ML030990665
| ML030990665 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/31/2002 |
| From: | Omaha Public Power District |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML030990665 (104) | |
Text
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 50 OF 132
- 6. BASIS 6.1 Instrumentation 6.1.1 Radioactive Liquid Effluent Instrumentation The Radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual (ODCM) to ensure that the alarmltrip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
6.1.2 Radioactive Gaseous Effluent Instrumentation The Radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in gaseous effluents during actual or potential releases of liquid effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual (ODCM) to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 51 OF 132 6.2 Radioactive Effluents 6.2.1 Radioactive Liquid Effluents A. Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section I.A design objectives of Appendix 1, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-133 is the controlling isotope and its effluent concentration in air (submersion) was converted to an equivalent concentration in water.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 52 OF 132 6.2.1 B. Dose This specification is provided to implement the requirements of Sections II.A, II.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section I.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept " as low as is reasonably achievable." Also, with fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in Part II of the ODCM implement the requirements in Section III.A that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in Part 11 of the ODCM for calculating the doses due to the actual release rates of radioactive material in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
C. Liquid Waste Treatment System The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept " as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix I to 10 CFR Part 50 and design objective and in Section lI.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified to ensure the design objectives set forth in Section IL.A of Appendix I, 10 CFR Part 50 for liquid effluents are not exceeded.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 53 OF 132 6.2.1 D. Liquid Holdup Tanks Restricting the quantity of radioactive material contained in the specified "U
tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest U
potable water supply and the nearest surface water supply in an unrestricted area.
6.2.2 Radioactive Gaseous Effluents A. Concentration This specification, in conjunction with 3.2.2.A and 3.2.3.A, is provided to ensure that the dose at or beyond the Site Boundary from gaseousu effluents will be within the annual dose limits of 10 CFR Part 20 for MEMBERS OF THE PUBLIC. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations for these radionuclides do not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted U
area boundary. To support plant operations, Supervisor-System Chemistry may increase this limit up to the limits specified in Technical Specifications 5.16.1.g. Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. Because these concentrations are applied on an instantaneous basis and because of the overriding 10 CFR Part 50 Appendix I cumulative dose limitations, these limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the Site Boundary, to annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR Part 20.1301(a).
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 54 OF 132 6.2.2 B.
Dose - Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section Il.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the ODCM for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.1 11, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary are consistent with Regulatory Guides 1.109 and 1.111.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 55 OF 132 6.2.2 C. Dose 131, Radioactive Material in Particulate Form with Half-Lives Greater than Eight Days (Other than Noble Gases) and Tritium This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section I.0C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the ODCM for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.1 11, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The release rate specification for 1-131, radioactive material in particulate form with half lives greater than eight days (other than noble gases) and tritium are dependant on the existing radionuclide pathways to man in the areas at or beyond the site boundary. The pathways that were examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
I' R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 56 OF 132 6.2.2 D. Gaseous Waste Treatment The OPERABILITY of the gaseous radwaste treatment system and the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable. This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix I to 10 CFR Part 50 and design objective and in Section II.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified to ensure the design objectives set forth in Section 11.8 and I.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 57 OF 132 6.2.2 E. Total Dose - Uranium Fuel Cycle This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d).
This requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mRems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mRems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR U
Part 190 if the plant remains within twice the dose design objectives of Appendix I, 10 CFR Part 50, and if direct radiation doses ( including outside storage tanks, etc.) are kept small. The Special Report shall describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site ora within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report, with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with thew provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4) and 20.2203(b) is considered to be a timely request and fulfills the requirements 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. Demonstration of U
compliance with the limits of 40 CFR Part 190 or with the design I
objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 58 OF 132 6.3 Radiological Environmental Monitoring 6.3.1 Monitoring Program The radiological environmental monitoring program required by this specification provides measurements of radiation and radioactive materials in those exposure pathways and for radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program was effective for at least the first three years of commercial operation. Following this period, program changes are initiated based on operational experience.
6.3.2 Land Use Survey This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this survey. The best survey information from door to door, aerial or consulting with local agricultural authorities, or equivalent, shall be used. This survey satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the survey to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/im2.
For milk, the survey is restricted to only milk animals (cow or goat) producing milk for human consumption. Air monitoring stations are strategically located to monitor the resident receptors who could potentially receive the highest doses from airborne radioactive material. Guidance provided in the Branch Technical Position and Technical Specification 5.16.2 is used to meet the intent of NUREG-0472.
6.3.3 Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 59 OF 132 PART II CALCULATIONS R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 60 OF 132
- 1. EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents There are two liquid discharge pathways to the Missouri River. These pathways originate with the radioactive liquid waste processing system (monitor or hotel tanks) and the steam generator blowdown system. Both of these pathways empty into the circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathways and associated radiation monitors. Figure 3 depicts the methods of liquid effluent treatment.
The flowrate for dilution water varies with the number of circulating water pumps in service, the number of raw water pumps in service, and with the operation of the warm water recirculation. Some warm water from the condenser outlet is diverted from the circulating water discharge to upstream of the intake structure to help prevent ice from forming on the circulating water pump intakes during winter months.
The varying dilution flowrate and utilization of warm water recirculation is accounted for in the dilution calculations for monitor tank and stream generation releases.
Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 pCi/ml total activity.
The liquid effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
The liquid effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
Cs-137 is used to calibrate the liquid effluent monitors.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 61 OF 132 NOTE: If the annual average X/Q value exceeds 1.4E-04 sec/mr3, consideration should be given to basing liquid radiation monitor setpoints on an 1-131 instantaneous limit of 2.OE-09 pCi/mI at the unrestricted area boundary with 10% vapor/liquid separation. Contact the Supervisor-System Chemistry for further instructions.
1.1.1 Liquid Effluent Radiation Monitors A. Steam Generator Blowdown Monitors (RM-054A and B)
These process radiation detectors monitor the flow through the steam generator blowdown lines and automatically close the blowdown isolation valves if the monitor high alarm setpoint is reached. The monitor controls liquid effluent releases so that 10 times the 10 CFR Part 20 limit at the unrestricted area boundary of 1.OE-06 pCi/cc, is not exceeded at the site discharge.
The following calculations for maximum concentration and alarm setpoints are valid when steam generator blowdown is the only liquid release pathway. For simultaneous radioactive liquid releases of steam generator blowdown and monitor tank discharge, refer to Section 1.3.
The maximum allowable concentration in the blowdown line is calculated as follows:
CMAX (1.OE-05 pCilm/)
(F) f Where:
1.OE-05 pCi/ml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2).
F
= Total dilution flow in the discharge tunnel (gpm).
(Normal flow is based on 1 circulating water pump at 120,000 gpm. Other flowrates may be used, as required.)
f
= Blowdown flow rate (gpm). (Normal blowdown flow rate is based on 2 transfer pumps with a design flow of 135 gpm each, 270 gpm total. Other flow rates may be used, as required.)
= Maximum allowable blowdown concentration (pCiml).
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 62 OF 132 NOTE: Setpoints may be recalculated based on adjusted dilution flow and adjusted blowdown flow.
1.1.1A The High Alarm Setpoint (CPM) =
0.75 [((Sf)(CmAx)) + B]
Where:
0.75
= An administrative correction factor which includes the following:
15% tolerance to ensure radmonitor response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.
10% tolerance to account for the difference in detector sensitivity for the range of isotopes detected.
Sf
= Detector sensitivity factor (CPM/pCi/ml). (Sensitivity based on Cs-1 37).
B
= Background (CPM)
CMA
= Maximum allowable blowdown line activity (pCiml).
The Alert Setpoint will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
B. Overboard Discharge Header Monitor (RM-055)
This process radiation monitor provides control of the waste monitor tank effluent by monitoring the overboard header prior to its discharge into the circulating water discharge tunnel. The concentration of activity at discharge is controlled below ten times the 10 CFR Part 20 limit of 1.OE-06 pCi/ml at site discharge for unidentified isotopes by the high alarm setpoint which closes the overboard flow control valve.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 63 OF 132 1.1.1 B The following calculations for maximum concentration and alarm setpoints are valid when Monitor Tank discharge is the only liquid release pathway. For simultaneous radioactive liquid releases of monitor tank discharge and steam generator blowdown, refer to Section 1.3.
The maximum allowable concentration in the overboard discharge header is:
C M
_ (1.OE-05 pCilmf (F) f Where:
1.OE-05 pCilml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2).
F
= Total dilution flow in the discharge tunnel (gpm).
(Normal flow is based on 1 circulating water pump at 120,000 gpm. Other flowrates such as raw water pump(s) may be used, as required.)
f
= Maximum monitor tank discharge flow rate (gpm).
(Normal monitor tank maximum flow is 50 gpm.
Other flow rates such as raw water pump(s) may be used, as required.)
CMAXC
= Maximum allowable activity in discharge header (PCi/ml).
R12 U
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 64 OF 132 1.1.1B The High Alarm Setpoint (CPM) =
0.75 [((Sf) (CMAx)) + B]
Where:
0.75
= An administrative correction factor which includes the following:
15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.
10% tolerance to account for the difference in detector sensitivity for the range of isotopes detected.
St
= Detector sensitivity factor (CPM/pCi/ml). (Sensitivity based on Cs-137).
CMAX
= Maximum allowable concentration in discharge header (pCi/ml).
B
= Background (CPM)
The Alert Setpoint will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 65 OF 132 1.2 Airborne Effluents There are three air effluent discharge pathways at the Fort Calhoun Station:
Condenser Offgas, Laboratory and Radioactive Waste Processing Building Exhaust Stack, and the Auxiliary Building Exhaust Stack. An airborne radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 4. The airborne waste disposal system is presented in Figure 5.
- Auxiliary Building - The Auxiliary Building Exhaust Stack receives discharges from the waste gas decay tanks, containment purge, containment vent systems and the auxiliary building ventilation system. Radiation Monitor RM-062 provides noble gas monitoring and iodine and particulate sampling for the Auxiliary Building Exhaust Stack. Backup noble gas monitoring and iodine and particulate sampling 0
is provided by RM-052. Ventilation Isolation Actuation Signal (VIAS) is actuated by exceeding a monitor's alarm setpoint. Actuation of VIAS will isolate releases from containment and waste gas decay tanks. The Auxiliary Building Exhaust fans will remain in operation.
- Laboratorv and Radioactive Waste Processing Building (LRWPB) - Noble gas monitoring and particulate and iodine sampling is provided by RM-043. This radiation monitor/sampler does not serve a control function.
- Condenser Off-Gas Monitors - Noble gas activity is monitored by RM-057. The condenser off-gas is discharged directly to the environment. Exceeding the high alarm setpoint on RM-057 will activate isolation of main steam to the Auxiliary Steam System.
Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.
The airborne effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
The airborne effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than 5 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 66 OF 132 1.2.1 Airborne Effluent Radiation Monitors A. Auxiliary Building Exhaust Stack Noble Gas Activity Monitor (RM-062/RM-052)
Either of these monitors may be used to measure the noble gas activity in the exhaust stack. The noble gas is monitored after passing through a particulate filter, and charcoal cartridge. The monitor controls airborne releases so that five times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.OE-07 pCi/cc, based upon Xe-133, is not exceeded.
The Ventilation Isolation Actuation Signal is initiated when the high alarm setpoint is reached.
The following calculations for maximum release rate and alarm setpoint are valid when Auxiliary Building Exhaust Stack is the only airborne release pathway. For simultaneous airborne releases from Auxiliary Building Exhaust Stack, Condenser Off-gas and the LRWPB Exhaust Stack, refer to Section 1.3.
The maximum allowable release rate for stack airborne activity is calculated as follows:
RMAx pCi/sec = 2.5E-06 pCi//cc x 1.0E+06 cc/M3 x/Q seC/rn 3 Where:
2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
x/Q sec/m3
= Annual average dispersion factor at the unrestricted area boundary from ODCM Part II Table 4 1.0E+06 cc/m3 = Constant of unit conversion.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 67 OF 132 1.2.1A The High Alarm Setpoint (CPM):
Setpoint = 0.75 ( (RMF)
(S) (60) l v
(F,) (28317))
j Where:
0.75
= An administrative correction factor which includes the following:
15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.
10% tolerance to allow for the contribution of noble gases other than Xe-1 33 towards the total ECL fraction sum.
Sf
= Detector sensitivity factor (CPM/pCi/cc). (Sensitivity based on Xe-1 33) 60
= Conversion (seconds to minutes).
28317
= Conversion factor (ft3 to cc).
F
= Auxiliary Building Exhaust stack flow rate (SCFM). (Default maximum flow rate is 122,500 cfm for 3 Auxiliary Building exhaust fans and 2 containment purge fans in operation.
Other flow rates may be used, as required.)
RmVx
= Maximum Allowable Release Rate in pCi/sec B
= Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint and VIAS actuation.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 68 OF 132 1.2.1 B.
Condenser Off Gas Monitor (RM-057)
This monitor is located in the turbine building and monitors the condenser off-gas. The purpose of this monitor is to monitor the condenser off-gas discharges so that five times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.OE-07 pCi/cc, based upon Xe-133, is not exceeded.
The following calculations for maximum release rate and alarm setpoint are valid when condenser off-gas is the only airborne release pathway.
For simultaneous airborne releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.3.
The maximum allowable release rate for condenser air ejector monitor is as follows:
RMAx pCi/sec 2.5E-06 pCil/cc X 1.0E+06 ccIM/3 x/Q sec/n Where:
2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
X/Q sec/M 3
= Annual average dispersion factor at the unrestricted area boundary from ODCM Part II, Table 4 1.OE+06 cc/M3 = Constant of unit conversion.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 69 OF 132 1.2.1B The High Alarm Setpoint (CPM):[((Rm~x)
(Sf) (60)
Setpoint = 0.75 a'(MX S
)
+6)
B p 0 (Fr) (28317)
+ j Where:
0.75
=
An administrative correction factor which includes the following:
15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.
10% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.
S
=
Detector sensitivity factor (CPM/pCi/cc). (Sensitivity based on Xe-1 33) 60
=
Conversion (seconds to minutes).
28317
=
Conversion factor (ft3 to cc).
F
=
Vent stack flow rate (SCFM). Default maximum flow rate is 4,755 scfm (3 vacuum pumps in hogging mode. Other flow rates may be used, as required.)
RmA
=
Maximum Allowable Release Rate in pCi/sec.
B
=
Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum J
of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint and tripping of the auxiliary steam supply valve, RCV-978.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 70 OF 132 1.2.1 C. Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and Iodine and Particulate Sampler (RM-043)
RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is based on five times the 10 CFR Part 20 limit for Xe-1 33 at the unrestricted area boundary.
The following calculations for maximum release rate and alarm setpoint are valid when the LRWPB Exhaust Stack is the only airborne release pathway. For simultaneous airborne releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack, refer to Section 1.3.
The maximum allowable release rate for RM-043 is as follows:
Rmx p Ci/sec = 2.5E-06 p Cl/cc x 1.OE+06 cc/rM3 x/Q sec/m 3 Where:
2.5E-06 pCi/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
X/a
= Annual average dispersion factor at the unrestricted area boundary from the ODCM Part II, Table 4 1.OE+06 cc/m3 = Constant of unit conversion R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 71 OF 132 NOTE: This monitor alarms in the Control Room. There are no automatic control functions associated with the actuation of the alarm.
1.2.1C The High Alarm Setpoint (CPM):
Setpoint = 0.75 (Rmx) (Sf) (60)
+ B1 Where:
0.75
= An administrative correction factor which includes the following:
15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.
10% tolerance to allow for the contribution of noble gases other than Xe-1 33 towards the total ECL fraction sum.
Sf
= Detector sensitivity factor (CPM/pCi/cc). (Sensitivity based on Xe-133) 60
= Conversion (seconds to minutes).
28317
= Conversion factor (ft3 to cc).
-v F,
= LRWPB Exhaust stack flow rate (SCFM). (Default flow rate is 28,700 cfm. Other flow rates may be used if required.)
RmAx
= Maximum Allowable Release Rate in pCi/sec.
B
= Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 72 OF 132 1.3 Simultaneous Release Pathways NOTE: If the annual average X/Q value exceeds 1.4E-04 sec/m3, consideration should be given to basing liquid radiation monitor setpoints on an 1-131 instantaneous limit of 2.OE-09 pCi/ml at the unrestricted area boundary with 10% vapor/liquid separation. Contact the Supervisor-System Chemistry for further instructions.
1.3.1 Liquid Release Pathways The liquid radiation monitors (RM-054A/054B and RM-055) control liquid releases so that ten times the 10 CFR Part 20 limit of 1.OE-06 pCiml for unidentified isotopes at site discharge is not exceeded. There are two liquid release pathways that contribute to the concentration at site discharge.
These are Steam Generator Blowdown and Monitor Tank Overboard Discharge Header. When more than one pathway is utilized for radioactive releases, it is necessary to adjust the alarm setpoints given in Section 1.1.1 so that unrestricted area concentration limits are not exceeded.
The calculations for the alarm setpoints for the liquid effluent monitors will be adjusted as follows:
CT= KOCMAX, + K1 CMAX, CT KO (1.OE-05 pCil/mI) (F)
K, (1.OE-05 pCilmo) (F) fo f,
Where:
=
Sum of individual maximum allowable concentrations for Steam Generator and Monitor Tank prior to dilution for simultaneous liquid releases (pCi/ml)
CMAO
=
Maximum allowable concentration in Steam Generator blowdown Line (pCi/ml)
=
Maximum allowable concentration in Monitor Tank Discharge Line (pC/ml)
K
=
Allocation factor for Steam Generator (See Table 1)
K,
=
Allocation factor for Monitor Tank (See Table 1)
F
=
Total dilution flow in Discharge Tunnel (GPM) f
=
Steam Generator Blowdown flowrate (GPM) f,
=
Monitor Tank Discharge flowrate (GPM)
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 73 OF 132 1.3.1 The High Alarm Setpoint for Steam Generator Blowdown monitors, RM-054A/054B, will then be:
Alarm Setpoint (CPM) = 0.75 [(K0 3, CMA)
+ B0]
The High Alarm Setpoint for Monitor Tank Discharge Monitor, RM-055, will then be:
Alarm Setpoint (CPM) = 0.75 [(K 1 Sf1 CMAX,) + B1]
Where:
Sfo
=
Detector Sensitivity factor for RM-054AN054B, CPM/(QCi/ml),
based on Cs-137.
Sf
=
Detector Sensitivity factor for RM-055, CPM/(pCi/ml), based on Cs-1 37.
Cmo
=
Maximum allowable concentration in S/G Blowdown line.
(pCimI)
CMA1
=
Maximum allowable concentration in MT Discharge line.
(pCi/ml)
Bo
=
RM-054A/054B background countrate. (CPM)
B,
=
RM-055 background countrate. (CPM)
KO K,=
Allocation factors. See Table 1.
The Alert Setpoint will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 74 OF 132 1.3.2 Airborne Release Pathway The noble gas radiation monitors (RM-043, RM-057, and RM-062/RM-052) control airborne releases so that five times the 10 CFR Part 20 limits of 5.OE-07 pCilcc for noble gases at the unrestricted area boundary is not exceeded. There are three pathways that contribute to the concentration at the unrestricted area boundary. These are the Auxiliary Building Exhaust Stack, Condenser Off-gas, and the LRWPB Exhaust Stack. When more than one pathway is utilized for radioactive releases, it is necessary to adjust the alarm setpoints given in Section 1.1.1 to ensure that unrestricted area concentration limits are not exceeded.
The calculations for the alarm setpoints for the liquid effluent monitors will be adjusted as follows:
The maximum allowable release rates for simultaneous releases is:
3 3
25-6pic Max. Release Rate = E KRMAX = E K, 2C5EM06 3
Clcc 1=1 i=:
X/Q sec/r 3 Where:
RmA 0
=
RM-062/RM-052 release rate (pCi/sec)
RmAx
=
RM-057 release rate (pCisec)
Rm~
=
RM-043 release rate (pCi/sec)
X/Q
=
Annual average dispersion factor at the unrestricted area boundary from the ODCM Part II, Table 4 K, - K3 =
Allocation factors. See Table 1.
2.5E-06 pCi/cc =
5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
R12
J-2 FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 75 OF 132 1.3.2 The maximum release rate Rmm then:
(K1) (2.5E-06 pCi/cc)
(K2) (2.5E-06 pCi/cc)
(K3) (2 5E-06 pCilcc)
X/Q sec/m3 X/Q secM 3 x/Q serm/r3 ]3
=
MA The High Alarm Setpoints for the noble gas monitors will then be:
RM-062/052 = 0.75 t(K F. (28317))) + B
[(07=
.5K (FV,) (28317) )
]I RM-043 = 0.75 f(K3 (RMAX) (St)(60)+
B1 IL (F,) (28317) )
]
Where:
0.75
=
An administrative correction factor which includes the following:
- 15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77.
- 10% tolerance to allow for the contribution of noble gases other than Xe-1 33 towards the total ECL fraction sum.
K, - K3 =
Allocation factors. See Table 1.
J Sf
=
Detector sensitivity factor.
\\
F
=
Vent stack flowrate. (Condenser off-gas flowrate for RM-057, LRWPB Exhaust stack flow rate for RM-043, Auxiliary Building Exhaust Stack flow rate for RM-062/052).
RmA
=
Maximum Allowable Release Rate in pCi/sec.
B
=
Monitor background count rate.
60
=
Constant of unit conversion (60 sec/min).
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 76 OF 139 Table 1 - Allocation Factors for Simultaneous Releases NOTE: The Fort Calhoun Station is capable of performing simultaneous airborne releases. The factors below may be adjusted to meet release requirements, provided that the sum of the Unrestricted Area Fraction Sum for all airborne releases remains less than or equal to 1.0.
A. Allocation Factors for Simultaneous Airborne Releases
- 1.
Auxiliary Building Exhaust Stack Total: 0.8(
K, Noble Gases (RM-062 or RM-052) 0.7(
lodine/Particulate/Tritium 0.1 Contributing Pathways:
a) Auxiliary Building 0.10 b) Containment Building 0.65 c) Waste Gas Decay Tanks 0.05
- 2.
Condenser/Off Gas Total:
0.1w K2 Noble Gases (RM-057) 0.0' Tritium O &
Contributing Pathways:
a) Condenser Off Gas 0.10
- 3.
Laboratory and Radioactive Waste Building Exhaust Stack Total: 0.11 K3 Noble Gases (RM-043) 0.0 lodine/Particulate 0.0 Contributing Pathways:
a)
Laboratory and Radioactive Waste Building Exhaust Stack 0.10 I
)
)
)
)
5 5
0 5
5 Airborne Release Total I
NOTE: The Fort Calhoun Station is capable of performing simultaneous liquid releases. The factors below may be adjusted to meet release requirements provided that the sum of the Unrestricted Area Fraction Sum for all liquid releases remains less than or equal to 1.0.
B. Allocation Factors for Simultaneous Liquid Releases
- 1.
K0 Steam Generator Releases (RM-054AN054B)
I
- 2.
K:
Waste Liquid Releases (RM-055)
I Liquid Release Total 1.00 I
0.30 0.70 1.00 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Figure 1 - Exclusion and Site Boundary Map CH-ODCM-0001 PAGE 77 OF 132 r---
II I
I NEBRASKA METS-I TOWER I
I f
True N
Site IOWA UNRESTRICTED a
\\
AREA BOUNDARY RESTRICTED alAREA FORT k
i XC CALHOUN UNIT # 1 I
BLAIR
""-ADMIN.
BLDG.
TRAINING CENTER UNRESTRICTED AREA O)
LIQUID EFFLUENTS DISCHARGE (O)
AIRBORNE EFFLUENTS DISCHARGE TO OMAHA 0
y('
I SCALE IN MILES EXCLUSION AND SITE BOUNDARY MAP R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 78 OF 132 Figure 2 - Liquid Radioactive Discharge Pathways R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Figure 3 - Liquid Radioactive Waste Disposal System REACTOR COOLANT AUXILIARY SYSTEMS WASTE PROCESS WASTE Mcs Bleedrr HOTEL WASTE Floor Drains EUpmeot Drains Lwdq Waste
&ap Flo" R Loop Drains Sow Drains CH-ODCM-0001 PAGE 79 OF 132
$Ptnt Regenrnt V
Waste Hiotl TnsHold*
11 Tanks 5538 Gel. (LiI ljlBlBJ45.8K Gel.
Got12 l.
Waste Filtrs 58 Hi38ont vessels Diacoal Filter 6i Cu. Ft.
loptional)
Monitor Tanks O 6771 Gl.
4 oad Header (To tiver)
LIQUID RADIOACTIVE WASTE DISPOSAL SYSTEM R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 80 OF 132 Figure 4 - Airborne Effluent Discharge Pathways
-t RM-043 Noble Gas Monitor, and Iodine & Particulate Sampler I -
LRWPB Laboratory LABORATORY AND RADIOACTIVE WASTE PROCESSING BUILDING RM-057 Noble Ga!
Monitor CONDENSER OFFGAS Condenser RM-062,052 Noble Gas Monitor Iodine & Particulate Sampler B
I
-AUXILIARY BUILDING EXHAUST STACK Ahuxiliary Building-Ventilation Containment Building Ventilation AIRBORNE EFFLUENT DISCHARGE PATHWAYS R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Figure 5 - Airborne Radioactive Waste Disposal System CH-ODCM-0001 PAGE 81 OF 132 Auxiliary Building Ventilation Stack 122.500 To Atmosphere CONTAINMENT BUILDING VENTILATION CONTROL Ground AIRBORNE RADIOACTIVE WASTE DISPOSAL SYSTEM R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 82 OF 132
- 2. EFFLUENT CONCENTRATIONS 2.1 Liquid Effluent Concentrations The concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) will be limited to the concentrations as specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. For batch releases (Monitor and Hotel Waste Tanks and Steam Generators) and for continuous releases (Steam Generator Blowdown), the analyses will be performed in accordance with Part I, Table 3.1, and the concentration of each radionuclide at site discharge will be calculated, based on the following equation:
Radionuclide concentration at site discharge:
- a. f iF
+ f A.-
and A
1
,=,
- wec, Where:
A,
=
concentration at site discharge for radionuclide (i), in PCi/ml.
a,
=
concentration of radionuclide (i) in the undiluted effluent, in pCi/ml.
f
=
undiluted effluent flowrate, in gpm.
F
=
total diluted effluent flowrate in gpm.
wec
=
water effluent concentration limit for radionuclide (i) per 10 CFR Part 20, Appendix B, Table 2, Column 2.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 83 OF 132 NOTE: In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable.
2.2 Airborne Effluent Concentrations The concentration at the unrestricted area boundary, due to airborne effluent releases, will be limited to less than Appendix B, Table 2, Column 1, values.
Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event an airborne effluent release from the station result in an alarm setpoint being exceeded, an evaluation of the unrestricted area boundary concentration resulting from the release will be performed:
To determine the concentration and air effluent concentration (aec) fraction summation at the unrestricted area boundary, the following equations will be used:
A, = Ko Qj WXQ) and n
A 1
,=,
- ECL, Where:
A,
= Concentration of radionuclide (i) at the unrestricted area boundary K0
= Constant of unit conversion. (1.OE-6 m3/cc)
ECLi = Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, Column 1 value for radionuclide(i))
Q.
= The release rate of radionuclide (i) in airborne effluents from all vent releases (in pCi/sec.)
