvest, to cow, to milk, to receptor, in sec.
f = fraction of the cow feed that is pasture grass while the cow s is on pasture (dimensionless).
fp = fraction of the year that the cow is on pasture (dimensionless).
SPECIAL NOTE:
fs = fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless).
The above equation is applicable in the case that the milk animal is a goat.
SPECIAL NOTE:     The above equation is applicable in the case that the milk animal is a goat.
Milk cattle are considered to be fed from two potential sources, pasture grass and stored feeds.
Milk cattle are considered to be fed from two potential sources, pasture grass and stored feeds.       Following the development in Regulatory Guide 1.109 (Rev. 1, 10/77), the values of f and f will be considered unit /, in lieu of site specific information provid0d in the annual land census report by the licensee.
Following the development in Regulatory Guide 1.109 (Rev. 1, 10/77), the values of f and f will be considered unit /, in lieu of site specific information provid0d in the annual land census report by the licensee.Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109 (Rev. 1, 10/77).
Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109 (Rev. 1, 10/77). In the case that the milk animal is a goat, rather than a cow, refer to Regulatory Guide 1.109 for the appropriate parameter value;.
In the case that the milk animal is a goat, rather than a cow, refer to Regulatory Guide 1.109 for the appropriate parameter value;.
Table R.G. 1.109 Pa rameter                           Value                   Rev. 1, 10/77 r (dimensionless)             1.0 for radiciodine               E-15 0.2 for particulates             E-15 Fm (days / liter)             Each stable element               E-1 Vap (liters /yr)-Infant       330                               E-5
Table R.G. 1.109 Pa rameter Value Rev. 1, 10/77 r (dimensionless) 1.0 for radiciodine E-15 0.2 for particulates E-15 Fm (days / liter)
                            -Child     330                               E-5
Each stable element E-1 Vap (liters /yr)-Infant 330 E-5-Child 330 E-5-Teen 400 E-5-Adult 310 E-5 (DFL )a mrem /pCi)
                            -Teen     400                               E-5
Each radionuclide E-11 to E-14 j Y[((kg/m Y kg/m 0.7 E-15 2.0 E-15 seconds)1.73 x 105 (2 days)
                            -Adult     310                               E-5 (DFLj )a mrem /pCi)           Each radionuclide           E-11 to E-14 Y   kg/m                     0.7                               E-15 Y[((kg/m                      2.0                               E-15 t    seconds)                 1.73 x 105 (2 days)               E-15 t
E-15 f((seconds) t h 7.78 x 106 (90 days)
f((seconds) h QF (kg/ day) 7.78 x 106 (90 days) 50 E-15 E-3 The concentratica of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RC is based on [x/Q]:
E-15 t QF (kg/ day) 50 E-3 The concentratica of tritium in milk is based on the airborne concentration rather than the deposition.
1 853   240
Therefore, the RC is based on [x/Q]:
 
1 853 240 3'R [x/Q] = .''K"F 0 Um F ap(DFLj )a [0.75(0.5/H](mrem /yr per uCi/m )
  '
'where: 3 K'"= a constant of unit conversion,10 gm/kg.
'                                                                                        3 R [x/Q] = .''K"F 0 Um F ap(DFLj )a [0.75(0.5/H](mrem /yr per uCi/m )
3 H=absolute humidity of the atmosphere, in gm/m , 0.75 = the fraction of total feed that is water.
where:
3 K'" = a constant of unit conversion,10 gm/kg.
H=   absolute humidity of the atmosphere, in gm/m3 ,
0.75 = the fraction of total feed that is water.
0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.
0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.
and other parameters and va}ues am given above.
and other parameters and va}ues am given above.               The value of H may be considered as 8 grams / meter , in li tu of site specific informtion (Ref. 6).
The value of H may be considered as 8 grams / meter , in li tu of site specific informtion (Ref. 6).
Grass-Cow-Meat Pathway Factor, RSI[Df Q]
Grass-Cow-Meat Pathway Factor, RSI[Df Q]
1_The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:
1
Q (Vap)ff (1-f f )e-A tih ps ps e -A tif R$I[D/Q]=K' F F (r)(DFLj)a
_
_+f 1 Y Y Aj+Aw p s 2.-(m . mrem /yr per pCi/sec) where: Ff = the stable element transfer coefficients, in days /kg.
The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore:
Q (Vap)                       ff ps      (1-f ps f )e-A tih R$I[D/Q]=K'     F           Ff (r)(DFLj)a   _
                                                                    +                   e -A tif 1
Aj+Aw                           Y p           Y s
                                                          .                             -
(m2 . mrem /yr per pCi/sec) where:
Ff = the stable element transfer coefficients, in days /kg.
Uap = the receptor's meat consumption rate for age (a), in kg/yr.
Uap = the receptor's meat consumption rate for age (a), in kg/yr.
tf = the transport time from pasture to receptor, in sec.
tf = the transport time from pasture to receptor, in sec.
th = the transport time fram crop field to receptor, in sec.
th = the transport time fram crop field to receptor, in sec.
Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109 (Rev. 1, 10/77).
Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109 (Rev. 1, 10/77).
Table Pa rameter Valuq R.G. 1.109 Rev. 1, 10/77 r (dimensionless) 1.0 for radiciodine E-15 0.2 for particulates E-15 Ff (days / liter)
Table Pa rameter                               Valuq                         R.G. 1.109 Rev. 1, 10/77 r (dimensionless)             1.0 for radiciodine                       E-15 0.2 for particulates                       E-15 Ff (days / liter)             Each stable element                       E-1 Vap (kg/yr) - Infant         0                                         E-5
Each stable element E-1 Vap (kg/yr) - Infant 0 E Child 41 E Teen 65 E Adult 110 E-5 (DFL )a mrem /pCi)
                      - Child         41                                         E-5
Each radionuclide E-11 to E-14 j Yp (kg/m )
                      - Teen         65                                         E-5
0.7 E-15 Ys (kg/m )
                      - Adult         110                                       E-5 (DFLj )a mrem /pCi)           Each radionuclide                   E-11 to E-14 Yp (kg/m )                   0.7                                       E-15 Ys (kg/m )                   2.0                                       E-15 tf (seconds)                 1.73 x 106 (20 days)                       E-15 t                            7.78 x 106 (90 days)                       E-15 QFhfseconds) kg/ day)                 50                                         E-3 853       241
2.0 E-15 tf (seconds) 1.73 x 106 (20 days)
 
E-15 7.78 x 106 (90 days)
  *
E-15 hfseconds) t kg/ day)50 E-3 QF 853 241  
'
*The concentration of tritium in meat is based)on the airborne concentration
The ratherconcentration than the deposition. of tritium    in meat Therefore,         isbased the R is 1
'rather than the deposition.
based)on    the airborne concent on [x/Q]:
Therefore, the R is based on [x/Q]:
R [x/Q] = K'K"F fQp  Uap(DFLj)a [0.75(0.5/H](mrem /yr per uCi/m3 )
1 f U 3 R [x/Q] = K'K"F Qp ap(DFLj)a [0.75(0.5/H](mrem /yr per uCi/m )
where all terms are defined above and Section 5.2 of this manual.
where all terms are defined above and Section 5.2 of this manual.
VegetationPathwayFactor,FY[D/Q]
VegetationPathwayFactor,FY[D/Q]
1 The ictegrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor.
1 The ictegrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor.           Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:
Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:
                                -                   ~
-( r) ~~-Ajtl-At'ih S RY[D/Q)=K' Y (AjAw)(DFLj)a L Ufe Ufe l I a ag y.__2 (m . mrem /yr per uCi/sec) where: 6 K' = a constant of unit conversion,10 pCi/uCi.
( r) ~               -Ajtl       -At' ih L
UL = the consumption rate of fresh leafy vegetation by the a receptor in age group (a), in kg/yr.
RY[D/Q)=K' Yy(AjAw) (DFLj)a Ufe I                                   a l
US = the consumption rate of stored vegetation oy the receptor a in age group (a), in kg/yr.
S Ufe ag
                                          .       _                      _
(m2 . mrem /yr per uCi/sec) where:
K' = a constant of unit conversion,106 pCi/uCi.
UL = the consumption rate of fresh leafy vegetation by the a   receptor in age group (a), in kg/yr.
US = the consumption rate of stored vegetation oy the receptor a   in age group (a), in kg/yr.
fL = the fraction of the annual intake of fresh leafy vegetation grown locally.
fL = the fraction of the annual intake of fresh leafy vegetation grown locally.
fg = the fraction of the annual intake of stored vegetation grown locally.tl = the average time between harvest of leafy vegetation and its consumption, in seconds.
fg = the fraction of the annual intake of stored vegetation grown locally.
tl = the average time between harvest of leafy vegetation and its consumption, in seconds.
th = the average time between harvest of stored vegetation and its consumption, in seconds.
th = the average time between harvest of stored vegetation and its consumption, in seconds.
2 Y = the vegetation areal density, in kg/m .
Yy = the vegetation areal density, in kg/m2 .
y and all other factors are defined in Section 5.2 of this manual .
and all other factors are defined in Section 5.2 of this manual .
Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109 (Rev.1,1U/77).
Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109 (Rev.1,1U/77).
Table R.G. 1.109 Pa rameter Value Rev. 1, 10/77 r (dimensionless) 1.0 for radiciodine E-1 0.2 for particulates E-1 ()(mrem /pCi)
Table R.G. 1.109 Pa rameter                             Value                     Rev. 1, 10/77 r (dimensionless)               1.0 for radiciodine                 E-1 0.2 for particulates                 E-1
Each radionuclide E-11 to E-14 U{F kg)yr)-Infant 0 E-5 a-Child 26 E-5-Teen 42 E-5 8 5 3 242  
(     )   (mrem /pCi)           Each radionuclide             E-11 to E-14 U{F kg)yr)-Infant                 0                                   E-5 a           -Child             26                                   E-5
'-Adult 64 E-5'US (kg/yr)-Infant 0 E-5-Child 520 E-5-Teen 630 E-5-Adult 520 E-5 f (dimensionless) site specific (default = 1.0) f (dimensionless) site specific (default = 0.76) 4 E-15 t (seconds) 8.6x10{1 day) th (seconds) 5.18 x 10 (60 days)
                        -Teen             42 E-5 8 5 3 242
E-15 Yy (kg/m2) 2.0 E-15 The concentration of tritium in vegetation is based on the airborne
 
