LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report
| ML23116A144 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/20/2023 |
| From: | Allan Barker Omaha Public Power District |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LIC-23-0004 | |
| Download: ML23116A144 (1) | |
Text
{{#Wiki_filter:---- ~- - - Omaha Public Power District 10 CFR 50 .36(a) 10 CFR 72.44 April 20, 2023 LIC-23-0004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington , DC 20555 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 Fort Calhoun Station Independent Spent Fuel Storage Installation NRC Docket No. 72-054
Subject:
Fort Calhoun Station (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report
References:
FCS Quality Assurance Topical Report (NO-FC-10) Pursuant to Fort Calhoun Station (FCS) , Unit No. 1, Quality Assurance Topical Report (QATR), procedure NO-FC-1 OAppendix E, Section E.4 .1 and E.4 .2, Omaha Public Power District (OPPD) provides the Annual Radiological Effluent Release Report and the Annual Radiological Environmental Operating Report. The Annual Radiological Effluent Release Report is submitted in accordance with QATR Section E.4.1 and encompasses the period of January 1, 2022 through December 31, 2022. The report is presented in the format outlined in Regulatory Guide 1.21 , Revision 1. In addition, the report provides the results of quarterly dose calculations performed in accordance with the Offsite Dose Calculation Manual (ODCM) . In accordance with QATR Section E.4.2, Section VII of the Annual Radiological Effluent Release Report includes the revisions to the ODCM made during this period . Section VII of the Annual Radiological Effluent Release Report also includes Process Control Program (PCP) changes made during this period . The Annual Radiological Environmental Operating Report is submitted in accordance with QATR Section E.4.2 and encompasses the period of January 1, 2022 through December 31 , 2022 . No commitments to the NRC are contained in this letter. 444 SOUTH 16TH STREET MALL* OMAHA, NE 68102- 22 47 EMPLOYMENT WITH EQUAL OPPORTUNITY
U.S . Nuclear Regulatory Commission Page 2 LIC-23-0004 Page 2 Please contact Mrs. Andrea K. Barker at (531) 226-6051 if you should have any questions. Respectfully,
~
Andrea K. Barker Regulatory Assurance & Emergency Planning Manager, AKB/akb Enclosures :
- 1. Annual Radiological Effluent Release Report (ARERR)
- 2. Annual Radiological Environmental Operating Report c: S. A. Morris, NRG Regional Administrator, Region IV J. D. Parrott, NRG Senior Project Manager S. Anderson , NRG Health Physicist, Region IV
DocuSign Envelope ID : EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 1 of 237 Enclosure 1 Omaha Public Power District Fort Calhoun Station Unit No. 1 Annual Radioactive Effluent Release Report (ARERR) January 1, 2022 to December 31 , 2022
F6B73ADF3B Page 2 of 237 DOCKET NO. 50-285 OPERATING LICENSE DPR-40 Annual Radiological Effluent Release Report This report is submitted for the period January 1, 2022 through December 31, 2022. The Effluent Report is presented in the format outlined in Regulatory Guide 1.21, Revision 2. In addition, this report provides the results of quarterly dose calculations performed in accordance with the Offsite Dose Calculation Manual. Results are presented by quarter for the period January 1, 2022 through December 31, 2022. Descriptions of any changes made during the preceding twelve months to the Offsite Dose Calculation Manual and/or the Process Control Program for the Fort Calhoun Station are presented . Plant Manager Decommissioning
-4A34-97A4-01 F6B73ADF3B Page 3 of 237 TABLE OF CONTENTS Section Section Title I. 1.0 Introduction 1.1 Executive Summary 2.0 Supplemental Information 2.1 Regulatory Limits 2.2 Effluent Concentration Limits 2.3 Measurements and Approximations of Total Radioactivity 2.4 Estimation of Total Percent Error 2.5 Batch Releases 2.6 Abnormal Releases 3.0 Gaseous Effluents 4.0 Liquid Effluents 5.0 Solid Wastes 6.0 Related Information 6.1 Functionality of Liquid and Gaseous Monitoring Instrumentation 6.2 Changes to Off-site Dose Calculation Manual (ODCM), CH-ODCM-0001 or Process Control Program (PCP), FCSD-RW-PG-101 6.3 New Locations or Modifications for Dose Calculations or Environmental Monitoring 6.4 Noncompliance with Radiological Effluent Control Requirements 6.5 Modifications to Liquid and Gaseous Waste Treatment and Ventilation Exhaust Systems 6.6 Meteorological Monitoring Program 6.7 Assessment of Doses 6.8 Groundwater Monitoring Program and Observations II. Quarterly Doses from Effluents, Offsite Dose Calculation Manual
Do cuSign Enve lope ID: EA65F186-46DE -4A34-97A4-01 F6B 73ADF3B Page 4 of 237 TABLE OF CONTENTS Ill. Radiological Effluent Releases Table 111.1 ; Batch Liquid and Gas Release Summary Table 111.2; Abnormal Batch Liquid and Gaseous Release Summary Table 111.3; Gaseous Effluents - Summation of All Releases Table 111.4; Gaseous Effluent Releases - Batch Mode Table 111.5; Gaseous Effluent Releases - Continuous Mode Table 111.6; Liquid Effluents - Summation of All Releases Table 111.7; Liquid Effluent Releases - Batch Mode Table 111.8; Liquid Effluent Releases - Continuous Mode Table 111.9 ; Groundwater Analysis Results IV. Dose From Gaseous Effluents - GASPAR II Output Tables IV-A-1 through IV-A Receptor Dose Projections Table IV-B Dose Contributions at Unrestricted Area Boundary Table IV-C ALARA Annual Integrated Dose Summary V. Dose From Liquid Effluents - LADTAP II Output Summary Dose Projections from Liquid Effluent Releases VI. Radioactive Effluent Releases-Solid Radioactive Waste VII. ATTACHMENTS
- 1. Off-Site Dose Calculation Manual (ODCM) and Process Control Program (PCP) Revisions
- 2. Joint Frequency Distribution Wind Direction vs . Wind Speed by Stability Class and Meteorological Data
F6873ADF3B Page 5 of 237
1.0 INTRODUCTION
This Annual Radiological Effluent Release Report, for Fort Calhoun Station Unit No. 1, is submitted for the period January 1, 2022 through December 31 , 2022 . ' 1.1 Executive Summary The Radioactive Effluent Monitoring program for the year 2022 was conducted as described in the following report. Major efforts were made to maintain the release of radioactive effluents to the environment as low as reasonably achievable . The total airborne activity released from noble gas was 0.00 curies . This was the same as from the 2021. This was due to all fuel being stored safely on the Independent Spent Fuel Storage Installation (ISFSI) pad. The total airborne activity from 1-131 , 1-133, and particulates with half-lives > 8 days in 2022 was 1.51 E-05 curies. This is a decrease from the 2021 activity of 3.95E-05 curies . This was due to fewer particulates being identified from decommissioning activities. The total airborne activity from Tritium was 1.94E-01 curies. This was a decrease from the 2021 activity of 2.67E-01 curies. :fhis decrease was due to a reduction in water inventory based on decommissioning activities. Dose contributions from airborne effluents at the unrestricted area boundary were; 0.00 mRad gamma air dose, 0.00 mRad beta air dose, 4.85E-03 mRem total body dose, and 3.20E-03 mRem critical organ dose . Gamma and beta doses were the same as from 2021 levels of 0.00 mRad gamma air dose and 0.00 mRad beta air dose, from releasing no noble gases. Whole body and critical organ doses decreased from 2021 levels of 6.14E-03 mRem total body dose and 4.26E-03 mRem critical organ dose . This decrease is due to the decrease in the amount of tritium released. 11-1
-4A34-97A4-01F6B73ADF3B Page 6 of 237 Total water activity (excluding tritium, dissolved gases , and alpha) released in 2022 in liquid effluents was 1.74E-02 curies . This was an increase from the 2021 activity of 1.33E-02 curies . This increase was due to an increase in liquid waste generated due to decommissioning activities and dust suppression . The total water tritium activity released in 2022 in liquid effluents was 7.84E-02 curies . This was a decrease from the 2021 activity of 4.77E+00 curies. This decrease was due to the source of the liquid waste generated being from dust suppression during decommissioning . The calculated whole body dose due to liquid effluents at the site discharge from all sources in 2022 was 2.71 E+00 mRem which was 90.33% of the annual dose limit. This was an increase from the 2021 dose of 1.88E+00 mRem , which was 62 .67% of the annual dose limit. Dose increased due to a decrease in dilution volume during the releases . The calculated critical organ dose due to liquid effluents at the site discharge from all sources in 2022 was 4.32E+00 mRem . This was an increase from the 2021 dose of 2.99E+00 mRem . This increase was due to a decrease in dilution volume during the releases. Historical average meteorological data was utilized in the preparation of the ARERR . The Fort Calhoun Station meteorological system for the period January 1, 2015 through December 31 , 2019 had a cumulative recovery rate of 78 .15% from the station meteorological tower with the remaining 21 .85% provided by the National Weather Service, for the joint frequency parameters required by Regulatory Guide 1.23 for wind speed , wind direction , and delta temperature . The low recovery rate was due to the loss of the onsite tower from flood damage . There were no abnormal releases during 2022. During 2022 there was one change to the Off-site Dose Calculations Manual (ODCM) , CH -ODCM-0001 and one change to the Process Control Program , FCSD-RW-PG-101 . For 2022, the total volume of solid radwaste released from the unit was 3.23E+04 cubic meters . This was an increase from the 2.19E+03 cubic meters of solid waste released from the unit in 2021. The increase was attributed to an increase in the volume of Dry Active Waste shipments . 11-2
F6B73ADF3B Page 7 of 237 The total activity released from the unit for 2022 was 5.35E+04 curies, 1.83E+01 curies from Resins, Filters, and Evaporator Bottoms, 4.20E+01 curies from Dry Active Waste, 5.35E+04 curies of Irradiated Components , and 5.02E-01 curies of Other Waste. This was an increase from the 2021 value of 5.09E+02 curies due to increase in waste generation from decommissioning activities . Overall , the effluent monitoring program was conducted in a manner to ensure the activity released and dose to the public were maintained as low as reasonably achievable. 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM Radiological Effluent Control Specifications applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections . 2.1.1 Fission and Activation Gases The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations of radionuclides do not exceed the values specified in 10 CFR 20 for airborne effluents at the unrestricted area boundary. 2.1.2 Doses from H-3 and Radioactive Material in Particulate Form with Half Lives Greater than 8 Days (Other than Noble Gases).
- a. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of H-3 and radioactive material in particulate form with half-lives greater than eight days (other than noble gases) in airborne effluents shall not exceed 7.5 millirem from all exposure pathways during any calendar quarter.
- b. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of H-3 and radioactive materials in particulate form with half-lives greater than eight days (other than noble gases) in airborne effluents shall not exceed 15 millirem from all exposure pathways during any calendar year.
11-3
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 8 of 237 2.1.3 Liquid Effluents The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides do not exceed the values specified in 10 CFR 20 for liquid effluents at site discharge . To support facility operations , RP/Chemistry supervision may increase this limit up to the limit specified in QATR Appendix E, E.2 .1.3.b. QATR Appendix E, E.2.1.3.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 20.1001-20.2401, Appendix B, Table 2, Column 2. The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited to :
- a. During any calendar quarter: Less than or equal to 1.5 mRem to the whole body and less than or equal to 5 mRem to any organ, and
- b. During any calendar year: Less than or equal to 3 mRem to the whole body and less than or equal to 10 mRem to any organ .
2.1.4 Total Dose-Uranium Fuel Cycle The dose to any real individual from uranium fuel cycle sources shall be limited to :5 25 mRem to the total body or any organ (except the thyroid , which shall be limited to :5 75 mRem) during each calendar year. 2.2 Effluent Concentration Limits (ECL) 2.2.1 Liquid Effluents The values specified in 10 CFR Part 20 , Appendix B, Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. 11-4
F6B73ADF3B Page 9 of 237 2.2.2 Gaseous Effluents The values specified in 10 CFR Part 20, Appendix B, Column 1 are used as the ECL for gaseous radioactive effluents released to unrestricted areas. 2.3 Measurements and Approximations of Total Radioactivity Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 4.1 and 4.2 of Part I of the ODCM. 2.3.1 Liquid Radioactive Effluents Each batch was sampled and analyzed for gamma-emitting radionuclides using gamma spectroscopy, before release. Composite samples were analyzed monthly and quarterly. Composite samples were analyzed monthly in the onsite laboratory for tritium and gross alpha radioactivity , using liquid scintillation and proportional counting techniques respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90, Fe-55, Ni-63, and Gross Alpha by a contract laboratory (Teledyne Brown Engineering, Inc.) . A software program was used to project the total body and critical organ dose contribution at the unrestricted area boundary for each release and the percent contribution to the annual objective dose. 2.3.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity before release. A software program was developed and installed that can project the total body and critical organ dose contribution at the unrestricted area boundary for each release and the percent contribution to the annual objective dose . This program also adds the projected dose to the current actual dose totals in a temporary file, until it is updated with actual release data after a purge . 11-5
86-46DE-4A34-97A4-01F6B 73ADF3B Page 10 of 237 Continuous release effluent pathways were continuously sampled using particulate filters and analyzed weekly for gamma-emitting radionuclides using gamma spectroscopy. Weekly particulate filters were analyzed for gross alpha radioactivity in the onsite laboratory using proportional counting techniques . Quarterly composites of particulate filters were analyzed for Sr-89, Sr-90, and Gross Alpha by a contract laboratory (Teledyne Brown Engineering, Inc.). 2.4 Estimation of Total Percent Error The estimated total percent error is calculated as follows : Total Percent Error= (El + E2 2 + Ei + ... + En 2)0 -5 Where En= percent error associated with each contributing parameter. Sample counting error is estimated by the Canberra Genie System Software for samples analyzed by gamma spectroscopy. This calculation can include the error associated with peak area determination, gamma ray abundance , efficiency, and half-life . Systematic error is estimated for gaseous and liquid effluent analyses and dilution and wastewater volume. 2.5 Batch Releases A summary of information for liquid and gaseous batch releases is included in Table 111.1 . 2.6 Abnormal Releases Abnormal Releases are defined as unplanned and unmonitored releases of radioactive material from the site . A summary of information for liquid and gaseous abnormal releases is included in Table 111.2. 3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 111.3 , 111.4 and 111.5. All radioactive materials released in gaseous form are considered to be ground level releases. 4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 111.6, 111.7 and 111.8 . 11-6
86-46DE-4A34-97A4-01 F6B73ADF3B Page 11 of 237 5.0 SOLID WASTES The quantities of radioactive material released as solid effluents are summarized in Section VI. 6.0 RELATED INFORMATION 6.1 Functionality of Liquid and Gaseous Monitoring Instrumentation During the reporting period , there was 1 instrument used to monitor radioactive effluent releases that failed to meet the minimum reportable instrument functionality requirements listed in the ODCM during the reporting period . During the reporting period RM-055 , Liquid Radwaste Effluent Monitor, was not functional for 1 day (11/30/2022- 12/1/2022) due to not passing a monthly check (OP-ST-RM-0003). During this period, no releases occurred from this release point. 6.2 Changes to the Offsite Dose Calculation Manual (ODCM), CH-ODCM-0001 and/or Process Control Program (PCP), FCSD-RW-PG-101 During 2022 there was one change to the Off-site Dose Calculations Manual (ODCM) , CH-ODCM-0001 , issued on 02/09/2022 , and one change to the Process Control Program , FCSD-RW-PG-101 , issued on 08/17/2022.
- The following change was made to the ODCM:
o Remove the Aux and Radwaste building forced draft effluent release method due to ventilation no longer available due to decommissioning activities. o Add the Waste Processing Structure (WPS) to the figures .
- The following change was made to PCP :
o Updated Review and Approval cover page. o Clarified Vendor Services definition o Clarified the reviews and sign offs for the FCS QATR o Added a reference for Reg Guide 1.21 6.3 New Locations or Modifications for Dose Calculations or Environmental Monitoring None 6.4 Noncompliance with Radiological Effluent Control Requirements 11 -7
F6B73ADF3B Page 12 of 237 This section provides a list of any event that did not comply with the applicable requirements of the Radiological Effluent Controls given in the Offsite Dose Calculation Manual (ODCM). Detailed documentation concerning the evaluations and corrective actions is maintained onsite. 6.4.1 Abnormal Gaseous and Liquid Releases No abnormal releases were made during the calendar year of 2022 . 6.4.2 Failure to Meet Specified Sampling Requirements During 2022, there were no instances in which specified sampling requirements were not met. 6.5 Modifications to Liquid and Gaseous Waste Treatment and Ventilation Exhaust Systems During the reporting period no design modifications were made to the Liquid Waste Treatment System. 6.6 Meteorological Monitoring Program A summary of hourly meteorological data, collected during 2022, is retained onsite and is maintained as documentation as required by Regulatory Guide 1.21 Rev 2. This data is available for review by the Nuclear Regulatory Commission upon request. Joint Frequency tables are included in Section VII, Attachment 2. The 5 year historical Average x/Q is utilized to determine the concentrations of radionuclides at the unrestricted area boundary. For quarterly estimates, during the year, an average X/Q is used, which is the highest X/Q calculated using the 5 year historical meteorological data. 11-8
Doc uSign Envelope ID: EA65F1 86-46DE -4A34-97A4-0 1F6B 73ADF3B Page 13 of 237 6.7 Assessment of Doses 6.7.1 Doses Due to Liquid Effluents Total body, skin, and organ doses for liquid releases were calculated in mRem for all significant liquid pathways using the annual configuration of the LADTAP II program. The site discharge location was chosen to present a most conservative estimate of dose for an average adult, teenager, child , and infant. A conservative approach is also presented by the assumption that Omaha and Council Bluffs receive all drinking water from the Missouri River. The LADTAP II program in its annual configuration was also used to calculate the total body and organ doses for the population of 1,053,476 within a 50-mile radius of the plant (based on the 2020 census) . The results of the calculations are listed in Section V. The doses due to liquid effluents for the total body and critical organ are also calculated quarterly using the methods in the ODCM . The results are listed in Section II. 6.7.2 Doses Due to Gaseous Effluents Total body, skin , and organ doses from ground releases were calculated in mRem to an average adult, teenager, child, and infant in each receptor using the annual configuration of the GASPAR II program . Also , the doses to the same groups , in units of mRad due to gamma and beta radiation carried by air, were computed using GASPAR II. The GASPAR II program in its annual configuration was also used to calculate the ALARA integrated population dose summary for the total body, skin , and organ doses in person-rem for all individuals within a 50-mile radius. The results of the calculations are shown in Section IV. The doses due to gaseous effluents for total body gamma and beta noble gas air dose are calculated quarterly using the methods in the ODCM with an average X/Q. The results are listed in Section II. 11-9
F6B73ADF3B Page 14 of 237 6.7.3 Doses Due to H-3 and Particulates with Half Lives Greater than 8 days. The doses due to H-3 and Particulates with half-lives greater than 8 days for total body and critical organ dose are calculated quarterly using the highest of infant or child dose factors and an average X/Q. The results are listed in Section II for inhalation, ground, and food. 6.7.4 Direct Radiation Dose to Individuals and Populations Direct radiation doses attributed to the gamma radiation emitted from the containment structure were not observed above local background at any TLD sample location for this annual period. 6.7.5 40 CFR 190 Dose Evaluation ODCM Radiological Effluent Controls require dose evaluations and a special report to demonstrate compliance with 40 CFR Part 190 only if calculated yearly doses exceed two times the annual design objectives for liquid and/or gaseous effluents. At no time during 2022 were any of these limits exceeded ; therefore, no special report was required. The external Total Body Dose is comprised of:
- 1) Total Body Dose due to noble gas radionuclides in gaseous effluents
- 2) Dose due to radioactive waste and the ISFSI
- 3) Total Body Dose due to radioactivity deposited on the ground (this dose is accounted for in the determination of the non-noble gas dose and is not considered here)
The Total Body Dose, external is given by: Dext = Dtb + Dosf Where Dext is the external dose Dtb is the total body dose Dost is the dose from on-site storage 11-10
F6B73ADF3B Page 15 of 237 The Total Dose is then given by: Dtot = Dex! + Diiq + Dnng Where D101 is the total dose Dext is the external dose Diiq is the dose from liquid effluents Dnng is the dose from non-noble gases Dose Limits Total Body, annual 25 mrem Thyroid, annual 75 mrem Other Organs, annual 25 mrem Calculation using REMP TLD Comparison Indicating TLD station {OTD-1 K-(1)}, closest to on site storage , in mrem/week minus background, in mrem/week OTD-1 K-(1) Background Net Qtr Dose Weeks/qtr mrem/wk mrem/wk mrem/wk mrem/qtr Quarter 1 1.5 1.4 0.1 13 1.3 Quarter 2 1.1 0.96 0.14 13 1.82 Quarter 3 1.8 1.5 0.3 13 3.9 Quarter 4 2.0 1.7 0.3 13 3.9 Dext 10.92 Dext = 10.92 mrem Maximum offsite doses from report Dtbwb = 4.85E-03 mrem , Dtbco = 3.20E-03 mrem Dliqwb = 2.71 E+00 mrem Dliqco = 4 .32E+00 mrem D101 wholebody = 10.92 + 4.85E-03 + 2.71 E+00 = 13.63 mrem Dtot critical organ= 10.92 + 3.20E-03 + 4.32E+00 = 15.24 mrem 11 -11
DocuSign Envelo pe ID: EA65F1 86-46DE-4A34-97A4-01 F6B73ADF3 B Page 16 of 237 These reported doses are bounding cases demonstrating compliance. Actual REMP TLD readings do not show any deviation from historical averages for this location , both pre and post-construction of the Steam Generator storage mausoleum and ISFSI. On-site TLDs used for dose monitoring at onsite rad storage facilities do not have identical counterparts at the site boundary or actual offsite receptors . Additionally, the liquid dose pathway, since it is downstream of the indicator location and is not hydro-geologically connected , would produce very conservative results compared to calculating the actual dose. 6.8 Groundwater Monitoring Program and Observations OPPD conducted groundwater sampling from 17 wells , 2 surface water sites, and 4 stormwater headers within the site property per NEI 07-07. Additionally , Nebraska requirements regarding avoidance of snow runoff were deleted , so stormwater sampling is now performed quarterly, if available . Well MW-5A was not sampled in the first quarter due to the well being dry. Well was reconditioned and sampled quarterly for the remainder of the year. Well MW-12A went dry during sampling in the 4 th quarter due to drought conditions . Ten sample locations in sectors experiencing significant (>10%) wind direction were established to assess potential atmospheric deposition. After an initial sampling regime in all ten sectors displayed no detectable tritium, the sampling program was switched to 2 affected sectors per rain event and an upwind background test. Two rain sampling events were conducted . No tritium activity above the vendor's Minimum Detectable Activity (MDA) was reported . Stormwater sampling was impacted by severe drought (rain was absorbed vice creating runoff) and/or had no rain or snow events significant enough to collect stormwater during the 3rd and 4th quarters. No tritium activity above the vendor's Minimum Detectable Activity (MDA) was reported in collected stormwater or rain sampling . No monitoring had tritium identified above 2 sigma error of MDA. Some Sr-90 results identified< MDA were retained during statistical data review based on historical station shallow well trends . Gamma isotopes and some hard to detect nuclides were reduced to an annual sample frequency ( Ni-63 , Fe-55, Sr-90 in deep wells) based on 2 years of quarterly sampling with no detections above MDA and Groundwater Protection assessment audit recommendations . The Fort Calhoun REMP sampling did not detect tritium in samples within the Missouri River downstream at the site boundary or the nearest municipal drinking water facility . No groundwater drinking pathway exist on site. Groundwater monitoring of neighboring 11-12
DocuSign Envelope ID : EA65F1 86-46DE -4A34-97A4-01 F6B 73ADF3B Page 17 of 237 drinking wells is performed to have data if a plume were identified on site . No state or federal drinking water limits and no site groundwater protection program administrative limits were exceeded . Since site radiological waste storage systems have been decommissioned ; liquid waste generated from deconstruction activities like dust suppression need to be stored in temporary containers . One of those tankers , DW-6, piping flanges failed and allowed the tank contents to drain. Water drained from the tank to the ground and into the cable tray near the tank within the Deconstruction Area. Approximately 13000 to 15000 gallons of water were drained . Since the ground was frozen , much of the liquid was recovered in the cable tray. Some soil remediation was performed , but the presence of the damaged tank and others made accessing all areas problematic. The tank was eventually moved and further soil samples and surveys were performed to create remediation plans . As part of the pre-decommissioning planning, storm and surface drains within the deconstruction area were removed or capped to prevent environmental release . This contained the spill in the area of occurrence . Two rounds of water sampling have been performed in monitoring wells near the impacted soil , no plant-related nuclides have been observed . Surface water from snow melt in the impacted area was collected and analyzed ; no plant-related radionuclides were detected. No pathway for environmental release is currently occurring . No sources of drinking water exist between the spill area and the Missouri river. All offsite wells sampled per OPPD Radiological Environmental Monitoring Program none have had any detections of plant-related nuclides. Since the spill occurred on the soil it is unlikely that particulate nuclides would reach the water table in appreciable amounts due to adsorption. A bounding dose case was performed using the entire tank volume and its tritium concentration. The resulting dose was 1.25 e-06 mrem. All groundwater stakeholders were notified of the event per established reporting and communication procedures. 11-13
F6B73AD F3B Page 18 of 237 SECTION II QUARTERLY DOSES FROM EFFLUENTS Offsite Dose Calculation Manual January 1, 2022 - December 31, 2022 11-14
Do cuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3 B Page 19 of 237 Quarterly Dose Calculation Results January 1, 2022 through December 31, 2022 With the implementation of the Fort Calhoun Station Radiological Effluent Technical Specifications (RETS) on October 1, 1985, radiation doses in the unrestricted area from liquid and gaseous effluents must be calculated quarterly per the Offsite Dose Calculation Manual (ODCM). These calculations are performed to ensure the annual dose limits delineated in Appendix I of 10 CFR 50 and implemented by RETS are not exceeded . If the results of the quarterly calculations exceed fifty percent (50%) of the annual limits of Appendix I, actions are taken to reduce effluents so that the resultant doses do not exceed the annual limits during the remainder of the year and a special report is submitted to the Nuclear Regulatory Commission. No special reports were required for 2022 calculated doses . This section presents the results of the quarterly dose calculations performed during the period January 1, 2022 , through December 31 , 2022. Details are shown as to the types , sources , and resultant doses from the effluents, the annual limits and a comparison to the annual limits . 11-15
F6B73ADF3B Page 20 of 237 FOR'T' C HOUN S'I' '!' ON c- 21
' HEM'.IS'f'P.'i ORM RB QU.Z..RTERLY CU1IDLA.TIV DOSI:: C."OWl'RIBUTlON FROM S:.ADIOACT'IVE - F T.lrt!:NTS r,'OR 'l' C hiOUt*, FI{""' . Qu.0..R*I'ER 2 22 DOSE PR --crIOl~ S I . L iQl.i - d 1*: **r1uo1;ents : T ot.al Body Cl'."i - ical Organ Do e ( mreml Dase j n:; r ,nJ Batch: O.OOE +OO 0.00*+00 Co o ~"': O.OOE.+00 0. 00 00 To t.a l s: 0. OE+ 0 OOCM Quarl:erly Objectiv-e: _,50iE+OO _ ODE .., 00 P,2-.rcont f Q 1arterl y Obj : 0 . 00 '-/; 0.00 ~
ODCt*l Annual Obj ec:ti ve: .OOE+OO _ . 0 OE
- 1 YTD Porcent of llnnual Obj: 0_0{) '5 (1.00 %
II. Ga~eous 6ffluen s : Tot.al Body *G,_urnr 1a 'l'Ot;;'! Body Beta Dc:1S*~ (mradl Dose Jmracl} p._. Noble Ga ldr Dose: 0.00£10,0 0. OCIE Q OD -,r r;;,;,ua.rt:.er.L y Objec ive : 5.00B+ 0 Per ~en of Quarte;rJ y Obj: 0.00 0 . 00 'iii. 1 , 00 ,+Ql 2 . OE+O1 YTD Pere e n o E 1-.:nnual Obj: 0.0 0 % B. I-lJ _ , I- 1 33, T.citi 1, C - 14, and Particula es w h Ha]f - Lives > B Days: ':'ota Bccly C:ri tica Or-g an Do .,.e ( mrem l Dos l.uir@m) Inhala i. on: 1.4 6E - 04 l . 628-04 Grq.llnd and Food : l.23 E-03 2. -*18E-O) T t a l., : l.38E-0J. QDCM Quart.erl y Objec~ive: 7.50 * +00 7_5 E+ Percen o C,;'Llarterly Obj: OCCM fillJ )Lld 1 Db j cc t i ve : l . 'i0E:..-01 1. SOE+0,1 Y , P re t. oE Annual Obj: f)_Ol % 0 . 02 t 11-16
OocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 21 of 237 l?OR*r CALH0IJN STAT' ON l:' -421 CHEMISTRY FO '.RM RB QOARTERLY CUt-lOLAT IV
- DOSE CONTR1 Il0'1'ION FROM ?..ADIOAC V6 E FFL UENTS FOR' CALHOUN SECOND QUAWi'ER 2'022 DOSE PRO,J
- C." TIONS I. Liquid Ef fluents: '!'ota l B-00.y Crl tical Organ Dose (m.rem) Dose (mr em)
B<1t ch : 7,92E - 03 2. 9E-02 Cont lnuous : O.OOE+OO 0.00 8 +00 Toti;;ilS: 7 .92E -0 3 2 . l 9 E-02 ODCM Qu,;;i -~Qrly Object.ive : l.50E + 00 5 . 008+ 1) (1 t'e-r-cgnt of Quar erly Obj: 0.53 % .4 4 % 0 DC i An.nuQ, 1 Obj ec ti 1.re : 3.00E+00 1 . OOE+O l Y'I'D E'C::rcen O*f Am1u o!U Obj : 0. 26 %. 0 .22 \\; I . G se u.5 Ef f luents : To ta Body Ga.rraria Tot al Body Be ta Do s,e !mrad) o se (mrad) n . Noble Octs Ajr Dos e: 0 . 00E 1-00 0.00.E: + 00 ODCM Qua.,* tgr ly Ob j ect. ve: 5 . 0E + 0O l , l) DE+0l Percent of. Quarter y Obj: 0 . 00 % 0.00 ODCM Armu;;il Ob j ec i ve: 1 ,0 0ET" 1 2 .O 0E+Ol
~TD Peruen t of ~.nnu al Obj: 0.00 i 0.0 0 B. I -1 l, I-133, Tr i i1.m, C-14, and P.i r tlcula tos wi. t Half-Live;:;> B Days: Total Bo dy Cri tical Orga.n bose (mr ern) Dose (mxemJ Inha.lai;:ion : 7 .85E-0 5 7,BJE - 05 G o n d and E'ooo : 3 .6U-04 3.6J.E- 0<l T tals: 4 . 41 E-M 4. UE -04 OtJCM Quarter l y Obj ective : 7 . S0E +0i) 7 . 50:S*t* OO Perc ell t of Q~1arter l y Ob :; : 0 . 01 % 0.01 ~
O Ct*1 A.rmua l Ob jective: 1.so:::: ,0 1 l.SO E+0 l YTD Per ce?.n t o f .Z..nnu,:1 1 Obj : 0 .01 't 0.02 % I Rl.!11iewed
... ~
- t. _,_,... -
11-17
DocuSig n Envelope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 22 of 237 N FORT CF>LHOUt* STAT-ON FC-421 CH!e! *fl STRY FORM RB QUARTE!. :L'i Cill l.J\'l'IVE DOSE COl>l'l'RIBU*T'ION FROM RAD OACTIVE EFFLUENTS FORT CALHOUN '!."HIRD QUAR""EIR 2022 DOSE PIROJE:C'rIONS
. Liquid t::ffluent.s: 'l'ot al Body Cri tl cal Or gan Dose (mrgr1;) t 1osc (m:rem)
Batch: 6. 99'E-O l 2. o;rn+oo Cor1t i nuous : O.OOE-.,0 0 0 . 00 *,+00
'!'.'otals: 5.99-. - 0 1 2.02E+OO OOCM Quarter l y Objective: 1. SOE ~oo 5. 0L+00 Pfil'Cent of Quart er l y Ob j : 40 . 40 i 0DCI1 Annua_ Objective: 3.00E+OO 1.00E!+ l YTD Pe.rcent of Amrnal Obj: 23.57 % 20.40 %
II . Gaseous E tluer.ts: 'I'ot.al Body Gamma Tot.,.l Body 3et_,a Dose (mr.i.dl Dose (ll ad) A. Noble C--as Air ose: 0, 00:S+OO 0.00E~oo ODCM Quarte ly O ~ective: :, . 00&+00 l.OOE+Ol Percent of Qtia.rte l y obj : 0.00 0.00 l!J ODCM ~Jl u~ l Ob i~ctive: l.OOE+Ol 2.00E+Ol YTO P0rc e~t of Annua Obj : O.DO % 0.00 B. t-131, I - 133, Tritium, C-14, and Particula t es *,nt h H f-Liv~s > 8 Days: Total Body Critical Organ nnse i:mro.rnJ Oose (rnrem) I nhal tion; 8.82&- 0"' B.82E- 05 Ground ~1d Food; 4.07E-04 4.078-04 To as: 4. % -04 ,;l . 96E-04 ODC'M Quarterly Obje-ct.ive; 7 .50E100 7. r:oE+00 Percent of Qu,arterly Obj: 0. 0 'h 0.01 i ODC1.f _;?i,,.11m~.a l Obj e-cti ve: 1.5 E ~Ol .50E+01 Y'l'D Percent of .l!illnual Obj; 0.02 % l Reviewed by: V 11-18
DocuSign Envelope ID : EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 23 of 237 FORT C.Z\LHOUN STA ION FC- _21 CHEMISTRY FORM R8 QTJ.z..RTERLY CUMULATIVE DGSE CONTRIBUTION FROM RAD I OACTI VE E PP L TJB:NTS F ORT Cl , L HOTJN FOURTH Q ARTBR 2 022 DOSE PROJ ECTIONS I. Li qu i d E ff luBr ts : TO oll Body r.l.t lca l Organ Dos.e (mrem) Dose (rnre111) Batch *: 3.72E - Ol 1.43 8 +00 Contllmol.lS : O.OO E+OO 0, OOB *~O O Totals: 3. 728-0 . ,13,H +OO ODC'J.1 Que r ter l y Obj ec':: i ve ! . S DE+OO 5 . 00E+OO Perce n t of Quarter l y Ob j : 2 4.8 0 % 28 .60 % DDC'.M P...nn u al Objective: 3 . OOE+OO 1 . 00E~Ol
\'Tli'.J Percei-1 of ltnnu.;, l Oh j:
II . G~seous BE Eluents: 'ota Body Ga.w.ma Total Bod y Be t:a Dose (m:rad) Ooae {mradl A. No b le Gag Air Dose: O. DO E*OO 0. OOE ""O 0 0DOI! Quart.er y Objective : S .DO E+ 0-0 1.00E+Ol Per ce n t cf Queirt er ly ob; : 0. 00 !/; 0, 0 0 % ODCM Ann ual Objec11: i ve: 1.008+01 2. DOE Q,_ YTD Perce t oE Arrnual Obj : 0,00 % B. I - 13 1 , I -13 3 , Tr i !I: i um, C - 1 *1 , and Pa r 11:iculatea wi th Half-Lives~ 8 D~ys: T ot: 1 Body Cr .Ltic<1.l organ Dose (11ll.:r e 111 ) ose I. re111l Inhud at :l.on: 9.608 - 06 9 . 608 - 06 Grou nd tii.nd Food : 4! . 448-05 4 ,448-05 Tota ls: . 408-05 5 . 40 8-0S ODC'.M Quarter y ObJec:tive: 7.S08 +00 7.SOEl+OO Pe*cen of Q ar&er y Obj: 0.00 % O!DC'M .~nnu c1l Objec t 1 Vo;'.!: l .SO E+ Ol . so::a:+0 1 YTD Perce t oE A1111ual Obj: 0.02 % 0.02 11 -19
F6B73ADF3B Page 24 of 237 RADIOLOGICAL EFFLUENT RELEASES Table 111.1 Batch Liquid and Gas Release Summary Table 111.2 Abnormal Batch Liquid and Gaseous Release Summary Table 111.3 Gaseous Effluents - Summation of all Releases Table 111.4 Gaseous Effluent Releases - Batch Mode Table 111.5 Gaseous Effluent Releases - Continuous Mode Table 111.6 Liquid Effluents - Summation of all Releases Table 111.7 Liquid Effluent Releases - Batch Mode Table 111.8 Liquid Effluent Releases - Continuous Mode Table 111.9 Groundwater Tritium Results January 1, 2022 - December 31, 2022 111-1
DE-4A34-97A4-01 F6B73ADF3B Page 25 of 237 TABLE III . 1 BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
JANUARY THROUGH DECEMBER 2022 A. Liquid Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
- 1. Number of Batch Releases: 2 5 20 27
- 2. Total Time Period for Batch Releases(min): 619 1,718 5,010 7,347
- 3. Maximum Time Period for Batch Releases (min) : 340 626 357 626
- 4. Average Time Period for Batch Releases(min): 31 0 344 251 272
- 5. Minimum Time Period for Batch Releases(min) : 279 2 16 163 163
- 6. Average Dilution Stream Flow During Periods of Release i nto the Missouri River (mls/min) : 2.289 E+07 l.1 52 E+07 l .526E+07 l.514E+07 B. Gaseous Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
- 1. Number of Batch Releases:
- 2. Tota l Time Period for Batch Releases(min):
- 3. Maximum Time Period for Batch Releases(min)
- 4. Average Time Period for Batch Releases(min)
- 5. Minimum Time Period for Batch Releases(min)
III-2
Page 26 of 237 TABLE III. 2 ABNORMAL BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
JANUARY THROUGH DECEMBER 2022 A. Liquid Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year Number of Releases: 0 0 0 0 0 Total Activity Releases(Ci) 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B. Gaseous Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year Number of Releases: 0 0 0 0 0 Total Acti v ity Releases (Ci): O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO III-3
F6B73ADF3B Page 27 of 237 TABLE III . 3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 2022 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activation Gases Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate (uCi / sec): 0.00E+00 0 . 00E+00 0.00E+00 0.00E+00 0.00E+00 To tal Err or ( %) : 21. 2 B. Iodines Total Release (Ci): 0 . 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate (uCi / sec): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E + 00 To tal Error (%): 21.2
- c. Parti c ulates Total Release (Ci): 1. 51E- 05 0 . 00E+00 0.00E+00 0.00E+00 1. 51E- 05 Average Release Rate (uCi / sec): l.94E-06 0.00E+00 0 . 00E+00 0.00E+00 l.94E-0 6 Total Error (%): 38.498 Gross Alpha:
Total Error (%): 29 . 90 9 . 09E-06 l.12E-06 3.08E-08 7.14E-06 l.74E-05 D. Tritium Total Release (Ci) : 8.38E-02 4.93E-02 5.54E-02 6.03E-03 l.94E-01 Average Release Rate (uCi/sec): 1.08E-02 6.27E-03 6.97E-03 7.59E-04 6 . 17E-03 Total Error (%): 25.08 E. Carbon-14 Total Release (Ci): 0 . 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate (uCi / sec) : 0 . 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Error (%): 41. 062 NOTE: Values reported as zero are determined to be below the Lower Limit of Dete c tion (LLD). III-4
F6B73ADF3B Page 28 of 237 TABLE III.4 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 2022 Batch Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter YEAR Fission & Activation Gases Totals for Period: O.OOE+OO 0 . 00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Iodines Totals for Period : O.OOE+OO O. OOE+OO O.OOE+OO 0.00E+OO O. OOE+OO Particulates O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals for Period: Tritium and Gro ss Alpha NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD) . III-5
F6B73ADF3B Page 29 of 237 TABLE III . 5 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 2022 Continuous Mode Nuclides (Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates CS-137 l.SlE-05 0 .0 0E+00 0.00E+00 0.00E+00 l. Sl E -05 Totals for Period: l . SlE-05 0.00E+00 0.00E+00 0.00E+00 1. 51E- 05 Tritium and Gross Alpha H-3 8.38E-02 4.93E -02 5.54E-02 6.03E - 03 l.94E -01 ALPHA 9.09E-06 l.12E-06 3.0BE-08 7.14E-06 l .7 4E -05 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD). III -6
A4-01 F6B73ADF3B Page 30 of 237 TABLE III.6 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 2022 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fiss i on & Act iviat i on Pr o ducts Total Rel ease (No H- 3,Gas,Al pha) (C i ): 0 . 00E+00 7.94E-05 6 . B0E-03 l.05E -02 l . 74E-02 Averaqe Di luted Concentrat i on (uC i / mL ): 0.00E+00 5 . 61E-09 3 .44E -0 7 1. 37E-07 l.57E - 07 1 0 CFR 20 , App. B Limit l.00E-06(uCi/mL) Percent of Limit (%) : 0 . 00E+00 5.61E - 01 3.4 4E+0l l. 37 E+0l l.57 E+0l Total Error (%): 18. 2 1 B. Tr i ti um Total Release (Ci ): 0 . 00E+00 6.76 E - 02 2.38 E-0 3 8.38E-03 7.8 4E -02 Averaqe Dil u ted Concentration (uC i / mL): 0.00E+00 4.77E-06 l.21 E - 07 1. 09 E- 07 7.07 E -0 7 1 0 CFR 20, App. B Limit l. 00E - 03 (uC i /mL ) Percent of Limit (% ): 0.00 E+00 4.77E-01 l.21E-0 2 l.09E -02 7.07E-02 Total Error ( %) : ~ C. Diss olved & Entrained Gases Tota l Releas e (C i ): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ave raqe Di luted Conc ent ration (uC i / mL ): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ODCM Limi t 2 . 00E-04 (u Ci / mL ) Pe rc ent of Limit (%): 0.00E+00 0.00E+00 0 . 00E+00 0.00E+00 0.00E+00 Total Error (%) : 18 .14 D. Gross Alpha Radi oact i vity Total Release (C i ): 0.00E+00 0.00E+00 0 . 00E+00 0.00E+00 0.00E+00 Total Error ( %) : ~ E. Volume of Waste Released Pr i or to Dilut i on (Lit e rs): l.08E+05 2 . 57E +0 5 9.42E+05 l.31E+06 F. Volume of Dilut i on Wat er Dur inq Releases (Lic ers): 0.00E+00 l .2 3E+07 l .6 4E+07 l . 1 2 E+ 08 l .40 E+0 8 NOTE: Values reported as zero are det e rmined to b e below t h e Lowe r Limi t of Detect i on (LLD) . III - 7
86-46DE-4A34-97A4-01 F6B73ADF3B Page 31 of 237 TABLE III . 7 LI QUID EFFLUENTS JANUARY THROUGH DECEMBER 2022 Batch Mode Nuclides (C i ) 1 st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases NI -63 0.008+00 0.008+00 2.068-03 7.7 28- 03 9 . 77 8- 03 TC-99 M O. OOE+OO O.OOE+OO O.OOE +OO l. 45E-07 l.45E-0'7 CS -1 37 O.OOE+OO 5.00E-05 4.58E-03 2.38E-03 '7.0lE - 03 C0-60 O.OOE+OO 2.94E-05 l.63E-04 4.28E-04 6.2 1E- 04 M0-99 O.OOE+OO O. OOE+OO O.OOE +OO 1. 45 E- 07 l .45E - 07 Totals for Period: .OOE+OO 7 . 94E - 05 6.80E-03 l .05 E- 02 l.74E-02 Di ssolved & Entrained Gases Totals for Period: O.OOE + OO 0 . 00E+OO 0.00E +OO O.OOE+OO O.OOE +OO Tritium and Gross Alpha H-3 0.00E+OO 6 . 76E-02 2 .38E- 03 8.38E-03 7.84E - 02 NOTE: Values reported as zero are decermined to b e below t h e Lowe r Limit of Detect i on (LLD) val u es. Reported Alpha activicy was attributed co natural s h ore -live d radi onu cl ides . This was conf irmed by quarterly offs ide vendor analysis. II I -8