(X/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from ODCM Part II, Table 4 As appropriate, simultaneous releases from the Auxiliary Building Ventilation Stack, Laboratory and Radwaste Building Stack and condenser off gas will be considered in evaluating compliance with the release rate limits of 10 CFR Part 20. Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. Historical annual average dispersion parameters, as presented in Table 4, may be used for evaluating the airborne effluent dose rate.
For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding those more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding 10 CFR Part 20 limits. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based upon the above criteria, no further analyses are required for demonstrating compliance with 10 CFR Part 20.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 84 OF 132
- 3. RADIOACTIVE EFFLUENT DOSE CALCULATIONS 3.1 Liquid Effluent Dose Calculations Three pathways for human exposure to liquid releases from FCS to the Missouri River exists: 1) fish, 2) drinking water, and 3) Shoreline deposition. Fish are considered to be taken from the vicinity of the plant discharge. The drinking water for Omaha is located 19 miles downstream from FCS. The dilution factors for these pathways are derived from the Revised Environmental Report for FCS, (1974), (page 4-29 and 4-31). This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be <14% of the concentration at discharge from FCS and will average 3%. This equates to a dilution factor of 7.14, which is used to calculate the maximum dose to an individual from liquid pathways and a dilution factor of 33.33, for calculating the average dose. All pathways combine to give the dose to an individual in unrestricted areas.
10 CFR Part 50, Appendix I restricts the dose to individuals in the unrestricted areas from radioactive materials in liquid effluents from the Fort Calhoun Station to the following limits:
- during any calendar quarter
<1.5 mrem to total body
<5.0 mrem to any organ and
- during any calendar year
< 3.0 mrem to total body
< 10.0 mrem to any organ The following calculational methods shall be used for determining the dose or dose commitment from liquid effluents.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 85 OF 132 3.1.1 Doses from Liquid Effluent Pathways A.
Potable Water U Mn Rapj = 1100 ap P E QDa1pJexp(-Atp)
F 11 Where:
Rapi =
is the total annual dose to organj) of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem/yr.
Uap =
is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in Q/yr. (Table 6)
=
is the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless. (Table 17)
F
=
is the flow rate of the liquid effluent, in ft3/ sec.
Q.
= is the annual release rate of radionuclide (i), in Ci/yr.
Daipj = is the dose factor specific to a given age group (a),
radionuclide (i), pathway (p), and organ () which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16)
Al
=
is the radiological decay constant of radionuclide (i), in hrW.
tP
=
is the average transit time required for radionuclides to reach the point of exposure. For internal dose, tP is the total time elapsed between release of the radionuclides and ingestion of water, in hours. (Table 17) 1100 =
Constant (pCi *yr* ft3/Ci
- sec* L)
R12
'J2
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 86 OF 132 3.1.1 B. Aquatic Foods Rapj = 1100
'F E QBPD8,,Pexp(-A,tP)
F M=
Where:
Rap; =
is the total annual dose to organ () of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem/yr.
Uap
= is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in kg/yr.
(Table 6)
=
is the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless. (Table 17)
F
= is the flow rate of the liquid effluent, in ft3/sec.
Q.
=
is the annual release rate of radionuclide (i), in Ci/yr.
-Bp
=
is the equilibrium bioaccumulation factor for radionuclide (i) in pathway (p) expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in (pCi/kg)/(pCi/liter). (Table 3)
Daipj
=
is the dose factor specific to a given age group (a),
radionuclide (i), pathway (p), and organ 0), which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16)
Al
=
is the radiological decay constant of radionuclide (i), in hr-.
tp
= is the average transit time required for radionuclides to reach Z
the point of exposure. For intemal dose, tp is the total time elapsed between release of the radionuclides and ingestion of food, in hours. (Table 17) 1100 =
Constant (pCi
- yr
- ft3/Ci
- sec
- L)
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 87 OF 132 3.1.1 C. Shoreline Deposits Rap = 110,000 ap QiTpDap[exp(-A,tp)][l-exp(-Atb)]
Where:
Rapj
= is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (i) in pathway (p), in mrem/yr.
Uap
= is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p), in hr/yr. (Table 6)
= is the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless. (Table 17)
W
= is the shore-width factor, dimensionless. (Table 17)
F
= is the flow rate of the liquid effluent, in ft3/sec.
a,
= is the annual release rate of radionuclide (i), in Ci/yr.
Tp
= is the radioactive half life of radionuclide (i), in days.
Daipj
= is the dose factor specific radionuclide (i) which can be used to calculate the radiation dose from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the real radionuclide concentration (in pCi/ine). (Table 8)
A,
= is the radiological decay constant of radionuclide (i), in hr'.
tp
= is the average transit time required for radionuclides to reach the point of exposure, in hours. (Table 17) tb
= is the period of time for which sediment or soil is exposed to the contaminated water, in hours. (Table 17) 110,000 = Constant [(100
- pCi
- yr
- ft3)/(Ci
- sec
- L)]
R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 88 OF 132 3.2 Airborne Effluent Dose Calculations 3.2.1 Noble Gas 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from noble gases in airborne effluents from the Fort Calhoun Station to the following limits:
During any calendar quarter
<5 mrad-gamma air dose
<10 mrad-beta air dose and During any calendar year
<10 mrad-gamma air dose
<20 mrad-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses:
A.
Doses from Noble Gases
- 1)
Annual Gamma/Beta Air Dose from All Other Noble Gas Releases DY(r,8) or DP(r,6) = 3.17 x 104 E Q,[XIQ]o(r,8)(DFY. or DFO)
Where:
DFl, DFP DY(r,e) or DO(r,B)
Q.
[XIQ]f(rE) 3.17x104
= are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide (i),
in mrad-m 3/pCi-yr. (Table 2)
= are the annual gamma and beta air doses at distance r, in the sector at angle e, from the discharge point, in mrad/yr.
= is the annual release rate of radionuclide (i),
in Ci/yr.
= is the annual average gaseous dispersion factor at distance r, in the sector at angle a, in sec/m 3. (Table 4)
= is the number of pCi per Ci divided by the number of seconds per year.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 89 OF 132 3.2.1A
- 2)
Annual Total Body Dose from All Other Noble Gas Releases DT(rG) = Sf S x,(rG)DFB,
, 1 Where:
DFBI
= is the total body dose factor for a semi-infinite cloud of the radionuclide (i), which includes the attenuation of 5 g/cm2 of tissue, in mrem-m 3/pCi-yr. (Table 2)
D: (r,G) = is the annual total body dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle e, in mrem/yr.
X,(r,)
= is the annual average ground-level concentration of radionuclide (i) at distance r, in the sector at angle i, in pCi/r 3. (Table 4)
S.
= Shielding Factor (Table 17)
- 3)
Annual Skin Dose from All Other Noble Gas Releases T
n n
D (r, 8) = 1.11 Sf Z X,(rO)DFY + S X,(r,6G)DFS,
't Where:
DI(r,e) = is the annual skin dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle 8, in mrem/yr.
DFS1
= is the beta skin dose factor for a semiinfinite cloud of radionuclide (i), in mrem-m 3/pCi-yr. (Table 2) 1.11
= is the average ratio of tissue to air energy absorption coefficients.
R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 90 OF 132 3.2.2 Radioiodine, Tritium, and Particulates 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from radioactive materials in gaseous airborne from the Fort Calhoun Station to:
During any calendar quarter
<7.5 mrem to any organ and During any calendar year
<15 mrem to any organ The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in airborne effluents released to unrestricted areas should be determined by the following expressions:
Radioiodine, Tritium, and Particulates (continued)
NOTE: In all cases, for releases of tritium, use the dispersion parameter for inhalation (X/Q).
A. Annual Organ Dose from External Irradiation from Radioactivity Deposited on the Ground Plane The ground plane concentration of radionuclide (i) at distance r, in the sector at angle e, with respect to the release point, may be determined by:
CG(r, ) =11 OX1016,{.0qpj [I -exp(_A,__)]
I A1 Where:
CG
= is the ground plane concentration of the radionuclide (i) at distance r, in the sector at angle e, from the release point, in pci/m2.
Q.
= is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
= is the time period over which the accumulation is evaluated, which is assumed to be 15 years (mid-point of plant operating life). (Table 17) 6,(r,G)
= is the annual average relative deposition of radionuclide (i) at distance r, in the sector at angle e, considering depletion of the plume by deposition during transport, in m-2. Table 4 A,
= is the radiological decay constant for radionuclide (i), in yr'.
1.0x1012 = is the number of pCi/Ci R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 91 OF 132 3.2.2A The annual organ dose is then calculated using the following equation:
G ~n G
D (r, 6) = 8760 Sf E C. (r, 6)DFGij i=1 Where:
C9r,B)
= is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle 0, in pCi/M2.
DFG'
= is the open field ground plane dose conversion factor for organ U) from radionuclide (i), in mrem-m 2/pCi-hr. (Table 8)
Dj~r,e)
= is the annual dose to the organ j) at distance r, in the sector at angle 0, in mrem/yr.
S.
= is the shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy, dimensionless. (Table 17) 8760
= is the number of hours in a year B. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide (i) at distance r, in the sector at angle 6, with respect to the release point, may be determined as:
X1(r,E) = 3.17 x 104Q,[XIQ]D(rG)
Where:
Q.
x,(r,)
=
is the annual release rate of radionuclide (i) to the atmosphere, in Cilyr.
= is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle 6, in pCi/M3.
[X/Q]D (r,E)
=
is the annual average atmosphere dispersion factor, in sec/M 3 (see Reg Guide 1.1 11). This includes depletion (for radioiodines and particulates) and radiological decay of the plume. (Table 4)
'-I 3.17x104
= is the number of pCi/Ci divided by the number of sec/yr.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 92 OF 132 3.2.2B The annual dose associated with inhalation of all radionuclides to organ
() of an individual in age group (a), is then:
An D. (re,)
= R. E X, (r10) DFAia ja=1 Where:
Dja(r,E)
= is the annual dose to organ (j) of an individual in the age group (a) at distance r, in the sector at angle 0, due to inhalation, in mrem/yr.
Ra
= is the annual air intake for individuals in the age group (a),
in m3l/yr. (Table 6)
DFAija
= is the inhalation dose factor for radionuclide (i), organ (),
and age group (a), in mrem/pCi. (Tables 9-12) 3.2.3 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases A.
Parameters for Calculating Concentrations in Forage, Produce, and Leafy Vegetables, excluding Tritium V
[r[1 - exp(-AE.e)] BJ[1 - exp(-Ah)]exp(-A/h)
Where:
Cv(r,E)
= is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle e, in pCi/kg.
d, (r,E)
= is the deposition rate of radionuclide (i) at distance r, in the sector at angle 0, in pCi/m2 hr.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 93 OF 132 3.2.3A The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa. C-6):
d,(r,e) = 1.1 x 1086,(r,e)Qi Where:
d,(r,G)
= is the deposition rate of radionuclide (i).
N(r,E)
= is the relative deposition of radionuclide (i), considering depletion and decay, in m-2 (see Reg Guide 1.111).
(Table 4) 1.1x108 = is the number of pCi/Ci (1012) divided by the number of hours per year (8760).
Q,
= is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 94 OF 132 3.2.3 B. For radioiodines, the model considers only the elemental fraction of the effluent:
d,(r,0) - 3.3 x 107 6,(r,0) Q, Where:
d, (r, 0)
= The deposition rate of radioiodine (i).
3.3 x 107 = The number of pCi/Ci (1012) divided by the number of hours per year (8760), then multiplied by the amount of radioiodine emissions considered to be elemental (0.5).
6, (r, 0) = The relative deposition of radioiodine (i), considering depletion and decay, in m2. (Table 4)
Q.
= The total (elemental and nonelemental) radioiodine (i) emission rate.
r
= is the fraction of deposited activity retained on crops, dimensionless. (Table 17)
AE,
= is the effective removal rate constant for radionuclide (i) from crops, in hr'.
AES = A, + A.
k = 0.0021/hr. (Table 17) te
= is the time period that crops are exposed to contamination during the growing season, in hours. (Table 17)
Yv1
= is the agricultural productivity (yield) in kg (wet weight)/m2.
(Table 17)
BIv
= is the concentration factor for uptake of radionuclide (i) from soil by edible parts of crops, in pCi/ kg (wet weight) per pCi/kg dry soil. (Table 5)
A 1
= is the radiological decay constant of radionuclide (I), in hr' tb
= is the period of time for which sediment or soil is exposed to the contaminated water, in hours (mid-point of plant life).
(Table 17)
P
= is the effective 'surface density" for soil, in kg (dry soil)/m2.
(Table 17) th
= is the holdup time that represents the time interval between harvest and consumption of the food, in hours. (Table 17)
Different values for the parameters te, Y4, and th, may be used to allow
- the use of the Equation for different purposes: estimating concentrations in produce consumed by, man; in leafy vegetables consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or goats; and in forage consumed as stored feed by dairy cows, beef cattle or goats. See Table 17.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 95 OF 132 3.2.3 C. Parameters for Calculating the Concentration of Radionuclide (i) in the Animal's Feed (Milk Cow, Beef Cow, and Goat)
CV(r,G) = f f pfC(rE), (1 -f,)CS(r,8) + fp(1 -f5)CS(r,8)
Where:
Cv,(r,8) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
Cjr,G)
= is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2.3C with th=0), in pCi/kg.
Cl(r,G)
= is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3C with th=90 days), in pCi/kg.
fp
= is the fraction of the year that animals graze on pasture.
(Table 17)
- f.
= is the fraction of daily feed that is pasture grass while the animal grazes on pasture. (Table 17) 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk CM(r,E) = F C V(r,8)QF exp(-A,tf)
Where:
Cm,(r,G) =
is the concentration of radionuclide (i) in milk, in pCi/liter.
Cv (r,e) =
is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
Fm
=
is the average fraction of the animal's daily intake of radionuclide (i) which appears in each liter of milk, in days/liter.