:oncentration rather than the deposition.
  '
Therefore, the RV is based on I[x/Q]: V l R [x/Q] = K'K' UfL+Ufg (DFLj )a [0.75(0.5/H)](mrem /yr per S pCi/m3), i a a where all tenns have been defined above and in Section 5.2 of this manual.
'
853 243  
                    -Adult         64                               E-5 US (kg/yr)-Infant         0                                 E-5
'5.5 Radioactive Gaseous Effluent Projected Dose (Specification 4.11.2.4.1)
                    -Child         520                               E-5
*The dose contributions shall be calculated for all radionuclides in gaseous effluents projected to be released to outside the exclusion area during any projected 31 day period using the following expressions:
                    -Teen           630                               E-5
                    -Adult         520                               E-5 f (dimensionless)         site specific (default = 1.0) f (dimensionless)         site specific (default = 0.76) 4                         E-15 t (seconds)               8.6x10{1   day) th (seconds)               5.18 x 10 (60 days)               E-15 Yy (kg/m2)                 2.0                               E-15 The concentration of tritium in vegetation is based on the airborne
:oncentration rather than the deposition. Therefore, the RV is based on I
[x/Q]:
RV [x/Q] = K'K'   l UfL+UfgS (DFLj )a [0.75(0.5/H)](mrem /yr per i                a    a                                pCi/m3),
where all tenns have been defined above and in Section 5.2 of this manual.
853 243
 
  '
* 5.5 Radioactive Gaseous Effluent Projected Dose (Specification 4.11.2.4.1)
The dose contributions shall be calculated for all radionuclides in gaseous effluents projected to be released to outside the exclusion area during any projected 31 day period using the following expressions:
For noble gases, the gamma radiation:
For noble gases, the gamma radiation:
3.17 x 10-8 Mj ( (x/Q) Qj + (x/q) gj ) 10.05 mrad, and For noble gases, the beta radiation:
3.17 x 10-8     Mj ( (x/Q) Qj + (x/q) gj ) 10.05 mrad, and For noble gases, the beta radiation:
3.17 x 10-8 tij ( (x/Q) Qj + (x/q) gj) 10.10 mrad, and i For radioiodines, radioactive materials in particulate form and radio-nuclides other than noble gases:
3.17 x 10-8     tij ( (x/Q) Qj + (x/q) gj) 10.10 mrad, and i
3.17 x 10-8 Rj (W Qj + w gj ) 10.075 mrem where: Qj = The projected release over the next 7 days of radionuclides, i, in gaseous effluents for long term releases (greater than 500 hrs /yr), in pCi .
For radioiodines, radioactive materials in particulate form and radio-nuclides other than noble gases:
3.17 x 10-8     Rj (W Qj + w gj ) 10.075 mrem where:
Qj = The projected release over the next 7 days of radionuclides, i, in gaseous effluents for long term releases (greater than 500 hrs /yr), in pCi .
qj = The projected release over the next 7 days of radionuclides, i, in gaseous effluents for short tenn releases (equal to or less than 500 hrs /yr), in pCi .
qj = The projected release over the next 7 days of radionuclides, i, in gaseous effluents for short tenn releases (equal to or less than 500 hrs /yr), in pCi .
and all other terms are defined in Sections 5.3 and 5.4.
and all other terms are defined in Sections 5.3 and 5.4.
853 244 1
1 853 244
.TABLE 5.1-1
 
-.DOSE FACTORS FOR NOBLE GASES AND DAUGilTERS
                                                                                                                    .
,.Tota! Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K-L-M-N-3 3 3 3 Radionuclide (mrem /yr per pCi/m 1 (mrem /yr per pCi/m 1 (mrad /yr per pCi/m 1 (mrad /yr p r pCi/m 1 Ar-41 8.84E+03 2.6aE+03 9.30E403 3.28E403 K r-89n 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E403 1.72E+01 1.95E+03 K r-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 K r-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-13 5m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E404 Xe-138 8.83E+03 4.13E+03 9.21E403 4.75E+03 co LD U N 5::=LJ"I  
TABLE 5.1-1                                                   -
...TABLE 5.2-1
                                                                                                                      .
-DOSE PARAMETERS FOR RADIGICDINES, RADI0 ACTIVE MATERIAL IN
DOSE FACTORS FOR NOBLE GASES AND DAUGilTERS               ,
'PARTICULATE FORM AND RADIONUCLIDES OTHER TilAN NOBLE GASES IN GASEOUS EFFLUENTS Pj Pj Pj Pj Radio-InhalationPathwag Fogd and Ground Pathways Radio-InhalationPathwag Fgod a Ground Pathways (mrem /yr per pCi/m 1 nuclide_(m . mrem /yr per pCi/sec) nuclide (mrem /yr per pCi/m 1 im . mrem /yr per pCi/sec)
                                                                                                .
_11 - 3 6.5E+02 2.4E+03 Sb-125 1.5E+04 1.1E+09 P-32 2.0E+06 1.5E+11 Te-127m 3.8E+04 7.4E+10 Mn-54 2.5E404 1.lE+09 Te-129m 3.2E+04 1.3E+09 Fe-59 2.4E+04 7.0E+08 I-131 1.5E+07 1.lE+12 Co-58 1.lE+04 5.7E+08 1-132 Co-60 3.2E+04 4.6E+09 I-133 3.6E+06 9.6E+09 Zn-65 6.3E+04 1.7E+10 I-134 Rb-88 I-135 Rb-89 Cs-134 7.0E+05 5.3E+10 Sr-89 4.0E+05 1.0E+10 Cs-136 1.3E+05 5.4E+09 Sr-90 4.lE+07 9.5E+10 Cs-137 6.lE+05 4.7E+10 Z r-95 2.2E+04 3.5E+08 Ba-140 5.6E+04 2.4E+08'c)1.3E+04 3.6Et08 La-140 Nb-95 ta Cd-119n 7.0E404 4.8E+07 Ce-141 2.2E+04 8.7E+07 Sn-123 Ps) 2.9E+05 3.4E409 Ce-144 1.5E+05 6.5E+08 n c7'Sn-126 l.2E+06 1.lE+09 Unidenti fied ** 4.lE+07 9.5E+10*ITf Sr-90 analysis is performed, use Pj given in Ru-106 for unidentified components.
Tota! Body                                           Gamma Air               Beta Air Dose Factor             Skin Dose Factor           Dose Factor           Dose Factor K-                         L-                       M-                     N-Radionuclide (mrem /yr per pCi/m31      (mrem /yr per pCi/m3 1   (mrad /yr per pCi/m3 1 (mrad /yr p r pCi/m31 Ar-41           8.84E+03                   2.6aE+03                 9.30E403               3.28E403 K r-89n         1.17E+03                   1.46E+03                 1.23E+03               1.97E+03 Kr-85           1.61E+01                   1.34E403                 1.72E+01               1.95E+03 K r-87         5.92E+03                   9.73E+03                 6.17E+03               1.03E+04 Kr-88           1.47E+04                   2.37E+03                 1.52E+04               2.93E+03 K r-89           1.66E+04                   1.01E+04                 1.73E+04               1.06E+04 Xe-131m         9.15E+01                   4.76E+02                 1.56E+02               1.11E+03 Xe-133m         2.51E+02                   9.94E+02                 3.27E+02               1.48E+03 Xe-133         2.94E+02                   3.06E+02                 3.53E+02               1.05E+03 Xe-13 5m       3.12E+03                   7.11E+02                 3.36E+03               7.39E+02 Xe-135         1.81E+03                   1.86E+03                 1.92E+03               2.46E+03 Xe-137         1.42E+03                   1.22E+04                 1.51E+03               1.27E404 Xe-138         8.83E+03                   4.13E+03                 9.21E403               4.75E+03 co LD U
N 5::=
LJ"I
 