A4-01 F6B73ADF3B Page 32 of 237 TABLE III. 8 LIQUID EFFLUENTS JANUARY THROUGH DECEMBER 2022 Continuous Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Products Totals for Period: O.OOE+OO O. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Dissol ved & Entrained Gases Totals for Period: O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO Tritium and Gross Alpha H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD) . III - 9
F6873ADF3B Page 33 of 237 TABLE III. 9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2022 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-lA Tritium O.OOE+OO O.OOE+OO 0.00E+OO O. OOE+OO FE-55 0 . 00E+OO NI-63 0 . 00E+OO Sr-90 O.OOE+OO Tota l Gamma O.OOE+OO MW-1B Tritium O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-SS O.OOE+OO NI-63 O.OOE+OO Sr-90 0 . 00E+OO Total Gamma 0.00E+OO MW-2 Tritium O.OOE+OO 0 . 00E+OO 0.00E+OO O.OOE+OO FE-55 O.OOE+OO NI-63 O.OOE+OO Sr-90 O.OOE+OO Total Gamma O.OOE+OO MW - 3 Tritium O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO FE-55 O.OO E+OO NI-63 O.OOE+OO Sr-90 0.00E+OO Total Gamma 0.00E+OO MW-3A Tritium O.OOE+OO O.OOE+OO O. OOE+OO O. OOE+OO FE-SS O. OOE+OO 0 . 00E+OO O.O OE+OO O. OOE+OO NI-63 O.OOE+OO O. OOE+OO 0.00E+OO O. OOE+OO Sr - 90 8 . 87E-01 O.OOE+OO 0.00E+OO 7 . 38E-01 Tota l Gamma O. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MW-3B Tritium O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO FE-SS O.OOE+OO 0.00E+OO O. OOE+OO O.OOE+OO NI-63 O.OOE+OO O.OOE+OO O. OOE+OO O.OOE+OO Sr-90 O.O OE+OO O.OOE+OO O.O OE+OO 0 . 00E+OO Total Gamma O.OOE+OO O.OOE+OO O.OOE+OO O. OOE+OO MW-4B Tritium O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO FE-SS O.OOE+OO NI-63 0 . 00E+OO Sr-90 O.OOE +OO Total Gamma 0.00E+OO MW-SA Tritium O. OOE+OO 0.00E+OO 0.00E+OO FE-55 O. OOE+OO NI - 63 O.OOE+OO Sr-90 6.37E-Ol Total Gamma O.OOE+OO MW-SB Tritium O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO FE-SS 0.00E+OO NI-63 O.OOE+OO Sr - 90 O.OOE+OO Total Gamma O.OOE+OO III-10
DocuSign Envelope ID : EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 34 of 237 TABLE III. 9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2022 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW- 6 Tritium O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO FE-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NI-63 0.00E+OO O.OOE+OO O.OOE+OO 0.00 E+OO Sr-90 6.48E-01 6.48E-01 0.00E+OO O.OOE+OO Total Gamma 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO MW-12A Tritium O.OOE+OO O.OOE+OO 0.00E+OO FE-55 NI-63 Sr-90 Total Gamma Tritium O. OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE - 55 O.OOE+OO NI-63 O.OOE+OO Sr-90 0.00E+OO Total Gamma 0.00E+OO EAST LAGOON Tritium O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE - 55 NI-63 Sr-90 Total Gamma 0 . 00E+OO O.OOE+OO O. OOE+OO O.OOE+OO WEST LAGOON Tritium 0.00E+OO O.OOE+OO O. OOE+OO O.OOE+OO FE-55 NI-63 Sr - 90 Total Gamma O.OOE+OO O. OOE+OO O.OOE+OO O.OOE+OO NORTH STORMWATER HDR Tritium 0 . 00E+OO 0 . 00E+OO FE-55 NI-63 Sr - 90 Tota l Gamma 0 . 00E+OO 0 . 00E+OO SOUTH S TORMWATER HDR Tritium O.OOE+OO O.OOE+OO FE - 55 NI-63 Sr-90 Tota l Gamma 0.00E+OO O.OOE+OO MW-13A Tritium 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO FE-55 0.00E+OO 0.00E+OO O.OOE+OO 0.00E+OO NI-63 O.OOE+OO O.OOE+OO O.OOE+OO O. OOE+OO Sr-90 0.00E+OO 0.00E+OO 0.00E+OO O.OOE+OO To t al Gamma O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MW-13B Tr i tium O.OOE+OO O.OOE+OO O.OOE+OO 0 . 00E+OO FE-55 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO NI-63 O.OOE+OO O.OOE+OO 0.00E+OO O.O OE+OO Sr - 90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Total Gamma O.OOE+OO O.OOE+OO 0.00E+OO O. OOE+OO III-11
DocuSig n Envelope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 35 of 237 TABLE III . 9 GROUNDWATER ANALYSIS RESULTS pCi / L JANUARY THROUGH DECEMBER 2022 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-14 Trit ium O. OOE+OO 0.00E+OO O.OOE+OO O. OOE+OO FE-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NI-63 O.OOE+OO O.OOE+OO O.OOE+OO O. OOE+OO Sr-90 6.BOE-01 O.OOE+OO O.OOE+OO O. OOE+OO Total Gamma O.OOE+OO 0.00E+OO O.OOE+OO O. OOE+OO MW-16 Tritium O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-55 O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO NI -63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO 7.77E - 01 Total Gamma O.OOE+OO O. OOE+OO 0.00E+OO 0 . 00E+OO MW-15 Tritium 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-55 O.O OE+OO O. OOE+OO O.OOE+OO O. OOE+OO NI-63 O. OOE+OO 0 . 00E+OO O.OOE+OO O.OOE+OO Sr-90 O.OOE+OO 0.00E+OO O. OOE+OO 0.00E+OO Total Gamma 0 . 00E+OO O. OOE+OO O.OOE+OO O.O OE+OO SW-6 ISFSI Tritium 0.00E+OO 0 . 00E+OO FE-55 NI-63 Sr - 90 Tota l Gamma 0.00E+OO O. OOE+OO SW - 8 NORTH PA Tritium O.OOE+OO 0.00E+OO FE-55 NI -63 Sr-90 Total Gamma O.OOE+OO 0.00E+OO NOTE: Values reported as zero are determined t o be below the Lower Limit of Detection (LLD ) . On ly Tritium and Gamma are required f or each sampling event . Hard to detect (HTD) nuclide sampling f requen cy is per station procedures. Missed sampling events are covered in the executive summary. I II - 1 2
F6B73ADF3B Page 36 of 237 SECTION IV DOSE FROM GASEOUS EFFLUENTS GASPAR II OUTPUT January 1, 2022 - December 31, 2022 IV-1
F6B73ADF3B Page 37 of 237 Radioactive Effluent Releases - First, Second, Third and Fourth Quarters 2022 GASEOUS EFFLUENTS Radioactive gaseous releases for the reporting period totaled 0.00E+00 curies of inert gas. The gross gaseous activity release rates were 0.00E+00 µCi/sec for the first quarter, 0.00E+00 µCi/sec for the second quarter, 0.00E+00 µCi/sec for the third quarter, and 0.00E+00 µCi/sec for the fourth quarter. No radioactive halogen releases were released during the reporting period from gaseous effluent discharges. Radioactive particulate releases for the reporting period totaled 1.51 E-05 curies . The particulate release rates were 1.94E-06 µCi/sec for the first quarter, 0.00E+00 µCi/sec for the second quarter, 0.00E+00 µCi/sec for the third quarter, and 0.00E+00 µCi/sec for the fourth quarter. Radioactive tritium released during the reporting period totaled 1.94E-01 curies . Off-site vendor analysis of weekly composite samples indicated that no gross alpha radioactivity was released during the reporting period . IV-2
F6B73ADF3B Page 38 of 237 POTENTIAL DOSES TO INDIVIDUALS AND POPULATIONS A. Potential Annual Doses to Individuals from Gaseous Releases Total body, skin, and organ doses from ground releases were calculated in mRem to an average adult, teenager, child , and infant using the annual configuration of the GASPAR II program. Results of each receptor are shown in Tables IV-A-1 through IV-A-36. Also, the doses to the same groups, Table IV-B-1, in units of mRad, due to gamma and beta radiation carried by air, were computed using GASPAR II. In its annual configuration , GASPAR II assumes that all release rates are entered in curies per year (Ci/yr) . The inputs to GASPAR II for the annual period from January 1, 2022 through December 31 , 2022 were as follows: (1) All gaseous effluents (2) Entrained gases (Ar-41, Xe-131 M, Xe-133M, Xe-133 , Xe-135M , Xe-135, Kr-85M, Kr-87 , and Kr-88) from liquid effluents. (3) Annual X/Q at the actual receptor locations, which are corrected for open terrain and plume depletion, are calculated according to Regulatory Guide 1.111 . Also included are annual deposition rates corrected for the open terrain factor. (4) The production, intake , and grazing fractions were as follows: 1.0 for leafy vegetables grown in the garden of interest, 0.76 for produce grown in the garden of interest, 0.5 for the pasture grazing season of the milk animal, 1.0 for pasture grazing season of the meat animal , and 8 g/m 3 for the air water (humidity) concentrations. (5) All dose factors, transport times from receptor to individual , and usage factors are defined by Regulatory Guide 1.109 and NUREG-0172. (6) Site specific information , within a five-mile radius of the plant, on types of receptors located in each sector was used . That is, if a cow was not present in a sector, then the milk pathway for that sector was not considered . If it was present, then the actual sector distance was used. These inputs introduce a most conservative approach for the following reasons : (1) The open terrain and deposition corrections increase annual X/Q by a factor ranging between 1.0 and 4.0 IV-3
F6B 73ADF3B Page 39 of 237 (2) The production, intake, and grazing fractions, as defined in the input definition statement, represent the environment in an extremely conservative manner. B. Potential Semiannual Doses to Population from Gaseous Releases The GASPAR II program in its annual configuration was also used to calculate the ALARA integrated population dose summary for the total body, skin , and organ doses in man-rem for all individuals within a 50-mile radius . The population-integrated dose is the summation of the dose received by all individuals and has units of man-thyroid-rem when applied to the summation of thyroid doses . The same inputs were used as in the individual case with the addition of the following: (1) A total population of 1,053,476 (based on the 2020 census) was used to define the sector segments within a 50-mile radius of the plant. (2) Production of milk, meat, and vegetation is based on 1973 annual data for Nebraska as recommended by the Nuclear Regulatory Commission for use in GASPAR II. IV-4
Page 40 of 237 TABLE IV - A- 1 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 1 RES AT 4 . 36 MILES N AN NUAL BETA AIR DOSE= 0 . 00E+OO MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00 E+O0 MILLRADS PATHWAY T . BODY GI -T RACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+- --------- +------ ----+---------- +----------+-------- --+------- --- +---------- +------- --- +
PL UME : 0 .00E +00 : 0 . 00E+00 : 0 . 00 E+ 00 : 0 . 00 E+00 : 0 . 00 E+ 00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
---------+-- -------- +---------- +----------+----------+------ ----+------- --- +---------- +---- ------ +
GRO UN D : 2 . Bl E- 06 : 2 . Bl E- 06 : 2 . Bl E- 06 : 2 . BlE - 06 : 2 . Bl E- 06 : 2 . BlE - 06 : 2 . BlE - 06 : 3 . 27E - 06 :
--------- +-------- --+------ ---- +---------- +-- -------- +----- -----+---------- +--- -------+----- ----- +
INHAL ADULT : 5 . 96 E- 07 : 5 . 76E - 07 : 2 . 30E- 08 : 6 . 06 E- 07 : 5 . 87E- 07 : 5 . 76E - 07 : 5 . 79E - 07 : 5 . 76E - 07 :
---------+ ---------- +--- -------+ ---------- +---------- +---------- +----------+---------- +- --------- +
TEEN : 5 . 96E - 07 : 5 . Bl E- 07 : 3 . 23E- 08 : 6 . 22E- 07 : 5 . 96E- 07 : 5 . Bl E- 07 : 5 . 87 E- 07 : 5 . BlE - 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHI LD : 5 .1 9E- 07 : 5 . 13E- 07 : 4 . 37E- 08 : 5 . 53E- 07 : 5.27E- 07 : 5 . 13E - 07 : 5 . lBE - 07 : 5 . 13E- 07 :
--------- +---------- +- --------- +---------- +---------- +-------- -- +---------- +---------- +----------+
INFANT : 2 . 97E - 07 : 2 . 95 E- 07 : 2 . 64E - 08 : 3 . 25E - 07 : 3 . 03E-07 : 2 . 95E - 07 : 2.99E - 07 : 2 . 95E - 07 :
--------- +----------+---------- +---------- +----------+--- ------- +---------- +---------- +---------- +
IV- 5
A4-01 F6B73ADF3 B Page 41 of 237 TABL E IV- A- 2 FORT CALHOUN ANNUAL 2022 , DOS E PROJECTI ONS SPECIAL LOCAT I ON NO . 2 RES AT 1 . 93 MILE S NNE ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E +00 MI LL RADS PATHWAY T . BODY GI - TRACT BONE LI VER KIDNEY THYROID LUNG SKIN
------ - -- +---------- +--- ------- +---------- +---------- +-- - - --- - - - +- --------- +------- --- +-- -------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +-------- -- +----- - -- -- +---------- +------ ---- +---------- +------- --- +
GROUND : l . lSE - 05 : l. lSE - 05 : l . lSE - 05 : l . lS E- 05 : l . lSE - 05 : l . lSE - 05 : l . l SE - 05 : l . 38 E- 05 :
--------- +---------- +---------- +-------- -- +--- - -- ---- +---------- +--------- - +-------- -- +---------- +
INHAL ADULT : 3 . 22E - 06 : 3 . l0E - 06 : l . 32E - 07 : 3 . 27E - 06 : 3 . 16E- 06 : 3 . l0E - 06 : 3 . 12E - 06 : 3 . l0E - 06 :
--------- +---------- +---------- +----- - --- - +- - --- ----- +---------- +---------- +------ - --- +---------- +
TEEN : 3 . 21E - 06 : 3 .1 3E-06 : l . 84 E- 07 : 3 . 36 E- 06 : 3 . 21E - 06 : 3 . 13 E- 06 : 3 . 16E - 06 : 3 . 13E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHIL D : 2 . S0 E- 06 : 2 . 76E - 06 : 2 . 49 E- 07 : 2 . 9 9E - 06 : 2 . 84 E- 06 : 2 . 76 E- 06 : 2 . 79 E- 06 : 2 . 76E - 06 :
--------- +---------- +---------- +--------- -+ ---------- +---------- +---------- +---------- +---------- +
INFANT : l. 60 E- 06 : l . 59E - 06 : l. SlE - 07 : l. 76 E- 06 : l . 6 4E- 06 : l. 59 E- 06 : l . 61 E- 06 : l . 59E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
I V- 6
A4-01 F6B73ADF3B Page 42 of 237 TABLE IV- A- 3 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO. 3 RES AT 1 . 59 MILES NE ANNUAL BETA AIR DOSE = 0 . 00E +00 MILLRADS ANNUAL GAMMA AIR DOSE = 0 . 00E+00 MI LLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0.00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
GROUND : l.25E - 05 : l . 25E - 05 : l . 25E - 05 : l . 25E - 05 : l . 25E - 05 : 1 . 25E - 05 : l. 25E - 05 : l . 45E - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
INHAL ADULT : 4 . 42E - 06 : 4 . 26E - 06 : l . 87E - 07 : 4 . 50E - 06 : 4.34E - 06 : 4 . 25E - 06 : 4 . 28E - 06 : 4 . 25E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
TEEN : 4 . 41E - 06 : 4 . 29E - 06 : 2 . 62E - 07 : 4 . 62E - 06 : 4 . 41E - 06 : 4 . 29E - 06 : 4 . 34E - 06 : 4 . 29E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 3 . 84E - 06 : 3 . 79E - 06 : 3 . 55E - 07 : 4 . l l E- 06 : 3 . 90E - 06 : 3 . 79E - 06 : 3.83E - 06 : 3 . 79E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
INFANT : 2 . 20E - 06 : 2 .l BE- 06 : 2 . 15E- 07 : 2 . 42E - 06 : 2 . 25E - 06 : 2 . l BE - 06 : 2.21E - 06 : 2 . lBE - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV- 7
A4-01 F6B73ADF3B Page 43 of 237 TABLE IV - A- 4 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 4 RES AT 4 . 79 MILES ENE ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +--------- - +----- -----+--- ------- +---------- +-------- -- +---------- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
---- ----- +---------- +- ----- --- - +---------- +---------- +--------- - +-------- -- +-------- --+------- --- +
GROUND : 6 . 05E - 07 : 6 . 05E-07 : 6 . 05E - 07 : 6 . 05E - 07 : 6 . 05E - 07 : 6 . 05E - 07 : 6 . 05E - 07 : 7 . 06 E-07 :
--------- +---------- +---- ------+----- ----- +---------- +---------- +----- ----- +---------- +---------- +
INHAL ADULT : 4 . 03E - 07 : 3 . 90E - 07 : l . 50E-08 : 4 . 09E - 07 : 3 . 97E - 07 : 3 . 90E - 07 : 3 . 92E - 07 : 3 . 90E - 07 :
---------+--- ------- +----------+---------- +----------+---------- +---------- +------- --- +---------- +
TEEN : 4.03E - 07 : 3 . 94E-07 : 2 . l0E - 08 : 4 . 20E - 07 : 4 . 03E - 07 : 3 . 93E - 07 : 3 . 97E - 07 : 3 . 93E - 07 :
--------- +---------- +----------+- --------- +-- -------- +---------- +---------- +---------- +---------- +
CHILD : 3 . 51E - 07 : 3 . 47E- 07 : 2.84E - 08 : 3 . 73E - 07 : 3.56E - 07 : 3 . 47E - 07 : 3.51E - 07 : 3 . 47E - 07 :
--------- +---------- +---------- +---------- +----------+---------- +---------- +---------- +---------- +
INFANT : 2 . 0lE - 07 : 2 . 00E - 07 : 1. 72E - 08 : 2 . 19E- 07 : 2 . 05E - 07 : 2 . 00E - 07 : 2 . 02E - 07 : 2 . 00E - 07 :
--------- +---------- +---------- +---------- +----------+---------- +----------+---------- +---------- +
IV - 8
F6B73ADF3B Page 44 of 237 TABLE IV- A- 5 FORT CALHOUN ANNUAL 2022 , DOS E PROJECTI ONS SP ECIAL LOCATI ON NO . 5 RES AT 4 . 67 MILES E ANNUAL BETA AIR DOSE= 0 . 00 E+O0 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +----------+-- ----- --- +---------- +------- --- +-------- -- +---------- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 .00E+00 : 0 . 00 E+ 00 : 0 . 00E+00 : 0 . 00E+00 :
---------+---------- +----------+ ---------- +----------+---------- +---------- +---------- +---------- +
GRO UND : 9 . 98E - 07 : 9 . 98E - 07 : 9 . 98 E- 07 : 9 . 98 E-07 : 9 . 98 E- 07 : 9 . 98 E- 0 7 : 9 . 98E-07 : l . 16E- 06 :
--------- +---------- +---------- +----------+----------+----------+----------+---------- +--------- - +
INHAL ADULT : 5 . 04E - 07 : 4 . SSE - 07 : l . 87E - 08 : 5 . llE - 07 : 4 . 96E - 07 : 4 . 87E - 07 : 4 . 90E - 07 : 4 . 87E - 07 :
--------- +---------- +---------- +---------- +- --------- +--------- -+--- ------- +---------- +---------- +
TEEN : 5 . 04 E- 07 : 4 . 92E - 07 : 2 . 61E- 08 : 5 . 25E- 07 : 5 . 03E - 07 : 4 . 92E - 07 : 4 . 96 E- 07 : 4 . 92E - 07 :
-- ------- +---------- +---------- +---------- +---------- +---------- +----------+---------- +---------- +
CH IL D : 4 . 39E - 07 : 4 . 34E - 07 : 3 . 5 4E-0 8 : 4 . 66E- 07 : 4 . 4 5E - 07 : 4 . 34E - 07 : 4 . 38E - 07 : 4 . 34E - 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
INFANT : 2 . SlE - 07 : 2 . S0 E-0 7 : 2 .14E-0 8 : 2 . 74E - 07 : 2 . 56E- 07 : 2 . S0E - 07 : 2 . 53E - 07 : 2 . S0 E-07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +----------+
IV- 9
F6B73ADF3B Page 45 of 237 TABLE IV - A- 6 FORT CALH OUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 6 RES AT 4 . 22 MIL ES ESE ANNUAL BETA AIR DOSE= 0.00E+00 MI LLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+0O MILLRADS PATHWAY T . BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--- ------+ ---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +- ---------+---------- +---------- +---------- +---------- +----------+---------- +---------- +
GROUND : 1.68E-06 : l . 68E - 06 : l . 68E - 06 : l.68E - 06 : l.68E - 06: 1.68E - 06 : l. 68E - 06 : 1 . 96E - 06 :
--------- +----------+---------- +---------- +---- ------ +---------- +----------+----------+---------- +
INHAL ADULT : 9 . 17E-07 : 8 . 86E - 07 : 3.48E - 08 : 9 . 31E-07 : 9 . 02E-07 : 8 . 86E - 07 : 8 . 91E- 07 : 8 . 86E - 07 :
-------- - +--------- -+----------+---------- +---------- +---------- +--- ------- +------- ---+----- ----- +
TEEN : 9 .1 6E - 07 : 8 . 94E - 07 : 4 . 87E - 08 : 9 . SSE-07 : 9 . 16E-07 : 8 . 94E - 07 : 9 . 03E-07 : 8 . 94E - 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 7 . 99E - 07 : 7 . 90E - 07 : 6 . 59E - 08 : 8 . 49E - 07 : 8 .l 0E - 07 : 7 . 89E - 07 : 7 . 97E - 07 : 7 . 89E - 07 :
--------- +---------- +----------+----------+----------+---------- +---------- +---------- +----------+
INFANT : 4 . 57E - 07 : 4 . 54E - 07 : 3 . 99E - 08 : 4 . 99E - 07 : 4 . 67E - 07 : 4 . 54E - 07 : 4 . 59E - 07 : 4 . 54E - 07 :
--------- +---------- +---------- +---------- +----------+----------+---------- +---------- +---------- +
IV-1 0
F6873ADF3B Page 46 of 237 TABLE I V- A- 7 FORT CALHO UN ANN UAL 2022 , DOS E PROJECTI ONS SP ECIAL LOCATI ON NO . 7 RES AT 1 . 67 MILES SE ANNUAL BETA AIR DOSE= 0 . 00E+00 MI LLRADS ANNUAL GAMMA AI R DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LI VER KI DNEY THYROID LUNG SK IN
--------- +------- -- - +-------- -- +---------- +---------- +------- --- +-------- -- +-------- - - +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+ 00 :
-- -- ----- +---------- +---------- +---------- +- -- - ----- - +------ ---- +----------+---------- +---------- +
GROUND : 2 .6 2E - 05 : 2 . 62 E- 05 : 2 . 62E - 05 : 2 . 62E - 05 : 2 . 62E - 05 : 2 . 62 E- 05 : 2 . 62 E- 05 : 3 . 06 E- 05 :
-- ---- --- +---------- +-- --- -----+ --------- - +---------- +------ ---- +-- -------- +--- ------- +------ ---- +
INHAL ADULT : 6 . 90E - 06 : 6 . 65E - 06 : 2 . 86E - 07 : 7 . 02E - 06 : 6 . 78E- 06 : 6 . 64E - 06 : 6 . 69E - 06 : 6 . 64E - 06 :
----- - ---+-- -------- +---------- +---------- +------ ---- +---------- +---------- +------ ---- +---------- +
TEEN : 6 . 89E - 06 : 6 . 71 E- 06 : 4 . 0l E- 07 : 7 . 21E - 06 : 6 . 89E - 06 : 6 . 70E - 06 : 6 . 78E - 06 : 6 . 70E - 06 :
--------- +---------- +---------- +--------- - +----------+---------- +---------- +---------- +---------- +
CHILD : 6 . 00E - 06 : 5 . 92 E- 06 : 5 . 42E - 07 : 6 . 41E - 06 : 6. 09 E- 06 : 5 . 92E - 06 : 5 . 98E - 06 : 5 . 92E - 06 :
------ --- +---------- +---------- +---------- +----------+----------+---------- +---------- +---------- +
I NFANT : 3 . 43 E- 06 : 3 . 4 1E- 06 : 3 . 28 E- 07 : 3 . 77E- 06 : 3 . Sl E- 06 : 3 . 41 E- 06 : 3 . 45E - 06 : 3 . 41E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +-- --- ----- +---------- +---------- +
IV- 11
F6B73ADF3B Page 4 7 of 237 TABLE IV- A- 8 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 8 RES AT 0.65 MILES SSE ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
-------- -+--- --- ----+----------+ --- -------+ --- ------ - +---------- +---------- +---------- +---------- +
PLUME : 0 . 00E+O0 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+OO : 0 . 00E+00 : 0 . 00E+00 :
--- ------ +---------- +------ ----+-- - -------+----------+--------- - +-------- -- +------ ---- +---------- +
GROUND : 3 . 74E-04 : 3 . 74E-04 : 3 . 74E- 04 : 3 . 74E - 04 : 3 . 74E - 04 : 3 . 74E - 04 : 3 . 74E - 04 : 4 . 36E-04 :
--- ------ +---------- +------ ----+----------+ --- ------ - +---------- +---------- +------ ---- +---- ------ +
INHAL ADULT : 3 . 09E-05 : 2 . 97E-05 : l.37E - 06 : 3 . lSE-05 : 3 . 03E-05 : 2 . 97E-05 : 2 . 99E-05 : 2 . 97E - 05 :
------- --+--- ---- ---+-------- --+----------+--------- - +---------- +-- -- ------ +---------- +---------- +
TEEN : 3 . 0BE - 05 : 3 . 00E-05 : l . 93E - 06 : 3 . 24E - 05 : 3 . 0BE - 05 : 2 . 99E - 05 : 3 . 03E - 05 : 2 . 99E - 05 :
-- ------- +---------- +--------- -+ ---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 2 . 68E - 05 : 2 . 65E - 05 : 2 . 60E - 06 : 2 . BBE - 05 : 2 . 73E - 05 : 2 . 64E - 05 : 2 . 67E - 05 : 2 . 64E - 05 :
-- ------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
INFANT : l . 53E - 05 : l . 52E - 05 : l. 58E- 06 : 1 . 70£ - 05 : 1.57£-05 : 1 . 52£ - 05 : 1 . 54£ - 05 : 1 . 52£ - 05 :
--------- +---------- +------ - --- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 1 2
A4-01 F6B73ADF3B Page 48 of 237 TAB LE IV- A- 9 FORT CAL HOUN ANNUAL 2022 , DOS E PROJECTI ONS SP ECIAL LOCATI ON NO . 9 RES AT 0 . 73 MI LES S ANNUAL BETA AIR DOSE= 0 . 00E + 00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MI LL RADS PATHWAY T. BODY GI - TRACT BON E LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +- --------- +----- - - --- +- --------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E + 00 :
------- - - +- - -- - - ---- +- -- - ----- - +---- - - --- - +- --------- +---- -- -- - - +---------- +---------- +---------- +
GRO UND : l. 68E - 04 : l . 68E - 04 : l. 68E - 04 : l. 68 E- 04 : l. 68 E- 04 : l . 68E - 04 : l . 68E - 04 : l . 96E - 04 :
------ -- - +---------- +----- - ---- +---------- +---------- +-- - ------- +-- -- - -- --- +- - - -- - ---- +---------- +
INHAL ADULT : l . 94E - 05 : l . 86E - 05 : 8 . 70E - 07 : l . 97E - 05 : l . 90 E- 05 : 1 . 86E - 05 : l . 87E - 05 : l . 86E - 05 :
-- - - - -- -- +---------- +---------- +---------- +---------- +---------- +---------- +--------- - +--- - ---- -- +
TEEN : l . 93 E- 05 : l . BBE - 05 : l. 22E - 06 : 2 . 03 E- 05 : l . 93 E- 05 : l. BB E- 05 : l . 90E - 05 : l . BBE- 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHIL D : l . 68E - 05 : l . 66E - 05 : l . 65 E- 06 : l . Bl E- 05 : l . 7 1E- 05 : l. 66 E- 05 : l . 68E - 05 : l . 66E- 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IN FAN T : 9 . 62E - 06 : 9 . 5 4E- 06 : 9 . 98 E- 07 : l. 06 E- 05 : 9 . 85 E- 06 : 9 . 53 E- 06 : 9 . 66 E- 06 : 9 . 53 E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 13
F6B73ADF3B Page 49 of 237 TAB LE IV - A-1 0 FORT CALHO UN ANNUAL 2022 , DOSE PROJECTI ONS SPEC I AL LOCATI ON NO. 10 RES AT 0 . 65 MILES SSW ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MI LL RADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +------- --- +----- - -- -- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0.00E+00 : 0.00E+00 : 0 . 00E +00 : 0 . 00E+00 : 0 . 00E+00 :
---------+----------+---------- +---------- +---------- +---------- +---------- +---------- +---------- +
GROUND : 8 . 73E - 05 : 8 . 73E - 05 : 8 . 73E - 05 : 8.73E - 05 : 8 . 73E - 05 : 8 .7 3E - 05 : 8 . 73E - 05 : l . 02E - 04 :
--------- +----------+----------+----------+---------- +---------- +---------- +---------- +---------- +
INHAL ADULT : l.99E-05 : l . 91E - 05 : 8 . 99E - 07 : 2.02E - 05 : l.95E - 05 : l.90E - 05 : l . 92 E- 05 : l . 90E - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +----------+---------- +---------- +
TEEN : l . 98E - 05 : l . 92E - 05 : 1.26E- 06 : 2.0BE - 05 : l.98E - 05 : 1.92E - 05 : l. 94 E- 05 : l . 92E - 05 :
--------- +---------- +---------- +----------+---------- +---------- +---------- +---------- +---------- +
CHILD : l.7 2E- 05 : 1 . 70E - 05 : 1. 70E - 06 : 1. BSE - 05 : 1.75E- 05 : 1.7 0E- 05 : 1 . 72E - 05 : l . 70E- 05 :
--------- +----------+---------- +---------- +---------- +---------- +----------+----------+---------- +
INFANT : 9.85 E- 06 : 9 . 76E - 06 : l. 03 E- 06 : l.0 9E-05 : l.0lE- 05 : 9 . 76E - 06 : 9 . 90 E- 06 : 9.76E - 06 :
--------- +----------+----------+----------+---------- +----------+----------+---------- +---------- +
IV - 14
F6B73ADF3B Page 50 of 237 TABLE IV - A- 11 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 1 1 RES AT 0 . 73 MIL ES SW ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +---------- +--------- - +------- --- +
PLUME : 0 . 00E+00 : 0.00E+00 : 0 . 00 E+00 : 0 . 00E+00 : 0.00 E+00 : 0 . 00E +00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +- --- - ----- +
GROUND : 5 . 30E - 05 : 5 . 30E - 05 : 5 . 30E - 05 : 5 . 30E - 05 : 5 . 30 E- 05 : 5 . 30E - 05 : 5.30E - 05 : 6 .l BE - 05 :
--- - - ---- +---------- +---------- +---------- +---------- +-- - --- ---- +----- -- -- - +- - - ------- +---------- +
INHAL ADULT : l . 48E - 05 : 1.42E- 05 : 6.70E - 07 : 1 . S0E - 05 : l . 45 E- 05 : l . 42E - 05 : l . 43E - 05 : l . 42E-05 :
-- --- - - -- +- - -- - - ---- +---------- +---------- +---------- +---------- +--- ---- - -- +---- - -- -- - +---------- +
TE EN : 1 . 47E - 05 : l . 43E - 05 : 9 . 39E - 07 : l . SSE - 05 : 1 . 47E - 05 : 1 . 43E - 05 : l.45E - 05 : l . 43E - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : l . 28E - 05 : 1 .26 E- 05 : 1 . 27 E- 06 : l . 38 E- 05 : 1 .30 E- 05 : l . 26 E- 05 : l . 28E - 05 : l . 26E - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
I NFANT : 7 . 33E - 06 : 7 . 27 E- 06 : 7 . 69E- 07 : 8 . 12E- 06 : 7 . Sl E- 06 : 7 . 26E - 06 : 7 . 36 E- 06 : 7 . 26E - 06 :
- -------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
I V- 15
86-46DE-4A34-97A4-01 F6B73ADF3B Page 51 of 237 TABLE IV- A- 12 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SP ECIAL LOCATI ON NO. 12 RES AT 1 . 06 MILES WSW ANNUAL BETA AIR DOSE = 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI-TRAC T BONE LI VER KIDNEY THYROID LUNG SKIN
-- - - ----- +---------- +---------- +------ - --- +-- - ------- +------- -- - +- --------- +---------- +---------- +
PLUME : 0 . 00E+00 : 0.00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00E+00 :
--------- +---------- +-- - ------- +------ - --- +---------- +---------- +----- - ---- +--- - - -----+---- - - ---- +
GROUND : 2 . 62E - 05 : 2 . 62E - 05 : 2 . 62E - 05 : 2 . 62E - 05 : 2 . 62E - 05 : 2 . 62E - 05 : 2 . 62E - 05 : 3 . 06E - 05 :
------ --- +- -- ------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
INHAL ADULT : 7 . 36E - 06 : 7 . 09 E- 06 : 3 . 03E - 07 : 7. 4 8E - 06 : 7.23E - 06 : 7 . 09E - 06 : 7 .1 3E - 06 : 7 . 09E - 06 :
--------- +--------- -+----- ----- +---------- +---------- +---------- +-------- - - +---------- +- -------- - +
TEEN : 7 . 35E - 06 : 7 . 16E- 06 : 4 . 25E - 07 : 7 . 69E - 06 : 7 . 34E - 06 : 7 . 1 5E - 06 : 7 . 23E - 06 : 7 . 15E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CH ILD : 6 . 40E - 06 : 6.32E - 06 : 5.74E - 07 : 6.84E - 06 : 6.49E - 06 : 6.3 1E - 06: 6.38E - 06 : 6 . 31 E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
INFANT : 3 . 66E - 06 : 3 . 63E - 06 : 3 . 4 8E - 07 : 4.02E - 06 : 3 . 74E - 06 : 3 . 63E - 06 : 3 .6 8E- 06 : 3 . 63E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV-1 6
86-46DE-4A34-97 A4-01 F6B73ADF3B Page 52 of 237 TABL E IV- A- 13 FORT CALHO UN ANNUAL 2022 , DOSE PROJECTI ONS SP ECI AL LOCATI ON NO . 13 RES AT 1 . 20 MILE S W ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI-TRAC T BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---- - -- - - - +--------- -+
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +-- --- - ---- +----- ----- +
GROUND : 2.56E - 05 : 2 . 56E- 05 : 2.56E - 05 : 2.56E - 05 : 2.56E - 05 : 2 . 56 E- 05 : 2 . 56E - 05 : 2 . 98E - 05 :
- - -- - ---- +- - - - ------ +---------- +---- - - - --- +- ---- -- - -- +-- - - - ----- +- - -------- +---------- +---------- +
INHAL ADU LT : 6 . 92E - 06 : 6 . 65E - 06 : 3 . 04E - 07 : 7 . 04E - 06 : 6.79E - 06 : 6.64E - 06 : 6 . 69E - 06 : 6 . 64E - 06 :
-------- - +---------- +---------- +---------- +---------- +--------- - +- -- - --- - -- +- - -- - - ---- +---------- +
TEEN : 6 . 90E - 06 : 6 . 71E - 06 : 4 . 25E-07 : 7 . 2 4E- 06 : 6.90E - 06 : 6 . 70 E- 06 : 6 . 78 E- 06 : 6 . 70E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CH IL D : 6 . 00 E- 06 : 5 . 92E - 06 : 5 . 75E - 07 : 6 . 44E - 06 : 6 .l 0E - 06 : 5 . 92E - 06 : 5.99 E- 06 : 5 . 92 E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
INFANT : 3 . 43 E- 06 : 3 . 41 E- 06 : 3 . 48E - 07 : 3 . 79E - 06 : 3 . 5 1E- 0 6 : 3 . 41E- 06 : 3 . 45 E- 06 : 3 . 4 1E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV -1 7
86-46DE-4A34-97 A4-01 F6B73ADF3 B Page 53 of 237 TABL E IV- A- 14 FORT CALHOUN ANNUAL 2022 , DOSE PRO JE CTI ONS S PECIAL LOCAT I ON NO . 1 4 RES AT 2.60 MIL ES WNW ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00 E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--- - ----- +---------- +---------- +---------- +-------- -- +-- - - ------ +---------- +------ ---- +-- -------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E +00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +- ------ -- - +-- -------- +--- - ------ +---------- +----- -- - -- +---------- +---------- +
GROUN D : 4 . 86E - 06 : 4 . 86E - 06 : 4 . 86 E- 06 : 4 . 86E - 06 : 4 . 86 E- 06 : 4 . 86E - 06 : 4 . 86E - 06 : 5 . 67E - 06 :
--------- +---------- +---------- +---------- +---------- +- ------- - - +---------- +--------- - +--- ------- +
INHAL ADULT : l . 56E - 06 : l . SlE - 06 : 6 . 2 9E - 08 : l . 59E - 06 : l. 54E - 06 : l . SlE - 06 : l . 52E - 06 : l . Sl E- 06 :
-- -- - ---- +---------- +---------- +---- -- - --- +- - -- - - ---- +---------- +---------- +---- - - ---- +---------- +
TEEN : l . 56 E- 06 : l. 52E-06 : 8 . BlE- 08 : l . 63 E- 06 : l. 56E - 06 : l . 52 E- 06 : l . 54 E- 06 : l . 52E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CH IL D : l. 36 E- 06 : l . 34 E- 06 : l .1 9E- 07 : l. 45E - 06 : l . 38E - 06 : l . 3 4E - 06 : l . 36 E- 06 : l . 34 E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
I NFANT : 7 . 78 E- 0 7 : 7 . 72 E- 07 : 7 . 22E - 08 : 8 . 52E - 07 : 7 . 95E - 07 : 7 . 7 2E- 07 : 7 . BlE - 07 : 7 . 72 E- 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV- 1 8
86-46DE-4A34-97A4-01F6B73ADF3B Page 54 of 237 TABLE I V- A- 1 5 FORT CAL HOUN ANNUAL 2022 , DOSE PRO JE CTI ONS S PECI AL LOCAT I ON NO . 1 5 RES AT 2 . 40 MIL ES NW ANNUAL BETA AIR DOS E = 0 . 00 E+00 MILLRADS ANNUAL GAMMA AI R DOS E = 0 . 00E+00 MIL LRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
- -- - - - --- +---------- +---------- +---------- +---- ------ +---- - - -- -- +---------- +---------- +------ - -- - +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
- ---- - --- +---------- +---------- +---------- +-------- - - +--- - ---- - - +--- - - ---- - +---------- +---------- +
GROOND : l . 18E - 05 : l . 18E- 05 : l . 18E - 05 : l . 18E- 05 : l . 18E- 05 : l . 18E - 05 : l . 1 8E - 05 : l . 38E - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +----- --- - - +
INHAL ADOL T : 2 . 39E - 06 : 2 . 31E - 06 : 9 . 78E - 08 : 2 . 43E - 06 : 2 . 35E - 06 : 2 . 30E - 06 : 2 . 32E - 06 : 2 . 30E - 06 :
---- ----- +---------- +---------- +---------- +---------- +---------- +---------- + ----- - ---- +---- - -- -- - +
TEEN : 2 . 39E - 06 : 2 . 33E - 06 : l . 37E - 07 : 2 . 50E - 06 : 2 . 39E - 06 : 2 . 32E - 06 : 2 . 35 E- 06 : 2 . 32E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 2 . 0SE - 06 : 2 . 05 E- 06 : l . 85 E- 07 : 2 . 22 E- 06 : 2 . l l E- 06 : 2 . 05E - 06 : 2 . 07E - 06 : 2 . 05 E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---- - ----- +
INFANT : 1 . 19E - 06 : l.1 8E- 06 : l . 12E- 07 : l . 3 1E- 06 : 1 . 22E - 06 : 1 . 18E - 0 6 : 1 . 20E - 06 : l.1 8E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +- - -------- +---------- +---------- +
I V- 19
A4-01 F6B73ADF3B Page 55 of 237 TABLE IV - A- 1 6 FORT CALHO UN ANNUAL 2022 , DOSE PROJECTI ONS SP ECIAL LOCATI ON NO . 16 RES AT 2 . 08 MILES NNW ANNUAL - BETA- AIR- DOSE = 0 . 00E+00 MILLRADS ANNUAL GAMMA AI R DOSE = 0 . 00E +00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +---------- +---------- +-- - - ------ +- - - ------- +---------- +---------- +---- ------ +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00E+00 : 0 . 00E+00 : 0.00E+00 :
--------- +---------- +---------- +---------- +------- --- +---- -- -- -- +---------- +--------- - +-- - - ------ +
GROUND : 2 . 12E - 05 : 2 . 1 2E - 05 : 2 . 12E- 05 : 2 . 12E- 05 : 2 . 12E- 05 : 2 . 12E - 05 : 2 . 12E- 05 : 2 . 47E - 05 :
- - - ----- -+ ------ -- -- +------ - --- +----- - - - - - +---------- +---------- +----- - -- - - +---------- +------- --- +
INHAL ADULT : 3 . 77E - 06 : 3 . 63E - 06 : l . 56E - 0 7 : 3 . 83E - 06 : 3 . 70 E- 06 : 3 . 63E - 06 : 3 . 66E - 06 : 3 . 63E - 06 :
--------- +---------- +---------- +---------- +---------- +- -- -- - ---- +---------- +---------- +--- - - ----- +
TEEN : 3 . 77 E- 06 : 3 . 67E - 06 : 2 . 19 E- 07 : 3 . 94E - 06 : 3 . 76 E- 06 : 3 . 66E - 06 : 3 . 70E- 06 : 3 . 66E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHI LD : 3 . 28 E- 06 : 3 . 2 4E - 06 : 2 . 96 E- 07 : 3 . Sl E- 06 : 3.33 E- 06 : 3 . 24 E- 06 : 3 . 27E - 06 : 3 . 2 4E- 06 :
--------- +---------- +--------- - +---------- +---------- +---------- +---------- +---------- +---------- +
IN FANT : l . SS E- 06 : l . 86E - 06 : l. 79 E- 07 : 2 . 06 E- 06 : l .92 E- 0 6 : l . 86 E- 0 6 : l . SS E- 06 : l . 86E - 06 :
- - ------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 20
F6B73ADF3B Page 56 of 237 TAB LE IV- A- 1 7 FORT CALHO UN ANNUAL 2022 , DOS E PROJEC T IONS SP ECIAL LOCATION NO . 17 VEG AT 2 . 23 MI LE S NNE ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRAC T BONE LI VER KIDNEY THYROID LUNG SKIN
- - - - ----- +---------- +---------- +---------- +---------- +---------- +----- - -- -- +-- - --- - --- +-- - -- ----- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E + 00 : 0 . 00E +00 : 0 . 00E +00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+00 :
- --- - ---- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +----- ----- +
GROUND : 7 . 48E - 06 : 7 . 48E - 06 : 7 . 4 8E - 06 : 7 . 48E - 06 : 7 . 48E - 06 : 7 . 48E - 06 : 7 . 48E - 06 : 8 . 73E - 06 :
--------- +---------- +- - -- --- - -- +---------- +- - -------- +----- - - - -- +-- -------- +---------- +---------- +
VEGET ADULT : 7 . 20 E- 06 : 3 . B0E - 06 : 3 . 92 E- 06 : 9.0S E- 06 : 5 . SlE - 06 : 3 . 69 E- 06 : 4 . 30E - 06 : 3 . 69E - 06 :
--------- +---------- +-- - - ---- -- +- ------ - - - +- - - - - - - --- +- --- - ----- +---------- +---------- +---------- +
TEEN : 7 . ll E- 06 : 4 . 34E - 06 : 6.24E - 06 : 1. 25 E- 05 : 7.0S E- 06 : 4 . 22 E- 06 : 5 . 32E - 06 : 4 . 22E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHI LD : 8 . 64 E- 06 : 6 . 65E - 06 : l . 47 E- 05 : 2 . 07 E- 05 : l.1 2E- 05 : 6 . 56 E- 06 : 8 . 21 E- 06 : 6 . 56E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 21
DocuS ign Envelope ID: EA65F186-46DE-4A34-97 A4-01 F6B73ADF3B Page 57 of 237 TABLE IV - A- 18 FORT CALHOON ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 18 VEG AT 3 . 20 MILES NE ANNUAL BETA AIR DOSE= 0 . 00E+OO MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+OO MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LONG SKIN
-- ------- +---------- +------ ---- +---------- +------ - --- +----- -----+----- - - --- +-- - - ---- -- +---------- +
PLUME : 0 . 00E+OO : O.OOE+OO : 0 . 00E+OO : 0 . 00E+OO : O. OOE+OO : O. OOE+OO : O. OOE+OO : 0 . 00E+OO :
------- --+- --------- +---------- +-------- - - +------- --- +---------- +---------- +---------- +---------- +
GROUND : l . 87E - 06 : l . 87E - 06 : l. 87E - 06 : l . 87E - 06 : l . 87E-06 : l . 87E - 06 : l . 87E-06 : 2 . lBE - 06 :
--------- +- - - -- -- -- -+ - - -------- +---------- +-------- -- +- - -- --- - - - +---------- +---------- +---------- +
VEGET ADULT : 2 . 24E - 06 : l . 39E - 06 : 9 . 79E - 07 : 2 . 70E- 06 : l . 82E - 06 : l . 36E - 06 : l . 52E - 06 : l . 36E - 06 :
------- -- +---------- +--- - -- ---- +---------- +- -- - ------ +----- -----+---- -- - --- +- ---------+--- --- -- -- +
TEEN : 2 . 28E - 06 : l . 59E-06 : l . 56E-06 : 3 . 64E - 06 : 2 . 27E- 06 : l . 56E - 06 : l . 83E - 06 : l . 56E - 06 :
--------- +---------- +---------- +---------- +----------+--------- -+ ---------- +---------- +---------- +
CHILD : 2 . 94E - 06 : 2 . 45E - 06 : 3 . 68E - 06 : 5 . 95E - 06 : 3 . 57E - 06 : 2 . 42E - 06 : 2 . 84E - 06 : 2 . 42E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +------- -- - +---------- +
IV- 22
86-46DE-4A34-97A4-01 F6B73ADF3B Page 58 of 237 TAB LE I V- A- 19 FORT CALHOUN ANN UAL 2022 , DOSE PROJECTIONS S PECIAL LOCATION NO . 19 VEG AT 4 . 79 MIL ES ENE ANNUAL BETA AIR DOSE= 0 . 00 E+00 MI LLRADS ANN UAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI -T RACT BONE LIV ER KIDN EY THYROID LUNG SKIN
--------- +---------- +---------- +----- ----- +---- -- - --- +---------- +---------- +--- ------- +- - -------- +
PLUME : 0 . 00E+00 : 0 . 00E +00 : 0.00 E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +------ ---- +- - --- ----- +---------- +---------- +------ ---- +
GROUND : 6 . 05E - 07 : 6 . 05E - 07 : 6 . 05 E- 07 : 6 . 05E - 07 : 6 . 05 E- 07 : 6 . 05E - 07 : 6 . 05E - 07 : 7 . 06E - 07 :
--------- +---------- +---------- +---------- +-------- - - +---------- +---------- +- - ------- - +---------- +
VEGET ADULT : 9 . 90E - 07 : 7 . 1 5E - 07 : 3 . 17E- 07 : l . 14 E- 06 : 8 . 53 E- 07 : 7 . 06E - 07 : 7 . 55E- 07 : 7 . 06E - 07 :
---- -- - -- +-------- - - +-- -- - - -- -- +- - -------- +---------- +---- - -- --- +- -- -- ----- +---------- +- - - ---- --- +
TEEN : l . 04 E- 06 : 8 . 17E- 07 : 5 . 05E - 07 : l . 48E - 06 : l. 04 E- 06 : 8 . 0BE - 07 : 8 . 96E - 07 : 8 . 0BE - 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CH I LD : l . 42 E- 06 : l . 26 E- 06 : l.1 9E- 06 : 2 . 39 E- 06 : l . 63E- 06 : l . 25 E- 06 : l . 39 E- 06 : l . 25E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
I V- 23
A4-01F6B73ADF3B Page 59 of 237 TABLE IV- A- 20 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 20 VEG AT 4.22 MILES ESE ANNUAL BETA AIR DOSE= 0.00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+0O MILLRADS PATHWAY T . BODY GI -T RACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+ ---------- +---------- +--------- -+--------- - +------- ---+------- --- +------ ----+--- ------- +
PLUME : 0.00E+00 : 0.00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +----------+---------- +------- ---+----------+----------+--------- - +- --- ------+------- --- +
GROUND : 1.68E-06 : l . 68E - 06 : l . 68E - 06: 1.68E- 06 : l . 68E - 06: 1 . 68E - 06 : l . 68E - 06 : l . 96E - 06 :
--------- +- --------- +-------- -- +-------- --+----------+----------+--------- - +----------+--------- - +
VEGET ADULT : 2 . 39E - 06 : 1 . 63E - 06 : 8 . BlE-07 : 2 . BlE-06 : 2 . 0lE - 06 : l . 60E - 06 : l . 74E-06 : l . 60E- 06 :
--------- +---------- +------ ----+- ----- ----+----------+----------+-------- -- +---------- +-------- --+
TEEN : 2 . 49E - 06 : 1 . 86E-06 : l . 40E-06 : 3 . 70E-06 : 2 . 47E - 06 : l . 84E - 06 : 2 . 0BE-06 : l . 84E - 06 :
--------- +----------+----------+---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 3 . 32E - 06 : 2 . 87E - 06 : 3.32E - 06 : 6 . 03E - 06 : 3 . 89E - 06 : 2 . BSE - 06 : 3 . 22E- 06 : 2 . BSE- 06 :
--------- +---------- +-------- -- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 24
A4-01 F6B73ADF3B Page 60 of 237 TABLE IV- A- 2 1 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 21 VEG AT 2 . 15 MIL ES SE ANNUAL BETA AIR DOSE= 0 . 00E+0O MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+OO MILLRADS PATHWAY T . BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+ ----- -----+------- --- +------ ----+------ -- - - +----------+----- ----- +------- - - -+- --------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
- - - ------ +---------- +--- --- ---- +---------- +---- - ----- +--------- -+ ---------- +---------- +---------- +
GROUND : l.25E - 05 : 1.25£ - 05 : l.25E - 05 : l.25E - 05 : l.25E - 05 : l . 25E - 05 : l . 25E - 05 : l . 45E-05 :
------ - - - +---------- +---------- +---------- +- --------- +---------- +---------- +------- - -- +- -- - - ---- - +