(Table 5)
QF
=
is the amount of feed consumed by the animal per day, in kg/day. (Table 7) t
=
is the average transport time of the radionuclide (i) from the feed to the milk and to the receptor (a value of 2 days is assumed). (Table 17)
A;
=
is the radiological decay constant of radionuclide (i), in days-'.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 96 OF 132 3.2.5 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium CF(r,G) = FfC V(re)QF exp(-Atf)
Where:
Cl (r,e)
=
is the concentration of radionuclide (i) in meat, in pCi/liter.
F.
=
is the average fraction of the animal's daily intake of radionuclide (i) which appears in each kilogram of flesh, in days/kilogram. (Table 5) t
=
is the average time from slaughter to consumption. (Table 17) 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.
CV(re) = 3.17 x 107Q, [x/Q] (r'8) (0.75) (0.5) = 1.2 x 107Q [x/Q] (r,0)
TH H
Where:
CT(r, 0) =
is the concentration of tritium in vegetation grown at distance r, in the sector at angle 6, in pCi/kg.
H
=
is the absolute humidity of the atmosphere at distance r, in the sector at angle 6, in g/m3. H=8 gm/kg.
QT
=
is the annual release rate of tritium, in Ci/yr.
/Q](rG)
=
is the atmospheric dispersion factor, in sec/m3. (Table 4) 0.5
=
is the ratio of tritium concentration in plant water to tritium concentration in atmospheric water, dimensionless.
0.75
=
is the fraction of total plant mass that is water, dimensionless.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 97 OF 132 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Foods A.
The total annual dose to organ (j) of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by:
D(r)= DFIa UfC(re) +
C r)
- UFCF(re)
U LLfCL(re)]
Where:
Da(r,8)
= is the annual dose to organ d) of an individual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem/yr.
DFl,,a
= is the dose conversion factor for the ingestion of radionuclide (i), organ (), and age group (a), in mrem/pCi.
Tables 13-16.
UvUm
= are the ingestion rates of produce (non-leafy vegetables, fruits, and grains); milk, meat, and leafy a, vegetables, respectively for individuals in age group (a). (Table 6) fg
= Fraction of ingested produce grown in garden of interest (Table 17) f,
= Fraction of leafy vegetables grown in garden of interest (Table 17)
B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce)
Vegetation for Radionuclide (i) to Each Organ U) and Age Group (a)
D1P(rG) = DFl fClvm - UV CJ(rm) jj a
aa cLrO uafcV e Where:
Da(r,e)
= is the annual dose from the ingestion of radionuclide (i) to organ () of an individual in age group (a) from dietary intake of atmospherically released radionuclides in vegetation, in mrrem/yr.
DFlija
= is the dose conversion factor for the ingestion of radionuclide (i), organ U), and age group (a), in mrem/pci.
Tables 13-16 UaUa
= are the ingestion rates of leafy vegetables and produce (non-leafy vegetables, fruits, and grains), for individuals in age group (a), in kg/yr. (Table 6)
CL,
= is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.
Ci V
= is the concentration of radionuclide (i) in and on produce, in pCi/kg.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 98 OF 132 3.2.7 C. Calculation Determining the Ingested Dose from Cow Milk for Radionuclide (i), Organ (), and Age Group (a)
DD(r6e) = DFILja [LMCMt)]
Where:
DaD(r,()
= is the annual dose from the ingestion of radionuclide (i),
organ () of an individual in age group (a) from dietary intake of atmospherically released radionuclides in cow milk, in mrem/yr.
DFIija
= is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi.
(Tables 13-16)
UM
= is the ingestion rate of cow milk for individuals in age group (a), in f/yr. (Table 6)
= is the radionuclide concentration in cow milk, in pCi/kg.
Equation 3.2.4 D. Calculation Determining the Ingested Dose from Meat for Radionuclide (i) to Organ 0) and Age Group (a)
D D(rE6) = DFIija [UFCi(re)]
jaFlia Where:
Djd (r,e)
= is the annual dose from the ingestion of radionuclide (i),
organ 0) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in meat, in mrem/yr.
DFIija
= is the dose conversion factor for the ingestion of radionuclide (i), organ (), and age group (a), in mrem/pCi.
(Tables 13-16)
= is the ingestion rate of meat for individuals in age group (a),
in kg/yr. (Table 6)
= is the radionuclide (i) concentration in meat, in pCi/kg.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 99 OF 132
- 4. LOWER LIMIT OF DETECTION (LLD)
The lower limit of detection (LLD) for liquid and airborne effluent discharges and environmental samples referenced in Part I, Tables 3.1, 3.2, and 4.3 is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD -
4.66
- sb E
- V
- D
- Y
- exp(-AAt)
Where:
LLD= the lower limit of detection as defined above, in either picoCuries or microCuries, per unit mass or volume as a function of the value of D Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate, as counts per minute E = the counting efficiency, as counts per disintegration V = the sample size in units of mass or volume D
2.22E+06 of disintegrations per minute per microCurie or 2.22 disintegrations per minute per picoCurie Y = the fractional radiochemical yield, when applicable A = the radioactive decay constant for the particular radionuclide At = the elapsed time between the midpoint of sample collection and time of counting Appropriate values of E, V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an A Priori limit representing the capability of a measurement system and not as a limit for a particular measurement.
LLD verifications will be performed on a periodic basis. This determination is to ensure that the counting system is able to detect levels of radiation at the LLD values for the specific type of analysis required. They will be performed with a blank (non-radioactive) sample in the same counting geometry as the actual sample.
R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE PAGE 100 OF 132 Table 2 - Dose Factors for Exposure to a Semi-infinite Cloud of Noble Gases Nuclide
,-Air' (Dfl)
P-Skin2 (DFS,)
y-Air' (Df')
y-Body2 (DFB,)
Kr-83m 2.88E-04 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61 E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01 E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131 m 1.11E-03 4.67E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51 E-04 Xe-1 33 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11 E-04 3.36E-03 3.12E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81 E-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xe-138 4.75E-03 4.13E-03 9.21 E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 1
mrad-m3 pci - yr 2
mrem - ml nCi - vr 3
2.88E-04 = 2.88 x 104 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 101 OF 132 Table 3 - Bioaccumulation Factors (pCilkg per pCilliter)
FRESHWATER Element Fish Invertebrate H
9.OE-01 9.OE-01 C
4.6E+03 9.1 E+03 Na 1.OE+02 2.OE+02 P
1.OE+05 2.OE+04 Cr 2.OE+02 2.0E+03 Mn 4.OE+02 9.OE+04 Fe 1.OE+02 3.2E+03 Co 5.OE+01 2.OE+02 Ni 1.OE+02 1.OE+02 Cu 5.OE+01 4.OE+02 Zn 2.OE+03 1.OE+04 Br 4.2E+02 3.3E+02 Rb 2.OE+03 1.OE+03 Sr 3.OE+01 1.OE+02 Y
2.5E+01 1.OE+03 Zr 3.3E+00 6.7E+OO Nb 3.OE+04 1.OE+02 Mo 1.OE+01 1.OE+01 Tc 1.5E+01 5.OE+OO Ru 1.OE+01 3.OE+02 Rh 1.OE+01 3.OE+02 Te 4.OE+02 6.1 E+03 I
1.5E+01 5.OE+OO Cs 2.OE+03 1.OE+03 Ba 4.OE+00 2.OE+02 La 2.5E+01 1.OE+03 Ce 1.OE+00 1.OE+03 Pr 2.5E+01 1.OE+03 Nd 2.5E+01 1.OE+03 W
1.2E+03 1.OE+01 Np 1.OE+01 4.OE+02 JU R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 102 OF 132 Table 4 - Highest Potential Exposure Pathways for Estimating Dose NOTE: The Annual Radiological Effluent Report uses the highest calculated value from real time meteorological data obtained for the entire year for calculating dose.
Exposure Location Direction Distance XIQ I DIQ 1 Pathway 2
2 from
{XIQ (r,O)}
{6 (r,O)}
Containment (sec/M 3)
(m2)
(miles) 2 Direct Exposure Site WNW 0.70 1.04E-05 N /A Boundary Inhalation Site WNW 0.70 1.04E-05 N IA Boundary Ingestion Residence SSE 0.88 N /A 1.6 E-08 These values are used for calculating quarterly dose estimates during the annual reporting period and are based on a 2 year average, updated only upon a +10% change from the previous value. Ten percent (10%)
should be added to these values for dose estimates during the reporting periods.
2 The location is subject to change based on an annual evaluation and is utilized only for ingestion exposure pathway dose estimates. This location may differ from the highest ingestion exposure pathway for offsite air monitoring locations as determined by the Land Use Survey performed biennially in accordance with Part 1, Section 6.3.2.
R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL CH-ODCM-0001 PAGE 103 OF 132 REFERENCE USE Table 5 - Stable Element Transfer Data J
B, Fm (cow)
F.
Element Veg./Soil Milk (d/A)
Meat (d/kg)
H 4.8E+00 1.OE-02 1.2E-02 C
5.5E+00 1.2E-02 3.1 E-02 Na 5.2E-02 4.OE-02 3.0E-02 P
1.1 E+00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.OE-02 Co 9.4E-03 1.OE-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1 E-02 Sr 1.7E-02 8.0E-04 6.0E-04 Y
2.6E-03 1.OE-05 4.6E-03 Zr 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.OE-01 Ru 5.OE-02 1.0E-06 4.0E-01 Rh 1.3E+1 1.OE-02 1.5E-03 Ag 1.5E-01 5.OE-02 1.7E-02 Te 1.3E+00 1.0E-03 7.7E-02 I
2.0E-02 6.0E-03 2.9E-03 Cs 1.OE-02 1.2E-02 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Ce 2.5E-03 1.OE-04 1.2E-03 Pr 2.5E-03 5.OE-06 4.7E-03 Nd 2.4E-03 5.OE-06 3.3E-03 W
1.8E-02 5.OE-04 1.3E-03 Np 2.5E-03 5.OE-06 2.0E-04
'-I
-J R12
FORT CALHOUN STATION CH-ODCM-0001 OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE..
PAGE 104 OF 132 Table 6 - Recommended Values for UaP to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data Pathway Infant Child Teen Adult Fruits, vegetables, & grain (kg/yr) 520 630 520 Leafy vegetables (kg/yr) 26 42 64 Milk (Q/yr) 330 330 400 310 Meat & poultry (kg/yr) 41 65 110 Fish (fresh or salt)(kg/yr) 6.9 16 21 Other Seafood (kg/yr) -
1.7 3.8 5
Drinking water (Q/yr) 330 510 510 730 Shoreline recreation (hr/yr) 14 67
- 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table 7 - Animal Consumption Rates Animal QF Feed or Forage [Kg/day (wet weigh)]
QAW Water (e/day)
Milk Cow 50 60 Beef Cattle 50 50 Goats 68 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-000 1 PAGE 105 OF 132 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Page 1 of 2 ELEMENT TOTAL BODY SKIN H-3 C-14 Na-24 2.50E-08 2.90E-08 P-32 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 Fe-59 8.OOE-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 Br-83 6.40E-11 9.30E-1 1 Br-84 1.20E-08 1.40E-08 Br-85 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.1 OE-09 8.30E-09 Sr-92 9.00E-09 1.OOE-08 Y-90 2.20E-12 2.60E-12 Y-91 M 3.80E-09 4.40E-09 Y-91 2.40E-1 1 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.OOE-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09
'JI R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 106 OF 132 Table 8 (continued)
Page 2 of 2 ELEMENT TOTAL BODY SKIN Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1 1.50E-09 1.80E-09 Ag-1OM 1.80E-08 2.1OE-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.1OE-12 1.30E-12 Te-127 1.OOE-i1 1.1OE-11 Te-129M
-7.70E-10 9.OOE-10 Te-129 7.1OE-10.
8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-1 32 1.70E-09 2.00E-09 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.OOE-08 I-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-1 36 1.50E-08 1.70E-08 Cs-1 37 4.20E-09 4.90E-09 Cs-138 2.1OE-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.1OE-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.OOE-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 Pr-144 2.OOE-10.
2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.1OE-09 3.60E-09 Np-239 9.50E-10 1.10E-09 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
CH-ODCM-0001 PAGE 107 OF 132 Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 1.08E-05 Cr-51 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 4.95E-06 7.87E-07 1.23E-06 1.75E-04 9.67E-06 Mn-56 1.55E-10 2.29E-11 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 9.01 E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 1.27E-04 2.35E-05 Co-58 1.98E-07 2.59E-07 1.16E-04 1.33E-05 Co-60 1.44E-06 1.85E-06 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 7.OOE-07 1.54E-06 Cu-64 1.83E-10 7.69E-11 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 5.27E-12 1.15E-07 2.04E-09 Br-83 3.01 E-08 2.90E-08 Br-84 3.91 E-08 2.05E-13 Br-85 1.60E-09 Rb-86 1.69E-05 7.37E-06 2.08E-06 Rb-88 4.84E-08 2.41 E-08 4.18E-19 Rb-89 3.20E-08 2.12E-08 1.16E-21 Sr-89 3.80E-05 1.09E-06 1.75E-04 4.37E-05 Sr-90 3.59E-03 7.21 E-05 1.20E-03 9.02E-05 Sr-91 7.74E-09 3.13E-10 4.56E-06 2.39E-05 Sr-92 8.43E-10 3.64E-11 2.06E-06 5.38E-06 Y-90 2.61 E-07 7.01 E-09 2.12E-05 6.32E-05 Y-91 M 3.26E-11 1.27E-12 2.40E-07 1.66E-10 I
R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE z
CH-ODCM-0001 PAGE 108 OF 132 Table 9 (continued)
Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-91 5.78E-05 1.55E-06 2.13E-04 4.81 E-05 Y-92 1.29E-09 3.77E-11 1.96E-06 9.19E-06 Y-93 1.18E-08 3.26E-10 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91 E-06 6.77E-06 2.21 E-04 1.88E-05 Zr 1.21 E-08 2.45E-09 1.13E-09 3.71 E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 9.67E-07 6.31 E-05 1.30E-05 Mo-99 1.51 E-08 2.87E-09 3.64E-08 1.14E-05 3.1 OE-05 Tc-99M 1.29E-13 3.64E-13 4.63E-12 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91 E-07 8.23E-08.