                                                                                                                                  .
                                                                                                                                          .
                                                                                                                                      .
TABLE 5.2-1                                                         -
                                                                                                                                        '
DOSE PARAMETERS FOR RADIGICDINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER TilAN NOBLE GASES IN GASEOUS EFFLUENTS Pj                         Pj                                   Pj                     Pj Radio-       InhalationPathwag                                       Radio-Fogd and Ground Pathways                 InhalationPathwag     Fgod a Ground Pathways nuclide      (mrem /yr per pCi/m 1   _(m . mrem /yr per pCi/sec) nuclide     (mrem /yr per pCi/m 1
_
im . mrem /yr per pCi/sec) 11 - 3             6.5E+02                     2.4E+03             Sb-125           1.5E+04                 1.1E+09 P-32               2.0E+06                     1.5E+11             Te-127m           3.8E+04                 7.4E+10 Mn-54               2.5E404                     1.lE+09             Te-129m           3.2E+04                 1.3E+09 Fe-59             2.4E+04                     7.0E+08               I-131           1.5E+07                 1.lE+12 Co-58               1.lE+04                     5.7E+08               1-132 Co-60               3.2E+04                     4.6E+09             I-133             3.6E+06                 9.6E+09 Zn-65             6.3E+04                     1.7E+10             I-134 Rb-88                                                               I-135 Rb-89                                                               Cs-134           7.0E+05                 5.3E+10 Sr-89             4.0E+05                     1.0E+10             Cs-136           1.3E+05                 5.4E+09 Sr-90             4.lE+07                     9.5E+10             Cs-137           6.lE+05                 4.7E+10
            '
Z r-95             2.2E+04                     3.5E+08             Ba-140           5.6E+04                 2.4E+08 Nb-95        c)   1.3E+04                     3.6Et08             La-140 ta Cd-119n           7.0E404                     4.8E+07             Ce-141           2.2E+04                 8.7E+07 Sn-123       Ps) 2.9E+05                       3.4E409             Ce-144           1.5E+05                 6.5E+08 n
c7' Sn-126             l.2E+06                     1.lE+09             Unidenti fied ** 4.lE+07                 9.5E+10
*ITf Sr-90 analysis is performed, use Pj given in Ru-106 for unidentified components.
If Sr-90 and Ru-106 analyses are performed, use Pj given in I-131 for unidentified components.
If Sr-90 and Ru-106 analyses are performed, use Pj given in I-131 for unidentified components.
If Sr-90, Ru-106 and I-131 analyses are performed, use Pj given in P-32 for unidentified components.  
If Sr-90, Ru-106 and I-131 analyses are performed, use Pj given in P-32 for unidentified components.
.'TABLE 5.1-2
 
-DISPERSION PARAMETER (i7Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 llR/QTR
                                                                                                              .
.Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 2.3E-06 8.2E-L/3.6E-07 2.1E-07 1.3E-07 9.6E-08 7.3E-08 5.7E-08 4.7E-08 NNE N/A 2.3E-06 8.1E-07 3.6E-07 2.0E-07 1.3E-07 9.5E-08 7.1E-08 5.6E-08 4.6E-08 NE N/A 2.9E-06 1.0E-06 4.3E-07 2.5E-07 1.6E-07 1.lE-07 8.6E-08 6.7E-08 5.5E-08 ENE N/A 3.4E-06 1.2E-06 5.1E-07 2.9E-07 1.9E-07 1.3E-07 1.0E-07 7.9E-08 6.4E-08 E N/A N/A 1.4E-06 6.0E-07 3.4E-07 2.2E-07 1.6E-07 1.2E-07 9.2E-08 7.5E-08 ESE N/A N/A 1.2E-06 5.4E-07 3.1E-07 2.0E-07 1.4E-07 1.1E-07 8.6E-08 7.0E-08 SE N/A N/A N/A 4.3E-07 2.5E-07 1.6E-07 1.2E-07 8.9E-08 7.0E-08 5.7E-08 SSE N/A N/A N/A 3.8E-07 2.2E-07 1.4E-07 1.0E-07 7.9E-08 6.2E-08 5.lE-08 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A U N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A co NU LJ'N/A N/A 2.3E-06 1.0E-06 6.lE-07 4.lE-07 2.9E-07 2.3E-07 1.8E-07 1.5E-07 u NNW N/A 3.4E-06 1.2E-06 5.4E-07 3.1E-07 2.0E-07 1.5E-07 1.lE-07 8.8E-08 7.2E-08 N-P-N  
                                                                                                                    '
.TABLE 5.1-3
TABLE 5.1-2                                                   -
-DISPERSION PARAMETER (D/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR
DISPERSION PARAMETER (i7Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 llR/QTR
,*Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 2.3E-06 8.2E-07 3.6E-07 2.1E-07 1.3E-07 9.6E-08 7.3E-08 5.7E-08 4.7E-08 NNE N/A 2.3E-06 8.lE-07 3.6E-07 2.0E-07 1.3E-07 9.5E-08 7.lE-08 5.6E-08 4.6E-08 NE N/A 2.9E-06 1.0E-06 4.3E-07 2.5E-07 1.6E-07 1.1E-07 8.6E-08 6.7E-08 5.5E-08 ENE N/A 3.4E-06 1.2E-06 5.lE-07 2.9E-07 1.9E-07 1.3E-07 1.0E-07 7.9E-08 6.4E-08 E N/A N/A 1.4E-06 6.0E-07 3.4E-07 2.2E-07 1.6E-07 1.2E-07 9.2E-08 7.5E-08 ESE N/A N/A 1.2E-06 5.4E-07 3.lE-07 2.0E-07 1.4E-07 1.1E-07 8.6E-08 7.0E-08 SE N/A N/A N/A 4.3E-07 2.5E-07 1.6E-07 1.2E-07 8.9E-08 7.0E-08 5.7E-08 SSE N/A N/A N/A 3.8E-07 2.2E-07 1.4E-07 1.0E-07 7.9E-08 6.2E-08 5.lE-08 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A NW N/A N/A 2.3E-06 1.0E-06 6.lE-07 4.1E-07 2.9E-07 2.3E-07 1.8E-07 1.5E-07[jk NNW N/A 3.4E-06 1.2E-06 5.4E-07 3.lE-07 2.0E-07 1.5E-07 1.1E-07 8.8E-08 7.2E-08 w N.P.CO  
                                                                                                                  .
.TABLE 5.1-4 2''DISPERSION PARAMETER (x/q) FOR SHORT TERM RELEASES < 500 HR/YR OR < 125 HR/QTR
Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0   1.0-1.5   1.5-2.0     2.0-2.5   2.5-3.0   3.0-3.5     3.5-4.0     4.0-4.5 4.5-5.0 N       N/A 2.3E-06   8.2E-L/   3.6E-07       2.1E-07   1.3E-07   9.6E-08     7.3E-08     5.7E-08 4.7E-08 NNE       N/A 2.3E-06   8.1E-07   3.6E-07       2.0E-07   1.3E-07   9.5E-08     7.1E-08     5.6E-08 4.6E-08 NE         N/A 2.9E-06   1.0E-06 4.3E-07       2.5E-07   1.6E-07   1.lE-07   8.6E-08     6.7E-08 5.5E-08 ENE         N/A 3.4E-06   1.2E-06 5.1E-07       2.9E-07   1.9E-07   1.3E-07     1.0E-07     7.9E-08 6.4E-08 E         N/A     N/A     1.4E-06 6.0E-07       3.4E-07   2.2E-07   1.6E-07     1.2E-07     9.2E-08 7.5E-08 ESE         N/A     N/A   1.2E-06   5.4E-07       3.1E-07   2.0E-07   1.4E-07     1.1E-07     8.6E-08 7.0E-08 SE         N/A     N/A       N/A   4.3E-07       2.5E-07   1.6E-07   1.2E-07   8.9E-08     7.0E-08 5.7E-08 SSE         N/A     N/A       N/A   3.8E-07       2.2E-07   1.4E-07   1.0E-07   7.9E-08     6.2E-08 5.lE-08 S         N/A     N/A       N/A       N/A         N/A         N/A     N/A         N/A         N/A     N/A SSW         N/A     N/A       N/A       N/A         N/A         N/A     N/A         N/A         N/A     N/A SW         N/A   N/A       N/A       N/A         N/A         N/A     N/A         N/A         N/A     N/A WSW         N/A   N/A       N/A       N/A         N/A         N/A     N/A         N/A         N/A     N/A U         N/A   N/A       N/A       N/A         N/A         N/A     N/A         N/A         N/A     N/A WNW         N/A   N/A       N/A       N/A         N/A         N/A     N/A         N/A         N/A     N/A co NU   LJ'   N/A   N/A     2.3E-06   1.0E-06     6.lE-07     4.lE-07   2.9E-07   2.3E-07     1.8E-07 1.5E-07 u
.Distance to the control location, in miles
NNW         N/A 3.4E-06   1.2E-06   5.4E-07     3.1E-07     2.0E-07   1.5E-07   1.lE-07     8.8E-08 7.2E-08 N
{3.5-4.0 Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 4.0-4.5 4.5-5.0 N N/A 1.5E-08 4.9E-09 1.9E-09 1.0E-09 6.3E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 NNE N/A 1.8E-08 5.7E-09 2.3E-09 1.2E-09 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.1E-10 NE N/A 2.0E-08 6.4E-09 2.5E-09 1.3E-09 8.2E-10 5.5E-10 4.0E-10 3.0E-16 2.3E-10 ENE N/A 2.5E-08 8.2E-09 3.2E-09 1.7E-09 1.0E-09 7.lE-10 5.lE-10 3.8E-10' 0E-10.E N/A N/A 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.0E-09 7.2E-10 5.4E-10 4.2E-10 ESE N/A N/A 9.1E-09 3.6E-09 1.9E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.3E-10 SE N/A N/A N/A 2.lE-09 1.1E-09 6.8E-10 4.6E-10 3.3E-10 2.5E-10 1.9E-10 SSE N/A N/A N/A 1.5E-09 8.0E-10 4.9E-10 3.3E-10 2.4E-10 1.8E-10 1.4E-10 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNU N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A co NW N/A N/A 7.lE-09 2.8E-09 1.5E-09 9.0E-10 6.lE-10 4.4E-10 3.3E-10 2.6E-10 LT.''d NNW N/A 1.5E-08 4.8E-09 1.9E-09 1.0E-09 6.2E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 N&W  
      -P-N
.TABLE 5.1-5
 
