LIC-21-0004, Radiological Effluent Release Report and Radiological Environmental Operating Report
| ML21119A026 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/29/2021 |
| From: | Allan Barker Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-21-0004 | |
| Download: ML21119A026 (422) | |
Text
{{#Wiki_filter:-~ Omaha Public Power District April 29, 2021 LIC-21-0004 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
Subject:
Fort Calhoun Station (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report
References:
FCS Permanently Defueled Technical Specifications (PDTS) Sections 5.9.4(a) and 5.9.4(b) Pursuant to Fort Calhoun Station (FCS), Unit No. 1, Permanently Defueled Technical Specifications (PDTS), Sections 5.9.4(a), and 5.9.4(b), 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 PDTS 5.9.4(a) and encompasses the period of January 1, 2020 through December 31, 2020. 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 PDTS Section 5.17(d), 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 PDTS 5.9.4(b) and encompasses the period of January 1, 2020 through December 31, 2020. No commitments to the NRC are contained in this letter. 444 SOUTH 16TH STREET MALL
- OMAHA, NE 68102-2247 EMPLOYMENT WITH EQUAL OPPORTUNITY
U. S. Nuclear Regulatory Commission LIC-21-0004 Page 2 Please contact Mrs. Andrea K. Barker at (531) 226-6051 or (402) 917-7207 if you should have any questions. Respectfully, 1 /DocuSigned by:
~
Andrea K. Barker Regulatory Assurance & Emergency Planning Manager, AKB/cac
Enclosures:
- 1. Annual Radiological Effluent Release Report
- 2. Annual Radiological Environmental Operating Report c: S. A. Morris, NRC Regional Administrator, Region IV J. D. Parrott, NRC Senior Project Manager C. D. Steely, NRC Senior Health Physicist, Region IV
Omaha Public Power District Fort Calhoun Station Unit No. 1 Annual Radioactive Effluent Release Report (ARERR) January 1, 2020 to December 31, 2020
DOCKET NO. 50-285 OPERATING LICENSE DPR-40 Annual Radiological Effluent Release Report This report is submitted for the period January 1, 2020 through December 31, 2020. 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, 2020 through December 31, 2020. 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
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 Operability of Liquid and Gaseous Monitoring Instrumentation 6.2 Changes to Off-site Dose Calculation Manual (ODCM), CH-ODCM-0001 or Process Control Program, 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
TABLE OF CONTENTS III. Radiological Effluent Releases Table III.1; Batch Liquid and Gas Release Summary Table III.2; Abnormal Batch Liquid and Gaseous Release Summary Table III.3; Gaseous Effluents - Summation of All Releases Table III.4; Gaseous Effluent Releases - Batch Mode Table III.5; Gaseous Effluent Releases - Continuous Mode Table III.6; Liquid Effluents - Summation of All Releases Table III.7; Liquid Effluent Releases - Batch Mode Table III.8; Liquid Effluent Releases - Continuous Mode Table III.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
1.0 INTRODUCTION
This Annual Radiological Effluent Release Report, for Fort Calhoun Station Unit No. 1, is submitted for the period January 1, 2020 through December 31, 2020. 1.1 Executive Summary The Radioactive Effluent Monitoring program for the year 2020 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 3.68 curies. This was an increase from the 2019 activity of 0.986 curies. This increase was due to releases of Kr-85 during the vacuum drying process of the Dry Cask campaign. The total airborne activity from I-131, I-133, and particulates with half-lives > 8 days in 2020 was 1.11E-07 curies. This is an increase from the 2019 activity of 0.00 curies. This was due to particulates being identified from decommissioning activities. The total airborne activity from Tritium was 1.15 curies. This was an increase from the 2019 activity of 0.879 curies. This increase was due to maintaining the Auxiliary Building at a higher temperature than in the past for the Dry Cask campaign, which added to the evaporation of the tritium. Dose contributions from airborne effluents at the unrestricted area boundary were; 1.26E-04 mRad gamma air dose, 1.43E-02 mRad beta air dose, 1.14E-02 mRem total body dose, and 1.14E-02 mRem critical organ dose. Gamma and beta dose showed an increase from 2019 levels of 2.63E-05 mRad gamma air dose and 2.99E-03 mRad beta air dose, from releasing gases during the Dry Cask campaign. Whole body and critical organ doses increased from 2019 levels of 5.86E-03 mRem total body dose and 5.46E-03 mRem critical organ dose. This increase is due to the increase in the tritium and Kr-85 released. II-1
Total water activity (excluding tritium, dissolved gases, and alpha) released in 2020 in liquid effluents was 5.63E-03 curies. This was an increase from the 2019 activity of 9.30E-04 curies. This increase was due to a substantial increase in liquid waste generated. The total water tritium activity released in 2020 in liquid effluents was 3.64E+00 curies. This was an increase from the 2019 activity of 9.41E-01 curies. This increase was due to a substantial increase in liquid waste generated. The calculated whole body dose due to liquid effluents at the site discharge from all sources in 2020 was 1.18E+00 mRem which was 39.33% of the annual dose limit. This was an increase from the 2019 dose of 9.91E-02 mRem, which was 3.30% of the annual dose limit. Dose increased due to an increase in volume released. The calculated critical organ dose due to liquid effluents at the site discharge from all sources in 2020 was 1.86E+00 mRem. This was an increase from the 2019 dose of 1.55E-01mRem. This increase was due to an increase in volume released. 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 2020. During 2020 there were two changes to the Off-site Dose Calculations Manual (ODCM), CH-ODCM-0001, both on 6/1/2020 and one change to the Process Control Program, FCSD-RW-PG-101, on 12/10/2020. For 2020, the total volume of solid radwaste released from the unit was 8.45E+02 cubic meters. This was an increase from the 669.38 cubic meters of solid waste released from the unit in 2019. The increase was mostly attributed to disposing of the one legacy Steam Generator and an increase in the number of Dry Active Waste shipments. II-2
The total activity released from the unit for 2020 was 3.44E+01 curies, 7.66E-01 curies from Dry Active Waste and 3.37E+01 curies of Other Waste. This was a decrease from the 2019 value of 176.208 curies. 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.
II-3
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 25 mRem to the total body or any organ (except the thyroid, which shall be limited to 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. II-4
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 3.1 and 3.2 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, prior to release. Composite samples were analyzed monthly and quarterly for the Monitor Tanks. 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 prior to 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 at the completion of a purge. II-5
Continuous release effluent pathways were continuously sampled using charcoal and 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 = (E12 + E22 + E32 + ... + En2)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 III.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 III.2. 3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables III.3, III.4 and III.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 III.6, III.7 and III.8. II-6
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 operability requirements listed in the ODCM during the reporting period. During the reporting period RM-043, Particulate-Laboratory and Radwaste Processing Building Stack Monitor, was not functional for 64 days (6/28/2020 - 8/31/2020) due to various mechanical issues. During this time period auxiliary sample collection equipment was initiated, allowing the effluent from the ventilation system to be monitored per the ODCM. 6.2 Changes to the Offsite Dose Calculation Manual (ODCM) and/or Process Control Program (PCP) During 2020 there were two changes to the Off-site Dose Calculations Manual (ODCM), CH-ODCM-0001, both on 6/1/2020 and one change to the Process Control Program, FCSD-RW-PG-101, on 12/10/2020. II-7
x The following changes were made to the ODCM: o Use historical average Meteorological data. o Created a Forced Draft Ventilation effluent release path. o Created an Open Air Demolition effluent release path. o Added more background TLDs. o Removed Noble Gases as a possible source of activity for releases. o Removed C-14 as a possible release source. o Changed the PORC to an Independent Safety Review (ISR). o Updated Functionality of liquid Effluent Instrumentation requirements to align with the DSAR. o Added the Particulate Air Samplers to the reporting criteria for Gaseous Effluent Instrumentation. o Administrative changes to be consistent within the ODCM related to the length of the historical data and removing the vague use on how to calculate dose estimates. x The following changes were made to the PCP: o This was reformatted, so revision bars were not used. o Responsibilities were more clearly defined and include the D&D waste group. o Removed the scope of Liquid Radioactive Waste Processing from the PCP, since it is included in the ODCM. This aligns with NRC Generic Letter 89-01 and NUREG-1301. o Updated guidance for solidification to use of a Vendor program. o Replaced specific direction for encapsulation, incineration, and use of evaporators, with a Special Cases section in the new PCP. o All guidance related to waste characterization and classification removed. D&D waste procedure, Waste Characterization and Classification contains all guidance. o Removed blending and concentration averaging associated with the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (BTP). D&D waste procedure, Waste Characterization and Classification contains all guidance. o Revised the required review and approval requirements from Safety Review Committee (SRC) to the Independent Safety Reviewer (ISR). This change aligns with the stations current Quality Assurance Topical Report (QATR). II-8
6.3 New Locations or Modifications for Dose Calculations or Environmental Monitoring None 6.4 Noncompliance with Radiological Effluent Control Requirements 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 2020. 6.4.2 Failure to Meet Specified Sampling Requirements During 2020, 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 approved nor implemented involving major changes to the Liquid and Gaseous Waste Treatment Systems. 6.6 Meteorological Monitoring Program A summary of hourly meteorological data, collected during 2020, 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 $YHUDJH4LVXWLOL]HGWRGHWHUPLQHWKH concentrations of radionuclides at the unrestricted area boundary. For quarterly estimates during the year an average /Q is used, which is the highest 4 calculated using the 5 years historical meteorological data. II-9
6.7 Assessment of Doses 6.7.1 Doses Due to Liquid Effluents Total body, skin, and organ dose 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 950,006 within a 50-mile radius of the plant (based on the 2010 census). The results of the calculations are listed in Section V. The doses due to liquid effluents for 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 4. The results are listed in Section II. II-10
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 4. 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 locations 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 2020 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 Dosf is the dose from on-site storage II-11
The Total Dose is then given by: Dtot = Dext + Dliq + Dnng Where Dtot is the total dose Dext is the external dose Dliq 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-S-(I)}, closest to on site storage, in mrem/week minus background, in mrem/week OTD-S-(I) Background Net Qtr Dose Weeks/qtr mrem/wk mrem/wk mrem/wk mrem/qtr Quarter 1 1.6 1.3 0.3 13 3.9 Quarter 2 1.7 1.4 0.3 13 3.9 Quarter 3 1.5 1.2 0.3 13 3.9 Quarter 4 1.8 1.7 0.1 13 1.3 Dext 13.0 Dext = 13.0 mrem Maximum offsite doses from report Dtbwb = 1.14E-02 mrem, Dtbco = 1.14E-02 mrem Dliqwb = 1.18E+00 mrem Dliqco = 1.86E+00 mrem Dtot wholebody = 13.0 + 1.14E-02 + 1.18E+00 = 14.19 mrem Dtot critical organ = 13.0 + 1.14E-02 + 1.86E+00 = 14.87 mrem II-12
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 SG 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 actual dose. 6.8 Groundwater Monitoring Program and Observations OPPD conducted groundwater sampling from 22 wells, 2 surface water sites, and 4 storm water headers within the site property per NEI 07-07. Additionally, Nebraska requirements regarding avoidance of snow runoff were deleted, so storm water sampling is now performed quarterly, if available. Wells MW-2 and MW-2B were decommissioned in the third quarter 2020 due to being within the building demolition footprint. Three wells (MW-13A &13B and MW-14) were added to the program to replace those lost. The well development was performed in the 4th quarter of 2020; the first sampling will occur in 2021. Wells MW-12A & 12B sampling was not conducted in the first quarter of 2020 due to lowland flooding at the locations. Additional radiological surveys were performed during decommissioning characterization; no plant related nuclides were discovered in soil. 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 in excess of the vendors Minimum Detectable Activity (MDA) was reported. Storm water sampling was impacted by severe drought (rain was absorbed versus creating runoff) and/or had no rain or snow events significant enough to collect storm water or rain samples. No tritium activity in excess of the vendors Minimum Detectable Activity (MDA) was reported in collected storm water or rain sampling. II-13
No wells had any identified tritium > 2 sigma of the MDA value. Some Sr-90 results identified < MDA were retained during statistical data review based on historical station shallow well trends. Gamma isotopics 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 at the nearest municipal drinking water facility. No groundwater drinking pathway exists on site. Groundwater monitoring of neighboring 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. II-14
SECTION II QUARTERLY DOSES FROM EFFLUENTS Offsite Dose Calculation Manual January 1, 2020 - December 31, 2020 II-15
Quarterly Dose Calculation Results January 1, 2020 through December 31, 2020 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 on a quarterly basis in accordance with 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 2020 calculated doses. This section presents the results of the quarterly dose calculations performed during the period January 1, 2020 through December 31, 2020. Details are shown as to the types, sources and resultant doses from the effluents, the annual limits and a comparison to the annual limits. II-16
FORT CALHOUN STATION FC-421 CHEMISTRY FORM R8 QcARTERLY cm!IJLA'l'IVB DOSE CONTRIBUTION PRCM RADIOACTIVE EPYLOBNTS FORT CALHOON FIRST QUARTER 2020 DOSE PROJEICTIONS I. Liquid Effluents: Total Bodf critical organ Dose (mrem) Dose <mrem) Batch: l.lSE- 01 3 . 23£- 01 Continuous : O.OOE+OO O.OOE+OO Totals: l.lSE-01 3.23E-01 ODCM Quarterly Objective: l.50E+OO 5 . 00E+OO Percent of Quarterly Obj: 7.67 % 6.46 % ODCM Annual Objective: 3.00E+OO 1. OOE+Ol YTD Percent of Annual Obj: 3.83 % 3.23 % II . Gaseous Effluents: Total Body G&M\a Total Body Beta Dose Cmrad) Dose (mrad) A. Noble Gas Air Dose: 1.07£- 04 1. 22E-02 ODCM Quarterly Objective : s. ooe+oo l.OOE+Ol Percent of Quarterly Obj : o.oo' 0.12 \ ODCl'l Annual Objective , 1.00E+Ol 2.00E+Ol YT-D Percent of Annual Obj: 0.00 % 0.06 % B. I-13 1, I -133, Tritium, C-14, and Particulates with Half .. Lives > 8 Days : Total Bod~* Critical Organ Dose (mren) .D ose (mrem} I nhalation : 6.25E-04 6. 25E-0 4 Ground and Pood: 2 . 89E-03 2 . 89E- 03 Totals: 3.511!- 03 3.51E-03 ODCM Quarterly Objective: 7.SOE+OO 7.SOE+OO Percent of Quarterly Obj: 0.05 % o.os % 0DCM Annual Object:.ve: 1 . SOB+Ol 1. SOE+Ol YTD Percent of Annual Obj : 0.02 % 0.02 % Review*ed II-17
POR'I' Cl,LHOUN S'l'A'l'I ON FC - 421 CHl:J<lS'J'RY FORM RS QUARTERLY CUMULATIVE OOSE CONTRIBU'l'IOH FROM RADIOACTtVE EFFLUENTS FORT CALHOUN SECOID QUARTER 202 0 DOSE PROJECTIONS I . ~iquid Eff luents, Total Body Cri :ical Organ Dose (rnre:m) Dose (mrem) Batch: 3. 1 26-01 8. 778- 01 Continuous: 0 . 00E+OO 1). OOE *OO
'l'o tals : 3 . 1 2e-01 s. 77 6-0 1 ODCM Quarterly Objective: 1. SOE*OO Percent of Quart erly Obj : 20 . 80 % 17 . 54 \
00CM Annual Objectiva: 3 . 00E*00 '.. . OOE.+01 YTD Percent of An~ual Obj : 14.20 % 12 .00 \ I
- - - - - - - - - - - - - -- -- - - - - - - -1 I II . Gaseous Eff luents : Total Body Gamma Total Body Beta I Dose (mrad) Dose (mrad) l\ . Nobl e Ga.ti Air Dose: 3 . 16 11-05 ~.58E-0) I ODCN. Quarterly Obj ! c t ive: 5.00!!+00 : .OOE+Ol II Percent of Quart -uly Obj: o.oo ' 0. 04 \
0DCM Annual Objecti v e: 1.008+01 I YTD Percent of ~~nual Obj : 0. 00 % 0.08 % B. l - 131, I - 133 , Tritium, C-14 , and Particul ates with Half - Lives > 8 Day.;: Total Body Critic a l Organ oose {mrem} Dose { mretr1) Inhalation: 2 .SOE- 04 L SOE- 04 Ground and Food: 1. 29E- 0 3 1 . 30E* 03 Totals : l.57E-03 l. SSE- 03 ODCM Quarteriy Objective : 7.SOE+OO *: . SOE+OO Percent of Quarte rly Obj: 0.02 % 0.02 % ODCM Annual Objecti ve: 1.soe+o1 I. SOE+Ol YTD Percent of M.nual Obj: 0.0) i 0 . 0) % Reviewed b y ~ II-18
FORT CALHOUN STATI ON N CHEMISTRY FORM FC- 421 RB QUARTERli'i CUMU'...ATIVE DOSE CONTRIBU'l'ION FROM RADIOAC~IVE £FPWENTS FORT CAUlOON '!'BIRD QUARTER 2020 DOSE PROJECTIONS I. Liquid Effl uents: 'l'Otal Body Critical Organ Dose (.m.rem} Dose (mrem) Batch: 2 .13E-01 6.04E- 01 Cont inuous: O.OOE+OO 0.00B+OO Total s: 2. 13E- 01 6.04B-01 OOCM Quarterly Objec tive : l. SOB*OO S:.00B+OO Percent of Quarterly Obj: 14.20 % 1 2.08 % OOCM Annual Obj ective: 3.00B+OO l.OOE*Ol Y'TD Percent of Annual Obj : 21.33 % 18.00 % II. Gaseous Effluents: Total Body GalMla Total Body Beta Dose (mrad) Dose lmrad} A. Noble Gas Air Dose: 0.00E+OO ().OOE+OO ODCM Q\:arterly Objecti ve: S.OOE*OO 1.. 00E+Ol Percent of Quarterly Obj: 0.00 I 0.00 \ ODCM Annual Object ive: l.OOE+Ol 2 .OOE+Ol YTD Per cent. of Annual Obj : o.oo' 0.08 \ B. I-13 1, I- 133, Tritium, C- 1 4, and Fartic~l ates with Ralf- Lives> 8 Days: Total Body Critical Organ Dose (m:reni.} Doa.e (mrem} Inhalation : 4.97!!-04 4 .978- 04 Ground and Food: 2.318-03 2.31E-03 Tot als: 2.808-03 2 . 81E- 03 OOCM Quarterl y Objective: 7.SOE+OO 7.SOB+OO Percent of Quarterl y Obj: 0. o, % 0.04 % ODCM Annual Obj ective: l.SOE* Ol 1 . SOB+Ol YTD Percent of Annual Obj: 0.05 \ o. os ' Reviewed~ II-19
FORT CALHOON STATION P'C- 421 CHl!lHI STRY FORM R8 QUART ERLY CUM!JLATJ:VE DOSE CONTRIBUTION FROM RADI OACTIVE EFFLUENTS FORT CAld!OON FOURTH QUARTER 202 0 DOSE PROuBCTIONS I. Liquid Effl uents: TOtal Body Critical Organ Dose (mremJ Dose {rnrem} Bat ch: 0.001!: 00 O.OOB+OO Concinuous: O.OOE+OO O.OOB+OO Tota.ls: 0,00B+OO O.OOE..00 ODCM Quart erl y Object ive: 1. SOB+OO 5.00E+OO Percent of Quarterly Obj : o.oo' 0.00 I ODCM Annual Objective: 3.00E+OO l . OOE+Ol YTD Percent of Annual Obj : 21.33 I 18 . 00 t II. Gaseous Effluents : TOtal Body Gamma Total Bocly Beta Dose (mrad) Dose (rnrad) A. Nobl e Gae Air Dose: O.OOE+OO 0.00B+OO OIX:M Quarterly Object ive, S.OOE*OO 1. 008+01 Perco.nt of Quarterl y Obj: o.oo' o.oo' OOCM Annual Objective: 1.00S+Ol 2 , 00EtOl YTD Percent of Annual Obj: 0.00 % 0.08 %
- 8. I- 1 31 , I-133, Tritium, C- 14, and Particulat.es with Hal t-Lives > 8 Days: TOtal Body Cri tical Organ Dose (mrem) Dose (mrein)
I nhalati on : t.30E- 0t 4.30E-04 Gr ound and Food, 1. 99&- 03 1.998- 03 Totals: 2 .428- 03 2.42E-03 ODCM Quarter l y Objecti ve: 7.SOE+OO 7.SOE+OO Percen t of Quarterl y Obj: 0.03 I 0.03 \ ODCH Ar.nual Objective: l .SOE+Ol l .SOE+Ol YTD Percent of Annual Obj, 0.07 t 0.07 % Reviewed~ II-20
RADIOLOGICAL EFFLUENT RELEASES Table III.1 Batch Liquid and Gas Release Summary Table III.2 Abnormal Batch Liquid and Gaseous Release Summary Table III.3 Gaseous Effluents - Summation of all Releases Table III.4 Gaseous Effluent Releases - Batch Mode Table III.5 Gaseous Effluent Releases - Continuous Mode Table III.6 Liquid Effluents - Summation of all Releases Table III.7 Liquid Effluent Releases - Batch Mode Table III.8 Liquid Effluent Releases - Continuous Mode Table III.9 Groundwater Tritium Results January 1, 2020 - December 31, 2020 III-1
TABLE III.1 BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
JANUARY THROUGH DECEMBER 2020 A. Liquid Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
- 1. Number of Batch Releases: 12 29 9 50
- 2. Total Time Period for Batch Releases(min): 2,839 9,933 2,001 14,773
- 3. Maximum Time Period for Batch Releases(min): 414 4,025 849 4,025
- 4. Average Time Period for Batch Releases(min): 237 343 222 295
- 5. Minimum Time Period for Batch Releases(min): 85 105 123 85
- 6. Average Dilution Stream Flow During Periods of Release into the Missouri River(mls/min): 2.735E+07 2.650E+07 2.436E+07 2.632E+07 B. Gaseous Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
- 1. Number of Batch Releases:
- 2. Total 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
TABLE III.2 ABNORMAL BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
JANUARY THROUGH DECEMBER 2020 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+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B. Gaseous 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+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 III-3
TABLE III.3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 2020 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activation Gases Total Release (Ci): 2.84E+00 8.35E-01 0.00E+00 0.00E+00 3.68E+00 Average Release Rate (uCi/sec): 3.61E-01 1.06E-01 0.00E+00 0.00E+00 1.16E-01 Total Error (%): 25.00 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 Total Error (%): 21.2 C. Particulates Total Release (Ci): 0.00E+00 1.27E-08 9.84E-08 0.00E+00 1.11E-07 Average Release Rate (uCi/sec): 0.00E+00 1.62E-09 1.24E-08 0.00E+00 3.51E-09 Total Error (%): 20.62 Gross Alpha: Total Error (%): 20.62 8.94E-07 1.93E-06 1.81E-06 6.55E-06 1.12E-05 D. Tritium Total Release (Ci): 3.92E-01 1.76E-01 3.12E-01 2.70E-01 1.15E+00 Average Release Rate (uCi/sec): 4.99E-02 2.24E-02 3.93E-02 3.40E-02 3.64E-02 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 (%): 20.62 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD). III-4
TABLE III.4 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 2020 Batch 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 Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium and Gross Alpha NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD). III-5
TABLE III.5 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 2020 Continuous Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases KR-85 2.84E+00 8.35E-01 0.00E+00 0.00E+00 3.68E+00 Totals for Period: 2.84E+00 8.35E-01 0.00E+00 0.00E+00 3.68E+00 Iodines Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates CS-137 0.00E+00 1.27E-08 9.84E-08 0.00E+00 1.11E-07 Totals for Period: 0.00E+00 1.27E-08 9.84E-08 0.00E+00 1.11E-07 Tritium and Gross Alpha H-3 3.92E-01 1.76E-01 3.12E-01 2.70E-01 1.15E+00 ALPHA 8.94E-07 1.93E-06 1.81E-06 6.55E-06 1.12E-05 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD). III-6
TABLE III.6 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 2020 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activiation Products Total Release (No H-3,Gas,Alpha) (Ci): 1.21E-03 2.61E-03 1.79E-03 0.00E+00 5.61E-03 Average Diluted Concentration (uCi/mL): 1.56E-08 1.55E-08 5.66E-08 0.00E+00 2.02E-08 10 CFR 20, App. B Limit 1.00E-06(uCi/mL) Percent of Limit (%): 1.56E+00 1.55E+00 5.66E+00 0.00E+00 2.02E+00 Total Error (%): 22.99 B. Tritium Total Release (Ci): 7.52E-01 2.23E+00 6.58E-01 0.00E+00 3.64E+00 Average Diluted Concentration (uCi/mL): 9.68E-06 1.32E-05 2.08E-05 0.00E+00 1.31E-05 10 CFR 20, App. B Limit 1.00E-03 (uCi/mL) Percent of Limit (%): 9.68E-01 1.32E+00 2.08E+00 0.00E+00 1.31E+00 Total Error (%): 25.00 C. Dissolved & Entrained Gases Total Release (Ci): 0.00E+00 2.81E-05 0.00E+00 0.00E+00 2.81E-05 Average Diluted Concentration (uCi/mL): 0.00E+00 1.67E-10 0.00E+00 0.00E+00 1.01E-10 ODCM Limit 2.00E-04 (uCi/mL) Percent of Limit (%): 0.00E+00 8.33E-05 0.00E+00 0.00E+00 5.06E-05 Total Error (%): 120.04 D. Gross Alpha Radioactivity Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Error (%): 27.22 E. Volume of Waste Released 2.27E+05 Prior to Dilution (Liters): 7.60E+05 1.81E+05 1.17E+06 F. Volume of Dilution Water During Releases (Liters): 7.74E+07 1.61E+08 3.14E+07 0.00E+00 2.70E+08 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD). III-7
TABLE III.7 LIQUID EFFLUENTS JANUARY THROUGH DECEMBER 2020 Batch Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases SB-125 0.00E+00 2.56E-06 0.00E+00 0.00E+00 2.56E-06 NI-63 2.48E-04 0.00E+00 0.00E+00 0.00E+00 2.48E-04 CS-137 9.42E-04 2.56E-03 1.77E-03 0.00E+00 5.27E-03 CO-60 2.04E-05 4.04E-05 2.07E-05 0.00E+00 8.15E-05 CS-134 8.60E-07 9.23E-07 3.00E-06 0.00E+00 4.79E-06 EU-152 0.00E+00 2.09E-07 0.00E+00 0.00E+00 2.09E-07 Totals for Period: 1.21E-03 2.61E-03 1.79E-03 .00E+00 5.61E-03 Dissolved & Entrained Gases KR-85 0.00E+00 2.81E-05 0.00E+00 0.00E+00 2.81E-05 Totals for Period: 0.00E+00 2.81E-05 0.00E+00 0.00E+00 2.81E-05 Tritium and Gross Alpha H-3 7.52E-01 2.23E+00 6.58E-01 0.00E+00 3.64E+00 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD) values. Reported Alpha activity was attributed to natural short-lived radionuclides. This was confirmed by quarterly offside vendor analysis. III-8
TABLE III.8 LIQUID EFFLUENTS JANUARY THROUGH DECEMBER 2020 Continuous Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Products Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dissolved & Entrained Gases Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium and Gross Alpha H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD). III-9
TABLE III.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2020 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-1A Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-1B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-2 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-2A Tritium 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-2B Tritium 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-3 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma MW-3A Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 5.76E-01 0.00E+00 0.00E+00 Total Gamma 0.00E+00 0.00E+00 MW-3B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Gamma 0.00E+00 MW-4B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 III-10
TABLE III.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2020 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-5A Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 8.28E-01 Total Gamma 0.00E+00 MW-5B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-6 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 4.84E-01 8.40E-01 8.64E-01 0.00E+00 Total Gamma 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MW-7 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 7.38E-01 Total Gamma 0.00E+00 MW-12A Tritium 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-12B Tritium 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 EAST LAGOON Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 0.00E+00 0.00E+00 WEST LAGOON Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NORTH STORMWATER HDR Tritium 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma III-11
TABLE III.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2020 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter SOUTH STORMWATER HDR Tritium 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma MW-13B Tritium FE-55 NI-63 Sr-90 Total Gamma SW-6 ISFSI Tritium 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma SW-8 NORTH PA Tritium 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma MW-14 Tritium FE-55 NI-63 Sr-90 Total Gamma MW-13A Tritium FE-55 NI-63 Sr-90 Total Gamma NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD). Only Tritium and Gamma are required for each sampling event. Hard to detect (HTD) nuclide sampling frequency is per station procedures. Missed sampling events are covered in the executive summary. III-12
SECTION IV DOSE FROM GASEOUS EFFLUENTS GASPAR II OUTPUT January 1, 2020 - December 31, 2020 IV-1
Radioactive Effluent Releases - First, Second, Third and Fourth Quarters 2020 GASEOUS EFFLUENTS Radioactive gaseous releases for the reporting period totaled 3.68E+00 curies of inert gas. The gross gaseous activity release rates were 3.61E-01 Ci/sec for the first quarter, 1.06E-01 Ci/sec for the second quarter, 0.00E+00 Ci/sec for the third quarter, and 0.00E+00 Ci/sec for the fourth quarter. No radioactive halogens releases were released during the reporting period from gaseous effluent discharges. Radioactive particulate releases for the reporting period totaled 1.11E-07 curies. The particulate release rates were 0.00E+00 Ci/sec for the first quarter, 1.62E-09 Ci/sec for the second quarter, 1.24E-08 Ci/sec for the third quarter, and 0.00E+00 Ci/sec for the fourth quarter. Radioactive tritium released during the reporting period totaled 1.15E+00 curies. Off-site vendor analysis of weekly composite samples indicated that no gross alpha radioactivity was released during the reporting period. IV-2
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 to 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, was 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, 2020 through December 31, 2020 were as follows: (1) All gaseous effluents (2) Entrained gases (Ar-41, Xe-131M, Xe-133M, Xe-133, Xe-135M, Xe-135, Kr-85M, Kr-87, and Kr-88) from liquid effluents. (3) Annual 4 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 garden of interest, 0.76 for produce grown in 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/m3 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 4 by a factor ranging between 1.0 and 4.0 IV-3
(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 950,006 (based on the 2010 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
TABLE IV-A- 1 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 1 RES AT 4.36 MILES N ANNUAL_BETA_AIR_DOSE = 2.96E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.61E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.71E-07 : 1.71E-07 : 1.71E-07 : 1.71E-07 : 1.71E-07 : 1.71E-07 : 4.54E-07 : 2.05E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 2.06E-08 : 2.06E-08 : 2.06E-08 : 2.06E-08 : 2.06E-08 : 2.06E-08 : 2.06E-08 : 2.41E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 3.41E-06 : 3.41E-06 : 1.69E-10 : 3.41E-06 : 3.41E-06 : 3.41E-06 : 3.41E-06 : 3.41E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.44E-06 : 3.44E-06 : 2.37E-10 : 3.44E-06 : 3.44E-06 : 3.44E-06 : 3.44E-06 : 3.44E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.04E-06 : 3.04E-06 : 3.21E-10 : 3.04E-06 : 3.04E-06 : 3.04E-06 : 3.04E-06 : 3.04E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.75E-06 : 1.75E-06 : 1.94E-10 : 1.75E-06 : 1.75E-06 : 1.75E-06 : 1.75E-06 : 1.75E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 5
TABLE IV-A- 2 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 2 RES AT 1.93 MILES NNE ANNUAL_BETA_AIR_DOSE = 1.59E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.40E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 9.20E-07 : 9.20E-07 : 9.20E-07 : 9.20E-07 : 9.20E-07 : 9.20E-07 : 2.45E-06 : 1.11E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 1.02E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.83E-05 : 1.83E-05 : 9.67E-10 : 1.83E-05 : 1.83E-05 : 1.83E-05 : 1.83E-05 : 1.83E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.85E-05 : 1.85E-05 : 1.35E-09 : 1.85E-05 : 1.85E-05 : 1.85E-05 : 1.85E-05 : 1.85E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.63E-05 : 1.63E-05 : 1.83E-09 : 1.64E-05 : 1.63E-05 : 1.63E-05 : 1.63E-05 : 1.63E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 9.40E-06 : 9.40E-06 : 1.11E-09 : 9.41E-06 : 9.40E-06 : 9.40E-06 : 9.40E-06 : 9.40E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 6
TABLE IV-A- 3 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 3 RES AT 1.52 MILES NE ANNUAL_BETA_AIR_DOSE = 2.27E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.01E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.31E-06 : 1.31E-06 : 1.31E-06 : 1.31E-06 : 1.31E-06 : 1.31E-06 : 3.50E-06 : 1.58E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.01E-07 : 1.01E-07 : 1.01E-07 : 1.01E-07 : 1.01E-07 : 1.01E-07 : 1.01E-07 : 1.18E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 2.62E-05 : 2.62E-05 : 1.46E-09 : 2.62E-05 : 2.62E-05 : 2.62E-05 : 2.62E-05 : 2.62E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.64E-05 : 2.64E-05 : 2.05E-09 : 2.64E-05 : 2.64E-05 : 2.64E-05 : 2.64E-05 : 2.64E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.34E-05 : 2.34E-05 : 2.77E-09 : 2.34E-05 : 2.34E-05 : 2.34E-05 : 2.34E-05 : 2.34E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.34E-05 : 1.34E-05 : 1.68E-09 : 1.34E-05 : 1.34E-05 : 1.34E-05 : 1.34E-05 : 1.34E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 7
TABLE IV-A- 4 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 4 RES AT 4.79 MILES ENE ANNUAL_BETA_AIR_DOSE = 2.00E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.77E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.16E-07 : 1.16E-07 : 1.16E-07 : 1.16E-07 : 1.16E-07 : 1.16E-07 : 3.08E-07 : 1.39E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 4.45E-09 : 4.45E-09 : 4.45E-09 : 4.45E-09 : 4.45E-09 : 4.45E-09 : 4.45E-09 : 5.19E-09 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 2.31E-06 : 2.31E-06 : 1.10E-10 : 2.31E-06 : 2.31E-06 : 2.31E-06 : 2.31E-06 : 2.31E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.33E-06 : 2.33E-06 : 1.54E-10 : 2.33E-06 : 2.33E-06 : 2.33E-06 : 2.33E-06 : 2.33E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.06E-06 : 2.06E-06 : 2.08E-10 : 2.06E-06 : 2.06E-06 : 2.06E-06 : 2.06E-06 : 2.06E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.18E-06 : 1.18E-06 : 1.26E-10 : 1.18E-06 : 1.18E-06 : 1.18E-06 : 1.18E-06 : 1.18E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 8
TABLE IV-A- 5 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 5 RES AT 4.67 MILES E ANNUAL_BETA_AIR_DOSE = 2.50E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.21E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.45E-07 : 1.45E-07 : 1.45E-07 : 1.45E-07 : 1.45E-07 : 1.45E-07 : 3.85E-07 : 1.74E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 7.33E-09 : 7.33E-09 : 7.33E-09 : 7.33E-09 : 7.33E-09 : 7.33E-09 : 7.33E-09 : 8.56E-09 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 2.88E-06 : 2.88E-06 : 1.37E-10 : 2.88E-06 : 2.88E-06 : 2.88E-06 : 2.88E-06 : 2.88E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.91E-06 : 2.91E-06 : 1.92E-10 : 2.91E-06 : 2.91E-06 : 2.91E-06 : 2.91E-06 : 2.91E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.57E-06 : 2.57E-06 : 2.60E-10 : 2.57E-06 : 2.57E-06 : 2.57E-06 : 2.57E-06 : 2.57E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.48E-06 : 1.48E-06 : 1.57E-10 : 1.48E-06 : 1.48E-06 : 1.48E-06 : 1.48E-06 : 1.48E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 9
TABLE IV-A- 6 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 6 RES AT 4.22 MILES ESE ANNUAL_BETA_AIR_DOSE = 4.55E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.01E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.63E-07 : 2.63E-07 : 2.63E-07 : 2.63E-07 : 2.63E-07 : 2.63E-07 : 6.99E-07 : 3.16E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.44E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 5.24E-06 : 5.24E-06 : 2.56E-10 : 5.24E-06 : 5.24E-06 : 5.24E-06 : 5.24E-06 : 5.24E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.29E-06 : 5.29E-06 : 3.58E-10 : 5.29E-06 : 5.29E-06 : 5.29E-06 : 5.29E-06 : 5.29E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.67E-06 : 4.67E-06 : 4.84E-10 : 4.67E-06 : 4.67E-06 : 4.67E-06 : 4.67E-06 : 4.67E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.69E-06 : 2.69E-06 : 2.93E-10 : 2.69E-06 : 2.69E-06 : 2.69E-06 : 2.69E-06 : 2.69E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-10
TABLE IV-A- 7 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 7 RES AT 1.67 MILES SE ANNUAL_BETA_AIR_DOSE = 3.41E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.01E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.97E-06 : 1.97E-06 : 1.97E-06 : 1.97E-06 : 1.97E-06 : 1.97E-06 : 5.24E-06 : 2.37E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.93E-07 : 1.93E-07 : 1.93E-07 : 1.93E-07 : 1.93E-07 : 1.93E-07 : 1.93E-07 : 2.25E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 3.93E-05 : 3.93E-05 : 2.10E-09 : 3.93E-05 : 3.93E-05 : 3.93E-05 : 3.93E-05 : 3.93E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.97E-05 : 3.97E-05 : 2.95E-09 : 3.97E-05 : 3.97E-05 : 3.97E-05 : 3.97E-05 : 3.97E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.50E-05 : 3.50E-05 : 3.99E-09 : 3.50E-05 : 3.50E-05 : 3.50E-05 : 3.50E-05 : 3.50E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.02E-05 : 2.02E-05 : 2.41E-09 : 2.02E-05 : 2.02E-05 : 2.02E-05 : 2.02E-05 : 2.02E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-11
TABLE IV-A- 8 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 8 RES AT 0.65 MILES SSE ANNUAL_BETA_AIR_DOSE = 1.52E-03 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.34E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.81E-06 : 8.81E-06 : 8.81E-06 : 8.81E-06 : 8.81E-06 : 8.81E-06 : 2.34E-05 : 1.06E-03 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 2.75E-06 : 2.75E-06 : 2.75E-06 : 2.75E-06 : 2.75E-06 : 2.75E-06 : 2.75E-06 : 3.21E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.76E-04 : 1.76E-04 : 1.01E-08 : 1.76E-04 : 1.76E-04 : 1.76E-04 : 1.76E-04 : 1.76E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.77E-04 : 1.77E-04 : 1.42E-08 : 1.77E-04 : 1.77E-04 : 1.77E-04 : 1.77E-04 : 1.77E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.56E-04 : 1.56E-04 : 1.91E-08 : 1.56E-04 : 1.56E-04 : 1.56E-04 : 1.56E-04 : 1.56E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 9.00E-05 : 9.00E-05 : 1.16E-08 : 9.00E-05 : 9.00E-05 : 9.00E-05 : 9.00E-05 : 9.00E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-12
TABLE IV-A- 9 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 9 RES AT 0.73 MILES S ANNUAL_BETA_AIR_DOSE = 9.55E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 8.43E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 5.52E-06 : 5.52E-06 : 5.52E-06 : 5.52E-06 : 5.52E-06 : 5.52E-06 : 1.47E-05 : 6.63E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.44E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.10E-04 : 1.10E-04 : 6.40E-09 : 1.10E-04 : 1.10E-04 : 1.10E-04 : 1.10E-04 : 1.10E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.11E-04 : 1.11E-04 : 8.96E-09 : 1.11E-04 : 1.11E-04 : 1.11E-04 : 1.11E-04 : 1.11E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 9.81E-05 : 9.81E-05 : 1.21E-08 : 9.81E-05 : 9.81E-05 : 9.81E-05 : 9.81E-05 : 9.81E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 5.64E-05 : 5.64E-05 : 7.34E-09 : 5.64E-05 : 5.64E-05 : 5.64E-05 : 5.64E-05 : 5.64E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-13
TABLE IV-A-10 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 10 RES AT 0.65 MILES SSW ANNUAL_BETA_AIR_DOSE = 9.78E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 8.63E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 5.65E-06 : 5.65E-06 : 5.65E-06 : 5.65E-06 : 5.65E-06 : 5.65E-06 : 1.50E-05 : 6.79E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 6.42E-07 : 6.42E-07 : 6.42E-07 : 6.42E-07 : 6.42E-07 : 6.42E-07 : 6.42E-07 : 7.49E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.13E-04 : 1.13E-04 : 6.61E-09 : 1.13E-04 : 1.13E-04 : 1.13E-04 : 1.13E-04 : 1.13E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.14E-04 : 1.14E-04 : 9.26E-09 : 1.14E-04 : 1.14E-04 : 1.14E-04 : 1.14E-04 : 1.14E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.00E-04 : 1.00E-04 : 1.25E-08 : 1.00E-04 : 1.00E-04 : 1.00E-04 : 1.00E-04 : 1.00E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 5.78E-05 : 5.78E-05 : 7.58E-09 : 5.78E-05 : 5.78E-05 : 5.78E-05 : 5.78E-05 : 5.78E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-14
TABLE IV-A-11 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 11 RES AT 0.73 MILES SW ANNUAL_BETA_AIR_DOSE = 7.28E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.42E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.21E-06 : 4.21E-06 : 4.21E-06 : 4.21E-06 : 4.21E-06 : 4.21E-06 : 1.12E-05 : 5.05E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 3.90E-07 : 3.90E-07 : 3.90E-07 : 3.90E-07 : 3.90E-07 : 3.90E-07 : 3.90E-07 : 4.55E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 8.39E-05 : 8.39E-05 : 4.93E-09 : 8.39E-05 : 8.39E-05 : 8.39E-05 : 8.39E-05 : 8.39E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 8.46E-05 : 8.46E-05 : 6.90E-09 : 8.46E-05 : 8.46E-05 : 8.46E-05 : 8.46E-05 : 8.46E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 7.47E-05 : 7.47E-05 : 9.33E-09 : 7.47E-05 : 7.47E-05 : 7.47E-05 : 7.47E-05 : 7.47E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 4.30E-05 : 4.30E-05 : 5.65E-09 : 4.30E-05 : 4.30E-05 : 4.30E-05 : 4.30E-05 : 4.30E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-15
TABLE IV-A-12 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 12 RES AT 1.06 MILES WSW ANNUAL_BETA_AIR_DOSE = 3.64E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.21E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.10E-06 : 2.10E-06 : 2.10E-06 : 2.10E-06 : 2.10E-06 : 2.10E-06 : 5.59E-06 : 2.53E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.93E-07 : 1.93E-07 : 1.93E-07 : 1.93E-07 : 1.93E-07 : 1.93E-07 : 1.93E-07 : 2.25E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 4.19E-05 : 4.19E-05 : 2.23E-09 : 4.19E-05 : 4.19E-05 : 4.19E-05 : 4.19E-05 : 4.19E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.23E-05 : 4.23E-05 : 3.12E-09 : 4.23E-05 : 4.23E-05 : 4.23E-05 : 4.23E-05 : 4.23E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.74E-05 : 3.74E-05 : 4.22E-09 : 3.74E-05 : 3.74E-05 : 3.74E-05 : 3.74E-05 : 3.74E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.15E-05 : 2.15E-05 : 2.56E-09 : 2.15E-05 : 2.15E-05 : 2.15E-05 : 2.15E-05 : 2.15E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-16
TABLE IV-A-13 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 13 RES AT 1.20 MILES W ANNUAL_BETA_AIR_DOSE = 3.41E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.01E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.97E-06 : 1.97E-06 : 1.97E-06 : 1.97E-06 : 1.97E-06 : 1.97E-06 : 5.24E-06 : 2.37E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.88E-07 : 1.88E-07 : 1.88E-07 : 1.88E-07 : 1.88E-07 : 1.88E-07 : 1.88E-07 : 2.19E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 3.93E-05 : 3.93E-05 : 2.23E-09 : 3.93E-05 : 3.93E-05 : 3.93E-05 : 3.93E-05 : 3.93E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.97E-05 : 3.97E-05 : 3.13E-09 : 3.97E-05 : 3.97E-05 : 3.97E-05 : 3.97E-05 : 3.97E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.50E-05 : 3.50E-05 : 4.23E-09 : 3.50E-05 : 3.50E-05 : 3.50E-05 : 3.50E-05 : 3.50E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.02E-05 : 2.02E-05 : 2.56E-09 : 2.02E-05 : 2.02E-05 : 2.02E-05 : 2.02E-05 : 2.02E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-17
TABLE IV-A-14 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 14 RES AT 2.60 MILES WNW ANNUAL_BETA_AIR_DOSE = 7.73E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.82E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.47E-07 : 4.47E-07 : 4.47E-07 : 4.47E-07 : 4.47E-07 : 4.47E-07 : 1.19E-06 : 5.37E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 3.58E-08 : 3.58E-08 : 3.58E-08 : 3.58E-08 : 3.58E-08 : 3.58E-08 : 3.58E-08 : 4.17E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 8.91E-06 : 8.91E-06 : 4.62E-10 : 8.91E-06 : 8.91E-06 : 8.91E-06 : 8.91E-06 : 8.91E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 8.99E-06 : 8.99E-06 : 6.48E-10 : 8.99E-06 : 8.99E-06 : 8.99E-06 : 8.99E-06 : 8.99E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 7.94E-06 : 7.94E-06 : 8.76E-10 : 7.94E-06 : 7.94E-06 : 7.94E-06 : 7.94E-06 : 7.94E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 4.57E-06 : 4.57E-06 : 5.30E-10 : 4.57E-06 : 4.57E-06 : 4.57E-06 : 4.57E-06 : 4.57E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-18
TABLE IV-A-15 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 15 RES AT 2.40 MILES NW ANNUAL_BETA_AIR_DOSE = 1.18E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.04E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 6.84E-07 : 6.84E-07 : 6.84E-07 : 6.84E-07 : 6.84E-07 : 6.84E-07 : 1.82E-06 : 8.21E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 1.02E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.36E-05 : 1.36E-05 : 7.19E-10 : 1.36E-05 : 1.36E-05 : 1.36E-05 : 1.36E-05 : 1.36E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.38E-05 : 1.38E-05 : 1.01E-09 : 1.38E-05 : 1.38E-05 : 1.38E-05 : 1.38E-05 : 1.38E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.21E-05 : 1.21E-05 : 1.36E-09 : 1.21E-05 : 1.21E-05 : 1.21E-05 : 1.21E-05 : 1.21E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 6.99E-06 : 6.99E-06 : 8.25E-10 : 6.99E-06 : 6.99E-06 : 6.99E-06 : 6.99E-06 : 6.99E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-19
TABLE IV-A-16 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 16 RES AT 2.08 MILES NNW ANNUAL_BETA_AIR_DOSE = 1.87E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.65E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.08E-06 : 1.08E-06 : 1.08E-06 : 1.08E-06 : 1.08E-06 : 1.08E-06 : 2.87E-06 : 1.29E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.56E-07 : 1.56E-07 : 1.56E-07 : 1.56E-07 : 1.56E-07 : 1.56E-07 : 1.56E-07 : 1.82E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 2.15E-05 : 2.15E-05 : 1.15E-09 : 2.15E-05 : 2.15E-05 : 2.15E-05 : 2.15E-05 : 2.15E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.17E-05 : 2.17E-05 : 1.61E-09 : 2.17E-05 : 2.17E-05 : 2.17E-05 : 2.17E-05 : 2.17E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.92E-05 : 1.92E-05 : 2.18E-09 : 1.92E-05 : 1.92E-05 : 1.92E-05 : 1.92E-05 : 1.92E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.10E-05 : 1.10E-05 : 1.32E-09 : 1.10E-05 : 1.10E-05 : 1.10E-05 : 1.10E-05 : 1.10E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-20
TABLE IV-A-17 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 17 VEG AT 2.23 MILES NNE ANNUAL_BETA_AIR_DOSE = 1.05E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 9.23E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 6.05E-07 : 6.05E-07 : 6.05E-07 : 6.05E-07 : 6.05E-07 : 6.05E-07 : 1.61E-06 : 7.26E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 5.50E-08 : 5.50E-08 : 5.50E-08 : 5.50E-08 : 5.50E-08 : 5.50E-08 : 5.50E-08 : 6.42E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 2.19E-05 : 2.18E-05 : 2.88E-08 : 2.19E-05 : 2.19E-05 : 2.18E-05 : 2.18E-05 : 2.18E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.50E-05 : 2.50E-05 : 4.59E-08 : 2.50E-05 : 2.50E-05 : 2.50E-05 : 2.50E-05 : 2.50E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.88E-05 : 3.88E-05 : 1.08E-07 : 3.89E-05 : 3.88E-05 : 3.88E-05 : 3.88E-05 : 3.88E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-21
TABLE IV-A-18 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 18 VEG AT 3.20 MILES NE ANNUAL_BETA_AIR_DOSE = 3.87E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.41E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.23E-07 : 2.23E-07 : 2.23E-07 : 2.23E-07 : 2.23E-07 : 2.23E-07 : 5.94E-07 : 2.68E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.60E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 8.08E-06 : 8.07E-06 : 7.20E-09 : 8.08E-06 : 8.08E-06 : 8.07E-06 : 8.07E-06 : 8.07E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 9.24E-06 : 9.23E-06 : 1.15E-08 : 9.25E-06 : 9.24E-06 : 9.23E-06 : 9.23E-06 : 9.23E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.43E-05 : 1.43E-05 : 2.71E-08 : 1.44E-05 : 1.43E-05 : 1.43E-05 : 1.43E-05 : 1.43E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-22
TABLE IV-A-19 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 19 VEG AT 4.79 MILES ENE ANNUAL_BETA_AIR_DOSE = 2.00E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.77E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.16E-07 : 1.16E-07 : 1.16E-07 : 1.16E-07 : 1.16E-07 : 1.16E-07 : 3.08E-07 : 1.39E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 4.45E-09 : 4.45E-09 : 4.45E-09 : 4.45E-09 : 4.45E-09 : 4.45E-09 : 4.45E-09 : 5.19E-09 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 4.18E-06 : 4.18E-06 : 2.33E-09 : 4.18E-06 : 4.18E-06 : 4.18E-06 : 4.18E-06 : 4.18E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.78E-06 : 4.78E-06 : 3.71E-09 : 4.78E-06 : 4.78E-06 : 4.78E-06 : 4.78E-06 : 4.78E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 7.42E-06 : 7.42E-06 : 8.76E-09 : 7.43E-06 : 7.43E-06 : 7.42E-06 : 7.42E-06 : 7.42E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-23
TABLE IV-A-20 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 20 VEG AT 4.22 MILES ESE ANNUAL_BETA_AIR_DOSE = 4.55E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.01E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.63E-07 : 2.63E-07 : 2.63E-07 : 2.63E-07 : 2.63E-07 : 2.63E-07 : 6.99E-07 : 3.16E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.24E-08 : 1.44E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 9.50E-06 : 9.50E-06 : 6.48E-09 : 9.51E-06 : 9.50E-06 : 9.50E-06 : 9.50E-06 : 9.50E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.09E-05 : 1.09E-05 : 1.03E-08 : 1.09E-05 : 1.09E-05 : 1.09E-05 : 1.09E-05 : 1.09E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.69E-05 : 1.69E-05 : 2.44E-08 : 1.69E-05 : 1.69E-05 : 1.69E-05 : 1.69E-05 : 1.69E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-24
TABLE IV-A-21 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 21 VEG AT 1.99 MILES SE ANNUAL_BETA_AIR_DOSE = 2.12E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.87E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.22E-06 : 1.22E-06 : 1.22E-06 : 1.22E-06 : 1.22E-06 : 1.22E-06 : 3.25E-06 : 1.47E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.19E-07 : 1.19E-07 : 1.19E-07 : 1.19E-07 : 1.19E-07 : 1.19E-07 : 1.19E-07 : 1.39E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 4.42E-05 : 4.42E-05 : 6.24E-08 : 4.43E-05 : 4.42E-05 : 4.42E-05 : 4.42E-05 : 4.42E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.06E-05 : 5.05E-05 : 9.94E-08 : 5.06E-05 : 5.06E-05 : 5.05E-05 : 5.05E-05 : 5.05E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 7.85E-05 : 7.85E-05 : 2.35E-07 : 7.87E-05 : 7.85E-05 : 7.85E-05 : 7.85E-05 : 7.85E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-25
TABLE IV-A-22 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 22 VEG AT 0.94 MILES SSE ANNUAL_BETA_AIR_DOSE = 6.82E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.02E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.94E-06 : 3.94E-06 : 3.94E-06 : 3.94E-06 : 3.94E-06 : 3.94E-06 : 1.05E-05 : 4.74E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.44E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.43E-04 : 1.42E-04 : 6.48E-07 : 1.43E-04 : 1.43E-04 : 1.42E-04 : 1.43E-04 : 1.42E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.63E-04 : 1.63E-04 : 1.03E-06 : 1.64E-04 : 1.63E-04 : 1.63E-04 : 1.63E-04 : 1.63E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.53E-04 : 2.53E-04 : 2.44E-06 : 2.55E-04 : 2.54E-04 : 2.53E-04 : 2.53E-04 : 2.53E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-26
TABLE IV-A-23 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 23 VEG AT 0.73 MILES S ANNUAL_BETA_AIR_DOSE = 9.55E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 8.43E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 5.52E-06 : 5.52E-06 : 5.52E-06 : 5.52E-06 : 5.52E-06 : 5.52E-06 : 1.47E-05 : 6.63E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.24E-06 : 1.44E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 2.00E-04 : 1.99E-04 : 6.48E-07 : 2.00E-04 : 2.00E-04 : 1.99E-04 : 2.00E-04 : 1.99E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.29E-04 : 2.28E-04 : 1.03E-06 : 2.29E-04 : 2.29E-04 : 2.28E-04 : 2.28E-04 : 2.28E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.55E-04 : 3.54E-04 : 2.44E-06 : 3.57E-04 : 3.55E-04 : 3.54E-04 : 3.55E-04 : 3.54E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-27
TABLE IV-A-24 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 24 VEG AT 0.99 MILES SSW ANNUAL_BETA_AIR_DOSE = 3.87E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.41E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.23E-06 : 2.23E-06 : 2.23E-06 : 2.23E-06 : 2.23E-06 : 2.23E-06 : 5.94E-06 : 2.68E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 2.61E-07 : 2.61E-07 : 2.61E-07 : 2.61E-07 : 2.61E-07 : 2.61E-07 : 2.61E-07 : 3.05E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 8.09E-05 : 8.07E-05 : 1.37E-07 : 8.09E-05 : 8.08E-05 : 8.07E-05 : 8.08E-05 : 8.07E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 9.24E-05 : 9.23E-05 : 2.18E-07 : 9.26E-05 : 9.24E-05 : 9.23E-05 : 9.24E-05 : 9.23E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.43E-04 : 1.43E-04 : 5.15E-07 : 1.44E-04 : 1.44E-04 : 1.43E-04 : 1.43E-04 : 1.43E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-28
TABLE IV-A-25 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 25 VEG AT 1.43 MILES SW ANNUAL_BETA_AIR_DOSE = 1.41E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.24E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.15E-07 : 8.15E-07 : 8.15E-07 : 8.15E-07 : 8.15E-07 : 8.15E-07 : 2.17E-06 : 9.79E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 6.88E-08 : 6.88E-08 : 6.88E-08 : 6.88E-08 : 6.88E-08 : 6.88E-08 : 6.88E-08 : 8.02E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 2.95E-05 : 2.94E-05 : 3.60E-08 : 2.95E-05 : 2.95E-05 : 2.94E-05 : 2.94E-05 : 2.94E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.37E-05 : 3.37E-05 : 5.74E-08 : 3.37E-05 : 3.37E-05 : 3.37E-05 : 3.37E-05 : 3.37E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.23E-05 : 5.23E-05 : 1.35E-07 : 5.24E-05 : 5.23E-05 : 5.23E-05 : 5.23E-05 : 5.23E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-29
TABLE IV-A-26 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 26 VEG AT 1.13 MILES WSW ANNUAL_BETA_AIR_DOSE = 2.96E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.61E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.71E-06 : 1.71E-06 : 1.71E-06 : 1.71E-06 : 1.71E-06 : 1.71E-06 : 4.54E-06 : 2.05E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.60E-07 : 1.60E-07 : 1.60E-07 : 1.60E-07 : 1.60E-07 : 1.60E-07 : 1.60E-07 : 1.87E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 6.18E-05 : 6.17E-05 : 8.40E-08 : 6.19E-05 : 6.18E-05 : 6.17E-05 : 6.17E-05 : 6.17E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 7.07E-05 : 7.06E-05 : 1.34E-07 : 7.08E-05 : 7.07E-05 : 7.06E-05 : 7.06E-05 : 7.06E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.10E-04 : 1.10E-04 : 3.16E-07 : 1.10E-04 : 1.10E-04 : 1.10E-04 : 1.10E-04 : 1.10E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-30
TABLE IV-A-27 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 27 VEG AT 2.65 MILES WNW ANNUAL_BETA_AIR_DOSE = 7.28E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.42E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.21E-07 : 4.21E-07 : 4.21E-07 : 4.21E-07 : 4.21E-07 : 4.21E-07 : 1.12E-06 : 5.05E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 3.39E-08 : 3.39E-08 : 3.39E-08 : 3.39E-08 : 3.39E-08 : 3.39E-08 : 3.39E-08 : 3.96E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.52E-05 : 1.52E-05 : 1.78E-08 : 1.52E-05 : 1.52E-05 : 1.52E-05 : 1.52E-05 : 1.52E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.74E-05 : 1.74E-05 : 2.83E-08 : 1.74E-05 : 1.74E-05 : 1.74E-05 : 1.74E-05 : 1.74E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.70E-05 : 2.70E-05 : 6.68E-08 : 2.71E-05 : 2.70E-05 : 2.70E-05 : 2.70E-05 : 2.70E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-31
TABLE IV-A-28 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 28 VEG AT 2.40 MILES NW ANNUAL_BETA_AIR_DOSE = 1.18E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.04E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 6.84E-07 : 6.84E-07 : 6.84E-07 : 6.84E-07 : 6.84E-07 : 6.84E-07 : 1.82E-06 : 8.21E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 8.71E-08 : 1.02E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 2.47E-05 : 2.47E-05 : 4.56E-08 : 2.48E-05 : 2.47E-05 : 2.47E-05 : 2.47E-05 : 2.47E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.83E-05 : 2.82E-05 : 7.27E-08 : 2.83E-05 : 2.83E-05 : 2.82E-05 : 2.83E-05 : 2.82E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.39E-05 : 4.39E-05 : 1.72E-07 : 4.40E-05 : 4.39E-05 : 4.39E-05 : 4.39E-05 : 4.39E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-32
TABLE IV-A-29 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 29 BEEF AT 4.72 MILES NNE ANNUAL_BETA_AIR_DOSE = 2.50E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.21E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.45E-07 : 1.45E-07 : 1.45E-07 : 1.45E-07 : 1.45E-07 : 1.45E-07 : 3.85E-07 : 1.74E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.01E-08 : 1.01E-08 : 1.01E-08 : 1.01E-08 : 1.01E-08 : 1.01E-08 : 1.01E-08 : 1.18E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 7.51E-07 : 7.51E-07 : 5.51E-10 : 7.52E-07 : 7.51E-07 : 7.51E-07 : 7.51E-07 : 7.51E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.48E-07 : 4.47E-07 : 4.57E-10 : 4.48E-07 : 4.48E-07 : 4.47E-07 : 4.47E-07 : 4.47E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.42E-07 : 5.42E-07 : 8.42E-10 : 5.43E-07 : 5.42E-07 : 5.42E-07 : 5.42E-07 : 5.42E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-33
TABLE IV-A-30 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 30 BEEF AT 4.91 MILES E ANNUAL_BETA_AIR_DOSE = 2.27E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.01E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.31E-07 : 1.31E-07 : 1.31E-07 : 1.31E-07 : 1.31E-07 : 1.31E-07 : 3.50E-07 : 1.58E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 6.42E-09 : 6.42E-09 : 6.42E-09 : 6.42E-09 : 6.42E-09 : 6.42E-09 : 6.42E-09 : 7.49E-09 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 6.83E-07 : 6.83E-07 : 3.51E-10 : 6.83E-07 : 6.83E-07 : 6.83E-07 : 6.83E-07 : 6.83E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.07E-07 : 4.07E-07 : 2.91E-10 : 4.07E-07 : 4.07E-07 : 4.07E-07 : 4.07E-07 : 4.07E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.93E-07 : 4.93E-07 : 5.36E-10 : 4.93E-07 : 4.93E-07 : 4.93E-07 : 4.93E-07 : 4.93E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-34
TABLE IV-A-31 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 31 BEEF AT 0.66 MILES S ANNUAL_BETA_AIR_DOSE = 1.21E-03 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.06E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 6.97E-06 : 6.97E-06 : 6.97E-06 : 6.97E-06 : 6.97E-06 : 6.97E-06 : 1.85E-05 : 8.37E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.56E-06 : 1.56E-06 : 1.56E-06 : 1.56E-06 : 1.56E-06 : 1.56E-06 : 1.56E-06 : 1.82E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 3.63E-05 : 3.62E-05 : 8.51E-08 : 3.63E-05 : 3.62E-05 : 3.62E-05 : 3.62E-05 : 3.62E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.16E-05 : 2.16E-05 : 7.07E-08 : 2.16E-05 : 2.16E-05 : 2.16E-05 : 2.16E-05 : 2.16E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.61E-05 : 2.61E-05 : 1.30E-07 : 2.62E-05 : 2.62E-05 : 2.61E-05 : 2.61E-05 : 2.61E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-35
TABLE IV-A-32 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 32 BEEF AT 0.76 MILES SW ANNUAL_BETA_AIR_DOSE = 6.82E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.02E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.94E-06 : 3.94E-06 : 3.94E-06 : 3.94E-06 : 3.94E-06 : 3.94E-06 : 1.05E-05 : 4.74E-04 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 3.58E-07 : 3.58E-07 : 3.58E-07 : 3.58E-07 : 3.58E-07 : 3.58E-07 : 3.58E-07 : 4.17E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 2.05E-05 : 2.05E-05 : 1.95E-08 : 2.05E-05 : 2.05E-05 : 2.05E-05 : 2.05E-05 : 2.05E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.22E-05 : 1.22E-05 : 1.62E-08 : 1.22E-05 : 1.22E-05 : 1.22E-05 : 1.22E-05 : 1.22E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.48E-05 : 1.48E-05 : 2.99E-08 : 1.48E-05 : 1.48E-05 : 1.48E-05 : 1.48E-05 : 1.48E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-36
TABLE IV-A-33 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 33 BEEF AT 3.25 MILES W ANNUAL_BETA_AIR_DOSE = 3.18E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.81E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.84E-07 : 1.84E-07 : 1.84E-07 : 1.84E-07 : 1.84E-07 : 1.84E-07 : 4.89E-07 : 2.21E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.38E-08 : 1.60E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 9.56E-07 : 9.56E-07 : 7.51E-10 : 9.57E-07 : 9.56E-07 : 9.56E-07 : 9.56E-07 : 9.56E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.70E-07 : 5.69E-07 : 6.24E-10 : 5.70E-07 : 5.70E-07 : 5.69E-07 : 5.69E-07 : 5.69E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.90E-07 : 6.90E-07 : 1.15E-09 : 6.91E-07 : 6.90E-07 : 6.90E-07 : 6.90E-07 : 6.90E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-37
TABLE IV-A-34 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 34 BEEF AT 4.59 MILES WNW ANNUAL_BETA_AIR_DOSE = 2.96E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.61E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.71E-07 : 1.71E-07 : 1.71E-07 : 1.71E-07 : 1.71E-07 : 1.71E-07 : 4.54E-07 : 2.05E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.10E-08 : 1.10E-08 : 1.10E-08 : 1.10E-08 : 1.10E-08 : 1.10E-08 : 1.10E-08 : 1.28E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 8.88E-07 : 8.87E-07 : 6.01E-10 : 8.88E-07 : 8.88E-07 : 8.87E-07 : 8.87E-07 : 8.87E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.29E-07 : 5.29E-07 : 4.99E-10 : 5.29E-07 : 5.29E-07 : 5.29E-07 : 5.29E-07 : 5.29E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.41E-07 : 6.40E-07 : 9.19E-10 : 6.41E-07 : 6.41E-07 : 6.40E-07 : 6.41E-07 : 6.40E-07 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-38
TABLE IV-A-35 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 35 GOAT AT 3.30 MILES SSW ANNUAL_BETA_AIR_DOSE = 2.07E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.83E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.20E-07 : 1.20E-07 : 1.20E-07 : 1.20E-07 : 1.20E-07 : 1.20E-07 : 3.18E-07 : 1.44E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.05E-08 : 1.05E-08 : 1.05E-08 : 1.05E-08 : 1.05E-08 : 1.05E-08 : 1.05E-08 : 1.23E-08 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GOATMILK : : : : : : : : : ADULT : 2.99E-06 : 2.98E-06 : 1.46E-08 : 3.00E-06 : 2.98E-06 : 2.98E-06 : 2.98E-06 : 2.98E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.88E-06 : 3.87E-06 : 2.65E-08 : 3.91E-06 : 3.88E-06 : 3.87E-06 : 3.88E-06 : 3.87E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.14E-06 : 6.13E-06 : 6.39E-08 : 6.20E-06 : 6.15E-06 : 6.13E-06 : 6.14E-06 : 6.13E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 9.32E-06 : 9.31E-06 : 1.02E-07 : 9.43E-06 : 9.34E-06 : 9.31E-06 : 9.32E-06 : 9.31E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-39
TABLE IV-A-36 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS SPECIAL LOCATION NO. 36 GOAT AT 4.20 MILES SW ANNUAL_BETA_AIR_DOSE = 1.46E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.28E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.41E-08 : 8.41E-08 : 8.41E-08 : 8.41E-08 : 8.41E-08 : 8.41E-08 : 2.24E-07 : 1.01E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 5.50E-09 : 5.50E-09 : 5.50E-09 : 5.50E-09 : 5.50E-09 : 5.50E-09 : 5.50E-09 : 6.42E-09 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GOATMILK : : : : : : : : : ADULT : 2.10E-06 : 2.09E-06 : 7.63E-09 : 2.10E-06 : 2.10E-06 : 2.09E-06 : 2.09E-06 : 2.09E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.73E-06 : 2.72E-06 : 1.38E-08 : 2.74E-06 : 2.73E-06 : 2.72E-06 : 2.73E-06 : 2.72E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.32E-06 : 4.31E-06 : 3.33E-08 : 4.35E-06 : 4.32E-06 : 4.31E-06 : 4.32E-06 : 4.31E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 6.55E-06 : 6.55E-06 : 5.32E-08 : 6.61E-06 : 6.56E-06 : 6.55E-06 : 6.55E-06 : 6.55E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-40
TABLE IV-B-1 FORT CALHOUN 1 DOSE CONTRIBUTIONS FROM GASEOUS EFFLUENTS UNRESTRICTED AREA BOUNDARY JANUARY 1, 2020 TO DECEMBER 31, 2020 MAXIMUM SITE BOUNDARY GAMMA AIR DOSE - 1.26E-04 MILLRADS MAXIMUM SITE BOUNDARY BETA AIR DOSE - 1.43E-02 MILLRADS IV-41
TABLE IV-C-1 FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS ALARA ANNUAL INTEGRATED POPULATION DOSE
SUMMARY
(PERSON-REM) PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.26E-05 : 1.26E-05 : 1.26E-05 : 1.26E-05 : 1.26E-05 : 1.26E-05 : 4.20E-05 : 2.12E-03 :
- 1.38% : 1.38% : 85.92% : 1.38% : 1.38% : 1.38% : 4.45% : 70.14% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 1.22E-06 : 1.22E-06 : 1.22E-06 : 1.22E-06 : 1.22E-06 : 1.22E-06 : 1.22E-06 : 1.43E-06 :
- 0.13% : 0.13% : 8.32% : 0.13% : 0.13% : 0.13% : 0.13% : 0.05% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : 3.46E-04 : 3.46E-04 : 1.70E-08 : 3.46E-04 : 3.46E-04 : 3.46E-04 : 3.46E-04 : 3.46E-04 :
- 37.84% : 37.86% : 0.12% : 37.82% : 37.85% : 37.86% : 36.68% : 11.46% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : 3.90E-04 : 3.89E-04 : 5.37E-07 : 3.90E-04 : 3.90E-04 : 3.89E-04 : 3.89E-04 : 3.89E-04 :
- 42.56% : 42.55% : 3.65% : 42.58% : 42.56% : 42.55% : 41.23% : 12.88% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
COW MILK : 7.76E-05 : 7.76E-05 : 2.17E-07 : 7.78E-05 : 7.76E-05 : 7.76E-05 : 7.76E-05 : 7.76E-05 :
- 8.48% : 8.48% : 1.48% : 8.50% : 8.48% : 8.48% : 8.22% : 2.57% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : 8.78E-05 : 8.78E-05 : 7.63E-08 : 8.79E-05 : 8.78E-05 : 8.78E-05 : 8.78E-05 : 8.78E-05 :
- 9.60% : 9.59% : 0.52% : 9.59% : 9.59% : 9.59% : 9.30% : 2.90% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
*TOTAL* : 9.15E-04 : 9.15E-04 : 1.47E-05 : 9.16E-04 : 9.15E-04 : 9.15E-04 : 9.44E-04 : 3.02E-03 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-42
SECTION V DOSE FROM LIQUID EFFLUENTS LADTAP II OUTPUT January 1, 2020 - December 31, 2020 V-1
Radioactive Effluent Releases - First, Second, Third, and Fourth Quarters 2020 LIQUID EFFLUENTS During the reporting period, a total of 5.61E-03 curies of radioactive liquid materials, less tritium, dissolved noble gases, and alpha, were released to the Missouri River at an average concentration of 2.02E-08 Ci/mL. This represents 2.02E+00 percent of the limits specified in Appendix B to 10 CFR 20 (1.0E-06 Ci/mL for unrestricted areas), 3.64E+00 curies of tritium were discharged at an average diluted concentration of 1.31E-05 Ci/mL or 1.31E+00 percent of ECL (1.0E-03 Ci/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 2.77E+08 liters, while liquid waste discharges consisted of 1.17E+06 liters of radioactive liquid waste. V-2
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, 2020 through December 31, 2020 were as follows: (1) All liquid effluents were as described in Section IV except for entrained noble gases (Ar-41, Xe-131M, 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 14.73 cubic feet per second (CFS) for 2020. The average discharge rate during releases was 14.82 cubic feet per second (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 shorewidth 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
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 950,006 within a 50-mile radius of the plant (based on the 2010 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
- L AAA DDDD TTTTT AAA PPPP IIIII 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 *
- LLLLL A A DDDD T A A P IIIII IIIII *
- EVALUATION OF RADIATION DOSES FROM RELEASES OF RADIACTIVITY *
- IN NUCLEAR POWER PLANTS LIQUID EFFLUENTS *
- REVISION DATE: PNL VAX - OCTOBER 1985 *
- FORT CALHOUN ANNUAL 2020, DOSE PROJECTIONS *
- RADIOLOGICAL ASSESSMENT BRANCH *
- DIVISION OF SYSTEMS INTEGRATION *
- U. S. NUCLEAR REGULATORY COMMISSION *
- WASHINGTON, D. C. *
- DATE OF RUN: 202103041
- V-5
LOCATION IS FRESHWATER SITE A D U L T D O S E S ______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________ PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.75E-01 2.39E-01 1.57E-01 4.07E-05 8.11E-02 2.70E-02 4.71E-03 DRINKING 7.74E-04 1.36E-03 1.02E-03 3.73E-04 7.07E-04 4.84E-04 3.98E-04 SHORELINE 2.56E-04 2.19E-04 2.19E-04 2.19E-04 2.19E-04 2.19E-04 2.19E-04 2.19E-04 SWIMMING 6.72E-07 6.72E-07 6.72E-07 6.72E-07 6.72E-07 6.72E-07 6.72E-07 BOATING 3.36E-07 3.36E-07 3.36E-07 3.36E-07 3.36E-07 3.36E-07 3.36E-07 TOTAL 2.56E-04 1.76E-01 2.40E-01 1.58E-01 6.33E-04 8.20E-02 2.77E-02 5.33E-03 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH 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 12.0 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 LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.88E-01 2.49E-01 8.67E-02 3.13E-05 8.47E-02 3.29E-02 3.60E-03 DRINKING 7.58E-04 1.21E-03 5.92E-04 2.62E-04 5.82E-04 3.87E-04 2.80E-04 SHORELINE 1.43E-03 1.22E-03 1.22E-03 1.22E-03 1.22E-03 1.22E-03 1.22E-03 1.22E-03 SWIMMING 3.75E-06 3.75E-06 3.75E-06 3.75E-06 3.75E-06 3.75E-06 3.75E-06 BOATING 1.88E-06 1.88E-06 1.88E-06 1.88E-06 1.88E-06 1.88E-06 1.88E-06 TOTAL 1.43E-03 1.90E-01 2.51E-01 8.86E-02 1.52E-03 8.65E-02 3.45E-02 5.11E-03 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
C H I L D D O S E S ______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________ PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 2.36E-01 2.25E-01 3.33E-02 2.59E-05 7.34E-02 2.64E-02 1.45E-03 DRINKING 2.22E-03 2.49E-03 8.03E-04 5.04E-04 1.15E-03 7.36E-04 5.20E-04 SHORELINE 2.98E-04 2.56E-04 2.56E-04 2.56E-04 2.56E-04 2.56E-04 2.56E-04 2.56E-04 SWIMMING 7.84E-07 7.84E-07 7.84E-07 7.84E-07 7.84E-07 7.84E-07 7.84E-07 BOATING 3.92E-07 3.92E-07 3.92E-07 3.92E-07 3.92E-07 3.92E-07 3.92E-07 TOTAL 2.98E-04 2.39E-01 2.28E-01 3.44E-02 7.87E-04 7.48E-02 2.74E-02 2.22E-03 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 6.9 7.3 24.00 DRINKING 510.0 30.8 18.60 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 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 2.25E-03 3.00E-03 6.77E-04 4.95E-04 1.16E-03 7.66E-04 5.05E-04 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 2.25E-03 3.00E-03 6.77E-04 4.95E-04 1.16E-03 7.66E-04 5.05E-04 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
LOCATION IS SITE DISCHG. A D U L T D O S E S ______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________ PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.28E+00 1.74E+00 1.14E+00 2.97E-04 5.92E-01 1.97E-01 3.44E-02 DRINKING 2.38E-02 4.19E-02 3.14E-02 1.15E-02 2.18E-02 1.49E-02 1.23E-02 SHORELINE 1.87E-03 1.60E-03 1.60E-03 1.60E-03 1.60E-03 1.60E-03 1.60E-03 1.60E-03 SWIMMING 4.90E-06 4.90E-06 4.90E-06 4.90E-06 4.90E-06 4.90E-06 4.90E-06 BOATING 2.45E-06 2.45E-06 2.45E-06 2.45E-06 2.45E-06 2.45E-06 2.45E-06 TOTAL 1.87E-03 1.30E+00 1.79E+00 1.18E+00 1.34E-02 6.15E-01 2.14E-01 4.82E-02 USAGE (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__(MREM PER YEAR INTAKE)________________________________________ PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.37E+00 1.82E+00 6.33E-01 2.28E-04 6.18E-01 2.40E-01 2.63E-02 DRINKING 2.34E-02 3.71E-02 1.82E-02 8.09E-03 1.79E-02 1.19E-02 8.63E-03 SHORELINE 1.04E-02 8.93E-03 8.93E-03 8.93E-03 8.93E-03 8.93E-03 8.93E-03 8.93E-03 SWIMMING 2.74E-05 2.74E-05 2.74E-05 2.74E-05 2.74E-05 2.74E-05 2.74E-05 BOATING 1.37E-05 1.37E-05 1.37E-05 1.37E-05 1.37E-05 1.37E-05 1.37E-05 TOTAL 1.04E-02 1.40E+00 1.86E+00 6.60E-01 1.73E-02 6.45E-01 2.61E-01 4.39E-02 USAGE (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
C H I L D D O S E S ______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________ PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.72E+00 1.65E+00 2.43E-01 1.89E-04 5.36E-01 1.93E-01 1.06E-02 DRINKING 6.84E-02 7.66E-02 2.47E-02 1.55E-02 3.53E-02 2.27E-02 1.60E-02 SHORELINE 2.18E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 1.87E-03 SWIMMING 5.72E-06 5.72E-06 5.72E-06 5.72E-06 5.72E-06 5.72E-06 5.72E-06 BOATING 2.86E-06 2.86E-06 2.86E-06 2.86E-06 2.86E-06 2.86E-06 2.86E-06 TOTAL 2.18E-03 1.79E+00 1.72E+00 2.70E-01 1.76E-02 5.73E-01 2.18E-01 2.85E-02 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 6.9 1.0 24.00 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 6.93E-02 9.23E-02 2.09E-02 1.52E-02 3.59E-02 2.36E-02 1.55E-02 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 6.93E-02 9.23E-02 2.09E-02 1.52E-02 3.59E-02 2.36E-02 1.55E-02 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
* *
- FISH CONSUMPTION POPULATION DOSES * *
- PERSON-REM
__________COMMERCIAL HARVEST__________
----------------------------DOSE (PERSON-REM)-------------------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH ADULT 4.18E+06 5.78E-02 7.89E-02 5.17E-02 1.34E-05 2.68E-02 8.91E-03 1.55E-03 FISH TEENAGER 4.88E+05 9.49E-03 1.26E-02 4.39E-03 1.58E-06 4.28E-03 1.66E-03 1.82E-04 FISH CHILD 3.38E+05 1.92E-02 1.83E-02 2.71E-03 2.10E-06 5.96E-03 2.15E-03 1.18E-04 FISH TOTAL 5.01E+06 8.65E-02 1.10E-01 5.88E-02 1.71E-05 3.70E-02 1.27E-02 1.85E-03 LOCATION DILUTION CATCH TIME(HR)-INCLUDES FOOD PROCESSING TIME OF 2.40E+02 HR POPULATION=8.53E+05 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 THYROID KIDNEY LUNG GI-LLI FISH ADULT 1.22E+05 1.02E+00 1.39E+00 9.08E-01 2.36E-04 4.71E-01 1.57E-01 2.73E-02 FISH TEENAGER 1.42E+04 1.67E-01 2.21E-01 7.71E-02 2.78E-05 7.53E-02 2.93E-02 3.20E-03 FISH CHILD 9.85E+03 3.37E-01 3.22E-01 4.76E-02 3.69E-05 1.05E-01 3.77E-02 2.07E-03 FISH TOTAL 1.46E+05 1.52E+00 1.93E+00 1.03E+00 3.01E-04 6.51E-01 2.24E-01 3.26E-02 V-10
* *
- POPULATION WATER CONSUMPTION DOSES * *
- SUPPLIER-OMAHA
----------------------------DOSE (PERSON-REM)-------------------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI DRINKING ADULT 1.39E+08 1.47E-01 2.59E-01 1.94E-01 7.09E-02 1.35E-01 9.21E-02 7.58E-02 DRINKING TEENAGER 1.51E+07 2.25E-02 3.58E-02 1.76E-02 7.79E-03 1.73E-02 1.15E-02 8.31E-03 DRINKING CHILD 2.48E+07 1.08E-01 1.21E-01 3.90E-02 2.45E-02 5.57E-02 3.57E-02 2.52E-02 DRINKING TOTAL 1.79E+08 2.78E-01 4.15E-01 2.51E-01 1.03E-01 2.07E-01 1.39E-01 1.09E-01 POPULATION=5.29E+05 DILUTION=3.08E+01 TRANSIT TIME=3.06E+01 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 2.08E+08 3.23E-01 4.83E-01 2.91E-01 1.20E-01 2.41E-01 1.62E-01 1.27E-01 __________HYDROSPHERE TRITIUM DOSE__________ AVERAGE INDIVIDUAL WATER CONSUMPTION = 3.0 L/DAY PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI WATER TOTAL 2.86E+11 0.00E+00 2.77E-05 2.77E-05 2.77E-05 2.77E-05 2.77E-05 2.77E-05 V-11
* *
- RECREATION POPULATION DOSES * *
- LOCATION- DOWN STREAM SWIMMING DILUTION= 7.30E+00 TRANSIT TIME= 6.70E-01 HR SWF= 0.2
________________DOSE (PERSON-REM)_____________ PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID SHORELINE TOTAL POPUL 4.10E+07 8.73E-01 7.48E-01 7.48E-01 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 2.30E-03 2.30E-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 1.15E-03 1.15E-03
- *
- DOSE TO BIOTA * *
- MRADS PER YEAR BIOTA DILUTION= 1.00E+00 TRANSIT TIME= 0.00E+00 HR INTERNAL EXTERNAL TOTAL FISH 3.82E+00 5.84E+00 9.66E+00 INVERTEBRATE 1.92E+00 1.17E+01 1.36E+01 ALGAE 9.65E-01 3.58E-03 9.69E-01 MUSKRAT 2.07E+01 3.89E+00 2.46E+01 RACCOON 7.73E+00 2.92E+00 1.07E+01 HERON 1.21E+02 3.89E+00 1.25E+02 DUCK 1.89E+01 5.84E+00 2.48E+01 V-12
SECTION VI RADIOACTIVE EFFLUENT RELEASES - SOLID RADIOACTIVE WASTE January 1, 2020 - December 31, 2020 VI-1
VI. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT January 1, 2020 through December 31, 2020 A. Resins, Filters, and Evaporator Bottoms Waste Volume Curies Class ft3 m 3 Shipped A 0.0 0.0 0.0 B 0.0 0.0 0.0 C 0.0 0.0 0.0 Unclassified 0.0 0.0 0.0 ALL 0.0 0.0 0.0 Major Nuclides for the Above Table: N/A B. Dry Active Waste Waste Volume Curies Class ft 3 m3 Shipped A 1.43E+04 4.06E+02 7.66E-01 B 0.0 0.0 0.0 C 0.0 0.0 0.0 Unclassified 0.0 0.0 0.0 ALL 1.43E+04 4.06E+02 7.66E-01 Major Nuclides for the Above Table: H-3, C-14, Co-60, Fe-55, Ni-63, Sr-90, Tc-99, I-129, Cs-137, Pu-238, Pu-239, Pu-241, Am-241, Cm-243, Cm-244 C. Irradiated Components Waste Volume Curies Class ft3 m3 Shipped A 0.0 0.0 0.0 B 0.0 0.0 0.0 C 0.0 0.0 0.0 Unclassified 0.0 0.0 0.0 ALL 0.0 0.0 0.0 Major Nuclides for the Above Table: N/A VI-2
VI. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT (Continued) D. Other Waste Waste Volume Curies Class ft3 m3 Shipped A 1.55E+04 4.39E+02 3.37E+01 B 0.0 0.0 0.0 C 0.0 0.0 0.0 Unclassified 0.0 0.0 0.0 ALL 1.55E+04 4.39E+02 3.37E+01 Major Nuclides for the Above Table: H-3, C-14, Co-60, Fe-55, Ni-63, Sr-90, Tc-99, I-129, Cs-137, Pu-238, Pu-239, Pu-241, Am-241, Cm-242, Cm-243 E. Sum of All Low-Level Waste Shipped from Site Waste Volume Curies Class ft3 m3 Shipped A 2.98E+04 8.45E+02 3.44E+01 B 0.0 0.0 0.0 C 0.0 0.0 0.0 Unclassified 0.0 0.0 0.0 ALL 2.98E+04 8.45E+02 3.44E+01 Major Nuclides for the Above Table: H-3, C-14, Co-60, Fe-55, Ni-63, Sr-90, Tc-99, I-129, Cs-137, Pu-238, Pu-239, Pu-241, Am-241, Cm-242, Cm-243, Cm-244 VI-3
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, 2020 through December 31, 2020. ____2__ revisions were made to the Offsite Dose Calculation Manual (ODCM). ____1__ revision was made to the Process Control Program (PCP). January 1, 2020 - December 31, 2020 VII-1
Page 1 of 126 CH-ODCM-0001 II II Off-Site Dose Calculation Manual (ODCM) Revision 32 Safety Classification: Usage Level: Non-Safety Reference II II II II Change No.: EC 70292 Reason for Change: ISFSI Only Tech Spec Preparer: J. Hoffman Fort Calhoun Station
CH-ODCM-0001 Reference Use Page 2 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table of Contents PART I 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 ................................................................................................. 29 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) .................. 30 5.1 Monitoring Program ................................................................................................. 30 5.2 Land Use Survey ..................................................................................................... 45 5.3 Interlaboratory Comparison Program ...................................................................... 46 6.0 ADMINISTRATIVE CONTROLS.................................................................................... 47 6.1 Responsibilities ....................................................................................................... 47 6.2 Radioactive Effluent Reporting Requirements ......................................................... 47 6.3 Change Mechanism ................................................................................................ 52 6.4 Meteorological Data ................................................................................................ 52 6.5 References .............................................................................................................. 53 7.0 BASIS ............................................................................................................................ 55 7.1 Instrumentation ....................................................................................................... 55 7.2 Radioactive Effluents............................................................................................... 55 7.3 Radiological Environmental Monitoring ................................................................... 60 7.4 Abnormal Release or Abnormal Discharge Reporting ............................................. 61
CH-ODCM-0001 Reference Use Page 3 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 List of Tables PART I Table 1.2 - Frequency Notation ............................................................................................... 8 Table 1.3 - Radiological Effluent Controls Program Technical Specification 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 4.3 - Sampler Deposition/Transportation Correction Factors ....................................... 26 Table 5.1 - Radiological Environmental Monitoring Program ................................................. 32 Table 5.2 - Radiological Environmental Sampling Locations And Media ............................... 35 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ................................................................................................... 43 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples ...................................................................................... 44 List of Figures PART I Figure 1 - Environmental Radiological Sampling Points ....................................................... 41 Figure 2 - 40CFR190 Sampling Points ................................................................................. 42
CH-ODCM-0001 Reference Use Page 4 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table of Contents PART II 1.0 EFFLUENT MONITOR SETPOINTS ............................................................................. 64 1.1 Liquid Effluents ........................................................................................................ 64 1.2 Airborne Effluents .................................................................................................... 67 2.0 EFFLUENT CONCENTRATIONS ................................................................................. 75 2.1 Liquid Effluent Concentrations ................................................................................ 75 2.2 Airborne Effluent Concentrations ............................................................................ 75 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS ................................................... 77 3.1 Liquid Effluent Dose Calculations ............................................................................ 77 3.2 Airborne Effluent Dose Calculations ........................................................................ 80 4.0 LOWER LIMIT OF DETECTION (LLD) ......................................................................... 93
CH-ODCM-0001 Reference Use Page 5 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 List of Tables PART II Table 1 - Deleted ................................................................................................................... 67 Table 2 - Deleted ................................................................................................................... 94 Table 3 - Bioaccumulation Factors ........................................................................................ 94 Table 4 - Highest Potential Exposure Pathways for Estimating Dose.................................... 95 Table 5 - Stable Element Transfer Data ................................................................................ 96 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data................................................................... 97 Table 7 - Animal Consumption Rates .................................................................................... 97 Table 8 - External Dose Factors for Standing on Contaminated Ground ............................... 98 Table 9 - Inhalation Dose Factors for Adult ......................................................................... 101 Table 10 - Inhalation Dose Factors for Teenager ................................................................ 104 Table 11 - Inhalation Dose Factors for Child ....................................................................... 107 Table 12 - Inhalation Dose Factors for Infant ...................................................................... 110 Table 13 - Ingestion Dose Factors for Adult ........................................................................ 113 Table 14 - Ingestion Dose Factors for Teenager ................................................................. 116 Table 15 - Ingestion Dose Factors for Child ........................................................................ 119 Table 16 - Ingestion Dose Factors for Infant ....................................................................... 122 Table 17 - Recommended Values for Other Parameters ..................................................... 125 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure .... Error! Bookmark not defined. List of Figures PART II Figure 1 - Exclusion and Site Boundary Map ........................................................................ 68 Figure 2 - Liquid Radioactive Discharge Pathways ............................................................... 69 Figure 3 - Liquid Radioactive Waste Disposal System .......................................................... 70 Figure 4 - Airborne Effluent Discharge Pathways .................................................................. 71 Figure 5 - Airborne Radioactive Waste Disposal System ...................................................... 72
CH-ODCM-0001 Reference Use Page 6 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 Contains 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.
CH-ODCM-0001 Reference Use Page 7 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 radioactive 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 Site Boundary - The Site Boundary is the line beyond which the land is neither owned, or leased, nor controlled by the licensee. 2.10 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. 2.11 Special Liquid - Non-routine release pathway in which normally non-radioactive liquid streams (such as Raw Water) found to contain radioactive material, are non-routine, and will be treated on a case specific basis if and when this occurs. 2.12 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. 2.13 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. 2.14 Water Effluent Concentration (WEC) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.
CH-ODCM-0001 Reference Use Page 8 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
CH-ODCM-0001 Reference Use Page 9 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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, 6.2.1D E.4.1 6.2.1 E.4.2 6.2.2
CH-ODCM-0001 Reference Use Page 10 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 11 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 12 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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
CH-ODCM-0001 Reference Use Page 13 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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-062, 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.
CH-ODCM-0001 Reference Use Page 14 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Channels Action Functional
- 1. Forced Draft releases 1.1 Particulate-Auxiliary Bldg. Exhaust Stack (RM-052, 1 1,4 RM-062) 1.2 Particulate-Laboratory and Radwaste Processing 1 2 Building Stack (RM-043) 1.3 Particulate air sampler-Portable filtered ventilation 1 5 systems discharge
- 2. Unventilated building opening 2.1 Particulate air sampler-open doorway/ open rollup 1 6 door
- 3. Open-air demolition 3.1 Particulate air samplers (4 air samplers at each 4 7 open-air location)
- 4. Flow Rate Measurement Devices 4.1 Auxiliary Building Exhaust Stack 1 3 4.2 Laboratory and Radwaste Processing Building Stack 1 3 4.3 Hand-held anemometer 1 3
CH-ODCM-0001 Reference Use Page 15 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 3.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation Table Notation ACTION 1 If the Auxiliary Building Exhaust Stack Particulate Sampler is non-functional, ventilation of the Auxiliary Building may continue through the Auxiliary Building Exhaust Stack provided sample collection in accordance with Table 4.2 using auxiliary sample collection equipment is initiated within 2 hours of the declaration of non-functionality by the ISFSI Shift Supervisor (ISS). ACTION 2 If the Particulate Sampler is non-functional, ventilation of the LRWPB may continue via the LRWPB Stack provided sample collection using auxiliary sample collection equipment is initiated within 2 hours of the declaration of non-functionality, by the ISFSI Shift Supervisor (ISS), in accordance with Table 4.2. ACTION 3 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 4 During the ventilation of airborne effluents from the Auxiliary Building Exhaust Stack at least one Auxiliary Building Exhaust fan shall be in operation. ACTION 5 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 6 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 7 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.
CH-ODCM-0001 Reference Use Page 16 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Calibration Function Check Check Test
- 1. Flowrate Monitors
------ 1.1 RM-043 Sampler D - R -Q- - ---- I 1.2 RM-062 Sampler D R Q ----
1.3 RM-052 Sampler D R Q ---- 1.4 Auxiliary Bldg Exhaust Stack D R Q ---- 1.5 Laboratory and Radwaste Process Bldg Exhaust Stack D R Q ---- Operations Check Air Flow Calibration
- 2. Environmental Monitors 2.1 RM-023 - Sample Station #40 M A 2.2 RM-024 - Sample Station #41 M A 2.3 RM-025 - Sample Station #28 ---- ----
2.4 RM-026 - Sample Station #36 ---- ---- 2.5 RM-027 - Sample Station #37 M A 2.6 RM-028 - Sample Station #38 ---- ---- 2.7 RM-029 - Sample Station #39 ---- ---- 2.8 RM-035 - Sample Station #1 ---- ---- 2.9 RM-036 - Sample Station #2 M A 2.10 RM-037 - Sample Station #3 ---- ---- 2.11 RM-038 - Sample Station #4 M A 2.12 RM-039 - Sample Station #5 ---- ---- 2.13 RM-040 - Sample Station #32 M A
- 3. Decommissioning portable air sampler flowmeters 3.1 All sample stations W1 A 1- Operation check performed only when the unit is started to support active decommissioning.
CH-ODCM-0001 Reference Use Page 17 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 18 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 19 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis A. Monitor, Hotel Waste Tanks & Special Liquid, Releases Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Each Batch Principal Gamma Emitters B 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.
CH-ODCM-0001 Reference Use Page 20 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 II of the Off-Site Dose Calculation Manual at least once per quarter.
CH-ODCM-0001 Reference Use Page 21 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
- 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 the monitor tanks for release.
CH-ODCM-0001 Reference Use Page 22 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 4.1.3B.2 (continued)
- b. Waste filters (WD-17A 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.
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.
CH-ODCM-0001 Reference Use Page 23 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 24 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis A. Auxiliary Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly Tritium (H-3) 1.0E-06 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Samples) Sr-89, Sr-90 1.0E-11 B. Laboratory and Radwaste Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-89, Sr-90 1.0E-11 C. Forced Draft Exhaust discharge Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-90 1.0E-11 D. Unventilated building doorways Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-90 1.0E-11
CH-ODCM-0001 Reference Use Page 25 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 E. Open-Air Demolition locations Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 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. D. Particulate samples shall be corrected for sampler deposition/transportation efficiency by using the approved software programs or by multiplying the activity obtained by the associated sampler multiplication factor (See Table 4.3).
CH-ODCM-0001 Reference Use Page 26 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 4.3 - Sampler Deposition/Transportation Correction Factors Particulate Sampler Sample DF ACTMULT RM-062 AB 0.411 2.433 RM-052 AB 0.638 1.567 RM-043 LRWPB 0.809 1.236 Forced Draft, Portable Air Unventilated Sampler Building, Open-Air 1.00 1.00 ACRONYM DEFINITIONS: AB - Auxiliary Building Exhaust Stack LRWPB - Laboratory and Rad Waste Processing Building DF - Deposition Factor ACTMULT - Activity multiplication factor to correct for sample loss.
CH-ODCM-0001 Reference Use Page 27 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
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
CH-ODCM-0001 Reference Use Page 28 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32
- 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.
- 2. FUNCTIONAL is defined as follows:
- a. Ventilation Exhaust Systems
- 1) The radioactive effluents from the controlled access area of the auxiliary building are filtered by the HEPA filters in the auxiliary building ventilation system. 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.
CH-ODCM-0001 Reference Use Page 29 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 25 mrem to the total body or any organ (except the thyroid, which shall be limited to 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.
CH-ODCM-0001 Reference Use Page 30 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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).
CH-ODCM-0001 Reference Use Page 31 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 surveillance 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.
CH-ODCM-0001 Reference Use Page 32 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 1. Direct Radiation 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 sector 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 Quarterly 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 unrestricted area composite boundary 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 composite for C. Missouri River upstream of H-3 Analysis Facility intake (background)F.
- 4. Milk D 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.
CH-ODCM-0001 Reference Use Page 33 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B 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 D/Q offsite location. C. One sample outside of 5 miles (background) F.
CH-ODCM-0001 Reference Use Page 34 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 Ci/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 (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") E. Samples should be collected from garden plots of 500 ft2 or more. (Reference Reg. Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants," Dec. 1975). 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".
CH-ODCM-0001 Reference Use Page 35 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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°/S 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
CH-ODCM-0001 Reference Use Page 36 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 14D 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,D,F Mohr Dairy 9.86 186°/S J X X X 21A Fish Sampling Area, 0.08 22 Missouri River (R.M. 645.0) 6°/N A X Fish Sampling Area, 17.9 23D Missouri River (R.M. 666.0) 358°/N A X 24A 25A 26A 27A
CH-ODCM-0001 Reference Use Page 37 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 28A 29A 30A 31A 32D 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 40A 41B,C Dowler Acreage 0.73 175°/S 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
CH-ODCM-0001 Reference Use Page 38 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 58D Sector A-2 4.54 350°/NORTH A X 59D Sector B-2 2.95 26°/NNE B X 60D Sector C-2 3.32 50°/NE C X 61D Sector D-2 3.11 75°/ENE D X 62D Sector E-2 2.51 90°/EAST E X 63D Sector F-2 2.91 110°/ESE F X 64D Sector G-2 3.00 140°/SE G X 65D Sector H-2 2.58 154°/SSE H X 66D Sector J-2 3.53 181°/SOUTH J X 67D Sector K-2 2.52 205°/SSW K X 68D Sector L-2 2.77 214°/SW L X 69D Sector M-2 2.86 243°/WSW M X
CH-ODCM-0001 Reference Use Page 39 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 70D Sector N-2 2.54 263°/WEST N X 71D Sector P-2 2.99 299°/WNW P X 72D Sector Q-2 3.37 311°/NW Q X 73D 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 X 76A 77G 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 80G Parking S-1 0.27 158°/SSE H X 81G 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°/SSW K X
CH-ODCM-0001 Reference Use Page 40 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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)
CH-ODCM-0001 Reference Use Page 41 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Figure 1 - Environmental Radiological Sampling Points N Q ORAWINCi FIL£ NO. P- 00075 (*) Locations currently discontinued are not illustrated.
CH-ODCM-0001 Reference Use Page 42 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Figure 2- 40CFR190 Sampling Points N
- fl-..
I
- I *, **
IQ1(A i' ' .... I NEBRASKA . ' UWf.S'l'lOTEO ARE'A B . !)ARY OR'T ALHOtN f #l TO fl:l JR , CD _QUID EFJl'LUEN1 rnsoHA~G AlREORNE EFFL NT8 D1$CHABGE
- SA PLI G POI NT t
s I SOAJ.E IN MILES SITE BOUNDARY MAP DRfl WI NG FILE t.'O. P-00423
CH-ODCM-0001 Reference Use Page 43 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) A, B, 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/m3 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.
CH-ODCM-0001 Reference Use Page 44 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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/m3 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: 1 2 3
+ + + . . . . 1.0 1 2 3 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.
CH-ODCM-0001 Reference Use Page 45 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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).
CH-ODCM-0001 Reference Use Page 46 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 Interlaboratory Comparison Program 5.3.1 Limiting Condition for Operation A. Analyses shall be performed on radioactive materials as part of an Interlaboratory 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).
CH-ODCM-0001 Reference Use Page 47 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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; Reg. Guide 4.8, Table 1; 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.
CH-ODCM-0001 Reference Use Page 48 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 following the format of Regulatory Guide 4.8, Table 1. 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 Interlaboratory Comparison Program. D. The results of land use survey required by Section 5.2. E. A map of the current environmental monitoring sample locations.
CH-ODCM-0001 Reference Use Page 49 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 50 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 6.2.6 ISFSI 10 CFR Part 72.104 Reporting Requirements The regulatory requirements of 10CFR20, 10CFR72 and 40CFR190 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 40CFR190. 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)
CH-ODCM-0001 Reference Use Page 51 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 Where D,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
CH-ODCM-0001 Reference Use Page 52 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 the Safety Review Committee 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 historical Average /Q 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 /Q 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 or as needed 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.
CH-ODCM-0001 Reference Use Page 53 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 Regulatory Guide 4.8, Environmental Technical Specification for Nuclear Power Plants. 6.5.5 NRC Branch Technical Position, March 1978 6.5.6 NUREG-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants. 6.5.7 NUREG-1301 - Offsite Dose Calculation Manual Guidance. 6.5.8 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. 6.5.9 Code of Federal Regulations, Title 10, Part 20 6.5.10 Code of Federal Regulations, Title 10, Part 50 6.5.11 Code of Federal Regulations, Title 10, Part 72 6.5.12 Code of Federal Regulations, Title 40, Part 190 6.5.13 Fort Calhoun Revised Environmental Report (Unit No. 1)-1972 6.5.14 NO-FC-10, Quality Assurance Topical Report 6.5.15 Defueled Safety Analysis Report 6.5.16 AR 12357, Implement Recommendations of Memo FC-0133-92, Part I, Table 3.2.1 Action 4, of the Off-Site Calculation Manual 6.5.17 AR 39127, NEI Industry Initiative on Groundwater Protection
CH-ODCM-0001 Reference Use Page 54 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 6.5.18 Regulatory Guide 4.1, Rev. 2 - Radiological Environmental Monitoring for Nuclear Power Plants 6.5.19 FC-19-001, ODCM rev 29 Change Support Document 6.5.20 FC-18-005, Habits of the Real Individual in Vicinity of Fort Calhoun Station, X/Q, Direct Radiation Dose Calculation
CH-ODCM-0001 Reference Use Page 55 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 II 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.
CH-ODCM-0001 Reference Use Page 56 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 B. Dose This specification is provided to implement the requirements of Sections II.A, III.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 III.A that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Part 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 II.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.
CH-ODCM-0001 Reference Use Page 57 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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. 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 II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.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 III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The 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.
CH-ODCM-0001 Reference Use Page 58 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 II.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 II.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded.
CH-ODCM-0001 Reference Use Page 59 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 60 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 61 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 7.3.3 Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. 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.
CH-ODCM-0001 Reference Use Page 62 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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
CH-ODCM-0001 Reference Use Page 63 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 PART II CALCULATIONS
CH-ODCM-0001 Reference Use Page 64 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents 1.1.1 There is one liquid discharge pathway to the Missouri River. The pathway originates with the radioactive liquid waste processing system (monitor or hotel tanks). This pathway empties into the circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathway and associated radiation monitor. Figure 3 depicts the methods of liquid effluent treatment. 1.1.2 The flowrate for dilution water varies with the number raw water 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.
CH-ODCM-0001 Reference Use Page 65 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 1.1.7 Liquid Effluent Radiation Monitor A. Overboard Discharge Header Monitor (RM-055)
- 1. This process radiation monitor provides control of the waste monitor tank effluent by monitoring the overboard header prior to its discharge into the circulating water discharge tunnel. The concentration of activity at discharge is controlled below ten times the 10 CFR Part 20 limit of 1.0E-06 Ci/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 monitor tank discharge.
- 3. The maximum allowable concentration in the overboard discharge header is:
(1.0 05 ) ()
=
Where: 1.0E-05 Ci/ml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2). F = Total dilution flow in the discharge tunnel (gpm). (Normal flow is based on 2 raw water pumps at 7,200 gpm total.) f = Maximum monitor tank discharge flow rate (gpm). (Normal monitor tank maximum flow is 15 gpm.) CMAX = Maximum allowable activity in discharge header (Ci/ml).
CH-ODCM-0001 Reference Use Page 66 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 1.1.7A (continued) The High Alarm Setpoint (CPM):
= 0.75 [((3 )( )( )) + ]
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. Sf = Detector sensitivity factor (CPM/Ci/ml). (Sensitivity based on Cs-137). K3 = Allocation factor for Waste Liquid Releases (1) CMAX = Maximum allowable concentration in discharge header (Ci/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.
CH-ODCM-0001 Reference Use Page 67 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 installed or portable filtered ventilation units with a fan with a rated cfm as the release rate. Monitoring of forced draft ventilation includes utilizing presently installed system monitors such as RM-062, RM-052, and RM-043. 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
CH-ODCM-0001 Reference Use Page 68 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Figure 1 - Exclusion and Site Boundary Map
,N
' \
!~-
I CD UQUID EFft' :HlNl' ' Dll:JCIHAROE AIR' ORNE '.lli:f'FL - ' El DlSOHARO TO owuu 0 l p r SCALE MILES SlfE BO _.'. DARY MAP P- 00414
CH-ODCM-0001 Reference Use Page 69 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Figure 2 - Liquid Radioactive Discharge Pathways HOTEL RAW WATER TANKS MONITOR TANKS RM-O55 OUTFALL CIRCULATING WATER WARM WATER RECIRCULATION LIQUID RADIOACTIVE DISCHARGE PATHWAYS DRAWING FILE NO. P-00410
CH-ODCM-0001 Reference Use Page 70 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Figure 3 - Liquid Radioactive Waste Disposal System REACTOR COOLANT AUXILIARY SYSTEMS WASTE PROCESS WASTE eves BlBedorf HOTEL wASTE r=-loor DraLn'l Equipment Di---mns Laundr~ Wav-te Sump Flow,; RC Loop Drains Sho1,1r;,r Drain~ Spent Rggr;,nr;,i---ant Tanks 55]0 Gol _ 11 \ 1
\1 De miner al izer VE'SsE'Js 30 Cu" FL 00000 Charcoal r=-Ll ter 69 Cu, Ft"
( op-tJOnall \1 [j[j r1onL tor Tankv G770 Cal" t OvBrboard Heodcor (To River) LIQUID RADIOACTIVE WASTE DISPOSAL SYSTEM
CH-ODCM-0001 Reference Use Page 71 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Figure 4 - Airborne Effluent Discharge Pathways RIM - 043 LRWPB Sampler LRVfPB L .boratory BORATOR ND RADIOACTIV G 1 M- 062,052 P artic u late Sampler AUXILIAR A x ihary Building Ven UlaUo AIRBOR E EFFLUE T DISCHARGE PATHWAYS ORA\li1I G FILE NO. P- 004 11
CH-ODCM-0001 Reference Use Page 72 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Figure 4 - Airborne Effluent Discharge Pathways (continued) 8d FORCED DRAFT AIR SAMPLER WITH EXHAUST TRUNK DISCHARGE FORCED DRAFT AIR SAMPLER WITH OUTLET PLENUM
,,I
, ' I
, I
, ' I o I J _ - - - --'- -
r---------------------------
~-----~---------- -*---------
CH-ODCM-0001 Reference Use Page 73 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 UNVENTILATED BUILDING RELEASE AIR SAMPLERS Figure 4 - Airborne Effluent Discharge Pathways (continued) w OPEN-AIR DEMOLITION AIR SAMPLERS
CH-ODCM-0001 Reference Use Page 74 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Figure 5 - Airborne Radioactive Waste Disposal System Au x ary Bu din Venlil lion SL ck 122,500 CFM Gro nd
CH-ODCM-0001 Reference Use Page 75 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 2.0 EFFLUENT CONCENTRATIONS 2.1 Liquid Effluent Concentrations 2.1.1 The concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) will be limited to the concentrations as specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. For batch releases (Monitor and Hotel Waste Tanks) 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:
=
+
1
=1 Radionuclide concentration at site discharge:
Where: Ai = concentration at site discharge for radionuclide (I), in Ci/ml. ai = concentration of radionuclide (I) in the undiluted effluent, in Ci/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 i I In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable. I i 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:
CH-ODCM-0001 Reference Use Page 76 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32
= 0 ( )
1
=1 Where:
Ai = Concentration of radionuclide (I) at the unrestricted area boundary K0 = Constant of unit conversion. (1.0E-6 m3/cc) ECLi = Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, Column 1 value for radionuclide(I)) Qi = The release rate of radionuclide (I) in airborne effluents from all vent releases (in Ci/sec.) (/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from Part II, 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.
CH-ODCM-0001 Reference Use Page 77 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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.
CH-ODCM-0001 Reference Use Page 78 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 3.1.3 Doses from Liquid Effluent Pathways A. Potable Water
= 1100 exp( )
=1 Where:
Rapj = is the total annual dose to organ(j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr. Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in
/yr. (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 ft3/ sec. Qi = 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 (j) which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = 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 water, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 79 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 3.1.3 (continued) B. Aquatic Foods
= 1100 exp( )
=1 Where:
Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr. Uap = is a usage factor that specifies the 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 ft3/sec. Qi = is the annual release rate of radionuclide (I), in Ci/yr. Bip = is the equilibrium bioaccumulation factor for radionuclide (I) in pathway (p) expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in (pCi/kg)/(pCi/liter). (Table 3) Daipj = is the dose factor specific to a given age group (a), radionuclide (I), pathway (p), and organ (j), which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = 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
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 80 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 3.1.3 (continued) C. Shoreline Deposits
= 110,000 [exp( )] [1 exp( )]
=1 Where:
Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr. Uap = is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p), in hr/yr. (Table 6) 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 ft3/sec. Qi = 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/m2). (Table 8) i = 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, in hours. (Table 17) tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours. (Table 17) 110,000 = Constant [(100
- pCi
- yr
- ft3)/(Ci
- sec
- L)]
3.2 Airborne Effluent Dose Calculations
CH-ODCM-0001 Reference Use Page 81 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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:
CH-ODCM-0001 Reference Use Page 82 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 NOTE I i In all cases, for releases of tritium, use the dispersion Iparameter for inhalation (/Q). I i 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 , with respect to the release point, may be determined by: [1.01012 ][ (, ) ] (, ) = [1 exp( )] Where: CGI = is the ground plane concentration of the radionuclide (I) at distance r, in the sector at angle , from the release point, in pCi/m2. Qi = is the annual release rate of radionuclide (I) to the atmosphere, in Ci/yr. tb = 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) i(r,) = is the annual average relative deposition of radionuclide (I) at distance r, in the sector at angle , considering depletion of the plume by deposition during transport, in m-2. Table 4 i = is the radiological decay constant for radionuclide (I), in yr-1. 1.0x1012 = is the number of pCi/Ci
CH-ODCM-0001 Reference Use Page 83 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 The annual organ dose is then calculated using the following equation: (, ) = 8760 (, )
=1 Where:
CGj(r,) = is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle , in pCi/m2. DFGij = is the open field ground plane dose conversion factor for organ (j) from radionuclide (i), in mrem-m2/pCi-hr. (Table 8) DGj(r,) = is the annual dose to the organ (j) at distance r, in the sector at angle , in mrem/yr. Sf = 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 , with respect to the release point, may be determined as: (, ) = 3.17 104 [] (, ) Where: Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr. i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
[/Q]D (r,) = is the annual average atmosphere dispersion factor, in sec/m3 (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.
CH-ODCM-0001 Reference Use Page 84 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 The annual dose associated with inhalation of all radionuclides to organ (j) of an individual in age group (a), is then: (, ) = (, )
=1 Where:
DAja(r,) = is the annual dose to organ (j) of an individual in the age group (a) at distance r, in the sector at angle , due to inhalation, in mrem/yr. Ra = is the annual air intake for individuals in the age group (a), in m3/yr. (Table 6) i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
DFAija = is the inhalation dose factor for radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 9-12)
CH-ODCM-0001 Reference Use Page 85 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 [1 exp( )] [1 exp( )] (, ) = (, ) [ + ] exp( ) Where: CVi(r,) = is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle , in pCi/kg. di (r,) = is the deposition rate of radionuclide (i) at distance r, in the sector at angle , in pCi/m2 hr. r = is the fraction of deposited activity retained on crops, dimensionless. (Table 17) Ei = is the effective removal rate constant for radionuclide (i) from crops, in hr-1. Ei = i + w w = 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) Biv = is the concentration factor for uptake of radionuclide (i) from soil by edible parts of crops, in pCi/ kg (wet weight) per pCi/kg dry soil. (Table 5) i = is the radiological decay constant of radionuclide (I), in hr-1 tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours (mid-point of plant life). (Table 17) P = is the effective "surface density" for soil, in kg (dry soil)/m2. (Table 17) th = is the holdup time that represents the time interval between harvest and consumption of the food, in hours. (Table 17) Different values for the parameters te, 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.
CH-ODCM-0001 Reference Use Page 86 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa. C-6): (, ) = 1.1 108 (, ) Where: di(r,) = is the deposition rate of radionuclide (i). i(r,) = is the relative deposition of radionuclide (i), considering depletion and decay, in m-2 (see Reg Guide 1.111). (Table 4) 1.1x108 = is the number of pCi/Ci (1012) divided by the number of hours per year (8760). Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
CH-ODCM-0001 Reference Use Page 87 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 B. For radioiodines, the model considers only the elemental fraction of the effluent: (, ) = 3.3 107 (, ) Where: di (r, ) = 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). i (r, ) = The relative deposition of radioiodine (i), considering depletion and decay, in m-2. (Table 4) Qi = 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) (, ) = (, ) + (1 ) (, ) + (1 ) (, ) Where: CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. CPi(r,) = is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2.3A with th=0), in pCi/kg. CSi(r,) = is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3A with th=90 days), in pCi/kg. fp = 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)
CH-ODCM-0001 Reference Use Page 88 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 3.2.3 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk (, ) = (, ) exp( ) Where: CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter. CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. Fm = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each liter of milk, in days/liter. (Table 5) QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) tf = 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) i = is the radiological decay constant of radionuclide (i), in days-1.
CH-ODCM-0001 Reference Use Page 89 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium (, ) = (, ) exp( ) Where: CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter. CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) Ff = 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. [](, )(0.75)(0.5) [](, ) (, ) = 3.17 107 = 1.2 107 Where: CVT(r, ) = is the concentration of tritium in vegetation grown at distance r, in the sector at angle , in pCi/kg. H = is the absolute humidity of the atmosphere at distance r, in the sector at angle , in g/m3. H=8 gm/kg. QT = is the annual release rate of tritium, in Ci/yr. [/Q](r,) = is the atmospheric dispersion factor, in sec/m3. (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.
CH-ODCM-0001 Reference Use Page 90 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 3.2.6 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ (j) of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by: (
, ) = [ (, ) + (, ) + (, ) + (, )]
Where: DDja(r,) = is the annual dose to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem/yr. DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. Tables 13-16. UVa = are the ingestion rates of produce (non-leafy vegetables, fruits, and grains) , respectively for individuals in age group (a). (Table 6) UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6) UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6) ULa = are the ingestion rates of leafy vegetables for individuals in age group (a), in kg/yr. (Table 6) CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter. CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter. CLI (r,) = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg. fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 91 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce) Vegetation for Radionuclide (i) to Each Organ (j) and Age Group (a) (, ) = [ (, ) + (, )] Where: DDja(r,) = is the annual dose from the ingestion of radionuclide (i) to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in vegetation, in mrem/yr. DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pci. Tables 13-16 ULa,UVa = 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) CLi = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg. CVi = 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) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 92 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 C. Calculation Determining the Ingested Dose from Cow Milk for Radionuclide (i), Organ (j), and Age Group (a) (, ) = [ (, )] Where: DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in cow milk, in mrem/yr. DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16) UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6) CMi = 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 (j) and Age Group (a) (, ) = [ (, )] Where: DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in meat, in mrem/yr. DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16) UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6) CFi = is the radionuclide (i) concentration in meat, in pCi/kg.
CH-ODCM-0001 Reference Use Page 93 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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
=
exp() 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
= the radioactive decay constant for the particular radionuclide t = the elapsed time between the midpoint of sample collection and time of counting Appropriate values of E, V, Y, and t 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.
CH-ODCM-0001 Reference Use Page 94 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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
CH-ODCM-0001 Reference Use Page 95 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 4 - Highest Potential Exposure Pathways for Estimating Dose Distance
/Q A D/Q A Exposure from Location B Direction B {/Q (r,)} { (r,)}
Pathway Containment (sec/m3) (m-2) (miles) B Direct Exposure Site NW 0.29 4.90E-05 N/A Boundary Inhalation Site NW 0.29 4.90E-05 N/A Boundary Ingestion Residence SSE 0.60 N/A 7.6E-08 A. These values are used for calculating quarterly dose estimates during the annual reporting period and are based on a 5 year historical average. At least ten percent (10%) should 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.
CH-ODCM-0001 Reference Use Page 96 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 5 - Stable Element Transfer Data Biv Fm (cow) Fm (goat) Ff Element Veg./Soil Milk (d/I) Milk (d/I) Meat (d/kg) H 4.8E+00 1.0E-02 1.7E-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 6.7E-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 1.7E-02 8.0E-04 1.4E-02 6.0E-04 Y 2.6E-03 1.0E-05 ------ 4.6E-03 Zr 1.7E-04 5.0E-06 ------ 3.4E-02 Nb 9.4E-03 2.5E-03 ------ 2.8E-01 Mo 1.2E-01 7.5E-03 ------ 8.0E-03 Tc 2.5E-01 2.5E-02 ------ 4.0E-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 ------ 1.7E-02 Sb 1.1E-02 1.5E-03 ------ 4.0E-03 Te 1.3E+00 1.0E-03 ------ 7.7E-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 ------ 4.7E-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
CH-ODCM-0001 Reference Use Page 97 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 (/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 (/yr) 330 510 510 730 Shoreline recreation (hr/yr) --- 14 67 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table 7 - Animal Consumption Rates Animal QF Feed or Forage [Kg/day (wet weigh)] QAW Water (/day) Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8
CH-ODCM-0001 Reference Use Page 98 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2) Element Total Body Skin H-3 --- --- C-14 --- --- Na-24 2.50E-08 2.90E-08 P-32 --- --- Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 --- --- Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-59 --- --- Ni-63 --- --- Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 --- --- Br-83 6.40E-11 9.30E-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 1.80E-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 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09
CH-ODCM-0001 Reference Use Page 99 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2) Element Total Body Skin 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 7.70E-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 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-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 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 --- --- Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09
CH-ODCM-0001 Reference Use Page 100 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2) Element Total Body Skin 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
CH-ODCM-0001 Reference Use Page 101 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 3.07E-06 2.12E-06 4.93E-07 --- --- 9.01E-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 1.81E-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 --- --- 3.01E-08 --- --- --- 2.90E-08 Br-84 --- --- 3.91E-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 2.41E-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 --- 7.21E-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 2.61E-07 --- 7.01E-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 4.81E-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 2.91E-06 --- 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 --- 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 --- 9.67E-07 6.31E-05 1.30E-05 Mo-99 --- 1.51E-08 2.87E-09 --- 3.64E-08 1.14E-05 3.10E-05 Tc-99M 1.29E-13 3.64E-13 4.63E-12 --- 5.52E-12 9.55E-08 5.20E-07
CH-ODCM-0001 Reference Use Page 102 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 5.22E-15 7.52E-15 7.38E-14 --- 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 --- 8.23E-08 --- 7.29E-07 6.31E-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-110M 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 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.11E-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-131M 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 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 --- 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 --- 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 --- 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 --- 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 --- 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-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 --- 1.07E-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 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 --- 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 --- 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 --- 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 --- 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 --- --- 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 --- --- 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 --- 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 --- 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 --- 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 --- 2.70E-07 3.51E-05 2.50E-05 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
CH-ODCM-0001 Reference Use Page 103 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 4.21E-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 6.71E-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 4.91E-05 Cm-243 1.10E+00 7.61E-01 4.61E-02 --- 2.15E-01 6.31E-02 4.84E-05 Cm-244 8.37E-01 5.88E-01 3.51E-02 --- 1.64E-01 6.06E-02 4.68E-05
CH-ODCM-0001 Reference Use Page 104 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 --- --- 1.91E-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 --- --- 1.41E-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 --- --- 5.41E-08 --- --- --- --- Br-85 --- --- 2.29E-09 --- --- --- --- Rb-86 --- 2.38E-05 1.05E-05 --- --- --- 2.21E-06 Rb-88 --- 6.82E-08 3.40E-08 --- --- --- 3.65E-15 Rb-89 --- 4.40E-08 2.91E-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 --- 2.21E-06 --- --- 3.67E-04 5.11E-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 1.21E-05 Mo-99 --- 2.11E-08 4.03E-09 --- 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 --- 7.20E-12 1.44E-07 7.66E-07
CH-ODCM-0001 Reference Use Page 105 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 2.01E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-06 9.99E-07 --- 3.13E-06 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 --- 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-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 --- 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81E-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-131M 1.23E-08 7.51E-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 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 --- 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 --- 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 --- 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 --- 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 --- 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 --- 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 --- 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 --- 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 --- 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 --- 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 --- 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 --- 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 --- 1.23E-14 4.11E-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 2.71E-07 --- 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 --- 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 --- 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 --- 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 --- 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 --- 6.28E-07 4.65E-05 2.28E-05
CH-ODCM-0001 Reference Use Page 106 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.50E-09 1.22E-09 4.29E-10 --- --- 5.92E-06 2.21E-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 8.05E-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 2.21E-09 --- 1.25E-08 8.11E-06 1.65E-05 Am-241 1.77E+00 1.20E+00 7.10E-02 --- 5.32E-01 1.05E-01 4.88E-05 Cm-242 3.17E-02 2.51E-02 1.41E-03 --- 6.40E-03 6.76E-02 5.21E-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 1.05E-01 4.96E-05
CH-ODCM-0001 Reference Use Page 107 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 --- 1.16E-05 2.57E-06 --- 2.71E-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 4.51E-06 --- --- 3.43E-04 1.91E-05 Co-58 --- 4.79E-07 8.55E-07 --- --- 2.99E-04 9.29E-06 Co-60 --- 3.55E-06 6.12E-06 --- --- 1.91E-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 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 --- --- 2.21E-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 4.41E-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 1.11E-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 --- --- 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 --- 1.61E-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 Tc-99M 4.81E-13 9.41E-13 1.56E-11 --- 1.37E-11 2.57E-07 1.30E-06
CH-ODCM-0001 Reference Use Page 108 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.19E-14 2.30E-14 2.91E-13 --- 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 --- 2.90E-07 --- 1.90E-06 1.79E-04 1.21E-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 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-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 2.31E-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 1.91E-09 2.71E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-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-131M 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 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 --- 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 --- 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 --- 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 --- 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 --- 2.58E-07 I-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 2.81E-05 9.78E-07 Cs-138 1.71E-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 --- 5.71E-09 4.71E-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 --- 2.31E-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 --- 8.11E-07 1.17E-04 2.63E-05 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
CH-ODCM-0001 Reference Use Page 109 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 4.41E-09 2.61E-09 1.17E-09 --- --- 1.11E-05 2.46E-05 Pu-238 2.55E+00 1.60E+00 1.21E-01 --- 4.47E-01 6.08E-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 8.31E-02 --- 3.06E-01 2.02E-01 4.82E-05
CH-ODCM-0001 Reference Use Page 110 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 --- 1.81E-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 1.41E-05 8.39E-06 2.38E-06 --- --- 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 --- --- 7.25E-04 1.77E-05 Co-58 --- 8.71E-07 1.30E-06 --- --- 5.55E-04 7.95E-06 Co-60 --- 5.73E-06 8.41E-06 --- --- 3.22E-03 2.28E-05 Ni-59 1.81E-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 1.71E-09 2.03E-10 8.79E-11 --- --- 5.80E-06 3.58E-05 Cu-64 --- 1.34E-09 5.53E-10 --- 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 --- 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-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 1.11E-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 2.91E-10 --- 9.90E-12 --- --- 1.99E-06 1.68E-06 Y-91 4.20E-04 --- 1.12E-05 --- --- 1.75E-03 5.02E-05 Y-92 1.17E-08 --- 3.29E-10 --- --- 1.75E-05 9.04E-05 Y-93 1.07E-07 --- 2.91E-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 2.31E-08 --- 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-11 --- 2.22E-11 5.79E-07 1.45E-06
CH-ODCM-0001 Reference Use Page 111 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 --- 7.61E-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 2.71E-05 3.97E-07 8.56E-06 7.18E-08 --- 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-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 6.81E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91E-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 8.51E-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 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 --- 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 --- 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 --- 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 --- 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 --- 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 --- 1.31E-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 9.61E-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 3.61E-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 1.11E-06 4.95E-07 La-140 3.61E-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 --- 1.41E-06 3.09E-04 2.66E-05 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 5.81E-06 3.57E-07 --- 2.25E-06 2.30E-04 2.23E-05
CH-ODCM-0001 Reference Use Page 112 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 1.31E-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 --- 3.91E-01 4.24E-01 5.02E-05 CM-244 2.07E+00 1.27E+00 8.89E-02 --- 3.21E-01 4.08E-01 4.86E-05
CH-ODCM-0001 Reference Use Page 113 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 3.91E-06 --- --- 2.85E-06 3.40E-05 Co-58 --- 7.45E-07 1.67E-06 --- --- --- 1.51E-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 9.01E-06 4.36E-06 --- --- --- 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 --- --- --- 1.74E-06 Cu-64 --- 8.33E-08 3.91E-08 --- 2.10E-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 --- --- 5.21E-08 --- --- --- 4.09E-13 Br-85 --- --- 2.14E-09 --- --- --- --- Rb-86 --- 2.11E-05 9.83E-06 --- --- --- 4.16E-06 Rb-88 --- 6.05E-08 3.21E-08 --- --- --- 8.36E-19 Rb-89 --- 4.01E-08 2.82E-08 --- --- --- 2.33E-21 Sr-89 3.08E-04 --- 8.84E-06 --- --- --- 4.94E-05 Sr-90 8.71E-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 1.41E-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 --- 4.31E-06 8.20E-07 --- 9.76E-06 --- 9.99E-06 Tc-99M 2.47E-10 6.98E-10 8.89E-09 --- 1.06E-08 3.42E-10 4.13E-07
CH-ODCM-0001 Reference Use Page 114 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 --- 5.31E-06 --- 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 --- 2.91E-07 --- 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-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 2.41E-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 --- 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 --- 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 --- 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 --- 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 --- 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 --- 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 --- 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 --- 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-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 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 --- 8.01E-08 7.91E-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 4.71E-08 3.56E-11 1.59E-09 --- 3.31E-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 --- 1.21E-07 --- 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 --- 2.13E-09 --- 4.03E-05 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
CH-ODCM-0001 Reference Use Page 115 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.03E-07 8.61E-08 3.01E-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 8.71E-05 1.91E-05 --- 8.11E-05 --- 6.66E-05 Pu-240 7.24E-04 8.70E-05 1.91E-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 5.41E-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 --- 7.81E-05 Cm-244 4.56E-04 4.27E-04 2.87E-05 --- 1.34E-04 --- 7.55E-05
CH-ODCM-0001 Reference Use Page 116 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 1.71E-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 --- 1.21E-05 Mn-56 --- 1.58E-07 2.81E-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 --- 2.81E-06 6.33E-06 --- --- --- 3.66E-05 Ni-59 1.32E-05 4.66E-06 2.24E-06 --- --- --- 7.31E-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 5.41E-08 --- 2.91E-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 --- --- --- 4.41E-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 --- 3.21E-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 2.01E-07 --- 5.39E-09 --- --- --- 8.24E-05 Y-92 1.21E-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 --- 1.91E-08 --- 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 --- 7.11E-10 --- 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 --- 4.42E-09 --- 1.95E-05 Mo-99 --- 6.03E-06 1.15E-06 --- 1.38E-05 --- 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 --- 1.38E-08 5.14E-10 6.08E-07
CH-ODCM-0001 Reference Use Page 117 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 1.51E-06 8.78E-09 --- 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-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 --- 2.41E-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 2.21E-06 2.08E-06 2.33E-06 2.12E-05 --- 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 --- 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 --- 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 --- 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 --- 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 --- 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-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 6.71E-08 5.01E-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 1.71E-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 1.71E-06 1.91E-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 1.31E-08 5.23E-09 6.52E-10 --- 3.04E-09 --- 4.31E-05 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
CH-ODCM-0001 Reference Use Page 118 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.46E-07 1.19E-07 4.17E-08 --- --- --- 3.22E-05 Pu-238 6.70E-04 8.58E-05 1.82E-05 --- 7.80E-05 --- 7.73E-05 Pu-239 7.65E-04 9.29E-05 2.01E-05 --- 8.57E-05 --- 7.06E-05 Pu-240 7.64E-04 9.27E-05 2.01E-05 --- 8.56E-05 --- 7.19E-05 Pu-241 1.75E-05 8.40E-07 3.69E-07 --- 1.71E-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 --- 4.31E-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 --- 1.91E-04 --- 8.28E-05 Cm-244 5.04E-04 4.77E-04 3.19E-05 --- 1.49E-04 --- 8.00E-05
CH-ODCM-0001 Reference Use Page 119 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 1.21E-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 5.51E-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 --- 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 --- 3.84E-08 --- 3.99E-06 Br-83 --- --- 1.71E-07 --- --- --- --- Br-84 --- --- 1.98E-07 --- --- --- --- Br-85 --- --- 9.12E-09 --- --- --- --- Rb-86 --- 6.70E-05 4.12E-05 --- --- --- 4.31E-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 --- --- --- 5.11E-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 --- --- --- 1.71E-04 Y-90 4.11E-08 --- 1.10E-09 --- --- --- 1.17E-04 Y-91M 3.82E-10 --- 1.39E-11 --- --- --- 7.48E-07 Y-91 6.02E-07 --- 1.61E-08 --- --- --- 8.02E-05 Y-92 3.60E-09 --- 1.03E-10 --- --- --- 1.04E-04 Y-93 1.14E-08 --- 3.13E-10 --- --- --- 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 --- 3.65E-08 --- 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 --- 1.45E-09 --- 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 --- 8.23E-09 --- 1.62E-05 Mo-99 --- 1.33E-05 3.29E-06 --- 2.84E-05 --- 1.10E-05 Tc-99M 9.23E-10 1.81E-09 3.00E-08 --- 2.63E-08 9.19E-10 1.03E-06
CH-ODCM-0001 Reference Use Page 120 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 1.07E-09 1.12E-09 1.42E-08 --- 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 --- 2.81E-07 --- 1.84E-06 --- 1.89E-05 Ru-105 6.45E-08 --- 2.34E-08 --- 5.67E-07 --- 4.21E-05 Ru-106 1.17E-05 --- 1.46E-06 --- 1.58E-05 --- 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91E-07 --- 6.78E-07 --- 4.33E-05 Sb-124 1.11E-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 1.71E-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 6.91E-06 8.24E-05 --- 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 --- 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 --- 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 --- 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 --- 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 --- 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 --- 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 --- 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 --- 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 --- 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 --- 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 --- 5.16E-07 I-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 2.01E-07 --- 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 --- 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 --- 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 --- 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 --- 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 --- --- --- 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 --- --- --- 3.31E-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 1.11E-07 --- 3.61E-07 --- 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 --- 6.39E-09 --- 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 --- 2.11E-11 --- 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 --- 1.24E-08 --- 3.58E-05
CH-ODCM-0001 Reference Use Page 121 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 3.31E-05 --- 1.22E-04 --- 6.85E-05 Pu-240 1.28E-03 1.43E-04 3.31E-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 7.01E-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
CH-ODCM-0001 Reference Use Page 122 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 --- --- --- 2.30E-05 Cr-51 --- --- 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 --- 1.99E-05 4.51E-06 --- 4.41E-06 --- 7.31E-06 Mn-56 --- 8.18E-07 1.41E-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 --- --- --- 7.16E-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 6.31E-05 2.91E-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 2.51E-03 --- 7.20E-05 --- --- --- 5.16E-05 Sr-90 2.83E-02 --- 5.74E-04 --- --- --- 2.31E-04 Sr-91 5.00E-05 --- 1.81E-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 --- 3.01E-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 --- 5.41E-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 Tc-99M 1.92E-09 3.96E-09 5.10E-08 --- 4.26E-08 2.07E-09 1.15E-06
CH-ODCM-0001 Reference Use Page 123 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 --- 5.41E-05 Ru-106 2.41E-05 --- 3.01E-06 --- 2.85E-05 --- 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81E-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 --- --- 1.11E-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 2.50E-04 --- 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 --- 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 --- 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 --- 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 --- 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 --- 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 --- 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 --- 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 --- 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 --- 1.84E-06 I-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 --- 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 --- 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 --- 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 --- 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 --- 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 --- 4.06E-08 1.05E-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 2.11E-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 --- 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 --- 1.13E-08 --- 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 --- 3.84E-11 --- 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 --- 2.19E-08 --- 3.60E-05
CH-ODCM-0001 Reference Use Page 124 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 --- 1.21E-04 --- 7.57E-05 Pu-239 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 6.91E-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 1.11E-08 9.93E-10 5.61E-10 --- 1.98E-09 --- 2.87E-05 Am-241 1.46E-03 1.27E-03 1.09E-04 --- 6.55E-04 --- 7.70E-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 9.70E-04 7.59E-05 --- 2.71E-04 --- 7.84E-05
CH-ODCM-0001 Reference Use Page 125 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol fg Fraction of ingested produce grown in garden 0.76 of interest. f Fraction of leafy vegetables grown in garden of 1.0 interest. P Effective surface density of soil (assumes a 240 kg/m2 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) Sf 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) tf 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.
CH-ODCM-0001 Reference Use Page 126 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 32 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/m2 (grass-cow-milk-man in wet weight) pathway) 2.0 kg/m2 (produce or leafy vegetable ingested by man) W Shore-width factor for river shoreline 0.2 w Rate constant for removal of activity on plant or 0.0021 hr-1 leaf structures by weathering (corresponds to a 14-day half-life)
Page 1 of 126 CH-ODCM-0001 II 11 Off-Site Dose Calculation Manual (ODCM) Revision 33 Safety Classification: Usage Level: Non-Safety Reference II II II II Change No.: EC 70444 Reason for Change: Change SRC to ISR and X/Q change for Historical Met Data Preparer: J. Hoffman Fort Calhoun Station
CH-ODCM-0001 Reference Use Page 2 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table of Contents PART I 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 ................................................................................................. 29 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) .................. 30 5.1 Monitoring Program ................................................................................................. 30 5.2 Land Use Survey ..................................................................................................... 45 5.3 Interlaboratory Comparison Program ...................................................................... 46 6.0 ADMINISTRATIVE CONTROLS.................................................................................... 47 6.1 Responsibilities ....................................................................................................... 47 6.2 Radioactive Effluent Reporting Requirements......................................................... 47 6.3 Change Mechanism ................................................................................................ 52 6.4 Meteorological Data ................................................................................................ 52 6.5 References .............................................................................................................. 53 7.0 BASIS ............................................................................................................................ 55 7.1 Instrumentation ....................................................................................................... 55 7.2 Radioactive Effluents............................................................................................... 55 7.3 Radiological Environmental Monitoring ................................................................... 60 7.4 Abnormal Release or Abnormal Discharge Reporting ............................................. 61
CH-ODCM-0001 Reference Use Page 3 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 List of Tables PART I Table 1.2 - Frequency Notation ............................................................................................... 8 Table 1.3 - Radiological Effluent Controls Program Technical Specification 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 4.3 - Sampler Deposition/Transportation Correction Factors ....................................... 26 Table 5.1 - Radiological Environmental Monitoring Program ................................................. 32 Table 5.2 - Radiological Environmental Sampling Locations And Media ............................... 35 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ................................................................................................... 43 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples ...................................................................................... 44 List of Figures PART I Figure 1 - Environmental Radiological Sampling Points ....................................................... 41 Figure 2 - 40CFR190 Sampling Points ................................................................................. 42
CH-ODCM-0001 Reference Use Page 4 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table of Contents PART II 1.0 EFFLUENT MONITOR SETPOINTS ............................................................................. 64 1.1 Liquid Effluents ........................................................................................................ 64 1.2 Airborne Effluents .................................................................................................... 67 2.0 EFFLUENT CONCENTRATIONS ................................................................................. 75 2.1 Liquid Effluent Concentrations ................................................................................ 75 2.2 Airborne Effluent Concentrations ............................................................................ 75 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS ................................................... 77 3.1 Liquid Effluent Dose Calculations ............................................................................ 77 3.2 Airborne Effluent Dose Calculations ........................................................................ 80 4.0 LOWER LIMIT OF DETECTION (LLD) ......................................................................... 93
CH-ODCM-0001 Reference Use Page 5 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 List of Tables PART II Table 1 - Deleted ................................................................................................................... 67 Table 2 - Deleted ................................................................................................................... 94 Table 3 - Bioaccumulation Factors ........................................................................................ 94 Table 4 - Highest Potential Exposure Pathways for Estimating Dose.................................... 95 Table 5 - Stable Element Transfer Data ................................................................................ 96 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data................................................................... 97 Table 7 - Animal Consumption Rates .................................................................................... 97 Table 8 - External Dose Factors for Standing on Contaminated Ground ............................... 98 Table 9 - Inhalation Dose Factors for Adult ......................................................................... 101 Table 10 - Inhalation Dose Factors for Teenager ................................................................ 104 Table 11 - Inhalation Dose Factors for Child ....................................................................... 107 Table 12 - Inhalation Dose Factors for Infant ...................................................................... 110 Table 13 - Ingestion Dose Factors for Adult ........................................................................ 113 Table 14 - Ingestion Dose Factors for Teenager ................................................................. 116 Table 15 - Ingestion Dose Factors for Child ........................................................................ 119 Table 16 - Ingestion Dose Factors for Infant ....................................................................... 122 Table 17 - Recommended Values for Other Parameters ..................................................... 125 List of Figures PART II Figure 1 - Exclusion and Site Boundary Map ........................................................................ 68 Figure 2 - Liquid Radioactive Discharge Pathways ............................................................... 69 Figure 3 - Liquid Radioactive Waste Disposal System .......................................................... 70 Figure 4 - Airborne Effluent Discharge Pathways .................................................................. 71 Figure 5 - Airborne Radioactive Waste Disposal System ...................................................... 72
CH-ODCM-0001 Reference Use Page 6 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 Contains 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.
CH-ODCM-0001 Reference Use Page 7 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 radioactive 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 Site Boundary - The Site Boundary is the line beyond which the land is neither owned, or leased, nor controlled by the licensee. 2.10 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. 2.11 Special Liquid - Non-routine release pathway in which normally non-radioactive liquid streams (such as Raw Water) found to contain radioactive material, are non-routine, and will be treated on a case specific basis if and when this occurs. 2.12 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. 2.13 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. 2.14 Water Effluent Concentration (WEC) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.
CH-ODCM-0001 Reference Use Page 8 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
CH-ODCM-0001 Reference Use Page 9 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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, 6.2.1D E.4.1 6.2.1 E.4.2 6.2.2
CH-ODCM-0001 Reference Use Page 10 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
CH-ODCM-0001 Reference Use Page 11 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
CH-ODCM-0001 Reference Use Page 12 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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
CH-ODCM-0001 Reference Use Page 13 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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-062, 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.
CH-ODCM-0001 Reference Use Page 14 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Channels Action Functional
- 1. Forced Draft releases 1.1 Particulate-Auxiliary Bldg. Exhaust Stack (RM-052, 1 1,4 RM-062) 1.2 Particulate-Laboratory and Radwaste Processing 1 2 Building Stack (RM-043) 1.3 Particulate air sampler-Portable filtered ventilation 1 5 systems discharge
- 2. Unventilated building opening 2.1 Particulate air sampler-open doorway/ open rollup 1 6 door
- 3. Open-air demolition 3.1 Particulate air samplers (4 air samplers at each 4 7 open-air location)
- 4. Flow Rate Measurement Devices 4.1 Auxiliary Building Exhaust Stack 1 3 4.2 Laboratory and Radwaste Processing Building Stack 1 3 4.3 Hand-held anemometer 1 3
CH-ODCM-0001 Reference Use Page 15 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 3.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation Table Notation ACTION 1 If the Auxiliary Building Exhaust Stack Particulate Sampler is non-functional, ventilation of the Auxiliary Building may continue through the Auxiliary Building Exhaust Stack provided sample collection in accordance with Table 4.2 using auxiliary sample collection equipment is initiated within 2 hours of the declaration of non-functionality by the ISFSI Shift Supervisor (ISS). ACTION 2 If the Particulate Sampler is non-functional, ventilation of the LRWPB may continue via the LRWPB Stack provided sample collection using auxiliary sample collection equipment is initiated within 2 hours of the declaration of non-functionality, by the ISFSI Shift Supervisor (ISS), in accordance with Table 4.2. ACTION 3 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 4 During the ventilation of airborne effluents from the Auxiliary Building Exhaust Stack at least one Auxiliary Building Exhaust fan shall be in operation. ACTION 5 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 6 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 7 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.
CH-ODCM-0001 Reference Use Page 16 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Calibration Function Check Check Test
- 1. Flowrate Monitors 1.1 RM-043 Sampler D R Q ----
1.2 RM-062 Sampler D R Q ---- 1.3 RM-052 Sampler D R Q ---- 1.4 Auxiliary Bldg Exhaust Stack D R Q ---- 1.5 Laboratory and Radwaste Process Bldg Exhaust Stack D R Q ---- Operations Check Air Flow Calibration
- 2. Environmental Monitors 2.1 RM-023 - Sample Station #40 M A 2.2 RM-024 - Sample Station #41 M A 2.3 RM-025 - Sample Station #28 ---- ----
2.4 RM-026 - Sample Station #36 ---- ---- 2.5 RM-027 - Sample Station #37 M A 2.6 RM-028 - Sample Station #38 ---- ---- 2.7 RM-029 - Sample Station #39 ---- ---- 2.8 RM-035 - Sample Station #1 ---- ---- 2.9 RM-036 - Sample Station #2 M A 2.10 RM-037 - Sample Station #3 ---- ---- 2.11 RM-038 - Sample Station #4 M A 2.12 RM-039 - Sample Station #5 ---- ---- 2.13 RM-040 - Sample Station #32 M A
- 3. Decommissioning portable air sampler flowmeters 3.1 All sample stations W1 A 1- Operation check performed only when the unit is started to support active decommissioning.
CH-ODCM-0001 Reference Use Page 17 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
CH-ODCM-0001 Reference Use Page 18 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
CH-ODCM-0001 Reference Use Page 19 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis A. Monitor, Hotel Waste Tanks & Special Liquid, Releases Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Each Batch Principal Gamma Emitters B 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.
CH-ODCM-0001 Reference Use Page 20 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 II of the Off-Site Dose Calculation Manual at least once per quarter.
CH-ODCM-0001 Reference Use Page 21 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
- 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 the monitor tanks for release.
CH-ODCM-0001 Reference Use Page 22 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 4.1.3B.2 (continued)
- b. Waste filters (WD-17A 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.
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.
CH-ODCM-0001 Reference Use Page 23 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
CH-ODCM-0001 Reference Use Page 24 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis A. Auxiliary Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly Tritium (H-3) 1.0E-06 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Samples) Sr-89, Sr-90 1.0E-11 B. Laboratory and Radwaste Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-89, Sr-90 1.0E-11 C. Forced Draft Exhaust discharge Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-90 1.0E-11 D. Unventilated building doorways Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-90 1.0E-11
CH-ODCM-0001 Reference Use Page 25 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 E. Open-Air Demolition locations Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 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. D. Particulate samples shall be corrected for sampler deposition/transportation efficiency by using the approved software programs or by multiplying the activity obtained by the associated sampler multiplication factor (See Table 4.3).
CH-ODCM-0001 Reference Use Page 26 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 4.3 - Sampler Deposition/Transportation Correction Factors Particulate Sampler Sample DF ACTMULT RM-062 AB 0.411 2.433 RM-052 AB 0.638 1.567 RM-043 LRWPB 0.809 1.236 Forced Draft, Portable Air Unventilated Sampler Building, Open-Air 1.00 1.00 ACRONYM DEFINITIONS: AB - Auxiliary Building Exhaust Stack LRWPB - Laboratory and Rad Waste Processing Building DF - Deposition Factor ACTMULT - Activity multiplication factor to correct for sample loss.
CH-ODCM-0001 Reference Use Page 27 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
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
CH-ODCM-0001 Reference Use Page 28 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33
- 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.
- 2. FUNCTIONAL is defined as follows:
- a. Ventilation Exhaust Systems
- 1) The radioactive effluents from the controlled access area of the auxiliary building are filtered by the HEPA filters in the auxiliary building ventilation system. 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.
CH-ODCM-0001 Reference Use Page 29 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 25 mrem to the total body or any organ (except the thyroid, which shall be limited to 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.
CH-ODCM-0001 Reference Use Page 30 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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).
CH-ODCM-0001 Reference Use Page 31 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 surveillance 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.
CH-ODCM-0001 Reference Use Page 32 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 1. Direct Radiation 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 sector 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 Quarterly 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 unrestricted area composite boundary 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 composite for C. Missouri River upstream of H-3 Analysis Facility intake (background)F.
- 4. Milk D 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.
CH-ODCM-0001 Reference Use Page 33 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B 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 D/Q offsite location. C. One sample outside of 5 miles (background) F.
CH-ODCM-0001 Reference Use Page 34 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 Ci/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 (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") E. Samples should be collected from garden plots of 500 ft2 or more. (Reference Reg. Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants," Dec. 1975). 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".
CH-ODCM-0001 Reference Use Page 35 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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°/S 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
CH-ODCM-0001 Reference Use Page 36 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 14D 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,D,F Mohr Dairy 9.86 186°/S J X X X A 21 Fish Sampling Area, 0.08 22 Missouri River (R.M. 645.0) 6°/N A X Fish Sampling Area, 17.9 23D Missouri River (R.M. 666.0) 358°/N A X 24A 25A 26A 27A
CH-ODCM-0001 Reference Use Page 37 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 28A 29A 30A 31A 32D Valley Substation #902 19.6 221°/SW L X X A 33 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 A 38 39A 40A 41B,C Dowler Acreage 0.73 175°/S 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
CH-ODCM-0001 Reference Use Page 38 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 D 58 Sector A-2 4.54 350°/NORTH A X D 59 Sector B-2 2.95 26°/NNE B X 60D Sector C-2 3.32 50°/NE C X 61D Sector D-2 3.11 75°/ENE D X D 62 Sector E-2 2.51 90°/EAST E X D 63 Sector F-2 2.91 110°/ESE F X D 64 Sector G-2 3.00 140°/SE G X D 65 Sector H-2 2.58 154°/SSE H X 66D Sector J-2 3.53 181°/SOUTH J X 67D Sector K-2 2.52 205°/SSW K X D 68 Sector L-2 2.77 214°/SW L X D 69 Sector M-2 2.86 243°/WSW M X
CH-ODCM-0001 Reference Use Page 39 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 70D Sector N-2 2.54 263°/WEST N X 71D Sector P-2 2.99 299°/WNW P X D 72 Sector Q-2 3.37 311°/NW Q X D 73 Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X B,C 75 Lomp Acreage 0.65 163°/SSE H X X X X 76A 77G River N-1 0.17 328°/NNW R X G 78 River S-1 0.14 85°/EAST E X G 79 Lagoon S-1 0.24 131°/SE G X G 80 Parking S-1 0.27 158°/SSE H X G 81 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 G 84 Switchyard NE-1 0.18 256°/WSW M X G 85 Switchyard W-1 0.29 233°/WEST L X G 86 Switchyard N-1 0.24 262°/WEST N X G 87 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°/SSW K X
CH-ODCM-0001 Reference Use Page 40 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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)
CH-ODCM-0001 Reference Use Page 41 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Figure 1 - Environmental Radiological Sampling Points N Q ORAWlNC FI LE N). P- 00075 (*) Locations currently discontinued are not illustrated.
CH-ODCM-0001 Reference Use Page 42 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Figure 2- 40CFR190 Sampling Points N lQJ(A NEBR.4..SKA UNRf.Sl'lCTM AR:EA BOUNDARY
~ 0~
AlltOl T #1 TO El ]R ; j l
'\
(l) _,QUID EFJl'LUEN't tA$0.HA~GE AIRBOifflE EFFL NT8 DISCHABG
- SA PLING POI NT SC!AlJE IN :MJLES SITE BOUNDARY MAP DRflWINC. FILE t..'O.
P-00423
CH-ODCM-0001 Reference Use Page 43 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) A, B, 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/m3 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.
CH-ODCM-0001 Reference Use Page 44 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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/m3 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: 1 2 3
.... 1.0 1 2 3 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.
CH-ODCM-0001 Reference Use Page 45 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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).
CH-ODCM-0001 Reference Use Page 46 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 Interlaboratory Comparison Program 5.3.1 Limiting Condition for Operation A. Analyses shall be performed on radioactive materials as part of an Interlaboratory 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).
CH-ODCM-0001 Reference Use Page 47 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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; Reg. Guide 4.8, Table 1; 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.
CH-ODCM-0001 Reference Use Page 48 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 following the format of Regulatory Guide 4.8, Table 1. 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 Interlaboratory Comparison Program. D. The results of land use survey required by Section 5.2. E. A map of the current environmental monitoring sample locations.
CH-ODCM-0001 Reference Use Page 49 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
CH-ODCM-0001 Reference Use Page 50 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 6.2.6 ISFSI 10 CFR Part 72.104 Reporting Requirements The regulatory requirements of 10CFR20, 10CFR72 and 40CFR190 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 40CFR190. 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)
CH-ODCM-0001 Reference Use Page 51 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 Where D,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
CH-ODCM-0001 Reference Use Page 52 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 /Q 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 /Q 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.
CH-ODCM-0001 Reference Use Page 53 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 Regulatory Guide 4.8, Environmental Technical Specification for Nuclear Power Plants. 6.5.5 NRC Branch Technical Position, March 1978 6.5.6 NUREG-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants. 6.5.7 NUREG-1301 - Offsite Dose Calculation Manual Guidance. 6.5.8 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. 6.5.9 Code of Federal Regulations, Title 10, Part 20 6.5.10 Code of Federal Regulations, Title 10, Part 50 6.5.11 Code of Federal Regulations, Title 10, Part 72 6.5.12 Code of Federal Regulations, Title 40, Part 190 6.5.13 Fort Calhoun Revised Environmental Report (Unit No. 1)-1972 6.5.14 NO-FC-10, Quality Assurance Topical Report 6.5.15 Defueled Safety Analysis Report 6.5.16 AR 12357, Implement Recommendations of Memo FC-0133-92, Part I, Table 3.2.1 Action 4, of the Off-Site Calculation Manual 6.5.17 AR 39127, NEI Industry Initiative on Groundwater Protection
CH-ODCM-0001 Reference Use Page 54 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 6.5.18 Regulatory Guide 4.1, Rev. 2 - Radiological Environmental Monitoring for Nuclear Power Plants 6.5.19 FC-19-001, ODCM rev 29 Change Support Document 6.5.20 FC-18-005, Habits of the Real Individual in Vicinity of Fort Calhoun Station, X/Q, Direct Radiation Dose Calculation
CH-ODCM-0001 Reference Use Page 55 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 II 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.
CH-ODCM-0001 Reference Use Page 56 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 B. Dose This specification is provided to implement the requirements of Sections II.A, III.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 III.A that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Part 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 II.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.
CH-ODCM-0001 Reference Use Page 57 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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. 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 II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.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 III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The 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.
CH-ODCM-0001 Reference Use Page 58 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 II.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 II.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded.
CH-ODCM-0001 Reference Use Page 59 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
CH-ODCM-0001 Reference Use Page 60 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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/m2. 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.
CH-ODCM-0001 Reference Use Page 61 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 7.3.3 Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. 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.
CH-ODCM-0001 Reference Use Page 62 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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
CH-ODCM-0001 Reference Use Page 63 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 PART II CALCULATIONS
CH-ODCM-0001 Reference Use Page 64 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents 1.1.1 There is one liquid discharge pathway to the Missouri River. The pathway originates with the radioactive liquid waste processing system (monitor or hotel tanks). This pathway empties into the circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathway and associated radiation monitor. Figure 3 depicts the methods of liquid effluent treatment. 1.1.2 The flowrate for dilution water varies with the number raw water 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.
CH-ODCM-0001 Reference Use Page 65 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 1.1.7 Liquid Effluent Radiation Monitor A. Overboard Discharge Header Monitor (RM-055)
- 1. This process radiation monitor provides control of the waste monitor tank effluent by monitoring the overboard header prior to its discharge into the circulating water discharge tunnel. The concentration of activity at discharge is controlled below ten times the 10 CFR Part 20 limit of 1.0E-06 Ci/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 monitor tank discharge.
- 3. The maximum allowable concentration in the overboard discharge header is:
1.0 05 Where: 1.0E-05 Ci/ml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2). F = Total dilution flow in the discharge tunnel (gpm). (Normal flow is based on 2 raw water pumps at 7,200 gpm total.) f = Maximum monitor tank discharge flow rate (gpm). (Normal monitor tank maximum flow is 15 gpm.) CMAX = Maximum allowable activity in discharge header (Ci/ml).
CH-ODCM-0001 Reference Use Page 66 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 1.1.7A (continued) The High Alarm Setpoint (CPM): 0.75 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. Sf = Detector sensitivity factor (CPM/Ci/ml). (Sensitivity based on Cs-137). K3 = Allocation factor for Waste Liquid Releases (1) CMAX = Maximum allowable concentration in discharge header (Ci/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.
CH-ODCM-0001 Reference Use Page 67 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 installed or portable filtered ventilation units with a fan with a rated cfm as the release rate. Monitoring of forced draft ventilation includes utilizing presently installed system monitors such as RM-062, RM-052, and RM-043. 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
CH-ODCM-0001 Reference Use Page 68 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Figure 1 - Exclusion and Site Boundary Map
,N
' \ I\ .
I I' CD UQUID Ent :ENT ' OHAROE ])Ji,; AIR' ORNE hn'L ' B DlSOHARG
- 1'0 OWW'A I) 1 r
SCME. MR.ES SlfE BO _:: DARY MAP P- 00414
CH-ODCM-0001 Reference Use Page 69 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Figure 2 - Liquid Radioactive Discharge Pathways HOTEL RAW WATER TANKS MONITOR TANKS RM-O55 OUTFALL CIRCULATING WATER WARM WATER RECIRCULATION LIQUID RADIOACTIVE DISCHARGE PATHWAYS DRAWING FILE NO. P-00410
CH-ODCM-0001 Reference Use Page 70 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Figure 3 - Liquid Radioactive Waste Disposal System REACTOR COOLANT AUXILIARY SYSTEMS WASTE PROCESS WASTE eves Bltoedoff HOTEL WASTE Floor Dracns Eq u1p men t Di---m n s LaundrLJ Wa5-te Sump FlofJ5 RC Loop Drains Shov1r:,r Drains Spent RQg r:, n r:, f- ant Tanks (:::==I===:I) 55]0 Gol. (I I)
\1 WasstQ FiltQf-SS 50 Microns Dem J ne r al iz er V E'S S E ' ] s 30 Cuo FL
~
00000 Charcoal F cl ter 59 Cu. FL ( opcional) f1onL tor Tank5 G770 Calo Ovtorboard He o dcor ( f o River) LIQUID RADIOACTIVE WASTE DISPOSAL SYSTEM
CH-ODCM-0001 Reference Use Page 71 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Figure 4 - Airborne Effluent Discharge Pathways RM - 043 LRW B mple r LRWPB L bor or y R - 062,052 Parli c u lale ampl r
CH-ODCM-0001 Reference Use Page 72 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Figure 4 - Airborne Effluent Discharge Pathways (continued) 8d FORCED DRAFT AIR SAMPLER WITH EXHAUST TRUNK DISCHARGE FORCED DRAFT AIR SAMPLER WITH OUTLET PLENUM r--------------------------- 1
, ~ ****r~*~******r************
I ,'
CH-ODCM-0001 Reference Use Page 73 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 UNVENTILATED BUILDING RELEASE AIR SAMPLERS Figure 4 - Airborne Effluent Discharge Pathways (continued) w OPEN-AIR DEMOLITION AIR SAMPLERS
CH-ODCM-0001 Reference Use Page 74 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Figure 5 - Airborne Radioactive Waste Disposal System Au xiliary Bu
- din Ve n l il lion SL ck 22,500 Cf' {
B PA Filler Ground
CH-ODCM-0001 Reference Use Page 75 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 2.0 EFFLUENT CONCENTRATIONS 2.1 Liquid Effluent Concentrations 2.1.1 The concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) will be limited to the concentrations as specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. For batch releases (Monitor and Hotel Waste Tanks) 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: 1 Radionuclide concentration at site discharge: Where: Ai = concentration at site discharge for radionuclide (I), in Ci/ml. ai = concentration of radionuclide (I) in the undiluted effluent, in Ci/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 i In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, IAppendix B, will also be applicable. I i 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:
CH-ODCM-0001 Reference Use Page 76 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 1 Where: Ai = Concentration of radionuclide (I) at the unrestricted area boundary K0 = Constant of unit conversion. (1.0E-6 m3/cc) ECLi = Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, Column 1 value for radionuclide(I)) Qi = The release rate of radionuclide (I) in airborne effluents from all vent releases (in Ci/sec.) (/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from Part II, 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.
CH-ODCM-0001 Reference Use Page 77 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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.
CH-ODCM-0001 Reference Use Page 78 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 3.1.3 Doses from Liquid Effluent Pathways A. Potable Water 1100 exp Where: Rapj = is the total annual dose to organ(j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr. Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in
/yr. (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 ft3/ sec. Qi = 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 (j) which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = 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 water, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 79 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 3.1.3 (continued) B. Aquatic Foods 1100 exp Where: Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr. Uap = is a usage factor that specifies the 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 ft3/sec. Qi = is the annual release rate of radionuclide (I), in Ci/yr. Bip = is the equilibrium bioaccumulation factor for radionuclide (I) in pathway (p) expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in (pCi/kg)/(pCi/liter). (Table 3) Daipj = is the dose factor specific to a given age group (a), radionuclide (I), pathway (p), and organ (j), which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = 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
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 80 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 3.1.3 (continued) C. Shoreline Deposits 110,000 exp 1 exp Where: Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr. Uap = is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p), in hr/yr. (Table 6) 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 ft3/sec. Qi = 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/m2). (Table 8) i = 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, in hours. (Table 17) tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours. (Table 17) 110,000 = Constant [(100
- pCi
- yr
- ft3)/(Ci
- sec
- L)]
3.2 Airborne Effluent Dose Calculations
CH-ODCM-0001 Reference Use Page 81 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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:
CH-ODCM-0001 Reference Use Page 82 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 NOTE I i In all cases, for releases of tritium, use the dispersion Iparameter for inhalation (/Q). I i 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 , with respect to the release point, may be determined by: 1.010 ,
, 1 exp Where:
CGI = is the ground plane concentration of the radionuclide (I) at distance r, in the sector at angle , from the release point, in pCi/m2. Qi = is the annual release rate of radionuclide (I) to the atmosphere, in Ci/yr. tb = 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) i(r,) = is the annual average relative deposition of radionuclide (I) at distance r, in the sector at angle , considering depletion of the plume by deposition during transport, in m-2. Table 4 i = is the radiological decay constant for radionuclide (I), in yr-1. 1.0x1012 = is the number of pCi/Ci
CH-ODCM-0001 Reference Use Page 83 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 The annual organ dose is then calculated using the following equation:
, 8760 ,
Where: CGj(r,) = is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle , in pCi/m2. DFGij = is the open field ground plane dose conversion factor for organ (j) from radionuclide (i), in mrem-m2/pCi-hr. (Table 8) DGj(r,) = is the annual dose to the organ (j) at distance r, in the sector at angle , in mrem/yr. Sf = 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 , with respect to the release point, may be determined as:
, 3.17 10 ,
Where: Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr. i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
[/Q]D (r,) = is the annual average atmosphere dispersion factor, in sec/m3 (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.
CH-ODCM-0001 Reference Use Page 84 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 The annual dose associated with inhalation of all radionuclides to organ (j) of an individual in age group (a), is then: Where: DAja(r,) = is the annual dose to organ (j) of an individual in the age group (a) at distance r, in the sector at angle , due to inhalation, in mrem/yr. Ra = is the annual air intake for individuals in the age group (a), in m3/yr. (Table 6) i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
DFAija = is the inhalation dose factor for radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 9-12)
CH-ODCM-0001 Reference Use Page 85 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 1 exp 1 exp
, , exp Where:
CVi(r,) = is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle , in pCi/kg. di (r,) = is the deposition rate of radionuclide (i) at distance r, in the sector at angle , in pCi/m2 hr. r = is the fraction of deposited activity retained on crops, dimensionless. (Table 17) Ei = is the effective removal rate constant for radionuclide (i) from crops, in hr-1. Ei = i + w w = 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) Biv = is the concentration factor for uptake of radionuclide (i) from soil by edible parts of crops, in pCi/ kg (wet weight) per pCi/kg dry soil. (Table 5) i = is the radiological decay constant of radionuclide (I), in hr-1 tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours (mid-point of plant life). (Table 17) P = is the effective "surface density" for soil, in kg (dry soil)/m2. (Table 17) th = is the holdup time that represents the time interval between harvest and consumption of the food, in hours. (Table 17) Different values for the parameters te, 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.
CH-ODCM-0001 Reference Use Page 86 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa. C-6):
, 1.1 10 ,
Where: di(r,) = is the deposition rate of radionuclide (i). i(r,) = is the relative deposition of radionuclide (i), considering depletion and decay, in m-2 (see Reg Guide 1.111). (Table 4) 1.1x108 = is the number of pCi/Ci (1012) divided by the number of hours per year (8760). Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
CH-ODCM-0001 Reference Use Page 87 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 B. For radioiodines, the model considers only the elemental fraction of the effluent:
, 3.3 10 ,
Where: di (r, ) = 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). i (r, ) = The relative deposition of radioiodine (i), considering depletion and decay, in m-2. (Table 4) Qi = 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)
, , 1 , 1 ,
Where: CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. CPi(r,) = is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2.3A with th=0), in pCi/kg. CSi(r,) = is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3A with th=90 days), in pCi/kg. fp = 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)
CH-ODCM-0001 Reference Use Page 88 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 3.2.3 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk
, , exp Where:
CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter. CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. Fm = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each liter of milk, in days/liter. (Table 5) QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) tf = 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) i = is the radiological decay constant of radionuclide (i), in days-1.
CH-ODCM-0001 Reference Use Page 89 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium
, , exp Where:
CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter. CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) Ff = 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.
, 0.75 0.5 ,
, 3.17 10 1.2 10 Where:
CVT(r, ) = is the concentration of tritium in vegetation grown at distance r, in the sector at angle , in pCi/kg. H = is the absolute humidity of the atmosphere at distance r, in the sector at angle , in g/m3. H=8 gm/kg. QT = is the annual release rate of tritium, in Ci/yr. [/Q](r,) = is the atmospheric dispersion factor, in sec/m3. (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.
CH-ODCM-0001 Reference Use Page 90 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 3.2.6 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ (j) of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by: Where: DDja(r,) = is the annual dose to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem/yr. DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. Tables 13-16. UVa = are the ingestion rates of produce (non-leafy vegetables, fruits, and grains) , respectively for individuals in age group (a). (Table 6) UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6) UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6) ULa = are the ingestion rates of leafy vegetables for individuals in age group (a), in kg/yr. (Table 6) CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg. CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter. CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter. CLI (r,) = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg. fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 91 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce) Vegetation for Radionuclide (i) to Each Organ (j) and Age Group (a) Where: DDja(r,) = is the annual dose from the ingestion of radionuclide (i) to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in vegetation, in mrem/yr. DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pci. Tables 13-16 ULa,UVa = 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) CLi = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg. CVi = 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) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 92 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 C. Calculation Determining the Ingested Dose from Cow Milk for Radionuclide (i), Organ (j), and Age Group (a) Where: DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in cow milk, in mrem/yr. DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16) UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6) CMi = 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 (j) and Age Group (a) Where: DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in meat, in mrem/yr. DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16) UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6) CFi = is the radionuclide (i) concentration in meat, in pCi/kg.
CH-ODCM-0001 Reference Use Page 93 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 exp 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
= the radioactive decay constant for the particular radionuclide t = the elapsed time between the midpoint of sample collection and time of counting Appropriate values of E, V, Y, and t 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.
CH-ODCM-0001 Reference Use Page 94 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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
CH-ODCM-0001 Reference Use Page 95 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 4 - Highest Potential Exposure Pathways for Estimating Dose Distance
/Q A D/Q A Exposure from Location B Direction B {/Q (r,)} { (r,)}
Pathway Containment (sec/m3) (m-2) (miles) B 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 SSE 0.65 N/A 6.00E-08 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.
CH-ODCM-0001 Reference Use Page 96 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 5 - Stable Element Transfer Data Biv Fm (cow) Fm (goat) Ff Element Veg./Soil Milk (d/I) Milk (d/I) Meat (d/kg) H 4.8E+00 1.0E-02 1.7E-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 6.7E-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 1.7E-02 8.0E-04 1.4E-02 6.0E-04 Y 2.6E-03 1.0E-05 ------ 4.6E-03 Zr 1.7E-04 5.0E-06 ------ 3.4E-02 Nb 9.4E-03 2.5E-03 ------ 2.8E-01 Mo 1.2E-01 7.5E-03 ------ 8.0E-03 Tc 2.5E-01 2.5E-02 ------ 4.0E-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 ------ 1.7E-02 Sb 1.1E-02 1.5E-03 ------ 4.0E-03 Te 1.3E+00 1.0E-03 ------ 7.7E-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 ------ 4.7E-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
CH-ODCM-0001 Reference Use Page 97 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 (/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 (/yr) 330 510 510 730 Shoreline recreation (hr/yr) --- 14 67 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table 7 - Animal Consumption Rates Animal QF Feed or Forage [Kg/day (wet weigh)] QAW Water (/day) Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8
CH-ODCM-0001 Reference Use Page 98 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2) Element Total Body Skin H-3 --- --- C-14 --- --- Na-24 2.50E-08 2.90E-08 P-32 --- --- Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 --- --- Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-59 --- --- Ni-63 --- --- Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 --- --- Br-83 6.40E-11 9.30E-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 1.80E-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 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09
CH-ODCM-0001 Reference Use Page 99 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2) Element Total Body Skin 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 7.70E-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 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-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 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 --- --- Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09
CH-ODCM-0001 Reference Use Page 100 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2) Element Total Body Skin 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
CH-ODCM-0001 Reference Use Page 101 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 3.07E-06 2.12E-06 4.93E-07 --- --- 9.01E-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 1.81E-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 --- --- 3.01E-08 --- --- --- 2.90E-08 Br-84 --- --- 3.91E-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 2.41E-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 --- 7.21E-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 2.61E-07 --- 7.01E-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 4.81E-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 2.91E-06 --- 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 --- 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 --- 9.67E-07 6.31E-05 1.30E-05 Mo-99 --- 1.51E-08 2.87E-09 --- 3.64E-08 1.14E-05 3.10E-05 Tc-99M 1.29E-13 3.64E-13 4.63E-12 --- 5.52E-12 9.55E-08 5.20E-07
CH-ODCM-0001 Reference Use Page 102 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 5.22E-15 7.52E-15 7.38E-14 --- 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 --- 8.23E-08 --- 7.29E-07 6.31E-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-110M 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 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.11E-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-131M 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 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 --- 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 --- 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 --- 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 --- 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 --- 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-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 --- 1.07E-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 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 --- 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 --- 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 --- 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 --- 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 --- --- 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 --- --- 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 --- 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 --- 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 --- 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 --- 2.70E-07 3.51E-05 2.50E-05 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
CH-ODCM-0001 Reference Use Page 103 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 4.21E-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 6.71E-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 4.91E-05 Cm-243 1.10E+00 7.61E-01 4.61E-02 --- 2.15E-01 6.31E-02 4.84E-05 Cm-244 8.37E-01 5.88E-01 3.51E-02 --- 1.64E-01 6.06E-02 4.68E-05
CH-ODCM-0001 Reference Use Page 104 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 --- --- 1.91E-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 --- --- 1.41E-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 --- --- 5.41E-08 --- --- --- --- Br-85 --- --- 2.29E-09 --- --- --- --- Rb-86 --- 2.38E-05 1.05E-05 --- --- --- 2.21E-06 Rb-88 --- 6.82E-08 3.40E-08 --- --- --- 3.65E-15 Rb-89 --- 4.40E-08 2.91E-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 --- 2.21E-06 --- --- 3.67E-04 5.11E-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 1.21E-05 Mo-99 --- 2.11E-08 4.03E-09 --- 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 --- 7.20E-12 1.44E-07 7.66E-07
CH-ODCM-0001 Reference Use Page 105 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 2.01E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-06 9.99E-07 --- 3.13E-06 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 --- 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-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 --- 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81E-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-131M 1.23E-08 7.51E-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 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 --- 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 --- 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 --- 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 --- 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 --- 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 --- 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 --- 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 --- 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 --- 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 --- 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 --- 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 --- 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 --- 1.23E-14 4.11E-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 2.71E-07 --- 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 --- 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 --- 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 --- 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 --- 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 --- 6.28E-07 4.65E-05 2.28E-05
CH-ODCM-0001 Reference Use Page 106 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.50E-09 1.22E-09 4.29E-10 --- --- 5.92E-06 2.21E-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 8.05E-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 2.21E-09 --- 1.25E-08 8.11E-06 1.65E-05 Am-241 1.77E+00 1.20E+00 7.10E-02 --- 5.32E-01 1.05E-01 4.88E-05 Cm-242 3.17E-02 2.51E-02 1.41E-03 --- 6.40E-03 6.76E-02 5.21E-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 1.05E-01 4.96E-05
CH-ODCM-0001 Reference Use Page 107 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 --- 1.16E-05 2.57E-06 --- 2.71E-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 4.51E-06 --- --- 3.43E-04 1.91E-05 Co-58 --- 4.79E-07 8.55E-07 --- --- 2.99E-04 9.29E-06 Co-60 --- 3.55E-06 6.12E-06 --- --- 1.91E-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 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 --- --- 2.21E-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 4.41E-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 1.11E-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 --- --- 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 --- 1.61E-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 Tc-99M 4.81E-13 9.41E-13 1.56E-11 --- 1.37E-11 2.57E-07 1.30E-06
CH-ODCM-0001 Reference Use Page 108 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.19E-14 2.30E-14 2.91E-13 --- 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 --- 2.90E-07 --- 1.90E-06 1.79E-04 1.21E-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 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-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 2.31E-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 1.91E-09 2.71E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-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-131M 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 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 --- 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 --- 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 --- 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 --- 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 --- 2.58E-07 I-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 2.81E-05 9.78E-07 Cs-138 1.71E-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 --- 5.71E-09 4.71E-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 --- 2.31E-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 --- 8.11E-07 1.17E-04 2.63E-05 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
CH-ODCM-0001 Reference Use Page 109 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 4.41E-09 2.61E-09 1.17E-09 --- --- 1.11E-05 2.46E-05 Pu-238 2.55E+00 1.60E+00 1.21E-01 --- 4.47E-01 6.08E-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 8.31E-02 --- 3.06E-01 2.02E-01 4.82E-05
CH-ODCM-0001 Reference Use Page 110 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 --- 1.81E-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 1.41E-05 8.39E-06 2.38E-06 --- --- 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 --- --- 7.25E-04 1.77E-05 Co-58 --- 8.71E-07 1.30E-06 --- --- 5.55E-04 7.95E-06 Co-60 --- 5.73E-06 8.41E-06 --- --- 3.22E-03 2.28E-05 Ni-59 1.81E-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 1.71E-09 2.03E-10 8.79E-11 --- --- 5.80E-06 3.58E-05 Cu-64 --- 1.34E-09 5.53E-10 --- 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 --- 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-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 1.11E-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 2.91E-10 --- 9.90E-12 --- --- 1.99E-06 1.68E-06 Y-91 4.20E-04 --- 1.12E-05 --- --- 1.75E-03 5.02E-05 Y-92 1.17E-08 --- 3.29E-10 --- --- 1.75E-05 9.04E-05 Y-93 1.07E-07 --- 2.91E-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 2.31E-08 --- 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-11 --- 2.22E-11 5.79E-07 1.45E-06
CH-ODCM-0001 Reference Use Page 111 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 --- 7.61E-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 2.71E-05 3.97E-07 8.56E-06 7.18E-08 --- 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-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 6.81E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91E-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 8.51E-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 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 --- 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 --- 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 --- 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 --- 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 --- 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 --- 1.31E-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 9.61E-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 3.61E-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 1.11E-06 4.95E-07 La-140 3.61E-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 --- 1.41E-06 3.09E-04 2.66E-05 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 5.81E-06 3.57E-07 --- 2.25E-06 2.30E-04 2.23E-05
CH-ODCM-0001 Reference Use Page 112 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 1.31E-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 --- 3.91E-01 4.24E-01 5.02E-05 CM-244 2.07E+00 1.27E+00 8.89E-02 --- 3.21E-01 4.08E-01 4.86E-05
CH-ODCM-0001 Reference Use Page 113 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 3.91E-06 --- --- 2.85E-06 3.40E-05 Co-58 --- 7.45E-07 1.67E-06 --- --- --- 1.51E-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 9.01E-06 4.36E-06 --- --- --- 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 --- --- --- 1.74E-06 Cu-64 --- 8.33E-08 3.91E-08 --- 2.10E-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 --- --- 5.21E-08 --- --- --- 4.09E-13 Br-85 --- --- 2.14E-09 --- --- --- --- Rb-86 --- 2.11E-05 9.83E-06 --- --- --- 4.16E-06 Rb-88 --- 6.05E-08 3.21E-08 --- --- --- 8.36E-19 Rb-89 --- 4.01E-08 2.82E-08 --- --- --- 2.33E-21 Sr-89 3.08E-04 --- 8.84E-06 --- --- --- 4.94E-05 Sr-90 8.71E-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 1.41E-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 --- 4.31E-06 8.20E-07 --- 9.76E-06 --- 9.99E-06 Tc-99M 2.47E-10 6.98E-10 8.89E-09 --- 1.06E-08 3.42E-10 4.13E-07
CH-ODCM-0001 Reference Use Page 114 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 --- 5.31E-06 --- 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 --- 2.91E-07 --- 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-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 2.41E-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 --- 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 --- 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 --- 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 --- 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 --- 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 --- 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 --- 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 --- 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-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 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 --- 8.01E-08 7.91E-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 4.71E-08 3.56E-11 1.59E-09 --- 3.31E-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 --- 1.21E-07 --- 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 --- 2.13E-09 --- 4.03E-05 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
CH-ODCM-0001 Reference Use Page 115 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.03E-07 8.61E-08 3.01E-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 8.71E-05 1.91E-05 --- 8.11E-05 --- 6.66E-05 Pu-240 7.24E-04 8.70E-05 1.91E-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 5.41E-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 --- 7.81E-05 Cm-244 4.56E-04 4.27E-04 2.87E-05 --- 1.34E-04 --- 7.55E-05
CH-ODCM-0001 Reference Use Page 116 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 1.71E-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 --- 1.21E-05 Mn-56 --- 1.58E-07 2.81E-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 --- 2.81E-06 6.33E-06 --- --- --- 3.66E-05 Ni-59 1.32E-05 4.66E-06 2.24E-06 --- --- --- 7.31E-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 5.41E-08 --- 2.91E-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 --- --- --- 4.41E-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 --- 3.21E-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 2.01E-07 --- 5.39E-09 --- --- --- 8.24E-05 Y-92 1.21E-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 --- 1.91E-08 --- 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 --- 7.11E-10 --- 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 --- 4.42E-09 --- 1.95E-05 Mo-99 --- 6.03E-06 1.15E-06 --- 1.38E-05 --- 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 --- 1.38E-08 5.14E-10 6.08E-07
CH-ODCM-0001 Reference Use Page 117 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 1.51E-06 8.78E-09 --- 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-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 --- 2.41E-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 2.21E-06 2.08E-06 2.33E-06 2.12E-05 --- 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 --- 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 --- 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 --- 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 --- 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 --- 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-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 6.71E-08 5.01E-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 1.71E-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 1.71E-06 1.91E-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 1.31E-08 5.23E-09 6.52E-10 --- 3.04E-09 --- 4.31E-05 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
CH-ODCM-0001 Reference Use Page 118 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.46E-07 1.19E-07 4.17E-08 --- --- --- 3.22E-05 Pu-238 6.70E-04 8.58E-05 1.82E-05 --- 7.80E-05 --- 7.73E-05 Pu-239 7.65E-04 9.29E-05 2.01E-05 --- 8.57E-05 --- 7.06E-05 Pu-240 7.64E-04 9.27E-05 2.01E-05 --- 8.56E-05 --- 7.19E-05 Pu-241 1.75E-05 8.40E-07 3.69E-07 --- 1.71E-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 --- 4.31E-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 --- 1.91E-04 --- 8.28E-05 Cm-244 5.04E-04 4.77E-04 3.19E-05 --- 1.49E-04 --- 8.00E-05
CH-ODCM-0001 Reference Use Page 119 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 1.21E-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 5.51E-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 --- 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 --- 3.84E-08 --- 3.99E-06 Br-83 --- --- 1.71E-07 --- --- --- --- Br-84 --- --- 1.98E-07 --- --- --- --- Br-85 --- --- 9.12E-09 --- --- --- --- Rb-86 --- 6.70E-05 4.12E-05 --- --- --- 4.31E-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 --- --- --- 5.11E-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 --- --- --- 1.71E-04 Y-90 4.11E-08 --- 1.10E-09 --- --- --- 1.17E-04 Y-91M 3.82E-10 --- 1.39E-11 --- --- --- 7.48E-07 Y-91 6.02E-07 --- 1.61E-08 --- --- --- 8.02E-05 Y-92 3.60E-09 --- 1.03E-10 --- --- --- 1.04E-04 Y-93 1.14E-08 --- 3.13E-10 --- --- --- 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 --- 3.65E-08 --- 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 --- 1.45E-09 --- 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 --- 8.23E-09 --- 1.62E-05 Mo-99 --- 1.33E-05 3.29E-06 --- 2.84E-05 --- 1.10E-05 Tc-99M 9.23E-10 1.81E-09 3.00E-08 --- 2.63E-08 9.19E-10 1.03E-06
CH-ODCM-0001 Reference Use Page 120 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 1.07E-09 1.12E-09 1.42E-08 --- 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 --- 2.81E-07 --- 1.84E-06 --- 1.89E-05 Ru-105 6.45E-08 --- 2.34E-08 --- 5.67E-07 --- 4.21E-05 Ru-106 1.17E-05 --- 1.46E-06 --- 1.58E-05 --- 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91E-07 --- 6.78E-07 --- 4.33E-05 Sb-124 1.11E-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 1.71E-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 6.91E-06 8.24E-05 --- 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 --- 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 --- 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 --- 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 --- 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 --- 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 --- 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 --- 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 --- 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 --- 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 --- 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 --- 5.16E-07 I-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 2.01E-07 --- 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 --- 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 --- 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 --- 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 --- 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 --- --- --- 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 --- --- --- 3.31E-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 1.11E-07 --- 3.61E-07 --- 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 --- 6.39E-09 --- 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 --- 2.11E-11 --- 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 --- 1.24E-08 --- 3.58E-05
CH-ODCM-0001 Reference Use Page 121 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 3.31E-05 --- 1.22E-04 --- 6.85E-05 Pu-240 1.28E-03 1.43E-04 3.31E-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 7.01E-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
CH-ODCM-0001 Reference Use Page 122 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 --- --- --- 2.30E-05 Cr-51 --- --- 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 --- 1.99E-05 4.51E-06 --- 4.41E-06 --- 7.31E-06 Mn-56 --- 8.18E-07 1.41E-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 --- --- --- 7.16E-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 6.31E-05 2.91E-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 2.51E-03 --- 7.20E-05 --- --- --- 5.16E-05 Sr-90 2.83E-02 --- 5.74E-04 --- --- --- 2.31E-04 Sr-91 5.00E-05 --- 1.81E-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 --- 3.01E-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 --- 5.41E-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 Tc-99M 1.92E-09 3.96E-09 5.10E-08 --- 4.26E-08 2.07E-09 1.15E-06
CH-ODCM-0001 Reference Use Page 123 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 --- 5.41E-05 Ru-106 2.41E-05 --- 3.01E-06 --- 2.85E-05 --- 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81E-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 --- --- 1.11E-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 2.50E-04 --- 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 --- 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 --- 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 --- 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 --- 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 --- 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 --- 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 --- 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 --- 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 --- 1.84E-06 I-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 --- 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 --- 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 --- 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 --- 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 --- 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 --- 4.06E-08 1.05E-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 2.11E-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 --- 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 --- 1.13E-08 --- 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 --- 3.84E-11 --- 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 --- 2.19E-08 --- 3.60E-05
CH-ODCM-0001 Reference Use Page 124 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 --- 1.21E-04 --- 7.57E-05 Pu-239 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 6.91E-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 1.11E-08 9.93E-10 5.61E-10 --- 1.98E-09 --- 2.87E-05 Am-241 1.46E-03 1.27E-03 1.09E-04 --- 6.55E-04 --- 7.70E-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 9.70E-04 7.59E-05 --- 2.71E-04 --- 7.84E-05
CH-ODCM-0001 Reference Use Page 125 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol fg Fraction of ingested produce grown in garden 0.76 of interest. f Fraction of leafy vegetables grown in garden of 1.0 interest. P Effective surface density of soil (assumes a 240 kg/m2 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) Sf 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) tf 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.
CH-ODCM-0001 Reference Use Page 126 of 126 Off-Site Dose Calculation Manual (ODCM) Revision 33 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/m2 (grass-cow-milk-man in wet weight) pathway) 2.0 kg/m2 (produce or leafy vegetable ingested by man) W Shore-width factor for river shoreline 0.2 w Rate constant for removal of activity on plant or 0.0021 hr-1 leaf structures by weathering (corresponds to a 14-day half-life)
DocuSign Envelope ID: 65549198-4214-4801-9A36-82C7DE995A29
~
ENERGYSOLUTIONS FCSD-RW-PG-101 Radwaste Process Control Program Revision 0
Authored By: Michael Wiskerchen, FCS Waste Manager Date
Reviewed By: Jason Spaide, FCS Manager of Special Projects Date
Approved By: Joseph Nowak, FCS Project Director Date
Approved By: Dan Whisler, OPPD/FCS Radiation Protection Manager Date 1 /DocuSigned by:
~
Approved By: Independent Safety Reviewer Date Non-Proprietary New Proprietary Title Change Restricted Information Revision Safeguards Information Rewrite Sensitive Security Information Cancellation Effective Date: Electronic documents, once printed, are uncontrolled and may become outdated. Refer to the Intranet or the Document Control authority for the correct revision.
)&6'5:3*
5DGZDVWH3URFHVV&RQWURO3URJUDP 5HYLVLRQ
5(&25'2)5(9,6,216 5HYLVLRQ 5HYLVLRQ7LWOH'HVFULSWLRQDQG5HDVRQIRU&KDQJH
,QLWLDOLVVXH1HZGRFXPHQW
3URSULHWDU\,QIRUPDWLRQ 3DJHRI
)&6'5:3*
5DGZDVWH3URFHVV&RQWURO3URJUDP 5HYLVLRQ
7DEOHRI&RQWHQWV
385326($1'6&23(
3XUSRVH
6FRSH
5()(5(1&(6
*(1(5$/
'HILQLWLRQV
5HVSRQVLELOLWLHV
3UHFDXWLRQVDQG/LPLWDWLRQV
5HFRUGV
5(48,5(0(176$1'*8,'$1&(
*HQHUDO,QVWUXFWLRQV
$GPLQLVWUDWLYH&RQWUROV
$77$&+0(176$1')2506
3URSULHWDU\,QIRUPDWLRQ 3DJHRI
)&6'5:3*
5DGZDVWH3URFHVV&RQWURO3URJUDP 5HYLVLRQ
385326($1'6&23(
3XUSRVH
7KHSXUSRVHRIWKLVGRFXPHQWLVWRHVWDEOLVKD3URFHVV&RQWURO3URJUDP
WKDWHQVXUHVSURFHVVLQJDQGSDFNDJLQJRIVROLGUDGLRDFWLYHZDVWHUHVXOWLQJ IURPWUHDWPHQWRIJDVHRXVDQGOLTXLGHIIOXHQWVDQGIURPRWKHUVRXUFHVWKDW LVFRPSOLDQWZLWK
$ $SSOLFDEOHIHGHUDODQGVWDWHUHJXODWLRQV
% 'LVSRVDOVLWHUHTXLUHPHQWV
& 2WKHUUHTXLUHPHQWVJRYHUQLQJWKHGLVSRVDORIUDGLRDFWLYHZDVWH
6FRSH
7KHVFRSHRIWKLVGRFXPHQWDSSOLHVWRDOOSHUVRQQHOSHUIRUPLQJDFWLYLWLHV
DVVRFLDWHGZLWKWKHSURFHVVLQJDQGSDFNDJLQJRIVROLGUDGLRDFWLYHZDVWH
5()(5(1&(6
&)53DUW6WDQGDUGVIRU3URWHFWLRQ$JDLQVW5DGLDWLRQ
&)53DUW$SSHQGL[$*HQHUDO'HVLJQ&ULWHULD&RQWURORI5HOHDVHVRI
5DGLRDFWLYH0DWHULDOWRWKH(QYLURQPHQW
&)53DUWD7HFKQLFDO6SHFLILFDWLRQVRQ(IIOXHQWVIURP1XFOHDU3RZHU
5HDFWRUV
&)53DUW/LFHQVLQJ5HTXLUHPHQWVIRU/DQG'LVSRVDORI5DGLRDFWLYH:DVWH
&)53DUW3DFNDJLQJDQG7UDQVSRUWDWLRQRI5DGLRDFWLYH0DWHULDOV
&)57UDQVSRUWDWLRQ
185(*2IIVLWH'RVH&DOFXODWLRQ0DQXDO*XLGDQFH 6WDQGDUG5DGLRORJLFDO
(IIOXHQW&RQWUROVIRU3UHVVXUL]HG:DWHU5HDFWRUV861XFOHDU5HJXODWRU\
&RPPLVVLRQ$SULO
15&*HQHULF/HWWHU ,PSOHPHQWDWLRQRI3URJUDPPDWLF&RQWUROVIRU
5DGLRORJLFDO(IIOXHQW7HFKQLFDO6SHFLILFDWLRQVDQGWKH5HORFDWLRQRI3URFHGXUDO
'HWDLOVRI5(7VWRWKH2IIVLWH'RVH&DOFXODWLRQ0DQXDORUWRWKH3URFHVV&RQWURO
3URJUDP-DQXDU\
8615&/RZ/HYHO:DVWH/LFHQVLQJ%UDQFK7HFKQLFDO3RVLWLRQRQ5DGLRDFWLYH
- DVWH)RUP5HY-DQXDU\
)&6'&+$QQXDO5DGLRDFWLYH(IIOXHQW5HOHDVH5HSRUW
)&6'5:353DFNDJLQJ6ROLG5DGLRDFWLYH:DVWH
(31'505HFRUGV0DQDJHPHQW3URJUDP
)&6'5:3*:DVWH0DQDJHPHQW3URJUDP
12)&4XDOLW\$VVXUDQFH7RSLFDO5HSRUW 4$75
3URSULHWDU\,QIRUPDWLRQ 3DJHRI
)&6'5:3*
5DGZDVWH3URFHVV&RQWURO3URJUDP 5HYLVLRQ
(QHUJ\Solutions8WDK'HSDUWPHQWRI(QYLURQPHQWDO4XDOLW\'LYLVLRQRI
5DGLDWLRQ&RQWURO5DGLRDFWLYH0DWHULDO/LFHQVH/LFHQVH1XPEHU87
*(1(5$/
'HILQLWLRQV
1RQH
5HVSRQVLELOLWLHV
7KH:DVWH0DQDJHUKDVRYHUDOOUHVSRQVLELOLW\IRUVROLGUDGLRDFWLYHZDVWH
DFWLYLWLHVDWWKH' 'SURMHFWVLWH
&RQWUDFWRUVDQGWKHLUVXEFRQWUDFWRUVKDYHWKHUROHVDQGDVVRFLDWHG
UHVSRQVLELOLWLHVRIDYHQGRULQDFFRUGDQFHZLWKWKLVSURFHGXUH
5DGLDWLRQ3URWHFWLRQ0DQDJHUKDVWKHUHVSRQVLELOLW\RIUHYLHZDQGDSSURYDORI
WKHYHQGRUVXEPLWWDOV
3UHFDXWLRQVDQG/LPLWDWLRQV
9HULI\FXUUHQWUHYLVLRQLQDFFRUGDQFHZLWKDSSOLFDEOHVLWHSURFHGXUHV
5HFRUGV
$OO:DVWH0DQDJHPHQWUHFRUGVZLOOEHPDLQWDLQHGLQDFFRUGDQFHZLWK)&6'
5:3* 5HI
5HFRUGVJHQHUDWHGIURPWKHXVHRIWKLVSURFHGXUHVKRXOGEHSURFHVVHGLQ
DFFRUGDQFHZLWK(31'50 5HI
5(48,5(0(176$1'*8,'$1&(
*HQHUDO,QVWUXFWLRQV
:HW:DVWH
$ 3URFHVVOLTXLGZHWZDVWHLQDFFRUGDQFHZLWK
6SHFLILFVLWHSURFHGXUHVWKDWSURYLGHVXIILFLHQWLQVWUXFWLRQVIRUVDIH
DQGHIILFLHQWSURFHVVLQJLPPRELOL]LQJDQGVWDELOL]LQJRIZHW ZDVWHVLQDFFRUGDQFHZLWK)&6'5:35 5HI
6KLSPHQWDQGGLVSRVDOUHTXLUHPHQWVWKDWPHHWWKHFULWHULDRQ)UHH
6WDQGLQJ:DWHU )6: LQDFFRUGDQFHZLWK8615&/RZ/HYHO
- DVWH/LFHQVLQJ%UDQFK7HFKQLFDO3RVLWLRQRQ5DGLRDFWLYH:DVWH
)RUP 5HI DQG(QHUJ\Solutions8WDK'HSDUWPHQWRI
(QYLURQPHQWDO4XDOLW\'LYLVLRQRI5DGLDWLRQ&RQWURO5DGLRDFWLYH 0DWHULDO/LFHQVH 5HI
$SSURYHGSURFHGXUHVWKDWFRQWDLQSURYLVLRQVIRUFRUUHFWLQJ
SURFHVVHGZDVWHLQZKLFK)6:LVGHWHFWHGLQH[FHVVRI)6:OLPLWV DQGFULWHULD 3URSULHWDU\,QIRUPDWLRQ 3DJHRI
)&6'5:3*
5DGZDVWH3URFHVV&RQWURO3URJUDP 5HYLVLRQ
% (QVXUHYHQGRUSURFHGXUHVDUHDSSURYHGE\WKH5DGLDWLRQ3URWHFWLRQ
0DQDJHU 530 SULRUWRXVH
6ROLGLILFDWLRQ
$ 4XDOLILHGYHQGRUVVKDOOVXSSO\VROLGLILFDWLRQ3URFHVV&RQWURO3URJUDPV
3&3V SURFHGXUHVDQGWRSLFDOUHSRUWVWRWKH530IRUDSSURYDO
% 7KHVHGRFXPHQWVVKRXOGLQFOXGH
3URFHVVGHVFULSWLRQ
6ROLGLILFDWLRQPHGLDXVHG
3URFHVVFRQWUROSDUDPHWHUV
3DUDPHWHUERXQGDU\FRQGLWLRQV
:DVWHIRUPSURSHUWLHV
6SHFLILFLQVWUXFWLRQVWRHQVXUHV\VWHPVDUHRSHUDWHGZLWKLQSURFHVV
SDUDPHWHUV
3UHVROLGLILFDWLRQODERUDWRU\VDPSOHPL[LQJFULWHULD
6DPSOLQJIUHTXHQF\DQGDFFHSWDQFHFULWHULD
([RWKHUPLFUHDFWLRQSURFHVVFRQWUROSDUDPHWHUV
& 6ROLGLILFDWLRQYHQGRUGRFXPHQWDWLRQVKDOOLQFOXGHSURYLVLRQVWRYHULI\
)6:FULWHULDDUHPHWIRUWKHVSHFLILFZDVWHW\SHEHLQJVROLGLILHG
' 7KHYHQGRUVXSSOLHG3&3VKDOOFRQWDLQWKHFXUUHQWIRUPXODVVDPSOLQJ
DQDO\VHVWHVWVDQGGHWHUPLQDWLRQVWREHPDGHWRHQVXUHWKDW SURFHVVLQJDQGSDFNDJLQJRIVROLGUDGLRDFWLYHZDVWHVEDVHGRQ GHPRQVWUDWHGSURFHVVLQJRIDFWXDORUVLPXODWHGZHWVROLGZDVWHVZLOO EHDFFRPSOLVKHGLQVXFKDZD\DVWRDVVXUHFRPSOLDQFHZLWK&)5 3DUWVDQG 5HIV VWDWHUHJXODWLRQVEXULDO JURXQGUHTXLUHPHQWVDQGRWKHUUHTXLUHPHQWVJRYHUQLQJWKHGLVSRVDORI VROLGUDGLRDFWLYHZDVWH
&RQWDLQHUV6KLSSLQJ&DVNVDQG3DFNDJLQJ
$ 6ROLGUDGLRDFWLYHZDVWHVKDOOEHSURFHVVHGSDFNDJHGDQGVKLSSHGLQ
DFFRUGDQFHZLWKDSSURYHGVLWHSURFHGXUHV
% 3URFHGXUHVVKDOOSURYLGHVSHFLILFLQVWUXFWLRQVWKDWHQVXUHFRPSOLDQFH
ZLWKDSSOLFDEOHIHGHUDOVWDWHDQGEXULDOVLWHUHTXLUHPHQWV
6KLSSLQJDQG'LVSRVDO
$ 3UHSDUHORDGDQGVKLSVROLGUDGLRDFWLYHZDVWHLQDFFRUGDQFHZLWK
VSHFLILFVLWHSURFHGXUHVWRPHHWIHGHUDOVWDWHDQGEXULDOVLWH UHTXLUHPHQWV 3URSULHWDU\,QIRUPDWLRQ 3DJHRI
)&6'5:3*
5DGZDVWH3URFHVV&RQWURO3URJUDP 5HYLVLRQ
2LO\0L[HG:DVWHV
$ 5DGLRDFWLYHZDVWHVFRQWDLQLQJRLORUKD]DUGRXVVXEVWDQFHVDUH
SURFHVVHGLQDFFRUGDQFHZLWKDSSURYHGVLWHSURFHGXUHVWRHQVXUH FRPSOLDQFHZLWKDSSOLFDEOHUHTXLUHPHQWV
6SHFLDO&DVHV
$ 8QLTXHZDVWHVPD\UHTXLUHVSHFLDOWHFKQLTXHVRUSURFHVVHV3URFHVV
VSHFLDOFDVHZDVWHLQDFFRUGDQFHZLWKVSHFLILFVLWHSURFHGXUHVWRPHHW DSSOLFDEOHUHTXLUHPHQWV
% ,PSOHPHQWLQJSURFHGXUHVDUHUHYLHZHGDQGDSSURYHGE\WKH:DVWH
0DQDJHU
& 6SHFLDOSURFHVVHVGHYHORSHGXQGHUWKLVSURYLVLRQVKRXOGEH
GRFXPHQWHGDVDFKDQJHWRWKH3&3SHU6HFWLRQRIWKLV SURFHGXUH
$GPLQLVWUDWLYH&RQWUROV
4XDOLW\$VVXUDQFH
$ 4XDOLW\$VVXUDQFHVKDOOEHLPSOHPHQWHGLQDJUDGHGDSSURDFKDV
GHVFULEHGLQ12)& 5HI
&KDQJHVWRWKH3URFHVV&RQWURO3URJUDPV 3&3V
$ /LFHQVHHLQLWLDWHGFKDQJHVWRWKH3&3VKDOO
%HGRFXPHQWHGDQGUHFRUGVRIUHYLHZVVKDOOEHUHWDLQHGLQ
DFFRUGDQFHZLWK12)& 5HI 7KLVGRFXPHQWDWLRQVKDOO FRQWDLQ L 6XIILFLHQWLQIRUPDWLRQWRVXSSRUWWKHFKDQJH V WRJHWKHUZLWK WKHDSSURSULDWHDQDO\VHVRUHYDOXDWLRQVMXVWLI\LQJWKHFKDQJH V LL $GHWHUPLQDWLRQWKDWWKHFKDQJH V ZLOOPDLQWDLQWKHRYHUDOO FRQIRUPDQFHRIWKHVROLGLILHGZDVWHSURGXFWWRWKHH[LVWLQJ UHTXLUHPHQWVRIIHGHUDOVWDWHDQGRWKHUDSSOLFDEOHUHJXODWLRQV DQG LLL 'RFXPHQWDWLRQWKDWWKHFKDQJHKDVEHHQUHYLHZHGDQGIRXQG DFFHSWDEOHWKURXJKH[HFXWLRQRIWKHDSSOLFDEOHUHJXODWRU\ UHYLHZSURFHVVIRUWKHSURMHFW
&KDQJHVPDGHWRWKH3&3VKDOOEHFRPPXQLFDWHGWR&KHPLVWU\DQG
(QYLURQPHQWDOIRULQFOXVLRQLQ$QQXDO5DGLRDFWLYH(IIOXHQW 5HOHDVH5HSRUWLQDFFRUGDQFHZLWK)&6'&+ 5HI
$77$&+0(176$1')2506
1RQH 3URSULHWDU\,QIRUPDWLRQ 3DJHRI
SECTION VII ATTACHMENT 2 JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA (Regulatory Guide 1.21) January 1, 2020 - December 31, 2020 VII-2
JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA A. Meteorological Data Recovery Data availability from the on-site weather tower for the period January 1, 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 B C 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.
VII-3
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY UNSTABLE (delta T/ delta z <= -1.9) PERIOD OF RECORD: JAN 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 10.0 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 0 211 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 30 146 173 184 126 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
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY UNSTABLE (-1.9 < delta T/ delta z <= -1.7) PERIOD OF RECORD: JAN 2015 - DEC 2019 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 1 110 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
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5) PERIOD OF RECORD: JAN 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- > 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 0 124 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 1 175 310 458 523 467 297 187 175 42 9 2644 Number of Calms 146 Number of Invalid Hours 0 Number of Valid Hours 2790 VII-6
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS NEUTRAL (-1.5 < delta T/ delta z <= -0.5) PERIOD OF RECORD: JAN 2015 - 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 0 584 E 1 38 112 159 265 148 58 23 10 2 0 816 ESE 1 45 86 170 301 222 85 39 34 8 1 992 SE 2 31 78 197 497 464 296 174 129 18 6 1892 SSE 2 25 53 164 522 655 497 340 342 34 8 2642 S 1 24 42 101 309 490 453 339 316 66 9 2150 SSW 1 18 32 61 168 200 164 153 151 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 72 175 163 111 58 50 2 0 743 NW 3 39 89 113 281 337 302 189 216 48 7 1624 NNW 2 49 171 269 816 768 462 239 209 26 1 3012 Total 29 591 1407 2196 4841 4562 2904 1822 1634 267 48 20301 Number of Calms 212 Number of Invalid Hours 0 Number of Valid Hours 20513 VII-7
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5) PERIOD OF RECORD: JAN 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 0 321 NNE 6 60 46 29 42 6 4 0 1 0 0 194 NE 10 46 64 33 29 3 1 0 0 0 0 186 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 59 157 206 452 288 131 43 48 6 2 1402 SSE 10 52 76 136 462 370 262 113 67 5 0 1553 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 70 104 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 1 758 NNW 13 70 142 168 271 113 26 13 10 1 0 827 Total 193 1029 1362 1287 2504 1586 1008 494 485 86 16 10050 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 10050 VII-8
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0) PERIOD OF RECORD: JAN 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 81 124 122 164 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 81 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 32 129 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 321 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
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY STABLE (delta T/ delta z > 4.0) PERIOD OF RECORD: JAN 2015 - 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 273 810 456 180 78 50 31 9 2 0 0 1889 Number of Calms 79 Number of Invalid Hours 0 Number of Valid Hours 1968 Hours Accounted For: 43799 VII-10
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY UNSTABLE (delta T/ delta z <= -1.9) PERIOD OF RECORD: JAN 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 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 0.16 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 0.12 0.02 0.00 0.48 S 0.00 0.00 0.01 0.01 0.04 0.10 0.06 0.06 0.10 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 Invalid Hours 0.00 Percent of Valid Hours 7.34 VII-11
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY UNSTABLE (-1.9 < delta T/ delta z <= -1.7) PERIOD OF RECORD: JAN 2015 - DEC 2019 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 0.00 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 0.14 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 Percent of Calms 0.04 Percent of Invalid Hours 0.00 Percent of Valid Hours 3.46 VII-12
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5) PERIOD OF RECORD: JAN 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- > 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 0.09 0.13 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 0.17 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 ESE 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
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT NEUTRAL (-1.5 < delta T/ delta z <= -0.5) PERIOD OF RECORD: JAN 2015 - 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 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 1.86 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 0.15 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 0.40 0.32 0.19 0.13 0.11 0.03 0.01 1.41 WSW 0.00 0.06 0.09 0.11 0.22 0.19 0.11 0.06 0.04 0.00 0.00 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 1.75 1.05 0.55 0.48 0.06 0.00 6.88 Total 0.07 1.35 3.21 5.01 11.05 10.42 6.63 4.16 3.73 0.61 0.11 46.35 Percent of Calms 0.48 Percent of Invalid Hours 0.00 Percent of Valid Hours 46.83 VII-14
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5) PERIOD OF RECORD: JAN 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 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 0.10 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 0.12 0.17 0.31 1.05 0.84 0.60 0.26 0.15 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 0.10 0.10 0.07 0.10 0.19 0.07 0.01 0.90 WSW 0.03 0.11 0.08 0.08 0.12 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 0.16 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 of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 22.95 VII-15
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0) PERIOD OF RECORD: JAN 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 0.78 NW 0.04 0.12 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 Total 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 of Invalid Hours 0.00 Percent of Valid Hours 8.56 VII-16
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY STABLE (delta T/ delta z > 4.0) PERIOD OF RECORD: JAN 2015 - 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 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 0.12 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 0.18 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 0.12 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 0.18 Percent of Invalid Hours 0.00 Percent of Valid Hours 4.49 Percent of Hours Accounted For: 100.00 VII-17
OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 01, 2020 - December 31, 2020
Annual Radiological Environmental Operating Report This report is submitted for the period January 01, 2020 through December 31, 2020. In addition, this report provides any observations and anomalies that occurred during the monitoring period. Reviewed by: Approved by: r - : DocuSigned by:
~
~D5~ 438 RP/Chem Supervisor Manager-RP/Chemistry Plant Manager Decommissioning Senior Director of Nuclear Decommissioning
Annual Radiological Environmental Operating Report The Fort Calhoun Station (FCS) Annual Radiological Environmental Operating Report for year 2020. 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 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, in accordance with Regulatory Guide 4.8, Table 1. 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 plant reactor containment building.
- 4) Table 3.0 is a listing of missed samples and explanations
- 5) Table 4.0 is the 2020 Land Use Survey
- 6) Review of Environmental Inc. Quality Assurance Program
- 7) Appendix A describes the Interlaboratory Comparison Program
- 8) Appendix B describes the vendor Data Reporting Conventions utilized
- 9) Appendix C is the Sample Location Maps Page 1 of 13
INTRODUCTION Radiological Environmental Monitoring Program (REMP) - 2020 This report gives the results of the Radiological Environmental Monitoring Program (REMP) for the year 2020. The REMP is a requirement of the Fort Calhoun Station (FCS) Quality Assurance Topical Report (QATR). It was initiated prior to 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 on a regular basis include: air, surface water, ground water, 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 0). 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 which 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 in accordance with Table 1 of Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants. Sample collection was conducted by plant chemistry/environmental staff. A contract 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 2020 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
- 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 2020 related to TLD sampling. One TLD was lost and could not be located; TLD OTD-1F. 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 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 stations ODCM. These TLDs were placed within the owner controlled area to assist with 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) 2020 Avg. Dose (mr/week) A 1.30 1.35 B 1.40 1.43 C 1.33 1.33 D 1.17 1.08 F 1.33 1.23 G 1.30 1.25 H 1.32 1.28 I 1.46 1.53 J 1.52 1.45 K 1.42 1.38 N 1.48 1.48 O 1.45 1.45 P 1.49 1.35 S 1.54 1.65 L (Control) 1.26 1.28 Page 3 of 13
- 2) Milk/Pasture Milk samples or pasture grasses, if milk is temporarily unavailable, are collected every two weeks during the pasture season from the beginning of May through September, and monthly the rest of the 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 lieu 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 purposes of the 2020 REMP.
Samples were comparable with historical results and within the range of results reported from the control location garden at Mohr Dairy. The additional special interest sample was not obtained from on-site farm fields due to no crops being planted because of decommissioning, documented in CR 2021-00093. This sample is documented in Table 3.0. 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
- 6) Air Monitoring Air sample results for 2020 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 21% difference when compared to historical average. All 2020 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/m3) 2020 Avg. Beta (pCi/m3) Sector B 0.027 0.021 Sector D 0.027 0.026 Sector I 0.024 0.021 Sector J 0.024 0.021 Sector K 0.026 0.021 Sector F (Control) 0.027 0.025
- 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) Ground Water 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: Lomp 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 2.0 pCi/liter to a high of 9.2 pCi/liter, with an average gross beta for the year of 4.5 pCi/liter for indicator locations. Strontium-90 analysis is being conducted on the wells as part of the stations groundwater protection program. No plant-related effects were detected. Page 5 of 13
Table 1.0 Sample Collection Program Collection Number of Samples Sample Class Frequency Sample Collected this Locations Period Background Radiation (TLDs) Quarterly 484 1875 Air Particulates Weekly 6 312 Airborne Iodine Weekly6 6 0 Biweekly Milk May thru Sept 2 241 Surface Water Monthly 3 36 Ground Water Quarterly 4 16 Fish Annually 2 52 Sediment Semi-annually 2 07 Food Crops Annually 2 93 TOTAL 589 Note 1: Milk sample collection total includes 4 vegetation samples performed for milk unavailability. Milk samples are collected every two weeks May-Sept. and monthly the rest of the 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 of missed samples for explanations. Note 6: Collection was terminated on 1/9/19. Note 7: Deleted from program. Page 6 of 13
Table 2 JRadiological EnffOnmental Monitoring Progam SU"l'lmary Reponing Period Ja nuary*December. 2020 Name of Facility Fo rt Calhoun Nu clear Power Station
- Unit 1 Docket No. 50-285 l ocation oi Facility W.JShington. Nebra.ska
( County, State ) Indicator l ocaton with Highest Control ~umb<< Satrple Type and Locations Annual Mean Locations Non* Ty,e (Urits) Number of Analyses* l LDt> Mean (F)" Rangee LOC.Jtione M,an (F)" Rangee Mean (F,C Rangee ......... P.oufoe Sackgoood Gamma 239 0.5 1.4 (2311231) O TO-S-{I) 1.6 (4/4) 1.3 (4/4) 0 Radation ( 0.9-2.0) 0.65@ 163' 1.5-1.8 (0.9-1.6) (TlO) 1.8 (111) (mR/wek) Airborne GB 3 12 0.005 0.022 (2601260) OAP-0-{I) 0.026 (52152) 0.025 (52152) 0 Particulates (0.00 1-0.06 1) 3.0 mi. @ 303 * (0.006-0.061) (0.0 11-0.050) (pCi1m1) GS 24 Cs* 134 0.00 1 < L LD . . < LLD 0 Cs* 137 0.00 1 < L LD . . < LLD 0 Other Gammas 0.00 1 < L LD . . < LLD 0 Airborne 1-131 0 0.07 < L LD . . < LLD 0 lodf t (CICi/m3) Ml k 1-131 20 0.5 < L LD . . < LLD 0 (pO/L) GS 20 K-40 150 1720 (818) Miller Fann 1720 (8/8) 1340 (12112) 0 (1278-20 12. 1) 0.S mi. @206 * (1278-20 12. 1) (1198- 1502 ) Cs- 134 15 < L LD . . < LLD 0 Cs- 137 15 < L LD . . < LLD 0 Other Gammas 15 < L LD . . < LLD 0 Gro-.n:!Water GB 16 4.5 (12112) Smith Fann 5.3 (4/4) 4.3 (4/4 ) 0 (pO/L) (2.0-9.2) 0.65 mi.@ 163* (3.8-9.2) (3 .5-5.5) H-3 16 300 < L LD . . < LLD 0 Sr-90 16 0.7 < L LD . . < LLD 0 GS 16 (pO/L) Cs- 134 15 < L LD . . < LLD 0 Cs- 137 18 < L LD . . < LLD 0 Other Gammas 15 < L LD . . < LLD 0 SurfacE Water GS 36 (pO/L) Cs- 134 15 < L LD . . < LLD 0 Cs- 137 18 < L LD . . < LLD 0 Other Gammas 15 < L LD . . < LLD 0 H-3 12 300 < L LD . . < LLD 0 Page 7 of 13
Table 2 JRadiological Env.-Onmental Monitoring Progan, Summary Reponing Period Ja nuary.De¢ember, 2020 Name oi Facility Fort Calhoun Nuclear Power Station
- Unit 1 Docket No . 50-285 l ocation of Facility W.3Shington. Nebra.ska
( County. State ) lndicatOf l ocation with Highest Control Number Sample Type and Locations A nnual Mean Locations Non-Type Number of LLIY Mean (Ff Mean ( Fr Mean (Ff Routine (Unils) A nalyses* R31lgee l ocatione Range" Range" Res.Ats* Fish GS 5 (pCifg wet) Mtk54 0.022 < LLD . - < LLD 0 Co-58 0 .04 1 < L LD <U D 0 Co-60 0 .0 15 < L LD <U D 0 Fe-59 0 .102 < L LD . - < LLD 0 Zn-65 0 .043 < L LD <U D 0 Ru -103 0.085 < L LD <U D 0 Cs- 134 0 .02 1 < L LD . - < LLD 0 Cs- 137 0.020 < L LD . - < LLD 0 Sediment GS 0 pCifg dry Mn-54 0.000 < L LD <U D 0 Co-58 0.000 < L LD . - < LLD 0 Co-60 0.000 < L LD . - < LLD 0 Fe-59 0.000 < L LD <U D 0 Zn-65 0.000 < L LD . - < LLD 0 Cs- 134 0.000 < L LD . - < LLD 0 Cs- 137 0.000 < L LD <U D 0 Food Crops GS g (pCifg wet) Mtk54 0 .0 12 < LLD . - < LLD 0 Co-58 0 .0 14 < L LD <U D 0 Co-60 0 .0 11 < L LD <U D 0 Fe-59 0.030 < L LD . - < LLD 0 Zn-65 0.030 < L LD <U D 0 Zr-Nb-95 0 .0 14 < L LD <U D 0 Cs- 134 0 .0 18 < L LD . - < LLD 0 Cs- 137 0 .0 18 < L LD . - < LLD 0 Ba-la-t 40 0 .0 15 < L LD LLD) Fraction of detectlble mea.surements a:! specified locations is indicated in p.3rentheses ( F). 0 Locations ar e speciflled: ( 1) by code. {2) by name, and (3) by distanoe and direction relative to the React.Of Conta:nment Buiding.
- Non-routine res.Ats are those which exceed ten times the control station V.llue.. If n o con trol station value is available. the result is considered non-routin e if it exceeds the typic.J! pre-<>perational l/.Jl ue for lhe mediU"n or location.
Page 8 of 13
Table 3.0 Listing of Missed Samples (samples scheduled but not collected) Sample Date Location Reason Type TLD 1/7/2020 OTD-1F-(I) Lost in field (CR 2020-00013) VE 8/5/2020 O-OVG-E-(I) No sample available. Corn not planted due to plant decommissioning. (CR 2021-00093) Page 9 of 13
Table 4.0 - 2020 Land Use Survey F ORT CALHOUN STATION F C-80 1 CHE M I STRY FORM REV 1 2020 Page 1 o f 3 Environmental Land Use Survey Report Secto1 Dir Land Use Owne r Miles Mete rs Deg S urve y Te chnique I
~
c: G
-a
~
C a I X OQ DOQ Re m arks t ~ Q C A I N R E S IDENCE WRIGHT 4 .36 70 16 .7< 351 IN TER VIE W X X 1 .30E-0i 4.50E-10 M ILK ANIMAL MEAT ANIMAL V E G E TATION GROUNOWATEF WRIGHT 4 .36 70 16 .7< 351 IN TER VIEW X X B INNE R E S IDENCE RAND,J 1 .93 3 106.0 , 1 2 MAIL SURVEY X 7 .00E-0i 1.90E-09 M ILK ANIMAL MEAT ANIMAL D U GDALE ,D 4 .72 75 96.1( 29 IN TER VIE W X 1 .10 E-0i 2.20E-10 V E G E TATION SHE PARD 2 .23 35 88.0' 1 6 C ITY REG ISTEF X X 4 .60E-0 , 1.20E-09 GROUNOWATEF RAND,J 1 .93 3 106.0, 1 2 MAIL SURVEY X C I NE R E S IDENCE HANSE N,M 1 .52 2446.21 4 2 MAIL SURVEY X X 1 .00E-0E 2.20E-"" M ILK ANIMAL MEAT ANIMAL V E G E TATION VENN ER ,R 3 .20 5 149.9( 48 C ITY REG ISTEF X 1 .70E-0i 3.00E-10 GROUNOWATEF HANSE N,M 1 .52 2446.21 4 2 MAIL SURVEY X X D I ENE R E S IDENCE MEADE. G 4 .79 7708.7E 63 IN TER VIE W X 8 .80E-0E 9.70E-1 1 M ILK ANIMAL MEAT ANIMAL V E G E TATION MEADE. G 4 .79 7708.7E 63 IN TER VIE W X 8 .80E-0E 9.70E-1 1 GROUNOWATEF MEADE. G 4 .79 7708.7E 63 IN TER VIE W X E I E R E S IDENCE LOVE 4 .67 75 15 .6' 89 IN TER VIEW X X 1 .10 E-0i 1.60E-10 M ILK ANIMAL MEAT ANIMAL BROTH ERS ,D 4 .9 1 7901 .~ 90 IN TER VIEW X 1 .00E-0i 1.40E-10 V E G E TATION GROUNOWATEF LOVE 4 .67 75 15 .6' 89 IN TER VIE W X X F ! ESE R E S IDENCE W ILSON ISLAND 4 .22 6791 .4, 1 2 1 IN TER VIEW X X X 2 .00E-0 , 2.70E-10 M ILK ANIMAL MEAT ANIMAL V E G E TATION W ILSON ISLAND 4 .22 6791 .4, 1 2 1 IN TER VIE W X X X 2 .00E-0i 2.70E-10 GROUNOWATEF W ILSON ISLAND 4 .22 6791 .4, 1 2 1 IN TER VIEW X X X G I SE R E S IDENCE CARTER ,T 1 .67 2687.6( 14 5 C ITY REG ISTEF X 1 .50E-0E 4.20E-"" M ILK ANIMAL MEAT ANIMAL V E G E TATION CARTER , S. 1 .99 3202.5! 1 34 C ITY REG ISTEF X 9 .30E-0i 2.60E-09 GROUNOWATEF H OW E LL,J 1 .7 1 275 1 .9! 14 5 C ITY REG ISTEF X Page 10 of 13
Table 4.0 - 2020 Land Use Survey F ORT CAL HOUN STATION FC-8Cl 1 CHEM ISTRY F OR M R EV 1 2020 Page 2 o f 3 Environ m,e ntall Land Use S urvey Report Land U se Owner Mli l es Mete rs Deg1 Survey I "= Groua I XOQ DOQ Remarks Secto 1 mr Technique I~ i ~ ]
~ {! 6 _c:
I H I SS E R ESID ENC E LOM IP .65 1046 .0i 163 C ITY REG ISTEIF X 6.?0 E-06 6.0ClE-08 M ILK A NI MAL M EAT ANI MAL V EGETAT IO N PECHN IK ,A .94 15 12 .7t 163 INTERVIEW X 3 .0 0 E-06 2 .7ClE"08 GROUNDWAT EA LOM IP .65 1046 .m 163 C ITY REG ISTEIF X J I s R ESID ENC E DOW LER .73 1 174.8~ 175 MAI L SURVEY X 4 .20 E-06 2 .7ClE-08 M ILK A NI MAL M EAT ANI MAL M I LL ER ,M .66 1062 . 1] 190 MAI L SURVEY X 5 .30 E-06 3.4ClE*08 V EGETAT IO N DOW LER .73 1 174.8~ 175 MAI L S URVEY X 4.20 E-06 2 .7ClE-08 GROUNDWAT ER DOW LER .73 1 174.8~ 175 MAI L SURVEY X K ISSW R ES I D ENC E D .M I LL ER .65 1 46 .m 203 C ITY REG ISTEIF X 4 .30 E-06 1.4 ClE-08 M ILK A NI MAL C . M ILLER 3.30 5310.84 2 110 INTERVIEW X 9 .1i0 E-08 2 .3ClE-10 M EAT ANI MAL V EGETAT IO N ANDERSON ,W .99 1593.2~ 196 C ITY REGISTE'r X 1 .?0 E-06 5 .7ClE* 09 GROUNDWAT ER D .M I U_ER .65 10 46.0i 203 C ITY REG ISTEIF X L l sw R ESID ENC E ROBER TSON ,D .73 1 174.B~ 224 MAI L SURVEY X 3 .20 E-06 8 .5ClE-09 M ILK A NI MAL BARRERA 4 .20 6759.24 2 119 C ITY REGISTEE; X X X 6 .40 E-08 1.2ClE-10 M EAT ANI MAL R YDER .76 1223. 1( 227 INTERVIEW X 3 .0 0 E-06 7 .8ClE* 09 V EGETAT IO N BU RGI N 1.43 2301 .3t 223 C ITY REGISTEIF X 6.20 E-07 1.5ClE"09 GROUNDWAT ER ROB ER TSON ,D .73 11 74 .B~ 224 MAI L SURVEY X M IWSW R ESID ENC E B ENSEN, M 1.06 17Cl5.9C 257 C ITY REG ISTEIF X 1 .6 0 E-06 4 .2ClE-09 M ILK A NI MAL M EAT ANI MAL LIST 1i9 V EGETAT IO N THOMAS 1 ..113 18 18.51: 259 C ITY REG ISTEIF X X 1.30 E-06 3 .5ClE-09 GROUNDWATER B ENSE N, M 1.06 17Cl5.9C 257 C ITY REG ISTEIF X N 1w R ES I OENC E NII ELS EN 1 .20 193 1.21 263 C ITY REG ISTEi;, X 1 .S0 E-06 4 . 1 ClE-09 M ILK A NI MAL M EAT ANI MAL ANDERSON ,J 3.25 5230.3] 281 INTERVIEW X 1 .4 0 E-07 3 .0ClE-10 V EGETAT IO N GROUNDWAT ER K EAS, J. 1.30 2092 . 1~ 270 MAI L SURVEY X X IP IWN\I\' R ESID ENC E LYTLE 2.60 4 184 .2<:: 283 C ITY REG ISTEIF X 3 .40 E-07 7 .8ClE-10 M ILK A NI MAL M EAT AN IMAL BROW N 4 .59 7386.8<:: 288 C ITY REGISTEE; X 1 .30 E-07 2.4CDE-10 V EGETAT IO N T ABOR 2.65 4264 .71: 285 C ITY REGISTEIF X X X 3.20 E-07 7.4ClE-10 GROUNDWAT ER LYTLE 2.60 4 1 84 .2~ 283 C ITY REGISTE'r X Page 11 of 13
Table 4.0 - 2020 Land Use Survey FORT CALIHOUN STAlilON FC-8[1 1 C HEM ISTRY FORM R EV 1 2020 Page 3 ,of 3 Environmental Land Use Survey Report: Sedo r Dir Land Use Ow111e r Mli lies Me*ters 1Deg1 Surve*y a .... Grour> XOQ DOQ Remarks Tedmi,que ~ i g i
- 5! ti 0 =
,ill Q NW R ESll[} ENC E HANS EN ,R 2.40 38 62.4!~ 3118 C ITY REGISTER X 5.20 E-07 1.9CIE-Cl9 MIILK ANI MAL M EAT ANI MAL VEGETAT ION HANS EN ,R 2.40 3862.4: 3118 C ITY REGISTER X 5.20 E-07 11.9CIE 0 [19 GROUNDW ATER HA.NS EN ,R 2-40 3862.4: 3118 C ITY REGISTER X R NNW R ESID ENC E BATTIA TO 2.08 3347.4!~ 33 [1 INTERVIE W X 8.20 E-07 3.4![1Ea[l9 MI LK ANI MAL M EAT ANI MAL VEGE TA T ION GROUNDWATER SOND ERUP 3.73 60(12.8<!: 328 MAI L S URVEY X Perto:nmed by_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Reviewed by_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Page 12 of 13
Review of Environmental Inc., Quality Assurance Program Fort Calhoun Station contracts with Environmental Inc., Midwest Laboratory (vendor lab) to perform radioanalysis 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 laboratorys procedures and processes, and provides indication of possible weaknesses. In addition, Environmental Inc. has its own in-house QA program of blind-spike and duplicate analyses. Routine FCS REMP duplicate samples were performed by the vendor to verify reproducibility of results. All duplicates were within acceptance criteria. Environmental resource cross check samples ERDW-53 for Ra-226 failed slightly below the acceptance criteria. The sample was re-run in duplicate and both results were acceptable. ERW-2297 for Ba-133 failed below the lower acceptance limit and no cause for the failure could be identified. NYW-3333 for Uranium failed above the acceptance limit and the uncertainty overlapped the upper acceptance limit. The lab passed the ERA and MAPEP studies for uranium in 2020. Three DOE MAPEP cross check samples failed in 2020. DOE cross check sample MAAP-664 sample for Gross Alpha failed the acceptance criteria due to the specific calibration caused the bias to shift. The subsequent analysis (MAAP-3101) was acceptable. MAW-599 for Ra-226 and Pu-239/240. The cause of the Ra-226 was inconclusive and the subsequent analyses were acceptable (ERA RAD-121, ERA RAD-122 and NY ELAP shipment 437R). The Pu-239/240 analysis was repeated in duplicate with acceptable results. MAAP-3177 for Cs-134 and Mn-54. The Cs-134 uncertainty overlapped the lower acceptance limit and the Mn-54 was due to a transcription error, which was acceptable when corrected. 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 vendors 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
~~f. ATI Environmental, Inc.
'f' /""'\I Midwest Laboratory 700 Landwehr Road* Northbrook. IL 60062-2310 phone /847) 564-0700
- fax /847) 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, 2020 through December, 2020
Appendix A Interlaboratory/ Intralaboratory 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 laboratorys 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. Results in Table A-2 were obtained through participation in the New York Department of Health Environmental Laboratory Approval Program (ELAP) PT. Table A-3 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-4 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-5 lists results of the analyses on intralaboratory blank samples for the past twelve months. Data for previous years available upon request. Table A-6 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-7 were obtained through participation in the Mixed Analyte Performance Evaluation Program. Results in Table A-8 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
Attachment A ACCEPTANCE CRITERIA FOR INTRALABORATORY SPIKED SAMPLES Analysis Ratio of lab result to known value. Gamma Emitters 0.8 to 1.2 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, 0.7 to 1.3 Radium-228 Plutonium 0.8 to 1.2 Iodine-129, 0.8 to 1.2 Iodine-131 Nickel-63, 0.7 to 1.3 Technetium-99, Uranium-238 Iron-55 0.8 to 1.2 Other Analyses 0.8 to 1.2 A-2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a. RAD study Concentration (pCi/L) Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance RAD-120 Study ERW-49 1/6/2020 Ba-133 60.8 +/- 4.4 64.5 53.7 - 71.0 Pass ERW-49 1/6/2020 Cs-134 22.7 +/- 2.8 22.9 17.5 - 25.6 Pass ERW-49 1/6/2020 Cs-137 225 +/-8 220 198 - 244 Pass ERW-49 1/6/2020 Co-60 94.6 +/- 4.6 91.2 82.1 - 103 Pass ERW-49 1/6/2020 Zn-65 331 +/- 13 298 268 - 348 Pass ERDW-51 1/6/2020 Gr. Alpha 52.3 +/- 2.4 58.9 30.8 - 73.3 Pass ERDW-51 1/6/2020 Gr. Beta 19.9 +/- 1.0 21.0 12.6 - 29.1 Pass ERDW-53 1/6/2020 Ra-226 12.8 +/- 0.5 17.4 12.9 - 19.9 Failb ERDW-53 1/6/2020 Ra-228 7.13 +/- 0.9 7.95 5.06 - 10.1 Pass ERDW-53 1/6/2020 Uranium 63.8 +/- 1.0 68.2 55.7 - 75.0 Pass ERW-55 1/6/2020 H-3 18,200 +/- 408 17,800 15,600 - 19,600 Pass RAD-121 Study ERDW-1034 4/6/2020 Ra-226 17.8 +/- 0.5 18.4 13.7 - 21.0 Pass ERDW-1034 4/6/2020 Ra-228 6.30 +/- 0.86 5.81 3.56 - 7.64 Pass ERDW-1034 4/6/2020 Uranium 18.7 +/- 1.3 18.6 14.9 - 20.9 Pass RAD-122 Study ERW-2297 7/6/2020 Ba-133 43.8 +/- 3.4 58.6 48.6 - 64.6 Failc ERW-2297 7/6/2020 Cs-134 19.8 +/- 2.4 22.3 17.0 - 25.0 Pass ERW-2297 7/6/2020 Cs-137 73.2 +/- 5.4 73.0 65.7 - 83.0 Pass ERW-2297 7/6/2020 Co-60 90.0 +/- 4.0 86.1 77.5 - 97.0 Pass ERW-2297 7/6/2020 Zn-65 84.9 +/- 7.5 82.9 74.6 - 99.6 Pass ERDW-2299 7/6/2020 Gr. Alpha 40.3 +/- 2.2 52.40 27.30 - 65.6 Pass ERDW-2299 7/6/2020 Gr. Beta 19.9 +/- 1.0 24.3 15.0 - 32.3 Pass ERDW-2303 7/6/2020 Ra-226 8.91 +/- 0.43 10.8 8.08 - 12.5 Pass ERDW-2303 7/6/2020 Ra-228 4.79 +/- 0.80 5.42 3.28 - 7.19 Pass ERDW-2303 7/6/2020 Uranium 27.7 +/- 0.9 29.3 23.7 - 32.5 Pass ERW-2305 7/6/2020 H-3 21,100 +/- 400 20,300 17,800 - 22,300 Pass ERW-2301 7/6/2020 I-131 27.8 +/- 1.2 26.1 21.7 - 30.8 Pass 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 Ra-226 was slightly below the lower limit of the study. The reported value was the mean of two results (12.5 & 13.0). The sample was re-run in duplicate and both results, 15.6 and 13.8 pCi/L, were within the acceptance band. c Ba-133 was below the lower acceptable limit of the study. No cause for the failure could be identified. Going forward gamma results will be monitored to see if any trend develops. A-3
TABLE A-2. Interlaboratory Comparison Crosscheck program, New York Department of Health (ELAP) a. Concentration (pCi/L) Lab Code Date Analysis Laboratory Assigned Acceptance Result Value Limits Acceptance Shipment 437R NYW-3307 9/15/2020 H-3 11,500 +/- 465 11,208 9760 - 12,300 Pass NYW-3331 9/15/2020 Gross Alpha 43.7 +/- 2.5 64.9 34.0 - 80.4 Pass NYW-3331 9/15/2020 Gross Beta 11.1 +/- 1.1 8.85 3.62 - 17.4 Pass NYW-3335 9/15/2020 I-131 14.1 +/- 1.4 12.6 10.3 - 16.0 Pass NYW-3333 9/15/2020 Ra-226 2.24 +/- 0.27 2.63 2.06 - 3.44 Pass NYW-3333 9/15/2020 Ra-228 4.91 +/- 1.12 5.41 3.27 - 7.18 Pass NYW-3333 9/15/2020 Uranium 42.8 +/- 1.94 37.1 30.1 - 41.0 Failb NYW-3337 9/15/2020 Co-60 46.4 +/- 3.8 42.3 38.1 - 49.2 Pass NYW-3337 9/15/2020 Zn-65 133 +/-9 116 104 - 138 Pass NYW-3337 9/15/2020 Ba-133 49.5 +/- 4.1 46.4 38.0 - 51.6 Pass NYW-3337 9/15/2020 Cs-134 32.5 +/- 3.1 33.0 26.0 - 36.3 Pass NYW-3337 9/15/2020 Cs-137 147 +/-7 134 121 - 150 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by the New York Department of Health Laboratory Approval Program(NY ELAP). b Lab passed all ERA and MAPEP studies for uranium in 2020.(See tables A-1, A-7 and A-8) Uncertainty overlaped upper acceptance limit. Lab will continue to monitor results going forward for trends. A-4
TABLE A-3. Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).a mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P) Environmental, Inc. Group 1 2020-1 10/28/2020 Spike 1 172.0 180.0 0.05 2020-1 10/28/2020 Spike 2 172.0 174.5 0.01 2020-1 10/28/2020 Spike 3 172.0 174.3 0.01 2020-1 10/28/2020 Spike 4 172.0 174.0 0.01 2020-1 10/28/2020 Spike 5 172.0 167.1 -0.03 2020-1 10/28/2020 Spike 6 172.0 161.9 -0.06 2020-1 10/28/2020 Spike 7 172.0 167.9 -0.02 2020-1 10/28/2020 Spike 8 172.0 171.0 -0.01 2020-1 10/28/2020 Spike 9 172.0 170.7 -0.01 2020-1 10/28/2020 Spike 10 172.0 170.1 -0.01 2020-1 10/28/2020 Spike 11 172.0 173.8 0.01 2020-1 10/28/2020 Spike 12 172.0 178.3 0.04 2020-1 10/28/2020 Spike 13 172.0 178.2 0.04 2020-1 10/28/2020 Spike 14 172.0 171.9 0.00 2020-1 10/28/2020 Spike 15 172.0 190.4 0.11 2020-1 10/28/2020 Spike 16 172.0 170.9 -0.01 2020-1 10/28/2020 Spike 17 172.0 183.3 0.07 2020-1 10/28/2020 Spike 18 172.0 170.6 -0.01 2020-1 10/28/2020 Spike 19 172.0 164.9 -0.04 2020-1 10/28/2020 Spike 20 172.0 175.7 0.02 Mean (Spike 1-20) 173.5 0.01 Passd Standard Deviation (Spike 1-20) 6.5 0.04 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)K a = 1.20 . mrem/cGy = 1000. c Performance Quotient (P) is calculated as ((reported dose - conventially true value) ÷ conventially true value) where the conventially 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
TABLE A-3. Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).a mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P) Environmental, Inc. Group 2 2020-2 10/28/2020 Spike 21 114.0 117.3 0.03 2020-2 10/28/2020 Spike 22 114.0 103.3 -0.09 2020-2 10/28/2020 Spike 23 114.0 106.2 -0.07 2020-2 10/28/2020 Spike 24 114.0 110.1 -0.03 2020-2 10/28/2020 Spike 25 114.0 114.9 0.01 2020-2 10/28/2020 Spike 26 114.0 115.5 0.01 2020-2 10/28/2020 Spike 27 114.0 110.4 -0.03 2020-2 10/28/2020 Spike 28 114.0 111.7 -0.02 2020-2 10/28/2020 Spike 29 114.0 111.3 -0.02 2020-2 10/28/2020 Spike 30 114.0 113.1 -0.01 2020-2 10/28/2020 Spike 31 114.0 116.4 0.02 2020-2 10/28/2020 Spike 32 114.0 111.8 -0.02 2020-2 10/28/2020 Spike 33 114.0 112.6 -0.01 2020-2 10/28/2020 Spike 34 114.0 105.7 -0.07 2020-2 10/28/2020 Spike 35 114.0 104.5 -0.08 2020-2 10/28/2020 Spike 36 114.0 103.6 -0.09 2020-2 10/28/2020 Spike 37 114.0 104.4 -0.08 2020-2 10/28/2020 Spike 38 114.0 104.5 -0.08 2020-2 10/28/2020 Spike 39 114.0 106.4 -0.07 2020-2 10/28/2020 Spike 40 114.0 107.7 -0.06 Mean (Spike 21-40) 109.6 -0.04 Passd Standard Deviation (Spike 21-40) 4.6 0.04 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)K a = 1.20 . mrem/cGy = 1000. c Performance Quotient (P) is calculated as ((reported dose - conventially true value) ÷ conventially true value) where the conventially 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-6
TABLE A-4. Intralaboratory "Spiked" Samples Concentrationa b Lab Code Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known SPW-481 1/1/2020 Ra-226 10.4 +/- 0.3 12.3 8.6 - 16.0 Pass 0.85 SPW-110 1/16/2020 H-3 2,101 +/- 154 2,110 1,688 - 2,532 Pass 1.00 W-041620 4/29/2016 Cs-134 35.7 +/- 8.8 36.2 29.0 - 43.4 Pass 0.99 W-041620 4/29/2016 Cs-137 75.0 +/- 6.6 71.9 57.5 - 86.3 Pass 1.04 W-042020 4/29/2016 Cs-134 40.6 +/- 10.2 36.2 29.0 - 43.4 Pass 1.12 W-042020 4/29/2016 Cs-137 71.2 +/- 7.0 71.9 57.5 - 86.3 Pass 0.99 SPW-190 1/23/2020 H-3 2,058 +/- 153 2,110 1,688 - 2,532 Pass 0.98 SPW-205 1/28/2020 Sr-90 17.6 +/- 1.2 17.9 14.3 - 21.5 Pass 0.99 SPW-217 1/31/2020 H-3 2,005 +/- 152 2,110 1,688 - 2,532 Pass 0.95 SPW-270 2/7/2020 H-3 2,153 +/- 157 2,110 1,688 - 2,532 Pass 1.02 SPW-288 2/11/2020 Ra-228 13.1 +/- 1.7 14.9 10.4 - 19.3 Pass 0.88 W-021220 4/29/2016 Cs-134 39.3 +/- 18.9 36.2 29.0 - 43.4 Pass 1.09 W-021220 4/29/2016 Cs-137 73.9 +/- 15.8 71.9 57.5 - 86.3 Pass 1.03 SPW-396 2/14/2020 H-3 2,298 +/- 160 2,110 1,688 - 2,532 Pass 1.09 W-022420 4/29/2016 Cs-134 33.4 +/- 10.5 36.2 29.0 - 43.4 Pass 0.92 W-022420 4/29/2016 Cs-137 75.6 +/- 7.8 71.9 57.5 - 86.3 Pass 1.05 SPW-716 2/26/2020 Ra-226 11.3 +/- 0.4 12.3 8.6 - 16.0 Pass 0.92 W-022820 4/29/2016 Cs-134 34.9 +/- 11.6 36.2 29.0 - 43.4 Pass 0.96 W-022820 4/29/2016 Cs-137 82.9 +/- 8.5 71.9 57.5 - 86.3 Pass 1.15 SPW-532 2/28/2020 H-3 2,054 +/- 153 2,110 1,688 - 2,532 Pass 0.97 W-030420 4/29/2016 Cs-134 29.7 +/- 9.6 36.2 29.0 - 43.4 Pass 0.82 W-030420 4/29/2016 Cs-137 74.2 +/- 7.3 71.9 57.5 - 86.3 Pass 1.03 W-031020 4/29/2016 Cs-134 41.6 +/- 17.8 36.2 29.0 - 43.4 Pass 1.15 W-031020 4/29/2016 Cs-137 78.6 +/- 14.3 71.9 57.5 - 86.3 Pass 1.09 SPW-711 3/12/2020 H-3 2,083 +/- 154 2,110 1,688 - 2,532 Pass 0.99 SPW-825 3/12/2020 Ra-226 12.4 +/- 0.4 12.3 8.6 - 16.0 Pass 1.01 SPW-774 3/18/2020 H-3 2,021 +/- 151 2,110 1,688 - 2,532 Pass 0.96 W-031820 4/29/2016 Cs-134 29.7 +/- 10.6 36.2 29.0 - 43.4 Pass 0.82 W-031820 4/29/2016 Cs-137 75.5 +/- 9.2 71.9 57.5 - 86.3 Pass 1.05 W-032520 4/29/2016 Cs-134 36.4 +/- 9.2 36.2 29.0 - 43.4 Pass 1.01 W-032520 4/29/2016 Cs-137 74.9 +/- 7.0 71.9 57.5 - 86.3 Pass 1.04 SPW-877 3/31/2020 Ra-228 13.0 +/- 2.0 14.9 10.4 - 19.3 Pass 0.88 SPW-925 3/23/2020 Ra-226 10.7 +/- 0.4 12.3 8.6 - 16.0 Pass 0.87 SPW-859 3/27/2020 H-3 2,065 +/- 153 2,110 1,688 - 2,532 Pass 0.98 W-040320 4/29/2016 Cs-134 38.1 +/- 10.3 36.2 29.0 - 43.4 Pass 1.05 W-040320 4/29/2016 Cs-137 78.6 +/- 7.5 71.9 57.5 - 86.3 Pass 1.09 SPDW-1009 4/8/2020 Gr. Alpha 11.5 +/- 0.9 18.7 9.4 - 28.1 Pass 0.61 SPDW-1009 4/8/2020 Gr. Beta 22.0 +/- 1.0 26.1 20.9 - 31.3 Pass 0.84 SPW-1033 4/9/2020 H-3 2,041 +/- 153 2,110 1,688 - 2,532 Pass 0.97 W-040920 4/29/2016 Cs-134 34.3 +/- 9.4 36.2 29.0 - 43.4 Pass 0.95 W-040920 4/29/2016 Cs-137 77.9 +/- 8.0 71.9 57.5 - 86.3 Pass 1.08 SPW-1145 4/15/2020 Ra-228 14.3 +/- 2.0 14.9 10.4 - 19.3 Pass 0.96 SPW-1186 4/17/2020 H-3 1,972 +/- 151 2,110 1,688 - 2,532 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). b Laboratory codes : W & SPW (Water), MI (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
TABLE A-4. Intralaboratory "Spiked" Samples Concentrationa Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known SPW-1284 4/24/2020 H-3 2,015 +/- 153 2,110 1,688 - 2,532 Pass 0.95 SPW-1745 4/24/2020 Ra-226 11.9 +/- 0.3 12.3 8.6 - 16.0 Pass 0.97 W-042220 4/29/2016 Cs-134 33.7 +/- 9.2 36.2 29.0 - 43.4 Pass 0.93 W-042220 4/29/2016 Cs-137 74.9 +/- 6.6 71.9 57.5 - 86.3 Pass 1.04 W-042420 4/29/2016 Cs-134 33.3 +/- 10.8 36.2 29.0 - 43.4 Pass 0.92 W-042420 4/29/2016 Cs-137 73.7 +/- 8.5 71.9 57.5 - 86.3 Pass 1.03 W-043020 4/29/2016 Cs-134 33.7 +/- 15.7 36.2 29.0 - 43.4 Pass 0.93 W-043020 4/29/2016 Cs-137 72.5 +/- 7.1 71.9 57.5 - 86.3 Pass 1.01 SPW-1327 5/1/2020 H-3 2,071 +/- 153 2,110 1,688 - 2,532 Pass 0.98 W-050520 4/29/2016 Cs-134 31.1 +/- 11.9 36.2 29.0 - 43.4 Pass 0.86 W-050520 4/29/2016 Cs-137 73.2 +/- 8.3 71.9 57.5 - 86.3 Pass 1.02 SPW-1394 5/5/2020 Sr-90 18.1 +/- 1.1 17.9 14.3 - 21.5 Pass 1.01 W-050720 4/29/2016 Cs-134 39.9 +/- 2.0 36.2 29.0 - 43.4 Pass 1.10 W-050720 4/29/2016 Cs-137 75.2 +/- 14.3 71.9 57.5 - 86.3 Pass 1.05 SPW-1500 5/18/2020 Ra-228 13.8 +/- 1.9 14.9 10.4 - 19.3 Pass 0.93 W-052020 4/29/2016 Cs-134 33.1 +/- 1.2 36.2 29.0 - 43.4 Pass 0.91 W-052020 4/29/2016 Cs-137 80.8 +/- 8.3 71.9 57.5 - 86.3 Pass 1.12 SPW-1613 5/22/2020 H-3 1,953 +/- 149 2,110 1,688 - 2,532 Pass 0.93 W-052620 4/29/2016 Cs-134 31.0 +/- 9.2 36.2 29.0 - 43.4 Pass 0.86 W-052620 4/29/2016 Cs-137 74.6 +/- 7.5 71.9 57.5 - 86.3 Pass 1.04 SPW-2061 5/21/2020 Ra-226 10.4 +/- 0.3 12.3 8.6 - 16.0 Pass 0.85 W-052620 4/29/2016 Cs-134 33.6 +/- 12.8 36.2 29.0 - 43.4 Pass 0.93 W-052620 4/29/2016 Cs-137 69.2 +/- 7.7 71.9 57.5 - 86.3 Pass 0.96 SPW-1741 5/27/2020 H-3 1,925 +/- 150 2,110 1,688 - 2,532 Pass 0.91 SPW-1824 6/3/2020 H-3 1,971 +/- 151 2,110 1,688 - 2,532 Pass 0.93 SPW-1853 6/4/2020 H-3 2,027 +/- 153 2,110 1,688 - 2,532 Pass 0.96 W-061120 4/29/2016 Cs-134 39.8 +/- 21.0 36.2 29.0 - 43.4 Pass 1.10 W-061120 4/29/2016 Cs-137 79.3 +/- 13.5 71.9 57.5 - 86.3 Pass 1.10 SPW-1982 6/12/2020 H-3 2,065 +/- 154 2,110 1,688 - 2,532 Pass 0.98 SPW-2038 6/18/2020 H-3 2,012 +/- 154 2,110 1,688 - 2,532 Pass 0.95 SPW-2116 6/25/2020 H-3 2,051 +/- 159 2,110 1,688 - 2,532 Pass 0.97 SPW-2173 7/1/2020 H-3 2,010 +/- 154 2,110 1,688 - 2,532 Pass 0.95 SPW-2328 7/10/2020 H-3 1,924 +/- 151 2,110 1,688 - 2,532 Pass 0.91 SPW-2458 7/16/2020 H-3 1,932 +/- 151 2,110 1,688 - 2,532 Pass 0.92 SPW-2556 7/27/2020 Sr-90 16.8 +/- 1.1 17.9 14.3 - 21.5 Pass 0.94 SPW-2558 7/6/2020 Gr. Alpha 29.9 +/- 2.1 58.9 29.5 - 88.4 Pass 0.51 SPW-2558 7/6/2020 Gr. Beta 20.0 +/- 1.0 21.0 16.8 - 25.2 Pass 0.95 SPW-2640 7/31/2020 H-3 1,984 +/- 154 2,110 1,688 - 2,532 Pass 0.94 SPW-2778 8/7/2020 H-3 1,936 +/- 151 2,110 1,688 - 2,532 Pass 0.92 SPW-2797 6/22/2020 Ra-226 10.4 +/- 0.3 12.3 8.6 - 16.0 Pass 0.85 SPW-2852 8/11/2020 Ra-228 10.2 +/- 1.6 12.5 8.7 - 16.2 Pass 0.82 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), MI (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-8
TABLE A-4. Intralaboratory "Spiked" Samples Concentrationa Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known SPW-2854 8/14/2020 H-3 1,927 +/- 153 2,110 1,688 - 2,532 Pass 0.91 SPW-2890 8/4/2020 Ra-226 11.6 +/- 0.4 12.3 8.6 - 16.0 Pass 0.95 SPW-3013 8/24/2020 H-3 2,005 +/- 153 2,110 1,688 - 2,532 Pass 0.95 SPW-3053 8/28/2020 H-3 1,904 +/- 149 2,110 1,688 - 2,532 Pass 0.90 SPW-3123 8/19/2020 Ra-226 10.4 +/- 0.3 12.3 8.6 - 16.0 Pass 0.85 SPW-3447 9/3/2020 Ra-226 9.8 +/- 0.3 12.3 8.6 - 16.0 Pass 0.80 SPW-3241 9/11/2020 H-3 1,952 +/- 154 2,110 1,688 - 2,532 Pass 0.93 SPW-3425 9/23/2020 Ra-228 10.7 +/- 1.6 12.3 8.6 - 16.0 Pass 0.87 SPW-3412 9/25/2020 H-3 2,099 +/- 155 2,110 1,688 - 2,532 Pass 0.99 SPW-4131 9/30/2020 Ra-226 13.2 +/- 0.4 12.3 8.6 - 16.0 Pass 1.07 SPW-3482 10/2/2020 H-3 1,984 +/- 154 2,110 1,688 - 2,532 Pass 0.94 SPW-3624 10/9/2020 H-3 1,924 +/- 152 2,110 1,688 - 2,532 Pass 0.91 SPW-3794 10/16/2020 H-3 2,109 +/- 156 2,110 1,688 - 2,532 Pass 1.00 SPW-3836 10/20/2020 Sr-90 16.8 +/- 1.1 17.9 14.3 - 21.5 Pass 0.94 SPW-4043 10/23/2020 H-3 1893.4 +/- 148.8 2,110 1,688 - 2,532 Pass 0.90 SPW-4179 10/28/2020 Ra-228 15.4 +/- 2.4 12.1 8.5 - 15.7 Pass 1.27 SPW-4422 10/30/2020 Ra-226 12.3 +/- 0.3 12.3 8.6 - 16.0 Pass 1.00 SPW-4234 11/11/2020 H-3 2,008 +/- 154 2,110 1,688 - 2,532 Pass 0.95 SPW-4634 11/23/2020 Ra-226 11.4 +/- 0.3 12.3 8.6 - 16.0 Pass 0.93 SPW-4509 12/4/2020 H-3 1,873 +/- 149 2,110 1,688 - 2,532 Pass 0.89 SPW-4625 12/18/2020 H-3 1,940 +/- 152 2,110 1,688 - 2,532 Pass 0.92 SPW-4741 12/18/2020 Ra-226 12.5 +/- 0.4 12.3 8.6 - 16.0 Pass 1.02 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), MI (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-9
TABLE A-5. Intralaboratory "Blank" Samples Concentrationa b c Lab Code Sample Date Analysis Laboratory results (4.66V) Acceptance Type LLD Activityd Criteria (4.66 V) SPW-480 Water 1/1/2020 Ra-226 0.03 0.12 +/- 0.02 2 SPW-93 Water 1/7/2020 Gr. Alpha 0.35 0.47 +/- 0.29 2 SPW-93 Water 1/7/2020 Gr. Beta 0.74 0.18 +/- 0.53 4 SPW-109 Water 1/16/2020 H-3 157 -6 +/- 73 200 SPW-154 Water 1/16/2020 I-131 0.47 -0.22 +/- 0.21 1 SPW-189 Water 1/23/2020 H-3 158 0 +/- 73 200 SPW-204 Water 1/28/2020 Sr-89 0.64 -0.16 +/- 0.50 5 SPW-204 Water 1/28/2020 Sr-90 0.54 0.11 +/- 0.27 1 SPW-216 Water 1/31/2020 H-3 156 86 +/- 78 200 SPW-269 Water 2/7/2020 H-3 153 79 +/- 80 200 SPW-287 Water 2/11/2020 Ra-228 0.81 1.49 +/- 0.53 2 SPW-395 Water 2/14/2020 H-3 154 46 +/- 75 200 SPW-463 Water 2/25/2020 I-131 0.16 0.02 +/- 0.09 1 SPW-715 Water 2/26/2020 Ra-226 0.01 0.17 +/- 0.01 2 SPW-531 Water 2/28/2020 H-3 156 44 +/- 75 200 SPW-710 Water 3/12/2020 H-3 157 -16 +/- 72 200 SPW-824 Water 3/12/2020 Ra-226 0.03 0.15 +/- 0.03 2 SPW-773 Water 3/18/2020 H-3 151 76 +/- 76 200 SPW-876 Water 3/31/2020 Ra-228 0.88 0.57 +/- 0.47 2 SPW-924 Water 3/23/2020 Ra-226 0.04 0.18 +/- 0.03 2 SPW-1032 Water 4/9/2020 H-3 157 68 +/- 77 200 SPW-1144 Water 4/15/2020 Ra-228 0.89 0.03 +/- 0.42 2 SPW-1185 Water 4/17/2020 H-3 158 8 +/- 74 200 SPW-1283 Water 4/24/2020 H-3 156 10 +/- 75 200 SPW-1744 Water 4/24/2020 Ra-226 0.03 -0.01 +/- 0.03 2 SPW-1326 Water 5/1/2020 H-3 153 67 +/- 75 200 SPW-1393 Water 5/5/2020 Sr-89 0.66 0.11 +/- 0.44 5 SPW-1393 Water 5/5/2020 Sr-90 0.63 -0.27 +/- 0.26 1 SPW-1499 Water 5/18/2020 Ra-228 0.88 0.03 +/- 0.41 2 SPW-1541 Water 5/19/2020 I-131 0.20 0.00 +/- 0.11 1 SPW-2060 Water 5/21/2020 Ra-226 0.03 -0.01 +/- 0.02 2 SPW-1612 Water 5/22/2020 H-3 153 91 +/- 76 200 SPW-1740 Water 5/27/2020 H-3 158 -26 +/- 71 200 SPW-1823 Water 6/3/2020 H-3 157 18 +/- 74 200 SPW-1852 Water 6/4/2020 H-3 159 33 +/- 76 200 SPW-1981 Water 6/12/2020 H-3 149 52 +/- 77 200 SPW-2037 Water 6/18/2020 H-3 156 101 +/- 81 200 SPW-2115 Water 6/25/2020 H-3 158 56 +/- 86 200 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m 3), charcoal (pCi/charcoal canister), and solid samples (pCi/g). b Laboratory codes : W & SPW (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine). c I-131(G); iodine-131 as analyzed by gamma spectroscopy. d Activity reported is a net activity result. A-10
TABLE A-5. Intralaboratory "Blank" Samples Concentrationa b c Lab Code Sample Date Analysis Laboratory results (4.66V) Acceptance Type LLD Activityd Criteria (4.66 V) SPW-2172 Water 7/1/2020 H-3 159 -15 +/- 75 200 SPW-2327 Water 7/10/2020 H-3 158 50 +/- 77 200 SPW-2457 Water 7/16/2020 H-3 159 -46 +/- 71 200 SPW-2555 Water 7/27/2020 Sr-89 0.48 0.18 +/- 0.40 5 SPW-2555 Water 7/27/2020 Sr-90 0.54 0.03 +/- 0.25 1 SPW-2557 Water 7/6/2020 Gr. Alpha 0.37 0.25 +/- 0.28 2 SPW-2557 Water 7/6/2020 Gr. Beta 0.75 -0.23 +/- 0.52 4 SPW-2639 Water 7/31/2020 H-3 158 80 +/- 81 200 SPW-2777 Water 8/7/2020 H-3 157 0 +/- 74 200 SPW-2796 Water 6/22/2020 Ra-226 0.03 -0.02 +/- 0.03 2 SPW-2851 Water 8/11/2020 Ra-228 0.85 0.44 +/- 0.45 2 SPW-2853 Water 8/14/2020 H-3 158 18 +/- 77 200 SPW-2880 Water 8/18/2020 I-131 0.42 -0.04 +/- 0.22 1 SPW-2889 Water 8/4/2020 Ra-228 0.05 0.13 +/- 0.11 2 SPW-3012 Water 8/24/2020 H-3 159 59 +/- 77 200 SPW-3052 Water 8/28/2020 H-3 155 46 +/- 75 200 SPW-3122 Water 9/3/2020 Ra-226 0.03 0.20 +/- 0.03 2 SPW-3240 Water 9/11/2020 H-3 161 3 +/- 78 200 SPW-3446 Water 9/3/2020 Ra-226 0.01 0.12 +/- 0.02 2 SPW-3424 Water 9/23/2020 Ra-228 0.85 0.81 +/- 0.48 2 SPW-3411 Water 9/25/2020 H-3 158 82 +/- 78 200 SPW-4130 Water 9/30/2020 Ra-226 0.04 0.01 +/- 0.04 2 SPW-3481 Water 10/2/2020 H-3 154 63 +/- 80 200 SPW-3623 Water 10/9/2020 H-3 156 57 +/- 81 200 SPW-3793 Water 10/16/2020 H-3 157 3 +/- 73 200 SPW-3835 Water 10/20/2020 Sr-89 0.55 -0.10 +/- 0.43 5 SPW-3835 Water 10/20/2020 Sr-90 0.59 0.09 +/- 0.28 1 SPW-4042 Water 10/23/2020 H-3 155 -6 +/- 72 200 SPW-4178 Water 10/28/2020 Ra-228 1.04 0.33 +/- 0.52 2 SPW-4421 Water 10/30/2020 Ra-226 0.03 0.07 +/- 0.03 2 SPW-4233 Water 11/11/2020 H-3 155 78 +/- 79 200 SPW-4356 Water 11/20/2020 H-3 157 52 +/- 76 200 SPW-4633 Water 11/23/2020 Ra-226 0.05 0.04 +/- 0.11 2 SPW-4508 Water 12/4/2020 H-3 159 -68 +/- 69 200 SPW-4624 Water 12/18/2020 H-3 160 8 +/- 77 200 SPW-4740 Water 12/18/2020 Ra-226 0.04 0.02 +/- 0.03 2 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m 3), charcoal (pCi/charcoal canister), and solid samples (pCi/g). b Laboratory codes : W & SPW (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine). c I-131(G); iodine-131 as analyzed by gamma spectroscopy. d Activity reported is a net activity result. A-11
TABLE A-6. Intralaboratory "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance SG-20,21 1/2/2020 Pb-214 2.23 +/- 0.12 1.61 +/- 0.09 1.92 +/- 0.08 Pass SG-20,21 1/2/2020 Ac-228 1.49 +/- 0.20 1.42 +/- 0.18 1.46 +/- 0.13 Pass AP-5060,5061 1/3/2020 Be-7 0.052 +/- 0.014 0.063 +/- 0.012 0.057 +/- 0.009 Pass AP-010720A,B 1/7/2020 Gr. Beta 0.023 +/- 0.004 0.022 +/- 0.004 0.022 +/- 0.003 Pass WW-72,73 1/7/2020 H-3 547 +/- 101 478 +/- 98 513 +/- 70 Pass WW-184,185 1/21/2020 H-3 265 +/- 88 311 +/- 90 288 +/- 63 Pass SWU-253,254 1/28/2020 Gr. Beta 1.73 +/- 0.58 2.10 +/- 0.62 1.92 +/- 0.42 Pass DW-20014,20015 1/29/2020 Ra-228 3.34 +/- 0.74 2.25 +/- 0.70 2.80 +/- 0.51 Pass DW-20014,20015 1/29/2020 Ra-226 1.05 +/- 0.15 0.64 +/- 0.24 0.85 +/- 0.14 Pass S-209,210 1/31/2020 K-40 8.28 +/- 0.20 7.95 +/- 0.42 8.12 +/- 0.23 Pass LW-383,384 1/31/2020 Gr. Beta 1.67 +/- 0.58 0.77 +/- 0.52 1.22 +/- 0.39 Pass AP-020320A,B 2/3/2020 Gr. Beta 0.021 +/- 0.004 0.024 +/- 0.004 0.023 +/- 0.003 Pass S-362,363 2/7/2020 Pb-214 2.39 +/- 0.11 2.25 +/- 0.10 2.32 +/- 0.07 Pass S-362,363 2/7/2020 Ac-228 1.84 +/- 0.18 1.95 +/- 0.17 1.90 +/- 0.12 Pass DW-20018,20019 2/7/2020 Gr. Alpha 0.23 +/- 0.86 0.37 +/- 0.88 0.30 +/- 0.62 Pass DW-20018,20019 2/7/2020 Gr. Beta 0.50 +/- 0.56 1.19 +/- 0.63 0.85 +/- 0.42 Pass DW-20026,20027 2/7/2020 Ra-226 2.40 +/- 0.21 2.11 +/- 0.15 2.26 +/- 0.13 Pass DW-20026,20027 2/7/2020 Ra-228 2.60 +/- 0.68 1.81 +/- 0.57 2.21 +/- 0.44 Pass WW-452,453 2/17/2020 H-3 583 +/- 102 678 +/- 106 630 +/- 74 Pass DW-20031,20032 2/25/2020 Gr. Alpha 1.02 +/- 0.77 0.80 +/- 0.81 0.91 +/- 0.56 Pass DW-20031,20032 2/25/2020 Gr. Beta 1.11 +/- 0.59 1.19 +/- 0.58 1.15 +/- 0.41 Pass DW-20038,20039 3/3/2020 Ra-226 8.39 +/- 0.43 8.78 +/- 0.49 8.59 +/- 0.33 Pass DW-20038,20039 3/3/2020 Ra-228 2.81 +/- 1.00 2.31 +/- 0.86 2.56 +/- 0.66 Pass WW-752,753 3/13/2020 H-3 435 +/- 94 393 +/- 92 414 +/- 66 Pass S-868,869 3/13/2020 Pb-214 0.97 +/- 0.10 0.99 +/- 0.09 0.98 +/- 0.07 Pass S-868,869 3/13/2020 Ac-228 0.93 +/- 0.18 1.01 +/- 0.23 0.97 +/- 0.15 Pass LW-977,978 3/25/2020 Gr. Beta 0.98 +/- 0.53 0.92 +/- 0.51 0.95 +/- 0.37 Pass AP-1220,1221 3/31/2020 Be-7 0.063 +/- 0.011 0.062 +/- 0.013 0.063 +/- 0.009 Pass SWT-912,913 3/31/2020 Gr. Beta 0.79 +/- 0.53 0.49 +/- 0.50 0.64 +/- 0.37 Pass AP-956,957 4/2/2020 Be-7 0.189 +/- 0.097 0.256 +/- 0.130 0.222 +/- 0.081 Pass AP-1110,1111 4/3/2020 Be-7 0.069 +/- 0.012 0.072 +/- 0.013 0.071 +/- 0.009 Pass WW-1047,1048 4/7/2020 H-3 438 +/- 96 478 +/- 98 458 +/- 69 Pass VE-1022,1023 4/8/2020 Be-7 9.28 +/- 0.57 8.00 +/- 0.62 8.64 +/- 0.42 Pass VE-1022,1023 4/8/2020 K-40 3.89 +/- 0.67 3.94 +/- 0.73 3.92 +/- 0.49 Pass S-1199,1200 4/12/2020 Pb-214 0.77 +/- 0.07 0.98 +/- 0.08 0.88 +/- 0.05 Pass S-1199,1200 4/12/2020 Ac-228 1.09 +/- 0.15 1.18 +/- 0.17 1.14 +/- 0.11 Pass SS-1419,1420 4/14/2020 K-40 10.8 +/- 0.6 9.4 +/- 0.4 10.1 +/- 0.4 Pass AP-1241,1242 4/16/2020 Be-7 0.203 +/- 0.113 0.245 +/- 0.145 0.224 +/- 0.092 Pass DW-20051,20052 4/23/2020 Ra-228 3.50 +/- 0.85 4.60 +/- 0.89 4.05 +/- 0.62 Pass DW-20051,20052 4/23/2020 Ra-226 0.80 +/- 0.10 0.60 +/- 0.10 0.70 +/- 0.07 Pass SS-1310,1311 4/23/2020 K-40 7,827 +/- 492 8,157 +/- 505 7,992 +/- 352 Pass LW-1375,1376 4/29/2020 Gr. Beta 1.62 +/- 0.59 1.61 +/- 0.58 1.62 +/- 0.41 Pass A-12
TABLE A-6. Intralaboratory "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance F-1828,1829 4/29/2020 K-40 1.35 +/- 0.41 0.98 +/- 0.33 1.16 +/- 0.27 Pass SG-1398,1399 5/5/2020 Pb-214 7.51 +/- 0.19 8.62 +/- 0.17 8.07 +/- 0.13 Pass SG-1398,1399 5/5/2020 Ac-228 6.80 +/- 0.31 6.77 +/- 0.27 6.79 +/- 0.21 Pass SW-1461,1462 5/7/2020 H-3 315 +/- 88 320 +/- 89 317 +/- 63 Pass AP-1610,1611 5/14/2020 Be-7 0.179 +/- 0.101 0.172 +/- 0.086 0.176 +/- 0.066 Pass DW-20062,20063 5/19/2020 Gr. Alpha 6.20 +/- 1.30 5.00 +/- 1.30 5.60 +/- 0.92 Pass DW-20062,20063 5/19/2020 Gr. Beta 6.09 +/- 0.77 5.51 +/- 0.72 5.80 +/- 0.53 Pass W-1805,1806 5/25/2020 Ra-226 0.42 +/- 0.16 0.24 +/- 0.17 0.33 +/- 0.12 Pass F-1763,1764 5/26/2020 K-40 2.82 +/- 0.47 3.01 +/- 0.45 2.92 +/- 0.33 Pass AP-052620A,B 5/26/2020 Gr. Beta 0.014 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.002 Pass DW-20066,20067 6/1/2020 Ra-226 0.21 +/- 0.09 0.33 +/- 0.12 0.27 +/- 0.08 Pass DW-20066,20067 6/1/2020 Ra-228 0.05 +/- 0.43 0.03 +/- 0.39 0.04 +/- 0.29 Pass P-1849,1850 6/1/2020 H-3 547 +/- 102 700 +/- 108 624 +/- 74 Pass AP-1893,1894 6/4/2020 Be-7 0.164 +/- 0.080 0.251 +/- 0.140 0.208 +/- 0.081 Pass SW-1872,1873 6/4/2020 H-3 385 +/- 94 400 +/- 95 393 +/- 67 Pass AP-052620A,B 6/8/2020 Gr. Beta 0.024 +/- 0.004 0.025 +/- 0.005 0.024 +/- 0.003 Pass WW-2025,2026 6/16/2020 H-3 318 +/- 92 320 +/- 92 319 +/- 65 Pass AP-061620A,B 6/16/2020 Gr. Beta 0.017 +/- 0.003 0.019 +/- 0.003 0.018 +/- 0.002 Pass DW-20078,20079 6/17/2020 Ra-226 0.53 +/- 0.11 0.50 +/- 0.10 0.52 +/- 0.07 Pass DW-20078,20079 6/17/2020 Ra-228 1.10 +/- 0.50 1.11 +/- 0.50 1.11 +/- 0.35 Pass AP-2048,2049 6/18/2020 Be-7 0.222 +/- 0.087 0.221 +/- 0.092 0.221 +/- 0.063 Pass SW-2157,2158 6/23/2020 H-3 175 +/- 86 235 +/- 89 205 +/- 62 Pass AP-062320A,B 6/23/2020 Gr. Beta 0.021 +/- 0.003 0.023 +/- 0.004 0.022 +/- 0.003 Pass AP-2136,2137 6/25/2020 Be-7 0.242 +/- 0.099 0.343 +/- 0.115 0.292 +/- 0.076 Pass AP-2366,2367 6/30/2020 Be-7 0.144 +/- 0.018 0.177 +/- 0.019 0.161 +/- 0.013 Pass SWU-2180,2181 6/30/2020 H-3 105 +/- 82 199 +/- 87 152 +/- 60 Pass AP-2473,2474 7/1/2020 Be-7 0.079 +/- 0.011 0.089 +/- 0.012 0.084 +/- 0.008 Pass AP-2473,2474 7/1/2020 K-40 0.010 +/- 0.006 0.015 +/- 0.009 0.013 +/- 0.005 Pass AP-2408,2409 7/2/2020 Be-7 0.084 +/- 0.016 0.085 +/- 0.014 0.085 +/- 0.011 Pass P-2264,2265 7/6/2020 H-3 149 +/- 83 144 +/- 83 147 +/- 59 Pass DW-20091,20092 7/10/2020 Ra-226 0.77 +/- 0.17 0.69 +/- 0.24 0.73 +/- 0.15 Pass DW-20091,20092 7/10/2020 Ra-228 0.61 +/- 0.56 0.59 +/- 0.55 0.60 +/- 0.39 Pass SW-2450,2451 7/14/2020 H-3 410 +/- 96 487 +/- 99 448 +/- 69 Pass VE-2494,2495 7/16/2020 K-40 1.68 +/- 0.25 2.08 +/- 0.26 1.88 +/- 0.18 Pass DW-20102,20103 7/17/2020 Gr. Alpha 1.98 +/- 0.82 2.65 +/- 0.82 2.32 +/- 0.58 Pass DW-20102,20103 7/17/2020 Ra-226 0.84 +/- 0.20 0.89 +/- 0.20 0.87 +/- 0.14 Pass DW-20102,20103 7/17/2020 Ra-228 1.24 +/- 0.67 1.57 +/- 0.70 1.41 +/- 0.48 Pass WW-2604,2605 7/20/2020 H-3 35,989 +/- 576 36,039 +/- 577 36,014 +/- 408 Pass SWU-2669,2670 7/28/2020 H-3 103 +/- 80 101 +/- 80 102 +/- 57 Pass SWU-2669,2670 7/28/2020 Gr. Beta 1.49 +/- 0.56 1.05 +/- 0.51 1.27 +/- 0.38 Pass S-2711,2712 7/29/2020 K-40 17.4 +/- 0.9 19.6 +/- 1.0 18.5 +/- 0.7 Pass A-13
TABLE A-6. Intralaboratory "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance WW-2799,2800 8/4/2020 H-3 471 +/- 100 437 +/- 99 454 +/- 70 Pass WW-2933,2934 8/4/2020 H-3 316 +/- 91 300 +/- 90 308 +/- 64 Pass S-2774,2775 8/4/2020 K-40 5.9 +/- 0.9 6.1 +/- 0.8 6.0 +/- 0.6 Pass WW-2912,2913 8/5/2020 H-3 176 +/- 84 226 +/- 87 201 +/- 60 Pass F-3040,3041 8/7/2020 Gr. Beta 4.55 +/- 0.12 4.63 +/- 0.12 4.59 +/- 0.09 Pass F-3040,3041 8/7/2020 K-40 3.58 +/- 0.42 3.32 +/- 0.41 3.45 +/- 0.29 Pass WW-2867,2868 8/12/2020 H-3 169 +/- 85 219 +/- 86 194 +/- 61 Pass VE-2842,2843 8/12/2020 K-40 3.18 +/- 0.30 3.14 +/- 0.37 3.16 +/- 0.24 Pass F-2891,2892 8/14/2020 K-40 2.98 +/- 0.39 2.82 +/- 0.35 2.90 +/- 0.26 Pass VE-2954,2955 8/20/2020 Be-7 0.222 +/- 0.106 0.283 +/- 0.166 0.252 +/- 0.099 Pass VE-2954,2955 8/20/2020 K-40 4.09 +/- 0.37 3.75 +/- 0.38 3.92 +/- 0.27 Pass DW-20126,20127 8/25/2020 Ra-226 0.90 +/- 0.14 0.73 +/- 0.12 0.82 +/- 0.09 Pass DW-20126,20127 8/25/2020 Ra-228 1.55 +/- 0.52 2.30 +/- 0.58 1.93 +/- 0.39 Pass LW-3154,3155 8/26/2020 Gr. Beta 1.43 +/- 0.60 1.33 +/- 0.55 1.38 +/- 0.41 Pass VE-3084,3085 8/28/2020 Be-7 0.52 +/- 0.12 0.48 +/- 0.07 0.50 +/- 0.07 Pass VE-3084,3085 8/28/2020 K-40 3.87 +/- 0.16 3.36 +/- 0.31 3.62 +/- 0.17 Pass SWU-3133,3134 9/1/2020 H-3 107 +/- 84 116 +/- 84 111 +/- 59 Pass VE-3208,3209 9/8/2020 K-40 5.99 +/- 0.43 5.85 +/- 0.35 5.92 +/- 0.28 Pass VE-3187,3188 9/8/2020 Be-7 0.50 +/- 0.17 0.61 +/- 0.23 0.55 +/- 0.14 Pass VE-3187,3188 9/8/2020 K-40 4.64 +/- 0.54 4.97 +/- 0.45 4.81 +/- 0.35 Pass WW-3427,3428 9/10/2020 H-3 2,321 +/- 163 2,323 +/- 164 2,322 +/- 116 Pass DW-21033,21034 9/14/2020 Gr. Alpha 1.27 +/- 0.79 0.94 +/- 0.75 1.11 +/- 0.54 Pass DW-21033,21034 9/14/2020 Gr. Beta 1.02 +/- 0.60 1.01 +/- 0.59 1.02 +/- 0.42 Pass SG-3265,3266 9/14/2020 Pb-214 11.8 +/- 0.49 10.4 +/- 0.57 11.1 +/- 0.38 Pass SG-3265,3266 9/14/2020 Ac-228 18.8 +/- 1.27 17.3 +/- 1.36 18.0 +/- 0.93 Pass SG-3265,3266 9/14/2020 Gr. Alpha 28.0 +/- 4.6 33.5 +/- 4.9 30.8 +/- 3.4 Pass SG-3265,3266 9/14/2020 Gr. Beta 42.1 +/- 2.8 44.5 +/- 3.0 43.3 +/- 2.1 Pass VE-3315,3316 9/15/2020 Be-7 0.25 +/- 0.10 0.28 +/- 0.16 0.27 +/- 0.09 Pass VE-3315,3316 9/15/2020 K-40 5.48 +/- 0.34 5.16 +/- 0.36 5.32 +/- 0.25 Pass WW-3339,3340 9/16/2020 H-3 196 +/- 85 199 +/- 85 198 +/- 60 Pass CF-3381,3382 9/21/2020 Be-7 0.20 +/- 0.10 0.19 +/- 0.11 0.20 +/- 0.07 Pass CF-3381,3382 9/21/2020 K-40 5.94 +/- 0.30 5.72 +/- 0.29 5.83 +/- 0.21 Pass AP-092120A,B 9/21/2020 Gr. Beta 0.043 +/- 0.005 0.041 +/- 0.005 0.042 +/- 0.004 Pass F-3706,3707 9/26/2020 K-40 1.86 +/- 0.35 1.83 +/- 0.39 1.84 +/- 0.26 Pass AP-092820A,B 9/28/2020 Gr. Beta 0.021 +/- 0.004 0.023 +/- 0.004 0.022 +/- 0.003 Pass XW-3620,3621 9/30/2020 Sr-89 11,760 +/- 140 12,487 +/- 133 12,124 +/- 97 Pass XW-3620,3621 9/30/2020 Sr-90 2,287 +/- 45 2,831 +/- 50 2,559 +/- 34 Pass XW-3620,3621 9/30/2020 Fe-55 1,623 +/- 462 1,833 +/- 474 1,728 +/- 331 Pass A-14
TABLE A-6. Intralaboratory "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance SW-3515,3516 10/1/2020 H-3 154 +/- 86 111 +/- 84 133 +/- 60 Pass DW-20141,20142 10/1/2020 Ra-226 1.34 +/- 0.16 1.39 +/- 0.16 1.37 +/- 0.11 Pass DW-20141,20142 10/1/2020 Ra-228 1.74 +/- 0.62 2.09 +/- 0.64 1.92 +/- 0.45 Pass SW-3536,3537 10/5/2020 H-3 376 +/- 97 378 +/- 97 377 +/- 68 Pass WW-3727,3728 10/8/2020 H-3 152 +/- 82 190 +/- 84 171 +/- 59 Pass VE-3748,3749 10/12/2020 K-40 3.07 +/- 0.25 2.88 +/- 0.26 2.98 +/- 0.18 Pass VE-3769,3770 10/12/2020 Be-7 0.80 +/- 0.31 0.51 +/- 0.15 0.66 +/- 0.17 Pass VE-3769,3770 10/12/2020 K-40 5.69 +/- 0.61 5.79 +/- 0.39 5.74 +/- 0.36 Pass WW-4092,4093 10/13/2020 H-3 6,484 +/- 252 6,275 +/- 248 6,380 +/- 177 Pass WW-3838,3839 10/14/2020 H-3 313 +/- 90 263 +/- 88 288 +/- 63 Pass WW-4394,4395 11/3/2020 H-3 161 +/- 83 199 +/- 85 180 +/- 60 Pass WW-4587,4588 11/4/2020 H-3 6,468 +/- 252 6,638 +/- 255 6,553 +/- 179 Pass WW-4524,4525 11/5/2020 H-3 160 +/- 86 131 +/- 84 145 +/- 60 Pass VE-4415,4416 11/24/2020 Be-7 0.28 +/- 0.08 0.22 +/- 0.07 0.25 +/- 0.05 Pass VE-4415,4416 11/24/2020 K-40 2.25 +/- 0.21 2.20 +/- 0.19 2.23 +/- 0.14 Pass AP-4845,4846 12/31/2020 Be-7 0.07 +/- 0.01 0.06 +/- 0.02 0.06 +/- 0.01 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/m3), food products, vegetation, soil and sediment (pCi/g). b AP (Air Particulate), AV (Aquatic Vegetation), BS (Bottom Sediment), CF (Cattle Feed), CH (Charcoal Canister), DW (Drinking Water), E (Egg), F (Fish), G (Grass), LW (Lake Water), MI (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), VE (Vegetation), W (Water), WW (Well Water). A-15
TABLE A-7. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentrationa Reference Known Control b Lab Code Date Analysis Laboratory result Activity Limits c Acceptance MAAP-664 2/1/2020 Gross Alpha 2.26 +/- 0.14 1.24 0.37 - 2.11 Fail d MAAP-664 2/1/2020 Gross Beta 2.40 +/- 0.07 2.00 1.00 - 3.00 Pass MAW-536 2/1/2020 Gross Alpha 0.86 +/- 0.06 1.03 0.31 - 1.75 Pass MAW-536 2/1/2020 Gross Beta 3.79 +/- 0.07 4.24 2.12 - 6.36 Pass MASO-662 2/1/2020 Cs-134 955 +/-9 1114 780 - 1448 Pass MASO-662 2/1/2020 Cs-137 1089 +/- 12 1020 714 - 1326 Pass MASO-662 2/1/2020 Co-57 1106 +/-8 1071 750 - 1392 Pass MASO-662 2/1/2020 Co-60 0.33 +/- 1.26 0 NA c Pass MASO-662 2/1/2020 Mn-54 1022 +/- 27 945 662 - 1229 Pass MASO-662 2/1/2020 Zn-65 842 +/- 17 751 526 - 976 Pass MASO-662 2/1/2020 K-40 710 +/- 42 625 438 - 813 Pass MAW-534 2/1/2020 I-129 0.81 +/- 0.09 1.001 0.701 - 1.301 Pass MAW-599 2/1/2020 H-3 202 +/-9 196 137 - 255 Pass MAW-599 2/1/2020 Am-241 0.41 +/- 0.09 0.547 0.383 - 0.711 Pass MAW-599 2/1/2020 Cs-134 16.1 +/- 0.3 18.5 13.0 - 24.1 Pass MAW-599 2/1/2020 Cs-137 11.5 +/- 0.4 11.3 7.9 - 14.7 Pass MAW-599 2/1/2020 Co-57 20.0 +/- 0.30 19.7 13.8 - 25.6 Pass MAW-599 2/1/2020 Co-60 10.6 +/- 0.2 10.6 7.4 - 13.8 Pass MAW-599 2/1/2020 Mn-54 20.5 +/- 0.4 19.6 13.7 - 25.5 Pass MAW-599 2/1/2020 Zn-65 24.1 +/- 0.70 22.2 15.5 - 28.9 Pass MAW-599 2/1/2020 K-40 0.57 +/- 1.54 0 NA c Pass MAW-599 2/1/2020 Fe-55 13.3 +/- 12.2 17.8 12.5 - 23.1 Pass MAW-599 2/1/2020 Ni-63 9.72 +/- 0.43 11.1 7.8 - 14.4 Pass MAW-599 2/1/2020 Sr-90 0.07 +/- 0.18 0 NA c Pass MAW-599 2/1/2020 Tc-99 3.41 +/- 0.31 3.63 2.54 - 4.72 Pass MAW-599 2/1/2020 Ra-226 0.56 +/- 0.06 0.365 0.256 - 0.475 Fail e MAW-599 2/1/2020 Pu-238 0.69 +/- 0.08 0.94 0.66 - 1.22 Pass MAW-599 2/1/2020 Pu-239/240 0.48 +/- 0.07 0.737 0.516 - 0.958 Fail f MAW-599 2/1/2020 U-234 1.04 +/- 0.08 0.97 0.68 - 1.26 Pass MAW-599 2/1/2020 U-238 1.02 +/- 0.08 0.95 0.67 - 1.24 Pass A-16
TABLE A-7. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentrationa Reference Known Control b Lab Code Date Analysis Laboratory result Activity Limits c Acceptance MAVE-668 2/1/2020 Cs-134 3.51 +/- 0.22 3.82 2.67 - 4.97 Pass MAVE-668 2/1/2020 Cs-137 3.04 +/- 0.18 2.77 1.94 - 3.60 Pass c MAVE-668 2/1/2020 Co-57 0.02 +/- 0.03 0 NA Pass MAVE-668 2/1/2020 Co-60 2.92 +/- 0.08 2.79 1.95 - 3.63 Pass MAVE-668 2/1/2020 Mn-54 5.16 +/- 0.14 4.58 3.21 - 5.95 Pass MAVE-668 2/1/2020 Zn-65 4.36 +/- 0.16 3.79 2.65 - 4.93 Pass MAW-689 2/1/2020 Ra-226 172 +/- 1 189 132 - 246 Pass MAW-689 2/1/2020 Ra-228 65 +/- 1 75 53 - 98 Pass MAAP-3181 8/1/2020 Gross Alpha 0.45 +/- 0.06 0.528 0.158 - 0.898 Pass MAAP-3181 8/1/2020 Gross Beta 0.97 +/- 0.04 0.915 0.458 - 1.373 Pass MADW-3101 8/1/2020 Gross Alpha 0.57 +/- 0.04 0.62 0.19 - 1.05 Pass MADW-3101 8/1/2020 Gross Beta 0.75 +/- 0.04 0.83 0.42 - 1.25 Pass MASO-3179 8/1/2020 Cs-134 599 +/-7 710 497 - 923 Pass MASO-3179 8/1/2020 Cs-137 3.33 +/- 4.81 0 NA c Pass MASO-3179 8/1/2020 Co-57 1145 +/-8 1100 770 - 1430 Pass MASO-3179 8/1/2020 Co-60 965 +/-9 1000 700 - 1300 Pass MASO-3179 8/1/2020 Mn-54 651 +/- 11 610 427 - 793 Pass MASO-3179 8/1/2020 Zn-65 524 +/- 14 470 329 - 611 Pass MASO-3179 8/1/2020 K-40 684 +/- 58 622 435 - 809 Pass MAW-3175 8/1/2020 Cs-134 13.9 +/- 0.3 15.2 10.6 - 19.8 Pass MAW-3175 8/1/2020 Cs-137 15.4 +/- 0.4 14.3 10.0 - 18.6 Pass MAW-3175 8/1/2020 Co-57 0.10 +/- 0.16 0 NA c Pass MAW-3175 8/1/2020 Co-60 12.5 +/- 0.3 12.2 8.5 - 15.9 Pass MAW-3175 8/1/2020 Mn-54 0.07 +/- 0.17 0 NA c Pass MAW-3175 8/1/2020 Zn-65 18.3 +/- 0.6 16.9 11.8 - 22.0 Pass MAW-3175 8/1/2020 K-40 1.06 +/- 1.65 0 NA c Pass A-17
TABLE A-7. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentrationa Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-3177 8/1/2020 Cs-134 1.28 +/- 0.05 1.83 1.28 - 2.38 Failg MAAP-3177 8/1/2020 Cs-137 0.981 +/- 0.068 0.996 0.697 - 1.295 Pass MAAP-3177 8/1/2020 Co-57 0.020 +/- 0.027 0 NA c Pass MAAP-3177 8/1/2020 Co-60 1.57 +/- 0.06 1.73 1.21 - 2.25 Pass MAAP-3177 8/1/2020 Mn-54 0.751 +/- 0.077 1.400 0.98 - 1.82 Failh MAAP-3177 8/1/2020 Zn-65 2.07 +/- 0.15 2.00 1.40 - 2.60 Pass MAVE-3185 8/1/2020 Cs-134 4.73 +/- 0.10 4.94 3.46 - 6.42 Pass MAVE-3185 8/1/2020 Cs-137 0.03 +/- 0.06 0 NA c Pass MAVE-3185 8/1/2020 Co-57 7.83 +/- 0.12 6.67 4.67 - 8.67 Pass MAVE-3185 8/1/2020 Co-60 4.41 +/- 0.10 4.13 2.89 - 5.37 Pass MAVE-3185 8/1/2020 Mn-54 6.52 +/- 0.18 5.84 4.09 - 7.59 Pass MAVE-3185 8/1/2020 Zn-65 7.26 +/- 0.19 6.38 4.47 - 8.29 Pass a Results are reported in units of Bq/kg (soil), 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 The lab utilized a MAPEP specific gross alpha/beta filter calibration as discussed in the MAPEP test instructions for MAAP-664. Using the MAPEP specific calibration for MAAP-664 caused the bias to shift from low to high. The subsequent MAPEP study result was acceptable. See Lab code MAAP-3101 (reference date 8/1/2020). e An investigation of the Radium-226 failure was inconclusive. Subsequent Ra-226 PT analyses were satisifactory. See ERA RAD-121 and RAD-122 studies Table A-1 and NY ELAP shipment 437R Table A-2. f Analysis was repeated in duplicate with acceptable results: Pu-238 (0.97 & 1.10 Bq/Kg); Pu-239 (0.83 & 0.83 Bq/Kg). The cause of the failure could not be determined. g Lab result barely missed lower contol limit. h A data transcription error resulted in an erroneous reported value. The actual result (1.36 +/- 0.08 Bq/L) passes. A-18
TABLE A-8. Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) a. MRAD-30 Study Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Value c Limits d Acceptance ERAP-769 3/16/2020 Am-241 71.0 74.7 53.3 - 99.6 Pass ERAP-769 3/16/2020 Cs-134 1210 1390 902 - 1700 Pass ERAP-769 3/16/2020 Cs-137 393 351 288 - 460 Pass ERAP-769 3/16/2020 Co-60 450.0 422.0 359.0 - 536 Pass ERAP-769 3/16/2020 Fe-55 1200 1260 460 - 2010 Pass ERAP-769 3/16/2020 Mn-54 < 2.4 < 50.0 0.00 - 50.0 Pass ERAP-769 3/16/2020 Zn-65 856 694 569 - 1060 Pass ERAP-769 3/16/2020 Pu-238 31.4 28.0 21.1 - 34.4 Pass ERAP-769 3/16/2020 Pu-239 43.9 40.1 30.0 - 48.4 Pass ERAP-769 3/16/2020 Sr-90 190 175 111 - 238 Pass ERAP-769 3/16/2020 U-234 56.7 56.2 41.7 - 65.9 Pass ERAP-769 3/16/2020 U-238 57.0 55.7 42.1 - 66.5 Pass ERAP-771 3/16/2020 Gross Alpha 33.4 29.3 15.3 - 48.3 Pass ERAP-771 3/16/2020 Gross Beta 68.3 66.4 40.3 - 100 Pass a 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-19
APPENDIX B DATA REPORTING CONVENTIONS
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 2 2 Reported result: x +/- s; where x = (1/2) (x1 + x2) and s = (1/2) I s1 + s 2 3.2. Individual results: <L1 , <L2 Reported result: <L, where L = lower of L1 and L2 3.3. Individual results: x +/- s, <L Reported result: x +/- s if [ / / otherwise. 4.0. Computation of Averages and Standard Deviations B-2
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: 1 x = n [ s= ~ (x- x )2 n-1 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
APPENDIX C SAMPLE LOCATION MAPS C-1
B N Q P-00075 C-2
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate Onsite Station, 110-meter 1 weather tower 0.53 293°/WNW P X 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 C-3
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate Fence around intake gate, Desoto Wildlife 7 Refuge 2.07 102°/ESE F X Onsite Station, 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 C-4
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate Metropolitan Utilities Dist., Florence Treatment Plant North Omaha, 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 14D river 0.09 4°/N A X X 15 Smith Farm 1.99 134°/SE G X 16A 17A C-5
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate 18A 19A 20B,D,F Mohr Dairy 9.86 186°/S J X X X 21A Fish Sampling 0.08 Area, Missouri 22 River (R.M. 645.0) 6°/N A X Fish Sampling 17.9 Area, Missouri 23D River (R.M. 666.0) 358°/N A X 24A 25A 26A 27A C-6
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate Alvin Pechnik 28 Farm 0.94 163 H X 29A 30A 31A Valley 32D 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 C-7
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate Offsite Station Desoto 37 Township 1.57 144°/SE G X X 38A 39A 40A 41B,C Dowler Acreage 0.73 175°/S 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 C-8
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites 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 58D Sector A-2 4.54 350°/NORTH A X 59D Sector B-2 2.95 26°/NNE B X C-9
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate 60D Sector C-2 3.32 50°/NE C X 61D Sector D-2 3.11 75°/ENE D X 62D Sector E-2 2.51 90°/EAST E X 63D Sector F-2 2.91 110°/ESE F X 64D Sector G-2 3.00 140°/SE G X 65D Sector H-2 2.58 154°/SSE H X 66D Sector J-2 3.53 181°/SOUTH J X 67D Sector K-2 2.52 205°/SSW K X 68D Sector L-2 2.77 214°/SW L X 69D Sector M-2 2.86 243°/WSW M X C-10
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate 70D Sector N-2 2.54 263°/WEST N X 71D Sector P-2 2.99 299°/WNW P X 72D Sector Q-2 3.37 311°/NW Q X 73D 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 77G 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 80G Parking S-1 0.27 158°/SSE H X 81G Training W-1 0.28 194°/SSW K X C-11
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Approximate Direction Vegetables from Center Sedi- Ground-Station Collection (degrees Sector TLD Water Milk Fish and Food of ment water No. Sites from true Products Containment Airborne north) (miles) Particulate 82G Switchyard S-1 0.21 219°/SW L X Switchyard SE-83G 1 0.14 231°/SW L X Switchyard NE-84G 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°/SSW K X C-12
Radiological Environmental Sampling Locations and Media 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) C-13}}