7.29E-07 6.31 E-05 1.38E-05 Ru-1 05 9.88E-1 I 3.89E-11 1.27E-1 0 1.37E-06 6.02E-06 Ru-106 8.64E-06 1.09E-06 1.67E-05 1.17E-03 1.14E-04 Ag-11 OM 1.35E-06 1.25E-06 7.43E-07 2.46E-06 5.79E-04 3.78E-05 Te-125M 4.27E-07 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21 E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-1 29M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131 M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 9.61 E-07 1-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 7.85E-07 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 5.08E-08 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 1.11 E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 1.26E-10 1-135 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 6.56E-07 Cs-I34 4.66E-05 1.06E-04 9.1 OE-05 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 1.07E-05 1.50E-06 1.46E-06 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 109 OF 132 Table 9 (continued)
Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Cs-137 5.98E-05 7.76E-05 5.35E-05 2.78E-05 9.40E-06 1.05E-06 Cs-1 38 4.14E-08 7.76E-08 4.05E-08 6.OOE-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21 E-07 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41 E-15 4.20E-13 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 7.91 E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91 E-07 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91 E-09 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 2.70E-07 3.51 E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91 E-13 8.81 E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.1OE-10 3.63E-06 1.94E-05 Np-239 2.87E-08 2.54E-08 1.55E-09 8.75E-09 4.70E-06 1.49E-05
,*~
R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE, Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
CH-ODCM-0001 PAGE 110 OF 132 Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.019E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 1.16E-05 Cr-51 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 6.39E-06 1.05E-06 1.59E-06 2.48E-04 8.35E-06 Mn-56 2.12E-10 3.15E-11 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 1.91 E-04 2.23E-05 Co-58 2.59E-07 3.47E-07 1.68E-04 1.19E-05 Co-60 1.89E-06 2.48E-06 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 1-1.17E-06 4.59E-06 Cu-64 2.54E-10 1.06E-10 8.01 E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 7.53E-12 1.98E-07 3.56E-08 Br-83 4.30E-08 Br-84 5.41 E-08 Br-85 2.29E-09 Rb-86 2.38E-05 1.05E-05 2.21 E-06 Rb-88 6.82E-08 3.40E-08 3.65E-15 Rb-89 4.40E-08 2.91 E-08 4.22E-17 Sr-89 5.43E-05 1.56E-06 3.02E-04 4.64E-05 Sr-90 4.14E-03 8.33E-05 2.06E-03 9.56E-05 Sr-91 1.1OE-08 4.39E-10 7.59E-06 3.24E-05 Sr-92 1.19E-09 5.08E-11 3.43E-06 1.49E-05 Y-90 3.73E-07 1.OOE-08 3.66E-05 6.99E-05 Y-91 M 4.63E-11 1.77E-12 4.OOE-07 3.77E-09 Y-91 8.26E-05 2.21 E-06 3.67E-04 5.11E-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 111 OF 132 Table 10 (continued)
Page 2 of 3 J~
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 1.84E-09 5.36E-11 3.35E-06 2.06E-05 Y-93 1.69E-08 4.65E-10 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 1.25E-06 9.39E-05 1.21 E-05 Mo-99 2.11 E-08 4.03E-09 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 1.12E-07 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 5.42E-11 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 1.55E-06 2.38E-05 2.01 E-03 1.20E-04 Ag-1I OM 1.73E-06 1.64E-06 9.99E-07 3.13E-06 8.44E-04 3.41 E-05 Te-125M 6.1 OE-07 2.80E-07 8.34E-08 1.75E-07 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51 E-10 1.14E-10 5.52E-11 1.77E-10 9.1 OE-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131 M 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-1 32 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 1-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 1.14E-06 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 8.11E-07 1-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 1.29E-06 1-134 1.11 E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 2.55E-09 1-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 8.69E-07 Cs-1 34 6.28E-05 1.41 E-04 6.86E-05 4.69E-05 1.83E-05 1.22E-06 Cs-1 36 6.44E-06 2.42E-05 1.71 E-05 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 3.80E-05 1.51 E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 I 8.28E-08 9.84E-09 3.38E-11 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE, CH-ODCM-0001 PAGE 112 OF 132 Table 10 (continued)
Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 1.67E-10 1.18E-13 4.87E-12 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 1.23E 4.11 E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 3.92E-15 2.39E-07 5.99E-20 La-1 40 5.99E-08 2.95E-08 7.82E-09 2.68E-05 6.09E-05 La-142 1.20E-10 5.31 E-11 1.32E-11 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71 E-07 1.11 E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11 E-04 2.53E-04 3.28E-05 1.51 E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41 E-08 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 5.92E-06 2.21 E:05 Np-239 4.23E-08 3.60E-08 2.21 E-09 1.25E-08 8.11 E-06 1.65E-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
CH-ODCM-0001 PAGE 113 OF 132 Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 1.14E-05 Cr-51 4.17E-08 2.31 E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 1.16E-05 2.57E-06 2.71 E-06 4.26E-04 6.19E-06 Mn-56 4.48E-10 8.43E-11 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.1OE-06 3.OOE-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51 E-06 3.43E-04 1.91 E-05 Co-58 4.79E-07 8.55E-07 2.99E-04 9.29E-06 Co-60 3.55E-06 6.12E-06 1.91 E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 7.43E-05 1.71 E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 2.21 E-06 2.27E-05 Cu-64 5.39E-10 2.90E-10 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 1.93E-05 2.69E-04 4.41 E-06 Zn-69 1.81 E-11 2.61 E-11 2.41 E-12 1.58E-11 3.84E-07 2.75E-06 Br-83 1.28E-07 Br-84 1.48E-07 Br-85 6.84E-09 Rb-86 5.36E-05 3.09E-05 2.16E-06 Rb-88 1.52E-07 9.90E-08 4.66E-09 Rb-89 9.33E-08 7.85E-08 5.11E-10 Sr-89 1.62E-04 4.66E-06 5.83E-04 4.52E-05 Sr-90 1.04E-02 2.07E-04 3.99E-03 9.28E-05 Sr-91 3.28E-08 1.24E-09 1.44E-05 4.70E-05 Sr-92 3.54E-09 1.42E-10 6.49E-06 6.55E-05 Y-90 1.11 E-06 2.99E-08 7.07E-05 7.24E-05 Y-91M 1.37E-10 4.98E-12 7.60E-07 4.64E-07 Y-91 2.47E-04 6.59E-06 7.1OE-04 4.97E-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE' CH-ODCM-0001 PAGE 114 OF 132 Table 11 (continued)
Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 5.50E-09 1.57E-10 6.46E-06 6.46E-05 Y-93 5.04E-08 1.38E-09 2.01 E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.OOE-05 1.61 E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 2.33E-06 1.66E-04 1.OOE-05 Mo-99 4.66E-08 1.15E-08 1.06E-07 3.66E-05 3.42E-05 Tc-99M 4.81 E-13 9.41 E-13 1.56E-11 1.37E-1I 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91 E-13 3.92E-13 1.58E-07 4.41 E-09 Ru-103 7.55E-07 2.90E-07 1.90E-06 1.79E-04 1.21 E-05 Ru-105 4.13E-10 1.50E-10 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 4.57E-06 4.97E-05 3.87E-03 1.16E-04 Ag-I1 OM 4.56E-06 3.08E-06 2.47E-06 5.74E-06 1.48E-03 2.71 E-05 Te-125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 1.29E-04 9.13E-06 Te-127M 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1.72E-05 4.O0E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71 E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91 E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-1I 6.94E-11 7.93E-07 6.89E-06 Te-131 M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 1.38E-06 1-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 7.68E-07 1-132 5.72E-07 1.1OE-06 5.07E-07 5.23E-05 1.69E-06 8.65E-07 1-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 1.48E-06 1-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 2.58E-07 1-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 7.63E-05 2.81 E-05 9.78E-07 Cs-1 38 1.71 E-07 2.27E-07 1.50E-07 1.68E-07 1.84E-08 7.29E-08 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 115 OF 132 Table 11 (continued)
Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 4.98E-10 2.66E-13 1.45E-11 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.OOE-05 1.75E-08 1.17E-06 5.71 E-09 4.71 E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 7.87E-15 4.44E-07 7.41 E-10 La-140 1.74E-07 6.08E-08 2.04E-08 4.94E-05 6.1 OE-05 La-142 3.50E-10 1.11E-10 3.49E-11 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 2.31 E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 8.11 E-07 1.17E-04 2.63E-05 Pr-144 1.61 E-11 4.99E-12 8.1OE-13 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 1.30E-06 8.87E-05 2.22E-05 W-187 4.41 E-09 2.61 E-09 1.17E-09 1.1 E-05 2.46E-05 Np-239 1.26E-07 8.14E-08 6.35E-09 2.63E-08 1.57E-05 1.73E-05 1__2 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE -
Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
CH-ODCM-0001 PAGE 116 OF 132 Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 1.15E-05 Cr-51 6.39E-08 4.11 E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54
-1.81 E-05 3.56E-06 3.56E-06 7.14E-04 5.04E-06 Mn-56 1.1OE-09 1.58E-10 7.86E-10
-8.95E-06 5.12E-05 Fe-55 1.41 E-05 8.39E-06 2.38E-06 6.21 E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 7.25E-04 1.77E-05 Co-58 8.71 E-07 1.30E-06 5.55E-04 7.95E-06 Co-60 5.73E-06 8.41 E-06 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 1.49E-04 1.73E-06 Ni-65 1.71 E-09 2.03E-10 8.79E-11 5.80E-06 3.58E-05 Cu-64 1.34E-09 5.53E-10 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91 E-11 5.13E-12 2.87E-11 1.05E-06 9.44E-06 Br-83 2.72E-07 Br-84 2.86E-07 Br-85 1.46E-08 Rb-86 1.36E-04 6.30E-05 2.17E-06 Rb-88 3.98E-07 2.05E-07 2.42E-07 Rb-89 2.29E-07 1.47E-07 4.87E-08 Sr-89 2.84E-04 8.15E-06 1.45E-03 4.57E-05 Sr-90 1.11 E-02 2.23E-04 8.03E-03 9.36E-05 Sr-91 6.83E-08 2.47E-09 3.76E-05 5.24E-05 Sr-92 7.50E-09 2.79E-10 1.70E-05 1.OOE-04 Y-90 2.35E-06 6.30E-08 1.92E-04 7.43E-05 Y-91M 2.91E-10 9.90E-12 1.99E-06 1.68E-06 Y-91 4.20E-04 1.12E-05 1.75E-03 5.02E-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 117 OF 132 Table 12 (continued)
Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 1.17E-08 3.29E-10 1.75E-05 9.04E-05 Y-93 1.07E-07 2.91 E-09 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 1.85E-08 7.88E-05 1.OOE-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 3.37E-06 3.42E-04 9.05E-06 Mo-99 1.18E-07 2.31 E-08 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-1 3 2.06E-1 2 2.66E-1 1 2.22E-1 1 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 6.99E-13 4.17E-07 6.03E-07 Ru-1 03 1.44E-06 4.85E-07 3.03E-06 3.94E-04 1.15E-05 Ru-1 05 8.74E-10 2.93E-10 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 7.77E-06 7.61 E-05 8.26E-03 1.17E-04 Ag-i1 OM 7.13E-06 5.16E-06 3.57E-06 7.80E-06 2.62E-03 2.36E-05 Te-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81 E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01 E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131 M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-1 32 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1-130 4.54E-06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 1.42E-06 1-131 2.71 E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 7.56E-07 1-132 1.21 E-06 2.53E-06 8.99E-07 1.21 E-04 2.82E-06 1.36E-06 1-133 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 1.54E-06 1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 9.21 E-07 1-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 1.31 E-06 Cs-1 34 2.83E-04 5.02E-04 5.32E-05 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61 E-05 3.78E-05 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 1.23E-04 5.09E-05 9.53E-07 Cs-1 38 3.61 E-07 5.58E-07 2.84E-07 2.93E-07 4.67E-08 6.26E-07 J_2 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE I CH-ODCM-0001 PAGE 118 OF 132 Table 12 (continued)
Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-1 39 1.06E-09 7.03E-13 3.07E-1 I 4.23E-1 3 4.25E-06 3.64E-05 Ba-140 4.OE-05 4.OE-08 2.07E-06 9.59E-09 i.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 1.36E-14 111E-06 4.95E-07 La-140 3.61 E-07 1.43E-07 3.68E-08 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.OOE-05 3.74E-06 4.99E-07 1.41 E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-1I 1.72E-12 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81 E-06 3.57E-07 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 2.83E-05 2.54E-05 Np-239 2.65E-07 2.13E-07 1.34E 4.73E-08 4.25E-05 I 1.78E-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
CH-ODCM-0001 PAGE 119 OF 132 N-Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 2.17E-05 Cr-51 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 4.57E-06 8.72E-07 1.36E-06 1.40E-05 Mn-56 1.15E-07 2.04E-08 1.46E-07 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91 E-06 2.85E-06 3.40E-05 Co-58 7.45E-07 1.67E-06 1.51 E-05 Co-60 2.14E-06 4.72E-06 4.02E-05 Ni-63 1.30E-04 9.01 E-06 4.36E-06 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 1.74E-06 Cu-64 8.33E-08 3.91E-08 2.1OE-07 7.1OE-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 1.03E-05 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 1.28E-08 2.96E-09 Br-83 4.02E-08 5.79E-08 Br-84 5.21 E-08 4.09E-13 Br-85 2.14E-09 Rb-86 2.11 E-05 9.83E-06 4.16E-06 Rb-88 6.05E-08 3.21 E-08 8.36E-19 Rb-89 4.01 E-08 2.82E-08 2.33E-21 Sr-89 3.08E-04 8.84E-06 4.94E-05 Sr-90 8.71 E-03 1.75E-04 2.19E-04 Sr-91 5.67E-06 2.29E-07 2.70E-05 Sr-92 2.15E-06 9.30E-08 4.26E-05 Y-90 9.62E-09 2.58E-10 1.02E-04 Y-91 M 9.09E-11 3.52E-12 2.67E-10 Y-91 1.41 E-07 3.77E-09 7.76E-05 R12
FORT CALHOUN STATION 11, OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 120 OF 132 Table 13 (continued)
Page 2 of 3
- Nuclide, Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 8.45E-1 0 2.47E-11 1.48E-05 Y-93 2.68E-09 7.40E-l1 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 1.53E-08 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 5.12E-10 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 3.42E-09 2.1 OE-05 Mo-99 4.31 E-06 8.20E-07 9.76E-06 9.99E-06 Tc-99M 2.47E-10 6.98E-10 8.89E-09 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 6.59E-09 1.87E-10 1.1 OE-21 Ru-1 03 1.85E-07 7.97E-08 7.06E-07 2.16E-05 Ru-1 05 1.54E-08 6.08E-09 1.99E-07 9.42E-06 Ru-106 2.75E-06 3.48E-07 5.31 E-06 1.78E-04 Ag-11OM 1.60E-07 1.48E-07 8.79E-08 2.91 E-07 6.04E-05 Te-125M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 2.27E-05 Te-127 1.1OE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 2.37E-08 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 8.40E-05 Te-1 31 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 7.71 E-05 1-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 1.92E-06 1-131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.9OE-05 8.65E-07 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 2.51 E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 1.31 E-06 Cs-134 6.22E-05 1.48E-04 1.21 E-04 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51 E-06 2.57E-05 1.85E-05 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 3.70E-05 1.23E-05 2.11 E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 8.01 E-08 7.91 E-09 4.65E-13 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 121 OF 132 U
Table 13 (continued)
Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 9.70E-08 6.91 E-11 2.84E-09 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71 E-08 3.56E-11 1.59E-09 3.31 E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 1.85E-11 1.24E-11 3.OOE-26 La-140 2.50E-09 1.26E-09 3.33E-10 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 2.94E-09 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 5.37E-10 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 1.21 E-07 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 2.13E-09 4.03E-05 Pr-144 3.01 E-11 1.25E-11 1.53E-12 7.05E-12 4.33E-18 Nd-1 47 6.29E-09 7.27E-09 4.35E-10 4.25E-09 3.49E-05 W-187 1.03E-07 8.61 E-08 3.01 E-08 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 3.65E-10 2.40E-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE, Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
CH-ODCM-0001 PAGE 122 OF 132 Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71 E-05 1.07E-05 2.32E-05 Cr-51 3.60E-09 2.OOE-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 5.90E-06 1.17E-06 1.76E-06 1.21 E-05 Mn-56 1.58E-07 2.81 E-08 2.OOE-07 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 4.32E-06 3.24E-05 Co-58 9.72E-07 2.24E-06 1.34E-05 Co-60 2.81 E-06 6.33E-06 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.OOE-06 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 5.19E-06 Cu-64 1.15E-07 5.41 E-08 2.91 E-07 8.92E-06 Zn-65 5.76E-06 2.OE-05 9.33E-06 1.28E-05 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 1.83E-08 5.16E-08 Br-83 5.74E-08 Br-84 7.22E-08 Br-85 3.05E-09 Rb-86 2.98E-05 1.40E-05 4.41 E-06 Rb-88 8.52E-08 4.54E-08.