.'DISPERSION PARAMETER (D/q) FOR S110RT TERM RELEASES < 500 HR/YR OR < 125 ilR/QTR
                                                                                                                  .
-_Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 1.5E-08 4.9E-09 1.9E-09 1.0E-09 6.3E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 NNE N/A 1.8E-08 5.7E-09 2.3E-09 1.2E-09 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.lE-10 NE N/A 2.0E-08 6.4E-09 2.5E-09 1.3E-09 8.2E-10 5.5E-10 4.0E-10 3.0E-10 2.3E-10 ENE N/A 2.5E-08 8.2E-09 3.2E-09 1.7E-09 1.0E-09 7.1E-10 5.iE-10 3.8E-10 3.0E-10 E N/A N/A 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.0E-09 7.2E-10 5.4E-10 4.2E-10 ESE N/A N/A 9.lE-09 3.6E-09 1.9E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.3E-10 SE N/A N/A N/A 2.lE-09 1.1E-09 6.8E-10 4.6E-10 3.3E-10 2.5E-10 1.9E-10 SSE N/A N/A N/A 1.5E-09 8.0E-10 4.9E-10 3.3E-10 2.4E-10 1.8E-10 1.4E-10 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A s.'SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A cy3 NW N/A N/A 7.lE-09 2.8E-09 1.5E-09 9.0E-10 6.lE-10 4.4E-10 3.3E-10 2.6E-10 LJ7 L/4 NNW N/A 1.5E-08 4.8E-09 1.9E-09 1.0E-09 6.2E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 N LD C3  
TABLE 5.1-3                                                 -
..TABLE 5.4-1
* DISPERSION PARAMETER (D/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR                   ,
-PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES
Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0   1.0-1.5   1.5-2.0     2.0-2.5     2.5-3.0 3.0-3.5     3.5-4.0   4.0-4.5 4.5-5.0 N       N/A   2.3E-06   8.2E-07   3.6E-07     2.1E-07     1.3E-07 9.6E-08     7.3E-08   5.7E-08 4.7E-08 NNE       N/A   2.3E-06   8.lE-07   3.6E-07     2.0E-07     1.3E-07 9.5E-08     7.lE-08   5.6E-08 4.6E-08 NE       N/A 2.9E-06     1.0E-06 4.3E-07       2.5E-07     1.6E-07 1.1E-07     8.6E-08   6.7E-08 5.5E-08 ENE       N/A 3.4E-06     1.2E-06 5.lE-07       2.9E-07   1.9E-07   1.3E-07     1.0E-07   7.9E-08 6.4E-08 E       N/A     N/A     1.4E-06 6.0E-07       3.4E-07   2.2E-07   1.6E-07     1.2E-07   9.2E-08 7.5E-08 ESE       N/A     N/A     1.2E-06   5.4E-07       3.lE-07   2.0E-07   1.4E-07     1.1E-07   8.6E-08 7.0E-08 SE         N/A     N/A       N/A   4.3E-07       2.5E-07   1.6E-07   1.2E-07     8.9E-08   7.0E-08 5.7E-08 SSE       N/A     N/A       N/A   3.8E-07     2.2E-07     1.4E-07   1.0E-07     7.9E-08   6.2E-08 5.lE-08 S       N/A     N/A       N/A       N/A         N/A         N/A     N/A         N/A       N/A     N/A SSW       N/A     N/A       N/A       N/A         N/A         N/A     N/A         N/A       N/A     N/A SW       N/A     N/A       N/A       N/A         N/A         N/A     N/A         N/A       N/A     N/A WSW       N/A     N/A       N/A       N/A         N/A         N/A     N/A         N/A       N/A     N/A W       N/A     N/A       N/A       N/A         N/A         N/A     N/A         N/A       N/A     N/A WNW       N/A     N/A       N/A       N/A         N/A         N/A     N/A         N/A       N/A     N/A NW       N/A     N/A     2.3E-06   1.0E-06     6.lE-07     4.1E-07   2.9E-07   2.3E-07     1.8E-07 1.5E-07
-, Inhalation Meat Ground Plane Cow-Milk-Infant Leafy Vegetables Pathway Pathway Pathway Pathway Pathway R-R-R-Rj 2 2 2 2 Radio-(mrem /yr (m . mrem /yr (m . mrem /yr (m . mrem /yr (m . mrem /yr nucliae per pCi/mh per pCi/sec) per pCi/sec) per pCi/sec) per pCi/sec)
[jk NNW       N/A   3.4E-06   1.2E-06   5.4E-07     3.lE-07     2.0E-07   1.5E-07     1.1E-07   8.8E-08 7.2E-08 w
.LD tr4 N tri_
N
,..''6.0 Radiological Environmental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b)
.P.
..4%i s-k f'l'r .$%\i., t.t s%'T\s 1%. '' 'e.g.'J\r T s'- s/m I k 4,\%t ', 4 s\e'.4~853 252 L.
CO
'' '7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports Specification 6.9.1.91  
 
..'' '8.0 Revisions to the ODCM (Specification 6.14.2)
                                                                                                                  .
'Changes to the ODCM shall be made by the following method:
                                                                                                                        '
1.Shall be submitted to the Comnission by inclusion in the Monthly Operating Report within 90 days in which the change (s) was made effective and shall contain:
2 TABLE 5.1-4
a.sufficiently detailed information to totally support the rationale for the change without berefit of additional or supplemental information.
                                                                                                                    '
Infonnation submitted should consist of a package of those pages of 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
DISPERSION PARAMETER (x/q) FOR SHORT TERM RELEASES < 500 HR/YR OR < 125 HR/QTR
b.a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint detenninations; and c.documentation of the fact that the change has been reviewed by the PRC and approved by the Plant Manager.
                                                                                                                      .
2.Shall become effective upon review by the PRC and approval by the Plant Manager.
Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0   1.0-1.5 1.5-2.0       2.0-2.5   2.5-3.0   3.0-3.5                 4.0-4.5 4.5-5.0
{3.5-4.0 N       N/A 1.5E-08   4.9E-09 1.9E-09       1.0E-09   6.3E-10   4.2E-10     3.0E-10     2.3E-10 1.8E-10 NNE       N/A 1.8E-08   5.7E-09 2.3E-09       1.2E-09   7.3E-10   4.9E-10     3.6E-10     2.7E-10 2.1E-10 NE       N/A 2.0E-08   6.4E-09 2.5E-09       1.3E-09   8.2E-10   5.5E-10     4.0E-10     3.0E-16 2.3E-10 ENE       N/A 2.5E-08   8.2E-09   3.2E-09       1.7E-09   1.0E-09   7.lE-10     5.lE-10     3.8E-10 ' 0E-10
                                                                                                            .
E       N/A     N/A     1.2E-08 4.6E-09       2.4E-09   1.5E-09   1.0E-09     7.2E-10     5.4E-10 4.2E-10 ESE       N/A   N/A     9.1E-09   3.6E-09       1.9E-09   1.2E-09   7.9E-10     5.7E-10     4.3E-10 3.3E-10 SE       N/A   N/A       N/A   2.lE-09       1.1E-09   6.8E-10   4.6E-10     3.3E-10     2.5E-10 1.9E-10 SSE       N/A   N/A       N/A   1.5E-09       8.0E-10   4.9E-10   3.3E-10     2.4E-10     1.8E-10 1.4E-10 S       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A       N/A SSW       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A       N/A SW       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A       N/A WSW       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A       N/A W       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A       N/A WNU       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A       N/A co NW       N/A   N/A     7.lE-09   2.8E-09       1.5E-09   9.0E-10   6.lE-10     4.4E-10     3.3E-10 2.6E-10 LT.
''d NNW       N/A 1.5E-08   4.8E-09   1.9E-09       1.0E-09   6.2E-10   4.2E-10     3.0E-10     2.3E-10 1.8E-10 N
&
W
 
                                                                                                                  .
TABLE 5.1-5                                                   .'
DISPERSION PARAMETER (D/q) FOR S110RT TERM RELEASES < 500 HR/YR OR < 125 ilR/QTR
_
                                                                                                                    -
Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0   1.0-1.5 1.5-2.0       2.0-2.5   2.5-3.0   3.0-3.5     3.5-4.0     4.0-4.5 4.5-5.0 N     N/A 1.5E-08   4.9E-09 1.9E-09       1.0E-09   6.3E-10   4.2E-10     3.0E-10     2.3E-10 1.8E-10 NNE       N/A 1.8E-08   5.7E-09 2.3E-09       1.2E-09   7.3E-10   4.9E-10     3.6E-10     2.7E-10 2.lE-10 NE       N/A 2.0E-08   6.4E-09 2.5E-09       1.3E-09   8.2E-10   5.5E-10     4.0E-10     3.0E-10 2.3E-10 ENE       N/A 2.5E-08   8.2E-09   3.2E-09       1.7E-09   1.0E-09   7.1E-10     5.iE-10     3.8E-10 3.0E-10 E       N/A     N/A     1.2E-08 4.6E-09       2.4E-09   1.5E-09   1.0E-09     7.2E-10     5.4E-10 4.2E-10 ESE       N/A   N/A     9.lE-09   3.6E-09       1.9E-09   1.2E-09   7.9E-10     5.7E-10     4.3E-10 3.3E-10 SE         N/A   N/A       N/A   2.lE-09       1.1E-09   6.8E-10   4.6E-10     3.3E-10     2.5E-10 1.9E-10 SSE       N/A   N/A       N/A   1.5E-09       8.0E-10   4.9E-10   3.3E-10     2.4E-10     1.8E-10 1.4E-10 S       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A     N/A SSW       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A     N/A SW         N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A     N/A s.'SW     N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A     N/A W       N/A   N/A       N/A       N/A         N/A       N/A       N/A         N/A         N/A     N/A WNW       N/A   N/A       N/A     N/A           N/A       N/A       N/A         N/A         N/A     N/A cy3 NW       N/A     N/A     7.lE-09   2.8E-09       1.5E-09   9.0E-10   6.lE-10     4.4E-10     3.3E-10 2.6E-10 LJ7 L/4 NNW       N/A   1.5E-08   4.8E-09   1.9E-09       1.0E-09   6.2E-10   4.2E-10     3.0E-10     2.3E-10 1.8E-10 N
LD C3
 
                                                                                                .
                                                                                                        .
TABLE 5.4-1                                           -
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES                     ,
                                                                                                      -
Inhalation       Meat           Ground Plane   Cow-Milk-Infant Leafy Vegetables Pathway       Pathway             Pathway       Pathway             Pathway R-               R-                 R-             Rj Radio- (mrem /yr       (m2. mrem /yr     (m2. mrem /yr   (m2. mrem /yr   (m2. mrem /yr nucliae per pCi/mh     per pCi/sec)     per pCi/sec)     per pCi/sec)     per pCi/sec)
.
LD tr4 N
tri
_
 
                                                                                                                          ,
        .           .
              '
          '
6.0 Radiological Environmental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b)
      ..
4
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L                                                          .                        853 252
 
    '
' '
7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports Specification 6.9.1.91
 
      .
  .
  '' '
'
8.0 Revisions to the ODCM (Specification 6.14.2)
Changes to the ODCM shall be made by the following method:
: 1. Shall be submitted to the Comnission by inclusion in the Monthly Operating Report within 90 days in which the change (s) was made effective and shall contain:
: a. sufficiently detailed information to totally support the rationale for the change without berefit of additional or supplemental information. Infonnation submitted should consist of a package of those pages of 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
: b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint detenninations; and
: c. documentation of the fact that the change has been reviewed by the PRC and approved by the Plant Manager.
: 2. Shall become effective upon review by the PRC and approval by the Plant Manager.
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Revision as of 15:38, 19 October 2019

Draft Offsite Dose Calculation Manual
ML19207B465
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/19/1979
From:
FLORIDA POWER CORP.
To:
Shared Package
ML19207B461 List:
References
NUDOCS 7908290506
Download: ML19207B465 (34)
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DRAFT OF CRYSTAL RIVER - UtilT 3 0FFSITE DOSE CALCULATI0t1 fMfiUAL APRIL 19, 1979 (for use with Draft of Crystal River - Unit 3 Technical Specifications, April 19,1979, Based on NUREG-0472, Revision 2, February 1978)

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TABLE OF CONTENTS 1.0 Introduction 2.0 Radioactive Liquid Effluent Instrumtr.t ? tion Setpoints (Speci fication 3.3.3.8) 3.0 Radioactive Gaseous Process and Effluent Instrumentation Setpoints (Specification 3.3.3.9) 4.0 Radioactive Liquid Effluent Releases and Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) 4.2 Radioactive Liquid Effluent Projected Dose (Specification 4.11.1.3) 5.0 Radioactive Gaseous Effluent Dose Caiculations 5.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1) 5.2 Radioactive Gaseous Effluent Other Than Noble Gas Dose Rate (Speci fIcation 4.11.2.1.4) 5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose (Speci fication 4.11.2.2) 5.4 Radioactive Gaseous Effluent Other Than Noble Gas Cumulative Dose (Specification 4.11.2.3) 5.5 Radioactive Gaseous Effluent Projected Dose (Speci fica tion 4.11.2.4.1) 6.0 Radiological Environnental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b) 7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports (Specification 6.9.1.9) 8.0 Revisions to the ODCM (Specification 6.14.2) 853 222

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1.0 Introduction This Offsite Dose Calculation Manual (0DCM) describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable Limiting Conditions for Operation (LCOs) contained in the Appendix A Technical Specifications for Crystal River Unit 3, 853 223

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2.0 Radficactive_ Liqui.d Ef fluent Instrumentation Setpoint Specification 3.3.3.G 3.0 Radoiactive Gaseous Process and Effluent Instrumentation Setpoints Specification 3.3.3.9)

The radiological effluent Technical Specifications require alann/ trip setpoints fer radiation monitors and flow measurement devices for each

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effinc ut line. Mpoint values are to be calculated to assure that alani and trip actions occur prior to exceeding the limits of 10 CFR 20 a? the release point to the unrestricted area. The calculated alann and trip action setpoints to be specified in the ODCM for each radioactive liquid effluent line monitor and flow measurement device must satisfy the following equation:

cf Rf $ C where:

C= the cffluent concentration limit (Specification 3.11.1) implementing 10 CFR 20 for the site, in uCi/ml c= The setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentracion in the effluent line prior tc dilution and subsequent reiease; the setpoint, which is propo.-tional to the volumetric flow of the effluent line and inversely proportional to the volumetric flow of the dilution stream plus the effTuent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the unrestricted area f= the flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below F= the dilution water flow setpoint as measured prior to the release point, in volume.per unit time.

(Note that if no dilution is pruided, c 1 C. Also, note that when (F) is large compared to (f), then F+f 2 F.)

The equation is satisfied when the following alarm / trip setpoints are provided for each effluent line in the ODCM:

f 1[F_ (in ml/sec; for example),

c F1 (in ml/sec; for example).

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cf (in uCi/ml; for example).

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Scme plants may be operated using a fixea value for or re of these three variables, c, f or F.

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Eg mple 1 By using a constant capacity radwaste system discharge pump (on the undiluted stream) the value of (f) is fixed; therefore, the setpoints to be given are:

f= ml/sec (fixed)

F> ml/sec = cf/C c= xF uCi/ml I CF/f If c = 3x10-8 pCi/ml, f = 4000 ml/sec and F > 4x106 ml/sec, the radiation monitor setpoint is calculated as follows:

c 1 CF/f

,(3x10-81F = 7.5x10-12F pCi/ml.

4000-If F is measured at some value in excess of the limiting value (the 6

limiting value is 4x10 ml/sec in this exgmple), then c may be established proportionately. If F = 8x10 ml/sec, the alarm setpoint is:

c = 7.5x10-12F (uCi/ml per ml/sec)(ml/sec)

= 7.5x10-12.(8x106) = 6x10-5 pCi/ml.

In this case, the alarm setpoint for the radioactive liquid effluent line nomitor can be established at 6x10-5 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:

c/F < 7x5x10-12 pCi/ml per ml/sec.

Example 2 By using a constant capacity dilution pump (on the dilution stream prior to a mixing box), the value of (F) is fixed; therefore, the setpoints to be given are:

  1. < ml/sec = CF/c F= ml/sec (fixed) c= x (1/f)uCi/ml I CF/f If C = 3x10-8 uCi/ml, F = 4x106 ml/sec and f < 4000 ml/sec, the radiation monitor setpoint is calculated as follows:

c I CF/f

= (3x10-8 x 4x106 1 = 0.12(1/f) uCi/ml.

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If f is measured at some value less than the limiting value (the limiting salue is 4000 ml/sec in this example), then c may be establisned proportionately. If f = 1000 ml/sec, the alarm setpoint is:

c = 0.12(1/f)(uCi/sec)(sec/ml)

= 0.12 = 1.2x10-4 uCi/ml.

1000 In this case, the alarm setpont for the radioactive liquid effluent line monitor can be established at 1.2x10-4 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:

cf > 0.12 pCi/sec.

Value of c A detailed description of the ethod to be used to obtain the value of (c) should be provided. Since (c) is dependent on the radionuclide distribution, yields, calibration and the monitor's parameters, each of these sariable: should be considered and the fixed or adjustable setpoint method o# determination described for each effuent monitor.

This may be accomplished by tabulation.

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4.0 Radioactive Liquid Effluent Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) m The dose contributions for the total time period I att shall be t=1 determined by calculation at least once per 31 days and a cumulative sumation of these total body and any organ doses shall be maintained for each calendar quarter. These dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression:

m Dt =I[Ait I att Ci g Fr]

i t=1 where:

Dt = the cumulative dose or dose commitment to the total body or an organ t fran the liquid effluents for the total time period m

I atg in mrem t=1 at g= the length of the gth time period over which Cjg and Fg are averaged for all liquid releases, in hours.

Ci g= the average concentration of radionuclide i in undiluted liquid effluent during the time period att from any liquid release, in pCi/ml.

Ait= the site related ingestion dose or dose cannitment factor to the total body or any organ t for each identified principal gamma and betta emitter listed in Table 4.1-1, in mrem-ml per hr-uCi .

Fr= the near field average dilution factor for Cig during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the produce of the average flow from the site discharge structure to unrestricted receiving water times 1.0.

For radionuclides not detennined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly canposite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual canposite analyses.

The dose factor Ait for each nuclide, i, embodies the dose factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin.

The adult total body dose factor and the maximum adult organ dose factor for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109; thus the list contains critical organ dose factors for various organs. The dose factor is written:

Ait = ko(Uw/Dw + UfBFi + UjBIj)DFj 853 M

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where:

Ait = composite dose parameter for the total body or critical organ of an adult for nuclide, i, for all appropriate pathways, mrem /hr per pCi/ml.

ko= units conversion factor,1.14x105 = 106 pCi/uCi x 10 3ml/kg +

8750 hr/yr.

Uw = 730 kg/hr, adult water consumption (fresh water cite only).

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Vf = 21 kg/hr, adult fish consumption (all sites).

Uj = 5 kg/yr, adult invertebrate consumption (salt water site only).

BFj = Bioaccumulation factor for nuclide, i, in fish (fresh or salt water site, as applicable), pCi/kg per Ci/1, from Table A-1 of Regulatory Guide 1.109 (Rev.1,10/77).

BIj = Bioaccumulation factor for nuclide, i, in invertebrates (salt water only), pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109 (Rev. 1, 10/77).

DFj = Dose conversion factor for nuclide, i, for adults in pre-selected organ, t, in mrem /pCi, from Table E-11 of Regulatory Guide 1.109 (Rev. 1, 10/77).

Dw = Dilution factor from the near field area within one-quarter mile of the release point (s) to the potable water intake for the adult water consumption (fresh water site only).

Inserting the usage factors of Regulatory Guide 1.109 (Rev.1,10/77) as appropriate into the equation gives the following expression:

Ait = 1.14x10 5(21BFj + 5BI j)DFj

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Table 4.1-1

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LIQUID EFFLUENT INGESTION DOSE FACTORS Ait Dose or Dose Conmitnent Factors BF BI Critical DF (mrem-ml per br-pCi)

Radionuclide (t/kg) (t/kg) Orga n (mrem /pCi) Total Body Critical Or9ans H-3 9.0E-01 9.3E-01 All 1.05E-07 2.80E-01 2.80E-01 Na-24 6.7E-02 1.9E-01 All 1.70E-06 4.60E-01 4.60E-01 P-32 2.9E+04 3.0E+04 Bone 1.93E-04 6.45E+05 1.67E+07 C r-51 4.0E+02 2.0e+03 GI-LLI 6.69E-07 5.58E+00 1.40E+03 Mn-54 5.5E+02 4.0E+02 GI-LLI 1.40E-05 1.35E+03 2.16E+04 Fe-55 3.0E+03 2.0E+04 Bone 2.75E-06 8.23E+03 5.llE+04 Fe-59 3.0E+0i 2.0E+04 GI-LLI 3.40E-05 7.27E404 6.32E+05 Co-58 1.0E+02 1.0E+03 GI-LLI 1.51E-05 1.35E+03 1.22E+04 Co-60 1.0E+02 1.0E+03 GI-LLI 4.02E-05 3.82E+05 3.25E+04 Zn-65 2.0E+03 5.0E+04 Liver 1.54E-05 2.32E+05 5.13E+05 Sr-89 2.0E+00 2.0E+01 Bone 3.08E-04 1.43E+02 4.99E+03 S r-90 2.0E+00 2.0E+01 Bone 7.58E-03 3.01E+04 1.23E+05 Zr-95 2.0E+02 8.0E+01 GI-LLI 3.09E-05 3.50E+00 1.62E+04 Nb-95 3.0E+04 1.0Et02 GI-LLI 2.10E-05 1.34E+02 1.51E+06 f50-99 1.0E+01 1.0E+01 GI-LLI 9.99E-06 2.43E+01 2.96E+02 Tc-99M 1.0E+01 5.0E+01 GI-LLI 4.13E-07 5.00E-01 2.17E401 Ag-llOn GI-LLI 6.04E-05 2.55E-01 1.75E+02 I-131 1.0E+01 5.0E+01 Thyroid 1.95E-03 1.79E+02 1.02E+05 I-132 1.0E+01 5.0E+01 Thyroid 1.90E-05 1.00E+01 9.96E+02 1-133 1.0E+01 5.0E+01 Thyroid 3.63E-04 3.95E+01 1.90E+04 I-135 1.0E+01 5.0E+01 Thyroid 7.65E-05 2.24E+01 4.01E+03 Cs-134 4.0E+01 2.5E+01 Liver 1.48E-04 1.33E+04 1.63E+04 Cs-137 4.0E+01 2.5E+01 Liver 1.09E-04 7.85E+03 1.20E+04 Ba-140 1.0E+01 1.0E402 GI-LLI 4.18E-05 1.08E+02 3.38E+03 cy3 La-140 2.5E+01 1.0E+03 GI-LLI 9.25E-05 2.00E-01 5.83E+04 t;, Ce-141 1.0E+01 6.0E+02 GI-LLI 2.42E-05 3.00E-01 8.86E+03 tsa Ce-144 1.0E+01 6.0E+02 GI-LLI 1.65E-04 9.60E+00 6.04E+04 Np-239 1.0E+01 1.0E+01 GI-LLI 2.40E-05 1.91E-03 7.llE+02 N

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4.2 Radioactive Liquid Effluent Projected Dose (Soecification 4.11.1.3) 853 230

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5.0 Radioactive Gaseous Effluent Dose Calculations 6.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1)

a. Release rate limit for noble gases:

E [Kj (x/Q) Qj] < 500 mrem /yr, and i .

I [(Lj + 1.1 Mj)(x/Q) Qj)] < 3000 mrem /yr i mrem /yr where:

Kj = The total body dose factor due to gamma emissions for eqch identified noble gas radionuclide, in mrem /yr per uCi/mo.

Lj = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3, iij = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 (unit conversion constant of 1.1 mrem / mrad converts air dose to skin dose).

Qi = The release rate of radionuclides, i, add in gaseous effluent from ail release points at the site in pCi/sec.

(x/Q) = sec/m3 The highest calculated annual average relative concentration for any area at or bayond the exclusion area bounda ry.

5.2 Gaseous Effluents Other than Noble Gas Dose Rate (Specification 4.11.2.1.4)

Release rate limit for all radionuclides and radioactive materials in particulate fonn and radionuclides other than noble gases:

I Pj [W Qj] < 1500 mrem /yr i

where:

Pj = The dose factor for radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases for the inhalation pathway, in mrem /yr oer aCi the food and ground plane pathways in /yr) m2 (mrem per /m3 and fo pCi/sec from Tchle 4.11-4. The dose factors are based on the critical individual organ and most restrictive age group (i nfa nt) .

W= The high calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location:

W= sec/m3, for the inhalation pathway. The location is the exclusion area boundary in the sector.

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W= meter-2, for th- food and ground plant pathways.

The location is the exclusion area boundary in the sector.

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Qj = The release rate of radionuclides, i, add in gaseous effluent from all release points at the site in uCi/sec. 853 232

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SPECIAL NOTES: (1) In all cases, the tritium relgases use the first W parameter, based on relative concentration (sec/m ). (2) All radio-iodines are assumed to be released in elemental form. If analysis includes the capability of detemining elemental and nonelemental foms in all releases, the food pathway rarameter may be adjusted accordi ngly.

The dose rate from the ith radionuclide (except tritium) is:

Pj(inhalation)(x/Q) Q + [Pj(food) + Pj(ground plant)] (F/iJ) Q (mrem /yr) and for tritium, is:

Pj (inhalation)(x/Q) Q + P j(food)(x/Q) Q = 3.0 x 10 (x/Q) 3 Q (mrem /yr)

Calculation of P4 (Inhalation)

Pj = K'(BR) DFAj (mrem /yr per pCi/m3) where:

K' = a constant of unit conversion,106 pCi/pCi.

BR = the breathing rate of the infant age group, in m /yr.3 DFAj = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide, in mrem /pCi. The total body is considered as an organ in the selection of DFA j.

is the infant group. The infant's breathing The age group considereg/yr rate is taken as 1400 m from Table E-5 of Regulatory Guide 1.109 (Rev. 1, 10/77). The inhalation dose factors for the infant, DFAj are presented in Table E-10 of Regulatory Guide 1.109, in units of mrem /pC1.

Resolution of the units yields:

Pj (inhalation) = 1.4 x 109 DFAj Calculation of Pi (Ground Plane)

Pj = K'K"DFGj (1-e-Ai t)Aj (m2 . mrem /yr per pCi/sec) where:

K' = a constant of unit conversion,106 pCi/pCi.

K" = a constant of unit conversion, 8760 hr/ year.

Aj = the decay constant for the ith radionculide, sec -1 t = the exposure period, 3.15 x 10 sec7 (1 year).

DFGj = the ground plane dose conversica factor for the ith radionculide (mrem /hr per pCi/m').

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The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for the ith radionuclide, DFG-are presented in Table E-6 of Regulatory Guide 1.109 (Rev.1,10/7f),,

in units of mrem /hr per pCi/m2 ).

Resolution of the units yields:

Pj (Ground) = 8.76 x 199 DFGj (1-e-Ai t)f39, Calculation of P4 (Food)

Q P j = K ' r _F(Vap) F 0Fl i [e-A tif

] y2. mrem /yr per uCi/sec)

Yp TAj+Aw ) m where:

K' = a constant of unit conversion 106 pCi/uCi.

QF = the cow's consumption rate, in kg/ day (wet weight).

Uap = The infant's milk consumption rate, in liters /yr.

Yp = the agricultural productivity by unit ared, in kg/m2 ,

Fm = the stable element transfer coefficients, in days / liter, r = fraction of deposited activity retained on cow's feed grass.

DFLj = the maximum organ ingestion dose factor for the ith radionuclide, in mrem /pCi.

Aj = the decay constant for the ith radionuclide, in sec -1 Aw = the dacay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-time),

tf = the transport time from pasture to cow, to milk, to infant, in sec.

A fraction of the airborne deposition is captured by the ground plant vegetation cover. The captured material is removed from the vegetation (grass) by both radiological decay and weathering p rocesses.

The values of QF, Va o, and Y are provided in Regulatory Guide 1.109 (Rev.1,10/77), Tables E-3,pE-5, and E-15, as 50 kg/ day, 330 liters / day and 0.7 kg/m2 respectively. The value tf is provided in Regulatory Guide 1.109 (Rev.1,10/77), Table E-15, as 2 days (1.73 x 10 seconds). The fraction, r, has a value of 1.0 for radiciodines and o.2 for particulates, as presented in Regulatory Guide 1.109, (Rev. 1, 10/77), Table E-15.

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Table E-1 of Regulatory Guide 1.109 (Rel,10/77) provides the stable element transfer coefficients, F m, and Table E-14 provides the ingestion dose factors, DFLj , for the infant's organs. The organ with the maximum value of DFLj is to be used.

Resolut. ion of the units yields:

Pj (food) = 2.4 x 10 10 % DFLj[e-A if t ](m . 2mrem /yr per uCi/sec)

A i 'A w f;r all radionuclides, except tritium.

The concentration of tritium in milk is based on its airborne concentration rather than the deposition rate.

Pj = K'K"F 0 Um F apDFLj [0.75(0.5/H)] (mrem /yr per pCi/m3 )

where:

K'" = a constant of unit conversion,103 gm/kg.

H = absolute humidity of the atmosphere, in gm/m3 ,

0.75 = the fraction of total feed that is water.

0.5 = the ration of the specific activity of the feed fass water to the atmospheric water.

From Table E-1 and E-14 of Regulatory Guide 1.lg9 (Rev.1,10/77), the values of Fm and DFLj for tritium are 1.0 x 10- day / liter and 3.08 x 10-7 mrem per pC , respectively. Assuming an average ab. solute humidity of 8 grams / meter {, the resolution of units yields:

Pi (food) = 2.4 x 103 mrem /yr per uCi/m3 for tritium, only.

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5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose

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(Specification 4.11.2.2)

The air dose due to noble gases released in gaseous effluents from the site shall be limited during any calendar quarter to the following expressions:

For gamma radiation:

3.17 x 10-8 EMj ((x/Q) Qj + (x/q) gj) 15 mrad, and i

for beta radiation:

3.17 x 10-8 I Nj ((x/Q) Qj + (x/q) gj) i 10 mrad i

where:

3.17 x 10-8 = The inverse of the number of seconds in a year.

M j = The air dose factor due to gamma emissions for eagh identi-fied noble gas radionuclide, in mrad /yr per uCi/m f rom Table 4.11-3.

each identified Nj = The nobleairgas dose factor due in radionuclide, to mrad beta emissions fog from Table

/yr per pCi/m 4.11-3.

x/Q = sec/m3 . The highest calculated annual average relative concentration for any area at or beyond the exclusion area boundary for long term releases (greater than 500 hrs / year).

x/q = sec/m3 . The relative concentration for any area at or beyond the exclusion area boundary for short term releases (equal to or less than 500 hrs /yr).

Qj = The release of noble gas radionuclides, i, in gaseous effluents, for long term releases (greater than 500 hrs /yr),

in pCi. Releases shall be cumulative over the calendar qua rte r.

qj = The release of noble gas radionuclides, i, in gaseous effluents, fer short term releases (equal to or less than 500 hrs /yr), in uCi. Releases shall be cumulative over the calendar quarter.

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  • 5.4 Radioactive Gaseous Effluent Other than Noble Gas Cumulative Dose Specification 4.11.2.3)

The dose to an individual from radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases in gaseous effluents released to unrestricted areas shall be limited during any calendar year to the following expression:

3.17 x 10-8 I Rj (W Qj + w gj ) f 7.5 mrem, and i

where:

3.17 x 10-8 = The inverse of the number of seconds in a year.

Qj = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs /yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate, qj = The release of radiciodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for short tenn releases (equal to or less than 500 hrs /yr), in pCi . Releases shall be cumulative aver the calendar quarter or year as appropriate.

W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long tena releases (greater than 500 hrs /yr):

W= x/Q for the inhalation pathway, in sec/m3 f rom Table 4.11-6a.

W= D/Q for the food and ground plane pathways, in meters-2 f rom Table 4.11-6b.

w= The dispersion parameter for estimating the dose to at the controlling location for short term releases less than 500 hrs /yr):

w= x/q for the inhalation pathway, in sec/m3 from Table 4.11-6c.

w= D/q for the food and ground plane pathway, in meters-2 from Table 4.11-6d.

2 Rj = The dose factor for each identified radigriuclide, i, in m mrem /yr per uCi/sec or mrem /yr per pCi/m f rom Table 4/11-7.

The dose factors are based on the most critical individual organ and most restrictive age group from historical dose calculations.

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  • For the direction sectors with existing pathways within 5 miles from the unit, use the values of Rj for these pathways. If no real pathway exists within 5 miles from the center of the building complex, use the cow-milk Rj assuming that this pathway exists at the 4.5 to 5.0 mile distance in the worst sector. If the Rj for an existing pathway within 5 miles is less than a cow-milk R at 4.5 to 5.0 miles, then use the 3

value of the cow-milk Rj at 4.5 to 5.0 miles. The values used for calculating dose contributions shall be consistent with the results of the land use census performed pursuant to Specification 3.12.2. The controlling value for each radionuclide of Table 4.11-7 shall be determined and made effective within 30 days after the completion of each required land use census. The parameters W and w shall correspond to the applicable Rj for the same sector, pathway and location con

  • 500 HR/YR OR > 125 llR/QTR . Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 2.3E-06 8.2E-L/ 3.6E-07 2.1E-07 1.3E-07 9.6E-08 7.3E-08 5.7E-08 4.7E-08 NNE N/A 2.3E-06 8.1E-07 3.6E-07 2.0E-07 1.3E-07 9.5E-08 7.1E-08 5.6E-08 4.6E-08 NE N/A 2.9E-06 1.0E-06 4.3E-07 2.5E-07 1.6E-07 1.lE-07 8.6E-08 6.7E-08 5.5E-08 ENE N/A 3.4E-06 1.2E-06 5.1E-07 2.9E-07 1.9E-07 1.3E-07 1.0E-07 7.9E-08 6.4E-08 E N/A N/A 1.4E-06 6.0E-07 3.4E-07 2.2E-07 1.6E-07 1.2E-07 9.2E-08 7.5E-08 ESE N/A N/A 1.2E-06 5.4E-07 3.1E-07 2.0E-07 1.4E-07 1.1E-07 8.6E-08 7.0E-08 SE N/A N/A N/A 4.3E-07 2.5E-07 1.6E-07 1.2E-07 8.9E-08 7.0E-08 5.7E-08 SSE N/A N/A N/A 3.8E-07 2.2E-07 1.4E-07 1.0E-07 7.9E-08 6.2E-08 5.lE-08 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A U N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A co NU LJ' N/A N/A 2.3E-06 1.0E-06 6.lE-07 4.lE-07 2.9E-07 2.3E-07 1.8E-07 1.5E-07 u NNW N/A 3.4E-06 1.2E-06 5.4E-07 3.1E-07 2.0E-07 1.5E-07 1.lE-07 8.8E-08 7.2E-08 N -P-N . TABLE 5.1-3 -
    • DISPERSION PARAMETER (D/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR ,
    Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 2.3E-06 8.2E-07 3.6E-07 2.1E-07 1.3E-07 9.6E-08 7.3E-08 5.7E-08 4.7E-08 NNE N/A 2.3E-06 8.lE-07 3.6E-07 2.0E-07 1.3E-07 9.5E-08 7.lE-08 5.6E-08 4.6E-08 NE N/A 2.9E-06 1.0E-06 4.3E-07 2.5E-07 1.6E-07 1.1E-07 8.6E-08 6.7E-08 5.5E-08 ENE N/A 3.4E-06 1.2E-06 5.lE-07 2.9E-07 1.9E-07 1.3E-07 1.0E-07 7.9E-08 6.4E-08 E N/A N/A 1.4E-06 6.0E-07 3.4E-07 2.2E-07 1.6E-07 1.2E-07 9.2E-08 7.5E-08 ESE N/A N/A 1.2E-06 5.4E-07 3.lE-07 2.0E-07 1.4E-07 1.1E-07 8.6E-08 7.0E-08 SE N/A N/A N/A 4.3E-07 2.5E-07 1.6E-07 1.2E-07 8.9E-08 7.0E-08 5.7E-08 SSE N/A N/A N/A 3.8E-07 2.2E-07 1.4E-07 1.0E-07 7.9E-08 6.2E-08 5.lE-08 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A NW N/A N/A 2.3E-06 1.0E-06 6.lE-07 4.1E-07 2.9E-07 2.3E-07 1.8E-07 1.5E-07 [jk NNW N/A 3.4E-06 1.2E-06 5.4E-07 3.lE-07 2.0E-07 1.5E-07 1.1E-07 8.8E-08 7.2E-08 w N .P. CO . ' 2 TABLE 5.1-4 ' DISPERSION PARAMETER (x/q) FOR SHORT TERM RELEASES < 500 HR/YR OR < 125 HR/QTR . Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 4.0-4.5 4.5-5.0 {3.5-4.0 N N/A 1.5E-08 4.9E-09 1.9E-09 1.0E-09 6.3E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 NNE N/A 1.8E-08 5.7E-09 2.3E-09 1.2E-09 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.1E-10 NE N/A 2.0E-08 6.4E-09 2.5E-09 1.3E-09 8.2E-10 5.5E-10 4.0E-10 3.0E-16 2.3E-10 ENE N/A 2.5E-08 8.2E-09 3.2E-09 1.7E-09 1.0E-09 7.lE-10 5.lE-10 3.8E-10 ' 0E-10 . E N/A N/A 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.0E-09 7.2E-10 5.4E-10 4.2E-10 ESE N/A N/A 9.1E-09 3.6E-09 1.9E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.3E-10 SE N/A N/A N/A 2.lE-09 1.1E-09 6.8E-10 4.6E-10 3.3E-10 2.5E-10 1.9E-10 SSE N/A N/A N/A 1.5E-09 8.0E-10 4.9E-10 3.3E-10 2.4E-10 1.8E-10 1.4E-10 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNU N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A co NW N/A N/A 7.lE-09 2.8E-09 1.5E-09 9.0E-10 6.lE-10 4.4E-10 3.3E-10 2.6E-10 LT. d NNW N/A 1.5E-08 4.8E-09 1.9E-09 1.0E-09 6.2E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 N & W . TABLE 5.1-5 .' DISPERSION PARAMETER (D/q) FOR S110RT TERM RELEASES < 500 HR/YR OR < 125 ilR/QTR _ - Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 1.5E-08 4.9E-09 1.9E-09 1.0E-09 6.3E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 NNE N/A 1.8E-08 5.7E-09 2.3E-09 1.2E-09 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.lE-10 NE N/A 2.0E-08 6.4E-09 2.5E-09 1.3E-09 8.2E-10 5.5E-10 4.0E-10 3.0E-10 2.3E-10 ENE N/A 2.5E-08 8.2E-09 3.2E-09 1.7E-09 1.0E-09 7.1E-10 5.iE-10 3.8E-10 3.0E-10 E N/A N/A 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.0E-09 7.2E-10 5.4E-10 4.2E-10 ESE N/A N/A 9.lE-09 3.6E-09 1.9E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.3E-10 SE N/A N/A N/A 2.lE-09 1.1E-09 6.8E-10 4.6E-10 3.3E-10 2.5E-10 1.9E-10 SSE N/A N/A N/A 1.5E-09 8.0E-10 4.9E-10 3.3E-10 2.4E-10 1.8E-10 1.4E-10 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A s.'SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A cy3 NW N/A N/A 7.lE-09 2.8E-09 1.5E-09 9.0E-10 6.lE-10 4.4E-10 3.3E-10 2.6E-10 LJ7 L/4 NNW N/A 1.5E-08 4.8E-09 1.9E-09 1.0E-09 6.2E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 N LD C3 . . TABLE 5.4-1 - PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES , - Inhalation Meat Ground Plane Cow-Milk-Infant Leafy Vegetables Pathway Pathway Pathway Pathway Pathway R- R- R- Rj Radio- (mrem /yr (m2. mrem /yr (m2. mrem /yr (m2. mrem /yr (m2. mrem /yr nucliae per pCi/mh per pCi/sec) per pCi/sec) per pCi/sec) per pCi/sec) . LD tr4 N tri _ , . . ' ' 6.0 Radiological Environmental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b) .. 4 % i - s k ' f l' r . $ % \ i . , t . t s % 'T \ s 1  % . ' . ' ' e g. ' J \ r T / s' - s m I k 4, \ % t ' , 4 s \ e ' . 4 ~ L . 853 252 ' ' ' 7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports Specification 6.9.1.91 . . ' ' 8.0 Revisions to the ODCM (Specification 6.14.2) Changes to the ODCM shall be made by the following method:
    1. Shall be submitted to the Comnission by inclusion in the Monthly Operating Report within 90 days in which the change (s) was made effective and shall contain:
    a. sufficiently detailed information to totally support the rationale for the change without berefit of additional or supplemental information. Infonnation submitted should consist of a package of those pages of 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
    b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint detenninations; and
    c. documentation of the fact that the change has been reviewed by the PRC and approved by the Plant Manager.
    2. Shall become effective upon review by the PRC and approval by the Plant Manager.
    853 254
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