VEGET ADULT : l . lBE - 05 : 6.llE - 06 : 6 . 53E - 06 : l . 49E - 05 : 8.97£ - 06 : 5.94E - 06 : 6.95E - 06 : 5 . 94E - 06 :
------ - - - +---------- +-- - - - ----- +-------- --+-- -- -- ---- +------ - --- +-- - ------- +---------- +-- - ------- +
TEEN : l . 16E - 05 : 6 . 99E-06 : l . 04E - 05 : 2 . 06E - 05 : l . 15E-05 : 6 . 79E-06 : 8 . 62E- 06 : 6 . 79E - 06 :
------- - - +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : l . 40E - 05 : l.07E - 05 : 2.46E - 05 : 3.41E - 05 : l . 82E - 05 : l . 05E - 05 : l . 33E- 05 : l . 05E- 05 :
-- - ------ +---------- +---------- +----------+---------- +---------- +---------- +---------- +-- - ------- +
IV- 25
86-46DE-4A34-97 A4-01 F6B73ADF3B Page 61 of 237 TAB LE IV- A- 22 FORT CALHO UN ANNUAL 2022 , DOSE PROJECTI ONS SP ECIAL LOCATI ON NO . 22 VEG AT 0 . 94 MIL ES SSE ANNUAL - BETA- AIR- DOSE= 0 . 00 E+00 MILLRADS ANNUAL GAMMA AIR DOSE = 0 . 00E +00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIV ER KIDNEY THYROID LUNG SKIN
------ - - - +-- - ------- +--- ------- +---------- +---------- +----- - - --- +---------- +------- --- +--- ------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00 E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +- ---- - - --- +---------- +--------- - +--- ------- +-------- -- +
GROUND : l . 68E - 04 : l . 68E - 04 : 1 . 68E - 04 : 1 . 68E - 04 : l . 68E - 04 : 1 . 68E - 04 : l . 68E - 04 : l . 96E - 04 :
-------- - +---------- +---------- +---------- +---------- +- --- -- - --- +---------- +------ -- - - +---------- +
VEGET ADULT : l . 03E - 04 : 2 . 64E - 05 : 8 . SlE - 05 : l . 45 E- 04 : 6 . S0 E- 05 : 2 . 41E - 05 : 3 . 77E - 05 : 2 . 4 1E- 05 :
- - - ------ +------ - --- +-- - - ------ +---- ------ +---------- +-------- - - +- - -- ------ +---------- +--- --- ---- +
TEEN : 9 . 26E - 05 : 3 . 02E - 05 : l . 40 E- 04 : 2 . 14 E- 04 : 9 .l l E- 05 : 2 . 75E - 05 : S . 22E - 05 : 2 . 75E - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CH I LD : 8 . 96 E- 05 : 4 . 48E - 05 : 3 . 32 E- 04 : 3 . 60 E- 04 : l . 4 6E- 04 : 4 . 28 E- 05 : 8 . 00E - 05 : 4 . 28E - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV- 26
A4-01 F6B73ADF3 B Page 62 of 237 TAB LE IV - A- 23 FORT CALHOUN ANNUAL 2022 , DOS E PROJE CTI ONS SP ECI AL LOCATI ON NO . 23 VEG AT 0 . 73 MILE S S ANNUAL BETA AIR DOSE = 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE = 0 . 00E +00 MILLRADS PATHWAY T . BODY GI - TRAC T BONE LI VER KI DNEY THYRO ID LUNG SKIN
--------- +--- - -- -- - - +-------- -- +---------- +---------- +---------- +---------- +---------- +------- -- - +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+ 00 : 0 . 00 E+ 00 : 0 . 00 E+00 : 0 . 00 E+ 00 :
--------- +---------- +---------- +------- - -- +- -- - - -- - - - +------ - --- +-- - -------+---------- +---- ------ +
GRO UND : 1 . 68 E- 04 : l . 68E - 04 : l . 68E - 04 : l . 68E - 04 : l . 68E - 04 : l . 68E - 04 : 1 . 68E - 04 : l . 96E - 04 :
------- -- +------- --- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
VEGET ADULT : l . 13 E- 0 4 : 3 . 60E - 05 : 8 . BlE - 05 : 1 . 54 E- 04 : 7 . 46E - 05 : 3 . 37 E- 05 : 4 . 73 E- 05 : 3 . 37E - 05 :
---- - -- -- +--- ------- +---------- +---------- +- - --- - - - -- +--- - - - ---- +------ - --- +------ - --- +--- - - ----- +
TEEN : l . 04 E- 04 : 4 .1 2E-05 : 1 . 40 E- 0 4 : 2 . 25 E- 04 : l . 02E - 0 4 : 3 . BS E- 05 : 6 . 33 E- 05 : 3 . SSE - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : l . 07E - 04 : 6 .1 9E- 05 : 3 . 32 E- 0 4 : 3 . 77 E- 0 4 : l . 63E- 0 4 : 5 . 9 9E - 05 : 9 . 7 1E- 05 : 5 . 99E - 05 :
--------- +---------- +------- - -- +---------- +---------- +---------- +---------- +---------- +---------- +
I V- 27
F6B73ADF3 B Page 63 of 237 TAB LE I V- A- 2 4 FORT CALH OUN AN NUAL 2022 , DOS E PROJECTI ONS SP ECIAL LOCATION NO. 24 VEG AT 0 . 99 MIL ES S SW ANNUAL BETA AIR DOSE= 0 . 00E + 00 MI LLRADS ANNUAL GAMMA AI R DOSE= 0 . 00 E+00 MILLRADS PATHWAY T. BODY GI - TRACT BONE LIVER KIDNE Y THYROID LUNG SK IN
--------- +---------- +-------- -- +-- - ------- +- - ------- - +------- - -- +-- --- - -- -- +--- - - - ---- +---------- +
PLUME : 0.00E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00 E+00 : 0 . 00 E+00 : 0 . 00 E+00 : 0 . 00 E+00 : 0 . 00E+00 :
--------- +----- - - -- - +------- - -- +- - -------- +---------- +------ - --- +---------- +---------- +- -- - ------ +
GRO UND : 3 . SS E- 05 : 3 . SSE - 05 : 3 . SS E- 05 : 3 . SS E- 05 : 3 . SS E- 05 : 3 . SS E- 05 : 3 . SSE - 05 : 4 . lSE - 05 :
--------- +---------- +----- -- - -- +--- - ------ +--- - -- - -- - +- ------- - - +- - - ----- -- +- ------ - -- +------ - - -- +
VEGET ADULT : 3 . 03E - 05 : 1 . 4 1E- 05 : l . 86 E- 05 : 3 . 91E - 05 : 2 . 23E - 05 : l . 36E - 05 : l . 65E - 05 : 1 . 36E - 05 :
-------- - +- - ---- - - -- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
TE EN : 2 . 93E - 05 : l . 62E - 05 : 2 . 97E - 05 : 5 . S0E - 05 : 2 . 90 E- 05 : 1 . 56E - 05 : 2 . 0BE - 05 : l . 56 E- 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 3 . 4 1E - 05 : 2 .4 7E- 05 : 7 . 00 E- 05 : 9 . 12 E- 05 : 4 . 61E - 05 : 2 . 42E- 05 : 3 . 2 1E- 05 : 2 . 42 E- 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 28
F6B73ADF3B Page 64 of 237 TABLE IV - A- 25 FORT CALHOON ANNUAL 2022 , DOSE PROJECTI ONS SPECIAL LOCATION NO . 25 VEG AT 1.43 MILES SW ANNUAL BETA AIR DOSE= 0 . 00E+OO MILLRADS ANNUAL GAMMA AIR DOSE= O. OOE+OO MI LLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LONG SKIN
---------+---------- +---------- +---------- +--------- - +---------- +---------- +---------- +---------- +
PLOME : O. OOE+OO : O. OOE+OO : O. OOE+OO : O. OO E+OO : O. OO E+ OO : O. OOE + OO : 0 . 00E+OO : 0 . 00E+OO :
--------- +----------+----------+---------- +-- ------- +--------- -+----- ----- +---------- +---------- +
GROUND : 9 . 35E - 06 : 9 . 35E - 06 : 9 . 35E - 06 : 9 . 35E - 06 : 9 . 35E - 06 : 9 . 35E - 06 : 9 . 35E - 06 : l . 09E-05 :
--------- +---------- +---------- +---------- +---------- +----------+---------- +---------- +--- --- ---- +
VEGET ADULT : 9 . 36E - 06 : 5 .l lE - 06 : 4 . 90E - 06 : l . 17E - 05 : 7 . 25E - 06 : 4 . 98E - 06 : 5 . 73E - 06 : 4 . 98E - 06 :
--------- +---------- +---------- +-- -------- +- --------- +---------- +---------- +---------- +---------- +
TEEN : 9 . 3 1E- 06 : 5 . 84E - 06 : 7 . 80E - 06 : l . 61E - 05 : 9 . 22E - 06 : 5 . 69E - 06 : 7 . 06E - 06 : 5 . 69E - 06 :
--------- +---------- +----------+---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 1 . 14E - 05 : 8.95E - 06 : 1.84E- 05 : 2 .6 5E - 05 : 1 . 46E - 05 : 8 . 84E - 06 : 1 . 09E - 05 : 8 . 84E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV- 29
A4-01 F6B73ADF3 B Page 65 of 237 TABLE IV- A- 26 FORT CALHOON ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO. 26 VEG AT 1 . 13 MILES WSW ANNUAL - BETA- AIR- DOSE = 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0.00E+00 MILLRADS PATHWAY T.BODY GI - TRACT BONE LIVER KIDNEY THYROID LONG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
GROUND : 2 . lSE - 05 : 2 . lBE - 05 : 2 . lBE - 05 : 2 . lBE - 05 : 2 . lBE - 05 : 2 . lSE - 05 : 2 . lSE - 05 : 2 . SSE - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
VEGET ADULT : 2 . 07E - 05 : l . 07E - 05 : l . 14E- 05 : 2 . 61E - 05 : l.57E - 05 : 1 . 04E - 05 : 1.22E- 05 : 1.04E- 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
TEEN : 2 . 04E - 05 : l . 23E - 05 : l . 82E - 05 : 3.62E - 05 : 2 . 02E - 05 : l . 19E - 05 : l . SlE - 05 : l . 19E- 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 2 . 46E - 05 : 1 . SSE - 05 : 4 . 30E - 05 : 5 . 97E - 05 : 3 . 19E- 05 : l . SSE - 05 : 2 . 34E - 05 : l . SSE - 05 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV- 30
86-46DE-4A34-97A4-01 F6B73ADF3B Page 66 of 237 TABL E I V- A- 2 7 FORT CALHO UN ANNUAL 2022 , DOS E PROJ ECTI ONS SP ECIAL LOCATI ON NO . 27 VEG AT 2 . 71 MILE S W ANNUAL BETA AIR DOSE= 0 . 00E+00 MIL LRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MI LL RADS PATHWAY T. BODY GI - TRACT BON E LI VER KIDN EY THYROID LUNG SKIN
-- - ------ +- - -- - - ---- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
PLUME : 0.00 E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +- - --- -- --- +- --------- +-- - ----- -- +- ---- --- - - +----- - --- - +- ------ - - - +-- - -- - ---- +------ - - -- +
GRO UN D : 2 . 87 E- 06 : 2 . 87E- 06 : 2 . 87E - 06 : 2.87 E- 06 : 2 . 87 E- 06 : 2.87 E- 06 : 2 . 87E - 06 : 3 . 35E - 06 :
- ---- - --- +-- - ------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
VEGE T AD UL T : 2 . 95E - 06 : l . 64 E- 06 : l . 50E - 06 : 3.66 E- 06 : 2 . 30E - 06 : l . 60 E- 06 : l . 84 E- 06 : l . 60E - 06 :
-- ------- +---------- +---------- +---------- +- - -- - ----- +-------- -- +-- - ------- +---------- +---------- +
TEEN : 2 . 94E - 06 : l . 88 E- 06 : 2 . 39 E- 06 : 5 . 02E - 06 : 2 . 92E - 06 : l. 84E - 06 : 2 . 26 E- 06 : l . 84E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHIL D : 3 . 65 E- 06 : 2 . 88 E- 0 6 : 5 . 65 E- 0 6 : 8 . 26 E- 06 : 4.61E - 06 : 2 . 85 E- 06 : 3 . 49 E- 06 : 2 . 85 E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV- 31
F6B73ADF3B Page 67 of 237 TABLE IV- A- 28 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO. 28 VEG AT 2 . 65 MILES WNW ANNUAL BETA AIR DOSE = 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T.BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +----------+---------- +----- -----+
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E + 00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0.00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +---------- +--- -------+--- ------- +---------- +------ ----+
GROUND : 4 . 61E - 06 : 4 . 61E - 06 : 4 . 61E- 06 : 4 . 61E - 06 : 4 . 61E - 06 : 4 . 61E - 06 : 4.61E-06 : 5 . 38E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +-- -------- +
VEGET ADULT : 4 . 73E - 06 : 2 . 63E - 06 : 2 . 42E - 06 : 5 . 87E - 06 : 3 . 69E - 06 : 2.57E - 06 : 2 . 94E - 06 : 2 . 57E - 06 :
--------- +---------- +- --------- +---------- +---------- +---------- +---------- +---------- +---------- +
TEEN : 4.72E - 06 : 3 . 0lE-06 : 3 . 85E - 06 : 8 . 06E-06 : 4 . 68E - 06 : 2 . 94E - 06 : 3 . 61E - 06 : 2 . 94E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CHILD : 5.85E - 06 : 4 . 62E - 06 : 9 . 09E - 06 : l . 33E - 05 : 7.40E - 06 : 4 . 56E - 06 : 5 . 58 E- 06 : 4.56E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +- --------- +- --------- +
IV- 32
A4-01 F6B73ADF3B Page 68 of 237 TABLE IV- A- 29 FORT CALHOON ANNUAL 2022 , DOS E PROJECTIONS SPECIAL LOCATION NO . 29 VEG AT 2 . 40 MIL ES NW ANNUAL BETA AIR DOSE= O. OOE+OO MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+OO MILLRADS PATHWAY T . BODY GI - TRAC T BONE LIVER KIDNEY THYROID LONG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +---------- +------ --- - +----------+
PLUME : 0 . 00E+OO : O. OOE+OO : O. OOE+OO : 0 . 00E+OO : 0 . 00E+OO : 0 . 00E+OO : O. OOE+OO : 0 . 00E+OO :
--------- +---------- +----------+---------- +---------- +---------- +---------- +---------- +-------- --+
GROUND : l . lBE - 05 : l.18E - 05 : l . lBE-05 : 1 . lBE - 05 : 1 . lBE - 05 : l . lBE - 05 : 1 . lBE - 05 : l . 38E - 05 :
--------- +---------- +----------+---------- +----------+---------- +- - --- -- - --+- --------- +---------- +
VEGET ADULT : 9 . 73E-06 : 4 . 34E-06 : 6 . 20E - 06 : 1.27E- 05 : 7 . 0SE - 06 : 4 . 17E-06 : 5 . 13E- 06 : 4 .1 7E - 06 :
--------- +---------- +----------+---------- +------- ---+ ---------- +---------- +--------- -+--- ------- +
TEEN : 9 . 35E - 06 : 4 . 96E - 06 : 9 . 88 E- 06 : l . 79E - 05 : 9 . 25 E- 06 : 4 . 77E - 06 : 6 . SlE - 06 : 4 . 77E-06 :
---------+----------+----------+----------+----------+----------+---------- +---------- +---------- +
CHILD : l . 07E - 05 : 7 . SSE - 06 : 2 . 33E - 05 : 2 . 98E - 05 : l . 47 E- 05 : 7 . 41E - 06 : l . OOE - 05 : 7 .41 E- 06 :
--------- +---------- +----------+---------- +---------- +---------- +---------- +---------- +---------- +
IV- 33
F6B73ADF3B Page 69 of 237 TABLE IV- A- 30 FORT CALHOUN ANNUAL 2022 , DOSE PROJECT I ONS SPECIAL LOCATION NO . 30 BEEF AT 4 . 72 MILES NNE ANNUAL BETA AIR DOS E= 0 . 00 E+ 00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +------ - - -- +-- - ------- +---------- +---------- +---------- +---------- +- - -- - --- - - +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 .00E +00 : 0 . 00E+00 :
- - - - ----- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
GROUND : l . 37E - 06 : l . 37E - 06 : l . 37E- 06 : l . 37E - 06 : l . 37E - 06 : l . 37E - 06 : l.37E - 06 : l.60E - 06 :
----- ---- +---------- +---------- +---------- +---------- +---------- +-------- - - +---------- +---- ------+
MEAT ADULT : l . 94E - 07 : l . 29E-07 : 7 . 49E - 08 : 2 . 29E - 07 : l . 62E - 07 : l . 27E - 07 : l.38E-07 : l.27E - 07 :
- -------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +-------- -- +
TEEN : l . 04E - 07 : 7.68 E- 08 : 6 . 22E - 08 : l .5 8E - 07 : l.04E - 07 : 7 . 56E - 08 : 8 . 65E-08 : 7 . 56 E- 08 :
------- - - +---------- +---------- +---------- +- -- ------- +---------- +---------- +---------- +---------- +
CHILD : l.0BE - 07 : 9 . 23 E- 08 : l . 15E- 07 : 2 . 0 lE - 07 : l . 27E - 07 : 9 .1 6E- 08 : l.04E - 07 : 9 .1 6E - 08 :
--------- +------- - -- +---- - ----- +---------- +---------- +---------- +---------- +--- - ------ +---------- +
IV - 34
F6B73ADF3B Page 70 of 237 TABLE I V- A- 31 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 31 BE EF AT 4 . 9 1 MILES E ANNUAL BETA AIR DOSE= 0.00E+00 MILLRADS ANNUAL GAMMA AIR DOSE = 0 . 00E+00 MILLRADS PATHWAY T.BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +- --------- +---------- +---------- +---------- +--------- -+ ---------- +---------- +--- --- ---- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0.00E+00 :
--------- +---------- +---------- +---- ------+- --------- +---------- +---------- +-- -------- +---------- +
GROUND : 8 . 73E - 07 : 8 . 73E-07 : 8 .7 3E - 07 : 8 . 73E - 07 : 8.73E - 07 : 8 . 73E - 07 : 8 . 73E - 07 : l . 02E-06 :
--------- +---------- +---------- +---------- +---------- +---------- +---- ------+- --------- +--------- -+
MEAT ADULT : l . 58E - 07 : l . 17E-07 : 4 . 77E - 08 : l . BlE - 07 : l.37E - 07 : l . 15E-07 : l . 23E - 07 : l . 15E - 07 :
----- ---- +---------- +---------- +---------- +- -- ------- +---------- +---------- +- --------- +---------- +
TEEN : 8 . 71E - 08 : 6.95E- 08 : 3 . 96E - 08 : l . 21E-07 : 8 . 67E - 08 : 6 . 87E - 08 : 7 . 57E - 08 : 6 . 87E - 08 :
--------- +---------- +---- ----- +---------- +---------- +---------- +----------+---------- +---------- +
CHILD : 9 . 36E - 08 : 8 . 37E - 08 : 7 . 29E - 08 : l. 53E - 07 : l.06E - 07 : 8 . 33E - 08 : 9 . 14E- 08 : 8 . 33E - 08 :
--------- +---------- +---------- +---------- +---------- +---------- +----------+----------+---------- +
IV - 35
DocuSign Envelope I 0 : EA65F186-46DE-4A34-97 A4-01 F6B73ADF3B Page 71 of 237 TAB LE IV - A- 32 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTI ONS SPECIAL LOCATION NO . 32 BEEF AT 0 . 76 MILES SW ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0.00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +--- ------- +---------- +---------- +------- ---+----------+----------+----------+
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +-------- -- +---------- +----------+---------- +---------- +
GROUND : 4 . 86E - 05 : 4 . 86E-05 : 4 . 86E-05 : 4 . 86E - 05 : 4.86E-05 : 4 . 86E - 05 : 4 . 86E - 05 : 5 . 67E - 05 :
---------+ ---------- +--- ----- -- +---------- +---------- +---------- +------ ---- +------ ----+---- -- - --- +
MEAT ADULT : 5 . 84E - 06 : 3 . 53E-06 : 2 . 66E-06 : 7 . 09E - 06 : 4 . 69E - 06 : 3 . 46E - 06 : 3 . 87E-06 : 3.46E - 06 :
--- ----- - +---------- +----- --- -- +------- ---+------ ---- +---------- +--- ------- +---------- +--- ------- +
TEEN : 3 . 0BE - 06 : 2 . lOE-06 : 2 . 21E - 06 : 5 . 00E - 06 : 3 . 06E-06 : 2 . 06E - 06 : 2 . 45E-06 : 2 . 06E-06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +------- ---+--- ------- +
CHILD : 3 . 07E - 06 : 2.52E - 06 : 4 . 06E- 06 : 6 . 39E - 06 : 3 . 77E - 06 : 2 . 50E - 06 : 2 . 95E - 06 : 2 . 50E - 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +----------+---------- +
IV- 36
F6B73ADF3B Page 72 of 237 TABLE IV- A- 33 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 33 BEEF AT 3 . 25 MILES W ANNUAL BETA AIR DOSE= 0.00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +- --- - ----- +---------- +---------- +---------- +---------- +---------- +------ - --- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +---------- +---------- +----- - -- --+ ---------- +---------- +
GROUND : l . 87E - 06 : l . 87E- 06 : l . 87E - 06 : l . 87E - 06 : l . 87E - 06 : l . 87E - 06 : 1 . 87E - 06 : 2 . lBE-06 :
--------- +---------- +---------- +---------- +---------- +---------- +-------- --+-- -------- +---------- +
MEAT ADULT : 2 . 53E - 07 : l . 64E - 07 : l . 02E - 07 : 3 . 0lE - 07 : 2 . 09E - 07 : l . 61E - 07 : l . 77E - 07 : 1 . 61E - 07 :
--------- +---------- +---- - - - --- +---------- +---------- +---------- +---------- +---------- +-- - - -- ---- +
TEEN : 1.36E - 07 : 9 . 78E - 08 : 8 . 49E - 08 : 2 . 09E-07 : 1.35E- 07 : 9.62E - 08 : 1 . llE - 07 : 9 . 62E - 08 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +----------+---------- +
CH I LD : 1.39E - 07 : 1 . 17E - 07 : 1 . 56E - 07 : 2 . 66E - 07 : 1 . 65E - 07 : 1.17E - 07 : 1 .34 E- 07 : l . 17E- 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 37
A4-01 F6B73ADF3B Page 73 of 237 TABLE IV - A- 34 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATION NO . 34 BEEF AT 4 . 59 MI LES WNW ANNUAL BETA AIR DOSE = 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E+00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
--------- +---------- +---------- +---------- +---------- +---- - ----- +---------- +---------- +---------- +
GROUND : l . S0E-06 : l . S0E - 06 : l . S0E - 06 : 1 . S0E - 06 : 1 . S0E - 06 : 1 . S0E - 06 : 1 . S0E - 06 : 1 . 75E - 06 :
-------- -+- - -------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
MEAT ADULT : 2 . 23E-07 : l . 52E - 07 : 8 . lBE - 08 : 2 . 62E - 07 : 1.BBE- 07 : 1.S0E - 07 : 1 . 63E - 07 : 1 . S0E - 07 :
--------- +---------- +------ -- -- +- --------- +---------- +---------- +---------- +---------- +---- ------+
TEEN : l.21E-07 : 9 . 06E - 08 : 6 . 79E - 08 : 1 . B0E - 07 : 1 . 20E - 07 : 8 . 93E - 08 : 1 . 0lE - 07 : 8 . 93E - 08 :
--------- +---------- +---------- +---------- +---------- +---------- +----------+---------- +---------- +
CH I LD : 1 . 26E - 07 : 1 . 09E - 07 : 1.25E- 07 : 2 . 28E - 07 : 1. 47E - 07 : 1 . 0BE - 07 : 1. 22E - 07 : 1 . 0BE - 07 :
--------- +---------- +---------- +---------- +----------+---------- +---------- +---------- +---------- +
IV - 38
A4-01 F6B73ADF3B Page 74 of 237 TABLE IV- A- 35 FORT CALHOUN ANN UAL 2022 , DOSE PROJECTIONS SPEC I AL LOCATION NO. 35 GOAT AT 3 . 30 MILES SSW ANNUAL BETA AIR DOSE= 0 . 00E+00 MIL LRADS ANNUAL GAMMA AI R DOSE= 0 . 00E+00 MI LLRADS PATHWAY T . BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
------ - -- +-- - - - - ---- +---------- +---------- +---- --- - -- +- --------- +---------- +---- ----- - +- --------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0.00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00 E+00 : 0 . 00E+00 :
--------- +---------- +---------- +- --- ------ +- -- ------- +---------- +------- --- +---- ------ +---------- +
GROUND : l . 43E - 06 : l . 43E - 06 : 1 . 43E - 06 : 1 . 43E - 06 : l . 43E - 06 : l . 43E - 06 : l. 43 E- 06 : l . 67E- 06 :
--------- +---------- +---------- +--------- - +- ---- - - -- - +---------- +---------- +-- ----- - - - +---------- +
GOATMILK : ADU LT : 2 . 29E - 06 : 5 . 56 E- 07 : l . 99E - 06 : 3 . 22E - 06 : l . 43E - 06 : 5 . 03E - 07 : 8 . l 0E - 07 : 5 . 03 E- 07 :
--------- +---------- +---------- +---------- +---------- +----- ----- +---------- +------ ---- +---------- +
TEEN : 2.33E - 06 : 7.23 E- 07 : 3 . 61E- 06 : 5 . 45E - 06 : 2 . 29E - 06 : 6 . 54E - 07 : l . 29E - 06 : 6 . 54 E- 07 :
--------- +---------- +---------- +---------- +---------- +-- - ------- +---------- +---------- +---------- +
CHILD : 2 . 26E - 06 : l. 09 E- 06 : 8 . 69 E- 06 : 9 . 35 E- 06 : 3 . 75 E- 06 : l . 04E - 06 : 2 . 0 l E- 06 : l . 04 E- 06 :
--------- +---------- +---------- +---- - ----- +---------- +---------- +---------- +---------- +---------- +
INFAN T : 2 . 72E - 06 : 1. 62 E- 06 : l . 39 E- 05 : l . 7 8 E- 05 : 5 . 93 E- 06 : l . 57 E- 06 : 3 . 34E - 06 : l . 57 E- 06 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 39
A4-01 F6B73ADF3B Page 75 of 237 TABLE IV - A- 36 FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS SPECIAL LOCATI ON NO . 36 GOAT AT 4 . 20 MILES SW ANNUAL BETA AIR DOSE= 0 . 00E+00 MILLRADS ANNUAL GAMMA AIR DOSE= 0 . 00E +00 MILLRADS PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
--------- +----------+---------- +---------- +---------- +---------- +---------- +---------- +---------- +
PLUME : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E +00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 : 0 . 00E+00 :
---------+----------+---------- +---------- +---------- +-------- --+- --------- +---------- +---------- +
GROUND : 7.48E - 07 : 7 . 48E - 07 : 7 .4 8E - 07 : 7 .4 8E - 07 : 7 . 48E-07 : 7 .4 8E - 07 : 7 . 48E - 07 : 8 . 73E - 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +------ ----+-- -------- +
GOATMILK : ADULT : 1 . 28E - 06 : 3 . BlE - 07 : 1.04E- 06 : 1 . 77E - 06 : 8 . 36E - 07 : 3 . 54E - 07 : 5 . 14E- 07 : 3 . 54E - 07 :
--------- +---------- +-- -------- +---------- +- --------- +---------- +---------- +----------+---------- +
TEEN : 1.33E - 06 : 4 . 96E - 07 : 1.BBE- 06 : 2.96E - 06 : 1.31E- 06 : 4.60E - 07 : 7 . 91E-07 : 4 . 60E - 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
CH ILD : 1. 37 E- 06 : 7 . 56E - 07 : 4 . 53E - 06 : 5 .07E- 06 : 2 .1 4E - 06 : 7 . 29E - 07 : 1. 24 E- 06 : 7.29E - 07 :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +
INFANT : 1.7 1E- 06 : 1 . 13E- 06 : 7.24E - 06 : 9 .S BE - 06 : 3 . 38E - 06 : 1 .ll E- 06 : 2 .0 3 E- 06 : 1.llE- 06 :
--------- +----------+---------- +---------- +---------- +---------- +---------- +---------- +---------- +
IV - 40
F6B73ADF3B Page 76 of 237 TABLE IV - B- 1 FORT CALHOUN 1 DOSE CONTRIBUTIONS FROM GASEOUS EFFLUENTS UNRESTRICTED AREA BOUNDARY JANUARY 1 , 2022 TO DECEMBER 31 , 2022 MAXIMUM SITE BOUNDARY GAMMA AIR DOSE - 0.00E+00 MAXIMUM SITE BOUNDARY BETA AIR DOSE - 0.00E+00 IV- 41
Page 77 of 237 TAB LE IV - C- 1 FORT CALHO UN ANNUAL 2022 , DOSE PROJECTIONS ALARA ANNUAL INT EGRATED POPULATI ON DOS E
SUMMARY
(PERSON - REM) PATHWAY T . BODY GI - TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
-- -- - - -- - +- - - --- - --- +---------- +---------- +---------- +---- --- - - - +- - - ------ - +---------- +---------- +
GROUND : l . 76E - 04 : l . 76E - 04 : l . 76E- 04 : l . 76E- 04 : l . 76E - 04 : l . 76E - 04 : l . 76E - 04 : 2 . 0SE - 04 : 43 . 34 % : 50 . 91 % : 58 . 51 % : 35 . 90 % : 44 . 8 1 % : 5 1 . 20 % : 48 . 77 % : 55 . 04 % :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +---- - -- --- +
INHAL : 6 . 67E - 05 : 6 . SlE - 05 : 2 . SBE - 06 : 6 . 81E-05 : 6 . 61 E- 05 : 6 . S0E - 05 : 6 . 54E - 05 : 6 . S0E - 05 : 16 . 43 % : 18 . 84 % : 0 . 86 % : 13 . 90 % : 16 . 85 % : 18 . 94 % : 18 . 15 % : 17 . 45 % :
--------- +---------- +---------- +---------- +---------- +---------- +---------- +---------- +--- ------- +
VEGET : l .1 3E-04 : 7 . 43E - 05 : 8 . l0E - 05 : l . 68E - 04 : l . 0SE - 04 : 7 . 30E - 05 : 8 . 41 E- 05 : 7 . 30 E- 05 : 27 . 91 % : 21 . 50 % : 26 . 96 % : 34.31 % : 26 .7 0 % : 21 . 25 % : 23 . 32 % : 19 . 58 % :
- - ------- +---------- +---------- +---------- +---------- +---------- +-------- - - +--- ------- +- - - - - ----- +
COW MIL K : 2 . 60 E- 05 : l . 35 E- 05 : 2 . 96E- 05 : 4 . 69 E- 05 : 2 . 4 4E- 05 : l . 3 1 E- 05 : l . 71 E- 05 : l. 31 E- 05 : 6 . 40 % : 3.92 % : 9 . 84 % : 9 . 58 % : 6 . 21 % : 3 . 82 % : 4 . 74 % : 3 . 52 % :
--------- +---------- +---------- +---- - ----- +---------- +---------- +---------- +---------- +---------- +
MEAT : 2 . 40 E- 05 : l . 67 E- 05 : l . l SE - 05 : 3 . 09E - 05 : 2 .1 3E- 05 : l. 6 4E- 05 : l. Bl E- 05 : l . 64 E- 05 : 5 . 92 % : 4 . 83 % : 3 . 83 % : 6 . 31 % : 5 . 43 % : 4 . 79 % : 5 . 03 % : 4 . 41 % :
--------- +---------- +---------- +---------- +------- +---------- +---------- +---------- +---------- +
*TOTAL * : 4 . 06 E- 04 : 3 . 45 E- 04 : 3 . 00E - 04 : 4 . 9 0 E- 04 : 3 . 92 E- 04 : 3 . 43 E- 04 : 3 . 61 E- 0 4 : 3 . 73 E- 0 4 :
-------- - +---------- +---------- +---------- +---------- +---------- +---------- +---------- +- --------- +
IV - 42
F6B73ADF3B Page 78 of 237 SECTION V DOSE FROM LIQUID EFFLUENTS LADTAP II OUTPUT January 1, 2022 - December 31, 2022 V-1
F6B73ADF3B Page 79 of 237 Radioactive Effluent Releases - First, Second , Third, and Fourth Quarters 2022 LIQUID EFFLUENTS During the reporting period, a total of 1.74E-02 curies of radioactive liquid materials, less tritium, dissolved noble gases, and alpha were released to the Missouri River at an average concentration of 1.57E-07 µCi/ml. This represents 1.57E+01 percent of the limits specified in Appendix B to 10 CFR 20 (1.0E-06 µCi/ml for unrestricted areas), 7.84E-02 curies of tritium were discharged at an average diluted concentration of 7.07E-07 µCi/ml or 7.07E-02 percent of ECL (1.0E-03 µCi/ml). No gross alpha radioactivity was identified by Off-site vendor analysis of quarterly liquid composites for the reporting period . Dilution water during the periods of release amounted to 1.40E+08 liters, while liquid waste discharges consisted of 1.31 E+06 liters of radioactive liquid waste. V-2
-4A34-97A4-01 F6B73ADF3B Page 80 of 237 A. Potential Annual Doses to Individuals from Liquid Releases Total body, skin, and organ mRem for liquid releases were calculated for all significant liquid pathways using the annual configuration of the LADTAP II program. The inputs to LADTAP II for the annual period from January 1, 2022 , through December 31, 2022, were as follows: (1) All liquid effluents were as described in Section IV except for entrained noble gases (Ar-41, Xe-131 M, Xe-133M , Xe-133, Xe-135M , Xe-135 , Kr-85M, Kr-87, and Kr-88) . (2) An average dilution stream flow during periods of release was 8.81 cubic feet per second (CFS) for 2022. The average discharge rate during releases was 8.91 CFS. (3) Dilution factors (inverse of the mixing ratios) were computed based on Regulatory Guide 1.113 (equation 7 in Section 2.a.1 of Appendix A) for a one dimensional transport model. (4) Drinking water transport times of 6.6 hours to the Omaha intake and 7.0 hours to the Council Bluffs intake were used for dose calculations. (5) A shore width factor of 0.2 was used. (6) All dose factors, transport times from receptor to individual, and usage factors are defined by Regulatory Guide 1.109 and NUREG-0172. The discharge site was chosen to present the most conservative estimate of mRem dose for an average adult, teenager, child , and infant. A conservative approach is also presented by the assumption that Omaha and Council Bluffs receive all drinking water from the Missouri River. V-3
F6B73ADF3B Page 81 of 237 B. Potential Annual Doses to Population from Liquid Releases The LADTAP II program in its annual configuration was also used to calculate to total body and organ doses for the population of 1,053,476 within a 50-mile radius of the plant (based on the 2020 census). The same input was used as in the individual cases with the addition of the following : (1) Dilution factors and transport times for the pathways of sport fish, commercial fish, recreation , and biota were calculated based on a distance of two miles downstream as approximately the distance to the nearest recreation facility - DeSoto National Wildlife Preserve . (2) The total fish harvest for both sport and commercial purposes was calculated using an average commercial fish catch for Nebraska. V-4
A4-01 F6B73ADF3B Page 82 of 237
- L AAA DODD TTTTT AAA pppp III II IIIII *
- L A A D D T A A p p I I *
- L A A D D T A A p p I I *
- L AAAAA D D T AAAAA pppp I I *
- L A A D D T A A p I I *
- 11111 A A DODD T A A p IIIII III II *
- EVALUATION OF RADIATION DOSES FROM RELEASES OF RADIACTIVITY *
- IN NUCLEAR POWER PLANTS LI QUID EFFLUENTS *
- REVISION DATE: PNL VAX - OCTOBER 1985 *
- FORT CALHOUN ANNUAL 2022 , DOSE PROJECTIONS *
- RADIOLOGICAL ASSESSMENT BRANCH *
- DIVISION OF SYSTEMS INTEGRATION *
- U. S . NUCLEAR REGULATORY COMMISSION *
- WASHINGT ON , D. C . *
- DATE OF RUN : 202303061
- V- 5
Page 83 of 237 LOCATION IS FRESHWATER SITE A D U L T D 0 S E s DOSE (MREM PER YEAR INTAKE) PATHWAY SKIN BON E LI VER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FI SH 4 . S0E - 01 5 . 56E - 01 3 . 64E - 01 l. 53E-06 l . 88E-01 6 . 24E - 02 l . 18E-02 DRINKING 5 . 45E - 03 2 . 56E-03 l.64E - 03 l.40E- 05 7 . 87E -0 4 2 . 71E - 04 l . 87E-04 SHORELINE 6.67E - 04 5 . 71E - 04 5 . 71E-0 4 5 . 71E -0 4 5 . 71E - 04 5 . 7 1E- 04 5 . 71E - 04 5 . 71E - 04 SWIMMING 2 . 04E - 06 2 . 04 E-0 6 2 . 04E - 06 2 . 04E- 06 2 . 04 E- 06 2 . 04E - 06 2 . 04E - 06 BOATING l . 02E - 06 l. 02E - 06 1. 02E - 06 l.0 2 E-06 l . 02 E- 06 l . 02E-06 1. 02E - 06 TOTAL 6 . 67 E- 04 4.56E - 01 5 . 59E- 01 3 . 66E - 01 5 . 90E-04 l . 89 E- 0 1 6 . 32E-02 1. 26E -0 2 USAGE (KG/YR , HR/YR) DI LUTION TIME(HR) SHOREWIDT H FACTOR=0 . 2 FISH 21. 0 7.3 24 . 00 DRINKING 730 . 0 30.8 18 . 60 SHORELINE 12 . 0 7.3 0 . 00 SWIMMING 1 2 .0 7. 3 0 . 00 BOATING 12 . 0 7.3 0 . 00 T E E N A G E R D O S E S DOSE (MREM PER YEAR INTAKE) PATHWAY SKIN BONE LI VER TOTAL BODY THYROID KIDNEY LUNG GI - LLI FISH 4 . 80E - 01 5 . 79E - 01 2 . 02E - 0 1 l . 17 E- 06 l. 96E- 01 7 . 61E - 02 9 . 04E- 03 DRINKING 5 . 23E - 03 2 . 44E - 03 8 . 97E - 04 9 . 86E- 06 7.S0E - 04 2 . 97E - 04 l.29E- 04 SH ORELINE 3 . 72 E- 03 3 . 19E- 03 3 . 19E-03 3 . 19E - 03 3 . 19E- 03 3.19E- 03 3 . 19E - 03 3 . 1 9E- 03 SWIMMING l . 14E-05 l .1 4E - 05 l . 14E - 05 l . 14E- 05 l .1 4 E- 05 l.14E - 0 5 1. 14E- 05 BOATING 5 . 69E - 06 5 . 69E - 06 5 . 69E-06 5 . 69E-06 5.69E - 06 5 . 69E - 06 5 . 69E-06 TOTAL 3 . 72E - 03 4 . 89E-01 5 . 85E - 01 2 . 06E-01 3 . 22E - 03 2.00E- 0 1 7 . 96 E- 02 l . 24E- 02 USAGE (KG/YR , HR/YR) DILUTION TIME( HR) SHOREWIDTH FACTOR=0 . 2 FISH 16 . 0 7.3 24 . 00 DRINKING 510 . 0 30 . 8 18.60 SHORELINE 67 . 0 7.3 0 . 00 SWIMMING 67 . 0 7.3 0 . 00 BOATING 67 . 0 7.3 0 . 00 V- 6
DE-4A34-97A4-01 F6B73ADF3B Page 84 of 237 C H I L D D 0 s E S DOSE (MREM PER YEAR INTAKE) PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 6 . 07E - 01 5 . 25E - 01 7 . 91E - 02 9 . 73E- 07 l.70E - 01 6 . llE - 02 3 . 60E - 03 DRINKING l . 57E-02 5 .l BE - 03 1. 09E - 03 l. 89E- 05 1. 51E - 03 5 . 54E - 04 l.25E-04 SHORELINE 7 . 78E- 04 6 . 66E - 04 6.66E - 04 6 . 66E-04 6 . 66E-04 6.66E - 04 6 . 66E - 04 6.66E- 04 SWIMMING 2 . 38E - 06 2 . 38E - 06 2 . 38E - 06 2 . 38E- 06 2 .38E- 06 2.38E - 06 2.38E- 06 BOATING l . 19E- 06 l.19E - 06 l . 19E - 06 l . 19E-06 l.19E-06 l.19E - 06 l.19E- 06 TOTAL 7.78E- 04 6 . 24E - 01 5 . 31E - 01 8 . 09E - 02 6 . 90E- 04 l.72E - 01 6 . 24E - 02 4.39E- 03 USAGE (KG/YR , HR/YR) DIL UTION TIME(HR) SHOREWIDTH FACTOR=0 . 2 FISH 6.9 7. 3 24 .00 DRINKING 510 . 0 30.8 18.6 0 SHORELINE 14 . 0 7.3 0.00 SWIMMING 14 . 0 7.3 0.00 BOATING 14 . 0 7. 3 0 . 00 I N F A N T D O S E S DOSE (MREM PER YEAR INTAKE) PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNE Y LUNG GI-LLI FISH 0 . 00E+00 0 . 00E+00 0 . 00E+00 0.00E+00 0 . 00E+00 0 . 00E+00 0 . 00E+00 DRINKING l. 33E - 02 6 . 31E-03 7 . 38 E- 04 l.86E-05 l . 57E - 03 6 . 45E-04 8 . 38E-05 SHORELINE 0 . 00E+00 0 . 00E+00 0.00E+00 0 . 00 E+ 00 0 . 00E+00 0 . 00E+00 0 . 00E+00 0 . 00E+00 TOTAL 0 . 00E+00 l.33E - 02 6 . 31E - 03 7 . 38E - 04 1. 86E-05 l . 57E - 03 6 . 45E-04 8 . 38E-05 USAGE (KG/YR,HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0 . 2 FISH 0.0 7.3 24 . 00 DRINKING 330 . 0 30 . 8 18 . 60 V-7
DE-4A34-97 A4-0 1 F6B73ADF3B Page 85 of 237 LOCATI ON I S SITE DISCHG . A D 0 L T D 0 S E s DOSE (MREM PER YEAR INT AKE ) PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LONG GI-LLI FISH 3 . 29E +OO 4 . 06E+OO 2 . 65E+OO l . 1 2E-05 l.37E+OO 4 . 55E - 01 8.62E- 02 DRINKING l.68E - 01 7 . BB E- 02 5 . 05E- 02 4 . 31E - 04 2.42E- 02 8 . 34E - 03 5. 76E-03 SHORELINE 4.87E- 03 4 . 17E-03 4 . 17E-03 4 . 17E-03 4.17E-03 4 . 17E- 03 4 . 17E - 03 4.17E-03 SWIMMING 1 . 49E-05 l.49E-05 l . 49E-05 l . 49E-05 1 . 49E-05 1. 49E-05 1. 49E-05 BOATING 7 . 44E-06 7 . 44E - 06 7 . 44E - 06 7.44E- 06 7 . 44E - 06 7 .44E- 06 7 . 44E-06 TOTAL 4 . 87E-03 3 . 46E+OO 4 . 14E+OO 2 . 7 1E +OO 4.63E-03 1 . 40E+OO 4 . 68E - 01 9 . 62E-02 OSAGE (KG/YR , HR/YR) DILUTION TIME (HR) SHOREWIDTH FACTOR=0.2 FISH 21. 0 1.0 24 . 00 DRINKING 730.0 1.0 12 . 00 SHORELINE 12 . 0 1.0 0 . 00 SWIMMING 12 . 0 1.0 0 . 00 BOATING 12 . 0 1.0 0 . 00 T E E N A G E R D O S E S DOSE (MR EM PER YEAR INTAKE) PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LONG GI -LLI FISH 3 . 51E+OO 4 . 23E+OO 1.48E+OO 8 . 57E-06 l . 43E+OO 5 . 56E - 0 1 6 . 60 E- 02 DRINKING 1 . 61E - 01 7 . 52E-02 2 . 76E- 02 3.04E-04 2 . 31E - 02 9 . 16E- 03 3 . 96E- 03 SHORELINE 2 . 72E - 02 2 . 33E - 02 2 . 33E - 02 2.33E - 02 2.33 E- 02 2 . 33E - 02 2 . 33E - 02 2 . 33E-02 SWIMMING 8 . 31E-05 8 . 31E - 05 8.31E - 05 8.31E- 05 8.31E - 05 8 . 31E - 05 8 . 31E-05 BOATING 4 . lSE - 05 4.lSE-05 4 . lSE - 05 4 . lSE-05 4.15E-05 4 . lSE - 05 4 . 15E-05 TOTAL 2 . 72E - 02 3 . 69E+OO 4 . 32E+OO l . 53E+OO 2 .37E- 02 1.48E+OO 5 . BBE - 01 9.33E- 02 OSAGE (KG/YR ,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0 . 2 FISH 16.0 1. 0 24 . 00 DRINKING 510.0 1.0 12 . 00 SHORELINE 67. 0 1.0 0 . 00 SWIMMING 67. 0 1.0 0 . 00 BOATING 67. 0 1.0 0 . 00 V- 8
OocuSign Envelope ID: EA65F1 86-46DE-4A34-97 A4-01 F6873ADF3B Page 86 of 237 C H I L D D 0 s E S DOSE (MREM PER YEAR INTAKE) PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI - LLI FISH 4.43E+00 3 . 83E+00 5 . 78E-01 7.l0E- 06 l . 24E+00 4 . 46E-01 2.63E - 02 DRINKING 4 . 84E-01 1. 60E - 01 3 . 34E - 02 5 . 83E- 04 4 . 64E - 02 1. 71E-02 3 . 84E - 03 SHORELINE 5.68E-03 4 . 86E-03 4 . 86E - 03 4 . 86E - 03 4 . 86E- 03 4.86E- 03 4 . 86E - 03 4 . 86E- 03 SWIMMING 1 . 74E - 05 1. 74E - 05 1.74E-05 l . 74E-05 1.74E- 05 1. 74E - 05 1 . 74E-05 BOATING 8.68E - 06 8.68E - 06 8 . 68E - 06 8.68E- 06 8 . 68E - 06 8 . 68E-06 8.68E - 06 TOTAL 5.68E-03 4.92E+00 4 . 00E+00 6.16E - 01 5.48E- 03 l . 29E+00 4 . 68E - 01 3 . 50E - 02 USAGE (KG/YR , HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0 . 2 FISH 6.9 1.0 2 4 . 00 DRINKING 510.0 1.0 12 . 00 SHORELINE 14 . 0 1. 0 0 . 00 SWIMMING 14 . 0 1.0 0 . 00 BOATING 14 . 0 1.0 0 . 00 I N F A N T D O S E S DOSE (MREM PER YEAR INTAKE) PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 0 . 00E+00 0.00E+00 0.00E+00 0 . 00E+00 0 . 00E+00 0.00E+00 0 . 00E+00 DRINKING 4 . 09E-01 1.94E- 01 2.27E-02 5.72E - 04 4 . 83E - 02 1.99E - 02 2 . 58E - 03 SHORELINE 0 . 00E+00 0 . 00E+00 0 . 00E+00 0.00E+00 0.00E+00 0 . 00E+00 0.00E+00 0 . 00E+00 TOTAL 0 . 00E +00 4 . 09E - 01 1.94E- 01 2.27E - 02 5 . 72E- 04 4 . 83E - 02 l.99E-02 2.58E-03 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 0.0 1.0 24 . 00 DRINKING 330 . 0 1.0 12 . 00 V- 9
F6B73ADF3B Page 87 of 237
* *
- FISH CONSUMPTION POPULATION DOSES * *
- PERSON - REM COMMERCIAL HARVEST
---------------------------- DOSE (PERSON - REM) ------- - -----------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI -L LI tISH ADULT 5.16E+06 l.83E-01 2 . 27E - 01 l.48E - 01 6 . 22E- 07 7.64E - 02 2 . 54E - 02 4 . BlE - 03 FISH TEENAGER 6.03E+05 3.00E - 02 3 . 62E - 02 l.26E - 02 7.33E- 08 1 . 22E - 02 4.75E - 03 5 . 64E - 04 FISH CHILD 4.17E+05 6.09E - 02 5 . 26E - 02 7 . 93E - 03 9.74E- 08 1 . 70E - 02 6 .1 3E - 03 3 . 61E - 04 FISH TOTAL 6.18E+06 2.74E-01 3.lSE-01 1.69E - 01 7.93E- 07 l . 06E - 01 3 . 63E - 02 5 . 74E - 03 LOCATION DILUTION CATCH TIME(HR) - INCLUDES FOOD PROCESSING TIME OF 2 . 40E+02 HR POPULATION=l . 05E+06 7 . 30E+00 7 . 30E+04 2 . 41E+02 AVERAGE INDIVIDUAL CONSUMPTION (KG/YR) ADULT=6 . 90E+00 TEEN=5.20E+00 CHILD=2 . 20E+00 _ _ _ _ _ NEPA DOSES _ _ _ __ NOTE -- TOTAL NEPA DOSE INCLUDES SPORT CATCH
--------------------------- - DOSE (PERSON - REM) -------- - -- - - ------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYRO I D KIDNEY LUNG GI - LLI FISH ADULT l.22E+05 2.61E+00 3 . 23E+00 2. llE+00 8 . 86E - 06 1 . 09E+00 3 . 62E - 01 6 . BSE - 02 FISH TEENAGER l.42E+04 4.27E - 01 5 . lSE - 01 l . BDE-01 1.04E- 06 1.74E- 01 6 . 77E - 02 8.04E - 03 FISH CHILD 9.85E+03 8.67E - 01 7.49E - 01 l.13E - 01 l. 39E - 06 2 . 43E - 01 8 . 73E - 02 5.14E - 03 FISH TOTAL l.46E+05 3.91E+00 4 . 49E+00 2.40E+00 1 . 13E- 05 1 . 51E+00 5.17E-01 8 . 17E - 02 V-10
86-46DE-4A34-97A4-01 F6B73ADF3B Page 88 of 237
* *
- POPULATION WATER CONSUMPTION DOSES * *
- SUPPLIER-OMAHA
---------------------------- DOSE (PERSON - REM) ------------------------ -
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI - LLI DRINKING ADULT l . 24E+08 9 . 28E - 01 4 . 35E - 01 2 . 79E - 01 2 . 38 E- 03 l . 34E-01 4 . 61E- 02 3.lBE-02 DRINKING TEENAGER l.35E+07 l . 39E - 01 6 . 48E - 02 2 . 38E-0 2 2 . 61E- 04 l . 99E - 02 7 . 89E - 03 3 . 41E - 03 DRINKING CHILD 2 . 21E+07 6 . 82E - 01 2.25E - 01 4 . 71E - 02 8 . 22E - 04 6 . 54E-02 2 . 41E - 02 5 . 42E - 03 DRINKING TOTAL l . 60E+08 l .7 5E+00 7 . 25E-01 3.S0E-01 3.46E- 03 2 . 19E-01 7.BlE - 02 4 . 07E - 02 POPULATION=4 . 73E+05 DILUTION=3.08E+01 TRANSIT TIME=3.06E+0l HR (INCLUDING 24 HR FOR TREATMENT FACILITY) AVERAGE INDIVIDUAL CONSUMPTION (L/YR) ADULT=3.70E+02 TEEN=2 . 60E+02 CHILD=2.60E+02
-----CUMULATIVE TOTAL--- --
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI DRINKING CUMUL TOTAL l . BlE+0B 1 . 98E+00 8.19E - 01 3 . 96E-01 3 . 92E-03 2 . 48E-01 8 . 82E - 02 4.60E - 02
- - - - -HYDROSPHERE TRITIUM DOSE- -- - -
AVE RAGE INDIVIDUAL WATER CONSUMPTION= 3 . 0 L/DAY PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI - LLI WATER TOTAL 2.86E+ll 0 . 00E+00 5 . 98E - 07 5 . 98E - 07 5.98E- 07 5 . 98E-07 5 . 98E - 07 5 . 98E - 07 V-11
F6B73ADF3B Page 89 of 237 LOCATION - DOWN STREAM SWIMMING DILUTION= 7 . 30E+00 TRANSIT TIME= 6 . 70E- 01 HR _ _ _ _ _ _ _ _ DOSE (PERSON - REM) _ __ _ _ __ PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID SWIMMING TOTAL POPUL 4.10E+07 6 . 97E-03 6 . 97E-03 LOCATION- DOWN STREAM BOATING DILUTION= 7.30E+00 TRANSIT TIME= 6 . 70E - 01 HR _ _ _ __ __ _ DOSE (PERSON- REM) _ _ _ _ _ __ PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID BOATING TOTAL POPUL 4 . 10E+07 3.48E- 03 3 . 48E - 03
* *
- DOSE TO BIOTA * *
- MRADS PER YEAR BIOTA DILUTION= l . 00E+00 TRANSIT TIME= 0 . 00E+00 HR INTERNAL EXTERNAL TOTAL FISH 8.89E+00 l . 52E+0l 2 . 41E+0l INVERTEBRATE 4.53E+D0 3 . 04E+Dl 3.50E+Dl ALGAE 2.30E+00 l . 09E - 02 2.31E+00 MUSKRAT 4.86E+Dl l . 02E+Dl 5 . 87E+Dl RACCOON l.BlE+0l 7 . 61E+00 2 . 57E+0l HERON 2.81E+02 l . 02E+0l 2.92E+02 DUCK 4.44E+0l l . 52E+0l 5.96E+Dl V-1 2
F6B73ADF3B Page 90 of 237 SECTION VI RADIOACTIVE EFFLUENT RELEASES - SOLID RADIOACTIVE WASTE January 1, 2022 - December 31 , 2022 Vl-1
DocuSign Enve lope ID: EA65F186-46DE -4A34-97A4-01 F6B73ADF3B Page 91 of 237 VI. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT January 1, 2022 through December 31, 2022 A. Resins, Filters, and Evaporator Bottoms Waste Volume Curies Class ft3 m3 Shipped A 8.08E+02 2.29E+01 1.83E+01 B 0.00E+00 0.00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00 0.00E+00 ALL 8.08E+02 2.29E+01 1.83E+01 Major Nuclides for the Above Table: H-3, C-14, Fe-55, Co-60, Ni-59, Ni-63, Sr-90, Nb-94, Tc-99, 1-129, Cs-137, Pu-238, Pu-239, Pu-241 , Am-241 , Cm-242, Cm-244 B. Dry Active Waste Waste Volume Curies Class ft 3 m3 Shipped A 1.13E+06 3.21E+04 4.20E+01 B 0.00E+00 0.00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 Unclassified 0.00E+00 0.00E+00 0.00E+00 ALL 1.13E+06 3.21 E+04 4.20E+01 Major Nuclides for the Above Table : H-3, C-14 , Fe-55 , Co-60, Ni-59, Ni-63, Sr-90, Nb-94, Tc-99, Sb-125 , 1-129, Cs-137, Pu-238 , Pu-239, Pu-240, Pu-241, Am-241, Cm-242 , Cm-243, Cm-244 Vl-2
DocuSign Enve lope ID : EA65F1 86-46DE-4A34-97A4-01 F6B73ADF3B Page 92 of 237 VI. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT (Continued) C. Irradiated Components Waste Volume Curies Class ft 3 m3 Shipped A 3.70E+03 1.05E+02 1.61 E+02 B 1.11 E+02 3.15E+00 1.35E+03 C 5.57E+02 1.58E+01 5.20E+04 Unclassified 0.00E+00 0.00E+00 0.00E+00 ALL 4 .37E+03 1.24E+02 5.35E+04 Major Nuclides for the Above Table: H-3, C-14, Fe-55 , Co-60 , Ni-59 , Ni-63, Sr-90, Nb-94, Tc-99 , 1-129, Cs-137 , Th-230 , U-234 , U-238 , Pu-238, Pu-239 , Pu-241, Am-241, Cm-242, Cm-244 D. Other Waste Waste Volume Curies Class ft 3 m3 Shipped A 2.69E+03 7.62E+01 5.02E-01 B 0.00E+00 0 .00E+00 0.00E+00 C 0.00E+00 0.00E+00 0.00E+00 Unclassified 0.00E+00 0 .00E+00 0.00E+00 ALL 2 .69E+03 7.62E+01 5.02E-01 Major Nuclides for the Above Table : H-3, C-14, Fe-55 , Co-60 , Ni-59, Ni-63, Sr-90 , Nb-94, Tc-99 , 1-129, Cs-137, Pu-238, Pu-239 , Pu-241 , Am-241 , Cm-242, Cm-244 E. Sum of All Low-Level Waste Shipped from Site Waste Volume Curies Class ft 3 m3 Shipped A 1.14E+06 3.23E+04 2.22E+02 B 1.11 E+02 3.15E+00 1.35E+03 C 5.57E+02 1.58E+01 5.20E+04 Unclassified 0.00E+00 0.00E+00 0.00E+00 ALL 1.14E+06 3.23E+04 5.35E+04 Major Nuclides for the Above Table: H-3, C-14, Fe-55 , Co-60, Ni-59, Ni-63 , Sr-90 , Nb-94, Tc-99, Sb-125, 1-129, Cs-137 , Th-230, U-234 , U-238 , Pu-238, Pu-239 , Pu-240 , Pu-241 , Am-241 , Cm-242, Cm-243, Cm-244 Vl-3
F6B73ADF3B Page 93 of 237 SECTION VII ATTACHMENT 1 The Annual Radioactive Effluent Release Report shall include any revisions to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP) for the period January 1, 2022 through December 31 , 2022 .
----- revisions were made to the Offsite Dose Calculation Manual (ODCM) .
______1_ revisions were made to the Process Control Program (PCP) . January 1, 2022 - December 31, 2022 Vll-1
Page 94 of 237 Page 1 of 120 CH-ODCM-0001 II 11 Off-Site Dose Calculation Manual (ODCM) Revision 38 Safety Classification: Usage Level: I Non-Safety I I Reference I Change No.: EC 70885 Reason for Change: Remove Aux Building and Radwaste Building ventilation effluent release paths. Preparer: Matt Marcellus Fort Calhoun Station (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 95 of 237 CH-ODCM-0001 Reference Use Page 2 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table of Contents PARTI 1.0 PURPOSE AND SCOPE ...... .. ................... .......... .. .. ...... .. .. ........ .... .. .. .. .. .... .... .............. .. .. 6 1.1 Purpose .. ... .. ... .. ... ... .... ..... ..... ........... .. .......... .. ... ..... ........ .. ............ .... .... .. .... ............. ... 6 1.2 Scope ... .. .. ..... .. ....... .... ... .... ... ...... .... .. ... ...... ..... ..... ... ...... ......... ... ....... .... .... .... ....... ... .... 6 2.0 DEFINITIONS .............. ..... .............. .... ........ ... .... .... ... .... ....... ... .... .. ............... ..... ..... ........ .. 6 3.0 INSTRUMENTATION .. .. ...... .. ..... .. ..... .. .... .. ..................... .. .. .... .. .. ..... ..... ...... ... .. ...... ... .. .. . 10 3.1 Radioactive Liquid Effluent Instrumentation .. ........ .. .......... .. ... .. ...... .. .. .. ... .. .... ... .. ..... 10 3.2 Radioactive Gaseous Effluent Instrumentation .... .. ...... ... .......... .... .... .. .......... .. ... .. .. . 13 4.0 RADIOACTIVE EFFLUENTS ................ .. .. .. .. .. .................................... .. .. ...................... 17 4.1 Radioactive Liquid Effluents .. .. .... .... .... ........ .. ........ .. ...... .... .. .. ...... .. ........ ............ .. .... 17 4.2 Radioactive Gaseous Effluents .. .... .. .... .. .. .. .......... .......... .. .... ...... .. .. ...... .. ... .. .... .. ...... 23 4 .3 Uranium Fuel Cycle ........ .... .......... .. ....... .. ...... .. ..... ...... ... .... .. ... ..... ...... .. .. ....... .. ..... .. .. 28 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) .... .. .... .. ...... 29 5.1 Monitoring Program ...... ...... .................. .... ........ .......................... .... .. ..... .. ............... . 29 5.2 Land Use Survey .. .. .. .. .. ......... ... ........ .. ... .. ....... .. .. .. .. ... .... .... ..... .......... ........ .... .. ..... .... 44 5.3 lnterlaboratory Comparison Program .. .... ...... .. ............ ... .. .................. .... ..... ........ .. .. 45 6.0 ADMINISTRATIVE CONTROLS ...... .. .. ... .. .. ........ ... .... ..... .. ... ............ .. ...... .. .. .. .. .. ........... . 46 6.1 Responsibilities ...... .... ..... .... .. ....... .. ....... .... ... ......... .. ...... ... .. .... ..... .... .. .. ... ........... ...... 46 6.2 Radioactive Effluent Reporting Requirements ................... .... .. .. .. .... ...... .. ... ... .. ........ 46 6.3 Change Mechanism ...... ...... ... .... .... ....... .... ..... .. ................ ...... ... .. .......... ..... ..... .... .. .. 51 6.4 Meteorological Data ....... ... ..... ...... ..... ................... ...................... ....... .. .. ..... ..... .. ...... 51 6.5 References ...... .... ..... ... ... ..... .. .... ............ ...... .................... ....... .. .... ...... ... .... ... ......... .. 52 7.0 BASIS ............ ..... ......... .. .... ..... .. .... ... .. ......... .... .................... .. ... .. .. .. ................ .. .. .. .......... 53 7 .1 Instrumentation ...... ...... ... .... ... .. .. .. .. ....... .. ..... .... .. .. ..... ...... ... .. .... ... ...... .. ... .. ............... 53 7 .2 Radioactive Effluents .......................... .. ..... .. ........... .... .. ....... .. ....... ..... ........ ..... .... ..... 53 7 .3 Radiological Environmental Monitoring ........ .. .... ........ ........ .... .. .. ... .... .... .... .. .... ........ 58 7.4 Abnormal Release or Abnormal Discharge Reporting ...... .. .. ... ... .............. .......... ..... 59 (Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 96 of 237 CH-ODCM-0001 Reference Use Page 3 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 List of Tables PARTI Table 1.2 - Frequency Notation ........ .. .... .... .................................... .. ...... .. .. .. ............ ...... .. .. ..... 8 Table 1.3 - Radiological Effluent Controls Program Implementation .... .. .... .. .......... .. .. .. .... .. ..... 9 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation .. ........ .. .. ................ .. .... 11 Table 3.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ... .. ....... ............ ... ..... ........... ..... ....... ...... .. ..................... .. .. ....... .. .. .... ....... .. .... .. .. 12 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation .. ...... .... .... .. ............ . 14 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .......................... .. ..................................................... .................. . 16 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis .. .... .......... ............................ . 19 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis ..... .. .. .... .... ........... ... .... ...... 24 Table 5.1 - Radiological Environmental Monitoring Program ....... ... .. ....... .. ............ .... ........ ... . 31 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) A, 8
- c .... .. ......... .. .......... ... .. .......... ......... ..... ... .... ... .... ... .... .. ..... .. ............... .. ...... 42 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples A. 43 List of Figures PARTI Figure 1 - Environmental Radiological Sampling Points ...... .. ......... ..... ................... .............. 40 Figure 2 - 40CFR190 Sampling Points .. ...... .. .... ... ...... .. .. .. .. ... .... .. ... ........ .. ...... .... .. ..... .. .. .... .. . 41 (Req Reviews: Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 97 of 237 CH-ODCM-0001 Reference Use Page 4 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table of Contents PART II 1.0 EFFLUENT MONITOR SETPOINTS ...... .. ... ..... ..... ... .... ..... ... ... .. ... .... .. ....... ...... .. .. .......... 62 1.1 Liquid Effluents ... .... .. .... .... ... .. .............. .. .. .... .... ... ... ..... ........ .... ........ ............. .......... .. 62 1.2 Airborne Effluents ..... .. .... ...... ...... .... ..... ... .. ..... .... .. ..... .... ... ... .. ...... .... ..... ....... ... ...... .... 65 2.0 EFFLUENT CONCENTRATIONS ................ ........ .. ......... ....... ...... .. ... .... ................ .... .... 69 2.1 Liquid Effluent Concentrations .. .. .. .......... ...... ........ ... ... .. ... ......... .............. .... .. ...... .... 69 2.2 Airborne Effluent Concentrations .. .. .. .... ....... ...... ... ... ....... ..... ... ..... .... .. ....... .... .... ..... . 69 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS .. ........ ... ......... .. .... .... ... ...... .. ... ..... 71 3.1 Liquid Effluent Dose Calculations ............. ... ........ ....... ...... .. .... ................................. 71 3.2 Airborne Effluent Dose Calculations ... ... .. .... .... .... .. .. .... ...... ... ... .. ... .... ... .. .. .. ....... ....... 75 4.0 LOWER LIMIT OF DETECTION (LLD) .. ... .. ..... ..... ..... ......... .. .. .. ............ .. .. .. ...... ....... .. ... 87 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 98 of 237 CH-ODCM-0001 Reference Use Page 5 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 List of Tables PART II Table 1 - Deleted .. ..... ..... .. ........... ..... ..... .. .. ... ..... ... ......... .... .. .. ...... ..... ............. ...... ... ... ............ 65 Table 2 - Deleted .. .... .. ......... ....... ............ .. .... .... ... ..... ... .. .. .... .. .... ...... ......... .... .... ..... ... .. ......... .. 88 Table 3 - Bioaccumulation Factors ......... ...... ..... ....... ..... ......... .......... ........ .... ......................... 88 Table 4 - Highest Potential Exposure Pathways for Estimating Dose ................ .... .......... .. ... . 89 Table 5 - Stable Element Transfer Data ..... .. ... .. ... ....... .... ...... ... .... ... .. ... ... ... .......... ......... ..... .. . 90 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data .. .... ... ..... ...... ... ... ... .... ... .. .... .... ............ ......... 91 Table 7 - Animal Consumption Rates ..... .. .... ...... ........ ... .... ...... .......... ... .. ... .... ..... .... ...... ...... ... 91 Table 8 - External Dose Factors for Standing on Contaminated Ground ... .. ...... .... ..... .......... . 92 Table 9 - Inhalation Dose Factors for Adult ... .. ... ........ .... .. ....... ...... .. .......... .. ........ .... .... ... ...... . 95 Table 10 - Inhalation Dose Factors for Teenager ............ ....... .... ................. ... ..... ... ............... 98 Table 11 - Inhalation Dose Factors for Child ... ......... ...... .... .. ...... .... ........ .. ........ ... .... ....... ..... 101 Table 12 - Inhalation Dose Factors for Infant .... .. .... .. .... .......... .... ..... ..... ..... ..... .. ... ... ... .... ..... 104 Table 13 - Ingestion Dose Factors for Adult ..... .. ... ........ .... ... .. .... ...... ... .... .. ........... ... .. ... ....... 107 Table 14 - Ingestion Dose Factors for Teenager ..... ... .... ... ....... .... ... ........ .. ....... .......... ....... .. 110 Table 15 - Ingestion Dose Factors for Child ......... ... ..... .... ............ .... ....... .. ... ... ..... .. .. .... ... .... 113 Table 16 - Ingestion Dose Factors for Infant .... .... .... ..... .. .. ... ... ..... .... ... ..... .... ...... ... .. .... ...... .. 116 Table 17 - Recommended Values for Other Parameters ......... ... .... .. ................ .............. ... .. 119 List of Figures PART II Figure 1 - Exclusion and Site Boundary Map ........ .... ....... ... ........... .... ..... ... .... .... .. .. .. ....... .. .... 66 Figure 2 - Deleted ...... ........ ... ... ............ ... ..... ... .. .. ...... .. .............. ..... ... .. ...... .. ... .... . Figure 3 - Deleted ... ... ... ..... ... .... ....... ..... ... .... ........ .. .... ... .. .......... .. ... ..... .... ... ..... ... . . Figure 4 - Airborne Effluent Discharge Pathways ......... .. .. .. .... ... ............... ..... ... ... .. ...... ..... .... . 67 Figure 5 - Deleted .. ............. ..... .. .... .. ................. ...... .... ..... ....... .. ...... ........... ..... ... .......... ..... ..... 67 (Req Reviews: Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-0 1F6B73ADF3B Page 99 of 237 CH-ODCM-0001 Reference Use Page 6 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 The purpose of the ODCM is to provide methodologies for and parameters necessary for calculating offsite doses, determination of gaseous and liquid radiation monitor set points , and administrative controls for effluent instrumentation , Radiological Effluent Tech Specs (RETS) , and the Radiological Environmental Monitoring Program (REMP). 1.2 Scope 1.2.1 Radioactive effluents are generated from station activities . These controls provide methodologies ensuring these effluents are properly monitored and quantified to promote accurate dose reporting . Additional controls ensure station equipment and processes are used to minimize release to the environment. The combination of minimizing release , accurately reporting dose , and monitoring the facility environs provides the basis for ensuring that station activities are not negatively impacting public health and the environment. 2.0 DEFINITIONS 2.1 Abnormal Discharge - The unplanned or uncontrolled emission of an effluent (i.e. , containing facility-related, licensed radioactive material) into the unrestricted area. 2.2 Abnormal Release - The unplanned or uncontrolled emission of an effluent (i.e., containing facility-related , licensed radioactive material) . 2.3 Channel Check - A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation . This determination shall include , where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. 2.4 Channel Function Test - Injection of a simulated signal into the channel to verify that it is functional , including any alarm and/or trip initiating action . 2.5 Effluent Concentration Limit (ECL) - Radionuclide limits listed in 10 CFR Part 20 , Appendix B, Table 2, Column 1. 2.6 Member(s) of the Public - Member(s) of the Public means any individual except when that individual is receiving occupational dose . (Req Reviews: Rad Review, ISR, RP)
Doc uSign Enve lope ID: EA65F186-46DE -4A34-97A4-0 1F6B 73ADF3B Page 100 of 237 CH-ODCM-0001 Reference Use Page 7 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 2.7 Functional-Functionality - A system , subsystem , train, component or device shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation , controls , normal or emergency electrical power sources , cooling and seal water, lubrication , and other auxiliary equipment that are required for the system , subsystem , train , component, or device to perform its function(s) are also capable of performing their related support function(s) . 2.8 Residual Radioactivity - Residual radioactivity means radioactivity in structures , materials , soils , ground water, and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee , but it excludes background radiation . It also includes rad ioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site , even if those burials were made in accordance with the provisions of 10 CFR Part 20 . 2.9 Restricted Area - An area to which access is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials . 2.10 Site Boundary - The Site Boundary is the line beyond which the land is neither owned, or leased , nor controlled by the licensee. 2.11 Source Check - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity . 2.12 Special Liquid - Non-routine release pathway in which normally non-radioactive liqu id streams found to contain radioactive material , are non-routine , and will be treated on a case specific basis if and when this occurs. 2.13 Unrestricted Area - An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials , or any area within the SITE BOUNDARY used for residential quarters or for industrial , commercial , institutional , and/or recreational purposes. 2.14 Venting - VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure , humidity, concentration , or other operating condition , in such a manner that replacement air or gas is not provided or required during VENTING . Vent, used in system names , does not imply a VENTING process . 2.15 Water Effluent Concentration (WEC) - Radionuclide limits listed in 10 CFR Part 20 , Appendix B, Table 2, Column 2. (Req Reviews: Rad Review, ISR, RP )
F6B 73ADF3B Page 101 of 237 CH-ODCM-0001 Reference Use Page 8 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 1.2 - Frequency Notation The surveillance intervals are defined as follows : Notation Title FrequencyA s Shift At least once per 12 hours D Daily At least once per 24 hours w Weekly At least once per 7 days BW Biweekly At least once per 14 days M Monthly At least once per 31 days Q Quarterly At least once per 92 days SA Semiannual At least once per 184 days A Annually At least once per 366 days R At least once per 18 months p Prior to Prior to each release (Performance within 24 hrs .) A. Each survei llance requirement shall be performed within the specified survei ll ance inte rval with a maximum allowab le extension not to exceed 25 percent of the specified survei llance interval. (Req Reviews: Rad Review, ISR, RP)
86-46DE-4A34-97A4-01 F6B73ADF3B Page 102 of 237 CH-ODCM-0001 Reference Use Page 9 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 1.3 - Radiological Effluent Controls Program Implementation NO-FC-10 Appendix E ODCM Implementing Step E.2.1 .3.a 3.1.1, 3.2 .1 E.2.1 .3.b 4.1.1 E.2.1 .3.c Table 4.1 , Table 4.2 E.2.1.3.d 4.1.2 E.2.1 .3.e 4.1.2B .1, 4.2.2B .1 E.2.1.3.f 4.1.3A, 4.2.4A E.2.1.3 .g 4.2.2 E.2.1.3 .h 4.2.3 E.2.1.3.i 4.3.1 E.3.1.3.a 5.1.1 E.3.1.3.b 5.2.1 E.3.1.3.c 5.3.1 E.1.2 6.3, 6.2.1 D E.4.1 6.2.1 E.4.2 6.2.2 (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 103 of 237 CH-ODCM-0001 Reference Use Page 10 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.0 INSTRUMENTATION 3.1 Radioactive Liquid Effluent Instrumentation 3.1 .1 Limiting Condition for Operation A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.1.1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 3.1.1 are not exceeded . The alarm/trip setpoints of these channels shall be determined in accordance with Part II of the Off-Site Dose Calculation Manual. APPLICABILITY: At all times ACTION:
- 1. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive liquid effluents monitored by the affected channel or declare the channel non-functional.
- 2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels functional, take the action shown in Table 3.1.1. Restore non-functional effluent monitoring instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this non-functionality was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent stream: RM-055.
3.1 .2 Surveillance Requirements A. Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.1.2. (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 104 of 237 CH-ODCM-0001 Reference Use Page 11 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrument Functional Action
- 1. Radioactivity Monitor Providing Alarm and Automatic Termination of Release .
1.1 Liquid Radwaste Effluent Line (RM-055) 1 1, 4
- 2. Flow Rate Measurement Device 2.1 Liquid Radwaste Effluent Line 1 2
- 3. Radioactivity Recorder 3.1 Liquid Radwaste Effluent Line 1 3 Table Notation ACTION 1 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided that prior to initiating a release :
- 1. At least two independent samples are analyzed in accordance with applicable chemistry procedures.
- 2. At least two qualified individuals independently verify the release rate calculations.
ACTION 2 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the flow rate is determined at least once per four hours during the actual release. ACTION 3 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the radioactivity is recorded manually at least once per four hours during the actual release . ACTION 4 During the performance of source checks the effluent radiation monitor is unable to respond , hence is considered non-functional. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. If the effluent radiation monitor fails the source check , carryout the action(s) of the Off-Site Dose Calculation Manual for the non-functional monitor or terminate the effluent release . (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 105 of 237 CH-ODCM-0001 Reference Use Page 12 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 3.1 .2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Function Check Calibration Check Test
- 1. Radioactivity Monitor Providing Alarm and Automatic Isolation 1.1 RM-055 ---- R Q p (Req Reviews: Rad Review, ISR, RP)
DocuSign Envelope ID : EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 106 of 237 CH-ODCM-0001 Reference Use Page 13 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.2 Radioactive Gaseous Effluent Instrumentation 3.2.1 Limiting Condition for Operation A. The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.2.1 shall be FUNCTIONAL to ensure that the limits of Specification 3.2.1 are not exceeded . APPLICABILITY: At all times ACTION :
- 1. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels functional, take the action shown in Table 3.2.1. Restore non-functional effluent monitoring instrumentation to FUNCTIONAL status within 30 days and , if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this non-functionality was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent streams: RM-043 , RM-052 and Particulate Air Samplers .
3.2.2 Surveillance Requirements A. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, CALIBRATION , and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.2.2. (Req Reviews : Rad Review, ISR, RP)
F6873ADF38 Page 107 of 237 CH-ODCM-0001 Reference Use Page 14 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Channels Action Functional
- 1. Forced Draft releases 1.1 Particulate air sampler-Portable filtered ventilation 1 2 systems discharge
- 2. Unventilated building opening 2.1 Particulate air sampler-open doorway/ open rollup 1 3 door
- 3. Open -air demolition 3.1 Particulate air samplers (4 air samplers at each 4 4 open-air location)
- 4. Flow Rate Measurement Devices 4.1 Hand-held anemometer 1 1 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 108 of 237 CH-ODCM-0001 Reference Use Page 15 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 3.2 .1 Radioactive Gaseous Effluent Monitoring Instrumentation Table Notation ACTION 1 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement , effluent releases may continue provided the flowrate is estimated or recorded manually at least once per four hours during the actual release. ACTION 2 If portable air sampler monitoring the discharged of a portable filtered ventilation unit OR its associated flowmeter is non-functional, active decommissioning may continue provided the portable air sampler is replaced within 2 hours of declaration of non-functionality. If air sampler is unable to be replaced within 2 hours, secure the release fan AND cease active decommissioning in the area monitored by the non-functioning air sampler. ACTION 3 If portable air sampler monitoring open doorways in unventilated building flowpaths OR its associated flowmeter is non-functional , active decommissioning may continue provided the portable air sampler is replaced within 2 hours of declaration of non-functionality. If air sampler is unable to be replaced within 2 hours, close the door associated with this air sampler OR cease active decommissioning work until the air sampler can be replaced. ACTION 4 If any of the 4 air samplers monitoring air around an open-air demolition location OR their associated flowmeters are non-functional , active decommissioning may continue provided the portable air sampler is replaced within 2 hours of declaration of non-functionality. If the open-air demolition location is unable to be monitored by 4 air samplers, cease active open-air decommissioning at the affected location. (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 109 of 237 CH-ODCM-0001 Reference Use Page 16 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Operations Check Air Flow Calibration
- 1. Environmental Monitors 1.1 RM-023 - Sample Station #40 M A 1.2 RM-024 - Sample Station #41 M A 1.3 RM-025 - Sample Station #28 ---- ----
1.4 RM-026 - Sample Station #36 ---- ---- 1.5 RM-027 - Sample Station #37 M A 1.6 RM-028 - Sample Station #38 ---- ---- 1.7 RM-029 - Sample Station #39 ---- ---- 1.8 RM-035 - Sample Station #1 ---- ---- 1.9 RM-036 - Sample Station #2 M A 1.10 RM-037 - Sample Station #3 ---- ---- 1.11 RM-038 - Sample Station #4 M A 1.12 RM-039 - Sample Station #5 ---- ---- 1.13 RM-040 - Sample Station #32 M A
- 2. Decommissioning portable air sampler flowmeters 2.1 All sample stations w1 A 1- Operation check performed only when the unit is started to support active decommissioning.
(Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 110 of 237 CH-ODCM-0001 Reference Use Page 17 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 4.0 RADIOACTIVE EFFLUENTS 4.1 Radioactive Liquid Effluents 4.1.1 Concentration A. Limiting Condition for Operation
- 1. The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides do not exceed the values specified in 10 CFR Part 20 for liquid effluents at site discharge. To support facility operations, RP/Chemistry supervision may increase this limit up to the limit specified in QATR Appendix E, E.2 .1.3.b.
- 2. QATR Appendix E, E.2.1.3.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.
APPLICABILITY: At all times ACTION:
- a. When the concentration of radioactive material released at site discharge exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.
(Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 111 of 237 CH-ODCM-0001 Reference Use Page 18 of 120 Off-Site Dose Calculation Manual (OOCM) Revision 38 B. Surveillance Requirements NOTE I Radioactive liquid waste includes water used for fire suppression in areas of the facility that may contain radioactivity. These liquids are required to be I monitored prior to release .
- 1. Radioactive liquid waste shall be sampled and analyzed according to the sampling and analysis program in Table 4.1.
- 2. The results of the radioactivity analysis shall be used with the calculational methods in Part II of the Off-Site Dose Calculation Manual.
- 3. To assure that the concentration at the point of release is maintained within the limits of QATR Appendix E, E.2.1.3 .b.
- 4. Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred . Analytical results shall be submitted to the Commission in accordance with Part I, Section 6.0 of the Off-Site Dose Calculation Manual.
(Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 112 of 237 CH-ODCM-0001 Reference Use Page 19 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis A. L"IQUI"dR e Ieases Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (µCi/ml) A Each Batch Principal Gamma Emitters 8 5.0E-07 Monthly Composite c H-3 1.0E-05 Monthly Composite c Gross Alpha 1.0E-07 Quarterly Composite c Sr-89, Sr-90 5.0E-08 Quarterly Composite c Fe-55, Ni-63 1.0E-06 NOTES: A. LLD is defined in Part II of the Off-Site Dose Calculation Manual. B. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59 , Co-58 , Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141 for fission and corrosion products. Ce-144 shall also be measured, but with a LLD of 5 .0E-06. C. To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples should be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite should be mixed in order for the composite sample to be representative of the average effluent release. (Req Reviews: Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 113 of 237 CH-ODCM-0001 Reference Use Page 20 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 4.1.2 Dose from Radioactive Liquid Effluents A. Limiting Condition for Operation
- 1. The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents shall be limited to the following :
- a. During any calendar quarter: Less than or equal to 1.5 mrem to the total body and 5 mrem to any organ; and
- b. During any calendar year: Less than or equal to 3 mrem to the total body and 10 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution , due to the cumulative release of radioactive materials in liquid effluents, exceeds the annual or quarterly dose objectives , submit a Special Report to the NRC ,
per Section 6.2.4, within 30 days . B. Surveillance Requirements
- 1. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Part 11 of the Off-Site Dose Calculation Manual at least once per quarter.
(Req Reviews: Rad Review, ISR, RP)
86-46DE-4A34-97A4-01F6B73ADF3B Page 114 of 237 CH-ODCM-0001 Reference Use Page 21 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 4 .1.3 Liquid Radwaste Treatment A. Limiting Condition for Operation
- 1. The Liquid Radwaste Treatment System shall be FUNCTIONAL, and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the whole body or 0 .2 mrem to any organ in a 31-day period.
APPLICABILITY: At all times ACTION :
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation ,
prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to 10 CFR 50, Appendix I, a Special Report that includes the following information:
- 1) Explanation of why liquid radwaste was being discharged without treatment, identification of equipment or subsystem(s) not functional and reasons for non-functionality.
- 2) Action(s) taken to restore the non-functional equipment to functional status.
- 3) Summary description of action(s) taken to prevent a recurrence .
B. Surveillance Requirements
- 1. Dose due to liquid releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual , when Liquid Radwaste Treatment Systems are not fully FUNCTIONAL.
(Req Reviews : Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 115 of 237 CH-ODCM-0001 Reference Use Page 22 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38
- 2. FUNCTIONAL is defined as follows:
- a. A filtration/ion exchange (FIX) system will be utilized for processing liquid radwaste. The system consists of a booster pump , charcoal pretreatment filter, and pressure vessels containing organic/inorganic resins, which can be configured for optimum performance. The effluent from the FIX system is directed to storage tanks for release.
- b. Waste filters (WD-17 A and WD-17B) are used only on those occasions when considered necessary, otherwise the flows from the low activity fluids may bypass the filters. No credit for decontamination factors (iodines, Cs, Rb, others) was taken for these filters during the 10 CFR Part 50 Appendix I dose design objective evaluation; therefore , the non-functionality of these filters does not affect the dose contributions to any individual in the unrestricted areas via liquid pathways. The non-functionality of waste filters will not be considered a reportable event in accordance with the Action listed above.
4 .1.4 Liquid Holdup Tanks Tanks included in this Specification are those outdoor tanks that are not surrounded by liners , dikes, or walls capable of holding the tanks contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system . A. Limiting Condition for Operation
- 1. The quantity of radioactive material contained in each unprotected outdoor liquid holdup tank shall not exceed 10 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times ACTION:
- a. When the quantity of radioactive material in any unprotected outdoor liquid holdup tank exceeds 10 curies , excluding tritium and dissolved or entrained noble gasses, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit.
(Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 116 of 237 CH-ODCM-0001 Reference Use Page 23 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 B. Surveillance Requirements
- 1. The quantity of radioactive material contained in each outdoor liquid holdup tank shall be determined to be within the above limit by analyzing a representative sample of the tanks contents at least once per 7 days when radioactive material is being added to the tank .
4.2 Radioactive Gaseous Effluents 4.2.1 Concentration A. Limiting Condition for Operation
- 1. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations of radionuclides does not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary.
APPLICABILITY : At all times ACTION:
- a. When the concentration of radioactive material released to unrestricted areas exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.
B. Surveillance Requirements NOTE Radioactive gaseous wastes include atmospheres in areas where gaseous I fire suppression systems are utilized or where smoke is produced as a result of fire in areas of the facility that may contain radioactivity. These I atmospheres are required to be monitored prior to gaseous release to unrestricted areas.
- 1. Radioactive gaseous wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4 .2 . The results of the radioactivity analysis shall be used to assure the limits in Step 4.2 .1A are not exceeded .
(Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B 73ADF3B Page 117 of 237 CH-ODCM-0001 Reference Use Page 24 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis A. Forced Draft Exhaust discharge Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (µCi/ml) A Weekly (Particulate Sample) Principal Gamma Emitters 8 1.0E-11 Monthly Composite c Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-90 1.0E-11 B. Unventilated building doorways Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (µCi/ml) A Weekly (Particulate Sample) Principal Gamma Emitters 8 1.0E-11 Monthly Composite c Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-90 1.0E-11 C. Open-Air Demolition locations Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (µCi/ml) A Weekly (Particulate Sample) Principal Gamma Emitters 8 1.0E-11 Monthly Composite c Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-90 1.0E-11 NOTES: A. LLD is defined in Part II of the Off-Site Dose Calculation Manual. B. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides : Mn-54 , Fe-59, Co-58, Co-60 , Zn-65 , Mo-99, Cs-134, Cs-137, Ce-141 , and Ce-144 for particulate releases . C. Frequency requirement may be satisfied using weekly gross alpha results from particulate sampling media . (Req Reviews: Rad Review, ISR, RP)
86-46DE -4A34-97A4-01 F6B73ADF3B Page 118 of 237 CH-ODCM-0001 Reference Use Page 25 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 4.2 .2 Dose - H-3 and Radioactive Material in Particulate Form with Half-Lives Greater than 8 Days (Other than Noble Gases) A. Limiting Condition for Operation
- 1. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of H-3 and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be limited to the following :
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ ; and
- b. During any calendar year: Less than or equal to 15 mrem to any organ .
APPLICABILITY: At all times ACTION :
- a. If the dose contribution , due to the cumulative release of H-3 and radioactive materials in particulate form with half-lives greater than eight days, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC per Section 6.2.4 , within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from H-3 and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be determined , in accordance with the methodologies and parameters of Part II of the Off-Site Dose Calculation Manual , on a quarterly basis.
(Req Reviews: Rad Review, ISR, RP )
-4A34-9 7A4-01 F6B73ADF3B Page 119 of 237 CH-ODCM-0001 Reference Use Page 26 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 4.2 .3 Gaseous Radwaste Treatment A. Limiting Condition for Operation
- 1. In accordance with QATR Appendix E, E.2.1.3.f, the Ventilation Exhaust Systems shall be FUNCTIONAL, and appropriate portions of these systems shall be used to reduce the releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed :
- a. 0.2 mrad to air from gamma radiation , or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC APPLICABILITY: At all times ACTION:
- a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit a report to the Nuclear Regulatory Commission within 30 days ,
pursuant to 10 CFR 50, Appendix I, a special report that includes the following information:
- 1) Identification of equipment or subsystem(s) not functional and reasons for non-functionality.
- 2) Action(s) taken to restore the non-functional equipment to functional status.
- 3) Summary description of action(s) taken to prevent a recurrence.
B. Surveillance Requirements
- 1. Dose due to gaseous releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual, when Ventilation Exhaust Systems are not fully FUNCTIONAL.
(Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 120 of 237 CH-ODCM-0001 Reference Use Page 27 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38
- 2. FUNCTIONAL is defined as follows:
- a. Ventilation Exhaust Systems
- 1) The radioactive effluents of forced draft ventilation systems are filtered by the HEPA. If the radioactive effluents are discharged without the HEPA filters and it is confirmed that one half of the annual dose objective will be exceeded during the calendar quarter, a special report shall be submitted to the Commission pursuant to Section 4.2.3A.
(Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 121 of 237 CH-ODCM-0001 Reference Use Page 28 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 4.3 Uranium Fuel Cycle 4.3.1 Total Dose-Uranium Fuel Cycle A. Limiting Condition for Operation
- 1. The dose to any real individual from uranium fuel cycle sources shall be limited to :5 25 mrem to the total body or any organ (except the thyroid, which shall be limited to :5 75 mrem) during each calendar year.
APPLICABILITY : At all times ACTION :
- a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specifications 4.1 .2A, or 4.2.2A, calculations shall be made including direct radiation contribution from the facility and outside storage tanks to determine whether the above limits have been exceeded . If such is the case , in lieu of any other report required by Section 6.2, prepare and submit a Special Report to the Commission pursuant to QATR Appendix E, E.2.1 that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report , as defined in 10 CFR Part 20 .2203(a)(4) and 20 .2203(b) , shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources , including all effluent pathways and direct radiation , for the calendar year that includes the release(s) covered by this report . It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 or 10 CFR Part 72.104 has not already been corrected , the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 or 10 CFR Part 72 .104. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete .
(Req Reviews : Rad Review, ISR, RP)
DocuSign Envelope ID : EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 122 of 237 CH-ODCM-0001 Reference Use Page 29 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 4 .3.1 (continued) B. Surveillance Requirements
- 1. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance requirements 4.1.2B and 4.2 .2B and in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual.
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 5.1 Monitoring Program 5.1.1 Limiting Condition for Operation A. The Radiological Environmental Monitoring Program shall be conducted as specified in Table 5.1. APPLICABILITY: At all times ACTION:
- 1. Analytical results of this program and deviations from the sampling schedule shall be reported to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 6.2).
- 2. If the level of radioactivity from calculated doses leads to a higher exposure pathway to individuals, this pathway shall be added to the Radiological Environmental Monitoring Program. Modifications to the program shall be reported in the Annual Radiological Environmental Operating Report to the Nuclear Regulatory Commission .
- 3. If the level of radioactivity in an environmental sampling medium exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.4). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 5.3 for Lower Level of Detection (LLD) .
(Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 123 of 237 CH-ODCM-0001 Reference Use Page 30 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 5.1.1A (continued)
- 4. If the level of radioactivity in a sample from either an onsite or offsite well, performed per the Site Groundwater Protection Program, exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.4). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 5.3 for Lower Level of Detection (LLD). Copies of the Special Report will be forwarded to State/Local authorities.
[AR 39127]
- 5. If the level of radioactivity from either an onsite or offsite well, performed per the Site Groundwater Protection Program exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operations, state and local authorities shall be notified by the end of the next business day. NRC shall be notified per FCSI-RA-105, Reporting of Events and Conditions. [AR 39127]
- 6. Radiological environmental sampling locations and the media that is utilized for analysis are presented in Table 5.2. Sampling locations are also illustrated on the map, Figure 1. Details of the quarterly emergency TLD locations are contained in test CH-FT-RV-0003, Environmental Sample Collection - Quarterly/Environmental Dosimeters (TLDs). Each TLD sample location contains one dosimeter that is exchanged quarterly for REMP sampling and as needed for Emergency Planning Zone monitoring.
- 7. Deviations from the monitoring program, presented in this section and detailed in Table 5.2, are permitted if specimens are unobtainable due to mitigating circumstances such as hazardous conditions, seasonal unavailability, malfunction of equipment, or if a person discontinues participation in the program, etc. If the equipment malfunctions, corrective actions will be completed as soon as practicable. If a person no longer supplies samples, a replacement will be made if possible. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report, pursuant to Section 6.2.
5.1.2 Surveillance Requirements A. The Radiological Environmental Monitoring Program (REMP) samples shall be collected and analyzed in accordance with Tables 5.1, 5.2, and 5.3. (Req Reviews : Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 124 of 237 CH-ODCM-0001 Reference Use Page 31 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis 8 Frequency and/or Sample
- 1. Direct Rad iation A. 14 TLD indicator stations. Gamma dose Quarterly B. An inner-ring of 16 stations , one Gamma dose Quarterly in each cardinal sector in the general area of the unrestricted area boundary and within 2.5 miles.
C. An outer-ring of 16 background Gamma dose Quarterly stations, one in each cardinal secto r located outside of the inner-ring , but not closer than approximately 2.5 miles and one additional remote background station for a total of 17.F D. Other TLDs may be placed at Gamma dose Qua rterly special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Omaha Public Power District employees have routine access .
- 2. Air Monitoring A. Indicator Stations Filter for Gross Beta c Weekly
- 1. Three stations in the general Filter for Gamma Isotopic Quarterly area of the un restricted area composite bounda ry of weekly filters
- 2. City of Blair
- 3. Desoto Township B. One background station F
- 3. Water A. Missouri River at nearest Gamma Isotopic, H-3 Monthly for downstream drinking water Gamma intake. isotopic analysis.
B. Missouri River downstream near the mixing zone. Quarterly compos ite for C. Missou ri River upstream of H-3 Analysis Facility intake (background)F. 4 . Milk 0 A. Nearest milk animal (cow or Gamma Isotopic Monthly goat) within 5 miles B. Milk animal (cow or goat) between 5 miles and 18.75 miles (background )F. (Req Reviews : Rad Review, ISR , RP)
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 125 of 237 CH-ODCM-0001 Reference Use Page 32 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis 8 Frequency and/or Sample
- 5. Fish A. Four fish samples within vicinity Gamma Isotopic Once per of Facility discharge . season (May to B. One background sample October) upstream of Facility discharge.
- 6. Vegetables or A. One sample in the highest Gamma Isotopic Once per Food Products E exposure pathway. season (May to B. One sample from onsite crop October) field C. One sample outside of 5 miles (background)f.
- 7. Groundwater A. Three samples from sources H3, Gross Beta, Gamma Quarterly potentially affected by facility Isotopic, Sr-90 operations.
B. One sample outside of 5 miles (background)f.
- 8. Vegetation in lieu A. One sample at the highest Gamma Isotopic Monthly (when of milk annual average D/Q offsite available) location .
B. One sample at the second highest annual average O/Q offsite location . C. One sample outside of 5 miles (background) F_ (Req Reviews : Rad Review, ISR , RP)
-4A34-97A4-01 F6B73ADF3B Page 126 of 237 CH-ODCM-0001 Reference Use Page 33 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 NOTES: A. See Table 5.3 for required detection limits. B. The Lower Limit of Detection (LLD) for analysis is defined in the Off-Site Dose Calculation Manual in accordance with the wording of NUREG-1301 . C. When a gross beta count indicates radioactivity greater than 2.5E-13 µCi/ml or 0.25 pCi/m3, (ten times the yearly mean), a gamma spectral analysis will be performed . D. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broad leaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II , Table 4 "Highest Potential Exposure Pathways for Estimating Dose") E. Samples should be collected from garden plots of 500 ft2 or more. F. This sample may not be located in the least prevalent wind direction . The Branch Technical Position paper, Table 1, subnote "d" says this regarding background information , or control locations. "The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted". (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 127 of 237 CH-ODCM-0001 Reference Use Page 34 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north) (miles) Particulate Onsite Station, 110-meter weather 1 tower 0.53 293°/WNW p X Onsite Station, adjacent 2C, E to old plant access road 0.59 207°/SSW K X X Offsite Station, Intersection of Hwy. 75 3 and farm access road 0.94 145°/SE G X 4 Blair OPPD office 2.86 305°/NW Q X X 5A Fort Calhoun, NE City 6 Hall 5.18 150°/SSE H X Fence around intake gate, Desoto Wildlife 7 Refuge 2.07 102°/ESE F X Onsite Station, entrance to Plant Site 8 from Hwy. 75 0.55 191 °1s J X Onsite Station, NW of 9 Plant 0.68 305°/NW Q X Onsite Station , WSW of 10 Plant 0.61 242°/WSW M X Offsite Station, SE of 11 Plant 1.07 39°/SE G X (Req Reviews : Rad Review, ISR , RP)
F6B73ADF3B Page 128 of 237 CH-ODCM-0001 Reference Use Page 35 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north) (miles) Particulate Metropolitan Utilities Dist., Florence Treatment Plant 12 North Omaha, NE 14.3 154°/SSE H X West bank Missouri River, downstream from 13 Plant discharge 0.45 108°/ESE F X X Upstream from Intake 14° Bldg, west bank of river 0.09 4°/N A X X 15 Smith Farm 1.99 134°/SE G X 16A 17A 18A 19A 20B,0,F Mohr Dairy 9.86 186°/S J X X X 21 A Fish Sampling Area , 0.08 22 Missouri River (R.M. 645.0) 6°/N A X Fish Sampling Area, 17.9 23° Missouri River (R.M. 666.0) 358°/N A X 24A 25A 26A 27A (Req Reviews : Rad Review, ISR , RP)
F6B73ADF3B Page 129 of 237 CH-ODCM-0001 Reference Use Page 36 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north) (miles) Particulate 28 Alvin Pechnik Farm 0.94 163 H X 29A 3QA 31 A 32° Valley Substation #902 19.6 221 °/SW L X X 33A 34A 35 Onsite Farm Field 0.52 118°/ESE F X Offsite Station Intersection Hwy 75/Co. 36 Rd . P37 0.75 227°/SW L X Offsite Station Desoto 37 Township 1.57 144°/SE G X X 38A 39A 4QA 41B,C Dowler Acreage 0.73 175°1s J X X 42 Sector A-1 1.94 0°/NORTH A X 43 Sector B-1 1.97 16°/NNE B X 44 Sector C-1 1.56 41 °/NE C X 45 Sector D-1 1.34 71 °/ENE D X 46 Sector E-1 1.54 90°/EAST E X 47 Sector F-1 0.45 108°/ESE F X (Req Reviews : Rad Review, ISR , RP)
A4-01 F6B73ADF3B Page 130 of 237 CH-ODCM-0001 Reference Use Page 37 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north) (miles) Particulate 48 Sector G-1 1.99 134°/SE G X 49 Sector H-1 1.04 159°/SSE H X 50 Sector J-1 0.71 179°/SOUTH J X 51 Sector K-1 0.61 205°/SSW K X 52 Sector L-1 0.74 229°/SW L X 53 Sector M- 1 0.93 248°/WSW M X 54 Sector N-1 1.31 266°/WEST N X 55 Sector P-1 0.60 291 °/WNW p X 56 Sector Q-1 0.67 307°/NW Q X 57 Sector R-1 2.32 328°/NNW R X 58° Sector A-2 4.54 350°/NORTH A X 59° Sector B-2 2.95 26°/NNE B X 6QO Sector C-2 3.32 50°/NE C X 61 ° Sector D-2 3.11 75°/ENE D X 62° Sector E-2 2.51 90°/EAST E X 63° Sector F-2 2.91 110°/ESE F X 64° Sector G-2 3.00 140°/SE G X 65° Sector H-2 2.58 154°/SSE H X 66D Sector J-2 3.53 181 °/SOUTH J X 67° Sector K-2 2.52 205°/SSW K X 68D Sector L-2 2.77 214°/SW L X 69° Sector M-2 2.86 243°/WSW M X (Req Reviews : Rad Review, ISR , RP)
86-46DE-4A34-97 A4-01 F6B73ADF3 B Page 131 of 237 CH-ODCM-0001 Reference Use Page 38 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north) (miles) Particulate 7Q0 Sector N-2 2.54 263°/WEST N X 71 0 Sector P-2 2.99 299°/WNW p X 720 Sector Q-2 3.37 311 °/NW Q X 73° Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X 75B,C Lomp Acreage 0.65 163°/SSE H X X X 76A 7?G River N- 1 0.17 328°/NNW R X 78G River S-1 0.14 85°/EAST E X 79G Lagoon S-1 0 .24 131 °/SE G X BOG Parking S- 1 0.27 158°/SSE H X 81 G Training W-1 0.28 194°/SSW K X 82G Switchyard S-1 0.21 219°/SW L X 83G Switchyard SE-1 0.14 231 °/SW L X 84G Switchyard NE-1 0.18 256°/WSW M X 85G Switchyard W-1 0.29 233°/WEST L X 86G Switchyard N- 1 0.24 262°/WEST N X 87G Range S- 1 0.20 286°/WNW p X 88G Mausoleum E-1 0 .37 216°/SW L X 89 C , Miller 3.30 210°1ssw K X (Req Reviews : Rad Review, ISR , RP)
A4-01 F6B73ADF3B Page 132 of 237 CH-ODCM-0001 Reference Use Page 39 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 NOTES: A. Location is either not in use or currently discontinued and is documented in the table for reference only. B. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass , etc.) shall be collected as an alternate sample at the site . If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available , at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II , Table 4 "Highest Potential Exposure Pathways for Estimating Dose") C. Locations represent highest potential exposure pathways as determined by the biennial Land Use Survey, performed in accordance with Part I, Section 7 .3.2, of the Off-Site Dose Calculation Manual and are monitored as such. D. Background location (control). All other locations are indicators . E. Location for monitoring Sector K High Exposure Pathway Resident Receptor for inhalation. F. When broad leaf (pasture grasses) are being collected in lieu of milk , background broad leaf samples will be collected at a background locale. G. Location for special interest monitoring general dose to the public per 40CFR190 (Figure 2) (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 133 of 237 CH-ODCM-0001 Reference Use Page 40 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Figure 1 - Environmental Radiological Sampling Points N Q E l)RAWLNG FILE ~- P- 000 75 (*) Locations currently discontinued are not illustrated. (Req Reviews: Rad Review, ISR, RP)
Do cuSign Envelope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 134 of 237 CH-ODCM-0001 Reference Use Page 41 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Figure 2- 40CFR190 Sampling Points IO 1f';a I I I I
")
I I CD L!QllID EF'FLUF,NTS DISCHARGE' AIR.B ORNE EFFLVEN'TS DISCHARGE 1'0 O:MAHA
- SAMPLI NG PO I NT 0 1(2 SOAI.E IN MILES SITE BOUNDARY MAP (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 135 of 237 CH-ODCM-0001 Reference Use Page 42 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) A, 8 , c Gross Co-58, Ba-140 Sample Units Beta H-3 Mn-54 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 La-140 Water pCi/L 4 2.0E+03 1.5E+01 3.0E+01 1.5E+01 3.0E+01 1.5E+01 1.5E+01 1.5E+01 1.8E+01 1.5E+01 pCi/kg Fish (wet) --- --- 1.3E+02 2 .6E+02 1.3E+02 2.6E+02 --- --- 1.3E+02 1.5E+02 --- Milk pCi/L --- --- --- --- --- --- --- --- 1.5E+01 1.8E+01 1.5E+01 Airborne Particulates pCi/m 3 1.0E-02 --- --- --- --- --- --- --- 1.0E-02 1.0E-02 --- pCi/kg Sediment (dry) --- --- --- --- --- --- --- --- 1.5E+02 1.8E+02 --- Grass or Broad Leaf Vegetation/ Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 6.0E+01 8.0E+01 --- A. This list does not mean that only these nuclides are to be considered . Other peaks that are identifiable as Facility effluents , together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Part I, Section 6.2, of the Off-Site Dose Calculation Manual. B. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4 .13 . C. The LLD is defined in Part II of the Off-Site Dose Calculation Manual. (Req Reviews : Rad Review, ISR , RP)
F6873ADF38 Page 136 of 237 CH-ODCM-0001 Reference Use Page 43 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples A Sample Units H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Water pCi/L 2.0E+04 1.0E+03 4.0E+02 1.0E+03 3.0E+02 3.0E+02 4.0E+02 4.0E+02 3.0E+01 5.0E+01 2.0E+02 Fish pCi/kg (wet) --- 3.0E+04 1.0E+04 3.0E+04 1.0E+04 2.0E+04 --- --- 1.0E+03 2.0E+03 --- Milk pCi/L --- --- --- --- --- --- --- --- 6.0E+01 7.0E+01 3.0E+02 Airborne pCi/m 3 Particulates --- -- --- --- --- --- --- --- 1.0E+01 2.0E+01 --- Grass or Broad Leaf Vegetation/ Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 1.0E+03 2.0E+03 --- A. A Non-routine report shall be submitted when more than one of the radionuclides listed above are detected in the sampling medium and : Concentration l Concentration 2 Concentration 3 Reporting Levell
+- - - - - - - + - - - - - - - + ... . 2::
Reporting Level 2 Reporting Level 3 1.0 When radionuclides other than those listed above are detected and are the result of Facility effluents , this report shall be submitted if the potential annual dose to a member of the general public is equal to or greater than the dose objectives of Part I, Section 4.1 and 4.2, of the Off-Site Dose Calculation Manual. This report is not required if the measured level of radioactivity was not the result of Facility effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. (Req Reviews : Rad Review, ISR , RP)
F6B73ADF3B Page 137 of 237 CH-ODCM-0001 Reference Use Page 44 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 5.2 Land Use Survey 5.2.1 Limiting Condition for Operation A. A Land Use Survey shall identify the location of the nearest milk animal, nearest meat animal, nearest vegetable garden, nearest groundwater source and the nearest residence in each of the 16 cardinal sectors within a distance of five miles. The survey shall be conducted under the following conditions:
- 1. Within a one-mile radius from the Facility site, enumeration by door-to-door or equivalent counting techniques.
- 2. Within a Five-mile radius, enumeration may be conducted door-to-door or by using referenced information from county agricultural agents or other reliable sources.
APPLICABILITY: At all times ACTION:
- a. If it is learned from this survey that milk animals, vegetable gardens and resident receptors are present at a location which yields a calculated dose greater than 20% from previously sampled location(s), the new location(s) shall be added to the monitoring program. Milk and vegetable garden sampling location(s) having the lowest calculated dose may then be dropped from the monitoring program at the end of the grazing and/or growing season during which the survey was conducted and the new location added to the monitoring program.
Groundwater monitoring is based on a determination if source(s) are potentially affected by facility operations. Modifications to the air monitoring locations, vegetable garden sampling locations, and milk sampling locations will be made as soon as practicable. The Nuclear Regulatory Commission shall be notified of modifications to the program in the Annual Radiological Environmental Operating Report (Section 6.2). (Req Reviews: Rad Review, ISR, RP)
F68 73ADF38 Page 138 of 237 CH-ODCM-0001 Reference Use Page 45 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 5.2 .1A.2 (continued)
- b. If it is learned from this survey that a pathway for dose to a MEMBER OF THE GENERAL PUBLIC no longer exists, an additional pathway has been identified or site specific factors affecting the dose calculations for a pathway have changed ,
then this information should be documented in the Land Use Survey, the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report. This information can be used to increase the accuracy of the dose models for the Annual Radioactive Effluent Release Report as well as dose estimates performed during the reporting period (i .e., quarterly dose estimates) . 5.2 .2 Surveillance Requirements A. A land use survey shall be conducted once per 24 months between the dates of June 1 and October 1. The results of the land use survey shall be submitted to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 6.2) for the year it was performed. 5.3 lnterlaboratory Comparison Program 5.3.1 Limiting Condition for Operation A. Analyses shall be performed on radioactive materials as part of an lnterlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commission. APPLICABILITY: At all times ACTION:
- 1. With analysis not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report (Section 6.2).
5.3.2 Surveillance Requirements A. The results of these analyses shall be included in the Annual Radiological Environmental Operating Report (Section 6.2) . (Req Reviews: Rad Review, ISR, RP)
DocuS ign Envelope ID: EA65F1 86-46DE-4A34-97A4-01 F6B73ADF3B Page 139 of 237 CH-ODCM-0001 Reference Use Page 46 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibilities 6.1.1 FCS RP/Chemistry Department is responsible for the implementation and maintenance of the Off-Site Dose Calculation Manual. 6 .1.2 ISFSI Shift Supervisor (ISS) is responsible for the compliance with the Off-Site Dose Calculation Manual in the operation of Fort Calhoun Station . 6.2 Radioactive Effluent Reporting Requirements The reporting requirements for radioactive effluents stated in this Section are to provide assurance that the limits set forth in Part I of the Off-Site Dose Calculation Manual are complied with . These reports will meet the requirements for documentation of radioactive effluents contained in 10 CFR Part 50.36a ; Reg . Guide 1.21 , Rev . 2; and Reg . Guide 1.109, Rev. 1. 6.2.1 Annual Radioactive Effluent Release Report A report covering the operation of the Fort Calhoun Station during the previous calendar year shall be submitted prior to May 1 of each year per the requirements of QATR Appendix E, E.4 .1 and 10 CFR Part 50. The Radioactive Effluent Release Report shall include : A. A summary of the quantities of radioactive liquid and airborne effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21 , Revision 2. B. A summary of the historical average meteorological data that provides joint frequency distributions of wind direction and wind speed by atmospheric stability class will be included in the annual report. C. An assessment of radiation doses from the radioactive liquid and airborne effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1 .21 , Revision 2. The assessment of radiation doses shall be performed in accordance with calculational methodology of the Regulatory Guide 1.109, Revision 1. D. Changes to the Process Control Program (PCP) or to the Offsite Dose Calculation Manual (ODCM) made during the reporting period . Each change shall be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed and shall indicate the date the change was implemented. (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 140 of 237 CH-ODCM-0001 Reference Use Page 47 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 6 .2.1 (continued) E. A list and description of abnormal releases or abnormal discharges from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period. F. An explanation of why instrumentation designated in Part I, Sections 3.1.1 and 3.2, of the Off-Site Dose Calculation Manual, was not restored to FUNCTIONAL status within 30 days . G. A description of any major design changes or modifications made to the Liquid and/or Gaseous Radwaste Treatment Systems or Ventilation Exhaust Systems during the reporting period . H. An explanation of why the liquid and/or gaseous radwaste treatment systems were not FUNCTIONAL, causing the limits of specifications 4.1.3A and 4 .2.3A to be exceeded . I. The results of sampling from offsite and onsite groundwater wells per the Site Groundwater Protection Plan. [AR 39127] J. Non-routine planned discharges (e.g ., discharges from remediation efforts like pumping contaminated groundwater from a leak). 6.2 .2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report for the previous one year of operation shall be submitted prior to May 1 of each year. This report contains the data gathered from the Radiological Environmental Monitoring Program . The content of the report shall include: A. Summarized and tabulated results of the radiological environmental sampling/analysis activities. In the event that some results are not available, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report . B. Interpretations and statistical evaluation of the results, including an assessment of the observed impacts of the facility operation and environment. C. The results of participation in a NRC approved lnterlaboratory Comparison Program. D. The results of land use survey required by Section 5.2 . E. A map of the current environmental monitoring sample locations . (Req Reviews : Rad Review, ISR, RP)
Do cuSign Envelope ID: EA65F186-46DE -4A34-97A4-01 F6B 73ADF3B Page 141 of 237 CH-ODCM-0001 Reference Use Page 48 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 6.2.3 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report. The Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report must be submitted within 60 days after the end of the 12-month monitoring period , per 10 CFR 72.44(d)(3). A. A Summary of the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous 12 months and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent releases. 6.2.4 Special Report If the limits or requirements of Sections 4 .1.2A, 4.1.3A, 4.2.2A, 4.3.1A, and/or 5.1.1A.3 and/or 5.1.1A.4 are exceeded , a Special Report shall be issued to the Commission, pursuant to QATR Appendix E, E.2. This report shall include : [AR 39127] A. The results of an investigation to identify the causes for exceeding the specification . B. Define and initiate a program of action to reduce levels to within the specification limits. C. The report shall also include an evaluation of any release conditions , environmental factors , or other aspects necessary to explain the condition . 6.2.5 EPA 40 CFR Part 190 Reporting Requirements With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of dose from specifications 4.1.2A or 4.2 .2A, calculations shall be made including direct radiation calculations , to prepare and submit a special report to the Commission within 30 days and limit the subsequent releases such that the dose to any real individual from uranium fuel cycle sources is limited to
- 25 mrem to the total body or any organ (except thyroid, which is limited to
- 75 mrem) over the calendar year. This special report shall include an analysis which demonstrates that radiation exposures to any member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 standard. Otherwise ,
obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 standard . The submittal of the report is to be considered a timely request and a variance is granted pending the final action on the variance request from the Commission . (Req Reviews: Rad Review, ISR , RP )
F6B73ADF3B Page 142 of 237 CH-ODCM-0001 Reference Use Page 49 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 6.2.6 ISFSI 10 CFR Part 72.104 Reporting Requirements The regulatory requirements of 10CFR20 , 10CFR72 and 40CFR 190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20, 10CFR72 and 40CFR190 not addressed by 10CFR50 Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public. The 10CFR72.104 dose limits are the same as those specified in 40CFR 190. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. If the dose limits of 40CFR190 or 10CFR72.104 are exceeded , a special report to the NRC , as well as an appropriate request for exemption/variance, is required to be submitted to the NRC. The requirement that the dose limits of 10CFR72.104 apply to any 'real individual' is controlled for ISFSI activities in the ISFSI 72 .212 report. Therefore, for the purposes of analyzing dose from the ISFSI, the member of the public as defined in 40CFR190 is the same as for the 'real individual'. The external Total Body Dose is comprised of:
- 1) Total Body Dose due to noble gas radionuclides in gaseous effluents
- 2) Dose due to radioactive waste and the ISFSI
- 3) Total Body Dose due to radioactivity deposited on the ground (this dose is accounted for in the determination of the non-noble gas dose and is not considered here)
(Req Reviews: Rad Review, ISR , RP)
86-46DE-4A34-97A4-01 F6B73ADF3B Page 143 of 237 CH-ODCM-0001 Reference Use Page 50 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Dose from onsite storage (such as the ISFSI) is given by: D,osf = max of: (TLD dose from indicator TLD i - average of all background TLDs)
- occupancy factor at TLD i Neutron dose is found by multiplying gamma dose by a neutron/gamma ratio determined from other site TLDs around the ISFSI.
The Total Body Dose , external is given by: D,ext = D,tb + D,osf WhereD,ext is the external dose D,tb is the total body dose D,osf is the dose from on-site storage The Total Dose is then given by: D,tot = D,ext + D,liq + D,nng Where D,tot is the total dose D,ext is the external dose D,liq is the dose from liquid effluents D,nng is the dose from non-noble gases Dose Limits Total Body, annual 25 mrem Thyroid , annual 75 mrem Other Organs, annual 25 mrem (Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 144 of 237 CH-ODCM-0001 Reference Use Page 51 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 6.3 Change Mechanism The Off-Site Dose Calculation Manual is the controlling document for all radioactive effluent releases . It is defined as a procedure under the guidance of QATR Section 5. It will be revised and reviewed by an Independent Safety Review (ISR) and approved by the Plant Manager in accordance with QATR Appendix E, E.1.2. All changes to the Off-Site Dose Calculation Manual will be forwarded to the Nuclear Regulatory Commission during the next reporting period for the Annual Radioactive Effluent Release Report in accordance with the requirements of QATR Appendix E, E.1 .2. 6.4 Meteorological Data The 5 year historical Average xtQ is utilized to determine the concentrations of radionuclides at the unrestricted area boundary. It is also the factor used in conjunction with the parameters and methodologies in Part II, of the Off-Site Dose Calculation Manual to determine unrestricted area dose on a quarterly bases or as needed . It is based on an average of the highest calculated sector xtO values , using all 16 sectors for previous multiple years Annual Radioactive Effluent Release Reports, and the XOQDOQ plume trajectory model. An additional 10 percent will be added to the average for unrestricted area dose estimates performed quarterly for conservatism. XOQDOQ model conforms with the Nuclear Regulatory Commissions Regulatory Guide 1.111 . Historical average meteorological data will be utilized in the preparation of the Annual Radioactive Effluent Release Report. Prior years of data is used to calculate the joint frequency table , the dispersion coefficients and deposition factors in all 16 sectors . These are used in the calculation of doses to individuals in unrestricted areas as a result of the operation of Fort Calhoun Station . The models used, GASPAR 2 and LADTAP 2, meet the intent of Nuclear Regulatory Commissions Reg . Guide 1.109 and 1.21 for the reporting of doses due to routine radioactive effluent releases. (Req Reviews: Rad Review, ISR, RP)
86-46DE-4A34-97A4-01 F6B73ADF3B Page 145 of 237 CH-ODCM-0001 Reference Use Page 52 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 6.5 References 6 .5.1 Regulatory Guide 1.109, Rev. 1 - Calculation of Annual Dose to man from Routine Releases of Reactor Effluents for the purpose of evaluation compliance with 10 CFR Part 50 , Appendix I 6.5 .2 Regulatory Guide 1.111, Rev. 1 - Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors. 6.5 .3 Regulatory Guide 1.113, Rev. 1 - Estimating Aquatic Dispersion of Effluents from Accidental and Routine Releases for the purpose of Implementing Appendix I. 6.5.4 NRC Branch Technical Position, March 1978 6 .5.5 NUREG-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants. 6 .5.6 NUREG-1301 - Offsite Dose Calculation Manual Guidance . 6.5 .7 Regulatory Guide 1.21, Rev. 2 - Measuring , Evaluating , and Reporting Radioactivity in solid wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants. 6.5.8 Code of Federal Regulations , Title 10, Part 20 6.5 .9 Code of Federal Regulations, Title 10, Part 50 6.5.10 Code of Federal Regulations, Title 10, Part 72 6.5.11 Code of Federal Regulations, Title 40 , Part 190 6.5 .12 Fort Calhoun Revised Environmental Report (Unit No. 1)-1972 6.5.13 NO-FC-10, Quality Assurance Topical Report 6.5.14 Defueled Safety Analysis Report 6.5 .15 AR 12357, Implement Recommendations of Memo FC-0133-92 , Part I, Table 3.2.1 Action 4, of the Off-Site Calculation Manual 6.5.16 AR 39127, NEI Industry Initiative on Groundwater Protection (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 146 of 237 CH-ODCM-0001 Reference Use Page 53 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 6.5.17 Regulatory Guide 4.1, Rev. 2 - Radiological Environmental Monitoring for Nuclear Power Plants 6.5.18 FC-19-001, ODCM rev 29 Change Support Document 6.5.19 FC-18-005, Habits of the Real Individual in Vicinity of Fort Calhoun Station , X/Q, Direct Radiation Dose Calculation 7.0 BASIS 7.1 Instrumentation 7.1.1 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 11 of the Offsite Dose Calculation Manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of DSAR-Appendix G Criterion 17 - Monitoring Radioactive Releases, Criterion 18 - Monitoring Fuel and Waste Storage, and Criterion 70 - Control of Release of Radioactivity to the Environment. 7.1 .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 gaseous effluents. 7.2 Radioactive Effluents 7.2.1 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 10 times 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 II.A design objectives of Appendix I, 10 CFR Part 50 , and (2) the limits of 10 CFR Part 20.1001-20.2401 to the population . (Req Reviews: Rad Review, ISR, RP)
DocuSig n Enve lope ID: EA65F1 86-46DE -4A34-97A4-01 F6B73ADF3B Page 147 of 237 CH-ODCM-0001 Reference Use Page 54 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 B. Dose This specification is provided to implement the requirements of Sections II.A, Ill.A and IV.A of Appendix I, 10 CFR Part 50 . The Limiting Condition for Operation implements the guides set forth in Section II.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 facility 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 Off-Site Dose Calculation Manual , implement the requirements in Section Ill.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 II of the Off-Site Dose Calculation Manual , 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 FUNCTIONALITY 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 A to 10 CFR Part 50 and design objective and in Section I1.D of Appendix I 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 II.A of Appendix I, 10 CFR Part 50 for liquid effluents are not exceeded . (Req Reviews: Rad Review, ISR, RP)
Do cuSign Enve lope ID: EA65F1 86-46DE -4A34-97A4-0 1 F6B73ADF3B Page 148 of 237 CH-ODCM-0001 Reference Use Page 55 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 D. Liquid Holdup Tanks Restricting the quantity of radioactive material contained in the specified 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 potable water supply and the nearest surface water supply in an unrestricted area. 7.2.2 Radioactive Gaseous Effluents A. Concentration This specification , in conjunction with Steps 4 .2.2A, is provided to ensure that the dose at or beyond the Site Boundary from gaseous 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 area boundary. (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 149 of 237 CH-ODCM-0001 Reference Use Page 56 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 B. Dose - 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 I1.C, Ill.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section I1.C 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 Ill.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 release rate specification for radioactive material in particulate form with half-lives greater than eight days (other than noble gases) and tritium are dependent 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. C. Gaseous Waste Treatment The FUNCTIONALITY of 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 A to 10 CFR Part 50 and design objective and in Section 11.D of Appendix I 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 I1.B and I1.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded . (Req Reviews: Rad Review, ISR, RP)
F6873ADF3B Page 150 of 237 CH-ODCM-0001 Reference Use Page 57 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 D. 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 Part 190 if the facility 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 or 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 the 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 compliance with the limits of 40 CFR Part 190 or with the design 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. (Req Reviews: Rad Review, ISR , RP)
DocuSign Enve lope ID : EA65F186-46DE-4A34-97A4-01 F6B 73ADF3B Page 151 of 237 CH-ODCM-0001 Reference Use Page 58 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 7.3 Radiological Environmental Monitoring 7.3.1 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 . 7.3.2 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 frequency of the Land Use Survey has been reduced to a biennial requirement in site procedures because persons knowledgeable in land use census monitor usage characteristics perform routine REMP sampling . This approach allows knowledge gained during sample collection to be integrated into the program , maintaining its effectiveness. 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/m 2 . 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. For groundwater, samples shall be taken when sources are determined to potentially be affected by facility operations , and when sources are tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. Guidance provided in the Branch Technical Position and QATR Appendix E, E.3.1.3 is used to meet the intent of NUREG-1301 . (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 152 of 237 CH-ODCM-0001 Reference Use Page 59 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 7.3.3 lnterlaboratory Comparison Program The requirement for participation in an lnterlaboratory 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. 7.4 Abnormal Release or Abnormal Discharge Reporting 7.4 .1 Specific information should be reported concerning abnormal (airborne and/or liquid) releases on site and abnormal discharges to the unrestricted area. The report should describe each event in a way that would enable the NRC to adequately understand how the material was released and if there was a discharge to the unrestricted area. The report should describe the potential impact on the ingestion exposure pathway involving surface water and ground water, as applicable. The report should also describe the impact (if any) on other affected exposure pathways (e.g., inhalation from pond evaporation). 7.4 .2 The following are the thresholds for reporting abnormal releases and abnormal discharges in the supplemental information section : A. Abnormal release or Abnormal Discharges that are voluntarily reported to local authorities under NEI 07-07, Industry Ground Water Protection Initiative. [AR 39127] B. Abnormal release or Abnormal discharges estimated to exceed 100 gallons of radioactive liquid where the presence of licensed radioactive material is positively identified (either in the on-site environs or in the source of the leak or spill) as greater than the minimum detectable activity for the laboratory instrumentation. C. Abnormal releases to on-site areas that result in detectable residual radioactivity after remediation. D. Abnormal releases that result in a high effluent radiation alarm without an anticipated trip occurring . E. Abnormal discharges to an unrestricted area . (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 153 of 237 CH-ODCM-0001 Reference Use Page 60 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 7.4.3 Information on Abnormal releases or Abnormal discharges should include the following, as applicable:
- Date and duration
- Location
- Volume
- Estimated activity of each radionuclide
- Effluent monitoring results (if any)
- On-site monitoring results (is any)
- Depth to the local water table
- Classification(s) of subsurface aquifer(s) (e.g., drinking water, unfit for drinking water, not used for drinking water)
- Size and extent of any ground water plume
- Expected movement/mobility of any ground water plume
- Land use characteristics (e.g., water used for irrigation)
- Remedial actions considered or taken and results obtained
- Calculated member of the public dose attributable to the release
- Calculated member of the public dose attributable to the discharge
- Actions taken to prevent recurrence, as applicable
- Whether the NRC was notified, the date(s), and the contact organization (Req Reviews: Rad Review, ISR, RP)
DocuSig n Envelope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 154 of 237 CH-ODCM-0001 Reference Use Page 61 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 PART II CALCULATIONS (Req Reviews: Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F1 86-46DE-4A34-97A4-01F6B 73ADF3B Page 155 of 237 CH-ODCM-0001 Reference Use Page 62 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents 1.1.1 There is one liquid discharge pathway to the Missouri River. This pathway empties into the circulating water system which discharges to the Missouri River (see Figure 1). 1.1.2 The flowrate for dilution water varies with the number dilution pumps in service 1.1.3 QATR Appendix E, E.2.1.3.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. 1.1.4 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. 1.1.5 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. 1.1.6 Cs-137 is used to calibrate the liquid effluent monitors. (Req Reviews : Rad Review, ISR, RP)
F6873ADF3B Page 156 of 237 CH-ODCM-0001 Reference Use Page 63 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 1.1.7 Liquid Effluent Radiation Monitor A. Overboard Discharge Header Monitor (RM-055)
- 1. This process radiation monitor provides control of the waste 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 1.0E-06 µCi/ml at site discharge for unidentified isotopes by the high alarm setpoint which closes the overboard flow control valve.
- 2. The following calculations for maximum concentration and alarm setpoints are valid for radioactive liquid releases of tank discharge.
- 3. The maximum allowable concentration in the overboard discharge header is:
(1.0E - 05 µCi/ml) (F) CMAX = f Where : 1.0E-05 µCi/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). f = Maximum tank discharge flow rate (gpm). CMAX = Maximum allowable activity in discharge header (µCi/ml) . (Req Reviews: Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01F6B73ADF3B Page 157 of 237 CH-ODCM-0001 Reference Use Page 64 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 1.1 .7A (continued) The High Alarm Setpoint (CPM) : Setpoint = 0.75 [((K3)(s1 )(CMAAJ) +s] Where: 0.75 = An administrative correction factor which includes the following: 25% tolerance to account for the difference in detector sensitivity for the range of isotopes detected . St = Detector sensitivity factor (CPM/µCi/ml) . (Sensitivity based on Cs-137) .
= Allocation factor for Waste Liquid Releases (1)
= Maximum allowable concentration in discharge header (µCi/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. (Req Reviews: Rad Review, ISR, RP)
F6873ADF3B Page 158 of 237 CH-ODCM-0001 Reference Use Page 65 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 1 .2 Airborne Effluents 1.2.1 There are multiple air effluent discharge pathways at the Fort Calhoun Station during decommissioning with three different mechanisms of release: Forced draft ventilation, Unventilated building release, and Open-air demolition.
- Forced draft ventilation uses portable filtered ventilation units with a fan with a rated cfm as the release rate. When portable ventilation systems are used, the air particulate sample head shall directly sample the airborne effluent discharge flowpath.
- Unventilated building releases in which the dimension of an open doorway coupled with windspeed blowing through the doorway are used to calculate the release rate. Unventilated building releases shall be monitored with a portable air sampler located outside of the doorway at any time the door is open, and active decommissioning that could generate airborne is in progress.
- Open-air demolition releases are rubble and building debris containing low level radioactive material may be wind-blown as a release. Other Open-air releases may include building demolition in which the structure of the building is demolished to the point where it becomes inaccurate to use doorway area as a release point each location shall be documented as they are established. Airborne effluent monitoring during Open-air demolition shall be accomplished by placing 4 air samplers in 4 general opposing directions around the area to be sampled, placed in areas that will not obstruct decommissioning activities around the area.
Table 1 - Deleted (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 159 of 237 CH-ODCM-0001 Reference Use Page 66 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Figure 1 - Exclusion and Site Boundary Map r**---- I l I I I I
\
CD LIQIJID EF'FLUEN TS DIS'OHAftGE* AIRBORNE EFFLUEN'I'B DISCHARGE TO OM.AHA 0 1 I SCALE IN :MJLES SITE BOUNDARY MAP 0:RAWING FILE NO. (Req Reviews: Rad Review, ISR, RP)
Do cuSign Envelope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 160 of 237 CH-ODCM-0001 Reference Use Page 67 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Figure 2 - Deleted Figure 3 - Deleted Figure 4 - Airborne Effluent Discharge Pathways
- - - - -- 8d FORCED DRAFT AIR SAMPLER WITH EXHAUST TRUNK DISCHARGE FORCED DRAFT AIR SAMPLER WITH OUTLET PLENUM (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 161 of 237 CH-ODCM-0001 Reference Use Page 68 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Figure 4 - Airborne Effluent Discharge Pathways (continued)
,1 f, '
I
'I
_ _____, ___ ~----~- --~- -------------------------- ----+---+---+--------- I ~., , UNVENTILATED BUILDING RELEASE AIR SAMPLERS w OPEN-AIR DEMOLITION AIR SAMPLERS Figure 5 - Deleted I (Req Reviews : Rad Review, ISR, RP)
86-46DE-4A34-97A4-01 F6B73ADF3B Page 162 of 237 CH-ODCM-0001 Reference Use Page 69 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 2.0 EFFLUENT CONCENTRATIONS 2.1 Liquid Effluent Concentrations 2.1.1 The concentration of radioactive material in liquid effluents, after dilution , will be limited to the concentrations as specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. For liquid releases the analyses will be performed in accordance with Part I, Table 4.1, of the Off-Site Dose Calculation Manual, and the concentration of each radionuclide at site discharge will be calculated , based on the following equation: aJ A*=-- i F+ f n A-and L i= l _i_:::; 1 wee
- l Radionuclide concentration at site discharge:
Where: Ai = concentration at site discharge for radionuclide (I), in µCi/ml. ai = concentration of radionuclide (I) in the undiluted effluent, in µCi/ml. f = undiluted effluent flowrate , in gpm . F = total diluted effluent flowrate in gpm. weci = water effluent concentration limit for radionuclide (I) per 10 CFR Part 20 , Appendix B, Table 2, Column 2. NOTE I In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable. I 2.2 Airborne Effluent Concentrations 2.2.1 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 . 2.2 .2 To determine the concentration and air effluent concentration (aec) fraction summation at the unrestricted area boundary, the following equations will be used : (Req Reviews: Rad Review, ISR, RP )
F6B73ADF3B Page 163 of 237 CH-ODCM-0001 Reference Use Page 70 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 f A-and LEC~ - $1 i=l t Where : Ai = Concentration of radionuclide (I) at the unrestricted area boundary Ko = Constant of unit conversion. (1 .0E-6 m3/cc) ECL = Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, Column 1 value for radionuclide(!)) Oi = The release rate of radionuclide (I) in airborne effluents from all vent releases (in µCi/sec.) (x/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from Part 11 , Table 4, of the Off-Site Dose Calculation Manual. 2.2.3 As appropriate, simultaneous releases from all release pathways will be considered in evaluating compliance with the release rate limits of 10 CFR Part 20. Historical annual average dispersion parameters , as presented in Table 4, may be used for evaluating the airborne effluent dose rate. (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 164 of 237 CH-ODCM-0001 Reference Use Page 71 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS 3.1 Liquid Effluent Dose Calculations 3.1.1 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 facility 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. 3.1 .2 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.
(Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 165 of 237 CH-ODCM-0001 Reference Use Page 72 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.1.3 Doses from Liquid Effluent Pathways A. Potable Water Where: Rapj = is the total annual dose to organU) 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 Uyr. (Table 6) Mp = 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 ft 3/ sec. Oi = 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 U) which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) Ai = is the radiological decay constant of radionuclide (1), in hr 1 . 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* ft 3/Ci
- sec
- L)
(Req Reviews: Rad Review, ISR, RP)
OocuSign Enve lope ID: EA65F1 86-46DE-4A34-97A4-01 F6B 73ADF3B Page 166 of 237 CH-ODCM-0001 Reference Use Page 73 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.1.3 (continued) B. Aquatic Foods Where : Rapj = is the total annual dose to organ U) 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) Mp = 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 ft 3/sec . Oi = is the annual release rate of radionuclide (I) , in Ci/yr. Sip = 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) Daipi = is the dose factor specific to a given age group (a) , radionuclide (I) , pathway (p) , and organ U) , which can be used to calculate the radiation dose from an intake of a radionuclide , in mrem/pCi. (Tables 13-16) Ai = is the radiological decay constant of radionuclide (I), in hr- 1 . 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 food , in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft 3/Ci
- sec
- L)
(Req Reviews: Rad Review, ISR, RP )
Doc uSign Enve lope ID: EA65F186-46DE -4A34-97A4-01 F6B 73ADF3 B Page 167 of 237 CH-ODCM-0001 Reference Use Page 74 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.1 .3 (continued) C. Shoreline Deposits Where: Rapj = is the total annual dose to organ U) 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) Mp = 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 ft 3/sec. Oi = is the annual release rate of radionuclide (I) , in Ci/yr. Tip = 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/m 2) . (Table 8) Ai = is the radiological decay constant of radionuclide (I), in h,1 . 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
- ft 3 )/(Ci
- sec
- L)]
(Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 168 of 237 CH-ODCM-0001 Reference Use Page 75 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.2 Airborne Effluent Dose Calculations 3.2.1 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:
(Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 169 of 237 CH-ODCM-0001 Reference Use Page 76 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 NOTE I In all cases , for releases of tritium , use the dispersion parameter for inhalation (x/Q) . I 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 8, with respect to the release point, may be determined by: Where :
= is the ground plane concentration of the radionuclide (I) at distance r, in the sector at angle 8, from the release point, in pCi/m 2 .
= 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 20 years (mid-point of plant operating life). (Table 17)
Oi(r,8) = is the annual average relative deposition of radionuclide (I) at distance r, in the sector at angle 8, considering depletion of the plume by deposition during transport, in m-2. Table 4
= is the radiological decay constant for radionuclide (1), in yr-1 .
1.0x10 12 = is the number of pCi/Ci (Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 170 of 237 CH-ODCM-0001 Reference Use Page 77 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 The annual organ dose is then calculated using the following equation: n DP (r, 0) = 8760 s1 L cp (r, 0)DFGij i=l Where : Ci(r,8) = is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle 8, in pCi/m 2 . DFGii = is the open field ground plane dose conversion factor for organ U) from radionuclide (i), in mrem-m 2/pCi-hr. (Table 8) Di(r,8) = is the annual dose to the organ U) at distance r, in the sector at angle 8, in mrem/yr. St = 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 8, with respect to the release point, may be determined as:
xi (r, 0) = 3.17 x 10 4 Qi [x / Q]D (r, 0) Where:
= is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
Xi(r,8) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle 8, in pCi/m 3 .
= is the annual average atmosphere dispersion factor, in sec/m 3 (see Reg Guide 1.111 ). This includes depletion (for radioiodines and particulates) and radiological decay of the plume. (Table 4) 3.17x104 = is the number of pCi/Ci divided by the number of sec/yr.
(Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 171 of 237 CH-ODCM-0001 Reference Use Page 78 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 The annual dose associated with inhalation of all radionuclides to organ U) of an individual in age group (a) , is then : n Dj! (r, 0) = Ra L xi (r, 8)DFA ij a i=l Where: D'ia(r,8) = is the annual dose to organ U) of an individual in the age group (a) at distance r, in the sector at angle 8, due to inhalation, in mrem/yr. Ra = is the annual air intake for individuals in the age group (a), in m 3/yr. (Table 6) Xi(r,8) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle 8, in pCi/m 3 . DFAija = is the inhalation dose factor for radionuclide (i), organ U), and age group (a), in mrem/pCi . (Tables 9-12) (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 172 of 237 CH-ODCM-0001 Reference Use Page 79 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.2.2 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases A. Parameters for Calculating Concentrations in Forage, Produce , and Leafy Vegetables , excluding Tritium r[l - exp(-;\, *t )] B* [1 - exp(-kt ))) C.V ( r, 0 ) = d i* (r, 0 ) Y, A . EL e + iv p A. L b exp ( - lli. t h ) 1 i [ V EL L Where: CY(r,8) = is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle 8, in pCi/kg . di(r,8) = is the deposition rate of radionuclide (i) at distance r, in the sector at angle 8 , in pCi/m 2 hr. r = is the fraction of deposited activity retained on crops , dimensionless. (Table 17)
= is the effective removal rate constant for radionuclide (i) from crops, in hr-1.
AEi = Ai + Aw Aw= 0.0021 /hr. (Table 17) te = is the time period that crops are exposed to contamination during the growing season , in hours . (Table 17) Yv = is the agricultural productivity (yield) in kg (wet weight)/m2 . (Table 17)
= 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)
= is the radiological decay constant of radionuclide (1), in hr-1
= 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)
= 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 , Yv, 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. (Req Reviews: Rad Review, ISR, RP)
F6873ADF38 Page 173 of 237 CH-ODCM-0001 Reference Use Page 80 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa . C-6): Where: di(r,8) = is the deposition rate of radionuclide (i). Oi(r,8) = 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 (10 12 ) divided by the number of hours per year (8760).
= is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
(Req Reviews: Rad Review, ISR, RP)
86-46DE-4A34-97A4-01 F6B73ADF3B Page 174 of 237 CH-ODCM-0001 Reference Use Page 81 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 B. For radioiodines , the model considers only the elemental fraction of the effluent: Where: d1(r, 8) = 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). Oi (r, 8) = The relative deposition of radioiodine (i), considering depletion and decay, in m-2 . (Table 4)
= The total (elemental and nonelemental) radioiodine (i) emission rate.
C. Parameters for Calculating the Concentration of Radionuclide (i) in the Animal's Feed (Milk Cow, Beef Cow, and Goat) er (r, 0) = [pfs er (r, 0) + ( 1 - [p)et (r, 0) + [p (1- fs)ef (r, 0) Where: CY(r,8) = is the concentration of radionuclide (i) in the animal's feed , in pCi/kg. C~(r,8) = is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2 .3A with th=0), in pCi/kg . C9(r,8) = is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3A with th=90 days), in pCi/kg.
= is the fraction of the year that animals graze on pasture. (Table 17) fs = is the fraction of daily feed that is pasture grass while the animal grazes on pasture. (Table 17)
(Req Reviews: Rad Review, ISR, RP)
86-46DE-4A34-97A4-01 F6B73ADF3B Page 175 of 237 CH-ODCM-0001 Reference Use Page 82 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.2.3 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk Where: C~ (r,8) = is the concentration of radionuclide (i) in milk, in pCi/liter. CY (r,8) = 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) OF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) tt = 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) Ai = is the radiological decay constant of radionuclide (i) , in days-1 . (Req Reviews: Rad Review, ISR, RP )
F6B73ADF3B Page 176 of 237 CH-ODCM-0001 Reference Use Page 83 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium Where: C~ (r,8) = is the concentration of radionuclide (i) in meat, in pCi/liter. CY (r,8) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. OF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) Ft = 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) ts = is the average time from slaughter to consumption. (Table 17) 3.2.5 Parameters for Calculating Tritium Concentrations in Vegetation The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation. Cl (r,0) = 3.17 X 10 7 Qy (x/Q](r,B~O.?S)(O.S) = 1.2 X 10 7 Qy [x/Qt(r,B) Where: C'f(r, 8) = is the concentration of tritium in vegetation grown at distance r, in the sector at angle 8, in pCi/kg. H = is the absolute humidity of the atmosphere at distance r, in the sector at angle 8, in g/m 3 . H=8 gm/kg . Qr = is the annual release rate of tritium, in Ci/yr. [x/Q](r,8) = is the atmospheric dispersion factor, in sec/m 3 . (Table 4) 0.5 = is the ratio of tritium concentration in facility water to tritium concentration in atmospheric water, dimensionless. 0.75 = is the fraction of total facility mass that is water, dimensionless. (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 177 of 237 CH-ODCM-0001 Reference Use Page 84 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 3 .2.6 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ U) of an individual in age group (a) resulting from ingestion of all radionuclides in produce , milk, and leafy vegetables is given by: Where: D9a(r,8) = is the annual dose to organ U) of an individual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem/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. U~ = are the ingestion rates of produce (non-leafy vegetables, fruits, and grains) , respectively for individuals in age group (a). (Table 6) urvii = is the ingestion rate of cow milk for individuals in age group (a), in P/yr. (Table 6) U~ = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6) U~ = are the ingestion rates of leafy vegetables for individuals in age group (a) , in kg/yr. (Table 6) CY (r,8) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. C~ (r,8) = is the concentration of radionuclide (i) in milk, in pCi/liter. C~ (r,8) = is the concentration of radionuclide (i) in meat, in pCi/liter. C~ (r,8) = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg. f9 = Fraction of ingested produce grown in garden of interest (Table 17) ft = Fraction of leafy vegetables grown in garden of interest (Table 17) (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 178 of 237 CH-ODCM-0001 Reference Use Page 85 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce) Vegetation for Radionuclide (i) to Each Organ U) and Age Group (a) Dfa (r, 0) = DFlja [U~ ft Cf (r, 0) + ui [9 er (r, 0)] Where: D9a(r,8) = is the annual dose from the ingestion of radionuclide (i) to organ U) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in vegetation, in mrem/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 U~ ,U\{i = 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) c~ = is the concentration of radionuclide (i) in and on leafy vegetation , in pCi/kg . C'i = is the concentration of radionuclide (i) in and on produce, in pCi/kg. fg = Fraction of ingested produce grown in garden of interest (Table 17) ft = Fraction of leafy vegetables grown in garden of interest (Table 17) (Req Reviews: Rad Review, ISR, RP)
Doc uSign Envelope ID: EA65F1 86-46DE-4A34-97A4-01 F6B73ADF3B Page 179 of 237 CH-ODCM-0001 Reference Use Page 86 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 C . Calculation Determining the Ingested Dose from Cow Milk for Radionuclide (i), Organ U), and Age Group (a) Where : D9a(r,8) = is the annual dose from the ingestion of radionuclide (i), organ U) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in cow milk, in mrem/yr. DFliia = is the dose conversion factor for the ingestion of radionuclide (i), organ U), and age group (a), in mrem/pCi. (Tables 13-16) U~ = is the ingestion rate of cow milk for individuals in age group (a), in P/yr. (Table 6) C~ = 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 U) and Age Group (a) Dfa (r, 0) = DFiija [Ut C{ (r, 0)] Where: D9a(r,8) = is the annual dose from the ingestion of radionuclide (i) , organ U) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in meat, in mrem/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) U~ = is the ingestion rate of meat for individuals in age group (a) , in kg/yr. (Table 6) C~ = is the radionuclide (i) concentration in meat, in pCi/kg. (Req Reviews : Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F68 73ADF38 Page 180 of 237 CH-ODCM-0001 Reference Use Page 87 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 4.0 LOWER LIMIT OF DETECTION (LLD) 4.1 The lower limit of detection (LLD) for liquid and airborne effluent discharges and environmental samples referenced in Part I, Tables 4.1, 4.2 and 5.3 , of the Off-Site Dose Calculation Manual, 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. 4.2 For a particular measurement system, which may include radiochemical separation: 4.66
- Sb LLD= - - - - - - - -
£
- V
- D
- Y
- exp(-tlL\t)
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 Llt = the elapsed time between the midpoint of sample collection and time of counting Appropriate values of E, V, Y, and lH should be used in the calculation .
4.3 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. 4.4 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 . (Req Reviews : Rad Review, ISR, RP)
Doc uSign Envelo pe ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 181 of 237 CH-ODCM-0001 Reference Use Page 88 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 2.- Deleted Table 3 - Bioaccumulation Factors (pCi/kg per pCi/liter) FRESHWATER Element Fish Invertebrate H 9.0E-01 9.0E-01 C 4.6E+03 9.1E+03 Na 1.0E+02 2.0E+02 p 1.0E+05 2.0E+04 Cr 2.0E+02 2.0E+03 Mn 4.0E+02 9.0E+04 Fe 1.0E+02 3.2E+03 Co 5.0E+01 2.0E+02 Ni 1.0E+02 1.0E+02 Cu 5.0E+01 4.0E+02 Zn 2.0E+03 1.0E+04 Br 4.2E+02 3.3E+02 Rb 2.0E+03 1.0E+03 Sr 3.0E+01 1.0E+02 y 2.5E+01 1.0E+03 Zr 3.3E+00 6.7E+00 Nb 3.0E+04 1.0E+02 Mo 1.0E+01 1.0E+01 Tc 1.5E+01 5.0E+00 Ru 1.0E+01 3.0E+02 Rh 1.0E+01 3.0E+02 Te 4 .0E+02 6.1E+03 I 1.5E+01 5.0E+00 Cs 2.0E+03 1.0E+03 Ba 4.0E+00 2.0E+02 La 2.5E+01 1.0E+03 Ce 1.0E+00 1.0E+03 Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E+03 w 1.2E+03 1.0E+01 Np 1.0E+01 4.0E+02 (Req Reviews: Rad Review, ISR, RP)
Page 182 of 237 CH-ODCM-0001 Reference Use Page 89 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 4 - Highest Potential Exposure Pathways for Estimating Dose Distance D/QA X/Q A Exposure 8 8 from Location Direction {x/Q (r,8)} {ij (r,8)} Pathway Containment (m-2) (sec/m 3 ) (miles) 8 Direct Exposure Site ESE 0.29 6.30E-05 N/A Boundary Inhalation Site ESE 0.29 6.30E-05 N/A Boundary Ingestion Residence NNW 0.29 N/A 2.30E-07 A. These values are used for calculating quarterly dose estimates during the annual reporting period and are based on a 5 year historical average. Ten percent (10%) will be added to these values for dose estimates during the reporting periods . These values are periodically re-evaluated by comparing the X/Q values reported by NOAA in similar locations. B. 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 7.3.2, of the Off-Site Dose Calculation Manual. (Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 183 of 237 CH-ODCM-0001 Reference Use Page 90 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 5 - Stable Element Transfer Data Biv Fm(cow) Fm (goat) Ft Element Veg./Soil Milk (d/1) Milk (d/1) Meat (d/kg) H 4.8E+00 1.0E-02 1.?E-01 1.2E-02 C 5.5E+00 1.2E-02 1.0E-01 3.1E-02 Na 5.2E-02 4.0E-02 ------ 3.0E-02 p 1.1E+00 2.5E-02 2.5E-01 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 1.3E-04 4.0E-02 Co 9.4E-03 1.0E-03 ------ 1.3E-02 Ni 1.9E-02 6.?E-03 ------ 5.3E-02 Cu 1.2E-01 1.4E-02 1.3E-02 8.0E-03 Zn 4.0E-01 3.9E-02 ------ 3.0E-02 Rb 1.3E-01 3.0E-02 ------ 3.1E-02 Sr 1.?E-02 8.0E-04 1.4E-02 6.0E-04 y 2.6E-03 1.0E-05 ------ 4.6E-03 Zr 1.?E-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 ------ 4.0E-01 Ru 5.0E-02 1.0E-06 ------ 4.0E-01 Rh 1.3E+1 1.0E-02 ------ 1.5E-03 Ag 1.5E-01 5.0E-02 ------ 1.?E-02 Sb 1.1E-02 1.5E-03 ------ 4.0E-03 Te 1.3E+00 1.0E-03 ------ 7.?E-02 I 2.0E-02 6.0E-03 6.0E-02 2.9E-03 Cs 1.0E-02 1.2E-02 3.0E-01 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 1.0E-04 ------ 1.2E-03 Pr 2.5E-03 5.0E-06 ------ 4.?E-03 Nd 2.4E-03 5.0E-06 ------ 3.3E-03 w 1.8E-02 5.0E-04 ------ 1.3E-03 Pu 2.5E-04 2.0E-06 ------ 1.4E-05 Np 2.5E-03 5.0E-06 ------ 2.0E-04 Am 2.5E-04 5.0E-06 ------ 2.0E-04 Cm 2.5E-03 5.0E-06 ------ 2.0E-04 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 184 of 237 CH-ODCM-0001 Reference Use Page 91 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 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 (P/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 (P/yr) 330 510 510 730 Shoreline recreation (hr/yr) --- 14 67 12 3 Inhalation (m /yr) 1400 3700 8000 8000 Table 7 - Animal Consumption Rates Animal QF Feed or Forage [Kg/day (wet weigh)] QAw Water (f/day) Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8 (Req Reviews: Rad Review, ISR, RP)
OocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 185 of 237 CH-ODCM-0001 Reference Use Page 92 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m 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.S0E-09 6.S0E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 --- --- Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.?0E-08 2.00E-08 Ni-59 --- --- Ni-63 --- --- Nr-65 3.?0E-09 4.30E-09 Cu-64 1.50E-09 1.?0E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 --- --- Br-83 6.40E-11 9.30E-11 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.S0E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.S0E-09 4.40E-09 Y-91 2.40E-11 2.?0E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.?0E-10 7.S0E-10 Zr-95 5.00E-09 5.S0E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 (Req Reviews: Rad Review, ISR, RP)
F6B 73ADF3B Page 186 of 237 CH-ODCM-0001 Reference Use Page 93 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m 2 ) Element Total Body Skin Tc-101 2.?0E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Sb-124 1.30E-08 1.50E-08 Sb-125 3.10E-09 3.50E-09 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.?0E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.?0E-09 2.00E-09 1-130 1.40E-08 1.?0E-08 1-131 2.80E-09 3.40E-09 1-132 1.?0E-08 2.00E-08 1-133 3.?0E-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-136 1.50E-08 1.?0E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.?0E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.?0E-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.?0E-10 Pr-143 --- --- Pr-144 2.00E-10 2.30E-10 (Req Reviews: Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 187 of 237 CH-ODCM-0001 Reference Use Page 94 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m 2 ) Element Total Body Skin Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Pu-238 1.30E-12 1.80E-11 Pu-239 7.90E-13 7.70E-12 Pu-240 1.30E-12 1.80E-11 Pu-241 4.60E-12 6.80E-12 Np-239 9.50E-10 1.10E-09 Am-241 1.80E-10 2.60E-10 Cm-242 5.50E-12 2.30E-11 Cm-243 2.30E-09 2.90E-09 Cm-244 2.90E-12 1.80E-11 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 188 of 237 CH-ODCM-0001 Reference Use Page 95 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled) 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 3.0?E-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-59 4.06E-06 1.46E-06 6.77E-07 --- --- 8.20E-06 6.11E-07 Ni-63 5.40E-05 3.93E-06 1.81 E-06 --- --- 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 --- --- 7.00E-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-91M 3.26E-11 --- 1.27E-12 --- --- 2.40E-07 1.66E-10 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-97 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 3.10E-05 (Req Reviews: Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 189 of 237 CH-ODCM-0001 Reference Use Page 96 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 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-105 9.88E-11 --- 3.89E-11 --- 1.27E-10 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 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 --- 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 --- 2.18E-04 1.26E-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-129M 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 4.0?E-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-134 4.66E-05 1.06E-04 9.10E-05 --- 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 --- 1.0?E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 --- 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 --- 6.00E-08 6.0?E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 --- 7.78E-14 4.?0E-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 2.0?E-13 --- 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 --- --- 1.?0E-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.?0E-07 3.51 E-05 2.50E-05 (Req Reviews: Rad Review, ISR, RP)
DocuSign Enve lope ID: EA65F186-46DE -4A34-97A4-01 F6B73ADF3B Page 190 of 237 CH-ODCM-0001 Reference Use Page 97 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Pr-144 3.76E-12 1.56E-12 1.91E-13 --- 8.81E-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 3.10E-10 --- --- 3.63E-06 1.94E-05 Pu-238 1.43E+00 9.71E-01 6.90E-02 --- 2.96E-01 1.82E-01 4.52E-05 Pu-239 1.66E+00 1.07E+00 7.75E-02 --- 3.30E-01 1.72E-01 4.13E-05 Pu-240 1.65E+00 1.07E+00 7.73E-02 --- 3.29E-01 1.72E-01 4.21 E-05 Pu-241 3.42E-02 8.69E-03 1.29E-03 --- 5.93E-03 1.52E-04 8.65E-07 Np-239 2.87E-08 2.54E-08 1.55E-09 --- 8.75E-09 4.70E-06 1.49E-05 Am-241 1.68E+00 1.13E+00 6.71 E-02 --- 5.04E-01 6.06E-02 4.60E-05 Cm-242 2.22E-02 1.77E-02 9.84E-04 --- 4.48E-03 3.92E-02 4.91 E-05 Cm-243 1.10E+00 7.61 E-01 4.61 E-02 --- 2.15E-01 6.31 E-02 4.84E-05 Cm-244 8.37E-01 5.88E-01 3.51 E-02 --- 1.64E-01 6.06E-02 4.68E-05 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 191 of 237 CH-ODCM-0001 Reference Use Page 98 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) 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 6.09E-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-59 5.44E-06 2.02E-06 9.24E-07 --- --- 1.41 E-05 6.48E-07 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 --- --- 1.17E-06 4.59E-06 Cu-64 --- 2.54E-10 1.06E-10 --- 8.01E-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 1.10E-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 --- 1.00E-08 --- --- 3.66E-05 6.99E-05 Y-91M 4.63E- 11 --- 1.77E-12 --- --- 4.00E-07 3.77E-09 Y-91 8.26E-05 --- 2.21 E-06 --- --- 3.67E-04 5.11 E-05 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 --- 2.11E-08 4.03E-09 --- 5.14E-08 1.92E-05 3.36E-05 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 192 of 237 CH-ODCM-0001 Reference Use Page 99 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 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-11 OM 1.73E-06 1.64E-06 9.99E-07 --- 3.13E-06 8.44E-04 3.41 E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 --- 4.81 E-04 4.98E-05 Sb-125 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 --- 3.42E-04 1.24E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 --- 6.?0E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.0?E-04 1.99E-05 Te-127 2.51 E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01 E-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-132 4.50E-08 3.63E-08 2.74E-08 3.0?E-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 --- 8.11 E-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-134 6.28E-05 1.41 E-04 6.86E-05 --- 4.69E-05 1.83E-05 1.22E-06 Cs-136 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 1.0?E-07 5.58E-08 --- 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 --- 1.11 E-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-14 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-140 5.99E-08 2.95E-08 7.82E-09 --- --- 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-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.?0E-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 (Req Reviews : Rad Review, ISR, RP)
F6B73ADF3B Page 193 of 237 CH-ODCM-0001 Reference Use Page 100 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 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 1.0?E-06 6.41 E-08 --- 6.28E-07 4.65E-05 2.28E-05 W-187 1.S0E-09 1.22E-09 4.29E-10 --- --- 5.92E-06 2.21 E-05 Pu-238 1.50E+00 1 .03E+00 7.22E-02 --- 3.10E-01 3.12E-01 4.79E-05 Pu-239 1.73E+00 1.12E+00 8.0SE-02 --- 3.44E-01 2.93E-01 4.37E-05 Pu-240 1.72E+00 1.12E+00 8.04E-02 --- 3.43E-01 2.93E-01 4.46E-05 Pu-241 3.74E-02 9.56E-03 1.40E-03 --- 6.47E-03 2.60E-04 9.17E-07 Np-239 4.23E-08 3.60E-08 2.21 E-09 --- 1.25E-08 8.11 E-06 1.65E-05 Am-241 1.77E+00 1.20E+00 7.10E-02 --- 5.32E-01 1.0SE-01 4.88E-05 Cm-242 3.17E-02 2.51 E-02 1.41 E-03 --- 6.40E-03 6.76E-02 5.21 E-05 Cm-243 1.19E+00 8.30E-01 5.00E-02 --- 2.34E-01 1.09E-01 5.13E-05 Cm-244 9.19E-01 6.53E-01 3.88E-02 --- 1.81E-01 1.0SE-01 4.96E-05 (Req Reviews: Rad Review, ISR, RP)
Do cuSign Enve lope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 194 of 237 CH-ODCM-0001 Reference Use Page 101 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) 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 2.10E-06 --- --- 3.00E-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-59 1.66E-05 4.67E-06 2.83E-06 --- --- 2.73E-05 6.29E-07 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 1.81E-11 2.61E-11 2.41E-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 --- --- 7.10E-04 4.97E-05 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 1.00E-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 1.00E-05 Mo-99 --- 4.66E-08 1.15E-08 --- 1.06E-07 3.66E-05 3.42E-05 (Req Reviews: Rad Review, ISR, RP)
Do cuSign Envelope ID: EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 195 of 237 CH-ODCM-0001 Reference Use Page 102 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Tc-99M 4.81 E-13 9.41E-13 1.56E-11 --- 1.37E-11 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-110M 4.56E-06 3.08E-06 2.47E-06 --- 5.74E-06 1.48E-03 2.71 E-05 Sb-124 1.55E-05 2.00E-07 5.41 E-06 3.41 E-08 --- 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 --- 6.27E-04 1.09E-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 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71E-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-11 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 1.10E-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-138 1.71 E-07 2.27E-07 1.50E-07 --- 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 --- 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-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 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 --- --- 4.94E-05 6.10E-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 (Req Reviews: Rad Review, ISR, RP)
OocuSign Envelope ID: EA65F186-46DE-4A34-97A4-01 F6B73AOF3B Page 196 of 237 CH-ODCM-0001 Reference Use Page 103 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Pr-144 1.61E-11 4 .99E-12 8.10E-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 --- --- 1.11 E-05 2.46E-05 Pu-238 2.55E+00 1.60E+00 1.21 E-01 --- 4.47E-01 6.0BE-01 4.65E-05 Pu-239 2.79E+00 1.68E+00 1.28E-01 --- 4 .78E-01 5.72E-01 4.24E-05 Pu-240 2.79E+00 1.68E+00 1.27E-01 --- 4 .77E-01 5.71E-01 4 .33E-05 Pu-241 7.94E-02 1.75E-02 2.93E-03 --- 1.10E-02 5.06E-04 8.90E-07 Np-239 1.26E-07 8.14E-08 6.35E-09 --- 2.63E-08 1.57E-05 1.73E-05 Am-241 2.97E+00 1.84E+00 1.24E-01 --- 7.63E-01 2.02E-01 4.73E-05 Cm-242 9.48E-02 5.68E-02 4.20E-03 --- 1.34E-02 1.31E-01 5.06E-05 Cm-243 2.32E+00 1.42E+00 9.95E-02 --- 3.74E-01 2.10E-01 4.98E-05 Cm-244 1.94E+00 1.18E+00 8.31 E-02 --- 3.06E-01 2.02E-01 4.82E-05 (Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 197 of 237 CH-ODCM-0001 Reference Use Page 104 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled) 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 --- 1.10E-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-59 1.81 E-05 5.44E-06 3.10E-06 --- --- 5.48E-05 6.34E-07 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 1.0?E-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 6.91E-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 1.00E-04 Y-90 2.35E-06 --- 6.30E-08 --- --- 1.92E-04 7.43E-05 Y-91M 2.91 E-10 --- 9.90E-12 --- --- 1.99E-06 1.68E-06 Y-91 4.20E-04 --- 1.12E-05 --- --- 1.75E-03 5.02E-05 Y-92 1.17E-08 --- 3.29E-10 --- --- 1.75E-05 9.04E-05 Y-93 1.0?E-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 1.00E-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 (Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 198 of 237 CH-ODCM -0001 Reference Use Page 105 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Tc-99M 9.98E-13 2.06E-12 2.66E-11 --- 2.22E-11 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-103 1.44E-06 --- 4.85E-07 --- 3.03E-06 3.94E-04 1.15E-05 Ru-105 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-110M 7.13E-06 5.16E-06 3.57E-06 --- 7.80E-06 2.62E-03 2.36E-05 Sb-124 2.71 E-05 3.97E-07 8.56E-06 7.18E-08 --- 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41 E-07 7.78E-06 4.45E-08 --- 1.17E-03 1.05E-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-131M 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-132 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 4.00E-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-134 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-138 3.61 E-07 5.58E-07 2.84E-07 --- 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 --- 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 --- 9.59E-09 1.14E-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 1.11 E-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 1.00E-05 3.74E-06 4.99E-07 --- 1.41 E-06 3.09E-04 2.66E-05 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 199 of 237 CH-ODCM-0001 Reference Use Page 106 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Pr-144 3.42E-11 1.32E-11 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 Pu-238 2.69E+00 1.68E+00 1.27E-01 --- 4.64E-01 9.03E-01 4.69E-05 Pu-239 2.93E+00 1.76E+00 1.34E-01 --- 4.95E-01 8.47E-01 4.28E-05 Pu-240 2.93E+00 1.75E+00 1.34E-01 --- 4.94E-01 8.47E-01 4.36E-05 Pu-241 8.43E-02 1.85E-02 3.11E-03 --- 1.15E-02 7.62E-04 8.97E-07 Np-239 2.65E-07 2.13E-07 1.34E-08 --- 4.73E-08 4.25E-05 1.78E-05 Am-241 3.15E+00 1.95E+00 1.31 E-01 --- 7.94E-01 4.06E-01 4.78E-05 Cm-242 1.28E-01 8.65E-02 5.70E-03 --- 1.69E-02 2.97E-01 5.10E-05 Cm-243 2.47E+00 1.52E+00 1.06E-01 --- 3.91 E-01 4.24E-01 5.02E-05 CM-244 2.07E+00 1.27E+00 8.89E-02 --- 3.21 E-01 4.08E-01 4.86E-05 (Req Reviews: Rad Review, ISR, RP)
DocuSign Envelope ID : EA65F186-46DE -4A34-97A4-01 F6B73ADF3B Page 200 of 237 CH-ODCM-0001 Reference Use Page 107 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) 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-59 9.76E-06 3.35E-06 1.63E-06 --- --- --- 6.90E-07 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 3.91 E-08 --- 2.10E-07 --- 7.10E-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-91M 9.09E- 11 --- 3.52E-12 --- --- --- 2.67E-10 Y-91 1.41 E-07 --- 3.77E-09 --- --- --- 7.76E-05 Y-92 8.45E-10 --- 2.47E-11 --- --- --- 1.48E-05 Y-93 2.68E-09 --- 7.40E-11 --- --- --- 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 --- 2.10E-05 Mo-99 --- 4.31 E-06 8.20E-07 --- 9.76E-06 --- 9.99E-06 (Req Reviews : Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 201 of 237 CH-ODCM-0001 Reference Use Page 108 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 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 1.10E-21 Ru-103 1.85E-07 --- 7.97E-08 --- 7.06E-07 --- 2.16E-05 Ru-105 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-11 OM 1.60E-07 1.48E-07 8.79E-08 --- 2.91 E-07 --- 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11 E-06 6.79E-09 --- 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 --- 1.38E-06 1.97E-05 Te-125M 2.68E-06 9.71E-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 1.10E-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-131 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 1.90E-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 Ba-139 9.70E-08 6.91E-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 3.00E-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 (Req Reviews: Rad Review, ISR, RP)
-4A34-97A4-01 F6B73ADF3B Page 202 of 237 CH-ODCM-0001 Reference Use Page 109 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Pr-144 3.01E-11 1.25E-11 1.53E-12 --- 7.05E-12 --- 4.33E-18 Nd-147 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 Pu-238 6.30E-04 7.98E-05 1.71E-05 --- 7.32E-05 --- 7.30E-05 Pu-239 7.25E-04 8.71 E-05 1.91 E-05 --- 8.11 E-05 --- 6.66E-05 Pu-240 7.24E-04 8.70E-05 1.91 E-05 --- 8.10E-05 --- 6.78E-05 Pu-241 1.57E-05 7.45E-07 3.32E-07 --- 1.53E-06 --- 1.40E-06 Np-239 1.19E-09 1.17E-10 6.45E-11 --- 3.65E-10 --- 2.40E-05 Am-241 7.55E-04 7.05E-04 5.41 E-05 --- 4.07E-04 --- 7.42E-05 Cm-242 2.06E-05 2.19E-05 1.37E-06 --- 6.22E-06 --- 7.92E-05 Cm-243 5.99E-04 5.49E-04 3.75E-05 --- 1.75E-04 --- 7.81 E-05 Cm-244 4.56E-04 4.27E-04 2.87E-05 --- 1.34E-04 --- 7.55E-05 (Req Reviews: Rad Review, ISR, RP)
Do cuSign Envelope ID: EA65F1 86-46DE-4A34-97A4-01 F6B73ADF3B Page 203 of 237 CH-ODCM-0001 Reference Use Page 110 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested) 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 2.00E-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 ---* 2.00E-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-59 1.32E-05 4.66E-06 2.24E-06 --- --- --- 7.31 E-07 Ni-63 1.77E-04 1.25E-05 6.00E-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 2.00E-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-07 --- --- --- 7.77E-05 Y-90 1.37E-08 --- 3.69E-10 --- --- --- 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 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 --- 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 --- 7.11 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 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 204 of 237 CH-ODCM-0001 Reference Use Page 111 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 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-110M 2.05E-07 1.94E-07 1.18E-07 --- 3.70E-07 --- 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 --- 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71 E-08 5.80E-07 2.37E-09 --- 2.18E-06 1.93E-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-127 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-131M 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 --- 7.00E-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 6.10E-07 --- 5.10E-09 1-135 6.10E-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-138 7.76E-08 1.49E-07 7.45E-08 --- 1.10E-07 1.28E-08 4.76E-11 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 --- 1.18E-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-09 --- 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 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 205 of 237 CH-ODCM-0001 Reference Use Page 112 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Pr-144 4.30E-11 1.76E-11 2.18E-12 --- 1.01E-11 --- 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 --- 5.99E-09 --- 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 --- --- --- 3.22E-05 Pu-238 6.?0E-04 8.58E-05 1.82E-05 --- 7.B0E-05 --- 7.73E-05 Pu-239 7.65E-04 9.29E-05 2.01 E-05 --- 8.57E-05 --- 7.06E-05 Pu-240 7.64E-04 9.27E-05 2.01 E-05 --- 8.56E-05 --- 7.19E-05 Pu-241 1.75E-05 8.40E-07 3.69E-07 --- 1.71 E-06 --- 1.48E-06 Np-239 1.76E-09 1.66E-10 9.22E-11 --- 5.21E-10 --- 2.67E-05 Am-241 7.98E-04 7.53E-04 5.75E-05 --- 4.31 E-04 --- 7.87E-05 Cm-242 2.94E-05 3.10E-05 1.95E-06 --- 8.89E-06 --- 8.40E-05 Cm-243 6.50E-04 6.03E-04 4.09E-05 --- 1.91 E-04 --- 8.28E-05 Cm-244 5.04E-04 4.77E-04 3.19E-05 --- 1.49E-04 --- 8.00E-05 (Req Reviews : Rad Review, ISR, RP)
-4A34-97A4-0 1F6B 73ADF3B Page 206 of 237 CH-ODCM-0001 Reference Use Page 113 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) 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 --- 3.00E-06 --- 8.98E-06 Mn-56 --- 3.34E-07 7.54E-08 --- 4.04E-07 --- 4.84E-05 Fe-55 1.15E-05 6.10E-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-59 4.02E-05 1.07E-05 6.82E-06 --- --- --- 7.10E-07 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 4.11 E-08 --- 1.10E-09 --- --- --- 1.17E-04 Y-91M 3.82E-10 --- 1.39E-11 --- --- --- 7.48E-07 Y-91 6.02E-07 --- 1.61 E-08 --- --- --- 8.02E-05 Y-92 3.60E-09 --- 1.03E-10 --- --- --- 1.04E-04 Y-93 1.14E-08 --- 3.13E-10 --- --- --- 1.?0E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 --- 3.65E-08 --- 2.66E-05 Zr-97 6.99E-09 1.01 E-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 (Req Reviews: Rad Review, ISR, RP)
DocuSign Envelope ID : EA65F186-46DE-4A34-97A4-01 F6B73ADF3B Page 207 of 237 CH-ODCM-0001 Reference Use Page 114 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Tc-99M 9.23E-10 1.81 E-09 3.00E-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 Sb-124 1.11 E-05 1.44E-07 3.89E-06 2.45E-08 --- 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 --- 3.99E-06 1.71 E-05 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 --- --- 1.10E-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 1.01 E-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-131M 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 1.01 E-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 8.00E-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 8.10E-05 --- 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 --- 3.44E-05 5.13E-06 2.27E-06 Cs-137 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 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 2.00E-07 1.12E-10 6.51 E-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 1.01 E-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 (Req Reviews: Rad Review, ISR, RP)
86-46DE-4A34-97A4-01F6B73ADF3B Page 208 of 237 CH-ODCM-0001 Reference Use Page 115 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Pr-144 1.29E-10 3.99E-11 6.49E-12 --- 2.11E-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 Pu-238 1.19E-03 1.38E-04 3.16E-05 --- 1.15E-04 --- 7.50E-05 Pu-239 1.29E-03 1.38E-04 3.31 E-05 --- 1.22E-04 --- 6.85E-05 Pu-240 1.28E-03 1.43E-04 3.31 E-05 --- 1.22E-04 --- 6.98E-05 Pu-241 3.87E-05 1.58E-06 8.04E-07 --- 2.96E-06 --- 1.44E-06 Np-239 5.25E-09 3.77E-10 2.65E-10 --- 1.09E-09 --- 2.79E-05 Am-241 1.36E-03 1.17E-03 1.02E-04 --- 6.23E-04 --- 7.64E-05 Cm-242 8.78E-05 7.01 E-05 5.84E-06 --- 1.87E-05 --- 8.16E-05 Cm-243 1.28E-03 1.04E-03 8.24E-05 --- 3.08E-04 --- 8.03E-05 Cm-244 1.08E-03 8.74E-04 6.93E-05 --- 2.54E-04 --- 7.77E-05 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 209 of 237 CH-ODCM-0001 Reference Use Page 116 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) 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 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 P-32 1.70E-03 1.00E-04 6.59E-05 --- --- --- 2.30E-05 Cr-51 --- --- 1.41 E-08 9.20E-09 2.01 E-09 1.79E-08 4.11E-07 Mn-54 --- 1.99E-05 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-59 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-59 4.73E-05 1.45E-05 8.17E-06 --- --- --- 7.1 6E-07 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 5.00E-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-91M 8.10E-10 --- 2.76E-11 --- --- --- 2.70E-06 Y-91 1.13E-06 --- 3.01 E-08 --- --- --- 8.10E-05 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 1.00E-08 --- 1.24E-08 --- 1.46E-05 Mo-99 --- 3.40E-05 6.63E-06 --- 5.08E-05 --- 1.12E-05 (Req Reviews: Rad Review, ISR, RP)
OocuSign Envelope ID: EA65F1 86-46DE-4A34-97A4-01 F6B 73ADF3B Page 210 of 237 CH-ODCM-0001 Reference Use Page 117 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Tc-99M 1.92E-09 3.96E-09 5.10E-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-105 1.36E-07 --- 4.58E-08 --- 1.00E-06 --- 5.41 E-05 Ru-106 2.41 E-05 --- 3.01 E-06 --- 2.85E-05 --- 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81 E-07 --- 1.04E-06 --- 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 --- 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 --- 7.12E-06 1.64E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 --- --- 1.11 E-05 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 --- 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 --- 2.10E-05 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.S0E-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 5.0SE-06 1.24E-05 4.21 E-05 --- 1.03E-04 Te-131 1.76E-07 6.S0E-08 4.94E-08 1.57E-07 4.S0E-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 7.10E-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 1.10E-05 2.0SE-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 Ba-139 8.81 E-07 5.84E-10 2.55E-08 --- 3.51E- 10 3.54E-10 5.58E-05 Ba-140 1.71 E-04 1.71 E-07 8.81 E-06 --- 4.06E-08 1.0SE-07 4.20E-05 Ba- 141 4.25E-07 2.91E-10 1.34E-08 --- 1.75E-10 1.77E- 10 5.19E-06 Ba- 142 1.84E-07 1.53E-10 9.06E-09 --- 8.81E- 11 9.26E-11 7.59E-07 La-140 2.11 E-08 8.32E-09 2.14E-09 --- --- --- 9.77E-05 La-142 1.10E-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 (Req Reviews: Rad Review, ISR, RP)
F6B73ADF3B Page 211 of 237 CH-ODCM-0001 Reference Use Page 118 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI 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 Pu-238 1.28E-03 1.50E-04 3.40E-05 --- 1.21 E-04 --- 7.57E-05 Pu-239 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 6.91 E-05 Pu-240 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 7.04E-05 Pu-241 4.25E-05 1.76E-06 8.82E-07 --- 3.17E-06 --- 1.45E-06 Np-239 1.11 E-08 9.93E-10 5.61 E-10 --- 1.98E-09 --- 2.87E-05 Am-241 1.46E-03 1.27E-03 1.09E-04 --- 6.55E-04 --- 7.?0E-05 Cm-242 1.37E-04 1.27E-04 9.10E-06 --- 2.62E-05 --- 8.23E-05 Cm-243 1.40E-03 1.15E-03 8.98E-05 --- 3.27E-04 --- 8.10E-05 Cm-244 1.18E-03 9.?0E-04 7.59E-05 --- 2.71 E-04 --- 7.84E-05 (Req Reviews: Rad Review, ISR, RP)
F6B73A DF3B Page 212 of 237 CH-ODCM-0001 Reference Use Page 119 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol fg Fraction of ingested produce grown in garden 0.76 of interest. fp Fraction of leafy vegetables grown in garden of 1.0 interest. p Effective surface density of soil (assumes a 240 kg/m 2 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) St 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 1.752E5 hr sediment or soil (20 years) te Period of crop, leafy vegetable , or pasture 30 days (grass-cow-milk-man grass exposure during growing season pathway) 60 days (crop/vegetation-man pathway) tt Transport time from animal feed-milk-man 2 days (maximum individual) provided by residential structures 4 days (general population) th 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) fs 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. (Req Reviews: Rad Revi ew, ISR, RP)
F6B73ADF3B Page 213 of 237 CH-ODCM-0001 Reference Use Page 120 of 120 Off-Site Dose Calculation Manual (ODCM) Revision 38 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol tp 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) ts Average time from slaughter of meat animal to 20 days consumption Yv Agricultural productivity by unit area (measured 0.7 kg/m 2 (grass-cow-milk-man in wet weight) pathway) 2.0 kg/m 2 (produce or leafy vegetable ingested by man) w Shore-width factor for river shoreline 0.2 Aw Rate constant for removal of activity on plant or 0.0021 hr- 1 leaf structures by weathering (corresponds to a 14-day half-life) (Req Reviews: Rad Review, ISR, RP)
F6873ADF38 Page 214 of 237 FCSD-RW-PG-101 Radwaste Process Control Program Revision 1 Radwaste Process Control Program Revision 1 Revision By: Aaron Dudas, OPPD/FCS Rad Specialist Date Reviewed By: James Miller, Waste Project Manager Date Reviewed By : Jedidiah Emich, FCS Waste Manager Date Approved By: Scott Baskett, ESI SVP Corporate Waste Date Approved By : Dan Whisler, OPPD/FCS Radiation Protection Manager Date Approved By: Independent Safety Reviewer - Andrea Barker, OPPD/FCS Reg Assurance & Emergency Planning Manager Date D Non-Proprietary D New
~ Proprietary D Title Change D Restricted Information ~ Revision D Safeguards Information D Rewrite D Sensitive Security Information D Cancellation Effective Date:
Proprietary Information Page 1 of 8
F6873ADF38 Page 215 of 237 FCSD-RW-PG-101 Radwaste Process Control Program Revision 1 RECORD OF REVISIONS Revision Revision Title Description and Reason for Change 0 Initial issue. New document. Updated Review and Approval cover page. Section 3.1.1 - Definition to clarify the difference between EnergySolutions 1 groups. Section 4.2.2 - Clarify reviews and sign offs for the FCS QA TR. Added reference 2. 16 for Reg Guide 1.21 Proprietary [nformation Page 2 of 8
F6B73ADF3B Page 216 of 237 FCSD-RW-PG-101 Radwaste Process Control Program Revision 1 Table of Contents 1 PURPOSE AND SCOPE ..... ............... ................................................................................. 4 1.1 Purpose ................................. .......................................... ............ .. ........ .... ................. 4 1.2 Scope ........ .... ................................................................ ... .. .................... .. ... ... ..... ........ 4 2 REFERENCES .... .... ........ ............ ....... .............................. .............. ...... .......................... .. .... 4 3 GENERAL ............................................................................................................................ 5 3.1 Definitions ................................................................................................................. 5 3.2 Responsibilities ......................................................................................................... 5 3.3 Precautions and Limitations ................................................................................... 5 3.4 Records ...................................................................................................................... 5 4 REQUIREMENTS AND GUIDANCE .............................................................................. 5 4.1 General Instructions ................................................................................................ 5 4.2 Administrative Controls ..... ..................................................................................... 7 5 ATTACHMENTS AND FORMS ....................................................................................... 8 Proprietary Information Page 3 of 8
F6B73ADF3B Page 217 of 237 FCSD-RW-PG-101 Radwaste Process Control Program Revision 1 1 PURPOSE AND SCOPE I. I Purpose 1.1.1 The purpose of this document is to establish a Process Control Program that ensures processing and packaging of solid radioactive waste resulting from treatment of gaseous and liquid effluents and from other sources that is compliant with : A. Applicable federal and state regulations B. Disposal site requirements C. Other requirements governing the disposal of radioactive waste 1.2 Scope 1.2. l The scope of this document applies to al I personnel performing activities associated with the processing and packaging of solid radioactive waste . 2 REFERENCES 2.1 10 CFR Patt 20, Standards for Protection Against Radiation 2.2 IO CFR Part 50, Appendix A, General Design Criteria 60, Control of Releases of Radioactive Material to the Environment 2.3 IO CFR Patt 50.36a, Technical Specifications on Effluents from Nuclear Power Reactors 2.4 10 CFR Part 61 , Licensing Requirements for Land Disposal of Radioactive Waste 2.5 10 CFR Part 71 , Packaging and Transpottation of Radioactive Materials 2.6 49 CFR, Transportation 2.7 NUREG 1301 , Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, U.S. Nuclear Regulatory Commission, Apri I 1991 2.8 NRC Generic Letter 89-01 , Implementation of Programmatic Controls for Radiological Effluent Technical Specifications and the Relocation of Procedural Details of RETs to the Offsite Dose Calculation Manual or to the Process Control Program, January 31 , 1989 2.9 USNRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Form, Rev. 1, January, 1991 2.10 FCSD-CH-108, Annual Radioactive Effluent Release Report 2.11 FCSD-RW-PR-308, Packaging Solid Radioactive Waste 2.12 EPND-RM-100, Records Management Program 2.13 FCSD-RW-PG-100, Waste Management Program 2.14 NO-FC-10, Quality Assurance Topical Report (QATR) Proprietary Information Page 4 of 8
F6B73ADF3B Page 218 of 237 FCSD-RW-PG-101 Radwaste Process Control Program Revision 1 2.15 Energy Solutions, Utah Depaiiment of Environmental Quality, Division of Radiation Control , Radioactive Material License, License Number UT 2300249 2.16 Regulatory Guide 1.21 , Measuring, Eva Iuating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste 3 GENERAL 3.1 Definitions 3.1. l Vendor Services - External services providing specific waste preparations or packaging services. This does not refer to the on-site EnergySolutions staff or this document which is based on an EnergySolutions project document template. This may refer to Energy Solutions services out of another facility with a separate license and QA program (e.g., Barnwell or Bear Creek). 3.2 Responsibilities 3.2.1 The Waste Manager has overall responsibility for solid radioactive waste activities at the D&D project site. 3.2.2 Contractors and their subcontractors have the roles and associated responsibilities of a vendor in accordance with this procedure. 3.2.3 Radiation Protection Manager has the responsibility of review and approval of the vendor submittals. 3 .3 Precautions and Limitations 3.3.1 Verify current revision in accordance with applicable site procedures. 3.4 Records 3.4. l All Waste Management records will be maintained in accordance with FCSD-RW-PG-100 (Ref. 2.13) . 3.4.2 Records generated from the use of this procedure should be processed in accordance with EPND-RM-100 (Ref. 2.12). 4 REQUIREMENTS AND GUIDANCE 4.1 General Instructions 4.1.1 Wet Waste A. Process liquid wet waste in accordance with: I. Specific site procedures that provide sufficient instructions for safe and efficient processing, immobilizing and, stabilizing of wet wastes in accordance with FCSD-RW-PR-308 (Ref. 2.11). Proprietary Information Page 5 of 8
F6873ADF38 Page 219 of 237 FCSD-RW-PG-101 Radwaste Process Control Program Revision 1
- 2. Shipment and disposal requirements that meet the criteria on Free Standing Water (FSW) in accordance with USNRC Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Form (Ref. 2.9) and EnergySolutions, Utah Department of Environmental Quality, Division of Radiation Control , Radioactive Material License (Ref. 2.15).
- 3. Approved procedures that contain provisions for correcting processed waste in which FSW is detected in excess of FSW limits and criteria.
B. Ensure vendor procedures are approved by the Radiation Protection Manager (RPM) prior to use.
- 4. I .2 Solidification A. Qualified vendor services shall supply solidification Process Control Programs (PCPs), procedures, and topical repo1ts to the RPM for approval.
B. These documents should include: I . Process description
- 2. Solidification media used
- 3. Process control parameters
- 4. Parameter boundary conditions
- 5. Waste form properties
- 6. Specific instructions to ensure systems are operated within process parameters
- 7. Pre-solidification laboratory sample mixing criteria
- 8. Sampling frequency and acceptance criteria
- 9. Exothermic reaction process control parameters C. Solidification vendor documentation shall include provisions to verify FSW criteria are met for the specific waste type being solidified.
D. The vendor supplied PCP shall contain the current formulas , sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with l O CFR Parts 20, 61 and 71 (Refs. 2.1 , 2.4, 2.5), state regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. Proprietary [nformation Page 6 of 8
F6B73ADF3B Page 220 of 237 FCSD-RW-PG-101 Radwaste Process Control Program Revision 1 4.1.3 Containers, Shipping Casks, and Packaging A. Solid radioactive waste shall be processed, packaged and shipped in accordance with approved site procedures . B. Procedures shall provide specific instructions that ensure compliance with applicable federal, state and burial site requirements. 4.1.4 Shipping and Disposal A. Prepare , load and ship solid radioactive waste in accordance with specific site procedures to meet federal , state, and burial site requirements. 4.1.5 Oily/Mixed Wastes A. Radioactive wastes containing oil or hazardous substances are processed in accordance with approved site procedures to ensure compliance with applicable requirements. 4.1.6 Special Cases A. Unique wastes may require special techniques or processes. Process special case waste in accordance with specific site procedures to meet applicable requirements. B. Implementing procedures are reviewed and approved by the Waste Manager. C. Special processes developed under this provision should be documented as a change to the PCP per Section 4.2.2 of this procedure. 4.2 Administrative Controls 4.2.1 Quality Assurance A. Quality Assurance shall be implemented in a graded approach as described in NO-FC-10 (Ref. 2.14). 4.2.2 Changes to the Process Control Programs (PCPs) A. The Process Control Program (PCP) is implemented through this controlling document for the processing and packaging of solid radioactive waste to comply with all applicable regulations and requirements. It is defined as a program under the guidance of QA TR, Appendix D. B. At a minimum, document completion of a NOS Review against the QATR, NO-FC-10 on the Document Routing Form for the PCP revision. Additional documentation ofreviews may be required per section 4.2.2.D of this procedure. Proprietary Information Page 7 of 8
F6B73ADF3B Page 221 of 237 FCSD-RW-PG-101 Radwaste Process Control Program Revision 1 C. Shall become effective after review and acceptance by the Independent Safety Reviewer and the approval of the Decommissioning Plant Manager/ISFSI Manager. D. Licensee-initiated changes to the PCP shall: I. Be documented and records of reviews shall be retained in accordance with NO-FC-L0 (Ref. 2.14). This documentation shal l contain:
- i. Sufficient information to support the change(s), together with the appropriate ana lyses or eva luations justifying the change(s),
- 11. A determination that the change(s) will maintain the overall conformance of the solidified waste product to the existing requirements of federal , state and other applicable regulations, and 111. Documentation that the change has been reviewed and found acceptable through execution of the applicable regulatory review process for the project.
- 2. Changes made to the PCP shall be communicated to Chemistry and Environmental for inclusion in Annual Radioactive Effluent Release Repot1 in accordance with FCSD-CH-108 (Ref. 2.10) and Regulatory Guide 1.21 (Ref. 2.16).
5 ATTACHMENTS AND FORMS None Proprietary [nformation Page 8 of 8
F6B73ADF3B Page 222 of 237 SECTION VII ATTACHMENT 2 JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA (Regulatory Guide 1.21) January 1, 2022 - December 31, 2022 Vll-2
OocuSign Envelope ID : EA65F186-46DE -4A34-97A4-01 F6B73ADF3B Page 223 of 237 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, 2015 through December 31, 2019 had a cumulative recovery rate of 78.15% from the meteorological tower with the remaining 21 .85% provided by Eppley Airfield Weather Station, a branch of the National Weather Service . The following table is a summary of the parameters and their respective recovery rates for the period. The tabulations of the Weather Tower Data for the period January 1, 2015 through December 31, 2019 look appropriate for the season indicated. The Pasquill Classes observed for the five year period are detailed below. Pasquill Class A BC D E F G Total
% Obs. 7.34 3.46 6.37 46.83 22.95 8.56 4.49 100 On the basis of the data and its cross-checks, the weather data as amended is completely valid for use in tabulating atmospheric releases.
Vll-3
Page 224 of 237 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 2015 - DEC 2019 PASQUILL A WIND SPEED (m/s) AT 10 - m LEVEL Wind < 0 . 5- 1.1 - 1. 6 - 2.1 - 3 . 1- 4.1 - 5.1 - 6 . 1- 8 . 1- > Direct 0.5 1.0 1. 5 2.0 3 .0 4.0 5.0 6.0 8.0 10.0 1 0 .0 Total N 0 3 19 31 76 97 56 14 13 0 0 309 NNE 1 6 22 20 22 23 6 5 0 0 0 105 NE 0 5 13 5 16 21 8 1 0 0 0 69 ENE 0 5 13 12 18 23 6 0 1 0 0 78 E 0 1 14 11 25 21 7 1 3 0 0 83 ESE 0 2 5 15 34 50 14 7 9 1 0 137 SE 0 2 9 12 21 24 33 18 22 3 1 145 SSE 0 3 3 8 29 34 39 33 53 9 0 2 11 s 0 1 3 5 19 44 27 26 42 10 2 179 SSW 1 1 4 3 21 32 24 17 30 10 1 144 SW 0 0 4 5 25 20 28 14 12 8 0 116 WSW 0 1 9 6 17 3 3 2 9 0 0 50 w 1 5 6 27 32 17 15 3 5 2 0 113 WNW 0 10 15 27 62 37 26 8 6 0 0 191 NW 0 9 17 15 73 94 122 68 71 12 5 486 NNW 0 6 18 30 14 6 173 184 126 88 15 4 790 Total 3 60 174 232 636 713 598 343 364 70 13 3206 Number of Calms 9 Number of Invalid Hours 0 Number of Valid Hours 3215 VII-4
F6B73ADF3B Page 225 of 237 Omaha Public Power District Fort Calhoun Nuc l ear Station JOINT FREQU ENCY DI STRIB UTION BY EVENTS MODERATELY UNS TABLE (- 1. 9 < de lta T/ delta z <= -1. 7) PERIOD OF RECORD : JAN 2015 - DEC 20 1 9 PASQUILL B WIND SPEED (m/s) AT 10 - m LEVEL Wind < 0 . 5- 1. 1- 1. 6 - 2 . 1- 3 . 1- 4 . 1- 5 . 1- 6 .1- 8 . 1- > Direct 0.5 1.0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10 . 0 10 . 0 Total N 0 15 18 23 52 28 12 4 2 0 0 154 NNE 0 4 10 10 16 4 4 0 0 0 0 48 NE 0 2 8 13 14 8 3 2 0 0 0 50 ENE 0 1 5 14 20 10 7 3 0 0 0 60 E 0 3 4 11 26 12 3 3 0 0 0 62 ESE 0 2 5 3 16 10 12 6 3 2 0 59 SE 0 1 1 7 9 29 31 29 15 2 0 124 SSE 0 5 3 7 4 17 30 15 22 2 0 105 s 0 0 2 6 16 23 23 12 19 8 1 11 0 SSW 0 3 2 4 8 10 10 13 18 3 0 71 SW 1 2 2 3 11 9 4 2 4 0 0 38 WSW 0 1 4 5 10 5 4 1 1 1 0 32 w 0 0 5 10 7 5 4 1 5 0 0 37 WNW 0 2 6 7 31 9 7 1 6 1 0 70 NW 0 3 9 7 23 27 30 21 18 3 1 142 NNW 0 2 14 21 85 80 57 42 29 4 0 334 Total 1 46 98 151 348 286 241 155 142 26 2 1496 Number of Calms 19 Number of Invalid Hours 0 Number of Valid Hours 1515 VII - 5
F6B73ADF3B Page 226 of 237 Omaha Public Power District Fo r t Ca l houn Nuclear Station JOIN T FREQUENCY DISTRIBUT ION BY EVENTS SLI GHTLY UNSTABLE (- 1 . 7 < delta T/ delta z <= - 1.5 ) PERIOD OF RECORD : JAN 2015 - DEC 2019 PASQUILL C WIND SPEED (m/s) AT 10 - m LEVE L Wind < 0 . 5- 1.1 - 1. 6- 2 . 1- 3 . 1- 4 . 1- 5 . 1- 6 .1- 8 . 1- > Direct 0.5 1.0 1. 5 2.0 3.0 4.0 5.0 6. 0 8.0 10 . 0 10 . 0 Total N 1 39 56 75 71 56 24 6 2 0 0 330 NNE 0 13 30 32 29 9 2 2 0 0 0 117 NE 0 7 13 16 22 12 2 1 1 0 0 74 ENE 0 7 14 18 28 16 7 2 0 0 0 92 E 0 11 17 28 26 8 7 2 1 0 0 100 ESE 0 11 15 19 28 21 15 7 7 1 0 1 24 SE 0 15 26 42 37 38 36 29 16 3 1 243 SSE 0 15 25 36 25 34 32 28 34 10 0 239 s 0 11 16 21 38 48 31 18 16 5 2 206 SSW 0 6 5 23 21 18 17 16 22 3 1 132 SW 0 6 12 11 13 19 14 6 5 3 1 90 WSW 0 3 5 14 11 10 5 5 2 0 0 55 w 0 9 17 20 21 13 4 2 6 1 0 93 WNW 0 6 13 19 24 19 12 5 6 0 0 104 NW 0 8 19 25 45 44 32 23 27 7 0 230 NNW 0 8 27 59 84 102 57 35 30 9 4 415 Total 1 175 310 458 523 4 67 2 97 18 7 175 42 9 2644 Number of Calms 146 Number of Invalid Hours 0 Number of Va l id Hours 2790 VII - 6
DE-4A34-97A4-0 1 F6B73ADF3B Page 227 of 237 Omaha Public Power District Fort Ca l houn Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS NEUTRAL (-1. 5 < delta T/ delta z <= - 0 . 5) PERIOD OF RECORD: JAN 20 1 5 - DEC 2019 PASQUILL D WIND SPEED (m/ s) AT 10-m LEVEL Wind < 0 . 5- 1.1 - 1. 6- 2 . 1- 3 .1- 4 . 1- 5 . 1- 6 . 1- 8 . 1- > Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 2 88 181 341 605 475 168 94 47 0 0 2001 NNE 2 58 142 148 194 145 47 15 7 1 0 759 NE 2 40 106 111 135 69 38 15 7 3 0 526 ENE 0 37 131 108 153 92 37 13 13 0 0 58 4 E 1 38 112 159 265 148 58 23 10 2 0 81 6 ESE 1 45 86 1 70 30 1 222 85 39 34 8 1 992 SE 2 31 78 1 97 4 97 4 64 296 174 129 18 6 1892 SSE 2 25 53 164 522 655 4 97 340 342 34 8 2642 s 1 24 42 101 309 490 453 339 316 66 9 2150 SSW 1 18 32 61 168 200 164 153 1 51 34 12 994 SW 2 12 37 43 177 139 83 56 50 14 4 617 WSW 1 25 39 48 96 83 48 26 17 2 0 385 w 1 25 39 91 147 112 55 49 36 9 0 564 WNW 6 37 69 72 17 5 163 111 58 50 2 0 743 NW 3 39 89 113 281 337 302 189 216 48 7 1624 NNW 2 49 171 269 816 7 68 4 62 239 209 26 1 3012 Total 29 591 1407 2196 4841 4 562 2904 1 822 1634 267 48 20301 Numb er of Calms 2 1 2 Number of Invalid Hours 0 Number of Valid Hours 20513 VII - 7
F6B73ADF3B Page 228 of 237 Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY STAB LE ( - 0 . 5 < delta T/ delta z <= 1 . 5) PERIOD OF RECORD: JAN 2015 - DEC 2019 PASQUILL E WIND SPEED (m/s) AT 10 - m LEVEL Wind < 0 . 5- 1.1 - 1. 6 - 2 . 1- 3 .1- 4 . 1- 5 . 1- 6 . 1- 8 .1- > Direct 0.5 1.0 1. 5 2. 0 3 .0 4.0 5.0 6.0 8.0 10 . 0 10 . 0 Total N 10 55 78 55 81 31 9 2 0 0 0 32 1 NNE 6 60 46 29 42 6 4 0 1 0 0 194 NE 10 46 64 33 29 3 1 0 0 0 0 18 6 ENE 5 47 64 35 44 9 5 1 0 0 0 210 E 9 50 79 64 85 22 8 3 2 0 0 322 ESE 8 47 142 131 163 44 14 8 5 0 0 562 SE 10 59 157 20 6 452 288 1 31 43 48 6 2 140 2 SSE 10 52 76 136 4 62 370 262 11 3 67 5 0 15 53 s 6 41 42 60 198 250 221 123 88 9 1 1039 SSW 11 45 45 21 74 80 123 95 140 29 4 667 SW 26 39 26 21 45 43 32 43 84 31 6 396 WSW 11 47 37 33 51 46 37 15 15 2 1 295 w 25 86 64 70 1 04 70 45 18 10 1 1 494 WNW 22 172 142 93 212 103 56 13 9 2 0 824 NW 11 113 158 132 191 108 34 4 6 0 1 75 8 NNW 13 70 142 168 271 113 26 13 10 1 0 827 Total 193 1029 1362 1287 2504 1586 1008 4 94 485 86 16 10050 Number of Calms 0 Number of I nvalid Hours 0 Number of Valid Hours 10050 VII - 8
1 F6B73A DF3 B Page 229 of 237 Omaha Pub lic Power District Fort Calhoun Nuclear Station JOINT FRE QU ENCY DI STRIBUTIO N BY EVENTS MODERATELY STABLE (1.5 < de lta T/ delta z <= 4 . 0) PERIOD OF RECORD : JAN 2015 - DEC 2019 PASQUILL F WIND SPEED (m/s) AT 10 - m LEVEL Wind < 0 . 5- 1. 1- 1. 6 - 2.1 - 3 . 1- 4 .1- 5.1 - 6 . 1- 8 .1- > Direct 0.5 1.0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10 . 0 10 . 0 Total N 8 24 21 27 17 4 1 0 0 0 0 102 NNE 8 27 12 10 1 0 0 0 0 0 0 58 NE 11 22 5 2 0 1 0 0 0 0 0 41 ENE 5 41 26 6 4 0 0 0 0 0 1 83 E 9 59 57 24 22 2 0 0 0 0 0 173 ESE 10 50 101 70 41 21 2 0 0 0 0 295 SE 14 81 124 1 22 164 62 25 7 0 0 0 599 SSE 23 78 59 96 160 35 4 1 0 0 0 456 s 26 76 24 35 81 52 23 4 1 0 0 322 SSW 39 72 31 15 29 37 27 8 1 0 0 259 SW 36 Bl 14 11 19 13 15 9 9 2 0 209 WSW 37 77 17 6 9 16 9 0 3 0 0 174 w 38 125 39 25 17 6 1 0 0 0 0 251 WNW 32 1 29 90 34 44 12 1 0 0 0 0 342 NW 16 54 43 23 25 6 0 0 0 0 0 167 NNW 9 22 21 26 31 12 3 3 3 1 0 131 Total 32 1 1018 684 532 664 279 111 32 17 3 1 3662 Number of Calms 86 Number of Invalid Hours 0 Number of Valid Hours 3748 VII - 9
A4-01 F6B73ADF3B Page 230 of 237 Omaha Pub l ic Power District Fort Calhoun Nuclear St ation JOINT FREQUENCY DISTRIB UTI ON BY EVENTS EXTREMELY STABLE (delta T / delta z > 4 . 0) PERIOD OF RECORD : JAN 20 1 5 - DEC 2019 PASQUILL G WIND SPEED (m/s) AT 10 - m LEVEL Wind < 0 . 5- 1.1 - 1. 6 - 2.1 - 3.1 - 4 . 1- 5.1 - 6 .1- 8 . 1- > Direct 0.5 1.0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10 . 0 10 . 0 Total N 5 19 9 6 1 1 0 0 0 0 0 41 NNE 13 16 7 3 1 3 0 0 0 0 0 43 NE 13 31 2 1 1 3 0 0 0 0 0 51 ENE 18 49 13 4 1 0 0 1 2 0 0 88 E 20 50 26 9 2 0 0 1 0 0 0 108 ESE 26 87 165 34 8 5 0 0 0 0 0 325 SE 22 101 75 37 20 5 2 0 0 0 0 262 SSE 32 88 56 34 8 1 0 0 0 0 0 219 s 19 84 24 13 14 8 2 2 0 0 0 166 SSW 23 77 13 7 8 8 3 2 0 0 0 141 SW 23 81 7 2 6 6 4 1 0 0 0 130 WSW 24 36 10 3 1 1 0 0 0 0 0 75 w 18 38 13 7 3 0 0 0 0 0 0 79 WNW 6 24 15 7 0 0 0 0 0 0 0 52 NW 9 19 12 5 1 1 0 0 0 0 0 47 NNW 2 10 9 8 3 8 20 2 0 0 0 62 Total 273 810 456 1 80 78 50 31 9 2 0 0 1889 Number of Calms 79 Number of Invalid Hours 0 Number of Valid Hours 19 68 Hours Accounted For : 437 99 VII-10
F6B73ADF3B Page 231 of 237 Oma ha Public Power District Fort Ca l houn Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY UNSTAB LE (delta T/ delta z <= - 1 . 9) PERIOD OF RECORD : JAN 2015 - DEC 20 1 9 PASQUILL A WIN D SPEED (m/s) AT 10 - m LEVE L Wind < 0 . 5- 1.1 - 1. 6- 2 .1- 3 . 1- 4 . 1- 5 .1 - 6.1 - 8 . 1- > Direct 0.5 1.0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10 . 0 10 . 0 Total N 0 . 00 0 . 01 0.04 0 . 07 0 . 17 0 . 22 0 . 13 0 . 03 0 . 03 0 . 00 0.00 0 . 71 NNE 0 . 00 0 . 01 0 . 05 0 . 05 0 . 05 0 . 05 0 . 01 0 . 01 0 . 00 0 . 00 0 . 00 0.24 NE 0 . 00 0 . 01 0 . 03 0 . 01 0 . 04 0 . 05 0 . 02 0 . 00 0 . 00 0 . 00 0 . 00 0 .1 6 ENE 0 . 00 0 . 01 0 . 03 0 . 03 0 . 04 0 . 05 0 . 01 0 . 00 0 . 00 0.00 0 . 00 0 . 18 E 0 . 00 0 . 00 0 . 03 0 . 03 0 . 06 0 . 05 0 . 02 0 . 00 0 . 01 0.00 0 . 00 0 . 19 ESE 0 . 00 0 . 00 0 . 01 0.03 0 . 08 0 .11 0 . 03 0 . 02 0 . 02 0.00 0 . 00 0 . 31 SE 0 . 00 0 . 00 0 . 02 0 . 03 0 . 05 0 . 05 0 . 08 0 . 04 0 . 05 0 . 01 0 . 00 0 . 33 SSE 0 . 00 0 . 01 0 . 01 0 . 02 0 . 07 0 . 08 0 . 09 0 . 08 0 .1 2 0 . 02 0 . 00 0 . 48 s 0 . 00 0 . 00 0 . 01 0 . 01 0 . 04 0 .1 0 0 . 06 0 . 06 0 .1 0 0 . 02 0 . 00 0 . 41 SSW 0 . 00 0 . 00 0.01 0 . 01 0 . 05 0 . 07 0 . 05 0 . 04 0 . 07 0 . 02 0 . 00 0 . 33 SW 0 . 00 0 . 00 0 . 01 0 . 01 0 . 06 0 . 05 0 . 06 0 . 03 0 . 03 0 . 02 0 . 00 0 . 26 WSW 0 . 00 0 . 00 0 . 02 0 . 01 0 . 04 0 . 01 0 . 01 0 . 00 0 . 02 0 . 00 0 . 00 0 . 11 w 0 . 00 0 . 01 0 . 01 0 . 06 0 . 07 0 . 04 0 . 03 0 . 01 0 . 01 0 . 00 0 . 00 0 . 26 WNW 0 . 00 0 . 02 0 . 03 0 . 06 0 .14 0 . 08 0.06 0 . 02 0 . 01 0 . 00 0.00 0 . 44 NW 0 . 00 0 . 02 0 . 04 0 . 03 0 . 17 0 . 21 0 . 28 0 . 16 0 . 16 0 . 03 0 . 01 1.11 NNW 0 . 00 0 . 01 0 . 04 0 . 07 0 . 33 0 . 39 0 . 42 0 . 29 0 . 20 0 . 03 0.01 1. 80 Total 0 . 01 0 . 14 0 . 40 0 . 53 1. 45 1. 63 1. 37 0 . 78 0 . 83 0 . 16 0 . 03 7 . 32 Percent of Calms 0 . 02 Percent of Inva li d Hours 0 . 00 Perce n t of Valid Hours 7 . 34 VII-11
B Page 232 Of 237 Oma ha Pub li c Powe r Di s t rict For t Cal h oun Nuclea r St a ti o n JOIN T FREQU ENCY DI STRI BUT I ON BY PERC ENT MO DE RATELY UN STABLE (- 1 . 9 < de lta T/ de lta z <= - 1 . 7) PER I OD OF RECORD: JAN 20 1 5 - DEC 2019 PASQUILL B WIN D SPEED (m/s) AT 1 0-m LEVEL Wind < 0 . 5- 1. 1- 1. 6- 2 .1- 3 . 1- 4.1 - 5 . 1- 6 . 1- 8 . 1- > Direc t 0.5 1. 0 1. 5 2. 0 3.0 4.0 5.0 6.0 8.0 10 . 0 10 . 0 To ta l N 0 . 00 0 . 03 0 . 04 0 . 05 0 . 12 0 . 06 0 . 03 0 . 01 0 . 00 0 . 00 0 . 00 0 . 35 NNE 0 . 00 0 . 01 0 . 02 0 . 02 0 . 04 0 . 01 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 11 NE 0 . 00 0 . 00 0 . 02 0 . 03 0 . 03 0 . 02 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 11 ENE 0 . 00 0 . 00 0 . 01 0 . 03 0 . 05 0 . 02 0 . 02 0 . 01 0 . 00 0 . 00 0 . 00 0 . 14 E 0 . 00 0 . 01 0 . 01 0 . 03 0 . 06 0 . 03 0 . 01 0 . 01 0 . 00 0 . 00 0 . 00 0 .1 4 ESE 0 . 00 0 . 00 0 . 01 0 . 01 0 . 04 0 . 02 0 . 03 0 . 01 0 . 01 0 . 00 0 . 00 0 . 13 SE 0.00 0 . 00 0 . 00 0 . 02 0 . 02 0 . 07 0 . 07 0 . 07 0 . 03 0 . 00 0 . 00 0 . 28 SSE 0 . 00 0 . 01 0 . 01 0 . 02 0 . 01 0 . 04 0 . 07 0 . 03 0 . 05 0 . 00 0 . 00 0 . 24 s 0 . 00 0 . 00 0 . 00 0 . 01 0 . 04 0 . 05 0 . 05 0 . 03 0 . 04 0 . 02 0 . 00 0 . 25 SSW 0 . 00 0 . 01 0 . 00 0 . 01 0 . 02 0 . 02 0 . 02 0 . 03 0 . 04 0 . 01 0 . 00 0 . 16 SW 0.00 0 . 00 0 . 00 0 . 01 0 . 03 0 . 02 0 . 01 0 . 00 0 . 01 0 . 00 0 . 00 0 . 09 WSW 0 . 00 0 . 00 0 . 01 0 . 01 0 . 02 0 . 01 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 07 w 0 . 00 0 . 00 0 . 01 0 . 02 0 . 02 0 . 01 0 . 01 0 . 00 0 . 01 0 . 00 0 . 00 0 . 08 WNW 0 . 00 0 . 00 0 . 01 0 . 02 0 . 07 0 . 02 0.02 0 . 00 0 . 01 0 . 00 0.00 0 . 16 NW 0 . 00 0 . 01 0 . 02 0 . 02 0 . 05 0 . 06 0 . 07 0 . 05 0 . 04 0 . 01 0 . 00 0 . 32 NNW 0 . 00 0 . 00 0 . 03 0 . 05 0 . 19 0 . 18 0 . 13 0 . 10 0 . 07 0 . 01 0 . 00 0 . 76 Total 0 . 00 0 . 11 0 . 22 0 . 34 0 . 79 0 . 65 0 . 55 0 . 35 0 . 32 0 . 06 0 . 00 3 . 42 Pe r cent o f Ca l ms 0 . 04 Pe r cen t o f Inva li d Hours 0 . 00 Perce n t of Valid Hour s 3 . 46 VII - 12
F186-46DE-4A34-97A4-01 F6B73ADF3 B Page 233 of 237 Omaha Public Power District Fort Ca l houn Nuclear Station JOINT FREQUENCY DIS TRIBUTION BY PERCENT SLIGHTLY UNSTAB LE (- 1 .7 < delta T/ delta z <= -1.5) PERIOD OF RECORD : JAN 2015 - DEC 2019 PASQUILL C WIND SPEED (m/s) AT 10 - m LEVEL Wind < 0 . 5- 1.1 - 1. 6 - 2 . 1- 3 . 1- 4 . 1- 5 . 1- 6 . 1- 8 . 1- > Di r ect 0.5 1.0 1. 5 2.0 3.0 4. 0 5.0 6.0 8.0 10 . 0 10 . 0 Total N 0 . 00 0 . 09 0 .1 3 0 . 17 0 . 16 0 .13 0 . 05 0 . 01 0 . 00 0 . 00 0 . 00 0 . 75 NNE 0 . 00 0 . 03 0 . 07 0 . 07 0 . 07 0.02 0 . 00 0 . 00 0 . 00 0 . 00 0.00 0 . 27 NE 0 . 00 0 . 02 0 . 03 0 . 04 0 . 05 0 . 03 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 .1 7 ENE 0 . 00 0 . 02 0 . 03 0 . 04 0.06 0.04 0 . 02 0 . 00 0 . 00 0 . 00 0 . 00 0.21 E 0 . 00 0 . 03 0 . 04 0 . 06 0 . 06 0 . 02 0 . 02 0 . 00 0.00 0 . 00 0 . 00 0.23 ES E 0.00 0.03 0.03 0 . 04 0 . 06 0 . 05 0 . 03 0 . 02 0.02 0.00 0 . 00 0 . 28 SE 0 . 00 0 . 03 0 . 06 0 . 10 0 . 08 0 . 09 0 . 08 0.07 0 . 04 0 . 01 0 . 00 0 . 55 SSE 0 . 00 0 . 03 0 . 06 0 . 08 0 . 06 0 . 08 0 . 07 0 . 06 0 . 08 0 . 02 0 . 00 0 . 55 s 0 . 00 0 . 03 0 . 04 0 . 05 0 . 09 0 . 11 0.07 0 . 04 0 . 04 0 . 01 0 . 00 0 . 47 SSW 0 . 00 0 . 01 0 . 01 0 . 05 0 . 05 0 . 04 0 . 04 0 . 04 0 . 05 0 . 01 0 . 00 0 . 30 SW 0 . 00 0 . 01 0 . 03 0.03 0 . 03 0 . 04 0 . 03 0 . 01 0 . 01 0 . 01 0 . 00 0 . 21 WSW 0 . 00 0 . 01 0 . 01 0 . 03 0 . 03 0 . 02 0 . 01 0 . 01 0 . 00 0 . 00 0 . 00 0 . 13 w 0 . 00 0 . 02 0 . 04 0 . 05 0 . 05 0 . 03 0 . 01 0 . 00 0 . 01 0 . 00 0 . 00 0 . 21 WNW 0 . 00 0 . 01 0 . 03 0 . 04 0 . 05 0 . 04 0 . 03 0.01 0 . 01 0.00 0 . 00 0 . 24 NW 0 . 00 0 . 02 0 . 04 0 . 06 0 . 10 0 . 10 0 . 07 0 . 05 0 . 06 0 . 02 0 . 00 0 . 53 NNW 0 . 00 0 . 02 0 . 06 0 . 13 0 . 19 0 . 23 0 . 13 0 . 08 0 . 07 0.02 0.01 0 . 95 Total 0 . 00 0 . 40 0. 71 1.05 1.19 1.07 0 . 68 0 . 43 0 . 40 0 . 10 0 . 02 6 . 04 Percent of Calms 0 . 33 Percent of Invalid Hours 0 . 00 Percent of Valid Hours 6.37 VII - 13
86-46DE-4A34-97A4-01 F6B73ADF3B Page 234 of 237 Omah a Public Power District Fort Ca l houn Nuclear Station JOINT FREQU ENCY DISTRIB UTION BY PERCENT NEUTRAL (-1. 5 < delta T/ delta z <= - 0 . 5) PER I OD OF RECORD : JAN 2015 - DEC 20 1 9 PASQUILL D WIND SPEED (m/s) AT 1 0 - m LEVEL Wind < 0 . 5- 1.1 - 1. 6 - 2 . 1- 3.1 - 4 . 1- 5 . 1- 6 . 1- 8 .1- > Direct 0.5 1.0 1.5 2.0 3.0 4. 0 5.0 6.0 8.0 10 . 0 10 . 0 Total N 0 . 00 0 . 20 0 . 41 0 . 78 1. 38 1.08 0.38 0 . 21 0 . 11 0 . 00 0 . 00 4.57 NNE 0 . 00 0 . 13 0 . 32 0 . 34 0 . 44 0 . 33 0 . 11 0 . 03 0 . 02 0.00 0 . 00 1. 73 NE 0.00 0 . 09 0 . 24 0 . 25 0 . 31 0 . 16 0 . 09 0 . 03 0 . 02 0 . 01 0 . 00 1. 20 ENE 0 . 00 0 . 08 0 . 30 0 . 25 0 . 35 0.21 0.08 0 . 03 0 . 03 0 . 00 0 . 00 1. 33 E 0 . 00 0 . 09 0 . 26 0 . 36 0 . 61 0 . 34 0 . 13 0 . 05 0 . 02 0 . 00 0 . 00 1. 8 6 ESE 0 . 00 0 . 10 0 . 20 0 . 39 0 . 69 0 . 51 0 . 19 0 . 09 0 . 08 0 . 02 0 . 00 2 . 26 SE 0 . 00 0.07 0 . 18 0 . 45 1. 13 1. 06 0 . 68 0 . 40 0 . 29 0 . 04 0.01 4 . 32 SSE 0 . 00 0 . 06 0 . 12 0 . 37 1. 19 1.50 1.13 0.78 0 . 78 0 . 08 0 . 02 6.03 s 0 . 00 0.05 0 . 10 0 . 23 0 . 71 1.12 1. 03 0 . 77 0 . 72 0 .1 5 0 . 02 4 . 91 SSW 0 . 00 0 . 04 0 . 07 0 . 14 0.38 0 . 46 0 . 37 0 . 35 0 . 34 0 . 08 0.03 2 . 27 SW 0 . 00 0 . 03 0 . 08 0 . 10 0 .4 0 0 . 32 0 .1 9 0 .1 3 0 . 11 0.03 0.0 1 1. 4 1 WSW 0 . 00 0 . 06 0 . 09 0 . 11 0 . 22 0 . 19 0 .11 0 . 06 0 . 04 0 . 00 0 .0 0 0 . 88 w 0 . 00 0 . 06 0 . 09 0 . 21 0.34 0 . 26 0 . 13 0 .11 0 . 08 0 . 02 0 . 00 1. 29 WNW 0 . 01 0 . 08 0 . 16 0 . 16 0 . 40 0 . 37 0 . 25 0 . 13 0 . 11 0.00 0 . 00 1. 70 NW 0 . 01 0 . 09 0 . 20 0 . 26 0 . 64 0. 77 0.69 0 . 43 0 . 49 0 . 11 0 . 02 3 . 71 NNW 0 . 00 0 . 11 0 . 39 0 . 61 1. 86 1. 7 5 1.0 5 0 . 55 0 . 48 0.06 0 . 00 6.88 Total 0.07 1. 35 3 . 21 5.01 11 . 05 10. 42 6 .6 3 4 . 16 3 .73 0 .61 0 .11 46.35 Percent of Ca l ms 0.48 Percent of Invalid Hours 0 . 00 Percent of Va l id Hours 46 . 83 VII - 14
86-46DE-4A34-97A4-01 F6B73ADF3B Page 235 of 237 Omaha Public Power Dist r i ct Fort Calhoun Nuc le ar Stat i on JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTL Y STABLE (- 0 . 5 < delta T/ delta z <= 1 . 5) PER I OD OF RECORD : JAN 20 1 5 - DEC 20 1 9 PASQUILL E WI ND SPEED (m/s) AT 1 0-m LEVEL Wind < 0 . 5- 1.1- 1. 6 - 2.1 - 3 . 1- 4 . 1- 5 .1- 6 . 1- 8 . 1- > Direct 0.5 1.0 1. 5 2.0 3.0 4.0 5.0 6. 0 8.0 10 . 0 10 . 0 Total N 0 . 02 0 . 13 0 . 18 0 . 13 0 . 18 0.07 0 . 02 0.00 0 . 00 0 . 00 0 . 00 0 . 73 NNE 0 . 01 0 . 14 0 . 11 0 . 07 0 .1 0 0 . 01 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 44 NE 0 . 02 0 . 11 0 . 15 0 . 08 0 . 07 0.01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 42 ENE 0 . 01 0 . 11 0 . 15 0 . 08 0 . 10 0.02 0 . 01 0 . 00 0.00 0 . 00 0 . 00 0.48 E 0 . 02 0 .11 0.18 0 . 15 0 . 19 0 . 05 0 . 02 0 . 01 0 . 00 0 . 00 0 . 00 0 . 74 ESE 0 . 02 0 . 11 0 . 32 0 . 30 0 . 37 0 . 10 0 . 03 0 . 02 0 . 01 0 . 00 0 . 00 1. 28 SE 0 . 02 0 . 13 0 . 36 0 . 47 1. 03 0 . 66 0 . 30 0 . 10 0 . 11 0 . 01 0 . 00 3 . 20 SSE 0 . 02 0 .1 2 0 . 17 0 . 31 1.05 0.84 0 . 60 0 . 26 0 .1 5 0 . 01 0 . 00 3 . 55 s 0 . 01 0 . 09 0 . 10 0 . 14 0 . 45 0 . 57 0 . 50 0 . 28 0 . 20 0 . 02 0 . 00 2 . 37 SSW 0 . 03 0 . 10 0 . 10 0 . 05 0 . 17 0 . 18 0 . 28 0 . 22 0 . 32 0 . 07 0 . 01 1. 52 SW 0 . 06 0 . 09 0 . 06 0 . 05 0 .1 0 0 . 10 0 . 07 0 . 10 0 . 19 0 . 07 0 . 01 0 . 90 WSW 0 . 03 0 . 11 0 . 08 0 . 08 0 .1 2 0 . 11 0.08 0 . 03 0 . 03 0 . 00 0 . 00 0 . 67 w 0 . 06 0 . 20 0 . 15 0.16 0 . 24 0 . 16 0 . 10 0 . 04 0 . 02 0 . 00 0 . 00 1.13 WNW 0 . 05 0 . 39 0 . 32 0 . 21 0 . 48 0 . 24 0 . 13 0 . 03 0 . 02 0 . 00 0 . 00 1.88 NW 0 . 03 0.26 0 . 36 0 . 30 0 . 44 0 .25 0 . 08 0 . 01 0 . 01 0 . 00 0 . 00 1. 73 NNW 0 . 03 0 .1 6 0.32 0 . 38 0 . 62 0 . 26 0 . 06 0 . 03 0.02 0 . 00 0 . 00 1. 89 Total 0 . 44 2 . 35 3 . 11 2 . 94 5 . 72 3 . 62 2 . 30 1.13 1.11 0 . 20 0 . 04 22 . 95 Percent o f Calms 0 . 00 Percent of Invalid Hours 0 . 00 Percent of Valid Hours 22 . 95 VII - 15
A4-01 F6B73ADF3B Page 236 of 237 Omaha Public Power District Fo r t Ca l houn Nuclear Station JO I NT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY STABLE (1 . 5 < delta T/ delta z <= 4 . 0) PER I OD OF RECORD : JAN 2015 - DEC 2019 PASQUILL F WIND SPEED (m/s) AT 10 - m LEVEL Wind < 0 . 5- 1.1 - 1. 6 - 2 . 1- 3 . 1- 4 . 1- 5 . 1- 6 . 1- 8.1 - > Direct 0.5 1.0 1. 5 2. 0 3.0 4.0 5.0 6.0 8.0 10 . 0 10.0 Total N 0 . 02 0 . 05 0 . 05 0 . 06 0 . 04 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 23 NNE 0 . 02 0 . 06 0 . 03 0 . 02 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 13 NE 0 . 03 0 . 05 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0.09 ENE 0 . 01 0 . 09 0 . 06 0 . 01 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 19 E 0 . 02 0 . 13 0 . 13 0 . 05 0 . 05 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0.00 0 . 39 ESE 0 . 02 0 . 11 0 . 23 0 . 16 0.09 0 . 05 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 67 SE 0 . 03 0 . 18 0 . 28 0 . 28 0 . 37 0 . 14 0 . 06 0.02 0.00 0 . 00 0 . 00 1. 37 SSE 0 . 05 0 . 18 0 . 13 0 . 22 0 . 37 0 . 08 0.01 0 . 00 0 . 00 0 . 00 0 . 00 1. 04 s 0 . 06 0 . 17 0 . 05 0 . 08 0 . 18 0 . 12 0 . 05 0 . 01 0 . 00 0 . 00 0 . 00 0 . 74 SSW 0 . 09 0 . 16 0 . 07 0 . 03 0 . 07 0 . 08 0 . 06 0 . 02 0 . 00 0 . 00 0.00 0 . 59 SW 0 . 08 0 . 18 0 . 03 0 . 03 0 . 04 0 . 03 0.03 0 . 02 0 . 02 0 . 00 0 . 00 0 . 48 WSW 0 . 08 0 . 18 0 . 04 0 . 01 0 . 02 0 . 04 0 . 02 0 . 00 0 . 01 0 . 00 0 . 00 0 . 40 w 0 . 09 0 . 29 0.09 0 . 06 0 . 04 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 57 WNW 0 . 07 0 . 29 0 . 21 0 . 08 0 . 10 0.03 0.00 0 . 00 0 . 00 0 . 00 0 . 00 0 .7 8 NW 0.04 0 .1 2 0 . 10 0 . 05 0 . 06 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 38 NNW 0 . 02 0 . 05 0 . 05 0 . 06 0 . 07 0 . 03 0 . 01 0 . 01 0.01 0 . 00 0 . 00 0 . 30 To tal 0 . 73 2 . 32 1. 56 1. 21 1. 52 0 . 64 0 . 25 0 . 07 0 . 04 0 . 01 0 . 00 8 . 36 Percent of Calms 0 . 20 Percent o f Invalid Hours 0 . 00 Percent of Valid Hours 8 . 56 VII - 16
DocuSign Envelo pe ID: EA65F1 86-46DE-4A34-97A4-01 F6B73ADF3B Page 237 of 237 Omaha Pub li c Powe r District Fort Calhoun Nuclear Stat i on JOINT FREQUENCY DI STRIBUTION BY PERCENT EXTREMELY STABLE (delta T/ delta z > 4 .0 ) PERIOD OF RECORD : JAN 2015 - DEC 2019 PASQUILL G WIND SPEED (m/s) AT 1 0- m LEVE L Wind < 0 . 5- 1.1- 1. 6- 2 .1- 3 .1- 4 . 1- 5 . 1- 6 .1 - 8 . 1- > Direct 0.5 1.0 1. 5 2.0 3.0 4.0 5.0 6.0 8.0 10 . 0 10 . 0 Total N 0 . 01 0 . 04 0 . 02 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 09 NNE 0 . 03 0 . 04 0 . 02 0 . 01 0 . 00 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 10 NE 0 . 03 0 . 07 0 . 00 0 . 00 0 . 00 0 . 01 0 . 00 0.00 0 . 00 0 . 00 0 . 00 0 .1 2 ENE 0 . 04 0 . 11 0 . 03 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 20 E 0 . 05 0 . 11 0 . 06 0 . 02 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 25 ESE 0 . 06 0 . 20 0 . 38 0 . 08 0 . 02 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 74 SE 0 . 05 0 . 23 0 . 17 0 . 08 0 . 05 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 60 SSE 0 . 07 0 . 20 0 . 13 0 . 08 0.02 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 50 s 0 . 04 0 . 19 0.05 0.03 0 . 03 0 . 02 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 38 SSW 0 . 05 0 . 18 0 . 03 0 . 02 0.02 0 . 02 0 . 01 0 . 00 0 . 00 0 . 00 0.00 0 . 32 SW 0 . 05 0 .1 8 0 . 02 0 . 00 0.01 0 . 01 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 30 WSW 0 . 05 0 . 08 0 . 02 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 17 w 0 . 04 0 . 09 0 . 03 0 . 02 0.01 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 18 WNW 0 . 01 0 . 05 0 . 03 0.02 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0 . 00 0. 1 2 NW 0 . 02 0 . 04 0 . 03 0 . 01 0 . 00 0 . 00 0 . 00 0 . 00 0.00 0 . 00 0 . 00 0 .11 NNW 0 . 00 0 . 02 0 . 02 0.02 0 . 01 0 . 02 0 . 05 0 . 00 0 . 00 0 . 00 0 . 00 0 . 14 Total 0 . 62 1.85 1.04 0 . 41 0 . 18 0 . 11 0 . 07 0.02 0 . 00 0 . 00 0 . 00 4 . 31 Percent of Calms 0 .1 8 Percent of Invalid Hour s 0 . 00 Percent of Valid Hours 4 . 49 Percent of Hours Accounted For : 100 . 00 VII - 17
Page 1 of 49 Enclosure 2 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 01, 2022 - December 31, 2022
Page 2 of 49 Annual Radiological Environmental Operating Report This report is submitted for the period January 01, 2022 through December 31, 2022. In addition, this report provides any observations and anomalies that occurred during the monitoring period . Reviewed by : Approved by: (lDocuSigned by: D~ ()J/uSUY C9 I 00965920 / 4SF ... RP/Chem Supervisor Manager-RP/Chemistry u~~n M'edrm Z ~~,mr::-...- - - - - Plant Manager Decommissioning Senior Director of Nuclear Decommissioning
4F-8E54-0375E3280E42 Page 3 of 49 Annual Radiological Environmental Operating Report The Fort Calhoun Station (FCS) Annual Radiological Environmental Operating Report for the year 2022. The data provided is consistent with the objectives as specified in Section 6.2.2 of the Offsite Dose Calculation Manual (ODCM) , "Annual Radiological Environmental Operating Report." The report is presented as follows :
- 1) An introductory discussion of the implementation of the Radiological Environmental Monitoring Program (REMP) , including program observations and environmental impact relevant to the operation of FCS .
- 2) The sample class, sample collection frequency , number of sample locations, and the number of samples collected during this reporting period for each parameter is delineated in Table 1.0.
- 3) A statistical evaluation of REMP data is summarized in Table 2.0. For each type of sample media and analysis , Table 2.0 presents data separately for all indicator locations, all control (background) locations, and the location having the highest annual mean result. For each of these classes, Table 2.0 specifies the following :
- a. The total number of analyses,
- b. The fraction of analyses yielding detectable results (i.e., results above the highest Lower Limit of Detection (LLD) for this period) ,
- c. The maximum, minimum, and average results ,
- d. Locations with the highest annual mean are specified by code , name, and by distance and direction from the center of the plant reactor containment building .
- 4) Table 3.0 is a listing of missed samples and explanations
- 5) Table 4.0 is the 2022 Land Use Survey
- 6) Review of Environmental Inc. Quality Assurance Program
- 7) Appendix A describes the lnterlaboratory Comparison Program
- 8) Appendix B describes the vendor Data Reporting Conventions utilized
- 9) Appendix C is the Sample Location Maps Page 1 of 13
71-414F-8E54-0375E3280E42 Page 4 of 49 INTRODUCTION Radiological Environmental Monitoring Program (REMP) - 2022 This report gives the results of the Radiological Environmental Monitoring Program (REMP) for the year 2022. The REMP is a requirement of the Fort Calhoun Station (FCS) Quality Assurance Topical Report (QATR) . It was initiated before plant operation in 1973. The main purpose of the REMP is to ensure public safety by monitoring plant discharges and assessing the effect, if any, of plant operations on the environment. Samples are collected that would account for various exposure pathways such as ingestion , inhalation , adsorption, and direct exposure . Samples collected regularly include ; air, surface water, groundwater, milk, vegetation, fish , sediment, and food crops . Direct radiation is measured by thermoluminescent dosimeters (TLDs). These samples and TLDs are sent to an independent vendor laboratory for analysis. The vendor uses analytical methods that are sensitive enough to detect a level of activity far below that which would be considered harmful. Locations for sample collection are based on radiological and meteorological data from the Annual Effluent Release Report and information obtained from the Environmental Land Use Survey. Most samples, particularly indicator samples , are collected in a circular area within a five-mile radius of plant containment. (However, control locations are usually outside of five miles.) This circle is divided into sixteen equal sectors, each assigned an identification letter "A" through "R" (note: letters "I" and "O" are not used, as they may be mistaken for the numbers "1" and "O"). Sector "A" is centered on North or zero degrees. Sectors are also given directional labels such as "West-Southwest" ("WSW"). Sample locations are listed by number along with their respective distances and direction from plant containment, in the Offsite Dose Calculation Manual (ODCM) . When assessing sample results , data from indicator locations (those most likely to be affected by plant operations) are compared to those from control locations (those least or not likely to be affected) . Results from an indicator location that were significantly higher than those from a control location could indicate a plant-attributable effect and could require additional investigation . The results of the sample analyses , as required by the FCS Offsite Dose Calculation Manual (ODCM), are presented in the attached statistical tables . Sample collection was conducted by plant chemistry/environmental staff. A contracted vendor (Environmental Inc., Northbrook, Illinois) performed sample analyses , preparation of monthly reports and the statistical evaluation of sample results. All vendor analysis techniques met the sensitivity requirements as stated in the ODCM . Results for 2022 were within expected ranges and compared closely with historical results. The result details and exceptions are listed in the following sections . Page 2 of 13
Page 5 of 49
- 1) Ambient Gamma Radiation Ambient gamma radiation is measured by thermoluminescent dosimeters (TLDs) provided by the vendor laboratory. These dosimeters contain calcium sulfate phosphors and are processed quarterly.
One incident condition report was documented in the Corrective Action Program in 2022 related to TLD sampling. One TLD was lost and could not be located; TLD O-CONT. The sample was added to Table 3.0 as a missed sample . All sample results are within the range of historical data and displayed less than 10% difference when compared to historical averages. All results were less than 3 sigma standard deviations from historical means. No discrepancy between released effluents and the resultant radiation dose measured was observed. No changes in plant operation/procedures are required based upon observed impacts to the environment to date. Twelve TLDs were added to the station 's ODCM. These TLDs were placed within the owner-controlled area to assist with the determination of 40 CFR 190 doses. These locations are not included in Table 1.0 but are being described to assist reviewers of vendor analysis records . 10-Year Trend Comparison of TLD Locations Location Avg . Dose (mr/week) 2022 Avg . Dose (mr/week) A 1.28 1.05 B 1.38 1.28 C 1.29 1.33 D 1.14 1.18 F 1.28 1.28 G 1.26 1.18 H 1.29 1.35 I 1.44 1.30 J 1.49 1.43 K 1.41 1.35 N 1.50 1.40 0 1.45 1.45 p 1.49 1.43 s 1.58 1.50 L (Control) 1.27 1.23 Page 3 of 13
DocuSign Enve lope ID: 14AB1 42A-3871 -41 4F-8E54-0375E3280E42 Page 6 of 49
- 2) Milk/Pasture Milk samples or pasture grasses, if milk is temporarily unavailable, are collected monthly for the entire calendar year. Indicator samples are collected from a herd of milk goats at a family farm located approximately 3.3 miles from the plant in Sector K (Southsouthwest) . The control samples are collected from a commercial dairy cow herd located approximately 9.9 miles from the plant in Sector J (South). No indicator milk samples were available until spring (May) due to the dairy owners suspending operations. Pasture grass in place of milk was collected at the indicator location due to unavailability.
All sample results for Cesium-134 , Cesium-137 , and other gammas were at the LLD for both indicator and control locations. No plant-related effects were observed .
- 3) Fish Fish are collected on an annual basis. Control samples are collected at a location approximately twenty miles upstream of the plant (river miles 665 - 667) . Indicator samples are collected in the immediate vicinity of the power plant (river miles 644 - 646) . Several species of fish , important to commercial and recreational interest, representing all levels of the aquatic food chain are collected at both locations.
All sample results are within the range of historical data. Results from both control and indicator locations were less than LLD for all gamma emitters , indicating no plant-related effects.
- 4) Food Crop Based on the results of the biennial Land Use Survey, the nearest high deposition pathway for food crops is the Alvin Pechnik Farm in Sector H (0.94 miles, 163°). Accordingly, vegetable samples were collected at Alvin Pechnik Farm for the 2022 REMP .
Samples were comparable with historical results and with in the range of results reported from the control location garden at Mohr Dairy. All results were at the LLD for all non-naturally occurring radionuclides . No plant-related effects were observed.
- 5) Sediment River sediment samples were deleted from the program due to shoreline sediment not being a significant pathway and reduced volume of effluent release and activity .
Page 4 of 13
Page 7 of 49
- 6) Air Monitoring Air sample results for 2022 were well within historical limits for all locations. Additionally, all indicator locations showed results very similar to the control locations.
All sample results are within the range of historical data. All indicator locations displayed less than 32% difference when compared to the historical average . All 2022 results when compared to historical averages are within the stated vendor error acceptance tolerance. Results from both control and indicator locations were less than LLD for gamma emitters and iodine. No changes in plant operation/procedures are required based upon observed impacts to the environment to date. 10-Year Trend Comparison of Air Sampling Locations Location Avg . Beta (pCi/m 3 ) 2022 Avg . Beta (pCi/m 3 ) Sector B 0.026 0.032 Sector D 0.026 0.028 Sector I 0.023 0.026 Sector J 0.024 0.029 Sector K 0.025 0.033 Sector F (Control) 0.027 0.032
- 7) Surface Water Water samples are collected upstream of the plant (control location) as well as half-mile downstream and at a municipal water treatment plant on the north edge of Omaha .
Results for Cs-134, Cs-137, and other gammas were all less than LLD. All tritium results were less than LLD . No plant-related effects were detected .
- 8) GroundWater Quarterly residential well water samples are collected at the following four locations: Station No. 15:
Smith Farm , Station No . 20: Mohr Dairy, Station No. 74 : D. Miller Farm, and Station No. 75 : Lamp Acreage. All sample results to date have been at the LLD except gross beta due to naturally occurring radionuclides. Gross beta results have ranged from a low of 2.2 pCi/liter to a high of 4.8 pCi/liter, with an average gross beta for the year of 3.4 pCi/liter for indicator locations. Strontium-90 analysis is being conducted on the wells as part of the station 's groundwater monitoring protection program. No plant-related effects were detected . Page 5 of 13
Page 8 of 49 Table 1.0 Sample Collection Program Collection Number of Samples Sample Class Frequency Sample Collected this Locations Period Background Radiation (TLDs) Quarterly 484 191 5 Air Particulates Weekly 6 312 Airborne Iodine Note 6 0 oa Milk Monthly 2 26 1 Surface Water Monthly 3 36 Groundwater Quarterly 4 16 Fish Annually 2 52 Sediment Note 6 0 oa Food Crops Annually 3 93 TOTAL 595 Note 1: Milk sample collection total includes 4 vegetation samples performed for milk unavailability. Milk samples are collected monthly for the entire year. Note 2: Includes one background sample. Note 3: Variety of samples collected during period Note 4: Twelve sample locations were added for assessing 40 CFR 190 doses. The results are not included in REMP program totals. Note 5: See Table 3.0 for explanations. Note 6: Deleted from program. Page 6 of 13
DocuS ign Envelope ID: 14AB142A-3871-414F-8E54-0375E3280E42 Page 9 of 49 Table 2.1 Radiological :ErnvironmaJta1 Mornitoring P,rogr.im SummnarJ Reporting Period January-December, 222 N,ame ofF a ty Fort Ca'lhomn ~. l'ea;rP'ower Sta'tion - 'Uniit I Docket No. EID-285 Locaoo11 oi Facility Washingtn
- l'lal.ras:ka
( Oovmtiy. Sllate j
*1111dii:ator Location with Highest Control N.nml!,ar Sample Type and Loca'liol'ls l!.nn w.al Mean l ocations tfon-Type Number of LL[)~ Me-an, (Fj" Mean (Ft Mean (F)° ,Rawline (Units) Anal~*ses* Ral'lg:e* locat10n,; I Rang,e* Range* Results" Elackgrownd Gamma 239 0 .5 1.3 {2321'2.~ j OID-11<,{I U l {4l'4 ) L:2 (7fl) jJ Radiation r[ Cl!6-2:. :1 0,6 1 @25 ° U -2.0 /-S-1 .5}
{TU)) 2:!0 {1/1) (mRlweek) Airborne GS 312 O. Oclii 0.1129 t'2-.J;J'2n"ililJ OAP-I<-{!) 0.033 {52i'52} 0.032 (521-52\ Particulates l).111 1 1-0.~94) 0 .6- rmii. @ 163 * {'.011-0. 094) ~0.012-0.168) (p Cil'm~t GS 24 Cs-1.34 0.001 < LLEII - - < LLD 0 Cs-137 0 .00*1 < l l !IlJ - - < LLD 0 Otne,- Gammas 0..001 < LLD - - < LLD a Airborrne 1-131 0 0.07 < LW - - < LLD 0 Iodine jpCil'm3J Mil 1-131 22 11.- < LLIJJ - - < LLD 0 (pCill} GS 22 K4D Wi 1742 ,[)mf9!1r r,l'JllerFami 1742 {Qf9) 12:8 1 {13113) ' { f 1&0-2 15) ,o.18 rni. @ 208 * (1 lci!l-201.5) {11 11- 1398) Cs-134 15 < LLIJJ - - < LLD ,a Cs-137 15 < llllJ1 - - < LLD D OllheGa.mmas 15 < LLD - - < LLD jJ G round Wate-r GB 16 3-A {IIJ'tlj lamp J<,creage 4.3 {3/4 ) 3.5 (4/4 ) ro cr,Cill) (2.2-'l.8J 0..65 lillli .@163" (3.@-4.5) (2.2-5. l ) 1-1-3 16 3.~,a < LLIJJ - - < LLD ,0 Sr-9 16 .7 < llli]r - - < LLD GS HI (pCill.) Cs-134 15 < LL[JI - - < LLD 0 Cs-137 18 < LLOJ - - < LLD 0 Other Gammas 15 < LLIJJ - - < LLD 0 Surace Water GS 36, (pCilt.) Cs-134 15 < l l [JI - - < LLD a Cs- 137 18 < Ll [i) - - < LLD a Other Gammas 15 < LLD - - < LLD a
.H-3 12 30@ < l l[]I - - < LLD ,o Page 7 of 13
DocuSign Enve lope ID: 14AB 142A-3871-414F-8E54-0375E3280E42 Page 10 of 49 Table 2.1 Radiological EnuironP.RP..Il~ r1t onitoring P rogram Su mmary Reporting Period Januaiy--Oecember, 2022 Nameo* Fa Fort Calhoun Iear Power Station
- Un* Dock.et No. 50-2-85 Location Di Facrnty Indicator Loca
- n with Highest Con rol t>lumber Sample Type and l ocations Annual Mean Locations Non-Type Number ,of LL!li" Mean. (Ff Mean (Ft Meara (F f Rou tine IUrnitsl Analyses* R<1A ge' Locationd Range' Rarng:e ' Results" Fish GS 5
{pCilg v1el) Mn-54 11.0,16 < LLD . . < LLD 10 Co-5S 11.02,tl < LLD - - < LLD a CCKl!l .cm < LLD - - < LLD a Fe-5'£1 O.CI 4 < LLD - < LLD a Zn-oo ID..04ii! < LLD - < LLD a Ru-1100 II.0G2 < LLD - < LW a Cs- 134 0..002 < LLD - - < LLD a Cs- 137 11.0'22 < LLD - - < LLD a Sediment GS (I pCilg dry Mn-54 11 . 0!II < LLD - - < LLD 0 Co-58 . O!l < LLD - < LLD a Co-60 ID.001]1 < LLD - - < LLD a Fe-54!1 @. o ,m < LLD - < LLD 0 Zn-65 o.o < LLD - < LLD 0 Cs-1 34 ID.ODO < LLD - - < LLD 0 Cs-13 1 Ill. < LLD - - < LLD a Food Crops GS ~ fpCilg v1elj Mn-54 o.rza < LLD - < LLD 0 Co-EIB 1m.02 1 < LLD - < LLD a Co-60 11.0Q.1 <U D - - < LLD a Fe-5/l! II.CM4 < LLD - - <U O a ZM-a6 11.04111 < LLD - - < LLD *0 Zr-Nb 1n1.orz*m < LLD - - < LLD 0 Cs- 134 !Jl.024 < LLD - - < LLD a Cs-137 ID.0G7 < LLD - < U O ,a Sa-L<1- 140 ID.OQ4 < LLD - - < LLD 0 Vegetation GS 41 (pCilg welj Mn-o4 IR.~ < LLD - - < LLD a Co-5-.S .0341 <U O - < LLD ,a Pasture grass Co-60 IIIl,CMIII < LLD - < LLD a irn tieu of~ Fe-::i@ lil.Ociil < LLD - - < LLD ,a Zn-65 Iii.DSC < LU) - < LLD ,0 Zr-Nb ll.054 < LLD - - < LLD a 1-131 lll.057 < LLD < LLD a Cs-1341 0 . .;6 < LLD - - <U D a Cs- l 31 ID..06 < LLD - - <U D a Ba-La-140 11.044 < LLD - - < LLD a
- GB = gross b eta, GS = gamma s,i:am,
- LLD = nomin lm-.ier it of d etection b a~ o,n a 95*,~- oonfideoce level.
c Mean and range are based o n * : tectab.le m eusur:ements only (i.e., >llil ) Fra"..tion of detectable rne asuremc ts at specified calfans Page 8 of 13
Page 11 of 49 Table 3.0 Listing of Missed Samples (samples scheduled but not collected) Sample Date Location Reason Type TLD 3rd Quarter CONTROL-00 Lost and could not be found (CR 2022-00260) Page 9 of 13
0 0 () C CJ)
<0' rn (1)
Table 4.0 - 2022 Land Use Survey 0 "O (1) q t FORT CALHOUN STATION FC -801 ~
.i:,.
C HEMISTR Y FORM REV 1 I\.) 2022 Page 1, of 3 =!>
~
Environmental Land Use Survey Report :::;! Secto1 Dir Land Use Owne r Miles Meters Deg Survey I A.ae- GrouD I XOQ DOQ Rcmark:s ~
.i:,.
Technique ~ ;; ~ ~
~ ~ *u i:: T1 Ol rn A I N RESIDENCE WRIGHT 4.36 7016.7L 351 CITY REGISTEF XX 1.306-07 4.SOE- 10 U1
.i:,.
MI LK ANIMAL 6 MEAT ANIMAL w
---i VEGETATION U1 rn GROUNDVI/ATER WRIGHT 4.36 70 16.7~ 351 CITY REGISTEF XX w I\.)
B INNE RES IDENCE RAND,J 1.93 3 106.0< 12 CITY RE GISTEF X 7.0DE-07 1.90E-09 ~ M ILK ANIMAL rn
.i:,.
I\.) MEAT ANIMAL DUGDALE,D 4.72 7596. 1( 29 CITY REGISTEF X 1. 10E--07 2.20E- 10 VEGETATION SHEPARD 2 .23 3588.8L 16 CITY REGISTEF X X 4.60E-07 1. 20 E- 09 GROUNDWATER RAND,J 1.93 31 06.0° 12 CITY REG ISTEF X C I NE RESIDENCE THIELE 1. 59 2558.81: 52 MAIL SURVEY X 9.60E-0 7 2.00E-09 MI LK ANIMAL MEAT ANIMAL VEGETATION VENNER , R 3. 20 5149.9{ 4.S CITY REGISTEF X 1. ?0E-0 7 3.00E-10 G ROUN DVIIATER THIELE 1.59 2558.8c 52 MAIL SURVEY X D IENE RESIDENCE MEADE, G 4.7'9 770 8.7 63 CITY REGISTEF X 8. BOE-0 8 9. 70 E -11 MI LK ANIMAL MEAT ANIMAL VEGETATION MEADE, G 4.79 7708.7 63 CITY REG ISTEF X 8.BOE-08 9.70E- 11 GROUND'.VATER MEADE, G 4.79 7708.71: 63 CITY REGISTEF X E I E RESIDENCE LOVE 4.67 75 15.6~ 89 CITY REGISTEF XX 1.10E-0 7 1.60E-10 MILK A NIMAL MEAT ANIMAL BROTHERS , D 4.91 7901.8f 90 CITY REGISTE F X 1. 00E-07 1.40E-10 VEGETATION G ROUN DVV'A TER LO V E 4 .67 75 15.6~ 89 CITY REGISTEF X X F !ESE RESIDENCE VV ILSON ISLAND 4.22 6791.4 1 2 1 INTERVIEW XX X 2.0DE-07 2 .70 E- 10 MILK AN I MAL MEAT ANIMAL VEGETATION 'N ILSON ISLAND 4.22 6791.4:: 121 INTERVIE 1,*,* XX X 2.00E-Oi 2. 70E- 10 GROUND\/1/ATER 1NILSON ISLAND 4 .22 6791.4 " 121 INTERV IE'N XX X G I SE RES IDENCE BELEKELSEE 1. 67 2687.6( 145 CITY REG ISTEF X 1. 5DE-0 4.20E-09 "'U MILK AN IMAL Ill (Q MEAT ANIMAL (D VEGETATION AMBERG, L 2. 15 3460 .0 E 1 28 CITY REGISTEF XX 7.40E-0 7 2 .00E -09 ....... N GROUNDVVATER HOVVE LL ,J 1.71 2751 .9-* 145 CITY REGISTEF X 0
.i::,..
co Page 10 of 13
0 0 n C en cc* rn (1) 0 Table 4.0 - 2022 Land Use Survey "O (1) 0 FORT CAL HOUN STATION FC - 80 1 CHEM I STRY FORM 2022 REV 1 Page 2 of 3 t
~
Environmental Land Use Su rvey Report .i,. N
)>
Secto1 D ir L an d Use Owner Miles Meters Deg Survey I Ao,, ,G rouo I XOQ DOQ Rema rks ~ Techn i que
~c( : ~u j= ~
~
~
H I SSE RES IDEN CE LO MP .65 1046 .0, 163 IN1ERVIEW X 6 .70E-0 6.00E-08 .i,. MILK AN I MAL 71 co MEAT ANIMAL rn U1
.i,.
V EGETATION PECHN IK,A .94 15 12.7E 163 MAIL SURVEY X 3.C,O E-0 2.70E-08 6 GROUNDVVAT ER LOMP .65 1046.0 , 163 IN1ERVI EW X w
---J J I s RES IDEN CE DOWLER .73 11 74 .8, 1 75 MAIL SURVEY X 4.20E-0 2. 70E-08 U1 rn MILK AN I MAL w N
MEAT ANIMAL co 0 VE GETA TION DOW LER .73 11 74.8, 175 MAI L SURVEY X 4.20E-0 2.70E-08 rn 11 74.8, 175
~
GROUNDWATER DOVI/ LE R ..73 MAIL SURVEY X K I SSW RESIDENCE D . MILL ER .65 1046 .0 1 203 IN1ERVIEW X 4 . 30E-0 1.40E--08 MILK AN I MAL C. MIL LER 3.30 53 10. 8< 2 10 IN1ERVIEW X 9.10 E-Oe 2 .30E-10 MEAT AN IMAL VEGETATION ANDERSO N ,W .9'9 1593 .21 1 96 MAIL SURVEY X 1. 70E-0 5. 70E-09 G ROUN DVI/A TER D.MILLER .65 1046.01 203 IN 1ERVI EW X L I S 'N RES IDEN CE ROBERTSON ,D .73 11 74 .8, 224 MAIL SURVEY X X 3.20E-0 8.SOE-09 MILK AN I MAL BARRERA 4 .20 6759 .2< 2 19 CITY REGISTE F XX X 6.40E-Oe 1.20E-10 MEAT ANIMAL RYDER .76 1223 .1{ 227 CITY REG ISTEF X 3.WE-0 7.BOE-09 VEGETAT ION BURG IN 1.43 2301. 3, 223 CITY REGISTE F X 6.20E-07 1.50E-0 9 GROUNDWATER ROBERTSON ,D .73 1174.8 224 MAI L SURVEY XX M IV1,.'SV1,1 RESIDENCE BENSEN ,M 1.06 1705.9{ 257 CITY REGISTEF X 1.60E-0 4.20E -09 MILK AN I MAL M EAT ANIMAL V EGETATION THOMAS 1.1 3 18 18.5, 259 MAIL SURVEY X X 1. 30E-0 3.SOE-09 GROUNDWATER BENSEN, M 1.06 1705 .9( 257 CITY REGISTEF X N I v,., RESIDENCE NIELSEN 1.20 1931.2 1 263 CITY REGISTE F X 1.SOE-0 4 . 10E-09 MILK AN I MAL MEAT ANIMAL ANDERSON ,J 3.25 5230 .3, 281 MAI L SU RVEY X 1. 40E-0 7 3.00E-10 V EGETATION JOHNSON , M 2. 71 4361.3 279 MAI L SURVEY X 2 .00E-0 7 4.60E-10 GROUND 1NATER KEAS , J. 1.30 2092 .1 1 270 CITY REGISTEF X X p i'NN\*, RE SID ENCE LYTLE 2.60 4184.2 1 283 MAI L SURVEY X 3.40E-07 7.BOE-10 MILK ANIMAL 7J Ill MEAT ANIMAL BROINN 4.59 7386.8~ 288 MAIL SURVEY X 1. 30E-07 2.40E-10 (0 (D VEGETATION TABOR 2.65 4264.7{ 285 CITY REGISTEF XX X 3.20E-0 7 7.40E-10 GROUND 1NAT ER LYTLE 2.60 4 184.2I 2 ,83 MAIL SURVEY X (,) 0
~
co Page 11 of 13
0 0 () C (/) cc* rn CD Table 4.0 - 2022 Land Use Survey 0
--0 CD CJ
~
FORTGALHOUN STATION FC-80 1 t
~
CH EM ISTRY FORM REV .j:>. 2022 Page 3 of 3 N
)>
~
Environmental Land Use Su rvey Report ":j_
.I,,.
Secto1 Di.r Land Use Owner Miles Meters Deg Survey Ao,; GrouD XOQ DOQ Remarks -IS-Technique "3 ; ~ ; Tl 00
<""' ~ -
~41 V.S rn U1
-IS-Q NW RESIDENCE HANSEN ,R 2.40 3862 .4° 3 18 CITY REG ISTER X 5.20E-07 1.90E-09 6 w
MILK AN IMAL ..... U1 M EAT ANI MAL rn w N V EGETATION HANSEN,R 2.40 3862.4° 318 CITY REG ISTE R X 5.20E-0 7 1.90E-09 ~ GR:OUND 1NATER HANSEN ,R 2.40 3862.4~ 3 18 CITY REG ISTER X m R NN VV RESIDENCE LONGV IEW PARK 2.08 3347 .4~ 330 CITY REGISTER X 8.20E-0 7 3.40E-09 t MILK ANIMAL M EAT ANIMAL V EGETATION GROUNDlNATER CLARK , D 3.73 6002.B ~ 328 CITY REG ISTER X Performed by_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Reviewed by _______________________
""O Ql cc CD
~
0 Page 12 of 13 ~ (0
Page 15 of 49 Review of Environmental Inc., Quality Assurance Program Fort Calhoun Station contracts with Environmental Inc., Midwest Laboratory (vendor lab) to perform radiological analysis of environmental samples. Environmental Inc. participates in inter-laboratory comparison (cross-check) programs as part of its quality control program . These programs are operated by such agencies as the Department of Energy, which supply blind-spike samples such as milk or water containing concentrations of radionuclides unknown to the testing laboratory. This type of program provides an independent check of the analytical laboratory's procedures and processes and indicates possible weaknesses . In addition , Environmental Inc. has its own in-house QA program for blind-spike and duplicate analyses . Routine FCS REMP duplicate samples were analyzed by the vendor to verify the reproducibility of results . All duplicates were within the acceptance criteria . Environmental resource cross check samples ERDW-95 failed slightly above the acceptance criteria for CS-137 and it is believed that detector drift could have contributed to the original Cs-137 result landing outside the upper acceptance limit. ERDW-2091 for Ra-226 failed below the acceptance limit and no cause for the failure could be identified . Two DOE MAPEP cross check samples failed in 2022 . MADW-500 for U-234 and U-238 failed for the known activity. The cause of the failure was due to a different dataset mistakenly input into the MAPEP system . If the correct dataset had been entered they would have been within the acceptance range. MAAP-502 for Co-57 and Sr-90 failed for the known activity. The Co-57 failure was likely due to MAPEP adding Eu-152 as an interference to Co-57 . This satisfies MAPEP criteria for passing a "false positive" test. The Sr-90 analysis was repeated and the result was within the acceptance range. No test results failed both the ERA and DOE methodologies for a given sample type . Reanalysis produced acceptable results, so no further action is necessary. The ordering of additional tests and successful testing after corrections were applied , visibly demonstrates the vendor's commitment to reporting and resolving deficiencies. These results indicate the vendor's ability to self-identify and correct any deviations from acceptable or expected results. The test results had no impact on Fort Calhoun samples and were documented as such by the vendor. No changes are deemed necessary to the FCS REMP program due to vendor performance. Page 13 of 13
DocuSign Enve lope ID: 14AB142A-3871 -414F-8E54-0375E3280E42 Page 16 of 49
~ * , ATI E~vironmental, Inc.
Jtlli( /""\I Midwest Laboratory 700 Landwehr Road
- Northbrook, IL 60062-23'10 phone (847) 564-0700
- fax (84 7) 564- 4517 APPENDIX A INTERLABORATORY AND INTRALABORATORY COMPARISON PROGRAM RESULTS NOTE : Appendix A is updated four times a year. The complete appendix is included in March, June, September and December monthly progress reports only.
January, 2022 through December, 2022
Page 17 of 49 Appendix A lnterlaboratory/ lntralaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971 . These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems. Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used . Results in Table A-1 were obtained through participation in the RAD PT Study Proficiency Testing Program administered by Environmental Resource Associates , serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Table A-2 lists results for thermoluminescent dosimeters (TLDs), via irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center. Table A-3 lists results of the analyses on intralaboratory "spiked" samples for the past twelve months . All samples are prepared using NIST traceable sources. Data for previous years available upon request. Table A-4 lists results of the analyses on intralaboratory "blank" samples for the past twelve months . Data for previous years available upon request. Table A-5 lists analytical results from the intralaboratory "duplicate" program for the past twelve months. Acceptance is based on each result being within 25% of the mean of the two results or the two sigma uncertainties of each result overlap. The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program. Results in Table A-7 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML). Attachment A lists the laboratory acceptance criteria for various analyses . Out-of-limit results are explained directly below the result. A-1
Page 18 of 49 Attachment A ACCEPTANCE CRITERIA FOR INTRALABORATORY "SPIKED " SAMPLES Analysis Ratio of lab result to known value. Gamma Emitters 0.8to1 .2 Strontium-89, 0.8 to 1.2 Strontium-90 Potassium-40 0.8 to 1.2 Gross alpha 0.5 to 1.5 Gross beta 0.8 to 1.2 Tritium 0.8 to 1.2 Radium-226 , 0.7to1 .3 Radium-228 Plutonium 0.8 to 1.2 lodine-129, 0.8 to 1.2 lodine-131 Nickel-63, 0.7 to 1.3 Technetium-99, Uranium-238 lron-55 0.8 to 1.2 Other Analyses 0.8 to 1.2 A-2
Page 19 of 49 TABLE A-1 . lnterlaboratory Comparison Crosscheck program , Environmental Resource Associates (ERA) ". RAD study Concentration (eCi/L) Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance RAD-128 Study ERDW-95 1/10/2022 Ba-133 67.4 +/- 4.3 63.0 52.4 - 69.4 Pass ERDW-95 1/10/2022 Cs-134 82 .6 +/- 4.1 84.9 69.6 - 93.4 Pass ERDW-95 1/10/2022 Cs-137 35.4 +/-4.6 29.3 25.2 - 35 .3 Fail b ERDW-95 1/10/2022 Co-60 104 +/-4 102 91 .8-114 Pass ERDW-95 1/10/2022 Zn-65 356 +/- 13 312 281 - 384 Pass ERDW-97 1/10/2022 Gr. Alpha 30 .9 +/- 2.2 32.5 16.6 -42 .1 Pass ERDW-97 1/10/2022 Gr. Beta 62 .9 +/- 2.3 68.3 47.4 - 75 .1 Pass ERDW-99 1/10/2022 Ra-226 8.40 +/- 0.72 9.53 7.14-11.1 Pass ERDW-99 1/10/2022 Ra-228 7.25 +/- 2.32 8.71 5.59 - 11.0 Pass ERDW-99 1/10/2022 Uranium 70 .9 +/- 2.3 69.0 56.4 - 75 .9 Pass ERDW-95 1/10/2022 H-3 23 ,600 +/- 700 22,200 19,500 - 24,400 Pass RAD-130 Study ERDW-2087 8/25/2022 Ba-133 37.2 +/- 3.9 38.2 30 .9 - 42 .8 Pass ERDW-2087 8/25/2022 Cs-134 81.8 +/- 3.9 88.6 72 .7 - 97 .5 Pass ERDW-2087 8/25/2022 Cs-137 174 +/- 6 170 153 - 189 Pass ERDW-2087 8/25/2022 Co-60 76 .9 +/- 4.0 72.4 65.2 - 82 .1 Pass ERDW-2087 8/25/2022 Zn-65 349 +/- 3 326 293 - 380 Pass ERDW-2087 8/25/2022 Gr. Alpha 52 .8 +/- 2.4 60.2 31 .5 - 74.8 Pass ERDW-2087 8/25/2022 Gr. Beta 18.7+/-1.0 17.7 10.1 -25 .9 Pass ERDW-2091 8/25/2022 Ra-226 9.23 +/- 0.57 13.1 9.77-15 .1 Fail c ERDW-2091 8/25/2022 Ra-228 8.72 +/- 1.49 8.40 5.38 - 10.6 Pass ERDW-2095 8/25/2022 H-3 23 ,900 +/- 481 22 ,100 19,400 - 24,300 Pass ERDW-2089 8/25/2022 1-131 30.8+/-1 .0 27.1 23.0 - 32 .5 Pass 090622D Study ERDW-2091 9/6/2022 Ra-226 21 .5+/-1.1 19.3 14.3 - 22 .0 Pass c a Results obtained by Environmental , Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resource Associates (ERA). b The cesium-137 result did not meet ERA acceptance criteria . It is believed that detector drift could have contributed to the original Cs-137 result landing outside the upper acceptance limit. c The radium-226 result did not meet ERA acceptance criteria. An ERA Quick Response PT sample was ordered . The results were within the acceptance criteria . The reason for the earlier failing result is not known . A-3
Page 20 of 49 TABLE A-2 . Thermoluminescent Dosimetry , (TLD, CaSO 4 : Dy Cards).8 mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P) Environmental, Inc. Group 1 2022-23-1 2/7/2023 Spike 1 134.0 134.5 0.00 2022-23-1 2/7/2023 Spike 2 134.0 131 .1 -0.02 2022-23-1 2/7/2023 Spike 3 134.0 134.0 0.00 2022-23-1 2/7/2023 Spike 4 134.0 130.7 -0.02 2022-23-1 2/7/2023 Spike 5 134.0 131 .5 -0.02 2022-23-1 2/7/2023 Spike 6 134.0 139.3 0.04 2022-23-1 2/7/2023 Spike 7 134.0 134.8 0.01 2022-23-1 2/7/2023 Spike 8 134.0 130.7 -0 02 2022-23-1 2/7/2023 Spike 9 134.0 133.1 -0.01 2022-23-1 2/7/2023 Spike 10 134.0 129.9 -0.03 I 2022-23-1 2/7/2023 Spike 11 134.0 125.6 -0.06 2022-23-1 2/7/2023 Spike 12 134.0 139.5 0.04 2022-23-1 2/7/2023 Spike 13 134.0 135.2 0.01 2022-23-1 2/7/2023 Spike 14 134.0 135.8 0.01 2022-23-1 2/7/2023 Spike 15 134.0 133.6 0.00 2022-23-1 2/7/2023 Spike 16 134.0 132.7 -0 .01 2022-23-1 2/7/2023 Spike 17 134.0 125.1 -0.07 2022-23-1 2/7/2023 Spike 18 134.0 131.9 -0.02 2022-23-1 2/7/2023 Spike 19 134.0 125.3 -0.06 2022-23-1 2/7/2023 Spike 20 134.0 128.2 -0.04 Mean (Spike 1-20) 132.1 -0.01 Passd Standard Deviation (Spike 1-20) 4.1 0.03 Passd a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate . TLD's were read and the results were submitted by Environmental Inc . to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose . b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(1 0)K. = 1.20 . mrem/cGy = 1000. c Performance Quotient (P) is calculated as ((reported dose - conventionally true value) + conventionally true value) where the conventionally true value is the delivered dose . d Acceptance is achieved when neither the absolute value of the mean of the P values , nor the standard deviation of the P values exceed 0.15. A-4
Page 21 of 49 TABLE A-2. Thermoluminescent Dosimetry , (TLD , CaSO 4 : Dy Cards) _a mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P) Environmental. Inc. Group 2 2022-23-2 2/7/2023 Spike 21 70.0 71 .7 0.02 2022-23-2 2/7/2023 Spike 22 70.0 72.1 0.03 2022-23-2 2/7/2023 Spike 23 70.0 66 .2 -0.05 2022-23-2 2/7/2023 Spike 24 70.0 70 .6 0.01 2022-23-2 2/7/2023 Spike 25 70.0 71.0 0.01 2022-23-2 2/7/2023 Spike 26 70.0 71 .3 0.02 2022-23-2 2/7/2023 Sp ike 27 70.0 68.4 -0 02 2022-23-2 2/7/2023 Spike 28 70.0 70 .2 0.00 2022-23-2 2/7/2023 Spike 29 70.0 72.1 0.03 2022-23-2 2/7/2023 Spike 30 70.0 71 .2 0.02 2022-23-2 2/7/2023 Spike 31 70.0 67 .5 -0.04 2022-23-2 2/7/2023 Spike 32 70.0 68 .8 -0.02 2022-23-2 2/7/2023 Spike 33 70.0 72.2 0.03 2022-23-2 2/7/2023 Spike 34 70.0 69 .6 -0.01 2022-23-2 2/7/2023 Spike 35 70.0 69 .7 0.00 2022-23-2 2/7/2023 Spike 36 70.0 68 .0 -0.03 2022-23-2 2/7/2023 Spike 37 70.0 72 .2 0.03 2022-23-2 2/7/2023 Spike 38 70.0 70 .6 0.01 2022-23-2 2/7/2023 Spike 39 70.0 70.4 0.01 2022-23-2 2/7/2023 Spike 40 70.0 66.5 -0.05 Mean (Spike 21-40) 70.0 0.00 Passd Standard Deviation (Spike 21-40) 1.9 0.03 Passd a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13 .37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose . b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)Ka = 1.20 . mrem/cGy = 1000. c Performance Quotient (P) is calculated as (( reported dose - conventiona lly true value) + conventionally true value) where the conventionally true value is the delivered dose . d Acceptance is achieved when neither the absolute value of the mean of the P values , nor the standard deviation of the P values exceed 0.15. A-5
DocuS ign Envelope ID: 14AB142A-3871-414F-8E54-0375E3280E42 Page 22 of 49 TABLE A-3 . lntralaboratory "Spiked" Samples Concentration
- Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1 c Activity Limitsd Acceptance Lab/Known SPDW-30305 1/5/2022 Gr. Alpha 3.9 +/- 0.8 6 .3 3.1 - 9.4 Pass 0 .62 SPDW-30305 1/5/2022 Gr. Beta 65 .5+/-1 .6 75 .9 60 .7 - 91 .1 Pass 0.86 SPDW-40000 1n/2022 H-3 2 ,220 +/- 162 2 ,110 1,688 - 2,532 Pass 1.05 SPDW-40013 1/6/2022 Ra-226 12.7 +/- 0.3 12.3 8.6 - 16 .0 Pass 1.03 SPDW-40014 7/12/2021 H-3 11 ,681 +/- 345 10,400 8,320 - 12,480 Pass 1.12 SPDW-40015 7/12/2021 H-3 11 ,318 +/-340 10,400 8,320 - 12,480 Pass 1.09 SPDW-40022 2/3/2022 Ra-228 14.5 +/- 3.9 15.3 10 .7 - 19.9 Pass 0.95 SPDW-40024 2/4/2022 H-3 10,502 +/- 321 10,400 8,320 - 12,480 Pass 1.01 SPDW-40025 1/11/2021 H-3 2,278 +/- 176 2 ,110 1,688 - 2,532 Pass 1.08 SPDW-40026 1/11/2021 H-3 2 ,291 +/- 176 2 ,110 1,688 - 2,532 Pass 1.09 SPDW-40028 2/11/2022 H-3 10,594 +/- 322 10,400 8,320 - 12,480 Pass 1.02 SPDW-40037 2/25/2022 H-3 10,724 +/- 322 10,400 8,320 - 12,480 Pass 1.03 SPDW-40045 3/3/2022 Sr-90 19.2 +/- 1.1 17.1 13.7 - 20.5 Pass 1.12 SPDW -40052 3/10/2022 H-3 10,851 +/- 328 10,400 8,320 - 12,480 Pass 1.04 SPDW-40064 3/18/2022 H-3 10,795 +/- 332 10,400 8,320 - 12,480 Pass 1.04 SPDW-40073 3/22/2022 Ra-228 15.1 +/- 2.4 13.4 9.4 - 17.4 Pass 1.13 SPDW-40075 1/28/2022 Ra-226 12.2 +/- 0.3 12.3 8.6 - 16.0 Pass 0.99 SPDW-40078 3/14/2022 U-234 28 .0 +/- 2 .0 23 .0 16.1 -29 .9 Pass 1.22 SPDW-40078 3/14/2022 U-238 29 .9 +/- 2.1 23.2 16.2 - 30.2 Pass 1.29 SPW-598 3/24/2022 Fe-55 10 ,505 +/- 1,100 10,006 8,005 - 12,007 Pass 1.05 SPDW-40087 3/24/2022 Ra-226 14.4 +/- 0.4 12.3 8.6 - 16 .0 Pass 1.17 LCS-W-032222 1/10/2022 Ba-133 65.4 +/- 6.5 63 .0 50 - 76 Pass 1.04 LCS-W-032222 1/10/2022 Cs-134 87 .7 +/- 6.0 84 .9 68 - 102 Pass 1.03 LCS-W-032222 1/10/2022 Cs-137 34 .2 +/- 6.6 29 .3 23 - 35 Pass 1.17 LCS-W-032222 1/10/2022 Co-60 106 +/- 6 102 82 - 122 Pass 1.04 LCS-W-032222 1/10/2022 Zn-65 341 +/- 18 312 250 - 374 Pass 1.09 SPDW-40083 4/1/2022 H-3 10,785 +/- 329 10,400 8,320 - 12,480 Pass 1.04 LCS-W-040622 1/10/2022 Ba-133 60.4+/-7.6 63.0 50.4 - 75.6 Pass 0.96 LCS-W-040622 1/10/2022 Cs-134 91.4 +/- 6 .8 84 .9 67 .9 - 102 Pass 1.08 LCS-W-040622 1/10/2022 Cs-137 31 .7+/-8 .5 29 .3 23.4 - 35 .2 Pass 1.08 LCS-W-040622 1/10/2022 Co-60 111 +/- 7 102 81 .6 - 122 Pass 1.08 LCS-W-040622 1/10/2022 Zn-65 330 +/- 28 312 250 - 374 Pass 1.06 LCS-S0-040822 8/1/2020 Cs-134 17,126 +/- 176 19 ,189 15,351 - 23,027 Pass 0.89 LCS-S0-040822 8/1/2020 Co-57 29 ,070 +/- 356 29 ,730 23 ,784 - 35,676 Pass 0.98 LCS-S0-040822 8/1/2020 Co-60 27 ,057 +/- 166 27 ,027 21,622 - 32,432 Pass 1.00 LCS-S0-040822 8/1/2020 Mn-54 17,886 +/- 455 16 ,486 13,189 -19 ,783 Pass 1.08 LCS-S0-040822 8/1/2020 K-40 18,799 +/- 685 16,810 13,448 - 20,172 Pass 1.12 LCS-S0-040822 8/1/2020 Zn-65 14 ,460 +/- 754 12 ,703 10,162 -15,244 Pass 1.14 SPDW-40085 4/4/2022 Sr-90 17.3 +/- 1.1 17.1 13.7 - 20 .5 Pass 1.01 SPDW-40089 4/8/2022 H-3 10,677 +/- 326 10,400 8,320 - 12,480 Pass 1.03 SPDW-40130 4/8/2022 Ra-226 11.4 +/- 0.3 12.3 8 .6 -16 .0 Pass 0.93 SPDW-40098 4/11/2022 Gr. Alpha 6.7 +/- 1.1 6 .3 3.1 - 9.4 Pass 1.07 SPDW-40098 4/11/2022 Gr. Beta 71 .7 +/- 1.7 75 .9 60 .7 - 91 .1 Pass 0.94 SPDW-40102 4/14/2022 H-3 10,369 +/- 323 10,400 8,320 - 12,480 Pass 1.00
- Liquid sample resu lts are reported in pC i/Liter, air fi lters ( pCi/m3), charcoal (pCi/charcoa l canister), and solid samples (pCi/kg) .
0 Labo ratory codes : W & SPW (Water) , Ml (milk) , AP (air filter) , SO (soil), V E (vegetation) , C H (charcoal canister) , F (fish) , U (u rine) . c Resu lts are based on single determinations. d Acceptance criteria are listed in Attachment A of this report. A-6
Page 23 of 49 TABLE A-3. lntralaboratory "Spiked" Samples Concentrationa Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1 c Activi~ Limitsd Acceetance Lab/Known SPDW-40132 5/3/2022 H-3 10,834 +/- 329 10,400 8,320 - 12,480 Pass 1.04 SPDW-40142 5/5/2022 Ra-226 11 .6+/-0.4 12.3 8.6 - 16.0 Pass 0.94 SPDW-40139 5/18/2022 H-3 10,465 +/- 322 10,400 8,320 - 12,480 Pass 1.01 SPDW-40147 5/9/2022 Gr. Alpha 22.1 +/- 1.2 32.5 16.3 - 48.8 Pass 0.68 SPDW-40132 5/3/2022 H-3 10,834 +/- 329 10,400 8,320 - 12,480 Pass 1.04 SPDW-40142 5/5/2022 Ra-226 11.6+/-0.4 12.3 8.6 - 16.0 Pass 0.94 SPDW-40139 5/18/2022 H-3 10,465 +/- 322 10,400 8,320 - 12,480 Pass 1.01 SPDW-40147 5/9/2022 Gr. Alpha 22 .1 +/- 1.2 32.5 16.3 - 48 .8 Pass 0.68 SPDW-40147 5/9/2022 Gr. Beta 63.1 +/- 1.6 62.9 50 .3 - 75 .5 Pass 1.00 SPDW-40157 5/25/2022 Ra-226 10.1+/-0.3 12.3 8.6 - 16.0 Pass 0.82 SPW-1856 6/14/2022 Sr-90 17.4 +/- 2.9 17.1 13.7 - 20 .5 Pass 1.02 LCS-AP-061522 3/21/2022 Cs-134 479 +/- 10 549 439 - 0,659 Pass 0.87 LCS-AP-061522 3/21/2022 Cs-137 1,418 +/- 117 1,320 1,056 - 1,584 Pass 1.07 LCS-AP-061522 3/21/2022 Co-60 891 +/- 8 885 708 - 1,062 Pass 1.01 LCS-AP-061522 3/21/2022 Zn-65 769 +/- 18 671 537 - 0,805 Pass 1.15 SPDW-40164 6/21/2022 Ra-228 14.2+/-1 .8 13.4 9.4 - 17.4 Pass 1 06 SPDW-40167 6/23/2022 H-3 10,497 +/- 322 10,400 8,320 - 12,480 Pass 1.01 SPDW-40177 6/30/2022 Ra-226 12.1 +/- 0.3 12.3 8.6 - 16.0 Pass 0.98 SPW-1881 6/27/2022 Tc-99 97.1 +/- 1.7 107.8 75.5 - 140.1 Pass 0.90 SPDW-40253 7/12/2022 Ra-226 11 .6+/-0.3 12.3 8.6 - 16.0 Pass 0.94 SPW-40179 7/15/2022 H-3 10,467 +/- 324 10,400 8,320 - 12,480 Pass 1.01 SPDW-40200 7/26/2022 Gr. Alpha 21 .1 +/- 1.3 32.5 16.3 - 48.8 Pass 0.65 SPDW-40200 7/26/2022 Gr. Beta 61 .0 +/- 1.6 62.9 50.3 - 75.5 Pass 0.97 SPDW-40220 7/29/2022 H-3 10,553 +/- 326 10,400 8,320 - 12,480 Pass 1.01 SPDW-40212 8/9/2022 Ra-228 14.5 +/- 2.3 13.4 9.4 - 17.4 Pass 1.08 SPDW-40220 8/16/2022 H-3 10,613 +/-326 10,400 8,320 - 12,480 Pass 1.02 SPDW-40239 8/22/2022 Gr. Alpha 37.1 +/-2.0 60.2 31 .5 - 74.8 Pass 0.62 SPDW-40239 8/22/2022 Gr. Beta 16.6 +/- 0.9 17.7 10.1 - 25.9 Pass 0.94 SPDW-40255 8/12/2022 Ra-226 9.1 +/- 0.3 12.3 8.6 - 16.0 Pass 0.74 SPDW-40265 9/2/2022 H-3 10,555 +/- 325 10,400 8,320 - 13,520 Pass 1.01 SPDW-40267 9/6/2022 Ra-228 14.0+/-1.4 13.4 9.4 - 17.4 Pass 1.04 SPDW-40283 9/9/2022 H-3 10,059 +/- 318 10,400 8,320 - 12,480 Pass 0.97 SPDW-40300 8/31/2022 Ra-226 11 .2 +/- 0.3 12.3 8.6 - 16.0 Pass 0.91 SPMl-2918 9/19/2022 Sr-90 17.9 +/- 1.0 17.1 13.7 - 20.5 Pass 1.05 SPDW-40321 9/20/2022 Ra-226 13.2 +/- 0.5 12.3 8.6 - 16.0 Pass 1.07 SPDW-40305 9/21/2022 Ra-228 12.5+/-1 .8 13.4 9.4 - 17.4 Pass 0.93 SPDW-40294 9/20/2022 Gr. Alpha 35.1 +/- 2.0 60.2 31 .5 - 74 .8 Pass 0.58 SPDW-40294 9/20/2022 Gr. Beta 16.5+/-1 .0 17.7 10.1 - 25 .9 Pass 0.93 SPDW-40303 9/19/2022 H-3 10,078 +/- 316 10,400 8,320 - 12,480 Pass 0.97 SPDW-40361 10/12/2022 Ra-226 10.0 +/- 0.3 12.3 8.6 - 16.0 Pass 0.81 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3) , charcoal (pCi/charcoal canister) , and solid samples (pCi/kg) . b Laboratory codes : W & SPW (Water) , Ml (milk), AP (air filter), SO (soil), VE (vegetation) , CH (charcoal canister) , F (fish) , U (urine) . c Results are based on single determinations. d Acceptance criteria are listed in Attachment A of this report . A-7
Page 24 of 49 TABLE A-3 . lntralaboratory "Spiked" Samples Concentration
- Lab Code" Date Analysis Laboratory results Known Control Ratio 2s, n=1 ° Activity Limitsd Acceptance Lab/Known SPDW-40344 11/3/2022 Ra-228 13.2 +/- 1.8 13.4 9.4 - 17.4 Pass 0.99 SPDW-40346 11/8/2022 Gr. Alpha 42 .0 +/- 2.2 60.2 31 .5 - 74.8 Pass 0.70 SPOW-40346 11/8/2022 Gr. Beta 16.6 +/- 1.0 17.7 10 .1 - 25.9 Pass 0.94 SPOW-40352 11/17/2022 Sr-90 18.8 +/- 1.2 17.1 13.7 - 20.5 Pass 1.10 SPDW-40355 11/18/2022 H-3 10,143 +/- 316 10,400 8,320 - 12 ,480 Pass 0.98 SPDW-40364 11/30/2022 Gr. Alpha 38.4 +/- 1.5 60 .2 31 .5 - 74 .8 Pass 0.64 SPDW-40364 11/30/2022 Gr. Beta 30.9 +/- 1.2 17.7 10 .1 - 25.9 Pass 1.75 LCS-W-110822 2/1/2022 Cs-137 222 +/- 10 206 165 - 247 Pass 1.08 LCS-W-110822 2/1/2022 Co-57 1,060 +/- 117 973 778-1,168 Pass 1.09 LCS-W-110822 2/1/2022 Co-60 250 +/-8 251 201 - 301 Pass 1.00 LCS-W-110822 2/1/2022 Mn -54 537 +/- 18 511 409 - 613 Pass 1.05 LCS-W-110822 2/1/2022 Zn-65 673 +/- 35 708 566 - 850 Pass 0.95 SPDW-40372 11/21/2022 Ra-226 11 .3 +/- 0.3 12.3 8.6 - 16.0 Pass 0.92 SPU-3883 12/1/2022 H-3 21 ,694 +/- 1,387 23 ,900 19,120 -28 ,680 Pass 0.91 SPW-3950 12/1/2022 Ni-63 1,937 +/- 28 2,135 .0 1,495 - 2,776 Pass 0.91 SPDW-40366 12/2/2022 H-3 22,466 +/- 464 23 ,900 19,120 - 28 ,680 Pass 0.94 SPW-3969 12/2/2022 Ni-63 2,123 +/- 29 2,135 .0 1,495 - 2,776 Pass 0.99 SPW-3881 12/5/2022 Tc-99 85 .0 +/- 1.6 107.8 75.5 - 140.1 Pass 0.79 SPDW-40374 12/12/2022 H-3 22 ,554 +/- 463 23 ,900 19,120 - 28 ,680 Pass 0.94 SPOW-40382 12/12/2022 Ra-226 12.7 +/- 0.4 12.3 8.6 - 16.0 Pass 1.03 SPDW-40380 12/22/2022 H-3 22,200 +/- 462 23,900.0 19,120 - 28,680 Pass 0.93 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3), charcoal (pCi/charcoal canister) , and solid samples (pCi/kg) .
0 Laboratory codes : W & SPW (Water), Ml (milk) , AP (air filter), SO (soil), VE (vegetation) , CH (charcoal canister) , F (fish), U (urine). 0 Results are based on single determinations. d Acceptance criteria are listed in Attachment A of this report. A-8
Page 25 of 49 TABLE A-4. lntralaboratory "Blank" Samples Concentration* Lab Codeb Sample Date Analysisc Laborato~ results (4.66cr) Acceptance Type LLD Activiti Criteria (4.66 cr) SPDW-30304 Water 1/5/2022 Gr. Alpha 0.47 0.07 +/- 0.33 2 SPDW-30304 Water 1/5/2022 Gr. Beta 0.77 0.33 +/- 0.55 4 SPDW-40001 Water 1/7/2022 H-3 156 3 +/- 75 200 SPDW-40012 Water 1/6/2022 Ra-226 0.06 -0 .08 +/- 0.05 2 SPDW-40016 Water 7/12/202 1 H-3 165 -41 +/- 85 200 SPDW-40017 Water 7/21 /2021 H-3 165 0 +/- 87 200 SPDW-40021 Water 2/3/2022 Ra-228 1.15 0.20 +/- 0.56 2 SPDW-40023 Water 2/4/2022 H-3 162 78 +/- 81 200 SPDW-40027 Water 2/11 /2022 H-3 168 26 +/- 85 200 SPDW-40036 Water 2/25/2022 H-3 160 55 +/- 78 200 SPDW-40044 Water 3/3/2022 Sr-89 0.62 0.20 +/- 0.44 5 SPDW-40044 Water 3/3/2022 Sr-90 0.60 -0.18 +/- 0.26 SPDW-40046 Water 3/3/2022 1-131 0.12 0.04 +/- 0.08 SPDW-40051 Water 3/10/2022 H-3 161 17 +/- 78 200 SPDW-40063 Water 3/18/2022 H-3 177 60 +/- 96 200 SPDW-40072 Water 3/22/2022 Ra-228 1.20 0.29 +/- 0.56 2 SPDW-40074 Water 1/28/2022 Ra-226 0.06 0.08 +/- 0.14 2 SPDW-40077 Water 3/14/2022 U-234 0.19 0.17 +/- 0.20 SPDW-40077 Water 3/14/2022 U-238 0.19 -0 .04 +/- 0.14 SPW-597 Water 3/31/2022 Fe-55 1159 92 +/- 708 2000 SPDW-40081 Water 3/30/2022 Ra-228 1.66 0.19+/-0.79 2 SPDW-40082 Water 4/1/2022 H-3 170 60 +/- 85 200 SPDW-40084 Water 4/4/2022 Sr-89 0.51 0.28 +/- 0.41 5 SPDW-40084 Water 4/4/2022 Sr-90 0.55 0.01 +/- 0.25 SPDW-40088 Water 4/8/2022 H-3 166.00 66 .00 +/- 83 .00 200 SPDW-40129 Water 4/8/2022 Ra-226 0.01 0.11 +/- 0.02 2 SPDW-40098 Water 4/11/2022 Gr. Alpha 0.42 0.06 +/- 0.30 2 SPDW-40098 Water 4/11/2022 Gr. Beta 0.75 -0 .73 +/- 0.50 4 SPDW-40101 Water 4/14/2022 H-3 164 37 +/- 84 200 SPDW-40120 Water 4/22/2022 H-3 109 74 +/- 84 200 SPDW-40131 Water 5/3/2022 H-3 165 75 +/- 86 200 SPDW-40141 Water 5/5/2022 Ra-226 0.08 0.01 +/- 0.07 2 SPU-1297 Urine 5/12/2022 H-3 1325 674 +/- 733 200 SPDW-40138 Water 5/18/2022 H-3 163 69 +/- 80 200 SPDW-40156 Water 5/25/2022 Ra-226 0.04 0.09 +/- 0.03 2 SPW-1855 Water 6/14/2022 Sr-89 0.63 0.02 +/- 0.49 5 SPW-1855 Water 6/14/2022 Sr-90 0.57 0.00 +/- 0.26 1 SPDW-40172 Water 6/14/2022 Ra-226 0.03 0.06 +/- 0.03 2 SPDW-40163 Water 6/21/2022 Ra-228 0.84 0.30 +/- 0.43 2 SPDW-40166 Water 6/23/2022 H-3 162 46 +/- 78 200 SPW-1876 Water 6/27/2022 C-14 9.99 -9 .14 +/- 5.92 200
- Liquid sample results are reported in pCi/Liter, air filters ( pCi/m 3J, charcoal (pCi/charcoat canister), and solid samples (pCi/g).
b Laboratory codes : W & SPW (Water), Mt (milk), AP (air filter) , SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine). 0 1-1 31(G) ; iodine-1 31 as analyzed by gamma spectroscopy. d Activity reported is a net acti vity result. A-9
Page 26 of 49 TABLE A-4. lntralaboratory "Blank" Samples Concentration* Lab Codeb Sample Date Analysisc Laboratory results (4 .66cr) Acceptance Type LLD Activity Criteria (4.66 cr) SPW-1878 Water 6/27/2022 Fe-55 522 -200 +/- 306 2000 SPW-1880 Water 6/27/2022 Tc-99 11.4 -6 .0 +/- 6.8 200 SPW-1891 Water 6/28/2022 Ni-63 75.9 0.0 +/- 46.1 200 SPDW-40176 Water 6/30/2022 Ra-226 0.04 0.06 +/- 0.04 2 SPDW-40252 Water 7/12/2022 Ra-226 0.04 -0.06 +/- 0.10 2 SPDW-40178 Water 7/15/2022 H-3 167 58 +/- 83 200 SPW-2220 Water 7/21/2022 C-14 3.52 -3.15 +/- 2.09 200 SPDW-40199 Water 7/26/2022 Gr. Alpha 0.80 0.47 +/- 0.58 2 SPDW-40199 Water 7/26/2022 Gr. Beta 0.77 0.98 +/- 0.57 4 SPDW-40207 Water 7/29/2022 H-3 161 -21 +/- 84 200 SPDW-40211 Water 8/9/2022 Ra-228 1.23 0.20 +/- 0.59 2 SPDW-40219 Water 8/16/2022 H-3 161 68 +/- 80 200 SPDW-40238 Water 8/22/2022 Gr. Alpha 0.47 0.05 +/- 0.34 2 SPDW-40238 Water 8/22/2022 Gr. Beta 0.75 0.34 +/- 0.54 4 SPDW-40263 Water 9/2/2022 1-131 0.17 -0.05 +/- 0.09 SPDW-40264 Water 9/2/2022 H-3 162 82 +/- 81 200 SPDW-40264 Water 9/6/2022 Ra-228 1.11 -0.22 +/- 0.49 2 SPDW-40282 Water 9/9/2022 H-3 163 71 +/- 83 200 SPDW-40291 Water 9/16/2022 1-131 0.11 -0.01 +/- 0.08 SPMl-2917 Milk 9/19/2022 Sr-89 0.58 0.03 +/- 0.47 5 SPMl-2917 Milk 9/19/2022 Sr-90 0.51 0.30 +/- 0.27 1 SPDW-40293 Water 9/20/2022 Gr. Alpha 0.52 0.1 0 +/- 0.37 2 SPDW-40293 Water 9/20/2022 Gr. Beta 0.78 0.26 +/- 0.55 4 SPDW-40302 Water 9/19/2022 H-3 160 97 +/- 80 200 SPDW-40304 Water 9/21/2022 Ra-228 0.87 0.09 +/-0.41 2 SPDW-40311 Water 9/30/2022 1-131 0.15 0.00 +/- 0.08 SPDW-40345 Water 11/8/2022 Gr. Alpha 0.53 -0.17 +/- 0.36 2 SPDW-40345 Water 11/8/2022 Gr. Beta 0.78 -0.05 +/- 0.54 4 SPDW-40350 Water 11/11/2022 H-3 166 96 +/- 84 200 SPDW-40352 Water 11/17/2022 Sr-89 0.66 -0.01 +/- 0.53 5 SPDW-40352 Water 11/17/2022 Sr-90 0.61 0.11 +/- 0.29 SPDW-40354 Water 11/18/2022 H-3 155 21 +/- 76 200 SPDW-40354 Water 11/18/2022 1-131 0.18 -0.11 +/- 0.09 1 SPW-3880 Water 12/1/2022 Tc-99 5.58 2.99 +/- 3.44 200 SPU-3882 Urine 12/1/2022 H-3 1157 599 +/- 642 2000 SPW-3949 Water 12/2/2022 Ni-63 16.3 9.0 +/- 10.0 200 SPW-3968 Water 12/2/2022 Ni-63 15.9 0.0 +/- 9.6 200 SPDW-40370 Water 12/7/2022 1-131 0.10 -0.04 +/- 0.06 SPDW-40381 Ra-226 12/12/2022 Ra-226 0.06 -0.04 +/- 0.05 2 SPDW-40379 H-3 12/22/2022 H-3 162 107 +/- 84 200
- Liquid sample results are reported in pCi/Liter, air filters ( pCiim\ charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b Laboratory codes : W & SPW (Water), Ml (milk) , AP (air filter), SO (soil) , VE (vegetation), CH (charcoal canister), F (fish), U (urine). 0 l-131(G); iodine-131 as analyzed by gamma spectroscopy. d Activity reported is a net activity result. A-10
Page 27 of 49 TABLE A-5. lntralaboratory "Duplicate" Samples Concentration* Averaged Lab Codeb Date Analtsis First Result Second Result Result Acceptance CF-20,21 1/3/2022 Gr. Beta 7.07 +/- 0.26 7.05 +/- 0.26 7.06 +/- 0.1 8 Pass CF-20,21 1/3/2022 K-40 9.06 +/- 0.28 7.54 +/- 0.70 8.30 +/- 0.38 Pass U-135, 136 1/20/2022 Beta (-K40) 5.74+/-1 .63 3.53 +/- 1.40 4.64 +/- 1.07 Pass DW-40019,40020 1/25/2022 Gr. Alpha 5.01 +/- 1.34 6.01 +/- 1.40 5.51 +/- 0.97 Pass DW-40019,40020 1/25/2022 Ra-226 1.19 +/- 0.15 0.98 +/-0.17 1.09 +/- 0.11 Pass DW-40019,40020 1/25/2022 Ra-228 4.84 +/- 0.98 5.38+/-1 .05 5.11 +/- 072 Pass W-159, 160 1/27/2022 Gr. Alpha 3.04 +/- 3.19 3.85 +/- 2.04 3.45 +/- 1.89 Pass W-159, 160 1/27/2022 Gr. Beta 14.4 +/- 2 .7 13.1 +/- 1.5 13 .7+/-1 .5 Pass W-159 ,160 1/27/2022 Ra-226 0.94 +/- 0.19 1.11+/-0.30 1.03 +/- 0.18 Pass W-159 ,160 1/27/2022 Ra-228 3.14 +/- 0.96 3.39 +/- 0.96 3.27 +/- 0.68 Pass W-888,889 2/14/2022 Ni-63 119 +/- 47 95 +/- 48 107 +/- 34 Pass S-391 ,392 2/17/2022 K-40 11 .2 +/- 0.8 9.8 +/- 0.7 10.5 +/- 0.5 Pass DW-40040,40041 2/25/2022 Ra-226 2.78 +/- 0.21 2.01 +/- 0.22 2.40 +/- 0.15 Pass DW-40040,40041 2/25/2022 Ra-228 3.15+/-0.95 3.29 +/- 0.94 3.22 +/- 0.67 Pass AP-022821A,B 2/28/2022 Gr. Beta 0.038 +/- 0.005 0.039 +/- 0.005 0.039 +/- 0.003 Pass S-435 ,436 3/2/2022 Pb-214 1.42+/-0.11 1.29+/-0.15 1.36 +/- 0.09 Pass S-435,436 3/2/2022 Ac-228 0.94 +/- 0.20 1.06+/-0.15 1.00 +/-0.13 Pass AP-030721A,B 3/7/2022 Gr. Beta 0.038 +/- 0.005 0.038 +/- 0.005 0.038 +/- 0.004 Pass S-477,478 3/8/2022 K-40 6.58 +/- 0.23 6.73 +/- 0.24 6.66 +/- 0.17 Pass SWT-657,658 3/9/2022 Gr. Beta 1.00 +/- 0.54 1.20 +/- 0.57 1.10 +/- 0.39 Pass DW-40059,40060 3/11/2022 Ra-226 0.40+/-0.10 0.53 +/- 0.11 0.47 +/- 0.07 Pass DW-40059,40060 3/11/2022 Ra-228 0.40 +/- 0.60 0.72 +/- 0.60 0.56 +/- 0.42 Pass AP-0315221A,B 3/15/2022 Gr. Beta 0.025 +/- 0.003 0.027 +/- 0.003 0.026 +/- 0.002 Pass AP-1161 ,1162 3/29/2022 Be-7 0.07 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass DW-700,701 4/4/2022 Gr. Alpha 1.70 +/- 1.83 2.82 +/- 1.78 2.26 +/- 1.28 Pass DW-700 ,701 4/4/2022 Gr. Beta 3.33 +/- 1.26 4.29 +/- 1.30 3.81 +/- 0.91 Pass DW-700,701 4/4/2022 Ra-226 0.50 +/-0.16 0.65 +/- 0.14 0.58+/-0.11 Pass DW-700,701 4/4/2022 Ra-228 5.04 +/- 1.00 4.79 +/- 0.99 4.92 +/- 0.70 Pass SG-706,707 4/4/2022 Gr. Alpha 25 .7 +/- 3.6 21 .7 +/- 3.2 23 .7 +/- 2.4 Pass SG-706 ,707 4/4/2022 Gr. Beta 23 .2+/-1 .7 24 .5+/-1 .8 23 .9+/-1 .3 Pass SG-706 ,707 4/4/2022 Ra-226 2.47 +/- 0.10 2.62 +/- 0.09 2.55 +/- 0.07 Pass SG-706 ,707 4/4/2022 Ra-228 4.63 +/- 0.22 4.40 +/- 0.20 4.52 +/- 0.15 Pass DW-40091,40092 4/5/2022 Gr. Alpha 0.43 +/- 0.78 0.57 +/- 0.82 0.50 +/- 0.57 Pass DW-40091,40092 4/6/2022 Ra-226 0.21 +/-0.10 0.24 +/- 0.08 0.23 +/- 0.06 Pass U-951 ,952 4/13/2022 Gr. Beta 2.72 +/- 1.55 4.11 +/- 1.45 3.41 +/- 1.06 Pass U-951 ,952 4/13/2022 H-3 861 +/- 723 1,015+/-732 938 +/- 514 Pass W-1014 ,1015 4/21/2022 Ra-228 1.76 +/-0 .93 1.51 +/- 0.92 1.64 +/- 0.65 Pass W-1014 ,1015 4/21/2022 Ra-226 1.23 +/- 0.27 1.36 +/- 0.29 1.30 +/- 0.20 Pass DW-40117,40118 4/26/2022 Ra-226 0.33 +/- 0.22 0.29 +/- 0.09 0.31 +/- 0.12 Pass SW-1034 ,1035 4/26/2022 H-3 15 ,159 +/- 386 16,022 +/- 396 15,591 +/- 277 Pass DW-40124,40125 4/28/2022 Gr. Alpha 0.70 +/-0.56 0.60 +/- 0.68 0.65 +/- 0.44 Pass A-11
Page 28 of 49 TABLE A-5 . lntralaboratory "Duplicate" Samples Concentration* Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance SO-1266, 1267 5/9/2022 K-40 17.7 +/- 0.8 16.0+/-1 .0 16.8 +/- 0.6 Pass SO-1266,1267 5/9/2022 Pb-214 0.42 +/- 0.05 0.30 +/- 0.06 0.36 +/- 0.04 Pass SO-1266,1267 5/9/2022 Ac-228 0.58 +/- 0.09 0.61 +/- 0.02 0.60 +/- 0.05 Pass AP-51721 ,51722 5/17/2022 Gr. Beta 0.023 +/- 0.003 0.022 +/- 0.003 0.022 +/- 0.002 Pass SG-1368,1369 5/18/2022 Pb-214 4.31 +/- 0.27 5.78 +/- 0.31 5.05 +/- 0.21 Pass SG-1368,1369 5/18/2022 Ac-228 6.08 +/- 0.56 6.59 +/- 0.50 6.34 +/- 0.38 Pass SG-1368,1369 5/18/2022 Gr. Alpha 37.8 +/- 1.7 40.6 +/- 1.7 39 .2 +/- 1.2 Pass SG-1368,1369 5/18/2022 Gr. Beta 34 .8 +/- 0.8 31 .2 +/-0.8 33 .0 +/- 0.6 Pass DW-40143,40144 5/19/2022 Ra-226 1.17 +/- 0.25 1.56 +/- 0.16 1.37 +/- 0.15 Pass DW-40143,40144 5/19/2022 Ra-228 1.29 +/- 0.72 2 .14+/-0.85 1.72 +/-0.56 Pass AP-53121 ,53122 5/31/2022 Gr. Beta 0.016 +/- 0.003 0.014 +/- 0.003 0.015 +/- 0.002 Pass PM-1646 ,1647 6/1/2022 K-40 14.2 +/- 0.8 13.9 +/- 0.4 14.1 +/- 0.5 Pass S-1731 ,1732 6/6/2022 K-40 16.5 +/- 0.8 15.8+/-1 .9 16.2 +/- 1.0 Pass DW-40152,40153 6/7/2022 Gr. Alpha 4.00 +/- 0.74 3.50 +/- 0.70 3.75 +/- 0.51 Pass AP-60721 ,60722 6/7/2022 Gr. Beta 0.014 +/- 0.003 0.013 +/- 0.003 0.013 +/- 0.002 Pass S-1773 ,1774 6/13/2022 Be-7 1.29 +/- 0.28 1.56 +/- 0.15 1.43 +/- 0.16 Pass S-1773 ,1774 6/13/2022 K-40 13.8 +/- 0.7 13.3 +/- 0.7 13.6 +/- 0.5 Pass AP-61321 ,61322 6/13/2022 Gr. Beta 0.023 +/- 0.004 0.023 +/- 0.004 0.023 +/- 0.003 Pass AP-62021,62022 6/20/2022 Gr. Beta 0.031 +/- 0.005 0.031 +/- 0.005 0.031 +/- 0.003 Pass AP-62721 ,62722 6/27/2022 Gr. Beta 0.027 +/- 0.005 0.027 +/- 0.005 0.027 +/- 0.003 Pass DW-40169,40170 6/29/2022 Ra-228 1.06 +/- 0.70 0.17+/-0.54 0.62 +/- 0.44 Pass DW-40169,40170 6/29/2022 Ra-226 0.22 +/-0 .12 0.03 +/- 0.12 0.13 +/- 0.08 Pass W-2014 ,2015 7/4/2022 Ra-226 0.73 +/- 0.24 0.72 +/- 0.27 0.73 +/-0.18 Pass S-2035 ,2036 7/7/2022 Pb-214 1.00 +/- 0.09 1.65 +/- 0.11 1.33 +/- 0.07 Pass S-2035,2036 7/7/2022 Ac-228 1.16 +/- 0.20 1.09+/-0.18 1.13 +/- 0.13 Pass S-2152,2153 7/13/2022 Pb-214 0.58 +/- 0.07 0.65 +/- 0.05 0.62 +/- 0.04 Pass S-2152,2153 7/13/2022 Ac-228 0.62 +/- 0.11 0.61 +/- 0.08 0.62 +/- 0.07 Pass S-2152,2153 7/18/2022 K-40 10.9 +/- 0.8 12.5 +/- 0.8 11 .7 +/-0.6 Pass DW-40192,40193 7/19/2022 Ra-226 0.80 +/-0.10 0.70 +/- 0.10 0.75 +/- 0.07 Pass DW-40192,40193 7/19/2022 Ra-228 0.03 +/- 0.60 1.20 +/- 0.68 0.62 +/- 0.45 Pass DW-40205,40206 7/27/2022 Ra-226 0.32 +/-0.15 0.28 +/- 0.10 0.30 +/- 0.09 Pass DW-40205,40206 7/27/2022 Ra-228 0.34 +/- 0.59 0.65 +/- 0.62 0.50 +/- 0.43 Pass G-2343,2344 8/1/2022 Be-7 3.00 +/- 0.31 3.04 +/- 0.26 3.02 +/- 0.20 Pass G-2343 ,2344 8/1/2022 K-40 5.82 +/- 0.53 6 .03 +/- 0.39 5.93 +/- 0.33 Pass W-2406 ,2407 8/1/2022 Gr. Alpha 4.27 +/- 3.20 4.60 +/- 2.95 4.44+/-2.18 Pass W-2406 ,2407 8/1/2022 Gr. Beta 11 .1 +/- 2.6 10.5 +/- 2.4 10.8 +/- 1.8 Pass W-2406,2407 8/1/2022 Ra-226 1.83 +/- 0.28 2.31 +/- 0.35 2.07 +/- 0.22 Pass W-2406 ,2407 8/1/2022 Ra-228 2.87 +/- 0.95 2.43 +/- 0.93 2.65 +/- 0.66 Pass DW-40213,40214 8/3/2022 Gr. Alpha 0.60 +/- 0.60 -0 .30 +/- 0.70 0.15+/-0.46 Pass DW-40213,40214 8/3/2022 Gr. Beta 0.72 +/- 0.59 0.85 +/- 0.54 0.79 +/- 0.40 Pass DW-40225,40226 8/10/2022 Ra-226 0.53 +/- 0.13 0.41 +/- 0.10 0.47 +/-0.08 Pass A-12
Page 29 of 49 TABLE A-5. lntralaboratory "Duplicate" Samples Concentration* Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance DW-40225,40226 8/10/2022 Ra-228 1.20 +/-0.71 1.00+/-0.71 1.10 +/- 0.50 Pass S-2553,2554 8/18/2022 K-40 1.74 +/-0.27 1.33 +/- 0.22 1.54 +/-0.17 Pass WW-2774 ,2775 8/19/2022 H-3 138 +/- 86 171 +/- 88 155 +/- 62 Pass S-2797,2798 8/22/2022 K-40 19.0 +/- 0.2 18 .7 +/- 0.2 18.9 +/-0 .1 Pass DW-40241,40242 8/23/2022 Ra-226 3.10+/-0.19 3.54+/-0.19 3.32 +/- 0.13 Pass DW-40241,40242 8/23/2022 Ra-228 6.05 +/- 0.98 6.61 +/- 1.02 6.33 +/- 0.71 Pass W-2681 ,2682 8/24/2022 H-3 1054 +/- 126 962 +/- 122 1008 +/- 88 Pass DW-40259,40260 8/30/2022 Ra-228 0.49 +/-0.11 0.11+/-0.10 0.30 +/- 0.07 Pass DW-40259,40260 8/30/2022 Ra-226 0.49+/-0.11 0.11+/-0.09 0.30 +/- 0.07 Pass DW-40259,40260 8/30/2022 Ra-228 0.00 +/- 0.57 0.47 +/-61 .00 0.24 +/- 30.50 Pass AP-830227A,B 8/30/2022 Gr. Beta 0.027 +/- 0.004 0.026 +/- 0.004 0.027 +/- 0.003 Pass AP-808227A,B 8/30/2022 Gr. Beta 0.016 +/- 0.004 0.018 +/- 0.004 0.017 +/- 0.003 Pass VE-2702,2703 8/30/2022 K-40 2.58 +/-0.12 2.62 +/- 0.27 2.60 +/- 0.15 Pass VE-2702 ,2703 8/30/2022 Be-7 0.21 +/- 0.05 0.30 +/- 0.13 0.26 +/- 0.07 Pass VE-2702 ,2703 8/30/2022 Sr-90 0.002 +/- 0.001 0.002 +/- 0.001 0.002 +/- 0.001 Pass SG-3978,3979 9/7/2022 Gr. Alpha 470 +/- 29 552 +/- 32 511 +/- 22 Pass SG-3978 ,3979 9/7/2022 Pb-214 31 .3 +/- 0.8 30.9+/-1.6 31 .1 +/- 0.9 Pass SG-3978,3979 9/7/2022 Ac-228 41 .6+/-1.5 43 .2 +/- 2.8 42.4 +/- 1.6 Pass SG-2844 9/9/2022 Gr. Alpha 25.7 +/- 4.0 18.7 +/- 3.5 22 .2 +/- 2.7 Pass SG-2844 9/9/2022 Gr. Beta 21 .3 +/- 2.0 22.2 +/- 2.0 21 .8 +/- 1.4 Pass SG-2844 9/9/2022 Pb-214 4.35 +/- 0.12 4.43 +/-0.10 4.39 +/- 0.08 Pass SG-2844 9/9/2022 Ac-228 5.37 +/- 0.22 5.39 +/-0.17 5.38 +/-0.14 Pass DW-40279,40280 9/9/2022 Ra-226 3.92 +/- 0.23 4.18 +/- 0.25 4.05 +/- 0.17 Pass DW-40279,40280 9/9/2022 Ra-228 7.05 +/- 1.09 6.58 +/- 1.06 6.82 +/- 0.76 Pass SG-2841 ,2842 9/9/2022 Pb-214 0.90 +/-0.50 1.16 +/- 0.12 1.03 +/- 0.26 Pass SG-2841,2842 9/9/2022 Ac-228 0.91 +/- 0.10 0.88 +/- 0.17 0.90 +/- 0.10 Pass DW-40295,40296 9/13/2022 Gr. Alpha 0.79 +/-0 .97 0.64 +/- 0.97 0.72 +/- 0.69 Pass DW-40295,40296 9/14/2022 Ra-226 2.75 +/- 0.32 2.89 +/- 0.24 2.82 +/- 0.20 Pass DW-40295,40296 9/14/2022 Ra-228 2.88 +/- 0.78 2.95 +/- 0.76 2.92 +/- 0.54 Pass SG-2862,2863 9/14/2022 Pb-214 11.8 +/- 0.2 11 .2 +/- 0.2 11 .5 +/- 0.1 Pass SG-2862,2863 9/14/2022 Ac-228 6.95 +/- 0.24 7.18 +/- 0.19 7.07 +/- 0.15 Pass SG-3119,3120 9/24/2022 Pb-214 3.10+/-0.21 3.10+/-0.22 3.10 +/- 0.15 Pass SG-3119,3120 9/24/2022 Ac-228 2.16 +/- 0.38 2.30 +/- 0.33 2.23 +/- 0.25 Pass SG-3075,3076 9/28/2022 Gr. Alpha 174 +/- 10 158 +/- 10 166 +/-7 Pass SG-3075 ,3076 9/28/2022 Pb-214 23 .6 +/- 0.9 24.4 +/- 0.4 24.0 +/- 0.5 Pass SG-3075,3076 9/28/2022 Ac-228 38 .2 +/- 1.9 35 .8 +/- 0.8 37.0 +/- 1.0 Pass DW-40318,40319 9/29/2022 Gr. Alpha 1.02 +/- 0.94 1.79 +/- 1.68 1.41 +/- 0.96 Pass AP-100321A/B 10/3/2022 Gr. Beta 0.015 +/- 0.003 0.011 +/- 0.003 0.013 +/- 0.002 Pass SO-3140 ,3141 10/3/2022 Be-7 0.353 +/- 0.180 0.304 +/- 0.163 0.328 +/- 0.121 Pass SO-3140 ,3141 10/3/2022 K-40 11 .2 +/- 0.6 11.0+/-0.6 11.1 +/-0.4 Pass SO-3140 ,3141 10/3/2022 Cs-137 0.055 +/- 0.016 0.069 +/- 0.020 0.062 +/- 0.013 Pass SO-3140 ,3141 10/3/2022 Tl-208 0.132 +/- 0.022 0.114 +/- 0.024 0.123 +/- 0.016 Pass A-13
DocuSign Envelope ID : 14AB142A-3871-414F-8E54-0375E3280E42 Page 30 of 49 TABLE A-5. lntralaboratory "Duplicate" Samples Concentration* Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance SO-3140,3141 10/3/2022 Bi-214 0.315 +/-0.041 0.390 +/- 0.041 0.353 +/- 0.029 Pass SO-3140,3141 10/3/2022 Pb-212 0.344 +/- 0.029 0.357 +/- 0.029 0.351 +/- 0.020 Pass SO-3140,3141 10/3/2022 Pb-214 0.362 +/- 0.043 0.446 +/- 0.047 0.404 +/- 0.032 Pass SO-3140,3141 10/3/2022 Ra-226 0.602 +/- 0.250 0.768 +/- 0.248 0.685 +/- 0.176 Pass SO-3140,3141 10/3/2022 Ac-228 0.442 +/- 0.101 0.405 +/- 0.083 0.423 +/- 0.066 Pass SO-3140,3141 10/3/2022 Gr. Alpha 4.07 +/- 1.77 4.43 +/- 2.17 4.25 +/- 1.40 Pass SO-3140,3141 10/3/2Q22 Gr. Beta 15.6 +/- 1.6 17.0 +/- 1.5 16.3+/-1 .1 Pass AP-101021A/B 10/10/2022 Gr. Beta 0.037 +/- 0.005 0.040 +/- 0.005 0.039 +/- 0.004 Pass S-3501,3502 10/18/2022 K-40 16.3 +/- 1.2 16.3+/-1 .3 16.3 +/- 0.9 Pass AP-101821A/B 10/18/2022 Gr. Beta 0.026 +/- 0.003 0.027 +/- 0.003 0.026 +/- 0.002 Pass DW-40328,40329 10/25/2022 Ra-226 2.13 +/- 0.18 2 .17+/-0.28 2.15 +/- 0.17 Pass AP-102621A/B 10/26/2022 Gr. Beta 0.051 +/- 0.005 0.047 +/- 0.005 0.049 +/- 0.003 Pass SG-3557,3558 11/1/2022 Gr. Alpha 24 .5 +/- 4.0 25.0 +/- 4.0 24.8 +/- 2.8 Pass SG-3557,3558 11/1/2022 Gr. Beta 26 .7 +/- 2.2 29.3 +/- 2.3 28 .0 +/- 1.6 Pass SG-3557,3558 11/1/2022 Pb-214 9.23 +/-0.15 9.23 +/- 0.32 9.23 +/- 0.18 Pass SG-3557,3558 11/1/2022 Ac-228 7.35 +/- 0.31 8.26 +/- 0.63 7.81 +/- 0.35 Pass AP-110221A/B 11/2/2022 Gr. Beta 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.002 Pass DW-40341,40342 11/7/2022 Ra-226 1.18 +/- 0.15 0.89 +/- 0.14 1.04 +/- 0.10 Pass DW-40341,40342 11/7/2022 Ra-228 1.98 +/- 0.95 3.32 +/- 1.12 2.65 +/- 0.73 Pass AP-110921A/B 11/9/2022 Gr. Beta 0.025 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.002 Pass AP-111621A/B 11/16/2022 Gr. Beta 0.013 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 Pass AP-112321A/B 11/23/2022 Gr. Beta 0.034 +/- 0.004 0.031 +/- 0.004 0.032 +/- 0.003 Pass AP-113021A/B 11/30/2022 Gr. Beta 0.056 +/- 0.005 0.058 +/- 0.005 0.057 +/- 0.003 Pass SG-4016,4017 12/5/2022 Gr. Alpha 24 .5 +/- 4 .0 25 .0 +/- 4.0 24 .7 +/- 2.9 Pass SG-4016,4017 12/5/2022 Gr. Beta 26 .7 +/- 2.2 29 .3 +/- 2.3 28 .0 +/- 1.6 Pass SG-4016,4017 12/5/2022 Pb-214 8.64 +/- 0.30 9.28 +/- 0.30 8.96 +/- 0.21 Pass SG-4016,4017 12/5/2022 Ac-228 10.8 +/- 0.8 10.0 +/- 0.8 10.4 +/- 0.6 Pass AP-120721 A/B 12/7/2022 Gr. Beta 0.034 +/- 0.003 0.030 +/- 0.003 0.032 +/- 0.002 Pass DW-40375,40376 12/14/2022 Ra-228 5.05 +/- 0.96 7.15 +/- 1.09 6.10 +/-0.73 Pass DW-40375,40376 12/14/2022 Ra-226 3.33 +/- 0.27 4.28 +/- 0.29 3.81 +/- 0.20 Pass AP-121621A/B 12/16/2022 Gr. Beta 0.039 +/- 0.004 0.033 +/- 0.004 0.036 +/- 0.003 Pass AP-122721A/B 12/27/2022 Gr. Beta 0.018 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.001 Pass AP-122821A/B 12/28/2022 Gr. Beta 0.042 +/- 0.003 0.039 +/- 0.003 0.041 +/- 0.002 Pass Note: Duplicate analyses are performed on every twentieth sample received . Results are not listed for those analyses with activities that measure below the LLD . a Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m 3}, food products , vegetation, soil and sediment (pCi/g). AP (Air Particulate} , AV (Aquatic Vegetation) , BS (Bottom Sediment), CF (Cattle Feed) , CH (Charcoal Canister) , OW (Drinking Water) , E (Egg) , F (Fish) , G (Grass), LW (Lake Water), Ml (Milk), P (Precipitation), PM (Powdered Milk), S (Solid), SG (Sludge), SO (Soil), SS (Shoreline Sediment) , SW (Surface Water), SWT (Surface Water Treated ), SWU (Surface Water Untreated), U (Urine), VE (Vegetation) , W (Water) , WW (Well Water) . A-14
Page 31 of 49 Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-506 2/1/2022 Gross Alpha 1.10 +/- 0.14 1.20 0.36 - 2.04 Pass MAAP-506 2/1/2022 Gross Beta 0.83 +/- 0.06 0.681 0.341 - 1.022 Pass MADW-408 2/1/2022 Gross Alpha 0.34 +/- 0.04 0.574 0.172 +/-0.976 Pass MADW-408 2/1/2022 Gross Beta 6.61 +/- 0.09 7.25 3.63 - 10.88 Pass MASO-504 2/1/2022 Cs-134 738 +/- 8 890 623 -1157 Pass MASO-504 2/1/2022 Cs-137 399 +/- 9 365 256 - 475 Pass MASO-504 2/1/2022 Co-57 1479 +/- 375 1400 980 - 1820 Pass MASO-504 2/1/2022 Co-60 433 +/- 6 443 310 - 576 Pass MASO-504 2/1/2022 Mn-54 1258+/-606 1140 798 - 1482 Pass MASO-504 2/1/2022 Zn-65 -2.11 +/- 4.44 0 NA C Pass MASO-504 2/1/2022 K-40 641 +/- 40 596 417 - 775 Pass MADW-500 2/1/2022 Cs-134 -0.06 +/- 0.11 0 NA C Pass MADW-500 2/1/2022 Cs-137 8.09 +/- 0.33 7.64 5.35 - 9.93 Pass MADW-500 2/1/2022 Co-57 37 .04 +/- 0.55 36 .0 25 .20 - 46 .80 Pass MADW-500 2/1/2022 Co-60 8.91 +/- 0.27 9.3 6.5-12 .1 Pass MADW-500 2/1/2022 Mn-54 20.4 +/- 0.6 18.9 13.2 - 24 .6 Pass MADW-500 2/1/2022 Zn-65 28 .65 +/- 0.94 26.2 18.3-34.1 Pass MADW-500 2/1/2022 K-40 4.80 +/- 2.57 0 NA C Pass MADW-500 2/1/2022 H-3 309 +/- 10 300 210 - 390 Pass MADW-500 2/1/2022 Ra-226 0.83 +/- 0.10 0.8 0.6 - 1.0 Pass MADW-500 2/1/2022 U-234 0.13 +/- 0.01 1.5 1.1-2.0 Fail d MADW-500 2/1/2022 U-238 0.12 +/- 0.01 1.54 1.08 - 2.00 Fail d MAAP-502 2/1/2022 Cs-134 0.83 +/- 0.05 0.93 0.65 -1 .21 Pass MAAP-502 2/1/2022 Cs-137 0.87 +/- 0.07 0.726 0.51 - 0.94 Pass MAAP-502 2/1/2022 Co-57 0.87 +/- 0.05 0 NA C Fail e MAAP-502 2/1/2022 Co-60 0.83 +/- 0.07 0.72 0.50 - 0.94 Pass MAAP-502 2/1/2022 Mn-54 0.02 +/- 0.02 0 NA C Pass MAAP-502 2/1/2022 Sr-90 0.72 +/- 0.10 0.54 0.38 - 0.70 Fail r MAVE-507 2/1/2022 Cs-134 7.53 +/- 0.17 7.61 5.33 - 9.89 Pass MAVE-507 2/1/2022 Cs-137 1.60+/-0.12 1.52 106 - 1.98 Pass MAVE-507 2/1/2022 Co-57 6.21 +/- 0.17 5.09 3.56 - 6.62 Pass MAVE-507 2/1/2022 Co-60 0.01 +/- 0.03 0 NA C Pass MAVE-507 2/1/2022 Mn-54 2.94+/-0.14 3 1.81 -3 .37 Pass MAVE-507 2/1/2022 Zn-65 1.69+/-0.17 1.47 1.03 - 1.91 Pass MADW-2613 8/1/2022 Gross Alpha 1.39+/-0.10 0.90 0.27 - 1.53 Pass MADW-2613 8/1/2022 Gross Beta 1.69 +/- 0.04 1.3 1 0.66 - 1.97 Pass A-15
Page 32 of 49 TABLE A-6 . Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration" Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MASO-2737 8/1/2022 Cs-134 523 +/- 5 627 439 - 815 Pass MASO-2737 8/1/2022 Cs-137 1.18+/-2.21 0 NA C Pass MASO-2737 8/1/2022 Co-57 715 +/- 6 786 550 - 1022 Pass MASO-2737 8/1/2022 Co-60 -0.04 +/- 1.07 0 NA C Pass MASO-2737 8/1/2022 Mn-54 903 +/- 11 841 589 - 1093 Pass MASO-2737 8/1/2022 Zn-65 1227 +/- 19 1140 798 - 1482 Pass MASO-2737 8/1/2022 K-40 595 +/- 37 537 376 - 698 Pass MADW-2733 8/1/2022 Cs-134 13.6 +/- 0 .3 17.1 12.0 - 22 .2 Pass MADW-2733 8/1/2022 Cs-137 16.0 +/- 0.4 16.8 11 .8-21 .8 Pass MADW-2733 8/1/2022 Co-57 27 .5 +/- 0.4 30.0 21 .0 - 39.0 Pass MADW-2733 8/1/2022 Co-60 14.4 +/- 0.3 17.0 11.9 - 22.1 Pass MADW-2733 8/1/2022 Mn-54 -0.03 +/- 0.10 0 NA C Pass MADW-2733 8/1/2022 Zn-65 11 .5 +/- 0.6 11 .3 7.9 - 14.7 Pass MADW-2733 8/1/2022 K-40 3.88 +/- 1.51 0 NA C Pass MADW-2733 8/1/2022 Sr-90 6.79 +/-0.32 7 .73 5.41 -10 .05 Pass MAAP-2735 8/1/2022 Cs-134 -0.001 +/- 0.029 0 NA C Pass MAAP-2735 8/1/2022 Cs-137 1.76+/-0.11 1.53 1.07 - 1.99 Pass MAAP-2735 8/1/2022 Co-57 3.50 +/- 0 .07 3 .32 2.32 - 4 .32 Pass MAAP-2735 8/1/2022 Co-60 2.11 +/-0.08 1.99 1.39 - 2 .59 Pass MAAP-2735 8/1/2022 Mn-54 2.18 +/-0.13 1.88 1.32 - 2.44 Pass MAAP-2735 8/1/2022 Zn-65 1.83 +/- 0 .22 1.58 1.11 - 2.05 Pass MAVE-2740 8/1/2022 Cs-134 0.01 +/- 0 .06 0 NA C Pass MAVE-2740 8/1/2022 Cs-137 1.15 +/- 0 .12 1.083 0. 758 - 1 .408 Pass MAVE-2740 8/1/2022 Co-57 -0 003 +/- 0.035 0 NA C Pass MAVE-2740 8/1/2022 Co-60 4.71 +/- 0 .14 4 .62 3 .23 - 6 01 Pass MAVE-2740 8/1/2022 Mn-54 2.67 +/- 0.19 2.43 170 - 3.16 Pass MAVE-2740 8/1/2022 Zn-65 7.73 +/- 0 .39 7.49 5.24 - 9 .74 Pass a Results are reported in units of Bq/kg (soi l) , Bq/L (water) or Bq/total sample (filters, vegetation). b Laboratory codes as follows: MAW (water), MADW (water) , MAAP (air filter) , MASO (soil) and MAVE (vegetation) . c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits. d Results for a different dataset were mistakenly input into the MAPEP system . If the correct dataset had been entered, the results, (U-234: 1.62 +/- 0.04 , U-238: 1.69 +/- 0.04), would have been within the aceptance range .
- MAPEP likely added Eu-152 as an interference to Co-57. Reanalyzing the spectra in duplicate with libraries to account for both Co-57 and Eu-152 yields Co-57 results of 0.03 +/- 0.04 & 18 +/- 0.18 Sq/sample. Which satisfies MAPEP criteria for passing a "false positive" test.
r The analysis of this sample was repeated and the result, (Sr-90: 0.52 +/- 0.09) , was within the acceptance range . A-16
Page 33 of 49 TABLE A-7. lnterlaboratory Comparison Crosscheck Program , Environmental Resource Associates (ERA)". MRAD-30 Stud Concentration
- Lab Code b Date Analysis Laboratory ERA Control Result Value c Limits d Acceptance ERAP-640 3/21/2022 Cs-134 458 549 356 - 673 Pass ERAP-640 3/21/2022 Cs-137 1430 1,320 1,080-1730 Pass ERAP-640 3/21/2022 Co-60 913 885 752-1120 Pass ERAP-640 3/21/2022 Mn-54 < 4.1 < 35 .0 0.00 - 35.0 Pass ERAP-640 3/21/2022 Zn-65 771 671 550 - 1030 Pass ERAP-639 3/21/2022 Gross Alpha 93.5 94.2 49.2 - 155 Pass ERAP-639 3/21/2022 Gross Beta 60.7 66 .8 40 .5 - 101 .0 Pass
- Results obtained by Environmental, Inc., Midwest Laboratory (EIML) as a participant in the crosscheck program for proficiency testing administered by Environmental Resource Associates , serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML) .
b Laboratory code ERAP (air filter). Results are reported in units of (pCi/Filter). c The ERA Assigned values for the air filter standards are equal to 100% of the parameter present in the standard as determined by the gravimetric and/or volumetric measurements made during standard preparation as applicable . d The acceptance limits are established per the guidelines contained in the Department of Energy (DOE) report EML-564, Analysis of Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP) Data Determination of Operational Criteria and Control Limits for Performance Evaluation Purposes or ERA's SOP for the generation of Performance Acceptance Limits. A-17
Page 34 of 49 APPENDIX B DATA REPORTING CONVENTIONS
-414F-8E54-0375E3280E42 Page 35 of 49 Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta , are decay corrected to collection time or the end of the collection period . 2.0. Single Measurements Each single measurement is reported as follows : x+/-s where: x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level). In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample. 3.0. Duplicate analyses 3.1 Individual results : For two analysis results ; x1 +/- s1 and x2 +/- s2 Reported result: x+/-s; where x= (1/2)(x1+x2)ands= ( 1 / 2 ) ~ 3.2 . Individual results : Reported result: <L, where L = lower of L1 and L2 3.3. Individual results : X +/- s, <L Reported result: X +/- s if X ;:: L; <L otherwise. 4.0. Computation of Averages and Standard Deviations B-2
DocuSign Enve lope ID: 14AB142A-3871-414F-8E54-0375E3280E42 Page 36 of 49 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged ; for example , an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1 , x2 . .. xn are defined as follows : s= 4.2 Values below the highest lower limit of detection are not included in the average . 4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported . 4.4 If all but one of the values are less than the highest LLD , the single value x and associated two sigma error is reported. 4.5 In rounding off, the following rules are followed: 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped , and the retained figures are kept unchanged. As an example , 11.443 is rounded off to 11.44. 4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to 11.45. 4.6 Composite samples which overlap the next month or year are reported for the month or year in which most of the sample is collected . B-3
Page 37 of 49 APPENDIX C SAMPLE LOCATION MAPS C-1
OocuSign Envelope ID: 14AB 142A-3871-414F-8E54-0375E3280E42 Page 38 of 49 N Q P- 00075 C-2
0 0 0 C (J) Radiological Environmental Sampling Locations and Media co*
- J rn
- J Cl) 0 Table 5.2 - Radiological Environmental Sampling Locations And Media ,:,
Cl) q Approximate Approximate Air t Distance Monitoring ~ Sample Approximate Direction Vegetables .i:,. from Center Sedi- Ground- "'
- p Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water ~
No. Sites from true Products ::1. Containment Airborne ~ north) (miles) Particulate .i:,. 71 00 rn U1
.i:,.
Onsite Station, 6 w 110-meter -.J U1 rn 1 weather tower 0.53 293 °/WNW p X w
"'gJ rn Onsite Station , ~
adjacent to old plant access 2C,E road 0.59 207°/SSW K X X Offsite Station , Intersection of Hwy. 75 and farm access 3 road 0.94 145°/SE G X Blair OPPD 4 office 2.86 305°/NW Q X X 5A Fort Calhoun , 6 NE City Hall 5.18 150°/SSE H X 0
~
co C-3
0 0 () C
'°.
(/) Radiological Environmental Sampling Locations and Media rn Table 5.2 - Radiological Environmental Sampling Locations And Media < Cl) 0
-0 Cl)
Air q Approximate Approximate Sample Approximate Distance Direction Monitoring Vegetables t from Center Sedi- Ground- ~
.t,.
Station Collection (degrees Sector TLD Water Milk Fish and Food N of ment water )> No. Sites Containment from true Airborne Products ~ north) ~ (miles) Particulate ~
.t,.
71 00 Fence around rn U1
.t,.
intake gate , 6 w
-..J Desoto Wildlife U1 rn 7 Refuge 2.07 102°/ESE F X w N
00 D rn Onsite Station, it entrance to Plant Site from 8 Hwy. 75 0.55 191 °/S J X Onsite Station , 9 NW of Plant 0.68 305°/NW Q X Onsite Station , 10 WSW of Plant 0.61 242°/WSW M X Offsite Station, 11 SE of Plant 1.07 39°/SE G X
~
0 0
.i,..
co C-4
0 0 () C (/) Radiological Environmental Sampling Locations and Media en* rn Table 5.2 - Radiological Environmental Sampling Locations And Media < co 0
"O co Approximate Air (J Approximate Sample Approximate Distance Direction Monitoring Vegetables t
from Center Sedi- Ground- ~
.i,.
Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water "':i=- No. Sites from true Products ~ Containment Airborne ":j north) (miles) Particulate l..
~
.i,.
- 1 OJ Metropolitan rn U1
.i,.
Utilities Dist. , 6 w Florence -.,J U1 rn Treatment Plant w gi rn North Omaha, ib 12 NE 14.3 154°/SSE H X West bank Missouri River, downstream from Plant 13 discharge 0.45 108°/ESE F X X Upstream from Intake Bldg, west bank of 14° river 0.09 4°/N A X X 15 Smith Farm 1.99 134°/SE G X 16A
- i:,,.
17A ...... 0
~
co C-5
D 0 () C: (/) Radiological Environmental Sampling Locations and Media <0'
- J rn
- J Table 5.2 - Radiological Environmental Sampling Locations And Media <1l 0
"Cl (1)
Approximate Air q Approximate Distance Monitoring Vegetables
- t Sample Approximate Direction [lJ from Center Sedi- Ground- ~
-I>-
Station Collection (degrees Sector TLD Water Milk Fish and Food "-' of ment water :p No. Sites from true Products ~ Containment Airborne -sJ north) ~ (miles) Particulate ~
-l>-
71 00 18A rn U1
-l>-
6 w
-sJ 19A U1 rn w
00 0 208,D,F Mohr Dairy 9.86 186°/S J X X X rn
;ti 21A Fish Sampling 0.08 Area, Missouri 22 River (R.M . 645 .0) 6°/N A X Fish Sampling 17.9 Area, Missouri 23° River (R.M. 666.0) 358°/N A X 24A 25A 26A 27A ~
N C-6 0
~
co
0 0 n C (/) Radiological Environmental Sampling Locations and Media co* rn Table 5.2 - Radiological Environmental Sampling Locations And Media Cl) 0 Cl) Approximate Air q Approximate Sample Approximate Distance Direction Monitoring Vegetables t OJ from Center Sedi- Ground- ~
-l'-
Station Collection (degrees Sector TLD Water Milk Fish and Food 1\.) of ment water )> No. Sites Containment from true Airborne Products ~
---J north) ~
(miles) Particulate ~
-l'-
71 (X) Alvin Pechnik rn (JJ
-l'-
28 Farm 0.94 163 H X 6 (,.)
---J (JJ rn
(,.) 29A I\.) (X) 0 rn
-l'-
1\.) 30A 31 A Valley 32° Substation #902 19.6 221 °/SW L X X 33A 34A Onsite Farm 35 Field 0.52 118°/ESE F X Offsite Station Intersection Hwy 75/Co. Rd . 36 P37 0.75 227°/SW L X :i::,.. (.,J C-7 0
.i:,..
c.o
0 0 (") C: (/) Radiological Environmental Sampling Locations and Media cc*
- J rn
- J Table 5.2 - Radiological Environmental Sampling Locations And Media (1) 0
-a (1)
Approximate Air CJ Approximate ~ Sample Approximate Distance Direction Monitoring Vegetables t Cll from Center Sedi- Ground- ~
.j:,.
Station Collection (degrees Sector TLD Water Milk Fish and Food N of ment water )> No. Sites from true Products ~ Containment Airborne :}_ north) (miles) Particulate ~
.j:,.
71 00 Offsite Station rn U1
.j:,.
Desoto 6 w
---i 37 Township 1.57 144°/SE G X X U1 rn w
N 00 0 38A rn
~
39A 40A 41 s,c Dowler Acreage 0.73 175°1s J X X 42 Sector A-1 1.94 0°/NORTH A X 43 Sector 8-1 1.97 16°/NNE B X 44 Sector C-1 1.56 41 °/NE C X 45 Sector D-1 1.34 71 °/ENE D X 46 Sector E-1 1.54 90 °/EAST E X
~
47 Sector F-1 0.45 108°/ESE F X ~ 0
~
co C-8
0 0 () C (/) Radiological Environmental Sampling Locations and Media <e" rn Table 5.2 - Radiological Environmental Sampling Locations And Media Cl> 0
-c, Cl>
Approximate Air CJ Approximate Sample Approximate Distance Direction Monitoring Vegetables t
~
from Center Sedi- Ground- .i:,. Station Collection (degrees Sector TLD Water Milk Fish and Food N of ment water :i=- No. Sites from true Products gi Containment Airborne north) :::: (miles) Particulate ~
.i:,.
71 co 48 Sector G-1 1.99 134°/SE G X rn U1
.i:,.
6
<,.)
--.J 49 Sector H-1 1.04 159°/SSE H X U1 rn
<,.)
N gJ 50 Sector J-1 0.71 179°/SOUTH J X rn
;t 51 Sector K-1 0.61 205 °/SSW K X 52 Sector L-1 0.74 229°/SW L X 53 Sector M-1 0.93 248°/WSW M X 54 Sector N-1 1.31 266°/WEST N X 55 Sector P-1 0.60 291 °/WNW p X 56 Sector Q-1 0.67 307°/NW Q X 57 Sector R-1 2.32 328°/NNW R X 58D Sector A-2 4.54 350°/NORTH A X
- i:,..
59° Sector B-2 2.95 26°/NNE B X 01 0
~
co C-9
0 0 0 C (/) Radiological Environmental Sampling Locations and Media <Ci" rn Table 5.2 - Radiological Environmental Sampling Locations And Media CD 0
-c:,
CD q Approximate Air Approximate Sample Approximate Distance Direction Monitoring Vegetables t
~
from Center Sedi- Ground- .i:,. Station Collection (degrees Sector TLD Water Milk Fish and Food N of ment water }> No. Sites Containment from true Airborne Products ~
- j north)
(miles) Particulate .ls.
~
.i:,.
71 (X) 6Q O Sector C-2 3.32 50°/NE C X rn Ul
.i:,.
6 w
--.J 61° Sector D-2 3.11 75°/ENE D X Ul rn w
N (X) 0 62° Sector E-2 2.51 90°/EAST E X rn
~
63° Sector F-2 2.91 110°/ESE F X 64° Sector G-2 3.00 140°/SE G X 65° Sector H-2 2.58 154°/SSE H X 66D Sector J-2 3.53 181°/SOUTH J X 67° Sector K-2 2.52 205°/SSW K X 68D Sector L-2 2.77 214°/SW L X 69° Sector M-2 2.86 243°/WSW M X
- i::,..
0) 0
~
co C-10
0 0 () C (/) Radiological Environmental Sampling Locations and Media IC. rn Table 5.2 - Radiological Environmental Sampling Locations And Media ct> 0 "O ct> Approximate Air CJ Approximate ~ Sample Approximate Distance Direction Monitoring Vegetables t Cl) from Center Sedi- Ground- ~
.t,.
Station Collection (degrees Sector TLD Water Milk Fish and Food "' of ment water :p No. Sites from true Products ~ Containment Airborne :::;! north) (miles) Particulate ~
.t,.
71 co 70° Sector N-2 2.54 263°/WEST N X rn Ul
.t,.
6 w
~
71° Sector P-2 2.99 299°/WNW p X Ul rn w
"'co0 720 Sector Q-2 3.37 311 °/NW Q X rn iti 730 Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X 75s.c Lamp Acreage 0.65 163°/SSE H X X X 76A 77G River N-1 0.17 328 °/NNW R X 78 8 River S-1 0.14 85 °/EAST E X 79 8 Lagoon S-1 0.24 131 °/SE G X 80 8 Parking S-1 0.27 158°/SSE H X
- i::,..
81 8 Training W-1 0.28 194°/SSW K X
~
0
~
co C-11
0 0 () C (/) Radiological Environmental Sampling Locations and Media cc*
- J rn
- J Table 5.2 - Radiological Environmental Sampling Locations And Media CD 0
-0 CD (J
Approximate Air Approximate ~ Sample Approximate Distance Direction Monitoring Vegetables t Sedi- Ground- ~ from Center .i:,.. Station Collection (degrees Sector TLD Water Milk Fish and Food N of ment water )> No. Sites Containment from true Airborne Products ~ north) ::::: (miles) Particulate ~
.i:,..
T' CD 82G Switchyard S-1 0.21 219°/SW L X rn (Jl
.i:,..
6 w
--.J Switchyard SE- (Jl rn 83G w 1 0.14 231 °/SW L X N CD D
rn
.i:,..
N Switchyard NE-84G 1 0.18 256°/WSW M X 85 G Switchyard W-1 0.29 233°/WEST L X 86 G Switchyard N-1 0.24 262°/WEST N X 87G Range S-1 0.20 286°/WNW p X 88 G Mausoleum E-1 0.37 216 °/SW L X 89 C, Miller 3.30 210°/SSW K X
~
CX) 0
~
co C-12
0 0 (") C en Radiological Environmental Sampling Locations and Media cc*
- J rn
- J Cl) a Cl)
CJ
~
NOTES: t
~
.i:,.
N A. Location is either not in use or currently discontinued and is documented in the table for reference only. :p f:xl B. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be ::!
~
collected as an alternate sample at the site . If there are no milk producers within the entire 5-mile radius of the facility , then vegetation shall be collected .i:,. 71 monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off- co rn U1 Site Dose Calculation Manual, Part II , Table 4 "Highest Potential Exposure Pathways for Estimating Dose") .i:,. 6 w
--.J U1 C. Locations represent highest potential exposure pathways as determined by the biennial Land Use Survey, performed in accordance with Part I, Section 7.3.2, rn w
of the Off-Site Dose Calculation Manual and are monitored as such. N co 0 rn D. Background location (control). All other locations are indicators. ti E. Location for monitoring Sector K High Exposure Pathway Resident Receptor for inhalation. F. When broad leaf (pasture grasses) are being collected in lieu of milk, background broad leaf samples will be collected at a background locale. G. Location for special interest monitoring general dose to the public per 40CFR190 (Figure 2)
"U Q) co (I)
~
co C-13 0
~
co}}