7.30E-15 Rb-89 5.50E-08 3.89E-08 8.43E-17 Sr-89 4.40E-04 1.26E-05 5.24E-05 Sr-90 1.02E-02 2.04E-04 2.33E-04 Sr-91 8.07E-06
-3.21 E-07 3.66E-05 Sr-92 3.05E-06 1.30E 7.77E-05 Y-90 1.37E-08 3.69E _
1.13E-04 Y-91M 1.29E-10 4.93E-12 6.09E-09 Y-91 2.01 E-07 5.39E-09 8.24E-05 R12
J__)
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 123 OF 132 Table 14 (continued)
Page 2 of3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 1.21 E-09 3.50E-11 3.32E-05 Y-93 3.83E-09 1.05E-10 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 1.91 E-08 3.OOE-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 7.1 E-10 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51 E-09 4.42E-09 1.95E-05 Mo-99 6.03E-06 1.15E-06 1.38E-05 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 1.09E-07 8.99E-07 2.13E-05 Ru-105 2.18E-08 8.46E-09 2.75E-07 1.76E-05 Ru-106 3.92E-06 4.94E-07 7.56E-06 1.88E-04 Ag-11OM 2.05E-07 1.94E-07 1.18E-07 3.70E-07 5.45E-05 Te-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 1.13E-05 Te-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 2.41 E-05 Te-1 27 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 1.22E-05 Te-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 2.45E-07 Te-131 M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 2.29E-09 Te-132 3.49E-06 2.21 E-06 2.08E-06 2.33E-06 2.12E-05 7.OOE-05 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 1.62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 3.18E-07 1-133 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 2.58E-06 1-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.1 OE-07 5.1 OE-09 1-135 6.1 OE-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 5.07E-05 1.97E-05 2.12E-06 Cs-1 38 7.76E-08 1.49E-07 7.45E-08 1.1 OE-07 1.28E-08 4.76E-1 1
'-I J~~
R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 124 OF 132
~i, '
Table 14 (continued) t i
Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 1.39E-07 9.78E-11 4.05E-09 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 1.1 8E-08 2.34E-08 4.38E-05 Ba-141 6.71 E-08 5.01 E-11 2.24E-09 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71 E-09 4.55E-10 9.28E-05 La-142 1.79E-10 7.95E-11 1.98E-11 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 4.18E 2.54E-05 Ce-143 2.35E-09 1.71 E-06 1.91 E-10 7.67E-10 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 1.72E-07 1.75E-04 Pr-143 1.31 E-08 5.23E-09 6.52E-10 3.04E-09 4.31 E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 1.01 E-11 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11 E-10 5.99E-09 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 5.21 E-10 2.67E-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
CH-ODCM-0001 PAGE 125 OF 132
'-I Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 C-14 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 2.28E-05 Cr-51 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 1.07E-05 2.85E-06 3.OOE-06 8.98E-06 Mn-56 3.34E-07 7.54E-08 4.04E-07 4.84E-05 Fe-55 1.15E-05 6.1 OE-06 1.89E-06 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 7.74E-06 2.78E-05 Co-58 1.80E-06 5.51 E-06 1.05E-05 Co-60 5.29E-06 1.56E-05 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 2.56E-05 Cu-64 2.45E-07 1.48E-07 5.92E-07 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 2.30E-05 6.41 E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 3.84E-08 3.99E-06 Br-83 1.71 E-07 Br-84 1.98E-07 Br-85 9.12E-09 Rb-86 6.70E-05 4.12E-05 4.31 E-06 Rb-88 1.90E-07 1.32E-07 9.32E-09 Rb-89 1.17E-07 1.04E-07 1.02E-09 Sr-89 1.32E-03 3.77E-05 5.11 E-05 Sr-90 2.56E-02 5.15E-04 2.29E-04 Sr-91 2.40E-05 9.06E-07 5.30E-05 Sr-92 9.03E-06 3.62E-07 1.71 E-04 Y-90 4.11E-08 1.10E-09 1.17E-04 Y-91 M 3.82E-10 1.39E-11 7.48E-07 Y-91 6.02E-07 1.61 E-08 8.02E-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE,,
CH-ODCM-0001 PAGE 126 OF 132 Table 15 (continued)
Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 3.60E-09 1.03E-10 1.04E-04 Y-93 1.14E-08 3.13E-10 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 3.65E-08 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 1.45E-09 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 8.23E-09 1.62E-05 Mo-99 1.33E-05 3.29E-06 2.84E-05 1.10E-05 Tc-99M 9.23E-10 1.81 E-09 3.OOE-08 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 1.91 E-08 5.92E-10 3.56E-09 Ru-103 7.31 E-07 2.81 E-07 1.84E-06 1.89E-05 Ru-105-6.45E-08 2.34E-08 5.67E-07 4.21 E-05 Ru-106 1.17E-05 1.46E-06 1.58E-05 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91 E-07 6.78E-07 4.33E-05 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 1.1OE-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 2.34E-05 Te-127 4.71 E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 8.34E-06 Te-131 M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41 E-05 1.01 E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51 E-06 4.15E-05 4.50E-05 1-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 2.76E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 1.54E-06 1-132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 1.73E-06 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 2.95E-06 1-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 5.16E-07 1-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.1OE-05 1.19E-04 4.27E-05 2.07E-06 Cs-1 36 2.35E-05 6.46E-05 4.18E-05 3.44E-05 5.13E-06 2.27E-06 Cs-1 37 3.27E-04 3.13E-04 4.62E-05 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01 E-07 2.23E-07 2.40E-08 1.46E-07 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 127 OF 132 Table 15 (continued)
Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 4.14E-07 2.21 E-10 1.20E-08 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31 E-05 7.28E-08 4.85E-06 2.37E-08 4.34E-08 4.21 E-05 Ba-141 2.OOE-07 1.12E-10 6.51E-09 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 3.31 E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 8.68E-09 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 1.59E-09 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11 E-07 3.61 E-07 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 6.39E-09 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 2.11 E-11 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 1.24E-08 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 1.09E-09 2.79E-05 I_4 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
CH-ODCM-0001 PAGE 128 OF 132 Page 1 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 1.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01 E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01 E-05 P-32 1.70E-03 1.OOE-04 6.59E-05.
2.30E-05 Cr-51 1.41 E-08 9.20E-09 2.01 E-09 1.79E-08 4.1 E-07 Mn-54 1.99E 4.51 E-06 4.41 E-06 7.31 E-06 Mn-56 8.18E-07 1.41 E-07 7.03E-07 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 4.36E-06 1.14E-06 Fe 3.08E-05 5.38E-05 2.12E-05 1.59E-05 2.57E-05 Co-58 3.60E-06 8.98E-06 8.97E-06 Co-60 1.08E-05 2.55E-05 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 4.05E-05 Cu-64 6.09E-07 2.82E-07 1.03E-06 1.25E-05 Zn-65 1.84E-05 6.31 E-05 2.91 E-05 3.06E-05 5.33E-05 Zn-69 9.33E-08
-1.68E-07 1.25E-08 6.98E-08 1.37E-05 Br-83 3.63E-07 Br-84 3.82E-07 Br-85 1.94E-08 Rb-86 1.70E-04 8.40E-05 4.35E-06 Rb-88 4.98E-07 2.73E-07 4.85E-07 Rb-89 2.86E-07 1.97E-07 9.74E-08 Sr-89 2.51 E-03 7.20E-05 5.16E-05 Sr-90 2.83E-02 5.74E-04 2.31 E-04 Sr-91 5.OOE-05 1.81 E-06 5.92E-05 Sr-92 1.92E-05 7.13E-07 2.07E-04 Y-90 8.69E-08 2.33E-09 1.20E-04 Y-91 M 8.1 OE-10 2.76E-11 2.70E-06 Y-91 1.13E-06 3.01 E-08 8.1OE-05 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 129 OF 132 Table 16 (continued)
Page 2 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Y-92 7.65E-09 2.15E-10 1.46E-04 Y-93 2.43E-08 6.62E-10 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 5.41 E-08 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 2.56E-09 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.OOE-08 1.24E-08 1.46E-05 Mo-99 3.40E-05 6.63E-06 5.08E-05 1.12E-05 Tc-99M 1.92E-09 3.96E-09 5.1 OE-08 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 4.95E-07 3.08E-06 1.80E-05 Ru-1 05 1.36E-07 4.58E-08 1.OOE-06 5.41 E-05 Ru-106 2.41 E-05 3.01 E-06 2.85E-05 1.83E-04 Ag-11OM 9.96E-07 7.27E-07 4.81 E-07 1.04E-06 3.77E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 1.11 E-05 Te-1 27M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 2.36E-05 Te-127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 2.1OE-05 Te-129M 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 2.27E-05 Te-131 M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 7.11 E-06 Te-132 2.08E-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 3.81 E-05 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 1.51 E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.1 OE-05 1.81 E-04 7.42E-05 1.91 E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 5.38E-05 1.1OE-05 2.05E-06 Cs-137 5.22E-04 6.11 E-04 4.33E-05 1.64E-04 6.64E-05 1.91 E-06 Cs-138 4.81 E-07 7.82E-07 3.79E-07 3.90E-07 6.09E-08 1.25E-06 J1 R12
2
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE CH-ODCM-0001 PAGE 130 OF 132 Table 16 (continued)
Page 3 of 3 Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ba-139 8.81 E-07 5.84E-10 2.55E-08 3.51 E-10 3.54E-10 5.58E-05 Ba-140 1.71 E-04 1.71 E-07 8.81 E-06 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91 E-10 1.34E-08 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 8.81 E-11 9.26E-11 7.59E-07 La-140 2.11 E-08 8.32E-09 2.14E-09 9.77E-05 La-142 1.1 OE-09 4.04E-10 9.67E-11 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 1.48E-08 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 2.86E-09 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 4.93E-07 1.71 E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 1.13E-08 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 3.84E-11 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 2.19E-08 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 3.69E-05 Np-239 1.11 E-08 9.93E-10 5.61 E-10 1.98E-09 2.87E-05 R12
-~
FORT CALHOUN STATION OFF-SITE DOSE CALCULATION MANUAL REFERENCE USE Table 17 - Recommended Values for Other Parameters CH-ODCM-0001 PAGE 131 OF 132 Page 1 of 2 Parameter Symbol Definition Values fg Fraction of ingested produce grown in garden of 0.76 interest.
f, Fraction of leafy vegetables grown in garden of 1.0 interest.
