LIC-17-0042, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report
| ML17116A472 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/26/2017 |
| From: | Blome B Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-17-0042 | |
| Download: ML17116A472 (303) | |
Text
{{#Wiki_filter:Omaha Public Power District April 26, 2017 LIC-17-0042 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 Technical Specifications (TS) 5.9.4a and 5.9.4b Pursuant to Fort Calhoun Station (FCS), Unit No. 1, Technical Specifications (TS) 5.9.4a, and 5.9.4b, the 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 TS 5.9.4a and encompasses the period of January 1, 2016 through December 31, 2016. 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 TS 5.17d, 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 changes made during this period. The Annual Radiological Environmental Operating Report is submitted in accordance with TS 5.9.4b and encompasses the period of January 1, 2016 through December 31, 2016. No commitments to the NRC are contained in this letter. 444 SOUTH 16TH STREET MALL
- OMAHA, NE 68102-2247 EMPtOIMENT WITH EQUAl OHORTIJNTIY
U.S. Nuclear Regulatory Commission L1 C-17-0042 Page2 Please contact Mr. Bradley H. Blome at (402) 533-7270 if you should have any questions. Respectfully, Bradley H. Blome Director, Licensing and Regulatory Assurance BHB/epm
Enclosures:
- 1. Annual Radiological Effluent Release Report
- 2. Annual Radiological Environmental Operating Report c: K. M. Kennedy, NRC Regional Administrator, Region IV J. S. Kim, NRC Project Manager S. M. Schneider, NRC Senior Resident Inspector
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MEMORANDUM Date: April19, 2017 FC-C-004-17 From: Plant Manager, Fort Calhoun Station To: Distribution Re: Annual Radiological Effluent Release Report for Technical Specification Section 5.9.4.a. January 1, 2016 through December 31, 2016 Attached is a copy of the 2016 Annual Radiological Effluent Release Report for January 1, 2016 through December 31, 2016. This report is submitted in accordance with Section 5.9.4.a of the Technical Specifications of Fort Calhoun Station Unit No. 1, Facility Operating License DPR-40. 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, 2016 through December 31, 2016. 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 described and included.
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- Plant Man er Fort Calh un Station Distribution:
Senior Director FCS Decom Plant Manager Director-Nuclear Engineering Director-Rad Prot and Chemistry Director-Lie and Reg Assurance Assistant Plant Manager Operations Manager-Radiation Protection Manager-Site Chemistry Supervisor-RP (Chem/Environ) Supervisor-RP (ALARA/Shipping)
Omaha Public Power District Fort Calhoun Station Unit No. 1 Annual Report For Technical Specifications, Section 5.9.4.a January 1, 2016 to December 31, 2016
DOCKET NO. 50-285 OPERATING LICENSE DPR-40 Annual Radiological Effluent Release Report This report is submitted in accordance with Section 5.9.4.a of the Technical Specifications of Fort Calhoun Station Unit No. 1, Facility Operating License DPR-40 for the period January 1, 2016 through December 31, 2016. 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, 2016 through December 31, 2016. 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
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, RW-AA-100 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, Technical Specification (5.9.4.a) 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, Technical Specification (5.9.4.a) VII. ATTACHMENTS
- 1. Off-Site Dose Calculation Manual (ODCM) and Process Control Program (PCP) Revisions (Technical Specifications 5.17.d and 5.18.d)
- 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 as required by Technical Specification 5.9.4.a for the period January 1, 2016 through December 31, 2016. 1.1 Executive Summary The Radioactive Effluent Monitoring program for the year 2016 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 1.04 curies. This was a decrease from the 2015 activity of 1.31 curies. This decrease was due to decrease in RCS source from past fuel failures. The total airborne activity from I-131, I-133, and particulates with half-lives > 8 days in 2016 was 0.00 curies. This a decrease from the 2015 activity of 3.70E-06 curies. Due to plant decommissioning, the scheduled outage maintenance scope was dramatically reduced. The total airborne activity from Tritium was 2.99 curies. This was an increase from the 2015 activity of 2.88 curies. This increase was due to maintaining containment purges post defuel to assist in preparing the plant for decommissioning activities. The total airborne activity from C-14 was 1.97 curies. This was the same as 2015. Airborne activity from C-14 is included in the 2016 annual report, per Regulatory Guide 1.21, Revision 2. This is a calculated value based on power generation and days of operation. Critical organ doses from C-14 were calculated using a ratio of 15% as CO2. This ratio was determined during an NRC in-plant source term study conducted at the Fort Calhoun Station between 1976 and 1977, NUREG/CR-0140. The power history for the year was essentially the same as 2015. Dose contributions from airborne effluents at the unrestricted area boundary were; 1.28 E-03 mRad gamma air dose, 5.70E-04 mRad beta air dose, 8.68E-02 mRem total body dose, and 4.20E-01 mRem critical organ dose. Gamma and beta dose showed a decrease from 2015 levels of 1.35 E-03 mRad gamma air dose and 6.66-04 mRad beta air dose, from not releasing iodines and a reduction in gas source term for Cycle 28. Whole body and critical organ doses decreased from 2015 levels of 9.97E-02 mRem total I-1
body dose and 4.83E-01 mRem critical organ dose. This decrease is attributed to the gas source term reduction previously mentioned. Total water activity (excluding tritium, dissolved gases, and alpha) released in 2016 in liquid effluents was 4.34E-02 curies. This was an increase from the 2015 activity of 1.21E-02 curies. Outage scoping resource decisions did not allow for repairs to leakage from RCS Pressurizer Quench Tank and Safety Injection Tanks. Troubleshooting activities slowed, but did not stop SIT leakage. Processing this leakage depleted FIX processing resins. The majority (96%) of the released activity was CS-137, which has one of the lowest IX selectivity coefficients. New wastes entered the FIX system and selectively removed metallic ions, and then released CS-137 previously captured. The total activity released increased due to a decrease in rad waste processing efficiency. The FIX system, which processes liquid waste, could not have its resin sluiced due to a broken crane and a lack of available space to sluice or transfer waste resin. Resin shipping container space was limited due to failure of a lateral in one of the primary IX vessels necessitating unanticipated resin sluices so RCS chemistry could be maintained within specifications. The total water tritium activity released in 2016 in liquid effluents was 149 curies. This was a decrease from the 2015 activity of 158 curies. This decrease was due to having to increase RCS makeup water due to increased RCS Pressurizer Quench Tank and Safety Injection Tank leakage the past two cycles. The calculated whole body dose due to liquid effluents at the site discharge from all sources in 2016 was 2.11E-01 mRem which was 7.03% of the annual dose limit. This was an increase from the 2015 dose of 3.11-02 mRem, which was 1.04% of the annual dose limit. Dose increased slightly due to an increase in released activity; station release volume and dilution flow were unchanged. The calculated critical organ dose due to liquid effluents at the site discharge from all sources in 2016 was 3.26E-01 mRem. This was an increase from the 2015 dose of 4.40E-02 mRem. Dose increased due to an increase in released activity; station release volume and dilution flow were unchanged. The Fort Calhoun Station meteorological system had a cumulative recovery rate of 99.46% from the station meteorological tower with the remaining 0.54% 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. There were no abnormal releases during 2016. I-2
During 2016 there was one change to the Off-site Dose Calculations Manual (ODCM), CH-ODCM-0001 and no changes to the Process Control Program, RW-AA-100. For 2016, the total volume of solid radwaste released from the unit was 69.04 cubic meters. This was a decrease from the 580 cubic meters of solid waste released from the unit in 2015. The decrease was attributed to only two shipments made in 2016. The total activity released from the unit for 2016 was 2.16E-02 curies, 0.00 curies from spent resin and 2.16E-02 curies from dry compressables. This was a decrease from the 2015 value of 0.711 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 (Noble 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. To support plant operations, Supervisor - System Chemistry may increase this limit up to the limits specified in Technical Specification 5.16.1.g. Technical Specification 5.16.1.g establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 1. The air dose due to noble gases released in gaseous effluents to areas at or beyond the unrestricted area boundary shall be limited to the following: I-3
- a. During any calendar quarter: Less than or equal to 5 mRad for gamma radiation and less than or equal to 10 mRad for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mRad for gamma radiation and less than or equal to 20 mRad for beta radiation.
2.1.2 Doses from I-131, I-133, C-14, Tritium, 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 I-131, I-133, C-14, 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 I-131, I-133, C-14, 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.
2.1.3 Liquid Effluents The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides, other than dissolved or entrained noble gases, do not exceed the values specified in 10 CFR 20 for liquid effluents at site discharge. To support plant operations, the Supervisor - System Chemistry may increase this limit up to the limit specified in Technical Specifications 5.16.1.b. Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR 20.1001-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/mL total activity. I-4
The dose or dose commitment to a MEMBER OF THE PUBLIC 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 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. A value of 2.0E-04 Ci/mL is used as the ECL for dissolved and entrained noble gases in liquid effluents. 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. I-5
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 and Steam Generators. 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. There were no continuous releases from the Steam Generator blowdown during the reporting period. 2.3.2 Gaseous Radioactive Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release. For release of Waste Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy. For releases from the Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and Tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release. The results of the analysis and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode. 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. 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 I-6
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. I-7
5.0 SOLID WASTES The quantities of radioactive material released as solid effluents are summarized in Section VI. 6.0 RELATED INFORMATION 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation During the reporting period there were 3 instruments used to monitor radioactive effluent releases that failed to meet the minimum reportable instrument operability requirements listed in the ODCM during the reporting period. RM-054A and RM-054B, Steam Generator Blowdown Effluent Line Monitors, were inoperable for 51 days (1/11/2016-3/2/2016) for a modification to plant radiation monitors. The instrument rack design necessitated that both SG radiation monitors be removed. After install and completion of primary calibrations, the monitors were returned to service. Shiftly grab samples and analysis as required in ODCM Table 3.1.1. Note 2 were performed during this unavailability. RM-057, Condenser Off-Gas Effluent Line Radiation Monitor, was inoperable for 82 days (1/11/2016-4/2/2016) after the cabling was damaged while moving the instrument racks for the SG radiation monitor upgrade. The unavailability of replacement parts prevented the monitor from being repaired in less than 30 days. Shiftly grab samples and analysis as required in ODCM Table 3.2.1. Note 5 were performed during this unavailability. 6.2 Changes to the Offsite Dose Calculation Manual (ODCM) and/or Process Control Program During 2016, one revision was made to the ODCM and no changes made to the PCP. The following change was made to the ODCM: To remove the term Plant Review Committee and replaced with Plant Operations Review Committee I-8
6.3 New Locations or Modifications for Dose Calculations or Environmental Monitoring Sample Station #75, Lomp Acreage was added. Sample Station #28, Alvin Pechnik Farm was removed after the 2016 samples were obtained. 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 2016. 6.4.2 Failure to Meet Specified Sampling Requirements During 2016, 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 2016, 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 I-9
Real time hourly meteorological data is used to calculate the annual air effluent dose to individuals. For quarterly estimates during the year an annual average /Q is used, which is an average of the highest /Qs calculated for each of the previous two years. 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 annual average /Q. The results are listed in Section II. I-10
6.7.3 Doses Due to I-131, I-133, C-14, H-3, and Particulates with Half Lives Greater than 8 days. The doses due to I-131, I-133, C-14, 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 annual average /Q. The results are listed in Section II for inhalation, ground and food. 6.7.4 Direct Radiation Dose to Individuals and Populations Direct radiation doses attributed to the gamma radiation emitted from the containment structure were not observed above local background at any TLD sample 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 2016 were any of these limits exceeded; therefore, no special report per Tech Specification 5.16 was required. I-11
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 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 I-12
Calculation using REMP TLD Comparison Indicating TLD station {OTD-B-(I)}, closest to on site storage, in mrem/week minus REMP environmental control {OTD-L-(C)}, in mrem/week Dext=1.38 - 1.18
- 52 weeks =10.4 mrem Maximum offsite doses from report Dtbwb=0.0868 mrem, Dtbco=0.42 mrem D liqwb=0.211mrem Dliqco=0.326 mrem Dtot wholebody=10.4+0.0868+0.211= 10.7 mrem Dtot critical organ=10.4+0.42+0.326= 11.2 mrem For cases when the general public accesses the site, see Table 18 of the ODCM, the calculated dose would be:
Dtot wholebody=10.4+5.08+0.211= 15.7 mrem Dtot critical organ=10.4+1.20+0.326= 11.9 mrem 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. I-13
6.8 Groundwater Monitoring Program and Observations OPPD conducted groundwater sampling from 19 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. No new monitoring wells were added to the sampling program during 2016. 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. Four rain sampling events were conducted. No tritium activity in excess of the vendors Minimum Detectable Activity (MDA) was reported. Fourth quarter had no rain or snow events significant enough to collect storm water samples. No tritium activity in excess of the vendors Minimum Detectable Activity (MDA) was reported in collected storm water. No monitoring wells had tritium in excess of the vendors Minimum Detectable Activity (MDA) reported in Table III.9. 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. 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. I-14
SECTION II QUARTERLY DOSES FROM EFFLUENTS Offsite Dose Calculation Manual January 1, 2016 - December 31, 2016 II-1
Quarterly Dose Calculation Results January 1, 2016 through December 31, 2016 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 2016 calculated doses. This section presents the results of the quarterly dose calculations performed during the period January 1, 2016 through December 31, 2016. 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-2
FORT CALHOUN STATION FC-421 CHEMISTRY FORM R8 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN FIRST QUARTER 2016 DOSE PROJECTIONS I. Liquid Effluents: Total Body Critical Organ Dose (mrem) Dose (mrem) Batch: 1.51E-02 2.19E-02 Continuous: O.OOE+OO O.OOE+OO Totals: 1.51E-02 2.19E-02 ODCM Quarterly Objective: 1.50E+00 S.OOE+OO Percent of Quarterly Obj: 1.01 % 0.44 % ODCM Annual Objective: 3.00E+00 1.00E+01 YTD Percent of Annual Obj: 0.50 % 0.22 % II. Gaseous Effluents: Total Body Gamma Total Body Beta Dose (mrad) Dose (mrad) A. Noble Gas Air Dose: 6.64E-04 2.85E-04 ODCM Quarterly Objective: S.OOE+OO 1.00E+01 Percent of Quarterly Obj: 0.01 % 0.00 % ODCM Annual Objective: 1.00E+01 2.00E+01 YTD Percent of Annual Obj: 0.01% 0.00 % B. I-131, I-133, Tritium, C-14, and Particulates with Half-Lives > 8 Days: Total Body Critical Organ Dose (mrem} Dose (mrem) Inhalation: 2.09E-04 2.09E-04 Ground and Food: 4.91E-02 2.41E-01 Totals: 4.93E-02 2.41E-01 ODCM Quarterly Objective: 7.50E+00 7.50E+00 Percent of Quarterly Obj: 0.66 % 3.22 % ODCM Annual Objective: 1.50E+01 1.50E+01 YTD Percent of Annual Obj: 0.33 % 1.61 %
FORT CALHOUN STATION FC-421 CHEMISTRY FORM R8 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN SECOND QUARTER 2016 DOSE PROJECTIONS I. Liquid Effluents: Total Body Critical Organ Dose (mrem) Dose (rnrern) Batch: 4.89E-02 7.54E-02 Continuous: O.OOE+OO O.OOE+OO Totals: 4.89E-02 7.54E-02 ODCM Quarterly Objective: 1.50E+00 S.OOE+OO Percent of Quarterly Obj: 3.26 % 1.51 % ODCM Annual Objective: 3.00E+00 1.00E+01 YTD Percent of Annual Obj: 2.13 % 0.97 % II. Gaseous Effluents: Total Body Gamma Total Body Beta Dose (mrad) Dose {rnrad) A. Noble Gas Air Dose: 6.70E-04 2.88E-04 ODCM Quarterly Objective: S.OOE+OO 1.00E+01 Percent of Quarterly Obj: 0.01 % 0.00 % ODCM Annual Objective: 1.00E+01 2.00E+01 YTD Percent of Annual Obj: 0.01% 0.00 % B. I-131, I-133, Tritium, C-14, and Particulates with Half-Lives > 8 Days: Total Body Critical Organ Dose (mrem) Dose (mrem) Inhalation: 1.94E-04 1.94E-04 Ground and Food: 4.57E-02 2.24E-01 Totals: 4.59E-02 2.24E-01 ODCM Quarterly Objective: 7.50E+00 7.50E+00 Percent of Quarterly Obj: 0.61 % 2.99 % ODCM Annual Objective: 1.50E+01 l.SOE+Ol YTD Percent of Annual Obj: 0.64 % 3.10 %
FORT CALHOUN STATION FC-421 CHEMISTRY FORM R8 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN THIRD QUARTER 2016 DOSE PROJECTIONS I. Liquid Effluents: Total Body Critical Organ Dose (mrem) Dose (mrem) Batch: 1.02E-01 1.58E-01 Continuous: O.OOE+OO O.OOE+OO Totals: 1.02E-01 1.58E-01 ODCM Quarterly Objective: 1.50E+00 S.OOE+OO Percent of Quarterly Obj: 6.80 % 3.16 % ODCM Annual Objective: 3.00E+00 1.00E+01 YTD Percent of Annual Obj: 5.53 % 2.55 % II. Gaseous Effluents: Total Body Gamma Total Body Beta Dose {mrad) Dose (mrad) A. Noble Gas Air Dose: 8.47E-04 3.62E-04 ODCM Quarterly Objective: S.OOE+OO 1.00E+01 Percent of Quarterly Obj: 0.02 % 0.00 % ODCM Annual Objective: 1.00E+01 2.00E+01 YTD Percent of Annual Obj: 0.02% 0.00 % B. I-131, I-133, Tritium, C-14, and Particulates with Half-Lives > 8 Days: Total Body Critical Organ Dose (mrem) Dose (mrem) Inhalation: 1.32E-04 1.32E-04 Ground and Food: 4.85E-02 2.40E-01 Totals: 4.86E-02 2.40E-01 ODCM Quarterly Objective: 7.50E+00 7.50E+00 Percent of Quarterly Obj: 0.65 % 3.20 % ODCM Annual Objective: 1.50E+01 1.50E+01 YTD Percent of Annual Obj: 0.96 % 4.70 %
FORT CALHOUN STATION FC-421 CHEMISTRY FORM R8 QUARTERLY CUMULATIVE DOSE CONTRIBUTION FROM RADIOACTIVE EFFLUENTS FORT CALHOUN FOURTH QUARTER 2016 DOSE PROJECTIONS I. Liquid Effluents: Total Body Critical Organ Dose {mrem) Dose (mrem) Batch: 7.87E-02 1.24E-01 Continuous: O.OOE+OO O.OOE+OO Totals: 7.87E-02 1.24E-01 ODCM Quarterly Objective: 1.50E+00 5.00E+00 Percent of Quarterly Obj: 5.25 % 2 . 48 % ODCM Annual Objective: 3.00E+00 1.00E+01 YTD Percent of Annual Obj: 8.17 % 3.78 % II. Gaseous Effluents: Total Body Gamma Total Body Beta Dose (mrad) Dose (mrad) A. Noble Gas Air Dose: 1.67E-04 l.lOE-04 ODCM Quarterly Objective: 5.00E+00 l.OOE+01 Percent of Quarterly Obj: 0.00 % 0.00 % ODCM Annual Objective: 1.00E+01 2.00E+01 YTD Percent of Annual Obj: 0.02 % 0.01 % B. I-131, I-1331 Tritium, C-14, and Particulates with Half-Lives > 8 Days: Total Body Critical Organ Dose (mrem) Dose (mrem) Inhalation: 4.49E-04 4.49E-04 Ground and Food: 1.49E-02 6.43E-02 Totals: 1.54E-02 6.47E-02 ODCM Quarterly Objective: 7.50E+00 7.50E+00 Percent of Quarterly Obj: 0.21 % 0.86 % ODCM Annual Objective: 1.50E+01 l.SOE+Ol YTD Percent of Annual Obj: 1.06 % 5.13 %
SECTION III RADIOLOGICAL EFFLUENT RELEASES Technical Specification (5.9.4.a) 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, 2016 - December 31, 2016
TABLE III.1 BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
JANUARY THROUGH DECEMBER 2016 A. Liquid Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
- 1. Number of Batch Releases: 27 40 51 51 169
- 2. Total Time Period for Batch Releases(min): 3,667 5,420 6,491 7,311 22,889
- 3. Maximum Time Period for Batch Releases(min): 170 200 175 242 242
- 4. Average Time Period for Batch Releases(min): 136 136 127 143 135
- 5. Minimum Time Period for Batch Releases(min): 85 100 93 105 85
- 6. Average Dilution Stream Flow During Periods of Release into the Missouri River(mls/min): 1.363E+09 1.272E+09 1.363E+09 8.107E+08 1.175E+09 B. Gaseous Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
- 1. Number of Batch Releases: 13 15 14 37 79
- 2. Total Time Period for Batch Releases(min): 93,757 103,447 110,799 79,329 387,332
- 3. Maximum Time Period for Batch Releases(min): 8,898 8,802 8,796 9,000 9,000
- 4. Average Time Period for Batch Releases(min): 7,212 6,896 7,914 2,144 4,903
- 5. Minimum Time Period for Batch Releases(min): 94 1,473 4,636 30 30 III-2
TABLE III.2 ABNORMAL BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
JANUARY THROUGH DECEMBER 2016 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 2016 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activation Gases Total Release (Ci): 2.70E-01 2.72E-01 3.39E-01 1.55E-01 1.04E+00 Average Release Rate (uCi/sec): 9.65E-04 7.94E-04 1.03E-03 1.16E-03 9.48E-04 Total Error (%): 25.98 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 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 Gross Alpha: Total Error (%): 20.62 1.32E-06 3.35E-06 1.52E-06 3.86E-06 1.00E-05 D. Tritium Total Release (Ci): 6.37E-01 5.90E-01 4.01E-01 1.37E+00 2.99E+00 Average Release Rate (uCi/sec): 3.28E-03 2.71E-03 1.89E-03 3.78E-03 3.02E-03 Total Error (%): 25.08 E. Carbon-14 Total Release (Ci): 6.17E-01 5.75E-01 6.14E-01 1.65E-01 1.97E+00 Average Release Rate (uCi/sec): 6.11E-03 5.69E-03 6.01E-03 5.24E-03 5.83E-03 Total Error (%): 25.08 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 2016 Batch Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter YEAR Fission & Activation Gases XE-133 1.14E-01 1.13E-01 1.39E-01 1.18E-01 4.84E-01 XE-135 3.86E-03 4.47E-03 5.92E-03 1.66E-03 1.59E-02 AR-41 1.52E-01 1.54E-01 1.94E-01 3.49E-02 5.35E-01 Totals for Period: 2.70E-01 2.72E-01 3.39E-01 1.55E-01 1.04E+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 H-3 1.42E-01 1.87E-01 1.42E-01 1.04E+00 1.51E+00 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 2016 Continuous Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates C-14 6.17E-01 5.75E-01 6.14E-01 1.65E-01 1.97E+00 Totals for Period: 6.17E-01 5.75E-01 6.14E-01 1.65E-01 1.97E+00 Tritium and Gross Alpha ALPHA 1.32E-06 3.35E-06 1.52E-06 3.86E-06 1.00E-05 H-3 4.95E-01 4.03E-01 2.59E-01 3.28E-01 1.49E+00 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 2016 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activiation Products Total Release (No H-3,Gas,Alpha) (Ci): 2.76E-03 8.49E-03 1.79E-02 1.42E-02 4.34E-02 Average Diluted Concentration (uCi/mL): 4.06E-10 1.58E-09 3.77E-09 7.78E-09 9.30E-09 10 CFR 20, App. B Limit 1.00E-06 (uCi/mL) Percent of Limit (%): 4.06E-02 1.58E-01 3.77E-01 7.78E-01 9.30E-01 Total Error (%): 24.17 B. Tritium Total Release (Ci): 3.01E+01 3.12E+01 6.62E+01 2.11E+01 1.49E+02 Average Diluted Concentration (uCi/mL): 4.43E-06 5.80E-06 1.39E-05 1.16E-05 3.19E-05 10 CFR 20, App. B Limit 1.00E-03(uCi/mL) Percent of Limit (%): 4.43E-01 5.80E-01 1.39E+00 1.16E+00 3.19E+00 Total Error (%): 25.08 C. Dissolved & Entrained Gases Total Release (Ci): 0.00E+00 7.97E-05 4.67E-04 1.93E-04 7.40E-04 Average Diluted Concentration (uCi/mL): 0.00E+00 1.48E-11 9.84E-11 1.06E-10 1.59E-10 ODCM Limit 2.00E-04 (uCi/mL): Percent of Limit (%): 0.00E+00 7.41E-06 4.92E-05 5.30E-05 7.94E-05 Total Error (%): 19.36 D. Gross Alpha Radioactivity Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 8.72E-04 8.72E-04 Total Error (%): 25.08 E. Volume of Waste Released Prior to Dilution (Liters): 2.99E+07 3.44E+07 3.07E+07 1.06E+07 1.06E+08 F. Volume of Dilution Water During Releases (Liters): 3.55E+11 3.48E+11 3.57E+11 1.04E+11 1.16E+12 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 2016 Batch Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases TC-99M 0.00E+00 0.00E+00 4.08E-06 0.00E+00 4.08E-06 MN-54 4.56E-06 2.02E-06 3.61E-05 1.34E-06 4.40E-05 BE-7 0.00E+00 4.15E-07 0.00E+00 0.00E+00 4.15E-07 CE-143 3.51E-07 0.00E+00 0.00E+00 0.00E+00 3.51E-07 I-133 0.00E+00 0.00E+00 9.18E-06 9.60E-07 1.01E-05 TC-101 3.51E-07 0.00E+00 0.00E+00 0.00E+00 3.51E-07 CS-137 2.29E-03 8.36E-03 1.75E-02 1.39E-02 4.20E-02 CS-134 1.59E-05 6.80E-05 1.37E-04 9.94E-05 3.20E-04 I-132 0.00E+00 0.00E+00 0.00E+00 3.08E-05 3.08E-05 CO-58 3.41E-05 6.00E-07 2.80E-06 0.00E+00 3.75E-05 MO-99 0.00E+00 0.00E+00 4.09E-06 0.00E+00 4.09E-06 I-131 2.08E-06 2.82E-05 1.59E-04 9.42E-05 2.83E-04 SB-124 0.00E+00 0.00E+00 0.00E+00 1.72E-05 1.72E-05 NI-63 3.70E-04 0.00E+00 0.00E+00 0.00E+00 3.70E-04 CO-60 4.64E-05 2.48E-05 1.13E-04 2.49E-05 2.09E-04 Totals for Period: 2.76E-03 8.49E-03 1.79E-02 1.42E-02 4.34E-02 Dissolved & Entrained Gases XE-133 0.00E+00 7.97E-05 4.67E-04 1.93E-04 7.40E-04 Totals for Period: 0.00E+00 7.97E-05 4.67E-04 1.93E-04 7.40E-04 Tritium and Gross Alpha ALPHA 0.00E+00 0.00E+00 0.00E+00 8.72E-04 8.72E-04 H-3 3.01E+01 3.12E+01 6.62E+01 2.11E+01 1.49E+02 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 2016 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 ALPHA 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 2016 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 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 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 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 0.00E+00 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 NI-63 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 Total Gamma 0.00E+00 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 0.00E+00 MW-4A 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 0.00E+00 III-10
TABLE III.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2016 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 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 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 0.00E+00 Total Gamma 0.00E+00 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Gamma 0.00E+00 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-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 0.00E+00 Total Gamma 0.00E+00 MW-9 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-10 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-11 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-12A 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-11
TABLE III.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2016 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-12B 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 EAST LAGOON Tritium 0.00E+00 0.00E+00 0.00E+00 5.15E+02 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 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 SOUTH STORMWATER HDR Tritium 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 SW-8 NORTH PA Tritium 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 SW-6 ISFSI Tritium 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 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 Technical Specification 5.9.4.a GASPAR II OUTPUT January 1, 2016 - December 31, 2016 IV-1
Radioactive Effluent Releases - First, Second, Third and Fourth Quarters 2016 GASEOUS EFFLUENTS Radioactive gaseous releases for the reporting period totaled 1.04 curies of inert gas. The gross gaseous activity release rates were 9.65E-04 Ci/sec for the first quarter, 7.94E-04 Ci/sec for the second quarter, 1.03E-03 Ci/sec for the third quarter, and 1.16E-03 Ci/sec for the fourth quarter. Radioactive halogens releases for the reporting period totaled 0.00E+00 curies. The halogen activity release rates were 0.00E+00 Ci/sec for the first quarter, 0.00E+00 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 from gaseous effluent discharges. No radioactive particulates with half-lives greater that eight days were released during the reporting period from gaseous effluent discharges. Radioactive tritium released during the reporting period totaled 2.99E+00 curies. Carbon-14 released for the reporting period totaled 1.97 curies, this is a calculated value based on reactor power and days of operation. The Fort Calhoun estimate of 1.97 Ci carbon-14 with a normalized C-14 production rate and 15% carbon dioxide fraction. 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-39. 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, 2016 through December 31, 2016 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 /Q at the actual receptor locations, which are corrected for open terrain and plume depletion, are calculated according to Regulatory Guide 1.111. Also included are annual deposition rates corrected for the open terrain factor. (4) The production, intake and grazing fractions were as follows: 1.0 for leafy vegetables grown in 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. IV-3
(7) Using approved methodologies the C-14 doses to the site specific pathways (e.g. inhalation, milk, meat, and vegetation pathways) age group and organs are based upon airborne composition rather than ground deposition. For this reason, X/Q is utilized to calculate doses from Carbon-14 effluent releases These inputs introduce a most conservative approach for the following reasons: (1) The open terrain and deposition corrections increase annual /Q by a factor ranging between 1.0 and 4.0 (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 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 1 RES AT 4.36 MILES N ANNUAL_BETA_AIR_DOSE = 3.84E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.77E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
---------+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.46E-06 : 4.46E-06 : 4.46E-06 : 4.46E-06 : 4.46E-06 : 4.46E-06 : 4.48E-06 : 7.58E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 6.68E-06 : 6.68E-06 : 0.00E+00 : 6.68E-06 : 6.68E-06 : 6.68E-06 : 6.68E-06 : 6.68E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 6.74E-06 : 6.74E-06 : 0.00E+00 : 6.74E-06 : 6.74E-06 : 6.74E-06 : 6.74E-06 : 6.74E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.95E-06 : 5.95E-06 : 0.00E+00 : 5.95E-06 : 5.95E-06 : 5.95E-06 : 5.95E-06 : 5.95E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 3.42E-06 : 3.42E-06 : 0.00E+00 : 3.42E-06 : 3.42E-06 : 3.42E-06 : 3.42E-06 : 3.42E-06 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 5
TABLE IV-A- 2 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 2 RES AT 1.93 MILES NNE ANNUAL_BETA_AIR_DOSE = 2.65E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 5.24E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.46E-05 : 3.46E-05 : 3.46E-05 : 3.46E-05 : 3.46E-05 : 3.46E-05 : 3.47E-05 : 5.79E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 3.68E-05 : 3.68E-05 : 0.00E+00 : 3.68E-05 : 3.68E-05 : 3.68E-05 : 3.68E-05 : 3.68E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.71E-05 : 3.71E-05 : 0.00E+00 : 3.71E-05 : 3.71E-05 : 3.71E-05 : 3.71E-05 : 3.71E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.28E-05 : 3.28E-05 : 0.00E+00 : 3.28E-05 : 3.28E-05 : 3.28E-05 : 3.28E-05 : 3.28E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.89E-05 : 1.89E-05 : 0.00E+00 : 1.89E-05 : 1.89E-05 : 1.89E-05 : 1.89E-05 : 1.89E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 6
TABLE IV-A- 3 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 3 RES AT 1.52 MILES NE ANNUAL_BETA_AIR_DOSE = 3.15E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 5.79E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.82E-05 : 3.82E-05 : 3.82E-05 : 3.82E-05 : 3.82E-05 : 3.82E-05 : 3.83E-05 : 6.44E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 5.11E-05 : 5.11E-05 : 0.00E+00 : 5.11E-05 : 5.11E-05 : 5.11E-05 : 5.11E-05 : 5.11E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.16E-05 : 5.16E-05 : 0.00E+00 : 5.16E-05 : 5.16E-05 : 5.16E-05 : 5.16E-05 : 5.16E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.56E-05 : 4.56E-05 : 0.00E+00 : 4.56E-05 : 4.56E-05 : 4.56E-05 : 4.56E-05 : 4.56E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.62E-05 : 2.62E-05 : 0.00E+00 : 2.62E-05 : 2.62E-05 : 2.62E-05 : 2.62E-05 : 2.62E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 7
TABLE IV-A- 4 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 4 RES AT 4.79 MILES ENE ANNUAL_BETA_AIR_DOSE = 1.23E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.25E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.19E-07 : 1.53E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 3.75E-06 : 3.75E-06 : 0.00E+00 : 3.75E-06 : 3.75E-06 : 3.75E-06 : 3.75E-06 : 3.75E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.78E-06 : 3.78E-06 : 0.00E+00 : 3.78E-06 : 3.78E-06 : 3.78E-06 : 3.78E-06 : 3.78E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.34E-06 : 3.34E-06 : 0.00E+00 : 3.34E-06 : 3.34E-06 : 3.34E-06 : 3.34E-06 : 3.34E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.92E-06 : 1.92E-06 : 0.00E+00 : 1.92E-06 : 1.92E-06 : 1.92E-06 : 1.92E-06 : 1.92E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 8
TABLE IV-A- 5 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 5 RES AT 4.67 MILES E ANNUAL_BETA_AIR_DOSE = 2.31E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.25E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.13E-06 : 2.13E-06 : 2.13E-06 : 2.13E-06 : 2.13E-06 : 2.13E-06 : 2.14E-06 : 3.75E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 5.45E-06 : 5.45E-06 : 0.00E+00 : 5.45E-06 : 5.45E-06 : 5.45E-06 : 5.45E-06 : 5.45E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.50E-06 : 5.50E-06 : 0.00E+00 : 5.50E-06 : 5.50E-06 : 5.50E-06 : 5.50E-06 : 5.50E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.86E-06 : 4.86E-06 : 0.00E+00 : 4.86E-06 : 4.86E-06 : 4.86E-06 : 4.86E-06 : 4.86E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.80E-06 : 2.80E-06 : 0.00E+00 : 2.80E-06 : 2.80E-06 : 2.80E-06 : 2.80E-06 : 2.80E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 9
TABLE IV-A- 6 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 6 RES AT 4.22 MILES ESE ANNUAL_BETA_AIR_DOSE = 8.04E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.81E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.97E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 7.50E-06 : 7.50E-06 : 0.00E+00 : 7.50E-06 : 7.50E-06 : 7.50E-06 : 7.50E-06 : 7.50E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 7.57E-06 : 7.57E-06 : 0.00E+00 : 7.57E-06 : 7.57E-06 : 7.57E-06 : 7.57E-06 : 7.57E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.68E-06 : 6.68E-06 : 0.00E+00 : 6.68E-06 : 6.68E-06 : 6.68E-06 : 6.68E-06 : 6.68E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 3.84E-06 : 3.84E-06 : 0.00E+00 : 3.84E-06 : 3.84E-06 : 3.84E-06 : 3.84E-06 : 3.84E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-10
TABLE IV-A- 7 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 7 RES AT 1.67 MILES SE ANNUAL_BETA_AIR_DOSE = 3.06E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.14E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.06E-05 : 4.06E-05 : 4.06E-05 : 4.06E-05 : 4.06E-05 : 4.06E-05 : 4.07E-05 : 6.77E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 4.09E-05 : 4.09E-05 : 0.00E+00 : 4.09E-05 : 4.09E-05 : 4.09E-05 : 4.09E-05 : 4.09E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.13E-05 : 4.13E-05 : 0.00E+00 : 4.13E-05 : 4.13E-05 : 4.13E-05 : 4.13E-05 : 4.13E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.65E-05 : 3.65E-05 : 0.00E+00 : 3.65E-05 : 3.65E-05 : 3.65E-05 : 3.65E-05 : 3.65E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.10E-05 : 2.10E-05 : 0.00E+00 : 2.10E-05 : 2.10E-05 : 2.10E-05 : 2.10E-05 : 2.10E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-11
TABLE IV-A- 8 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 8 RES AT 0.65 MILES SSE ANNUAL_BETA_AIR_DOSE = 4.75E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.07E-03 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 7.08E-04 : 7.08E-04 : 7.08E-04 : 7.08E-04 : 7.08E-04 : 7.08E-04 : 7.09E-04 : 1.16E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 4.43E-04 : 4.43E-04 : 0.00E+00 : 4.43E-04 : 4.43E-04 : 4.43E-04 : 4.43E-04 : 4.43E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.47E-04 : 4.47E-04 : 0.00E+00 : 4.47E-04 : 4.47E-04 : 4.47E-04 : 4.47E-04 : 4.47E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.95E-04 : 3.95E-04 : 0.00E+00 : 3.95E-04 : 3.95E-04 : 3.95E-04 : 3.95E-04 : 3.95E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.27E-04 : 2.27E-04 : 0.00E+00 : 2.27E-04 : 2.27E-04 : 2.27E-04 : 2.27E-04 : 2.27E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-12
TABLE IV-A- 9 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 9 RES AT 0.73 MILES S ANNUAL_BETA_AIR_DOSE = 1.75E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.94E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.61E-04 : 2.61E-04 : 2.61E-04 : 2.61E-04 : 2.61E-04 : 2.61E-04 : 2.62E-04 : 4.29E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.64E-04 : 1.64E-04 : 0.00E+00 : 1.64E-04 : 1.64E-04 : 1.64E-04 : 1.64E-04 : 1.64E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.65E-04 : 1.65E-04 : 0.00E+00 : 1.65E-04 : 1.65E-04 : 1.65E-04 : 1.65E-04 : 1.65E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.46E-04 : 1.46E-04 : 0.00E+00 : 1.46E-04 : 1.46E-04 : 1.46E-04 : 1.46E-04 : 1.46E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 8.39E-05 : 8.39E-05 : 0.00E+00 : 8.39E-05 : 8.39E-05 : 8.39E-05 : 8.39E-05 : 8.39E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-13
TABLE IV-A-10 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 10 RES AT 0.65 MILES SSW ANNUAL_BETA_AIR_DOSE = 1.39E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.12E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.07E-04 : 2.07E-04 : 2.07E-04 : 2.07E-04 : 2.07E-04 : 2.07E-04 : 2.07E-04 : 3.40E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.30E-04 : 1.30E-04 : 0.00E+00 : 1.30E-04 : 1.30E-04 : 1.30E-04 : 1.30E-04 : 1.30E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.31E-04 : 1.31E-04 : 0.00E+00 : 1.31E-04 : 1.31E-04 : 1.31E-04 : 1.31E-04 : 1.31E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.15E-04 : 1.15E-04 : 0.00E+00 : 1.15E-04 : 1.15E-04 : 1.15E-04 : 1.15E-04 : 1.15E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 6.64E-05 : 6.64E-05 : 0.00E+00 : 6.64E-05 : 6.64E-05 : 6.64E-05 : 6.64E-05 : 6.64E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-14
TABLE IV-A-11 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 11 RES AT 0.73 MILES SW ANNUAL_BETA_AIR_DOSE = 1.83E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.11E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.72E-04 : 2.72E-04 : 2.72E-04 : 2.72E-04 : 2.72E-04 : 2.72E-04 : 2.73E-04 : 4.47E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.70E-04 : 1.70E-04 : 0.00E+00 : 1.70E-04 : 1.70E-04 : 1.70E-04 : 1.70E-04 : 1.70E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.72E-04 : 1.72E-04 : 0.00E+00 : 1.72E-04 : 1.72E-04 : 1.72E-04 : 1.72E-04 : 1.72E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.52E-04 : 1.52E-04 : 0.00E+00 : 1.52E-04 : 1.52E-04 : 1.52E-04 : 1.52E-04 : 1.52E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 8.74E-05 : 8.74E-05 : 0.00E+00 : 8.74E-05 : 8.74E-05 : 8.74E-05 : 8.74E-05 : 8.74E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-15
TABLE IV-A-12 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 12 RES AT 1.06 MILES WSW ANNUAL_BETA_AIR_DOSE = 8.04E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.81E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.20E-04 : 1.20E-04 : 1.20E-04 : 1.20E-04 : 1.20E-04 : 1.20E-04 : 1.20E-04 : 1.97E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 7.50E-05 : 7.50E-05 : 0.00E+00 : 7.50E-05 : 7.50E-05 : 7.50E-05 : 7.50E-05 : 7.50E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 7.57E-05 : 7.57E-05 : 0.00E+00 : 7.57E-05 : 7.57E-05 : 7.57E-05 : 7.57E-05 : 7.57E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.68E-05 : 6.68E-05 : 0.00E+00 : 6.68E-05 : 6.68E-05 : 6.68E-05 : 6.68E-05 : 6.68E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 3.84E-05 : 3.84E-05 : 0.00E+00 : 3.84E-05 : 3.84E-05 : 3.84E-05 : 3.84E-05 : 3.84E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-16
TABLE IV-A-13 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 13 RES AT 1.20 MILES W ANNUAL_BETA_AIR_DOSE = 5.86E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.24E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.18E-05 : 8.18E-05 : 8.18E-05 : 8.18E-05 : 8.18E-05 : 8.18E-05 : 8.20E-05 : 1.36E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 6.82E-05 : 6.82E-05 : 0.00E+00 : 6.82E-05 : 6.82E-05 : 6.82E-05 : 6.82E-05 : 6.82E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 6.88E-05 : 6.88E-05 : 0.00E+00 : 6.88E-05 : 6.88E-05 : 6.88E-05 : 6.88E-05 : 6.88E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.08E-05 : 6.08E-05 : 0.00E+00 : 6.08E-05 : 6.08E-05 : 6.08E-05 : 6.08E-05 : 6.08E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 3.49E-05 : 3.49E-05 : 0.00E+00 : 3.49E-05 : 3.49E-05 : 3.49E-05 : 3.49E-05 : 3.49E-05 :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
IV-17
TABLE IV-A-14 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 14 RES AT 2.60 MILES WNW ANNUAL_BETA_AIR_DOSE = 1.97E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.44E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.94E-05 : 2.94E-05 : 2.94E-05 : 2.94E-05 : 2.94E-05 : 2.94E-05 : 2.94E-05 : 4.83E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 1.84E-05 : 1.84E-05 : 0.00E+00 : 1.84E-05 : 1.84E-05 : 1.84E-05 : 1.84E-05 : 1.84E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.86E-05 : 1.86E-05 : 0.00E+00 : 1.86E-05 : 1.86E-05 : 1.86E-05 : 1.86E-05 : 1.86E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.64E-05 : 1.64E-05 : 0.00E+00 : 1.64E-05 : 1.64E-05 : 1.64E-05 : 1.64E-05 : 1.64E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 9.44E-06 : 9.44E-06 : 0.00E+00 : 9.44E-06 : 9.44E-06 : 9.44E-06 : 9.44E-06 : 9.44E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-18
TABLE IV-A-15 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 15 RES AT 2.40 MILES NW ANNUAL_BETA_AIR_DOSE = 2.52E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.95E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.27E-05 : 3.27E-05 : 3.27E-05 : 3.27E-05 : 3.27E-05 : 3.27E-05 : 3.28E-05 : 5.47E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 3.55E-05 : 3.55E-05 : 0.00E+00 : 3.55E-05 : 3.55E-05 : 3.55E-05 : 3.55E-05 : 3.55E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.58E-05 : 3.58E-05 : 0.00E+00 : 3.58E-05 : 3.58E-05 : 3.58E-05 : 3.58E-05 : 3.58E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.16E-05 : 3.16E-05 : 0.00E+00 : 3.16E-05 : 3.16E-05 : 3.16E-05 : 3.16E-05 : 3.16E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.82E-05 : 1.82E-05 : 0.00E+00 : 1.82E-05 : 1.82E-05 : 1.82E-05 : 1.82E-05 : 1.82E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-19
TABLE IV-A-16 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 16 RES AT 2.08 MILES NNW ANNUAL_BETA_AIR_DOSE = 2.78E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.99E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.29E-05 : 3.29E-05 : 3.29E-05 : 3.29E-05 : 3.29E-05 : 3.29E-05 : 3.30E-05 : 5.57E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : : ADULT : 4.70E-05 : 4.70E-05 : 0.00E+00 : 4.70E-05 : 4.70E-05 : 4.70E-05 : 4.70E-05 : 4.70E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.75E-05 : 4.75E-05 : 0.00E+00 : 4.75E-05 : 4.75E-05 : 4.75E-05 : 4.75E-05 : 4.75E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.19E-05 : 4.19E-05 : 0.00E+00 : 4.19E-05 : 4.19E-05 : 4.19E-05 : 4.19E-05 : 4.19E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.41E-05 : 2.41E-05 : 0.00E+00 : 2.41E-05 : 2.41E-05 : 2.41E-05 : 2.41E-05 : 2.41E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-20
TABLE IV-A-17 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 17 VEG AT 2.23 MILES NNE ANNUAL_BETA_AIR_DOSE = 1.48E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.69E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.78E-05 : 1.78E-05 : 1.78E-05 : 1.78E-05 : 1.78E-05 : 1.78E-05 : 1.78E-05 : 3.00E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 6.55E-04 : 6.55E-04 : 3.05E-03 : 6.55E-04 : 6.55E-04 : 6.55E-04 : 6.55E-04 : 6.55E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.04E-03 : 1.04E-03 : 4.95E-03 : 1.04E-03 : 1.04E-03 : 1.04E-03 : 1.04E-03 : 1.04E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.47E-03 : 2.47E-03 : 1.19E-02 : 2.47E-03 : 2.47E-03 : 2.47E-03 : 2.47E-03 : 2.47E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-21
TABLE IV-A-18 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 18 VEG AT 1.52 MILES NE ANNUAL_BETA_AIR_DOSE = 3.15E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 5.79E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.82E-05 : 3.82E-05 : 3.82E-05 : 3.82E-05 : 3.82E-05 : 3.82E-05 : 3.83E-05 : 6.44E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.37E-03 : 1.37E-03 : 6.36E-03 : 1.37E-03 : 1.37E-03 : 1.37E-03 : 1.37E-03 : 1.37E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.17E-03 : 2.17E-03 : 1.03E-02 : 2.17E-03 : 2.17E-03 : 2.17E-03 : 2.17E-03 : 2.17E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.14E-03 : 5.14E-03 : 2.49E-02 : 5.14E-03 : 5.14E-03 : 5.14E-03 : 5.14E-03 : 5.14E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-22
TABLE IV-A-19 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 19 VEG AT 4.79 MILES ENE ANNUAL_BETA_AIR_DOSE = 1.23E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.25E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.19E-07 : 1.53E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.00E-04 : 1.00E-04 : 4.67E-04 : 1.00E-04 : 1.00E-04 : 1.00E-04 : 1.00E-04 : 1.00E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.59E-04 : 1.59E-04 : 7.57E-04 : 1.59E-04 : 1.59E-04 : 1.59E-04 : 1.59E-04 : 1.59E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.77E-04 : 3.77E-04 : 1.82E-03 : 3.77E-04 : 3.77E-04 : 3.77E-04 : 3.77E-04 : 3.77E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-23
TABLE IV-A-20 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 20 VEG AT 4.67 MILES E ANNUAL_BETA_AIR_DOSE = 2.31E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.25E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.13E-06 : 2.13E-06 : 2.13E-06 : 2.13E-06 : 2.13E-06 : 2.13E-06 : 2.14E-06 : 3.75E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.46E-04 : 1.46E-04 : 6.79E-04 : 1.46E-04 : 1.46E-04 : 1.46E-04 : 1.46E-04 : 1.46E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.31E-04 : 2.31E-04 : 1.10E-03 : 2.31E-04 : 2.31E-04 : 2.31E-04 : 2.31E-04 : 2.31E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.48E-04 : 5.48E-04 : 2.65E-03 : 5.48E-04 : 5.48E-04 : 5.48E-04 : 5.48E-04 : 5.48E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-24
TABLE IV-A-21 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 21 VEG AT 4.22 MILES ESE ANNUAL_BETA_AIR_DOSE = 8.04E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.81E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.97E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 2.00E-04 : 2.00E-04 : 9.33E-04 : 2.00E-04 : 2.00E-04 : 2.00E-04 : 2.00E-04 : 2.00E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.18E-04 : 3.18E-04 : 1.51E-03 : 3.18E-04 : 3.18E-04 : 3.18E-04 : 3.18E-04 : 3.18E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 7.54E-04 : 7.54E-04 : 3.65E-03 : 7.54E-04 : 7.54E-04 : 7.54E-04 : 7.54E-04 : 7.54E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-25
TABLE IV-A-22 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 22 VEG AT 1.74 MILES SE ANNUAL_BETA_AIR_DOSE = 4.09E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 9.20E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 6.10E-05 : 6.10E-05 : 6.10E-05 : 6.10E-05 : 6.10E-05 : 6.10E-05 : 6.11E-05 : 1.00E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.02E-03 : 1.02E-03 : 4.75E-03 : 1.02E-03 : 1.02E-03 : 1.02E-03 : 1.02E-03 : 1.02E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.62E-03 : 1.62E-03 : 7.70E-03 : 1.62E-03 : 1.62E-03 : 1.62E-03 : 1.62E-03 : 1.62E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.84E-03 : 3.84E-03 : 1.86E-02 : 3.84E-03 : 3.84E-03 : 3.84E-03 : 3.84E-03 : 3.84E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-26
TABLE IV-A-23 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 23 VEG AT 0.65 MILES SSE ANNUAL_BETA_AIR_DOSE = 4.75E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.07E-03 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 7.08E-04 : 7.08E-04 : 7.08E-04 : 7.08E-04 : 7.08E-04 : 7.08E-04 : 7.09E-04 : 1.16E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.18E-02 : 1.18E-02 : 5.51E-02 : 1.18E-02 : 1.18E-02 : 1.18E-02 : 1.18E-02 : 1.18E-02 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.88E-02 : 1.88E-02 : 8.94E-02 : 1.88E-02 : 1.88E-02 : 1.88E-02 : 1.88E-02 : 1.88E-02 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.45E-02 : 4.45E-02 : 2.16E-01 : 4.45E-02 : 4.45E-02 : 4.45E-02 : 4.45E-02 : 4.45E-02 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-27
TABLE IV-A-24 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 24 VEG AT 0.73 MILES S ANNUAL_BETA_AIR_DOSE = 1.75E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.94E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.61E-04 : 2.61E-04 : 2.61E-04 : 2.61E-04 : 2.61E-04 : 2.61E-04 : 2.62E-04 : 4.29E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 4.37E-03 : 4.37E-03 : 2.04E-02 : 4.37E-03 : 4.37E-03 : 4.37E-03 : 4.37E-03 : 4.37E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 6.94E-03 : 6.94E-03 : 3.30E-02 : 6.94E-03 : 6.94E-03 : 6.94E-03 : 6.94E-03 : 6.94E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.64E-02 : 1.64E-02 : 7.96E-02 : 1.64E-02 : 1.64E-02 : 1.64E-02 : 1.64E-02 : 1.64E-02 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-28
TABLE IV-A-25 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 25 VEG AT 2.00 MILES SSW ANNUAL_BETA_AIR_DOSE = 1.02E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.30E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.52E-05 : 1.52E-05 : 1.52E-05 : 1.52E-05 : 1.52E-05 : 1.52E-05 : 1.53E-05 : 2.51E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 2.55E-04 : 2.55E-04 : 1.19E-03 : 2.55E-04 : 2.55E-04 : 2.55E-04 : 2.55E-04 : 2.55E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.05E-04 : 4.05E-04 : 1.93E-03 : 4.05E-04 : 4.05E-04 : 4.05E-04 : 4.05E-04 : 4.05E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 9.59E-04 : 9.59E-04 : 4.64E-03 : 9.59E-04 : 9.59E-04 : 9.59E-04 : 9.59E-04 : 9.59E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-29
TABLE IV-A-26 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 26 VEG AT 1.43 MILES SW ANNUAL_BETA_AIR_DOSE = 2.32E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.51E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.98E-05 : 2.98E-05 : 2.98E-05 : 2.98E-05 : 2.98E-05 : 2.98E-05 : 2.99E-05 : 4.99E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 8.92E-04 : 8.92E-04 : 4.16E-03 : 8.92E-04 : 8.92E-04 : 8.92E-04 : 8.92E-04 : 8.92E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.42E-03 : 1.42E-03 : 6.74E-03 : 1.42E-03 : 1.42E-03 : 1.42E-03 : 1.42E-03 : 1.42E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.36E-03 : 3.36E-03 : 1.62E-02 : 3.36E-03 : 3.36E-03 : 3.36E-03 : 3.36E-03 : 3.36E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-30
TABLE IV-A-27 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 27 VEG AT 1.13 MILES WSW ANNUAL_BETA_AIR_DOSE = 5.29E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.11E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 7.34E-05 : 7.34E-05 : 7.34E-05 : 7.34E-05 : 7.34E-05 : 7.34E-05 : 7.36E-05 : 1.22E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.67E-03 : 1.67E-03 : 7.81E-03 : 1.67E-03 : 1.67E-03 : 1.67E-03 : 1.67E-03 : 1.67E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.66E-03 : 2.66E-03 : 1.27E-02 : 2.66E-03 : 2.66E-03 : 2.66E-03 : 2.66E-03 : 2.66E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.30E-03 : 6.30E-03 : 3.05E-02 : 6.30E-03 : 6.30E-03 : 6.30E-03 : 6.30E-03 : 6.30E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-31
TABLE IV-A-28 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 28 VEG AT 1.30 MILES W ANNUAL_BETA_AIR_DOSE = 4.38E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 9.05E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 5.99E-05 : 5.99E-05 : 5.99E-05 : 5.99E-05 : 5.99E-05 : 5.99E-05 : 6.00E-05 : 9.95E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 1.44E-03 : 1.44E-03 : 6.70E-03 : 1.44E-03 : 1.44E-03 : 1.44E-03 : 1.44E-03 : 1.44E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.28E-03 : 2.28E-03 : 1.09E-02 : 2.28E-03 : 2.28E-03 : 2.28E-03 : 2.28E-03 : 2.28E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.41E-03 : 5.41E-03 : 2.62E-02 : 5.41E-03 : 5.41E-03 : 5.41E-03 : 5.41E-03 : 5.41E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-32
TABLE IV-A-29 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 29 VEG AT 2.65 MILES WNW ANNUAL_BETA_AIR_DOSE = 8.92E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.45E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 9.50E-06 : 9.50E-06 : 9.50E-06 : 9.50E-06 : 9.50E-06 : 9.50E-06 : 9.55E-06 : 1.63E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 4.73E-04 : 4.73E-04 : 2.21E-03 : 4.73E-04 : 4.73E-04 : 4.73E-04 : 4.73E-04 : 4.73E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 7.52E-04 : 7.52E-04 : 3.58E-03 : 7.52E-04 : 7.52E-04 : 7.52E-04 : 7.52E-04 : 7.52E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.78E-03 : 1.78E-03 : 8.62E-03 : 1.78E-03 : 1.78E-03 : 1.78E-03 : 1.78E-03 : 1.78E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-33
TABLE IV-A-30 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 30 VEG AT 2.40 MILES NW ANNUAL_BETA_AIR_DOSE = 2.52E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.95E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.27E-05 : 3.27E-05 : 3.27E-05 : 3.27E-05 : 3.27E-05 : 3.27E-05 : 3.28E-05 : 5.47E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 9.47E-04 : 9.47E-04 : 4.41E-03 : 9.47E-04 : 9.47E-04 : 9.47E-04 : 9.47E-04 : 9.47E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.50E-03 : 1.50E-03 : 7.15E-03 : 1.50E-03 : 1.50E-03 : 1.50E-03 : 1.50E-03 : 1.50E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.56E-03 : 3.56E-03 : 1.72E-02 : 3.56E-03 : 3.56E-03 : 3.56E-03 : 3.56E-03 : 3.56E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-34
TABLE IV-A-31 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 31 VEG AT 3.73 MILES NNW ANNUAL_BETA_AIR_DOSE = 5.31E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 7.20E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.71E-06 : 4.71E-06 : 4.71E-06 : 4.71E-06 : 4.71E-06 : 4.71E-06 : 4.74E-06 : 8.35E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : : ADULT : 3.46E-04 : 3.46E-04 : 1.61E-03 : 3.46E-04 : 3.46E-04 : 3.46E-04 : 3.46E-04 : 3.46E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.50E-04 : 5.50E-04 : 2.61E-03 : 5.50E-04 : 5.50E-04 : 5.50E-04 : 5.50E-04 : 5.50E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.30E-03 : 1.30E-03 : 6.30E-03 : 1.30E-03 : 1.30E-03 : 1.30E-03 : 1.30E-03 : 1.30E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-35
TABLE IV-A-32 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 32 BEEF AT 4.91 MILES E ANNUAL_BETA_AIR_DOSE = 2.08E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.79E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.82E-06 : 1.82E-06 : 1.82E-06 : 1.82E-06 : 1.82E-06 : 1.82E-06 : 1.84E-06 : 3.24E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 4.86E-05 : 4.86E-05 : 2.36E-04 : 4.86E-05 : 4.86E-05 : 4.86E-05 : 4.86E-05 : 4.86E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.07E-05 : 4.07E-05 : 2.00E-04 : 4.07E-05 : 4.07E-05 : 4.07E-05 : 4.07E-05 : 4.07E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 7.60E-05 : 7.60E-05 : 3.75E-04 : 7.60E-05 : 7.60E-05 : 7.60E-05 : 7.60E-05 : 7.60E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-36
TABLE IV-A-33 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 33 BEEF AT 1.82 MILES SSE ANNUAL_BETA_AIR_DOSE = 3.13E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.29E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.16E-05 : 4.16E-05 : 4.16E-05 : 4.16E-05 : 4.16E-05 : 4.16E-05 : 4.17E-05 : 6.93E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 3.95E-04 : 3.95E-04 : 1.92E-03 : 3.95E-04 : 3.95E-04 : 3.95E-04 : 3.95E-04 : 3.95E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.31E-04 : 3.31E-04 : 1.62E-03 : 3.31E-04 : 3.31E-04 : 3.31E-04 : 3.31E-04 : 3.31E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.18E-04 : 6.18E-04 : 3.05E-03 : 6.18E-04 : 6.18E-04 : 6.18E-04 : 6.18E-04 : 6.18E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-37
TABLE IV-A-34 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 34 BEEF AT 2.48 MILES S ANNUAL_BETA_AIR_DOSE = 8.77E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.97E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.31E-05 : 1.31E-05 : 1.31E-05 : 1.31E-05 : 1.31E-05 : 1.31E-05 : 1.31E-05 : 2.15E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 7.77E-05 : 7.77E-05 : 3.78E-04 : 7.77E-05 : 7.77E-05 : 7.77E-05 : 7.77E-05 : 7.77E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 6.51E-05 : 6.51E-05 : 3.19E-04 : 6.51E-05 : 6.51E-05 : 6.51E-05 : 6.51E-05 : 6.51E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.22E-04 : 1.22E-04 : 6.00E-04 : 1.22E-04 : 1.22E-04 : 1.22E-04 : 1.22E-04 : 1.22E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-38
TABLE IV-A-35 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 35 BEEF AT 0.65 MILES SSW ANNUAL_BETA_AIR_DOSE = 1.39E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.12E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.07E-04 : 2.07E-04 : 2.07E-04 : 2.07E-04 : 2.07E-04 : 2.07E-04 : 2.07E-04 : 3.40E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 1.23E-03 : 1.23E-03 : 5.99E-03 : 1.23E-03 : 1.23E-03 : 1.23E-03 : 1.23E-03 : 1.23E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.03E-03 : 1.03E-03 : 5.06E-03 : 1.03E-03 : 1.03E-03 : 1.03E-03 : 1.03E-03 : 1.03E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.93E-03 : 1.93E-03 : 9.50E-03 : 1.93E-03 : 1.93E-03 : 1.93E-03 : 1.93E-03 : 1.93E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-39
TABLE IV-A-36 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 36 BEEF AT 0.76 MILES SW ANNUAL_BETA_AIR_DOSE = 1.68E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.78E-04 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.50E-04 : 2.50E-04 : 2.50E-04 : 2.50E-04 : 2.50E-04 : 2.50E-04 : 2.51E-04 : 4.12E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 1.49E-03 : 1.49E-03 : 7.25E-03 : 1.49E-03 : 1.49E-03 : 1.49E-03 : 1.49E-03 : 1.49E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.25E-03 : 1.25E-03 : 6.12E-03 : 1.25E-03 : 1.25E-03 : 1.25E-03 : 1.25E-03 : 1.25E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.33E-03 : 2.33E-03 : 1.15E-02 : 2.33E-03 : 2.33E-03 : 2.33E-03 : 2.33E-03 : 2.33E-03 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-40
TABLE IV-A-37 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 37 BEEF AT 2.18 MILES WSW ANNUAL_BETA_AIR_DOSE = 1.39E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.12E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.07E-05 : 2.07E-05 : 2.07E-05 : 2.07E-05 : 2.07E-05 : 2.07E-05 : 2.07E-05 : 3.40E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 1.23E-04 : 1.23E-04 : 5.99E-04 : 1.23E-04 : 1.23E-04 : 1.23E-04 : 1.23E-04 : 1.23E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.03E-04 : 1.03E-04 : 5.06E-04 : 1.03E-04 : 1.03E-04 : 1.03E-04 : 1.03E-04 : 1.03E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.93E-04 : 1.93E-04 : 9.50E-04 : 1.93E-04 : 1.93E-04 : 1.93E-04 : 1.93E-04 : 1.93E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-41
TABLE IV-A-38 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 38 BEEF AT 2.28 MILES W ANNUAL_BETA_AIR_DOSE = 1.61E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.61E-05 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.39E-05 : 2.39E-05 : 2.39E-05 : 2.39E-05 : 2.39E-05 : 2.39E-05 : 2.40E-05 : 3.94E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 1.43E-04 : 1.43E-04 : 6.93E-04 : 1.43E-04 : 1.43E-04 : 1.43E-04 : 1.43E-04 : 1.43E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.19E-04 : 1.19E-04 : 5.85E-04 : 1.19E-04 : 1.19E-04 : 1.19E-04 : 1.19E-04 : 1.19E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.23E-04 : 2.23E-04 : 1.10E-03 : 2.23E-04 : 2.23E-04 : 2.23E-04 : 2.23E-04 : 2.23E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-42
TABLE IV-A-39 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 39 BEEF AT 4.59 MILES WNW ANNUAL_BETA_AIR_DOSE = 2.15E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.67E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.06E-06 : 1.06E-06 : 1.06E-06 : 1.06E-06 : 1.06E-06 : 1.06E-06 : 1.08E-06 : 2.15E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : : ADULT : 7.13E-05 : 7.13E-05 : 3.47E-04 : 7.13E-05 : 7.13E-05 : 7.13E-05 : 7.13E-05 : 7.13E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.97E-05 : 5.97E-05 : 2.93E-04 : 5.97E-05 : 5.97E-05 : 5.97E-05 : 5.97E-05 : 5.97E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.11E-04 : 1.11E-04 : 5.50E-04 : 1.11E-04 : 1.11E-04 : 1.11E-04 : 1.11E-04 : 1.11E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-43
TABLE IV-A-40 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS SPECIAL LOCATION NO. 40 GOAT AT 3.44 MILES S ANNUAL_BETA_AIR_DOSE = 2.93E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 5.84E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.86E-06 : 3.86E-06 : 3.86E-06 : 3.86E-06 : 3.86E-06 : 3.86E-06 : 3.87E-06 : 6.44E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GOATMILK : : : : : : : : : ADULT : 4.48E-05 : 4.48E-05 : 1.99E-04 : 4.48E-05 : 4.48E-05 : 4.48E-05 : 4.48E-05 : 4.48E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 7.99E-05 : 7.99E-05 : 3.68E-04 : 7.99E-05 : 7.99E-05 : 7.99E-05 : 7.99E-05 : 7.99E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.91E-04 : 1.91E-04 : 9.04E-04 : 1.91E-04 : 1.91E-04 : 1.91E-04 : 1.91E-04 : 1.91E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 3.93E-04 : 3.93E-04 : 1.77E-03 : 3.93E-04 : 3.93E-04 : 3.93E-04 : 3.93E-04 : 3.93E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-44
TABLE IV-B-1 FORT CALHOUN 1 DOSE CONTRIBUTIONS FROM GASEOUS EFFLUENTS UNRESTRICTED AREA BOUNDARY JANUARY 1, 2016 TO DECEMBER 31, 2016 MAXIMUM SITE BOUNDARY GAMMA AIR DOSE - 1.28E-03 MILLRADS MAXIMUM SITE BOUNDARY BETA AIR DOSE - 5.70E-04 MILLRADS IV-45
TABLE IV-C-1 FORT CALHOUN ANNUAL 2016, DOSE PROJECTIONS ALARA ANNUAL INTEGRATED POPULATION DOSE
SUMMARY
(PERSON-REM) PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.25E-04 : 1.25E-04 : 1.25E-04 : 1.25E-04 : 1.25E-04 : 1.25E-04 : 1.27E-04 : 2.61E-04 :
- 0.47% : 0.47% : 0.10% : 0.47% : 0.47% : 0.47% : 0.48% : 0.98% :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : 6.64E-04 : 6.64E-04 : 0.00E+00 : 6.64E-04 : 6.64E-04 : 6.64E-04 : 6.64E-04 : 6.64E-04 :
- 2.51% : 2.51% : 0.00% : 2.51% : 2.51% : 2.51% : 2.50% : 2.49% :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : 1.48E-02 : 1.48E-02 : 7.03E-02 : 1.48E-02 : 1.48E-02 : 1.48E-02 : 1.48E-02 : 1.48E-02 :
- 55.81% : 55.81% : 56.93% : 55.81% : 55.81% : 55.81% : 55.81% : 55.52% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
COW MILK : 3.73E-03 : 3.73E-03 : 1.79E-02 : 3.73E-03 : 3.73E-03 : 3.73E-03 : 3.73E-03 : 3.73E-03 :
- 14.08% : 14.08% : 14.52% : 14.08% : 14.08% : 14.08% : 14.08% : 14.01% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : 7.19E-03 : 7.19E-03 : 3.52E-02 : 7.19E-03 : 7.19E-03 : 7.19E-03 : 7.19E-03 : 7.19E-03 :
- 27.14% : 27.14% : 28.45% : 27.14% : 27.14% : 27.14% : 27.13% : 27.00% :
---------+----------+----------+----------+----------+----------+----------+----------+----------+ *TOTAL* : 2.65E-02 : 2.65E-02 : 1.24E-01 : 2.65E-02 : 2.65E-02 : 2.65E-02 : 2.65E-02 : 2.66E-02 :
IV-46
SECTION V DOSE FROM LIQUID EFFLUENTS LADTAP II OUTPUT Technical Specification 5.9.4.a January 1, 2016 - December 31, 2016 V-1
Radioactive Effluent Releases - First, Second, Third, and Fourth Quarters 2016 LIQUID EFFLUENTS During the reporting period, a total of 4.34E-02 curies of radioactive liquid materials less tritium, dissolved noble gases, and alpha were released to the Missouri River at an average concentration of 9.30E-09 Ci/mL. This represents 9.30E-01 percent of the limits specified in Appendix B to 10 CFR 20 (1.0E-06 Ci/mL for unrestricted areas), 149 curies of tritium were discharged at an average diluted concentration of 3.19E-05 Ci/mL or 3.19 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. Ni-63 was identified in the first quarterly composite, and represented 0.85% of the total activity released. Dilution water during the period amounted to 1.16E+12 liters, while liquid waste discharges consisted of 1.06E+08 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, 2016 through December 31, 2016 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 691.4 cubic feet per second (CFS) was utilized for 2016. The average discharge rate during releases was 725.0 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 2016, DOSE PROJECTIONS *
- RADIOLOGICAL ASSESSMENT BRANCH *
- DIVISION OF SYSTEMS INTEGRATION *
- U. S. NUCLEAR REGULATORY COMMISSION *
- WASHINGTON, D. C. *
- DATE OF RUN: 20170308
- V-5
LOCATION IS FRESHWATER INTAKE 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 2.99E-02 4.11E-02 2.70E-02 6.94E-05 1.40E-02 4.67E-03 8.34E-04 DRINKING 1.25E-04 4.95E-04 4.37E-04 3.45E-04 3.83E-04 3.45E-04 3.29E-04 SHORELINE 4.29E-05 3.68E-05 3.68E-05 3.68E-05 3.68E-05 3.68E-05 3.68E-05 3.68E-05 SWIMMING 1.13E-07 1.13E-07 1.13E-07 1.13E-07 1.13E-07 1.13E-07 1.13E-07 BOATING 5.64E-08 5.64E-08 5.64E-08 5.64E-08 5.64E-08 5.64E-08 5.64E-08 TOTAL 4.29E-05 3.01E-02 4.17E-02 2.75E-02 4.51E-04 1.44E-02 5.05E-03 1.20E-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 3.20E-02 4.28E-02 1.50E-02 5.90E-05 1.46E-02 5.68E-03 6.38E-04 DRINKING 1.23E-04 3.91E-04 2.86E-04 2.46E-04 2.85E-04 2.51E-04 2.32E-04 SHORELINE 2.40E-04 2.05E-04 2.05E-04 2.05E-04 2.05E-04 2.05E-04 2.05E-04 2.05E-04 SWIMMING 6.30E-07 6.30E-07 6.30E-07 6.30E-07 6.30E-07 6.30E-07 6.30E-07 BOATING 3.15E-07 3.15E-07 3.15E-07 3.15E-07 3.15E-07 3.15E-07 3.15E-07 TOTAL 2.40E-04 3.24E-02 4.34E-02 1.55E-02 5.11E-04 1.51E-02 6.14E-03 1.08E-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 4.03E-02 3.88E-02 5.76E-03 5.53E-05 1.26E-02 4.56E-03 2.66E-04 DRINKING 3.58E-04 7.80E-04 4.91E-04 4.80E-04 5.51E-04 4.80E-04 4.43E-04 SHORELINE 5.01E-05 4.29E-05 4.29E-05 4.29E-05 4.29E-05 4.29E-05 4.29E-05 4.29E-05 SWIMMING 1.32E-07 1.32E-07 1.32E-07 1.32E-07 1.32E-07 1.32E-07 1.32E-07 BOATING 6.58E-08 6.58E-08 6.58E-08 6.58E-08 6.58E-08 6.58E-08 6.58E-08 TOTAL 5.01E-05 4.07E-02 3.96E-02 6.30E-03 5.78E-04 1.32E-02 5.09E-03 7.52E-04 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 3.69E-04 8.61E-04 4.63E-04 4.94E-04 5.48E-04 4.79E-04 4.34E-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 3.69E-04 8.61E-04 4.63E-04 4.94E-04 5.48E-04 4.79E-04 4.34E-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 2.19E-01 3.00E-01 1.97E-01 5.07E-04 1.02E-01 3.41E-02 6.09E-03 DRINKING 3.85E-03 1.53E-02 1.35E-02 1.06E-02 1.18E-02 1.06E-02 1.01E-02 SHORELINE 3.13E-04 2.69E-04 2.69E-04 2.69E-04 2.69E-04 2.69E-04 2.69E-04 2.69E-04 SWIMMING 8.24E-07 8.24E-07 8.24E-07 8.24E-07 8.24E-07 8.24E-07 8.24E-07 BOATING 4.12E-07 4.12E-07 4.12E-07 4.12E-07 4.12E-07 4.12E-07 4.12E-07 TOTAL 3.13E-04 2.23E-01 3.16E-01 2.11E-01 1.14E-02 1.14E-01 4.50E-02 1.65E-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 2.34E-01 3.13E-01 1.09E-01 4.30E-04 1.06E-01 4.15E-02 4.65E-03 DRINKING 3.78E-03 1.21E-02 8.81E-03 7.58E-03 8.76E-03 7.72E-03 7.15E-03 SHORELINE 1.75E-03 1.50E-03 1.50E-03 1.50E-03 1.50E-03 1.50E-03 1.50E-03 1.50E-03 SWIMMING 4.60E-06 4.60E-06 4.60E-06 4.60E-06 4.60E-06 4.60E-06 4.60E-06 BOATING 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 TOTAL 1.75E-03 2.39E-01 3.26E-01 1.20E-01 9.52E-03 1.17E-01 5.07E-02 1.33E-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 2.94E-01 2.83E-01 4.21E-02 4.04E-04 9.23E-02 3.33E-02 1.94E-03 DRINKING 1.10E-02 2.40E-02 1.51E-02 1.48E-02 1.70E-02 1.48E-02 1.36E-02 SHORELINE 3.66E-04 3.13E-04 3.13E-04 3.13E-04 3.13E-04 3.13E-04 3.13E-04 3.13E-04 SWIMMING 9.61E-07 9.61E-07 9.61E-07 9.61E-07 9.61E-07 9.61E-07 9.61E-07 BOATING 4.81E-07 4.81E-07 4.81E-07 4.81E-07 4.81E-07 4.81E-07 4.81E-07 TOTAL 3.66E-04 3.06E-01 3.07E-01 5.75E-02 1.55E-02 1.10E-01 4.84E-02 1.59E-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 1.14E-02 2.65E-02 1.43E-02 1.53E-02 1.69E-02 1.48E-02 1.34E-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 1.14E-02 2.65E-02 1.43E-02 1.53E-02 1.69E-02 1.48E-02 1.34E-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
__________SPORT HARVEST__________
----------------------------DOSE (PERSON-REM)-------------------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH ADULT 6.10E+04 8.69E-02 1.19E-01 7.84E-02 1.61E-04 4.06E-02 1.35E-02 2.42E-03 FISH TEENAGER 7.12E+03 1.42E-02 1.90E-02 6.66E-03 2.05E-05 6.48E-03 2.53E-03 2.84E-04 FISH CHILD 4.93E+03 2.88E-02 2.77E-02 4.11E-03 3.00E-05 9.02E-03 3.26E-03 1.90E-04 FISH TOTAL 7.30E+04 1.30E-01 1.66E-01 8.92E-02 2.12E-04 5.61E-02 1.93E-02 2.89E-03 LOCATION DILUTION CATCH TIME(HR)-INCLUDES FOOD PROCESSING TIME OF 1.68E+02 HR POPULATION=1.24E+04 7.30E+00 7.30E+04 1.69E+02 AVERAGE INDIVIDUAL CONSUMPTION (KG/YR) ADULT=6.90E+00 TEEN=5.20E+00 CHILD=2.20E+00
* *
- 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 9.88E-03 1.36E-02 8.92E-03 1.69E-05 4.61E-03 1.54E-03 2.75E-04 FISH TEENAGER 4.88E+05 1.62E-03 2.17E-03 7.58E-04 2.11E-06 7.37E-04 2.87E-04 3.22E-05 FISH CHILD 3.38E+05 3.28E-03 3.15E-03 4.68E-04 3.05E-06 1.03E-03 3.70E-04 2.16E-05 FISH TOTAL 5.01E+06 1.48E-02 1.89E-02 1.01E-02 2.20E-05 6.38E-03 2.20E-03 3.29E-04 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 1.74E-01 2.39E-01 1.57E-01 3.10E-04 8.11E-02 2.71E-02 4.84E-03 FISH TEENAGER 1.42E+04 2.85E-02 3.81E-02 1.33E-02 3.91E-05 1.30E-02 5.05E-03 5.67E-04 FISH CHILD 9.85E+03 5.76E-02 5.53E-02 8.23E-03 5.68E-05 1.80E-02 6.51E-03 3.79E-04 FISH TOTAL 1.46E+05 2.60E-01 3.32E-01 1.78E-01 4.05E-04 1.12E-01 3.87E-02 5.78E-03 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 2.38E-02 9.43E-02 8.32E-02 6.55E-02 7.30E-02 6.56E-02 6.27E-02 DRINKING TEENAGER 1.51E+07 3.64E-03 1.16E-02 8.49E-03 7.27E-03 8.44E-03 7.44E-03 6.88E-03 DRINKING CHILD 2.48E+07 1.74E-02 3.79E-02 2.38E-02 2.32E-02 2.68E-02 2.33E-02 2.15E-02 DRINKING TOTAL 1.79E+08 4.48E-02 1.44E-01 1.16E-01 9.59E-02 1.08E-01 9.64E-02 9.11E-02 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 SUPPLIER-COUNCIL BLUFFS
----------------------------DOSE (PERSON-REM)-------------------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI DRINKING ADULT 2.29E+07 3.85E-03 1.53E-02 1.35E-02 1.06E-02 1.18E-02 1.06E-02 1.01E-02 DRINKING TEENAGER 2.49E+06 5.89E-04 1.88E-03 1.37E-03 1.18E-03 1.37E-03 1.20E-03 1.11E-03 DRINKING CHILD 4.07E+06 2.81E-03 6.13E-03 3.86E-03 3.75E-03 4.33E-03 3.77E-03 3.48E-03 DRINKING TOTAL 2.94E+07 7.25E-03 2.33E-02 1.87E-02 1.55E-02 1.75E-02 1.56E-02 1.47E-02 POPULATION=8.70E+04 DILUTION=3.13E+01 TRANSIT TIME=3.10E+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 5.21E-02 1.67E-01 1.34E-01 1.11E-01 1.26E-01 1.12E-01 1.06E-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 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.13E-03 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 1.47E-01 1.26E-01 1.26E-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 3.85E-04 3.85E-04 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 1.93E-04 1.93E-04
- *
- DOSE TO BIOTA * *
- MRADS PER YEAR BIOTA DILUTION= 1.00E+00 TRANSIT TIME= 0.00E+00 HR INTERNAL EXTERNAL TOTAL FISH 6.59E-01 9.81E-01 1.64E+00 INVERTEBRATE 3.37E-01 1.96E+00 2.30E+00 ALGAE 1.69E-01 6.01E-04 1.70E-01 MUSKRAT 3.58E+00 6.54E-01 4.24E+00 RACCOON 1.33E+00 4.90E-01 1.83E+00 HERON 2.08E+01 6.54E-01 2.15E+01 DUCK 3.27E+00 9.81E-01 4.25E+00 V-12
SECTION VI RADIOACTIVE EFFLUENT RELEASES - SOLID RADIOACTIVE WASTE Technical Specifications 5.9.4.a January 1, 2016 - December 31, 2016 VI-1
VI. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT January 1, 2016 through December 31, 2016 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED) Month Number of Volume Curie Est. Total
- 1. Type of Waste Shipped Shipments Cu. Meter Content % Error
- a. Spent resins, filter January 0 0 0 N/A sludges, evaporator February 0 0 0 N/A bottoms, etc. March 0 0 0 N/A April 0 0 0 N/A May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A September 0 0 0 N/A October 0 0 0 N/A November 0 0 0 N/A December 0 0 0 N/A Total (Type a) 0 0 0 N/A
- b. Dry compressible, January 0 0 0 N/A contaminated equipment, February 0 0 0 N/A etc. March 0 0 0 N/A April 1 32.79 1.77E-02 20 May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A September 0 0 0 N/A October 0 0 0 N/A November 0 0 0 N/A December 1 36.25 3.87E-03 20 Total (Type b) 2 69.04 2.16E-02 20 VI-2
VI. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT (Continued) Month Number of Volume Curie Est. Total
- 1. Type of Waste Shipped Shipments Cu. Meter Content % Error
- c. Irradiated components January 0 0 0 N/A and other categories. February 0 0 0 N/A March 0 0 0 N/A April 0 0 0 N/A May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A September 0 0 0 N/A October 0 0 0 N/A November 0 0 0 N/A December 0 0 0 N/A Total (Type c) 0 0 0 N/A
- d. Other January 0 0 0 N/A February 0 0 0 N/A March 0 0 0 N/A April 0 0 0 N/A May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A September 0 0 0 N/A October 0 0 0 N/A November 0 0 0 N/A December 0 0 0 N/A Total (Type d) 0 0 0 N/A VI-3
III. RADIOACTIVE EFFLUENT RELEASES-SOLID RADIOACTIVE (Continued) B. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (By Type of Waste)
- 1. Percentage of Curies from Represented Isotopes Isotope Percent Curies
- a. N/A N/A N/A
- b. Cs-137 24.6 1.33E-04 Ni-63 17.5 9.43E-05 Nb-95 16.5 8.93E-02 Co-60 12.4 6.71E-05 Zr-95 9.3 5.04E-05 Fe-55 8.6 4.64E-02 Cr-51 6.4 3.45E-05 Co-58 2.6 1.40E-05 All Other Nuclides Constitute Less than 1%
- c. N/A N/A N/A
- d. N/A N/A N/A C. SOLID WASTE (DISPOSITION)
Number of Shipments Transportation Mode Destination 2 Sole Use Vehicle Energy Solutions, Bear Creek TN D. IRRADIATED FUEL SHIPMENTS (DISPOSITION) Number of Shipments Transportation Mode Destination N/A N/A N/A VI-4
SECTION VII ATTACHMENT 1 ODCM and PCP revisions for the period January 1, 2016 through December 31, 2016 in accordance with Technical Specification 5.17.d and 5.18.d, the radioactive effluent release report shall include any revisions to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP). ____1__ revisions were made to the Offsite Dose Calculation Manual (ODCM). ____0__ revisions were made to the Process Control Program (PCP). January 1, 2016 - December 31, 2016 VII-1
Page 1 of 130 CH-ODCM-0001 Off-Site Dose Calculation Manual (ODCM) Revision 25 Safety Classification: Usage Level: Non-Safety Reference Change No.: EC 68214 Reason for Change: Removed the term Plant Review Committee and replaced with Plant Operations Review Committee Requestor: R. Layman Preparer: J. Shirah Issued: 06-30-16 3:00 pm Fort Calhoun Station
CH-ODCM-0001 Reference Use Page 2 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 ......................................................... 14 4.0 RADIOACTIVE EFFLUENTS ........................................................................................ 20 4.1 Radioactive Liquid Effluents ..................................................................................... 20 4.2 Radioactive Gaseous Effluents ................................................................................ 26 4.3 Uranium Fuel Cycle .................................................................................................. 35 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) .................. 36 5.1 Monitoring Program .................................................................................................. 36 5.2 Land Use Survey ...................................................................................................... 48 5.3 Interlaboratory Comparison Program ....................................................................... 49 6.0 ADMINISTRATIVE CONTROLS.................................................................................... 50 6.1 Responsibilities ........................................................................................................ 50 6.2 Radioactive Effluent Reporting Requirements .......................................................... 50 6.3 Change Mechanism.................................................................................................. 53 6.4 Meteorological Data.................................................................................................. 54 6.5 References ............................................................................................................... 54 7.0 BASIS ............................................................................................................................ 55 7.1 Instrumentation ......................................................................................................... 55 7.2 Radioactive Effluents ................................................................................................ 56 7.3 Radiological Environmental Monitoring .................................................................... 63 7.4 Abnormal Release or Abnormal Discharge Reporting .............................................. 64
CH-ODCM-0001 Reference Use Page 3 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 ........................................................................................................................ 13 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation ............................... 15 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .................................................................................................... 19 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis ............................................. 22 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis ......................................... 27 Table 4.3 - Sampler Deposition/Transportation Correction Factors ....................................... 29 Table 5.1 - Radiological Environmental Monitoring Program ................................................. 38 Table 5.2 - Radiological Environmental Sampling Locations And Media ............................... 40 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) .................................................................................................................... 46 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples ........................................................................................................ 47 List of Figures PART I Figure 1 - Environmental Radiological Sampling Points ....................................................... 45
CH-ODCM-0001 Reference Use Page 4 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table of Contents PART II 1.0 EFFLUENT MONITOR SETPOINTS ............................................................................. 67 1.1 Liquid Effluents ......................................................................................................... 67 1.2 Airborne Effluents ..................................................................................................... 72 2.0 EFFLUENT CONCENTRATIONS ................................................................................. 85 2.1 Liquid Effluent Concentrations .................................................................................. 85 2.2 Airborne Effluent Concentrations .............................................................................. 86 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS ................................................... 87 3.1 Liquid Effluent Dose Calculations ............................................................................. 87 3.2 Airborne Effluent Dose Calculations ......................................................................... 91 4.0 LOWER LIMIT OF DETECTION (LLD) ....................................................................... 104 List of Tables PART II Table 1 - Allocation Factors for Simultaneous Releases ....................................................... 79 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases ................... 105 Table 3 - Bioaccumulation Factors ...................................................................................... 106 Table 4 - Highest Potential Exposure Pathways for Estimating Dose.................................. 107 Table 5 - Stable Element Transfer Data .............................................................................. 108 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data................................................................. 109 Table 7 - Animal Consumption Rates .................................................................................. 109 Table 8 - External Dose Factors for Standing on Contaminated Ground ............................. 110 Table 9 - Inhalation Dose Factors for Adult ......................................................................... 112 Table 10 - Inhalation Dose Factors for Teenager ................................................................ 114 Table 11 - Inhalation Dose Factors for Child ....................................................................... 116 Table 12 - Inhalation Dose Factors for Infant ...................................................................... 118 Table 13 - Ingestion Dose Factors for Adult ........................................................................ 120 Table 14 - Ingestion Dose Factors for Teenager ................................................................. 122 Table 15 - Ingestion Dose Factors for Child ........................................................................ 124 Table 16 - Ingestion Dose Factors for Infant ....................................................................... 126 Table 17 - Recommended Values for Other Parameters ..................................................... 128 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure ........ 130
CH-ODCM-0001 Reference Use Page 5 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 List of Figures PART II Figure 1 - Exclusion and Site Boundary Map ........................................................................ 80 Figure 2 - Liquid Radioactive Discharge Pathways ............................................................... 81 Figure 3 - Liquid Radioactive Waste Disposal System .......................................................... 82 Figure 4 - Airborne Effluent Discharge Pathways .................................................................. 83 Figure 5 - Airborne Radioactive Waste Disposal System ...................................................... 84
CH-ODCM-0001 Reference Use Page 6 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 operations. 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 plant environs provides the basis for ensuring that station operation is 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 plant-related, licensed radioactive material) into the unrestricted area. 2.2 Abnormal Release - The unplanned or uncontrolled emission of an effluent (i.e., containing plant-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 operable, 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 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 2.7 Operable-Operability - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety 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 specified safety function(s) are also capable of performing their related support function(s). 2.8 Purge-Purging - PURGE or PURGING shall be any 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 required to purify the confinement. 2.9 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. 2.10 Site Boundary - The Site Boundary is the line beyond which the land is neither owned, or leased, nor controlled by the licensee. 2.11 Source Check - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. 2.12 Special Liquid - Non-routine release pathway in which normally non-radioactive 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. 2.13 Unrestricted Area - An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. 2.14 Venting - VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. 2.15 Water Effluent Concentration (WEC) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.
CH-ODCM-0001 Reference Use Page 8 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 Refueling 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 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation Technical Specification ODCM Implementing Step 5.16.1.a 3.1.1, 3.2.1 5.16.1.b 4.1.1 5.16.1.c Table 4.1, Table 4.2 5.16.1.d 4.1.2 5.16.1.e 4.1.2B.1, 4.2.2B.1 5.16.1.f 4.1.3A, 4.2.4A 5.16.1.g 4.2.1 5.16.1.h 4.2.2 5.16.1.i 4.2.3 5.16.1.j 4.3.1 5.16.2.a 5.1.1 5.16.2.b 5.2.1 5.16.2.c 5.3.1 5.17 6.3, 6.2.1D 5.18 6.2.1D
CH-ODCM-0001 Reference Use Page 10 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 OPERABLE 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 inoperable.
- 2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels operable, take the action shown in Table 3.1.1. Restore inoperable effluent monitoring instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this inoperability was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent streams: RM-055, RM-054A, and RM-054B.
3.1.2 Surveillance Requirements A. Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE 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 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrument Operable Action
- 1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release.
1.1 Liquid Radwaste Effluent Line (RM-055) 1 1, 5 1.2 Steam Generator Blowdown Effluent Line (RM-054A and B) 1A 2, 5
- 2. Flow Rate Measurement Devices 2.1 Liquid Radwaste Effluent Line 1 3 2.2 Steam Generator Blowdown Effluent Line 1 3
- 3. Radioactivity Recorders 3.1 Liquid Radwaste Effluent Line 1 4 3.2 Steam Generator Blowdown Effluent Line 1 4 A. If one of the two radiation monitors is inoperable, the activity of both blowdown lines shall be monitored by the operable monitor within 2 hours of the declaration of inoperability by the Shift Manager, or the action steps of ACTION 2, Table 3.1.1 should be performed on the Steam Generator that is not being monitored.
CH-ODCM-0001 Reference Use Page 12 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 3.1.1 (continued) Table Notation ACTION 1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE 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 OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that grab samples are analyzed for principal gamma emitters at a sensitivity of 5.0E-07 Ci/gram:
- 1. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 Ci/gram dose equivalent I-131.
- 2. At least daily when the specific activity of the secondary coolant is less than or equal to 0.01 Ci/gram equivalent I-131. Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided the flow rate is determined at least once per four hours during the actual release. ACTION 4 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided the radioactivity is recorded manually at least once per four hours during the actual release. ACTION 5 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. 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 inoperable monitor or terminate the effluent release.
CH-ODCM-0001 Reference Use Page 13 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 3.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Function Check Calibration Check Test
- 1. Radioactivity Monitors Providing Alarm and Automatic Isolation 1.1 RM-054A/054B DA R Q M 1.2 RM-055 ---- R Q P
- 2. Flowrate Monitors 2.1 Steam Generator Blowdown D R Q ----
A. Visual Flowcheck Daily
CH-ODCM-0001 Reference Use Page 14 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.2.1 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 gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
- 2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Table 3.2.1. Restore inoperable effluent monitoring instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this inoperability was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent streams: RM-057, RM-043, RM-062, RM-063, and RM-052.
3.2.2 Surveillance Requirements A. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.2.2.
CH-ODCM-0001 Reference Use Page 15 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Channels Action Operable
- 1. Auxiliary Bldg. Exhaust Stack (RM-052, RM-062) 1.1 Noble Gas 1 1, 9, 11 1.2 Iodine and Particulate 1 2, 9, 11
- 2. Laboratory and Radwaste Processing Building Stack (RM-043) 2.1 Noble Gas 1 3, 9 2.2 Iodine and Particulate 1 4, 9
- 3. Condenser Off Gas (RM-057) 3.1 Noble Gas 1 5, 9
- 4. Containment Purge Line (RM-051, RM-052) 4.1 Noble Gas 1 1, 6, 9, 11, 12 4.2 Iodine and Particulate 1 2, 9, 11, 12
- 5. Containment Pressure Relief Line (RM-051, RM-052) 5.1 Noble Gas 1 1, 9, 11 5.2 Iodine and Particulate 1 2, 9, 11
- 6. Containment Penetrations M72 and M74 (Integrated Leak Rate Test Depressurization Vent Path) N/A 10
- 7. Flow Rate Measurement Devices 7.1 Waste Gas Discharge Header 1 7
CH-ODCM-0001 Reference Use Page 16 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Channels Action Operable 7.2 Auxiliary Building Stack 1 7 7.3 Laboratory and Radwaste Processing Building Stack 1 7 7.4 Containment Purge Line 1 7 7.5 Containment Pressure Relief Line Annubar D/P 1 7
- 8. Radioactivity Chart Recorders 8.1 Auxiliary Building Exhaust Stack 1 8
CH-ODCM-0001 Reference Use Page 17 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 3.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation TABLE NOTATION ACTION 1 If the Auxiliary Building Exhaust Stack Noble Gas Monitor is inoperable, releases from the containment pressure relief line and the containment purge line are to be secured in the most expeditious manner. Ventilation of the auxiliary building via the Auxiliary Building Exhaust Stack may continue provided grab samples are taken once per 12 hours. (See Table 4.2) ACTION 2 If the Auxiliary Building Exhaust Stack Iodine and Particulate Sampler is inoperable, ventilation of the Auxiliary Building and releases from the gaseous waste discharge header, containment pressure relief line or the containment purge line 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 inoperability by the Shift Manager. ACTION 3 If the Noble Gas Monitor is inoperable, ventilation of the LRWPB may continue via the LRWPB stack provided grab samples are taken at least once per 12 hours. (See Table 4.2) ACTION 4 If the Iodine and Particulate Sampler is inoperable, 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 inoperability, by the Shift Manager, in accordance with Table 4.2. ACTION 5 During power operation, when the condenser air ejector is in service, the condenser off gas discharge shall be monitored for gross radioactivity. If this monitor is inoperable, grab samples are taken at least once per 12 hours. (See Table 4.2) ACTION 6 The release of airborne effluents from the Containment purge line will be secured if a noble gas monitor is unavailable to monitor the containment building atmosphere. ACTION 7 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided the flowrate is estimated or recorded manually at least once per four hours during the actual release. ACTION 8 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided the radioactivity level is recorded manually at least once per four hours during the actual release. ACTION 9 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered inoperable. 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 inoperable monitor or terminate the effluent release.
CH-ODCM-0001 Reference Use Page 18 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 3.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation TABLE NOTATION ACTION 10 Automatic release termination capability is not required provided manual isolation can be accomplished in accordance with the requirements of SE-ST-ILRT-0001, Containment Integrated Leakage Rate Test (CILRT). ACTION 11 During the ventilation of airborne effluents from the Auxiliary Building Stack at least one Auxiliary Building Exhaust fan shall be in operation. ACTION 12 IF containment purges are made without processing through at least one of the Containment Air Cooling and Filtering Units, and it is confirmed that one half of the annual dose objective listed in Section 4.2.2 will be exceeded during the calendar quarter, a special report shall be submitted to the NRC as defined in Section 4.2.4.
CH-ODCM-0001 Reference Use Page 19 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Calibration Function Check Check Test
- 1. Radioactivity Monitors Providing Alarm and Automatic Isolation 1.1 RM-043 D R Q M 1.2 RM-057 D R Q M 1.3 RM-062 D R Q M, P 1.4 RM-052 A D R Q M, PA
- 2. Flowrate Monitors 2.1 RM-043 Sampler D R Q ----
2.2 RM-062 Sampler D R Q ---- 2.3 RM-052 Sampler D R Q ---- 2.4 Auxiliary Bldg Exhaust Stack D R Q ---- 2.5 Laboratory and Radwaste Process Bldg Exhaust Stack D R Q ---- Operations Check Air Flow Calibration
- 3. Environmental Monitors 3.1 RM-023 - Sample Station #40 M A 3.2 RM-024 - Sample Station #41 M A 3.3 RM-025 - Sample Station #28 ---- ----
3.4 RM-026 - Sample Station #36 ---- ---- 3.5 RM-027 - Sample Station #37 M A 3.6 RM-028 - Sample Station #38 ---- ---- 3.7 RM-029 - Sample Station #39 ---- ---- 3.8 RM-035 - Sample Station #1 ---- ---- 3.9 RM-036 - Sample Station #2 M A 3.10 RM-037 - Sample Station #3 ---- ---- 3.11 RM-038 - Sample Station #4 M A 3.12 RM-039 - Sample Station #5 ---- ---- 3.13 RM-040 - Sample Station #32 M A A. Required when RM-052 is sampling the Auxiliary Building Exhaust Stack.
CH-ODCM-0001 Reference Use Page 20 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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, other than dissolved or entrained noble gases, do not exceed the values specified in 10 CFR Part 20 for liquid effluents at site discharge. To support plant operations, Supervisor-System Chemistry may increase this limit up to the limit specified in Technical Specifications 5.16.1.b. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/ml, total activity.
- 2. Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/ml total activity.
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.
B. Surveillance Requirements NOTE i Radioactive liquid waste includes water used for fire suppression in areas of the plant that may contain radioactivity. These liquids are required to be i monitored prior to release in accordance with SO-G-28.
- 1. Radioactive liquid waste shall be sampled and analyzed according to the sampling and analysis program in Table 4.1.
CH-ODCM-0001 Reference Use Page 21 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25
- 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 Technical Specification 5.16.1.b.
4.1.1B (continued)
- 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 22 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 Each Batch I-131 1.0E-06 Dissolved Noble Gases Each Batch (Gamma Emitters) B 1.0E-05 Monthly Composite D H-3 1.0E-05 Monthly Composite D Gross Alpha 1.0E-07 Quarterly Composite D Sr-89, Sr-90 5.0E-08 Quarterly Composite D Fe-55 1.0E-06 B. Steam Generator Blowdown Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly Composite D Principal Gamma Emitters B 5.0E-07 Weekly Composite D I-131 C 1.0E-06 Dissolved Noble Gases (Gamma Weekly Composite D Emitters) B 1.0E-05 Monthly Composite D H-3 1.0E-05 D Monthly Composite Gross Alpha 1.0E-07 D Quarterly Composite Sr-89, Sr-90 5.0E-08 Quarterly Composite D Fe-55 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: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved or entrained gases and 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. A weekly grab sample and analyses program including gamma isotopic identification will be initiated for the turbine building sump effluent when the steam generator blowdown water composite analysis indicates the I-131 concentration is greater than 1.0E-06 Ci/ml. D. 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 23 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 6.2.3, 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 24 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 4.1.3 Liquid Radwaste Treatment A. Limiting Condition for Operation
- 1. The Liquid Radwaste Treatment System shall be OPERABLE, 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 operable and reasons for inoperability.
- 2) Action(s) taken to restore the inoperable equipment to operable 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 OPERABLE.
- 2. OPERABLE 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 25 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 inoperability of these filters does not affect the dose contributions to any individual in the unrestricted areas via liquid pathways. The inoperability 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 tank=s contents at least once per 7 days when radioactive material is being added to the tank.
CH-ODCM-0001 Reference Use Page 26 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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. To support plant operations, Supervisor-System Chemistry may increase this limit up to the limits specified in Technical Specification 5.16.1.g.
- 2. Technical Specification 5.16.1.g establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.
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 i fire suppression systems are utilized or where smoke is produced as a result of fire in areas of the plant that may contain radioactivity. These atmospheres are required to be monitored prior to gaseous release to unrestricted areas in accordance with SO-G-28.
- 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 27 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis A. Gas Decay Tank Releases Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Prior to each release Principal Gamma Emitters B 1.0E-04 B. Containment Purge Releases or Containment Pressure Relief Line Releases E Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Prior to each release Principal Gamma Emitters B 1.0E-04 Prior to each release H-3 1.0E-06 C. Condenser Off Gas Releases E Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Monthly C Tritium (H-3) 1.0E-06 Monthly Principal Gamma Emitters B 1.0E-04 D. Auxiliary Building Exhaust Stack E Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Charcoal Sample) I-131 1.0E-12 Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly (Noble Gases) Principal Gamma Emitters B 1.0E-4 Weekly Tritium (H-3) 1.0E-06 Monthly Composite D Gross Alpha 1.0E-11 Quarterly Composite (Particulate Samples) Sr-89, Sr-90 1.0E-11
CH-ODCM-0001 Reference Use Page 28 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis E. Laboratory and Radwaste Building Exhaust Stack E Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Charcoal Sample) I-131 1.0E-12 Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly (Noble Gases) Principal Gamma Emitters B 1.0E-4 Monthly Composite D Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-89, 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: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for Iodine and particulate releases. C. Required only when steam generator blowdown radioactivity for tritium (Table 4.1, Item B) exceeds 3.0E-03 Ci/milliliter. D. Frequency requirement may be satisfied using weekly gross alpha results from particulate sampling media. E. Particulate and Iodine 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 29 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 4.3 - Sampler Deposition/Transportation Correction Factors Particulate Iodine Sampler Sample DF ACTMULT DF ACTMULT RM-062 AB 0.411 2.433 0.669 1.495 RM-052 AB 0.638 1.567 0.653 1.531 RM-052 CONT 0.525 1.905 0.688 1.453 RM-051 CONT 0.624 1.603 0.714 1.401 RM-043 LRWPB 0.809 1.236 0.873 1.236 PORTABLE CONT 1.000 1.000 0.950 1.053 ACRONYM DEFINITIONS: AB - Auxiliary Building Exhaust Stack CONT - Containment Building 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 30 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 4.2.2 Dose - Noble Gases A. Limiting Condition for Operation
- 1. The dose or dose commitment to an individual at the site boundary from release of noble gases in airborne effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of noble gases in airborne effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from radioactive 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 Dose - I-131, I-133, H-3, C-14, 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 I-131, I-133, H-3, C-14, 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
CH-ODCM-0001 Reference Use Page 31 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 4.2.3A.1 (continued)
- 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 I-131, I-133, H-3, C-14, 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 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from I-131, I-133, H-3, C-14 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.
4.2.4 Gaseous Radwaste Treatment A. Limiting Condition for Operation
- 1. In accordance with Technical Specification 5.16.1.f, the Waste Gas System and the Ventilation Exhaust Systems shall be OPERABLE, and appropriate portions of these systems shall be used to reduce the releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed:
- a. 0.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC
CH-ODCM-0001 Reference Use Page 32 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 4.2.4A.1 (continued) 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 operable and reasons for inoperability.
- 2) Action(s) taken to restore the inoperable equipment to operable 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 Waste Gas Systems and Ventilation Exhaust Systems are not fully OPERABLE.
CH-ODCM-0001 Reference Use Page 33 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 4.2.4B (continued)
- 2. OPERABLE is defined as follows:
- a. Waste Gas System
- 1) The waste airborne radioactive material at Fort Calhoun Station is collected in the vent header where the gas compressors take suction, compress the gas and deliver it to one of the four gas decay tanks. The waste airborne radioactive material is treated in these gas decay tanks by holding for radioactive decay prior to final controlled release to the environs. In order to provide conformance with the dose design objectives, gas decay tanks are normally stored for approximately 30 days and thus achieve decay of short half-life radioactive materials, e.g.,
I-131, Xe-133. Earlier release is allowed when a plant need exists and analytical results are in accordance with ALARA release objectives. If the radioactive airborne wastes from the gas decay tanks are discharged without processing in accordance with the above conditions, 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 4.2.4A.
- b. 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, a special report shall be submitted to the NRC as defined in Action 4.2.4B.2.a above.
- 2) The discharge from the gas decay tanks is routed through charcoal and HEPA filter unit VA-82. No credit was taken for the operation of hydrogen purge filters during the 10 CFR Part 50, Appendix I dose design evaluation and doses through the airborne effluent pathways were well below the design objectives. The unavailability of hydrogen purge filters will not be considered a reportable event.
CH-ODCM-0001 Reference Use Page 34 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 4.2.4B.2.b (continued)
- 3) The containment air is processed through at least one of the redundant containment HEPA and charcoal filters in the Containment Air Cooling and Filtering Units prior to purging. If the containment purges are made without processing through one of the Containment Air Cooling and Filtering Units, 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 NRC as defined in Action 4.2.4B.2.a above.
CH-ODCM-0001 Reference Use Page 35 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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, 4.2.2A, or 4.2.3A, calculations shall be made including direct radiation contribution from the plant 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 Technical Specification 5.16 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 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. 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 36 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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, 4.2.2B and 4.2.3B 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 plant operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.3). 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 37 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 plant operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.3). 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 plant operations, state and local authorities shall be notified by the end of the next business day. NRC shall be notified per SO-R-1, Reportability Determinations. [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-ST-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 38 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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, one Gamma dose Quarterly background stationF, total of 15.
B. An inner-ring of 16 stations, one in each cardinal sector in the Gamma dose Quarterly general area of the unrestricted area boundary and within 2.5 miles. C. An outer-ring of 16 stations, one in each cardinal sector located Gamma dose Quarterly outside of the inner-ring, but no more distant than approximately 5 miles.
- 2. Air Monitoring A. Indicator Stations Filter for Gross Beta C Weekly
- 1. Three stations in the general Charcoal for I-131 Weekly area of the unrestricted area boundary Filter for Gamma Isotopic Quarterly composite
- 2. City of Blair of weekly filters
- 3. Desoto Township B. One background station F
- 3. Water A. Missouri River at nearest Gamma Isotopic, H-3 Composite downstream drinking water sample over intake. I131 analysis on each 2 week period composite when the dose when I131 B. Missouri River downstream near calculated for the analysis is the mixing zone. consumption of water is performed,
> 1 mrem/yearG monthly C. Missouri River upstream of Plant otherwise for intake (background)F. Gamma isotopic analysis.
Quarterly composite for H-3 Analysis
- 4. Milk D A. Nearest milk animal (cow or Gamma Isotopic and I-131 Biweekly goat) within 5 miles grazing season (May to B. Milk animal (cow or goat) October),
between 5 miles and monthly at 18.75 miles (background)F. other times
- 5. Fish A. Four fish samples within vicinity Gamma Isotopic Once per of Plant discharge. season (May to B. One background sample October) upstream of Plant discharge.
CH-ODCM-0001 Reference Use Page 39 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 6. Sediment A. One sample from downstream Gamma Isotopic Semiannually area on the station side of the Missouri River.
B. One sample from upstream of Plant Intake (background)F.
- 7. 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.
- 8. Groundwater A. Three samples from sources H3, Gross Beta, Gamma Quarterly potentially affected by plant Isotopic, Sr-90 operations.
B. One sample outside of 5 miles (background)F.
- 9. 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. 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 plant, 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". G. The dose shall be calculated for the maximum organ and age group, using methodology and parameters in the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 40 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 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 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 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 41 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 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 20D Mohr Dairy 9.86 186°/S J B 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 42 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 28 Alvin Pechnik Farm 0.94 163°/SSE H X 29A 30A 31A 32D Valley Substation #902 19.6 221°/SW L X 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 X A 38 39A 40A 41C Dowler Acreage 0.73 175°/S J X X X B,C 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 43 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 48 Sector G-1 1.99 134°/SE G X 49 Sector H-1 1.04 159°/SSE H X 50 Sector J-1 0.71 179°/SOUTH J X 51 Sector K-1 0.61 205°/SSW K X 52 Sector L-1 0.74 229°/SW L X 53 Sector M-1 0.93 248°/WSW M X 54 Sector N-1 1.31 266°/WEST N X 55 Sector P-1 0.60 291°/WNW P X 56 Sector Q-1 0.67 307°/NW Q X 57 Sector R-1 2.32 328°/NNW R X 58 Sector A-2 4.54 350°/NORTH A X 59 Sector B-2 2.95 26°/NNE B X 60 Sector C-2 3.32 50°/NE C X 61 Sector D-2 3.11 75°/ENE D X 62 Sector E-2 2.51 90°/EAST E X 63 Sector F-2 2.91 110°/ESE F X 64 Sector G-2 3.00 140°/SE G X 65 Sector H-2 2.58 154°/SSE H X 66 Sector J-2 3.53 181°/SOUTH J X 67 Sector K-2 2.52 205°/SSW K X 68 Sector L-2 2.77 214°/SW L X 69 Sector M-2 2.86 243°/WSW M X
CH-ODCM-0001 Reference Use Page 44 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 70 Sector N-2 2.54 263°/WEST N X 71 Sector P-2 2.99 299°/WNW P X 72 Sector Q-2 3.37 311°/NW Q X 73 Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X C B, C 75 Lomp Acreage 0.65 163°/SSE H X X X X 76 Stangl Farm 3.40 169°/S J X 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 plant, 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.
CH-ODCM-0001 Reference Use Page 45 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Figure 1 - Environmenta l Radiological Sampling Points N (*) Locations currently discontinued are not illustrated.
CH-ODCM-0001 Reference Use Page 46 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 I-131 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 1.0E+00D 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 --- --- --- --- --- --- --- --- 1.0E+00 1.5E+01 1.8E+01 1.5E+01 Airborne Particulates or Gases pCi/m3 1.0E-02 --- --- --- --- --- --- --- 7.0E-02 1.0E-02 1.0E-02 --- pCi/kg Sediment (dry) --- --- --- --- --- --- --- --- --- 1.5E+02 1.8E+02 --- Grass or Broad E E E Leaf Vegetation/ Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 6.0E+01 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 Plant 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. D. LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used. E. I-131 analysis performed on broadleaf/pasture grass samples when milk is unavailable. Gamma isotopic analysis performed on food products/vegetables.
CH-ODCM-0001 Reference Use Page 47 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 I-131 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 2.0E+00B 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 --- --- --- --- --- --- --- --- 3.0E+00 6.0E+01 7.0E+01 3.0E+02 Airborne Particulates or pCi/m3 Gases --- --- --- --- --- --- --- --- 9.0E-01 1.0E+01 2.0E+01 --- Grass or Broad Leaf Vegetation/ Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 1.0E+02 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 Plant 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 Plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
B. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
CH-ODCM-0001 Reference Use Page 48 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 Plant 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 plant 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 49 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 50 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibilities 6.1.1 FCS Chemistry Department is responsible for the implementation and maintenance of the Off-Site Dose Calculation Manual. 6.1.2 FCS Operations Department 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 Technical Specifications 5.9.4.a. 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 plant as outlined in Regulatory Guide 1.21, Revision 2. B. A summary of the annual meteorological data that provides joint frequency distributions of wind direction and wind speed by atmospheric stability class will be included in the annual report. In addition, hourly meteorological data is recorded and retained on site as outlined in Regulatory Guide 1.21, Revision 2. 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 51 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 OPERABLE 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 OPERABLE, causing the limits of specifications 4.1.3A and 4.2.4A 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 plant 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.
CH-ODCM-0001 Reference Use Page 52 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 6.2.2 (continued) E. The results of specific activity analysis in which the primary coolant exceeded the limits of Technical Specification 2.1.3. The following information shall be included:
- 1. Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded.
- 2. Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations.
- 3. Purification system flow history starting 48 hours prior to the first sample in which the limit was exceeded.
- 4. Graph of the I-131 concentration and one other radioiodine isotope concentration in micro-curies per gram as a function of time for the duration of the specific activity above the steadystate level, AND
- 5. The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
F. A map of the current environmental monitoring sample locations. 6.2.3 Special Report If the limits or requirements of Sections 4.1.2A, 4.1.3A, 4.2.2A, 4.2.3A, 4.2.4A, 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 Technical Specification 5.16. 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.
CH-ODCM-0001 Reference Use Page 53 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 6.2.4 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, 4.2.2A, or 4.2.3A, 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. 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 Technical Specification 5.8. It will be revised and reviewed by the Plant Operations Review Committee and approved by the Plant Manager in accordance with Technical Specification 5.17. 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 Technical Specification 5.17.
CH-ODCM-0001 Reference Use Page 54 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 6.4 Meteorological Data The Annual 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 each of the three previous year 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. When calculating /Q data for the Annual Radiological Effluent Release Report, if the highest calculated /Q for the reporting period is observed to be greater than +/- 10% of the Annual Average /Q previously calculated, contact the Supervisor-System Chemistry for further instructions. This model conforms with the Nuclear Regulatory Commissions Regulatory Guide 1.111. Current year meteorological data will be utilized in the preparation of the Annual Radioactive Effluent Release Report. This 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. 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.
CH-ODCM-0001 Reference Use Page 55 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 40, Part 190 6.5.12 Fort Calhoun Revised Environmental Report (Unit No. 1)-1972 6.5.13 Fort Calhoun Technical Specifications (Unit No. 1) 6.5.14 Updated Safety Analysis Report 6.5.15 AR 12357, Implement Recommendations of Memo FC-0133-92, Part I, Table 3.2.1 Action 4, of the Off-Site Calculation Manual 6.5.16 AR 39127, NEI Industry Initiative on Groundwater Protection 6.5.17 Regulatory Guide 4.1, Rev. 2 - Radiological Environmental Monitoring for Nuclear Power Plants 6.5.18 SO-G Station Fire Plan 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 OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
CH-ODCM-0001 Reference Use Page 56 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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. 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 OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. 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. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-133 is the controlling isotope and its effluent concentration in air (submersion) was converted to an equivalent concentration in water.
CH-ODCM-0001 Reference Use Page 57 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 7.2.1 (continued) 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 plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in Part II of the 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 OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix I to 10 CFR Part 50 and design objective and in Section II.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified to ensure the design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents are not exceeded.
CH-ODCM-0001 Reference Use Page 58 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 7.2.1 (continued) 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 and 4.2.3A, 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. To support plant operations, Supervisor-System Chemistry may increase this limit up to the limits specified in Technical Specifications 5.16.1.g. Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. Because these concentrations are applied on an instantaneous basis and because of the overriding 10 CFR Part 50 Appendix I cumulative dose limitations, these limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the Site Boundary, to annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR Part 20.1301(a).
CH-ODCM-0001 Reference Use Page 59 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 7.2.2 (continued) B. Dose - Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the Off-Site Dose Calculation Manual, for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The Off-Site Dose Calculation Manual, equations provided for determining the air doses at the site boundary are consistent with Regulatory Guides 1.109 and 1.111.
CH-ODCM-0001 Reference Use Page 60 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 7.2.2 (continued) C. Dose - I-131, Radioactive Material in Particulate Form with Half-Lives Greater than Eight Days (Other than Noble Gases) and Tritium This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section 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 dose calculation methodology and parameters established in Part II of the Off-Site Calculation Manual, for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The release rate specification for I-131, 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 61 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 7.2.2 (continued) D. Gaseous Waste Treatment The OPERABILITY of the gaseous radwaste treatment system and the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable. This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix I to 10 CFR Part 50 and design objective and in Section II.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified to ensure the design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded.
CH-ODCM-0001 Reference Use Page 62 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 7.2.2 (continued) E. Total Dose - Uranium Fuel Cycle This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mRems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mRems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the plant remains within twice the dose design objectives of Appendix I, 10 CFR Part 50, and if direct radiation doses (including outside storage tanks, etc.) are kept small. The Special Report shall describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site 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 63 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 plant 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 Technical Specification 5.16.2 is used to meet the intent of NUREG-1301.
CH-ODCM-0001 Reference Use Page 64 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 65 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 66 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 PART II CALCULATIONS
CH-ODCM-0001 Reference Use Page 67 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents 1.1.1 There are two liquid discharge pathways to the Missouri River. These pathways originate with the radioactive liquid waste processing system (monitor or hotel tanks) and the steam generator blowdown system. Both of these pathways empty into the circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathways and associated radiation monitors. Figure 3 depicts the methods of liquid effluent treatment. 1.1.2 The flowrate for dilution water varies with the number of circulating water pumps in service, the number of raw water pumps in service, and with the operation of the warm water recirculation. Some warm water from the condenser outlet is diverted from the circulating water discharge to upstream of the intake structure to help prevent ice from forming on the circulating water pump intakes during winter months. The varying dilution flowrate and utilization of warm water recirculation is accounted for in the dilution calculations for monitor tank and stream generation releases. 1.1.3 Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 Ci/ml total activity. 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 68 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 NOTE If the annual average /Q value exceeds 1.4E-04 sec/m3, consideration i should be given to basing liquid radiation monitor setpoints on an I-131 instantaneous limit of 2.0E-09 Ci/ml at the unrestricted area boundary i with 10% vapor/liquid separation. Contact the Supervisor-System Chemistry for further instructions. 1.1.7 Liquid Effluent Radiation Monitors A. Steam Generator Blowdown Monitors (RM-054A and B)
- 1. These process radiation detectors monitor the flow through the steam generator blowdown lines and automatically close the blowdown isolation valves if the monitor high alarm setpoint is reached. The monitor controls liquid effluent releases so that 10 times the 10 CFR Part 20 limit at the unrestricted area boundary of 1.0E-06 Ci/cc, is not exceeded at the site discharge.
- 2. The following calculations for maximum concentration and alarm setpoints are valid for simultaneous radioactive liquid releases of steam generator blowdown and monitor tank discharge.
- 3. The maximum allowable concentration in the blowdown line is calculated as follows:
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 1 circulating water pump at 120,000 gpm. Other flowrates may be used, as required.) f = Blowdown flow rate (gpm). (Normal blowdown flow rate is based on 2 transfer pumps with a design flow of 135 gpm each, 270 gpm total. Other flow rates may be used, as required.) CMAX = Maximum allowable blowdown concentration (Ci/ml).
CH-ODCM-0001 Reference Use Page 69 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.1.7A (continued) NOTE i Setpoints may be recalculated based on adjusted dilution flow and adjusted blowdown flow. i The High Alarm Setpoint (CPM): 0.75 Where: 0.75 = An administrative correction factor which includes the following: 15% tolerance to ensure radmonitor response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77. 10% tolerance to account for the difference in detector sensitivity for the range of isotopes detected. Sf = Detector sensitivity factor (CPM/Ci/ml). (Sensitivity based on Cs-137). K4 = Allocation factor for Individual Steam Generator Release (See Table 1) B = Background (CPM) CMAX = Maximum allowable blowdown line activity (Ci/ml). 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 70 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.1.7 (continued) B. 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 simultaneous radioactive liquid releases of monitor tank discharge and steam generator blowdown.
- 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 1 circulating water pump at 120,000 gpm. Other flowrates such as raw water pump(s) may be used, as required.) f = Maximum monitor tank discharge flow rate (gpm). (Normal monitor tank maximum flow is 50 gpm. Other flow rates such as raw water pump(s) may be used, as required.) CMAX = Maximum allowable activity in discharge header (Ci/ml).
CH-ODCM-0001 Reference Use Page 71 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.1.7B (continued) The High Alarm Setpoint (CPM): 0.75 Where: 0.75 = An administrative correction factor which includes the following: 15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77. 10% tolerance to account for the difference in detector sensitivity for the range of isotopes detected. Sf = Detector sensitivity factor (CPM/Ci/ml). (Sensitivity based on Cs-137). K5 = Allocation factor for Waste Liquid Releases (See Table 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 72 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.2 Airborne Effluents 1.2.1 There are three air effluent discharge pathways at the Fort Calhoun Station: Condenser Offgas, Laboratory and Radioactive Waste Processing Building Exhaust Stack, and the Auxiliary Building Exhaust Stack. An airborne radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 4. The airborne waste disposal system is presented in Figure 5. Auxiliary Building - The Auxiliary Building Exhaust Stack receives discharges from the waste gas decay tanks, containment purge, containment vent systems and the auxiliary building ventilation system. Radiation Monitor RM-062 provides noble gas monitoring and iodine and particulate sampling for the Auxiliary Building Exhaust Stack. Backup noble gas monitoring and iodine and particulate sampling is provided by RM-052. Ventilation Isolation Actuation Signal (VIAS) is actuated by exceeding a monitor's alarm setpoint. Actuation of VIAS will isolate releases from containment and waste gas decay tanks. The Auxiliary Building Exhaust fans will remain in operation. Laboratory and Radioactive Waste Processing Building (LRWPB) - Noble gas monitoring and particulate and iodine sampling is provided by RM-043. This radiation monitor/sampler does not serve a control function. Condenser Off-Gas Monitors - Noble gas activity is monitored by RM-057. The condenser off-gas is discharged directly to the environment. Exceeding the high alarm setpoint on RM-057 will activate isolation of main steam to the Auxiliary Steam System. Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. The airborne effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1. The airborne effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than 5 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
CH-ODCM-0001 Reference Use Page 73 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.2.2 Airborne Effluent Radiation Monitors A. Auxiliary Building Exhaust Stack Noble Gas Activity Monitor (RM-062/RM-052)
- 1. Either of these monitors may be used to measure the noble gas activity in the exhaust stack. The noble gas is monitored after passing through a particulate filter, and charcoal cartridge. The monitor controls airborne releases so that five times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.0E-07 Ci/cc, based upon Xe-133, is not exceeded. The Ventilation Isolation Actuation Signal is initiated when the high alarm setpoint is reached.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from Auxiliary Building Exhaust Stack, Condenser Off-gas and the LRWPB Exhaust Stack.
- 3. The maximum allowable release rate for stack airborne activity is calculated as follows:
2.5 06 1.0 06 Where: 2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q sec/m3 = Annual average dispersion factor at the unrestricted area boundary from Part II Table 4, of the Off-Site Dose Calculation Manual.
1.0E+06 cc/m3 = Constant of unit conversion.
CH-ODCM-0001 Reference Use Page 74 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.2.2A (continued) The High Alarm Setpoint (CPM): 60 0.75 28317 Where: 0.75 = An administrative correction factor which includes the following: 15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77. 10% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum. Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133) K1 = Allocation factor for Auxiliary Building Exhaust Stack (See Table 1) 60 = Conversion (seconds to minutes). 28317 = Conversion factor (ft3 to cc). Fv = Auxiliary Building Exhaust stack flow rate (SCFM). (Default maximum flow rate is 122,500 cfm for 3 Auxiliary Building exhaust fans and 2 containment purge fans in operation. Other flow rates may be used, as required.) RMAX = Maximum Allowable Release Rate in Ci/sec B = Background (CPM) The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint and VIAS actuation.
CH-ODCM-0001 Reference Use Page 75 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.2.2 (continued) B. Condenser Off Gas Monitor (RM-057)
- 1. This monitor is located in the turbine building and monitors the condenser off-gas. The purpose of this monitor is to monitor the condenser off-gas discharges so that five times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.0E-07 Ci/cc, based upon Xe-133, is not exceeded.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack.
- 3. The maximum allowable release rate for condenser air ejector monitor is as follows:
2.5 06 1.0 06 Where: 2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q sec/m3 = Annual average dispersion factor at the unrestricted area boundary from Part II, Table 4, of the Off-Site Dose Calculation Manual.
1.0E+06 cc/m3 = Constant of unit conversion.
CH-ODCM-0001 Reference Use Page 76 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.2.2B (continued) The High Alarm Setpoint (CPM): 60 0.75 28317 Where: 0.75 = An administrative correction factor which includes the following: 15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77. 10% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum. Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133) K2 = Allocation factor for Condenser Off Gas (See Table 1) 60 = Conversion (seconds to minutes). 28317 = Conversion factor (ft; to cc). Fv = Vent stack flow rate (SCFM). Default maximum flow rate is 4,755 scfm (3 vacuum pumps in hogging mode. Other flow rates may be used, as required.) RMAX = Maximum Allowable Release Rate in Ci/sec. B = Background (CPM) The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint and tripping of the auxiliary steam supply valve, RCV-978.
CH-ODCM-0001 Reference Use Page 77 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.2.2 (continued) C. Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and Iodine and Particulate Sampler (RM-043)
- 1. RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is based on five times the 10 CFR Part 20 limit for Xe-133 at the unrestricted area boundary.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from condenser off-gas, Auxiliary Building Exhaust Stack, and the LRWPB Exhaust Stack.
2.5 06 sec 1.0 06 The maximum allowable release rate for RM-043 is as follows: Where: 2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q = Annual average dispersion factor at the unrestricted area boundary from Part II of the Off-Site Dose Calculation Manual, Table 4.
1.0E+06 cc/m3 = Constant of unit conversion
CH-ODCM-0001 Reference Use Page 78 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 1.2.2C (continued) i i NOTE This monitor alarms in the Control Room. There are no automatic control functions associated with the actuation of the alarm. The High Alarm Setpoint (CPM): 60 0.75 28317 Where: 0.75 = An administrative correction factor which includes the following: 15% tolerance to ensure radmonitor VIAS response in accordance with License Event Report 77-17, Docket Number 050-0285 and Telecon FC-472-77. 10% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum. Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133) K3 = Allocation factor for LRWPB Exhaust Stack (See Table 1) 60 = Conversion (seconds to minutes). 28317 = Conversion factor (ft3 to cc). Fv = LRWPB Exhaust stack flow rate (SCFM). (Default flow rate is 28,700 cfm. Other flow rates may be used if required.) RMAX = Maximum Allowable Release Rate in Ci/sec. B = Background (CPM) The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 79 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 1 - Allocation Factors for Simultaneous Releases NOTE i The Fort Calhoun Station is capable of performing simultaneous airborne releases. The factors below may be adjusted to meet release requirements, provided that the sum of the Unrestricted Area Fraction Sum for all airborne releases remains less i than or equal to 1.0. A. Allocation Factors for Simultaneous Airborne Releases
- 1. Auxiliary Building Exhaust Stack Total: 0.80 K1 Noble Gases (RM-062 or RM-052) 0.70 Iodine/Particulate/Tritium 0.10 Contributing Pathways:
a) Auxiliary Building 0.10 b) Containment Building 0.65 c) Waste Gas Decay Tanks 0.05
- 2. Condenser/Off Gas Total: 0.10 K2 Noble Gases (RM-057) 0.05 Tritium 0.05 Contributing Pathways:
a) Condenser Off Gas 0.10
- 3. Laboratory and Radioactive Waste Building Exhaust Total: 0.10 Stack K3 Noble Gases (RM-043) 0.05 Iodine/Particulate 0.05 Contributing Pathways:
a) Laboratory and Radioactive Waste Building Exhaust Stack 0.10 Airborne Release Total 1.00 NOTE i The Fort Calhoun Station is capable of performing simultaneous liquid releases. The factors below may be adjusted to meet release requirements provided that the sum of the Unrestricted Area Fraction Sum for all liquid releases remains less than i or equal to 1.0. B. Allocation Factors for Simultaneous Liquid Releases
- 1. K4 Steam Generator Releases (RM-054A/054B) Total: 0.30 Contributing Pathways:
a) Alpha Steam Generator (RM-054A) 0.15 b) Bravo Steam Generator (RM-054B) 0.15
- 2. K5 Waste Liquid Releases (RM-055) 0.70 Liquid Release Total 1.00
CH-ODCM-0001 Reference Use Page 80 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Figure 1 - Exclusion and Site Boundary Map N IOWA '- UNRESTICTED--------". AREA BOUNDARY ', I I J
\
I \
'J \
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I I
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\
CD LIQUID EFFLUENTS DISCHARdE AIRBORNE EFFLUENTS DISCHARdE TO OMAHA 0 1 SCALE IN MILES EXCLUSION AND SITE BOUNDARY MAP
CH-ODCM-0001 Reference Use Page 81 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Figure 2 - Liquid Radioactive Discharge Pathways HOTEL S/G S/G RAW TANKS 1- A s WATER
~
,. SLOWDOWN SLOWDOWN
~~
MONITOR 1 2 TANKS 3 RIVER RIVER CD RM-054A Cl) RM-054S Q) RM-055 LIQUID RADIOACTIVE DISCHARGE PATHWAYS
CH-ODCM-0001 Reference Use Page 82 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Figure 3 - Liquid Radioactive Waste Disposal System REACTOR COOLANT AUXILIARY SYSTEMS WASTE PROCESS WASTE eves BlE:edo-ff HOTEL WASTE Floor DraLn3 Equ1pment Dc-aLns Laundr~ Wavte Sump Flow:;; RC Loop DraJns Shov~r Drcnns:; Spent R~g~n~e--ant Tanks 55]0 Go]~ Wagt~ r=- Jl t~r--£ 50 M1crons De m J ne r al1z er 00000 Chor--cool F Ll ter 5g Cu, Ft, ( optJonall t 0[ rlonL tor Tank5 G770 Cal,
~
OvE:rboard Heoder (To R1verl LIQUID RADIOACTIVE WASTE DISPOSAL SYSTEM
CH-ODCM-0001 Reference Use Page 83 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Figure 4 - Airborne Effluent Discharge Pathways RM 043 Noble Gas Monitor, and lodirre & :='articulate Sampler I
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CH-ODCM-0001 Reference Use Page 84 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Figure 5 - Airborne Radioactive Waste Disposal System Turbine Auxiliary Building Ventilation Conderuler ~!ltlk To Atm phere 122,500 oF1.1
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~
Blowdown '-- Fla sh Tilnk da~ Holdup Tanks (4) ( 400 CuFt (each) j ~
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CH-ODCM-0001 Reference Use Page 85 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 and Steam Generators) and for continuous releases (Steam Generator Blowdown), 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.
CH-ODCM-0001 Reference Use Page 86 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 NOTE i In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable. i 2.2 Airborne Effluent Concentrations 2.2.1 The concentration at the unrestricted area boundary, due to airborne effluent releases, will be limited to less than Appendix B, Table 2, Column 1, values. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event an airborne effluent release from the station result in an alarm setpoint being exceeded, an evaluation of the unrestricted area boundary concentration resulting from the release will be performed: 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: 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 the Auxiliary Building Ventilation Stack, Laboratory and Radwaste Building Stack and condenser off gas will be considered in evaluating compliance with the release rate limits of 10 CFR Part 20. Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. Historical annual average dispersion parameters, as presented in Table 4, may be used for evaluating the airborne effluent dose rate.
CH-ODCM-0001 Reference Use Page 87 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 2.2.4 For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding those more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding 10 CFR Part 20 limits. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based upon the above criteria, no further analyses are required for demonstrating compliance with 10 CFR Part 20. 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 plant discharge. The drinking water for Omaha is located 19 miles downstream from FCS. The dilution factors for these pathways are derived from the Revised Environmental Report for FCS, (1974), (page 4-29 and 4-31). This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be <14% of the concentration at discharge from FCS and will average 3%. This equates to a dilution factor of 7.14, which is used to calculate the maximum dose to an individual from liquid pathways and a dilution factor of 33.33, for calculating the average dose. All pathways combine to give the dose to an individual in unrestricted areas. 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 88 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 89 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 90 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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)]
CH-ODCM-0001 Reference Use Page 91 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2 Airborne Effluent Dose Calculations 3.2.1 Noble Gas 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from noble gases in airborne effluents from the Fort Calhoun Station to the following limits: During any calendar quarter 5 mrad-gamma air dose 10 mrad-beta air dose and During any calendar year 10 mrad-gamma air dose 20 mrad-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses: A. Doses from Noble Gases
- 1. Annual Gamma/Beta Air Dose from All Other Noble Gas Releases
, , 3.17 10 ,
Where: DFi or DFi = are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide (I), in mrad-m3/pCi-yr. (Table 2) D (r,) or D(r,) = are the annual gamma and beta air doses at distance r, in the sector at angle , from the discharge point, in mrad/yr. Qi = is the annual release rate of radionuclide (I), in Ci/yr. [/Q]D(r,) = is the annual average gaseous dispersion factor at distance r, in the sector at angle , in sec/m3. (Table 4) 3.17x104 = is the number of pCi per Ci divided by the number of seconds per year.
CH-ODCM-0001 Reference Use Page 92 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.1A (continued)
- 2. Annual Total Body Dose from All Other Noble Gas Releases Where:
DFBi = is the total body dose factor for a semi-infinite cloud of the radionuclide (I), which includes the attenuation of 5 g/cm2 of tissue, in mrem-m3/pCi-yr. (Table 2) DT (r,) = is the annual total body dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle , in mrem/yr. i(r,) = is the annual average ground-level concentration of radionuclide (I) at distance r, in the sector at angle , in pCi/m3. (Table 4) Sf = Shielding Factor (Table 17)
- 3. Annual Skin Dose from All Other Noble Gas Releases
, 1.11 , ,
Where: DT(r,) = is the annual skin dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle , in mrem/yr. DFSi = is the beta skin dose factor for a semiinfinite cloud of radionuclide (I), in mrem-m3/pCi-yr. (Table 2) 1.11 = is the average ratio of tissue to air energy absorption coefficients.
CH-ODCM-0001 Reference Use Page 93 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.2 Radioiodine, Tritium, and Particulates 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from radioactive materials in gaseous airborne from the Fort Calhoun Station to: During any calendar quarter 7.5 mrem to any organ and During any calendar year 15 mrem to any organ The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in airborne effluents released to unrestricted areas should be determined by the following expressions: Radioiodine, Tritium, and Particulates (continued)
CH-ODCM-0001 Reference Use Page 94 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.2 (continued) NOTE i In all cases, for releases of tritium, use the dispersion parameter for inhalation (/Q). i A. Annual Organ Dose from External Irradiation from Radioactivity Deposited on the Ground Plane The ground plane concentration of radionuclide (I) at distance r, in the sector at angle , with respect to the release point, may be determined by: 1.0 10 ,
, 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 95 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.2A (continued) 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 96 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.2B (continued) 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) DFAija = is the inhalation dose factor for radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 9-12) 3.2.3 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases A. Parameters for Calculating Concentrations in Forage, Produce, and Leafy Vegetables, excluding Tritium 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.
CH-ODCM-0001 Reference Use Page 97 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.3A (continued) 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 98 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.3 (continued) 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. 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 99 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.3 (continued) 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 3.2.3C with th=0), in pCi/kg. CSi(r,) = is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3C with th=90 days), in pCi/kg. fp = is the fraction of the year that animals graze on pasture. (Table 17) fs = is the fraction of daily feed that is pasture grass while the animal grazes on pasture. (Table 17) 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk
, , 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 100 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.5 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. 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) 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.
, 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 plant water to tritium concentration in atmospheric water, dimensionless. 0.75 = is the fraction of total plant mass that is water, dimensionless.
CH-ODCM-0001 Reference Use Page 101 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ (j) of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by: 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,UMa = are the ingestion rates of produce (non-leafy vegetables, fruits, and grains); milk, meat, and leafy UFa,ULa vegetables, respectively for individuals in age group (a). (Table 6) fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17) 3.2.7 (continued) 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
CH-ODCM-0001 Reference Use Page 102 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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. 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 3.2.7 (continued) D. Calculation Determining the Ingested Dose from Meat for Radionuclide (i) to Organ (j) and Age Group (a) Where:
CH-ODCM-0001 Reference Use Page 103 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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. 3.2.8 Annual Dose from Carbon 14 A. This is a calculated value based on power generation and days of operation. Critical organ doses from C-14 were calculated using a ratio of 15% as CO2. This ratio was determined during an NRC in-plant source term study conducted at the Fort Calhoun Station between 1976 and 1977, NUREG/CR-0140.
CH-ODCM-0001 Reference Use Page 104 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 105 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Nuclide -Air1 (Dfi) -Skin2 (DFSi) -Air1 (Dfi) -Body2 (DFBi) Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11E-03 4.67E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 1. 2.
- 3. 2.88 04 2.88 10
CH-ODCM-0001 Reference Use Page 106 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 107 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 4 - Highest Potential Exposure Pathways for Estimating Dose NOTE i The Annual Radiological Effluent Report uses the highest calculated value from real time meteorological data obtained for the entire year for calculating i 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 SSE 0.60 1.30E-05 N/A Boundary Inhalation Site SSE 0.60 1.30E-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 2 year average, updated only upon a +10% change from the previous value. At least ten percent (10%) should be added to these values for dose estimates during the reporting periods. 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 108 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 5 - Stable Element Transfer Data Biv Fm (cow) Ff Element Veg./Soil Milk (d/I) Meat (d/kg) H 4.8E+00 1.0E-02 1.2E-02 C 5.5E+00 1.2E-02 3.1E-02 Na 5.2E-02 4.0E-02 3.0E-02 P 1.1E+00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-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 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 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 Te 1.3E+00 1.0E-03 7.7E-02 I 2.0E-02 6.0E-03 2.9E-03 Cs 1.0E-02 1.2E-02 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Ce 2.5E-03 1.0E-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 Np 2.5E-03 5.0E-06 2.0E-04
CH-ODCM-0001 Reference Use Page 109 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 110 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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-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 Ru-103 3.60E-09 4.20E-09
CH-ODCM-0001 Reference Use Page 111 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2) Element Total Body Skin Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 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 Np-239 9.50E-10 1.10E-09
CH-ODCM-0001 Reference Use Page 112 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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-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 Tc-101 5.22E-15 7.52E-15 7.38E-14 --- 1.35E-13 4.99E-08 1.36E-21
CH-ODCM-0001 Reference Use Page 113 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 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 W-187 1.06E-09 8.85E-10 3.10E-10 --- --- 3.63E-06 1.94E-05 Np-239 2.87E-08 2.54E-08 1.55E-09 --- 8.75E-09 4.70E-06 1.49E-05
CH-ODCM-0001 Reference Use Page 114 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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 6.019E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 --- --- --- 1.16E-05 Cr-51 --- --- 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 --- 6.39E-06 1.05E-06 --- 1.59E-06 2.48E-04 8.35E-06 Mn-56 --- 2.12E-10 3.15E-11 --- 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 --- --- 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 --- --- 1.91E-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-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 Tc-101 7.40E-15 1.05E-14 1.03E-13 --- 1.90E-13 8.34E-08 1.09E-16
CH-ODCM-0001 Reference Use Page 115 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 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 W-187 1.50E-09 1.22E-09 4.29E-10 --- --- 5.92E-06 2.21E-05 Np-239 4.23E-08 3.60E-08 2.21E-09 --- 1.25E-08 8.11E-06 1.65E-05
CH-ODCM-0001 Reference Use Page 116 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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-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 Tc-101 2.19E-14 2.30E-14 2.91E-13 --- 3.92E-13 1.58E-07 4.41E-09
CH-ODCM-0001 Reference Use Page 117 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 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 W-187 4.41E-09 2.61E-09 1.17E-09 --- --- 1.11E-05 2.46E-05 Np-239 1.26E-07 8.14E-08 6.35E-09 --- 2.63E-08 1.57E-05 1.73E-05
CH-ODCM-0001 Reference Use Page 118 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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-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 Tc-101 4.65E-14 5.88E-14 5.80E-13 --- 6.99E-13 4.17E-07 6.03E-07
CH-ODCM-0001 Reference Use Page 119 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 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-139 119.06E- 7.03E-13 3.07E-11 --- 4.23E-13 4.25E-06 3.64E-05 09 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 W-187 9.26E-09 6.44E-09 2.23E-09 --- --- 2.83E-05 2.54E-05 Np-239 2.65E-07 2.13E-07 1.34E-08 --- 4.73E-08 4.25E-05 1.78E-05
CH-ODCM-0001 Reference Use Page 120 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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-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 Tc-101 2.54E-10 3.66E-10 3.59E-09 --- 6.59E-09 1.87E-10 1.10E-21
CH-ODCM-0001 Reference Use Page 121 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 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 W-187 1.03E-07 8.61E-08 3.01E-08 --- --- --- 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 --- 3.65E-10 --- 2.40E-05
CH-ODCM-0001 Reference Use Page 122 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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-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 Tc-101 3.60E-10 5.12E-10 5.03E-09 --- 9.26E-09 3.12E-10 8.75E-17
CH-ODCM-0001 Reference Use Page 123 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 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 W-187 1.46E-07 1.19E-07 4.17E-08 --- --- --- 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 --- 5.21E-10 --- 2.67E-05
CH-ODCM-0001 Reference Use Page 124 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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-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 Tc-101 1.07E-09 1.12E-09 1.42E-08 --- 1.91E-08 5.92E-10 3.56E-09
CH-ODCM-0001 Reference Use Page 125 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 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 W-187 4.29E-07 2.54E-07 1.14E-07 --- --- --- 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 --- 1.09E-09 --- 2.79E-05
CH-ODCM-0001 Reference Use Page 126 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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-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 Tc-101 2.27E-09 2.86E-09 2.83E-08 --- 3.40E-08 1.56E-09 4.86E-07
CH-ODCM-0001 Reference Use Page 127 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 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 W-187 9.03E-07 6.28E-07 2.17E-07 --- --- --- 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 --- 1.98E-09 --- 2.87E-05
CH-ODCM-0001 Reference Use Page 128 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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) f 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 129 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 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)
%CO2 Fraction of C-14 used for organ dose 0.15 calculations from gaseous releases.
CH-ODCM-0001 Reference Use Page 130 of 130 Off-Site Dose Calculation Manual (ODCM) Revision 25 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure NOTE i The Dose Estimates are based on normal public activities conducted within the Fort Calhoun Station Site Boundary. i Estimated Individual Dose Estimated Total Combined Distance Rate (mR/hour) Annual Dose (mRem)B from Direct Inhalation Direct Inhalation Containment Exposure (Critical Exposure (Critical Location Direction (miles) (Total Body) OrganA) (Total Body) OrganA) Firing Range 200° 0.24 4.08E-05 9.67E-06 5.08E+00 1.20E+00 Burn Pad 241° 0.33 1.95E-05 4.63E-06 1.41E-01 3.34E-02 On-Site Farming 118° 0.52 2.12E-05 5.03E-06 2.38E-02 5.64E-03 On-Site Farming 200° 0.51 1.03E-05 2.45E-06 2.30E-02 5.50E-03 On-Site Farming 308° 0.50 2.77E-05 6.64E-06 4.66E-02 1.12E-02 Site Maintenance Admin Bldg 145° 0.20 1.18E-04 2.84E-05 5.50E-02 1.33E-02 Site Maintenance Training Center 180° 0.20 1.45E-04 3.50E-05 6.78E-02 1.64E-02 A. Critical organ doses are based on adult thyroid. B. Estimated totals are based on summation of all individual doses for members of the General Public while within the Fort Calhoun Station site boundary.
SECTION VII ATTACHMENT 2 JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA (Regulatory Guide 1.21) January 1, 2016 - December 31, 2016 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, 2016 through December 31, 2016 had a cumulative recovery rate of 99.46% from the meteorological tower with the remaining 0.54% provided by Eppley Airfield Weather Station, a branch of the National Weather Service. The data provided by Eppley Airfield Weather Station. 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, 2016 through December 31, 2016 look appropriate for the season indicated. The Pasquill Classes observed for the twelve-month period are detailed below. Pasquill Class A B C D E F G Total
% Obs. 9.50 4.69 6.25 43.37 24.88 7.77 3.55 100 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 2016 - DEC 2016 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 2 4 3 16 23 11 2 1 0 0 62 NNE 0 1 7 6 3 2 1 0 0 0 0 20 NE 0 1 5 2 7 7 2 0 0 0 0 24 ENE 0 1 2 4 4 3 4 0 1 0 0 19 E 0 0 3 5 4 1 2 1 1 0 0 17 ESE 0 0 1 2 7 8 3 2 7 1 0 31 SE 0 1 2 4 0 9 8 6 14 2 0 46 SSE 0 1 1 2 4 2 1 8 20 4 0 43 S 0 1 1 1 0 1 1 2 7 2 0 16 SSW 0 1 1 1 2 2 1 1 2 2 0 13 SW 0 0 1 2 5 5 1 5 9 7 0 35 WSW 0 0 4 1 6 2 2 1 6 0 0 22 W 0 0 1 4 9 8 8 2 3 2 0 37 WNW 0 1 2 4 19 12 11 6 4 0 0 59 NW 0 0 3 5 27 31 42 22 23 6 3 162 NNW 0 3 5 6 39 42 60 37 25 7 4 228 Total 0 13 43 52 152 158 158 95 123 33 7 834 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 834 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 2016 - DEC 2016 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 1 3 4 19 11 1 0 0 0 0 39 NNE 0 0 0 3 2 0 1 0 0 0 0 6 NE 0 1 4 2 2 0 1 0 0 0 0 10 ENE 0 0 1 4 3 6 4 1 0 0 0 19 E 0 1 1 2 9 1 1 1 0 0 0 16 ESE 0 0 2 1 4 4 4 4 2 0 0 21 SE 0 0 0 1 4 13 13 13 7 1 0 52 SSE 0 1 1 0 2 1 8 6 12 2 0 33 S 0 0 0 0 2 3 2 2 10 4 1 24 SSW 0 1 0 0 1 3 1 5 5 1 0 17 SW 0 1 1 1 0 2 1 1 1 0 0 8 WSW 0 0 0 2 3 0 2 1 1 0 0 9 W 0 0 1 5 0 2 0 0 1 0 0 9 WNW 0 0 1 1 15 3 4 0 1 0 0 25 NW 0 1 1 2 7 10 7 13 5 0 1 47 NNW 0 0 3 2 14 27 18 7 6 0 0 77 Total 0 7 19 30 87 86 68 54 51 8 2 412 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 412 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 2016 - DEC 2016 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 1 7 3 18 7 2 0 0 0 0 39 NNE 0 0 7 1 4 4 0 0 0 0 0 16 NE 0 4 1 4 11 3 1 1 0 0 0 25 ENE 0 1 1 4 10 2 2 0 0 0 0 20 E 0 1 2 4 7 5 0 1 0 0 0 20 ESE 0 0 3 4 11 10 6 2 3 0 0 39 SE 0 0 1 2 8 14 18 21 10 2 0 76 SSE 0 0 0 0 3 5 7 12 18 5 0 50 S 0 0 1 2 3 3 11 7 9 2 1 39 SSW 0 0 1 3 3 4 8 6 11 0 0 36 SW 0 1 0 1 3 2 4 2 0 0 0 13 WSW 0 0 1 1 2 4 2 0 0 0 0 10 W 0 0 0 2 4 2 1 0 3 0 0 12 WNW 0 1 2 3 6 4 2 2 3 0 0 23 NW 0 1 1 2 12 10 12 7 5 3 0 53 NNW 0 0 4 8 13 22 10 10 6 4 1 78 Total 1 10 32 44 118 101 86 71 68 16 2 549 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 549 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 2016 - DEC 2016 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 1 11 33 45 68 35 4 6 2 0 0 205 NNE 1 11 25 19 15 6 4 1 0 0 0 82 NE 1 6 16 17 18 3 2 2 3 3 0 71 ENE 0 11 27 21 16 17 5 3 7 0 0 107 E 1 5 15 26 33 18 1 0 0 0 0 99 ESE 0 8 16 29 55 45 14 10 6 0 0 183 SE 1 8 17 29 104 103 91 62 40 10 1 466 SSE 0 7 8 16 71 98 119 84 96 14 1 514 S 1 1 10 12 36 68 107 95 89 17 0 436 SSW 0 3 7 8 43 44 51 51 69 14 7 297 SW 0 6 4 8 38 22 15 10 16 7 1 127 WSW 1 5 9 9 12 11 8 6 4 0 0 65 W 1 7 7 17 22 19 9 17 11 2 0 112 WNW 0 13 18 12 43 46 28 11 16 0 0 187 NW 0 7 23 24 52 49 58 27 26 12 1 279 NNW 1 25 39 62 152 135 92 29 37 7 0 579 Total 9 134 274 354 778 719 608 414 422 86 11 3809 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 3809 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 2016 - DEC 2016 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 1 13 10 8 12 3 2 0 0 0 0 49 NNE 1 8 7 2 12 0 0 0 0 0 0 30 NE 3 13 10 5 2 2 1 0 0 0 0 36 ENE 2 14 6 4 14 5 2 0 0 0 0 47 E 2 12 12 10 8 7 3 3 1 0 0 58 ESE 2 11 27 34 37 9 5 4 5 0 0 134 SE 2 15 39 48 126 80 35 15 15 2 1 378 SSE 0 17 26 18 70 51 45 17 6 1 0 251 S 0 13 7 14 32 46 54 27 17 1 1 212 SSW 2 8 10 6 10 23 38 23 33 4 0 157 SW 6 13 5 5 9 6 6 11 22 16 4 103 WSW 3 14 10 5 8 3 10 5 2 0 1 61 W 10 34 13 16 21 16 22 5 4 1 1 143 WNW 3 69 26 23 40 29 25 4 6 2 0 227 NW 3 20 36 21 40 17 8 1 1 0 0 147 NNW 5 18 24 28 56 16 2 1 2 0 0 152 Total 45 292 268 247 497 313 258 116 114 27 8 2185 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 2185 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 2016 - DEC 2016 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 3 2 2 2 0 0 0 0 0 0 0 9 NNE 2 5 1 1 0 0 0 0 0 0 0 9 NE 4 6 2 1 0 0 0 0 0 0 0 13 ENE 0 8 4 0 0 0 0 0 0 0 0 12 E 1 11 9 4 3 0 0 0 0 0 0 28 ESE 2 16 16 16 10 10 2 0 0 0 0 72 SE 3 20 18 18 30 16 14 3 0 0 0 122 SSE 7 21 6 4 21 7 0 1 0 0 0 67 S 4 24 5 1 10 9 3 1 0 0 0 57 SSW 11 14 4 5 6 6 1 4 0 0 0 51 SW 7 22 3 0 1 1 1 0 4 2 0 41 WSW 9 16 2 0 1 1 0 0 2 0 0 31 W 8 29 7 4 2 0 1 0 0 0 0 51 WNW 8 34 14 5 12 4 0 0 0 0 0 77 NW 4 16 7 1 0 0 0 0 0 0 0 28 NNW 2 6 3 1 1 0 0 0 1 0 0 14 Total 75 250 103 63 97 54 22 9 7 2 0 682 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 682 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 2016 - DEC 2016 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 2 0 0 1 0 0 0 0 0 0 3 NNE 0 1 1 1 0 0 0 0 0 0 0 3 NE 4 4 0 0 0 0 0 0 0 0 0 8 ENE 4 7 1 0 0 0 0 0 0 0 0 12 E 5 11 3 1 0 0 0 0 0 0 0 20 ESE 9 21 8 3 0 1 0 0 0 0 0 42 SE 7 26 16 6 1 2 1 0 0 0 0 59 SSE 12 26 7 2 0 0 0 0 0 0 0 47 S 3 20 2 2 1 4 1 0 0 0 0 33 SSW 6 16 2 3 3 0 0 0 0 0 0 30 SW 5 16 0 0 0 0 1 0 0 0 0 22 WSW 6 3 1 0 0 0 0 0 0 0 0 10 W 3 6 0 0 0 0 0 0 0 0 0 9 WNW 0 5 0 1 0 0 0 0 0 0 0 6 NW 1 3 0 0 1 0 0 0 0 0 0 5 NNW 1 2 0 0 0 0 0 0 0 0 0 3 Total 66 169 41 19 7 7 3 0 0 0 0 312 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 312 Hours Accounted For: 8783 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 2016 - DEC 2016 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 0.02 0.05 0.03 0.18 0.26 0.13 0.02 0.01 0.00 0.00 0.71 NNE 0.00 0.01 0.08 0.07 0.03 0.02 0.01 0.00 0.00 0.00 0.00 0.23 NE 0.00 0.01 0.06 0.02 0.08 0.08 0.02 0.00 0.00 0.00 0.00 0.27 ENE 0.00 0.01 0.02 0.05 0.05 0.03 0.05 0.00 0.01 0.00 0.00 0.22 E 0.00 0.00 0.03 0.06 0.05 0.01 0.02 0.01 0.01 0.00 0.00 0.19 ESE 0.00 0.00 0.01 0.02 0.08 0.09 0.03 0.02 0.08 0.01 0.00 0.35 SE 0.00 0.01 0.02 0.05 0.00 0.10 0.09 0.07 0.16 0.02 0.00 0.52 SSE 0.00 0.01 0.01 0.02 0.05 0.02 0.01 0.09 0.23 0.05 0.00 0.49 S 0.00 0.01 0.01 0.01 0.00 0.01 0.01 0.02 0.08 0.02 0.00 0.18 SSW 0.00 0.01 0.01 0.01 0.02 0.02 0.01 0.01 0.02 0.02 0.00 0.15 SW 0.00 0.00 0.01 0.02 0.06 0.06 0.01 0.06 0.10 0.08 0.00 0.40 WSW 0.00 0.00 0.05 0.01 0.07 0.02 0.02 0.01 0.07 0.00 0.00 0.25 W 0.00 0.00 0.01 0.05 0.10 0.09 0.09 0.02 0.03 0.02 0.00 0.42 WNW 0.00 0.01 0.02 0.05 0.22 0.14 0.13 0.07 0.05 0.00 0.00 0.67 NW 0.00 0.00 0.03 0.06 0.31 0.35 0.48 0.25 0.26 0.07 0.03 1.84 NNW 0.00 0.03 0.06 0.07 0.44 0.48 0.68 0.42 0.28 0.08 0.05 2.60 Total 0.00 0.15 0.49 0.59 1.73 1.80 1.80 1.08 1.40 0.38 0.08 9.50 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 9.50 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 2016 - DEC 2016 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 0.01 0.03 0.05 0.22 0.13 0.01 0.00 0.00 0.00 0.00 0.44 NNE 0.00 0.00 0.00 0.03 0.02 0.00 0.01 0.00 0.00 0.00 0.00 0.07 NE 0.00 0.01 0.05 0.02 0.02 0.00 0.01 0.00 0.00 0.00 0.00 0.11 ENE 0.00 0.00 0.01 0.05 0.03 0.07 0.05 0.01 0.00 0.00 0.00 0.22 E 0.00 0.01 0.01 0.02 0.10 0.01 0.01 0.01 0.00 0.00 0.00 0.18 ESE 0.00 0.00 0.02 0.01 0.05 0.05 0.05 0.05 0.02 0.00 0.00 0.24 SE 0.00 0.00 0.00 0.01 0.05 0.15 0.15 0.15 0.08 0.01 0.00 0.59 SSE 0.00 0.01 0.01 0.00 0.02 0.01 0.09 0.07 0.14 0.02 0.00 0.38 S 0.00 0.00 0.00 0.00 0.02 0.03 0.02 0.02 0.11 0.05 0.01 0.27 SSW 0.00 0.01 0.00 0.00 0.01 0.03 0.01 0.06 0.06 0.01 0.00 0.19 SW 0.00 0.01 0.01 0.01 0.00 0.02 0.01 0.01 0.01 0.00 0.00 0.09 WSW 0.00 0.00 0.00 0.02 0.03 0.00 0.02 0.01 0.01 0.00 0.00 0.10 W 0.00 0.00 0.01 0.06 0.00 0.02 0.00 0.00 0.01 0.00 0.00 0.10 WNW 0.00 0.00 0.01 0.01 0.17 0.03 0.05 0.00 0.01 0.00 0.00 0.28 NW 0.00 0.01 0.01 0.02 0.08 0.11 0.08 0.15 0.06 0.00 0.01 0.54 NNW 0.00 0.00 0.03 0.02 0.16 0.31 0.20 0.08 0.07 0.00 0.00 0.88 Total 0.00 0.08 0.22 0.34 0.99 0.98 0.77 0.61 0.58 0.09 0.02 4.69 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 4.69 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 2016 - DEC 2016 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 0.01 0.01 0.08 0.03 0.20 0.08 0.02 0.00 0.00 0.00 0.00 0.44 NNE 0.00 0.00 0.08 0.01 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.18 NE 0.00 0.05 0.01 0.05 0.13 0.03 0.01 0.01 0.00 0.00 0.00 0.28 ENE 0.00 0.01 0.01 0.05 0.11 0.02 0.02 0.00 0.00 0.00 0.00 0.23 E 0.00 0.01 0.02 0.05 0.08 0.06 0.00 0.01 0.00 0.00 0.00 0.23 ESE 0.00 0.00 0.03 0.05 0.13 0.11 0.07 0.02 0.03 0.00 0.00 0.44 SE 0.00 0.00 0.01 0.02 0.09 0.16 0.20 0.24 0.11 0.02 0.00 0.87 SSE 0.00 0.00 0.00 0.00 0.03 0.06 0.08 0.14 0.20 0.06 0.00 0.57 S 0.00 0.00 0.01 0.02 0.03 0.03 0.13 0.08 0.10 0.02 0.01 0.44 SSW 0.00 0.00 0.01 0.03 0.03 0.05 0.09 0.07 0.13 0.00 0.00 0.41 SW 0.00 0.01 0.00 0.01 0.03 0.02 0.05 0.02 0.00 0.00 0.00 0.15 WSW 0.00 0.00 0.01 0.01 0.02 0.05 0.02 0.00 0.00 0.00 0.00 0.11 W 0.00 0.00 0.00 0.02 0.05 0.02 0.01 0.00 0.03 0.00 0.00 0.14 WNW 0.00 0.01 0.02 0.03 0.07 0.05 0.02 0.02 0.03 0.00 0.00 0.26 NW 0.00 0.01 0.01 0.02 0.14 0.11 0.14 0.08 0.06 0.03 0.00 0.60 NNW 0.00 0.00 0.05 0.09 0.15 0.25 0.11 0.11 0.07 0.05 0.01 0.89 Total 0.01 0.11 0.36 0.50 1.34 1.15 0.98 0.81 0.77 0.18 0.02 6.25 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 6.25 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 2016 - DEC 2016 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 0.01 0.13 0.38 0.51 0.77 0.40 0.05 0.07 0.02 0.00 0.00 2.33 NNE 0.01 0.13 0.28 0.22 0.17 0.07 0.05 0.01 0.00 0.00 0.00 0.93 NE 0.01 0.07 0.18 0.19 0.20 0.03 0.02 0.02 0.03 0.03 0.00 0.81 ENE 0.00 0.13 0.31 0.24 0.18 0.19 0.06 0.03 0.08 0.00 0.00 1.22 E 0.01 0.06 0.17 0.30 0.38 0.20 0.01 0.00 0.00 0.00 0.00 1.13 ESE 0.00 0.09 0.18 0.33 0.63 0.51 0.16 0.11 0.07 0.00 0.00 2.08 SE 0.01 0.09 0.19 0.33 1.18 1.17 1.04 0.71 0.46 0.11 0.01 5.31 SSE 0.00 0.08 0.09 0.18 0.81 1.12 1.35 0.96 1.09 0.16 0.01 5.85 S 0.01 0.01 0.11 0.14 0.41 0.77 1.22 1.08 1.01 0.19 0.00 4.96 SSW 0.00 0.03 0.08 0.09 0.49 0.50 0.58 0.58 0.79 0.16 0.08 3.38 SW 0.00 0.07 0.05 0.09 0.43 0.25 0.17 0.11 0.18 0.08 0.01 1.45 WSW 0.01 0.06 0.10 0.10 0.14 0.13 0.09 0.07 0.05 0.00 0.00 0.74 W 0.01 0.08 0.08 0.19 0.25 0.22 0.10 0.19 0.13 0.02 0.00 1.28 WNW 0.00 0.15 0.20 0.14 0.49 0.52 0.32 0.13 0.18 0.00 0.00 2.13 NW 0.00 0.08 0.26 0.27 0.59 0.56 0.66 0.31 0.30 0.14 0.01 3.18 NNW 0.01 0.28 0.44 0.71 1.73 1.54 1.05 0.33 0.42 0.08 0.00 6.59 Total 0.10 1.53 3.12 4.03 8.86 8.19 6.92 4.71 4.80 0.98 0.13 43.37 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 43.37 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 2016 - DEC 2016 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 0.01 0.15 0.11 0.09 0.14 0.03 0.02 0.00 0.00 0.00 0.00 0.56 NNE 0.01 0.09 0.08 0.02 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.34 NE 0.03 0.15 0.11 0.06 0.02 0.02 0.01 0.00 0.00 0.00 0.00 0.41 ENE 0.02 0.16 0.07 0.05 0.16 0.06 0.02 0.00 0.00 0.00 0.00 0.54 E 0.02 0.14 0.14 0.11 0.09 0.08 0.03 0.03 0.01 0.00 0.00 0.66 ESE 0.02 0.13 0.31 0.39 0.42 0.10 0.06 0.05 0.06 0.00 0.00 1.53 SE 0.02 0.17 0.44 0.55 1.43 0.91 0.40 0.17 0.17 0.02 0.01 4.30 SSE 0.00 0.19 0.30 0.20 0.80 0.58 0.51 0.19 0.07 0.01 0.00 2.86 S 0.00 0.15 0.08 0.16 0.36 0.52 0.61 0.31 0.19 0.01 0.01 2.41 SSW 0.02 0.09 0.11 0.07 0.11 0.26 0.43 0.26 0.38 0.05 0.00 1.79 SW 0.07 0.15 0.06 0.06 0.10 0.07 0.07 0.13 0.25 0.18 0.05 1.17 WSW 0.03 0.16 0.11 0.06 0.09 0.03 0.11 0.06 0.02 0.00 0.01 0.69 W 0.11 0.39 0.15 0.18 0.24 0.18 0.25 0.06 0.05 0.01 0.01 1.63 WNW 0.03 0.79 0.30 0.26 0.46 0.33 0.28 0.05 0.07 0.02 0.00 2.58 NW 0.03 0.23 0.41 0.24 0.46 0.19 0.09 0.01 0.01 0.00 0.00 1.67 NNW 0.06 0.20 0.27 0.32 0.64 0.18 0.02 0.01 0.02 0.00 0.00 1.73 Total 0.51 3.32 3.05 2.81 5.66 3.56 2.94 1.32 1.30 0.31 0.09 24.88 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 24.88 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 2016 - DEC 2016 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 0.03 0.02 0.02 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 NNE 0.02 0.06 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 NE 0.05 0.07 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.15 ENE 0.00 0.09 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 E 0.01 0.13 0.10 0.05 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.32 ESE 0.02 0.18 0.18 0.18 0.11 0.11 0.02 0.00 0.00 0.00 0.00 0.82 SE 0.03 0.23 0.20 0.20 0.34 0.18 0.16 0.03 0.00 0.00 0.00 1.39 SSE 0.08 0.24 0.07 0.05 0.24 0.08 0.00 0.01 0.00 0.00 0.00 0.76 S 0.05 0.27 0.06 0.01 0.11 0.10 0.03 0.01 0.00 0.00 0.00 0.65 SSW 0.13 0.16 0.05 0.06 0.07 0.07 0.01 0.05 0.00 0.00 0.00 0.58 SW 0.08 0.25 0.03 0.00 0.01 0.01 0.01 0.00 0.05 0.02 0.00 0.47 WSW 0.10 0.18 0.02 0.00 0.01 0.01 0.00 0.00 0.02 0.00 0.00 0.35 W 0.09 0.33 0.08 0.05 0.02 0.00 0.01 0.00 0.00 0.00 0.00 0.58 WNW 0.09 0.39 0.16 0.06 0.14 0.05 0.00 0.00 0.00 0.00 0.00 0.88 NW 0.05 0.18 0.08 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.32 NNW 0.02 0.07 0.03 0.01 0.01 0.00 0.00 0.00 0.01 0.00 0.00 0.16 Total 0.85 2.85 1.17 0.72 1.10 0.61 0.25 0.10 0.08 0.02 0.00 7.77 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 7.77 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 2016 - DEC 2016 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 0.00 0.02 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.03 NNE 0.00 0.01 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 NE 0.05 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 ENE 0.05 0.08 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 E 0.06 0.13 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.23 ESE 0.10 0.24 0.09 0.03 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.48 SE 0.08 0.30 0.18 0.07 0.01 0.02 0.01 0.00 0.00 0.00 0.00 0.67 SSE 0.14 0.30 0.08 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.54 S 0.03 0.23 0.02 0.02 0.01 0.05 0.01 0.00 0.00 0.00 0.00 0.38 SSW 0.07 0.18 0.02 0.03 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.34 SW 0.06 0.18 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.25 WSW 0.07 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.11 W 0.03 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.10 WNW 0.00 0.06 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 NW 0.01 0.03 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.06 NNW 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 Total 0.75 1.92 0.47 0.22 0.08 0.08 0.03 0.00 0.00 0.00 0.00 3.55 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 3.55 Percent of Hours Accounted For: 100.00 VII-17
Joint Frequency Distribution 2016 FCS Meterological Tower N 12.88 4.62 8.21 1.89 2.13 6.88 2.69 W 4.25 2.94 E 2.37 5.94 3.97 6.84 13.65 9.30 11.44 S Calms excluded. 0.1 3.5 6.9 11.5 18.4 24.2 Rings drawn at 5% intervals. Wind flow is FROM the directions shown. Wind Speed ( Miles Per Hour) No observations were missing.
OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TECHNICAL SPECIFICATION 5.9.4.b January 01, 2016 - December 31, 2016
Annual Radiological Environmental Operating Report This report is submitted in accordance with Section 5.9.4.b of the Technical Specifications of Fort Calhoun Station Unit No. 1, Facility Operating License DPR-40 for the period January 01, 2016 through December 31, 2016. In addition, this report provides any observations and anomalies that occurred during the monitoring period. Reviewed by: Approved by: Supervisor-RadWaste/Environmental Manager-Chemistry 0£14#t/4.U-Senior Director of Nuclear Decommissioning
Annual Radiological Environmental Operating Report In accordance with Technical Specification 5.9.4.b, herein is the Fort Calhoun Station (FCS) Annual Radiological Environmental Operating Report for year 2016. The data provided is consistent with the objectives as specified in Section 5.2.2 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 2016 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 reports the information required when primary coolant specific activity has exceeded the limits of Technical Specification 2.1.3
- 10) Appendix Dis the Sample Location Maps Page 1 of 14
INTRODUCTION Radiological Environmental Monitoring Program (REMP)- 2016 This report gives the results of the Radiological Environmental Monitoring Program (REMP) for the year 2016. The REMP is a requirement of the Fort Calhoun Station (FCS) operating license. 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 "0" 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 2016 were within expected ranges and compared closely with historical results. The result details and exceptions are listed in the following sections. Page 2 of 14
- 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.
Thirty-two new thermoluminescent dosimeters were added to the program during the fourth quarter of 2010. The returned results were evaluated for their validity. The results appeared to be consistent with the results from previous quarters and to nearby TLDs, so the results were deemed to be valid. All sample results are within the range of historical data and displayed less than 17% 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. 10-Year Trend Comparison of TLD Locations Location Avg. Dose (mr/week) 2016 Avg. Dose (mr/week) A 1.32 1.10 B 1.42 1.38 c 1.38 1.25 D 1.23 1.03 F 1.36 1.23 G 1.32 1.28 H 1.39 1.18 I 1.48 1.40 J 1.53 1.40 K 1.45 1.30 N 1.43 1.50 0 1.41 1.40 p 1.47 1.53 s 1.49 1.60 L (Control) 1.26 1.18 Page 3 of 14
- 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 3.4 miles from the plant in Sector J (South). The control samples are collected from a commercial dairy cow herd located approximately 9.9 miles from the plant in Sector J (South). The indicator station and control location are unchanged from last year. No indicator milk samples were available after June due to the dairy owners suspending operations. Late fall samples were not performed due to the does drying up before birthing. 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 2016 REMP.
Samples were comparable with historical results and within the range of results reported from the control location garden at Mohr Dairy. Additional special interest samples were obtained from on-site farm fields per plant Technical Specifications. All results were at the LLD for all non-naturally occurring radionuclides. No plant-related effects were observed.
- 5) Sediment River sediment samples are collected twice a year at an upstream control location and a downstream indicator location. All results were at the LLD for all non-naturally occurring radionuclides. No plant-related effects were observed.
Page 4 of 14
- 6) Air Monitoring Air sample results for 2016 were well within historical limits for all locations. Additionally, all indicator locations showed results very similar to the control locations.
No incidents were documented in the Corrective Action Program in 2016 related to air sampling. All sample results are within the range of historical data. All indicator locations displayed less than 15% difference when compared to historical average. All 2016 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 ) 2016 Avg. Beta (pCi/m3 ) Sector B 0.029 0.026 Sector D 0.029 0.025 Sector I 0.025 0.022 Sector J 0.027 0.023 Sector K 0.027 0.024 Sector F (Control) 0.029 0.026 Page 5 of 14
- 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 other 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 2.5 pCi/liter to a high of 8.1 pCi/liter, with an average gross beta for the year of 7.2 pCi/liter for indicator locations. Strontium-90 analysis is being conducted on wells as part of the station's groundwater protection program. No plant-related effects were detected. Page 6 of 14
Table 1.0 Sample Collection Program Collection Number of Samples Sample Class Frequency Sample Collected this Locations Period Background Radiation (TLDs) Quarterly 47 188 Air Particulates Weekly 6 312 Airborne Iodine Weekly 6 312 Biweekly Milk May thru Sept 2 381 Surface Water Monthly 3 36 Ground Water Quarterly 4 16 Fish Annually 2 52 Sediment Semi-annually 2 4 Food Crops Annually 3 g3 TOTAL 920 Note 1: Milk sample collection total includes 11 vegetation samples performed for milk unavailability. Milk samples are collected every two weeks May-Sept. and monthly the rest of the year. Three milk samples were performed in August. Note 2: Includes one background sample. Note 3: Variety of samples collected during period Page 7 of 14
Table 2.1 Radiological Environmental Monitoring Program Summary Reporting Period January-December, 2016 Name of Facility Fort Calhoun Nuclear Power station- Unit 1 Docket No. 50-285 Location of Facility Washington , Nebraska ( County, state ) Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses* Rangec Locationd Ran gee Rangec Results* Background Gamma 188 0.5 1.4 (184/184) OTD-S-(1) 1.6 (4/4) 1.2(4/4) 0 Radiation (0.8-2.0) 0.65@ 163° 1.5-1 .7 ( 0.9-1.4) (TLD) (mRt'Neek) Airborne GB 312 0.005 0.026 (260/260) OAP- B-(1) 0.026 (52152) 0.026 (52/52) 0 Particulates (0 .008-0.059) 0. 59 mi. @207* (0.012-0.059) (0 .01 2-0.050) (pCi/m 3) GS 24 Cs-134 0.001 < LLD - - < LLD 0 Cs-137 0.001 < LLD - - < LLD 0 other Gammas 0.001 < LLD - - < LLD 0 Airborne 1-131 318 O.Q7 < LLD - - < LLD 0 Iodine (pCi/m3) Milk 1-131 27 0.5 < LLD - - < LLD 0 (pCi/L) GS 27 OFM-G-(1) K-40 150 1803 (818) stangl Farm 1803 (8/8) 1347 (19/19) 0 (1598-2014) 3.4mi.@ 369 o (1598-2014) (1189-1507) Cs-134 15 < LLD - - < LLD 0 Cs-137 15 < LLD - - < LLD 0 Other Gammas 15 < LLD - - < LLD 0 Ground Water GB 16 6.2 (12/12) OGW-F-(1) 7.2 (4/4) 7.0 (4/4) 0 (pCi/L) (2.5-8.1) Lomp Acreage (6.4-7.5) (6.5-7 .4) H-3 16 300 < LLD 0.65 mi.@163° - < LLD 0 Sr-90 16 0.7 < LLD - - < LLD 0 GS 16 (pCi/L) Cs-134 15 < LLD - - < LLD 0 Cs-137 18 < LLD - - < LLD 0 Other Gammas 15 < LLD - - < LLD 0 Surface Water GS 36 (pCi/L) Cs-134 15 < LLD - - < LLD 0 Cs-137 18 < LLD - - < LLD 0 Other Gammas 15 < LLD - - < LLD 0 H-3 12 300 < LLD - - <LLD 0 Page 8 of 14
Table 2.1 Radiological Environmental Monitoring Program Summary Reporting Period January-December, 2016 Name of Facility Fort Calhoun Nuclear Power station- Unit 1 Docket No. 50-285 Location of Facility Washington, Nebraska ( County, state ) Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses* Range< Locationd Range< Ran gee Results" Fish GS 5 (pCi/gwet) Mn-54 0.026 < LLD . . < LLD 0 Co-58 0.027 < LLD . . < LLD 0 Co-60 0.023 < LLD . . < LLD 0 Fe-59 0.118 < LLD . . < LLD 0 Zn-65 0.050 < LLD . . < LLD 0 Ru-103 0.058 < LLD . . < LLD 0 Cs-134 0.026 < LLD . . < LLD 0 Cs-137 0.022 < LLD . . < LLD 0 Sediment GS 4 pCi/g dry Mn-54 0.040 < LLD . . < LLD 0 Co-58 0.065 < LLD . . < LLD 0 Co-60 0.026 < LLD . . < LLD 0 Fe-59 0.111 < LLD . . < LLD 0 Zn-65 0.113 < LLD . . < LLD 0 Cs-134 0.027 < LLD . . < LLD 0 Cs-137 0.044 < LLD . . < LLD 0 Food Crops GS 9 (pCi/gwet) Mn-54 0.011 < LLD . . < LLD 0 Co-58 0.012 < LLD . . < LLD 0 Co-60 0.011 < LLD . . < LLD 0 Fe-59 0.030 < LLD . . < LLD 0 Zn-65 0.022 < LLD . . < LLD 0 Zr-Nb-95 O.D19 < LLD . . < LLD 0 Cs-134 0.014 < LLD . . < LLD 0 Cs-137 0.016 < LLD . . < LLD 0 Ba-La-140 0.024 < LLD . . < LLD 0 Vegetation GS 11 (pCi/gwet) Mn-54 0.036 < LLD . . <LLD 0 Co-58 0.034 < LLD . . < LLD 0 Pasture grass Co-60 0.034 < LLD . . < LLD 0 in lieu of milk Fe-59 0.062 < LLD . . < LLD 0 Zn-65 0.053 < LLD . . < LLD 0 Zr-Nb-95 0.036 < LLD . . < LLD 0 Cs-134 0.035 < LLD . . < LLD 0 Cs-137 0.036 < LLD . . < LLD 0 Ba-La-140 0.040 < LLD . . < LLD 0 a GB =gross beta, GS = gamma scan. b LLD =nominal lower limit of detection based on a 95% confidence level. c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F). d Locations are specified: (1) by code, (2) by name, and (3) by distance and direction relative to the Reactor Containment Building.
- Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds the typical pre-operational value for the medium or location.
Page 9 of 14
Table 3.0 Listing of Missed Samples (samples scheduled but not collected) Sample Date Location Reason Type Page 10 of 14
FORT CALHOUN STATION FC-801 CHEMISTRY FORM REV1 2016 Page 1 of3 Environmental Land Use Survey Report Sec:to1 Dir Land Use Owner Miles Meters Deg Survey Age Group XOQ DOQ Remarks Technique ~ i ~ ~
- 1 .. CJ .5 A I N RESIDENCE WRIGHT 4.36 7016.74 351 INTERVIEW X X 1.10E-07 4.50E-10 MILK ANIMAL MEAT ANIMAL VEGETATION GROUNDWATER WRIGHT 4.36 7016.74 351 INTERVIEW X X B INNE RESIDENCE RAND,J 1.93 3106.03 12 MAIL SURVEY X 5.60E-07 2.20E-09 MILK ANIMAL MEAT ANIMAL VEGETATION SHEPARD 2.23 3588.84 16 INTERVIEW X X 3.70E-07 1.49E-09 GROUNDWATER RAND,J 1.93 3106.03 12 MAIL SURVEY X c I NE RESIDENCE HANSEN,M 1.52 2446.20 42 MAIL SURVEY X X 1.00E-06 2.90E-09 MILK ANIMAL MEAT ANIMAL VEGETATION HANSEN,M 1.52 2446.20 42 MAIL SURVEY X X 1.00E-06 2.90E-09 GROUNDWATER HANSEN,M 1.52 2446.20 42 MAIL SURVEY X X D !ENE RESIDENCE MEADE,G 4.79 7708.76 63 MAIL SURVEY X 8.70E-08 1.30E-10 MILK ANIMAL MEAT ANIMAL VEGETATION MEADE,G 4.79 7708.76 63 MAIL SURVEY X 8.70E-08 1.30E-10 GROUNDWATER MEADE,G 4.79 7708.76 63 MAIL SURVEY X E I E RESIDENCE LOVE 4.67 7515.6 89 MAIL SURVEY XX 9.80E-08 1.80E-10 MILK ANIMAL MEAT ANIMAL BROTHERS,D 4.91 7901 .88 90 INTERVIEW X 9.20E-08 1.60E-10 VEGETATION LOVE 4.67 7515.64 89 MAIL SURVEY XX 9.80E-08 1.80E-10 GROUNDWATER LOVE 4.67 7515.64 89 MAIL SURVEY XX F lESE RESIDENCE WILSON ISLAND 4.22 6791 .43 121 MAIL SURVEY X X 1.30E-07 2.90E-10 MILK ANIMAL MEAT ANIMAL VEGETATION WILSON ISLAND 4.22 6791 .43 121 MAIL SURVEY X X 1.30E-07 2.90E-10 GROUNDWATER WILSON ISLAND 4.22 6791 .43 121 MAIL SURVEY X X Page 11 of 14
FORT CALHOUN STATION FC-801 REV 1 CHEMISTRY FORM 2016 Page 2 of3 Environmental Land Use Survey Report Secto1 Dlr Land Use Owner Miles Meters Deg Survey A eGr
; ;g XOQ DOQ Remarks
~
Technique ~
~ ~ ti G I SE RESIDENCE CARTER,T 1.67 2687.60 145 INTERVIEW X 6.20E-07 3.60E-09 MILK ANIMAL MEAT ANIMAL VEGETATION KALIN,W 1.74 2800.26 145 MAIL SURVEY X 5.60E-07 3.30E-09 GROUNDWATER KALIN,W 1.74 2800.26 145 MAIL SURVEY X pGW-A-(1) SMITH FARM RETAINED TO MAINTAIN HISTORICAL DATA FROM PRE-OP TO PRESENT H I SSE RESIDENCE LOMP .65 1046.07 163 MAIL SURVEY X 6.60E-06 6.10E-08 MILK ANIMAL MEAT ANIMAL HINELINE,R 1.82 2929.01 146 INTERVIEW X 6.20E-07 5.30E-09 VEGETATION LOMP .65 1046.07 163 MAIL SURVEY X 6.60E-06 6.10E-08 GROUNDWATER LOMP .65 1046.07 163 MAIL SURVEY X J s RESIDENCE DOWLER .73 1174.82 175 MAIL SURVEY X 2.90E-06 1.90E-08 MILK ANIMAL STANGL 3.44 5536.1 169 INTERVIEW X X X 7.10E-08 3.60E-10 MEAT ANIMAL PRATI 2.48 3991 .17 170 INTERVIEW X X 1.41E-07 8.40E-10 VEGETATION DOWLER .73 1174.82 175 MAIL SURVEY X 2.90E-06 1.90E-08 GROUNDWATER DOWLER .73 1174.82 175 MAIL SURVEY X K ssw RESIDENCE D. MILLER .65 1046.07 203 INTERVIEW X 2.70E-06 1.10E-08 MILK ANIMAL MEAT ANIMAL D. MILLER .65 1046.07 203 INTERVIEW X 2.70E-06 1.10E-08 VEGETATION T. DEIN 2.00 3218.69 193 INTERVIEW X X 1.90E-07 7.30E-10 GROUNDWATER D. MILLER .65 1046.07 203 INTERVIEW X L I sw RESIDENCE ROBERTSON,D .73 1174.82 224 MAIL SURVEY X 2.60E-06 8.40E-09 MILK ANIMAL MEAT ANIMAL RYDER .76 1223.10 227 MAIL SURVEY X 2.40E-06 7.70E-09 VEGETATION BURGIN 1.43 2301.36 223 MAIL SURVEY X 5.00E-07 1.50E-09 GROUNDWATER ROBERTSON,D .73 1174.82 224 MAIL SURVEY X M ~sw RESIDENCE BENSEN,M 106 1705.90 257 INTERVIEW X 1.40E-06 4.20E-09 MILK ANIMAL MEAT ANIMAL FREDERICK 2.18 3508.37 258 MAIL SURVEY X 2.40E-07 6.40E-10 VEGETATION THOMAS 1.13 1818.51: 259 INTERVIEW X 1.10E-06 3.40E-09 GROUNDWATER BENSEN,M 1.06 1705.90 257 INTERVIEW X Page 12 of 14
FORT CALHOUN STATION FC-801 REV1 CHEMISTRY FORM 2016 Page 3 of3 Environmental Land Use Survey Report Secto1 Dlr Land Use Owner Miles Meters Deg SUrvey A eGro XOQ DOQ Remarks i ~~~ Technique N w RESIDENCE NIELSEN 1.20 1931 .21 263 INTERVIEW X 1.30E-06 4.20E-09 MILK ANIMAL MEAT ANIMAL BREITHAUPT 2.28 3669.30 261 INTERVIEW X 2.80E-07 8.10E-10 VEGETATION ASMUSSEN,G 1.30 2092.15 270 MAIL SURVEY X 1.00E-06 3.30E-09 GROUNDWATER ASMUSSEN,G 1.30 2092.15 270 MAIL SURVEY X p [WNW RESIDENCE STONE 2.60 4184.29 283 INTERVIEW X 2.50E-07 8.50E-10 MILK ANIMAL MEAT ANIMAL BROWN 4.59 7386.89 288 MAIL SURVEY X 9.60E-08 2.60E-10 VEGETATION TABOR 2.65 4264.76 285 MAIL SURVEY XXX 2.40E-07 8.00E-10 GROUNDWATER STONE 2.60 4184.29 283 INTERVIEW X Q NW RESIDENCE HANSEN,R 2.40 3882.43 318 INTERVIEW X 5.00E-07 1.90E-09 MILK ANIMAL MEAT ANIMAL VEGETATION HANSEN,R 2.40 3862.43 318 INTERVIEW X 5.00E-07 1.90E-09 GROUNDWATER HANSEN,R 2.40 3862.43 318 INTERVIEW X R NNW RESIDENCE BADIATO 2.08 3347.44 330 CITY REGISTER X 6.40E-07 3.50E-09 MILK ANIMAL MEAT ANIMAL VEGETATION SONDERUP 3.73 6002.85 328 INTERVIEW X 1.70E-07 7.90E-10 GROUNDWATER SONDERUP 3.73 6002.85 328 INTERVIEW X Performed by_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Reviewed by_ _ _ _ __ _ _ _ __ _ __ __ _ __ Page 13 of 14
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 laboratory's 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. Vendor in-house spike sampling was performed without a failure and in-house blank analyses were performed within acceptable ranges. DOE water sample MAW-989 dated 2/1/2016, failed for Co-57. The laboratory properly identified the Sn-75 interfering peak in the vicinity of Co-57 and stated so in the comment field. MAPEP requires results to be reported as an activity with an uncertainty. Since the calculated uncertainty was less than the activity MAPEP interpreted, they submitted result as a "false positive" resulting in a failure . ERA water sample, ERW-1394, failed for Ba-133 on 4/4/2016. The investigation into ERW-1394 failure for Ba-133 lead to no known reason as to why the unacceptable results occurred . The reanalysis created acceptable results. The FCS REMP program does not perform Ba-133 analyses on water samples. Three failures occurred in ERA soil sample MAS0-4780 in August 2016 (Ni-63, U-233/234 and U-238). Ni-63 passed MAPEP soil testing and reanalysis with a smaller aliquot. Vendor lab is investigating improved techniques for analyzing samples with complex matrices. MAPEP states that U-233/234 & U-238 were analyzed the soluble fraction versus total and the HF acid treatment cannot assure complete dissolution. Results report for the soluble fraction only were performed correctly. The lab subsequently passed the ERA test for U-233/234 & 238. No test results failed both the ERA and DOE methodologies for a given sample type. Reanalysis produced acceptable results. The ordering of additional tests and successful testing after corrections were applied, visibly demonstrates the vendor's commitment to reporting and resolving deficiencies. These results indicate the vendor's ability to self-identify and correct any deviations from acceptable or expected results. The test results had no impact on Fort Calhoun samples and were documented as such by the vendor. Page 14 of 14
APPENDIX A INTERLABORATO RY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercornparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD lntercornparison results, in- house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only. January, 2016 through December, 2016
Appendix A lnter1aboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems. Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. Results in Table A-1 were obtained through participation in the RAD PT Study Proficiency Testing Program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Table A-2 lists results for thermoluminescent dosimeters (TLDs), via irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center. Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request. Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request. Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Complete analytical data for duplicate analyses is available upon request. The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program. Results in Table A-7 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML). Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma. Out-of-limit results are explained directly below the result. A1
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES" One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCilliter
> 100 pCilliter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCilliter
> 50 pCilliter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCilliter
> 30 pCilliter or kg 10% of known value Potassium-40 =: 0.1 g/liter or kg 5% of known value Gross alpha :s: 20 pCilliter 5.0 pCilliter
> 20 pCilliter 25% of known value G ross beta :s: 100 pCilliter 5.0 pCilliter
> 100 pCilliter 5% of known value Tritium :s: 4,000 pCilliter +/- 1a =
169.85 x (known) 0*0933
> 4,000 pCilliter 10% of known value Radium-226,-228 =: 0.1 pCilliter 15% of known value Plutonium <: 0.1 pCilliter, gram, or sample 10% of known value lodine-131, :s: 55 pCilliter 6 pCi/liter lodine-129b > 55 pCilliter 10% of known value Uranium-238, :s: 35 pCilliter 6 pCi/liter Nickel-63b > 35 pCilliter 15% of known value Technetium-99b lron-55b 50 to 100 pCi/liter 10 pCilliter
> 100 pCilliter 10% of known value Other Analyses b 20% of known value
- From EPA publication, "Environmental Radioactivity Laboratory lntercomparison studies Program", Fiscal Year, 1981-1982, EPA-600/4-81-004.
0 Laboratory lim tt. A2
TABLEA-1. lnte~aboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'. RADstudy Concentration ~~OIL} Lab Code Date Analysis Laboratory ERA Control Result Result Umits Acce~tance ERW-1392 4/412016 Sr-89 43.5 +/-4.3 48.2 37.8-55.6 Pass ERW-1392 4/412016 Sr-90 27.5 +/- 1.9 28.5 20.7-33.1 Pass ERW-1394 ° 4/412016 Ba-133 65.2 +/-3.8 58.8 48.7-64.9 Fail ERW-1394 ' 4/412016 Ba-133 57.8 +/-5.3 58.8 48.7-64.9 Pass ERW-1394 4/412016 Cs-134 43.7+/-3.0 43.3 34.6-47.6 Pass ERW-1394 4/412016 Cs-137 86.1 +/-5.3 78.4 70.6-88.9 Pass ERW-1394 4/412016 Co-60 108 +/-44 102 91.8-114 Pass ERW-1394 4/412016 Zn-65 240 +/- 13 214 193-251 Pass ERW-1397 4/412016 Gr. Alpha 52.0 +/-2.2 62.7 32.9-77.8 Pass ERW-1397 4/412016 Gr. Beta 33.9 +/- 1.2 39.2 26.0-46.7 Pass ERW-1400 4/412016 1-131 24.7 +/-0.6 26.6 22.1 -31 .3 Pass ERW-1402 4/412016 Ra-226 15.6 +/-0.5 15.2 11.3-17.4 Pass ERW-1402 4/412016 Ra-228 5.28 +/-0.76 5.19 3.12-6.93 Pass ERW-1403 4/412016 Uranium 4.02 +/-0.42 4.64 3.39-5.68 Pass ERW-1405 4/412016 H-3 8,150 +/-270 7,840 6,790- 8,620 Pass SPW-2845 71712015 Ba-133 60.3 +/-5.7 64.7 53.9-71.2 Pass SPW-2845 71712015 Cs-134 48.8 +/-9.3 50.1 40.3-55.1 Pass SPW-2845 71712015 Cs-137 101 +/-8 89.8 80.8- 101 Pass SPW-2845 71712015 Co-60 65.1 +/-5.8 59.9 53.9-68.4 Pass SPW-2845 71712015 Zn-65 288 +/-29 265 238 - 310 Pass ERW-3485 7/1112016 Sr-89 43.3 +/-6.5 53.3 42.3 - 60.9 Pass ERW-3485 7/1112016 Sr-90 39.0 +/-2.8 39.2 28.8-45.1 Pass ERW-3487 7/1112016 Ba-133 83.3 +/-4.9 82.9 69.7-91.2 Pass ERW-3487 7/1112016 Cs-134 62.5 +/-4.4 65.3 53.1 -71.8 Pass ERW-3487 7/1112016 Cs-137 98.1 +/-5.6 95.2 85.7-107 Pass ERW-3487 7/1112016 Co-60 122 +/-5 117 105 - 131 Pass ERW-3487 7/1112016 Zn-65 124 +/-9 113 102 - 134 Pass ERW-3490 7/1112016 Gr. Alpha 46.6 +/-2.2 48.1 25.0-60.5 Pass ERW-3490 7/1112016 Gr. Beta 26.8 +/-1.1 28.6 18.2-36.4 Pass ERW-3492 7/1112016 1-131 23.7 +/- 1.0 24.9 20.7-29.5 Pass ERW-3493 7/1112016 Ra-226 12.9 +/-0.4 12.3 9.2- 14.2 Pass ERW-3493 7/1112016 Ra-228 5.8 +/-0.8 5.8 3.5-7.6 Pass ERW-3493 7/1112016 Uranium 32 .8 +/-0.8 25.2 28.4-39.3 Pass ERW-3495 7/1112016 H-3 12,400 +/-334 12,400 10,800- 13,600 Pass ' Results obtained by Environmental, Inc ., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA). 0 No reason determined for failure of Ba-133 resuft. ' The resuft of reanalysis (Compare to original resuft, footnoted 'b' above). Al-1
TABLE A-2. Thermoluminescent Dosimetry, (TLD, GaS04 : D)' Cards). a b mrem Lab Code lrradi ation Delivered Reported Performance ' Date Descri~tion Dose Dose Quotient!Pl Acceptance *
!;;D~irllD!D!:Dlsll Icc Group 1 2016-1 10/712016 Spike 1 135.0 148.3 0.10 2016-1 10/712016 Spike 2 135.0 144.3 0.07 2016-1 10/712016 Spike 3 135.0 133.2 -0.01 2016-1 10/712016 Spike 4 135.0 139.6 0.03 2016-1 10/712016 Spike 5 135.0 128.4 -0.05 2016-1 10/712016 Spike 6 135.0 123.9 -0.08 2016-1 10/712016 Spike 7 135.0 124.0 -0.08 2016-1 10/712016 Spike 8 135.0 121.5 -0.10 2016-1 10/712016 Spike 9 135.0 148.3 0.10 2016-1 10/712016 Spike 10 135.0 126.8 -0.06 2016-1 10/712016 Spike 11 135.0 123.3 -0.09 2016-1 10/712016 Spike 12 135.0 137.9 0.02 2016-1 10/712016 Spike 13 135.0 126.0 -0.07 2016-1 10/712016 Spike 14 135.0 127.2 -0.06 2016-1 10/712016 Spike 15 135.0 144.5 0.07 2016-1 10/712016 Spike 16 135.0 140.5 0.04 2016-1 10/712016 Spike 17 135.0 146.0 0.08 2016-1 10/712016 Spike 18 135.0 127.7 -0.05 2016-1 10/712016 Spike 19 135.0 146.8 0.09 2016-1 10/712016 Spike 20 135.0 122.6 -0.09 2016-1 10/712016 Spike 21 135.0 108.6 -0.20 2016-1 10/712016 Spike 22 135.0 119.6 -0.11 2016-1 10/712016 Spike 23 135.0 135.1 0.00 2016-1 10/712016 Spike 24 135.0 116.2 -0.14 2016-1 10/712016 Spike 25 135.0 118.9 -0.12 2016-1 10/712016 Spike 26 135.0 128.5 -0.05 2016-1 10/712016 Spike 27 135.0 115.6 -0.14 2016-1 10/712016 Spike 28 135.0 126.4 -0.06 2016-1 10/712016 Spike 29 135.0 115.0 -0.15 2016-1 10/712016 Spike 30 135.0 147.3 0.09 Mean (Spike 1-30) 130.4 0 .03 Pass standard Deviation (Spike 1-30) 11.5 0.09 Pass a Table A-2 assumes 1 roentgen = 1 rem (NRC -Health Physics Questions and Answers 10 CFR Part 20- Question 96 -Page Last Reviewed/Updated Thursday, October 01 , 2015).
0 TLD's were irradiated by the University of Wsconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the resu~s were submitted by Environmental inc. to the University of Wsconsin-Madison Radiation Calibration Laboratory for comparison to the dell-ed dose. ' Performance Quaient (P) is calculated as ((reported dose- conventially true value) + conventially true value) v.tlere the conventially true value is the delivered dose. 0 Acceptance is achie-.oed v.tlen neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15. A2-1
TABLE A-2 Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards). ab mrem Lab Code Irradiation Delivered Reported Performance c Date Descnetion Dose Dose Quotient !P! Acceptance d Environmental, Inc. Group 2 2016-2 10/712016 Spike 31 87.0 83.0 -0.05 2016-2 10/712016 Spike 32 87.0 88.3 0.01 2016-2 10/712016 Spike 33 87.0 83.1 -0.04 2016-2 10/712016 Spike 34 87.0 81.4 -0.06 2016-2 10/712016 Spike 35 87.0 78.9 -0.09 2016-2 101712016 Spike 36 87.0 80.3 -0.08 2016-2 10/712016 Spike 37 87.0 101 .1 0.16 2016-2 10/712016 Spike 38 87.0 78.3 -0.10 2016-2 10/712016 Spike 39 87.0 86.6 0.00 2016-2 10/712016 Spike 40 87.0 81 .8 -0.06 2016-2 10/712016 Spike 41 87.0 84.8 -0.03 2016-2 10/712016 Spike 42 87.0 79.9 -0.08 2016-2 10/712016 Spike 43 87.0 80.8 -0.07 2016-2 10/712016 Spike 44 87.0 80.2 -0.08 2016-2 10/712016 Spike 45 87.0 82.7 -0.05 2016-2 10/712016 Spike 46 87.0 104.0 0.20 2016-2 10/712016 Spike 47 87.0 86.1 -0.01 2016-2 10/712016 Spike 48 87.0 104.0 0.20 2016-2 10fi/2016 Spike 49 87.0 86.1 -0.01 2016-2 10/712016 Spike 50 87.0 90.8 0.04 2016-2 10/712016 Spike 51 87.0 85.7 -0.01 2016-2 10/712016 Spike 52 87.0 86.5 -0.01 2016-2 10/712016 Spike 53 87.0 86.4 -0.01 2016-2 10/712016 Spike 54 87.0 92.6 0.06 2016-2 10/712016 Spike 55 87.0 88.6 0.02 2016-2 10/712016 Spike 56 87.0 78.9 -0.09 2016-2 10/712016 Spike 57 87.0 82.6 -0.05 2016-2 10/712016 Spike 58 87.0 80.6 -0.07 2016-2 10/712016 Spike 59 87.0 89.9 0.03 2016-2 10/712016 Spike 60 87.0 85.0 -0.02 Mean (Spike 31-60) 86.0 0.01 Pass Standard Deviation (Spike 31-60) 6.9 0.08 Pass
- Table A-2 assumes 1 roentgen= 1 rem (NRC -Health Physics Questions and Answers 10 CFR Part 20- Question 96 - Page Last Re<liewed/Updated Thursday, October 01, 2015).
' TLD's were irradiated by the University of Wisconsi~Madison Radiation Calibration Laboratory follov.ing ANSI N13.37 protocol !Tom a known air kenna rate. TLD's were read and the resu~s were submitted by Environmental Inc. to the Univers~y of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose. ' Performance Quotient (P) is calculated as ((reported dose- conventially true value) + conventially true value) v.tlere the conventially true value is the delivered dose. d Acceptance is achieved v.tlen neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15. A2-2
TABLE A-3. In-House "Spiked" Samples Concentration a lab Code b Date Analysis laboratory results Known Control 2s, n=1 c Activity limitsd Acceptance SPW-290 1/21/2016 Sr-90 36.6 +/- 1.5 37.3 22.4- 52.2 Pass SPW-292 1/21/2016 Sr-90 35.6 +/- 1.6 37.3 22.4- 52.2 Pass SPW-294 1/21/2016 C-14 4,669 +/- 16 4,735 2,641 - 6,629 Pass SPW-414 211/2016 Ra-226 16.4 +/- 2.2 17.7 10.6 - 24.6 Pass W-020416 2/4/2016 Gr. Alpha 20.6 +/- 0.4 20.1 12.0-26.1 Pass W-020416 2/4/2016 Gr. Beta 29.7 +/- 0.3 28.9 17.3 - 40.4 Pass W-021716 2/17/2016 Ra-226 17.9 +/- 0.5 16.7 10.0-23.4 Pass W-030716 3/7/2016 Gr. Alpha 16.3 +/- 0.6 20.1 12.0-28.1 Pass W-030716 3/7/2016 Gr. Beta 27.0 +/- 0.7 28.9 17.3 - 40.4 Pass SPDW-70046 3/29/2016 Ra-226 13.4 +/- 0.4 16.7 10.0- 23.4 Pass SPW-1163 3/2212016 Ra-226 4.2 +/- 0.7 4.4 2.6-6.2 Pass SPW-1235 3/29/2016 Gr. Alpha 21.0 +/- 0.4 20.1 12.0-28.1 Pass SPW-1235 3/29/2016 Gr. Beta 29.4 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-1739 4/21/2016 Ra-226 16.2 +/- 2.0 17.7 10.6- 24.6 Pass SPW-2052 4/21/2016 Ra-226 16.0 +/- 0.5 16.7 10.0- 23.4 Pass W-042616 4/21/2016 Fe-55 1,519 +/-61 1,482 889 - 2,075 Pass SPW-1623 4/23/2016 Gr. Alpha 21 .0 +/- 0.4 20.1 12.0 - 26.1 Pass SPW-1623 4/23/2016 Gr. Beta 26.6 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-1996 4/29/2016 Cs-134 35.9 +/- 6.0 36.2 21.7 - 50.6 Pass SPW-1998 4/29/2016 Cs-137 82.5 +/- 7.6 71.9 43.1 - 100.6 Pass SPW-2097 513/2016 H-3 3,349 +/- 164 3,260 1,966 - 4,592 Pass SPW-2132 5/4/2016 H-3 3,174 +/- 176 3,260 1,966 - 4,592 Pass SPW-2229 5/7/2016 H-3 3,162 +/- 179 3,260 1,968 - 4,592 Pass SPW-2313 5/1312016 H-3 3,163 +/- 179 3,280 1,966 - 4,592 Pass SPW-2341 5/13/2016 H-3 3,201 +/- 178 3,260 1,968 - 4,592 Pass SPW-2374 5/14/2016 H-3 3,037 +/- 175 3,260 1,966 - 4,592 Pass SPW-2411 5/1712016 Sr-90 37.3 +/- 1.6 37.3 22.4 - 52.2 Pass SPW-2455 5/19/2016 Gr. Alpha 19.3 +/- 0.4 20.1 12.0 - 28.1 Pass SPW-2455 5/19/2016 Gr. Beta 26.6 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-2457 5119/2016 U-238 48 .2 +/- 2.4 41 .7 25.0- 58.4 Pass SPW-2504 5/20/2016 H-3 3,161 +/- 176 3,260 1,966 - 4,592 Pass SPW-2526 5/23/2016 H-3 2,996 +/- 175 3,260 1,968 - 4,592 Pass SPW-2566 5/24/2016 Gr. Alpha 19.6 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-2566 5/24/2016 Gr. Beta 30.4 +/- 0.3 28.9 17.3- 40.4 Pass W-053116 4/29/2016 Cs-134 34.0 +/- 5.0 36.2 21 .7- 50.6 Pass W-053116 4/29/2016 Cs-137 76.6 +/- 7.0 71 .9 43.1 - 100.6 Pass SPW-2704 611/2016 Sr-90 38.0 +/- 1.6 37.3 22.4-52.2 Pass SPW-2719 6/2/2016 Ra-226 18.1 +/- 2.1 17.7 10.6- 24.8 Pass SPW-2749 613/2016 H-3 3,197 +/- 160 3,260 1,966 - 4,592 Pass SPW-2643 6/7/2016 H-3 3,133 +/- 179 3,260 1,966 - 4,592 Pass SPW-3227 6/17/2016 Ra-226 16.6 +/- 0.4 16.7 10.0 - 23 .4 Pass W-061716 4/29/2016 Cs-134 37.3 +/- 6.2 36.2 21.7 - 50.6 Pass W-061716 4/29/2016 Cs-137 79.7 +/- 10.8 71 .9 43.1 - 100.6 Pass SPW-3240 6/26/2016 Gr. Alpha 25.3 +/- 0.5 20.1 12.0 - 28.1 Pass SPW-3240 6/26/2016 Gr. Beta 27.1 +/- 0.3 28.9 17.3-40.4 Pass A3-1
TABLE A-3. In-House "Spiked" Samples Concentration
- Lab Code b Date Analysis Laboratory results Known Control 2s, n=1' ActiV!!i: Limits d Acce~nce SPW-3241 7/1/2016 H-3 8,821 +/- 283 8,650 5,190-12,110 Pass SPW-3309 7/1/2016 H-3 8,619 +/- 278 8,650 5,190-12,110 Pass SPW-3313 7/1/2016 Ra-228 16.6 +/- 2.0 17.7 10.6-24.8 Pass SPW-3328 7/6/2016 Sr-89 13.4 +/- 9.2 14.8 8.9-20.7 Pass SPW-3328 7/6/2016 Sr-90 12.3 +/- 1.3 11.4 6.8- 16.0 Pass SPAP-3365 717/2016 Gr. Beta 39.7+/-0.1 42.2 25.3-59.0 Pass SPAP-3367 717/2016 Cs-134 1.2 +/-0.7 1.2 0.7- 1.7 Pass SPAP-3367 717/2016 Cs-137 94.4 +/- 2.8 94.0 56.4- 131.6 Pass SPW-3370 717/2016 C-14 4,444 +/- 17 4,735 2,841 -6,629 Pass SPW-3373 1n12o16 Ni-63 446 +/-5 401 241 -561 Pass SPW-3375 717/2016 Tc-99 545 +/-9 539 324-755 Pass SPW-3519 7/1412016 H-3 8,621 +/- 279 8650 5,190-12,110 Pass SPW-3688 6129/2016 Ra-226 17.5 +/- 0.4 16.7 10.0-23.4 Pass SPW-3711 7/20/2016 H-3 44,368 +/- 612 43,766 26,260 - 61 ,273 Pass SPW-3774 7/22/2016 H-3 45,259 +/- 619 43,766 26,260-61,273 Pass SPW-3776 7/22/2016 Gr. Alpha 23.3 +/- 0.5 20.1 12.0-28.1 Pass SPW-3776 7/2212016 Gr. Beta 27.5 +/- 0.3 28.9 17.3-40.4 Pass SPW-3884 7/26/2016 H-3 45,850 +/- 623 43,766 26,260 - 61,273 Pass SPW-3950 7/2812016 Ra-228 17.8 +/- 1.8 16.7 10-23 Pass SPW-3982 7129/2016 H-3 45,273 +/- 619 43,766 26,260-61 ,273 Pass W-073016 4/29/2016 Cs-134 36.5 +/- 6.1 36.2 21.7-50.6 Pass W-073016 4129/2016 Cs-137 80.6 +/- 7.5 71.9 43.1 - 100.6 Pass SPW-4134 8/4/2016 Ra-228 5.5 +/- 0.8 6.7 4.0-9.3 Pass SPW-4340 8/17/2016 Ra-228 19.9 +/- 2.0 16.7 10.0-23.4 Pass SPW-4386 7/1512016 Ra-226 18.0 +/- 0.4 16.7 10.0-23.4 Pass W-082716 4129/2016 Ra-228 32.5 +/- 5.2 36.2 21.7-50.6 Pass W-082716 4/29/2016 Ra-226 78.5 +/- 8.3 71.9 43.1 -100.6 Pass SPW-4642 9/6/2016 U-238 45.8 +/- 2.5 41.7 25.0-58.4 Pass SPW-4999 9/26/2016 Sr-90 35.1 +/- 2.2 36.8 22.1-51.5 Pass SPW-5091 9/12/2016 Ra-226 18.2 +/- 0.4 16.7 10.0 - 23.4 Pass W-092716 4/29/2016 Cs-134 37.3 +/- 11.8 36.2 21.7 - 50.6 Pass W-092716 4/29/2016 Cs-137 78.3 +/- 11.2 71.9 43.1 - 100.6 Pass SPW-5165 9/30/2016 Gr. Alpha 22.2 +/- 0.4 20.1 12.0 - 28.1 Pass SPW-5165 9/30/2016 Gr. Beta 27.2 +/- 0.3 28.9 17.3 - 40.4 Pass SPW-5426 9/28/2016 Ra-226 18.2 +/- 0.4 16.7 10.0 - 23.4 Pass SPW-5510 10/18/2016 H-3 44,398 +/- 618 43,766 26,260 - 61273 Pass SPW-5553 10/19/2016 U-238 50.0 +/- 2.6 41.7 25.0-58.4 Pass SPW-5555 10/19/2016 Ra-228 17.4 +/- 1.9 16.7 10.0- 23.4 Pass SPW-5612 10/20/2016 H-3 44,681 +/- 622 43,766 26,260-61,273 Pass SPW-5741 10/25/2016 H-3 44,946 +/- 624 43,766 26,260- 61,273 Pass SPU-5833 10126/2016 H-3 10,018 +/- 946 8,622 5,173-12,071 Pass SPW-5862 10/28/2016 H-3 18,061 +/- 374 17,244 10,346-24,141 Pass W-103116 4/29/2016 Cs-134 36.0 +/- 4.6 36.2 21.7-50.6 Pass W-103116 4/2912016 Cs-137 81.1 +/-7.3 71 .9 43.1 - 100.6 Pass A3-2
TABLE A-3 . In-House "Spiked" Samples Concentration " Lab Code b Date Analysis Laboratory results Known Control 2s, n=1c Activity Limits d Acceptance SPW-5984 111212016 H-3 17,727 +/-399 17,244 10,346 - 24,141 Pass SPW-6008 11/412016 H-3 17,854 +/- 402 17,244 10,346-24,141 Pass SPW-6124 111812016 Ra-228 14.4 +/- 1.9 16.0 9.6-22.4 Pass SPW-6132 11/912016 H-3 18,135 +/- 374 17,243 10,346 - 24,140 Pass SPW-6135 10/12/2016 Ra-226 18.9 +/- 0.4 16.7 10.0-23.4 Pass SPW-6146 11/10/2016 H-3 17,488 +/- 398 17,243 10,346-24,140 Pass SPW-6222 11/12/2016 H-3 17,787 +/-408 17,243 10,346-24,140 Pass SPW-6318 11/16/2016 H-3 17,379 +/- 408 17,243 10,346-24,140 Pass SPW-6349 11/17/2016 H-3 17,893 +/- 371 17,243 10,346-24,140 Pass SPW-6424 11/19/2016 H-3 18,258 +/- 379 17,243 10,346-24,140 Pass W - 112616 4/2912016 Cs-134 35.0 +/- 6.0 36.2 21.7-50.6 Pass W-112616 4/2912016 Cs-137 75.0 +/-7.1 71.9 43.1 - 100.6 Pass SPW-6456 11128/2016 Sr-90 41 .9 +/- 2.5 36.8 22.1 - 51.5 Pass SPW-6486 11/30/2016 Sr-90 35.6 +/- 2.2 36.6 21.9 - 51.2 Pass SPW-6490 11129/2016 Ra-226 18.8 +/-0.4 16.7 10.0 - 23.4 Pass SPW-6519 11/30/2016 Ni-63 438 +/-4 400 240 - 560 Pass SPW-6527 12/112016 U-238 49.5 +/-2.5 41 .7 25.0 - 58.4 Pass SPW-6616 12/312016 H-3 18,018 +/- 374 17,243 10,346-24,140 Pass SPW-6669 121512016 H-3 18,237 +/- 377 17,243 10,346 - 24,140 Pass SPW-6735 12/912016 H-3 17,939 +/- 396 17,243 10,346 - 24,140 Pass SPW-6880 12121/2016 H-3 17,835 +/- 396 17,243 10,346 - 24,140 Pass SPW-6947 12122/2016 Ni-63 450 +/-4 400 240-560 Pass W-122316 4/2912016 Cs-134 36.0 +/-2.2 36.2 21.7-50.6 Pass W-122316 4/2912016 Cs-134 76.1 +/-2.9 71 .9 43.1-100.6 Pass SPW-6948 12/30/2016 H-3 17,999 +/-398 17,243 10,346-24,140 Pass SPW-6974 12129/2016 Ra-226 17.6 +/- 0.4 16.7 10.0-23.4 Pass
- Liquid sample results are reported in pO/Liter, air filters ( p0/m3), charcoal (pCVcharcoal canister), and solid samples (pQikg).
' Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine). c Results are based on single determinations.
' Controllimtts are established from the precision values listed in Attachment A of this report , adjusted to+/- 2s.
NOTE: For fish , gelatin is used for the spike matrix. For vegetation, cabbage is used for the spike matrix. A3-3
TABLE A-4. In-House "Blank" Samples Concentration ' Lab Code Sample Date Analysis" Laboratory results (4.66a) Acceptance TYpe LLD Activity' Criteria (4.66 a) SPW-289 Water 1/21/2016 Sr-90 0.55 0.28 :t 0.29 SPW-291 Water 1121/2016 Sr-90 0.61 0.15 :t 0.30 SPW-293 Water 1121/2016 C-14 147 -12 :t89 200 SPW-413 Water 2/112016 Ra-228 0.86 1.86 :t 0.60 2 W-020416 Water 2/4/2016 Gr. Alpha 0.43 -0.17 :t 0.28 2 W-020416 Water 2/4/2016 Gr. Beta 0.73 0.36 :t 0.53 4 W-020916 Water 2/9/2016 Ra-226 0.02 0.01 :t0.01 2 W-030716 Water 317/2016 Gr. Alpha 0.90 -0.36 :t 0.32 2 W-030716 Water 317/2016 Gr. Beta 1.59 -0.62 +/- 0.71 4 SPDW-70045 Water 3/29/2016 Ra-226 0.03 0.01 :t 0.02 2 SPDW-1234 Water 3130/2016 Gr. Alpha 0.44 -0.05 :t 0.30 2 SPDW-1234 Water 3/30/2016 Gr. Beta 0.79 -0.54 :t 0.54 4 SPW-1738 Water 4/21/2016 Ra-228 1.05 0.13 :t 0.50 2 SPW-1822 Water 4/23/2016 Gr. Alpha 0.50 -0.18 :t 0.33 2 SPW-1822 Water 4/23/2016 Gr. Beta 0.08 -0 .35 :t 0.51 4 SPW-2051 Water 4/1212016 Ra-226 0.02 0.03 :t 0.02 2 SPW-2069 Water 513/2016 1-131 0.15 0.06 :t 0.09 SPW-2133 Water 5/4/2016 H-3 148 55 +/-76 200 SPW-2230 Water 517/2016 H-3 149 -11 :t 73 200 SPW-2314 Water 5/13/2016 H-3 150 -29 :t 72 200 SPW-2342 Water 5/13/2016 H-3 143 50 :!:74 200 SPW-2364 Water 5/13/2016 1-131 0.22 -0.03 :t 0.12 SPW-2375 Water 5/14/2016 H-3 146 1 +/-70 200 SPW-2410 Water 5/17/2016 Sr-90 0.59 0.10 :t 0.29 1 SPW-2454 Water 5/19/2016 Gr. Alpha 0.47 -0.21 :!: 0.31 2 SPW-2454 Water 5/19/2016 Gr. Beta 0.77 -0 .49:!: 0.52 4 SPW-2456 Water 5/19/2016 U-238 0.15 0.00:!: 0.09 1 SPW-2485 Water 5/20/2016 1-131 0.18 -0.01 :!:0.10 SPW-2505 Water 5/2012016 H-3 144 64 :!:75 200 SPW-2529 Water 5/23/2016 H-3 152 -3:!: 75 200 SPW-2530 Water 5/23/2016 Ra-228 0.96 -0.12 :t 0.43 2 SPW-2565 Water 5/24/2016 Gr. Alpha 0.47 0.03 :t 0.33 2 SPW-2565 Water 5/24/2016 Gr. Beta 0.77 -0.23:!: 0.53 4 SPW-2703 Water 6/1/2016 Sr-89 0.68 -0.13:!: 0.50 5 SPW-2703 Water 6/1/2016 Sr-90 0.55 0.11 :!:0.27 1 SPW-2718 Water 6/212016 Ra-228 0.67 0.23:!: 0.34 2 SPW-2720 Water 6/212016 1-131 0.16 O.ot :1: 0.09 1 SPW-2750 Water 6/3/2016 H-3 151 -31 :!: 73 200 SPW-2844 Water 617/2016 H-3 148 -55:!: 75 200 SPMI-2959 Milk 6/14/2016 1-131 0.16 0.09:!: 0.10 1 SPW-3137 Water 6/23/2016 1-131 0.15 -0.03 +/- 0.08 SPW-3226 Water 6/17/2016 Ra-226 0.02 -0.01 :!: 0.04 2 SPW-3239 Water 6/28/2016 Gr. Alpha 0.40 -0.15:!: 0.26 2 SPW-3239 Water 6/28/2016 Gr. Beta 0.73 0.14 +/- 0.52 4 SPW-3687 Water 6/29/2016 Ra-226 0.04 0.03:!: 0.03 2 ' Liquid sample resuHs are reported In pCIILHer, air ftHers ( pCihn 3), charcoal (pCilcharcoal canister), and solid samples (pCVg). ' I-131(G); lodlne-131 as analyzed by gamma spectroscopy. ' ActMty reported Is a net actMty resuH. M-1
TABLE A-4. In-House " Blank" Samples Concentration ' Lab Code Sample Date Analysis" Laboratory results (4.66u) Acceptance TYpe LLD Activity' Criteria (4.66 u) SPW-289 Water 1/21/2016 Sr-90 0.55 0.28 :1:0.29 SPW-291 Water 1121/2016 Sr-90 0.61 0.15:1:0.30 SPW-293 Water 1121/2016 C-14 147 -12 :1:89 200 SPW-413 Water 2/1/2016 Ra-228 0.86 1.86 :1:0.60 2 W-020416 Water 2/4/2016 Gr. Alpha 0.43 -0.17+/-0.28 2 W-020416 Water 2/4/2016 Gr. Beta 0.73 0.36 :1:0.53 4 W-020916 Water 2/9/2016 Ra-226 0 .02 0.01 :1:0.01 2 W-030716 Water 3/7/2016 Gr. Alpha 0 .90 -0.36 :1:0.32 2 W-030716 Water 3/7/2016 Gr. Beta 1.59 -0.62 :1: 0.71 4 SPDW-70045 Water 3/29/2016 Ra-226 0 .03 0.01 :1:0.02 2 SPDW-1234 Water 3/30/2016 Gr. Alpha 0.44 -0.05 :1: 0.30 2 SPDW-1234 Water 3/30/2016 Gr. Beta 0.79 -0.54 :1:0.54 4 SPW-1738 Water 4/21/2016 Ra-228 1.05 0.13 :1:0.50 2 SPW-1822 Water 4/2312016 Gr. Alpha 0 .50 -0.18 :1:0.33 2 SPW-1822 Water 4/23/2016 Gr. Beta 0.08 -0.35 :1:0.51 4 SPW-2051 Water 4/12/2016 Ra-226 0 .02 0 .03 :1:0.02 2 SPW-2069 Water 5/3/2016 1-131 0.15 0 .06 :1:0.09 SPW-2133 Water 5/4/2016 H-3 148 55 +/-76 200 SPW-2230 Water 5/7/2016 H-3 149 -11 :1:73 200 SPW-2314 Water 5/13/2016 H-3 150 -29 :1:72 200 SPW-2342 Water 5/13/2016 H-3 143 50 +/-74 200 SPW-2364 Water 5/13/2016 1-131 0.22 -0.03 :1:0.12 SPW-2375 Water 5/14/2016 H- 3 146 1 :1:70 200 SPW-2410 Water 5/17/2016 Sr-90 0.59 0.10:1:0.29 SPW-2454 Water 5/19/2016 Gr. Alpha 0.47 -0.21 :1: 0.31 2 SPW- 2454 Water 5/19/2016 Gr. Beta 0.77 -0.49 :1:0.52 4 SPW-2456 Water 5/19/2016 U-238 0.15 0 .00 :1:0.09 SPW-2485 Water 5/20/2016 1-131 0 .18 -0.01 :1:0.10 SPW-2505 Water 5/20/2016 H-3 144 64 :1:75 200 SPW-2529 Water 5/2312016 H-3 152 -3 :1:75 200 SPW-2530 Water 5/23/2016 Ra-228 0 .96 -0.12:1:0.43 2 SPW-2565 Water 5/24/2016 Gr. Alpha 0.47 0 .03 :1:0.33 2 SPW-2565 Water 5/24/2016 Gr. Beta 0 .77 -0 .23 :1:0.53 4 SPW-2703 Water 6/112016 Sr-89 0.68 -0.13 :1:0.50 5 SPW-2703 Water 6/1/2016 Sr-90 0.55 0 .11 :1:0.27 1 SPW-2718 Water 6/2/2016 Ra-228 0.67 0 .23 :1:0.34 2 SPW-2720 Water 6/2/2016 1-131 0 .16 0.01 :1:0.09 SPW-2750 Water 6/3/2016 H-3 151 -31 :1: 73 200 SPW-2844 Water 6/7/2016 H-3 148 -55 :1: 75 200 SPMI-2959 Milk 6/14/2016 1-131 0 .16 0.09 +/-0.10 SPW-3137 Water 6/23/2016 1-131 0.15 -0.03 :1:0.08 1 SPW-3226 Water 6/17/2016 Ra-226 0.02 -0.01 :1:0.04 2 SPW-3239 Water 6/28/2016 Gr. Alpha 0.40 -0 .15 :1:0.26 2 SPW-3239 Water 6/28/2016 Gr. Beta 0.73 0 .14 :1:0.52 4 SPW-3687 Water 6/29/2016 Ra-226 0.04 0 .03 :1:0.03 2 ' Liquid sample rosuHs are reported In pCVLHer, airfiHers ( pCihn'). charcoal (pCI/charcoal canister). and solid samples (pCVg) . ' I-131(G); lodine-131 as analyzed by gamma spectroscopy. ' Ac1Mty reported Is a netac1Miy rosun. A4-1
TABLE A-4. In-House "Blank" Samples Concentration ' Lab Code Sample Date Analysis' Laboratory results (4.66o) Acceptance TyPe LLD Activity' Criteria (4.66 o) SPW-3312 Water 7/112016 Ra-228 0.67 0.35 +/- 0.35 2 SPW-3327 Water 7/612016 Sr-89 0.67 0.51 +/- 0.51 5 SPW-3327 Water 7/612016 Sr-90 0.60 -0.14 +/- 0.26 SPAP-3364 AP 71712016 Gr.Beta 0.002 0.005 +/- 0.001 0.01 SPW-3370 Water 71712016 C-14 115 49 +/-71 200 SPW-3372 Water 71712016 Ni-63 122 115 +/- 76 200 SPW-3374 Water 71712016 Tc-99 6.07 1.00 +/- 3.70 10 SPW-3710 Water 712012016 H-3 147 35 +/-75 200 SPW-3n5 Water 712212016 Gr. Alpha 0.73 0.41 +/- 0.53 2 SPW-3n5 Water 712212016 Gr. Beta 0.45 -0.14 +/- 0.30 4 SPW-3884 Water 7126/2016 H-3 151 -1 +/- 73 200 SPW-3949 Water 7128/2016 Ra-228 0.76 0.32 +/- 0.39 2 SPW-3982 Water 7129/2016 H-3 145 49 +/-75 200 SPW-4133 Water 81412016 Ra-228 0.80 0.26 +/-0.40 2 SPW-4257 Water 8/11/2016 1-131 0.17 -0.01 +/- 0.10 1 SPW-4339 Water 8117/2016 Ra-228 0.73 0.36 +/-0.39 2 SPW-4385 Water 7/15/2016 Ra-226 0.09 0.75 +/-0.09 2 SPW-4641 Water 9/612016 U-238 0.21 0.00 +/- 0.13 SPW-4684 Water 9/612016 H-3 151 48 +/- 78 200 SPW-4872 Water 9/1612016 1-131 0.21 0.05 +/-0.11 SPW-4998 Water 9126/2016 Sr-89 0.54 0.06 +/-0.39 5 SPW-4998 Water 912612016 Sr-90 0.53 -0.03 +/-0.24 1 SPW-5090 Water 8119/2016 Ra-226 0.03 0.03 +/- 0.02 2 SPW-5164 Water 9130/2016 Gr. Alpha 0.46 -0.05 +/- 0.32 2 SPW-5164 Water 9130/2016 Gr. Beta 0.74 -0.02 +/- 0.52 4 SPW-5425 Water 9/2812016 Ra-226 0.02 0.07 +/- 0.05 2 SPW-5323 Water 1017/2016 H-3 157 -12 +/- 75 200 SPW-5552 Water 10/1912016 U-238 0.18 0.00 +/-0.11 SPW-5554 Water 10/1912016 Ra-228 0.72 0.22 +/-0.36 2 SPW-5611 Water 10120/2016 H-3 153 67 +/-80 200 SPW-5613 Water 1012112016 Gr. Alpha 0.76 -0.55 +/- 0.51 2 SPW-5613 Water 10/2112016 Gr. Beta 0.42 0.02 +/- 0.29 4 SPW-5740 Water 10/2512016 H-3 154 -2 +/-72 200 SPW-5743 Water 1012512016 Sr-90 1.26 0.72 +/- 0.67 1 SPW-5861 Water 1012812016 H-3 179 129 +/- 91 200 SPW-5983 Water 1112/2016 H-3 156 8 +/-78 200 SPW-6007 Water 11/4/2016 H-3 156 -34 +/- 73 200 SPW-6131 Water 11/9/2016 H-3 180 80 +/-92 200 SPW-6134 Water 10/1212016 Ra-226 0.05 -0.02 +/-0.12 2 SPW-6145 Water 1111012016 H-3 171 -46 +/- 80 200 SPW-6317 Water 11/1612016 H-3 180 -43 +/- 82 200 SPW-6348 Water 11/1712016 H-3 182 -45 +/- 88 200 SPW-6423 Water 11/1912016 H-3 181 8 +/-95 200 SPW-6455 Water 1112812016 Sr-89 0.58 -0.15 +/- 0.46 5 SPW-6455 Water 11128/2016 Sr-90 0.67 0.09 +/- 0.32 1 SPW-6489 Water 1112912016 Ra-226 0.03 0.03 +/- 0.02 2
' Liquid sample resuh are reported in pCi/L~er, air fitters ( pCihn"l, charcoal (pCileharcoal canister), and solid samples (pCilg). ' ~131(G); iodine-131 as analyzed by gamma spectroscopy. ' Actillity reported is a net activity resuft.
M-2
TABLE A-4. In-House "Blank" Samples Concentration a Lab Code Sample Date Analysisb Laborato~ results ( 4.66cr) Acceptance T:tEe LLD Activi!i:c Criteria !4.66 cr) SPW-6529 Water 12/112016 1-131 0.18 -0.03 +/- 0.10 SPW-6616 Water 1213!2016 H-3 180 72 +/-92 200 SPW-6670 Water 121512016 H-3 174 28 +/-92 200 SPW-6735 Water 1219!2016 H-3 152 2 +/-73 200 SPW-6792 Water 12/15/2016 1-131 0.17 0.03 +/-0.12 1 SPW-6819 Water 12/1612016 H-3 158 14 +/-77 200 SPW-6879 Water 12121/2016 H-3 147 80 +/-75 200 SPW-6947 Water 12122/2016 Ni-63 93 26 +/-57 200 SPW-6973 Water 12129/2016 Ra-226 0.03 0.03 +/- 0.02 2 a Liquid sample results are reported in pCill~er, air filters ( pCilm 3), charcoal (pCilchan:oal canister), and solid samples (pCilg). 0 1-131(G); iodine-131 as analyzed by gamma spectroscopy. c Activ~ reported is a net activ~ result. A4-3
TABLE A-5. In-House "Duplicate" Samples Concentration ' Averaged Lab Code Date Analysis First Resutt Second Resutt Resutt Acceptance AP-010416 1/4/2016 Gr. Beta 0.044 +/- 0.006 0.051 +/- 0.006 0.047 +/- 0.004 Pass SPS-62, 63 tn/2016 K-40 21.1 +/-1.9 21 .2 +/- 2.1 21 .2 +/-1 .4 Pass WW-125, 126 1n12016 H-3 659 +/- 102 748 +/- 106 703 +/- 74 Pass SPS-199, 200 1n12016 Cs-137 0.09 +/-0.02 0.08 +/- 0.03 0.08 +/-0.02 Pass SPS-199, 200 1n12016 K-40 7.60 +/-0.60 8.62 +/- 0.62 8.11 +/-0.43 Pass AP-011116 1111/2016 Gr. Beta 0.024 +/- 0.005 0.027 +/- 0.005 0.026 +/- 0.003 Pass AP-011216 111212016 Gr. Beta 0.030 +/- 0.004 0.034 +/- 0.004 0.032 +/- 0.003 Pass WW-262,263 1/14/2016 H-3 153 +/- 78 141 +/-78 147 +/-55 Pass WW-346, 347 1114/2016 H-3 1,036 +/- 117 959 +/- 115 997 +/-82 Pass WW-283, 284 1118/2016 H-3 437 +/-92 427 +/- 91 432 +/-65 Pass AP-011916 1119/2016 Gr. Beta 0.042 +/- 0.005 0.037 +/- 0.004 0.040 +/- 0.003 Pass AP-012016 1/20/2016 Gr. Beta 0.023 +/- 0.003 0.030 +/- 0.004 0.027 +/- 0.002 Pass AP-020116 2/1/2016 Gr. Beta 0.023 +/- 0.005 0.023 +/- 0.005 0.023 +/- 0.004 Pass SWU-472, 473 2/212016 Gr. Beta 4.37 +/-0.47 4.60 +/- 0.49 4 .49 +/-0.34 Pass SG-493, 494 2/6/2016 Ac-228 2.10 +/-0.20 2.13 +/- 0.20 2.12 +/-0.14 Pass SG-493, 494 2/6/2016 K-40 5.79 +/-0.57 5.50 +/- 0.69 5.65 +/-0.45 Pass SG-493,494 2/6/2016 Pb-214 1.84 +/-0.11 1.91 +/-0.11 1.88 +/-0.08 Pass AP-020816 218/2016 Gr. Beta 0.020 +/- 0.004 0.019 +/- 0.004 0.020 +/- 0.003 Pass AP-020916 2/9/2016 Be-7 0.032 +/- 0.005 0.041 +/- 0.006 0.036 +/- 0.004 Pass SPS-619, 620 2/18/2016 K-40 20.0 +/- 1.8 19.1 +/- 1.6 19.5 +/-1.2 Pass WW-840,641 2/18/2016 H-3 90.1 +/-75.0 153.6 +/- 78.4 121 .8 +/-54.2 Pass AP-021916 2/19/2016 Gr. Beta 0.021 +/- 0.003 0.025 +/- 0.004 0.023 +/- 0.002 Pass WW-822, 823 2/26/2016 H-3 2,770 +/- 173 2,974 +/- 178 2,872 +/- 124 Pass DW-70010, 70011 2/29/2016 Ra-226 4.88 +/-0.29 4.93 +/- 0.28 4.91 +/-0.20 Pass DW-7001 0, 70011 2/29/2016 Ra-228 3.00 +/-0.77 1.90 +/- 0.62 2.45 +/-0.49 Pass SW~34.935 3/1/2016 Gr. Beta 0.94 +/-0.52 1.36 +/- 0.60 1.15 +/- 0.40 Pass SPS-913, 914 313/2016 Cs-137 0.08 +/-0.03 0.10 +/- 0.03 0.09 +/-0.02 Pass SPS-913, 914 313/2016 K-40 17.45 +/- 0.94 16.83 +/- 0.95 17.14 +/- 0.67 Pass SPS-913, 914 313/2016 Ra-226 1.02 +/- 0.08 1.13 +/- 0.17 1.07 +/-0.09 Pass SPS-913, 914 313/2016 Ra-228 1.09 +/-0.15 1.13 +/- 0.17 1.11 +/-0.11 Pass AP-030716 3ni2016 Gr. Beta 0.018 +/- 0.005 0.021 +/- 0.005 0.019 +/- 0.003 Pass F-1303,1304 Jn/2016 K-40 3.320 +/- 0.475 3.508 +/- 0.396 3.414 +/- 0.309 Pass SG-976, 977 3/812016 Ra-226 6.75 +/-0.25 6.28 +/- 0.22 6.52 +/-0.17 Pass SG-976, 977 3/812016 Ra-228 9.21 +/-0.49 9.09 +/- 0.49 9.15 +/-0.35 Pass PM-1094, 1095 3/9/2016 K-40 14.01 +/-0.68 14.47 +/- 0.72 14.24 +/-0.49 Pass Ml-1042,1043 3n/2016 K-40 1,684 +/- 124 1,804 +/- 119 1,744 +/- 86 Pass DW-70023, 70024 3ni2016 Ra-226 3.40 +/-0.43 2.68 +/- 0.35 3.04 +/-0.28 Pass DW-70023, 70024 3ni2016 Ra-228 4.46 +/-0.83 5.74 +/- 0.94 5.10 +/-0.63 Pass DW-70014, 70015 3ni2016 Gr. Alpha 13.38 +/- 1.58 11.40 +/-1.43 12.39 +/- 1.07 Pass DW-70026, 70027 3ni2016 Gr. Alpha 3.46 +/-0.79 3.08 +/- 0.74 3.27 +/-0.54 Pass DW-70038, 70039 318/2016 Gr. Alpha 1.14 +/-0.89 1.73 +/- 0.95 1.44 +/-0.65 Pass DW-70035, 70036 318/2016 Ra-226 0.47 +/-0.10 0.45 +/- 0.09 0.46 +/-0.07 Pass DW-70035, 70036 318/2016 Ra-228 0.56 +/-0.45 0.47 +/- 0.44 0.52 +/-0.31 Pass AP-031516 3/15/2016 Gr. Beta 0.014 +/- 0.003 0.016 +/- 0.004 O.D15 +/- 0.002 Pass AP-032116 3121/2016 Gr. Beta 0.014 +/- 0.004 0.020 +/- 0.004 0.017 +/- 0.003 Pass AP-1218,1219 3/24/2016 Be-7 0.135 +/- 0.065 0.167 +/- 0.081 0.151 +/- 0.052 Pass AP-1719,1720 3128/2016 Be-7 0.075 +/- 0.008 0.076 +/- 0.007 0.076 +/- 0.005 Pass AP-033016 3/30/2016 Gr. Beta 0.023 +/- 0.004 0.025 +/- 0.004 0.024 +/- 0.003 Pass SPS-1260, 1261 3130/2016 K-40 18.00 +/-1.92 19.67 +/- 1.77 18.84 +/-1 .30 Pass XW-1467, 1468 3130/2016 H-3 310 +/- 87 295 +/- 86 303 +/- 61 Pass XWW-1530, 1531 3130/2016 H-3 198 +/-84 162 +/- 82 180 +/-59 Pass AP-1827, 1828 3130/2016 Be-7 0.069 +/- 0.011 0.072 +/- 0.011 0.071 +/- 0.008 Pass AP-1323, 1324 3131/2016 Be-7 0.206 +/-0.120 0.197 +/- 0.091 0.202 +/- 0.076 Pass LW-1446,1447 3131/2016 Gr. Beta 2.36 +/-0.93 2.23 +/- 1.01 2.29 +/-0.69 Pass AS-1
TABLE A-5. In-House "Duplicate" Samples Concentration a Averaged Lab Code Date Analysis First Resu~ Second Result Resu~ Acceptance WW-1740,1741 4/212016 H-3 21 ,162 :120 21,091 +/-427 21,126 +/-222 Pass SPS-1344, 1345 4/4/2016 K-40 17.98 ,. 0.93 17.14 +/-0.96 17.56,. 0.67 Pass SPS-1344, 1345 4/4/2016 Pb-214 1.12 :0.09 1.04 +/-0.08 1.08,. 0.06 Pass SPS-1344, 1345 4/4/2016 Ac-228 1.23:0.15 1.33 +/-0.19 1.28 +/-0.12 Pass SPS-1344, 1345 4/4/2016 Cs-137 0.13,. 0.03 0.13,. 0.03 0.13,. 0.02 Pass P-1509,1510 4/812016 H-3 1,094 :120 1,038 +/-119 1,061 +/-85 Pass AP-041116 4/11/2016 Gr. Beta 0.020 ,. 0.004 0.019,. 0.004 0.019 ,. 0.003 Pass SS-1551 ,1552 4/1212016 Gr. Beta 8.71 :1.11 8.88 +/-1.13 8.80,. 0.79 Pass SS-1551 ,1552 4/1212016 K-40 3.50,. 0.25 3.06 +/-0.28 3.28,. 0.19 Pass SS-1551 ,1552 4/1212016 Tl-208 0.05,. 0.02 0.05 +/-0.02 0.05,. 0.01 Pass SS-1551,1552 4/12/2016 Bl-214 0.10,. 0.02 0.09 +/-0.02 0.10 +/-0.02 Pass SS-1551,1552 4/1212016 Pb-212 0.13,. 0.02 0.11 +/-0.02 0.12,. 0.01 Pass SS-1551,1552 4/1212016 Ra-226 0.35,. 0.17 0.30 +/-0.17 0.32 ,. 0.12 Pass SS-1551,1552 4/1212016 Ac-228 0.16,. 0.05 0.17 +/-0.05 0.17 +/-0.04 Pass SS-1593,1594 4/1212016 K-40 14.80,. 0.73 14.89,. 0.78 14.85,. 0.53 Pass WW-1677, 1678 4/14/2016 Ra-226 0.23:0.13 0.35 +/-0.15 0.29,. 0.10 Pass WW-1783,1794 4/1412016 H-3 768:111 632 +/-107 700,. 77 Pass BS-1 804,1 805 4/1812016 K-40 0.79,. 0.02 0.87 +/-0.19 0.83,. 0.10 Pass WW-2021 ,2022 4/1812016 H-3 5,548,. 221 5,707 +/-224 5,627 +/-157 Pass XWW-2240, 2241 4/1812016 H-3 638 +/-104 543 +/-101 591 +/-72 Pass XWW-2109, 2110 4/1912016 H-3 3461 :185 3250 +/-180 3356 +/-129 Pass SPS-2130, 2131 4/2512016 K-40 7.80,. 0.84 6.80 +/-0.60 7.30,. 0.52 Pass AP-042516 4/2512016 Gr. Beta 0.020 ,. 0.004 0.023 ,. 0.004 0.022 ,. 0.003 Pass BS-2065, 2066 4/2512016 K-40 14.40 +/-1 .50 14.72 +/-1.19 14.56,. 0.96 Pass AP-042716 4/27/2016 Gr. Beta 0.023 ,. 0.003 0.019 ,. 0.003 0.021 ,. 0.002 Pass SPS-1999, 2000 4/2812016 K-40 19.94 +/-1.76 18.963 ,. 2.42 19.40 +/-1 .50 Pass S0-2153,2154 5/212016 K-40 21 .80 ,. 0.81 21 .17 +/-0.85 21.48,. 0.59 Pass S0-2153,2154 5/212016 Cs-137 0.11 +/-0.03 0.11 +/-0.07 0.11,. 0.04 Pass S0-2153,2154 5/212016 Ra-226 1.50,. 0.29 1.22 +/-0.29 1.36 +/-0.21 Pass S0-2153,2154 51212016 Pb-214 0.56,. 0.06 0.57 +/-0.06 0.57,. 0.04 Pass W-2394,2395 5/512016 H-3 736 +/-106 631 +/-102 683,. 74 Pass VE-2294,2285 5/912016 K-40 3.50,. 0.25 3.06 +/-0.28 3.28 ,. 0.19 Pass AP-051016 5/10/2016 Gr. Beta 0.020 ,. 0.005 0.018,. 0.005 0.019 ,. 0.003 Pass SG-2261, 2262 5/10/2016 Ac-228 34.4 +/-1.2 34.4 +/-1.4 34.4,. 0.9 Pass SG-2261, 2262 5110/2016 Pb-214 29.5,. 3.0 31.9 +/-3.3 30.7,. 2.2 Pass BS-2439, 2440 5/1212016 K-40 9.96,. 0.91 10.27,. 0.76 10.11 +/-0.59 Pass WW-2534,2535 5/1612016 H-3 14,342,. 354 14,613 +/-357 14,477,. 252 Pass AP-051716 5/17/2016 Gr. Beta 0.014 ,. 0.004 0.015 +/-0.004 0.014 ,. 0.003 Pass SPS-2945, 2946 5/1912016 K-40 30.71 ,. 0.74 31 .75 +/-0.78 31 .23,. 0.54 Pass SPS-2945, 2946 5/1912016 Be-7 1.55,. 0.24 1.90 +/-0.35 1.73 +/-0.21 Pass SPS-2578, 2579 5/24/2016 Pb-214 0.96 ,. 0.12 0.80 +/-0.14 0.88,. 0.09 Pass AP-052516 5/2512016 Gr. Beta 0.022 ,. 0.004 0.022 ,. 0.004 0.022 ,. 0.003 Pass G-2642,2643 5/2612016 Be-7 0.443 ,. 0.178 0.247 ,. 0.247 0.345 ,. 0.152 Pass S0-2663, 2664 5/2612016 Cs-137 0.08,. 0.03 0.07 +/-0.03 0.07,. 0.02 Pass S0-2663, 2664 5/2612016 K-40 12.44,. 0.68 11 .64 +/-0.63 12.04,. 0.46 Pass S0-2663, 2664 5/2612016 Tl-208 0.13,. 0.02 0.14 +/-0.03 0.14,. 0.02 Pass S0-2663, 2664 512612016 Pb-212 0.43,. 0.04 0.41 +/-0.04 0.42,. 0.03 Pass S0-2663, 2664 5/2612016 Ra-226 1.19 ,. 0.34 0.87 +/-0.28 1.03,. 0.22 Pass S0-2663, 2664 5/2612016 Ac-228 0.45,. 0.09 0.53 +/-0.10 0.49,. 0.07 Pass SPS-2817, 2818 5131/2016 K-40 12.10 +/-0.70 11 .05 +/-0.70 11.58,. 0.49 Pass DW-70091 , 70092 6/1/2016 Ra-226 5.61 ,. 0.29 5.53 +/-0.30 5.57,. 0.21 Pass DW-70091, 70092 6/1/2016 Ra-228 1.45,. 0.58 1.91 +/-0.62 1.68,. 0.42 Pass BS-2925,2926 6/312016 K-40 7.74 +/-0.44 7.86 +/-0.42 7.80,. 0.30 Pass SPS-2796, 2797 6/212016 K-40 20.91 ,. 2.38 21 .16 +/-1.82 21.04 +/-1.50 Pass SPS-2882, 2883 6/7/2016 K-40 14.64,. 0.52 14.60 +/-0.52 14.62,. 0.37 Pass SPS-2882, 2883 6/7/2016 Be-7 2.00,. 0.25 1.94 +/-0.20 1.97 +/-0.16 Pass DW-70102, 70103 6/1312016 Ra-226 0.34,. 0.09 0.36 +/-0.08 0.35,. 0.06 Pass AS-2
TABLE A-5. ln-l-iouse "Duplicate" Samples Concentration 8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance DW-70102, 70103 611312016 Ra-228 0.93 +/-0.47 1.11 +/-0.53 1.02 +/-0.35 Pass AP-{)61416 611412016 Gr. Beta 0.026 z 0.004 0.023 z 0.004 0.024 z 0.003 Pass SG-3144, 3145 6117/2016 Be-7 2.23 +/-0.12 2.24 +/-0.12 2.24 +/-0.08 Pass SG-3144, 3145 6117/2016 K-40 7.57 z 0.25 7.09 +/-0.23 7.33 +/-0.17 Pass SPS-3165, 3166 6122/2016 K-40 21.14 +/-2.27 22.88 z 1.60 22.01 z 1.39 Pass SPS-3323, 3324 612412016 K-40 18.67 +/-1.57 21.53 +/-1.65 20.10 z 1.1 4 Pass WW-3231, 3232 612712016 H-3 414 z 104 498 z 108 456 +/-75 Pass AP-3830 ,3831 612912016 Gr. Beta 0.088 z 0.012 0.093 z 0.015 0.091 +/-0.010 Pass AP-{)70516A 7/5/2016 Gr. Beta 0.018 z 0.002 0.014 z 0.002 0.016 z 0.002 Pass AP-{)705168 7/512016 Gr. Beta 0.025 z 0.005 0.026 z 0.005 0.025 z 0.004 Pass XWW~605,3606 7/712016 H-3 3,316 z 186 3,316 z 181 3,316 +/-130 Pass DW-70135,70136 7/8/2016 Gr. Alpha 3.68 z 1.01 2.76 +/-0.98 3.22 +/-0.70 Pass DW-70132,70133 7/812016 Ra-226 1.32 +/-0.14 1.11 +/-0.15 1.22+/-0.10 Pass DW-70132,70133 7/8/2016 Ra-228 3.92 +/-0.94 2.94 +/-0.90 3.43 +/-0.65 Pass AP-{)71216 7/12/2016 Gr. Beta 0.014 z 0.004 0.018 z 0.004 0.016 "'0.003 Pass DW-70150,70151 7/14/2016 Gr. Alpha 5.00 z 1.06 4.43 z 1.04 4.72 z 0.74 Pass SPS-3649,3650 7/1512016 Cs-137 0.12 z 0.03 0.12 z 0.03 0.12 ... 0.02 Pass SPS-3649,3650 7/15/2016 K-40 16.68 z 0.79 16.52 "'0.86 16.6 +/-0.58 Pass SPS-3649,3650 7/1512016 Pb-214 1.20 +/-0.08 1.17 +/-0.08 1.19 +/-0.06 Pass SPS-3649,3650 7/1512016 Ac-228 1.29 +/-0.16 1.28 z 0.16 1.28 +/-0.11 Pass AP-{)71816 7/18/2016 Gr. Beta 0.022 z 0.005 0.024 z 0.005 0.023 z 0.003 Pass DW-70163,70164 7/19/2016 Gr. Alpha 1.08 +/-0.66 1.36 z 0.70 1.22 "'0.48 Pass WW-3761 ,3762 7/20/2016 H-3 347 z 90 466 +/-96 407 +/-66 Pass SPS-4003,4004 7/2312016 K-40 7.15+/-1.59 6.86 z 1.21 7.00 "'1.00 Pass AP-{)72516 7/2512016 Gr. Beta 0.023 z 0.004 0.020 z 0.004 0.022 "'0.003 Pass VE~936,3937 7/25/2016 Sr-90 0.048 +/-0.007 0.058 z 0.010 0.053 "'0.006 Pass VE~936 ,3937 7/2512016 Be-7 0.49 z 0.15 0.51 +/-0.15 0.50+/-0.10 Pass VE-3936,3937 7/25/2016 K-40 4.70 +/-0.35 4.86 +/-0.37 4.78 ... 0.25 Pass VE~959 ,3960 7/27/2016 Sr-90 0.002 z 0.002 0.003 z 0.001 0.003 z 0.001 Pass VE-3959 ,3960 7/2712016 Be-7 0.30 +/-0.14 0.25 +/-0.12 0.27 ... o.09 Pass VE~959,3960 7/27/2016 K-40 4.01 +/-0.37 4.16 +/-0.34 4.08 +/-0.25 Pass DW-70169,70170 7/28/2016 Ra-226 0.83+/-0.11 0.69 +/-0.11 o.76 ... o.o8 Pass DW-70169,70170 7/2812016 Ra-228 1.85 +/-0.63 1.31 +/-0.94 1.58 ... 0.53 Pass AP-{)80116 811/2016 Gr. Beta 0.029 z 0.003 0.033 z 0.003 0.031 z 0.002 Pass SS-4131 ,4132 8/1/2016 K-40 12.47 z 0.71 13.24 +/-0.81 12.86 ... o.54 Pass SS-4131 ,4132 811/2016 Cs-137 0.10 z 0.03 0.13 +/-0.04 0.12 +/-0.02 Pass SPS-4087,4088 81212016 K-40 17.06 "'1.58 19.5 z 1.97 18.28 z 1.26 Pass WW-4976,4977 814/2016 H-3 17,043 +/- 390 16,821 z 388 16,932 +/-275 Pass SPS-4266,4267 8110/2016 K-40 1.06 z 0.47 1.69 +/-0.52 1.375 +/-0.35 Pass AP-{)81616 8116/2016 Gr. Beta 0.029 z 0.005 0.025 z 0.004 0.027 z 0.003 Pass VE-4399,4400 8118/2016 K-40 3.85 +/-0.23 3.27 z 0.41 3.56 +/-0.24 Pass VE-4399 ,4400 8118/2016 Be-7 0.30 +/-0.08 0.45 +/-0.20 0.37 +/-0.11 Pass WW-6394,5395 8118/2016 H-3 947 +/- 122 846 +/-119 896 +/-85 Pass SPS-4441 ,4442 8122/2016 K-40 20.55 +/-2.23 19.69 +/-1.74 20.12 +/-1.41 Pass AP-{)82216 8122/2016 Gr. Beta 0.021 +/- 0.005 0.015 z 0.005 0.018 "'0.003 Pass VE-4462 ,4463 812212016 Be-7 0.91 +/-0.09 0.89 +/-0.11 o.9o ... o.o7 Pass VE-4462 ,4463 812212016 K-40 7.48 +/-0.26 7.60 +/-0.23 7.54 +/-0.17 Pass WW-4594,4595 812812016 H~ 675 z 107 788 +/-111 731 z 77 Pass WW-4663,4664 8126/2016 H~ 607 z 104 501 z 100 554 +/-72 Pass SPS-4529,4530 8126/2016 K-40 21.98 +/-2.52 21.85 +/-1.56 21.92 z 1.48 Pass AP-{)83016A 8130/2016 Gr. Beta 0.030 z 0.003 0.035 z 0.004 o.o33 ... o.oo2 Pass AP-{)830168 8130/2016 Gr. Beta 0.032 z 0.009 0.026 z 0.004 0.029 z 0.005 Pass VE-4615,4616 8131/2016 K-40 2.96 +/-0.16 3.11 +/-0.17 3.03 +/-0.11 Pass AS-3
TABLE A-5. In-House "Duplicate" Samples Concentration
- Averaged Lab Code Date Ana~is First Resu~ Second Resuft Result Acceetance AP-090216 912/2016 Gr. Beta 0.022 :1: 0.004 0.027 :1: 0.004 0.024 :1: 0.003 Pass AP-090616 916/2016 Gr. Beta 0.023 :1:0.005 0.023 :1: 0.005 0.023 :1: 0.003 Pass Ml-4751 ,4752 917/2016 K-40 1,693 +/-112 1,760 :1:99 1,726 +/-75 Pass Ml-4751 ,4752 917/2016 Sr-90 1.23 :1:0.38 1.00 :1:0.33 1.11 :1:0.25 Pass SW-4772,4773 916/2016 H-3 196 :1:91 236 :1:93 216 :1:65 Pass WW-5285,5286 9/1312016 H-3 18,010 :1:400 18,686 :1:407 18,348 :1:286 Pass Ml-4826,4827 9/14/2016 K-40 1,372.6 :1: 105 1,198.1 :1:97 1,285.4 :1:71 Pass VE-4868,4869 9/15/2016 Gr. Beta 2.50 :1:0.06 2.57 :1:0.06 2.53 :1:0.04 Pass VE-4868,4869 9/15/2016 1(-40 2.20 :1:0.17 2.30 :1:0.17 2.25 :1:0.12 Pass CF-4934,4935 9119/2016 K-40 11.47 :1:0.82 11.76 :1:0.50 11 .61 :1:0.48 Pass CF-4934,4935 9/19/2016 Be-7 0.43 :1:0.22 0.46 :1:0.13 0.45 :1:0.13 Pass AP-092016 9120/2016 Gr. Beta 0.021 :t 0.004 0.017 :t 0.004 0.019 :t 0.003 Pass DW-70196,70197 9120/2016 Gr. Alpha 13.8 :1:1 .36 15.28 :1:1 .36 14.54 :1:0.96 Pass F-4955,4956 9120/2016 K-40 3.40 :1:0.44 2.86 :1:0.39 3.13 :1:0.30 Pass VE-5044,5045 9120/2016 Be-7 0.46 :1:0.05 0.50:1:0.11 0.48 :1:0.06 Pass VE-5044,5045 9120/2016 K-40 4.37 :1:0.12 4.68 :1:0.24 4.53 :1:0.13 Pass WW-5219,5220 9120/2016 H-3 63,744 :t 743 64,755 :t 749 64,250 :t527 Pass SPS-5087,5088 912312016 K-40 21 .04 +/-2.32 18.64 :t 1.88 19.94 :t 1.49 Pass AP-092716 9127/2016 Gr. Beta 0.031 :1:0.005 0.032 :t 0.005 0.031 :t 0.003 Pass AP-5660,5661 912812016 Be-7 0.093 :t 0.014 0.086 :t 0.019 0.089 :t 0.012 Pass AP-5681 ,5682 9127/2016 Be-7 0.079 :t 0.019 0.071 :t 0.015 0.075 :t 0.012 Pass VE-511 0,5111 912812016 K-40 1.82 :1:0.15 2.14 :1:0.18 1.98 :1:0.12 Pass AP-5154,5155 9129/2016 Be-7 0.237 :1:0.116 0.195 :t 0.096 0.216 :t 0.075 Pass AP-5702,5703 9/30/2016 Be-7 0.064 :t 0.015 0.070 :t 0.018 0.077 :t 0.012 Pass M~5264,5265 10/4/2016 K-40 1,636 :1:128 1,610 :t 124 1,623 :t89 Pass M~5264 ,5265 10/4/2016 Sr-90 2.00 +/-0.44 1.28 +/-0.37 1.64 +/-0.29 Pass SS-5547,5548 10/11/2016 Gr. Beta 11.27 +/-1.19 9.47 :t 1.20 10.37 :1:0.64 Pass SS-5547,5548 10/11/2016 K-40 8.03 :1:0.45 7.23 :1:0.46 7.63 :1:0.32 Pass SS-5547,5548 10/11/2016 T~208 0.04 :1:0.02 0.04 :1:0.02 0.04 :1:0.01 Pass SS-5547,5548 10/1112016 Bi-214 0.14 :1:0.03 0.12 :1:0.03 0.13 :t 0.02 Pass SS-5547,5548 10/11/2016 Pb-212 0.12 +/-0.02 0.11 :1:0.02 0.11 :1:0.01 Pass SS-5547,5548 10/11/2016 Ac-228 0.10 :1:0.05 0.16 :1:0.05 0.13 :1:0.04 Pass AP-101116 10/11/2016 Gr. Beta 0.032 :t 0.004 0.028 :t 0.004 0.030 :t 0.003 Pass WW-5526.5527 10/1112016 H-3 18,865 :1:408 18,904 :1:408 18,864 :t 289 Pass WW-5639,5640 10/19/2016 H-3 192 :1:103 52 :t98 122 :t71 Pass WW-5723,5724 10/1812016 H-3 36,012 :1:560 36,207 :t561 36,110 :t 396 Pass F-5811 ,5812 10120/2016 K-40 0.91 :1:0.30 0.75 :t 0.22 0.83 :1:0.19 Pass S0-5900,5901 10122/2016 Cs-137 0.05 :1:0.02 0.03 :1:0.02 0.04 :1:0.02 Pass S0-5900,5901 10122/2016 K-40 9.82 :1:0.60 10.77 :1:0.61 10.29 :t 0.43 Pass S0-5900,5901 10122/2016 Tl-208 0.10 :1:0.02 0.14 :1:0.03 0.12:1:0.02 Pass S0-5900,5901 10122/2016 Pb-212 0.32 :1:0.03 0.33 :1:0.03 0.32 :1:0.02 Pass S0-5900,5901 10122/2016 Bi-214 0.20 :1:0.04 0.27 :1:0.04 0.23 :1:0.03 Pass S0-5900,5901 10122/2016 Ac-228 0.41 +/-0.08 0.48 +/-0.09 0.44 +/-0.06 Pass S0-5900,5901 10122/2016 Ra-226 0.45 :1:0.23 0.61 :1:0.27 0.53 :1:0.18 Pass S0-5900 ,5901 10122/2016 Gr. Beta 16.49 :1:1 .01 17.71 +/-1.03 17.10 :1:0.72 Pass SS-5879,5880 10125/2016 K-40 14.94 :1:0.83 15.26 :1:0.64 15.10 :1:0.59 Pass SS-5879,5880 10125/2016 Cs-137 0.06 :1:0.03 0.09 :1:0.04 0.08 :1:0.02 Pass LW~072,6073 10127/2016 Gr. Beta 0.88 :1:0.49 1.53 :1:0.56 1.21 :1:0.37 Pass BS-6009, 6010 10127/2016 Cs-137 0.14 :1:0.08 0.13 :1:0.06 0.13 :1:0.05 Pass BS-6009, 6010 10127/2016 K-40 17.04 :t 1.58 18.30 :t 1.42 17.67 +/- 1.06 Pass F~211 ,6212 1012812016 Gr. Beta 3.25 :1:0.07 3.27 +/-0.07 3.26 :1:0.05 Pass F~211,6212 1012812016 K-40 2.45 :1:0.33 2.49 :1:0.37 2.47 :1:0.25 Pass DW-70230, 70231 1012812016 Ra-226 4.00 +/-0.20 4.10 :1:0.30 4.05 +/-0.18 Pass DW-70230, 70231 1012812016 Ra-228 5.30 :1:0.80 5.20 +/-0.80 5.25 :1:0.57 Pass F~093,6094 10/31/2016 K-40 3.77 :1:0.50 3.51 :1:0.44 3.64 :1:0.33 Pass AS-4
TABLE A.JS. In-House "Duplicate* Samples Concentration a Averaged Lab Code Date Anal~is First Resuh Second Resuh Resuft Acceetance AP-110116 11/1/2016 Gr. Beta 0.021 "'0.004 0.024 "' 0.004 0.023 "'0.003 Pass S-5963, 5964 11/1/2016 K-40 20.35 ,1,2.29 18.59 ,1,1 .90 19.47 ,~o1.49 Pass SG-6119, 6120 11/1/2016 Ac-228 5.70 ,~o0 .44 6.28 "'0.57 5.99 ,~o0 . 36 Pass SG-6119, 6120 11/1/2016 Gr. Alpha 21 .59 ,~o1 . 88 24.35 "'1 .93 22.97 "'1 .35 Pass SG-6119, 6120 11/1/2016 K-40 4.89 ,~o1 . 10 5.90 "'1 .08 5.40 "'0.77 Pass SG-6119, 6120 11/1/2016 Pb-214 3.99 ,~o0 . 21 4.35 "'0.32 4 .17 ,~o0 . 19 Pass S-6051 ' 6052 11/4/2016 K-40 7.05 ,~o0 . 60 7.56 "'0.53 7.31 .t0.40 Pass WW-6297, 6298 11/8/2016 H-3 207 .t98 165 ,~o97 186 .t69 Pass WW-6341 ,6342 11/812016 H-3 1,356 .to 140 1,404 .to 141 1,380 .t99 Pass S0-6406,6407 11/912016 Cs-137 0.36 .t0.04 0.43 .to 0.05 0.40 .t0.03 Pass S0-6406,6407 11/9/2016 K-40 10.90 .t0.68 11 .29 .t0.74 11.09 .t0.50 Pass AP-111416 11/14/2016 Gr. Beta 0.024 .to 0.005 0.021 .to 0.006 0.022 .to 0.004 Pass WW-6829,6830 11/1512016 H-3 39,982 .t589 40,315 "' 591 40,149 .t417 Pass DW-70239, 70240 11/17/2016 Gr. Alpha 7.99 .t1.15 6.41 .to 1.05 7.20 .t0.78 Pass AP-112216 11/22/2016 Gr. Beta 0.049 .to 0.005 0.045 "' 0.005 0.047 "'0.003 Pass S-6473, 6474 11/24/2016 K-40 19.37 "'1 .97 23.80 "'3.54 21 .58 ,.,2.02 Pass SG-6938, 6939 11/28/2016 Ac-228 18.99 ,.,0.59 19.92 .t0.79 19.46 ,.,0.49 Pass SG-6838, 6939 11 /2812016 Pb-214 15.28 ,.,0.34 14.96 ,.,0.43 15.12 "'0.27 Pass AP-120116 12/1/2016 Gr. Beta 0.029 "'0.003 0.030 .to 0.003 0.030 "'0.002 Pass F-6567,6568 12/1/2016 K-40 3.76 +/-0.40 3.83 +/- 0.46 3.80 +/-0.30 Pass S-6522, 6523 12/1/2016 Ac-228 1.08 +/-0.13 1.29 +/-0.16 1.19 ,.,0.10 Pass S-6522, 6523 12/1/2016 Pb-214 1.00 +/-0.08 1.01 ,1,0.09 1.01 ,~o0.08 Pass S-6609, 6610 12/1/2016 K-40 15.57 +/-1 .01 15.99 +/- 0.78 15.78 ,~o0 . 64 Pass S-6718, 6719 12/7/2016 K-40 18.19 +/- 2.13 18.76 +/- 1.80 18.48 +/-1 .39 Pass WW-6784 , 6785 12/7/2016 H-3 922 +/-1 17 905 +/- 116 914 ,~o82 Pass AP-121216 12/12/2016 Gr. Beta 0.026 +/- 0.005 0.028 +/- 0.005 0.027 +/- 0.003 Pass AP-7178,7179 1/312017 Be-7 0.047 ,.,0.015 0.062 "' 0.01 7 0.054 +/- 0.012 Pass Note: Duplicate analyses are performed on every twentieth sample received in-llouse. Results are not listed fur those analyses 'IIIith activ~ies that measure below the LLD. ' Results are reported in units ofpCVL, except fur air filters (pCi/Fifter or pCihn3), food products, vegetation, soil and sediment (pCi/g). AS-S
TABLE A-6. Department of Energy's Mixed Analyte Perfonnance Evaluation Program (MAPEP). Concentration
- Reference Known Control Lab Code b Date Anal~is Laborato~ result Activi~ Limits c Acce~tance MAS0-1053 211!2016 Ni-63 1,206 +/-20 1250 875- 1625 Pass MAS0-1053 211!2016 Sr-90 0.65 +/- 1.27 0.00 NA ' Pass MAS0-1053 211!2016 Tc-99 0.1 +/- 5.5 0.0 NA ' Pass MAS0-1053 211!2016 Cs-134 908 +/-26 1030 721 -1339 Pass MAS0-1053 211!2016 Cs-137 0.10 +/- 6.20 0.00 NA ' Pass MAS0-1053 211!2016 Co-57 1058 +/- 26 992 694 -1290 Pass MAS0-1053 211!2016 Co-60 1229 +/- 28 1190 833 -1547 Pass MAS0-1053 211!2016 Mn-54 1235 +/-43 1160 812 -1508 Pass MAS0-1053 211!2016 Zn-65 753 +/-64 692 484-900 Pass MAS0-1053 211!2016 K-40 753 +/- 140 607 425-789 Pass MAS0-1053 211!2016 Am-241 79 +/-6 103 72 - 134 Pass MAS0-1053 211!2016 Pu-238 73.9 +/-9.2 63.6 44.5-82.7 Pass MAS0-1053 211!2016 Pu-239/240 0.76 +/- 1.34 0.21 NA d Pass MAS0-1053 211!2016 U-234!233 45.0 +/-5.1 45.9 32.1 -59 .7 Pass MAS0-1053 211!2016 U-238 129 +/-9 146 102 -190 Pass MAW-989 211!2016 Am-241 0.018 +/- 0.015 0.00 NA ' Pass MAW-989 211!2016 H-3 0.2 +/-2.8 0.0 NA ' Pass MAW-989 211!2016 Ni-63 12.8 +/-2.7 12.3 8.6-16.0 Pass MAW-989 211!2016 Sr-90 8.70 +/- 1.20 8.74 6.12 -11.36 Pass MAW-989 211!2016 Tc-99 -1 .1 +/-0.6 0.0 NA ' Pass MAW-989 211!2016 Cs-134 15.5 +/-0.3 16.1 11.3 +/-20.9 Pass MAW-989 211!2016 Cs-137 23.7 +/-0.5 21 .2 14.8 - 27.6 Pass MAW-989" 211!2016 Co-57 1.38 +/-0.12 0.00 NA ' Fail MAW-989 211!2016 Co-60 12.5 +/- 0.3 11 .8 8.3- 15.3 Pass MAW-989 211!2016 Mn-54 12.2 +/-0.4 11 .1 7.8- 14.4 Pass MAW-989 211!2016 Zn-65 15.7 +/- 0.7 13.6 9.5- 17.7 Pass MAW-989 211!2016 K-40 288 +/-5 251 176-326 Pass MAW-989 211!2016 Fe-55 17.3 +/-7.0 16.2 11.3-21.1 Pass MAW-989 211!2016 Ra-226 0.710 +/- 0.070 0.718 0.503 - 0.933 Pass MAW-989 211!2016 Pu-238 1.280 +/-0.110 1.244 0.871 +/- 1.617 Pass MAW-989 211!2016 Pu-239/240 0.640 +/- 0.080 0.641 0.449 - 0.833 Pass MAW-989 211!2016 U-234!233 1.39 +/-0.12 1.48 1.04 - 1.92 Pass MAW-989 211!2016 U-238 1.43 +/-0.12 1.53 1.07-1 .99 Pass MAW-893 211!2016 Gross Alpha 0.600 +/- 0.050 0.673 0.202 - 1.144 Pass MAW-893 211!2016 Gross Beta 2.10 +/- 0.06 2.15 1.08 - 3.23 Pass MAW-896 211!2016 1-129 3.67 +/- 0.20 3. 85 2.70-5.01 Pass MAAP-1056 211!2016 Gross Alpha 0.39 +/- 0.05 1.20 0.36-2.04 Pass MAAP-1056 211!2016 Gross Beta 1.03 +/- 0.07 0.79 0.40-1.19 Pass A6-1
TABLEA-6. Deparbnent of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Reference Known Control Lab Code b Date Analysis Laborato~ result Acliv!!l: Limits' Acce~nce MAAP-1057 2/1/2016 Sr-90 1.34 +/-0.15 1.38 0.97 +/- 1.79 Pass MAAP-1057 2/1/2016 Cs-134 -0.01 +/-0.03 0.00 NA' Pass MAAP-1057 2/1/2016 Cs-137 2.57 +/-0.10 2.30 1.61 -2.99 Pass MAAP-1057 2/1/2016 Co-57 3.01 +/-0.06 2.94 2.06-3.82 Pass MAAP-1057 2/1/2016 Co-60 4.28 +/-0.10 4.02 2.81 -5.23 Pass MAAP-1057 2/1/2016 Mn-54 4.90 +/-0.13 4.53 3.17-5.89 Pass MAAP-1057 2/1/2016 Zn-65 4.09 +/-0.18 3.57 2.50-4.64 Pass MAAP-1057 2/112016 Am-241 0.059 +/-0.015 0.0805 0.0564 -0.1047 Pass MAAP-1057 2/1/2016 Pu-238 0.066 +/- 0.020 0.0637 0.0446 - 0.0828 Pass MAAP-1057 2/1/2016 Pu-239/240 0.074 +/-0.020 0.099 NA d Pass MAAP-1057 2/1/2016 U-234/233 0.151 +/- 0.026 0.165 0.116-0.215 Pass MAAP-1057 2/1/2016 U-238 0.160 +/-0.026 0.172 0.120 -0.224 Pass MAVE-1050 2/1/2016 Cs-134 9.83 +/-0.19 10.62 7.43 -13.81 Pass MAVE-1050 2/1/2016 Cs-137 6.06 +/-0.19 5.62 3.93-7.31 Pass MAVE-1050 2/112016 Co-57 13.8 +/-0.2 11.8 8.3 - 15.3 Pass MAVE-1050 2/1/2016 Co-60 0.022 +/- 0.040 0.00 NA' Pass MAVE-1050 2/1/2016 Mn-54 0.009 +/- 0.044 0.000 NA' Pass MAVE-1050 2/1/2016 Zn-65 10.67 +/-0.39 9.60 6.70 - 12.50 Pass MAS0-47801 8/1/2016 Ni-63 648 +/- 14 990 693 - 1287 Fail MAS0-4780g 8/1/2016 Ni-63 902 +/-46 990 693 - 1287 Pass MAS0-4780 8/1/2016 Sr-90 757 +/- 16 894 626 - 1162 Pass MAS0-4780 8/1/2016 Tc-99 559 +/- 12 556 389-723 Pass MAS0-4780 8/1/2016 Cs-134 0.93 +/-2.92 0.00 NA c Pass MAS0-4780 8/112016 Cs-137 1061 +/- 12 1067 747 -1387 Pass MAS0-4780 8/1/2016 Co-57 1178 +/- 8 1190 833- 1547 Pass MAS0-4780 8/1/2016 Co-60 841 +/-9 851 596 -1106 Pass MAS0-4780 8/1/2016 Mn-54 0.69 +/-2.53 q.oo NA' Pass MAS0-4780 8/112016 Zn-65 724 +/- 19 695 487-904 Pass MAS0-4780 8/1/2016 K-40 566 +/-52 588 412-764 Pass MAS0-4780 8/1/2016 Am-241 0.494 +/- 0.698 0.000 NA' Pass MAS0-4780 8/1/2016 Pu-238 69.7+/-7.4 70.4 49.3-91.5 Pass MAS0-4780 8/1/2016 Pu-239/240 53.9 +/-6.3 53.8 37.7 -69.9 Pass MAS0-4780h 8/112016 U-233/234 46.8 +/-3.9 122 85 - 159 Fail MAS0-4780h 8/1/2016 U-238 46.6 +/-3.9 121 85 - 157 Fail MAW-4776 8/1/2016 1-129 4.40 +/-0.20 4.54 3.18-5.90 Pass MAVE-4782 8/1/2016 Cs-134 -0.01 +/-0.05 0.00 NA c Pass MAVE-4782 8/1/2016 Cs-137 6.18 +/-0.20 5.54 3.88 -7.20 Pass MAVE-4782 8/1/2016 Co-57 8.13 +/-0.16 6.81 4.77 -8.85 Pass MAVE-4782 8/1/2016 Co-60 5.30 +/-0.15 4.86 3.40-6.32 Pass MAVE-4782 8/1/2016 Mn-54 8.08 +/-0.24 7.27 5.09-9.45 Pass MAVE-4782 8/1/2016 Zn-65 6.24 +/-0.36 5.40 3.78-7.02 Pass AG-2
TABLE A..Q. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP). Concentration a Reference Known NA' Lab Code' Date Analysis Laboratory result Activity Limits ' Acceptance MAAP-4784 811!2016 Sr-90 1.18 +/-0.10 1.03 0.72- 1.34 Pass MAAP-4784 811!2016 Cs-134 1.58 +/-0.08 2.04 1.43-2.65 Pass MAAP-4784 811!2016 Cs-137 1.85 +/-0.09 1.78 1.25-2.31 Pass MAAP-4784 811!2016 Co-57 2.39 +/-0.52 2.48 1.74-3.22 Pass MAAP-4784 811!2016 Co-60 3.22 +/-0.08 3.26 2.28-4.24 Pass MAAP-4784 811!2016 Mn-54 2.82 +/-0.12 2.75 1.93-3.58 Pass MAAP-4784 811!2016 Zll-65 -0.015 +/- 0.062 0.00 NA ' Pass MAAP-4784 811!2016 Am-241 -0.001 +/- 0.006 0.00 NA ' Pass MAAP-4784 811!2016 Pu-238 0.075 +/- 0.022 0.069 0.049-0.090 Pass MAAP-4784 811!2016 Pu-239!240 0.048 +/- 0.015 0.054 0.038 - 0.070 Pass MAAP-4784 811!2016 U-234/233 0.151 +/-0.036 0.150 0.105- 0.195 Pass MAAP-4784 811!2016 U-238 0.147 +/- 0.034 0.156 0. 109 - 0.203 Pass MAW-4778 811!2016 H-3 365 +/- 11 334 234-434 Pass MAW-4778 811!2016 Fe-55 23.6 +/- 16.3 21 .5 15.1 +/-28.0 Pass MAW-4778 811!2016 Ni-63 17.0 +/- 2.8 17.2 12.0 +/-22.4 Pass MAW-4778 811!2016 Sr-90 0.17 +/-0.28 0.00 NA ' Pass MAW-4778 811!2016 Tc-99 9.50 +/-0.41 11 .60 8.10-15.10 Pass MAW-4778 811!2016 Cs-134 22.6 +/- 0.4 23.9 16.7-31.1 Pass MAW-4778 811!2016 Cs-137 0.018 +/-0.117 0.00 NA' Pass MAW-4778 811!2016 Co-57 27.6 +/-0.2 27.3 19.1 +/-35.5 Pass MAW-4778 811!2016 Co-60 0.018 +/- 0.090 0.00 NA ' Pass MAW-4778 811!2016 Mn-54 16.2 +/- 0.4 14.8 10.4- 19.2 Pass MAW-4778 811!2016 Zll-65 19.3 +/-0.7 17.4 12.2-22.6 Pass MAW-4778 811!2016 K-40 286 +/-6 252 176-328 Pass MAW-4778 811!2016 Ra-226 1.48 +/-0.09 1.33 0.93- 1.73 Pass MAW-4778 811!2016 Pu-238 1.09 +/-0.13 1.13 0.79- 1.47 Pass MAW-4778 811!2016 Pu-239!240 0.003 +/- 0.011 0.016 NA ' Pass MAW-4778 811!2016 U-234/233 1.80 +/-0.13 1.86 1.30-2.42 Pass MAW-4778 811!2016 U-238 1.77 +/-0.13 1.92 1.34-2.50 Pass MAW-4778 811!2016 Am-241 0.678 +/- 0.086 0.814 0.570 +/- 1.058 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/tctal sample (filters, ~~egetation). ' Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (~~egetation) . ' MAPEP resuHs 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 net pr!Mde control limits. ' Pr!Mded in the series for "sensitivity evaluation". MAPEP does not provide control limits. ' The laboratory property identified the 51)-75 interfering peak in the vicinity of Co-57 and stated so in the comment field. MAPEP requires resuHs to be reported as an activity with an uncertainty. Since the calculated uncertainty was less than the activity MAPEP interpreted the submitted result as a "false positive" resulting in a failure. ' Original analysis for Ni-63 failed. 9 Reanalysis with a smaller aliquot resuHed in acceptable results. An investigation is in process to identify better techniques for analyzing samples v.ith complex matrices.
"MAPEP states that samples contain two fractions of Uranium; one that is soluble in concentrated HN0 3 and HCI acid and one that is "fundamentally insoluble in these acids". They also state that HF treatment can not assure complete dissolution.
Results are consistent v.ilh measuring the soluble form. AG-3
TABLEA-7. Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)". MRAD stud Concentration
- Lab Code b Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERAP-1101 3/14/2016 Am-241 37.3 45.9 28.3 -62.1 Pass ERAP-1101 3/14/2016 Co-60 637 623 482 -778 Pass ERAP-1101 3/14/2016 Cs-134 251 304 193-377 Pass ERAP-1101 3/14/2016 Cs-137 1,273 1,150 864-1,510 Pass ERAP- 1101 3/14/2016 Fe-55 < 162 126 39.1 -246 Pass ERAP-1101 3/14/2016 Mn-54 < 2.64 < 50.0 0.00 - 50.0 Pass ERAP-1101 3/14/2016 Pu-238 68.0 70.5 48.3-92.7 Pass ERAP-1101 3/14/2016 Pu-239/240 54.1 54.8 39.70 -71 .60 Pass ERAP-1101 3/14/2016 Sr-90 139 150 73.3-225.0 Pass ERAP-1101 3/14/2016 U-233/234 59.3 64.8 40.2-97.7 Pass ERAP-1101 3/14/2016 U-238 55.5 64.2 41.5 -88.8 Pass ERAP-1101 3/14/2016 Zn-65 428 356 255-492 Pass ERAP-1101 3/14/2016 Gr. Alpha 98.0 70.1 23.5 -109 Pass ERAP-1101 3/14/2016 Gr. Beta 78.6 54.4 34.4 -79.3 Pass ERS0-1105 3/14/2016 Am-241 1,030 1,360 796 -1,770 Pass ERS0-1105 3/14/2016 Ac-228 1,540 1,240 795 -1 ,720 Pass ERS0-1105 3/14/2016 Bi-212 1,550 1,240 330 - 1,820 Pass ERS0-1105 3/14/2016 Bi-214 3,100 3,530 2,130 -5,080 Pass ERS0-1105 3/14/2016 Co-60 5,600 5,490 3,710 -7,560 Pass ERS0-1105 3/14/2016 Cs-134 3,030 3,450 2,260 -4,140 Pass ERS0-1105 3/14/2016 Cs-137 4,440 4,310 3,300 - 5,550 Pass ERS0-1105 3/14/2016 K-40 10,300 10,600 7,740 - 14,200 Pass ERS0-1105 3/14/2016 Mn-54 < 50.8 < 1000 0.0 -1,000 Pass ERS0-1105 3/14/2016 Pb-212 1,140 1,240 812 -1 ,730 Pass ERS0-1105 3/14/2016 Pb-214 3,190 3,710 2,170 - 5,530 Pass ERS0-1105 3/14/2016 Pu-238 680 658 396-908 Pass ERS0-1105 3/14/2016 Pu-239/240 460 496 324-0,685 Pass ERS0-1105 3/14/2016 Sr-90 7,740 8,560 3,260 - 13,500 Pass ERS0-1105 3/14/2016 Th-234 3,630 3,430 1,080 -6,450 Pass ERS0-1105 3/14/2016 U-233/234 3,090 3,460 2,110 - 4,430 Pass ERS0-1105 3/14/2016 U-238 3,280 3,430 2,120-4,350 Pass ERS0-1105 3/14/2016 Zn-65 2,940 2,450 1,950 - 3,260 Pass ERW-1115 3/14/2016 Gr. Alpha 105.0 117.0 41.5 - 181 .0 Pass ERW-1115 3/14/2016 Gr. Beta 76.2 75.5 43.2 - 112.0 Pass ERW-1117 3/14/2016 H-3 8,870 8,650 5,800 - 12,300 Pass A7-1
TABLE A-7. Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)". MRAD Stud Concentration a Lab Code b Date Analysis laboratory ERA Control Result Result limits Acceetance ERVE-1108 3/14/2016 Am-241 1,930 2,120 1,300 - 2,820 Pass ERVE-1108 3/1412016 Cm-244 1,294 1,560 764 - 2,430 Pass ERVE-1108 3/14/2016 Co-60 1,164 1,100 759- 1,540 Pass ERVE-1108 3/14/2016 Cs-134 1,056 1,070 687- 1,390 Pass ERVE-1108 3/14/2016 Cs-137 930 838 608- 1,170 Pass ERVE-1108 3/14/2016 K-40 32,200 31,000 22,400 - 43,500 Pass ERVE-1108 3/14/2016 Mn-54 < 24.5 < 300 0.00- 300 Pass ERVE-1108 3/14/2016 Zn-65 3,320 2,820 2,030 - 3,960 Pass ERVE-1108 3/14/2016 Pu-238 3,410 2,810 1,680 - 3,850 Pass ERVE-1108 3/14/2016 Pu-239/240 4,120 3,640 2,230 - 5,010 Pass ERVE-1108 3/14/2016 Sr-90 8,120 8,710 4,960 - 11,500 Pass ERVE-1108 3/14/2016 U-2331234 4,350 4,160 2,740- 5,340 Pass ERVE-1108 3/14/2016 U-238 4,220 4,120 2,750 - 5,230 Pass ERW-1111 3/14/2016 Am-241 113 121 81.5- 162 Pass ERW-1111 3/14/2016 Co-60 1,120 1,050 912- 1,230 Pass ERW-1111 3/14/2016 Cs-134 806 842 618-968 Pass ERW-1111 3/1412016 Cs-137 1,190 1,100 934- 1,320 Pass ERW-1111 3/14/2016 Mn-54 < 5.89 < 100 0.00- 100 Pass ERW-1111 3/14/2016 Pu-238 159 138 102- 172 Pass ERW-1111 3/14/2016 Pu-239/240 113 98.7 76.6 - 124 Pass ERW-1111 3/14/2016 U-2331234 46.9 52.7 39.6-68.0 Pass ERW-1111 3/14/2016 U-238 50.4 52.3 39.9 - 64.2 Pass ERW-1111 3/1412016 Zn-65 1,160 1,010 842- 1,270 Pass ERW-1111 3/14/2016 Fe-55 1,600 1,650 984-2,240 Pass ERW-1111 3/14/2016 Sr-90 430 434 283-574 Pass
- Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted pre'Jiously by the En'Jironmental Measurements Laboratory Qual tty Assessment Program (EML).
0 Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pOll, except for air filters (pCi/Filter), vegetation and soil (pOikg). c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA A7-2
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 Reported result: x +/- s; where x = (1/2) (x1 + x2) and s = (1/2) ~ 3.2. Individual results: Reported result: <L, where L =lower of L1 and L2 3.3. Individual results: X+/- s, <L Reported result: X +/- s if X ~ L; <L otherwise. 4.0. Computation of Averages and Standard Deviations B-2
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 =r; LX s= 4.2 Values below the highest lower limit of detection are not included in the average. 4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported. 4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported. 4.5 In rounding off, the following rules are followed: 4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44. 4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to 11.45. 4.6 Composite samples which overlap the next month or year are reported for the month or year in which most of the sample is collected. B-3
APPENDIX C TECHNICAL SPECIFICATION 2.1.3 REACTOR COOLANT DOSE EQUIVALENT IODINE ABOVE TECHNICAL SPECIFICATION LIMIT C-1
During the 2016 reporting period, radioactivity of primary coolant did not exceed the limits of Technical Specification 2.1.3. C-2
APPENDIX D SAMPLE LOCATION MAPS D-1
N I D-2
Radiological Environmental Sampling Locations and Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine Onsite Station, 11 0-meter weather 1 tower 0.53 293"fWNW p X Onsite Station, adjacent 2C.E to old plant access road 0.59 207"/SSW K X 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 X SA 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 D-3
Radiological Environmental Sampling Locations and Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine Onsite Station, entrance to Plant Site 8 from Hwy. 75 0.55 191 *ts 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 Metropolitan Utilities Dist., Florence Treatment Plant 12 North Omaha, NE 14.3 154./SSE H X West bank Missouri River, downstream from 13 Plant discharge 0.45 108./ESE F X X Upstream from Intake 14° Bldg, west bank of river 0.09 4*/N A X X D-4
Radiological Environmental Sampling Locations and Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 15 Smith Farm 1.99 134"/SE G X 16A 17A 18A 19A 20° Mohr Dairy 9.86 186"/S J B X X 21A Fish Sampling Area, 0.08 Missouri River 22 (R.M. 645.0) 6"/N A X Fish Sampling Area, 17.9 Missouri River 23° (R.M. 666.0) 358"/N A X 24A 25A D-5
Radiological Environmental Sampling Locations and Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 26A 27A 28A 29A 30A 31A 32° Valley Substation #902 19.6 221./SW L X 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 D-6
Radiological Environmental Sampling Locations and Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine Offsite Station Desoto 37 Township 1.57 144./SE G X X X 38A 39A 40A 41c Dowler Acreage 0.73 175°/S J X X X B,C 42 Sector A-1 1.94 o*tNORTH 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 48 Sector G-1 1.99 134./SE G X D-7
Radiological Environmental Sampling Locations and Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 49 Sector H-1 1.04 159./SSE H X 50 Sector J-1 0.71 179./SOUTH J X 51 Sector K-1 0.61 205./SSW K X 52 Sector L-1 0.74 229"/SW L X 53 Sector M-1 0.93 248./WSW M X 54 Sector N-1 1.31 266./WEST N X 55 Sector P-1 0.60 291 "/WNW p X 56 Sector Q-1 0.67 307"/NW Q X 57 Sector R-1 2.32 328./NNW R X 58 Sector A-2 4.54 350./NORTH A X 59 Sector B-2 2.95 26"/NNE B X 60 Sector C-2 3.32 5o*tNE c X D-8
Radiological Environmental Sampling Locations and Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 61 Sector D-2 3.11 75°/ENE D X 62 Sector E-2 2.51 90°/EAST E X 63 Sector F-2 2.91 110°/ESE F X 64 Sector G-2 3.00 140°/SE G X 65 Sector H-2 2.58 154°/SSE H X 66 Sector J-2 3.53 181./SOUTH J X 67 Sector K-2 2.52 205°/SSW K X 68 Sector L-2 2.77 214°/SW L X 69 Sector M-2 2.86 243°/WSW M X D-9
Radiological Environmental Sampling Locations and Media Approximate Air Monitoring Approximate Distance Sample Direction 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 Airborne north) (miles) Particulate Iodine 70 Sector N-2 2.54 263°/WEST N X 71 Sector P-2 2.99 299°/WNW p X 72 Sector Q-2 3.37 311°/NW Q X 73 Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X 75c Lomp Acreage 0.65 163°/SSE H X X X B,C X X 76 Stangl Farm 3.40 169°/S J X 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 plant, 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 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. D-10}}