P Effective surface density of soil (assumes a 240 kg/im2 15 cm plow layer, expressed in dry weight) r Fraction of deposited activity retained on crops, 0.25 leafy vegetables, or pasture grass 1.0 (iodines) 0.2 (other particulates)
S.
Attenuation factor accounting for shielding 0.7 (maximum individual) provided by residential structures 0.5 (general population) tb Period of long-term buildup for activity in 1.31 x 1 05 hr sediment or soil (nominally 15 years) te Period of crop, leafy vegetable, or pasture grass 30 days (grass-cow-milk-man exposure during growing season pathway) 60 days (crop/vegetation-man pathway)
Transport time from animal feed-milk-man 2 days (maximum individual) provided by residential structures 4 days (general population)
Time delay between harvest of vegetation or crops and ingestion:
For ingestion of forage by animals Zero (pasture grass) 90 days (stored feed)
For ingestion of crops by man 1 day (leafy vegetables and max. individual feed) 60 days (produce and max.
individual) 14 days (general population)
- f.
The fraction of daily feed that is pasture grass 1.0 while the animals graze on pasture.
MP The mixing ratio at the point of withdrawal of Site Discharge 7.14 drinking water.
M.U.D. Intake 30.8 fp Fraction of the year that animals graze on 0.5 pasture.
'-9
'-4 R12
FORT CALHOUN STATION OFF-SITE DOSE CALCULATIONJ MANUAL REFERENCE USE CH-ODCM-0001 PAGE 132 OF 132 Table 17 (continued)
Page 2 of 2 Parameter Symbol Definition Values tv Environmental transit time, release to receptor 12 hrs. (maximum)
(add time from release to exposure individual 1 day (maximum individual) point to minimums shown for distribution) 1 day (general population) 7 days (population-sport fish doses) 10 days (population-commercial fish doses)
Average time from slaughter of meat animal to 20 days consumption Y4 Agricultural productivity by unit area (measured 0.7 kg/m2 (grass-cow-milk-man in wet weight) pathway) 2.0 kg/M2 (produce or leafy vegetable ingested by man)
W Shore-width factor for river shoreline 0.2 A.
Rate constant for removal of activity on plant or 0.0021 hr1 leaf structures by weathering (corresponds to a 14-day half-life)
R12
SECTION VII ATTACHMENT 2 JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA (Regulatory Guide 1.21)
January 1, 2002 - December 31, 2002 VI1-2
JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA A.
Meteorological Data Recovery Data availability from the on-site weather tower for the period January 1, 2002 through December 31, 2002 was less than the previous 12 months. The regulatory guide recovery was met with a cumulative recovery rate of 94.41 % from the meteorological tower with the remaining 5.59% provided by the National Weather Service. The following table is a summary of the parameters and their respective recovery rates for the period.
Hourly meteorological data used to replace missing tower data for the period January 1, 2002 through December 31, 2002 originated at Eppley Airfield Weather Station, a branch of the National Weather Service. The hourly data was treated in accordance with monthly correction factors and a proceduralized Pasquill-Turner transformation which utilizes solar angle, time of day, cloud cover, and wind speed to determine the Pasquill Class.
The tabulations of the Weather Tower Data for the period January 1, 2002 through December 31, 2002 look appropriate for the season indicated.
The Pasquill Classes observed for the twelve-month period are detailed below.
Pasquill Class A
B C
D E
F G
Total
% Obs.
10.09 9.32 7.23 34.41 25.23 9.38 4.35 100 The data when corrected and/or supplemented by synthetic data derived from the National Weather Service brought the recovery rate up above that required for maintaining adequate recovery as specified by the Nuclear Regulatory Commission. Recovery of synthetic and actual data requires a minimum recovery rate of 90% for the period.
On the basis of the data and its cross-checks, the weather data as amended is completely valid for use in tabulating reactor vent releases.
VII-3
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY UNSTABLE (delta T/ delta z < -1.9)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL A WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
5 33 24 2
0 0
64 NNE 5
16 11 0
0 0
32 NE 2
12 5
0 0
0 19 ENE 3
14 4
0 0
0 21 E
3 5
8 3
0 0
19 ESE 1
11 9
7 0
0 29 SE 1
10 20 18 3
0 52 SSE 3
14 32 24 6
1 80 S
2 15 48 29 9
4 107 SSW 6
11 22 15 3
1 60 SW 10 13 18 1
1 0
43 WSW 7
24 11 2
0 0
44 W
3 30 2
0 0
0 35 WNW 5
26 26 1
0 0
59 NW 7
24 35 22 0
0 88 NNW 7
52 54 19 0
0 132 Total 70 310 329 143 22 6
880 Number of Calms 4
Number of Invalid Hours 0
Number of Valid Hours 884 VII-4
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY UNSTABLE (-1.9 c= delta T/ delta z <= -1.7)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL B WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
NNE NE ENE E
WNW NW NNW 7
25 4
21 1
10 7
25 4
17 3
11 3
20 3
10 4
20 4
15 2
11 1
14 3
11 4
20 7
37 8
44 22 5
4 4
8 15 21 26 36 27 15 9
8 12 24 49 0
0 0
0 0
4 10 25 34 18 11 0
2 4
14 11 0
0 0
0 0
0 2
3 8
3 0
0 0
0 0
0 0
54 0
31 0
15 0
36 0
29 0
33 0
56 0
67 1
103 0
69 0
39 0
25 0
24 0
40 0
82 0
113 Total 65 311 285 133 16 1
811 Number of Calms 5
Number of Invalid Hours 0
Number of Valid Hours 816 VII-5
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL C WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
11 38 13 0
0 0
64 NNE 5
15 4
0 0
0 24 NE 1
10 4
0 0
0 16 ENE 4
11 3
0 0
0 18 E
4 11 3
0 0
0 18 ESE 5
11 10 3
0 0
29 SE 3
10 22 7
1 0
43 SSE 4
11 24 17 4
0 60 S
2 21 32 18 2
0 76 SSW 3
18 24 10 0
0 55 SW 9
11 7
7 0
0 34 WSW 4
5 5
1 0
0 17 W
2 16 4
0 0
0 23 WNW 4
7 7
1 0
0 19 NW 9
24 15 5
1 0
55 NNW 8
34 31 9
0 0
82 Total 78 253 208 78 8
0 625 Number of Calms 8
Number of Invalid Hours 0
Number of Valid Hours 633 v~
VII-6
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS NEUTRAL (-1.5 < delta T/ delta z <= -0.5)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL D WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
71 153 61 11 0
0 300 NNE 49 62 19 4
0 0
137 NE 28 42 12 2
0 0
84 ENE 22 39 7
2 0
0 71 E
22 36 12 1
0 0
74 ESE 25 52 55 18 1
0 155 SE 17 70 71 33 4
0 195 SSE 16 78 123 106 7
1 342 S
14 57 123 83 22 0
309 SSW 21 46 61 42 12 1
186 SW 18 35 24 25 5
0 112 WSW 15 30 5
2 2
0 59 W
11 27 4
2 0
0 46 WNW 15 45 18 6
0 0
87 NW 33 167 118 37 3
0 359 NNW 69 234 155 38 0
0 498 Total 446 1173 868 412 56 2
2957 Number of Calms 57 Number of Invalid Hours 0
Number of Valid Hours 3014 VII-7
-j 1-1)
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL E WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total J
N NNE NE ENE E
WNW NW NNW 27 20 21 7
31 12 21 16 25 21 38 66 41 134 35 115 32 73 36 30 27 17 26 12 52 46 77 96 78 105 68 66 4
2 1
1 3
15 45 114 122 91 29 10 9
22 23 6
0 0
1 0
0 2
3 12 47 70 35 8
0 0
3 2
0 0
0 0
0 0
0 0
2 3
4 0
0 0
0 0
0 51 0
30 0
47 0
38 0
51 0
125 0
226 0
283 0
293 0
241 0
113 0
57 0
107 0
196 0
210 0
142 Total 635 836 497 183 9
0 2160 Number of Calms 50 Number of Invalid Hours 0
Number of Valid Hours 2210 VII-8
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY-EVENTS MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL F WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
19 7
0 0
0 0
27 NNE 9
3 0
0 0
0 13 NE 14 0
1 0
0 0
17 ENE 11 1
0 0
0 0
12 E
16 7
1 0
0 0
26 ESE 53 30 1
0 0
0 90 SE 41 62 3
0 0
0 112 SSE 20 52 2
0 0
0 78 S
23 27 8
0 0
0 61 SSW 27 14 20 0
0 0
64 SW 17 9
5 8
0 0
39 WSW 29 10 6
2 0
0 48 W
46 7
3 1
0 0
61 WNW 67 21 1
0 0
0 92 NW 37 13 0
-0 0
0 53 NNW 22 5
1 0
0 0
29 Total 451 268 52 11 0
0 782 Number of Calms 40 Number of Invalid Hours 0
Number of Valid Hours 822 VII-9
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY STABLE (delta T/ delta z > 4.0)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL G WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
NNE NE ENE E
WNW NW NNW 6
11 11 12 14 36 39 26 31 24 18 10 12 12 9
2 1
1 1
1 4
12 10 4
5 6
2 1
0 1
1 0
0 0
0 0
0 0
0 0
1 3
2 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 12 0
15 0
14 0
14 0
19 0
57 0
52 0
34 0
44 0
37 0
25 0
14 0
15 0
16 0
11 0
2 Total_________273_________0___7____1___0____0____331___
Total 273 so 7
1 0
0 331 Number of Calms 50 Number of Invalid Hours 0
Number of Valid Hours 381 Hours Accounted For:
8760
--1/
VII-10
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY UNSTABLE (delta T/ delta z <
-1'.9)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL A WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
.NNE NE ENE E
WNW NW NNW 0.06 0.06
- 0. 02
- 0. 03
- 0. 03 0. 01
- 0. 01 0. 03
- 0. 02 0.07
- 0. 11 0.08
- 0. 03 0.06 0.08 0.08 0.38 0.18
- 0. 14
- 0. 16 0.06 0.13 0. 11 0.16
- 0. 17 0.13
- 0. 15 0.27 0.34 0.30 0.27 0.59 0.27 0
. 13 0.06 0.05 0.09 0.10 0.23 0.37
- 0. 55 0.25 0.21
- 0. 13
- 0. 02 0.30 0.40
- 0. 62 0.02 0. 00 0.00
- 0. 00
- 0. 03
- 0. 08 0.21 0.27 0.33 0.17 0. 01
- 0. 02 0.00 0.01 0.25 0.22 0.00 0.00 0.00 0.00 0. 00 0.00
- 0. 03
- 0. 07 0.10
- 0. 03
- 0. 01 0.00 0. 0 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- 0. 00 0.01
- 0. 05 0.01
- 0. 00 0.00 0.00 0.00 0.00 0.00 0.73 0.37 0.22 0.24 0.22 0.33 0.59 0. 91 1.22 0.68 0.49 0.50 0.40
- 0. 67 1.00 1.51 Total 0.80 3.54 3.76 1.63 0.25 0.07 10.05 Percent Percent Percent of Calms 0.05 of Invalid Hours 0.00 of Valid Hours 10.09 VII-11
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY UNSTABLE (-1.9 <= delta T/ delta z <= -1.7)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL B WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
NNE NE ENE E
WNW NW NNW 0.08 0.05 0.01 0.08 0.05
- 0. 03
- 0. 03
- 0. 03
- 0. 05 0.05
- 0. 02
- 0. 01
- 0. 03 0.05 0.08
- 0. 09 0.29 0.24 0. 11 0.29 0. 19 0. 13 0.23 0. 11 0.23 0. 17
- 0. 13 0. 16 0.13 0.23 0.42 0.50 0.25
- 0. 06
- 0. 05
- 0. 05
- 0. 09
- 0. 17 0.24 0.30 0.41 0.31
- 0. 17 0.10
- 0. 09
- 0. 14 0.27 0.56 0.00 0.00 0.00 0.00 0.00
- 0. 05 0.11 0.29 0.39 0.21
- 0. 13 0. 00 0. 02
- 0. 05
- 0. 16
- 0. 13 0.00 0.00 0.00 0.00 0.00 0.00 0.02 0.03 0.09
- 0. 03
- 0. 00
- 0. 00
- 0. 00
- 0. 00 0. 00
- 0. 0 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- 0. 01
- 0. 0 0
- 0. 0 0 0. 0 0
- 0. 0 0 0. 0 0 0. 0 0 0.00
- 0. 62 0.35
- 0. 17 0.41 0.33 0.38
- 0. 64 0.76 1.18 0.79 0.45 0.29 0.27 0.46
- 0. 94 1.29 Total____0.74___3.55__3.25___1.52___0.18___0.01___9.26_
Total 0.74 3.55 3.25 1.52 0.18 0.01 9.26 Percent of Calms 0.06 Percent of Invalid Hours 0.00 Percent of Valid Hours 9.32 VII-12
'-I.
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL C WIND-SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9
.18.9 24.0
+24.0 Total N
NNE NE ENE E
WNW NW NNW
- 0. 13
- 0. 06
- 0. 01
- 0. 05
- 0. 05 0.06 0. 03 0. 05
- 0. 02
- 0. 03 0. 10 0.05 0. 02 0. 05 0.10 0.09 0.43 0.17 0.11
- 0. 13
- 0. 13
- 0. 13 0.11 0.13 0.24 0.21
- 0. 13 0.06
- 0. 18 0.08 0.27 0.39
- 0. 15
- 0. 05
- 0. 05
- 0. 03
- 0. 03 0.11 0.25 0.27 0.37 0.27 0.08 0.06 0
. 05
- 0. 08
-0. 17 0.35 0.00 0.00 0.00 0.00 0.00
- 0. 03 0.08
- 0. 19-0.21 0.11
- 0. 08
- 0. 01 0.00 0.01 0.06 0.10 0.00 0.00 0.00 0.00 0.00
- 0. 00
- 0. 01
- 0. 05
- 0. 02
- 0. 00
- 0. 00 0.00 0. 00 0. 00 0. 01 0. 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.73 0.27 0.18 0.21 0.21 0.33 0.49
- 0. 68 0.87
- 0. 63 0.39 0.19 0.26 0.22
- 0. 63
- 0. 94 Total 0.89 2.89 2.37 0.89 0.09 0.00 7.13 Percent of Calms 0.09 Percent of Invalid Hours Percent of Valid Hours 0.00 7.23 VII-13
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT NEUTRAL (-1.5 < delta T/ delta z <= -0.5)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL D WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total
.xJ N
NNE NE ENE E
WNW NW NNW 0.81 0.56
- 0. 32 0.25 0.25 0.29 0. 19 0.18 0.16 0.24 0.21 0. 17
- 0. 13
- 0. 17 0.38
- 0. 79
- 1. 75 0.71 0.48 0.45 0.41 0.59 0.80 0.89 0.65 0.53 0.40 0.34 0.31 0.51
- 1. 91
- 2. 67
- 0. 70 0.22
- 0. 14 0.08 0. 14
- 0. 63 0.81 1.40 1.40 0.70 0.27 0.06
- 0. 05 0.21 1.35
- 1. 77
- 0. 13
- 0. 05
- 0. 02
- 0. 02 0.01 0.21 0.38 1.21
- 0. 95 0.48 0.29
- 0. 02
- 0. 02 0.07 0.42 0.43 0.00 0.00 0.00 0.00 0.00 0.01
- 0. 05 0.08 0.25
- 0. 14 0.06
- 0. 02 0. 0 0 0. 0 0 0. 03 0. 0 0 0. 0 0 0. 0 0 0.00 0.00 0. 0 0
- 0. 00 0. 0 0
- 0. 0 1 0.00
- 0. 01 0.00 0. 0 0
- 0. 0 0 0.00 0. 0 0
- 0. 0 0 3.42 1.56 0.96 0.81 0.84 1.77 2.23
- 3. 90 3. 53 2. 12 1.28 0.67 0.53 0. 99 4.10 5.68 Total 5.09 13.39 9.91 4.70 0.64 0.02 33.76 Percent of Calms 0.65 Percent of Invalid Hours 0.00 Percent of Valid Hours 34.41 1--
VII-14
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL E WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-Direct 3.9 7.9 8.0-13.0-19.0-12.9 18.9 24.0
+24.0 Total N
NNE NE ENE E
WNW NW NNW 0.31 0.24 0.35 0.24 0.29 0.43 0.47 0.40 0.37 0.41 0.31 0.30 0.59 0.88 0.89 0.78 0.23 0.08
- 0. 14 0.18 0.24
- 0. 75 1.53 1.31
- 0. 83 0.34 0.19 0.14 0.53
- 1. 10 1.20
- 0. 75 0. 05 0. 02 0.01 0.01
- 0. 03
- 0. 17 0.51 1.30 1.39
- 1. 04 0.33 0. 11 0.10 0.25 0.26
- 0. 07 0. 0 0 0.00 0. 01 0. 0 0 0.00
- 0. 02
- 0. 03
- 0. 14
- 0. 54 0.80 0.40 0. 09 0. 00
- 0. 0 0 0. 03
- 0. 02 0. 0 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- 0. 02 0
. 03 0.05 0. 00 0.00 0.00 0.00 0.00 0.00
- 0. 00
- 0. 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- 0. 00 0.00 0.00 0.00 0.00 0.58 0.34
- 0. 54 0.43
- 0. 58 1.43 2.58 3.23 3.34
- 2. 75 1.29
- 0. 65 1.22 2.24 2.40
- 1. 62 Total 7.25 9.54 5.67 2.09 0.10 0.00 24.66 Percent of Calms 0.57 Percent of Invalid Hours 0.00 Percent of Valid Hours 25.23 VII-15
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL F WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total kJ-N NNE NE ENE E
WNW NW NNW 0.22 0.10 0.16
- 0. 13 0.18
- 0. 61 0.47 0.23 0.26 0.31 0.19 0.33 0.53 0.76 0.42 0.25 0.08 0.03 0.00 0.01 0.08 0.34 0.71 0.59 0.31 0.16 0.10
- 0. 11 0.08 0.24
- 0. 15 0.06 0.00 0.00 0.01 0.00 0.01 0.01
- 0. 03 0. 02 0.09 0.23 0.06 0.07 0. 03 0.01 0.00 0. 01 0.00 0.00 0. 0 0 0.00 0.00 0.00
- 0. 0 0
- 0. 0 0
- 0. 00
- 0. 00
- 0. 09 0.02
- 0. 01 0.00 0.00 0.00 0. 0 0
- 0. 00 0. 0 0 0. 0 0
- 0. 00
- 0. 00
- 0. 00
- 0. 00
- 0. 00
- 0. 00 0. 00
- 0. 00 0. 00
- 0. 00 0. 00 0. 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0. 00 0.00 0. 00 0. 0 0 0.00 0.31
- 0. 15 0.19
- 0. 14 0.30 1.03 1.28 0.89 0.70 0.73 0.45 0.55 0.70 1.05 0
. 61 0.33 Total____5.15___3.06__0.59___0.13___0.00___0.00___8.93_
Total 5.15 3.06 0.59 0.13 0.00 0.00 8.93 Percent of Calms 0.46 Percent of Invalid Hours Percent of Valid Hours 0.00 9.38 VII-16
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY STABLE (delta T/ delta z > 4.0)
PERIOD OF RECORD:
JAN 2002 -
DEC 2002 PASQUILL G WIND SPEED (mph) AT 10-m LEVEL Wind 1.0-4.0-8.0-13.0-19.0-Direct 3.9 7.9 12.9 18.9 24.0
+24.0 Total N
NNE NE ENE E
WNW NW NNW 0.07
- 0. 13
- 0. 13
- 0. 14
- 0. 16 0.41 0.45 0.30 0.35 0.27 0.21
- 0. 11
- 0. 14
- 0. 14 0.10
- 0. 02
- 0. 01
- 0. 01
- 0. 01
- 0. 01 0.05
- 0. 14 0.11 0. 05 0.06 0.07
- 0. 02 0.01 0.00 0.01
- 0. 01 0.00 0.00 0.00 0. 00 0.00 0. 00 0. 0 0 0.00 0. 00
- 0. 01
- 0. 03
- 0. 02 0.01 0.00 0.00 0.00 0.00 0. 00
- 0. 0 0 0.00 0. 0 0 0.00 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0. 0 0 0. 0 0 0. 0 0 0. 0 0 0. 00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- 0. 00 0.00 0.00 0.00 0.00
- 0. 00 0.00
- 0. 14
- 0. 17 0.16 0.16 0.22
- 0. 65
- 0. 59 0.39 0.50 0.42 0.29
- 0. 16
- 0. 17
- 0. 18
- 0. 13
- 0. 02 Total 3.12 0.57 0.08 0.01 0.00 0.00 3.78 Percent of Calms 0.57 Percent of Invalid Hours 0.00 Percent of Valid Hours 4.35 Percent of Hours Accounted For:
100.00 VII-17
Joint Frequency Distribution 2002 FCS Tower Data N
11.67 996 I
==g A
2.68-55.79 N
I 5.82 W
3.51 - -s---
XI 2.90 'I tI I
L --------
E I
I I
II I
I 8 49 7.97 10.77 11.20 S
1 4
e 13 19 24 Wind Speed (Miles Per Hour)
Calms exduded.
Rings drawn at 5% intervals.
Wind flow is FROM the directions shown.
No observations were missing.
VII-18
SECTION VII ATTACHMENT 3 ANNUAL OCCUPATIONAL EXPOSURE REPORT Technical Specification 5.9.1 b January 1, 2002 - December 31, 2002 Vil-19
C ( (7,(
C ( 'C C ( C C ( C ( C ( ( ( ( C ( ( C(
- ( C C C-C (
IQ((
( 1(( C( ( ( (I PORT CALHOUN STATION OMAHA PUBLIC POWER DISTRICT
- p.
- o. Box 550 FT. CALHOUN, NE. 68023-0550 Date: 10-FEB-2003 08:55 LICENSE:
DPR-40 Regulatory Guide 1.16 Information End of Year Report 2002 Number of Personnel
) 100 mrem Station Utility Contractor Work and Job Function Total man-rem
- Station Utility Contractor REACTOR OPERATIONS AND SURVEILLANCE MAINTENANCE AND CONSTRUCTION OPERATIONS HEALTH PHYSICS SUPERVISORY ENGINEERING ROUTINE MAINTENANCE MAINTENANCE AND CONSTRUCTION OPERATIONS HEALTH PHYSICS SUPERVISORY ENGINEERING INSERVICE INSPECTION MAINTENANCE AND CONSTRUCTION OPERATIONS HEALTH PHYSICS SUPERVISORY ENGINEERING SPECIAL MAINTENANCE MAINTENANCE AND CONSTRUCTION OPERATIONS HEALTH PHYSICS SUPERVISORY ENGINEERING WASTE PROCESSING MAINTENANCE AND CONSTRUCTION OPERATIONS HEALTH PHYSICS SUPERVISORY ENGINEERING 0.325
- 24. 491 7.909 4.457 0.988 34.730 2.647 8.170 12.277 7.128 14.702 0.324 0.606 2.236 1.385 0.503 0.021 0.030 0.149 0.008 0.038 0. 000 0.000 0.000 0.000 14.823 0. 000 0.000 O. 000 0. 000 11.907 0.000 0.000 0.000 0. 000 0.005 0.000 0.000 0.000 O.000 0.000 0.000 0.000 0.000 0. 000 3.947 0.000 26.821 0.127 0.000 79.769 0.000 20.224 4.747 2.148 18.728 0.000 9.745 5.804 56.884 0.520 0.000 0.029 0.233 0.000 0.135 0.000 0.818 0.000 0.000 0.167 9.206 4.295 1.060 0.133 14.462 1.055 5.326 3.118 1.327 7.956 0.093 0.422 1.423 0.172 0.241 0.016 0.018 0.029 0.001 0.006 0.188 2.053 0.012 0.000 0.015 0.000 0.000 0.000 0.000 4.980 0.000 0.000 0. 000 0.000 5.182 0. 000 0.000 0. 000 0.000 0.003 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0. 000 0.000 0.722 0.000 7.591 0.023 0.000 19 209 0.000 6.375 1 089 0.392 4.546 0.000 3.005 1.831 26.253 0.073 0.000 0.011 0.059 0.000 0.033 0.000 0.141 0.000 0.000 0.011 0.245 3.038 0.087 0.000 VI1-20
Regulatory Guide 1.16 Information End of Year Report 2002 Number of Personnel
) 100 mrem Station Utility Contractor Total man-rem
- Station Utility Contractor Work and Job Function REFUELING MAINTENANCE AND CONSTRUCTION OPERATIONS HEALTH PHYSICS SUPERVISORY ENGINEERING Totals MAINTENANCE AND CONSTRUCTION OPERATIONS HEALTH PHYSICS SUPERVISORY ENGINEERING 8.729 7.226 1.283 0.000 0.249 0.000 4.794 0.000 1.492 0.000 34.901 O. 000 4.377 3.076 11.967 138.000 0.000 62.0 14 13.986 71.000 3.557 0.232 0.153 1.262 0.200 26.389 10.790 12.267 6.904 1.833 58.183 3.090 O.000 0.000 0.000 O.000
- 13. 270 0.000 0.000 0.000 0.000 13.270 20.090 0.000 1.402
- 1. 322 4.773 44.673 0.000 18.525 4.324 31.418 98.940 59.000 29.011 20.002 24.000 1 1.000 34.000 0.000 0.000 0.000 0.000 Grand Totals 143.013 34.000 285.000
- The man-rem totals include dose only from individuals receiving more than 100 mrem throughout the year at the site.
VI1-21 C ( C C
C
(
C (
C C C C
C (C C C C C ( C C C C C ( C C C C C C C C C C C C C C C C C
Submitted by: LITTLE Date: 14-FEB-2003 08:59 Sorted by: None Required Page: 1 Year-to-Date 2002 TEDE Distribution Report All Monitored Personnel Year-to-Date TEDE rem No. of Persons Cum.
TEDE Percent Percent Total Cum.
Ave.
Percent Percent TEDE Ave.
Age No Measurable t-Exposure 0.001 -
0.100 0.100 -
0.250
\\
0.250 -
0.500 0.500 -
0.750 0.750 -
1.000 1.000 -
2.000 2.000 -
3.000 3.000 -
4.000 4.000 -
5.000 5.000 -
6.000 6.000 -
7.000 7.000 -
8.000 8.000 -
9.000 9.000 -
10.000 10.000 624 45.68 45.68 0.000 302 187 153 78 21 1
0 0
0 0
0 0
0 0
0
- 22. 11 13. 69 11.20 5.71 1. 54 0. 07 0. 0 0 0. 0 0 0.00 0. 0 0 0. 0 0 0. 0 0 0. 0 0 0.00 0. 00 67.79 81.48 92.68 98.39
- 99. 93 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 100.00 13.095 30.862 54.561 47.012 17.137 1.139 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 7.99 18.84 33.31 28.70 10.46 0.70 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 7.99 26.83 60.14 88.84 99.30 100.00 100. 00 100.00 100.00 100. 00 100.00 100.00 100.00 100.00 100.00 0.043 0.165 0.357 0.603 0.816 1.139 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 0.000 46 44 46 42 43 42 39 0
0 0
0 0
0 0
0 0
Total Number of Monitored Personnel:
Total Exposure:
Average Exposure: