PNP 2016-024, Transmittal of 2015 Annual Radioactive Effluent Release and Waste Disposal Report
| ML16120A339 | |
| Person / Time | |
|---|---|
| Site: | Palisades, Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/25/2016 |
| From: | Hardy J Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| PNP 2016-024 | |
| Download: ML16120A339 (266) | |
Text
{{#Wiki_filter:Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043 Tel 269 764 2000 Jeffery A. Hardy Regulatory Assurance Manager PNP 2016-024 April 25, 2016 10 CFR 50.36a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
2015 Annual Radioactive Effluent Release and Waste Disposal Report Palisades Nuclear Plant Big Rock Point Docket 50-255 Dockets 50-155 and 72-043 License No. DPR-20 License No. DPR-6
Dear Sir or Madam:
Attached are the Entergy Nuclear Operations, Inc. 2015 Annual Radioactive Effluent Release and Waste Disposal Reports for Palisades Nuclear Plant (PNP) and Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). These reports are submitted in accordance with 10 CFR 50.36a(a)(2). contains the report for PNP. Attachment 2 contains the report for the BRP ISFSI. These reports provide a summary of the quantities of radioactive liquid and gaseous effluent releases and solid radioactive waste processed during the period of January 1, 2015, through December 31, 2015.
PNP 2016-024 Document Control Desk Page2 This letter contains no new commitments and no revision to existing commitments. Sincerely, JAH/bed : Palisades Nuclear Plant 2015 Radioactive Effluent Release Report : Big Rock Point Independent Spent Fuel Storage Installation 2015 Radioactive Effluent Release Report CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC (w/o Attachments) Resident Inspector, Palisades, USNRC (w/o Attachmens) NRC NMSS Project Manager, USNRC (w/o Attachments) American Nuclear Insurers (ANI)
ATTACHMENT 1 Palisades Nuclear Plant 2015 Radioactive Effluent Release Report 2015 Plant Operating History Palisades Nuclear Plant (PNP) entered the reporting period online on January 1, 2015, at essentially 100% full power. PNP experienced an unexpected scram on September 16, 2015, because of a digital electrohydraulic control system malfunction on the turbine. Refueling outage 1R24 commenced shortly thereafter on September 18, 2015. The unit attained criticality on October 19, 2015, and returned to full power on October 22, 2015. The unit generated 6,318,519 MWHrs of net electrical energy during 2015. A. Gaseous Effluents Tables 1A, "Gaseous Effluents - Summation of All Releases," 1B, "Gaseous Effluents - Ground-Level Release - Batch Mode," and 1C, "Gaseous Effluents - Ground-Level Release - Continuous Mode," list and summarize gaseous effluents released during this reporting period. B. Liquid Effluents Tables 2A, "Liquid Effluents - Summation of All Releases," 2B, "Liquid Effluents - Batch Mode," and 2C, "Liquid Effluents - Continuous Mode," list and summarize liquid effluents released during this reporting period. C. Solid Waste Storage and Shipments Table 3, "Low-Level Waste for Waste Classification A, Band C, summarizes solid radioactive waste shipped for processing or burial in 2015 for the following waste streams: resins, filters and evaporator bottoms, dry active waste, irradiated components and other waste. D. Dose Assessments Tables 4, "Dose Assessments, 10 CFR Part 50, Appendix I," and 5, "EPA 40 CFR Part 190, Individual in the Unrestricted Area," lists annual dose to the members of the public. E. Supplemental Information
- 1. Regulatory Limits
- a. Noble Gases The air dose in unrestricted areas due to noble gas released in gaseous effluents shall be limited to the following:
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*During the calendar quarter, to s 5 mrad for gamma radiation ands 10 mrad for beta radiation.
- During the calendar year, to s 10 mrad gamma radiation and s 20 mrad for beta radiation.
- b. Iodines - Particulates The dose to a member of the public from radioiodines, radioactive material in particulate form with half-lives greater than eight days, and radionuclides other than noble gas, e.g., tritium, in gaseous effluents released to unrestricted areas shall be limited to the following:
*During any calendar quarter, to s 7.5 mrem to any organ
- During any calendar year, to s 15 mrem to any organ
- c. Liquid Effluents The dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas shall be limited to the following:
- During any calendar quarter to s 1.5 mrem to the total body and s 5 mrem to any organ.
- During any calendar quarter to s 3 mrem to the total body and s .1 O mrem to any organ.
- d. Total Dose The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to s 25 mrem to the total body <?r any organ (except the thyroid, which is limited to s 75 mrem) over a period of 12 consecutive months.
- 2. Maximum Permissible Concentrations (Effluent Concentration Limits)
- a. Gaseous Effluents The dose rate due to radioactive material released in gaseous effluents from the site shall be limited to the following:
- For noble gases: s 500 mrem/yr to the total body and s 3000 mrem/yr to the skin
- For all radioiodines and for all radioactive materials in particulate form with half-lives greater than eight days and for radionuclides other than noble gases: s 1500 mrem/yr to any organ.
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The above limits are provided to ensure that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits of 10 CFR 20, Appendix B, Table 2, Column 1.
- b. Liquid Effluents The concentration of radioactive material. released at any time from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 µCi/ml total activity.
- 3. Average Energy The average energy ( E) of the radionuclide mixture in releases of fission and activation gases as defined in Regulatory Guide 1.21, Appendix B, Section A.3 is not applicable because the limits used for gaseous releases are based on calculated dose to members of the public.
- 4. Measurements and Approximations of Total Radioactivity PNP uses 0.25 KeV per channel with a range of 0-2000 KeV.
- a. Fission and activation gases are sampled and then analyzed on an 8192 channel analyzer with a high purity germanium (HpGe) detector.
- b. Iodines are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector.
- c. Particulates are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector.
- d. Liquid effluents are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector. Tritium analysis is performed using liquid scintillation.
Fe-55, Ni-63, Sr-89, and Sr-90 analyses are performed by an offsite vendor. Page 3 of 10
- 5. Batch Releases - 2015 For PNP, these totals are not directly proportional to actual release volumes due to PNP having two sets of tanks with different volumes in both the gaseous and liquid release systems that are utilized for batch releases. The number of batches performed in this section will fluctuate from year to year due to the utilization of the smaller and larger tanks in different frequencies. This information is better quantified in the tables contained later in this report. Reporting average stream flow during periods of release of effluent into a flowing stream is not required as PNP's releases are made into Lake Michigan, and not a flowing stream of water.
- a. Liquid Number of batch releases for each quarter: 1 in the 1st quarter 1 in the 2nd quarter 5 in the 3rd quarter 4 in the 4th quarter Total time period for batch releases: 10598 minutes Maximum time period for a batch release: 2580 minutes Average time period for a batch release: 963 minutes Minimum time period for a batch release: 434 minutes
- b. Gaseous Number of batch releases for each quarter: 2 in the 1st quarter
\
0 in the 2nd quarter 2 in the 3rd quarter 5 in the 4th quarter Total time period for batch releases: 2897 minutes Maximum time period for a batch release: 930 minutes Average time period for a batch release: 322 minutes _ Minimum time period for a batch release: 78 minutes Page 4 of 10
- 6. Abnormal Discharges
- a. Liquid Number of releases for each quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1 0 0 0 Total activity released in Curies (Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0.0387 0 0 0 On February 26, 2015, as a result of routine monitoring well sampling, PNP identified tritium in temporary wells 7 and 8, located within the plant protected area. PNP completed notifications, in accordance with NEI 07-07 Criterion 2.2.b, on March 19, 2015. Tritium concentrations were less than the threshold value (20,000 pci/L) for initiating voluntary communications in accordance with NEI Ground Water Protection Initiative. The station promptly isolated the pipe that runs from the turbine sump oil/water separator to the turbine building drain tank as the likely source. Subsequent sample concentrations from samples obtained on March 18, 2015, resulted in concentrations of tritium less than the minimum detectable activity, thus confirming the source.
The pipe that runs from the turbine sump oil/water separator to the turbine building drain tank is a monitored effluent pathway that discharges waste to Lake Michigan. All activity and volume along this pathway is accounted for by routine effluent calculations, as shown in Table 2C. However, the activity released to the ground through this path is considered abnormal due to the fact that the release did not occur at the designed discharge location. The fraction of release from the pipe is unknown, so it was conservatively assumed that 100% of the liquid discharge traveling through the pipe went to the ground. The most conservative range of time during which this could have occurred was calculated to be between October 2, 2014, and March 7, 2015, based upon groundwater well measurements and groundwater flowrates. Therefore, it is conservatively estimated that 0.0387 Ci of tritium in 1st Quarter 2015, and 0.0533 Ci in 4th Quarter 2014 was released to the ground from this pipe. Voluntary notifications were made to the Michigan Department of Environmental Quality, VanBuren County Administrator, Covert, Geneva, and South Haven Township Supervisors, as well as the City of South Haven Mayor and City Manager. The NRC Resident Inspectors were notified, and reporting was completed in accordance with 10 CFR 50.72(b)(2)(xi). Page 5 of 10
- b. Gaseous None.
- 7. Controlled Discharge
- a. Liquid None.
- b. Gaseous Number of releases for each quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 1 8 -----'-'15"------
Total activity released in Curies (Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 0.00000626 1.42 0.0165
- 8. Radioactive Waste Treatment System Changes None.
- 9. Annual Land Use Census Changes The garden critical receptor is unchanged and remains located in the SSE sector at 0.69 miles. The residence critical receptor is unchanged and remains in the SSW sector at 0.49 miles. The goat critical receptor is unchanged and remains in the NE sector at 2.45 miles and are fed stored feed. Beef cattle remain located in the SE sector at 4.27 miles. There are no dairy cows located within five miles of the plant.
- 10. Effluent Monitoring System lnoperability One effluent monitor was out of service for greater than 30 days during the reporting period.
RIA-2320, steam generator blowdown tank vent monitor, was declared inoperable on November 3, 2015, due to the failure of a monthly monitor functional check. Compensatory actions were taken in accordance with the ODCM Table A-1. The monitor was declared operable on December 8, 2015. The extended delay was a result of having to send the spare detector to the vendor upon failing to make the spare detector operable. Page 6 of 10
- 11. Offsite Dose Calculation Manual (ODCM) Changes The Offsite Dose Calculation Manual (ODCM), ODCM Appendix A, and ODCM Appendix B were not revised in 2015. The General Manager Plant Operations approval is required for changes to the ODCM.
The ODCM, ODCM Appendix A and ODCM Appendix B are being revised in 2016. Revision will include the updated meteorological data and turbine sump totalizer surveillance frequency. A copy of the ODCM, ODCM Appendix A, and ODCM Appendix B are attached in Enclosure 1.
- 12. Process Control Program Changes None.
- 13. Errata/Corrections to Previous Reports On page 18 of 108 of the 2014 Annual Radioactive Effluent Release and Waste Disposal Report the volume of type 'a' waste, spent resin, filters, evaporator 3
bottoms, etc., was reported as 1.38 m3 but should have been reported as 1.83 m . This means the value reported was less conservative than the actual value by 25%. This is considered a large error under the guidance of regulatory guide 1.21. A special submittal was not made to the NRC upon discovery of this error because the error was discovered within 90 days of the submittal of this report which is within guidance of Regulatory guide 1.21. The total curries shipped for this category was reported correctly. Page 7 of 10
- 14. Other Groundwater Monitoring PNP has 21 ground water monitoring wells (MW) strategically placed within the owner controlled area to allow for detection of radioactive contamination of ground water due to leaks or spills from plant systems. Four of these MW were installed in December, 2014 for monitoring starting in 2015. PNP added 18 temporary wells (TW) in 2009 to determine the potential source of tritium in groundwater in the vicinity of MW-3. Of the 18 TW installed, 16 are still functional. Tanks T-90, primary makeup tank, T-91, utility water storage tank, and associated underground piping between these tanks and the auxiliary building addition are located in this area.
TW-15 is most indicative of an historic leak that continues to be monitored. 2015 tritium levels in TW-15 peaked in January at 31,846 pCi/L. Tritium levels spike in TW-15 when the water table rises from a large rainfall or spring melt. The high tritium levels in this area are a result of a leak which was reported to the NRC on December 10, 2007. None of the wells between TW-15 and Lake Michigan have had reportable concentrations of tritium in this reporting period. Monitoring of the groundwater tritium plume continues to assess repair effectiveness and follow the site hydrology data. Well. locations are depicted in Figure t. Depth to Local Water Table - The depth range for 2015 was approximately 7 to 8.5 feet. Classification of Subsurface Aquifers - Not used for drinking water. Expected Movement/Mobility of Groundwater Plume - Westerly direction down-gradient toward Lake Michigan at approximately 2.2 feet per day. Land Use Characteristics - PNP site property, water not used for drinking or irrigation. Page 8 of 10
Carbon-14 In 2010, PNP and other facilities participated in an EPRI task force to build a model to accurately estimate gaseous C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc). This work was completed in November 2010. The estimates for C-14 were constructed using the aforementioned EPRI methodology contained within EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents. Using the C-14 curie estimates, the annual dose to man was derived from guidance contained within Regulatory Guide 1.109. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required. Gaseous C-14 is reported as C02 Curies because the major pathway by which C-14 contributes to the dose to man is by entering vegetables in the form of C02 and then being ingested. Annual C-14 release for PNP and subsequent doses for 2015: Total Gaseous C-14 Released Curies= 7.74 Gaseous C-14 as C02 Curies = 2.32 Effective Child TB Dose, C-14 mrem = 0.0703 Effective Child Bone Dose, C-14 mrem = 0.352 The quarterly curies released are provided in Table 1A, Table 1B, arid Table 1C. Airborne doses due to C-14 are contained in Table 1A. Meteorological Data A meteorological monitoring report is generated semiannually. From January 1, 2015, to June 30, 2015, the meteorological data recovery was at 96% or greater for all variables. The two most frequently occurring directions at the 10-meter level were in the SSE and WNW sectors, accounting for over 22% of the observations from January through June. The two most frequently occurring directions at 60 meters were WNW*and S, accounting for over 19% of the observations from January through June. The highest average speeds were associated with NNW winds at both the 10-meter and 60-meter levels. The mean speed for all directions at 10 meters was 3.63 mis (8.12 mph), and at 60 meters was 6.42 mis (14.36 mph). Compared to the same period in the previous year, the 10-meter speed was 0.23 mis (0.51 mph) lower while the 60-meter speed was 0.50 mis (1.12 mph) lower. Page 9 of 10
From July 1, 2015, to December 31, 2015, the meteorological data recovery was at 99% or greater for all variables. The two most frequently occurring directions at the 10-meter level were SE and SSE, which accounted for over 24% of all observations from July to December. At 60 meters, the two predominant directions were SW and NNW, which accounted for over 20% of all observations from July to December. The highest average speeds were associated with SE winds at 10 meters and SW winds at 60 meters. The mean speed for all directions at 10 meters was 2.26 mis (5.06 mph), and at 60 meters was 4.91 mis (10.98mph). Compared to the same period in the previous year, the 10-meter speed is 0.02 mis (0.04 mph) higher while the 60-meter speed is 0.19 mis (0.43 mph) higher. Data from this report and the annual meteorological data (Hourly Average Data or Joint Frequency Distribution) will be maintained on site and will be made available upon NRC request. Page 10 of 10
ATTACHMENT 1 Palisades - Table 1A 2015 Gaseous Effluents - Sum of All Releases Summation of Uncertainty All Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (%) Fission and Activation Gases Ci 2.79E+OO 1.86E+OO 2.99E+OO 3.16E+OO 1.08E+01 24.03 Average Release Rate Ci/s 3.59E-01 2.36E-01 3.76E-01 3.98E-01 3.43E-01 % of Limit 3.66E-03 2.67E-03 4.69E-03 3.28E-03 3.58E-03 1-131 4.27E-05 3.50E-05 5.64E-05 9.45E-05 2.29E-04 Average Release Rate Ci/s 5.49E-06 4.45E-06 7.10E-06 1.19E-05 7.25E-06 % of Limit % 6.29E-08 5.09E-08 8.13E-08 1.36E-07 a. 30E-08 Particulates Ci O.OOE+OO 1.88E-05 1.89E-05 1.82E-04 2.20E-04 Average Release Rate Ci/s O.OOE+OO 2.40E-06 2.38E.:06 2.29E-05 6.96E-06 % of Limit % O.OOE+OO 1.10E-05 1.0BE-05 9.66E-06 7.90E-06 Tritium Ci 1.93E+OO 1.71 E+OO 2.88E+OO 4.37E+OO 1.09E+01 Average Release Rate Ci/s 2.48E-01 2.1 BE-01 3.62E-01 5.SOE-01 3.45E-01 % of Limit % 5.68E-04 4.99E-04 8.30E-04 1,26E-03 7.91 E-04 Gross Alpha Ci ND ND ND ND ND C-14 Ci 2.13E+OO 2.15E+OO 1.78E+OO 1.71 E+OO 7.74E+OO Average Release Rate Ci/s 2.73E-01 2.73E-01 2.24E-01 2.15E-01 2.45E-01 % of Limit % 2.09E-06 2.0BE-06 1.71 E-06 1.64E-06 1.87E-06 Page 1 of 1
ATTACHMENT 1 Palisades - Table 1 B 2015 Gaseous Effluents - Ground Level Release, Batch Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Ar-41 Ci ND ND ND ND ND Kr-85 Ci ND ND 2.70E-04 2.35E-04 5.05E-04 Kr-85m Ci ND ND ND 2.30E-03 2.30E-03 Kr-87 Ci ND ND ND ND ND Kr-88 Ci ND ND ND ND ND Xe-131m Ci ND ND ND 2.40E-03 2.40E-03 Xe-133 Ci ND ND 8.40E-04 1.03E+OO 1.03E+OO Xe-133m Ci ND ND ND 2.13E-02 2.13E-02 Xe-135 Ci ND ND 2.36E-05 5.48E-02 5.48E-02 Xe-135m Ci ND ND ND ND ND Xe-137 Ci ND ND ND ND ND Xe-138 Ci ND ND ND ND ND (List Others) Ci ND ND ND ND ND Total Ci ND ND 1.13E-03 1.11 E+OO 1.11 E+OO Iodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1-131 Ci ND ND ND 7.99E-05 7.99E-05 1-132 Ci ND ND ND ND ND 1-133 Ci ND ND ND ND ND 1-134 Ci ND ND ND ND ND 1-135 Ci ND ND ND ND ND Total Ci ND ND ND 7.99E-05 7.99E-05 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Co-58 Ci ND 3.53E-08 1.02E-07 9.99E-06 1.01 E-05 Co-60 Ci ND 1.88E-05 1.88E-05 1.60E-05 5.36E-05 Cr-51 Ci ND ND ND 4.25E-07 4.25E-07 Mn-54 Ci ND ND ND ND ND Mn-56 Ci ND ND ND ND ND Rb-88 Ci ND ND ND 1.47E"04 1.47E-04 Sr-89 Ci NR NR NR NR NR Sr-90 Ci NR NR NR NR NR Sr-92 Ci ND ND ND ND ND Nb-95 Ci ND ND ND 2.63E-06 2.63E-06 Zr-95 Ci ND ND ND 1.4BE-07 1.48E-07 Nb-97 Ci ND ND ND 5.43E-06 5.43E-06 Ag,1 iom Ci ND ND ND 1.47E-07 1.47E-07 Sb-125 Ci ND ND ND ND ND Cs"137 Ci ND ND ND 9.82E-08 9.82E-08 Ce-144 Ci ND ND ND ND ND Total Ci ND 1.88E-05 1.89E-05 1.82E-04 2.20E-04 Page 1 of 2
ATTACHMENT 1 Palisades - Table 1 B 2015 Gaseous Effluents - Ground Level Release, Batch Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium Ci ND ND ND 3.83E-01 3.83E-01 Gross Alpha Ci NR NR NR NR NR C-14 Ci NA NA NA NA ND ND = Measurements performed but no activity detected. NA = Not applicable NR = Analysis not required & not performed Page 2of2
ATTACHMENT 1 Palisades - Table 1C 2015 Gaseous Effluents - Ground Level Release, Continuous Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Ar-41 Ci 3.62E-01 3.01 E-01 9.40E-01 6.04E-01 2.21E+OO Kr-85 Ci ND ND ND ND ND Kr-85m Ci 7.00E-02 3.51 E-02 4.79E-02 9.47E-03 1.62E-01 Kr-87 Ci 1.60E~01 8.11 E-02 9.45E-02 8.74E-02 4.23E-01 Kr-88 Ci 1.16E-01 7.22E-02 3.71 E-02 3.08E-02 2.56E-01 Xe-131m Ci ND ND ND ND ND Xe-133 Ci 2.46E-01 1.48E-01 3.82E-01 1.11 E-01 8.88E-01 Xe-133m Ci ND ND ND ND ND Xe-135 Ci 7.04E-01 3.25E-01 4.38E-01 5.02E-01 1.97E+OO Xe-135m Ci 3.48E-02 1.62E-02 1.99E-03 ND 5.30E-02 Xe-137 Ci 2.33E-01 3.54E-01 4.41 E-01 1.52E-01 1.18E+OO Xe-138 Ci 8.66E-01 5.26E-01 6.07E-01 5.55E-01 2.55E+OO Total Ci 2.79E+OO 1.86E+OO 2.99E+OO 2.05E+OO 9.69E+OO Iodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1-131 Ci 4.27E-05 3.50E-05 5.64E-05 1.46E-05 1.49E-04 1-132 Ci ND ND ND ND ND 1-133 Ci 8.15E"05 1.03E-04 5.76E-05 ND 2.42E-04 1-134 Ci ND ND ND ND ND 1-135 Ci ND ND ND ND ND Total Ci 1.24E~04 1.38E-04 .1.14E-04 1.46E-05 3.91 E-04 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Co-58 Ci ND ND ND ND ND Co-60 Ci ND ND ND ND ND Cr-51 Ci ND ND ND ND ND Mn-54 Ci ND ND ND ND ND Mn"56 Ci ND ND ND* ND ND Rb-88 Ci ND ND ND ND ND Sr-89 Ci ND ND ND ND ND Sr-90 Ci ND ND ND ND ND Sr-92 Ci ND ND ND ND ND Nb-95 Ci ND ND ND ND ND Zr-95 Ci ND ND ND ND ND Nb~97 Ci ND ND ND ND ND Ag-110m Ci ND ND ND ND ND Sb-125 Ci ND ND ND ND ND Cs-137 Ci ND ND ND ND ND Ce-144 Ci ND ND ND ND ND Total Ci ND ND ND ND ND Page 1 of 2
ATTACHMENT 1 Palisades - Table 1C 2015 Gaseous Effluents - Ground Level Release, Continuous Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter3 Quarter 4 Annual Tritium Ci 1.93E+OO 1.71 E+OO 2.88E+OO 3.99E+OO 1.05E+01 Gross Alpha Ci ND ND ND ND ND C-14 Ci 2.13E+OO 2.15E+OO 1.78E+OO 1.71 E+OO 7.74E+OO ND =Measurements performed but rio activity detected. Page 2 of 2
ATIACHMENT1 Palisades -Table 2A 2015 Liquid Effluents - Sum of All Releases Summation of All Uncertainty Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total O/o Fission and Activation Products (excluding tritium, gases, and gross al ha Ci O.OOE+OO 1.17E-04 4.19E-04 2.58E-03 3.11 E-03 11.50 Average Concentration Ci/ml O.OOE+OO 3.49E-12 1.26E-11 8.03E-11 2.25E-11 % of Limit % O.OOE+OO 4.97E-05 2.43E-04 1.01 E-03 3.05E-04 Tritium Ci 8.09E+01 1.71 E+02 2.41 E+02 3.70E+01 5.30E+02 Average Concentration Ci/ml 2.Q6E-06 5.10E-06 7.21 E-06 1.15E-06 3.83E-06 % of Limit % 2.06E-01 5.1 OE-01 7.21 E-01 1.15E-01 3.83E-01 Dissolved and Entrained Gases Ci O.OOE+OO O.OOE+OO 6.57E-04 O.OOE+OO 6.57E-04 Average Concentration Ci/ml O.OOE+OO 0.00E+OO 1.97E-11 O.OOE+OO 4.75E-12 % Of Limit % O.OOE+OO O.OOE+OO 9.85E-06 O.OOE+OO 2.38E-06 Gross Alpha Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO Average Concentration Ci/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Volume of Batch Liquid Effluent (Before Dilution) Liters O.OOE+OO 1.79E+05 O.OOE+OO O.OOE+OO 1.79E+05 Dilution Water Used for Above Liters 3.93E+10 3.36E+10 3.34E+10 3.21E+10 1.38E+11 Volume of Continuous or Balance-of-Plant Liquid Effluent (e.g., low-activity or unprocessed) Before Dilution Liters 7.84E+09 7.93E+09 8.49E+09 7.75E+09 3.20E+10 Average Stream 3 Flow m /s 5.05E+OO 4.27E+OO 4.20E+OO 4.04E+OO 4.39E+OO Dilution flow rate (gal/qtr) = # of Dilution pumps running x days running/qtr x 4000 gpm/pump x min/day Page 1 of 1
ATTACHMENT 1 Palisades - Table 28 2015 Liquid Effluents - Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products Cr-51 Ci ND ND ND ND ND Mn-54 Ci ND ND ND ND ND Fe-55 Ci ND ND ND ND ND Fe-59 Ci ND ND 3.56E-05 3.56E-05 Co-57 Ci ND ND ND ND Co-58 Ci ND 2.45E-05 2.42E-05 1.51 E-03 1.56E-03 Co-60 Ci ND ND 1.45E-04 2.15E-04 3.60E-04 Sr-89 Ci ND ND ND ND ND Sr-90 Ci ND ND ND ND ND Nb-95 Ci ND ND ND 5.55E-05 5.55E-05 Nb-97 Ci ND ND 6.03E-05 ND 6.03E-05 Ag-11 Om Ci ND 9.28E-05 1.89E-04 6.40E-04 9.22E-04 Sn-113 Ci ND ND ND ND ND Sb-124 Ci ND ND ND ND ND Sb-125 Ci ND ND ND ND ND 1-131 Ci ND ND ND ND ND 1-133 Ci ND ND ND ND ND 1-135 Ci ND ND ND ND ND Cs-134 Ci ND ND ND ND ND Cs-137 Ci ND ND ND 2.68E-05 2.68E-05 Ni-63 Ci ND ND ND ND ND Zn-65 Ci ND ND ND ND ND Zr-95 Ci ND ND ND ND ND Mo-99 Ci ND ND ND ND ND Ru-105 Ci ND ND ND 5.65E-05 5.65E-05 La-140 Ci ND ND ND ND ND Ce-141 Ci ND ND ND ND ND Ce-144 Ci ND ND ND ND ND Totals Ci ND 1.17E-04 4.19E-04 2.54E-03 3.08E-03 Dissolved and Entrained Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Gases Kr-85 Ci ND ND ND ND ND Kr-85m Ci ND ND ND ND ND Kr-88 Ci ND ND ND ND ND Xe-131m Ci ND ND ND ND ND Xe-133 Ci ND ND 6.57E-04 ND 6.57E-04 Xe-133m Ci ND ND ND ND ND Xe-135 Ci ND ND ND ND ND Xe-135m Ci ND ND ND ND ND Totals ND ND 6.57E-04 ND 6.57E-04 Page 1 of 2
ATTACHMENT 1 Palisades - Table 28 2015 Liquid Effluents - Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products Tritium Ci 8.08E+01 1.71 E+02 2.41 E+02 3.70E+01 5.30E+02 Gross Alpha Ci ND ND ND ND ND ND= None Detected Page 2 of 2
ATTACHMENT 1 Palisades -Table 2C 2015 Liquid Effluents - Continuous Mode Fission and Activation Units Quarter 1 Quarter2 Quarter 3 Quarter 4 Annual Products Cr-51 Ci ND ND ND ND ND Mn-54 Ci ND ND ND ND ND Fe-55 Ci ND ND ND ND ND Fe-59 Ci ND ND ND ND ND Co-57 Ci ND ND ND ND ND Co-58 Ci ND ND ND ND ND Co-60 Ci ND ND ND ND ND Sr-89 Ci ND ND ND ND ND Sr-90 Ci ND ND ND ND ND Nb-95 Ci ND ND ND ND ND Nb-97 Ci ND ND ND ND ND Ag-110m Ci ND ND ND ND ND Sn-113 Ci ND ND ND ND ND Sb-124 Ci ND ND ND ND ND Sb-125 Ci ND ND ND ND ND 1-131 Ci ND ND ND ND ND 1-133 Ci ND ND ND ND ND 1-135 Ci ND ND ND ND ND Cs-134 Ci ND ND ND ND ND Cs-137 Ci ND ND ND 3.75E-05 3.75E"05 Ni-63 Ci ND ND ND ND ND Zn-65 Ci ND ND ND ND ND Zr-95 Ci ND ND ND ND ND Mo-99 Ci ND ND ND ND ND Ru-105 Ci ND ND ND ND ND La-140 Ci ND ND ND ND ND Ce-141 Ci ND ND ND ND ND Ce-144 Ci ND ND ND ND ND Totals Ci ND ND ND 3.75E-05 3.75E-05 Dissolved and Entrained Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Gases Kr-85 Ci ND ND ND ND ND Kr-85m Ci ND ND ND ND ND Kr-88 Ci ND ND ND ND ND Xe-131m Ci ND ND ND ND ND Xe-133 Ci ND ND ND ND ND Xe-133m Ci ND ND ND ND ND Xe-135 Ci ND ND ND ND ND Xe-135m Ci ND ND ND ND ND Totals ND ND ND ND ND Page 1 of 2
ATTACHMENT 1 Palisades - Table 2C 2015 Liquid Effluents - Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter3 Quarter 4 Annual Products Tritium Ci 5.40E-02 5.34E-02 1.50E-02 1.37E-02 1.36E-01 Gross Alpha Ci ND ND ND ND ND ND = None Detected Page 2 of 2
ATTACHMENT 1 Palisades - Table 3 2015 Low-Level Waste
- 1. Solid waste shipped offsite for burial or disposal (not irradiated fuel)
- 1. Type of waste Unit Estimated amount Est Total Error,%
- a. Spent resin, filters, m;:i 9.28E+OO evaporator bottoms, etc. 25 Curies 2.65E+01
- b. Dry compressible waste, m;:i 2.22E+02 dry active waste Curies 25 contaminated equipment, 3.50E+OO etc.
- c. Irradiated components, m;:i O.OOE+OO control rods, etc.
Curies O.OOE+OO
- d. Other (metal waste, and m;:i 8.62E+OO used oil) 25 Curies 3.67E+OO
- e. sum of all waste m;j 2.40E+02 25 Curies 3.37E+01 Page 1 of 3
ATTACHMENT 1 Palisades - Table 3 2015 Low-Level Waste
- 2. Estimate of Major Nuclide composition (by type of waste), list nuclides as needed
- a. Co-60 52% H-3 1.64%
Fe-55 18% Sb-125 1.73% Ni-63 19% Co-58 5.28%
- b. Co-60 24% Co-58 16.71%
Fe-55 17% Ni-63 11.79% Cs-137 1% Nb-95 5.94% Cr-51 5% Cm-243 1.69% AG-110m 4.73% H-3 1.27% Zr-95 3.44% C-14 2.81%
- c. NA NA NA NA
- d. H-3 3% Co-60 5.39%
C-14 2% Ni-63 77.79% Sr-90 1% Fe-55 9% Pu-241 1%
- e. H-3 1.72% Ag-110m 1.06%
Fe-55 16.71% Sb-125 1.43% Co-58 5.90% Ni-63 24.84% Co-60 43.70% NA - Not Applicable Page 2 of 3
ATTACHMENT 1 Palisades - Table 3 2015 Low-Level Waste
- 3. Solid waste disposition Number of shipments Mode of transportation Destination 2 Hittman Transport Alaron-Nuclear 2138 State Route 18 1 Hittman Transport Duratek Gallaher Road Facility 628 Gallaher Road 11 Hittman Transport Entergy Solutions Bear Creek Facility 1560 Bear Creek Road 1 Landstar lnway Entergy Solutions Bear Creek Facility 1560 Bear Creek Road 1 Landstar Ranger Inc. Entergy Solutions Bear Creek Facility 1560 Bear Creek Road Irradiated fuel shipments (disposition)
Number of shipments Mode of transportation Destination 0 N/A N/A Page 3 of 3
ATTACHMENT 1 Palisades - Table 4 2015 Dose Assessments, 10 CFR Part 50, Appendix I Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Dose Limit, Total 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem Body Total Body Dose (mrem) 6.07E-05 1.52E-04 2.43E-04 2.65E-04 6.44E-04 % Of Limit 0.00% 0.01% 0.02% 0.02% 0.02% Liquid Effluent Dose Limit, Any 5 mrem 5mrem 5 mrem 5 mrem 10 mrem Organ Liquid Effluent Organ Dose 6.07E-05 1.53E-04 2.45E-04 4.88E-04 8.72E (mrem) % of Limit 0.00% 0.00% 0.00% 0.01% 0.01% Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad GammaAir Gamma Air Dose (mrad) 1.16E-03 7.62E-04 1.24E-03 9.72E-04 4.14E-03 % of Limit 0.02% 0.02% 0.02% 0.02% 0.04% Gaseous Effluent Dose Limit, 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Beta Air Beta Air Dose (mrad) 8.97E-04 7.27E-04 1.03E-03 7.35E-04 3.39E-03 % of Limit 0.009% 0.007% 0.010% 0.007% 0.017% Gaseous Effluent Dose Limit, Any 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ (mrem) (Iodine, Tritium, Particulates) Gaseous Effluent Organ Dose 4.50E-03 3.94E-03 6.07E-03 7.BBE-03 2.24E-02 (mrem) (Iodine, Tritium, Particulates) % of Limit 0.06% 0.05% 0.08% 0.11% 0.15% Page 1 of 1
ATTACHMENT 1 Palisades - Table 5 2015 Dose Assessments, EPA 40 CFR Part 190, Individual in the Unrestricted Area Whole Body Thyroid Any Other Organ Dose Limit (mrem) 25 75 25 Dose (mrem) 8.05E-02 8.98E~02 3.75E-01 % of Limit 0.32% 0.12% 1.50% Page 1 of 1
ENCLOSURE 1 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL, REVISION 26 OFFSITE DOSE CALCULATION MANUAL APPENDIX A, REVISION 18 OFFSITE DOSE CALCULATION MANUAL APPENDIX B, REVISION 0 229 Pages Follow
ODCM Revision 26 lss ued Date 7/30/14 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: OFF SITE DOSE CALCULATION MANUAL J Process Applicability Exclusion D AKGennrich I 7/30/14 Procedure Sponsor Date MESoja I 6/22/14 Technical Reviewer Date CLJones I 7/29/14 User Reviewer Date ALWilliams I 7/29/14 General Manager Plant Operations Date
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Table of Contents I. GASEOUS EFFLUENTS ............................................................................................... 1 A. ALARM/TRIP SETPOINT METHOD .............................................................. 1
- 1. Allowable Concentration ................................... 2
- 2. Monitor Response ............................................. 3 B. DOSE RATE CALCULATION ........................................................................ 4 C. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION ................. 19
- 1. System Description ......................................... 19
- 2. Determination of Satisfactory Operation ....... 19 D. RELEASE RA TE FOR OFFSITE EC .......*................................................... 20 E. PARTICULATE AND IODINE SAMPLING .................................................. 20 F. NOBLE GAS SAMPLING ............................................................................ 21 G. TRITIUM SAMPLING ................................................................................... 21 H. FIGURE-GASEOUS EFFLUENTS FLOW PATHS ................................... 22 II. LIQUID EFFLUENTS ................................................................................................... 23 A. CONCENTRATION ...................................................................................... 23
- 1. Requirements ................................................... 23
- 2. Prerelease Analysis ......................................... 23
- 3. Effluent Concentration (EC) - Sum of the Ratios ................................................................ 24 B. INSTRUMENT SETPOINTS ......................................................................... 25
- 1. Setpoint Determination ................................... 25
- 2. Composite Samplers ....................................... 25
- 3. Post-Release Analysis .................................... 26 C. DOSE ........................................................................................................... 26
- 1. RETS Requirement .......................................... 26
- 2. Release Analysis ............................................. 26 D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT .............................. 30 E. RELEASE RATE FOR OFFSITE EC (50 MREMNR) .................................. 30 F. FIGURES ..................................................................................................... 31
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Table of Contents Ill. URANIUM FUEL CYCLE DOSE .................................................................................. 33 A. SPECIFICATION .......................................................................................... 33
- 8. ASSUMPTIONS ........................................................................................... 33 C. DOSE CALCULATION ................................................................................ 34 IV. SOURCE REFERENCE DOCUMENTS ....................................................................... 34 , "Palisades Gaseous And Liquid Source Terms, Curies/Year" , "Basic Radionuclide Data" , "Dose Factors for Submersion in Noble Gases" , "Stable Element Transfer Data" , "Inhalation Dose Commitment Factors" , "External Dose Factors for Standing on Contaminated Ground (DFGi)
(mrem/hr per pCi/m 2 )" , "Bioaccumulation Factors (µCi/gm per µCi/ml)" , "Ingestion Dose Commitment Factors" , "Palisades 10 Year X/Q - D/Q Data"
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 I. GASEOUS EFFLUENTS A. ALARM/TRIP SETPOINT METHOD Appendix A, Section 111.B.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following: For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and For iodine-131, for iodine-133, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. Appendix A, Section 111.A.1 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations, when averaged over 1 hour, will not be greater than Appendix A, Section 111.B.1. This section of the ODCM describes the methodology that will be used to determine these setpoints. The methodology for determining alarm/trip setpoints is divided into two major parts. The first consists of calculating an allowable concentration for the nuclide mixture to be released. The second consists of determining monitor response to this mixture in order to establish the physical settings on the monitors. 1
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 1. Allowable Concentration NOTE: If a batch release is made while a continuous release or another batch release is in progress, the sum of all values of Rk must be less than 10.0.
The total EC-fraction (Rk) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20: Rk =XIQ x F x Li C/ECi :5 10.0 (1.1) where: Actual or measured concentration, at ambient temperature and pressure of nuclide i (µCi/cc) The EC of nuclide i from 10 CFR 20, Appendix B, Table 2 The total EC-fraction for release point k X/Q = Most conservative sector site boundary dispersion (sec/m 3) (listed in site procedure CH 6.41, "Land Use Census") F = Release flow rate (83,000 cfm = 39.2 m 3/sec) for stack monitor considerations; variable for other monitors 2
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 2. Monitor Response Normal radioactivity releases consist mainly of well-decayed fission gases.
Therefore, monitor response calibrations are performed to fission gas typical of normal releases (mainly Xe-133). Response of monitors used to define fission product release rates under accident conditions may vary from that of Xe-133, however. Monitor response for the two categories of monitor is determined as follows:
- a. Normal Release (aged fission gasses)
Total gas concentration (µCi/cc) at the monitor is calculated. The detector response to isotopic activities (cpm/µCi/cc) is applied to determine cpm expected. The setting for monitor alarms is established at some factor (b) greater than 1 but less than 1/Rk (Equation 1.1) times the measured concentration (c): s=bxc (1.2)
- b. Accident Releases Monitors are preset to alarm at or before precalculated offsite dose rates would be achieved under hypothetical accident conditions.
These setpoints are established in accordance with Emergency Plan requirements for defining Emergency Action Levels and associated actions. Emergency Implementing Procedures contain monitor-specific curves or calibration constants for conversion between cpm and µCi/cc (or R/hr and µCi/cc), depending on monitor type, for fission product mixtures as a function of mixture decay time. When these monitors are utilized for other than accident conditions, either an appropriately decayed "accident" conversion curve may be used, or a decayed fission gas calibration factor may be applied. In these cases, setpoints are established as in 1.A above. Setpoints of accident monitors (if set to monitor normal releases) are reset to the accident alarm settings at the end of normal release. Setpoints of other release monitors are maintained at the level used at the latest release (well below the level which would allow 10 times EC to be exceeded at the site boundary), or are reset to approximately three times background in order to detect leakage or inadvertent releases of low level gases. 3
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 B. DOSE RATE CALCULATION
- 1. Dose rates are calculated for (1) noble gases and (2) iodines and particulates.
Dose rates as defined in this section are based on 10 CFR 50 Appendix I limits of mrem per quarter and millirem per year. All dose pathways of major importance in the Palisades environs are considered. NRCDose is the Effluent Dose Calculation software that supports LADTAP, GASPAR, and XOQDOQ which perform the actual dose calculations using the equations supplied here.
- a. Equations and assumptions for calculating doses from noble gases are as follows:
- 1) Assumptions a) Doses to be calculated are the maximum offsite point in air, total body and skin.
b) Exposure pathway is submersion within a cloud of noble
\.
gases. c) Noble gas radionuclide mix is based on the historically observed source term given in Attachment 2, plus additional nuclides. d) Basic radionuclide data are given in Attachment 2. e) All releases are treated as ground-level. f) Meteorological data expressed as joint-frequency distribution of wind speed, wind direction, and atmospheric stability for the period resulting in X/Q's and D/Q's shown in site procedure CH 6.41, "Land Use Census." g) Raw meteorological data consists of wind speed and direction measurements at 1Om and temperature measurements at 1Om and 60m. h) Dose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist (overland sector site boundaries), and nearest residents. 4
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 i) Potential maximum population (resident) exposure points are identified in site procedure CH 6.41, "Land Use Census." j) A semi-infinite cloud model is used. k) Radioactive decay is considered for the plume. I) Building wake effects on effluent dispersion are considered. m) A sector-average dispersion equation is used. n) The wind speed classes that are used are as follows: Wind Speed Class Number Range (m/s) Midpoint (m/s) 1 0.0-0.4 0.2 2 0.4-1.5 0.95 3 1.5-3.0 2.25 4 3.0-5.0 4.0 5 5.0-7.5 6.25 6 7.5-10.0 8.75
~1 > 10.0 o) The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, 8=2, ... , G=7.
p) Terrain effects are not considered. 5
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 2) Equations To calculate the dose for any one of the exposure points, the following equations are used.
For determining the air concentration of any radionuclide: X = I9 I7 ( 2) 1/2 f1k Qi P [ - ;i. x Jl ( (1.3)
' j=l k=l 7r LzkVJ (27rxln) exp IUi where:
= Air concentration of radionuclide i, µCi/m 3 .
= Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
= Average release rate of radionuclide i, µCits.
p = Fraction of radionuclide remaining in plume. Lzk = Vertical dispersion coefficient for stability class k (m). Uj = Midpoint value of wind speed class interval j, m/s. x = Downwind distance, m. n = Number of sectors, 16. Ai = Radioactive decay coefficient of radionuclide i, s- 1. 2nx/n = Sector width at point of interest, m. 6
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the total body dose rate: (1.4) where: Drs = Total body dose rate, mrem/y. 3 xi = Air concentration of radionuclide I, µCi/m . DFBi = Total body dose factor due to gamma radiation, 3 mrem/y per µCi/m (Attachment 3). For determining the skin dose rate: (1.5) where:
= Skin dose rate, mrem/y.
= Air concentration of radionuclide i, µCi/m 3 Skin dose factor due to beta radiation, mrem/y per
µGi/m 3 (Attachment 3).
1.11 = The average ratio of tissue to air energy absorption coefficients, mrem/mrad. Gamma-to-air dose factor for radionuclide i, mrad/y per µCi/m 3 (Attachment 3). For determining dose rate to a point in air: (1.6) where:
= Air dose rate, mrad/yr.
Air dose factor for beta radiation (Attachment 3). 7
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- b. Equations and assumptions for calculating doses from radioiodines and particulates are as follo'!lfs:
- 1) Assumptions a) Dose is to be calculated for the critical organ, thyroid, and the critical age groups (adult, teen, child, infant), infant (milk) and child (green, leafy vegetables).
b) Exposure pathways from iodines and particulates are milk ingestion, ground contamination, green leafy vegetables from home gardens, and inhalation. c) The radioiodine and particulate mix is based on the historically observed source term given in Attachment 2. d) Basic radionuclide data are given in Attachment 3. e) All releases are treated as ground-level. f) Mean annual average X/Q's are given in site procedure CH 6.41, "Land Use Census." g) Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 1Om and temperature measurements at 1Om and 60m. h) Dose is to be evaluated at the potential offsite exposure points where maximum doses to man are expected to exist. i) Real cow, goat and garden locations are considered. j) Potential maximum exposure points (site procedure CH 6.41, "Land Use Census") considered are the nearest cow, goat, and home garden locations in each sector. k) Terrain effects and open terrain recirculation factors are not considered. I) Building wake effects on effluent dispersion are considered. 8
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 m) Plume depletion and radioactive decay are considered for air-concentration calculations. n) Radioactive decay is considered for ground-concentration calculations. o) Deposition is calculated based on the curves given in Figure 1.2. p) Milk cows and goats obtain 100% of their food from pasture grass May through October of each year. Use default values of 0.58 for cows and 0.67 for goats for fraction of year on pasture.
- 2) Equations To calculate the dose for any one of the potential maximum-exposure points, the following equations in Section 1.2.2 are used.
a) Inhalation Equation for calculating air concentration, Xi is the same as in the Noble Gas Section (Equation 1.3). For determining the organ dose rate: Di= 1x106 L X;DFI; BR (1.7) where: Di = Organ dose rate due to inhalation, mrem/y. xi = Air concentration of radionuclide i, µCi/m 3 . DFli = Inhalation dose factor, mrem/pCi (Attachment 5). BR = Breathing rate 1400 m3/y infant; 3700 m 3/y child; or 8000 m3/y teen and adult. 1x10 6
= pCi/µCi conversion factor.
9
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 b) Ground Contamination For determining the ground concentration of any nuclide; where: Ground concentration of radionuclide i, 2
µCi/m .
k = Stability class. Joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point, expressed as a fraction. Average release rate of radionuclide i,
µCi/s.
DR = Relative deposition rate, m-1 (Fig 1.2). x = Downwind distance, m. n = Number of sectors, 16. 2mc/n = Sector width at point of interest, m.
= Radioactive decay coefficient of radionuclide i, y- 1.
= Time for buildup of radionuclides on the ground, 15 y.
3.15x10 7 = s/y conversion factor. 10
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Figure 1.2 Corrected 10 3 January 1977 I I I I~ : I
' 'l
~~ .. !
i.o-4 II
-a:
II.I
- i j ~ ;
II.I
- I cc:
II.I
' ""Iii.
II.I
~ "' ~
c( a: co
"' '"- lilo 0 ~
11J""i'
~ ..
-~
"'Q ......... "'2 ~ '""' ....ct ... IC
'\\. I 1o-8 I I iI !
I 1 ' I I I I J 11 10-7 11 I; ' j 0.1 . 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) Figure 7. Relative Deposition for Ground Level R1leam (All Atmospheric St1bility Cl1sses) n - -- r-11
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the total body or organ dose rate from ground contamination: Da = (8, 760)(1X10 6)(0. 7) LG; DFG; (1.9) where: Dose rate due to ground contamination, mrem/y. Ground concentration of radionuclide i,
µCi/m 2 .
Dose factor for standing on contaminated ground, mrem/h per pCi/m 2 (Attachment 6). 8,760 = Occupation time, h/y. 1x106 = pCi/µCi conversion factor. 0.7 = Shielding factor accounting for a distance of 1.0 meter above ordinary ground, dimensionless. c) Milk and Vegetation Ingestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation: 7 .
.=
3,600 L fkQ;DR (r[l-exp(-A,E;te)] + B;Jl-exp(-.4/b)]Jrrex (- . ))) ( 1.10) CV, ( xi) . PA. u_ P .4,!b k = 1 2 Jr n Yv AE1 i where: cvi = Concentration of radionuclide i in and on vegetation, µCi/kg. k = Stability class. fk = Frequency of this stability class and wind direction combination, expressed as a fraction. 12
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Qi = Average release rate of radionuclide i,
µCi/s.
DR = Relative deposition rate, m- 1 (Figure 1.2). x = Downwind distance, m. n = Number of sectors, 16. 2nx/n = Sector width at point of interest, m. r = Fraction of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulates). AEi = Effective removal rate constant,
=
AEi Ai + "'J..w, where Ai is the radioactive decay coefficient, h- 1 , and "'J..w is a measure of physical loss by weathering
=
("'J..w 0.0021 h} te = Period over which deposition occurs, 720 h. Yv = Agricultural yield, 0.7 kg/m 2 . Biv = Transfer factor from soil to vegetation of radionuclide i (Attachment 4). Ai = Radioactive decay coefficient of radionuclide i, h-1 . tb = Time for buildup of radionuclides on the ground, 1.31x105 h (15Y). 2 p = Effective surface density of soil, 240 kg/m . 3,600 = s/h conversion factor. th = Holdup time between harvest and consumption of food (2, 160 hours for stored food). 13
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the concentration of C-14 in vegetation: CV14 =1 X10 3 X14 (0.11/0.16) (1.11) where: Concentration of C-14 in vegetation, µCi/kg. Air concentration of C-14, µCi/m 3 . 0.11 = Fraction of total Plant mass that is natural carbon. 0.16 = Concentration of natural carbon in the atmosphere, g/m 3 . 1x103 = g/kg conversion factor. For determining the concentration of H-3 in vegetation: CVr=1x1Q 3 Xr(0.75)(0.5/H) (1.12) where: CVr = Concentration of H-3 in vegetation, µCi/m 3 . Xr = Air concentration of H-3, µCi/m 3 . 0.75 = Fraction of total Plant mass that is water. 0.5 = Ratio of tritium concentration in Plant water to tritium concentration in atmospheric water.
- H = Absolute humidity of the atmosphere, g/m 3 .
1x103 = g/kg conversion factor. 14
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the concentration of any nuclide in cow's or goat's milk: (1.13) where: CMi = Concentration of radionuclide i (including C-14 and H-3) in milk, µCi/I. cvi = Concentration of radionuclide i in and on vegetation, µCi/kg. FMi = Transfer factor from feed to milk for radionuclide i, d/I (Attachment 4). Ot = Amount of feed consumed by the milk animal per day, kg/d (cow, 50 kg/d or goat 6 kg/d).
= Radioactive decay coefficient of radionuclide i, d-1*
= Transport time of activity from feed to milk to receptor, 2 days.
15
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the organ dose rate from ingestion 'Of green leafy vegetables and milk: D=l xl0 6 LCM; DE UM (1.14) where: D = Organ dose rate due to ingestion, mrem/y. CMi = Concentration of radionuclide i in vegetables or milk, µCi/kg (or liters). DFi = Ingestion dose factor, mrem/pCi (Attachment 8). UM = Ingestion rate for milk, 330 l/y; for vegetables 26 kg/yr (child), no ingestion by infant. 1x106 = pCi/µCi conversion factor. d) Meat Ingestion (Beef) To calculate the concentration of a nuclide in animal flesh: (1.15) where: cfi = Concentration-of nuclide i in the animal flesh, pCi/kg. Fraction of animal's daily intake which appears in each kg of flesh, days/kg (Attachment 4). Concentration of radionuclide i in the animal's feed (Equation 1.10). 16
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
= Amount of feed consumed by the cow per day, 50 kg/d.
= Average time from slaughter to consumption, 20 days.
To determine the organ dose from ingestion of beef: (1.16) where:
= Ingestion dose factor for age group, mrem/pCi (Attachment 8) for nuclide i.
= Ingestion rate of meat for age group, kg/y (child-41, teen-65, adult-110).
e) OrganDose Rates For determining the total body and organ dose rate from iodines and particulates: (1.17) where: D = Total organ dose rate, mrem/y. D1 = Dose rate due to inhalation, mrem/y. DG = Dose rate due to ground contamination, mrem/y. DM = Dose rate due to milk ingestion, mrem/y. Dv = Dose rate due to vegetable ingestion, mrem/y. DF = Dose rate due to beef ingestion, mrem/y. 17
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 3) The maximum organ dose rate, maximum total body dose rate, and maximum skin dose rate calculated in the previous section (Sec l.B) are used to calculate design basis quantities as described in Section l.B.1.3.
- c. Land Use Census Appendix A, Sections J.3.b and J.3.c describe the requirements for an annual land use census. Changes will be effective on January 1 of the year following the year of the survey.
- d. Gaseous Releases From the Steam Generator Slowdown Vent and Atmosphere Release Valves Releases from the steam generator blowdown vent and atmospheric relief valves are difficult to quantify as there are no sampling capabilities on these steam release systems. However, neither system is a normal release path. The steam generator blowdown vent is normally routed to the main condenser and recirculated. Radioactive releases will be calculated by analyzing steam generator blowdown liquid and assuming that 100 percent of Noble Gases, 10 percent of the Iodines and 1 percent of the Particulates will be released to the environment in the steam phase, Volumes will be released to the environment in the steam phase. Volumes will be calculated using water balances or alternate means as available.
18
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 C. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA.
- 1. System Description A flow diagram for the GRTS is given in Figure 1-1. The system consists of three waste-gas compressor packages, six gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown and displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header.
Design of the system precludes hydrogen explosion by means of ignition source elimination (diaphragm valves, low flow diaphragm compressors and system electrical grounding), and minimization of leakage outside the system. Explosive mixtures of hydrogen and oxygen have been demonstrated compatible with the system by operational experience.
- 2. Determination of Satisfactory Operation Doses will be calculated for batch and continuous releases as described in Section l.B. These calculations will be used to ensure that the GRTS is operating as designed. Because the Plant was designed to collect and hold for decay a vast majority of the high level gases generated within the primary system, and because the operating history of the Plant has demonstrated the system's consistent performance well below Appendix I limits, no additional operability requirements are specified.
19
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 D. RELEASE RATE FOR OFFSITE EC 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be in concentrations less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. (Note: there are no unrestricted areas anywhere within the site boundary as defined by Figure 1-1.) Concentrations at this level if inhaled or ingested continuously for one year will result in a dose of 50 mrem whole body except for submersion dose isotopes (gaseous tritium and noble gasses) which will results in a dose of 100 mrem whole body. 10 CFR 50.36a requires that the release of radioactive materials be kept as low as reasonably achievable. However, the section further states that the licensee is permitted the flexibility of operation, to assure a dependable source of power even under unusual operating conditions, to release quantities of material higher than a small percentage of 10 CFR 20.1302 limits but still within those limits, Appendix I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement. The GASPAR code has been run to determine the dose due to external radiation and inhalation. The source term used is listed in Attachment 2. The meteorology data is given in site procedure CH 6.41, "Land Use Census." Dose using annual average meteorology, to the most limiting organ of the person assume to be residing at the site boundary with highest X/Q, is 2.15E-02 mrem (for one year). The release rate which would result in a dose rate equivalent to 50 mrem/year (using the more conservative total body limit) is the curies/year given in Attachment 2 multiplied by 50/2.15E-02 or 0.11 Ci/sec. E. PARTICULATE AND IODINE SAMPLING Particulate and iodine samples are obtained from the continuous sample stream pulled from the Plant stack. Samples typically are obtained to represent an
. integrated release from a gas batch (waste gas decay tank or Containment purge, for example), or a series of samples are obtained to follow the course of a release.
In any event, sample intervals are weekly, at a minimum. Because HEPA filters are present between most source inputs to the stack and the sample point, releases of particulates normally are significantly less than pre-release calculations indicate. This provides for conservatism in establishing setpoints and in estimation of pre-release dose calculations. However, for the sake of maintaining accurate release totals, monitor results (for gases) and sample results (for particulates and iodines) utilized rather than the pre-release estimates, for cumulative records. 20
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released. Sampling and analysis will be performed per Appendix A, Table B-1 requirements. F. NOBLE GAS SAMPLING Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the Containment prior to purging. Analysis of these samples will be used for accountability of noble gases. Off gas will be sampled at least weekly and used to calculate monthly noble gas releases. Non-routine releases will be quantified from the stack noble gas monitor (RE 2326) which has a LLD of 1E-06 µCi/cc. Sampling and analysis will be performed per Appendix A, Table B-1 requirements. G. TRITIUM SAMPLING Tritium has a low dose consequence to the public because of low energy decay. The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded). Because of the low dose impact, gaseous tritium sampling will not be required. Tritium effluents will be estimated using conservative evaporation rate calculations from the fuel pool and reactor cavity. 21
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 11. LIQUID EFFLUENTS A. CONCENTRATION
- 1. Requirements Appendix A, Section 111.G requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to ten times the Effluent Concentration (EC) specified in 10 CFR 20, Appendix B, Table 2, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 µCi/ml total activity. To ensure. compliance, the following approach will be used for each release.
- 2. Prerelease Analysis Most tanks will be recirculated through two volume changes prior to sampling for release to the environment to ensure that a representative sample is obtained. The appropriate recirculation time for those tanks too large to provide two volume changes will be the time that the suspended particulate concentration reaches steady state. Either a one-time test, or prior sampling data, may be used to determine appropriate recirculation time.
Prior to release, a grab sample will be analyzed for each release, and the concentration of each radionuclide determined. c = (2.1) where: c = Total concentration in the liquid effluent at the release point, µCi/ml.
= Concentration of a single radionuclide i, µCi/ml.
23
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 3. Effluent Concentration (EC) - Sum of the Ratios The EC-Fraction (Rj) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:
Rj I __9_:::;10.0 (2.2) EC where: Ci = Effluent concentration of radionuclide i, µCi/ml. ECi = The EC of radionuclide i, 10 CFR 20, Appendix B, Table 2, Column 2 - µCi/ml. Ri = The Total EC-Fraction for the release point. The sum of the ratios at the discharge to the lake must be:::; 10 due to the releases from any or all concurrent releases. The following relationship will assure this criterion is met: (2.3) where:
= The effluent flow rate (gallons/minute) for the respective releases, determined by Plant personnel.
= The Total EC-Fractions for the respective releases as determined by Equation 2.2.
F = Minimum required dilution flow rate. Normally, a conservatively high dilution flow rate is used, that is, flow
=
rate used (bi)(F) where bi is a conservative factor greater than 1.0. 24
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 B. INSTRUMENT SETPOINTS
- 1. Setpoint Determination Appendix A, Section 111.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to ensure the requirements of Appendix A, Section 111.G are not exceeded. Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivalent setpoint in counts per minute (cpm). The identification number for each liquid effluent radiation detector is contained in Figure 2-2.
The respective alarm/trip setpoints at each release point will be set such that the sum of the ratios at each point, as calculated by Equation 2.2, will not be exceeded. The value of R is directly related to the total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the value of R. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm/trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint (S) be set above the effluent concentration (C) by the same factor (b) utilized in setting dilution flow. That is: S = bxC (2.4) Liquid effluent flow paths and release points are indicated in Figure 2.1.
- 2. Composite Samplers Effluent pathways, Turbine Sump and Service Water, are equipped with continuous compositors to meet the requirements of Appendix A, Table D-1.
These compositors are adjustable and normally set in a time mode and collect three to six samples hourly, 24 hours a day with a total collection of approximately one gallon per day. A representative sample is collected daily from the compositor and saved for the weekly, monthly, and quarterly analysis requirements of Appendix A, Table D-1. In the event that a compositor is not operational, effluent releases via this pathway may continue provided that grab samples are collected and analyzed for gross beta or gamma radioactivity at least once per 24 hours per Appendix A, Table C-1, Action 3. 25
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 3. Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 1 were not exceeded.
A composite list on concentrations (Ci), by isotope, will be used with the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate compliance with the limits in Section 1. This data and setpoints will be recorded in auditable records by Plant personnel. C. DOSE
- 1. RETS Requirement Appendix A, Section 111.H.1 requires that the quantity of radionuclides released by limited such that the dose or dose commitment to an individual from radioactive materials in liquid effluents release to unrestricted areas from the reactor (see Figure 2-1) will not exceed:
- a. During any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ, and
- b. During any calendar year, 3 mrem to the total body and 10 mrem to any organ.
To ensure compliance, quantities of activity of each radionuclide released will be summed for each release and accumulated for each quarter as follows in Section 2.
- 2. Release Analysis Dose calculations shall be performed for each batch release, and weekly for continuous releases unless documentation exists to demonstrate an activity below which dose limits of Section 11.C.1 will not be exceeded.
- a. Water Ingestion The dose to an individual from ingestion of radioactivity from any source as described by the following equation:
Di I (DCF)ii x h (2.5) i= I 26
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 where:
= Dose for the r organ from radionuclides releases, mrem.
= The organ of interest.
(DCF)ij = Ingestion dose commitment factor for the jth organ from the i1h radionuclide mrem/pCi, see Attachment 8.
= Activity ingested of the i1h radionuclide, pCi.
Ii is described by: I*= (Ai)(V)(365) (1E06) (2.6) I (1QQQ)(d} where: 365 = Days per year. Ai = Annual activity released of i1h radionuclide, µCi. v = Average rate of water consumption (2000 ml/d - adult, 1400 ml/d - teen and child, 900 ml/d - infant, ICRP 23, p 358). d = Dilution water flow for year, ml. 1000 = Dispersion factor from discharge to nearest drinking water supply. 1E06 = Conversion µCi to pCi. The dose equation then becomes: i Di= ( 3 .SS~OS)(V) L: (DCF)iiXAimrem (2.7) i=1 27
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- b. Fish Ingestion*
The dose to an individual from the consumption of fish is described by Equation 2.10. In this case, the activity ingested of the ith radionuclide (h) is described by: _ AiBiF(1E09) _ c* h- 15d -p I (2.8) where:
= Annual released of ith radionuclide, µCi.
= Fish concentration factor of ith radionuclide
µCi/gm
µCi/ml (see Attachment 7).
F = Amount of fish eaten per year (21 kg adult, 16 kg teen, 6.9 kg child, none infant). 15 = Dispersion factor from discharge to fish exposure point. d = Dilution water flow for year, ml. 1E09 = Conversion of µCi, gm, and Kg to pCi. Substitution of Equation 2.8 into Equation 2.5 gives: i (6.7E07)F Di= d I AiXBiXDCFimrem (2.9) i =1 28
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- c. Annual*Analysis A complete analysis utilizing the NRC computer code LADTAP with the total source release Will be done annually in conjunction with the annual environmental report. This analysis will provide estimates of dose to the total body *and various organs in addition to the dose limiting organs considered in the method of Section 2. The following approach is utilized on LADTAP. The dose to the j1h organ from m radionuclides, Dj, is described by:
m Di= I oiimrem (2.10) i =1 m
= I (DCF )ii x Ii mrem (2.11) i =1 where:
Dose to the j1h organ from the i1h radionuclide, mrem.
= The organ of interest (bone, GI tract, thyroid, liver, kidney, lung, or total body).
(DCF)ij = Adult ingestion dose commitment factor for the j1h organ from the i1h radionuclide, mrem/pCi (see Attachment 8).
= Activity ingested of the i1h radionuclide, µCi.
hfor water ingestion is described by: I* _AiVr
---µ er* (2.12)
I Vd and for fish ingestion Ii is described by: (2.13) 29
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 where: Ai = Activity release of j1h radionuclide during the year, µCi. v = Average rate of water consumption (2000 mild). r = Number of days during the year (365 d). v = Dispersion factor from point of discharge to point of exposure. d = Dilution water volume (ml). Bi = Fish concentration factor of the i1h radionuclide,
µCi/gm Attachment 7, µCi/ml F = Amount of fish eaten per day (57.5 gm/d).
D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT The Palisades liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their discharge (through deep bed filtration and ion exchange) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2-1) will not exceed the limits of Appendix A, 111.H.1. E. RELEASE RATE FOR OFFSITE EC (50 MREMNR) 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. Concentrations at this Effluent Concentration (EC) level, if ingested for one year, will result in a dose of 50 millirem to the total body. In addition, 10 CFR 50.36a requires that the release of radioactive materials be kept as low as is reasonably achievable. Appendix I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement. The LADTAP code has been run to determine the dose due to drinking water at Plant discharge concentration (1,000 x nearest drinking water intake concentration). The nominal average source term used is given in Attachment 2. Dose to the most limiting organ of the person hypothetically drinking this water is 3.88E-03 mrem. This is only 0.13% of the more conservative 50 mrem/yr total body value. 30
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Ill. URANIUM FUEL CYCLE DOSE A. SPECIFICATION In accordance with Appendix A, Section 111.1.1, if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Appendix A, Sections 111.C.1, 111.D.1, or 111.H.1, then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste storage tanks) shall be calculated. The dose is to be determined for the member of the public protected to be the most highly exposed to these combined sources. B. ASSUMPTIONS
- 1. The full time resident determined to be maximally exposed individual (excluding infant) is assumed also to be a fisherman. This individual is assumed to drink water and ingest local fish at the rates specified in Sections 11.C.2.1 and 11.C.2.2.
- 2. Amount of shore line fishing (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours per quarter (average of approximately 1/2 hour per day each day of the quarter) for the second and third quarters of the year, 36 hours for the fourth quarter and 16 hours for the first quarter.
33
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 C. DOSE CALCULATION Maximum doses to the total body and internal organs of an individual shall be determined by use of LADTAP and GASPAR computer codes, and doses to like organs and total body summed. Added to this sum will be a mean dose rate, calculated or measured for the shoreline due to Plant present curing the quarter in question, times the assumed fishing time. D4o = (2.15) where: D4o = 40 CFR 190 dose (mrem). DG = Limiting dose to an individual from gaseous source term (mrem). DL = Limiting dose to an individual from liquid source term (mrem). Rr = Mean dose rate calculated to be applicable to Lake Michigan shoreline adjacent to Plant site (mrem/hr). T = Assumed shoreline fishing time for the quarter in questions (hours). IV. SOURCE REFERENCE DOCUMENTS
- 1. Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioacitve Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, R 1.
- 2. 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, R1.
- 3. NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, April 91.
- 4. NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, R3.
- 5. NUREG/CR-4013, LADTAP II - Technical Reference and User Guide, April 86.
- 6. NUREG/CR-4653, GASPAR II - Technical Reference and User Guide, March 87.
- 7. CH 6.61, Revising the ODCM and ODCM Appendix A.
34
Proc No ODCM Attachment 1 Revision 26 Page 1of1 PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIESNEAR (1) Nuclide Gaseous(2) Liquid(2) H-3 5.5 159 Kr-85 4.1 NA Kr-85m 0.12 NA Kr-87 8.4E-02 NA Kr-88 2.1E-01 NA Ar-41 3.1E-02 NA Xe-131m 2.2 NA Xe-133 1493 NA Xe-133m 0.43 NA Xe-135 1.11 NA Xe-135m 0.3 NA 1-131 0.025 3.21E-03 1-132 2.91E-03 NA 1-133 6.5E-03 4.7E-05 1-134 4.8E-04 NA 1-135 1.84E-02 NA Na-24 1.5E-06 NA Cr-51 '2.5E-04 3.9E-03 Mn-54 4.1E-04 7.8E-03 Co~57 2.1 E-06 3.2E-05 Co-58 8.6E-04 2.9E-02 Fe-59 6.6E-06 4.1E-04 Co-60 1.1E-03 1.24E-02 Se-75 3.7E-06 NA Nb-95 2.4E-05 4.53E-04 Zr-95 4.7E-06 1.79E-04 Mo-99 1.5E-07 NA Ru-103 0.3E-07 0.1 E-05 Sb-127 NA 3.5E-05 Cs-134 4.5E-05 0.7 Cs-136 NA 1.8E-06 Cs-137 2.6E-04 1.36E-02 Ba-140 2.8E-07 NA La-140 7.5E-07 1.1 E-04 Unidentified beta 3.9E-04 3.3E-03 (1) Data derived from taking the effluents released during July-December 1978 through January-June 1982 and dividing by 4. (2) Nuclide values listed as NA have not been observed at detectable levels in these waste streams.
Proc No ODCM Attachment 2 Revision 26 Page 1of2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA1 GAMMA1 (days) (1/s) (MEV/DIS) (MEV/DIS) 1 Tritium 4.49E 03 1.79E-09 5.68E-03 0.0 2 C-14 2.09E 06 3.84E-12 4.95E-02 0.0 3 N-13 6.94E-03 1.16E-03 4.91 E-01 1.02E 00 4 0-19 3.36E-04 2.39E-02 1.02E 00 1.05E 00 5 F-18 7.62E-02 1.05E-04 2.50E-01 1.02E 00 6 NA-24 6.33E-01 1.27E-05 5.55E-01 4.12E 00 7 P-32 1.43E 01 5.61E-07 6.95E-01 0.0 8 AR-41 7.63E-02 1.05E-04 4.64E-01 1.28E 00 9 CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02 10 MN-54 3.03E 02 2.65E-08 3.80E-03 8.36E-01 11 MN-56 1.07E-01 7.50E-05 8.29E-01 1.69E 00 12 FE-59 4.50E 01 1.78E-07 1.18E-01 1.19E 00 13 C0-58 7.13E 01 1.12E-07 3.41 E-02 9.78E-01 14 C0-60 1.92E 03 4.18E-09 9.68E-02 2.50E 00 15 ZN-69m 5.75E-01 1.39E-05 2.21E-02 4.16E-01 16 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 BR-84 2.21E-02 3.63E-04 1.28E 00 1.77E 00 18 BR-85 2.08E-03 3.86E-03 1.04E 00 6.60E-02 19 KR-85m 1.83E-01 4.38E-05 2.53E~01 1.59E-01 20 KR-85 3.93E 03 2.04E-09 2.51 E-01 2.21E-03 21 KR-87 5.28E-02 1.52E-04 1.32E 00 7.93E-01 22 KR-88 1.17E-01 6.86E-05 3.61E-01 1.96E 00 23 KR-89 2.21E-03 3.63E-03 1.36E 00 1.83E 00 24 RB-88 1.24E-02 6.47E-04 2.06E 00 6.26E-01 25 RB-89 1.07E-02 7.50E-04 1.01E 00 2.05E-OO 26 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 28 SR-91 4.03E-01 1.99E-05 6.50E-01 6.95E-01 29 SR-92 1.13E-01 7.1 OE-05 1.95E-01 1.34E 00 30 SR-93 5.56E-03 1.44E-03 9.20E-01 2.24E 00 31 Y-90 2.67E 00 3.00E-06 9.36E-01 0.0 32 Y-91m 3.47E-02 2.31E-04 2.73E-02 5.30E-01 33 Y-91 5.88E 01 1.36E-07 6.06E-01 3.61E-03 34 Y-92 1.47E-01 5.46E-05 1.44E 00 *2.50E-01 35 Y-93 4.29E-01 1.87E-05 1.17E 00 8.94E-02 36 ZR-95 6.50E 01 1.23E-07 1.16E-01 7.35E-01 37 NB-95m 3.75E 00 2.14E-06 1.81 E-01 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-01 39 M0-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 40 TC-99m 2.50E-01 3.21E-05 1.56E-02 1.26E-01
Proc No ODCM Attachment 2 Revision 26 Page 2 of2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA1 GAMMA1
~ (1/s) (MEV/DIS) (MEV/DIS) 41 TC-99 7.74E 07 1.04E-13 8.46E-02 0.0 42 TC-104 1.25E-02 6.42E-04 1.60E 00 1 ,95E 00 43 RU-106 3.67E 02 2.19E-08 1.01 E-02 0.0 44 TE-132 3.24E 00 2.48E-06 1.00E-01 2.33E-01 45 1-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02 46 1-131 8.05E 00 9.96E-07 1.94E-01 3.81 E-01 47 1-132 9.58E-02 8.37E-05 4.89E-01 2.24E 00 48 1-133 8.75E-01 9.17E-06 4.08E-01 6.02E-01 49 1-134 3.61E-02 2.22E-04 6.16E-01 2.59E 00 50 1-135 2.79E-01 2.87E-05 3.68E-01 1.55E 00 51 XE-131m 1.18E 01 6.80E-07 1.43E-01 2.01E-02 52 XE-133m 2.26E 00 3.55E-06 1.90E-01 4.15E-02 53 XE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02 54 XE-135m 1.08E-02 7.43E-04 9.58E-02 4.32E-01 55 XE-135 3.83E-01 2.09E-05 3.17E-01 2.47E-01 56 XE-137 2.71E 03 2.96E-03 1.77E 00 1.88E-01 57 XE-138 9.84E-03 8.15E-04 6.65E-01 1.10E 00 58 CS-134 7.48E 02 1.07E-08 1.63E-01 1.55E 00 59 CS-135 1.10E 09 7.29E-15 5.63E-02 0.0 60 CS-136 1.30E 01 6.17E-07 1.37E-01 2.15E 00 61 CS-137 1.10E 04 7.29E-10 1.71E-01 5.97E-01 62 CS-138 2.24E-02 3.58E-04 1.20E 00 2.30E 00 63 BA-139 5.76E-02 1.39E-04 8.96E-01 3.53E-02 64 BA-140 1.28E 01 6.27E-07 3.15E-01 1.71 E-01 65 LA-140 1.68E 00 4.77E-06 5.33E-01 2.31E00 66 CE-144 2.84E 02 2.82E-08 9.13E-02 1.93E-02 67 PR-143 1.36E 01 5.90E-07 3.14E-01 0.0 68 PR-144 1.20E-02 6.68E-04 1.21E 00 3.18E 00 Average energy per disintegration values were obtained from ICRP Publication No 38, Radionuclide Transformations: Energy and Intensity of Emissions 1983 and NUREG/CR-1413 (ORNUNUREG-70), a Radionuclide Decay Data Base - Index and Summary Table, DC Kocher, May 1980.
Proc No ODCM Attachment 3 Revision 26 Page 1of1 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES* Gamma body Gamma air Beta skin Beta air dose 1 dose2 dose 1 dose2 Kr-85m 1.17E3 1.23E3 1.46E3 1.97E3 Kr-85 1.61 E1 1.72E1 1.34E3 1.95E3 Kr-87 5.92E3 6.17E3 9.73E3 1.03E4 Kr-88 1.47E4 1.52E4 2.37E3 2.93E3 Kr-89 1.66E4 1.73E4 1.01 E4 1.06E4 Xe-131 m 9.15E1 1.56E2 4.76E2 1.11 E3 Xe-133m 2.51E2 3.27E2 9.94E2 1.48E3 Xe-133 2.94E2 3.53E2 3.06E2 1.05E3 Xe-135m 3.12E3 3.36E3 7.11E2 7.39E3 Xe-135 1.81 E3 1.92E3 1.86E3 2.46E3 Xe-137 1.42E3 1.51 E3 1.22E4 1.27E4 Xe-138 8.83E3 9.21E3 4.13E3 4.75E3 Ar-41 8.84E3 9.30E3 2.69E3 3.28E3
- 1. mrem/y per µCi/m 3
- 2. mrad/y per µCi/m 3
- Dose factors for exposure to a semi-infinite cloud of noble gases. Values were obtained from USN RC Regulatory Guide 1.109, Revision 1 (October 1977).
Proc No ODCM Attachment 4 Revision 26 Page 1of1 STABLE ELEMENT TRANSFER DATA Fm - MILK (COW) Fm - MILK (GOAT) Ft- MEAT Biv ELEMENT (DAYS/L) (DAYS/L) (DAYS/KG) (VEG/SOIL) H 1.0E-02 1.?E-01 1.2E-02 4.8E-OO c 1.2E-02 1.0E-01 3.1 E-02 5.5E-OO Na 4.0E-02 4.0E-02 3.0E-02 5.2E-02 p 2.5E-02 2.5E-01 4.6E-02 1.1 E-00 Cr 2.2E-03 2.2E-03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.0E-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.0E-02 6.6E-04 Co 1.0E-03 1.0E-03 1.3E-02 9.4E-03 Ni 6.?E-03 6.?E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E-02 8.0E-03 1.2E-01 Zn 3.9E-02 3.9E-02 3.0E-02 4.0E-01 Rb 3.0E-02 3.0E-02 3.1 E-02 1.3E-01 Sr 8.0E-04 1.4E-02 6.0E-04 1.?E-02 y 1.0E-05 1.0E-05 4.6E-03 2.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 1.?E-04 Nb 2.5E-03 2.5E-03 2.8E-01 9.4E-03 Mo 7.5E-03 7.5E-03 8.0E-03 1.2E-01 Tc 2.5E-02 2.5E-02 4.0E-01 2.5E-01 Ru 1.0E-06 1.0E-06 4.0E-01 5.0E-02 Rh 1.0E-02 1.0E-02 1.5E-03 1.3E+01 Ag 5.0E-02 5.0E-02 1.?E-02 1.5E-01 Te 1.0E-03 1.0E-03 7.?E-02 1.3E-OO I 6.0E-03 6.0E-02 2.9E-03 2.0E-02 Cs 1.2E-02 3.0E-01 4.0E-03 1.0E-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0E-06 5.0E-06 2.0E-04 2.5E-03 Ce 1.0E-04 1.0E-04 1.2E-03 2.5E-03 Pr 5.0E-06 5.0E-06 4.?E-03 2.5E-03 Nd 5.0E-06 5.0E-06 3.3E-03 2.4E-03 w 5.0E-04 5.0E-04 1.3E-03 1.8E-02 Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03
Proc NoODCM Attachment 5 Revision 26 Page 1 of 16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 BE10 9.49E-04 1.25E-04 2.65E-05 0. 0. 1.49E-03 1.73E-05 C14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 N13 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 F18 3.92E-06 0. 3.33E-07 0. 0. 0. 6.10E-07 NA22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 NA24 7.54E-06 7.54E-06 7.54E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 P32 1.4SE-03 8.03E-OS S.S3E-OS 0. 0. 0. 1.1SE-OS AR39 0. 0. 0. 0. 0. 1.00E-08 0. AR41 0. 0. 0. 0. 0. 3.14E-08 0. CA41 7.48E-OS 0. 8.16E-06. 0. 0. 6.94E-02 2.96E-07 SC46 3.?SE-04 5.41E*04 1.69E-04 0. 3.S6E-04 0. 2.19E-OS CRS1 0. 0. 6.39E-08 4.11E-08 9.4SE-09 9.176-06 2.SSE-07 MNS4 0. 1.81 E-OS 3.S6E-06 0. 3.S6E-06 7.14E-04 S.04E-06 MNS6 0. 1.10E-09 1.S8E-10 0. 7.86E-10 8.9SE-06 S.12E-OS FESS 1.41E-OS 8.39E-06 2.38E-06 0. 0. 6.21E-05 7.82E-07 FES9 9.69E-06 1.68E-OS 6.77E-06 0. 0. 7.2SE-04 1.77E-05 COS? 0. 4.6SE-07 4.S8E-07 0. 0. 2.71E-04 3.47E-06 C058 0. 8.71E-07 1.306-06 0. 0. S.SSE-04 7.95E-06 C060 0. S.73E-06 8.41 E-06 0. 0. 3.22E-03 2.28E-OS Nl59 1.81 E-OS 5.44E-06 3.10E-06 0. 0. S.48E-OS 6.34E-07 Nl63 2.42E-04 1.466-05 8.29E-06 0. 0. 1.49E-04 1.73E-06 Nl6S 1.71E-09 2.03E-10 8.79E-11 0. 0. S.80E-06 3.58E-OS CU64 0. 1.34E-09 5.53E-10 0. 2.84E-09 6.64E-06 1.07E-OS ZN65 1.38E-OS 4.47E-OS 2.22E-OS 0. 2.32E-OS 4.62E-04 3.67E-05 ZN69M 8.98E-09 1.84E-08 1.67E-09 0. 7.4SE-09 1.91 E-OS 2.92E-OS ZN69 3.85E-11 6.91E-11 S.13E-12 0. 2.87E-11 1.05E-06 9.44E-06 SE79 0. 2.2SE-06 4.20E-07 0. 2.47E-06 2.99E-04 3.46E-06 BR82 0. 0. 9.49E-06 0. 0. 0. 0. BR83 0. 0. 2.72E-07 0. 0. 0. 0. BR84 0. 0. 2.86E-07 0. 0. 0. 0. BR8S 0. 0. 1.46E-08 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 2.SOE-09 0. KR8SM 0. 0. 0. 0. 0. 1.31E-oa 0. KR8S 0. 0. 0. 0. 0. 1.16E-08 0. KR87 0. 0. 0. 0. 0. 6.S9E-08 0. KR88 0. 0. 0. 0. 0. 1.38E-07 0. KR89 0. 0. 0. 0. 0. 8.67E-08 0. RB86 0. 1.36E-04 6.30E-OS 0. 0. 0. 2.17E-06 RB87 0. 7.11 E-OS 2.64E-0S 0. 0. 0. 2.99E-07 RB88 0. 3.98E-07 2.0SE-07 0. 0. 0. 2.42E-07 RB89 0. 2.29E-07 1.47E-07 0. 0. 0. 4.87E-08 SR89 2.84E-04 0. 8.1SE-06 0. 0. 1.4SE-03 4.S7E-OS SR90 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-OS SR91 6.83E-08 0. 2.47E-09 0. 0. 3.76E-OS S.24E-OS SR92 7.50E-09 0. 2.79E-10 0. 0. 1.70E-OS 1.00E-04
- Includes a SO% increase to account for percutaneous transpiration.
Proc NoODCM Attachment 5 Revision 26 Page 2of16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92E-04 7.43E-05 Y91M 2.91E-10 0. 9.90E-12 0. 0. 1.99E-06 1.68E-06 Y91 4.20E-04 0. 1.12E-05 0. 0. 1.75E-03 5.02E-05 Y92 1.17E-08 0. 3.29E-10 0. 0. 1.75E-05 9.04E-05 Y93 1.07E-07 0. 2.91E-09 0. 0. 5.46E-05 1.19E-04 ZR93 2.24E-04 9.51E-05 6.18E-05 0. 3.19E-04 1.37E-03 1.48E-05 ZR95 8.24E-05 1.99E-05 1.45E-05 0. 2.22E-05 1.25E-03 1.55E-05 ZR97 1.07E-07 1.83E-08 8.36E-09 0. 1.85E-08 7.88E-05 1.00E-04 N893M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06 N895 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06 N897 2.44E-10 5.21 E-11 1.BBE-11 0. 4.07E-11 2.37E-06 1.92E-05 M093 0. 6.46E-06 2.22E-07 0. 1.54E-06 3.40E-04 3.76E-06 M099 0. 1.18E-07 2.31E-08 0. 1.89E-07 9.63E-05 3.48E-05 TC99M 9.98E-13 2.06E-12 2.66E-11 0. 2.22E-11 5.79E-07 1.45E-06 TC99 2.09E-07 2.68E-07 8.85E-08 0. 2.49E-06 6.77E-04 7.82E-06 TC101 4.65E-14 5.BBE-14 5.BOE-13 0. 6.99E-13 4.17E-07 6.03E-07 RU103 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15E-05 RU105 8.74E-10 0. 2.93E-10 0. 6.42E-10 1.12E-05 3.46E-05 RU106 6.20E-05 0. 7.77E-06 0. 7.61E-05 8.26E-03 1.17E-04 RH105 8.26E-09 5.41 E-09 3.63E-09 0. 1.50E-08 2.0BE-05 1.37E-05 PD107 0. 4.92E~07 4.11E-08 0. 2.75E-06 6.34E-05 7.33E-07 PD109 0. 3.92E-09 1.05E-09 0. 1.28E-08 1.68E-05 2.85E-05 AG110M 7.13E-06 5.16E-06 3.57E-06 0. 7.BOE-06 2.62E-03 2.36E-05 AG111 3.75E-07 1.45E-07 7.75E-08 0. 3.05E-07 2.06E-04 3.02E-05 CD113M 0. 6.67E-04 2.64E-05 0. 5.BOE-04 1.40E-03 1.65E-05 CD115M 0. 1.73E-04 6.19E-06 0. 9.41E-05 1.47E-03 5.02E-05 8N123 2.09E-04 4.21E-06 7.28E-06 4.27E-06 0. 2.22E-03 4.0BE-05 8N125 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0. 6.43E-04 7.26E-05 8N126 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 1.65E-05 88124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0. 1.89E-03 4.22E-05 88125
- 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0. 1.17E-03 1.05E-05 88126 3.0BE-06 6.01E-08 1.11E-06 2.35E-08 0. 6.BBE-04 5.33E-05 88127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. 1.54E-04 3.78E-05 TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0. 3.19E-04 9.22E-06 TE127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129M 1.01 E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.BBE-05 TE131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 TE133M 6.13E-11 3.59E-11 2.74E-11 5.52E-11 1.72E-10 3.92E-06 1.59E-05 TE134 3.18E-11 2.04E-11 1.68E-11 2.91E-11 9.59E-11 2.93E-06 2.53E-06 1129 2.16E-05 1.59E-05 1.16E-05 1.04E-02 1.BBE-05 0. 2.12E-07 1130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0. 1.42E-06 1131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E~05 0. 7.56E-07
Proc No ODCM Attachment 5 Revision 26 Page 3of16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.21 E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0. 1.36E-06 1133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0. 1.54E-06 1134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0. 9.21E-07 1135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0. 1.31 E-06 XE131M 0. 0. 0. 0. 0. 6.77E-09 0. XE133M 0. 0. 0. 0. 0. 8.89E-09 0. XE133 0. 0. 0. 0. 0. 7.41 E-09 0. XE135M 0. 0. 0. 0. 0. 8.05E-09 0. XE135 0. 0. 0. 0. 0. 1.80E-08 0. XE137 0. 0. 0. 0. 0. 8.30E-08 0. XE138 0. 0. 0. 0. 0. 9.78E-08 0. CS134M 1.32E-07 2.10E-07 1.11E-07 0. 8.50E-08 2.00E-08 1.16E-07 CSt34 2.83E-04 5.02E-04 5.32E-05 0. 1.36E-04 5.69E-05 9.53E-07 CS135 1.00E-04 8.66E-05 4.73E-06 0. 2.58E-05 1.01 E-05 2.18E-07 CS136 3.45E-05 9.61E-05 3.78E-05 0. 4.03E-05 8.40E-06 1.02E-06 CS137 3.92E-04 4.37E-04 3.25E-05 0. 1.23E-04 5.09E-05 9.53E-07 CS138 3.61E-07 5.58E-07 2.84E-07 0. 2.93E-07 4.67E-08 6.26E-07 CS139 2.32E-07 3.03E-07 1.22E-07 0. 1.65E-07 2.53E-08 1.33E-08 BA139 1.06E-09 7.03E-13 3.07E-11 0. 4.23E-13 4.25E-06 3.64E-05 BA140 4.00E-05 4.00E-08 2.07E-06 0. 9.59E-09 1.141:-03 2.74E-05 BA141 1.12E-10 7.70E-14 3.55E-12 0. 4.64E-14 2.12E-06 3.39E-06 BA142 2.84E-11 2.36E-14 1.40E-12 0. 1.36E-14 1.11 E~o6 4.95E-07 LA140 3.61E-07 1.43E-07 3.68E-08 0. 0. 1.20E-04 6.06E-05 LA141 4.85E-09 1.40E-09 2.45E-10 0. 0. 1.22E-05 5.96E-05 LA142 7.36E-10 2.69E-10 6.46E-11 0. 0. 5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 0. 3.75E-06 3.69E-04 1.54E-05 CE143 2.09E-07 1.38E-07 1.58E-08 0. 4.03E-08 8.30E-05 3.55E-05 CE144 2.28E-03 8.65E-04 1.26E-04 0. 3.84E-04 7.03E-03 1.06E-04 PR143 1.00E-05 3.74E-06 4.99E-07 0. 1.41 E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 0. 4.80E-12 1.15E-06 3.06E-06 ND147 5.67E-06 5.81E-06 3.57E-07 0. 2.25E-06 2.30E-04 2.23E-05 PM147 3.91E-04 3.07E-05 1.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 PM148M 5.0QE-05 1.24E-05 9.94E-06 0. 1.45E-05 1.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 0. 5.76E-07 3.20E-04 6.04E-05 PM149 3.10E-07 4.08E-08 1.78E-08 0. 4.96E-08 6.50E-05 3.01E-05 PM151 7.52E-08 1.10E-08 5.55E-09 0. 1.30E-08 3.25E-05 2.58E-05 SM151 3.38E-04 6.45E-05 1.63E-05 0. 5.24E-05 2.98E-04 3.46E-06 SM153 1.53E-07 1.18E-07 9.06E-09 0. 2.47E-08 3.70E-05 1.93E-05 EU152 7.83E-04 1.77E-04 1.72E-04 0. 5.94E-04 1.48E-03 9.88E-06 EU154 2.96E-03 3.46E-04 2.45E-04 0. 1.14E-03 3.05E-03 2.84E-05 EU155 5.97E-04 5.72E-05 3.46E-05 0. 1.58E-04 5.20E-04 5.19E-05 EU156 1.56E-05 9.59E-06 1.54E-06 0. 4.48E-06 6.12E-04 4.14E-05 TB160 1.12E-04 0. 1.40E-05 0. 3.20E-05 1.11 E-03 2.14E-05 H0166M 1.45E-03 3.07E-04 2.51E-04 0. 4.22E-04 2.05E-03 1.65E-05 W181 4.86E-08 1.46E-08 1.67E-09 0. 0. 1.33E-05 2.63E-07 W185 1.57E-06 4.83E-07 5.58E-08 0. 0. 4.48E-04 1.12E-05 W187 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05
Proc No ODCM Attachment 5 Revision 26 Page4of16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1.76E-01 3.79E-05 81210 0. 1.33E-05 1.18E-06 0. 1.03E-04 9.96E-03 3.27E-05 P0210 2.98E-03 5.63E-03 7.12E-04 0. 1.30E-02 2.40E-01 4.36E-05 RN222 0. 0. 0. 0. 0. 9.88E-06 0. RA223 1.56E-03 2.26E-06 3.12E-04 0. 4.16E-05 2.25E-01 3.04E-04 RA224 1.77E-04 4.00E-07 3.54E-05 0. 7.30E-06 7.91E-02 3.42E-04 RA225 2.57E-03 2.88E-06
- 5.13E-04 0. 5.31E-05 2.57E-01 2.87E-04 RA226 2.48E-01 1.46E-05 2.05E-01 0. 2.94E-04 7.83E-01 3.05E-04 RA228 1.60E-01 7.61E-06 1.80E-01 0. 1.53E-04 1.09E-OO 5.19E-05 AC225 3.69E-03 4.72E-03 2.48E.04 0. 3.49E-04 1.96E-01 2.71E-04 AC227 5.29E+OO 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+OO 5.27E-05 TH227 1.82E-03 3.03E-05 5.24E-05 0. 1.13E-04 3.27E*01 3.53E-04 TH228 8.46E-01 1.10E-02 2.86E-02 0. 5.61E-02 4.65E+OO 3.62E-04 TH229 1.34E+01 1.82E-01 6.62E-01 0. 8.99E-01 1.22E+01 3.29E-04 TH230 3.46E+OO 1.79E-01 9.65E-02 0. 8.82E-01 2.18E+OO 3.87E-05 TH232 3.86E+OO 1.53E-01 2.29E-01 0. 7.54E-01 2.09E+OO 3.29E-05 TH234 1.33E-05 7.17E-07 3.84E-07 0. 2.70E-06 .1.62E-03 7.40E-05 PA231 9.10E+OO 3.00E-01 3.62E-01 0. 1.62E+OO 3.85E-01 4.61E-05 PA233 6.84E-06 1.32E-06 1.19E-06 0. 3.68E-06 2.19E-04 9.04E-06 U232 2.57E-01 0. 2.13E-02 0. 2.40E-02 1.49E+OO 4.36E-05 U233 5.44E-02 0. 3.83E-03 0. 1.09E-02 3.56E-01 4.03EM05 U234 5.22E-02 0. 3.75E-03 0. 1.07E-02 3.49E-01 3.95E-05 U235 5.01E-02 0. 3.52EM03 0. 1.01E-02 . 3.28E-01 5.02E-05 U236 5.01E-02 0. 3.60E-03 0. 1.03E-02 3.35E-01 3.71E-05 U237 3.25E-07 0. 8.65E-08 0. 8.08E-07 9.13E-05 1.31 E-05 U238 4.79E-02 0. 3.29E-03 0. 9.40E-03 3.06E-01 3.54E-05 NP237 3.03E+OO 2.32E-01 1.26E-01 0: 7.69E-01 3.49E-01 5.10E-05 NP238 2.67E-06 6.73E-08 4.16E-08 0. 1.47E-07 9.19E-05 2.58E-05 NP239 2.65E-07 2.37E-08 1.34E-08 0. 4.73E-08 4.25E-05 1.78E-05 PU238 5.02E+OO 6.33E-01 1.27E-01 0. 4.64E-01 9.03E-01 4.69E-05 PU239 5.50E+OO 6.72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05 PU240 6.49E+OO 6.71E-01 1.34E-01 0. 4.94E-01 8.47E-01 4.36E-05 PU241 1.55E-01 6.69E-03 3.11E-03 0. 1.15E-02 7.62E-04 8.97EM07 PU242 5.09E+OO 6.47E-01 1.29E-01 0. 4.77E-01 8.15E-01 4.20E-05 PU244 5.95E+OO 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05 AM241 1.84E+OO 8.44E-01 1.31E-01 0. 7.94E-01 4.06E-01 4.78E-05 AM242M 1.90E+OO 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.01E-05 AM243 1.82E+OO 8.10E-01 1.27E-01 0. 7.72E-01 3.85E-01 5.60E-05 CM242 8.58E-02 7.44E-02 5.70E-03 0. 1.69E-02 2.97E-01 5.10E-05 CM243 1.73E+OO 7.94E-01 1.06E-01 0. 3.91 E-01 4.24E-01 5.02E-05 CM244 1.43E+00 7.04E-01 8.89E-02 0. 3.21 E-01 4.08E-01 4.86E-05 CM245 2.26E+OO 8.80E-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05 CM246 2.24E+OO 8.79E-01 1.36E-01 0. 5.23E-01 3.99E-01 4.45E-05 CM247 2.18E+OO 8.64E-01 1.33E-01 0. 5.15E-01 3.92E-01 5.85E-05 CM248 1.82E+01 7.12E+OO 1.10E+OO 0. 4.24E+OO 3.23E+OO 9.43E-04 CF292 4.26E+OO 0. 1.01E-01 0. 0. 1.37E+OO 1.85E-04
Proc No ODCM Attachment 5 Revision 26 Page 5of16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 BE10 8.43E-04 9.83E-OS 2.12E~os 0. 0. 7.41E-04 1.72E-OS C14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 N13 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 F18 1.88E-06 0. 1.~SE-07 0. 0. 0. 3.37E-07 NA22 4.41E-OS 4.41 E-OS 4.41E-OS 4.41E-OS 4.41E-OS 4.41 E-OS 4.41E-OS NA24 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 P32 7.04E-04 3.09E-OS 2.67E-OS 0. 0. 0. 1.14E-OS AR39 0. 0. 0. 0. 0. 4.89E-09 0. AR41 0. 0. 0. 0. 0. 1.68E-08 0. CA41 7.06E-OS 0. 7.70E-06 0. 0. 7.21E-02 2.94E-07 SC46 1.97E-04 2.70E-04 1.04E-04 0. 2.39E-04 0. 2.4SE-OS CRS1 0. 0 .. 4.17E-08 2.31E-08 6.S7E-09 4.S9E-06 2.93E-07 MNS4 0. 1.16E-OS 2.S7E-06 0. 2.71E-06 4.26E-04 6.19E-06 MNS6 0. 4.48E-10 8.43E-11 0. 4.S2E-10 3.SSE-06 3.33E-OS FESS 1.28E-OS 6.BOE-06 2.10E-06 0. 0. 3.00E-OS 7.7SE-07 FES9 S.S9E-06 9.04E-06 4.S1E-06 0. 0. 3.43E-04 1.91 E-OS COS? 0. 2.44E-07 2.88E-07 0. 0. 1.37E-04 3.SBE-06 COSS 0. 4.79E-07 8.SSE-07 0. 0. 2.99E-04 9.29E-06 C060 0. 3.SSE-06 6.12E-06 b. 0. 1.91 E-03 2.60E-OS NIS9 1.66E-OS 4.67E-06 2.83E-06 0. 0. 2.73E-OS 6.29E-07 Nl63 2.22E-04 1.2SE-OS 7.S6E-06 0. 0. 7.43E-OS 1.71E-06 Nl6S 8.0BE-10 7.99E-11 4.44E-11 0. 0. 2.21E-06 2.27E-OS CU64 0. S.39E-10 2.90E-10 0. 1.63E-09 2.S9E-06 9.92E-06 ZN65 1.1SE-OS 3.06E-OS 1.90E-OS 0. 1.93E-OS 2.69E-04 4.41E-06 ZN69M 4.26E-09 7.28E-09 8.S9E-10 0. 4.22E-09 7.36E-06 2.71E-OS ZN69 1.81E-11 2.61E-11 2.41E-12 0. 1.SBE-11 3.84E-07 2.7SE-06
- SE79 0. 1.23E-06 2.60E-07 0. 1.71E-06 1.49E-04 3.43E-06 BR82 0. 0. S.66E-06 0. 0. 0. 0.
BR83 0. 0. 1.28E-07 0. 0. 0. 0. BR84 0. 0. 1.48E-07 0. 0. 0. 0. BR8S 0. 0. 6.84E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 1.22E-09 0. KR8SM o .. 0. 0. 0. 0. 6.SBE-09 0. KR8S 0. 0. 0. 0. 0. S.66E-09 0. KR87 0. 0. 0. 0. 0. 3.38E-08 0. KR88 0. 0. 0. 0. 0. 6.99E-08 0. KR89 0. 0. 0. 0. 0. 4.SSE-08 0. RB86 0. S.36E-OS 3.09E-OS 0. 0. 0. 2.16E-06 RB87 0. 3.16E-OS 1.37E-OS 0. 0. 0. 2.96E-07 RB88 0. 1.o2E-07 9.90E-08 0. 0. 0. 4.66E-09 RB89 0. 9.33E-08 7.83E-08 0. 0. 0. S.11E-10 SR89 1.62E-04 0. 4.66E-06 0. 0. S.83E-04 4.S2E-OS SR90 2.73E-02 0. 1.74E-03 0. o, 3.99E-03 9.28E-OS SR91 3.28E-08 0. 1.24E-09 0. 0. 1.44E-OS 4.70E-OS SR92 3.S4E-09 0. 1.42E-10 0. 0. 6.49E-06 6.SSE-OS
*Includes a SO% increase to account for percutaneous transpiration.
Proc No ODCM Attachment 5 Revision 26 Page 6of16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 1.11 E-06 0. 2.99E-08 0. 0. 7.07E-05 7.24E-05 Y91M 1.37E-10 0. 4.98E-12 0. 0. 7.606-07 4.64E-07 Y91 2.47E-04 0. 6.59E-06 o. 0. 7.10E-04 4.97E-05 Y92 5.50E-09 0. 1.57E-10 0. 0. 6.46E-06 6.46E-05 Y93 5.04E-08 0. 1.38E-09 0. 0. 2.01E-05 1.05E-04 ZR93 2.07E-04 7.80E-05 5.55E-05 0. 3.00E-04 7.10E-04 1.47E-05 ZR95 5.13E-05 1.13E-05 1.00E-05 0. 1.61E-05 6.03E-04 1.65E-05 ZR97 5.07E-08 7.34E-09 4.32E-09 0. 1.05E-08 3.06E-05 9.49E-05 NB93M 1.27E-04 3.17E-05 1.04E-05 0. 3.44E-05 1.04E-04 2.45E-06 NB95 6.35E-06 2.48E-06 1.77E-06 0. 2.33E-06 1.66E-04 1.00E-05 NB97 1.16E-10 2.08E-11 9.74E-12 0. 2.31 E-11 9.23E-07 7.52E-06 M093 0. 3.76E-06 1.35E-07 0. 1.06E-06 1.70E-04 3.78E-06 M099 0. 4.66E-08 1.15E-08 0. 1.06E-07 3.66E-05 3.42E-05 TC99M 4.81E-13 9.41E-13 1.56E-11 0. 1.37E-11 2.57E-07 1.30E-06 TC99 1.34E-07 1.49E-07 5.35E-08 0. 1.75E-06 3.37E-04 7.75E-06 TC101 2.19E-14 2.30E-14 2.91E-13 0. 3.92E-13 1.58E-07 4.41E-09 RU103 7.55E-07 0. 2.90E-07 0. 1.90E-06 1.79E-04 1.21 E-05 RU105 4.13E-10 0. 1.50E-10 0. 3.63E-10 4.30E-06 2.69E-05 RU106 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 1.16E-04 RH105 3.91E-09 2.10E-09 1.79E-09 0. 8.39E-09 7.82E-06 1.33E-05 PD107 0. 2.65E-07 2.51E-08 0. 1.97E-06 3.16E-05 7.26E-07 PD109 0. 1.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05 AG110M 4.56E-06 3.08E-06 2.47E-06 0. 5.74E-06 1.48E-03 2.71E-05 AG111 1.81 E-07 5.68E-08 3.75E-08 0. 1.71 E-07 7.73E-05 2.98E-05 CD113M 0. 4.93E-04 2.12E-05 0. 5.13E-04 6.94E-04 1.63E-05 CD115M 0. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05 SN123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 0. 9.59E-04 4.05E-05 SN125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05 SN126 6.23E-04 1.04E-05 2.36E-05 2.84E-06 0. 3.02E-03 1.63E-05 SB124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0. 8.76E-04 4.43E-05 SB125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0. 6.27E-04 1.09E-05 SB126 1.72E-06 2.62E-08 6.16E-07 1.00E-08 0. 2.86E-04 5.67E-05 SB127 1.36E-07 2.09E-09 4.70E-08 1.51 E-09 0. 6.17E-05 3.826-05 TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 TE127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71E-06 1.52E-05 TE129M 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 TE133M 2.93E-11 1.51E-11 1.50E-11 2.32E-11 1.01E-10 1.60E-06 4.77E-06 TE134 1.53E-11 8.81E-12 9.40E-12 1.24E-11 5.71 E-11 1.23E-06 4.87E-07 1129 1.05E-05 6.40E-06 5.71E-06 4.28E-03 1.08E-05 0. 2.15E-07 1130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0. 1.38E-06 1131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07
Proc No ODCM Attachment 5 Revision 26 Page 7of16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-07 1133 4.48E-06 5.49E-06 2.0BE-06 1.04E-03 9.13E-06 0. 1.48E-06 1134 3.17E-07 5.84E~07 2.69E-07 1.37E-05 8.92E-07 0. 2.58E-07 1135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0. 1.20E-06 XE131M 0. 0. 0. 0. 0. 3.30E-09 0. XE133M 0. 0. 0. 0. 0. 4.36E-09 0. XE133 0. 0. 0. 0. 0. 3.66E-09 0. XE135M 0. 0. 0. 0. 0. 4.48E-09 0. XE135 0. o. 0. 0. 0. 9.09E-09 0. XE137 0. 0. 0. 0: 0. 4.07E-08 0. XE138 0. 0. 0. 0. 0. 5.17E-08 0. CS134M 6.33E~oa 8.92E-08 6.12E-08 0. 4.94E-08 8.35E-09 7.92E-08 CS134 1,76E-04 2.74E-04 6.07E-05 0. 8.93E-05 3.27E-05 1.04E-06 CS135 6.23E-05 4.13E-05 4.45E-06 0. 1.53E-05 5.22E-06 2.17E-07 CS136 1.76E-05 4.62E-05 3.14E-05 0. 2.58E-05 3.93E-06 1.13E-06 CS137 2.45E-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81E-05 9.78E-07 CS138 1.71 E-07 2.27E-07 1.50E-07 0. 1.68E-07 1.84E-08 7.29E-08 CS139 1.09E-07 1.15E-07 5.80E-08 0. 9.08E-08 9.36E-09 7.23E-12 BA139 4.98E-10 2.66E-13 1.45E-11 0. 2.33E-13 1.56E-06 1.56E-05 BA140 2.00E-05 1.75E-08 1.17E-06 0. 5.71E-09 4.71E-04 2.75E-05 BA141 5.29E-11 2.95E-14 1.72E-12 0. 2.56E-14 7.89E-07 7.44E-08 BA142 1.35E-11 9.73E-15 7.54E-13 0. 7.87E-15 4.44E-07 7.41E-10 LA140 1.74E-07 6.0BE-08 2.04E-08 0. 0. 4.94E-05 6.10E-05 LA141 2.28E-09 5.31E-10 1.15E-10 0. 0. 4.48E-06 4.37E-05 LA142 3.50E-10 1.11E-10 3.49E-11 0. 0. 2.35E-06 2.05E-05 CE141 1.06E-05 5.28E-06 7.83E-07 0. 2.31E-06 1.47E-04 1.53E-05 CE143 9.89E-08 5.37E-08 7.77E-09 0. 2.26E-08 3.12E-05 3.44E-05 CE144 1.83E-03 5.72E-04 9.77E-05 o: 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.11E-07 1.17E-04 2.63E-05 PR144 1.61E-11 4.99E-12 8.10E-13 0. 2.64E-12 4.23E-07 5.32E-08 ND147 2.92E-06 2.36E-06 1.84E-07 0. 1.30E-06 8.87E-05 2.22E-Q5 PM147 3.52E-04 2.52E-05 1.36E-05 0. 4.45E-05 2.20E-04 5.70E-06 PM148M 3.31E-05 6.55E-06 6.55E-06 0. 9.74E-06 5.72E-04 3.58E-05 PM148 1.61E-06 1.94E-07 1.25E-07 0. 3.30E-07 1.24E-04 6.01E-05 PM149 1.47E-07 1.56E-08 8.45E-09 0. 2.75E-08 2.40E-05 2.92E-05 PM151 3.57E-08 4.33E-09 2.82E-09 0. 7.35E-09 1.24E-05 2.50E-05 SM151 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06 SM153 7.24E-08 4.51E-08 4.35E-09 0. 1.37E-08 1.37E~o5 1.87E-05 EU152 7.42E-04 1.37E-04 1.61 E-04 0. 5.nE-04 9.00E-04 1.14E-05 EU154 2.74E-03 2.49E-04 2.27E-04 0. 1.09E-03 1.66E-03 2.98E-05 EU155 5.60E-04 4.05E-05 3.18E-05 0. 1.51E-04 2.79E-04 5.39E-05 EU156 7.89E-06 4.23E-06 8.75E-07 0. 2.72E-06 2.54E-04 4.24E-05 TB160 7.79E-05 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05 H0166M 1.34E-03 2.81E-04 2.37E-04 0. 4.01E-04 1.13E-03 1.63E-05 W181 2.66E-08 6.52E-09 8.99E-10 0. 0. 5.71E-06 2.61E-07 W185 8.31E-07 2.08E-07 2.91E-08 0. 0. 1.86E-04 1.11 E-05 W187 4.41E-09 2.61E-09 1.17E-09 0. 0. 1.11 E-05 2.46E-05
Proc No ODCM Attachment 5 Revision 26 Page 8of16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROIO KIDNEY LUNG GI-LLI PB210 8.03E-02 1.85E-02 3.18E-03 0. 6.31E-02 8.74E-02 3.75E-05 81210 0. 5.11E-06 5.65E-07 0. 5.76E-05 3.70E-03 3.21E-05 P0210 1.70E-03 2.76E-03 4.09E-04 0. 8.85E-03 1.05E-01 4.32E-05 RN222 0. 0. 0. 0. 0. 4.82E-06 0. RA223 7.69E-04 8.89E-07 1.54E-04 0. 2.36E-05 8.48E-02 3.00E-04 RA224 8.44E-05 1.53E-07 1.69E-05 0. 4.06E*06 2.92E-02 3.34E-04 RA225 1.28E-03 1.14E-06 2.56E-04 0. 3.02E-05 9.74E-02 2.84E-04 RA226 2.34E-01 7.66E-06 1.92E-01 0. 2.03E-04 3.90E-01 3.02E-04 RA228 1.49E-01 3.94E-06 1.68E-01 0. 1.04E-04 5.37E-01 5.14E-05 AC225 1.81E-03 1.87E-03 1.21 E-04 0. 1.99E-04 7.37E-02 2.67E-04 AC227 4.96E+OO 8.05E-01 3.07E-01 0. 1.77E-01 8.04E-01 5.22E-05 TH227 9.24E-04 1.26E-05 2.67E-05 0. 6.67E-05 1.26E-01 3.49E-04 TH228 8.06E-01 1.04E-02 2.72E-02 0. 5.41E-02 3.34E+OO 3.59E-04 TH229 1.28E+01 1.76E-01 6.31 E-01 0. 8.68E-01 1.04E+01 3.27E-04 TH230 3.30E+OO 1.73E-01 9.20E-02 0. 8.52E-01 1.85E+OO 3.84E-05 TH232 3.68E+OO 1.47E-01 1.28E-01 0. 7.28E-01 1.77E+OO 3.27E-05 TH234 6.94E-06 3.07E-07 2.00E-07 0. 1.62E-06 6.31E-04 7.32E-05 PA231 8.62E+OO 2.86E-01 3.43E-01 0. 1.56E+OO 1.92E-01 4.57E-05 PA233 4.14E-06 6.48E-07 7.25E-07 0. 2.38E-06 9.77E-05 8.95E-06 U232 2.19E-01 0. 1.56E-02 0. 1.67E-02 7.42E-01 4.33E-05 U233 4.64E-02 0. 2.82E-03 0. 7.62E-03 1.77E-01 4.00E-05 U234 4.46E-02 0. 2.76E-03 0. 7.47E-03 1.74E-01 3.92E-05 U235 4.27E-02 0. 2.59E-03 0. 7.01E-03 1.63E-01 4.98E-05 U236 4.27E-02 0. 2.65E-03 0. 7.16E-03 1.67E-01 3.67E-05 U237 1.57E-07 0. 4.17E-08 0. 4.53E-07 3.40E-05 1.29E-05 U238 4.09E-02 0. 2.42E-03 0. 6.55E-03 1.53E-01 3.51E-05 NP237 2.88E+OO 2.21 E-01 1.19E-01 0. 7.41E-01 1.74E-01 5.06E-05 NP238 1.26E-06 2.56E-08 1.97E-08 0. 8.16E-08 3.39E-05 2.50E-05 NP239 1.26E-07 9.04E-09 6.35E-09 0. 2.63E-08 1.57E-05 1.73E-05 PU238 4.77E+OO 6.05E-01 1.21 E-01 0. 4.47E-01 6.0BE-01 4.65E-05 PU239 5.24E+OO 6.44E-01 1.28E-01 0. 4.78E-01 5.72E-01 4.24E-05 PU240 5.23E+OO 6.436-01 1.27E-01 0. 4.77E-01 5.71E-01 4.33E-05 PU241 1.46E-01 6.33E-03 2.93E-03 0. 1.10E-02 5.06E-04 8.90E~07 PU242 4.85E+OO 6.20E-01 1.23E-01 0. 4.60E-01 5.50E-01 4.16E-05 PU244 5.67E+OO 7.10E-01 1.41 E-01 0. 5.27E-01 6.30E-01 6.20E-05 AM241 1.74E+OO 7.85E-01 1.24E-01 0. 7.63E-01 2.02E-01 4.73E-05 AM242M 1.79E+OO 7.65E-01 1.27E-01 0. 7.71E-01 8.14E-02 5.96E-05 AM243 1.72E+OO 7.53E-01 1.20E-01 0. 7.42E-01 1.92E-01 5.55E-05 CM242 6.33E-02 4.84E-02 4.20E-03 0. 1.34E-02 1.31E-01 5.06E-05 CM243 1.61E+OO 7.33E-01 9.95E-02 0. 3.74E-01 2.10E-01 4.98E-05 CM244 1.33E+OO 6.48E-01 8.31E-02 0. 3.06E-01 2.02E-01 4.82E-05 CM245 2.14E+OO 8.16E-01 1.28E-'01 0. 5.03E-01 1.95E-01 4.49E-05 CM246 2.13E+OO 8.15E-01 1.28E-01 0. 5.03E-01 1.99E-01 4.41E-05 CM247 2.07E+OO 8.02E-01 1.26E-01 0. 4.95E-01 1.95E-01 5.BOE-05 CM248 1.72E+01 6.61E+OO 1.04E+OO 0. 4.08E+OO 1.61E+OO 9.35E-04 CF252 3.92E+OO 0. 9.33E-02 0. 0. 6.62E-01 1.84E-04
Proc NoODCM Attachment 5 Revision 26 Page 9of16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 BE10 2.78E-04 4.33E-OS 7.09E-06 0. 0. 3.84E-04 1.77E-OS C14 3.2SE-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 N13 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 F18 6.S2E-07 0. 7.10E-08 0. 0. 0. 3.89E-08 NA22 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS NA24 1.72E-06 1.72E~06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P32 2.36E-04 1.37E-OS 8.9SE-06 0. 0. 0. 1.16E-OS AR39 0. 0. 0. 0. 0. 4.00E-09 0. AR41 0. 0. 0. 0. 0. 1.44E-08 0. CA41 4.0SE-OS 0. 4.38E-06 0. 0. 1.01E-01 3.03E-07 SC46 7.24E-OS 1.41E-04 4.18E-OS 0. 1.3SE-04 0. 2.98E-OS CRS1 0. 0. 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.7SE-07 MNS4 0. 6.39E-06 1.0SE-06 0. 1.S9E-06 2.48E-04 8.3SE-06 MNS6 0. 2.12E-10 3.1SE-11 0. 2.24F-10 1.90E-06 7.18E-06 FESS 4.18E-06 2.98E-06 6.93E-07 0. 0. 1.SSE-OS 7.99E-07 FES9 1.99E-06 4.62E-06 1.79E-06 0. 0. 1.91 E-04 2.23E-OS COS7 0. 1.18E-07 1.1SE-07 0. 0. 7.33E-OS 3.93E-06 COSS 0. 2.S9E-07 3.47E-07 0. 0. 1.68E-04 1.19E-OS C060 0. 1.89E-06 2.48E-06 0. 0. 1.09E-03 3.24E-OS NIS9 S.44E-06 2.02E-06 9.24E-07 0. 0. 1.41E-OS 6.48E-07 Nl63 7.2SE-OS S.43E-06 2.47E-06 0. 0. 3.84E-05 1.77E-06 Nl6S 2.73E-10 3.66E-11 1.S9E-11 0. 0. 1.17E-06 4.S9E-06 CU64 0. 2.S4E-10 1.06E-10 0. 8.01E-10 1.39E-06 7.68E-06 ZN6S 4.82E-06 1.67E-OS 7.BOE-06 0. 1.08E-OS 1.SSE-04 S.83E-06 ZN69M 1.44E-09 3.39E-09 3.11E-10 0. 2.06E-09 3.92E-06 2.14E-OS ZN69 6.04E-12 1.1SE-11 8.07E-13 0. 7.S3E-12 1.98E-07 3.S6E-08 SE79 0. S.43E-07 8.71E-08 0. 8.13E-07 7.71E-OS 3.S3E-06 BR82 0. 0. 2.28E-06 0. 0. 0. 0. BR83 0. 0. 4.30E-08 0. 0. 0. 0. BR84 0. 0. S.41E-08 0. 0. 0. 0. BR8S 0. 0. 2.29E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 9.97E-10 0. KR8SM 0. 0. 0. 0. 0. S.46E-09 0. KR8S 0. 0. 0. 0. 0. 4.63E-09 0. KR87 0. 0. 0. 0. 0. 2.82E-08 0. KR88 0. 0. 0. 0. 0. S.81E-08 0. KR89 0. 0. 0. 0. 0. 3.BSE-08 0. RB86 0. 2.38E-OS 1.0SE-OS 0. 0. 0. 2.21E-06 RB87 0. 1.40E-OS 4.SBE-06 0. 0. 0. 3.0SE-07 RB88 0. 6.82E-08 3.40E-08 0. 0. 0. 3.6SE-1S RB89 0. 4.40E-08 2.91E-08 0. 0. 0. 4.22E-17 SR89 S.43E-OS 0. 1.S6E-06 o. 0. 3.02E-04 4.64E-OS SR90 1.3SE-02 0. 8.3SE-04 0. 0. 2.06E-03 9.S6E-OS SR91 1.10E-08 0. 4.39E-10 0. 0. . 7.S9E-06 3.24E-OS SR92 1.19E-09 0. S.OBE-11 0. 0. 3.43E-06 1.49E-OS
- Includes a SO% increase to account for percutaneous transpiration.
Proc NoODCM Attachment 5 Revision 26 Page 10of16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 3.73E-07 0. 1.00E-08 0. 0. 3.66E-05 6.99E-05 Y91M 4.63E-11 0. 1.77E-12 0. 0. 4.00E-07 3.77E-09 Y91 8.26E-05 0. 2.21E-06 0. 0. 3.67E-04 5.11E-05 Y92 1.84E-09 0. 5.36E-11 0. 0. 3.35E-06 2.06E-05 Y93 1.69E-08 0. 4.65E-10 0. 0. 1.04E-05 7.24E-05 ZR93 6.83E-05 3.38E-05 1.84E-05 0. 1.16E-04 3.67E-04 1.60E-05 ZR95 1.82E-05 5.73E-06 3.94E-06 0. 8.42E-06 3.36E-04 1.86E-05 ZR97 1.72E-08 3.40E-09 1.57E-09 0. 5.15E-09 1.62E-05 7.88E-05 N893M 4.14E-05 1.36E-05 3.41E-06 0. 1.59E-05 5.36E-05 2.52E-06 N895 2.32E-06 1.29E-06 7.08E-07 0. 1.25E-06 9.39E-05 1.21 E-05 N897 3.92E-11 9.72E-12 3.55E-12 0. 1.14E-11 4.91E-07 2.71E-07 M093 0. 1.66E-06 4.52E-08 0. 5.06E-07 8.81E-05 3.99E-06 M099 0. 2.11 E-08 4.03E-09 0. 5.14E-08 1.92E-05 3.36E-05 TC99M 1.73E-13 4.83E-13 6.24E-12 0. 7.20E-12 1.44E-07 7.66E-07 TC99 4.48E-08 6.58E-08 1.79E-08 0. 8.35E-07 1.74E-04 7.99E-06 TC101 7.40E-15 1.05E-14 1.03E-13 0. 1.90E-13 8.34E-08 1.09E-16 RU103 2.63E-07 0. 1.12E-07 0. 9.29E-07 9.79E-05 1.36E-05 RU105 1.40E-10 0. 5.42E-11 0. 1.76E-10 2.27E-06 1.13E-05 RU106 1.23E-05 0. 1.55E-06 0. 2.38E-05 2.01E-03 1.20E-04 RH105 1.32E-09 9.48E-10 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05 PD107 0. 1.17E-07 8.39E-09 0. 9.39E-07 1.63E-05 7.49E-07 PD109 0. 6.56E-10 1.66E-10 0. 3.36E"09 3.19E-06 1.96E-05 AG110M 1.73E-06 1.64E-06 9.99E-07 0. 3.13E-06 8.44E-04 3.41E-05 AG111 6.07E-08 2.52E-08 1.26E-08 0. 8.17E-08 4.00E-05 3.00E-05 CD113M 0. 2.17E-04 7.10E-06 0. 2.43E-04 3.59E-04 1.68E-05 CD115M 0. 3.48E-05 1.14E-oe 0. 2.82E-05 3.03E-04 5.10E-05 8N123 4.31E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05 8N125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05 8N126 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1.72E-03 1.68E-05 88124 5.38E-06 9.92E-OB 2.10E-06 1.22E-08 0. 4.81E-04 4.98E-05 88125 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 0. 3.42E-04 1.24E-05 88126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.01E-05 88127 4.64E-08 9.92E-10 1.75E-08 5.21 E-10 0. 3.31E-05 3.94E-05 TE125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0. 6.70E-05 9.38E-06 TE127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01 E-05 TE129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 TE133M 1.01E-11 7.33E-12 5.71E-12 8.18E-12 5.07E-11 8.71E-07 1.23E-07 TE134 5.31E-12 4.35E-12 3.64E~12 4.46E-12 2.91E-11 6.75E-07 1.37E-09 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07 1130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0. 1.14E-06 1131 4.43E-06 6.14E-06 3.306-06 1.83E-03 1.05E-05 0. 8.11 E-07
Proc NoODCM Attachment 5 Revision 26 Page 11of16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. 1.59E-07 1133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E~06 0. 1.29E-06 1134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0. 2.55E-09 1135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0. 8.69E-07 XE131M 0. 0. 0. 0. 0. 2.70E-09 0. XE133M 0. 0. 0. 0. 0. 3.59E-09 0. XE133 0. 0. 0. 0. 0. 2.99E-09 0. XE135M 0. 0. 0. 0. 0. 3.88E-09 0. XE135 0. 0. 0. 0. 0. 7.55E-09 0. XE137 0. 0. 0. 0. 0. 3.33E-08 0. XE138 0. 0. 0. 0. 0. 4.38E-08 0. CS134M 2.20E-08 4.35E-08 2.35E~08 0. 2.54E-08 4.56E-09 2.02E-08 CS134 6.28E-05 1.41E-04 6.86E~05 0. 4.69E-05 1.83E-05 1.22E-06 CS135 2.08E-05 1.82E-05 4.47E-06 0. 7.30E-06 2.70E-06 2.23E-07 CS136 6.44E-06 2.42E-05 1.71E-05 0. 1.38E-05 2.22E-06 1.36E-06 CS137 8.38E-05 1.06E-04 3.89E-05 0. 3.80E-05 1.51 E-05 1.06E-06 CS138 5.82E-08 1.07E-07 5.58E-08 0. 8.28E-08 9.84E-09 3.38E-11 CS139 3.65E-08 5.12E-08 1.97E-08 0. 4.34E-08 4.86E-09 1.66E-23 BA139 1.67E-10 1.18E-13 4.87E-12 0. 1.11E-13 8.08E-07 8.06E-07 BA140 6.84E-06 . 8.38E-09 4.4.0E-07 0. 2.85E-09 2.54E-04 2.86E-05 BA141 1.78E-11 1.32E-14 5.93E-13 0. 1.23E-14 4.11E-07 9.33E-14 BA142 4.62E-12 4.63E-15 2.84E-13 0. 3.92E-15 2.39E-07 5.99E-20 LA140 5.99E-08 2.95E-08 7.82E-09 0. 0. 2.68E-05 6.09E-05 LA141 7.63E-10 2.35E-10 3.87E-11 0. 0. 2.31E-06 1.54E-05 LA142 1.20E-10 5.31E-11 1.32E-11 0. 0. 1.27E-06 1.50E-06 CE141 3.55E-06 2.37E-06 2.71E-07 0. 1.11E-06 7.67E-05 1.58E-05 CE143 3.32E-08 2.42E-08 2.70E-09 0. 1.08E-08 1.63E-05 3.19E-05 CE144 6.11E-04 2.53E-04 3.28E-05 0. 1.51 E-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 0. 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E~13 0. 1.26E-12 2.19E-07 2.94E-14 ND147 9.83E-07 1.07E-06 6.41E-08 0. 6.28E-07 4.65E-05 2.28E-05 PM147 1.15E-04 1.10E-05 4.50E-06 0. 2.10E-05 1.14E-04 5.87E-06 PM148M 1.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4.10E-05 PM148 5.44E-07 8.88E-08 4.48E-08 0. 1.60E-07 6.52E-05 6.14E-05 PM149 4.91E-08 6.89E-09 2.84E-09 0. 1.31 E-08 1.24E-05 2.79E-05 PM151 1.20E-08 1.99E-09 1.01E-09 0. 3.57E-09 6.56E-06 2.27E-05 SM151 1.07E-:04 2.10E-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.01E-08 1.47E-09 0. 6.56E-09 7.11 E-06 1.77E-05 EU152 2.96E-04 7.19E-05 6.30E-05 0. 3.34E-04 5.01E-04 1.35E-05 EU154 9.43E-04 1.23E-04 8.60E-05 0. 5.44E-04 9.12E-04 3.34E-05 EU155 2.00E-04 1.96E-05 1.21E-05 0. 7.65E-05 1.51 E-03 5.97E-05 EU156 2.70E-06 2.03E-06 3.30E-07 0. 1.36E-06 1.37E-04 4.56E-05 TB160 3.04E-05 0. 3.79E-06 0. 1.20E-05 2.97E-04 2.60E-05 H0166M 4.40E-04 1.36E-04 9.87E-05 0. 2.00E-04 6.24E-04 1.68E-05 W181 8.90E-09 2.88E-09 3.01E-10 o, 0. 2.95E-06 2.69E-07 W185 2.78E-07 9.17E-08 9.73E-09 0. 0. 9.60E-05 1.14E-05 W187 1.50E-09 1.22E-09 4.29E-10 0. 0. 5.92E-06 2.21E-05
Proc No ODCM Attachment 5 Revision 26 Page 12of16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 3.09E-02 8.28E-03 1.0?E-03 0. 2.95E-02 4.52E-02 3.87E-05 81210 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91E-03 3.19E-05 P0210 5.68E-04 1.22E-03 1.37E-04 0. 4.21 E-03 5.41E-02 4.45E-05 RN222 0. 0. 0. 0. 0. 3.94E-06 0. RA223 2.57E-04 3.93E-07 5.14E-05 0. 1.12E-05 4.39E-02 3.04E-04 RA224 2.83E-05 6.77E-08 5.65E-06 0. 1.93E-06 1.51 E-02 3.29E-04 RA225 4.28E-04 5.04E-07 8.56E-05 0. 1.44E-05 5.04E-02 2.89E-04 RA226 1.33E-01 3.38E-06 9.87E-02 0. 9.67E-05 2.02E-01 3.11E-04 RA228 5.34E-02 1.74E-06 5.88E-02 0. 4.97E-05 2.78E-01 5.30E~05 AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.81E-02 2.?0E-04 AC227 2.49E+OO 3.69E-01 1.48E-01 0. 1.0?E-01 4.16E-01 5.38E-05 TH227 3.09E-04 5.56E-06 8.93E-06 0. 3.18E-05 6.50E-02 3.57E-04 TH228 2.60E-01 4.37E-03 8.78E-03 0. 2.45E-02 1.69E+OO 3.?0E-04 TH229 9.06E+OO 1.36E-01 4.45E-01 0. 6.67E-01 5.05E+OO 3.36E-04 TH230 2.34E+OO 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05 TH232 2.61E+OO 1.14E-01 9.21E-02 0. 5.60E-01 8.60E-01 3.36E-05 TH234 2.32E-06 1.35E-07 6.71E-08 0. 7.73E-07 3.26E-04 7.49E-05 PA231 5.32E+OO 2.00E-01 2.0?E-01 0. 1.12E+OO 9.91E-02 4.71E-05 PA233 1.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.00E-05 U232 7.31E-02 0. 5.23E-03 0. 7.94E-03 3.84E-01 4.46E-05 U233 1.55E-02 0. 9.42E-04 0. 3.63E-03 9.18E-02 4.12E-05 U234 1.48E-02 0. 9.23E-04 0. 3.55E-03 8.99E-02 4.04E-05 U235 1.42E-02 0. 8.67E-04 0. 3.34E-03 8.44E-02 5.13E-05 U236 1.42E-02 0. 8.86E-04 0. 3.41E-03 8.62E-02 3.79E-05 U237 5.25E-08 0. 1.40E-08 0. 2.16E-07 1.76E-05 1.29E-05 U238 1.36E-02 0. 8.10E-04 0. 3.12E-03 7.89E-02 3.62E-05 NP237 1.77E+OO 1.54E-01 7.21E-02 0. 5.35E-01 8.99E-02 5.22E-05 NP238 4.23E-07 1.13E-08 6.59E-09 0. 3.88E-08 1.75E-05 2.38E-05 NP239 4.23E-08 3.99E-09 2.21E-09 0. 1.25E-08 8.11 E-06 1.65E-05 PU238 2.86E+OO 4.06E-01 7.22E-02 0. 3.1 OE-01 3.12E-01 4.79E-05 PU239 3.31E+OO 4.50E-01 8.05E-02 0. 3.44E-01 2.93E-01 4.37E-05 PU240 3.31E+OO 4.49E-01 8.04E-02 0. 3.43E-01 2.93E-01 4.46E-05 PU241 6.97E-02 3.57E-03 1.40E-03 0. 6.47E-03 2.60E-04 9.17E-07 PU242 3.07E+OO 4.33E-01 7.75E-02 0. 3.31 E-01 2.82E-01 4.29E-05 PU244 3.59E+OO 4.96E-01 8.88E-02 0. 3.79E-01 3.23E-01 6.39E-05 AM241 1.06E+OO 4.0?E-01 7.10E-02 0. 5.32E-01 1.05E-01 4.88E-05 AM242M 1.07E+OO
- 3.93E-01 7.15E-02 0. 5.30E-01 4.21E-02 6.14E-05 AM243 1.06E+OO 3.92E-01 6.95E-02 0. 5.21E-01 9.91E-02 5.72E-05 CM242 2.12E-02 2.14E-02 1.41 E-03 0. 6.40E-03 6.76E-02 5.21E-05 CM243 8.45E-01 3.50E-01 5.00E-02 0. 2.34E-01 1.09E-01 5.13E-05 CM244 6.46E-01 3.03E-01 3.88E-02 0. 1.81 E-01 1.05E-01 4.96E-05 CM245 1.32E+OO 4.11E-01 7.53E-02 0. 3.52E-01 1.01E-01 4.63E-05 CM246 1.31E+OO 4.11E-01 7.52E-02 0. 3.51 E-01 1.03E-01 4.54E-05 CM247 1.28E+OO 4.04E-01 7.41 E-02 0. 3.46E-01 1.01 E-01 5.97E-05 CM248 1.06E+01 3.33E+OO 6.11E-01 0. 2.85E+OO 8.32E-01 9.63E-04 CF252 1.29E+OO 0. 3.0?E-02 0. 0. 3.43E-01 1.89E-04
Proc No ODCM Attachment 5 Revision 26 Page 13of16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 BE10 1.98E-04 3.06E-05 4.96E-06 0. 0. 2.22E-04 1.67E-05 C14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 N13 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 F18 4.71E-07 0. 5.19E-08 0. 0. 0. 9.24E-09 NA22 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 NA24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P32 1.65E-04 9.64E-06 6.26E-06 0. 0. 0. 1.08E-05 AR39 0. 0. 0. 0. 0. 2.08E-09 0. AR41 0. 0. 0. 0. 0. 8.06E-09 0. CA41 3.83E-05 0. 4.13E-06 0. 0. 3.83E-06 2.86E-07 SC46 5.51E-05 1.07E-04 3.11E-05 0. 9.99E-05 0. 3.23E-05 CR51 0. 0. 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN54 0. 4.95E-06 7.87E-07 0. 1.23E-06 1.75E-04 9.67E-06 MN56 0. 1.55E-10 2.29E-11 0. 1.63E-10 1.18E-06 2.53E-06 FE55 3.07E-06 2.12E-06 4.93E-07 0. 0. 9.01E-06 7.54E-07 FE59 1.47E-06 3.47E-06 1.32E-06 0. 0. 1.27E-04 2.35E-05 C057 0. 8.65E-08 8.39E-08 0. 0. 4.62E-05 3.93E-06 C058 0. 1.98E-07 2.59E-07 0. 0. 1.16E-04 1.33E-05 C060 0. 1.44E-06 1.85E-06 0. 0. 7.46E-04 3.56E-05 Nl59 4.06E-06 1.46E-06 6.77E-07 0. 0. 8.20E-06 6.11E-07 Nl63 5.40E-05 3.93E-06 1.81 E-06 0. 0. 2.23E-05 1.67E-06 Nl65 1.92E-10 2.62E-11 1.14E-11 0. 0. 7.00E-07 1.54E-06 CU64 0. 1.83E-10 7.69E-11 0. 5.76E-10 8.48E-07 6.12E-06 ZN65 4.05E-06 1.29E-05 5.82E-06 0. 8.62E-06 1.08E-04 6.68E-06 ZN69M 1.02E-09 2.45E-09 2.24E-10 0. 1.48E-09 2.38E-06 1.71E-05 ZN69 4.23E-12 8.14E-12 5.65E-13 0. 5.27E-12 1.15E-07 2.04E-09 SE79 0. 3.83E-07 6.09E-08 0. 5.69E-07 4.47E-05 3.336-06 BR82 0. 0. 1.69E-06 0. 0. 0. 1.30E-06 BR83 0. 0. 3.01E-08 0. 0. 0. 2.90E-08 BR84 0. 0. 3.91E-08 0. 0. 0. 2.05E-13 BR85 0. 0. 1.60E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 5.19E-10 0. KR85M 0. 0. 0. 0. 0. 2.91E-09 0. KR85 0. 0. 0. 0. 0. 2.41E-09 0. KR87 0. 0. 0. 0. 0. 1.53E-08 0. KR88 0. 0. 0. 0. 0. 3.13E-08 0. KR89 0. 0. 0. 0. 0. 2.13E-08 0. RB86 0. 1.69E-05 7.37E-06 0. 0. 0. 2.08E-06 RB87 0. 9.86E-06 3.21E-06 0. 0. 0. 2.88E-07 RB88 0. 4.84E-08 2.41E-08 0. 0. 0. 4.18E-19 RB89 0. 3.20E-08 2.12E-08 0. 0. 0. 1.16E-21 SR89 3.80E-05 0. 1.09E-06 0. 0. 1.75E-04 4.37E-05 SR90 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05 SR91 7.74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05 SR92 8.43E-10 0. 3.64E-11 0. 0. 2.06E-06 5.38E-06
- Includes a 50% increase to account for percutaneous transpiration.
Proc No ODCM Attachment 5 Revision 26 Page 14of16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 2.61E-07 0. 7.01E-09 0. 0. 2.12E-05 6.32E-05 Y91M 3.26E-11 0. 1.27E-12 0. 0. 2.40E-07 1.66E-10 Y91 5.78E-05 0. 1.55E-06 0. 0. 2.13E-04 4.81E-05 Y92 1.29E-09 0. 3.77E-11 0. 0. 1.96E-06 9.19E-06 Y93 1.18E-08 0. 3.26E-10 0. 0. 6.06E-06 5.27E-05 ZR93 5.22E-05 2.92E-06 1.37E-06 0. 1.11E-05 2.13E-05 1.51 E-06 ZR95 1.34E-05 4.30E-06 2.91E-06 0. 6.77E-06 2.21E-04 1.88E-05 ZR97 1.21 E-08 2.45E-09 1.13E-09 0. 3.71E-09 9.84E-06 6.54E-05 NB93M 3.10E-05 1.01E-05 2.49E-06 0. 1.16E-05 3.11 E-05 2.38E-06 NB95 1.76E-06 9.77E-07 5.26E-07 0. 9.67E-07 6.31E-05 1.30E-05 NB97 2.78E-11 7.03E-12 2.56E-12 0. 8.18E-12 3.00E-07 3.02E-08 M093 0. 1.17E-06 3.17E-08 0. 3.55E-07 5.11E-05 3.79E-06 M099 0. 1.51E-08 2.87E-09 0. 3.64E-08 1.14E-05 3.10E-05 TC99M 1.29E-13 3.64E-13 4.63E-12 0. 5.52E-12 9.55E-08 5.20E-07 TC99 3.13E-08 4.64E-08 1.25E-08 0. 5.85E-07 1.01 E-04 7.54E-06 TC101 5.22E-15 7.52E-15 7.38E-14 0. 1.35E-13 4.99E-08 1.36E-21 RU103 1.91 E-07 0. 8.23E-08 0. 7.29E-07 6.31E-05 1.38E-05 RU105 9.88E-11 0. 3.89E-11 0. 1.27E-10 1.37E-06 6.02E-06 RU106 8.64E-06 0. 1.09E-06 0. 1.67E-05 1.17E-03 1.14E-04 RH105 9.24E-10 6.73E-10 4.43E-10 0. 2.86E-09 2.41E-06 1.09E-05 PD107 0. 8.27E-08 5.87E-09 0. 6.57E-07 9.47E-06 7.06E-07 PD109 0. 4.63E-10 1.16E-10 0. 2.35E-09 1.85E-06 1.52E-05 AG110M 1.35E-06 1.25E-06 7.43E-07 0. 2.46E-06 5.79E-04 3.78E-05 AG111 4.25E-08 1.78E-08 8.87E-09 0. 5.74E-08 2.33E-05 2.79E-05 CD113M 0. 1.54E-04 4.97E-06 0. 1.71E-04 2.08E-04 1.59E-05 CD115M 0. 2.46E-05 7.95E-07 0. 1.98E-05 1.76E-04 4.SOE-05 SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0. 2.88E-04 3.92E-05 SN125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.81E-05 SN126 1.58E-04 4.18E-06 6.00E-06 1.23E-06 0. 1.17E-03 1.59E-05 SB124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0. 3.10E-04 5.0SE-05 SB125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0. 2.18E-04 1.26E-05 SB126 4.50E-07 9.13E-09 1.62E-07 2.75E-09 0. 9.57E-05 6.01E-05 SB127 3.30E-08 7.22E-10 1.27E-08 3.97E-10 0. 2.05E-05 3.77E-05 TE125M 4.27E-07 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 TE127M 1.58E-06 7.21E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 TE133M 7.24E-12 5.40E-12 4.17E-12 6.27E-12 3.74E-11 5.51E-07 5.49E-08 TE134 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.18E-11 4.343-07 2.97E-11 1129 2.48E-06 2.11E-06 6.91E-06 5.54E-03 4.53E-06 0. 2.22E-07 1130 5.72E-07 1.68E-06
- 6.60E-07 1.42E-04 2.61E-06 0. 9.61E-07 1131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 o. 7.85E-07
Proc No ODCM Attachment 5 Revision 26 Page 15of16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0. 5.08E-08 1133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0. 1.11E-06 1134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0. 1.26E-10 1135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0. 6.56E-07 XE131M 0. 0. 0. 0. 0. 1.40E-09 0. XE133M 0. 0. 0. 0. 0. 1.89E-09 0. XE133 0. 0. 0. 0. 0. 1.57E-09 0. XE135M 0. 0. 0. 0. 0. 2.22E-09 0. XE135 0. 0. 0. 0. 0. 4.05E-09 0. XE137 0. 0. 0. 0. 0. 1.74E-08 0. XE138 0. 0. 0. 0. 0. 2.44E-08 0. CS134M 1.59E-08 3.20E-08 1.72E-08 0. 1.83E-08 2.93E-09 7.92E-09 CS134 4.66E-05 1.06E-04 9.10E-05 0. 3.59E-05 1.22E-05 1.30E-06 CS1.35 1.46E-05 1.29E-05 5.99E-06 0. 5.11E-06 1.57E-06 2.11E-07 CS136 4.88E-06 1.83E-05 1.38E-05 0. 1.07E-05 1.50E-b6 1.46E-06 CS137 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 1.05E-06 CS138 4.14E-08 7.76E-08 4.05E-08 0. 6.00E-08 6.07E-09 2.33E-13 CS139 2.56E-08 3.63E-08 1.39E-08 0. 3.05E-08 2.84E-09 5.49E-31 BA139 1.17E-10 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07 BA140 4.88E-06 6.13E-09 3.21E-07 0. 2.09E-09 1.59E-04 2.73E-05 BA141 1.25E-11 9.41E-15 4.20E-13 0. 8.75E-15 2.42E-07 1.45E-17 BA142 3.29E-12 3.38E-15 2.07E-13 0. 2.86E-15 1.49E-07 1.96E-26 LA140 4.30E-08 2.17E-08 5.73E-09 0. 0. . 1.70E-05 5.73E-05 LA141 5.34E-10 1.66E-10 2.71E-11 0. 0. 1.35E-06 7.31E-06 LA142 8.54E-11 3.88E-11 9.65E-12 0. 0. 7.91E-07 2.64E-07 CE141 2.49E-06 1.69E-06 1.91 E-07 0. 7.83E-07 4.52E-05 1.50E-05 CE143 2.33E-08 1.72E-08 1.91 E-09 0. 7.60E-09 9.97E-06 2.83E-05 CE144 4.29E-04 1.79E-04 2.30E-05 0. 1.06E-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.80E-08 0. 2.70E-07 3.51E-05 2.50E-05 PR144 3.76E-12 1.56E-12 1.91E-13 0. 8.81E-13 1.27E-07 2.69E-18 ND147 6.59E-07 7.62E-07 4.56E-08 0. 4.45E-07 2.76E-05 2.16E-05 PM147 8.37E-05 7.87E-06 3.19E-06 0. 1.49E-05 6.60E-05 5.54E-06 PM148M 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2.14E-04 4.18E-05 PM148 3.84E-07 6.37E-08 3.20E-08 0. 1.20E-07 3.91E-05 5.80E-05 PM149 3.44E-08 4.87E-09 1.99E-09 0. 9.19E-09 7.21E-06 2.50E-05 PM151 8.50E-09 1.42E-09 7.21E-10 0. 2.55E-09 3.94E-06 2.00E-05 SM151 8.59E-05 1.48E-05 3.55E-06 0. 1.66E-05 4.45E-05 3.25E-06 SM153 1.70E-08 1.42E-08' 1.04E-09 0. 4.59E-09 4.14E-06 1.58E-05 EU152 2.38E-04 5.41 E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05 EU154 7.40E-04 9.10E-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05 EU155 1.01E-04 1.43E-05 9.21E-06 0. 6.59E-05 9.46E-05 5.95E-06 EU156 1.93E-06 1.48E-06 2.40E-07 0. 9.95E-07 8.56E-05 4.50E-05 TB160 2.21E-05 0. 2.75E-06 0. 9.10E-06 1.92E-04 2.68E-05 H0166M 3.37E-04 1.05E-04 8.00E-05 0. 1.57E-04 3.94E-04 1.59E-05 W181 6.23E-09 2.03E-09 2.17E-10 0. 0. 1.71E-06 2.53E-07 W185 1.95E-07 6.47E-08 6.81E-09 0. 0. 5.57E-05 1.07E-05 W187 1.06E-09 8.85E-10 3.10E-10 0. 0. 3.63E-06 1.94E-05
Proc No ODCM Attachment 5 Revision 26 Page 16of16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 81210 0. 1.59E-06 1.32E-07 0. 1.92E-05 1.11E-03 2.95E-05 P0210 3.97E-04 8.60E-04 9.58E-05 0. 2.95E-03 3.14E-02 4.19E-05 RN222 0. 0. 0. 0. 0. 2.05E-06 0. RA223 1.BOE-04 2.77E-07 3.60E-05 0. 7.85E-06 2.55E-02 2.84E-04 RA224 1.98E-05 4.78E-08 3.96E-06 0. 1.35E-06 8.77E-03 3.01E-04 RA225 3.00E-04 3.56E-07 5.99E-05 0. 1.01 E-05 2.92E-02 2.71E-04 RA226 1.25E-01 2.39E-06 9.14E-02 0. 6.77E-05 1.17E-01 2.94E-04 RA228 4.41E-02 1.23E-06 4.78E-02 0. 3.48E-05 1.61E-01 5.00E-05 AC225 4.23E-04 5.82E-04 2.84E-05 0. 6.63E-05 2.21E-02 2.52E-04 AC227 2.30E+OO 3.05E-01 1.36E-01 0. 9.82E-02 2.41E-01 5.08E-05 TH227 2.17E-04 3.92E~06 6.25E-06 0. 2.22E-05 3.77E-02 3.34E-04 TH226 2.00E-01 3.39E~03 6.77E-03 0. 1.89.E-02 1.01E+OO 3.49E-04 TH229 8.88E+OO 1.33E-01 4.36E-01 0. 6.52E-01 3.49E+OO 3.17E-04 TH230 2.29E+OO 1.31E-01 6.36E-02 0. 6.40E-01 6.21 E-01 3.73E-05 TH232 2.56E+OO 1.12E-01 9.04E-02 0. 5.47E-01 5.96E-01 3.17E-05 TH234 1.63E-06 9.56E-08 4.70E-08 0. 5.41E-07 1.89E-04 7.03E-05 PA231 5.08E+OO 1.91E-01 1.98E-01 0. 1.076+00 5.75E-02 4.44E-05 PA233 1.21E-06 2.42E-07 2.09E-07 0. 9.15E-07 3.52E-05 1.02E-05 U232 5.14E-02 0. 3.66E-03 0. 5.56E-03 2.22E-01 4.21E-05 U233 1.09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05 U234 1.04E-02 0. 6.46E-04 0. 2.49E-03 5.22E-02 3.81E-05 U235 1.00E-02 0. 6.07E-04 0. 2.34E-03 4.90E-02 4.84E-05 U236 1.00E-02 0. 6.20E-04 0. 2.39E-03 5.00E-02 3.57E-05 U237 3.67E-08 0. 9.77E-09 0. 1.51 E-07 1.02E-05 1.20E-05 U238 9.58E-03 0. 5.67E-04 0. 2.18E-03 4.58E-02 3.41 E-05 NP237 1.69E+OO 1.47E-01 6.87E-02 0. 5.10E-01 5.22E-02 4.92E-05 NP238 2.96E-07 8.00E-09 4.61E-09 0. 2.72E-08 1.02E-05 2.13E-05 NP239 2.87E-08 2.82E-09 1..55E-09 0. 8.75E-09 4.70E-06 1.49E-05 PU238 2.74E+OO 3.87E-01 6.90E-02 0. 2.96E-01 1.82E-01 4.52E-05 PU239 3.19E+OO 4.31E-01 7.75.E-02 0. 3.30E-01 1.72E-01 4.13E-05 PU240 3.18E+OO 4.30E-01 7.73E-02 0. 3.29E-01 1.72E-01 4.21E-05 PU241 6.41 E-02 3.28E-03 1.29E-03 0. 5.93E-03 1.52E-04 8.65E-07 PU242 2.95E+OO 4.15E-01 7.46E-02 0. 3.17E-01 1.65E-01 4.05E-05 PU244 3.45E+OO 4.76E-01 8.54E-02 0. 3.64E-01 1.89E-01 6.03E-05 AM241 1.01E+OO 3.59E-01 6.71E-02 0. 5.04E-01 6.06E-02 4.60E-05 AM242M 1.02E+OO 3.46E-01 6.73E-02 0. 5.01 E-01 2.44E-02 5.79E-05 AM243 1.01E+OO 3.47E-01 6.57E-02 0. 4.95E-01 5.75E-02 5.40E-05 CM242 1.48E-02 1.51 E-02 9.84E-04 0. 4.48E-03 3.92E-02 4.91E-05 CM243 7.86E-01 2.97E-01 4.616-02 0. 2.15E-01 6.31E-02 4.84E-05 CM244 5.90E-01 2.54E-01 3.51E-02 0. 1.64E-01 6.06E-02 4.68E-05 CM245 1'.26E+OO 3.59E-01 7.14E-02 0 .. 3.33E-01 5.85E-02 4.36E-05 CM246 1.25E+OO 3.59E-01 7.13E-02 0. 3.33E-01 5.96E-02 4.29E-05 CM247 1.22E+OO 3.53E-01 7.03E-02 0. 3.28E-01 5.85E-02 5.63E-05 CM248 1.01 E+01 2.91 E+OO 5.79E-01 0. 2.70E+OO 4.82E-01 9.096-04 CF252 9.78E-01 0. 2.33E-02 0. 0. 1.99E-01 1.78E-04
Proc No ODCM Attachment 6 Revision 26 Page 1of2 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (DFG1l (mrem/hr per pCi/m 2) ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.BOE-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 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 0.0 0.0 Ni-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 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 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.BOE-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
Proc No ODCM Attachment 6 Revision 26 Page 2 of 2 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (DFG1l (mrem/hr per pCi/m 2) ELEMENT TOTAL BODY SKIN Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-08 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 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20~-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 0.0 0.0 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
Proc NoODCM Attachment 7 Revision 26 Page 1 of 1 BIOACCUMULATION FACTORS uCi/gm per uCi/ml FRESHWATER ELEMENT FISH H 9.0E-01 c 4.6E 03 NA 1.0E 02 p 1.0E 05 CR 2.0~ 02 MN 4.0E 02 FE 1.0E 02 co 5.0E 01 NI 1.0E 02 cu 5.0E 01 ZN 2.0E 03 BR 4.2E 02 RB 2.0E 03 SR 3.0E 01 y 2.5E 01 ZR 3.3E 00 NB 3.0E 04 MO 1.0E 01 TC 1.5E 01 RU 1.0E 01 RH 1.0E 01
~TE 4.0E 02 I 1.5E 01 cs 2.0E 03 BA 4.0E 00 LA 2.5E 01 CE 1.0E 00 PR 2.5E 01 ND 2.5E 01 w 1.2E 03 NP 1.0E 01
Proc No ODCM Attachment 8 Revision 26 Page 1 of 16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07 BE10 1.71 E-OS 2.49E-06 S.16E-07 0. 1.64E-06 0. 2.78E-OS C14 2.37E-OS S.06E-06 S.06E-06 S.06E-06 S.06E-06 S.06E-06 S.06E-06 N13 S.8SE-08 S.8SE-08 S.8SE-08 S.83SE-08 S.8SE-08 S.8SE-08 S.8SE-08 F18 S.19E-06 0. 4.43E.07 0. 0. 0. 1.22E-06 NA22 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS NA24 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS P32 1.70E-03 1.00E-04 6.S9E-OS 0. 0. 0. 2.30E-OS AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 3.74E-04 0. 4.08E-OS 0. 0. 0. 1.91 E-07 SC46 3.7SE-08 S.41 E-08 1.69E-08 0. 3.S6E-08 0. 3.S3E-OS CRS1 0. 0. 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MNS4 0. 1.99E-OS 4.S1E-06 0. 4.41E-06 0. 7.31E-06 MNS6 0. 8.18E-07 1.41E-07 0. 7.03E-07 0. 7.43E-OS FESS 1.39E-OS 8.98E-06 2.40E-06 0. 0. 4.39E-06 1.14E-06 FES9 3.08E-OS S.38E-OS 2.12E-OS 0. 0. 1.S9E-OS 2.S7E-OS COS7 0. 1.1SE-06 1.87E-06 0. 0. 0. 3.92E-06 COS8 0. 3.60E-06 8.98E-06 0. 0. 0. 8.97E-06 C060 0. 1.08E-OS 2.SSE-OS 0. 0. 0. 2.S7E-OS NIS9 4.78E-OS 1.4SE-OS 8.17E-06 0. 0. 0. 7.16E-07 Nl63 6.34E-04 3.92E-OS 2.20E-OS 0. 0. 0. 1.9SE-06 Nl6S 4.70E-06 S.32E-07 2.42E-07 0. 0. 0. 4.0SE-OS CU64 0. 6.09E-07 2.82E-07 0. 1.03E-06 0. 1.2SE-OS ZN6S 1.84E-OS 6.31E-OS 2.91E-OS 0. 3.06E-OS 0. S.33E-OS ZN69M 1.SOE-06 3.06E-06 2.79E-07 0. 1.24E-06 0. 4.24E-OS ZN69 9 ..33E-08 1.68E-07 1.2SE-08 0. 6.98E-08 0. 1.37E-OS SE79 0. 2.10E-OS 3.90E-06 0. 2.43E-OS 0. S.S8E-07 BR82 0. 0. 1.27E-OS 0. 0. 0. 0. BR83 0. 0. 3.63E-07 0. 0. 0. 0. BR84 0. 0. 3.82E-07 0. 0. 0. 0. BR8S 0. 0. 1.94E-08 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 0. 0. KR8SM 0. 0. 0. 0. 0. 0. 0. KR8S 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 1.70E-04 8.40E-OS 0. 0. 0. 4.3SE-06 RB87 0. 8.88E-OS 3.S2E-OS 0. 0. 0. S.98E-07 RB88 0. 4.98E-07 2.73E-07 0. 0. 0. 4.8SE-07 R889 0. 2.86E-07 1.97E-07 0. 0. 0. 9.74E-08 SR89 2.S1E-03 0. 7.20E-OS 0. 0. 0. S.16E-OS SR90 1.8SE-02 0. 4.71E-03 0. 0. 0. 2.31E-04 SR91 S.OOE-OS 0. 1.81 E-06 0. 0. 0. S.92E-OS SR92 1.92E-OS 0. 7.13E-07 0. 0. 0. 2.07E-04
Proc NoODCM Attachment 8 Revision 26 Page 2of16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04 Y91M 8.10E-10 0. 2.76E-11 0. 0. 0. 2.70E-06 Y91 1.13E-06 0. 3.01E-08 0. 0. 0. 8.10E-05 Y92 7.65E-09 0. 2.15E-10 0. 0. 0. 1.46E-04 Y93 2.43E-08 0. 6.62E-10 0. 0. 0. 1.92E-04 ZR93 1.93E-07 9.18E-08 5.54E-08 0. 2.71E-07 0. 2.39E-05 ZR95 2.06E-07 5.02E-08 3.56E-08 0. 5.41E-08 0. 2.50E-05 ZR97 1.48E-08 2.54E-09 1.16E-09 0. 2.56E-09 0. 1.62E-04 NB93M 1.23E-07 3.33E-08 1.04E-08 0. 3.25E-08 0. 3.98E-06 NB95 4.20E-08 1.73E-08 1.00E-08 0. 1.24E-08 0. 1.46E-05 NB97 4.59E-10 9.79E-11 3.53E-11 0. 7.65E-11 0. 3.09E-05 M093 0. 5.65E-05 1.82E-06 0. 1.13E-05 0. 1.21 E-06 M099 0. 3.40E-05 6.63E-06 0. 5.08E-05 0. 1.12E-05 TC99M 1.92E-09 3.96E-09 5.10E-08 0. 4.26E-08 2.07E-09 1.15E-06 TC99 1.08E-06 1.46E-06 4.55E-07 0. 1.23E-05 1.42E-07 6.31E-06 TC101 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 0. 4.95E-07 0. 3.08E-06 0. 1.80E-05 RU105 1.36E-07 0. 4.58E-08 0. 1.00E-06 0. 5.41 E-05 RU106 2.41E-05 0. 3.01E-06 0. 2.85E-05 0. 1.83E-04 RH105 1.09E-06 7.13E-07 4.79E-07 0. 1.98E-06 0. 1.77E-05 PD107 0. 1.19E-06 8.45E-08 0. 6.79E-06 0. 9.46E-07 PD109 0. 1.50E-06 3.62E-07 0. 5.51E-06 0. 3.68E-05 AG110M 9.96E-07 7.27E-07 4.81E-07 0. 1.04E-06 0. 3.77E-05 AG111 5.20E-07 2.02E-07 1.07E-07 0. 4.22E-07 0. 4.82E~05 CD113M 0. 1.77E-05 6.52E-07 0. 1.34E-05 0. 2.66E-05 CD115M 0. 1.42E-05 4.93E-07 0. 7.41E-06 0. 8.09E~05 SN123 2.49E-04 3.89E-06 6.50E-06 3.91E-06 0. 0. 6.58E-05 SN125 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0. 0. 1.11E-04 SN126 5.53E-04 7.26E-06 1.80E-05 1.91 E-06 0. 0. 2.52E-05 SB124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0. 1.34E-05 6.60E-05 SB125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0. 7.72E-06 1.64E-05 SB126 8.06E-06 1.58E-07 2.91E-06 6.19E-08 0. 5.07E-06 8.35E-05 SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0. 1.15E-06 5.91E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0. 0. 1.11E-05 TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0. 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0. 2.10E-05 TE129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0. 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0. 2.27E-05 TE131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0. 1.03E-04 TE131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0. 7.11E-06 TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0. 3.81E-05 TE133M 3.91E-07 1.79E-07 1.71E-07 3.45E-07 1.22E-06 0. 1.93E-05 TE134 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 0. 3.06E-06 1129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51E-05 0. 4.24E-07 1130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0. 2.83E-06 1131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0. 1.51E-06
Proc NoODCM Attachment 8 Revision 26 Page 3of16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0. 2.73E.06 1133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0. 3.08E-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0. 1.84E-06 1135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0. 2.62E-06 XE131M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 0. 0. 0. 0. 0. o. 0. CS134M 1.76E-07 2.93E-07 1.48E-07 0. 1.13E-07 2.60E-08 2.32E-07 CS134 3.77E.-04 7.03E-04 7.10E-05 0. 1.81 E-04 7.42E-05 1.91 E-06 CS135 1.33E-04 1.21 E-04 6.30E-06 0. 3.44E-05 1.31 E-05 4.37E-07 CS136 4.59E-05 1.35E-04 5.04E-05 0. 5.38E-05 1.10E-05 2.05E-06 CS137 5.22E-04 6.11E-04 4.33E-05 0. 1.64E-04 6.64E-05 1.91 E-06 CS138 4.81E-07 7.82E-07 3.79E-07 0. 3.90E-07 6.09E-08 1.25E-06 CS139 3.10E-07 4.24E-07 1.62E-07 0. 2.19E-07 3.30E-08 2.66E-08 BA139 8.81E-07 5.84E-10 2.55E-08 0. 3.51E-10 3.54E-10 5.58E-05 BA140 1.71E-04 1.71E-07 8.81E-06 0. 4.06E-08 1.05E-07 4.20E-05 BA141 4.25E-07 2.91E-10 1.34E-08 0. 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.53E-10 9.06E-09 0. 8.81E-11 9.26E-11 7.59E-07 LA140 2.11 E-08 8.32E-09 2.14E-09 0. 0. 0. 9.77E-05 LA141 2.89E-09 8.38E-10 1.46E-10 0. 0. 0. 9.61E-05 LA142 1.10E-09 4.04E-10 9.67E-11 0. 0. 0. 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 0. 1.48E-08 0. 2.48E-05 CE143 1.48E-08 9.82E-06 1.12E-09 0. 2.86E-09 0. 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 0. 4.93E-07 0. 1.71 E-04 PR143 8.18E-08 3.04E-08 4.03E-09 0. 1.13E-08 0: 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 0. 3.84E-11 o, 4.93E-06 Nb147 5.53E-08 5.68E-08 3.48.E-09 0. 2.19E-08 0. 3.60E-05 PM147 3.88E-07 3.27E-08 1.59E-08 0. 4.88E-08 0. 9.27E-06 PM148M 1.65E-07 4.18E-08 3.28E-08 0. 4.80E-08 0. 5.443-05 PM148 6.32E-08 9.13E-09 4.60E-09 0. 1.09E-08 0. 9.74E-05 PM149 1.38E-08 1.81 E-09 7.90E-10 0. 2.20E-09 0. 4.86E-05 PM151 6.18E-09 9.01E-10 4.56E-10 0. 1.07E-09 0. 4.17E-05 SM151 2.90E*07 6.67E-08 1.44E-08 0. 4.53E-08 0. 5.58E-06 SM153 7.72E-09 5.97E-09 4.58E-10 0. 1.25E-09 0. 3.12E-05 EU152 6.74E-07 1.79E-07 1.51 E-07 0. 5.02E-07 0. 1.59E-05 EU154 2.64E-06 3.67E-07 2.20E-07 0. 9.95E-07 0. 4.58E-05 EU155 5.42E-07 6.25E-08 3.23E-08 0. 1.40E-07 0. 8.37E-05 EU156 1.14E-07 7.06E-08 1.12E-08 0. 3.26E-08 0. 6.67E-05 TB160 2.59E-07 0. 3.24E-08 0. 7.37E-08 0. 3.45E-05 H0166M 1.25E-06 2.69E-07 2.13E-07 0. 3.57E-07 0. 0. W181 8.85E-08 2.72E-08 3.04E-09 0. 0. 0. 3.82E-07 W185 3.62E-06 1.13E-06 1.29E-07 0. 0. 0. 1.62E-05 W187 9.03E-07 6.28E-07 2.17E-07 0. 0. 0. 3.69E-05
Proc No ODCM Attachment 8 Revision 26 Page 4of16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05 81210 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.27E-05 P0210 3.10E-03 5.93E-03 7.41E-04 0. 1.26E-02 0. 6.61E-05 RN222 0. 0. 0. 0. 0. 0. 0. RA223 4.41E-02 6.42E-05 8.82E-03 0. 1.17E-03 0. 3.43E-04 RA224 1.46E-02 3.29E-05 2.91E-03 0. 6.00E-04 0. 3.86E-04 RA225 5.78E-02 6.42E-05 1.15E-02 0. 1.19E-03 0. 3.24E-04 RA226 6.20E-01 4.76E-05 5.14E-01 0. 8.71E-04 0. 3.44E-04 RA228 4.32E-01 2.58E-05 4.86E-01 0. 4.73E-04 0. 5.86E-05 AC225 3.92E-05 5.03E-05 2.63E-06 0. 3.69E-06 0. 4.36E-04 AC227 4.49E-03 7.67E-04 2.79E-04 0. 1.56E-04 0. 8.50E-05 TH227 1.20E-04 2.01E-06 3.45E-06 0. 7.41 E-06 0. 5.70E-04 TH228 2.47E-03 3.38E-05 8.36E-05 0. 1.58E-04 0. 5.84E-04 TH229 1.48E-02 1.94E-04 7.29E-04 0. 9.29E-04 0. 5.31E-04 TH230 3.80E-03 1.90E-04 1.06E-04 0. 9.12E-04 0. 6.24E-05 TH232 4.24E-03 1.63E-04 1.65E-04 0. 7.79E-04 0. 5.31E-05 TH234 6.92E-07 3.77E-08 2.00E-08 0. 1.39E-07 0. 1.19E-04 PA231 7.57E-03 2.50E-04 3.02E-04 0. 1.34E-03 0. 7.44E-05 PA233 3.11E-08 6.09E-09 5.43E-09 0. 1.67E-08 0. 1.46E-05 U232 2.42E-02 0. 2.16E-03 0. 2.37E-03 0. 7.04E-05 U233 5.08E-03 0. 3.87E-04 0. 1.08E-03 0. 6.51E-05 U234 4.88E-03 0. 3.80E-04 0. 1.06E-03 0. 6.37E-05 U235 4.67E-03 0. 3.56E-04 0. 9.93E-04 0. 8.10E-05 U236 4.67E-03 0. 3.64E-04 0. 1.01 E-03 0. 5.98E-05 U237 4.95E-07 0. 1.32E-07 0. 1.23E-06 0. 2.11E-05 U238 4.47E-03 0. 3.33E-04 0. 9.28E-04 0. 5.71E-05 NP237 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 0. 8.23E-05 NP238 1.24E-07 3.12E-09 1.92E-09 0. 6.81E-09 0. 4.17E-05 NP239 1.11E-08 9.93E-10 5.61E-10 0. 1.98E-09 0. 2.87E-05 PU238 1.34E-03 1.69E-04 3.40E-05 0. 1.21E-04 0. 7.57E-05 PU239 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 6.91E-05 PU240 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 7.04E-05 PU241 4.38E-05 1.90E-06 8.82E-07 0. 3.17E-06 0. 1.45E-06 PU242 1.35E-03 1.70E-04 3.41E-05 0. 1.23E-04 0. 6.77E-05 PU244 1.57E-03 1.95E-04 3.91E-05 0. 1.41 E-04 0. 1.01 E-04 AM241 1.53E-03 7.18E-04 1.09E-04 0. 6.55E-04 0. 7.70E-05 AM242M 1.58E-03 7:02E-04 1.13E-04 0. 6.64E-04 0. 9.69E-05 AM243 1.51 E-03 6.88E-04 1.06E-04 0. 6.36E-04 0. 9.03E-05 CM242 1.37E-04 1.24E-04 9.10E-06 0. 2.62E-05 0. 8.23E-05 CM243 1.45E-03 6.88E-04 8.98E-05 0. 3.27E-04 0. 8.10E-05 CM244 1.22E-03 6.16E-04 7.59E-05 0. 2.71E-04 0. 7.84E-05 CM245 1.88E-03 7.49E-04 1.13E-04 0. 4.32E-04 0. 7.30E-05 CM246 1.87E-03 7.49E-04 1.13E-04 0. 4.31E-04 0. 7.17E-05 CM247 1.82E-03 7.36E-04 1.11E-04 0. 4.24E-04 0. 9.43E-05 CM248 1.51E-02 6.07E-03 9.16E-04 0. 3.50E-03 0. 1.52E-03 CF252 1.24E-03 0. 2.95E-05 0 0. 0. 2.99E-04
Proc No ODCM Attachment 8 Revision 26 Page 5of16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 BE10 1.35E-05 1.57E-06 3.39E-07 0. 1.11E-06 0. 2.75E-05 C14 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 N13 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 F18 2.49E-06 0. 2.47E-07 0. 0. 0. 6.74E-07 NA22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 NA24 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 P32 8.25E-04 3.86E-05 3.18E-05 0. 0. 0. 2.28E-05 AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. ' 0. 0. CA41 3.47E-04 0. 3.79E-05 0. 0. 0. 1.90E-07 SC46 1.97E-08 2.70E-08 1.04E-08 0. 2.30E-08 0. 3.95E-05 CR51 0. 0. 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN54 0. 1.07E-05 2.85E-06 0. 3.00E-06 0. 8.98E-06 MN56 0. 3.34E-07 7.54E-08 0. 4.04E-07 . 0. 4.84E*05 FE55 1.15E-05 6.10E-06 1.89E-06 .o. 0. 3.45E-06 1.13E-06 FE59 1.65E-05 2.67E-05 1.33E-05 0. 0. 7.74E-06 2.78E-05 C057 0. 4.93E-07 9.98E-07 0. 0. 0. 4.04E-06 C058 0. 1.BOE-06 5.51E-06 0. 0. 0. 1.05E-05 C060 0. 5.29E-06 1.56E-05 0. 0. 0. 2.93E-05 Nl59 4.02E-05 1.07E-05 6.82E-06 0. 0. 0. 7.10E-07 Nl63 5.38E-04 2.88E-05 1.83E-05 0. 0. 0. 1.94E-06 Nl65 2.22E-06 2.09E-07 1.22E-07 0. 0. 0. 2.56E-05 CU64 0. 2.45E-07 1.48E-07 0. 5.92E-07 0. 1.15E-05 ZN65 1.37E-05 3.65E-05 2.27E-05 0. 2.30E-05 0. 6.41E*06 ZN69M 7.10E-07 1.21 E-06 1.43E-07 0. 7.03E-07 0. 3.94E-05 ZN69 4.38E-08 6.33E-08 5.85E-09 0. 3.84E-08 0. 3.99E-06 SE79 0. 8.43E-06 1.87E-06 0. 1.37E-05 0. 5.53E-07 BR82 0. 0. 7.55E-06 0. 0. 0. 0. BR83 0. 0. 1.71E-07 0. 0. 0. 0. BR84 0. 0. 1.98E-07 0. 0. 0. 0. BR85 0 0. 9.12E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 0. 0. KR85M 0. 0. 0. 0. 0. 0. 0. KR85 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 6.70E-05 4.12E-05 0. 0. 0. 4.31E-06 RB87 0. 3.95E-05 1.83E-05 0. 0. 0. 5.92E-07 RB88 0. 1.90E-07 1.32E-07 0. 0. 0. 9.32E-09 RB89 0. 1.17E-07 1.04E-07 0. 0. 0. 1.02E-09 SR89. 1.32E-03 0. 3.77E-05 0. 0. 0. 5.11 E-05 SR90 1.70E-02 0. 4.31E-03 0. 0. 0. 2.29E-04 SR91 2.40E-05 0. 9.06E-07 0. 0. 0. 5.30E-05 SR92 9.03E-06 0. 3.62E-07 0. 0. 0. 1.71E-04
Proc No ODCM Attachment 8 Revision 26 Page 6of16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 4.11 E-08 0. 1.10E-09 0. 0. 0. 1.17E-04 Y91M 3.82E-10 0. 1.39E-11 0. 0. 0. 7.48E-07 Y91 6.02E-07 0. 1.61 E-08 0. 0. 0. 8.02E-05 Y92 3.60E-09 0. 1.03E-10 0. 0. 0. 1.04E-04 Y93 1.14E-08 0. 3.13E-10 0. 0. 0. 1.70E-04 ZR93 1.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 0. 2.37E-05 ZR95 1.16E-07 2.55E-08 2.27E-08 0. 3.65E-08 0. 2.66E-05 ZR97 6.99E-09 1.01 E-09 5.96E-10 0. 1.45E-09 0. 1.53E-04 NB93M 1.05E-07 2.62E-08 8.61E-09 0. 2.83E-08 0. 3.95E-06 NB95 2.25E-08 8.76E-09 6.26E-09 0. 8.23E-09 0. 1.62E-05 NB97 2.17E-10 3.92E-11 1.83E-11 0. 4.35E-11 0. 1.21 E-05 M093 0. 2.41 E-05 8.65E-07 0. 6.35E-06 0. 1.22E-06 M099 0. 1.33E-05 3.29E-06 0. 2.84E-05 0. 1.10E-05 TC99M 9.23E-10 1.81 E-09 3.00E-08 0. 2.63E-08 9.19E-10 1.03E-06 TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06 TC101 1.07E-09 1.12E-09 1.42E-08 0. 1.91 E-08 5.92E-10 3.56E-09 RU103 7.31E-07 0. 2.81E-07 0. 1.84E-06 0. 1.89E-05 RU105 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21E-05 RU106 1.17E-05 0. 1.46E-06 0. 1.58E-05 0. 1.82E-04 RH105 5.14E-07 2.76E-07 2.36E-07 0. 1.10E-06 0. 1.71 E-05 PD107 0. 4.72E-07 4.01E-08 0. 3.95E-06 0. 9.37E-07 PD109 0. 5.67E-07 1.70E-07 0. 3.04E-06 0. 3.35E-05 AG110M 5.39E-07 3.64E-07 2.91E-07 0. 6.78E-07 0. 4.33E-05 AG111 2.48E-07 7.76E-08 5.12E-08 0. 2.34E-07 0. 4.75E-05 CD113M 0. 1.02E-05 4.34E-07 0. 1.05E-05 0. 2.63E-05 CD115M 0. 5.89E-06 2.51E-07 0. 4.38E-06 0. 8.01E-05 SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0. 0. 6.52E-05 SN125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0. 0. 1.10E-04 SN126 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0. 0. 2.50E-05 SB124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0. 6.16E-06 6.94E-05 SB125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0. 3.99E-06 1.71E-05 SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0. 2.10E-06 8.87E-05 SB127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0. 4.60E-07 5.97E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0. 0. 1.10E-05 TE127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0. 2.34E-05 TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0. 1.84E-05 TE129M 4.87E-05 1.36E-05 7.56E._06 1.57E-05 1.43E-04 0. 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0. 1.01 E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0. 4.36E-07 TE132 1.01 E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0. 4.50E-05 TE133M 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 0. 5.77E-06 TE134 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 0. 5.89E-07 1.129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 0. 4.29E-07 1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0. 2.76E-06 1131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0. 1.54E-06
Proc No ODCM Attachment 8 Revision 26 Page 7of16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0. 1.73E-06 1133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0. 2.95E-06 1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0. 5.16E-07 1135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06 XE131M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 0. 0. 0. 0. 0. 0. 0. CS134M 8.44E-08 1.25E-07 8.16E-08 0. 6.59E-08 1.09E-08 1.58E-07 CS134 2.34E-04 3.84E-04 8.10E-05 0. 1.19E-04 4.27E-05 2.07E-06 CS135 8.30E-05 5.78E-05 5.93E-06 0. 2.04E-05 6.81E-06 4.33E-07 CS136 2.35E-05 6.46E-05 4.18E-05 0. 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 0. 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 0. 2.23E-07 2.40E-08 1.46E-07 CS139 1.45E-07 1.61E-07 7.74E-08 0. 1.21 E-07 1.22E-08 1.45E-11 BA139 4.14E-07 2.21E-10 1.20E-08 0. 1.93E-10 1.30E-10 2.39E-05 BA140 8.31E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21E-05 BA141 2.00E-07 1.12E-10 6.51E-09 0. 9.69E-11 6.58E-10 1.14E-07 BA142 8.74E-08 6.29E-11 4.88E-09 0. 5.09E-11 3.70E-11 1.14E-09 LA140 1.01 E-08 3.53E-09 1.19E-09 0. 0. 0. 9.84E-05 LA141 1.35E-09 3.17E-10 6.88E-11 0. 0. 0. 7.05E-05 LA142 5.24E-10 1.67E-10 5.23E-11 0. 0. 0. 3.31E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0. 8.68E-09 0. 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-10 0. 1.59E-09 0. 5.55E-05 CE144 2.08E-06 6.52E-07 1.11E-07 0. 3.61E-07 0. 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 0. 6.39E-09 0. 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 0. 2.11E-11 0. 8.59E-08 ND147 2.79E-08 2.26E-08 1.75E-09 0. 1.24E-08 0. 3.58E-05 PM147 3.18E-07 2.27E-08 1.22E-08 0. 4.01E-08 0. 9.19E-06 PM148M 1.03E-07 2.05E-08 2.05E-08 0. 3.04E-08 0. 5.78E-05 PM148 3.02E-08 3.63E-09 2.35E-09 0. 6.17E-09 0. 9.70E-05 PM149 6.49E-09 6.90E-10 3.74E-10 0. 1.22E-09 0. 4.71E-05 PM151 2.92E-09 3.55E-10 2.31E-10 0. 6.02E-10 0. 4.03E-05 SM151 2.56E-07 3.81E-08 1.20E-08 0. 3.94E-08 0. 5.53E-06 SM153 3.65E-09 2.27E-09 2.19E-10 0. 6.91E-10 0. 3.02E-05 EU152 6.15E-07 1.12E-07 1.33E-07 0. 4.73E-07 0. 1.84E-05 EU154 2.30E-06 2.07E-07 1.89E-07 0. 9.09E-07 0. 4.81E-05 EU155 4.82E-07 3.47E-08 2.72E-08 0. 1.30E-07 0. 8.69E-05 EU156 5.62E-08 3.01E-08 6.23E-09 0. 1.94E-08 0. 6.83E-05 TB160 1.66E-07 0. 2.06E-08 0. 4.94E-08 0. 3.68E-05 H0166M 1.08E-06 2.26E-07 1.91E-07 0. 3.22E-07 0. 0. W181 4.23E-06 1.04E-08 1.43E-09 0. 0. 0. 3.79E-07 W185 1.73E-06 4.32E-07 6.05E-08 0. 0. 0. 1.61 E-05 W187 4.29E-07 2.54E-07 1.14E-07 0. 0. 0. 3.57E-05
Proc No ODCM Attachment 8 Revision 26 Page 8of16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 4.75E-02 1.22E-02 2.09E-03 0. 3.67E-02 0. 5.576-05 81210 1.97E-06 1.02E-05 1.69E-07 0. 1.15E-04 0. 5.1.7E~05 P0210 1.52E-03 2.43E-03 3.67E-04 0. 7.56E-03 0. 6.55E-05 RN222 0. 0. 0. 0. 0. 0. 0. RA223 2.12E-02 2.45E-05 4.24E-03 0. 6.50E-04 0. 3.38E-04 RA224 6.89E-03 1.25E-05 1.38E-03 0. 3.31E-04 0. 3.78E-04 RA225 2.80E-02 2.50E-05 5.59E-03 0. 6.62E-04 0. 3.21E-04 RA226 5.75E-01 1.84E-05
- 4.72E-01 0. 4.88E-04 0. 3.41E-04 RA228 3.85E-01 9.99E-06 4.32E-01 0. 2.65E-04 0. 5.81E-05 AC225 1.88E-05 1.94E-05 1.26E-06 0. 2.07E-06 0. 4.31E-04 AC227 4.12E-03 6.63E-04 2.55E-04 0. 1.46E-04 0. 8.43E-05 TH227 5.85E-05 7.96E-07 1.69E-06 0. 4.22E-06 0. 5.63E-04 TH228 2.07E-03 2.65E-05 7.00E-05 0. 1.38E-04 0. 5.79E~04 TH229 1.38E-02 1.81E-04. 6.80E-04 0. 8.84E-04 0. 5.27E-04 TH230 3.55E-03 1.78E-04 9.91E~o5 0. 8.67E-04 0. 6.19E-05 TH232 3.96E-03 1.52E-04 3.01E-04 0. 7.41E-04 0. 5.27E-05 TH234 3.42E-07 1.51 E-08 9.88E-09 0. 8.01E-08 0. 1.18E-04 PA231 7.07E-03 2.34E-04 2.81E-04 0. 1.28E-03 0. 7.37E-05 PA233 1.81 E-08 2.82E-09 3.16E-09 0. 1.04E-08 0. 1.44E-05 U232 1.76E-02 0. 1.26E-03 0. 1.34E-03 0. 6.98E-05 U233 3.72E-03 0. 2.25E-04 b. 6.10E-04 0. 6.45E-05 U234 3.57E-03 0. 2.21E-04 0. 5.98E-04 0. 6.32E-05 U235 3.42E-03 0. 2.07E-04 0. 5.61E-04 0. 8.03E-05 U236 . 3.42E-03 0. 2.12E-04 0. 5.73E-04 0. 5.92E-05 U237 2.36E-07 0. 6.27E-08 0. 6.81E-07 0. 2.08E-05 U238 3.27E-03 0. 1.94E-04 0. 5.24E-04 0. 5.66E-05 NP237 2.36E-03 1.81 E-04 9.79E-05 0. 6.05E-04 0. 8.16E-05 NP238 5.83E-08 1.18E-09 9.08E-10 0. 3.76E-09 0. 4.04E-05 NP239 5.25E-09 3.77E-10 2.65E-10 0. 1.09E-09 0. 2.79E-05 PU238 1.25E-03 1.56E-04 3.16E-05 0. 1.15E-04 0. 7.50E-05 PU239 1.36E-03 1.65E-04 3.31E-05 0. 1.22E-04 0. 6.85E-05 PU240 1.36E-03 1.65E-04 3.31E-05 0. 1.22E-04 0. 6.98E-05 PU241 4.00E-05 1.72E-06 8.04E-07 0. 2.96E-06 0. 1.44E-06 PU242 1.26E-03 1.59E-04 3.19E-05 0. 1.17E-04 0. 6.71E-05 PU244 1.47E-03 1.82E-04 3.65E-05 0. 1.35E-04 0. 1.00E-04 AM241 1.43E-03 6.40E-04 1.02E-04 0. 6.23E-04 0. 7.64E-05 AM242M 1.47E-03 6.25E-04 1.04E-04 0. 6.30E-04 0. 9.61E-05 AM243 1.41E-03 6.14E-04 9.83E-05 0. 6.06E-04 0. 8.95E-05 CM242 8.80E-05 6.73E-05 5.84E-06 0. 1.87E-05 0. 8.16E-05 CM243 1.33E-03 6.03E-04 8.24E-05 0. 3.08E-04 0. 8.03E-05 CM244 1.11E-03 5.36E-04 6.93E-05 0. 2.54E-04 0. 7.77E-05 CM245 1.76E-03 6.64E-04 1.05E-04 0. 4.11E-04 0. 7.24E-05 CM246 1.74E-03 6.64E-04 1.05E-04 0. 4.10E-04 0. 7.11E-05 CM247 1.70E-03 6.53E-04 1.03E-04 0. 4.04E-04 0. 9.35E-05 CM248 1.41E-02 5.38E-03 8.52E-04 0. 3.33E-03 0. 1.51 E-03 CF252 1.07E-03 0. 2.54E-05 0. 0. 0. 2.96E-04
Proc NoODCM Attachment 8 Revision 26 Page 9of16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E~07 BE10 4.48E-06 6.94E-07 1.13E-07 0. S.30E-07 0. 2.84E-OS C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 N13 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 F18 8.64E-07 0. 9.47E-08 0. 0. 0. 7.78E-08 NA22 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71E-OS 1.07E-OS 0. 0. 0. 2.32E-OS AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 1.97E-04 0. 2.13E-OS 0. 0. 0. 1.9SE-07 SC46 7.24E-09 1.41 E-08 4.18E-09 0. 1.3SE-08 0. 4.80E-OS CRS1 0. 0. 3.60E-09 2.00E-09 7.89E-10 S.14E-09 6.0SE-07 MNS4 0. S.90E-06 1.17E-06 0. 1.76E-06 0. 1.21E-OS MNS6 0. 1.S8E-07 2.81E-08 0. 2.00E-07 0. 1.04E-OS FESS 3.78E-06 2.68E-06 6.2SE-07 0. 0. 1.?0E-06 1.16E-06 FES9 S.87E-06 1.37E-OS S.29E-06 0. 0. 4.32E-06 3.24E-OS COS? 0. 2.38E-07 3.99E-07 0. 0. 0. 4.44E-06 COS8 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-OS C060 0 2.81E-06 6.33E-06 0. 0. 0. 3.66E-OS NIS9 1.32E-OS 4.66E-06 2.24E-06 0. 0. 0. 7.31E-07 Nl63 1.77E-04 1.2SE-OS 6.00E-06 0. 0. 0. 1.99E-06 Nl6S 7.49E-07 9.S?E-08 4.36E-08 0. 0. 0. S.193-06 CU64 0. 1.1SE-07 S.41 E-08 0. 2.91E-07 0. 8.92E-06 ZN6S S.76E-06 2.00E-05 9.33E-06 0. 1.28E-OS 0. 8.47E-06 ZN69M 2.40E-07 S.66E-07 S.19E-08 0. 3.44E-07 0. 3.11E-OS ZN69 1.47E-08 2.80E-08 1.96E-09 0. 1.83E-08 0. S.16E-08 SE79 0. 3.73E-06 6.27E-07 0. 6.SOE-06 0. S.?OE-07 BR82 0. 0. 3.04E-06 0. 0. 0. 0. BR83 0. 0. S.74E-08 0. 0. 0. 0. BR84 0. 0. 7.22E-08 0. 0. 0. 0. BR8S 0. 0. 3.0SE-09 0. 0. 0. 0. KR83M 0. 0. 0. . 0. 0. 0. 0. KR8SM 0. 0. 0. 0. 0. 0. 0. KR8S 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 2.98E-OS 1.40E-OS 0. 0. 0. 4.41E-06 RB87 0. 1.7SE-OS 6.11E-06 0. 0. 0. 6.11E-07 RB88 0. 8.S2E-08 4.S4E-08 0. 0. 0. 7.30E-1S RB89 0. S.SOE-08 3.89E-08 0. 0. 0. 8.43E-17 SR89 4.40E-04 0.
- 1.26E-OS 0. 0. 0. S.24E-OS SR90 8.30E-03 0. 2.0SE-03 0. 0. 0. 2.33E-04 SR91 8.0?E-06 0. 3.21E-07 0. 0. 0. 3.66E-OS SR92 3.0SE-06 0. 1.30E-07 0. 0. 0. 7.77E-OS
Proc No ODCM Attachment 8 Revision 26 Page 10of16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 1.37E-08 0. 3.69E-10 0. 0. 0. 1.13E-04 Y91M 1.29E-10 0. 4.93E-12 0. 0. 0. 6.09E-09 Y91 2.01E-07 0. 5.39E-09 0. 0. 0. 8.24E~05 Y92 1.21 E-09 0. 3.50E-11 0. 0. 0. 3.32E-05 Y93 3.83E-09 0. 1.05E-10 0. 0. 0. 1.17E-04 ZR93 5.53E-08 2.73E-08 1.49E-08 0. 9.65E-08 0. 2.58E-05 ZR95 4.12E-08 1.30E-08 8.94E-09 0. 1.91 E-08 0. 3.00E-05 ZR97 2.37E-09 4.69E-10 2.16E-10 0. 7.11E-10 0. 1.27E-04 NB93M 3.44E-08 1.13E-08 2.83E-09 0. 1.32E-08 0. 4.07E-06 NB95 8.22E-09 4.56E-09 2.51E-09 0. 4.42E-09 0. 1.95E-05 NB97 7.37E-11 1.83E-11 6.68E-12 0. 2.14E-11 0. 4.37E-07 M093 0. 1.06E~05 2.90E-07 0. 3.04E-06 0. 1.29E-06 M099 0. 6.03E-06 1.15E-06 0. 1.38E-05 0. 1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0. 1.38E-08 5.14E-10 6.08E-07 TC99 1.79E-07 2.63E-07 7.17E-08 0. 3.34E-06 2.72E-08 6.44E-06 TC101 3.60E-10 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.75E-17 RU103 2.55E-07 0. 1.09E-07 0. 8.99E-07 0. 2.13E-05 RU105 2.18E-08 0. 8.46E-09 0. 2.75E-07 0. 1.76E-05 RU106 3.92E-06 0. 4.94E-07 0. 7.56E-06 0. 1.88E-04 RH105 1.73E-07 1.25E-07 8.20E-08 0. 5.31E-07 0. 1.59E-05 PD107 0. 2.08E-07 1.34E-08 0. 1.88E-06 0. 9.66E-07 PD109 0. 2.51E-07 5.706-08 0. 1.45E-06 0. 2.53E-05 AG110M 2.05E-07 1.94E-07 1.18E-07 0. 3.70E-07 0. 5.45E-05 AG111 8.29E-08 3.44E-08 1.73E-08 0. 1.12E-07 0. 4.80E-05 C0113M 0. 4.51E-06 1.45E-07 0. 4.99E-06 0. 2.71E-05 CD115M 0. 2.60E-06 8.39E-08 0. 2.08E-06 0. 8.23E-05 SN123 4.44E-05 7.29E-07 1.08E-06 5.84E-07 0. 0. 6.71E-05 SN125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. 1.12E-04 SN126 1.16E-04 2.16E-06 3.30E-06 5.69E-07 0. 0. 2.58E-05 SB124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0. 3.386-06 7.80E-05 SB125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0. 2.18E-06 1.93E-05 SB126 1.59E-06 3.25E-08 5.71E-07 8.99E-09 0. 1.14E~06 9.41E-05 SB127 3.63E-07 7.76E-09 1.37E-07 4.08E-09 0. 2.47E-07 6.16E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0. 0. 1.13E-05 TE127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0. 2.41E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0. 1.22E-05 TE129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0. 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0. 2.45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0. 9.39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0. 2.29E-09 TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0. 7.00E-05 TE133M 6.44E-08 3.66E-08 3.56E-08 5.11 E-08 3.62E-07 0. 1.48E-07 TE134 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 0. 1.66E-09 1129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.01E-06 0. 4.57E-07 1130 1.036-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0. 2.29E-06 1131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 0. 1.62E-06
Proc NoODCM Attachment 8 Revision 26 Page 11of16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0. 3.18E-07 1133 2.01E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0. 2.58E-06 1134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0. 5.10E-09 1135 6.10E-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0. 1.74E-06 XE131M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 0. 0. 0. 0. 0. 0. 0. CS134M 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.95E-09 4.05E-08 CS134 8.37E-05 1.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06 CS135 2.78E-05 2.55E-05 5.96E-06 0. 9.73E-06 3.52E-06 4.46E-07 CS136 8.59E-06 3.38E-05 2.27E-05 0. 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 0. 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0. 1.10E-07 1.28E-08 6.76E-11 CS139 4.87E-08 7.17E-08 2.63E-08 0. 5.79E-08 6.34E-09 3.33E-23 BA139 1.39E-07 9.78E-11 4.05E-09 0. 9.22E-11 6.74E-11 1.24E-06 BA140 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05 BA141 6.71E-08 5.01E-11 2.24E-09 0. 4.65E-11 3.43E-11 1.43E-13 BA142 2.99E-08 2.99E-11 1.84E-09 0. 2.53E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71 E-09 4.55E-10 0. 0. 0. 9.82E-05 LA141 4.55E-10 1.40E-10 2.31E-11 0. 0. 0. 2.48E-05 LA142 1.79E-10 7.95E-11 1.98E-11 0. 0. 0. 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0. 4.18E-09 0. 2.54E-05 CE143 2.35E-09 1.71E-06 1.91E-10 0. 7.67E-10 0. 5.14E-05 CE144 6.96E-07 2.88E-07 3.74E-08 0. 1.72E-07 0. 1.75E-04 PR143 1.31 E-08 5.23E-09 6.52E-10 0. 3.04E-09 0. 4.31E-05 PR144 4.30E-11 1.76E-11 2.18E-12 0. 1.01E-11 0. 4.74E-14 ND147 9.38E-09 1.02E-08 6.11E-10 0. 5.99E-09 0. 3.68E-05 PM147 1.05E-07 9.96E-09 4.06E-09 0. 1.90E-08 0. 9.47E-06 PM148M 4.14E-08 1.05E-08 8.21E-09 0. 1.59E-08 0. 6.61E-05 PM148 1.02E-08 1.66E-09 8.36E-10 0. 3.00E-09 0. 9.90E-05 PM149 2.17E-09 3.05E-10 1.25E-10 0. 5.81E-10 0. 4.49E-05 PM151 9.87E-10 1.63E-10 8.25E-11 0. 2.93E-10 0. 3.66E-05 SM151 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06 SM153 1.22E-09 1.01 E-09 7.43E-11 0. 3.30E-10 0. 2.85E-05 EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07 0. 2.17E-05 EU154 7.91E-07 1.02E-07 7.19E-08 0. 4.56E-07 0. 5.39E-05 EU155 1.74E-07 1.68E-08 1.04E-08 0. 6.57E-08 0. 9.63E-05 EU156 1.92E-08 1.44E-08 2.35E-09 0. 9.69E-09 0. 7.36E-05 TB160 6.47E-08 0. 8.07E-09 0. 2.56E-08 0. 4.19E-05 H0166M 3.57E-07 1.10E-07 7.96E-08 0. 1.61E-07 0. 0. W181 1.42E-08 4.58E-09 4.79E-10 0. 0. 0. 3.90E-07 W185 5.79E-07 1.91 E-07 2.02E-08 0. 0. 0. 1.65E-05 W187 1.46E-07 1.19E-07 4.17E-08 0. 0. 0. 3.22E-05
Proc No ODCM Attachment 8 Revision 26 Page 12of16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 1.81E-02 5.44E-03 7.01E-04 0. 1.72E-02 0. 5.74E-05 81210 6.59E-07 4.51E-06 5.66E-08 0. 5.48E-05 0. 5.15E-05 P0210 6.09E-04 1.07E-03 1.23E-04 0. 3.60E-03 0. 6.75E-05 RN222 0. 0. 0. 0. 0. 0. 0. RA223 7.11E-03 1.08E-05 1.42E-03 0. 3.10E-04 0. 3.43E-04 RA224 2.31E-03 5.52E-06 4.61E-04 0. 1.58E-04 0. 3.71E-04 RA225 9.37E-03 1.10E-05 1.876-03 0. 3.15E-04 0. 3.27E-04 RA226 3.22E-01 8.13E-06 2.39E-01 0. 2.32E-04 0. 3.51E-04 RA228 1.37E-01 4.41 E-06 1.51E-01 0. 1.26E-04 0. 5.98E-05 AC225 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.36E-04 AC227 2.05E-03 3.03E-04 1.22E-04 0. 8.81E-05 0. 8.68E-05 TH227 1,96E-05 3.52E-07 5.65E-07 0. 2.01E-06 0. 5.75E-04 TH228 6.80E-04 1.14E-05 2.30E-05 0. 6.41 E-05 0. 5.97E-04 TH229 8.39E-03 1.26E-04 4.11E-04 0. 6.10E-04 0. 5.43E-04 TH230 2.16E-03 1.23E-04 6.00E-05 0. 5.99E-04 0. 6.38E-05 TH232 2.42E-03 1.05E-04 1.63E-04 0. 5.11 E-04 0. 5.43E-05 TH234 1.14E-07 6.68E-09 3.31E-09 0. 3.81E-08 0. 1.21E-04 PA231 4.31E-03 1.62E-04 1.68E-04 0. 9.10E-04 0. 7.60E-05 PA233 7.33E-09 1.41 E-09 1.26E-09 0. 5.32E-09 0. 1.61 E-05 U232 5.89E-03 0. 4.21E-04 0. 6.38E-04 0. 7.19E-05 U233 1.24E-03 0. 7.543-05 0. 2.90E-04 0. 6.65E-05 U234 1.19E-03 0. 7.39E-05 0. 2.85E-04 0. 6.51E-05 U235 1.14E-03 0. 6.94E-05 0. 2.67E-04 0. 8.28E-05 U236 1.14E-03 o. 7.09E-05 0. 2.73E-04 0. 6.11 E-05 U237 7.89E-08 0. 2.10E-08 0. 3.24E-07 0. 2.09E-05 U238 1.09E-03 0. 6.49E-05 0. 2.50E-04 0. 5.83E-05 NP237 1.44E-03 1.25E-04 5.85E-05 0. 4.33E-04 0. 8.41E-05 NP238 1.95E-08 5.22E-10 3.04E-10 0. 1.79E-09 0. 3.83E-05 NP239 1.76E-09 1.66E-10 9.22E-11 0. 5.21E-10 0. 2.67E-05 PU238 7.21E-04 1.02E-04 1.82E-05 0. 7.80E-05 0. 7.73E-05 PU239 8.27E-04 1.12E-04 2.01E-05 0. 8.57E-05 0. 7.06E-05 PU240 8.26E-04 1.12E-04 2.01E-05 0. 8.56E-05 0. 7.19E-05 PU241 1.84E-05 9.42E-07 3.69E-07 0. 1.71 E-06 0. 1:48E-06 PU242 7.66E-04 1.08E-04 1.94E-05 0. 8.256-05 0. 6.92E-05 PU244 8.95E-04 1.236-04 2.22E-05 0. 9.45E-05 0. 1.03E-04 AM241 8.62E-04 3.29E-04 5.75E-05 0. 4.31E-04 0. 7.87E-05 AM242M 8.70E-04 3.19E-04 5.80E-05 0. 4.30E-04 0. 9.90E-05 AM243 8.60E-04 3.17E-04 5.62E-05 0. 4.22E-04 0. 9.23E-05 CM242 2.94E-05 2.97E-05 1.95E-06 0. 8.89E-06 0. 8.40E-05 CM243 6.91E-04 2.86E-04 4.09E-05 0. 1.91 E-04 0. 8.28E-05 CM244 5.32E-04 2.49E-04 3.19E-05 0. 1.49E-04 0. 8.00E-05 CM245 1.07E-03 3.33E-04 6.10E-05 0. 2.85E-04 0. 7.46E-05 CM246 1.06E-03 3.32E-04 6.09E-05 0. 2.84E-04 0. 7.33E-05 CM247 1.03E-03 3.27E-04 6.00E-05 0. 2.80E-04 0. 9.63E-05 CM248 8.606-03 2.69E-03 4.95E-04 0. 2.31E-03 0. 1.55E-03 CR252 3.51E-04 0. 8.37E-06 0. 0. 0. 3.05E-04
Proc No ODCM Attachment 8 Revision 26 Page 13of16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 BE10 3.18E-06 4.91E-07 7.94E-08 0. 3.71E-07 0. 2.68E-05 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 N13 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 F18 6.24E-07 0. 6.92E-08 0. 0. 0. 1.85E-08 NA22 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 NA24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0. 0. 0. 2.17E-05 AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 1.83E-05 0. 2.00E-05 0. 0. 0. 1.84E-07 SC46 5.51E-09 .1.07E-08 3.11 E-09 0. 9.99E-09 0. 5.21E-05 CR51 0. 0. 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN54 0. 4.57E-06 8.72E-07 0. 1.36E-06 0. 1.40E-05 MN56 0. 1.15E-07 2.04E-08 0. 1.46E-07 0. 3.67E-06 FESS 2.75E-06 1.90E-06 4.43E-07 0. 0. 1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91E-06 0. 0. 2.85E-06 3.40E-05 C057 0. 1.75E-07 2.91E-07 0. 0. 0. 4.44E-06 C058 0. 7.45E-07 1.67E-06 0. 0. 0. 1.51 E-05 C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05 Nl59 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07 Nl63 1.30E-04 9.01E-06 4.36E-06 0. 0. 0. 1.88E-06 Nl65 5.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1.74E-06 CU64 0. 8.33E-08 3.91E-08 0. 2.10E-07 0. 7.10E-06 ZN65 4.84E-06 1.54E-05 6.96E-06 0. 1.03E-05 0. 9.70E-06 ZN69M 1.70E-07 4.08E-07 3.73E-08 0. 2.47E-07 0. 2.49E-05 ZN69 1.03E-08 1.97E-08 1.37E-09 0. 1.28E-08 0. 2.96E-09 SE79 0. 2.63E-06 4.39E-07 0. 4.55E-06 0. 5.38E-07 BR82 0. 0. 2.26E~06 0. 0. 0. 2.59E-06 BR83 0. 0. 4.02E-08 0. 0. 0. 5.79E-08 BR84 0. 0. 5.21E-08 0. 0. 0. 4.09E-13 BR85 0. 0. 2.14E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. o, 0. 0. KR85M 0. 0. 0. 0. 0. 0. 0. KR85 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 2.11E-05 9.83E-06 0. 0. 0. 4.16E-06 RB87 0. 1.23E-05 4.28E-06 0. 0. 0. 5.76E-07 RB88 0. 6.0SE-08 3.21E-08 0. 0. 0. 8.36E-19 RB89 0. 4.01E-08 2.82E-08 0. 0. 0. 2.33E-21 SR89 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05 SR90 7.58E-03 0. 1.86E-03 0. 0. 0. 2.19E-04 SR91 5.67E-06 0. 2.29E-07 0. 0. 0. 2.70E-05 SR92 2.15E-06 0. 9.30E-08 0. 0. 0. 4.26E-05
Proc No ODCM Attachment 8 Revision 26 Page 14of16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 9.62E-09 0. 2.58E-10 0. 0. 0. 1.02E-04 Y91M 9.09E-11 0. 3.52E-12 0. 0. 0. 2.67E-10 Y91 1.41E-07 0. 3.77E-09 0. 0. 0. 7.76E-05 Y92 8.45E-10 0. 2.47E-11 0. 0. 0. 1.48E-05 Y93 2.68E-09 0. 7.40E-11 0. 0. 0. 8.50E-05 ZR93 4.18E-08 2.34E-09 1.09E-09 0. 8.87E-09 0. 2.43E-06 ZR95 3.04E-08 9.75E-09 6.60E-09 0. 1.53E-08 0. 3.09E-05 ZR97 1.68E-09 3.39E-10 1.55E-10 0. 5.12E-10 0. 1.05E-04 N893M 2.55E-08 8.32E-09 2.05E-09 0. 9.57E-09 0. 3.84E-06 N895 6.22E-09 3.46E-09 1.86E-09 0. 3.42E-09 0. 2.10E-05 N897 5.22E-11 1.32E-11 4.82E-12 0. 1.54E-11 0. 4.87E-08 M093 0. 7.51E-06 2.03E-07 0. 2.13E-06 0. 1.22E-06 M099 0. 4.31E-06 8.20E-07 0. 9.766-06 0. 9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0. 1.06E-08 3.42E-10 4.13E-07 TC99 1.25E-07 1.86E-07 5.02E-08 0. 2.34E-06 1.58E-08 6.08E-06 TC101 2.54E-10 3.66E-10 3.59E-09 0. 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.16E-05 RU105 1.54E-08 0. 6.08E-09 0. 1."99E-07 0. 9.42E-06 RU106 2.75E-06 0. . 3.48E-07 0. 5.31E-06 0. 1.78E-04 RH105 1.21 E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41 E-05 PD107 0. 1.47E-07 9.40E-09 0. 1.32E-06 0. 9.11E-07 PD109 0. 1.77E-07 3.99E-08 0. 1.01 E-06 0. 1.96E-05 AG110M 1.60E-07 1.48E-07 8.79E-08 0. 2.91E-07 0. 6.04E-05 AG111 5.81E-08 2.43E-08 1.21 E-08 0. 7.84E-08 0. 4.46E-05 CD113M 0. 3.18E-06 1.02E-07 0. 3.50E-06 0. 2.56E-05 CD115M 0. 1.84E-06 5.87E-08 0. 1.46E-06 0. 7.74E~05 8N123 3.11E-05 5.15E-07 7.59E-07 4.38E-07 0. 0. 6.33E-05 8N125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0. 0. 1.04E-04 8N126 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05 88124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0. 2.18E-06 7.95E-05 88125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0. 1.38E-06 1.97E-05 88126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05 88127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 0. 1.53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0. 1.07E-05 TE125M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0. 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.156-08 4.48E-07 0. 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0. 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0. 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0. 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0. 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0. 7.71E-05 TE133M 4.62E-08 2.70E-08 2.60E-08 3.91E-08 2.676-07 0. 6.64E-08 TE134 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 0. 3.59E-11 1129 3.27E-06 2.81E-06 9.21E-06 7.23E-03 6.04E-06 0. 4.44E-07 1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0. 1.92E-06 1131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0. 1.57E-06
Proc No ODCM Attachment 8 Revision 26 Page 15of16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0. 1.02E-07 1133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0. 2.22E-06 1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51E-10 1135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0. 1.31 E-06 XE131M 0. 0. 0. 0. 0. 0. 0. XE133M o. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 0. 0. 0. 0. 0. 0. 0. CS134M 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.58E-08 CS134 6.22E-05 1.48E-04 1.21E-04 0. 4.79E-05 1.59E-05 2.59E-06 CS135 1.95E-05 1.80E-05 7.99E-06 0. 6.81E-06 2.04E-06 4.21E-07 CS136 6.51E-06 2.57E-05 1.85E-05 0. 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.11 E-06 CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.01E-08 7.91E-09 4.65E-13 CS139 3.41 E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.10E-30 BA139 9.70E-08 6.91 E-11 2.84E-09 0. 6.46E-11 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11 1.59E-09 0. 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2.19E-11 1.34E~09 0. 1.85E-11 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10 0. 0. 0. 9.25E-05 LA141 3.19E-10 9.90E-11 1.62E-11 0. 0. 0. 1.18E-05 LA142 1.28E-10 5.82E-11 1.45E-11 0. 0. 0. 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 0. 5.37E-10 0. 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 0. 1.21 E-07 0. 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 0. 2.13E-09 0. 4.03E-05 PR144 3.01E-11 1.25E-11 1.53E-12 0. 7.05E-12 0. 4.33E-18 ND147 6.29E-09 7.27E-09 4.35E-10 0. 4.25E-09 0. 3.49E-05 PM147 7.54E-08 7.09E-09 2.87E-09 0. 1.34E-08 0. 8.93E-06 PM148M 3.07E-08 7.95E-09 6.QSE-09 0. 1.20E-08 0. 6.74E-05 PM148 7.17E-09 1.19E-09 5.99E-10 0. 2.25E-09 0. 9.35E-05 PM149 1.52E-09 2.15E-10 8.78E-11 0. 4.06E-10 0. 4.03E-05 PM151 6.97E-10 1.17E-10 5.91 E-11 0. 2.09E-10 0. 3.22E-05 SM151 6.90E-08 1.19E-08 2.85E-09 0. 1.33E-08 0. 5.25E-06 SM153 8.57E-10 7.15E-10 5.22E-11 0. 2.31E-10 0. 2.55E-05 EU152 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05 EU154 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05 EU155 8.60E-08 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.60E-06 EU156 1.37E-08 1.06E-08 1.71E-09 0. 7.08E-09 0. 7.26E-05 TB160 4.70E-08 0. 5.86E-09 0. 1.94E-08 0. 4.33E-05 H0166M 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0. W181 9.91E-09 3.23E-09 3.46E-10 0. 0. 0. 3.68E-07 W185 4.05E-07 1.35E-07 1.42E-08 0. 0. 0. 1.56E-05 W187 1.03E-07 8.61E-08 3.01E-08 0. 0. 0. 2.82E-05
Proc No ODCM Attachment 8 Revision 26 Page 16of16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.42E-05 81210 4.61E-07 3.18E-06 3.96E-08 0. 3.83E-05 0. 4.75E-05 P0210 3.56E-04 7.56E-04 8.59E-05 0. 2.52E-03 0. 6.36E-05 RN222 0. 0. 0. 0. 0. 0. 0. RA223 4.97E-03 7.65E-06 9.94E-04 0. 2.17E-04 0. 3.21E-04 RA224 1.61 E-03 3.90E-06 3.23E-04 0. 1.10E-04 0. 3.40E-04 RA225 6.56E-03 7.78E-06 1.31 E-03 0. 2.21E-04 0. 3.06E-04 RA226 3.02E-01 5.74E-06 2.20E-01 0. 1.63E-04 0. 3.32E-04 RA228 1.12E-01 3.12E-06 1.21E-01 0. 8.83E-05 0. 5.64E-05 AC225 4.40E-06 6.06E-06 2.96E-07 0. 6.90E-07 0. 4.07E-04 AC227 1.87E-03 2.48E-04 1.11E-04 0. 8.00E-05 0. 8.19E-05 TH227 1.37E-05 2.48E-07 3.95E-07 0. 1.41E-06 0. 5.40E-04 TH228 4.96E-04 8.40E-06 1.68E-05 0. 4.67E-05 0. 5.63E-04 TH229 7.98E-03 1.19E-04 3.91E-04 0. 5.75E-04 0. 5.12E-04 TH230 2.06E-03 1.17E-04 5.70E-05 0. 5.65E-04 0. 6.02E-05 TH232 2.30E-03 1.00E-04 1.50E-04 0. 4.82E-04 0. 5.12E-05 TH234 8.01E-08 4.71E-09 2.31E-09 0. 2.67E-08 0. 1.13E-04 PA231 4.10E-03 1.54E-04 1.59E-04 0. 8.64E-04 0. 7.17E-05 PA233 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. 1.64E-05 U232 4.13E-03 0. 2.95E-04 0. 4.47E-04 0. 6.78E-05 U233 8.71E-04 0. 5.28E-05 0. 2.03E-04 0. 6.27E-05 U234 8.36E-04 0. 5.17E-05 0. 1.99E-04 0. 6.14E-05 U235 8.01E-04 0. 4.86E-05 0. 1.87E-04 0. 7.81E-05 U236 8.01E-04 0. 4.96E-05 0. 1.91 E-04 0. 5.76E-05 U237 5.52E-8 0. 1.47E-08 0. 2.27E-07 0. 1.94E-05 U238 7.67E-04 0. 4.54E-05 0. 1.75E-04 0. 5.50E-05 NP237 1.37E-03 1.19E-04 5.54E-05 0. 4.12E-04 0. 7.94E-05 NP238 1.37E-08 3.69E-10 2.13E-10 0. 1.25E-09 0. 3.43E-05 NP239 1.19E-09 1.17E-10 6.45E-11 0. 3.65E-10 0. 2.40E-05 PU238 6.80E-04 9.58E-05 1.71E-05 0. 7.32E-05 0. 7.30E-05 PU239 7.87E-04 1.06E-04 1.91E-05 0. 8.11E-05 0. 6.66E-05 PU240 7.85E-04 1.06E-04 1.91E-05 0. 8.10E-05 0. 6.78E-05 PU241 1.65E-05 8.44E-07 3.32E-07 0. 1.53E-06 0. 1.40E-06 PU242 7.29E-04 1.02E-04 1.84E-05 0. 7.81E-05 0. 6.53E-05 PU244 8.52E-04 1.17E-04 2.11E-05 0. 8.95E-05 0. 9.73E-05 AM241 8.19E-04 2.88E-04 5.41E-05 0. 4.07E-04 0. 7.42E-05 AM242M 8.24E-04 2.78E-04 5.43E-05 0. 4.05E-04 0. 9.34E-05 AM243 8.18E-04 2.78E-04 5.30E-05 0. 3.99E-04 0. 8.70E-05 CM242 2.06E-05 2.10E-05 1.37E-06 0. 6.22E-06 0. 7.92E-05 CM243 6.39E-04 2.41E-04 3.75E-05 0. 1.75E-04 0. 7.81E-05 CM244 4.83E-04 2.07E-04 2.87E-05 0. 1.34E-04 0. 7.55E-05 CM245 1.02E-03 2.87E-04 5.76E-05 0. 2.69E-04 0. 7.04E-05 CM246 1.01 E-03 2.87E-04 5.75E-05 0. 2.68E-04 0. 6.91E-05 CM247 9.84E-04 2.83E-04 5.67E-05 0. 2.64E-04 0. 9.09E-05 CM248 8.18E-03 2.33E-03 4.67E-04 0. 2.18E-03 0. 1.47E-03 CF252 2.64E-04 0. 6.29E-06 0. 0. 0. 2.88E-04
Proc No ODCM Attachment 9 Revision 26 Page 1of1 PALISADES 10 YEAR X/Q- DIQ DATA USNRC COHPUTER CODE - .XOQDOQ, *v'ERS ION 2
- 0 RUN DATE: 28FEB14
- ~ PALISADES XOQDOQ82 **H* USING 01/01/2004 - l2/-31/20"13 HE.T' DATA **~***
GROUND LEVEL RELEAS.E - TO? OF :coN'.rAINl~NT BUILDING iSP15Cil!'lC POJ:NT.S OF J:'NTI!:RE.3:" REL.El1SE TYPE OF QIREC.TION DISTl\NCE XIQ X/.Q X/Q D/Q ID LOCATION F~OH SI'rE (MILES) (METERS) \ SEC°Jccs. ~lETER} (SE*::!/CUB.METER) (SEC/CUB.METER) (PER SQ.ME.TER) NO DECAY, 2.260 DAY DECAY. 8.000 DAY DECAY UNDEPLETED UfTDEPLETED DEPLETED A SITE BOUNDARY NNE 0 .50 805. l.58E-{)6 I. 5_7E-0:6 l -44J>-06 7. 61E,...09 A. SITE 'BOUNDARY NE 0. 65 1046. 1.23E-06 1.23E-06 l.llE-06 8.80E-09 A SITE BOUNDARY EN.f; 0.87 140.0. 5. 88E-07 5.86E:-07 5.* 19E-07 4 .* 27E-09 A SITE BOUNDARY E 0.82 1320. 6_.99E-07 6.96E-07 6;19E-07 5*. 29E-09
'A SITE BOUNDARY ESE 0.76 1223. 8.34E-07 8 *. 3.lE-07 7.* 42E-07 .6.**93E-09 A ~ITE ~qUNDARY *SE 0.63 1014 .* l. 39:£0:.06 l *. 3.BE-06 1.25E-06 L-25E-0,8.
A .SITE :soUNDARY S;5E 0-.<18 772. 2, 28E-OG '2', 28E.-.o*6 2. 09E-0.6 ':2 .* O}E-.08 A SITE BOUNDARY *s. 0 *. 42 676. 1. 96E-0..6 1. 95E'...06 L 89.E-06 1. llE-(i8 A SITE BOUNDARY SSW 0.48 772. 1. 26E-06 1. 25E,-06 l;15E-06 6.25E-09 A RE.SI DENCE NNE 1.68 ;;:704. 2. 59E-07 2.57E-07 2. HE-07 9 *. 83E-10
.A RE.SI DENCE NE l. l*l 1835. 5, 32E-0.7 5.30E-07 t,.61E-0-7 *3. 39E-0.9 A RESIDENCE ENE 1 .. I.Si 1915. 3.70E-07 3.67E-07 3.19E-07 '2 .. 50E-0.9 A RESIDENCE E 1.67 2688. 2. 43E-0.7 2.4fa..,.07 2 .ME-07 ; 1. 56E;..09 f.. REp!DENCE J;;SE 0.99 1593. 5 .60E-07 5-.58E-07 ~.!)OE-07 4. 43E.:...'a9. .A *RESIDE!~CE SE 0.90 1448
- a .'ozE-67 7 *. 98E-07 7. 06E-07 6.86E-09 A *RESIDENCE SSE 0;80 1287. 1.0SE-06 1.04E-06 9.28E-07 *8.64E-09 A JIBSIDENCE s p.77 1239. i. 87E.-Cr7 7. S<lE-07 6.99E-07 :4 .12E-09 A 'RESIQENCE SSW 0.49 7.89 - l.22E-06 l.21E-06 l .llE-06 6.04E-09 A .GARDEN NNE 1. 75 :2816. 2 .45E-0.7 2.43E-07 2 .. 0SE-07 9.16E-10 A QJ;RDEN *NE 1 .* 67 2688. 3.03E-07 3.0lE-o'7 2.54E_.:07 1. 76E-09 A GARDEN ENE 2.62 4216. l.16E-07 l.HE-07 9.*. 29E'-08 6.34E-10 A *GARDEN E :2.68 4313 *. l .21E-07 1. 20E-07 9.7QE-08 6.83E-10 A GARDEN *ESE 1. 83 2945. 2. 24E-07 2.22E-07 1.86E-07 1.54E-0.9 A Gl\RDEN SE 1.49 2398. 3. 7.7E-07 .3. 75E.-07 3 .. 20E-0.7 *i.a9E-<i9 A GARDEN SSE 0.69 11'10. l.JlE-06 L31E-06 LI 7E-06 l. llE-,08 A ,GARPEN SSW *4 :a2 7757. 4. 54E-08 *l .43E-08 3, 2'8E-08 1.17E"'l0 A GOAT ENE 2.62 4216. l .16E-07 1. 14E-07 '9.29E-08 6.34E-10 A GOAT E 4.25 6840. 6.* 17E-08 6'. 05E-0.8 t,.67E-08 3 .* 0lE...,10 A l3EE,F .CATTLE SE 4.27 6872. 8.0lE-08 7.85E-OB 6:. Q6E,...08 4.~3E'.'..lO
ODCM Appendix A Revision 18 Issued Date 11/17/14 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) IProcess Applicability Exclusion D CLJones I 11/13/14 Procedure Sponsor Date CLJones I 9/17/14 Technical Reviewer Date ALWilliams I 11/11/14 General Manager Plant Operations Date
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page i TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table of Contents I. INTRODUCTION ............................................................................................................ 1 II. DEFINITIONS ................................................................................................................. 1 A. CHANNEL CALIBRATION ............................................................................ 1 B. CHANNEL CHECK ........................................................................................ 1 C. CHANNEL FUNCTIONAL TEST .................................................................... 2 D. SOURCE CHECK .......................................................................................... 2 E. OFFSITE DOSE CALCULATION MANUAL. ................................................. 2 F. GASEOUS RADWASTE TREATMENT SYSTEM ......................................... 2 G. MEMBERS OF THE PUBLIC ......................................................................... 2 H. PROCESS CONTROL PROGRAM (PCP) ..................................................... 3 I. SITE BOUNDARY .......................................................................................... 3 J. UNRESTRICTED AREA ................................................................................ 3 K. VENTILATION EXHAUST TREATMENT SYSTEM ....................................... 3 Ill. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES ..................... 4 A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..................................................................................... 4
- 1. Requirement ............................................................................ 4
- 2. Action ....................................................................................... 4
- 3. Surveillance Requirements .................................................... 4
- 4. Bases .*.......................*............................................................. 5 B. GASEOUS EFFLUENTS DOSE RATE ........................................................ 10
- 1. Requirement .......................................................................... 10
- 2. Action ..................................................................................... 10
- 3. Surveillance Requirements .....................*............................ 10
- 4. Bases ..................................................................................... 11 C. NOBLE GASES DOSE ................................................................................ 12
- 1. Requirement .......................................................................... 12
- 2. Action ..................................................................................... 12
- 3. Surveillance Requirements .................................................. 12
- 4. Bases ..................................................................................... 13
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page ii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table of Contents D. 1-131, 1-133, TRITIUM, AND PARTICULATES ....................................*....... 14
- 1. Requirement *......................................................................... 14
- 2. Action ..................................................................................... 14
- 3. Surveillance Requirements ............................................. '. .... 14
- 4. Bases ..................................................................................... 15 E. GASEOUS WASTE TREATMENT SYSTEM .........................................*..... 19
.1. Requirement .............................................*............................ 19
- 2. Action ..........................................................................*.......... 19
- 3. Surveillance Requirements .................................................. 19
- 4. Bases ............ ,........*......................*........................................ 20 F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 20
- 1. Requirement .......................................................................... 20
- 2. Action ........................................................................*............ 21
- 3. Surveillance Requirements .................................................. 21
- 4. Bases ..................................................................................... 21 G. LIQUID EFFLUENTS CONCENTRATION ................................................... 26
- 1. Requirement ......*................................................................... 26
- 2. Action ...................................................................................... 26
- 3. Surveillance Requirements .................................................. 26
- 4. Bases ..................................................................................... 27 H. LIQUID EFFLUENT DOSE .......................................................................... 30
- 1. Requirement .......................................................................... 30
- 2. Action ................*.................................................................... 30
- 3. Surveillance Requirements ..............................................*... 30
- 4. Bases .....*............................................................................... 31 I. TOTAL DOSE ..............................*............................................................... 32
- 1. Requirement .......................................................................... 32
- 2. Action ..................................................................................... 32
- 3. Surveillance Requirements .................................*................ 33
- 4. Bases ..................................................................................... 34
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page iii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table of Contents J. RADIOLOGICAL ENVIRONMENTAL MONITORING ................................. 35
- 1. Requirement .......................................................................... 35
- 2. Action ..................................................................................... 35
- 3. Surveillance Requirements .................................................. 36
- 4. Bases ..................................................................................... 37 K. SIRW OR TEMPORARY LIQUID STORAGE TANK ................................... 52
- 1. Requirement ................................................................,....... ,. 52
- 2. Action ..................................................................................... 52
- 3. Surveillance Requirement .................................................... 52
- 4. Bases ................................................................*.................... 53 L. SURVEILLANCE REQUIREMENT TIME INTERVALS ............................... 53
- 1. Requirement .......................................................................... 53
- 2. Action ............................................................*......................... 53
- 3. Surveillance Requirements .................................................. 54
- 4. Bases ..................................................................................... 54 M. SEALED SOURCE CONTAMINATION ....... ;............................................... 54
- 1. Requirement .......................................................................... 54
- 2. Action ..................................................................................... 54
- 3. Surveillance Requirements .................................................. 55
- 4. Bases ..................................................................................... 55 IV. REPORTING REQUIREMENTS .................................................................................. 56 A. RADIOLOGICAL EFFLUENT RELEASE REPORT .................................... 56 B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ................... 57 C. NONROUTINE REPORTS ........................................................................... 57 V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS ............................................................................................. 59 A. LICENSEE MODIFICATIONS ...................................................................... 59 B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION ............. 60 VI. ONSITE GROUND WATER MONITORING ................................................................. 61
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page iv TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table of Contents TABLES A-1 Radioactive Gaseous Effluent Monitoring Instrumentation A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 8-1 Radioactive Gaseous Waste Sampling and Analysis Program C-1 Radioactive Liquid Effluent Monitoring Instrumentation C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements D-1 Radioactive Liquid Waste Sampling and Analysis Program E-1 Radiological Environmental Monitoring Program E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples E-3 Detection Capabilities for Environmental Sample Analysis E-4 Radiological Environmental Monitoring Program Locations F-1 Environmental Radiological Monitoring Program Summary
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 1of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) I. INTRODUCTION The NRC, through 10CFR50.36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01, dated January 31, 1989, allowed relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 85, November 9, 1984). The relocated procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program, and associated procectural reporting requirements follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specification to satisfy the regulatory requirements of 10CFR50.36a. The Technical Specifications programmatic controls include requirements for the establishment, implementation, maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well as record retention and reporting requirements. II. DEFINITIONS A. CHANNEL CALIBRATION
- a Channel Calibration shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Function Test.
The Channel Calibration may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. B. 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 instrumentation channels measuring the same parameter.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 2 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) C. CHANNEL FUNCTIONAL TEST
- a Channel Functional Test shall be:
- 1. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.
- 2. Bistable channels - the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functions.
D. SOURCE CHECK
- a source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
E. OFFSITE DOSE CALCULATION MANUAL
- (per Plant Technical Specifications) - the Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain: 1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by the Technical Specifications, and 2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by the Technical Specifications.
F. GASEOUS RADWASTE TREATMENT SYSTEM
- any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
G. MEMBERS OF THE PUBLIC
- all persons who are not occupationally associated with the Plant. This category does not include employees of the utility, its contractors, or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 3 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) H. PROCESS CONTROL PROGRAM (PCP)
- shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Part 20, 10CFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.
I. SITE BOUNDARY
- that line beyond which the land is neither owned nor otherwise controlled by the licensee.
J. UNRESTRICTED AREA
- any area at or beyond the Site Boundary access 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.
K. VENTILATION EXHAUST TREATMENT SYSTEM
- any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 4 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Ill. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
- 1. Requirement The radioactive gaseous effluent monitoring instrumentation channels shown in Table A-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of requirement 111.B.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
- 2. Action
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above requirement, without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Table A-1. Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in, the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- 3. Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check, Source Check, Channel Calibration, and Channel Functional Test operations at the frequencies shown in Table A-2.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 5 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR 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 10CFR Part 50.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 6 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) TableA-1 Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Operable Applicability Action Channels
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor (RIA 1113) Providing Alarm and Automatic Termination of Release (1) At All Times 1
- 2. CONDENSER EVACUATION SYSTEM (RIA 0631)
- a. Noble Gas Activity Monitor (1) Above 210°F 3 Modes 1, 2, 3, 4 Above 210°F
- b. Evacuation Flow Indicator (Fl-0631 or Fl-0632) (1 )*** Modes 1, 2, 3, 4
- 3. STACK GAS EFFLUENT SYSTEM
- a. Noble Gas Activity Monitor (RIA 2326)* (1) At All Times 3
- b. Iodine/Particulate/Sampler/Monitor {RIA 2325) (1) At All Times 6
- c. Sampler Flow Rate Monitor (FE-2346) (1) At All Times 2
- d. Hi Range Noble Gas (RIA 2327)* (1) Above 210°F 4 Modes 1, 2, 3, 4
- 4. STEAM GENERATOR SLOWDOWN VENT SYSTEM
- a. *Noble Gas Activity Monitor (RIA 2320) (1) Above 210°F 3 Modes 1, 2, 3, 4
- 5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE
- a. Gross Gamma Activity Monitor* 1 per Main Above 325°F 4 (RIA 2323 and 2324) Steam Line Modes 1, 2, 3
- 6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM
- a. Noble Gas Activity Monitor ** 1 per Room Above 210°F 5 (RIA 1810 and 1811) Modes 1, 2, 3, 4
- Setpomts for these instruments are exempted from 111.B.1 limits, but are governed by Emergency Implementing Procedures or Operating procedures.
- Setpoints for these instruments are exempted from 111.B.1 limits, but are governed by Technical Specifications SR 3.3.1 Q.3.
- Documentation of operability not required.
- Setpoints for these instruments are exempted from 111.B.1 limits, but are governed by Technical Specifications SR 3.3.1 Q.3.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 7 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table A-1 (Cont'd) TABLE NOTATION -ACTION STATEMENTS ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels requirements, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve line up; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 2 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 24 hours. ACTION 3 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. ACTION4 - With the number of operable channels less than required by the Minimum Operable Channels requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), Within 72 hours, and:
- a. Either restore the inoperable channel(s) to operable status within 7 days of the event, or
- b. Prepare and submit a Special Report to the NRC within 30 days following the event outlining the actions taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.
ACTION 5 - If either channel fails low or is otherwise inoperable, the ventilation dampers associated with that channel shall be closed immediately and action shall be taken to have the affected channel repaired. The dampers associated with the channel shall not be opened until the affected channel has been declared operable. (Reference Technical Specifications LCO 3.3.10.) ACTION 6 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table B-1.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 8 of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Modes in Which Channel Source Channel Instrument Functional Surveillance Check Check Calibration Required Test
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor-Providing Alarm and 0(4) p R(3) Q(1 )(2)
- Automatic Termination of Release *
- 2. CONDENSER EVACUATION SYSTEM
- a. Noble Gas Activity Monitor D M R(3) Q(2) Above 210°F
- b. Evacuation Flow Indicator (Fl-0632) or *** *** *** *** Modes 1, 2, 3, 4
- c. Evacuation Flow Indicator (Fl-0631) *** *** *** ***
- 3. STACK GAS EFFLUENT SYSTEM
- a. Noble Gas Activity Monitor D M R(3) Q(2) *
- b. Iodine Particulate Sampler/Monitor w M** R(3)** NA
- C. Sampler Flow Rate Monitor D NA R NA *
- d. Hi Range Noble Gas D M R(3) Q(2) Above 210°F Modes 1, 2, 3, 4
- 4. STEAM GENERATOR SLOWDOWN VENT SYSTEM Above 210°F
- a. Noble Gas Activity Monitor D M R(3) Q(2) Modes 1, 2, 3, 4
- 5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE Above 325°F D M R(3) Q(2) Modes 1, 2, 3
- a. Gross Gamma Activitv Monitor
- 6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION. SYSTEM
- a. Noble Gas Activity Monitor 12 hours 31 days 18 months (3) 31 days(1)(2) Above 210°F (Technical Specifications SR 3.3.1 O and Modes 1, 2, 3, 4 SR 3.7.13.1)
- At all times other than when the hne 1s valved out and locked.
- Sampler not applicable
- This type of Flowmeter doesn't have any surveillance requirements.
- Sampler not applicable
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 9 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table A-2 (Cont'd) Table Notation (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint. (2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists.
- a. Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3.d, Hi Range Noble Gas).
- b. Circuit failure.
(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.
- b. For subsequent Channel Calibration, sources that have been related to the (1) calibration may be used.
(4) Channel Check shall be made at least once per 24 hours on days on which continuous or batch releases are made. TABLE FREQUENCY NOTATION S At least once per 12 hours D At least once per 24 hours M At least once per 31 days P Prior to radioactive batch release Q At least_ once per 92 days R At least once per 18 months W At least once per week
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 10 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 8. GASEOUS EFFLUENTS DOSE RATE
- 1. Requirement The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For lodine-131, for lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
- 2. Action With the dose rate(s) averaged over a period of one hour exceeding the above limits, without delay, restore the release rate to within the above limit(s).
- 3. Surveillance Requirements
- a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of 8.1.a in accordance with the methodology and parameters in the ODCM.
- b. The dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits of 8.1.b in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 8-1.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CA LC ULATION MANUAL Appendix A Revision 18 Page 11 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This is provided to ensure that the dose at any time at and beyond the Site Boundary from gaseous effluents from all units on the site will be within 10 times the annual dose limits of 10CFR Part 20 to Unrestricted Areas. The annual dose limits are the doses associated with the concentrations of 10 times 10CFR Part 20, Appendix B, Table 2, Column 1. These restrictions provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either within or outside the Site Boundary, to annual exposure greater than design objectives of 10CFR 50, Appendix I, Section 11.B.1. For Members of the Public who may at times be within the Site Boundary, the occupancy of the Member of the Public will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the Site Boundary. Examples of calculations for such Members of the Public, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rate above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mrems/yr to the total body.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 12 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) C. NOBLE GASES DOSE
- 1. Requirement The air dose due to noble gases released in gaseous effluents to areas at and beyond the Site Boundary (see Figure 2-1) 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.
- 2. Action With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRG within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- 3. Surveillance Requirements Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 13 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to implement the requirements of Sections 11.B, Ill.A, and IV.A of Appendix I, 10CFR Part 50. The limiting Condition for Operation implements the guides set forth in Section 11.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 to assure that the releases of radioactive material in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the 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 10CFR 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 ODCM equations provided for determining the air doses at and beyond the Site Boundary are based upon the historical average atmospheric conditions.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 14 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) D. 1-131, 1-133, TRITIUM, AND PARTICULATES
- 1. Requirement The dose to a Member of the Public from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
- 2. Action With the calculated dose from the release of lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit and define(s) the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- 3. Surveillance Requirements Cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 15 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to implement the requirements of Sections 11.C, Ill.A, and IV.A of Appendix I, 10CFR Part 50. The requirements are the guides set forth in Section 11.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 to assure that the releases of radioactive materials in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section II.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials 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 10CFR 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. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate requirements for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 16 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table B-1 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Type Sampling Minimum Type of Lower Limit Frequency Analysis Activity Analysis Detection (LLD)a Frequency (µCi/ml) A. Waste Gas Storage Tank p Each Tank p 4 Grab Sample Each Tank Principal Gamma Emittersb 1 x 10 B. Containment PURGE p Each PURGE p 4 Grab Sample Each PURGE Principal Gamma Emittersb 1 x 10 C. Stack Gas Effluent \,J\f*e Continuousc Charcoal 1-131,1-133 1 x 10*12 Sample
\,/\f*e Continuousc Particulate Principal Gamma Emittersb 1x10*11 Sample Q
Composite Sr-89, Sr-90, and 11 Continuousc 1 x 10" Particulate Gross Alpha Sample Noble Gas Noble Gases 1E-06 Continuousc Monitor Gross Beta or Gamma
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 17 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Gaseous Release Type Sampling Minimum Type of Lower Limit Frequency Analysis Activity Analysis Detection (LLD)a Frequency (µCi/ml) D. Condenser Evacuation System Continuous Noble Gas Noble Gases 1 x 1o-6 Monitor wt Grab w Principal Gamma Emittersb 1 x 10 4
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 18 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table 8-1 (Cont'd) Table Notation a The LLD is defined, in Table E-3, note C. 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 gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report. c The ratio of the sample flow rate to the sample stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with requirements 111.B.1, 111.C.1, and 111.D.1. d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing or after removal from sampler. e With channels operable on iodine monitor RIA 2325 less than required per 111.A.1, sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, start-up or Thermal Power change exceeding 15 percent of Rated Thermal Power in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if, 1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3, and 2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. f Obtain and analyze a gas sample weekly for noble gas quantification.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 19 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) E. GASEOUS WASTE TREATMENT SYSTEM
- 1. Requirement When gaseous waste exceeds a Xe-133 concentration of 1E-05 µCi/cc, the Waste Gas Decay Tank System shall be used to reduce radioactive gaseous effluents by holding gaseous waste collected by the system for a minimum of 15 days.
- 2. Action
- a. If a waste gas decay tank is required to be released with less than 15 days holdup time, the system waste gas tank contents shall be evaluated and the waste gas decay tank with the lowest dose consequence shall be released.
- b. Gaseous waste may be discharged directly from the waste gas surge tank through a high-efficiency filter or from a waste gas decay tank with less than 15 days of holdup directly to the stack for a period not to exceed 7 days if the holdup system equipment is not available and the release rates meet requirements 111.B, C, and D.
- 3. Surveillance Requirements Not Applicable.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 20 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable" by meeting the design objectives given in Section 11.D of Appendix I to 10CFR50.
It is expected that releases of radioactive materials in effluents shall be kept at small fractions of the limits specified in 20.1302 of 10CFR20. At the same time the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in 111.B, C, and D. F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
- 1. Requirement The radioactive liquid effluent monitoring instrumentation channels shown in Table C-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of 111.G are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 21of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 2. Action
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels Operable, take the Action shown in Table C-1. Exert best efforts to return the instruments to Operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- 3. Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated Operable by performance of the Channel Check, Source Check, Channel Calibration, and Channel Functional Test operations at the frequencies shown in Table C-2.
- 4. Bases The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding 10 times the limits of 10CFR 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 10CFR Part 50.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 22 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-1 Radioactive Liquid Effluent Monitoring Instrumentation Minimum Instrument Operable Applicability Action Channels
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line (RIA 1049) (1) For Effluent Releases 1
- b. Steam Generator Slowdown Effluent Line (1) For Effluent Releases 2 (RIA 0707)
- 2. GROSS BETA OR GAMMA RADIOACTIVE MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent Line (RIA 0833) (1) For Effluent Releases 3
- b. Turbine Building (Floor Drains) Sumps Effluent (1) For Effluent Releases 3 Line (RIA 5211)
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line (FIC 1051 or (1) For Effluent Releases 4 1050)
- 4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip Setpoints are not applicable)
- a. Turbine Building Sumps Effluent Line (1) For Effluent Releases 3
- b. Service Water System Effluent (1) For Effluent Releases 3
- c. Steam Generator Slowdown Effluent (1) For Effluent Releases 3
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 23 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-1 (Cont'd) TABLE NOTATION ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with requirements and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 2- With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table D-1 for principle gamma emitters and 1-131 at least once per 12 hours. The Steam Generator blowdown monitor is normally used in a clean up closed NOTE: loop system instead of as an effluent monitor. The action statement only applies when the monitor is used as an effluent monitor. ACTION 3- With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided that, at least once per 24 hours, grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table D-1 for principle gamma emitters and 1-131. ACTION 4- With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves or tank levels may be used to estimate flow.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 24 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Channel Instrument Functional Check Check Calibration Test
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line (RIA 1049) p p R(3) Q(1)(2)
- b. Steam Generator Slowdown Effluent Line (RIA 0707) D M R(3) Q(1)(2)
- 2. GROSS GAMMA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent Line (RIA 0833) D M R(3) Q(2)
- b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211) D M R(3) Q(2)
- 3. FLOW RATE MEASUREMENT DEVICES (5)
- a. Liquid Radwaste Effluent Line (FIC 1051 or 1050) 0(4) NA R NA
- 4. TURBINE SUMP EFFLUENT COMPOSITER 0(4) NA NA NA
- 5. SERVICE WATER SYSTEM EFFLUENT COMPOSITE SAMPLER 0(4) NA NA NA
- 6. STEAM GENERATOR SLOWDOWN EFFLUENT COMPOSITER 0(4) NA NA NA
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 25 of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-2 (Cont'd) TABLE NOTATION (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint. (2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists:
- a. Instrument indicates measured levels above the alarm setpoint.
- b. Circuit failure.
(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.
- b. For subsequent Channel Calibration, sources that have been related to the (a) calibration may be used.
(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check shall be made at least once per 24 hours on days on which continuous or batch releases are made. (5) Turbine Sump Discharge Flow Meter FQl-5210 was calibrated at factory and doesn't require recalibration. TABLE FREQUENCY NOTATION D At least once per 24 hours Q At least once per 92 days M At least once per 31 days R At least once per 18 months p Prior to radioactive batch release w At least once per week
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 26 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) G. LIQUID EFFLUENTS CONCENTRATION
- 1. Requirement The concentration of radioactive material released in liquid effluents to Unrestricted Areas shall be limited to 10 times the concentrations specified in 10CFR Part 20, Appendix 8, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/ml total activity.
- 2. Action With the concentration of radioactive material released in liquid effluents to Unrestricted Areas exceeding the above limits, without delay, restore the concentration to within the above limits.
- 3. Surveillance Requirements
- a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table D-1.
- b. The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of G.1 above.
PALISADES NUCLEAR PLANT ODOM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 27 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to Unrestricted Areas will be less than 10 times the concentration levels specified in 10CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in Unrestricted Areas will result in exposures within the Section II.A design objectives of Appendix I, 10CFR Part 50, to a Member of the Public. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and 10 times the effluent concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination*_ Application to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 28 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table D-1 Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Type Sampling Minimum Analysis Type of Activity Analysis Lower Limit Frequency Frequency Detection (LLD)a (µCi/ml) A. Batch Waste Release Tanksu p p Principal Gamma Emittersc 5x10"7 Each Batch Each Batch 1-131 1 x 10"6 p M Dissolved and Entrained Gases 5 1x10" One Batch/M (Gamma Emitters) p M H-3 1 x 10-5 Each Batch Composited Gross Alpha 1x10"7 p Q Sr-89, Sr-90 5 x 10"8 Each Batch Composited Fe-55, Ni-63 1x10"6 B. Continuous Releasese Continuous' w Principal Gamma Emittersc 5x10"7 1 6 (Turbine Sump, Steam Generator Composite 1-131 1x10" Slowdown, and Service Water) M M Dissolved and Entrained Gases Grab Sample (Gamma Emitters) 1 x 10"5 Continuous' M H-3 1 x 10"5 1 Composite Gross Alpha 1x10*7 Continuous' Q Sr-89, Sr-90 5 x 10" 8 Composite1 Frequency Notation P Prior to batch release M Calendar month Q Calendar quarter W Calendar week
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 29 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table D-1 (Cont'd) TABLE NOTATION a The LLD is defined, in Table E-3, Note C. b A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. c The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144*. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.
- LLD - 5E-06 because of low gamma yields.
d A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. e A continuous release is the discharge of liquid wastes of a nondiscrete volume; eg, from a volume of a system that has an input flow during the continuous release. f To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in a series of aliquots of constant volume collected at regular time intervals and combined to form a single sample. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 30 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) H. LIQUID EFFLUENT DOSE
- 1. Requirement The dose or dose commitment to a Member of the Public from radioactive materials in liquid effluents released from each reactor unit to Unrestricted Areas shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
- 2. Action With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include the results of radiological analyses of the drinking water source.
- 3. Surveillance Requirements 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 the ODCM at least once every 31 days.
- PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 31of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix I, 10CFR 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 to Unrestricted Areas will be kept "as low as is reasonably achievable." Also, for freshwater sites with drinking water supplies that 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 40CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials 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 10CFR 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 32 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) I. TOTAL DOSE
- 1. Requirement The annual (calendar year) dose or dose commitment to any Member of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
- 2. Action With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of 111.C.1.a, 111.C.1.b, 111.D.1.a, 111.D.1.b, 111.H.1.a, or 111.H.1.b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of 111.1.1 have been exceeded. If such is the case, prepare and submit to the NRC within 30 days a Special Report 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 10CFR Part 20.2203, 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 concentrations of radioactive material involved and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR Part 190. Submittal of the report is considered a timely request and a variance is granted until staff action on the request is complete.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 33 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 750~0)
- 3. Surveillance Requirements
- a. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with 111.C.1, 111.D.1, and 111.H.1 and in accordance with the methodology and parameters in the ODCM.
- b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Action 1.2 above.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 34 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to meet the dose limitations of 40CFR Part 190 that have been incorporated into 10CFR Part 20 by 46 FR 18525. It also requires the preparation and submittal of a Special Report whenever the calculated doses from Plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except for thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a Member of the Public will exceed the dose limits of 40CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a Member of the Public to within the 40CFR Part 190 limits. For the 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 40CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR Part 190 have not already been corrected), in accordance with the provisions of 40CFR Part 190.11 and 10CFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10CFR 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 35 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) J. RADIOLOGICAL ENVIRONMENTAL MONITORING
- 1. Requirement The radiological environmental monitoring program shall be conducted as specified in Table E-1.
- 2. Action
- a. With the radiological environmental monitoring program not being conducted as specified in Table E... 1, prepare and submit to the NRG, in the Annual Radiological Environmental Operating Report a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity as the result of Plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table E-2 when averaged over any calendar quarter, prepare and submit to the NRG within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents. When more than one of the radionuclides in Table E-2 are detected in the sampling medium, this report shall be submitted if:
Concentration (1) + Concentration (2) + .... ~ 1.0 Reporting Level (1) Reporting Level (2) When radionuclides other than those in Table E-2 are detected and are the result of Plant effluents, this report shall be submitted if the potential annual dose to a Member of the Public is equal to or greater than the calendar year limits of 111.C.1, 111.D.1, and 111.H.1. 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 36 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table E-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radiological Environmental Report.
- 3. Surveillance Requirements
- a. The radiological environmental monitoring samples shall be collected pursuant to Table E-1 and shall be analyzed pursuant to the requirements of Table E-1 and the detection capabilities required by Table E-3.
- b. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 9 overland meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 tt2) producing broad leaf vegetation.
- c. The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report and shall be included in a revision of the ODCM for use in the following calendar year.
- d. Analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program that has been approved by the NRC.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 37 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- e. A summary of the results obtained as part of the above required lnterlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.
- f. The environmental air samplers shall be operationally checked monthly and airflow verified annually.
- 4. Bases
- a. Monitoring Program The radiological environmental monitoring program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of Members of the Public resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR Part 50 and 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 the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table E-3 are considered optimum for routine environmental measurements in industrial laboratories. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-92 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-15 (June 1975).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CA LC ULATION MANUAL Appendix A Revision 18 Page 38 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- b. Land Use Census:
This requirement is provided to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the radiological environmental monitoring program are made if required by results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR Part 50. Restricting the census to gardens of greater than 50 m2 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 (16 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (ie, similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2 .
- c. lnterlaboratory Comparison Program:
The requirement for participation in an approved lnterlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR Part 50.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 39 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-1 Radiological Environmental Monitoring Program Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locations 3 Collection Frequency of Analysis
- 1. DIRECT RADIATIONb 23 routine monitoring stations either with two or Quarterly Gamma dose quarterly more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
One on site TLD in the vicinity of the Plant. An inner ring of stations, one in each overland meteorological sector (9) in the general area of the Site Boundary and one additional location near the State Park camping area in the NE sector. An outer ring of stations, one in each overland meteorological sector (9) within the 12 km range from the site. The balance of the stations (3) to be placed to serve as control stations.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 40 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis
- 2. AIRBORNE Radioiodine and Samples from 5 locations. Continuous sample Radioiodine Canister:
Particulates operation with sample 1-131 analysis weekly for 3 samples from within 6 km of the Site Boundary collection weekly or more each filter change. in different sectors (2.5 km-SSW, 5.8 km-ESE frequently if required by and .96 km-NE). dust loading. Particulate Sam12ler: Gross beta radioactivity 1 sample from the vicinity of a community having analysis following filter the highest calculated annual average ground changed. Gamma isotopice level D/Q (Covert-6.2 km-SE). analysis on quarterly composite 1 sample from a control location in the least prevalent wind directionc (Grand Rapids 82 km-NE)h.
- 3. WATERBORNE
- a. Lake (surface) Plant lake water inlet. Composite sample over Gamma isotopice and tritium 1-month periodt. analyses monthly.
- b. Lake (drinking) 1 sample of South Haven drinking water supply. Composite sample over Gamma isotopice, gross 1-month periodt. beta, and tritium analyses
'- monthly.
1 sample from a control location (Ludington Composite sample over Gamma isotopice, gross Pumped Storage 201 km N) 1-month periodt. beta, and tritium analyses monthly.
- c. Well (drinking) 1 grab sample per month when Palisades Park 1 grab sample per month Gamma isotopice and tritium community drinking water well is in operation when operational analyses monthly when (Park is seasonal in operations and is only open Park is operational.
for the summer months)
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 41 of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis
- d. Sediment from 1 sample from between north boundary and Van Semiannually Gamma isotopice analysis shoreline Buren State Park beach, approximately Yz mile semiannually.
north of the Plant discharge.
- 4. INGESTION 0
- a. Milk Samples from milking animals in 3 locations Monthly Gamma isotopic and 1-131 between 5-8 km distance. analyses monthly.
0 1 sample from milking animals at a control location, Monthly Gamma isotopic and 1-131 15-30 km distance. analyses monthly. 0
- b. Broad leaf Samples of 3 different kinds of broad leaf vegetation Monthly during growing Gamma isotopic and 1-131 vegetation grown nearest each of two different offsite locations season analyses of highest predicted annual average ground level D/Q if milk sample is not performed. (SE or SSE sectors near site.)
0 1 sample of each of the similar broad leaf vegetation Monthly during growing Gamma isotopic and 1-131 grown 15-30 km distance in the least prevalent wind season analyses direction if milk sampling is not performed. (NNE or NE sectors.) 0
- c. Fish Sample 2 species of commercially and/or Sample in season or Gamma isotopic analysis recreationally important species in vicinity of Plant semiannually if they are discharge area. 1 sample of same species in areas not seasonal.
not influenced by Plant discharge.
- d. Food Products 1 sample each of two principal fruit crops At time of harvest9 0 Gamma isotopic and 1-131 (blueberries and apples). analyses.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page42 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-1 (Cont'd) Table Notation a Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. b One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors or phosphor readout zones in a packet are considered as two or more dosimeters. c 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 that provide valid background data may be substituted. d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. e Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. f A composite sample is one in which the .quantity (aliquot) of liquid samples is proportional to the quantity of liquid discharged and in which the method of sampling employed results in a specimen that is representative of the liquid released {continuous composites or daily grab composites which meet this criteria are acceptable). g If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. h The Control Air sample results from Cook Nuclear Plant, except Coloma, may be used as a backup of the Grand Rapids control.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 43 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 {TAC NO 75060) Table E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Reporting Levels Water Airborne Particulates Fish Milk Food Products Analysis 3 (pCi/I) or Gases (pCi/m ) (pCi/kg, Wet) (pCi/I) (pCi/kg, Wet) H-3 20,000* Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
- For drinking water samples. This is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 44 of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)bc Water Airborne Particulates Fish Milk Food Products Sediment Analysis 3 (pCi/I) or Gases (pCi/m ) (pCi/kg, Wet) (pCi/I) (pCi/kg, Wet) (pCi/kg, Dry) Gross Beta 4 0.01 H-3 2,000* Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1d 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15
- If no drinking water pathway exists, a value of 3,000 pCi/I may be used.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 45 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 (Cont'd) TABLE NOTATION a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. c The LLD 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% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD= 4.66 x Sb Ex V x 2.22 x Y x Exp(-A-M) Where: LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume. sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute. E is the counting efficiency, as counts per disintegration. V is the sample size in units of mass or volume. 2.22 is the number of disintegrations per minute per picocurie. Y is the fractional radiochemical yield, when applicable. A is the radioactive decay constant for the particular radionuclide. LH for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting. Typical values of E, V, Y, and Lit should be used in the calculation.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 46 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 (Cont'd) Table Notation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 47 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS Seven Mile Map
*.. ' *{~_ 'J. ***. ' ~
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 48 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS Four Mile Map
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 49 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER89-01 (TAC NO 75060) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS TLDs Location Coordinates Distance (miles) DeQrees Sector Stack N 42 19 22.5 w 86 18 50.8 1 N 42 19 20.5 0.213 100.36 E w 86 18 36.1 Inner Ring 13 N 42 19 47.2 0.530 26.56 NNE w 86 18 34.1 8 N 42 19 46.8 0.602 39.19 NE w 861824.0 14 N 42 19 41.1 0.551 49.64 NE w 8618 21.2 15 N 42 19 41.7 0.834 63.76 ENE w 86 17 58.1 16 N 42 19 28.0 0.804 82.45 E w 86 17 54.6 17 N 42 19 10.5 0.572 113.74 ESE w 86 18 13.9 18 N 42 19 4.2 0.469 138.49 SE w 86 18 28.9 19 N42190.9 0.443 159.19 SSE w 86 18 39.7 20 N 42 19 1.1 0.412 176.05 s w 86 18 48.8 21 N42193.4 0.382 196.40 SSW w 86 18 58.4 Outer Ring - Displayed on 7 mile map 7 N 42 22 40.8 4.115 22.35 NNE w 86 17 0.4 6 N 42 22 30.6 5.314 47.18 NE w 86 14 15.9 23 N 42 20 44.6 3.189 60.37 ENE w 8615 35.4 24 N 42 19 59.5 6.021 83.19 E w 86 11 49.4 5 N 42 18 27.6 3.475 107.63 ESE w 8614 57.5 4 N 42 17 10.8 3.668 133.54 SE w 86 15 43.5 3 N 42 14 37.9 5.684 163.92 SSE w 86 16 60.0
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 50 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS TLDs Location Coordinates Distance (miles) Degrees Sector 2 N 42 14 33.4 S.560 183.7S s W861916.4 9 N 4218 1.73 1.670 201.86 SSW W8619 34.6 Control TLDs 10 N 42 53 16.7 S0.746 39.49 NE was 40 3S.9 11 N 42 1S 24.S 39.472 96.39 E was 32 49.3 12 N 41 S6 54.3 27.971 1S7.61 SSE W86 6 24.S TLD 10 is located within the Consumers Energy Grand Rapids service facility attached to a pole located adjacent to the south fence. TLD 11 is located within Consumers Energy Kalamazoo service facility attached to a pole in the far NE corner of the facility, past the employee parking lot. TLD 12 is located approximately 30 yards from the road, NE and next to a private residence located at S8399 Wilbur Road, Dowagiac, Ml. ' A"Ir SampleI Sta1ons f Location Coordinates Distance (miles) Degrees Sector AB (State Park) N 42 19 46.8 O.S95 38.34 NE w 86 18 24.8 A9 (Township N42184.6 1.S2S 191.38 SSW Park) w 86 19 12.0 A4 (Covert) N421712.1 3.882 130.12 SE w 861S 21.7 AS (Rood) N 42 18 30.5 3.590 106.12 ESE W861447.8 A10 (Grand N 42 S3 16.7 S0.765 39.S2 NE Rapids) was 40 33.8 Air Sample Station 10 is located within Consumers Energy Grand Rapids service facility, south side, next to a small service building and due east of TLD 10. Control fish and water samples are normally obtained from the Consumers Energy Pump Storage Facility located in Ludington, Ml or another location not influenced by Palisades plant discharges.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 51of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Palisade Park Wells Location Coordinates Distance (miles) Degrees Sector Community Well N 42 18 47.5 0.729 203.63 SSW w 86 19 11.4 Commercial Well N 42 18 48.5 .652 175.06 s w 86 18 46.8 The Community Well services the community residents with well water to their homes; the Commercial Well services the community gardens and drinking fountains on the east side of the property.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 52 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) K. SIRW OR TEMPORARY LIQUID STORAGE TANK
- 1. Requirement The concentration of radioactive material (excluding tritium and noble gases) contained in the SIRW tank or any unprotected outside temporary tank* shall be limited such that the mixture radionuclides do not exceed 1,000 times the effluent concentration (EC) as listed in 10CFR Part 20, Appendix B, Table 2, Column 2 .
.Qg + ~ ... + ~ = < 1000 ECa ECb ECi
- 2. Action With the quantity of radioactive material in any of the above listed tanks exceeding the above concentration, immediately suspend all additions of radioactive material to the tank, within 48 hours reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radiological Effluent Release Report.
- 3. Surveillance Requirement The concentration of radioactive material contained in each of the above listed tanks 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 materials are being added to the tank.
A calculational methodology performed prior to the material being transferred may be used to show compliance with the requirement of this section if a representative sample cannot be obtained at least once per seven days. A representative sample of the radioactive material to be added to the SIRW or Temporary Liquid Storage Tank shall be analyzed and a calculation performed to show compliance with the 1000 EC limit.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 53 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement will provide reasonable assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10CFR Part 20, Appendix B; Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an Unrestricted Area.
(The dilution between Palisades and the South Haven drinking water supply has been established as 1000.)
*Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
NOTE: The limit for the SIRW Tank may be exceeded for operational flexibility if the conditions of this section are met. L. SURVEILLANCE REQUIREMENT TIME INTERVALS
- 1. Requirement 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.
- 2. Action Failure to perform a Surveillance Requirement within the allowed surveillance interval shall constitute noncompliance with the operability requirements. The time limits of the action requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The action requirements may be delayed for up to 24 hours to permit the completion of the surveillance when the allowed outage time limits of the action requirements are less than 24 hours.
Surveillance Requirements do not have to be performed on inoperable equipment.
PALISADES NUCLEAR PLANT ODCM CFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 54 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 3. Surveillance Requirements The applicable surveillance interval frequencies are specified in Tables A-2 and C-2. The applicable sampling and/or analysis frequencies are specified in Tables A-1, B-1, C-1, D-1, and E-1.
Extendable surveillance requirements are limited to Channel Checks, Source Checks, Channel Calibrations, Channel Functional Checks, sampling frequencies and/or analysis frequencies.
- 4. Bases The maximum allowable extension for a surveillance interval *is consistent with the surveillance requirements specified in the Technical Specifications, Section 4.0. Until relocated in the ODCM, all of the effluent surveillances were subject to these same requirements.
M. SEALED SOURCE CONTAMINATION
- 1. Requirement Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.
- 2. Action
- a. With a sealed source having removable contamination in excess of 0.005 microcuries, immediately withdraw the sealed source from use and either:
(1) Decontaminate and repair the sealed source, or (2) Dispose of the sealed source in accordance with applicable regulations.
- b. A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 55 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 3. Surveillance Requirements
- a. Each category of sealed sources as described in the requirement with a half-life greater than 30 days (excluding Hydrogen-3), and in any other form than gas, shall be tested for leakage and/or contamination at intervals not to exceed 6 months.
- b. The test shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
- c. The test sample shall be taken from the sealed source or, in the case of permanently mounted sources, from the surfaces of the mounting device on which contamination would be expected to accumulate.
- d. The periodic leak test does not apply to sealed sources that are stored and not being used. These sources shall be tested prior to use or transfer to another licensee, unless tested within the previous 6 months. Sealed sources which ari continuously enclosed within a shielded mechanism (ie, sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
- e. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed in use.
- 4. Bases The requirement, actions, and surveillance requirements are the same as contained in the Technical Specifications 6.21 prior to relocation to the ODCM and will provide assurance that sealed sources are tested to demonstrate that source integrity is being maintained.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 56 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) IV. REPORTING REQUIREMENTS A. RADIOLOGICAL EFFLUENT RELEASE REPORT The Radioactive Effluent Release Report (RERR) shall be submitted in accordance with 10CFR 50.36a prior to May 1 of each year. The report shall include a summary of the quantities of liquid and gaseous effluents and solid waste released as outlined in Regulatory Guide 1.21, R1, Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants, with data summarized on a quarterly basis following the format of Appendix B, thereof. The following information shall also be included in the RERR:
- Assessment of the radiation doses due to the liquid and gaseous effluents released during the previous year
- Inoperable effluent radiation monitors that exceeded 30 continuous days; explain causes of inoperability and actions taken to prevent reoccurrence
- Evaluation to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation
- Unplanned releases of radioactive materials in gaseous or liquid effluents to unrestricted areas on a quarterly basis
- Any changes to this procedure made during the reporting period
- Groundwater monitoring results taken in support of the Groundwater Protection Initiative, but are not part of the REMP Solid radioactive waste data shall be reported as follows:
- Type of waste (example: spent resin, dry waste. Irradiated components)
- Volume in cubic meters, include estimated error
- Curie quantity per type of waste, include estimated error
- Principal radionuclides in each category
- Disposition of waste shipments and irradiated fuel shipments (identify number of shipments mode of transport and destination)
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 57 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in: (1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix 1 to 10CFR50. The Annual Radiological Environmental Operating Reports shall include summaries, interpretation and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the Plant operation on the environment. The reports shall also include the results of land use census pursuant to 111.J.3.c. The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results in the format of Table F-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, 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. The reports shall also include the following; a summary description of the radiological environmental monitoring program, including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by 111.J.3.c and results of the lnterlaboratory Comparison Program required by 111.J.3.e. C. NONROUTINE REPORTS A report shall be submitted to the NRC in the event that: 1) the Radiological Environmental Monitoring Programs are not substantially conducted as described in Section 111.J, or 2) an unusual or important event occurs from Plant operation that causes a significant environmental impact or affects a potential environmental impact. Reports shall be submitted within 30 days.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 58 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table F-1 Environmental Radiological Monitoring Program Summarv Name of Facility Docket No Location of Facility Reporting Period _ _ _ _ _ __ (County, State Type/Total Lower Limit All Indicator Medium or Pathway Control Locations Number of Number of of Locations Name Mean (~b Sampled Mean<!t REPORTABLE Analyses Detectiona Mean (~b Distance & Direction Range (Unit of Measure) Range OCCURRENCES Performed (LLD) Range Air Particulates Gross r.. 416 0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/104)- 1 (pCi/m 3 ) (200/312) 5 miles 340° (0.08-2.0) (0.05-1.40) y-Spec 32 (0.05-2.0) Cs-137 0.003 0.05 (4/24) Smithville 0.08 (2/4) <LLD 4 (0.03-0.13) 2.5 miles 160° (0.03-0.13) Ba-140 0.003 0.03 (2/24) Podunk 0.05 (2/4) 0.02 (1/8) 1 (0.01-0.08) 4 miles 270° (0.01-0.08) Sr-89 40 0.002 <LLD -- -- <LLD 0 Sr-90 40 0.0003 <LLD -- -- <LLD 0 Fish y-Spec 8 pCi/kg (dry weight) <LLD Cs-137 80 -- <LLD 90 (1/4) 0
<LLD Cs-134 80 -- <LLD <LLD 0 120 (3/4)
Co-60 80 (90-200) River Mile 35 See <LLD 0 Podunk River Column 4 a Nominal Lower Limit of Detection (LLD) as defined in table notation c.ofTable E-3. b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is indicated in parentheses (f). NOTE: The example data are provided for illustrative purposes only.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 59 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS A. LICENSEE MODIFICATIONS Licensee initiated major modifications to the radioactive liquid and gaseous waste systems.
- 1. Shall be reported to the NRC pursuant to 10CFR 50.59. The discussion of each modification shall contain:
- a. A summary of the evaluation that led to the determination that the modification could be made in accordance with 10CFR Part 50.59.
- b. A description of the equipment, components and processes involved, and the interfaces with other Plant systems.
- c. Documentation of the fact that the modification was reviewed and found acceptable by the PRC.
- 2. Shall become effective upon review and acceptance by the General Manager Plant Operations.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 60 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 8. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION 1.
Purpose:
The purpose of this definition is to assure that this requirement will be satisfied under clearly identifiable circumstances, and with the objective that current radwaste system capabilities are not jeopardized.
- 2. Definition:
A major radwaste system modification is a modification which would remove (either by bypassing for greater than 7 days or physical removal) or replace with less efficient equipment, any components of the radwaste system:
- a. Letdown filters or demineralizers.
- b. Vacuum degassifier (not applicable when the reactor is in cold shutdown and depressurized).
- c. Miscellaneous or clean waste evaporators.
- d. The present waste gas compressor/decay tank system.
- e. Fuel Pool filters/demineralizers.
- f. Radwaste polishing demineralizers.
- g. Radwaste Solidification system.
Improvements or additions to improve efficiency will not be considered major modifications unless a complete substitution of equipment or systems is made with equipment of unrelated design. Examples would be: 1) replacement of mechanical degassifier with steam, jet degassifier, 2) replacement of waste gas system with cryogenic system, 3) replacement of asphalt solidification with cement system, and 4) change from deep bead resins to Powdex, etc.
- PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 61of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
VI. ONSITE GROUND WATER MONITORING Palisades installed 5 ground water monitoring wells in 2007 and added an additional 9 wells in 2008. These wells were installed in response to NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document. These wells are strategically placed within the Owner Controlled Area, both inside and outside the Protected Area to allow detection of radioactive contamination of ground water due to leaks or spills from plant systems.
ODCM Appendix B DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR 20.302 Revision 0 August 1, 1991 Approved KM Haas 8/20/91 MRN Manager - ~adiological Services Date TP Neal 8/1/91 RMC Administrator Date ML Grogan 8/14/91 Tech Review Date PF Bruce 9l-082d 8/14/91 Date Applicability Reviewed: ---'Tu...P.u.:Ne=aw....l_-=5~/~5/~9~3_ _ Gerald B. Slade 11/30/93 Pl ant General Manager .. Date Applicability Reviewed: ~ s-,/(ffe-
ODCK Appendix B Page 1 Request to Retain Soil in Accordance with 10CFR 20.302 Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose of contaminated soil in place as specified by 10CFR 20.302. The area known as the South Radwaste Area has been contaminated by numerous cooling tower overflows and contamination was redistributed by heavy rain showers. Although the majority of the radioactive material has been packed for waste shipment, a large volume of very low activity radioactive material remains. This volume of material would be very expensive to ship as waste. The specific area contaminated is noted as Area B on the attached survey grid map in reference 1. The entire area is fenced and is about 12,000 sq ft of soil exposed with the remainder buildings and asphalt. The inhalation pathway is for breathing suspended soil from this area. The radworker could receive 8.03E-04 mRem/50-year maximum organ (liver) dose and the infant could receive 3.16E-05 mRem/50-year maximum organ (liver) dose, both of which are insignificant. Direct dose to a radworker is less than 2E-03 mRem/hr. Occupancy in this area should not average more than 2 hours/week or 100 hours/year, which would result in a dose of <1 mRem/year. The radwaste activities which caused the contamination of the soil were completely relocated to a new east radwaste area. The South Building has been deconned and is being used for non-radwaste activities. Some fixed contamination is present in floor cracks and vaults. This has been documented for plant decommissioning. No further contamination will be added to the south area from the South Radwaste Building. In spite of this commitment, revocation of Michigan shipping privileges in November 1990 require the use of this area to store packaged low level radioactive waste (LLW). Use of this building is addressed in CPCo's letter to NRC Document_ Control Desk, April 24, 1991 which is entered as reference 6. This LLW, in the form of dry active waste (DAW) will be packaged in metal boxes and labeled, ready for future shipment to burial sites. The DAW metal shipping boxes will be stored off the floor to prevent water damage. The metal shipping boxes are strong, tight containers designed to prevent any leakage of radioactive material during transportation. Incidental water contact will not result in the spread of contamination. Radioactive waste will not be processed in the South Radwaste Building and the bullding will be maintained as a normally clean (radiologically) area. Rev 0 8-1-91
ODCH Appendix B Page 2 References (1) CPCo's letters, T.C. Bordine to NRC Document Control Desk, November 12, 1987 and January 25, 1988. (2) Memorandum from L.J. Cunningham, DREP to T.R. Quay, T.V. Vambach, "Request for Additional Information (RAI)", March 15, 1988, April 7, 1989, and January 12, 1990. * (3) CPCo's supplement to Reference (1), J.L. Kuemin to NRC Document Control Desk, June 27, 1988. (4) CPCo's supplement to References (1, 2), G.B. Slade to NRC Document Control Desk, August 31, 1990. (5) CPCo's letter, T.P. Neal to B. Holian, October 23, 1990. (Typo of 10/13/90 in original reference). (6) CPCo's letter, G.B. Slade to NRC Document Control Desk, April 24, 1991.
"Use of South Storage Building as an Interim Radi6active Yaste Storage Building".
(7) NRC Letter, Brian Holian to G.B. Slade, CPCo, June 7, 1991, "Approval and Conditions to Retain Soil in Place". Rev O 8-1-91
ODCM - APPENDIX B REFERENCE 1 consumers Power POWERING MICHlliAN'S l'IUIGllES5 General Offlc.. : 1945 Wen Pernell Roed, Jackson, Ml 49201 * (5171 788-0550 November 12, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH IOCFR20.302 The Code of Federal Regulations, Title IO, section 20.302 allows for approval of proposed procedures to dispose of licensed material in a manner not other-wise authorized in the regulations. Flooding of the South Radwaste Building has caused contamination of 4,173 cubic feet of soil with 2,992.6 µCi of N Cs-137 and 79.3 µCi of Co-60. The area is approximately 30 meters from Lake Michigan. Site hydrology (Attachment 2, FSAR 2.2) indicates most of the activity will ~!grate to Lake Michigan in a few years. In July, 1986 a two-fold evaluation began to identify and map the extent of the ground contamination in the flood plain. The initial findings and evaluation were provided to NRC and the Michigan Department of Public Health by internal letter dated September 26, 1986, to LHueter, NRC, Region III. Consumers Power Company requests authorization to dispose of this soil inplace as the costs of disposal at a burial ground is estimated at $270,000 while radiological consequences to the general public and site employees is very low. The activities in the contaminated soil were input as a single radio-active liquid release to Lake Michigan into the NRC LADTAP Code. The output indicated an estimated wholebody dose to the general public (50 mile radius population l.05E06) of I.69E-02 manRem or I.6E-OS millirem per person. The maximum estimated wholebody dose to an individual would be 5.13E-03 millirem and maximum organ dose (teenage liver) would be 8.67E-03 millirem. The maximum whole body dose rate was assumed to be at 18 inches from contaminated soil. The maximum whole body dose rate calculated using the Microshield Code was I.02E-02 mR/hr. Occupancy of this area is controlled by the Radiological Safety Department and secured by a locked fence. Average yearly occupancy is approximately 8 hours per week per individual for 4 to 5 individuals. *A radiation worker should not exceed an additional wholebody dose of 4.08 millirem/year. Flooding of the South Radwaste Building as a result of the cooling tower overflows is being addressed in two stages. "For the short term the cooling tower bypass valve is now electrically isolated during cooling tower opera-tion. Most previous flooding has been due to instrument failures that cause the valve to open during normal operation. In addition the South Radwaste Building has been decontaminated to eliminate ~r minimize contamination that TPN-HPOl-~01 Rev O 8-1-9"1
Nuclear Regulatory Commission 2 Palisades Plant 10CFR20.302 Request November 12, 1987 could be transported to the environment. A long term solution to remove radwaste activities from this area is being included in the Five-Year Plan. The activity released to the environment from a flooding release prior to 1986 was estimated and added to the liquid section of the Semi-Annual Radiological Effluent Release Report dated February 28, 1986. Following approval of this application, it is proposed .to account for current activity as an abnormal liquid release included in the semi-annual effluent report. A background, evaluation and survey results discussion follows in Attachment A. Attachment 1 is the Microshield Code output and Attachment 2 is FSAR section 2.2 (including referenced tables and figures) on site hydrology. Pursuant to 10CFR170.12(c) a check in the amount of $150 is attached. Thomas C Bordine (Signed) Thomas C Bordine Administrator, Nuclear Licensing ('"'. CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment TPN-HPOl-NLOl Rev 0 8-1-91
ATTACHMENT A Consumers Power Company Palisades Plant Docket 50-255 EVALUATION AND SURVEY RESULTS November 12, 1987 10 Pages TPN-HPOl-NLOl Rev O 8-1-91
1
Background
In 1986, a soil survey was conducted south of the Turbine Building which included the South Radwaste area. The survey was conducted due to the South Radwaste Building being in the main flowpath of 'A' Cooling Tower, which has overflowed on three separate occasions in 8 years. The survey found that radioactive material was deposited in the soil due to the flooding of contami-nation and radioactive material areas inside the South Radwaste Building. Other areas sampled that were not in the flood plain were; liquid radwaste storage tanks, T-90, T-91, storm drains, the beach and the sand dunes. The survey included a survey grid, surface sample results and core sample results. All contaminated areas found in Are~ A (Figure 1) were packaged as radwaste. In addition, the highest activity areas adjoining the South Radwaste Building were also packaged. A total of 16-98 cubic foot boxes were packaged containing over 85 percent of the estimated activity.
- Evaluation In August of 1987, the survey was conduc.ted again to prepare this report and to verify the location of the ground contamination and if any contamination migrated further into the ground since the 1986 su~ey. The survey was a two phase evaluation with the first phase being a mapped area consisting of 25' x 25' ~quares south of the Turbine Building. Once mapped out, surface samples were taken in this area. The intent of this phase was to accurately map the location and determine the activity in µCi/gram of all ground surface contami~
nation. Each surface sample consisted of approximately 20 grams of soil taken Rev 0 MI0987-0066A-NL02 8-1-91
2 from the top l / 211 of gr*ound and placed in a petri dish for analysis on the Multi-Channel Analyzer (MCA). Over 275 samples were collected and analyzed with two surface samples being taken in each sector. All.samples were counted on MCA, Intrinsic Detector #1. Figure 2 shows the sector where activity was detected and their highest levels in µCi/gram. Phase II was initiated after completion of the "surface" sample analysis. This consisted of taking core samples in 6" increments where activity was detected. Core samples were taken until two consecutive core ~amples reflected no activ-ity. Core samples were also taken below the activity levels found in the 1986 soil survey until two consecutive core samples revealed no activity. Figure 3 indicates the depth level where activity was no longer detectable. For example, 6 inches is indicated in H-10 on Figure 3. This indicates that activity was only detected on the surface. H-9 and I-10 indicate 18" which tn means activity was detected only at 12 11
- Table 1 shows the results summary in
µCi/gram of the highest activity at all sample locations. The sector numbers respond to grid coordinates shown on Figures 1, 2 and 3.
In addition to the sample sectors shown on Figure 1, 25 samples were collected at various locations on site. These include surface and core samples around T-90, and T-91 on the Northwest side of the Turbine Building (location not shown on figures). Surface samples were taken under the asphalt around the South Radwaste Building. These are indicated by a hexagon on Figure 1 in F-11, I-12 and K-10 sectors. Core samples taken under the South Radwaste Building are indicated by circles on Figure 1. Of the areas sampled above activity was Rev a* MI0987-0066A-NL02 8-1-91
3 found only under the East side of the So.uth Radwaste Building in sector I-9 (Table 1). In *the 1986 soil survey other areas were sampled that were not in the flood plain of the South Radwaste Building. Those included Feedwater Purity Build-ing, North Storage Building, beach areas North and South of Plant, North and Northeast sand *dunes and various storm drains. In all of these areas no activity was detected. Therefore, they were not sampled in the 1987 soil survey as they were not in *the flood plain. Since the 1986 soil survey, asphalt has been placed over various locations in the protected area. Asphalt was placed around all storm drains and approx!- mately 50% of the South end of the Turbine Building. Before asphalt was laid down. about 3-6" of the top soil was removed and taken offsite. The soil before leaving site was sampled and counted with no activity detected. !.n Results To quantify activity and determine impact, the areas of ground contamination were separated into two areas. Area A which contains all the sectors (A-L, 1-8) North of the "black top" to the Turbine Building. Area B contains all sectors (C-L. 9-14) South of "black top" in the vicinity of the South Radwaste Build.ing. In Area A no activity was detected, therefore it was not used in determining activity or impact. Rev 0 MI0987-0066A-NL02 8-1-91
4 In *Area B activity was detected in almost all sectors to the East of the South Ra_dwaste Building (Figur'e 2). Activities r~nged from 2 .07E-6 µCi/gram (E-11) to 3.75E-5 µCi/gram (H-11). Cs-137 was the primary radionuclide present in all samples with two other samples containing Co~60 l.12E-5 µCi/gram at 6" and 5.80E-6 µCi/gram at 12" (I-9 East Figure 2). The greatest depth where activity was detected was in sector H..:11 at 18" and when compared to the 1986 soil survey the activity has migrated down into the soil 6" inches further. Activity was detected at the surf~ce in sectors E-11, E-13, J-12 and L-9 and at 6" in L-9. This was a result of moving the sand deposited on the asphalt during the flood to these sectors and the movement of soil during the grading and dumping during the asphalting of the South Radwaste area. Activity in µCi was calculated for each sector (Table 2) by the following formula: sector ft 2 x depth of activity ft x *48144 grams/ft 3 x activity (µCi/gram) ~ µCi. *Average liter of soil weighed 1700 grams x 28.32 L/ft 3
- tn 48144 grams/ft 3
- The first level at which no activity was detected was used to
~ determine depth of activity. In a few sectors, activity was only detected on the first 1/2" of soil, but for determining cubic feet and activity a depth of 6" was use_d. For example, activity for .H-10 was calculated as follows: 625 ft 2 x .5 ft. depth x 48144 grams/ft 3 x 2.6E-6 µCi/gram activity of surface sample equals 39.12 µCi.
Total volume in cubic feet and total activity in µC~ were calculated for each sector of Area B. For sectors with activity, the highest activity detected per sector was used in* the µCi calculation. Total contaminated area in Area B is Rev 0 MI0987-0066A-NL02 8-1-91
5 4173 ft 3 , total activity is 3071.9 µCi. Sector H-11 contains 73.5% of the
- total activity which comprises 14.5% of the total contaminated area of Area B.
To quantify the dose to the population projections, 2992.6 µCi of Cs-137 and 79.3 µCi of Co-60 was entered into the LADTAP computer program. Assuming that the total 3071.9 µCi was eventually released to Lake Michigan thru the water table, and the uptake pathways which included fish, drinking, swimming, boating and shoreline the 50 mile population estimated at l.05E6 would receive a total body dose of l.69E-2 manRem, or l.61E-5 millirem per person. The maximum wholebody do.se to an individual* would be 5 .13E-3 millirem and maximum organ dose (teenage liver) would be 8.67E-03 millirem. Direct dose to an individual working in the affected areas was calculated using the MICROSHIELD code. The activities from sec;ors H-11 and I-9 were used for a dose 18 inches above the surface. The dose rates from H-11 and I-9 are tn 8.75E-06 R/hr .and l.02E*05 R/hr respectively (Attachment 1). Therefore, a 50 hour occupancy in one week could result in a maximum exposure of 0.51 millirem. Normal occupancy of this area is on an as needed bases and averages less than 8 hours/week per individual in contact with contaminated soil. Rev O MI0987-0066A-NL02 8-1-91
Table 1 Soil Sample Core Results Cuci/gram) Sector Surf ace 6.. 12 11 18 11 24 30 11 36 11 42" 48" E-11 E-13
' 2.07£-6 4.39E-6
<HDA
<HDA
<HDA
<HDA
<HDA
<HDA H-9 4 .19E-6 <HDA 4.79E-6 <HDA <HDA <HDA H-10 2.60£-6 <HDA <HDA H-11 3. 75E-5 <HDA <HDA 8.45E-6 <HDA <HDA <HDA I-9 1.24£-5 <HDA <HDA I-10 <HDA <HDA 5.39£-6 <HDA <HDA <HDA <HDA <HDA J-9 5.39E-6 <HDA <HDA J-12 6.39E-6 <HDA <HDA L-9 * <HDA 6. 77£-6 <HDA <HDA T-90 <HDA <H~A 0 T-91 <HDA <HDA
**I-9 #1 <HDA <HDA <HDA' <HDA <Hl>A <HDA <HDA
<HDA <HDA
'°'N **I-9 #2
**I-10 #3
**I-11 #4
<HDA
<HOA
<HDA l.40E-5* 5.80E-6+
<HDA
<HDA
<HDA <HDA 0
***K-10 <HDA
>h'n':J-12 <HDA
*>""F-11 <HDA
+ Activity is all Co-60
- Includes l.12E-5 µCi/gram of Co-60. All other activities listed were identified as Cs-137.
'°'* Core samples unde.r foundation of the South Radwaste Building.
*** Surface ~amples ~nder asphalt in South Radwaste area.
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7 Table 2 Activity Calculations per Sector Area B Sector IJ Sq.ft. x Depth ::z ft 3 x g/ft 3 X uCi/g = Total uCi. E-11 375 0.5 187.5 48144 2. 07E-6 18.7 E-13 375 0.5 187.5 48144 4.39E-6 39.6 H-9 625 1.5 937.5 48144 4. 79E-6 216.2 H-10 625 o.s 312.5 48144 2.60E-6 39.l H-11 625 2.0 1250.0* 48144 3.75E-5 2256.8* I-9 527 0.5 263.5 48144 l.24E-5 157.3 I-10 275 1.5 412.5 48144 5 .39E-6 107 .o J-9 450 0 .5 225 48144 5*.39E-6 58.4 J-12 200 0.5 100 48144 6.39E-6 30.8 L-9 150 1.0 150 48144 6.77E-6 48.9 I-9 east 98 1.5 147 48144 l.40E-5 . 99.1 4325 4173 3071.9 '° N
*1250 = *2256.8 =
0 73.5% of total activity Ln 'q" 1' ~ Rev 0 HI0986-0062A-HP01 8-1-91
FIGURE~ SURVEY ...- GRID I. LEGEND ~ ASPHALT AREAS LI . 21*
- 21* SECTORS 0 ARE.\ *s*
µ (f=l AREA "" ():) !:O I <D I-'~ I AUGUST 1987
\0 o.
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AUGUST 1987 =1GURE 2 SURFACE ASPHALT AREAS ():> !:ti *EXAMPLE . ONLY I CD I-' < I
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. UNDER FOUNDATION .
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ATTACHMENT l Consumers Power Company Palisades Plant Docket 50-255 r.n ..o. N MICROSHIELD CODE OUTPUT November 12, 1987 8 Pages TPN-HPOl-NLOl Rev O 8-1-91
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ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 FSAR SECTION 2.2 - SITE HYDROLOGY November 12, 1987 r..n
~
10 Pages Rev 0 TPN-HPOl-NLOl 8-1-91
2.2 HYDROLOGY The Palisades Plant site is surrounded on the north, east and south sides by sand dunes. The west side of the site is the Lake Michigan shoreline. As a result of this local topography, the site drainage is independent of the Brandywine Creek drainage basin which drains the hinterland. All sur-face water runoff drains directly to the lake and the percolating runoff also discharges to the lake (see Reference 3). There are no data available to verify the amount of surface runoff from the site; however, the flow from the Brandywine Creek drainage basin should be useful for the putpose of comparison: Data obtained to establish base flow.figures for Van Buren County streams indicate that the Brandywine Cree~drainage basin is about 17 square miles (see Reference 4). The average annual rainfall for the area is 34 inches. During the period September 1962 to O~tober 1963, the base flow measure-ments varied from a minimum of 0.90 cubic feet per second (ft 3 /s) to a maximum of 11.4 ft 3 /s. This resulted in a mean annual 7-day minimum flow of 1.6 ft 3 /s or 0.094 ft 3 /s/sq mi (cubic feet per second per square mile). The period of stream measurements was representatiye of drought conditions. The deposits of Brandywine Creek drainage basin are of low permeability which results in ~ nearly total runoff to Lake Michigan. This runoff prob-ably occurs soon after precipitation. Minor groundwater storage in the oLd beach and reworked older.sandy lake deposits observed on the surface to the east of the site area probably maintain Brandywine Creek during periods of low rainfall *. 2.2.1 GROUNDWATER Almost all the water used in Van Buren County is obtained from wells. r.n Exceptions are the City of South Haven that obtains its municipal suppiy from Lake Mi;chigan and some irrigation supplies th.a.t are obtained from streams, lakes and local ditches (see Reference 4). The glacial drift.is the only known source of fresh groundwater in the county. All the glacial deposits are capable of yielding some water to wells, but the sand and gravel outwash deposits yield the largest quantities (see Reference 4). The area of sand dunes along Lake Michigan is not generally favorable for obtaining large supplies of groundwater. Probably most of the dune sand is above the water table and most wells must be drilled into the underlying,, lake deposits (see Reference 4). *
- 1. General Groundwater levels were established by the 1966 Geology and Groundwater Investigation conducted by Bechtel Company for Consumers Power Company (see Reference 3). The results of the investigation are shown on Figure 2-9.
It is rea*dily apparent that subsurface drainage is generally westward fsl281-129la-09-72 2.2-1 Rev 0 8-1-91
ATTACH.'1E~T ' toward the lake (see Profile A-A). Minor variations; ie, flow toward surface streams, may exist but are not considered significant. An average hydraulic gradient toward the lake of about 13 feet per mile was obtained along Profile A*A as shown on Figure 2*9. This gradient repre-sents only the upper surface of unconfined groundwater. Water released on the surface would move toward the lake at an estimated rate of 650 feet per year (see Reference 3). The nearest domestic wells to the site are located one-half mile to the east and south. The data indicates that groundwater in the vicinity of the eastern wells is flowing west toward the site. Local groundwater in the area of the southern wells is also flowing west toward the lake, perpendic-ular to the shoreline. There are no major sources of groundwater withdrawal, eg, large-scale industrial or agricultural pumping, that might reverse the direction of groundwater flow and cause groundwater to flow from the Plant area toward any existing domestic wells. Without such pumping, it is difficult to envis1on a condition which would cause sufficient groundwater lowering at any of the domestic wells such that the direction of flow might be reversed.
- 2. Plant Site Groundwater levels in the vicinity of the site are shown on Figure 2-9.
The water table generally slopes toward the lake. During the site inve~ti gations, groundwater elevations averaged 580 feet MSL beneath the building site. This elevation corresponds to the approximate mean level of Lake Michigan. As shown by water levels measured during drilling, groundwater levels rise *to the east to approximately 604 feet MSL beneath the switch* yard and 601 fee~ MSL near the eastern site boundary (see Reference 3). Field permeability tests performed during the 1965 exploratory drilling yielded values ranging from 30 to 1,720 feet per year in the site area, Table 2-11. In Drill Hole S, located approximately 500 feet northwest of the containment ~uilding, the permeability values ranged from 30.4 feet per year to 143 feet per year. In Drill Hole 7, located approximately 650 feet south of the containment building,- the permeability values ranged from 156 feet per year to 1,720 feet per year.
- 3. Groundwater Movement An unconfined aquifer is present in the dune area with groundwater levels controlled by the level of Lake Michigan. The rate of movement of ground-water downward into material underlying the dunes appears to be very slow.
Nine samples from Drill Hole 22 in the site area were tested (or sodium ab-sorption ratio (SAR), Table 2*12. A high SAR indicates poor downward per-colation of water due to sodium deposition on and between soil particles. At the Plant site, the SAR is considered to be high between elevations 596 and 566 feet MSL and low between 566 and 555 feet MSL (see Reference 3). fsl281-129la-09-72 2.2-2 Rev 0 8-1-91
Groundwater levels and permeability data from the sandy lake deposits underlying the dunes indicate a slow rate of discharge into Lake ~ichigan .
. 4. Conclusions
- a. Groundwater in the unconfined aquifer moves westerly from the Brandywine Creek basin to Lake Michigan.
- b. The hydraulic gradient is approximately 13 feet per mile and flow is essentially perpendicular to the shoreline.
- c. Water discharged on the ground surface at the Plant site will percolate downward at a slow rate and mix with groundwater moving toward Lake Michigan.
- d. Infiltration of surface water from the site to domestic wells offsite does not appear to be possible under present groundwater conditions.
2.2.2 GENERAL LAI<E HYDROLOGY
- 1. Lake Levels The level of Lake Michigan is cyclic and is expected to fluctuate with time and is dependent on long*term above-normal or below-normal amounts of pre-
- cipitation. The highest monthly mean stage of Lake Michigan was 583.68 feet MSL in 1886. Subsequent modifications in the St Clair River and the opening of the diversion out of the basin at Chicago have tended to reduce the maximum level attainable. During the recent period of record (1900 to present), the highest recorded monthly mean stage was 582.6 feet MSL in July 1974, and the lowest monthly mean stage was 576.91 feet MSL in March and April 1964 (see Reference 5). Great Lakes levels are reported t.n using International Great Lakes Datwn which is converted to MSL at the Palisades site by adding 1.558 feet. The l.558*foot correction factor is taken from the reference point at St Joseph, Michigan.
Short*time variations in lake levels (seiches), caused by meteorological factors and measured in hours rath.er than days, occur occasionally. The greatest level change of this type on record over a 105*year period in* volved a sudden.rise of 6 feet at Michigan City, Indiana (8:10 AM, June 26, 1954) and a rise of 8 feet at Montrose Harbor, Chicago (9:30 AM on the same date) (see Reference 6). These seiches were reported in the "Science" article by Ewing, Press and Donn (Vol 120, Page 684). On passing into tGe shallow water at Michigan City, the wave was reflected and refracted to reach the Chicago shore of the lake. The US Lake Survey gauge at Holland, Michigan, which is 30 miles north of the Palisades site and has similar lake geometry to the site, indicated no surge on June 26, 1954. As part of the Syst.ematic Evaluation Program (SEP Topic II-3.B), the maxi-mum probable surge elevation, was reevaluated. The offshore sur.ge value was reevaluated to produce an onshore surge height of 10.9 feet. The maximum monthly mean level was also* reduced from 583.6 feet MSL to 582.6 feet MSL. fs1281-1291a-09-72 2.2*3 Rev 0 8-1-91
This resulted in a probable maximum flood protection level for the Palisades Plant of 593.5 *feet MSL. The service water pump motors at 594.7 feet MSL provide the basis for determining the minimum flood protection requirements for the Plant. Therefore, the resultant wave surges from Lake Michigan do not present a problem at Palisades.
- 2. Water Movements Conclusions from a study of lake hydrology in the Palisades Park, Michigan area by Dr J L Hough (see Reference 6) indicate that surface currents gen-erated by wind conditions and .modified by the earth's rotation and lake configuration will provide adequate mixing of Plant liquid effluents into the lake. The study included actual measurements of lake water movement in the area near the.Plant site, and water mixing where the Black River enters Lake Michigan at South Haven.
A summary of the study is as follows: Lake water is almost constantly moving past the Palisades site, with an appreci~ble velocity of flow, under the influence of winds. It is es-timated, on the basis of wind records, that an alongshore current flows northward about 33\ o*f the time and an alongshore current flows south-ward about 23% of the time. Offshore drift of surface water should occur about 38% of the time, according to frequency of offshore winds, but these would have a minimal effect close to shore, which is bordered by a high dune ridge. It is likely, therefore, that the alongshore currents would tend to persist, once set up, while offshore winds were blowing. Thus, the frequency of alongshore current flow is probably greater* than the 33% and 23% based on wind directions. Under the procedure of taking water from a depth of about 20 feet, 3,500 feet offshore, raising its temperature as it is used for service water and dilution of c~oling tower blowdown, and returning the efflu~ ent to the lake near shore, the effluent water will almost always be warmer than the lake water into which it is discharged. This is because- a sin-gle take Michigan water mass is involved during most. of the year. When the effluent is warmer, it will tend to float at the surface, to drift with the surface current, and to be mixed by surface turbulence due to wave action. On rare occasions, during the spring wa~ing period when the upper layer of lake water is less than 20 feet deep, and during the summer when strong offshore winds *cause a thinning of the normally deep surface mass to less* than 20 feet, the intake
- water coming from a colder layer may not be warmed in the Plant suf fic-iently to have a temperature higher than that of the surface lake water. At such times, the effluent water will tend to sink to the thermocline and it will not be subject to vigorous turbulence caused by surface wave action. It will tend to mix more slowly.
Surveys of the performance of Black River water, entering Lake Michigan at South Haven under various weather conditions, have indicated that fsl281-129la-09-72 2.2-4 Rev 0 8-l-9l
the river water is diluted rapidly, reaching a concentration of ab~ut only 1% in ~he lake witbin a mile of the river mouth. The disch~rge of the Black River was evaluated because the rate was deter-mined to be nearly the same as the discharge* rate from the Palisades Plant with once-through coolidg. Since th~ Plant is now operated with cooling towers, the discharge to the lake has been reduced to approximately 60,000 gpm or about 1/7 the original rate. The mixing and dilution factors are considered to be as great as during the higher discharge periods and the discharge concentrations should be diluted at least 1,000 times by the time the discharge could reach the public water intake at South Haven, Michigan.
- 3. Conclusions
- a. The level of Lake Michigan is cyclic; howeve.r, the recorded high of 1886 is unlikely to be exceeded. High lake levels are not expected to present a problem at the Plant site.
- b. There is no recorded evidence of short-time variations in lak*e levels (s.eiches) along the eastern shore of Lake Michigan which would be expected to affect the Plant site.
- c. Surface currents generated by wind conditions and modified by the earth's rotation and lake c~.nfiguration will provide adequate mixing of Plant liquid effluents into the lake.
r.n fs128l-1291a-09*72 2.2-S Rev 0 B-1-91
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TABU 2-U FIELD PERMEABILITY TEST RESULTS Drill Hole Elevation Flow "Q" Head "H" Permeabil ity 3"K" Number of Test ( G12m) (Feet) (ft/Yr) (cm /s) 5 576 0.0029 12.3 30.4 0.3 x 10-_,4 570 0.0101 12.3 106.0 l. 1 l( 10 '+ 4 565 0.0088 12.3 92.0 0.89 l( 10-560 0.0035 12.3 36.8 0.36 x 10-~ 555 0.0136 12.3 143.0 1.4 x 10-... 4 550 0.0064 12.3 67.0 0.65 x 10- 4 545 0.0033 12.3 34.6 0.34 l( 10-4 Average 72.8 0. 72 x 10 "' 4 0 7 580 0.0303 25 156 1.5 x l0- 4 575 0.0477 25 246 2. 4 l( 10"' 4 Q) 570 0.0588 25 303 2.9 l( 10- 4 565 0.0588 25 303 2.9 l( 10- 4
- 't 560 0.0834 25 430 4.2 x 10- 4
,,.... 550 0.3333 25 1,720 16.7 x 10- 4 545 0.0677 25 350 3.4 x lo"' 4 540 0.2500 25 1,290 12.5 l< lo-* 4 535 0.2000 25 11035 10. 1 l( 10-4 Average 648 6.3 x 10"' t.n
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TABLE 2*12 ANALYSES OF SOIL SA...'1PLES Saturation Extract Values Millieguivalents Eer Liter Sample Sample No ....£!L ECe Caldwn Magnesium Sodium SAR DescriEtion 1 8.2S 1.2 0.5 Trace 11. 7 23.5 DH 22 El 596
*2 8.4 1.4 0.5 Trace 13.0 26 DH 22 El 59 l.
J 8.3 1.3 o.s Trace 12.3 24.5 DH 22 El 586 4 8.45 1.4 0.5 Trace 14.4 29 DH 22 El 581 5 8.5 1.5 0.5 0.1 14.8 27 DH 22 El 576 6 8.3 1.5 0.5 Trace 14.8 29.5 DH 22 El 571
*7 8.5 1.3 0.5 0.05 12: 7 24 DH 22 El 566 N
8 8.2 0.5 J,O 0.4 1. 1 1 DH 22 El 561 9 8.1 0.6 3.4 0.7 2.4 1.5 DH 22 El 555 ECe ~ Millimhos per centimeter SAR = Sodium adsorption ratio on saturation extract tn . ,.., v fsl281-129lo-09-72 Rev 0 8-1-91
LEGEllD I SITE PROPERTY BOUMDARY & EXCLUSION AREA 2 l'GWER BLOCK PUN 3 CIRCULATING WATER COOLIMG TOWERS
' SITE COllTOUR INTERVALS Of 20' IMCREHENTS 5 3300 FOOT INTAKE PIPE TO CRIB Ii DISCHARGE STRUCTURE 1 PARllllG
- 8. TOl'OGllAPlllC ELEVATIONS IN FEET ABOVE MUI SU LEVEL N
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'-,, 10 COOl llN (A.E.P.) CO CONSUMERS POWER COMPANY PALISADES PLANT FSAR UPDATE
. *' --* . SITE LAYOUT 677 METEIS IEAREST ACCESS ROAD 19UIOARY POllT TO COllTA1114ENT f IGURE 110 2-2 CP ~
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- FSAR UPDATE SITE TOPOGKAfHY,
- r; CllllltO. . IHllWALI a' IOl116 LOCATIOllS, AID SEISMIC PllOFILU tn*
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.arug!!.A=A_PAll'ilLLEL TO 241h 51. LOCAJEll .:I UIL[5 SOUTH.
ANO AREA GRADIENTS FIGURE 110 2-9 REVISION NO . 0 CX> :::0 I CD f--' < I
'00 f--' ATTACllMENT 2
consumers Power POWERING MICHlliAN"S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788*0550 January 25, 1988 Nuclear Regulatory Co1m11ission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR.20.302 Consumers Power Company letter dated November 12, 1987, requested authori-zation to dispose of soil in place as specified by 10CFR.20.302. The letter
*included the results of a survey and evaluation performed in*August, 1987.
Following submittal of that letter, a cooling tower overflow on November 13, 1987 again flooded the South Radwaste Building. The flooding caused additional activity that necessitated Consumers Power Company to request placing our November 12, 1987 request on hold until further evaluation and surveys could be completed. This letter includes the results of our evaluation and survey of the November 13, 1987 flooding incident and is intended to supplement our original November 12, 1987 request. Following the cooling tower overflow, a survey indicated additional activity ' had been released from the building. The building was being maintained in a non~contaminated condition to prevent this type of occurrence; however, during this period a destructive testing program on waste packages was being con-ducted in a small area of the building. The survey clearly showed the release of activ~ty from the building adjoining the testing area, The top six inches of soil from the sectors adjoining the building were removed"and packaged (588 cubic feet) to prevent additional dispersion of radioactivity. The area was then completely resurveyed. An evaluation of the August 1987 and November 1987 (post packaging) activities is att.ached. The survey indicates a drop of 49% in activities between the August and.November surveys. We propose the activities specified in the November 12, 1987 submittal be used ~s jµstification for the request because they are consei::vative. In addition since the November 13, 1987 flooding and following the most recent survey the area was subject to.heavy rains which could have diluted some activities to below minimum detectable activity (MDA is nominally lE-06 µCi/g), Rev 0 OC0188-0018-NL02 8-1-91
- Nuclear Regulatory Commission 2 Palisades Nuclear Plant Retain Soil in Accord. with 10CFR20.302 January 25, 1988 The one non-conservative value from our August survey and evaluation is* the maximum dose rate at 18 inches above the surface. The November survey value from MICROSHIELD is 1.17 mR/hr as opposed to 1.02 mR/hr. This small increase only slightly changes the radiation workers' conservative dose estimate from 4.08 mR/year to 4.7 mR/year.
*Following approval of this application, it is p*roposed to account for the most conservative values of activity, which was stated in the November 12, 1987 submittal, as an abnormal release in the semi-annual report. In order to prevent recurrence of these releases to the environment, Consumers Power Company is also committing to transfer radwaste activities from this area, except for high level vault use which is not a potential flooding release problem.
Relocation of these activities to a new radwaste facility is currently scheduled to.be completed in 1988. A check in the amount of $150.00 was attached to our November 12, 1987 submittal pursuant to 10CFR170.12(c). Thomas C Bordine (Signed) Thomas C Bordine Administrator, Nuclear Licensing CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment Rev O 8-1-9.1 OC0188-0018-NL02
Attachment A Consumers Power Company Palisades Nuclear Plant Docket 50-255 Evaluation and Survey Results Comparison Post November I .. Flood and Packaging Versus the November 12, i987 Submittal 1*:* Rev 0 8-1-91* MI0188-0001A-HP01
,.A' Cooling Tower - South Radwaste Flood In August of 1987, a resurvey was conducted of the soil at the South Radwaste Building and its adjacent areas. The resurvey was conducted to verify the location of ground contamination and i f any .contamination migrated further into the ground since the 1986 survey.
After submittal of the 1987 soil results and request to retain, in accordance with 10CFR20.302, 'A' Cooling Tower Basin overflowed again flooding the South Radwaste Building and outlying areas. Immediately following the occurrence, one liter sample was taken with no activity detected on the Multi-Channel Analyzer (MCA). Then, another complete survey was conducted which included at least two surface samples and core samples in every sector (Figures 1 and 2). Surface sample results showed that activities have increased as well as new sectors contaminated. The most heavily affected sectors were I-10, I-11, J-9 and K-9 (Figure lA). To keep these areas from spreading, the top 6" of each of these sectors was removed and placed in 6 LSA boxes (approx. 588 cu.ft) and ,. stored for disposition at a later date. ,. After removal of soil, the sectors were resurveyed (Figure lB) and core samples were taken in each sector in 6-inch increments. Core samples were taken as far down as in the 1986 and August 1987 surveys, and in some instances even further in this survey. *Results showed that no activity was detected below 6 inches as shown in Figure 2. Table 1 and Table 2 show comparisons between the August and November 1987 soil surveys. Table 1 compares the depths, the activities, the total cu.ft. and total µCi per sector. After the removal of soil, the November 1987 soil survey results showed approximately a 49.3% drop in total contaminated soil (cu.ft.) ' and a 51.1% drop in total µCi in comparison to the August 1987 survey results. In Table 2 the comparison is between sectors affected in each survey and the depth at which each of these sectors were sampled. No activity was detected past 6 inches in the November 1987 soil survey, in comparison to that of 18 inches detected in August 1987. Direct dose to an individual working in the affected areas was calculated using the MICROSHIELD code. The activities from sectors H-9 and J-9 were used for a dose at 18" inches above the surface. The dose rates from H-9 and J-9 are
*9.97E-6 R/hr and l.17E-5 R/hr, respectively. Therefore, a SO-hour occupancy in one week could result in a maximum exposure of .59 millirem. Normal occupancy of this are~ is on an "as needed basis" and averages less than 8 hours/week per individual in contact with the contaminated soil.
In reviewing the soil results between August and November 1987, the August 1987 soil survey remains more conservative based on the information shown on Tables 1 and 2. Therefore, the August 1987 soil survey is still valid in support of our request to retain the soil in accordance with 10CFR20.302. Rev 0 S-1-91 MI0188-0001A-HP01
Table 1 Comparison Table Between Total Cu. Ft. and Total µCi August 1987 Sector fl sg.ft. *X DeEth = ft 3 x g/ft 3 x µCi/g . Total µCi E-11 375 0.5 187.5 48144 2.07E-6 18.7 E-13 375 0.5 187.5 48144 4.39E-6 39.6 H-9 625 1.5 937.5 48144 ~.79E-6 216.2 H-10 625 0.5 312.5 48144 2.60E-6 39.1 H-11 625 2.0 1250* 48144 3.75E-5 2256.8 I-9 527 0.5 263.5 48144 l.24E-5 157.3 I-10 275 1.5 412.5 48144 5.39E-6 107.0 J-9 450 0.5 225 48144 5.39E-6 58.4 J-12 200 0.5 100 48144 6.39E-6 30.8 L-9 150 1.0 150 48144 6.77E-6 48.9 I-9 East 98 1.5 147 48144 l .40E-5 99.1 4325 4173 3011.2 ~
*1250 *2256.8 m
) 73.5% of total activity November 1987 E-11 375 0.5 187.5 48144 l.80E-6 16.25 H-9 625 0.5 312.5 48144 4.35E-5 654.46 H-10 625 0.5 312.5 48144 3.20E-6 48.14 r H-11 625 0.5 312.5 48144 3.22E-5 484.45 ,. H-12 I-9 250
*527 0.5 0.5 125 263.5 48144 48144 2.20E-6 6.79E-6 13.24 86.14 I-12 220 0.5 110 48144 3.0E-6 15.89 J-9 450 0.5 225 48144 2.05E-5 222.06
- l. J-1*2 200 0.5 100 48144 2.60E-6 12.52 K-9 216 0.5 108 48144 3.39E-6 17.63 iUl 20~6!5 1570.78 Rev 0 8-l-9l MI0188-0001A-HP01
Table 2 Survey Comparison Between August and November 1987 Soil Surveys August 1987 November 1987 Sector Surface 6" 12 11 18" 24 11 30 11 36 11 42" E-11 2.07E-6 <MDA <MDA <MDA l.SOE-6 <MDA <MDA <MDA E-13 4.39E-6 <MDA <MDA <MDA
<MDA H/A <MDA <MDA H-9 4.19E-6 <MDA 4.79E-6 <MDA <HDA <HDA 4.JSE-5 <MDA <MDA <MDA <MDA <HDA H-10 2.60E-6 <MDA <MDA 3*.20E-6 <MDA <MDA H-11 J.75E-5 <MDA <MDA 8.45E-6 <MDA <MDA <HDA 3.22E-5 <MDA <MDA <MDA <MDA <MDA <MDA H-12 <MDA Nf A 2.20E-6 N/A I-9 l.24E~5 <HOA <MDA 6.79E-6 <MDA <MDA I-10 <MDA <MDA 5.39E-6 <MDA <MDA <MDA <MDA <MDA
<MDA <MDA <MDA <MDA <MDA <MDA <MDA <HDA I-11 <MDA Nf A
<MDA <MDA <MDA <MDA I-12 <MDA N/A 3.00E-6 N/A J-9 5.39E-6 <MDA <MDA 2.0SE-5 <MDA <MDA
. J-12 6.39E-6 <MDA <MDA*
2.60E-6 N/A <MDA lC-9 <MDA Nf A 3.J9E-6 <MDA <MDA <MDA <MDA <MDA <MDA L-9 <MDA 6. 77E-6 <MDA <MDA a:> ?:d <MDA N/A <MDA <MDA I CD I-'< I \00 I-' MI0188-0001A-HP01
Microshield 3.02
===;=============
(ConsuMer's Power CoMpany - #037) Page 1 File SOIL1 .MSH Run date: January 18, 1988 Run tiMe: 4:17 p.M. CASE: CONTAMINATED SOIL@ H-9 LOCATION <6 INCHES DEEP> GEOMETRY 11: Rectangular solid source. - slab shields Distance to detector ......................... x 60.960 CM, Source width*
- t
- I C II II II I' 11 II 11 11 11 II I II I I 11 °1 11 I I
- II II S II
- II
- w 762. II Source length ... I.*.* I . ** * * * * ** *
- I I I *********** I L 762. "
Rectangular solid, thickness toward dose pt ** Tl 15.240 " Thickness ci f second ~hield .................... T2 45.720 " Source Volul'le: B.84901e+6 cubic centit11eters MATERIAL DENSITIES (g/cc>: Material Source Shield 2 ., Air .001220 .001220 Alut11inuP1 Carbon 1. 70 Concrete Hydrogen Iron Lead LithiuPI Nickel Tin Ti taniul"I Tungsten o* Urania UraniuPI Water 1.0 Zirconiul"I Rev O 8-1-91
Page 2 File: SOIL1 .MSH CASE: CONTAMINATED SOIL@ H-9 LOCATION (6 INCHES DEEP> BUILDUP FACTOR: based on TAYLOR Method. Using the characteristics of the Materials in shield 1
- INTEGRATION PARAMETERS:
NuMber or lateral angle segPlents (Nthetal..... 5 NuMber of aziMuthal angle segMents <Npsi)..... 5 NuP1ber of radial segMents (Nradius)........... 5 SOURCE NUCLIDES: Ba-137M: 3.8493e-04 curies RESULTS: Group Energy Activity Do3e point flux Dose rate -; # <MeVl (photons/sec) MeV/(sq cpi)/sec ( l'lr/hr > 1 .664 I. 282e+07 4.908e+00 9.969e-03 2 3
- r: 4 5
6 7 8 9 10
. 11
, 12 13 14 15
- '.). 16 17 18 19 20 TOTALS: 1. 282e+07 4.808e+00 9.969e-03 Rev 0 8-1-91
Microshield 3.02
=================
(ConsuMer's Power CoMpany - #037) Page 1 File SOIL2.MSH Run date: January 18, 1988 Run tiMe: 4:26 p.M. CASE: CONTAMINATED SOIL@ J-9 LOCATION {6 INCHES DEEP> GEOMETRY 11: Rectangular solid source - slab shields Distance to detector ..*.. ,.,.* ***.*. ~ .**....* , .)( 60.960 CM, II Source width ........... , ...................... lJ 762. Source length ..................*.............. L 548.640 Rectangular solid, thickness toward dose pt *. Tl 15.240 II Thickness of second shield', ..*..*.***...**** , T2 45.720 II Source VoluMe: 6.37129e+6 cubic centi111eters MATERIAL DENSITIES (g/cc): Material Source Shield 2 Air .001220 .001220 Alu111inufll Carbon f. 70 ,. Concrete Hydrogen
- r *Iron Lead Li thiul'I Ni'ckel Tin T1taniuP1 Tungsten
,.. Urania Uraniu111 Water 1.0 ' Zirconiul"I Rev O 8-1-9],
Page 2 File: SOIL2.MSH CASE: CONTAMINATED SOIL @ J~g LOCATION CS INCHES DEEPl BUILDUP FACTOR: based on TAYLOR Method. Using the characteristics of the Materials in shield 1. INTEGRATION PARAMETERS: NuMber of lateral angle segMents CNthetal..... 5 NuMber of aziMuthal angle segMents (Npsil..... 5 NuMber of radial segl'lents (Nradius).. ......... 5
. SOURCE NUCLIDES:
Co-80: 8.9198e-05 curies RESULTS: Group *Energy Activity Dose point Hux Dose rate
# <MeV) (photons/sec) MeV/(sq cP1)/sec; <Mr/hr>
1 1 .336 . 3 .300e+06 3.411 e+00 6 .1 SSe-03 ., 2 3 1
- 180
.695 3.300e+~6 5.303e+02 2.958e+00 2.aase-04 5.497e-03 5.950e-07 l'" 4 5
6 7 a 9 ,.. 10 11 , 12 13 14 15 ~. 16 17 10 19 20 TOTALS: 6.S01e+06 6.370e+00 1 .165e-02 Rev 0 8-1-91
- 1GURE 1A SURFACE
~ESULTS
. . .ACE ACTMTYOFSECTOR ASPHALT AMAS
*1xA11PLI: ONLY rl 00\
I ID I rl P'.i <X)
- 1GURE 1B .
SURFACE . L I. i.EGEND
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- IURMCI! AMA IN>ER ASPHALT 't/'"" . * .
&J CORE SAMPLE UNDER FOUNDATION. *
/~
SURFACE ACTIVITY OF SECTOR ASPHALT AflEAS
*EXAMPLE: ONLY 00\
ri (°
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L c. I . .Ei~END
- -I Lat IUt llJ-cawr.tN
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~ OIPTM 1.DIL AT.WllCll NO Ll ICllVlirWAIMNCTID ~ _AINIALT A~ J ,.--.,,..-~ i1
ODCM - APPENDIX B REFERENCE 2
/>woa/OB>eg
~-
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 15, 1988 MAN 1 fi ,988 NUCt!AI uaNSING Mr. Kenneth W. Berry Director, Nuclear Licensing Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201
Dear Mr. Berry:
SUBJECT:
PALISADES PLANT - REQUEST TO .RETAIN CONTAMINATED SOIL IN ACCORDANCE WITH 10 CF.R 20.302 (TAC NO. 67408) The subject request submitted by Consumers Power Company by letter dated November 12, 1987 and supp1emented by information forwarded by letter dated January 25, 1988 contains detailed information evaluating the radiation doses via the liquid pathways for very low levels of contamination presently in areas of soil near the Palisades Plant South Radwaste Building. Detailed evaluations are also presented of potential occupational doses from this contaminated so.i l . One additional dose pathway should, however,*be evaluated to complete the analysis of the impact viz., the inhalation pathway. In your submittals, you have presented diagrams showing areas in which contamination has been detected. It appears that for some of these areas 611 of soil has been removed, others are now covered by black top, and still others have not been disturbed. In order for the staff to complete the evaluation under 10 CFR 20.302, we ask that you submit a diagram indicating all contaminated soil surface areas included in this request, the condition of this soil surface, and an evaluation of the radiation dose.s via the inhalation pathway associated with these soil surfaces. The request in this letter affects fewer than ten respondents; therefore, OMB clearance is not required under PL 96-511. Sincerely,
~1(~
Thomas V. Wambach, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V
&Special Projects cc; Sse* *Next. -Rage
I
*Mr. Kenneth W. Berry Consumers Power Company Palisades Plant cc:
M. I. Miller, Esquire Isham, Ljncoln &Beale Nuclear Facilities and Slst Floor Environmental Monitoring Three First National Plaza Section Office Chicago, Illinois 60602 Division of Radiological Health Mr. Thomas A. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Michigan 48909 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire
- Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator. Region III U.S. Nuclear Regulatory Commission 799 Roos*eve 1t Road Glen Ellyn, Illinois 60137 Jerry Sarno Township Supervisor Covert Townsh1 p 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building
,. Lansing, Michigan 48913 , Mr. David P. Hoffman Plant General Manager Palisades Plant
- l. 27780 Blue Star Memorial Hwy.
Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Commission Palisades Plant 27782 Blue Star Memorial Hwy. Covert, Michigan 49043 Rev O 8-'l-91
Lt# 5ooe89 llEt:c;1vED UNITED STATES NUCLEAR REGULATORY COMMISSION JAN 1 ~ f93~ WASHINGTON, D. C. 20555 January 12, 1990 11r.1 FL\O ~ :FN~INn Docket No. 50-255 Serial No. PAL 90-002 Mr. Kenneth W. Berry Director, Nuclear Licensing Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201
Dear Mr. Berry:
SUBJECT:
PALISADES PLANT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10 CFR 20.302 (TAC NO. 67408) By letters dated November 12, 1987 and January 25 1 1988, Consumers Power Company requested authorization under the provisions of 10 CFR 20.302 to dispose . contaminated soil in place. The NRC staff replied with a request for additional information which was forwarded to you on March 15 1 1988. * * ~* By letter dated June 27, 1988, Consumers Power Company provided additional*~ 1 information in response to ou.r request. Howeve.r, in that response, CPCo expanded the original request to include the entire South Radwaste area as a contingency against future spread of co.ntamination and to obviate the* need for additional requests under 10 CFR 20.302. For the staff to complete its review of this request, additional specific information is required. This is because NRC approval under 10 CFR 20.302 is for the disposa'l of specifically identified and characterized slightly contaminated material by the applicant. We request that you provide a revised submittal describing the licensed material for disposal and the analysis and evaluation called for under 10 CFR 20.302. The attached request for additional information provides additional detail for the content of the revised submittal. The reporting and/or recordkeepfng requirements of this letter affect fewer
*than ten respondents; therefore, OMB clearance under Pl 96-511 is not required.
Sincerely,
~/~
Albert W. De Ag;~-a,-~;:ject Manager Project Directorate III-1 . Division of Reactor Projects - III, IV, V &Special Projects Office of Nuclear Reactor Regulation cc: See next page Rev 0 8-1-91
r' Mr. Kenneth w. Berry Palisades Plant Consumers Power Company cc: M. I. Miller, Esquire Sidley &Austin Nuclear Facilities and 54th Floor Environmental Monitoring One First National Plaza Section Office Chicago, Illinois 60603 Division of Radiological Health Mr. Thomas A. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Mfch1gan 48909 212 West Michigan Avenue
*Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Con111ission 799 Roosevelt Road Glen El~yn, Illinois 60137 Jerry Sarno Township Supervisor Covert Township 36197 M*140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. Gerald B. Slade Plant General Manager Palisades Plant 27780 Blue Star Memorial Hwy.
Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Conmiss1on Pa 1i sades Pl ant 27782 Blue Star Memorial Hwy. Covert, Michigan 49043 Rev 0 8-1-91
I ENCLOSURE SECOND REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE CONSUM.ERS POWER COMPANY PALISADES PLANT REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10 CFR 20.302 The subject request submitted by Consumers Power Company (licensee) by letter dated November 12, 1987 and supplemented by information forwarded by letter dated January 25, 1988 contained detailed infor~ation evaluating the radiation doses via the liquid pathways for very low levels of contamination presently in areas of soil near the Palisades Plant South R.adwaste Building. Detailed evaluations were also presented of potential occup~tional doses from this contaminated soil. Three significant questions arose during the staff evaluation of this request:
- 1. The inhalation pathway for doses from the contaminated soil was not addressed.
- 2. The proposals contain no delineation of the specific contaminated areas covered by the disposal request.
- 3. The licensee's Technical Specifications for radiological environmental
-1 1 3 7 Cs monitoring require an LLD of 2 x 10 µCi/gm for determinations in sediment - yet all of the measurements reported in the request were made with equipment 5 to 10 times less sensitive for these gamma radiations.
Re-v 0 8-1-91
By letter dated June 27, 1988 the licensee submitted additional information in response to the staff's RAI of March 15, 1988. This submittal was unacceptable in that it addressed potentially contaminated areas and hypothetical maximum contamination parameters rather than measured licensed material to be disposed of under the regulations. It is requested that. the licensee submit a complete, revised 20.302 request incorporating the dose evaluation information of the measured contamination considered in the No.vember 12, 1987 and January 25, 1988 submissionsand updated if appropriate with dose evaluations of the inhalation pathway based on the same measured contamination. As part of the proposal the licensee should record exactly what areas of measured contamination are covered by the request for which disposal under 10 CFR 20.302 is proposed. Rev O 2 8-l-9l
.ODCM - APPENDIX B REFERENCE 3 consumers Power POWERING MICHlliAN-S PROGRSS General Offices: 1945 West Parn11ll Road, Jackson, Ml 49201 * (517) 788-0550 June 27, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR-20-- PALISADES PLANT -
SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302 , Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose contaminated soil inplace as specified r by 10 CFR 20.302. The area, known as the South Radwaste Area, has been contaminated by numerous cooling tower overflows and redistributed by heavy rain showers. Although the majority of the radioactive material has been packaged for waste *shipment, a large volume of very low ac_tivity radioactive material remains. This volume of material would be very expensive to ship as waste. The NRC, by letter of March 15, 1988 to Consumers Power Company, requested additional inhalation dose information and clarification of the contaminated area
- A generic inhalation dose evaluation is described in Attachment A. Conserva-tive assumptions have been made to get the maximum organ dose possible from inhalation of contaminated soil. The inhalation doses are not significant.
Consumers Power Comp*any requests to expand this 10 CFR 20.302 request to _include the entire South Radwaste Area * . Periodic cooling tower overflows and occasional heavy rains have caused redistribution of radioactive material to
-areas which were below Lower Limits of Detection (LLD) during previous evalua-tions. Expanding the area would eliminate the need for a new 10 CFR 20.302 submittal if radioactive material is redistributed within the South Radwaste Area. The South Radwaste Are~ is completely fenced and located directly South of tpe Plant South Security fence. Area fence is shown in dark outline on Figure 1.
As desc~ibed in our January 25, 1988, letter we intend to transfer the radwaste activities which caused the contamination of soil from the South Radwaste Area, except for the high level* vault use which is not a potential flooding release problem. Rev 0 OC0688-0049-NL02 8-1-91
Nuclear Regulatory Commission 2 Palisades Nuclear Plant Retain Soil in Accordance w/10CFR20.302 June 27, 1988 Consumers Power Company requests approval to dispose of inplace low level radioactive materials which meet the following conditions ~ithout further 10 CFR 20.302 submittals.
- 1. Material contained in the fenced area described as South Radwaste Area.
- 2. Direct dose to a radiation worker would not exceed SE-02 mRem/hour.from contaminated soil. *
- 3. Average gross beta/gamma concentration not to exceed SE-05 µCi/gm so in~alation doses to a radiation worker or at the site boundary would not exceed the values contained in Attachment 1.
- 4. Additional radioactive material releases shall be identified in liquid Semi-Annual Effluents Reports as an 'Abnormal Release'.
') Sampling, analyses and Semiannual Effluent Report inclusions of 'Abnormal 'l Release' will be performed only when further flooding of the area occurs. James L Kuemin (Signed) James L Kuemin Staff Licensing Engineer CC Administrator, Region III,° NRC ' NRC Resident Inspector - Palisades ~.. Attachment Rev 0 OC0688-0049-NL02 8-1-91
Attachment 1 The inhalation doses have been calculated on a generic worst case basis. A generic basis has been selected to compensate for the elevated Lower Limit of Detection (LLD) in analysis and also to address movement of radioactivity within the South Radwaste Area. The assumptions made are the worst case Dose Conversion Factor (DCF) used (see Table 3), a total average activity concentra-tion.of 5E-05 µCi/gram and the entire area (500 m2 ) used instead of the indi-cated contaminated area (117 m2 ). Increasing the area is self-explanatory. The total average activity concentra-tion is being used il!tstead of actual to account for dose important isotopes which may be present near the analysis LLD of lE-0~ µCi/gm, but not detected. The worst case D9F is used to demonstrate a maximum organ dose. A variation in isotope mixes could shift the maximum dose to a different organ but could not 0 exceed the dose indicated. 0 Radworker and site boundary inhalation dose calculat~ons are attached. T
.Rev 0 OC0688-0049-NL02 8-1-91
*Table 1 Inhalation Dose From Contaminated Soil -
Adult Radiation Worker* Where: CS = concentration of waste: 5.0E04 pCi/Kg. Ef .. occupancy factor: 2080 worker hours + 8760 hrs/yr = 0.2.37 f =areal mass available for resuspension (top 1 cm of soil): 16 18 Kg/m2 ... f 1 = resuspension. factor: 8.5E-9/m 4 ., f = adult annual inhalation rate: 7300 m3 (RG 1.109) 15 r DCFi =- 7 .46E-04 mRem/ (50 yr
- pCi): adult lung (RG 1.109)
- Substituting: DW = 8.78E-03 mRem/50 yr: maxim.um organ dose
Reference:
AIF/NESP-035 Evaluation of the Potential for De-Regulated*Disposal of Very Low Level Wastes From Nuclear Power Plants Rev O OC0688-0049-NL02 8-1-91
Table 2 Inhalation Dose At Site Boundary.- Infant Most Limiting X/Q µ A Where: Terms are identified in Table 1 and F 16
= 2045 ms: infant annual breathing rate (RG 1.109)
X/Q ~ 1.4 E-6 sec/ms: actual 5 year site average
µ = 3.8 m/sec averag~ wind speed: actual 1986
, A = 500 m2 : contaminated area DCFi = 3.22E-03 mR/(50 yr. pCi): infant lung (RG 1.109) T - Subs t i tu ting DSB = 1.19E-04 mRem/50 yr: ~aximum organ dose Rev O OC0688-0049-NL02 8-1-91
Table 3 Dose Conversion Factors for Inhalation: Committed dose (mRem) over 50 years per pCi inhaled, per Regulatory Guide 1.109. Onsite - Radiation Worker Bone Liver Kidney Lung GI Cs-134 4.66E-05 l .06E-04 3.59E-05 l.22E-05 l.30E-06 Cs-137 5.98E-05 7.76E-05 2.78E-05 9.40E-06 l.05E-06 Ba.:..140+D 4.88E-06 6.13E-09 2.09E-09 l.59E-04 2.73E-05 Sr-90* l.24E-02 0.0 o.o l.20E-Ol 9.02E-05 Co-60** o.o l.44E-06 o.o 7.46E-04 3.56E-05
- Sr-90 is a factor of 5E-Ol lower than Cs-137 based upon 10 CFR 61 sampling analysis and cannot be limiting. Cs-137 was present in all samples where activity was identified.
** Given the concentration restriction on Sr-90 noted above, Co-60 lung dose is
-* most limiting. Offsite ,.. Infant Most Limiting for Inhalation Cs-134 2.83E-04 5.02E-04 . l.36E-04 5.69E-05 9.53E-07 Cs-137 3.92E-04 4.37E-04 l.23E-04 5.09E-05 9.53E-07 Ba-140 4.00E-05 4.00E-08 9.59E-09 l.14E-03 2.74E-05 Sr-90* 2.92E-02 o.o o.o 8.03E-03 9.36E-05 Co-60** 0.0 5.73E-06 o.o 3.22E-Ol 2.28E-5
- Sr-90 is a factor of 5E-03 lower than Cs-137 based upon 10 CFR 61 sampling analy~is and cannot be limiting. Cs-137 was present in all samples where activity was identified. *
** Given the concentration restriction on Sr-90 noted above, Co-60 lung dose is most limiting.
Rev 0 OC0688-0049-NL02 8-1-91
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ODCM - APPENDIX B REF~CE 4. consumers Power G BSlade General Managft POWERING M.IClllGAN"S l'llll&llUS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert. Ml 49043 August 31, 1990 Nuclear Regulatory Commission Document Control Desk Washington, D C 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR 20.302 Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose of contaminated soil in place as specified by 10CFR 20.302. The area known as the South Radwaste Area has been contaminated by numerous cooling tower overflows and contamination was
- redistributed by heavy rain showers. Although the majority of the radioactive material has-been packed for waste shipment, a large volume of very low activity radioactive material remains. This volume of material would be very expensive to ship as waste. The NRC, by letter of March 15, 1988 to Consumers Power Company, requested additional inhalation dose information and clarification of the contaminated area.
After discussions with the NRC reviewer, a supplement was submitted on June 2.7, 1988 which was based on generic approval. It proposed that further submittals would not be required if flooding moved activity from an identified to an unidentified sector. Subsequently, on January 12, 1990, the NRC Staff requested additional information. The information request required the licensee to submit a revised proposal incorporating the dose evaluation information of the measured contamination considered in the November 12, 1987 and January 25, 1988 submittals and updated, if appropriate, with dose evaluations of the inhalation pathway based on the same measured contamination. As part of the proposal, the licensee was asked to record exactly what areas of measured contamination are covered by the request for which disposal under 10CFR 20.302 is proposed, The attached material supplie~ the requested information. The specific area contaminated is noted as Area Bon the attached survey grid map. The entire area is fenced* and is about 12 ,000 sq ft of soil exposed with the remainder buildings and asphalt. The inhalation pathway is for breathing suspended soil from this area. Table 2 addresses a radworker in Area B, and Table 3 addresses an infant on the site boundary. The radworker could receive 8.03E-04 mRem/50-year maximum organ (liver) dose and the infant could receive 3.16E-05 mRem/50-year maximum organ (liver) dose, both of which are insignif-icant. Rev O 8-1-91 OC0890-0074A-NL03 .
4 . When the flooding problem was discovered and planning for a formal survey was done, the environmental sediment LLD was not considered, as this was a nuclear plant site. We attempted.to get the best LLDj we could usi~g our equipment and the number of samples we were going to have to run. With the hundreds of samp*les run, we felt rn . . 06 uCi/gm was adequate. To be conservative, we . expanded the August and November 1987 surveys to use l.OE-06 uci/gm Cs-137 in any sector which showed LLD. This will increase the radioactivity to 5,006 uCi from 4,643 uCi, an increase of 8%. The activities are on Table 1 and lA. If this submittal is approved, we will add the released activity to the Liquid Semi-annual Effluent Report as an aQnormal release, and the approval to retain the soil in place will be documented in the FSAR. In summation, Consumers Power Company requests approval to dispose of i~ place the low-level radioactive materials which are contaminated soil contained* in the fenced area described as South Radwaste Area (Area B). Direct dose to a radiation worker would not exceed l.7E-02 mRem/hour from this contaminated soil. Inhalation doses to a radiation worker or at the site boundary would. not exceed 8.03E-04 mRem/50-year. Tables 1 and lA radioactive material release shall be identified in liquid Semi-an~ual Effluent Reports as an
'abnormal release'. The disposal in place would be documented in the FSAR.
The radwaste activities which caused the contamination of the soil have bee*n completely relocated to a new east radwaste area. The South Building has been deconned and is being useQ. for non-radwaste activities. Some fixed contamination is present in floor cracks and vaults. This has been documented for plant decommissioning. No further contamination will be added to the south area from the South Radwaste Building. Gerald B Slade (Signed) Gerald B Slade General Manager pc: Administrator, Regio~ III, USNRC NRC Resident Inspector, Palisades Rev 0 8-1-91 OC0890-0074A-NL03
Attachment A Consumers Power Company Palisades Nuclear Plant Docket 50-255
- Tables l and lA,. Survey Results Microshield Direct Dose Calculation Table 2 - Radworker Inhalation Dose Table 3 - Site Boundary Inhalation Dose Figure l - Survey Crid Figure 2 - Survey Results Rev 0 8-1-91 MI0890-00 74A-liPOl
, I Table 1 August 1987 Survey Sector (} S9.ft. x De 2th = ft) x g/ ft l x ~Ci/g = Total ~Ci E-11 375 o.5 187.5 48144 2.07E-6 18.7 E-13 375 0.5 187.5 48144 4.39E-6 39.6 H-9 625 1.5 937.5 48144 4.79E-6 216.2 H-10 625 o.5 312.5 48144 2.60E-6 39.l H-11 6*25 2.0 1250* 48144 3.75E-5 2256.8 I-9 527 0.5 263.5 48144 l.24E-5 15 7 .3 I-10 275 1.5 412.5 48144 5.39E-6 107.0 J-9 450 0.5 225 48144 5* .39E-6 58.4 J-12 200 0.5 100 48144 6.39E-6 30.8 l.-9 150 1.0 150 48144 *6.77E-6 48.9 1.5 147 48144 l.40E-5 99.l I-9 East ~ Subtotals 4325 4173 3071.9 Remainder 7613 0.5 3807 48144 l .OE-06 183 i: Section TOTAL 11, 938 3,255. Rev 0 a..:.1-91 MI0890-0074A-HP01
Table lA November 1987 SurveI Sector ~ Sg. ft. x Deeth = ft J x ~)ft J x ~Ci/g = Total ~Ci B-9 125 0.5 62.5 48144 lE-06 3 C-9 625 0.5 312 *.5 48144 lE-06 15 c-10 500 0.5 250 48144 lE-06 12 D-9 500 0.5 250 48144 lE-06 12
.D-10 625 0.5 312.5 48144 lE-06 15 D-11 550 o.5 275 48144 lE-0"6 13 D~l2 75 0.5 37.5 48144 lE-06 2 E-10 125 0.5 62.5 48144 lE-06 3 E-11 375 0.5 187.5 48144 l.8E-06 16 E-12 625 0.5 312.5 48144 l.E-06 15 E-13 550 0.5 275 48144 lE-06 13 F-12 300 0.5 150 48144 lE-06 7 F-13 625 0.5 312.5 48144 lE-06 15 G-12 750 0.5 125 48144 lE-06 6 C-13 625 0.5 312.5 48144 lE-06 15 H-9 625 0.5 312.5 48144 4.4E-05 662 H-10 625 0.5 312.5 48144" 3.2E-06 48 H-11 600 0.5 300 48144 3.2E-05 462 H-12 250 0.5 125 48144 2.2E-06 13 H-13 625 0.5 312.5 48144 1. OE-06 15 I-9 527 0.5 263.5 48144 6.8E-06 86 I-10 275 0.5 137. 5 48144 l.OE-06 7 I-11 250 0.5 125 48144 l.OE-06 6 I-12 220 0.5 110 48144 3.0E-06 16 J-9 450 0.5 225 48144 2. lE-05* 227.
J-12 200 0.5 100 48144 2.6E-06 13 K-9 216 0.5 108 48144 3.4E-06 18 L-9 150 0.5 75 48144 *i.oE-06 4 L-10 150 0.5 75 48144 l.OE-06 4 L-11 150 0.5 75 48144 l.OE-06 4 L-12 150 0.5 75 48144 l.OE-06 4
\
Subtotals 11,938 ft 2 5,969 ft 3 Maximum 4.4E-05 1751 Average 6. lE-06 Re-v 0 8-l-91 HI0890-0074A-HP01
Microsh1eld 3.~2
<Consu111er's Power Co111pany - #037l Page I File SOIL! .MSH Run date: January 19, 1999 Run ti111e: 4:17 p.111.
CASE: CONTAMINATED SOIL ~ H-9 LOCATION (6 INCHES DEEP> GEOMETRY 11: Rectangular solid !ource - !lab shields Distance to detector ************************* X 60.960 CPI, Source widtti .*.**.. , ....**..*........ ~ ....... W 762. Source length ..*...*.....*........*.......... L 762. Rectangular solid, th1cknese toward dose pt ** ft 15.240 Thickness o.f second shield ****.**.**..*.**..* TZ 45.720 " Source Volul'le: 8.84901e+6 cubic centil'leters MATERIAL DENSITIES Cgicc): Materh! Source Sh1e!d 2 Air .001220 .001220 Alul!linul'I Carbon !. 70 Concrete Hydrogen Iron Lead. L1 tl"liUl'I Nickel Tin TitaniuPI Tungsten Urania Uraniul'I Water 1.0 Zi.rconiu111 Rev 0 8-1-9.1
8U[L0UP FACrCR: oased on rAvLOR Met~od.
!J!lnQ tlie clier-acte1"15t1cs or* tl'le l'li!ter-lcds tn 9h1eld I*
INrEGRAT[ON PARAMErERS: Nul'lber or later-al angle seQMent5 <Ntnetal,,, .. 5
!\Ju111cer- or ~Zll"lutnal angle segMenh <Npul..... 5 Nul'lt1er- or '.ad1 al seg111ent ! <Nrad11.Js l., ... ,.,,., 5 SOURCE NUCUOES:
Sa-137,.,,:
- 3. S493e-04 cur us .Actual 6.SlE-04.Ci (4 *.4E-05 uCi/gm)
RESULTS: Gr-ou~ Energy l'ict1111ty Dose point rlux Dose rate
# (MeVl <gnotonstsecJ MeV/(s~ cll\Jtsec f
.664 I .282e+07 4.S08e+00 (I'll'"/ hr-)
z 9.969e-03 3 4 s s 7 s s 10 1I 12 13 14 15 rs 17 I8 19 ZI TOTALS: --------- I. 282e+07 --------- 4.8081+00 9.969e-03 6.51 Ci
- Ratio of 3.85 Ci= 1.69 x 9.969E-03 = l.7E-02 ?:lR/hr Rev 0 8-1-91
Table 2 Inhalation Dose From Contaminated Soil - Adult Radiation Worker Dw = Cg f14 Where: Cs = concentrati.on of waste - 4.4E04 pCi/Kg Cs-137 (actual max concentration) Ef = occupancy factor - 2080 worker hours ~ 8760 hrs/yr = 0.237 f18 = a real/mass available for resuspension (top l cm of soil) - 16 Kg/m 2 f14 = resuspension factor - 8.SE-9/m f15 = adult 3 annual inhalation rate - 7300 m (RC 1.109) DCFi = 7.76E-o5* mRem/50 yr* pCi - Cs-137 adult liver (RG 1.109)
- substituting:
Ow = 8.03E-04 mRem/50 yr - maximum organ dose
* ~ference: AIF/NESP-035 Evaluation of the Potential for De-regulated Disposal of Very Low Level Wastes From Nuclear Power Plants Rev O 8-l-91 HI0890-0Q74A-HP0l
Table 3 Inhalation Dose At Site Boundary - Infant Most Limiting Dse = cs f18 X/Q µ A DCFi Where: Terms are identified in Table 1 and F16 = 2045 ml - infant annual breathing rate (RG 1.109) X/Q = 1.4 E-6 sec/ml - actual 5 year site average
µ = 3.8 m/sec average wind speed -'actual 1986 A - 1110 m2 - contaminated area DCFi - 4.37E-04 mR/50 yr
- pCi - Cs-137 infant liver (RG 1.109)
>stituting:
Dss = 3.16E-05 mRem/50 yt - maximum organ dose Rev 0 B-1-91 MI0890-0074A-HP01
FIGUIE ~B ' SURFACE RESULTS AINALT MEAS
-EXAMPLI : ONLY rl 0.0\
I
> rl
- DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
- 0l) which required implementation of actions to prevent future flooding. In 1988 it was decided to relocate the radwaste processing functions performed in the South Radwaste Building to a new addition at the East Radwaste Building to prevent the spread of contamination in the event of future cooling tower overflows. All radwaste processing equipment was relocated to the East Radwaste Building and the South Radwaste Building was decontaminated. The South Radwaste Building (then re-named the South Storage Building) has since been used for non-radiological m.aterial storage.
- 1. \
- LI I
- I.
Dear Mr. Slade:
SUBJECT:
REQUEST UNDER 10 CFR 20.302 TO RETAIN CONTAMINATED SOIL ONSITE AT PALISADES PLANT (TAC NO. 67408) By letters dated N*avember 12, 1987, and January 25, 1988, (Reference 1 of the enclosed Safety Evaluation (SE)), Consumers Power Company submitted a request pursuant to 10 CFR 20.302(a) for the disposal of contaminated soil onsite at the Palisades Plant. We have completed our review of the request and find your procedures, (~,!,th. comnitmeJJt~. -~.~ dQc.~m~o~~cl.~lP-"~~f e.r:-ence l) to be acceptable. Ttf'ls:' a.* ._
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.. Also-:~fir ure Minucfl':;(r .A mo shall'be"reporte(:f tottie NRC. in accordance with the applicable ODCM. change protocol. We fu.rther find that the radiological environmental impact of the proposed action meets the staff criteria as reflected in Reference 6 of the enclosed Safety Evaluation.
Sincerely, Brian Holian, Project Manager Project Directorate JII .. 1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated Rev o 8-1-91
Mr. Gerald B. Slade Consumers Power Company Palisades Plant cc: M. I. Miller, Esquire Sidley & Austin Nuclear Facilities and 54th Floor Environmental Monitoring One First National Plaza Section Office Chicago, Illinois 60603 Division of Radiological Health Mr. Thomas ~. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Michigan 48909 212 West Michigan Avenue Jackson, Michigan 49201 Gerald Charnoff, P.C. Shaw, Pittman, Potts & Trowbridge Judd L. Bacon, Esquire 2300 N. Street, N.W. Consumers Power Company Washington, D.C. 20037 212 West Michigan Avenue Jackson, Michigan 49201 Hr. David L. Brannen Vice President Regional Administrator, Region III Palisades Generating Company U.S. Nuclear Regulatory Conmission c/o Bechtel Power Corporation 799 Roosevelt Road 15740 Shady Grove Road Glen Ellyn, Illinois 60137. Gaithersburg, Maryland 20877 Jerry Sarno Roy w. Jones Township Supervisor Manager, Strategic Program Covert Township Development 36197 M-140 Highway Westinghouse Electric Corporation Covert, Michigan 49043 4350 Northern Pike Monroeville, Pennsylvania 15146 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. Patrick M. Donnelly Director, Safety and Licensing Palisades Plant 27780 Blue Star Memorial Hwy. Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Conmission Pa 11 sades Plant 27782 Blue Star Memorial Hwy. Covert, Michigan 49043 Rev 0 8-1-91
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 SAFETY EVALUATION RELATED TO THE PALISADES NUCLEAR PLANT RETENTION OF CONTAMINATED SOIL ONSITE INTRODUCTION In reference (1). Consumers Power Company {CPCo) requested approval pursuant to Section 20.302 of Title 10 of the Code of Federal Regulations {CFR) for the disposal of licensed material not previously considered by the NRC in the Palisades Final Environmental Statement (FES). dated June 1972. The petition submitted contains a detailed description of the licensed material {i.e ** contaminated so;1) subject to this 10 CFR 20.302 request. The 6,000 cubic feet of onsite contaminated soil contains a total radionuclide inventory of 5.1 mCi. based on radioactive material that was deposited in the soil due to the flooding of the South Radwaste Building. The contaminated area is located inside the security fences, and is on company controlled land. This area {South Radwaste Area) is fenced in, within the plant's south security fences. Thus it*is inaccessible to the public {see Figures 1 and 2). In the submittals (References 1-5), the licensee addressed specific information requested in accordance with 10 CFR 20.302(a), provided a detailed description of the licensed material, thoroughly analyzed and evaluated the environmental effects relative to retention of the contaminated soil onsite, and coD111itted to follow specific procedures to minimize the risk of unexpected exposures. Although the environmental impact of the proposed action is well within the dose criteria contained in the Conmission's Below Regulatory Concern {BRC) Policy Statement, dated July 3, 1990. the licensee has not requested. and the staff has not considered, the act.tons described:-herein to be exempt from NRC regulation. CPCo plans to dispose of the 6,000 cubic feet of contaminated soil ons;te pursuant to 10 CFR 20.302. The area, known as thd South Radwaste Area, has been contaminated by several cooling tower overflows (three times in an eight-year period), and has subsequently been redistributed by heavy rain showers. The cooling tower overflows were caused by instrument failures that opened the cooling tower bypass valve during.normal operation. This valve is now electri-cally isolated during cooling tower operation. The licensee conducted a soil survey because the South Radwaste Building was in the main path of the water overflows from the cooling tower. Survey results indicated that radioactive material was deposited in the soil. Although the majority of the radioactive material has been packaged as radwaste and will be subsequently shipped offsite (16 boxes each having a volume of 98 cubic feet, containing 85% of the estimated activity), a large volume of. low level contaminated soil is contained in the fenced area described as the South Radwaste Area. Rev 0 8-1-91
The specific area contaminated is noted as Area B on the survey grid map (sed Figure 2). The total activity of this area (5.1 mCi) is based on 6,000 cubic feet of soil contaminated with the spoils from the South Radwaste Building. Table 1 lists the principal nuclides identified in the contaminated soil. The activity in this table is based on measurements in 1987; see data from a recent submittal (Reference 5) shows that activity concentrations in the contaminated area have decreased by approximately 10 percent. The radionuclide half-lives, which are dominated by 30.-year Cs-137, meet the staff's 10 CFR 20.302 guidelines (Reference 6, which applies to radionuclides with half-lives less than 35 years). Tab le 1 Average Nuclide Concentration (pCi/g) Total Activity (mCi) Co-60 0.05 0.079 Cs-137 30 5.0 Total r.n7§ RADIOLOGICAL IMPACTS The licensee has evaluated the following potential exposure pathways to members of the general public from the radionuclides in the contaminated soil: (1) external exposure caused by direct radiation from radionuclides in the soil; and (2) internal exposure from inhalation of resuspended radionuclides. The staff has reviewed the licensee's calculational methods and assumptions and finds that they are consistent with NRC 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, 11 Revision 1, October 1977. The staff finds the assessment methodology_acceptable. The dose assessments are based on the following:
- 1. 5.1 mCi of contaminated soil distributed over 12,000 square foot planar source having a thickness of 0.5 feet {6000 cubic feet source volume).
- 2. Direct radiation exposure of 2000 hours per year.
- 3. Inhalation exposure based on 2000 hours per year is minimized due to six-inch layer of gravel {which inhibits wind erosion.)
- 4. Groundwater not considered because there are no domestic wells in the area down~gradient from the plant.
Doses calculated from these pathways are shown in Table 2. The total dose of 0.85 mrem per year is within the staff's guideline of 1 mrem per year {Reference 6). Rev 0 8-l-9l
Table 2 Whole Body Dose Received by Maximally Exposed Individual Pathway (mrem/year} Groundshine 0.85 Inhalation 0.00081 Groundwater Ingestion o.o TOTAL 0.85 The above doses are a small fraction of the 300 mrem received annually by members of the general public in the United States and Canada from sources of natural background radiation (Reference 7}. Based on our review of the proposed disposal of contaminated soil onsite, we conclude that: (l} The radioactive material will be disposed in a manner such that it is unlikely that the material will be recycled; (2} Doses to the total whole body and any body organ of a maximally exposed individual (a member of the general public or a non-occupationally exposed member} from the probable pathways of exposure to the disposed material will be less than l mrem per year; (3} Doses to the total whole body and any body organ of an inadvertent intruder from the probable pathways*of exposure will be less than 5 mrem per year since the burial location is on company-controlled land; (4} The radiation exposures to the nuclear station workers are small compared to the routine occupational exposures at the Palisades Plant; (5} The possible radiation risks to members of the general public as a result of such disposal are well below regulatory limits and small in comparison to the doses they receive each year from natural background radiation. The licensee's procedures and conmitments as documented in the submittal are acceptable, provided that they are permanently incorporated into the licensee ~ffsite Dose Calculation Manual (ODCM} as an Appendix, and that future modifications be reported to NRC in accordance with the applicable ODCH change protocol. Rev 0 8-1-91
REFERENCES 1 (1) CPC0 s letters, T. C. Berdine to NRC Document Control Desk, November 12, 1987 and January 25, 1 988. (2) Memorandum from L. J. Cunningham, DREP to T. R. Quay, T. V. Wambach, 11 Request for Additiona 1 Information (RAI), March 15, 1988, Apri 1 7, 11 1989, and January 12, 1990. (3) CPCo's supplement to Reference (1), J. L. Kuemin to NRC Document Control Desk, June 27, 1988. (4) CPCo's supplement to References (1, 2), G. B. Slade to NRC Document Control Desk, August 31, 1990. ( 5) CPCo's letter, T. P. Neal to B. Holian, October 13, 1990. (6) E. F. Branagan, Jr. and F. J. Congel, "Disposal of Slightly Contaminated Radioacthe Wastes from Nuclear Power Plants," presented at CONF-860203, Health Physics Considerations Decontamination Deconmissioning, Knoxville, TN, February, 1986. (7) National Counci 1 on Radiation Protection and Measurements, "Exposure of the Population in the United States and Canada from Natural Background Radiatfon, NCRP Report No. 94, Bethesda, MD. Deceni>er 30, 11 1987. Principal Contributor: J. L. Minns Rev O 8-1-91
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ATTACHMENT 2 BIG ROCK POINT INDEPENDENT SPENT FUEL STORAGE INSTALLATION 2015 RADIOACTIVE EFFLUENT RELEASE REPORT This report provides information relating to radioactive effluent releases and solid radioactive waste disposal at Big Rock Point (BRP) for the year 2015. The report format is detailed in the BRP Offsite Dose Calculation Manual (ODCM). Effluent releases from BRP are controlled by the Defueled Technical Specifications and the ODCM requirements. The ODCM was not revised in 2015. 2015 Operating History On January 8, 2007, the Nuclear Regulatory Commission (NRC) approved release of the former BRP nuclear plant property for unrestricted use in accordance with the BRP License Termination Plan 1
- On April 11, 2007, the license for BRP, DPR-06, was transferred to Entergy Nuclear Operations, Inc.
During 2015, normal independent spent fuel storage installation (ISFSI) operations continued. There were no operational activities that generated any solid radioactive waste. Liquid and gaseous effluent monitoring is no longer conducted as the former BRP nuclear plant property has been released from the license. Short-lived radionuclides, including iodine and noble gas, are neither expected nor reported.
- 1. Supplemental Information A. Batch Releases There were no batch releases of gaseous or liquid effluents during 2015. All batch releases of radioactive liquids as described in the ODCM ceased in 2004.
B. Abnormal Releases There were no abnormal releases from BRP during 2015. C. Radioactive Effluent Monitoring Instrumentation BRP ODCM currently specifies required actions when less than the minimum numbers of radioactive effluent monitoring instrument channels are operable. The ODCM also specifies these actions be taken when installed effluent monitoring systems are removed from service for decommissioning. All plant-installed liquid and gaseous radioactive effluent monitoring instrument channels have been permanently removed and dismantled. 1 Letter from the USN RC dated January B, 2007, "Release of Land from Part 50 License for Unrestricted Use" Page 1 of 2
- 2. Gaseous Effluents Although there were no gaseous effluents released during 2015, Table 2 provides a summary of all gaseous radioactive effluent monitoring conducted during the reporting period as required by the ODCM.
- 3. Liquid Effluents There were no liquid effluent batch releases during 2015. Table 3 lists and summarizes liquid effluent releases in accordance with the ODCM.
- 4. Solid Waste There was no solid radioactive waste generated or shipped during 2015.
- 5. Summary of Radiological Impact on Man The ODCM specifies that the annual effluent release report provide potential dose calculations based on measured effluent to liquid and gaseous pathways, if estimates of dose exceed one millirem to an organ or total body of any individual or more than one person-rem to the population within 50 miles. During 2015, there were no releases. Therefore, no calculations were required.
- 6. Offsite Dose Calculation Manual The ODCM describes the radiological release requirements for the BRP site.
There were no revisions to the ODCM in 2015.
- 7. Process Control Program (PCP)
The Process Control Program (PCP) describes solid waste processing and disposal methods utilized at the BRP site. The PCP was not revised during 2015. Page 2 of 2
TABLE 1 Big Rock Point Batch Releases January 1, 2015 to December 31, 2015 A.GASEOUS Units 1ST QTR 2NDQTR 3RD QTR 4TH QTR Number of Releases N/A N/A N/A N/A Total Release Time Minutes N/A N/A N/A N/A Maximum Release Time Minutes N/A N/A N/A N/A Average Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A B. LIQUID Units 1ST QTR 2NDQTR 3RD QTR 4TH QTR Number of Releases N/A N/A N/A N/A Total Release Time Minutes N/A N/A N/A N/A Maximum Release Time Minutes N/A N/A N/A N/A Average Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A Page 1 of 1
TABLE 2 Big Rock Point Gaseous Effluent Releases January 1, 2015 to December 31, 2015 1ST 2ND 3RD 4TH Es!Total A. FISSION AND ACTIVATION GASES Units QTR QTR QTR QTR Error%
- 1. Total release Ci N/A N/A N/A N/A
- 2. Average release rate for period µCi/sec N/A N/A N/A N/A N/A
- 3. Percent of annual ava EC % N/A N/A N/A N/A B. IODINES
- 1. Total iodine Ci N/A N/A N/A N/A
- 2. Averaqe release rate for period µCi/sec N/A N/A N/A N/A N/A
- 3. Percent of annual avi:i EC % N/A N/A N/A N/A C. PARTICULATES
- 1. Particulates with half-life >8 dav Ci N/A N/A N/A N/A
- 2. Averaae release rate for period uCi/sec NIA NIA NIA NIA NIA
- 3. Percent of annual avi:i EC % NIA NIA NIA NIA
- 4. Gross alpha radioactivity Ci NIA NIA NIA NIA D. TRITIUM
- 1. Total Release Ci NIA NIA NIA NIA
- 2. Averaae release rate for period uCi/sec NIA NIA NIA NIA
- 3. Percent of annual avi:i EC % NIA NIA NIA NIA E. WHOLE BODY DOSE
- 1. Beta Air dose at Site Boundary due to Noble Gases (ODCM Section 1, 1.3.2 a (1) (2)) mrads NIA NIA NIA NIA
- 2. Percent limit % NIA NIA N/A NIA
- 3. Gamma Air dose at Site Boundary due to Noble Gas (ODCM Section 1, 1.3.2 a (1) (2)) mrads NIA NIA NIA NIA
- 4. Percent limit % N/A N/A NIA NIA F. ORGAN DOSE (ODCM Section 1, 1.3.2b (1) (2))
- 1. Maximum organ dose to pubic based on Critical Receptors (child bone) mrem NIA NIA NIA NIA
- 2. Percent of limit (7.5 mrem/quarter) % N/A NIA NIA NIA Page 1 of 3
TABLE 2 Big Rock Point Gaseous Effluent Releases January 1, 2015 to December31, 2015
- 1. FISSION GASES Units 1STQTR 2ND QTR 3RDQTR 4TH QTR Krypton-85m Ci N/A N/A N/A N/A Krvoton-87 Ci N/A N/A N/A N/A Krvoton-88 Ci N/A N/A N/A N/A Xenon-133 Ci N/A N/A N/A N/A Xenon-133m Ci N/A N/A N/A N/A Xenon-135 Ci N/A N/A N/A N/A Xenon-135m Ci N/A N/A N/A N/A Xenon-138 Ci N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A
- 2. IODINES lodine-131 Ci N/A N/A N/A N/A lodine-132 Ci N/A N/A N/A N/A lodine-133 Ci N/A N/A N/A N/A lodine-134 Ci N/A N/A N/A N/A lodine-135 Ci N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A Page 2 of 3
TABLE 2 Big Rock Point Gaseous Effluent Releases January 1, 2015 to December 31, 2015
- 3. PARTICULATES* Units 1STQTR 2NDQTR 3RDQTR 4TH QTR Chromium-51 Ci N/A N/A N/A N/A Manrianese-54 Ci N/A N/A N/A N/A Cobalt-58 Ci N/A N/A N/A N/A lron-59 Ci N/A N/A N/A N/A Cobalt-60 Ci N/A N/A N/A N/A Zinc-65 Ci N/A N/A N/A N/A Silver-11 Om Ci N/A N/A N/A N/A Cesium-134 Ci N/A N/A N/A N/A Cesium-137 Ci N/A N/A N/A N/A Barium-140 Ci N/A N/A N/A N/A Europium-152 Ci N/A N/A N/A N/A Strontium-89 Ci N/A N/A N/A N/A Stronlium-90 Ci N/A N/A N/A N/A Net unidentified beta Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A
- Particulates with half-life >8 days Page 3 of 3
TABLE 3 Big Rock Point Liquid Effluent Releases January 1, 2015 to December 31, 2015 Es!Total A. FISSION AND ACTIVATION PRODUCTS Units 1STQTR 2ND QTR 3RD QTR 4TH QTR Error%
- 1. Total release (not includina tritium, aases, aloha) Ci N/A N/A N/A N/A N/A
- 2. Averaae diluted concentration durina period uCi/ml N/A N/A N/A N/A
- 3. Percent of EC % N/A N/A N/A N/A B TRITIUM
- 1. Total release Ci N/A N/A N/A N/A N/A
- 2. Averaae diluted concentration durina oeriod uCi/ml N/A N/A N/A N/A
- 3. Percent of EC % N/A N/A N/A N/A C DISSOLVED AND ENTRAINED GASES
- 1. Total release Ci N/A N/A N/A N/A N/A
- 2. Averaae diluted concentration durina period uCi/ml N/A N/A N/A N/A
- 3. Percent of EC % N/A N/A N/A N/A D. GROSS ALPHA RADIOACTIVITY Ci N/A N/A N/A N/A E. VOLUME OF WASTE RELEASED (Prior to dilution) Liters N/A N/A N/A N/A F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters N/A N/A N/A N/A G. MAXIMUM DOSE COMMITMENT WHOLEBODY mrem N/A N/A N/A N/A Percent of ODCM Section 1, 2.3.2 a (1.5 mrem) % N/A N/A N/A N/A H. MAXIMUM DOSE COMMITMEtilT - ORGAN Mrem N/A N/A N/A N/A Percent of ODCM Section 1, 2.3.2 b (3.0 mrem) % N/A N/A N/A N/A Page 1 of 2
TABLE 3 Big Rock Point Liquid Effluent Releases January 1, 2015 to December 31, 2015
- 1. NUCLIDES RELEASED Units 1STQTR 2NDQTR 3RD QTR 4THQTR Chromium-51 Ci -- -- -- --
Manoanese 54 Ci -- -- -- -- Cobalt-58 Ci -- -- -- -- lron-59 Ci -- -- -- -- Cobalt-60 Ci -- -- -- -- Zinc-65 Ci -- -- -- -- Strontium-89 Ci -- -- -- -- Strontium-90 Ci -- -- -- -- Molvbdenum-99 Ci -- -- -- -- Silver-110m Ci -- -- -- -- lodine-131 Ci -- -- -- -- Cesium-134 Ci -- -- -- -- Cesium-137 Ci -- -- -- -- Antimony-125 Ci -- -- -- -- Tin-113 Ci -- -- -- -- Net Unidentified Beta Ci -- -- -- -- Fission & Activation Product Total Ci -- -- -- -- Xenon-133 Ci -- -- -- -- Tritium Ci -- -- -- -- Grand Total Ci -- -- -- -- Page 2 of 2
Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043 Tel 269 764 2000 Jeffery A. Hardy Regulatory Assurance Manager PNP 2016-024 April 25, 2016 10 CFR 50.36a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
2015 Annual Radioactive Effluent Release and Waste Disposal Report Palisades Nuclear Plant Big Rock Point Docket 50-255 Dockets 50-155 and 72-043 License No. DPR-20 License No. DPR-6
Dear Sir or Madam:
Attached are the Entergy Nuclear Operations, Inc. 2015 Annual Radioactive Effluent Release and Waste Disposal Reports for Palisades Nuclear Plant (PNP) and Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). These reports are submitted in accordance with 10 CFR 50.36a(a)(2). contains the report for PNP. Attachment 2 contains the report for the BRP ISFSI. These reports provide a summary of the quantities of radioactive liquid and gaseous effluent releases and solid radioactive waste processed during the period of January 1, 2015, through December 31, 2015.
PNP 2016-024 Document Control Desk Page2 This letter contains no new commitments and no revision to existing commitments. Sincerely, JAH/bed : Palisades Nuclear Plant 2015 Radioactive Effluent Release Report : Big Rock Point Independent Spent Fuel Storage Installation 2015 Radioactive Effluent Release Report CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC (w/o Attachments) Resident Inspector, Palisades, USNRC (w/o Attachmens) NRC NMSS Project Manager, USNRC (w/o Attachments) American Nuclear Insurers (ANI)
ATTACHMENT 1 Palisades Nuclear Plant 2015 Radioactive Effluent Release Report 2015 Plant Operating History Palisades Nuclear Plant (PNP) entered the reporting period online on January 1, 2015, at essentially 100% full power. PNP experienced an unexpected scram on September 16, 2015, because of a digital electrohydraulic control system malfunction on the turbine. Refueling outage 1R24 commenced shortly thereafter on September 18, 2015. The unit attained criticality on October 19, 2015, and returned to full power on October 22, 2015. The unit generated 6,318,519 MWHrs of net electrical energy during 2015. A. Gaseous Effluents Tables 1A, "Gaseous Effluents - Summation of All Releases," 1B, "Gaseous Effluents - Ground-Level Release - Batch Mode," and 1C, "Gaseous Effluents - Ground-Level Release - Continuous Mode," list and summarize gaseous effluents released during this reporting period. B. Liquid Effluents Tables 2A, "Liquid Effluents - Summation of All Releases," 2B, "Liquid Effluents - Batch Mode," and 2C, "Liquid Effluents - Continuous Mode," list and summarize liquid effluents released during this reporting period. C. Solid Waste Storage and Shipments Table 3, "Low-Level Waste for Waste Classification A, Band C, summarizes solid radioactive waste shipped for processing or burial in 2015 for the following waste streams: resins, filters and evaporator bottoms, dry active waste, irradiated components and other waste. D. Dose Assessments Tables 4, "Dose Assessments, 10 CFR Part 50, Appendix I," and 5, "EPA 40 CFR Part 190, Individual in the Unrestricted Area," lists annual dose to the members of the public. E. Supplemental Information
- 1. Regulatory Limits
- a. Noble Gases The air dose in unrestricted areas due to noble gas released in gaseous effluents shall be limited to the following:
Page 1 of 10
*During the calendar quarter, to s 5 mrad for gamma radiation ands 10 mrad for beta radiation.
- During the calendar year, to s 10 mrad gamma radiation and s 20 mrad for beta radiation.
- b. Iodines - Particulates The dose to a member of the public from radioiodines, radioactive material in particulate form with half-lives greater than eight days, and radionuclides other than noble gas, e.g., tritium, in gaseous effluents released to unrestricted areas shall be limited to the following:
*During any calendar quarter, to s 7.5 mrem to any organ
- During any calendar year, to s 15 mrem to any organ
- c. Liquid Effluents The dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas shall be limited to the following:
- During any calendar quarter to s 1.5 mrem to the total body and s 5 mrem to any organ.
- During any calendar quarter to s 3 mrem to the total body and s .1 O mrem to any organ.
- d. Total Dose The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to s 25 mrem to the total body <?r any organ (except the thyroid, which is limited to s 75 mrem) over a period of 12 consecutive months.
- 2. Maximum Permissible Concentrations (Effluent Concentration Limits)
- a. Gaseous Effluents The dose rate due to radioactive material released in gaseous effluents from the site shall be limited to the following:
- For noble gases: s 500 mrem/yr to the total body and s 3000 mrem/yr to the skin
- For all radioiodines and for all radioactive materials in particulate form with half-lives greater than eight days and for radionuclides other than noble gases: s 1500 mrem/yr to any organ.
Page 2 of 10
The above limits are provided to ensure that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits of 10 CFR 20, Appendix B, Table 2, Column 1.
- b. Liquid Effluents The concentration of radioactive material. released at any time from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 µCi/ml total activity.
- 3. Average Energy The average energy ( E) of the radionuclide mixture in releases of fission and activation gases as defined in Regulatory Guide 1.21, Appendix B, Section A.3 is not applicable because the limits used for gaseous releases are based on calculated dose to members of the public.
- 4. Measurements and Approximations of Total Radioactivity PNP uses 0.25 KeV per channel with a range of 0-2000 KeV.
- a. Fission and activation gases are sampled and then analyzed on an 8192 channel analyzer with a high purity germanium (HpGe) detector.
- b. Iodines are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector.
- c. Particulates are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector.
- d. Liquid effluents are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector. Tritium analysis is performed using liquid scintillation.
Fe-55, Ni-63, Sr-89, and Sr-90 analyses are performed by an offsite vendor. Page 3 of 10
- 5. Batch Releases - 2015 For PNP, these totals are not directly proportional to actual release volumes due to PNP having two sets of tanks with different volumes in both the gaseous and liquid release systems that are utilized for batch releases. The number of batches performed in this section will fluctuate from year to year due to the utilization of the smaller and larger tanks in different frequencies. This information is better quantified in the tables contained later in this report. Reporting average stream flow during periods of release of effluent into a flowing stream is not required as PNP's releases are made into Lake Michigan, and not a flowing stream of water.
- a. Liquid Number of batch releases for each quarter: 1 in the 1st quarter 1 in the 2nd quarter 5 in the 3rd quarter 4 in the 4th quarter Total time period for batch releases: 10598 minutes Maximum time period for a batch release: 2580 minutes Average time period for a batch release: 963 minutes Minimum time period for a batch release: 434 minutes
- b. Gaseous Number of batch releases for each quarter: 2 in the 1st quarter
\
0 in the 2nd quarter 2 in the 3rd quarter 5 in the 4th quarter Total time period for batch releases: 2897 minutes Maximum time period for a batch release: 930 minutes Average time period for a batch release: 322 minutes _ Minimum time period for a batch release: 78 minutes Page 4 of 10
- 6. Abnormal Discharges
- a. Liquid Number of releases for each quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1 0 0 0 Total activity released in Curies (Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0.0387 0 0 0 On February 26, 2015, as a result of routine monitoring well sampling, PNP identified tritium in temporary wells 7 and 8, located within the plant protected area. PNP completed notifications, in accordance with NEI 07-07 Criterion 2.2.b, on March 19, 2015. Tritium concentrations were less than the threshold value (20,000 pci/L) for initiating voluntary communications in accordance with NEI Ground Water Protection Initiative. The station promptly isolated the pipe that runs from the turbine sump oil/water separator to the turbine building drain tank as the likely source. Subsequent sample concentrations from samples obtained on March 18, 2015, resulted in concentrations of tritium less than the minimum detectable activity, thus confirming the source.
The pipe that runs from the turbine sump oil/water separator to the turbine building drain tank is a monitored effluent pathway that discharges waste to Lake Michigan. All activity and volume along this pathway is accounted for by routine effluent calculations, as shown in Table 2C. However, the activity released to the ground through this path is considered abnormal due to the fact that the release did not occur at the designed discharge location. The fraction of release from the pipe is unknown, so it was conservatively assumed that 100% of the liquid discharge traveling through the pipe went to the ground. The most conservative range of time during which this could have occurred was calculated to be between October 2, 2014, and March 7, 2015, based upon groundwater well measurements and groundwater flowrates. Therefore, it is conservatively estimated that 0.0387 Ci of tritium in 1st Quarter 2015, and 0.0533 Ci in 4th Quarter 2014 was released to the ground from this pipe. Voluntary notifications were made to the Michigan Department of Environmental Quality, VanBuren County Administrator, Covert, Geneva, and South Haven Township Supervisors, as well as the City of South Haven Mayor and City Manager. The NRC Resident Inspectors were notified, and reporting was completed in accordance with 10 CFR 50.72(b)(2)(xi). Page 5 of 10
- b. Gaseous None.
- 7. Controlled Discharge
- a. Liquid None.
- b. Gaseous Number of releases for each quarter 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 1 8 -----'-'15"------
Total activity released in Curies (Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 0.00000626 1.42 0.0165
- 8. Radioactive Waste Treatment System Changes None.
- 9. Annual Land Use Census Changes The garden critical receptor is unchanged and remains located in the SSE sector at 0.69 miles. The residence critical receptor is unchanged and remains in the SSW sector at 0.49 miles. The goat critical receptor is unchanged and remains in the NE sector at 2.45 miles and are fed stored feed. Beef cattle remain located in the SE sector at 4.27 miles. There are no dairy cows located within five miles of the plant.
- 10. Effluent Monitoring System lnoperability One effluent monitor was out of service for greater than 30 days during the reporting period.
RIA-2320, steam generator blowdown tank vent monitor, was declared inoperable on November 3, 2015, due to the failure of a monthly monitor functional check. Compensatory actions were taken in accordance with the ODCM Table A-1. The monitor was declared operable on December 8, 2015. The extended delay was a result of having to send the spare detector to the vendor upon failing to make the spare detector operable. Page 6 of 10
- 11. Offsite Dose Calculation Manual (ODCM) Changes The Offsite Dose Calculation Manual (ODCM), ODCM Appendix A, and ODCM Appendix B were not revised in 2015. The General Manager Plant Operations approval is required for changes to the ODCM.
The ODCM, ODCM Appendix A and ODCM Appendix B are being revised in 2016. Revision will include the updated meteorological data and turbine sump totalizer surveillance frequency. A copy of the ODCM, ODCM Appendix A, and ODCM Appendix B are attached in Enclosure 1.
- 12. Process Control Program Changes None.
- 13. Errata/Corrections to Previous Reports On page 18 of 108 of the 2014 Annual Radioactive Effluent Release and Waste Disposal Report the volume of type 'a' waste, spent resin, filters, evaporator 3
bottoms, etc., was reported as 1.38 m3 but should have been reported as 1.83 m . This means the value reported was less conservative than the actual value by 25%. This is considered a large error under the guidance of regulatory guide 1.21. A special submittal was not made to the NRC upon discovery of this error because the error was discovered within 90 days of the submittal of this report which is within guidance of Regulatory guide 1.21. The total curries shipped for this category was reported correctly. Page 7 of 10
- 14. Other Groundwater Monitoring PNP has 21 ground water monitoring wells (MW) strategically placed within the owner controlled area to allow for detection of radioactive contamination of ground water due to leaks or spills from plant systems. Four of these MW were installed in December, 2014 for monitoring starting in 2015. PNP added 18 temporary wells (TW) in 2009 to determine the potential source of tritium in groundwater in the vicinity of MW-3. Of the 18 TW installed, 16 are still functional. Tanks T-90, primary makeup tank, T-91, utility water storage tank, and associated underground piping between these tanks and the auxiliary building addition are located in this area.
TW-15 is most indicative of an historic leak that continues to be monitored. 2015 tritium levels in TW-15 peaked in January at 31,846 pCi/L. Tritium levels spike in TW-15 when the water table rises from a large rainfall or spring melt. The high tritium levels in this area are a result of a leak which was reported to the NRC on December 10, 2007. None of the wells between TW-15 and Lake Michigan have had reportable concentrations of tritium in this reporting period. Monitoring of the groundwater tritium plume continues to assess repair effectiveness and follow the site hydrology data. Well. locations are depicted in Figure t. Depth to Local Water Table - The depth range for 2015 was approximately 7 to 8.5 feet. Classification of Subsurface Aquifers - Not used for drinking water. Expected Movement/Mobility of Groundwater Plume - Westerly direction down-gradient toward Lake Michigan at approximately 2.2 feet per day. Land Use Characteristics - PNP site property, water not used for drinking or irrigation. Page 8 of 10
Carbon-14 In 2010, PNP and other facilities participated in an EPRI task force to build a model to accurately estimate gaseous C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc). This work was completed in November 2010. The estimates for C-14 were constructed using the aforementioned EPRI methodology contained within EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents. Using the C-14 curie estimates, the annual dose to man was derived from guidance contained within Regulatory Guide 1.109. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required. Gaseous C-14 is reported as C02 Curies because the major pathway by which C-14 contributes to the dose to man is by entering vegetables in the form of C02 and then being ingested. Annual C-14 release for PNP and subsequent doses for 2015: Total Gaseous C-14 Released Curies= 7.74 Gaseous C-14 as C02 Curies = 2.32 Effective Child TB Dose, C-14 mrem = 0.0703 Effective Child Bone Dose, C-14 mrem = 0.352 The quarterly curies released are provided in Table 1A, Table 1B, arid Table 1C. Airborne doses due to C-14 are contained in Table 1A. Meteorological Data A meteorological monitoring report is generated semiannually. From January 1, 2015, to June 30, 2015, the meteorological data recovery was at 96% or greater for all variables. The two most frequently occurring directions at the 10-meter level were in the SSE and WNW sectors, accounting for over 22% of the observations from January through June. The two most frequently occurring directions at 60 meters were WNW*and S, accounting for over 19% of the observations from January through June. The highest average speeds were associated with NNW winds at both the 10-meter and 60-meter levels. The mean speed for all directions at 10 meters was 3.63 mis (8.12 mph), and at 60 meters was 6.42 mis (14.36 mph). Compared to the same period in the previous year, the 10-meter speed was 0.23 mis (0.51 mph) lower while the 60-meter speed was 0.50 mis (1.12 mph) lower. Page 9 of 10
From July 1, 2015, to December 31, 2015, the meteorological data recovery was at 99% or greater for all variables. The two most frequently occurring directions at the 10-meter level were SE and SSE, which accounted for over 24% of all observations from July to December. At 60 meters, the two predominant directions were SW and NNW, which accounted for over 20% of all observations from July to December. The highest average speeds were associated with SE winds at 10 meters and SW winds at 60 meters. The mean speed for all directions at 10 meters was 2.26 mis (5.06 mph), and at 60 meters was 4.91 mis (10.98mph). Compared to the same period in the previous year, the 10-meter speed is 0.02 mis (0.04 mph) higher while the 60-meter speed is 0.19 mis (0.43 mph) higher. Data from this report and the annual meteorological data (Hourly Average Data or Joint Frequency Distribution) will be maintained on site and will be made available upon NRC request. Page 10 of 10
ATTACHMENT 1 Palisades - Table 1A 2015 Gaseous Effluents - Sum of All Releases Summation of Uncertainty All Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (%) Fission and Activation Gases Ci 2.79E+OO 1.86E+OO 2.99E+OO 3.16E+OO 1.08E+01 24.03 Average Release Rate Ci/s 3.59E-01 2.36E-01 3.76E-01 3.98E-01 3.43E-01 % of Limit 3.66E-03 2.67E-03 4.69E-03 3.28E-03 3.58E-03 1-131 4.27E-05 3.50E-05 5.64E-05 9.45E-05 2.29E-04 Average Release Rate Ci/s 5.49E-06 4.45E-06 7.10E-06 1.19E-05 7.25E-06 % of Limit % 6.29E-08 5.09E-08 8.13E-08 1.36E-07 a. 30E-08 Particulates Ci O.OOE+OO 1.88E-05 1.89E-05 1.82E-04 2.20E-04 Average Release Rate Ci/s O.OOE+OO 2.40E-06 2.38E.:06 2.29E-05 6.96E-06 % of Limit % O.OOE+OO 1.10E-05 1.0BE-05 9.66E-06 7.90E-06 Tritium Ci 1.93E+OO 1.71 E+OO 2.88E+OO 4.37E+OO 1.09E+01 Average Release Rate Ci/s 2.48E-01 2.1 BE-01 3.62E-01 5.SOE-01 3.45E-01 % of Limit % 5.68E-04 4.99E-04 8.30E-04 1,26E-03 7.91 E-04 Gross Alpha Ci ND ND ND ND ND C-14 Ci 2.13E+OO 2.15E+OO 1.78E+OO 1.71 E+OO 7.74E+OO Average Release Rate Ci/s 2.73E-01 2.73E-01 2.24E-01 2.15E-01 2.45E-01 % of Limit % 2.09E-06 2.0BE-06 1.71 E-06 1.64E-06 1.87E-06 Page 1 of 1
ATTACHMENT 1 Palisades - Table 1 B 2015 Gaseous Effluents - Ground Level Release, Batch Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Ar-41 Ci ND ND ND ND ND Kr-85 Ci ND ND 2.70E-04 2.35E-04 5.05E-04 Kr-85m Ci ND ND ND 2.30E-03 2.30E-03 Kr-87 Ci ND ND ND ND ND Kr-88 Ci ND ND ND ND ND Xe-131m Ci ND ND ND 2.40E-03 2.40E-03 Xe-133 Ci ND ND 8.40E-04 1.03E+OO 1.03E+OO Xe-133m Ci ND ND ND 2.13E-02 2.13E-02 Xe-135 Ci ND ND 2.36E-05 5.48E-02 5.48E-02 Xe-135m Ci ND ND ND ND ND Xe-137 Ci ND ND ND ND ND Xe-138 Ci ND ND ND ND ND (List Others) Ci ND ND ND ND ND Total Ci ND ND 1.13E-03 1.11 E+OO 1.11 E+OO Iodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1-131 Ci ND ND ND 7.99E-05 7.99E-05 1-132 Ci ND ND ND ND ND 1-133 Ci ND ND ND ND ND 1-134 Ci ND ND ND ND ND 1-135 Ci ND ND ND ND ND Total Ci ND ND ND 7.99E-05 7.99E-05 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Co-58 Ci ND 3.53E-08 1.02E-07 9.99E-06 1.01 E-05 Co-60 Ci ND 1.88E-05 1.88E-05 1.60E-05 5.36E-05 Cr-51 Ci ND ND ND 4.25E-07 4.25E-07 Mn-54 Ci ND ND ND ND ND Mn-56 Ci ND ND ND ND ND Rb-88 Ci ND ND ND 1.47E"04 1.47E-04 Sr-89 Ci NR NR NR NR NR Sr-90 Ci NR NR NR NR NR Sr-92 Ci ND ND ND ND ND Nb-95 Ci ND ND ND 2.63E-06 2.63E-06 Zr-95 Ci ND ND ND 1.4BE-07 1.48E-07 Nb-97 Ci ND ND ND 5.43E-06 5.43E-06 Ag,1 iom Ci ND ND ND 1.47E-07 1.47E-07 Sb-125 Ci ND ND ND ND ND Cs"137 Ci ND ND ND 9.82E-08 9.82E-08 Ce-144 Ci ND ND ND ND ND Total Ci ND 1.88E-05 1.89E-05 1.82E-04 2.20E-04 Page 1 of 2
ATTACHMENT 1 Palisades - Table 1 B 2015 Gaseous Effluents - Ground Level Release, Batch Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium Ci ND ND ND 3.83E-01 3.83E-01 Gross Alpha Ci NR NR NR NR NR C-14 Ci NA NA NA NA ND ND = Measurements performed but no activity detected. NA = Not applicable NR = Analysis not required & not performed Page 2of2
ATTACHMENT 1 Palisades - Table 1C 2015 Gaseous Effluents - Ground Level Release, Continuous Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Ar-41 Ci 3.62E-01 3.01 E-01 9.40E-01 6.04E-01 2.21E+OO Kr-85 Ci ND ND ND ND ND Kr-85m Ci 7.00E-02 3.51 E-02 4.79E-02 9.47E-03 1.62E-01 Kr-87 Ci 1.60E~01 8.11 E-02 9.45E-02 8.74E-02 4.23E-01 Kr-88 Ci 1.16E-01 7.22E-02 3.71 E-02 3.08E-02 2.56E-01 Xe-131m Ci ND ND ND ND ND Xe-133 Ci 2.46E-01 1.48E-01 3.82E-01 1.11 E-01 8.88E-01 Xe-133m Ci ND ND ND ND ND Xe-135 Ci 7.04E-01 3.25E-01 4.38E-01 5.02E-01 1.97E+OO Xe-135m Ci 3.48E-02 1.62E-02 1.99E-03 ND 5.30E-02 Xe-137 Ci 2.33E-01 3.54E-01 4.41 E-01 1.52E-01 1.18E+OO Xe-138 Ci 8.66E-01 5.26E-01 6.07E-01 5.55E-01 2.55E+OO Total Ci 2.79E+OO 1.86E+OO 2.99E+OO 2.05E+OO 9.69E+OO Iodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1-131 Ci 4.27E-05 3.50E-05 5.64E-05 1.46E-05 1.49E-04 1-132 Ci ND ND ND ND ND 1-133 Ci 8.15E"05 1.03E-04 5.76E-05 ND 2.42E-04 1-134 Ci ND ND ND ND ND 1-135 Ci ND ND ND ND ND Total Ci 1.24E~04 1.38E-04 .1.14E-04 1.46E-05 3.91 E-04 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Co-58 Ci ND ND ND ND ND Co-60 Ci ND ND ND ND ND Cr-51 Ci ND ND ND ND ND Mn-54 Ci ND ND ND ND ND Mn"56 Ci ND ND ND* ND ND Rb-88 Ci ND ND ND ND ND Sr-89 Ci ND ND ND ND ND Sr-90 Ci ND ND ND ND ND Sr-92 Ci ND ND ND ND ND Nb-95 Ci ND ND ND ND ND Zr-95 Ci ND ND ND ND ND Nb~97 Ci ND ND ND ND ND Ag-110m Ci ND ND ND ND ND Sb-125 Ci ND ND ND ND ND Cs-137 Ci ND ND ND ND ND Ce-144 Ci ND ND ND ND ND Total Ci ND ND ND ND ND Page 1 of 2
ATTACHMENT 1 Palisades - Table 1C 2015 Gaseous Effluents - Ground Level Release, Continuous Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter3 Quarter 4 Annual Tritium Ci 1.93E+OO 1.71 E+OO 2.88E+OO 3.99E+OO 1.05E+01 Gross Alpha Ci ND ND ND ND ND C-14 Ci 2.13E+OO 2.15E+OO 1.78E+OO 1.71 E+OO 7.74E+OO ND =Measurements performed but rio activity detected. Page 2 of 2
ATIACHMENT1 Palisades -Table 2A 2015 Liquid Effluents - Sum of All Releases Summation of All Uncertainty Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total O/o Fission and Activation Products (excluding tritium, gases, and gross al ha Ci O.OOE+OO 1.17E-04 4.19E-04 2.58E-03 3.11 E-03 11.50 Average Concentration Ci/ml O.OOE+OO 3.49E-12 1.26E-11 8.03E-11 2.25E-11 % of Limit % O.OOE+OO 4.97E-05 2.43E-04 1.01 E-03 3.05E-04 Tritium Ci 8.09E+01 1.71 E+02 2.41 E+02 3.70E+01 5.30E+02 Average Concentration Ci/ml 2.Q6E-06 5.10E-06 7.21 E-06 1.15E-06 3.83E-06 % of Limit % 2.06E-01 5.1 OE-01 7.21 E-01 1.15E-01 3.83E-01 Dissolved and Entrained Gases Ci O.OOE+OO O.OOE+OO 6.57E-04 O.OOE+OO 6.57E-04 Average Concentration Ci/ml O.OOE+OO 0.00E+OO 1.97E-11 O.OOE+OO 4.75E-12 % Of Limit % O.OOE+OO O.OOE+OO 9.85E-06 O.OOE+OO 2.38E-06 Gross Alpha Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO Average Concentration Ci/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Volume of Batch Liquid Effluent (Before Dilution) Liters O.OOE+OO 1.79E+05 O.OOE+OO O.OOE+OO 1.79E+05 Dilution Water Used for Above Liters 3.93E+10 3.36E+10 3.34E+10 3.21E+10 1.38E+11 Volume of Continuous or Balance-of-Plant Liquid Effluent (e.g., low-activity or unprocessed) Before Dilution Liters 7.84E+09 7.93E+09 8.49E+09 7.75E+09 3.20E+10 Average Stream 3 Flow m /s 5.05E+OO 4.27E+OO 4.20E+OO 4.04E+OO 4.39E+OO Dilution flow rate (gal/qtr) = # of Dilution pumps running x days running/qtr x 4000 gpm/pump x min/day Page 1 of 1
ATTACHMENT 1 Palisades - Table 28 2015 Liquid Effluents - Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products Cr-51 Ci ND ND ND ND ND Mn-54 Ci ND ND ND ND ND Fe-55 Ci ND ND ND ND ND Fe-59 Ci ND ND 3.56E-05 3.56E-05 Co-57 Ci ND ND ND ND Co-58 Ci ND 2.45E-05 2.42E-05 1.51 E-03 1.56E-03 Co-60 Ci ND ND 1.45E-04 2.15E-04 3.60E-04 Sr-89 Ci ND ND ND ND ND Sr-90 Ci ND ND ND ND ND Nb-95 Ci ND ND ND 5.55E-05 5.55E-05 Nb-97 Ci ND ND 6.03E-05 ND 6.03E-05 Ag-11 Om Ci ND 9.28E-05 1.89E-04 6.40E-04 9.22E-04 Sn-113 Ci ND ND ND ND ND Sb-124 Ci ND ND ND ND ND Sb-125 Ci ND ND ND ND ND 1-131 Ci ND ND ND ND ND 1-133 Ci ND ND ND ND ND 1-135 Ci ND ND ND ND ND Cs-134 Ci ND ND ND ND ND Cs-137 Ci ND ND ND 2.68E-05 2.68E-05 Ni-63 Ci ND ND ND ND ND Zn-65 Ci ND ND ND ND ND Zr-95 Ci ND ND ND ND ND Mo-99 Ci ND ND ND ND ND Ru-105 Ci ND ND ND 5.65E-05 5.65E-05 La-140 Ci ND ND ND ND ND Ce-141 Ci ND ND ND ND ND Ce-144 Ci ND ND ND ND ND Totals Ci ND 1.17E-04 4.19E-04 2.54E-03 3.08E-03 Dissolved and Entrained Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Gases Kr-85 Ci ND ND ND ND ND Kr-85m Ci ND ND ND ND ND Kr-88 Ci ND ND ND ND ND Xe-131m Ci ND ND ND ND ND Xe-133 Ci ND ND 6.57E-04 ND 6.57E-04 Xe-133m Ci ND ND ND ND ND Xe-135 Ci ND ND ND ND ND Xe-135m Ci ND ND ND ND ND Totals ND ND 6.57E-04 ND 6.57E-04 Page 1 of 2
ATTACHMENT 1 Palisades - Table 28 2015 Liquid Effluents - Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products Tritium Ci 8.08E+01 1.71 E+02 2.41 E+02 3.70E+01 5.30E+02 Gross Alpha Ci ND ND ND ND ND ND= None Detected Page 2 of 2
ATTACHMENT 1 Palisades -Table 2C 2015 Liquid Effluents - Continuous Mode Fission and Activation Units Quarter 1 Quarter2 Quarter 3 Quarter 4 Annual Products Cr-51 Ci ND ND ND ND ND Mn-54 Ci ND ND ND ND ND Fe-55 Ci ND ND ND ND ND Fe-59 Ci ND ND ND ND ND Co-57 Ci ND ND ND ND ND Co-58 Ci ND ND ND ND ND Co-60 Ci ND ND ND ND ND Sr-89 Ci ND ND ND ND ND Sr-90 Ci ND ND ND ND ND Nb-95 Ci ND ND ND ND ND Nb-97 Ci ND ND ND ND ND Ag-110m Ci ND ND ND ND ND Sn-113 Ci ND ND ND ND ND Sb-124 Ci ND ND ND ND ND Sb-125 Ci ND ND ND ND ND 1-131 Ci ND ND ND ND ND 1-133 Ci ND ND ND ND ND 1-135 Ci ND ND ND ND ND Cs-134 Ci ND ND ND ND ND Cs-137 Ci ND ND ND 3.75E-05 3.75E"05 Ni-63 Ci ND ND ND ND ND Zn-65 Ci ND ND ND ND ND Zr-95 Ci ND ND ND ND ND Mo-99 Ci ND ND ND ND ND Ru-105 Ci ND ND ND ND ND La-140 Ci ND ND ND ND ND Ce-141 Ci ND ND ND ND ND Ce-144 Ci ND ND ND ND ND Totals Ci ND ND ND 3.75E-05 3.75E-05 Dissolved and Entrained Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Gases Kr-85 Ci ND ND ND ND ND Kr-85m Ci ND ND ND ND ND Kr-88 Ci ND ND ND ND ND Xe-131m Ci ND ND ND ND ND Xe-133 Ci ND ND ND ND ND Xe-133m Ci ND ND ND ND ND Xe-135 Ci ND ND ND ND ND Xe-135m Ci ND ND ND ND ND Totals ND ND ND ND ND Page 1 of 2
ATTACHMENT 1 Palisades - Table 2C 2015 Liquid Effluents - Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter3 Quarter 4 Annual Products Tritium Ci 5.40E-02 5.34E-02 1.50E-02 1.37E-02 1.36E-01 Gross Alpha Ci ND ND ND ND ND ND = None Detected Page 2 of 2
ATTACHMENT 1 Palisades - Table 3 2015 Low-Level Waste
- 1. Solid waste shipped offsite for burial or disposal (not irradiated fuel)
- 1. Type of waste Unit Estimated amount Est Total Error,%
- a. Spent resin, filters, m;:i 9.28E+OO evaporator bottoms, etc. 25 Curies 2.65E+01
- b. Dry compressible waste, m;:i 2.22E+02 dry active waste Curies 25 contaminated equipment, 3.50E+OO etc.
- c. Irradiated components, m;:i O.OOE+OO control rods, etc.
Curies O.OOE+OO
- d. Other (metal waste, and m;:i 8.62E+OO used oil) 25 Curies 3.67E+OO
- e. sum of all waste m;j 2.40E+02 25 Curies 3.37E+01 Page 1 of 3
ATTACHMENT 1 Palisades - Table 3 2015 Low-Level Waste
- 2. Estimate of Major Nuclide composition (by type of waste), list nuclides as needed
- a. Co-60 52% H-3 1.64%
Fe-55 18% Sb-125 1.73% Ni-63 19% Co-58 5.28%
- b. Co-60 24% Co-58 16.71%
Fe-55 17% Ni-63 11.79% Cs-137 1% Nb-95 5.94% Cr-51 5% Cm-243 1.69% AG-110m 4.73% H-3 1.27% Zr-95 3.44% C-14 2.81%
- c. NA NA NA NA
- d. H-3 3% Co-60 5.39%
C-14 2% Ni-63 77.79% Sr-90 1% Fe-55 9% Pu-241 1%
- e. H-3 1.72% Ag-110m 1.06%
Fe-55 16.71% Sb-125 1.43% Co-58 5.90% Ni-63 24.84% Co-60 43.70% NA - Not Applicable Page 2 of 3
ATTACHMENT 1 Palisades - Table 3 2015 Low-Level Waste
- 3. Solid waste disposition Number of shipments Mode of transportation Destination 2 Hittman Transport Alaron-Nuclear 2138 State Route 18 1 Hittman Transport Duratek Gallaher Road Facility 628 Gallaher Road 11 Hittman Transport Entergy Solutions Bear Creek Facility 1560 Bear Creek Road 1 Landstar lnway Entergy Solutions Bear Creek Facility 1560 Bear Creek Road 1 Landstar Ranger Inc. Entergy Solutions Bear Creek Facility 1560 Bear Creek Road Irradiated fuel shipments (disposition)
Number of shipments Mode of transportation Destination 0 N/A N/A Page 3 of 3
ATTACHMENT 1 Palisades - Table 4 2015 Dose Assessments, 10 CFR Part 50, Appendix I Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Dose Limit, Total 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem Body Total Body Dose (mrem) 6.07E-05 1.52E-04 2.43E-04 2.65E-04 6.44E-04 % Of Limit 0.00% 0.01% 0.02% 0.02% 0.02% Liquid Effluent Dose Limit, Any 5 mrem 5mrem 5 mrem 5 mrem 10 mrem Organ Liquid Effluent Organ Dose 6.07E-05 1.53E-04 2.45E-04 4.88E-04 8.72E (mrem) % of Limit 0.00% 0.00% 0.00% 0.01% 0.01% Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad GammaAir Gamma Air Dose (mrad) 1.16E-03 7.62E-04 1.24E-03 9.72E-04 4.14E-03 % of Limit 0.02% 0.02% 0.02% 0.02% 0.04% Gaseous Effluent Dose Limit, 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Beta Air Beta Air Dose (mrad) 8.97E-04 7.27E-04 1.03E-03 7.35E-04 3.39E-03 % of Limit 0.009% 0.007% 0.010% 0.007% 0.017% Gaseous Effluent Dose Limit, Any 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ (mrem) (Iodine, Tritium, Particulates) Gaseous Effluent Organ Dose 4.50E-03 3.94E-03 6.07E-03 7.BBE-03 2.24E-02 (mrem) (Iodine, Tritium, Particulates) % of Limit 0.06% 0.05% 0.08% 0.11% 0.15% Page 1 of 1
ATTACHMENT 1 Palisades - Table 5 2015 Dose Assessments, EPA 40 CFR Part 190, Individual in the Unrestricted Area Whole Body Thyroid Any Other Organ Dose Limit (mrem) 25 75 25 Dose (mrem) 8.05E-02 8.98E~02 3.75E-01 % of Limit 0.32% 0.12% 1.50% Page 1 of 1
ENCLOSURE 1 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL, REVISION 26 OFFSITE DOSE CALCULATION MANUAL APPENDIX A, REVISION 18 OFFSITE DOSE CALCULATION MANUAL APPENDIX B, REVISION 0 229 Pages Follow
ODCM Revision 26 lss ued Date 7/30/14 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: OFF SITE DOSE CALCULATION MANUAL J Process Applicability Exclusion D AKGennrich I 7/30/14 Procedure Sponsor Date MESoja I 6/22/14 Technical Reviewer Date CLJones I 7/29/14 User Reviewer Date ALWilliams I 7/29/14 General Manager Plant Operations Date
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Table of Contents I. GASEOUS EFFLUENTS ............................................................................................... 1 A. ALARM/TRIP SETPOINT METHOD .............................................................. 1
- 1. Allowable Concentration ................................... 2
- 2. Monitor Response ............................................. 3 B. DOSE RATE CALCULATION ........................................................................ 4 C. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION ................. 19
- 1. System Description ......................................... 19
- 2. Determination of Satisfactory Operation ....... 19 D. RELEASE RA TE FOR OFFSITE EC .......*................................................... 20 E. PARTICULATE AND IODINE SAMPLING .................................................. 20 F. NOBLE GAS SAMPLING ............................................................................ 21 G. TRITIUM SAMPLING ................................................................................... 21 H. FIGURE-GASEOUS EFFLUENTS FLOW PATHS ................................... 22 II. LIQUID EFFLUENTS ................................................................................................... 23 A. CONCENTRATION ...................................................................................... 23
- 1. Requirements ................................................... 23
- 2. Prerelease Analysis ......................................... 23
- 3. Effluent Concentration (EC) - Sum of the Ratios ................................................................ 24 B. INSTRUMENT SETPOINTS ......................................................................... 25
- 1. Setpoint Determination ................................... 25
- 2. Composite Samplers ....................................... 25
- 3. Post-Release Analysis .................................... 26 C. DOSE ........................................................................................................... 26
- 1. RETS Requirement .......................................... 26
- 2. Release Analysis ............................................. 26 D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT .............................. 30 E. RELEASE RATE FOR OFFSITE EC (50 MREMNR) .................................. 30 F. FIGURES ..................................................................................................... 31
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Table of Contents Ill. URANIUM FUEL CYCLE DOSE .................................................................................. 33 A. SPECIFICATION .......................................................................................... 33
- 8. ASSUMPTIONS ........................................................................................... 33 C. DOSE CALCULATION ................................................................................ 34 IV. SOURCE REFERENCE DOCUMENTS ....................................................................... 34 , "Palisades Gaseous And Liquid Source Terms, Curies/Year" , "Basic Radionuclide Data" , "Dose Factors for Submersion in Noble Gases" , "Stable Element Transfer Data" , "Inhalation Dose Commitment Factors" , "External Dose Factors for Standing on Contaminated Ground (DFGi)
(mrem/hr per pCi/m 2 )" , "Bioaccumulation Factors (µCi/gm per µCi/ml)" , "Ingestion Dose Commitment Factors" , "Palisades 10 Year X/Q - D/Q Data"
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 I. GASEOUS EFFLUENTS A. ALARM/TRIP SETPOINT METHOD Appendix A, Section 111.B.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following: For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and For iodine-131, for iodine-133, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. Appendix A, Section 111.A.1 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations, when averaged over 1 hour, will not be greater than Appendix A, Section 111.B.1. This section of the ODCM describes the methodology that will be used to determine these setpoints. The methodology for determining alarm/trip setpoints is divided into two major parts. The first consists of calculating an allowable concentration for the nuclide mixture to be released. The second consists of determining monitor response to this mixture in order to establish the physical settings on the monitors. 1
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 1. Allowable Concentration NOTE: If a batch release is made while a continuous release or another batch release is in progress, the sum of all values of Rk must be less than 10.0.
The total EC-fraction (Rk) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20: Rk =XIQ x F x Li C/ECi :5 10.0 (1.1) where: Actual or measured concentration, at ambient temperature and pressure of nuclide i (µCi/cc) The EC of nuclide i from 10 CFR 20, Appendix B, Table 2 The total EC-fraction for release point k X/Q = Most conservative sector site boundary dispersion (sec/m 3) (listed in site procedure CH 6.41, "Land Use Census") F = Release flow rate (83,000 cfm = 39.2 m 3/sec) for stack monitor considerations; variable for other monitors 2
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 2. Monitor Response Normal radioactivity releases consist mainly of well-decayed fission gases.
Therefore, monitor response calibrations are performed to fission gas typical of normal releases (mainly Xe-133). Response of monitors used to define fission product release rates under accident conditions may vary from that of Xe-133, however. Monitor response for the two categories of monitor is determined as follows:
- a. Normal Release (aged fission gasses)
Total gas concentration (µCi/cc) at the monitor is calculated. The detector response to isotopic activities (cpm/µCi/cc) is applied to determine cpm expected. The setting for monitor alarms is established at some factor (b) greater than 1 but less than 1/Rk (Equation 1.1) times the measured concentration (c): s=bxc (1.2)
- b. Accident Releases Monitors are preset to alarm at or before precalculated offsite dose rates would be achieved under hypothetical accident conditions.
These setpoints are established in accordance with Emergency Plan requirements for defining Emergency Action Levels and associated actions. Emergency Implementing Procedures contain monitor-specific curves or calibration constants for conversion between cpm and µCi/cc (or R/hr and µCi/cc), depending on monitor type, for fission product mixtures as a function of mixture decay time. When these monitors are utilized for other than accident conditions, either an appropriately decayed "accident" conversion curve may be used, or a decayed fission gas calibration factor may be applied. In these cases, setpoints are established as in 1.A above. Setpoints of accident monitors (if set to monitor normal releases) are reset to the accident alarm settings at the end of normal release. Setpoints of other release monitors are maintained at the level used at the latest release (well below the level which would allow 10 times EC to be exceeded at the site boundary), or are reset to approximately three times background in order to detect leakage or inadvertent releases of low level gases. 3
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 B. DOSE RATE CALCULATION
- 1. Dose rates are calculated for (1) noble gases and (2) iodines and particulates.
Dose rates as defined in this section are based on 10 CFR 50 Appendix I limits of mrem per quarter and millirem per year. All dose pathways of major importance in the Palisades environs are considered. NRCDose is the Effluent Dose Calculation software that supports LADTAP, GASPAR, and XOQDOQ which perform the actual dose calculations using the equations supplied here.
- a. Equations and assumptions for calculating doses from noble gases are as follows:
- 1) Assumptions a) Doses to be calculated are the maximum offsite point in air, total body and skin.
b) Exposure pathway is submersion within a cloud of noble
\.
gases. c) Noble gas radionuclide mix is based on the historically observed source term given in Attachment 2, plus additional nuclides. d) Basic radionuclide data are given in Attachment 2. e) All releases are treated as ground-level. f) Meteorological data expressed as joint-frequency distribution of wind speed, wind direction, and atmospheric stability for the period resulting in X/Q's and D/Q's shown in site procedure CH 6.41, "Land Use Census." g) Raw meteorological data consists of wind speed and direction measurements at 1Om and temperature measurements at 1Om and 60m. h) Dose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist (overland sector site boundaries), and nearest residents. 4
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 i) Potential maximum population (resident) exposure points are identified in site procedure CH 6.41, "Land Use Census." j) A semi-infinite cloud model is used. k) Radioactive decay is considered for the plume. I) Building wake effects on effluent dispersion are considered. m) A sector-average dispersion equation is used. n) The wind speed classes that are used are as follows: Wind Speed Class Number Range (m/s) Midpoint (m/s) 1 0.0-0.4 0.2 2 0.4-1.5 0.95 3 1.5-3.0 2.25 4 3.0-5.0 4.0 5 5.0-7.5 6.25 6 7.5-10.0 8.75
~1 > 10.0 o) The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, 8=2, ... , G=7.
p) Terrain effects are not considered. 5
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 2) Equations To calculate the dose for any one of the exposure points, the following equations are used.
For determining the air concentration of any radionuclide: X = I9 I7 ( 2) 1/2 f1k Qi P [ - ;i. x Jl ( (1.3)
' j=l k=l 7r LzkVJ (27rxln) exp IUi where:
= Air concentration of radionuclide i, µCi/m 3 .
= Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
= Average release rate of radionuclide i, µCits.
p = Fraction of radionuclide remaining in plume. Lzk = Vertical dispersion coefficient for stability class k (m). Uj = Midpoint value of wind speed class interval j, m/s. x = Downwind distance, m. n = Number of sectors, 16. Ai = Radioactive decay coefficient of radionuclide i, s- 1. 2nx/n = Sector width at point of interest, m. 6
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the total body dose rate: (1.4) where: Drs = Total body dose rate, mrem/y. 3 xi = Air concentration of radionuclide I, µCi/m . DFBi = Total body dose factor due to gamma radiation, 3 mrem/y per µCi/m (Attachment 3). For determining the skin dose rate: (1.5) where:
= Skin dose rate, mrem/y.
= Air concentration of radionuclide i, µCi/m 3 Skin dose factor due to beta radiation, mrem/y per
µGi/m 3 (Attachment 3).
1.11 = The average ratio of tissue to air energy absorption coefficients, mrem/mrad. Gamma-to-air dose factor for radionuclide i, mrad/y per µCi/m 3 (Attachment 3). For determining dose rate to a point in air: (1.6) where:
= Air dose rate, mrad/yr.
Air dose factor for beta radiation (Attachment 3). 7
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- b. Equations and assumptions for calculating doses from radioiodines and particulates are as follo'!lfs:
- 1) Assumptions a) Dose is to be calculated for the critical organ, thyroid, and the critical age groups (adult, teen, child, infant), infant (milk) and child (green, leafy vegetables).
b) Exposure pathways from iodines and particulates are milk ingestion, ground contamination, green leafy vegetables from home gardens, and inhalation. c) The radioiodine and particulate mix is based on the historically observed source term given in Attachment 2. d) Basic radionuclide data are given in Attachment 3. e) All releases are treated as ground-level. f) Mean annual average X/Q's are given in site procedure CH 6.41, "Land Use Census." g) Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 1Om and temperature measurements at 1Om and 60m. h) Dose is to be evaluated at the potential offsite exposure points where maximum doses to man are expected to exist. i) Real cow, goat and garden locations are considered. j) Potential maximum exposure points (site procedure CH 6.41, "Land Use Census") considered are the nearest cow, goat, and home garden locations in each sector. k) Terrain effects and open terrain recirculation factors are not considered. I) Building wake effects on effluent dispersion are considered. 8
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 m) Plume depletion and radioactive decay are considered for air-concentration calculations. n) Radioactive decay is considered for ground-concentration calculations. o) Deposition is calculated based on the curves given in Figure 1.2. p) Milk cows and goats obtain 100% of their food from pasture grass May through October of each year. Use default values of 0.58 for cows and 0.67 for goats for fraction of year on pasture.
- 2) Equations To calculate the dose for any one of the potential maximum-exposure points, the following equations in Section 1.2.2 are used.
a) Inhalation Equation for calculating air concentration, Xi is the same as in the Noble Gas Section (Equation 1.3). For determining the organ dose rate: Di= 1x106 L X;DFI; BR (1.7) where: Di = Organ dose rate due to inhalation, mrem/y. xi = Air concentration of radionuclide i, µCi/m 3 . DFli = Inhalation dose factor, mrem/pCi (Attachment 5). BR = Breathing rate 1400 m3/y infant; 3700 m 3/y child; or 8000 m3/y teen and adult. 1x10 6
= pCi/µCi conversion factor.
9
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 b) Ground Contamination For determining the ground concentration of any nuclide; where: Ground concentration of radionuclide i, 2
µCi/m .
k = Stability class. Joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point, expressed as a fraction. Average release rate of radionuclide i,
µCi/s.
DR = Relative deposition rate, m-1 (Fig 1.2). x = Downwind distance, m. n = Number of sectors, 16. 2mc/n = Sector width at point of interest, m.
= Radioactive decay coefficient of radionuclide i, y- 1.
= Time for buildup of radionuclides on the ground, 15 y.
3.15x10 7 = s/y conversion factor. 10
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Figure 1.2 Corrected 10 3 January 1977 I I I I~ : I
' 'l
~~ .. !
i.o-4 II
-a:
II.I
- i j ~ ;
II.I
- I cc:
II.I
' ""Iii.
II.I
~ "' ~
c( a: co
"' '"- lilo 0 ~
11J""i'
~ ..
-~
"'Q ......... "'2 ~ '""' ....ct ... IC
'\\. I 1o-8 I I iI !
I 1 ' I I I I J 11 10-7 11 I; ' j 0.1 . 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) Figure 7. Relative Deposition for Ground Level R1leam (All Atmospheric St1bility Cl1sses) n - -- r-11
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the total body or organ dose rate from ground contamination: Da = (8, 760)(1X10 6)(0. 7) LG; DFG; (1.9) where: Dose rate due to ground contamination, mrem/y. Ground concentration of radionuclide i,
µCi/m 2 .
Dose factor for standing on contaminated ground, mrem/h per pCi/m 2 (Attachment 6). 8,760 = Occupation time, h/y. 1x106 = pCi/µCi conversion factor. 0.7 = Shielding factor accounting for a distance of 1.0 meter above ordinary ground, dimensionless. c) Milk and Vegetation Ingestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation: 7 .
.=
3,600 L fkQ;DR (r[l-exp(-A,E;te)] + B;Jl-exp(-.4/b)]Jrrex (- . ))) ( 1.10) CV, ( xi) . PA. u_ P .4,!b k = 1 2 Jr n Yv AE1 i where: cvi = Concentration of radionuclide i in and on vegetation, µCi/kg. k = Stability class. fk = Frequency of this stability class and wind direction combination, expressed as a fraction. 12
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Qi = Average release rate of radionuclide i,
µCi/s.
DR = Relative deposition rate, m- 1 (Figure 1.2). x = Downwind distance, m. n = Number of sectors, 16. 2nx/n = Sector width at point of interest, m. r = Fraction of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulates). AEi = Effective removal rate constant,
=
AEi Ai + "'J..w, where Ai is the radioactive decay coefficient, h- 1 , and "'J..w is a measure of physical loss by weathering
=
("'J..w 0.0021 h} te = Period over which deposition occurs, 720 h. Yv = Agricultural yield, 0.7 kg/m 2 . Biv = Transfer factor from soil to vegetation of radionuclide i (Attachment 4). Ai = Radioactive decay coefficient of radionuclide i, h-1 . tb = Time for buildup of radionuclides on the ground, 1.31x105 h (15Y). 2 p = Effective surface density of soil, 240 kg/m . 3,600 = s/h conversion factor. th = Holdup time between harvest and consumption of food (2, 160 hours for stored food). 13
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the concentration of C-14 in vegetation: CV14 =1 X10 3 X14 (0.11/0.16) (1.11) where: Concentration of C-14 in vegetation, µCi/kg. Air concentration of C-14, µCi/m 3 . 0.11 = Fraction of total Plant mass that is natural carbon. 0.16 = Concentration of natural carbon in the atmosphere, g/m 3 . 1x103 = g/kg conversion factor. For determining the concentration of H-3 in vegetation: CVr=1x1Q 3 Xr(0.75)(0.5/H) (1.12) where: CVr = Concentration of H-3 in vegetation, µCi/m 3 . Xr = Air concentration of H-3, µCi/m 3 . 0.75 = Fraction of total Plant mass that is water. 0.5 = Ratio of tritium concentration in Plant water to tritium concentration in atmospheric water.
- H = Absolute humidity of the atmosphere, g/m 3 .
1x103 = g/kg conversion factor. 14
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the concentration of any nuclide in cow's or goat's milk: (1.13) where: CMi = Concentration of radionuclide i (including C-14 and H-3) in milk, µCi/I. cvi = Concentration of radionuclide i in and on vegetation, µCi/kg. FMi = Transfer factor from feed to milk for radionuclide i, d/I (Attachment 4). Ot = Amount of feed consumed by the milk animal per day, kg/d (cow, 50 kg/d or goat 6 kg/d).
= Radioactive decay coefficient of radionuclide i, d-1*
= Transport time of activity from feed to milk to receptor, 2 days.
15
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 For determining the organ dose rate from ingestion 'Of green leafy vegetables and milk: D=l xl0 6 LCM; DE UM (1.14) where: D = Organ dose rate due to ingestion, mrem/y. CMi = Concentration of radionuclide i in vegetables or milk, µCi/kg (or liters). DFi = Ingestion dose factor, mrem/pCi (Attachment 8). UM = Ingestion rate for milk, 330 l/y; for vegetables 26 kg/yr (child), no ingestion by infant. 1x106 = pCi/µCi conversion factor. d) Meat Ingestion (Beef) To calculate the concentration of a nuclide in animal flesh: (1.15) where: cfi = Concentration-of nuclide i in the animal flesh, pCi/kg. Fraction of animal's daily intake which appears in each kg of flesh, days/kg (Attachment 4). Concentration of radionuclide i in the animal's feed (Equation 1.10). 16
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
= Amount of feed consumed by the cow per day, 50 kg/d.
= Average time from slaughter to consumption, 20 days.
To determine the organ dose from ingestion of beef: (1.16) where:
= Ingestion dose factor for age group, mrem/pCi (Attachment 8) for nuclide i.
= Ingestion rate of meat for age group, kg/y (child-41, teen-65, adult-110).
e) OrganDose Rates For determining the total body and organ dose rate from iodines and particulates: (1.17) where: D = Total organ dose rate, mrem/y. D1 = Dose rate due to inhalation, mrem/y. DG = Dose rate due to ground contamination, mrem/y. DM = Dose rate due to milk ingestion, mrem/y. Dv = Dose rate due to vegetable ingestion, mrem/y. DF = Dose rate due to beef ingestion, mrem/y. 17
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 3) The maximum organ dose rate, maximum total body dose rate, and maximum skin dose rate calculated in the previous section (Sec l.B) are used to calculate design basis quantities as described in Section l.B.1.3.
- c. Land Use Census Appendix A, Sections J.3.b and J.3.c describe the requirements for an annual land use census. Changes will be effective on January 1 of the year following the year of the survey.
- d. Gaseous Releases From the Steam Generator Slowdown Vent and Atmosphere Release Valves Releases from the steam generator blowdown vent and atmospheric relief valves are difficult to quantify as there are no sampling capabilities on these steam release systems. However, neither system is a normal release path. The steam generator blowdown vent is normally routed to the main condenser and recirculated. Radioactive releases will be calculated by analyzing steam generator blowdown liquid and assuming that 100 percent of Noble Gases, 10 percent of the Iodines and 1 percent of the Particulates will be released to the environment in the steam phase, Volumes will be released to the environment in the steam phase. Volumes will be calculated using water balances or alternate means as available.
18
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 C. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA.
- 1. System Description A flow diagram for the GRTS is given in Figure 1-1. The system consists of three waste-gas compressor packages, six gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown and displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header.
Design of the system precludes hydrogen explosion by means of ignition source elimination (diaphragm valves, low flow diaphragm compressors and system electrical grounding), and minimization of leakage outside the system. Explosive mixtures of hydrogen and oxygen have been demonstrated compatible with the system by operational experience.
- 2. Determination of Satisfactory Operation Doses will be calculated for batch and continuous releases as described in Section l.B. These calculations will be used to ensure that the GRTS is operating as designed. Because the Plant was designed to collect and hold for decay a vast majority of the high level gases generated within the primary system, and because the operating history of the Plant has demonstrated the system's consistent performance well below Appendix I limits, no additional operability requirements are specified.
19
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 D. RELEASE RATE FOR OFFSITE EC 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be in concentrations less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. (Note: there are no unrestricted areas anywhere within the site boundary as defined by Figure 1-1.) Concentrations at this level if inhaled or ingested continuously for one year will result in a dose of 50 mrem whole body except for submersion dose isotopes (gaseous tritium and noble gasses) which will results in a dose of 100 mrem whole body. 10 CFR 50.36a requires that the release of radioactive materials be kept as low as reasonably achievable. However, the section further states that the licensee is permitted the flexibility of operation, to assure a dependable source of power even under unusual operating conditions, to release quantities of material higher than a small percentage of 10 CFR 20.1302 limits but still within those limits, Appendix I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement. The GASPAR code has been run to determine the dose due to external radiation and inhalation. The source term used is listed in Attachment 2. The meteorology data is given in site procedure CH 6.41, "Land Use Census." Dose using annual average meteorology, to the most limiting organ of the person assume to be residing at the site boundary with highest X/Q, is 2.15E-02 mrem (for one year). The release rate which would result in a dose rate equivalent to 50 mrem/year (using the more conservative total body limit) is the curies/year given in Attachment 2 multiplied by 50/2.15E-02 or 0.11 Ci/sec. E. PARTICULATE AND IODINE SAMPLING Particulate and iodine samples are obtained from the continuous sample stream pulled from the Plant stack. Samples typically are obtained to represent an
. integrated release from a gas batch (waste gas decay tank or Containment purge, for example), or a series of samples are obtained to follow the course of a release.
In any event, sample intervals are weekly, at a minimum. Because HEPA filters are present between most source inputs to the stack and the sample point, releases of particulates normally are significantly less than pre-release calculations indicate. This provides for conservatism in establishing setpoints and in estimation of pre-release dose calculations. However, for the sake of maintaining accurate release totals, monitor results (for gases) and sample results (for particulates and iodines) utilized rather than the pre-release estimates, for cumulative records. 20
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released. Sampling and analysis will be performed per Appendix A, Table B-1 requirements. F. NOBLE GAS SAMPLING Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the Containment prior to purging. Analysis of these samples will be used for accountability of noble gases. Off gas will be sampled at least weekly and used to calculate monthly noble gas releases. Non-routine releases will be quantified from the stack noble gas monitor (RE 2326) which has a LLD of 1E-06 µCi/cc. Sampling and analysis will be performed per Appendix A, Table B-1 requirements. G. TRITIUM SAMPLING Tritium has a low dose consequence to the public because of low energy decay. The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded). Because of the low dose impact, gaseous tritium sampling will not be required. Tritium effluents will be estimated using conservative evaporation rate calculations from the fuel pool and reactor cavity. 21
- c UElfrS "T1 STACK G) c
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)>
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 11. LIQUID EFFLUENTS A. CONCENTRATION
- 1. Requirements Appendix A, Section 111.G requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to ten times the Effluent Concentration (EC) specified in 10 CFR 20, Appendix B, Table 2, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 µCi/ml total activity. To ensure. compliance, the following approach will be used for each release.
- 2. Prerelease Analysis Most tanks will be recirculated through two volume changes prior to sampling for release to the environment to ensure that a representative sample is obtained. The appropriate recirculation time for those tanks too large to provide two volume changes will be the time that the suspended particulate concentration reaches steady state. Either a one-time test, or prior sampling data, may be used to determine appropriate recirculation time.
Prior to release, a grab sample will be analyzed for each release, and the concentration of each radionuclide determined. c = (2.1) where: c = Total concentration in the liquid effluent at the release point, µCi/ml.
= Concentration of a single radionuclide i, µCi/ml.
23
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 3. Effluent Concentration (EC) - Sum of the Ratios The EC-Fraction (Rj) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:
Rj I __9_:::;10.0 (2.2) EC where: Ci = Effluent concentration of radionuclide i, µCi/ml. ECi = The EC of radionuclide i, 10 CFR 20, Appendix B, Table 2, Column 2 - µCi/ml. Ri = The Total EC-Fraction for the release point. The sum of the ratios at the discharge to the lake must be:::; 10 due to the releases from any or all concurrent releases. The following relationship will assure this criterion is met: (2.3) where:
= The effluent flow rate (gallons/minute) for the respective releases, determined by Plant personnel.
= The Total EC-Fractions for the respective releases as determined by Equation 2.2.
F = Minimum required dilution flow rate. Normally, a conservatively high dilution flow rate is used, that is, flow
=
rate used (bi)(F) where bi is a conservative factor greater than 1.0. 24
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 B. INSTRUMENT SETPOINTS
- 1. Setpoint Determination Appendix A, Section 111.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to ensure the requirements of Appendix A, Section 111.G are not exceeded. Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivalent setpoint in counts per minute (cpm). The identification number for each liquid effluent radiation detector is contained in Figure 2-2.
The respective alarm/trip setpoints at each release point will be set such that the sum of the ratios at each point, as calculated by Equation 2.2, will not be exceeded. The value of R is directly related to the total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the value of R. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm/trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint (S) be set above the effluent concentration (C) by the same factor (b) utilized in setting dilution flow. That is: S = bxC (2.4) Liquid effluent flow paths and release points are indicated in Figure 2.1.
- 2. Composite Samplers Effluent pathways, Turbine Sump and Service Water, are equipped with continuous compositors to meet the requirements of Appendix A, Table D-1.
These compositors are adjustable and normally set in a time mode and collect three to six samples hourly, 24 hours a day with a total collection of approximately one gallon per day. A representative sample is collected daily from the compositor and saved for the weekly, monthly, and quarterly analysis requirements of Appendix A, Table D-1. In the event that a compositor is not operational, effluent releases via this pathway may continue provided that grab samples are collected and analyzed for gross beta or gamma radioactivity at least once per 24 hours per Appendix A, Table C-1, Action 3. 25
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- 3. Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 1 were not exceeded.
A composite list on concentrations (Ci), by isotope, will be used with the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate compliance with the limits in Section 1. This data and setpoints will be recorded in auditable records by Plant personnel. C. DOSE
- 1. RETS Requirement Appendix A, Section 111.H.1 requires that the quantity of radionuclides released by limited such that the dose or dose commitment to an individual from radioactive materials in liquid effluents release to unrestricted areas from the reactor (see Figure 2-1) will not exceed:
- a. During any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ, and
- b. During any calendar year, 3 mrem to the total body and 10 mrem to any organ.
To ensure compliance, quantities of activity of each radionuclide released will be summed for each release and accumulated for each quarter as follows in Section 2.
- 2. Release Analysis Dose calculations shall be performed for each batch release, and weekly for continuous releases unless documentation exists to demonstrate an activity below which dose limits of Section 11.C.1 will not be exceeded.
- a. Water Ingestion The dose to an individual from ingestion of radioactivity from any source as described by the following equation:
Di I (DCF)ii x h (2.5) i= I 26
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 where:
= Dose for the r organ from radionuclides releases, mrem.
= The organ of interest.
(DCF)ij = Ingestion dose commitment factor for the jth organ from the i1h radionuclide mrem/pCi, see Attachment 8.
= Activity ingested of the i1h radionuclide, pCi.
Ii is described by: I*= (Ai)(V)(365) (1E06) (2.6) I (1QQQ)(d} where: 365 = Days per year. Ai = Annual activity released of i1h radionuclide, µCi. v = Average rate of water consumption (2000 ml/d - adult, 1400 ml/d - teen and child, 900 ml/d - infant, ICRP 23, p 358). d = Dilution water flow for year, ml. 1000 = Dispersion factor from discharge to nearest drinking water supply. 1E06 = Conversion µCi to pCi. The dose equation then becomes: i Di= ( 3 .SS~OS)(V) L: (DCF)iiXAimrem (2.7) i=1 27
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- b. Fish Ingestion*
The dose to an individual from the consumption of fish is described by Equation 2.10. In this case, the activity ingested of the ith radionuclide (h) is described by: _ AiBiF(1E09) _ c* h- 15d -p I (2.8) where:
= Annual released of ith radionuclide, µCi.
= Fish concentration factor of ith radionuclide
µCi/gm
µCi/ml (see Attachment 7).
F = Amount of fish eaten per year (21 kg adult, 16 kg teen, 6.9 kg child, none infant). 15 = Dispersion factor from discharge to fish exposure point. d = Dilution water flow for year, ml. 1E09 = Conversion of µCi, gm, and Kg to pCi. Substitution of Equation 2.8 into Equation 2.5 gives: i (6.7E07)F Di= d I AiXBiXDCFimrem (2.9) i =1 28
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26
- c. Annual*Analysis A complete analysis utilizing the NRC computer code LADTAP with the total source release Will be done annually in conjunction with the annual environmental report. This analysis will provide estimates of dose to the total body *and various organs in addition to the dose limiting organs considered in the method of Section 2. The following approach is utilized on LADTAP. The dose to the j1h organ from m radionuclides, Dj, is described by:
m Di= I oiimrem (2.10) i =1 m
= I (DCF )ii x Ii mrem (2.11) i =1 where:
Dose to the j1h organ from the i1h radionuclide, mrem.
= The organ of interest (bone, GI tract, thyroid, liver, kidney, lung, or total body).
(DCF)ij = Adult ingestion dose commitment factor for the j1h organ from the i1h radionuclide, mrem/pCi (see Attachment 8).
= Activity ingested of the i1h radionuclide, µCi.
hfor water ingestion is described by: I* _AiVr
---µ er* (2.12)
I Vd and for fish ingestion Ii is described by: (2.13) 29
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 where: Ai = Activity release of j1h radionuclide during the year, µCi. v = Average rate of water consumption (2000 mild). r = Number of days during the year (365 d). v = Dispersion factor from point of discharge to point of exposure. d = Dilution water volume (ml). Bi = Fish concentration factor of the i1h radionuclide,
µCi/gm Attachment 7, µCi/ml F = Amount of fish eaten per day (57.5 gm/d).
D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT The Palisades liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their discharge (through deep bed filtration and ion exchange) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2-1) will not exceed the limits of Appendix A, 111.H.1. E. RELEASE RATE FOR OFFSITE EC (50 MREMNR) 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. Concentrations at this Effluent Concentration (EC) level, if ingested for one year, will result in a dose of 50 millirem to the total body. In addition, 10 CFR 50.36a requires that the release of radioactive materials be kept as low as is reasonably achievable. Appendix I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement. The LADTAP code has been run to determine the dose due to drinking water at Plant discharge concentration (1,000 x nearest drinking water intake concentration). The nominal average source term used is given in Attachment 2. Dose to the most limiting organ of the person hypothetically drinking this water is 3.88E-03 mrem. This is only 0.13% of the more conservative 50 mrem/yr total body value. 30
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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 Ill. URANIUM FUEL CYCLE DOSE A. SPECIFICATION In accordance with Appendix A, Section 111.1.1, if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Appendix A, Sections 111.C.1, 111.D.1, or 111.H.1, then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste storage tanks) shall be calculated. The dose is to be determined for the member of the public protected to be the most highly exposed to these combined sources. B. ASSUMPTIONS
- 1. The full time resident determined to be maximally exposed individual (excluding infant) is assumed also to be a fisherman. This individual is assumed to drink water and ingest local fish at the rates specified in Sections 11.C.2.1 and 11.C.2.2.
- 2. Amount of shore line fishing (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours per quarter (average of approximately 1/2 hour per day each day of the quarter) for the second and third quarters of the year, 36 hours for the fourth quarter and 16 hours for the first quarter.
33
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 26 C. DOSE CALCULATION Maximum doses to the total body and internal organs of an individual shall be determined by use of LADTAP and GASPAR computer codes, and doses to like organs and total body summed. Added to this sum will be a mean dose rate, calculated or measured for the shoreline due to Plant present curing the quarter in question, times the assumed fishing time. D4o = (2.15) where: D4o = 40 CFR 190 dose (mrem). DG = Limiting dose to an individual from gaseous source term (mrem). DL = Limiting dose to an individual from liquid source term (mrem). Rr = Mean dose rate calculated to be applicable to Lake Michigan shoreline adjacent to Plant site (mrem/hr). T = Assumed shoreline fishing time for the quarter in questions (hours). IV. SOURCE REFERENCE DOCUMENTS
- 1. Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioacitve Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, R 1.
- 2. 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, R1.
- 3. NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, April 91.
- 4. NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, R3.
- 5. NUREG/CR-4013, LADTAP II - Technical Reference and User Guide, April 86.
- 6. NUREG/CR-4653, GASPAR II - Technical Reference and User Guide, March 87.
- 7. CH 6.61, Revising the ODCM and ODCM Appendix A.
34
Proc No ODCM Attachment 1 Revision 26 Page 1of1 PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIESNEAR (1) Nuclide Gaseous(2) Liquid(2) H-3 5.5 159 Kr-85 4.1 NA Kr-85m 0.12 NA Kr-87 8.4E-02 NA Kr-88 2.1E-01 NA Ar-41 3.1E-02 NA Xe-131m 2.2 NA Xe-133 1493 NA Xe-133m 0.43 NA Xe-135 1.11 NA Xe-135m 0.3 NA 1-131 0.025 3.21E-03 1-132 2.91E-03 NA 1-133 6.5E-03 4.7E-05 1-134 4.8E-04 NA 1-135 1.84E-02 NA Na-24 1.5E-06 NA Cr-51 '2.5E-04 3.9E-03 Mn-54 4.1E-04 7.8E-03 Co~57 2.1 E-06 3.2E-05 Co-58 8.6E-04 2.9E-02 Fe-59 6.6E-06 4.1E-04 Co-60 1.1E-03 1.24E-02 Se-75 3.7E-06 NA Nb-95 2.4E-05 4.53E-04 Zr-95 4.7E-06 1.79E-04 Mo-99 1.5E-07 NA Ru-103 0.3E-07 0.1 E-05 Sb-127 NA 3.5E-05 Cs-134 4.5E-05 0.7 Cs-136 NA 1.8E-06 Cs-137 2.6E-04 1.36E-02 Ba-140 2.8E-07 NA La-140 7.5E-07 1.1 E-04 Unidentified beta 3.9E-04 3.3E-03 (1) Data derived from taking the effluents released during July-December 1978 through January-June 1982 and dividing by 4. (2) Nuclide values listed as NA have not been observed at detectable levels in these waste streams.
Proc No ODCM Attachment 2 Revision 26 Page 1of2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA1 GAMMA1 (days) (1/s) (MEV/DIS) (MEV/DIS) 1 Tritium 4.49E 03 1.79E-09 5.68E-03 0.0 2 C-14 2.09E 06 3.84E-12 4.95E-02 0.0 3 N-13 6.94E-03 1.16E-03 4.91 E-01 1.02E 00 4 0-19 3.36E-04 2.39E-02 1.02E 00 1.05E 00 5 F-18 7.62E-02 1.05E-04 2.50E-01 1.02E 00 6 NA-24 6.33E-01 1.27E-05 5.55E-01 4.12E 00 7 P-32 1.43E 01 5.61E-07 6.95E-01 0.0 8 AR-41 7.63E-02 1.05E-04 4.64E-01 1.28E 00 9 CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02 10 MN-54 3.03E 02 2.65E-08 3.80E-03 8.36E-01 11 MN-56 1.07E-01 7.50E-05 8.29E-01 1.69E 00 12 FE-59 4.50E 01 1.78E-07 1.18E-01 1.19E 00 13 C0-58 7.13E 01 1.12E-07 3.41 E-02 9.78E-01 14 C0-60 1.92E 03 4.18E-09 9.68E-02 2.50E 00 15 ZN-69m 5.75E-01 1.39E-05 2.21E-02 4.16E-01 16 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 BR-84 2.21E-02 3.63E-04 1.28E 00 1.77E 00 18 BR-85 2.08E-03 3.86E-03 1.04E 00 6.60E-02 19 KR-85m 1.83E-01 4.38E-05 2.53E~01 1.59E-01 20 KR-85 3.93E 03 2.04E-09 2.51 E-01 2.21E-03 21 KR-87 5.28E-02 1.52E-04 1.32E 00 7.93E-01 22 KR-88 1.17E-01 6.86E-05 3.61E-01 1.96E 00 23 KR-89 2.21E-03 3.63E-03 1.36E 00 1.83E 00 24 RB-88 1.24E-02 6.47E-04 2.06E 00 6.26E-01 25 RB-89 1.07E-02 7.50E-04 1.01E 00 2.05E-OO 26 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 28 SR-91 4.03E-01 1.99E-05 6.50E-01 6.95E-01 29 SR-92 1.13E-01 7.1 OE-05 1.95E-01 1.34E 00 30 SR-93 5.56E-03 1.44E-03 9.20E-01 2.24E 00 31 Y-90 2.67E 00 3.00E-06 9.36E-01 0.0 32 Y-91m 3.47E-02 2.31E-04 2.73E-02 5.30E-01 33 Y-91 5.88E 01 1.36E-07 6.06E-01 3.61E-03 34 Y-92 1.47E-01 5.46E-05 1.44E 00 *2.50E-01 35 Y-93 4.29E-01 1.87E-05 1.17E 00 8.94E-02 36 ZR-95 6.50E 01 1.23E-07 1.16E-01 7.35E-01 37 NB-95m 3.75E 00 2.14E-06 1.81 E-01 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-01 39 M0-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 40 TC-99m 2.50E-01 3.21E-05 1.56E-02 1.26E-01
Proc No ODCM Attachment 2 Revision 26 Page 2 of2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA1 GAMMA1
~ (1/s) (MEV/DIS) (MEV/DIS) 41 TC-99 7.74E 07 1.04E-13 8.46E-02 0.0 42 TC-104 1.25E-02 6.42E-04 1.60E 00 1 ,95E 00 43 RU-106 3.67E 02 2.19E-08 1.01 E-02 0.0 44 TE-132 3.24E 00 2.48E-06 1.00E-01 2.33E-01 45 1-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02 46 1-131 8.05E 00 9.96E-07 1.94E-01 3.81 E-01 47 1-132 9.58E-02 8.37E-05 4.89E-01 2.24E 00 48 1-133 8.75E-01 9.17E-06 4.08E-01 6.02E-01 49 1-134 3.61E-02 2.22E-04 6.16E-01 2.59E 00 50 1-135 2.79E-01 2.87E-05 3.68E-01 1.55E 00 51 XE-131m 1.18E 01 6.80E-07 1.43E-01 2.01E-02 52 XE-133m 2.26E 00 3.55E-06 1.90E-01 4.15E-02 53 XE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02 54 XE-135m 1.08E-02 7.43E-04 9.58E-02 4.32E-01 55 XE-135 3.83E-01 2.09E-05 3.17E-01 2.47E-01 56 XE-137 2.71E 03 2.96E-03 1.77E 00 1.88E-01 57 XE-138 9.84E-03 8.15E-04 6.65E-01 1.10E 00 58 CS-134 7.48E 02 1.07E-08 1.63E-01 1.55E 00 59 CS-135 1.10E 09 7.29E-15 5.63E-02 0.0 60 CS-136 1.30E 01 6.17E-07 1.37E-01 2.15E 00 61 CS-137 1.10E 04 7.29E-10 1.71E-01 5.97E-01 62 CS-138 2.24E-02 3.58E-04 1.20E 00 2.30E 00 63 BA-139 5.76E-02 1.39E-04 8.96E-01 3.53E-02 64 BA-140 1.28E 01 6.27E-07 3.15E-01 1.71 E-01 65 LA-140 1.68E 00 4.77E-06 5.33E-01 2.31E00 66 CE-144 2.84E 02 2.82E-08 9.13E-02 1.93E-02 67 PR-143 1.36E 01 5.90E-07 3.14E-01 0.0 68 PR-144 1.20E-02 6.68E-04 1.21E 00 3.18E 00 Average energy per disintegration values were obtained from ICRP Publication No 38, Radionuclide Transformations: Energy and Intensity of Emissions 1983 and NUREG/CR-1413 (ORNUNUREG-70), a Radionuclide Decay Data Base - Index and Summary Table, DC Kocher, May 1980.
Proc No ODCM Attachment 3 Revision 26 Page 1of1 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES* Gamma body Gamma air Beta skin Beta air dose 1 dose2 dose 1 dose2 Kr-85m 1.17E3 1.23E3 1.46E3 1.97E3 Kr-85 1.61 E1 1.72E1 1.34E3 1.95E3 Kr-87 5.92E3 6.17E3 9.73E3 1.03E4 Kr-88 1.47E4 1.52E4 2.37E3 2.93E3 Kr-89 1.66E4 1.73E4 1.01 E4 1.06E4 Xe-131 m 9.15E1 1.56E2 4.76E2 1.11 E3 Xe-133m 2.51E2 3.27E2 9.94E2 1.48E3 Xe-133 2.94E2 3.53E2 3.06E2 1.05E3 Xe-135m 3.12E3 3.36E3 7.11E2 7.39E3 Xe-135 1.81 E3 1.92E3 1.86E3 2.46E3 Xe-137 1.42E3 1.51 E3 1.22E4 1.27E4 Xe-138 8.83E3 9.21E3 4.13E3 4.75E3 Ar-41 8.84E3 9.30E3 2.69E3 3.28E3
- 1. mrem/y per µCi/m 3
- 2. mrad/y per µCi/m 3
- Dose factors for exposure to a semi-infinite cloud of noble gases. Values were obtained from USN RC Regulatory Guide 1.109, Revision 1 (October 1977).
Proc No ODCM Attachment 4 Revision 26 Page 1of1 STABLE ELEMENT TRANSFER DATA Fm - MILK (COW) Fm - MILK (GOAT) Ft- MEAT Biv ELEMENT (DAYS/L) (DAYS/L) (DAYS/KG) (VEG/SOIL) H 1.0E-02 1.?E-01 1.2E-02 4.8E-OO c 1.2E-02 1.0E-01 3.1 E-02 5.5E-OO Na 4.0E-02 4.0E-02 3.0E-02 5.2E-02 p 2.5E-02 2.5E-01 4.6E-02 1.1 E-00 Cr 2.2E-03 2.2E-03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.0E-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.0E-02 6.6E-04 Co 1.0E-03 1.0E-03 1.3E-02 9.4E-03 Ni 6.?E-03 6.?E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E-02 8.0E-03 1.2E-01 Zn 3.9E-02 3.9E-02 3.0E-02 4.0E-01 Rb 3.0E-02 3.0E-02 3.1 E-02 1.3E-01 Sr 8.0E-04 1.4E-02 6.0E-04 1.?E-02 y 1.0E-05 1.0E-05 4.6E-03 2.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 1.?E-04 Nb 2.5E-03 2.5E-03 2.8E-01 9.4E-03 Mo 7.5E-03 7.5E-03 8.0E-03 1.2E-01 Tc 2.5E-02 2.5E-02 4.0E-01 2.5E-01 Ru 1.0E-06 1.0E-06 4.0E-01 5.0E-02 Rh 1.0E-02 1.0E-02 1.5E-03 1.3E+01 Ag 5.0E-02 5.0E-02 1.?E-02 1.5E-01 Te 1.0E-03 1.0E-03 7.?E-02 1.3E-OO I 6.0E-03 6.0E-02 2.9E-03 2.0E-02 Cs 1.2E-02 3.0E-01 4.0E-03 1.0E-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0E-06 5.0E-06 2.0E-04 2.5E-03 Ce 1.0E-04 1.0E-04 1.2E-03 2.5E-03 Pr 5.0E-06 5.0E-06 4.?E-03 2.5E-03 Nd 5.0E-06 5.0E-06 3.3E-03 2.4E-03 w 5.0E-04 5.0E-04 1.3E-03 1.8E-02 Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03
Proc NoODCM Attachment 5 Revision 26 Page 1 of 16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 BE10 9.49E-04 1.25E-04 2.65E-05 0. 0. 1.49E-03 1.73E-05 C14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 N13 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 F18 3.92E-06 0. 3.33E-07 0. 0. 0. 6.10E-07 NA22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 NA24 7.54E-06 7.54E-06 7.54E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 P32 1.4SE-03 8.03E-OS S.S3E-OS 0. 0. 0. 1.1SE-OS AR39 0. 0. 0. 0. 0. 1.00E-08 0. AR41 0. 0. 0. 0. 0. 3.14E-08 0. CA41 7.48E-OS 0. 8.16E-06. 0. 0. 6.94E-02 2.96E-07 SC46 3.?SE-04 5.41E*04 1.69E-04 0. 3.S6E-04 0. 2.19E-OS CRS1 0. 0. 6.39E-08 4.11E-08 9.4SE-09 9.176-06 2.SSE-07 MNS4 0. 1.81 E-OS 3.S6E-06 0. 3.S6E-06 7.14E-04 S.04E-06 MNS6 0. 1.10E-09 1.S8E-10 0. 7.86E-10 8.9SE-06 S.12E-OS FESS 1.41E-OS 8.39E-06 2.38E-06 0. 0. 6.21E-05 7.82E-07 FES9 9.69E-06 1.68E-OS 6.77E-06 0. 0. 7.2SE-04 1.77E-05 COS? 0. 4.6SE-07 4.S8E-07 0. 0. 2.71E-04 3.47E-06 C058 0. 8.71E-07 1.306-06 0. 0. S.SSE-04 7.95E-06 C060 0. S.73E-06 8.41 E-06 0. 0. 3.22E-03 2.28E-OS Nl59 1.81 E-OS 5.44E-06 3.10E-06 0. 0. S.48E-OS 6.34E-07 Nl63 2.42E-04 1.466-05 8.29E-06 0. 0. 1.49E-04 1.73E-06 Nl6S 1.71E-09 2.03E-10 8.79E-11 0. 0. S.80E-06 3.58E-OS CU64 0. 1.34E-09 5.53E-10 0. 2.84E-09 6.64E-06 1.07E-OS ZN65 1.38E-OS 4.47E-OS 2.22E-OS 0. 2.32E-OS 4.62E-04 3.67E-05 ZN69M 8.98E-09 1.84E-08 1.67E-09 0. 7.4SE-09 1.91 E-OS 2.92E-OS ZN69 3.85E-11 6.91E-11 S.13E-12 0. 2.87E-11 1.05E-06 9.44E-06 SE79 0. 2.2SE-06 4.20E-07 0. 2.47E-06 2.99E-04 3.46E-06 BR82 0. 0. 9.49E-06 0. 0. 0. 0. BR83 0. 0. 2.72E-07 0. 0. 0. 0. BR84 0. 0. 2.86E-07 0. 0. 0. 0. BR8S 0. 0. 1.46E-08 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 2.SOE-09 0. KR8SM 0. 0. 0. 0. 0. 1.31E-oa 0. KR8S 0. 0. 0. 0. 0. 1.16E-08 0. KR87 0. 0. 0. 0. 0. 6.S9E-08 0. KR88 0. 0. 0. 0. 0. 1.38E-07 0. KR89 0. 0. 0. 0. 0. 8.67E-08 0. RB86 0. 1.36E-04 6.30E-OS 0. 0. 0. 2.17E-06 RB87 0. 7.11 E-OS 2.64E-0S 0. 0. 0. 2.99E-07 RB88 0. 3.98E-07 2.0SE-07 0. 0. 0. 2.42E-07 RB89 0. 2.29E-07 1.47E-07 0. 0. 0. 4.87E-08 SR89 2.84E-04 0. 8.1SE-06 0. 0. 1.4SE-03 4.S7E-OS SR90 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-OS SR91 6.83E-08 0. 2.47E-09 0. 0. 3.76E-OS S.24E-OS SR92 7.50E-09 0. 2.79E-10 0. 0. 1.70E-OS 1.00E-04
- Includes a SO% increase to account for percutaneous transpiration.
Proc NoODCM Attachment 5 Revision 26 Page 2of16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92E-04 7.43E-05 Y91M 2.91E-10 0. 9.90E-12 0. 0. 1.99E-06 1.68E-06 Y91 4.20E-04 0. 1.12E-05 0. 0. 1.75E-03 5.02E-05 Y92 1.17E-08 0. 3.29E-10 0. 0. 1.75E-05 9.04E-05 Y93 1.07E-07 0. 2.91E-09 0. 0. 5.46E-05 1.19E-04 ZR93 2.24E-04 9.51E-05 6.18E-05 0. 3.19E-04 1.37E-03 1.48E-05 ZR95 8.24E-05 1.99E-05 1.45E-05 0. 2.22E-05 1.25E-03 1.55E-05 ZR97 1.07E-07 1.83E-08 8.36E-09 0. 1.85E-08 7.88E-05 1.00E-04 N893M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06 N895 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06 N897 2.44E-10 5.21 E-11 1.BBE-11 0. 4.07E-11 2.37E-06 1.92E-05 M093 0. 6.46E-06 2.22E-07 0. 1.54E-06 3.40E-04 3.76E-06 M099 0. 1.18E-07 2.31E-08 0. 1.89E-07 9.63E-05 3.48E-05 TC99M 9.98E-13 2.06E-12 2.66E-11 0. 2.22E-11 5.79E-07 1.45E-06 TC99 2.09E-07 2.68E-07 8.85E-08 0. 2.49E-06 6.77E-04 7.82E-06 TC101 4.65E-14 5.BBE-14 5.BOE-13 0. 6.99E-13 4.17E-07 6.03E-07 RU103 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15E-05 RU105 8.74E-10 0. 2.93E-10 0. 6.42E-10 1.12E-05 3.46E-05 RU106 6.20E-05 0. 7.77E-06 0. 7.61E-05 8.26E-03 1.17E-04 RH105 8.26E-09 5.41 E-09 3.63E-09 0. 1.50E-08 2.0BE-05 1.37E-05 PD107 0. 4.92E~07 4.11E-08 0. 2.75E-06 6.34E-05 7.33E-07 PD109 0. 3.92E-09 1.05E-09 0. 1.28E-08 1.68E-05 2.85E-05 AG110M 7.13E-06 5.16E-06 3.57E-06 0. 7.BOE-06 2.62E-03 2.36E-05 AG111 3.75E-07 1.45E-07 7.75E-08 0. 3.05E-07 2.06E-04 3.02E-05 CD113M 0. 6.67E-04 2.64E-05 0. 5.BOE-04 1.40E-03 1.65E-05 CD115M 0. 1.73E-04 6.19E-06 0. 9.41E-05 1.47E-03 5.02E-05 8N123 2.09E-04 4.21E-06 7.28E-06 4.27E-06 0. 2.22E-03 4.0BE-05 8N125 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0. 6.43E-04 7.26E-05 8N126 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 1.65E-05 88124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0. 1.89E-03 4.22E-05 88125
- 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0. 1.17E-03 1.05E-05 88126 3.0BE-06 6.01E-08 1.11E-06 2.35E-08 0. 6.BBE-04 5.33E-05 88127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. 1.54E-04 3.78E-05 TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0. 3.19E-04 9.22E-06 TE127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129M 1.01 E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.BBE-05 TE131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 TE133M 6.13E-11 3.59E-11 2.74E-11 5.52E-11 1.72E-10 3.92E-06 1.59E-05 TE134 3.18E-11 2.04E-11 1.68E-11 2.91E-11 9.59E-11 2.93E-06 2.53E-06 1129 2.16E-05 1.59E-05 1.16E-05 1.04E-02 1.BBE-05 0. 2.12E-07 1130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0. 1.42E-06 1131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E~05 0. 7.56E-07
Proc No ODCM Attachment 5 Revision 26 Page 3of16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.21 E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0. 1.36E-06 1133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0. 1.54E-06 1134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0. 9.21E-07 1135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0. 1.31 E-06 XE131M 0. 0. 0. 0. 0. 6.77E-09 0. XE133M 0. 0. 0. 0. 0. 8.89E-09 0. XE133 0. 0. 0. 0. 0. 7.41 E-09 0. XE135M 0. 0. 0. 0. 0. 8.05E-09 0. XE135 0. 0. 0. 0. 0. 1.80E-08 0. XE137 0. 0. 0. 0. 0. 8.30E-08 0. XE138 0. 0. 0. 0. 0. 9.78E-08 0. CS134M 1.32E-07 2.10E-07 1.11E-07 0. 8.50E-08 2.00E-08 1.16E-07 CSt34 2.83E-04 5.02E-04 5.32E-05 0. 1.36E-04 5.69E-05 9.53E-07 CS135 1.00E-04 8.66E-05 4.73E-06 0. 2.58E-05 1.01 E-05 2.18E-07 CS136 3.45E-05 9.61E-05 3.78E-05 0. 4.03E-05 8.40E-06 1.02E-06 CS137 3.92E-04 4.37E-04 3.25E-05 0. 1.23E-04 5.09E-05 9.53E-07 CS138 3.61E-07 5.58E-07 2.84E-07 0. 2.93E-07 4.67E-08 6.26E-07 CS139 2.32E-07 3.03E-07 1.22E-07 0. 1.65E-07 2.53E-08 1.33E-08 BA139 1.06E-09 7.03E-13 3.07E-11 0. 4.23E-13 4.25E-06 3.64E-05 BA140 4.00E-05 4.00E-08 2.07E-06 0. 9.59E-09 1.141:-03 2.74E-05 BA141 1.12E-10 7.70E-14 3.55E-12 0. 4.64E-14 2.12E-06 3.39E-06 BA142 2.84E-11 2.36E-14 1.40E-12 0. 1.36E-14 1.11 E~o6 4.95E-07 LA140 3.61E-07 1.43E-07 3.68E-08 0. 0. 1.20E-04 6.06E-05 LA141 4.85E-09 1.40E-09 2.45E-10 0. 0. 1.22E-05 5.96E-05 LA142 7.36E-10 2.69E-10 6.46E-11 0. 0. 5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 0. 3.75E-06 3.69E-04 1.54E-05 CE143 2.09E-07 1.38E-07 1.58E-08 0. 4.03E-08 8.30E-05 3.55E-05 CE144 2.28E-03 8.65E-04 1.26E-04 0. 3.84E-04 7.03E-03 1.06E-04 PR143 1.00E-05 3.74E-06 4.99E-07 0. 1.41 E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 0. 4.80E-12 1.15E-06 3.06E-06 ND147 5.67E-06 5.81E-06 3.57E-07 0. 2.25E-06 2.30E-04 2.23E-05 PM147 3.91E-04 3.07E-05 1.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 PM148M 5.0QE-05 1.24E-05 9.94E-06 0. 1.45E-05 1.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 0. 5.76E-07 3.20E-04 6.04E-05 PM149 3.10E-07 4.08E-08 1.78E-08 0. 4.96E-08 6.50E-05 3.01E-05 PM151 7.52E-08 1.10E-08 5.55E-09 0. 1.30E-08 3.25E-05 2.58E-05 SM151 3.38E-04 6.45E-05 1.63E-05 0. 5.24E-05 2.98E-04 3.46E-06 SM153 1.53E-07 1.18E-07 9.06E-09 0. 2.47E-08 3.70E-05 1.93E-05 EU152 7.83E-04 1.77E-04 1.72E-04 0. 5.94E-04 1.48E-03 9.88E-06 EU154 2.96E-03 3.46E-04 2.45E-04 0. 1.14E-03 3.05E-03 2.84E-05 EU155 5.97E-04 5.72E-05 3.46E-05 0. 1.58E-04 5.20E-04 5.19E-05 EU156 1.56E-05 9.59E-06 1.54E-06 0. 4.48E-06 6.12E-04 4.14E-05 TB160 1.12E-04 0. 1.40E-05 0. 3.20E-05 1.11 E-03 2.14E-05 H0166M 1.45E-03 3.07E-04 2.51E-04 0. 4.22E-04 2.05E-03 1.65E-05 W181 4.86E-08 1.46E-08 1.67E-09 0. 0. 1.33E-05 2.63E-07 W185 1.57E-06 4.83E-07 5.58E-08 0. 0. 4.48E-04 1.12E-05 W187 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05
Proc No ODCM Attachment 5 Revision 26 Page4of16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1.76E-01 3.79E-05 81210 0. 1.33E-05 1.18E-06 0. 1.03E-04 9.96E-03 3.27E-05 P0210 2.98E-03 5.63E-03 7.12E-04 0. 1.30E-02 2.40E-01 4.36E-05 RN222 0. 0. 0. 0. 0. 9.88E-06 0. RA223 1.56E-03 2.26E-06 3.12E-04 0. 4.16E-05 2.25E-01 3.04E-04 RA224 1.77E-04 4.00E-07 3.54E-05 0. 7.30E-06 7.91E-02 3.42E-04 RA225 2.57E-03 2.88E-06
- 5.13E-04 0. 5.31E-05 2.57E-01 2.87E-04 RA226 2.48E-01 1.46E-05 2.05E-01 0. 2.94E-04 7.83E-01 3.05E-04 RA228 1.60E-01 7.61E-06 1.80E-01 0. 1.53E-04 1.09E-OO 5.19E-05 AC225 3.69E-03 4.72E-03 2.48E.04 0. 3.49E-04 1.96E-01 2.71E-04 AC227 5.29E+OO 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+OO 5.27E-05 TH227 1.82E-03 3.03E-05 5.24E-05 0. 1.13E-04 3.27E*01 3.53E-04 TH228 8.46E-01 1.10E-02 2.86E-02 0. 5.61E-02 4.65E+OO 3.62E-04 TH229 1.34E+01 1.82E-01 6.62E-01 0. 8.99E-01 1.22E+01 3.29E-04 TH230 3.46E+OO 1.79E-01 9.65E-02 0. 8.82E-01 2.18E+OO 3.87E-05 TH232 3.86E+OO 1.53E-01 2.29E-01 0. 7.54E-01 2.09E+OO 3.29E-05 TH234 1.33E-05 7.17E-07 3.84E-07 0. 2.70E-06 .1.62E-03 7.40E-05 PA231 9.10E+OO 3.00E-01 3.62E-01 0. 1.62E+OO 3.85E-01 4.61E-05 PA233 6.84E-06 1.32E-06 1.19E-06 0. 3.68E-06 2.19E-04 9.04E-06 U232 2.57E-01 0. 2.13E-02 0. 2.40E-02 1.49E+OO 4.36E-05 U233 5.44E-02 0. 3.83E-03 0. 1.09E-02 3.56E-01 4.03EM05 U234 5.22E-02 0. 3.75E-03 0. 1.07E-02 3.49E-01 3.95E-05 U235 5.01E-02 0. 3.52EM03 0. 1.01E-02 . 3.28E-01 5.02E-05 U236 5.01E-02 0. 3.60E-03 0. 1.03E-02 3.35E-01 3.71E-05 U237 3.25E-07 0. 8.65E-08 0. 8.08E-07 9.13E-05 1.31 E-05 U238 4.79E-02 0. 3.29E-03 0. 9.40E-03 3.06E-01 3.54E-05 NP237 3.03E+OO 2.32E-01 1.26E-01 0: 7.69E-01 3.49E-01 5.10E-05 NP238 2.67E-06 6.73E-08 4.16E-08 0. 1.47E-07 9.19E-05 2.58E-05 NP239 2.65E-07 2.37E-08 1.34E-08 0. 4.73E-08 4.25E-05 1.78E-05 PU238 5.02E+OO 6.33E-01 1.27E-01 0. 4.64E-01 9.03E-01 4.69E-05 PU239 5.50E+OO 6.72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05 PU240 6.49E+OO 6.71E-01 1.34E-01 0. 4.94E-01 8.47E-01 4.36E-05 PU241 1.55E-01 6.69E-03 3.11E-03 0. 1.15E-02 7.62E-04 8.97EM07 PU242 5.09E+OO 6.47E-01 1.29E-01 0. 4.77E-01 8.15E-01 4.20E-05 PU244 5.95E+OO 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05 AM241 1.84E+OO 8.44E-01 1.31E-01 0. 7.94E-01 4.06E-01 4.78E-05 AM242M 1.90E+OO 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.01E-05 AM243 1.82E+OO 8.10E-01 1.27E-01 0. 7.72E-01 3.85E-01 5.60E-05 CM242 8.58E-02 7.44E-02 5.70E-03 0. 1.69E-02 2.97E-01 5.10E-05 CM243 1.73E+OO 7.94E-01 1.06E-01 0. 3.91 E-01 4.24E-01 5.02E-05 CM244 1.43E+00 7.04E-01 8.89E-02 0. 3.21 E-01 4.08E-01 4.86E-05 CM245 2.26E+OO 8.80E-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05 CM246 2.24E+OO 8.79E-01 1.36E-01 0. 5.23E-01 3.99E-01 4.45E-05 CM247 2.18E+OO 8.64E-01 1.33E-01 0. 5.15E-01 3.92E-01 5.85E-05 CM248 1.82E+01 7.12E+OO 1.10E+OO 0. 4.24E+OO 3.23E+OO 9.43E-04 CF292 4.26E+OO 0. 1.01E-01 0. 0. 1.37E+OO 1.85E-04
Proc No ODCM Attachment 5 Revision 26 Page 5of16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 BE10 8.43E-04 9.83E-OS 2.12E~os 0. 0. 7.41E-04 1.72E-OS C14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 N13 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 F18 1.88E-06 0. 1.~SE-07 0. 0. 0. 3.37E-07 NA22 4.41E-OS 4.41 E-OS 4.41E-OS 4.41E-OS 4.41E-OS 4.41 E-OS 4.41E-OS NA24 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 P32 7.04E-04 3.09E-OS 2.67E-OS 0. 0. 0. 1.14E-OS AR39 0. 0. 0. 0. 0. 4.89E-09 0. AR41 0. 0. 0. 0. 0. 1.68E-08 0. CA41 7.06E-OS 0. 7.70E-06 0. 0. 7.21E-02 2.94E-07 SC46 1.97E-04 2.70E-04 1.04E-04 0. 2.39E-04 0. 2.4SE-OS CRS1 0. 0 .. 4.17E-08 2.31E-08 6.S7E-09 4.S9E-06 2.93E-07 MNS4 0. 1.16E-OS 2.S7E-06 0. 2.71E-06 4.26E-04 6.19E-06 MNS6 0. 4.48E-10 8.43E-11 0. 4.S2E-10 3.SSE-06 3.33E-OS FESS 1.28E-OS 6.BOE-06 2.10E-06 0. 0. 3.00E-OS 7.7SE-07 FES9 S.S9E-06 9.04E-06 4.S1E-06 0. 0. 3.43E-04 1.91 E-OS COS? 0. 2.44E-07 2.88E-07 0. 0. 1.37E-04 3.SBE-06 COSS 0. 4.79E-07 8.SSE-07 0. 0. 2.99E-04 9.29E-06 C060 0. 3.SSE-06 6.12E-06 b. 0. 1.91 E-03 2.60E-OS NIS9 1.66E-OS 4.67E-06 2.83E-06 0. 0. 2.73E-OS 6.29E-07 Nl63 2.22E-04 1.2SE-OS 7.S6E-06 0. 0. 7.43E-OS 1.71E-06 Nl6S 8.0BE-10 7.99E-11 4.44E-11 0. 0. 2.21E-06 2.27E-OS CU64 0. S.39E-10 2.90E-10 0. 1.63E-09 2.S9E-06 9.92E-06 ZN65 1.1SE-OS 3.06E-OS 1.90E-OS 0. 1.93E-OS 2.69E-04 4.41E-06 ZN69M 4.26E-09 7.28E-09 8.S9E-10 0. 4.22E-09 7.36E-06 2.71E-OS ZN69 1.81E-11 2.61E-11 2.41E-12 0. 1.SBE-11 3.84E-07 2.7SE-06
- SE79 0. 1.23E-06 2.60E-07 0. 1.71E-06 1.49E-04 3.43E-06 BR82 0. 0. S.66E-06 0. 0. 0. 0.
BR83 0. 0. 1.28E-07 0. 0. 0. 0. BR84 0. 0. 1.48E-07 0. 0. 0. 0. BR8S 0. 0. 6.84E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 1.22E-09 0. KR8SM o .. 0. 0. 0. 0. 6.SBE-09 0. KR8S 0. 0. 0. 0. 0. S.66E-09 0. KR87 0. 0. 0. 0. 0. 3.38E-08 0. KR88 0. 0. 0. 0. 0. 6.99E-08 0. KR89 0. 0. 0. 0. 0. 4.SSE-08 0. RB86 0. S.36E-OS 3.09E-OS 0. 0. 0. 2.16E-06 RB87 0. 3.16E-OS 1.37E-OS 0. 0. 0. 2.96E-07 RB88 0. 1.o2E-07 9.90E-08 0. 0. 0. 4.66E-09 RB89 0. 9.33E-08 7.83E-08 0. 0. 0. S.11E-10 SR89 1.62E-04 0. 4.66E-06 0. 0. S.83E-04 4.S2E-OS SR90 2.73E-02 0. 1.74E-03 0. o, 3.99E-03 9.28E-OS SR91 3.28E-08 0. 1.24E-09 0. 0. 1.44E-OS 4.70E-OS SR92 3.S4E-09 0. 1.42E-10 0. 0. 6.49E-06 6.SSE-OS
*Includes a SO% increase to account for percutaneous transpiration.
Proc No ODCM Attachment 5 Revision 26 Page 6of16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 1.11 E-06 0. 2.99E-08 0. 0. 7.07E-05 7.24E-05 Y91M 1.37E-10 0. 4.98E-12 0. 0. 7.606-07 4.64E-07 Y91 2.47E-04 0. 6.59E-06 o. 0. 7.10E-04 4.97E-05 Y92 5.50E-09 0. 1.57E-10 0. 0. 6.46E-06 6.46E-05 Y93 5.04E-08 0. 1.38E-09 0. 0. 2.01E-05 1.05E-04 ZR93 2.07E-04 7.80E-05 5.55E-05 0. 3.00E-04 7.10E-04 1.47E-05 ZR95 5.13E-05 1.13E-05 1.00E-05 0. 1.61E-05 6.03E-04 1.65E-05 ZR97 5.07E-08 7.34E-09 4.32E-09 0. 1.05E-08 3.06E-05 9.49E-05 NB93M 1.27E-04 3.17E-05 1.04E-05 0. 3.44E-05 1.04E-04 2.45E-06 NB95 6.35E-06 2.48E-06 1.77E-06 0. 2.33E-06 1.66E-04 1.00E-05 NB97 1.16E-10 2.08E-11 9.74E-12 0. 2.31 E-11 9.23E-07 7.52E-06 M093 0. 3.76E-06 1.35E-07 0. 1.06E-06 1.70E-04 3.78E-06 M099 0. 4.66E-08 1.15E-08 0. 1.06E-07 3.66E-05 3.42E-05 TC99M 4.81E-13 9.41E-13 1.56E-11 0. 1.37E-11 2.57E-07 1.30E-06 TC99 1.34E-07 1.49E-07 5.35E-08 0. 1.75E-06 3.37E-04 7.75E-06 TC101 2.19E-14 2.30E-14 2.91E-13 0. 3.92E-13 1.58E-07 4.41E-09 RU103 7.55E-07 0. 2.90E-07 0. 1.90E-06 1.79E-04 1.21 E-05 RU105 4.13E-10 0. 1.50E-10 0. 3.63E-10 4.30E-06 2.69E-05 RU106 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 1.16E-04 RH105 3.91E-09 2.10E-09 1.79E-09 0. 8.39E-09 7.82E-06 1.33E-05 PD107 0. 2.65E-07 2.51E-08 0. 1.97E-06 3.16E-05 7.26E-07 PD109 0. 1.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05 AG110M 4.56E-06 3.08E-06 2.47E-06 0. 5.74E-06 1.48E-03 2.71E-05 AG111 1.81 E-07 5.68E-08 3.75E-08 0. 1.71 E-07 7.73E-05 2.98E-05 CD113M 0. 4.93E-04 2.12E-05 0. 5.13E-04 6.94E-04 1.63E-05 CD115M 0. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05 SN123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 0. 9.59E-04 4.05E-05 SN125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05 SN126 6.23E-04 1.04E-05 2.36E-05 2.84E-06 0. 3.02E-03 1.63E-05 SB124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0. 8.76E-04 4.43E-05 SB125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0. 6.27E-04 1.09E-05 SB126 1.72E-06 2.62E-08 6.16E-07 1.00E-08 0. 2.86E-04 5.67E-05 SB127 1.36E-07 2.09E-09 4.70E-08 1.51 E-09 0. 6.17E-05 3.826-05 TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 TE127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71E-06 1.52E-05 TE129M 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 TE133M 2.93E-11 1.51E-11 1.50E-11 2.32E-11 1.01E-10 1.60E-06 4.77E-06 TE134 1.53E-11 8.81E-12 9.40E-12 1.24E-11 5.71 E-11 1.23E-06 4.87E-07 1129 1.05E-05 6.40E-06 5.71E-06 4.28E-03 1.08E-05 0. 2.15E-07 1130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0. 1.38E-06 1131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07
Proc No ODCM Attachment 5 Revision 26 Page 7of16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-07 1133 4.48E-06 5.49E-06 2.0BE-06 1.04E-03 9.13E-06 0. 1.48E-06 1134 3.17E-07 5.84E~07 2.69E-07 1.37E-05 8.92E-07 0. 2.58E-07 1135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0. 1.20E-06 XE131M 0. 0. 0. 0. 0. 3.30E-09 0. XE133M 0. 0. 0. 0. 0. 4.36E-09 0. XE133 0. 0. 0. 0. 0. 3.66E-09 0. XE135M 0. 0. 0. 0. 0. 4.48E-09 0. XE135 0. o. 0. 0. 0. 9.09E-09 0. XE137 0. 0. 0. 0: 0. 4.07E-08 0. XE138 0. 0. 0. 0. 0. 5.17E-08 0. CS134M 6.33E~oa 8.92E-08 6.12E-08 0. 4.94E-08 8.35E-09 7.92E-08 CS134 1,76E-04 2.74E-04 6.07E-05 0. 8.93E-05 3.27E-05 1.04E-06 CS135 6.23E-05 4.13E-05 4.45E-06 0. 1.53E-05 5.22E-06 2.17E-07 CS136 1.76E-05 4.62E-05 3.14E-05 0. 2.58E-05 3.93E-06 1.13E-06 CS137 2.45E-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81E-05 9.78E-07 CS138 1.71 E-07 2.27E-07 1.50E-07 0. 1.68E-07 1.84E-08 7.29E-08 CS139 1.09E-07 1.15E-07 5.80E-08 0. 9.08E-08 9.36E-09 7.23E-12 BA139 4.98E-10 2.66E-13 1.45E-11 0. 2.33E-13 1.56E-06 1.56E-05 BA140 2.00E-05 1.75E-08 1.17E-06 0. 5.71E-09 4.71E-04 2.75E-05 BA141 5.29E-11 2.95E-14 1.72E-12 0. 2.56E-14 7.89E-07 7.44E-08 BA142 1.35E-11 9.73E-15 7.54E-13 0. 7.87E-15 4.44E-07 7.41E-10 LA140 1.74E-07 6.0BE-08 2.04E-08 0. 0. 4.94E-05 6.10E-05 LA141 2.28E-09 5.31E-10 1.15E-10 0. 0. 4.48E-06 4.37E-05 LA142 3.50E-10 1.11E-10 3.49E-11 0. 0. 2.35E-06 2.05E-05 CE141 1.06E-05 5.28E-06 7.83E-07 0. 2.31E-06 1.47E-04 1.53E-05 CE143 9.89E-08 5.37E-08 7.77E-09 0. 2.26E-08 3.12E-05 3.44E-05 CE144 1.83E-03 5.72E-04 9.77E-05 o: 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.11E-07 1.17E-04 2.63E-05 PR144 1.61E-11 4.99E-12 8.10E-13 0. 2.64E-12 4.23E-07 5.32E-08 ND147 2.92E-06 2.36E-06 1.84E-07 0. 1.30E-06 8.87E-05 2.22E-Q5 PM147 3.52E-04 2.52E-05 1.36E-05 0. 4.45E-05 2.20E-04 5.70E-06 PM148M 3.31E-05 6.55E-06 6.55E-06 0. 9.74E-06 5.72E-04 3.58E-05 PM148 1.61E-06 1.94E-07 1.25E-07 0. 3.30E-07 1.24E-04 6.01E-05 PM149 1.47E-07 1.56E-08 8.45E-09 0. 2.75E-08 2.40E-05 2.92E-05 PM151 3.57E-08 4.33E-09 2.82E-09 0. 7.35E-09 1.24E-05 2.50E-05 SM151 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06 SM153 7.24E-08 4.51E-08 4.35E-09 0. 1.37E-08 1.37E~o5 1.87E-05 EU152 7.42E-04 1.37E-04 1.61 E-04 0. 5.nE-04 9.00E-04 1.14E-05 EU154 2.74E-03 2.49E-04 2.27E-04 0. 1.09E-03 1.66E-03 2.98E-05 EU155 5.60E-04 4.05E-05 3.18E-05 0. 1.51E-04 2.79E-04 5.39E-05 EU156 7.89E-06 4.23E-06 8.75E-07 0. 2.72E-06 2.54E-04 4.24E-05 TB160 7.79E-05 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05 H0166M 1.34E-03 2.81E-04 2.37E-04 0. 4.01E-04 1.13E-03 1.63E-05 W181 2.66E-08 6.52E-09 8.99E-10 0. 0. 5.71E-06 2.61E-07 W185 8.31E-07 2.08E-07 2.91E-08 0. 0. 1.86E-04 1.11 E-05 W187 4.41E-09 2.61E-09 1.17E-09 0. 0. 1.11 E-05 2.46E-05
Proc No ODCM Attachment 5 Revision 26 Page 8of16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROIO KIDNEY LUNG GI-LLI PB210 8.03E-02 1.85E-02 3.18E-03 0. 6.31E-02 8.74E-02 3.75E-05 81210 0. 5.11E-06 5.65E-07 0. 5.76E-05 3.70E-03 3.21E-05 P0210 1.70E-03 2.76E-03 4.09E-04 0. 8.85E-03 1.05E-01 4.32E-05 RN222 0. 0. 0. 0. 0. 4.82E-06 0. RA223 7.69E-04 8.89E-07 1.54E-04 0. 2.36E-05 8.48E-02 3.00E-04 RA224 8.44E-05 1.53E-07 1.69E-05 0. 4.06E*06 2.92E-02 3.34E-04 RA225 1.28E-03 1.14E-06 2.56E-04 0. 3.02E-05 9.74E-02 2.84E-04 RA226 2.34E-01 7.66E-06 1.92E-01 0. 2.03E-04 3.90E-01 3.02E-04 RA228 1.49E-01 3.94E-06 1.68E-01 0. 1.04E-04 5.37E-01 5.14E-05 AC225 1.81E-03 1.87E-03 1.21 E-04 0. 1.99E-04 7.37E-02 2.67E-04 AC227 4.96E+OO 8.05E-01 3.07E-01 0. 1.77E-01 8.04E-01 5.22E-05 TH227 9.24E-04 1.26E-05 2.67E-05 0. 6.67E-05 1.26E-01 3.49E-04 TH228 8.06E-01 1.04E-02 2.72E-02 0. 5.41E-02 3.34E+OO 3.59E-04 TH229 1.28E+01 1.76E-01 6.31 E-01 0. 8.68E-01 1.04E+01 3.27E-04 TH230 3.30E+OO 1.73E-01 9.20E-02 0. 8.52E-01 1.85E+OO 3.84E-05 TH232 3.68E+OO 1.47E-01 1.28E-01 0. 7.28E-01 1.77E+OO 3.27E-05 TH234 6.94E-06 3.07E-07 2.00E-07 0. 1.62E-06 6.31E-04 7.32E-05 PA231 8.62E+OO 2.86E-01 3.43E-01 0. 1.56E+OO 1.92E-01 4.57E-05 PA233 4.14E-06 6.48E-07 7.25E-07 0. 2.38E-06 9.77E-05 8.95E-06 U232 2.19E-01 0. 1.56E-02 0. 1.67E-02 7.42E-01 4.33E-05 U233 4.64E-02 0. 2.82E-03 0. 7.62E-03 1.77E-01 4.00E-05 U234 4.46E-02 0. 2.76E-03 0. 7.47E-03 1.74E-01 3.92E-05 U235 4.27E-02 0. 2.59E-03 0. 7.01E-03 1.63E-01 4.98E-05 U236 4.27E-02 0. 2.65E-03 0. 7.16E-03 1.67E-01 3.67E-05 U237 1.57E-07 0. 4.17E-08 0. 4.53E-07 3.40E-05 1.29E-05 U238 4.09E-02 0. 2.42E-03 0. 6.55E-03 1.53E-01 3.51E-05 NP237 2.88E+OO 2.21 E-01 1.19E-01 0. 7.41E-01 1.74E-01 5.06E-05 NP238 1.26E-06 2.56E-08 1.97E-08 0. 8.16E-08 3.39E-05 2.50E-05 NP239 1.26E-07 9.04E-09 6.35E-09 0. 2.63E-08 1.57E-05 1.73E-05 PU238 4.77E+OO 6.05E-01 1.21 E-01 0. 4.47E-01 6.0BE-01 4.65E-05 PU239 5.24E+OO 6.44E-01 1.28E-01 0. 4.78E-01 5.72E-01 4.24E-05 PU240 5.23E+OO 6.436-01 1.27E-01 0. 4.77E-01 5.71E-01 4.33E-05 PU241 1.46E-01 6.33E-03 2.93E-03 0. 1.10E-02 5.06E-04 8.90E~07 PU242 4.85E+OO 6.20E-01 1.23E-01 0. 4.60E-01 5.50E-01 4.16E-05 PU244 5.67E+OO 7.10E-01 1.41 E-01 0. 5.27E-01 6.30E-01 6.20E-05 AM241 1.74E+OO 7.85E-01 1.24E-01 0. 7.63E-01 2.02E-01 4.73E-05 AM242M 1.79E+OO 7.65E-01 1.27E-01 0. 7.71E-01 8.14E-02 5.96E-05 AM243 1.72E+OO 7.53E-01 1.20E-01 0. 7.42E-01 1.92E-01 5.55E-05 CM242 6.33E-02 4.84E-02 4.20E-03 0. 1.34E-02 1.31E-01 5.06E-05 CM243 1.61E+OO 7.33E-01 9.95E-02 0. 3.74E-01 2.10E-01 4.98E-05 CM244 1.33E+OO 6.48E-01 8.31E-02 0. 3.06E-01 2.02E-01 4.82E-05 CM245 2.14E+OO 8.16E-01 1.28E-'01 0. 5.03E-01 1.95E-01 4.49E-05 CM246 2.13E+OO 8.15E-01 1.28E-01 0. 5.03E-01 1.99E-01 4.41E-05 CM247 2.07E+OO 8.02E-01 1.26E-01 0. 4.95E-01 1.95E-01 5.BOE-05 CM248 1.72E+01 6.61E+OO 1.04E+OO 0. 4.08E+OO 1.61E+OO 9.35E-04 CF252 3.92E+OO 0. 9.33E-02 0. 0. 6.62E-01 1.84E-04
Proc NoODCM Attachment 5 Revision 26 Page 9of16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 BE10 2.78E-04 4.33E-OS 7.09E-06 0. 0. 3.84E-04 1.77E-OS C14 3.2SE-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 N13 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 F18 6.S2E-07 0. 7.10E-08 0. 0. 0. 3.89E-08 NA22 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS NA24 1.72E-06 1.72E~06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P32 2.36E-04 1.37E-OS 8.9SE-06 0. 0. 0. 1.16E-OS AR39 0. 0. 0. 0. 0. 4.00E-09 0. AR41 0. 0. 0. 0. 0. 1.44E-08 0. CA41 4.0SE-OS 0. 4.38E-06 0. 0. 1.01E-01 3.03E-07 SC46 7.24E-OS 1.41E-04 4.18E-OS 0. 1.3SE-04 0. 2.98E-OS CRS1 0. 0. 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.7SE-07 MNS4 0. 6.39E-06 1.0SE-06 0. 1.S9E-06 2.48E-04 8.3SE-06 MNS6 0. 2.12E-10 3.1SE-11 0. 2.24F-10 1.90E-06 7.18E-06 FESS 4.18E-06 2.98E-06 6.93E-07 0. 0. 1.SSE-OS 7.99E-07 FES9 1.99E-06 4.62E-06 1.79E-06 0. 0. 1.91 E-04 2.23E-OS COS7 0. 1.18E-07 1.1SE-07 0. 0. 7.33E-OS 3.93E-06 COSS 0. 2.S9E-07 3.47E-07 0. 0. 1.68E-04 1.19E-OS C060 0. 1.89E-06 2.48E-06 0. 0. 1.09E-03 3.24E-OS NIS9 S.44E-06 2.02E-06 9.24E-07 0. 0. 1.41E-OS 6.48E-07 Nl63 7.2SE-OS S.43E-06 2.47E-06 0. 0. 3.84E-05 1.77E-06 Nl6S 2.73E-10 3.66E-11 1.S9E-11 0. 0. 1.17E-06 4.S9E-06 CU64 0. 2.S4E-10 1.06E-10 0. 8.01E-10 1.39E-06 7.68E-06 ZN6S 4.82E-06 1.67E-OS 7.BOE-06 0. 1.08E-OS 1.SSE-04 S.83E-06 ZN69M 1.44E-09 3.39E-09 3.11E-10 0. 2.06E-09 3.92E-06 2.14E-OS ZN69 6.04E-12 1.1SE-11 8.07E-13 0. 7.S3E-12 1.98E-07 3.S6E-08 SE79 0. S.43E-07 8.71E-08 0. 8.13E-07 7.71E-OS 3.S3E-06 BR82 0. 0. 2.28E-06 0. 0. 0. 0. BR83 0. 0. 4.30E-08 0. 0. 0. 0. BR84 0. 0. S.41E-08 0. 0. 0. 0. BR8S 0. 0. 2.29E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 9.97E-10 0. KR8SM 0. 0. 0. 0. 0. S.46E-09 0. KR8S 0. 0. 0. 0. 0. 4.63E-09 0. KR87 0. 0. 0. 0. 0. 2.82E-08 0. KR88 0. 0. 0. 0. 0. S.81E-08 0. KR89 0. 0. 0. 0. 0. 3.BSE-08 0. RB86 0. 2.38E-OS 1.0SE-OS 0. 0. 0. 2.21E-06 RB87 0. 1.40E-OS 4.SBE-06 0. 0. 0. 3.0SE-07 RB88 0. 6.82E-08 3.40E-08 0. 0. 0. 3.6SE-1S RB89 0. 4.40E-08 2.91E-08 0. 0. 0. 4.22E-17 SR89 S.43E-OS 0. 1.S6E-06 o. 0. 3.02E-04 4.64E-OS SR90 1.3SE-02 0. 8.3SE-04 0. 0. 2.06E-03 9.S6E-OS SR91 1.10E-08 0. 4.39E-10 0. 0. . 7.S9E-06 3.24E-OS SR92 1.19E-09 0. S.OBE-11 0. 0. 3.43E-06 1.49E-OS
- Includes a SO% increase to account for percutaneous transpiration.
Proc NoODCM Attachment 5 Revision 26 Page 10of16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 3.73E-07 0. 1.00E-08 0. 0. 3.66E-05 6.99E-05 Y91M 4.63E-11 0. 1.77E-12 0. 0. 4.00E-07 3.77E-09 Y91 8.26E-05 0. 2.21E-06 0. 0. 3.67E-04 5.11E-05 Y92 1.84E-09 0. 5.36E-11 0. 0. 3.35E-06 2.06E-05 Y93 1.69E-08 0. 4.65E-10 0. 0. 1.04E-05 7.24E-05 ZR93 6.83E-05 3.38E-05 1.84E-05 0. 1.16E-04 3.67E-04 1.60E-05 ZR95 1.82E-05 5.73E-06 3.94E-06 0. 8.42E-06 3.36E-04 1.86E-05 ZR97 1.72E-08 3.40E-09 1.57E-09 0. 5.15E-09 1.62E-05 7.88E-05 N893M 4.14E-05 1.36E-05 3.41E-06 0. 1.59E-05 5.36E-05 2.52E-06 N895 2.32E-06 1.29E-06 7.08E-07 0. 1.25E-06 9.39E-05 1.21 E-05 N897 3.92E-11 9.72E-12 3.55E-12 0. 1.14E-11 4.91E-07 2.71E-07 M093 0. 1.66E-06 4.52E-08 0. 5.06E-07 8.81E-05 3.99E-06 M099 0. 2.11 E-08 4.03E-09 0. 5.14E-08 1.92E-05 3.36E-05 TC99M 1.73E-13 4.83E-13 6.24E-12 0. 7.20E-12 1.44E-07 7.66E-07 TC99 4.48E-08 6.58E-08 1.79E-08 0. 8.35E-07 1.74E-04 7.99E-06 TC101 7.40E-15 1.05E-14 1.03E-13 0. 1.90E-13 8.34E-08 1.09E-16 RU103 2.63E-07 0. 1.12E-07 0. 9.29E-07 9.79E-05 1.36E-05 RU105 1.40E-10 0. 5.42E-11 0. 1.76E-10 2.27E-06 1.13E-05 RU106 1.23E-05 0. 1.55E-06 0. 2.38E-05 2.01E-03 1.20E-04 RH105 1.32E-09 9.48E-10 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05 PD107 0. 1.17E-07 8.39E-09 0. 9.39E-07 1.63E-05 7.49E-07 PD109 0. 6.56E-10 1.66E-10 0. 3.36E"09 3.19E-06 1.96E-05 AG110M 1.73E-06 1.64E-06 9.99E-07 0. 3.13E-06 8.44E-04 3.41E-05 AG111 6.07E-08 2.52E-08 1.26E-08 0. 8.17E-08 4.00E-05 3.00E-05 CD113M 0. 2.17E-04 7.10E-06 0. 2.43E-04 3.59E-04 1.68E-05 CD115M 0. 3.48E-05 1.14E-oe 0. 2.82E-05 3.03E-04 5.10E-05 8N123 4.31E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05 8N125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05 8N126 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1.72E-03 1.68E-05 88124 5.38E-06 9.92E-OB 2.10E-06 1.22E-08 0. 4.81E-04 4.98E-05 88125 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 0. 3.42E-04 1.24E-05 88126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.01E-05 88127 4.64E-08 9.92E-10 1.75E-08 5.21 E-10 0. 3.31E-05 3.94E-05 TE125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0. 6.70E-05 9.38E-06 TE127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01 E-05 TE129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 TE133M 1.01E-11 7.33E-12 5.71E-12 8.18E-12 5.07E-11 8.71E-07 1.23E-07 TE134 5.31E-12 4.35E-12 3.64E~12 4.46E-12 2.91E-11 6.75E-07 1.37E-09 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07 1130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0. 1.14E-06 1131 4.43E-06 6.14E-06 3.306-06 1.83E-03 1.05E-05 0. 8.11 E-07
Proc NoODCM Attachment 5 Revision 26 Page 11of16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. 1.59E-07 1133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E~06 0. 1.29E-06 1134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0. 2.55E-09 1135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0. 8.69E-07 XE131M 0. 0. 0. 0. 0. 2.70E-09 0. XE133M 0. 0. 0. 0. 0. 3.59E-09 0. XE133 0. 0. 0. 0. 0. 2.99E-09 0. XE135M 0. 0. 0. 0. 0. 3.88E-09 0. XE135 0. 0. 0. 0. 0. 7.55E-09 0. XE137 0. 0. 0. 0. 0. 3.33E-08 0. XE138 0. 0. 0. 0. 0. 4.38E-08 0. CS134M 2.20E-08 4.35E-08 2.35E~08 0. 2.54E-08 4.56E-09 2.02E-08 CS134 6.28E-05 1.41E-04 6.86E~05 0. 4.69E-05 1.83E-05 1.22E-06 CS135 2.08E-05 1.82E-05 4.47E-06 0. 7.30E-06 2.70E-06 2.23E-07 CS136 6.44E-06 2.42E-05 1.71E-05 0. 1.38E-05 2.22E-06 1.36E-06 CS137 8.38E-05 1.06E-04 3.89E-05 0. 3.80E-05 1.51 E-05 1.06E-06 CS138 5.82E-08 1.07E-07 5.58E-08 0. 8.28E-08 9.84E-09 3.38E-11 CS139 3.65E-08 5.12E-08 1.97E-08 0. 4.34E-08 4.86E-09 1.66E-23 BA139 1.67E-10 1.18E-13 4.87E-12 0. 1.11E-13 8.08E-07 8.06E-07 BA140 6.84E-06 . 8.38E-09 4.4.0E-07 0. 2.85E-09 2.54E-04 2.86E-05 BA141 1.78E-11 1.32E-14 5.93E-13 0. 1.23E-14 4.11E-07 9.33E-14 BA142 4.62E-12 4.63E-15 2.84E-13 0. 3.92E-15 2.39E-07 5.99E-20 LA140 5.99E-08 2.95E-08 7.82E-09 0. 0. 2.68E-05 6.09E-05 LA141 7.63E-10 2.35E-10 3.87E-11 0. 0. 2.31E-06 1.54E-05 LA142 1.20E-10 5.31E-11 1.32E-11 0. 0. 1.27E-06 1.50E-06 CE141 3.55E-06 2.37E-06 2.71E-07 0. 1.11E-06 7.67E-05 1.58E-05 CE143 3.32E-08 2.42E-08 2.70E-09 0. 1.08E-08 1.63E-05 3.19E-05 CE144 6.11E-04 2.53E-04 3.28E-05 0. 1.51 E-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 0. 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E~13 0. 1.26E-12 2.19E-07 2.94E-14 ND147 9.83E-07 1.07E-06 6.41E-08 0. 6.28E-07 4.65E-05 2.28E-05 PM147 1.15E-04 1.10E-05 4.50E-06 0. 2.10E-05 1.14E-04 5.87E-06 PM148M 1.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4.10E-05 PM148 5.44E-07 8.88E-08 4.48E-08 0. 1.60E-07 6.52E-05 6.14E-05 PM149 4.91E-08 6.89E-09 2.84E-09 0. 1.31 E-08 1.24E-05 2.79E-05 PM151 1.20E-08 1.99E-09 1.01E-09 0. 3.57E-09 6.56E-06 2.27E-05 SM151 1.07E-:04 2.10E-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.01E-08 1.47E-09 0. 6.56E-09 7.11 E-06 1.77E-05 EU152 2.96E-04 7.19E-05 6.30E-05 0. 3.34E-04 5.01E-04 1.35E-05 EU154 9.43E-04 1.23E-04 8.60E-05 0. 5.44E-04 9.12E-04 3.34E-05 EU155 2.00E-04 1.96E-05 1.21E-05 0. 7.65E-05 1.51 E-03 5.97E-05 EU156 2.70E-06 2.03E-06 3.30E-07 0. 1.36E-06 1.37E-04 4.56E-05 TB160 3.04E-05 0. 3.79E-06 0. 1.20E-05 2.97E-04 2.60E-05 H0166M 4.40E-04 1.36E-04 9.87E-05 0. 2.00E-04 6.24E-04 1.68E-05 W181 8.90E-09 2.88E-09 3.01E-10 o, 0. 2.95E-06 2.69E-07 W185 2.78E-07 9.17E-08 9.73E-09 0. 0. 9.60E-05 1.14E-05 W187 1.50E-09 1.22E-09 4.29E-10 0. 0. 5.92E-06 2.21E-05
Proc No ODCM Attachment 5 Revision 26 Page 12of16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 3.09E-02 8.28E-03 1.0?E-03 0. 2.95E-02 4.52E-02 3.87E-05 81210 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91E-03 3.19E-05 P0210 5.68E-04 1.22E-03 1.37E-04 0. 4.21 E-03 5.41E-02 4.45E-05 RN222 0. 0. 0. 0. 0. 3.94E-06 0. RA223 2.57E-04 3.93E-07 5.14E-05 0. 1.12E-05 4.39E-02 3.04E-04 RA224 2.83E-05 6.77E-08 5.65E-06 0. 1.93E-06 1.51 E-02 3.29E-04 RA225 4.28E-04 5.04E-07 8.56E-05 0. 1.44E-05 5.04E-02 2.89E-04 RA226 1.33E-01 3.38E-06 9.87E-02 0. 9.67E-05 2.02E-01 3.11E-04 RA228 5.34E-02 1.74E-06 5.88E-02 0. 4.97E-05 2.78E-01 5.30E~05 AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.81E-02 2.?0E-04 AC227 2.49E+OO 3.69E-01 1.48E-01 0. 1.0?E-01 4.16E-01 5.38E-05 TH227 3.09E-04 5.56E-06 8.93E-06 0. 3.18E-05 6.50E-02 3.57E-04 TH228 2.60E-01 4.37E-03 8.78E-03 0. 2.45E-02 1.69E+OO 3.?0E-04 TH229 9.06E+OO 1.36E-01 4.45E-01 0. 6.67E-01 5.05E+OO 3.36E-04 TH230 2.34E+OO 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05 TH232 2.61E+OO 1.14E-01 9.21E-02 0. 5.60E-01 8.60E-01 3.36E-05 TH234 2.32E-06 1.35E-07 6.71E-08 0. 7.73E-07 3.26E-04 7.49E-05 PA231 5.32E+OO 2.00E-01 2.0?E-01 0. 1.12E+OO 9.91E-02 4.71E-05 PA233 1.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.00E-05 U232 7.31E-02 0. 5.23E-03 0. 7.94E-03 3.84E-01 4.46E-05 U233 1.55E-02 0. 9.42E-04 0. 3.63E-03 9.18E-02 4.12E-05 U234 1.48E-02 0. 9.23E-04 0. 3.55E-03 8.99E-02 4.04E-05 U235 1.42E-02 0. 8.67E-04 0. 3.34E-03 8.44E-02 5.13E-05 U236 1.42E-02 0. 8.86E-04 0. 3.41E-03 8.62E-02 3.79E-05 U237 5.25E-08 0. 1.40E-08 0. 2.16E-07 1.76E-05 1.29E-05 U238 1.36E-02 0. 8.10E-04 0. 3.12E-03 7.89E-02 3.62E-05 NP237 1.77E+OO 1.54E-01 7.21E-02 0. 5.35E-01 8.99E-02 5.22E-05 NP238 4.23E-07 1.13E-08 6.59E-09 0. 3.88E-08 1.75E-05 2.38E-05 NP239 4.23E-08 3.99E-09 2.21E-09 0. 1.25E-08 8.11 E-06 1.65E-05 PU238 2.86E+OO 4.06E-01 7.22E-02 0. 3.1 OE-01 3.12E-01 4.79E-05 PU239 3.31E+OO 4.50E-01 8.05E-02 0. 3.44E-01 2.93E-01 4.37E-05 PU240 3.31E+OO 4.49E-01 8.04E-02 0. 3.43E-01 2.93E-01 4.46E-05 PU241 6.97E-02 3.57E-03 1.40E-03 0. 6.47E-03 2.60E-04 9.17E-07 PU242 3.07E+OO 4.33E-01 7.75E-02 0. 3.31 E-01 2.82E-01 4.29E-05 PU244 3.59E+OO 4.96E-01 8.88E-02 0. 3.79E-01 3.23E-01 6.39E-05 AM241 1.06E+OO 4.0?E-01 7.10E-02 0. 5.32E-01 1.05E-01 4.88E-05 AM242M 1.07E+OO
- 3.93E-01 7.15E-02 0. 5.30E-01 4.21E-02 6.14E-05 AM243 1.06E+OO 3.92E-01 6.95E-02 0. 5.21E-01 9.91E-02 5.72E-05 CM242 2.12E-02 2.14E-02 1.41 E-03 0. 6.40E-03 6.76E-02 5.21E-05 CM243 8.45E-01 3.50E-01 5.00E-02 0. 2.34E-01 1.09E-01 5.13E-05 CM244 6.46E-01 3.03E-01 3.88E-02 0. 1.81 E-01 1.05E-01 4.96E-05 CM245 1.32E+OO 4.11E-01 7.53E-02 0. 3.52E-01 1.01E-01 4.63E-05 CM246 1.31E+OO 4.11E-01 7.52E-02 0. 3.51 E-01 1.03E-01 4.54E-05 CM247 1.28E+OO 4.04E-01 7.41 E-02 0. 3.46E-01 1.01 E-01 5.97E-05 CM248 1.06E+01 3.33E+OO 6.11E-01 0. 2.85E+OO 8.32E-01 9.63E-04 CF252 1.29E+OO 0. 3.0?E-02 0. 0. 3.43E-01 1.89E-04
Proc No ODCM Attachment 5 Revision 26 Page 13of16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 BE10 1.98E-04 3.06E-05 4.96E-06 0. 0. 2.22E-04 1.67E-05 C14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 N13 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 F18 4.71E-07 0. 5.19E-08 0. 0. 0. 9.24E-09 NA22 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 NA24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P32 1.65E-04 9.64E-06 6.26E-06 0. 0. 0. 1.08E-05 AR39 0. 0. 0. 0. 0. 2.08E-09 0. AR41 0. 0. 0. 0. 0. 8.06E-09 0. CA41 3.83E-05 0. 4.13E-06 0. 0. 3.83E-06 2.86E-07 SC46 5.51E-05 1.07E-04 3.11E-05 0. 9.99E-05 0. 3.23E-05 CR51 0. 0. 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN54 0. 4.95E-06 7.87E-07 0. 1.23E-06 1.75E-04 9.67E-06 MN56 0. 1.55E-10 2.29E-11 0. 1.63E-10 1.18E-06 2.53E-06 FE55 3.07E-06 2.12E-06 4.93E-07 0. 0. 9.01E-06 7.54E-07 FE59 1.47E-06 3.47E-06 1.32E-06 0. 0. 1.27E-04 2.35E-05 C057 0. 8.65E-08 8.39E-08 0. 0. 4.62E-05 3.93E-06 C058 0. 1.98E-07 2.59E-07 0. 0. 1.16E-04 1.33E-05 C060 0. 1.44E-06 1.85E-06 0. 0. 7.46E-04 3.56E-05 Nl59 4.06E-06 1.46E-06 6.77E-07 0. 0. 8.20E-06 6.11E-07 Nl63 5.40E-05 3.93E-06 1.81 E-06 0. 0. 2.23E-05 1.67E-06 Nl65 1.92E-10 2.62E-11 1.14E-11 0. 0. 7.00E-07 1.54E-06 CU64 0. 1.83E-10 7.69E-11 0. 5.76E-10 8.48E-07 6.12E-06 ZN65 4.05E-06 1.29E-05 5.82E-06 0. 8.62E-06 1.08E-04 6.68E-06 ZN69M 1.02E-09 2.45E-09 2.24E-10 0. 1.48E-09 2.38E-06 1.71E-05 ZN69 4.23E-12 8.14E-12 5.65E-13 0. 5.27E-12 1.15E-07 2.04E-09 SE79 0. 3.83E-07 6.09E-08 0. 5.69E-07 4.47E-05 3.336-06 BR82 0. 0. 1.69E-06 0. 0. 0. 1.30E-06 BR83 0. 0. 3.01E-08 0. 0. 0. 2.90E-08 BR84 0. 0. 3.91E-08 0. 0. 0. 2.05E-13 BR85 0. 0. 1.60E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 5.19E-10 0. KR85M 0. 0. 0. 0. 0. 2.91E-09 0. KR85 0. 0. 0. 0. 0. 2.41E-09 0. KR87 0. 0. 0. 0. 0. 1.53E-08 0. KR88 0. 0. 0. 0. 0. 3.13E-08 0. KR89 0. 0. 0. 0. 0. 2.13E-08 0. RB86 0. 1.69E-05 7.37E-06 0. 0. 0. 2.08E-06 RB87 0. 9.86E-06 3.21E-06 0. 0. 0. 2.88E-07 RB88 0. 4.84E-08 2.41E-08 0. 0. 0. 4.18E-19 RB89 0. 3.20E-08 2.12E-08 0. 0. 0. 1.16E-21 SR89 3.80E-05 0. 1.09E-06 0. 0. 1.75E-04 4.37E-05 SR90 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05 SR91 7.74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05 SR92 8.43E-10 0. 3.64E-11 0. 0. 2.06E-06 5.38E-06
- Includes a 50% increase to account for percutaneous transpiration.
Proc No ODCM Attachment 5 Revision 26 Page 14of16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 2.61E-07 0. 7.01E-09 0. 0. 2.12E-05 6.32E-05 Y91M 3.26E-11 0. 1.27E-12 0. 0. 2.40E-07 1.66E-10 Y91 5.78E-05 0. 1.55E-06 0. 0. 2.13E-04 4.81E-05 Y92 1.29E-09 0. 3.77E-11 0. 0. 1.96E-06 9.19E-06 Y93 1.18E-08 0. 3.26E-10 0. 0. 6.06E-06 5.27E-05 ZR93 5.22E-05 2.92E-06 1.37E-06 0. 1.11E-05 2.13E-05 1.51 E-06 ZR95 1.34E-05 4.30E-06 2.91E-06 0. 6.77E-06 2.21E-04 1.88E-05 ZR97 1.21 E-08 2.45E-09 1.13E-09 0. 3.71E-09 9.84E-06 6.54E-05 NB93M 3.10E-05 1.01E-05 2.49E-06 0. 1.16E-05 3.11 E-05 2.38E-06 NB95 1.76E-06 9.77E-07 5.26E-07 0. 9.67E-07 6.31E-05 1.30E-05 NB97 2.78E-11 7.03E-12 2.56E-12 0. 8.18E-12 3.00E-07 3.02E-08 M093 0. 1.17E-06 3.17E-08 0. 3.55E-07 5.11E-05 3.79E-06 M099 0. 1.51E-08 2.87E-09 0. 3.64E-08 1.14E-05 3.10E-05 TC99M 1.29E-13 3.64E-13 4.63E-12 0. 5.52E-12 9.55E-08 5.20E-07 TC99 3.13E-08 4.64E-08 1.25E-08 0. 5.85E-07 1.01 E-04 7.54E-06 TC101 5.22E-15 7.52E-15 7.38E-14 0. 1.35E-13 4.99E-08 1.36E-21 RU103 1.91 E-07 0. 8.23E-08 0. 7.29E-07 6.31E-05 1.38E-05 RU105 9.88E-11 0. 3.89E-11 0. 1.27E-10 1.37E-06 6.02E-06 RU106 8.64E-06 0. 1.09E-06 0. 1.67E-05 1.17E-03 1.14E-04 RH105 9.24E-10 6.73E-10 4.43E-10 0. 2.86E-09 2.41E-06 1.09E-05 PD107 0. 8.27E-08 5.87E-09 0. 6.57E-07 9.47E-06 7.06E-07 PD109 0. 4.63E-10 1.16E-10 0. 2.35E-09 1.85E-06 1.52E-05 AG110M 1.35E-06 1.25E-06 7.43E-07 0. 2.46E-06 5.79E-04 3.78E-05 AG111 4.25E-08 1.78E-08 8.87E-09 0. 5.74E-08 2.33E-05 2.79E-05 CD113M 0. 1.54E-04 4.97E-06 0. 1.71E-04 2.08E-04 1.59E-05 CD115M 0. 2.46E-05 7.95E-07 0. 1.98E-05 1.76E-04 4.SOE-05 SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0. 2.88E-04 3.92E-05 SN125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.81E-05 SN126 1.58E-04 4.18E-06 6.00E-06 1.23E-06 0. 1.17E-03 1.59E-05 SB124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0. 3.10E-04 5.0SE-05 SB125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0. 2.18E-04 1.26E-05 SB126 4.50E-07 9.13E-09 1.62E-07 2.75E-09 0. 9.57E-05 6.01E-05 SB127 3.30E-08 7.22E-10 1.27E-08 3.97E-10 0. 2.05E-05 3.77E-05 TE125M 4.27E-07 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 TE127M 1.58E-06 7.21E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 TE133M 7.24E-12 5.40E-12 4.17E-12 6.27E-12 3.74E-11 5.51E-07 5.49E-08 TE134 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.18E-11 4.343-07 2.97E-11 1129 2.48E-06 2.11E-06 6.91E-06 5.54E-03 4.53E-06 0. 2.22E-07 1130 5.72E-07 1.68E-06
- 6.60E-07 1.42E-04 2.61E-06 0. 9.61E-07 1131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 o. 7.85E-07
Proc No ODCM Attachment 5 Revision 26 Page 15of16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0. 5.08E-08 1133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0. 1.11E-06 1134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0. 1.26E-10 1135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0. 6.56E-07 XE131M 0. 0. 0. 0. 0. 1.40E-09 0. XE133M 0. 0. 0. 0. 0. 1.89E-09 0. XE133 0. 0. 0. 0. 0. 1.57E-09 0. XE135M 0. 0. 0. 0. 0. 2.22E-09 0. XE135 0. 0. 0. 0. 0. 4.05E-09 0. XE137 0. 0. 0. 0. 0. 1.74E-08 0. XE138 0. 0. 0. 0. 0. 2.44E-08 0. CS134M 1.59E-08 3.20E-08 1.72E-08 0. 1.83E-08 2.93E-09 7.92E-09 CS134 4.66E-05 1.06E-04 9.10E-05 0. 3.59E-05 1.22E-05 1.30E-06 CS1.35 1.46E-05 1.29E-05 5.99E-06 0. 5.11E-06 1.57E-06 2.11E-07 CS136 4.88E-06 1.83E-05 1.38E-05 0. 1.07E-05 1.50E-b6 1.46E-06 CS137 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 1.05E-06 CS138 4.14E-08 7.76E-08 4.05E-08 0. 6.00E-08 6.07E-09 2.33E-13 CS139 2.56E-08 3.63E-08 1.39E-08 0. 3.05E-08 2.84E-09 5.49E-31 BA139 1.17E-10 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07 BA140 4.88E-06 6.13E-09 3.21E-07 0. 2.09E-09 1.59E-04 2.73E-05 BA141 1.25E-11 9.41E-15 4.20E-13 0. 8.75E-15 2.42E-07 1.45E-17 BA142 3.29E-12 3.38E-15 2.07E-13 0. 2.86E-15 1.49E-07 1.96E-26 LA140 4.30E-08 2.17E-08 5.73E-09 0. 0. . 1.70E-05 5.73E-05 LA141 5.34E-10 1.66E-10 2.71E-11 0. 0. 1.35E-06 7.31E-06 LA142 8.54E-11 3.88E-11 9.65E-12 0. 0. 7.91E-07 2.64E-07 CE141 2.49E-06 1.69E-06 1.91 E-07 0. 7.83E-07 4.52E-05 1.50E-05 CE143 2.33E-08 1.72E-08 1.91 E-09 0. 7.60E-09 9.97E-06 2.83E-05 CE144 4.29E-04 1.79E-04 2.30E-05 0. 1.06E-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.80E-08 0. 2.70E-07 3.51E-05 2.50E-05 PR144 3.76E-12 1.56E-12 1.91E-13 0. 8.81E-13 1.27E-07 2.69E-18 ND147 6.59E-07 7.62E-07 4.56E-08 0. 4.45E-07 2.76E-05 2.16E-05 PM147 8.37E-05 7.87E-06 3.19E-06 0. 1.49E-05 6.60E-05 5.54E-06 PM148M 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2.14E-04 4.18E-05 PM148 3.84E-07 6.37E-08 3.20E-08 0. 1.20E-07 3.91E-05 5.80E-05 PM149 3.44E-08 4.87E-09 1.99E-09 0. 9.19E-09 7.21E-06 2.50E-05 PM151 8.50E-09 1.42E-09 7.21E-10 0. 2.55E-09 3.94E-06 2.00E-05 SM151 8.59E-05 1.48E-05 3.55E-06 0. 1.66E-05 4.45E-05 3.25E-06 SM153 1.70E-08 1.42E-08' 1.04E-09 0. 4.59E-09 4.14E-06 1.58E-05 EU152 2.38E-04 5.41 E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05 EU154 7.40E-04 9.10E-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05 EU155 1.01E-04 1.43E-05 9.21E-06 0. 6.59E-05 9.46E-05 5.95E-06 EU156 1.93E-06 1.48E-06 2.40E-07 0. 9.95E-07 8.56E-05 4.50E-05 TB160 2.21E-05 0. 2.75E-06 0. 9.10E-06 1.92E-04 2.68E-05 H0166M 3.37E-04 1.05E-04 8.00E-05 0. 1.57E-04 3.94E-04 1.59E-05 W181 6.23E-09 2.03E-09 2.17E-10 0. 0. 1.71E-06 2.53E-07 W185 1.95E-07 6.47E-08 6.81E-09 0. 0. 5.57E-05 1.07E-05 W187 1.06E-09 8.85E-10 3.10E-10 0. 0. 3.63E-06 1.94E-05
Proc No ODCM Attachment 5 Revision 26 Page 16of16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 81210 0. 1.59E-06 1.32E-07 0. 1.92E-05 1.11E-03 2.95E-05 P0210 3.97E-04 8.60E-04 9.58E-05 0. 2.95E-03 3.14E-02 4.19E-05 RN222 0. 0. 0. 0. 0. 2.05E-06 0. RA223 1.BOE-04 2.77E-07 3.60E-05 0. 7.85E-06 2.55E-02 2.84E-04 RA224 1.98E-05 4.78E-08 3.96E-06 0. 1.35E-06 8.77E-03 3.01E-04 RA225 3.00E-04 3.56E-07 5.99E-05 0. 1.01 E-05 2.92E-02 2.71E-04 RA226 1.25E-01 2.39E-06 9.14E-02 0. 6.77E-05 1.17E-01 2.94E-04 RA228 4.41E-02 1.23E-06 4.78E-02 0. 3.48E-05 1.61E-01 5.00E-05 AC225 4.23E-04 5.82E-04 2.84E-05 0. 6.63E-05 2.21E-02 2.52E-04 AC227 2.30E+OO 3.05E-01 1.36E-01 0. 9.82E-02 2.41E-01 5.08E-05 TH227 2.17E-04 3.92E~06 6.25E-06 0. 2.22E-05 3.77E-02 3.34E-04 TH226 2.00E-01 3.39E~03 6.77E-03 0. 1.89.E-02 1.01E+OO 3.49E-04 TH229 8.88E+OO 1.33E-01 4.36E-01 0. 6.52E-01 3.49E+OO 3.17E-04 TH230 2.29E+OO 1.31E-01 6.36E-02 0. 6.40E-01 6.21 E-01 3.73E-05 TH232 2.56E+OO 1.12E-01 9.04E-02 0. 5.47E-01 5.96E-01 3.17E-05 TH234 1.63E-06 9.56E-08 4.70E-08 0. 5.41E-07 1.89E-04 7.03E-05 PA231 5.08E+OO 1.91E-01 1.98E-01 0. 1.076+00 5.75E-02 4.44E-05 PA233 1.21E-06 2.42E-07 2.09E-07 0. 9.15E-07 3.52E-05 1.02E-05 U232 5.14E-02 0. 3.66E-03 0. 5.56E-03 2.22E-01 4.21E-05 U233 1.09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05 U234 1.04E-02 0. 6.46E-04 0. 2.49E-03 5.22E-02 3.81E-05 U235 1.00E-02 0. 6.07E-04 0. 2.34E-03 4.90E-02 4.84E-05 U236 1.00E-02 0. 6.20E-04 0. 2.39E-03 5.00E-02 3.57E-05 U237 3.67E-08 0. 9.77E-09 0. 1.51 E-07 1.02E-05 1.20E-05 U238 9.58E-03 0. 5.67E-04 0. 2.18E-03 4.58E-02 3.41 E-05 NP237 1.69E+OO 1.47E-01 6.87E-02 0. 5.10E-01 5.22E-02 4.92E-05 NP238 2.96E-07 8.00E-09 4.61E-09 0. 2.72E-08 1.02E-05 2.13E-05 NP239 2.87E-08 2.82E-09 1..55E-09 0. 8.75E-09 4.70E-06 1.49E-05 PU238 2.74E+OO 3.87E-01 6.90E-02 0. 2.96E-01 1.82E-01 4.52E-05 PU239 3.19E+OO 4.31E-01 7.75.E-02 0. 3.30E-01 1.72E-01 4.13E-05 PU240 3.18E+OO 4.30E-01 7.73E-02 0. 3.29E-01 1.72E-01 4.21E-05 PU241 6.41 E-02 3.28E-03 1.29E-03 0. 5.93E-03 1.52E-04 8.65E-07 PU242 2.95E+OO 4.15E-01 7.46E-02 0. 3.17E-01 1.65E-01 4.05E-05 PU244 3.45E+OO 4.76E-01 8.54E-02 0. 3.64E-01 1.89E-01 6.03E-05 AM241 1.01E+OO 3.59E-01 6.71E-02 0. 5.04E-01 6.06E-02 4.60E-05 AM242M 1.02E+OO 3.46E-01 6.73E-02 0. 5.01 E-01 2.44E-02 5.79E-05 AM243 1.01E+OO 3.47E-01 6.57E-02 0. 4.95E-01 5.75E-02 5.40E-05 CM242 1.48E-02 1.51 E-02 9.84E-04 0. 4.48E-03 3.92E-02 4.91E-05 CM243 7.86E-01 2.97E-01 4.616-02 0. 2.15E-01 6.31E-02 4.84E-05 CM244 5.90E-01 2.54E-01 3.51E-02 0. 1.64E-01 6.06E-02 4.68E-05 CM245 1'.26E+OO 3.59E-01 7.14E-02 0 .. 3.33E-01 5.85E-02 4.36E-05 CM246 1.25E+OO 3.59E-01 7.13E-02 0. 3.33E-01 5.96E-02 4.29E-05 CM247 1.22E+OO 3.53E-01 7.03E-02 0. 3.28E-01 5.85E-02 5.63E-05 CM248 1.01 E+01 2.91 E+OO 5.79E-01 0. 2.70E+OO 4.82E-01 9.096-04 CF252 9.78E-01 0. 2.33E-02 0. 0. 1.99E-01 1.78E-04
Proc No ODCM Attachment 6 Revision 26 Page 1of2 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (DFG1l (mrem/hr per pCi/m 2) ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.BOE-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 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 0.0 0.0 Ni-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 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 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.BOE-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
Proc No ODCM Attachment 6 Revision 26 Page 2 of 2 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (DFG1l (mrem/hr per pCi/m 2) ELEMENT TOTAL BODY SKIN Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-08 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 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20~-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 0.0 0.0 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
Proc NoODCM Attachment 7 Revision 26 Page 1 of 1 BIOACCUMULATION FACTORS uCi/gm per uCi/ml FRESHWATER ELEMENT FISH H 9.0E-01 c 4.6E 03 NA 1.0E 02 p 1.0E 05 CR 2.0~ 02 MN 4.0E 02 FE 1.0E 02 co 5.0E 01 NI 1.0E 02 cu 5.0E 01 ZN 2.0E 03 BR 4.2E 02 RB 2.0E 03 SR 3.0E 01 y 2.5E 01 ZR 3.3E 00 NB 3.0E 04 MO 1.0E 01 TC 1.5E 01 RU 1.0E 01 RH 1.0E 01
~TE 4.0E 02 I 1.5E 01 cs 2.0E 03 BA 4.0E 00 LA 2.5E 01 CE 1.0E 00 PR 2.5E 01 ND 2.5E 01 w 1.2E 03 NP 1.0E 01
Proc No ODCM Attachment 8 Revision 26 Page 1 of 16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07 BE10 1.71 E-OS 2.49E-06 S.16E-07 0. 1.64E-06 0. 2.78E-OS C14 2.37E-OS S.06E-06 S.06E-06 S.06E-06 S.06E-06 S.06E-06 S.06E-06 N13 S.8SE-08 S.8SE-08 S.8SE-08 S.83SE-08 S.8SE-08 S.8SE-08 S.8SE-08 F18 S.19E-06 0. 4.43E.07 0. 0. 0. 1.22E-06 NA22 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS NA24 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS P32 1.70E-03 1.00E-04 6.S9E-OS 0. 0. 0. 2.30E-OS AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 3.74E-04 0. 4.08E-OS 0. 0. 0. 1.91 E-07 SC46 3.7SE-08 S.41 E-08 1.69E-08 0. 3.S6E-08 0. 3.S3E-OS CRS1 0. 0. 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MNS4 0. 1.99E-OS 4.S1E-06 0. 4.41E-06 0. 7.31E-06 MNS6 0. 8.18E-07 1.41E-07 0. 7.03E-07 0. 7.43E-OS FESS 1.39E-OS 8.98E-06 2.40E-06 0. 0. 4.39E-06 1.14E-06 FES9 3.08E-OS S.38E-OS 2.12E-OS 0. 0. 1.S9E-OS 2.S7E-OS COS7 0. 1.1SE-06 1.87E-06 0. 0. 0. 3.92E-06 COS8 0. 3.60E-06 8.98E-06 0. 0. 0. 8.97E-06 C060 0. 1.08E-OS 2.SSE-OS 0. 0. 0. 2.S7E-OS NIS9 4.78E-OS 1.4SE-OS 8.17E-06 0. 0. 0. 7.16E-07 Nl63 6.34E-04 3.92E-OS 2.20E-OS 0. 0. 0. 1.9SE-06 Nl6S 4.70E-06 S.32E-07 2.42E-07 0. 0. 0. 4.0SE-OS CU64 0. 6.09E-07 2.82E-07 0. 1.03E-06 0. 1.2SE-OS ZN6S 1.84E-OS 6.31E-OS 2.91E-OS 0. 3.06E-OS 0. S.33E-OS ZN69M 1.SOE-06 3.06E-06 2.79E-07 0. 1.24E-06 0. 4.24E-OS ZN69 9 ..33E-08 1.68E-07 1.2SE-08 0. 6.98E-08 0. 1.37E-OS SE79 0. 2.10E-OS 3.90E-06 0. 2.43E-OS 0. S.S8E-07 BR82 0. 0. 1.27E-OS 0. 0. 0. 0. BR83 0. 0. 3.63E-07 0. 0. 0. 0. BR84 0. 0. 3.82E-07 0. 0. 0. 0. BR8S 0. 0. 1.94E-08 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 0. 0. KR8SM 0. 0. 0. 0. 0. 0. 0. KR8S 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 1.70E-04 8.40E-OS 0. 0. 0. 4.3SE-06 RB87 0. 8.88E-OS 3.S2E-OS 0. 0. 0. S.98E-07 RB88 0. 4.98E-07 2.73E-07 0. 0. 0. 4.8SE-07 R889 0. 2.86E-07 1.97E-07 0. 0. 0. 9.74E-08 SR89 2.S1E-03 0. 7.20E-OS 0. 0. 0. S.16E-OS SR90 1.8SE-02 0. 4.71E-03 0. 0. 0. 2.31E-04 SR91 S.OOE-OS 0. 1.81 E-06 0. 0. 0. S.92E-OS SR92 1.92E-OS 0. 7.13E-07 0. 0. 0. 2.07E-04
Proc NoODCM Attachment 8 Revision 26 Page 2of16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04 Y91M 8.10E-10 0. 2.76E-11 0. 0. 0. 2.70E-06 Y91 1.13E-06 0. 3.01E-08 0. 0. 0. 8.10E-05 Y92 7.65E-09 0. 2.15E-10 0. 0. 0. 1.46E-04 Y93 2.43E-08 0. 6.62E-10 0. 0. 0. 1.92E-04 ZR93 1.93E-07 9.18E-08 5.54E-08 0. 2.71E-07 0. 2.39E-05 ZR95 2.06E-07 5.02E-08 3.56E-08 0. 5.41E-08 0. 2.50E-05 ZR97 1.48E-08 2.54E-09 1.16E-09 0. 2.56E-09 0. 1.62E-04 NB93M 1.23E-07 3.33E-08 1.04E-08 0. 3.25E-08 0. 3.98E-06 NB95 4.20E-08 1.73E-08 1.00E-08 0. 1.24E-08 0. 1.46E-05 NB97 4.59E-10 9.79E-11 3.53E-11 0. 7.65E-11 0. 3.09E-05 M093 0. 5.65E-05 1.82E-06 0. 1.13E-05 0. 1.21 E-06 M099 0. 3.40E-05 6.63E-06 0. 5.08E-05 0. 1.12E-05 TC99M 1.92E-09 3.96E-09 5.10E-08 0. 4.26E-08 2.07E-09 1.15E-06 TC99 1.08E-06 1.46E-06 4.55E-07 0. 1.23E-05 1.42E-07 6.31E-06 TC101 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 0. 4.95E-07 0. 3.08E-06 0. 1.80E-05 RU105 1.36E-07 0. 4.58E-08 0. 1.00E-06 0. 5.41 E-05 RU106 2.41E-05 0. 3.01E-06 0. 2.85E-05 0. 1.83E-04 RH105 1.09E-06 7.13E-07 4.79E-07 0. 1.98E-06 0. 1.77E-05 PD107 0. 1.19E-06 8.45E-08 0. 6.79E-06 0. 9.46E-07 PD109 0. 1.50E-06 3.62E-07 0. 5.51E-06 0. 3.68E-05 AG110M 9.96E-07 7.27E-07 4.81E-07 0. 1.04E-06 0. 3.77E-05 AG111 5.20E-07 2.02E-07 1.07E-07 0. 4.22E-07 0. 4.82E~05 CD113M 0. 1.77E-05 6.52E-07 0. 1.34E-05 0. 2.66E-05 CD115M 0. 1.42E-05 4.93E-07 0. 7.41E-06 0. 8.09E~05 SN123 2.49E-04 3.89E-06 6.50E-06 3.91E-06 0. 0. 6.58E-05 SN125 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0. 0. 1.11E-04 SN126 5.53E-04 7.26E-06 1.80E-05 1.91 E-06 0. 0. 2.52E-05 SB124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0. 1.34E-05 6.60E-05 SB125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0. 7.72E-06 1.64E-05 SB126 8.06E-06 1.58E-07 2.91E-06 6.19E-08 0. 5.07E-06 8.35E-05 SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0. 1.15E-06 5.91E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0. 0. 1.11E-05 TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0. 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0. 2.10E-05 TE129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0. 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0. 2.27E-05 TE131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0. 1.03E-04 TE131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0. 7.11E-06 TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0. 3.81E-05 TE133M 3.91E-07 1.79E-07 1.71E-07 3.45E-07 1.22E-06 0. 1.93E-05 TE134 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 0. 3.06E-06 1129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51E-05 0. 4.24E-07 1130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0. 2.83E-06 1131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0. 1.51E-06
Proc NoODCM Attachment 8 Revision 26 Page 3of16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0. 2.73E.06 1133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0. 3.08E-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0. 1.84E-06 1135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0. 2.62E-06 XE131M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 0. 0. 0. 0. 0. o. 0. CS134M 1.76E-07 2.93E-07 1.48E-07 0. 1.13E-07 2.60E-08 2.32E-07 CS134 3.77E.-04 7.03E-04 7.10E-05 0. 1.81 E-04 7.42E-05 1.91 E-06 CS135 1.33E-04 1.21 E-04 6.30E-06 0. 3.44E-05 1.31 E-05 4.37E-07 CS136 4.59E-05 1.35E-04 5.04E-05 0. 5.38E-05 1.10E-05 2.05E-06 CS137 5.22E-04 6.11E-04 4.33E-05 0. 1.64E-04 6.64E-05 1.91 E-06 CS138 4.81E-07 7.82E-07 3.79E-07 0. 3.90E-07 6.09E-08 1.25E-06 CS139 3.10E-07 4.24E-07 1.62E-07 0. 2.19E-07 3.30E-08 2.66E-08 BA139 8.81E-07 5.84E-10 2.55E-08 0. 3.51E-10 3.54E-10 5.58E-05 BA140 1.71E-04 1.71E-07 8.81E-06 0. 4.06E-08 1.05E-07 4.20E-05 BA141 4.25E-07 2.91E-10 1.34E-08 0. 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.53E-10 9.06E-09 0. 8.81E-11 9.26E-11 7.59E-07 LA140 2.11 E-08 8.32E-09 2.14E-09 0. 0. 0. 9.77E-05 LA141 2.89E-09 8.38E-10 1.46E-10 0. 0. 0. 9.61E-05 LA142 1.10E-09 4.04E-10 9.67E-11 0. 0. 0. 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 0. 1.48E-08 0. 2.48E-05 CE143 1.48E-08 9.82E-06 1.12E-09 0. 2.86E-09 0. 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 0. 4.93E-07 0. 1.71 E-04 PR143 8.18E-08 3.04E-08 4.03E-09 0. 1.13E-08 0: 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 0. 3.84E-11 o, 4.93E-06 Nb147 5.53E-08 5.68E-08 3.48.E-09 0. 2.19E-08 0. 3.60E-05 PM147 3.88E-07 3.27E-08 1.59E-08 0. 4.88E-08 0. 9.27E-06 PM148M 1.65E-07 4.18E-08 3.28E-08 0. 4.80E-08 0. 5.443-05 PM148 6.32E-08 9.13E-09 4.60E-09 0. 1.09E-08 0. 9.74E-05 PM149 1.38E-08 1.81 E-09 7.90E-10 0. 2.20E-09 0. 4.86E-05 PM151 6.18E-09 9.01E-10 4.56E-10 0. 1.07E-09 0. 4.17E-05 SM151 2.90E*07 6.67E-08 1.44E-08 0. 4.53E-08 0. 5.58E-06 SM153 7.72E-09 5.97E-09 4.58E-10 0. 1.25E-09 0. 3.12E-05 EU152 6.74E-07 1.79E-07 1.51 E-07 0. 5.02E-07 0. 1.59E-05 EU154 2.64E-06 3.67E-07 2.20E-07 0. 9.95E-07 0. 4.58E-05 EU155 5.42E-07 6.25E-08 3.23E-08 0. 1.40E-07 0. 8.37E-05 EU156 1.14E-07 7.06E-08 1.12E-08 0. 3.26E-08 0. 6.67E-05 TB160 2.59E-07 0. 3.24E-08 0. 7.37E-08 0. 3.45E-05 H0166M 1.25E-06 2.69E-07 2.13E-07 0. 3.57E-07 0. 0. W181 8.85E-08 2.72E-08 3.04E-09 0. 0. 0. 3.82E-07 W185 3.62E-06 1.13E-06 1.29E-07 0. 0. 0. 1.62E-05 W187 9.03E-07 6.28E-07 2.17E-07 0. 0. 0. 3.69E-05
Proc No ODCM Attachment 8 Revision 26 Page 4of16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05 81210 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.27E-05 P0210 3.10E-03 5.93E-03 7.41E-04 0. 1.26E-02 0. 6.61E-05 RN222 0. 0. 0. 0. 0. 0. 0. RA223 4.41E-02 6.42E-05 8.82E-03 0. 1.17E-03 0. 3.43E-04 RA224 1.46E-02 3.29E-05 2.91E-03 0. 6.00E-04 0. 3.86E-04 RA225 5.78E-02 6.42E-05 1.15E-02 0. 1.19E-03 0. 3.24E-04 RA226 6.20E-01 4.76E-05 5.14E-01 0. 8.71E-04 0. 3.44E-04 RA228 4.32E-01 2.58E-05 4.86E-01 0. 4.73E-04 0. 5.86E-05 AC225 3.92E-05 5.03E-05 2.63E-06 0. 3.69E-06 0. 4.36E-04 AC227 4.49E-03 7.67E-04 2.79E-04 0. 1.56E-04 0. 8.50E-05 TH227 1.20E-04 2.01E-06 3.45E-06 0. 7.41 E-06 0. 5.70E-04 TH228 2.47E-03 3.38E-05 8.36E-05 0. 1.58E-04 0. 5.84E-04 TH229 1.48E-02 1.94E-04 7.29E-04 0. 9.29E-04 0. 5.31E-04 TH230 3.80E-03 1.90E-04 1.06E-04 0. 9.12E-04 0. 6.24E-05 TH232 4.24E-03 1.63E-04 1.65E-04 0. 7.79E-04 0. 5.31E-05 TH234 6.92E-07 3.77E-08 2.00E-08 0. 1.39E-07 0. 1.19E-04 PA231 7.57E-03 2.50E-04 3.02E-04 0. 1.34E-03 0. 7.44E-05 PA233 3.11E-08 6.09E-09 5.43E-09 0. 1.67E-08 0. 1.46E-05 U232 2.42E-02 0. 2.16E-03 0. 2.37E-03 0. 7.04E-05 U233 5.08E-03 0. 3.87E-04 0. 1.08E-03 0. 6.51E-05 U234 4.88E-03 0. 3.80E-04 0. 1.06E-03 0. 6.37E-05 U235 4.67E-03 0. 3.56E-04 0. 9.93E-04 0. 8.10E-05 U236 4.67E-03 0. 3.64E-04 0. 1.01 E-03 0. 5.98E-05 U237 4.95E-07 0. 1.32E-07 0. 1.23E-06 0. 2.11E-05 U238 4.47E-03 0. 3.33E-04 0. 9.28E-04 0. 5.71E-05 NP237 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 0. 8.23E-05 NP238 1.24E-07 3.12E-09 1.92E-09 0. 6.81E-09 0. 4.17E-05 NP239 1.11E-08 9.93E-10 5.61E-10 0. 1.98E-09 0. 2.87E-05 PU238 1.34E-03 1.69E-04 3.40E-05 0. 1.21E-04 0. 7.57E-05 PU239 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 6.91E-05 PU240 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 7.04E-05 PU241 4.38E-05 1.90E-06 8.82E-07 0. 3.17E-06 0. 1.45E-06 PU242 1.35E-03 1.70E-04 3.41E-05 0. 1.23E-04 0. 6.77E-05 PU244 1.57E-03 1.95E-04 3.91E-05 0. 1.41 E-04 0. 1.01 E-04 AM241 1.53E-03 7.18E-04 1.09E-04 0. 6.55E-04 0. 7.70E-05 AM242M 1.58E-03 7:02E-04 1.13E-04 0. 6.64E-04 0. 9.69E-05 AM243 1.51 E-03 6.88E-04 1.06E-04 0. 6.36E-04 0. 9.03E-05 CM242 1.37E-04 1.24E-04 9.10E-06 0. 2.62E-05 0. 8.23E-05 CM243 1.45E-03 6.88E-04 8.98E-05 0. 3.27E-04 0. 8.10E-05 CM244 1.22E-03 6.16E-04 7.59E-05 0. 2.71E-04 0. 7.84E-05 CM245 1.88E-03 7.49E-04 1.13E-04 0. 4.32E-04 0. 7.30E-05 CM246 1.87E-03 7.49E-04 1.13E-04 0. 4.31E-04 0. 7.17E-05 CM247 1.82E-03 7.36E-04 1.11E-04 0. 4.24E-04 0. 9.43E-05 CM248 1.51E-02 6.07E-03 9.16E-04 0. 3.50E-03 0. 1.52E-03 CF252 1.24E-03 0. 2.95E-05 0 0. 0. 2.99E-04
Proc No ODCM Attachment 8 Revision 26 Page 5of16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 BE10 1.35E-05 1.57E-06 3.39E-07 0. 1.11E-06 0. 2.75E-05 C14 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 N13 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 F18 2.49E-06 0. 2.47E-07 0. 0. 0. 6.74E-07 NA22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 NA24 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 P32 8.25E-04 3.86E-05 3.18E-05 0. 0. 0. 2.28E-05 AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. ' 0. 0. CA41 3.47E-04 0. 3.79E-05 0. 0. 0. 1.90E-07 SC46 1.97E-08 2.70E-08 1.04E-08 0. 2.30E-08 0. 3.95E-05 CR51 0. 0. 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN54 0. 1.07E-05 2.85E-06 0. 3.00E-06 0. 8.98E-06 MN56 0. 3.34E-07 7.54E-08 0. 4.04E-07 . 0. 4.84E*05 FE55 1.15E-05 6.10E-06 1.89E-06 .o. 0. 3.45E-06 1.13E-06 FE59 1.65E-05 2.67E-05 1.33E-05 0. 0. 7.74E-06 2.78E-05 C057 0. 4.93E-07 9.98E-07 0. 0. 0. 4.04E-06 C058 0. 1.BOE-06 5.51E-06 0. 0. 0. 1.05E-05 C060 0. 5.29E-06 1.56E-05 0. 0. 0. 2.93E-05 Nl59 4.02E-05 1.07E-05 6.82E-06 0. 0. 0. 7.10E-07 Nl63 5.38E-04 2.88E-05 1.83E-05 0. 0. 0. 1.94E-06 Nl65 2.22E-06 2.09E-07 1.22E-07 0. 0. 0. 2.56E-05 CU64 0. 2.45E-07 1.48E-07 0. 5.92E-07 0. 1.15E-05 ZN65 1.37E-05 3.65E-05 2.27E-05 0. 2.30E-05 0. 6.41E*06 ZN69M 7.10E-07 1.21 E-06 1.43E-07 0. 7.03E-07 0. 3.94E-05 ZN69 4.38E-08 6.33E-08 5.85E-09 0. 3.84E-08 0. 3.99E-06 SE79 0. 8.43E-06 1.87E-06 0. 1.37E-05 0. 5.53E-07 BR82 0. 0. 7.55E-06 0. 0. 0. 0. BR83 0. 0. 1.71E-07 0. 0. 0. 0. BR84 0. 0. 1.98E-07 0. 0. 0. 0. BR85 0 0. 9.12E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. 0. 0. 0. KR85M 0. 0. 0. 0. 0. 0. 0. KR85 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 6.70E-05 4.12E-05 0. 0. 0. 4.31E-06 RB87 0. 3.95E-05 1.83E-05 0. 0. 0. 5.92E-07 RB88 0. 1.90E-07 1.32E-07 0. 0. 0. 9.32E-09 RB89 0. 1.17E-07 1.04E-07 0. 0. 0. 1.02E-09 SR89. 1.32E-03 0. 3.77E-05 0. 0. 0. 5.11 E-05 SR90 1.70E-02 0. 4.31E-03 0. 0. 0. 2.29E-04 SR91 2.40E-05 0. 9.06E-07 0. 0. 0. 5.30E-05 SR92 9.03E-06 0. 3.62E-07 0. 0. 0. 1.71E-04
Proc No ODCM Attachment 8 Revision 26 Page 6of16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 4.11 E-08 0. 1.10E-09 0. 0. 0. 1.17E-04 Y91M 3.82E-10 0. 1.39E-11 0. 0. 0. 7.48E-07 Y91 6.02E-07 0. 1.61 E-08 0. 0. 0. 8.02E-05 Y92 3.60E-09 0. 1.03E-10 0. 0. 0. 1.04E-04 Y93 1.14E-08 0. 3.13E-10 0. 0. 0. 1.70E-04 ZR93 1.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 0. 2.37E-05 ZR95 1.16E-07 2.55E-08 2.27E-08 0. 3.65E-08 0. 2.66E-05 ZR97 6.99E-09 1.01 E-09 5.96E-10 0. 1.45E-09 0. 1.53E-04 NB93M 1.05E-07 2.62E-08 8.61E-09 0. 2.83E-08 0. 3.95E-06 NB95 2.25E-08 8.76E-09 6.26E-09 0. 8.23E-09 0. 1.62E-05 NB97 2.17E-10 3.92E-11 1.83E-11 0. 4.35E-11 0. 1.21 E-05 M093 0. 2.41 E-05 8.65E-07 0. 6.35E-06 0. 1.22E-06 M099 0. 1.33E-05 3.29E-06 0. 2.84E-05 0. 1.10E-05 TC99M 9.23E-10 1.81 E-09 3.00E-08 0. 2.63E-08 9.19E-10 1.03E-06 TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06 TC101 1.07E-09 1.12E-09 1.42E-08 0. 1.91 E-08 5.92E-10 3.56E-09 RU103 7.31E-07 0. 2.81E-07 0. 1.84E-06 0. 1.89E-05 RU105 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21E-05 RU106 1.17E-05 0. 1.46E-06 0. 1.58E-05 0. 1.82E-04 RH105 5.14E-07 2.76E-07 2.36E-07 0. 1.10E-06 0. 1.71 E-05 PD107 0. 4.72E-07 4.01E-08 0. 3.95E-06 0. 9.37E-07 PD109 0. 5.67E-07 1.70E-07 0. 3.04E-06 0. 3.35E-05 AG110M 5.39E-07 3.64E-07 2.91E-07 0. 6.78E-07 0. 4.33E-05 AG111 2.48E-07 7.76E-08 5.12E-08 0. 2.34E-07 0. 4.75E-05 CD113M 0. 1.02E-05 4.34E-07 0. 1.05E-05 0. 2.63E-05 CD115M 0. 5.89E-06 2.51E-07 0. 4.38E-06 0. 8.01E-05 SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0. 0. 6.52E-05 SN125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0. 0. 1.10E-04 SN126 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0. 0. 2.50E-05 SB124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0. 6.16E-06 6.94E-05 SB125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0. 3.99E-06 1.71E-05 SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0. 2.10E-06 8.87E-05 SB127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0. 4.60E-07 5.97E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0. 0. 1.10E-05 TE127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0. 2.34E-05 TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0. 1.84E-05 TE129M 4.87E-05 1.36E-05 7.56E._06 1.57E-05 1.43E-04 0. 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0. 1.01 E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0. 4.36E-07 TE132 1.01 E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0. 4.50E-05 TE133M 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 0. 5.77E-06 TE134 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 0. 5.89E-07 1.129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 0. 4.29E-07 1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0. 2.76E-06 1131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0. 1.54E-06
Proc No ODCM Attachment 8 Revision 26 Page 7of16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0. 1.73E-06 1133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0. 2.95E-06 1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0. 5.16E-07 1135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06 XE131M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 0. 0. 0. 0. 0. 0. 0. CS134M 8.44E-08 1.25E-07 8.16E-08 0. 6.59E-08 1.09E-08 1.58E-07 CS134 2.34E-04 3.84E-04 8.10E-05 0. 1.19E-04 4.27E-05 2.07E-06 CS135 8.30E-05 5.78E-05 5.93E-06 0. 2.04E-05 6.81E-06 4.33E-07 CS136 2.35E-05 6.46E-05 4.18E-05 0. 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 0. 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 0. 2.23E-07 2.40E-08 1.46E-07 CS139 1.45E-07 1.61E-07 7.74E-08 0. 1.21 E-07 1.22E-08 1.45E-11 BA139 4.14E-07 2.21E-10 1.20E-08 0. 1.93E-10 1.30E-10 2.39E-05 BA140 8.31E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21E-05 BA141 2.00E-07 1.12E-10 6.51E-09 0. 9.69E-11 6.58E-10 1.14E-07 BA142 8.74E-08 6.29E-11 4.88E-09 0. 5.09E-11 3.70E-11 1.14E-09 LA140 1.01 E-08 3.53E-09 1.19E-09 0. 0. 0. 9.84E-05 LA141 1.35E-09 3.17E-10 6.88E-11 0. 0. 0. 7.05E-05 LA142 5.24E-10 1.67E-10 5.23E-11 0. 0. 0. 3.31E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0. 8.68E-09 0. 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-10 0. 1.59E-09 0. 5.55E-05 CE144 2.08E-06 6.52E-07 1.11E-07 0. 3.61E-07 0. 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 0. 6.39E-09 0. 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 0. 2.11E-11 0. 8.59E-08 ND147 2.79E-08 2.26E-08 1.75E-09 0. 1.24E-08 0. 3.58E-05 PM147 3.18E-07 2.27E-08 1.22E-08 0. 4.01E-08 0. 9.19E-06 PM148M 1.03E-07 2.05E-08 2.05E-08 0. 3.04E-08 0. 5.78E-05 PM148 3.02E-08 3.63E-09 2.35E-09 0. 6.17E-09 0. 9.70E-05 PM149 6.49E-09 6.90E-10 3.74E-10 0. 1.22E-09 0. 4.71E-05 PM151 2.92E-09 3.55E-10 2.31E-10 0. 6.02E-10 0. 4.03E-05 SM151 2.56E-07 3.81E-08 1.20E-08 0. 3.94E-08 0. 5.53E-06 SM153 3.65E-09 2.27E-09 2.19E-10 0. 6.91E-10 0. 3.02E-05 EU152 6.15E-07 1.12E-07 1.33E-07 0. 4.73E-07 0. 1.84E-05 EU154 2.30E-06 2.07E-07 1.89E-07 0. 9.09E-07 0. 4.81E-05 EU155 4.82E-07 3.47E-08 2.72E-08 0. 1.30E-07 0. 8.69E-05 EU156 5.62E-08 3.01E-08 6.23E-09 0. 1.94E-08 0. 6.83E-05 TB160 1.66E-07 0. 2.06E-08 0. 4.94E-08 0. 3.68E-05 H0166M 1.08E-06 2.26E-07 1.91E-07 0. 3.22E-07 0. 0. W181 4.23E-06 1.04E-08 1.43E-09 0. 0. 0. 3.79E-07 W185 1.73E-06 4.32E-07 6.05E-08 0. 0. 0. 1.61 E-05 W187 4.29E-07 2.54E-07 1.14E-07 0. 0. 0. 3.57E-05
Proc No ODCM Attachment 8 Revision 26 Page 8of16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 4.75E-02 1.22E-02 2.09E-03 0. 3.67E-02 0. 5.576-05 81210 1.97E-06 1.02E-05 1.69E-07 0. 1.15E-04 0. 5.1.7E~05 P0210 1.52E-03 2.43E-03 3.67E-04 0. 7.56E-03 0. 6.55E-05 RN222 0. 0. 0. 0. 0. 0. 0. RA223 2.12E-02 2.45E-05 4.24E-03 0. 6.50E-04 0. 3.38E-04 RA224 6.89E-03 1.25E-05 1.38E-03 0. 3.31E-04 0. 3.78E-04 RA225 2.80E-02 2.50E-05 5.59E-03 0. 6.62E-04 0. 3.21E-04 RA226 5.75E-01 1.84E-05
- 4.72E-01 0. 4.88E-04 0. 3.41E-04 RA228 3.85E-01 9.99E-06 4.32E-01 0. 2.65E-04 0. 5.81E-05 AC225 1.88E-05 1.94E-05 1.26E-06 0. 2.07E-06 0. 4.31E-04 AC227 4.12E-03 6.63E-04 2.55E-04 0. 1.46E-04 0. 8.43E-05 TH227 5.85E-05 7.96E-07 1.69E-06 0. 4.22E-06 0. 5.63E-04 TH228 2.07E-03 2.65E-05 7.00E-05 0. 1.38E-04 0. 5.79E~04 TH229 1.38E-02 1.81E-04. 6.80E-04 0. 8.84E-04 0. 5.27E-04 TH230 3.55E-03 1.78E-04 9.91E~o5 0. 8.67E-04 0. 6.19E-05 TH232 3.96E-03 1.52E-04 3.01E-04 0. 7.41E-04 0. 5.27E-05 TH234 3.42E-07 1.51 E-08 9.88E-09 0. 8.01E-08 0. 1.18E-04 PA231 7.07E-03 2.34E-04 2.81E-04 0. 1.28E-03 0. 7.37E-05 PA233 1.81 E-08 2.82E-09 3.16E-09 0. 1.04E-08 0. 1.44E-05 U232 1.76E-02 0. 1.26E-03 0. 1.34E-03 0. 6.98E-05 U233 3.72E-03 0. 2.25E-04 b. 6.10E-04 0. 6.45E-05 U234 3.57E-03 0. 2.21E-04 0. 5.98E-04 0. 6.32E-05 U235 3.42E-03 0. 2.07E-04 0. 5.61E-04 0. 8.03E-05 U236 . 3.42E-03 0. 2.12E-04 0. 5.73E-04 0. 5.92E-05 U237 2.36E-07 0. 6.27E-08 0. 6.81E-07 0. 2.08E-05 U238 3.27E-03 0. 1.94E-04 0. 5.24E-04 0. 5.66E-05 NP237 2.36E-03 1.81 E-04 9.79E-05 0. 6.05E-04 0. 8.16E-05 NP238 5.83E-08 1.18E-09 9.08E-10 0. 3.76E-09 0. 4.04E-05 NP239 5.25E-09 3.77E-10 2.65E-10 0. 1.09E-09 0. 2.79E-05 PU238 1.25E-03 1.56E-04 3.16E-05 0. 1.15E-04 0. 7.50E-05 PU239 1.36E-03 1.65E-04 3.31E-05 0. 1.22E-04 0. 6.85E-05 PU240 1.36E-03 1.65E-04 3.31E-05 0. 1.22E-04 0. 6.98E-05 PU241 4.00E-05 1.72E-06 8.04E-07 0. 2.96E-06 0. 1.44E-06 PU242 1.26E-03 1.59E-04 3.19E-05 0. 1.17E-04 0. 6.71E-05 PU244 1.47E-03 1.82E-04 3.65E-05 0. 1.35E-04 0. 1.00E-04 AM241 1.43E-03 6.40E-04 1.02E-04 0. 6.23E-04 0. 7.64E-05 AM242M 1.47E-03 6.25E-04 1.04E-04 0. 6.30E-04 0. 9.61E-05 AM243 1.41E-03 6.14E-04 9.83E-05 0. 6.06E-04 0. 8.95E-05 CM242 8.80E-05 6.73E-05 5.84E-06 0. 1.87E-05 0. 8.16E-05 CM243 1.33E-03 6.03E-04 8.24E-05 0. 3.08E-04 0. 8.03E-05 CM244 1.11E-03 5.36E-04 6.93E-05 0. 2.54E-04 0. 7.77E-05 CM245 1.76E-03 6.64E-04 1.05E-04 0. 4.11E-04 0. 7.24E-05 CM246 1.74E-03 6.64E-04 1.05E-04 0. 4.10E-04 0. 7.11E-05 CM247 1.70E-03 6.53E-04 1.03E-04 0. 4.04E-04 0. 9.35E-05 CM248 1.41E-02 5.38E-03 8.52E-04 0. 3.33E-03 0. 1.51 E-03 CF252 1.07E-03 0. 2.54E-05 0. 0. 0. 2.96E-04
Proc NoODCM Attachment 8 Revision 26 Page 9of16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E~07 BE10 4.48E-06 6.94E-07 1.13E-07 0. S.30E-07 0. 2.84E-OS C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 N13 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 F18 8.64E-07 0. 9.47E-08 0. 0. 0. 7.78E-08 NA22 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71E-OS 1.07E-OS 0. 0. 0. 2.32E-OS AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 1.97E-04 0. 2.13E-OS 0. 0. 0. 1.9SE-07 SC46 7.24E-09 1.41 E-08 4.18E-09 0. 1.3SE-08 0. 4.80E-OS CRS1 0. 0. 3.60E-09 2.00E-09 7.89E-10 S.14E-09 6.0SE-07 MNS4 0. S.90E-06 1.17E-06 0. 1.76E-06 0. 1.21E-OS MNS6 0. 1.S8E-07 2.81E-08 0. 2.00E-07 0. 1.04E-OS FESS 3.78E-06 2.68E-06 6.2SE-07 0. 0. 1.?0E-06 1.16E-06 FES9 S.87E-06 1.37E-OS S.29E-06 0. 0. 4.32E-06 3.24E-OS COS? 0. 2.38E-07 3.99E-07 0. 0. 0. 4.44E-06 COS8 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-OS C060 0 2.81E-06 6.33E-06 0. 0. 0. 3.66E-OS NIS9 1.32E-OS 4.66E-06 2.24E-06 0. 0. 0. 7.31E-07 Nl63 1.77E-04 1.2SE-OS 6.00E-06 0. 0. 0. 1.99E-06 Nl6S 7.49E-07 9.S?E-08 4.36E-08 0. 0. 0. S.193-06 CU64 0. 1.1SE-07 S.41 E-08 0. 2.91E-07 0. 8.92E-06 ZN6S S.76E-06 2.00E-05 9.33E-06 0. 1.28E-OS 0. 8.47E-06 ZN69M 2.40E-07 S.66E-07 S.19E-08 0. 3.44E-07 0. 3.11E-OS ZN69 1.47E-08 2.80E-08 1.96E-09 0. 1.83E-08 0. S.16E-08 SE79 0. 3.73E-06 6.27E-07 0. 6.SOE-06 0. S.?OE-07 BR82 0. 0. 3.04E-06 0. 0. 0. 0. BR83 0. 0. S.74E-08 0. 0. 0. 0. BR84 0. 0. 7.22E-08 0. 0. 0. 0. BR8S 0. 0. 3.0SE-09 0. 0. 0. 0. KR83M 0. 0. 0. . 0. 0. 0. 0. KR8SM 0. 0. 0. 0. 0. 0. 0. KR8S 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 2.98E-OS 1.40E-OS 0. 0. 0. 4.41E-06 RB87 0. 1.7SE-OS 6.11E-06 0. 0. 0. 6.11E-07 RB88 0. 8.S2E-08 4.S4E-08 0. 0. 0. 7.30E-1S RB89 0. S.SOE-08 3.89E-08 0. 0. 0. 8.43E-17 SR89 4.40E-04 0.
- 1.26E-OS 0. 0. 0. S.24E-OS SR90 8.30E-03 0. 2.0SE-03 0. 0. 0. 2.33E-04 SR91 8.0?E-06 0. 3.21E-07 0. 0. 0. 3.66E-OS SR92 3.0SE-06 0. 1.30E-07 0. 0. 0. 7.77E-OS
Proc No ODCM Attachment 8 Revision 26 Page 10of16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 1.37E-08 0. 3.69E-10 0. 0. 0. 1.13E-04 Y91M 1.29E-10 0. 4.93E-12 0. 0. 0. 6.09E-09 Y91 2.01E-07 0. 5.39E-09 0. 0. 0. 8.24E~05 Y92 1.21 E-09 0. 3.50E-11 0. 0. 0. 3.32E-05 Y93 3.83E-09 0. 1.05E-10 0. 0. 0. 1.17E-04 ZR93 5.53E-08 2.73E-08 1.49E-08 0. 9.65E-08 0. 2.58E-05 ZR95 4.12E-08 1.30E-08 8.94E-09 0. 1.91 E-08 0. 3.00E-05 ZR97 2.37E-09 4.69E-10 2.16E-10 0. 7.11E-10 0. 1.27E-04 NB93M 3.44E-08 1.13E-08 2.83E-09 0. 1.32E-08 0. 4.07E-06 NB95 8.22E-09 4.56E-09 2.51E-09 0. 4.42E-09 0. 1.95E-05 NB97 7.37E-11 1.83E-11 6.68E-12 0. 2.14E-11 0. 4.37E-07 M093 0. 1.06E~05 2.90E-07 0. 3.04E-06 0. 1.29E-06 M099 0. 6.03E-06 1.15E-06 0. 1.38E-05 0. 1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0. 1.38E-08 5.14E-10 6.08E-07 TC99 1.79E-07 2.63E-07 7.17E-08 0. 3.34E-06 2.72E-08 6.44E-06 TC101 3.60E-10 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.75E-17 RU103 2.55E-07 0. 1.09E-07 0. 8.99E-07 0. 2.13E-05 RU105 2.18E-08 0. 8.46E-09 0. 2.75E-07 0. 1.76E-05 RU106 3.92E-06 0. 4.94E-07 0. 7.56E-06 0. 1.88E-04 RH105 1.73E-07 1.25E-07 8.20E-08 0. 5.31E-07 0. 1.59E-05 PD107 0. 2.08E-07 1.34E-08 0. 1.88E-06 0. 9.66E-07 PD109 0. 2.51E-07 5.706-08 0. 1.45E-06 0. 2.53E-05 AG110M 2.05E-07 1.94E-07 1.18E-07 0. 3.70E-07 0. 5.45E-05 AG111 8.29E-08 3.44E-08 1.73E-08 0. 1.12E-07 0. 4.80E-05 C0113M 0. 4.51E-06 1.45E-07 0. 4.99E-06 0. 2.71E-05 CD115M 0. 2.60E-06 8.39E-08 0. 2.08E-06 0. 8.23E-05 SN123 4.44E-05 7.29E-07 1.08E-06 5.84E-07 0. 0. 6.71E-05 SN125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. 1.12E-04 SN126 1.16E-04 2.16E-06 3.30E-06 5.69E-07 0. 0. 2.58E-05 SB124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0. 3.386-06 7.80E-05 SB125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0. 2.18E-06 1.93E-05 SB126 1.59E-06 3.25E-08 5.71E-07 8.99E-09 0. 1.14E~06 9.41E-05 SB127 3.63E-07 7.76E-09 1.37E-07 4.08E-09 0. 2.47E-07 6.16E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0. 0. 1.13E-05 TE127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0. 2.41E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0. 1.22E-05 TE129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0. 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0. 2.45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0. 9.39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0. 2.29E-09 TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0. 7.00E-05 TE133M 6.44E-08 3.66E-08 3.56E-08 5.11 E-08 3.62E-07 0. 1.48E-07 TE134 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 0. 1.66E-09 1129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.01E-06 0. 4.57E-07 1130 1.036-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0. 2.29E-06 1131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 0. 1.62E-06
Proc NoODCM Attachment 8 Revision 26 Page 11of16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0. 3.18E-07 1133 2.01E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0. 2.58E-06 1134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0. 5.10E-09 1135 6.10E-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0. 1.74E-06 XE131M 0. 0. 0. 0. 0. 0. 0. XE133M 0. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 0. 0. 0. 0. 0. 0. 0. CS134M 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.95E-09 4.05E-08 CS134 8.37E-05 1.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06 CS135 2.78E-05 2.55E-05 5.96E-06 0. 9.73E-06 3.52E-06 4.46E-07 CS136 8.59E-06 3.38E-05 2.27E-05 0. 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 0. 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0. 1.10E-07 1.28E-08 6.76E-11 CS139 4.87E-08 7.17E-08 2.63E-08 0. 5.79E-08 6.34E-09 3.33E-23 BA139 1.39E-07 9.78E-11 4.05E-09 0. 9.22E-11 6.74E-11 1.24E-06 BA140 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05 BA141 6.71E-08 5.01E-11 2.24E-09 0. 4.65E-11 3.43E-11 1.43E-13 BA142 2.99E-08 2.99E-11 1.84E-09 0. 2.53E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71 E-09 4.55E-10 0. 0. 0. 9.82E-05 LA141 4.55E-10 1.40E-10 2.31E-11 0. 0. 0. 2.48E-05 LA142 1.79E-10 7.95E-11 1.98E-11 0. 0. 0. 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0. 4.18E-09 0. 2.54E-05 CE143 2.35E-09 1.71E-06 1.91E-10 0. 7.67E-10 0. 5.14E-05 CE144 6.96E-07 2.88E-07 3.74E-08 0. 1.72E-07 0. 1.75E-04 PR143 1.31 E-08 5.23E-09 6.52E-10 0. 3.04E-09 0. 4.31E-05 PR144 4.30E-11 1.76E-11 2.18E-12 0. 1.01E-11 0. 4.74E-14 ND147 9.38E-09 1.02E-08 6.11E-10 0. 5.99E-09 0. 3.68E-05 PM147 1.05E-07 9.96E-09 4.06E-09 0. 1.90E-08 0. 9.47E-06 PM148M 4.14E-08 1.05E-08 8.21E-09 0. 1.59E-08 0. 6.61E-05 PM148 1.02E-08 1.66E-09 8.36E-10 0. 3.00E-09 0. 9.90E-05 PM149 2.17E-09 3.05E-10 1.25E-10 0. 5.81E-10 0. 4.49E-05 PM151 9.87E-10 1.63E-10 8.25E-11 0. 2.93E-10 0. 3.66E-05 SM151 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06 SM153 1.22E-09 1.01 E-09 7.43E-11 0. 3.30E-10 0. 2.85E-05 EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07 0. 2.17E-05 EU154 7.91E-07 1.02E-07 7.19E-08 0. 4.56E-07 0. 5.39E-05 EU155 1.74E-07 1.68E-08 1.04E-08 0. 6.57E-08 0. 9.63E-05 EU156 1.92E-08 1.44E-08 2.35E-09 0. 9.69E-09 0. 7.36E-05 TB160 6.47E-08 0. 8.07E-09 0. 2.56E-08 0. 4.19E-05 H0166M 3.57E-07 1.10E-07 7.96E-08 0. 1.61E-07 0. 0. W181 1.42E-08 4.58E-09 4.79E-10 0. 0. 0. 3.90E-07 W185 5.79E-07 1.91 E-07 2.02E-08 0. 0. 0. 1.65E-05 W187 1.46E-07 1.19E-07 4.17E-08 0. 0. 0. 3.22E-05
Proc No ODCM Attachment 8 Revision 26 Page 12of16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 1.81E-02 5.44E-03 7.01E-04 0. 1.72E-02 0. 5.74E-05 81210 6.59E-07 4.51E-06 5.66E-08 0. 5.48E-05 0. 5.15E-05 P0210 6.09E-04 1.07E-03 1.23E-04 0. 3.60E-03 0. 6.75E-05 RN222 0. 0. 0. 0. 0. 0. 0. RA223 7.11E-03 1.08E-05 1.42E-03 0. 3.10E-04 0. 3.43E-04 RA224 2.31E-03 5.52E-06 4.61E-04 0. 1.58E-04 0. 3.71E-04 RA225 9.37E-03 1.10E-05 1.876-03 0. 3.15E-04 0. 3.27E-04 RA226 3.22E-01 8.13E-06 2.39E-01 0. 2.32E-04 0. 3.51E-04 RA228 1.37E-01 4.41 E-06 1.51E-01 0. 1.26E-04 0. 5.98E-05 AC225 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.36E-04 AC227 2.05E-03 3.03E-04 1.22E-04 0. 8.81E-05 0. 8.68E-05 TH227 1,96E-05 3.52E-07 5.65E-07 0. 2.01E-06 0. 5.75E-04 TH228 6.80E-04 1.14E-05 2.30E-05 0. 6.41 E-05 0. 5.97E-04 TH229 8.39E-03 1.26E-04 4.11E-04 0. 6.10E-04 0. 5.43E-04 TH230 2.16E-03 1.23E-04 6.00E-05 0. 5.99E-04 0. 6.38E-05 TH232 2.42E-03 1.05E-04 1.63E-04 0. 5.11 E-04 0. 5.43E-05 TH234 1.14E-07 6.68E-09 3.31E-09 0. 3.81E-08 0. 1.21E-04 PA231 4.31E-03 1.62E-04 1.68E-04 0. 9.10E-04 0. 7.60E-05 PA233 7.33E-09 1.41 E-09 1.26E-09 0. 5.32E-09 0. 1.61 E-05 U232 5.89E-03 0. 4.21E-04 0. 6.38E-04 0. 7.19E-05 U233 1.24E-03 0. 7.543-05 0. 2.90E-04 0. 6.65E-05 U234 1.19E-03 0. 7.39E-05 0. 2.85E-04 0. 6.51E-05 U235 1.14E-03 0. 6.94E-05 0. 2.67E-04 0. 8.28E-05 U236 1.14E-03 o. 7.09E-05 0. 2.73E-04 0. 6.11 E-05 U237 7.89E-08 0. 2.10E-08 0. 3.24E-07 0. 2.09E-05 U238 1.09E-03 0. 6.49E-05 0. 2.50E-04 0. 5.83E-05 NP237 1.44E-03 1.25E-04 5.85E-05 0. 4.33E-04 0. 8.41E-05 NP238 1.95E-08 5.22E-10 3.04E-10 0. 1.79E-09 0. 3.83E-05 NP239 1.76E-09 1.66E-10 9.22E-11 0. 5.21E-10 0. 2.67E-05 PU238 7.21E-04 1.02E-04 1.82E-05 0. 7.80E-05 0. 7.73E-05 PU239 8.27E-04 1.12E-04 2.01E-05 0. 8.57E-05 0. 7.06E-05 PU240 8.26E-04 1.12E-04 2.01E-05 0. 8.56E-05 0. 7.19E-05 PU241 1.84E-05 9.42E-07 3.69E-07 0. 1.71 E-06 0. 1:48E-06 PU242 7.66E-04 1.08E-04 1.94E-05 0. 8.256-05 0. 6.92E-05 PU244 8.95E-04 1.236-04 2.22E-05 0. 9.45E-05 0. 1.03E-04 AM241 8.62E-04 3.29E-04 5.75E-05 0. 4.31E-04 0. 7.87E-05 AM242M 8.70E-04 3.19E-04 5.80E-05 0. 4.30E-04 0. 9.90E-05 AM243 8.60E-04 3.17E-04 5.62E-05 0. 4.22E-04 0. 9.23E-05 CM242 2.94E-05 2.97E-05 1.95E-06 0. 8.89E-06 0. 8.40E-05 CM243 6.91E-04 2.86E-04 4.09E-05 0. 1.91 E-04 0. 8.28E-05 CM244 5.32E-04 2.49E-04 3.19E-05 0. 1.49E-04 0. 8.00E-05 CM245 1.07E-03 3.33E-04 6.10E-05 0. 2.85E-04 0. 7.46E-05 CM246 1.06E-03 3.32E-04 6.09E-05 0. 2.84E-04 0. 7.33E-05 CM247 1.03E-03 3.27E-04 6.00E-05 0. 2.80E-04 0. 9.63E-05 CM248 8.606-03 2.69E-03 4.95E-04 0. 2.31E-03 0. 1.55E-03 CR252 3.51E-04 0. 8.37E-06 0. 0. 0. 3.05E-04
Proc No ODCM Attachment 8 Revision 26 Page 13of16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 BE10 3.18E-06 4.91E-07 7.94E-08 0. 3.71E-07 0. 2.68E-05 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 N13 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 F18 6.24E-07 0. 6.92E-08 0. 0. 0. 1.85E-08 NA22 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 NA24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0. 0. 0. 2.17E-05 AR39 0. 0. 0. 0. 0. 0. 0. AR41 0. 0. 0. 0. 0. 0. 0. CA41 1.83E-05 0. 2.00E-05 0. 0. 0. 1.84E-07 SC46 5.51E-09 .1.07E-08 3.11 E-09 0. 9.99E-09 0. 5.21E-05 CR51 0. 0. 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN54 0. 4.57E-06 8.72E-07 0. 1.36E-06 0. 1.40E-05 MN56 0. 1.15E-07 2.04E-08 0. 1.46E-07 0. 3.67E-06 FESS 2.75E-06 1.90E-06 4.43E-07 0. 0. 1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91E-06 0. 0. 2.85E-06 3.40E-05 C057 0. 1.75E-07 2.91E-07 0. 0. 0. 4.44E-06 C058 0. 7.45E-07 1.67E-06 0. 0. 0. 1.51 E-05 C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05 Nl59 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07 Nl63 1.30E-04 9.01E-06 4.36E-06 0. 0. 0. 1.88E-06 Nl65 5.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1.74E-06 CU64 0. 8.33E-08 3.91E-08 0. 2.10E-07 0. 7.10E-06 ZN65 4.84E-06 1.54E-05 6.96E-06 0. 1.03E-05 0. 9.70E-06 ZN69M 1.70E-07 4.08E-07 3.73E-08 0. 2.47E-07 0. 2.49E-05 ZN69 1.03E-08 1.97E-08 1.37E-09 0. 1.28E-08 0. 2.96E-09 SE79 0. 2.63E-06 4.39E-07 0. 4.55E-06 0. 5.38E-07 BR82 0. 0. 2.26E~06 0. 0. 0. 2.59E-06 BR83 0. 0. 4.02E-08 0. 0. 0. 5.79E-08 BR84 0. 0. 5.21E-08 0. 0. 0. 4.09E-13 BR85 0. 0. 2.14E-09 0. 0. 0. 0. KR83M 0. 0. 0. 0. o, 0. 0. KR85M 0. 0. 0. 0. 0. 0. 0. KR85 0. 0. 0. 0. 0. 0. 0. KR87 0. 0. 0. 0. 0. 0. 0. KR88 0. 0. 0. 0. 0. 0. 0. KR89 0. 0. 0. 0. 0. 0. 0. RB86 0. 2.11E-05 9.83E-06 0. 0. 0. 4.16E-06 RB87 0. 1.23E-05 4.28E-06 0. 0. 0. 5.76E-07 RB88 0. 6.0SE-08 3.21E-08 0. 0. 0. 8.36E-19 RB89 0. 4.01E-08 2.82E-08 0. 0. 0. 2.33E-21 SR89 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05 SR90 7.58E-03 0. 1.86E-03 0. 0. 0. 2.19E-04 SR91 5.67E-06 0. 2.29E-07 0. 0. 0. 2.70E-05 SR92 2.15E-06 0. 9.30E-08 0. 0. 0. 4.26E-05
Proc No ODCM Attachment 8 Revision 26 Page 14of16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 9.62E-09 0. 2.58E-10 0. 0. 0. 1.02E-04 Y91M 9.09E-11 0. 3.52E-12 0. 0. 0. 2.67E-10 Y91 1.41E-07 0. 3.77E-09 0. 0. 0. 7.76E-05 Y92 8.45E-10 0. 2.47E-11 0. 0. 0. 1.48E-05 Y93 2.68E-09 0. 7.40E-11 0. 0. 0. 8.50E-05 ZR93 4.18E-08 2.34E-09 1.09E-09 0. 8.87E-09 0. 2.43E-06 ZR95 3.04E-08 9.75E-09 6.60E-09 0. 1.53E-08 0. 3.09E-05 ZR97 1.68E-09 3.39E-10 1.55E-10 0. 5.12E-10 0. 1.05E-04 N893M 2.55E-08 8.32E-09 2.05E-09 0. 9.57E-09 0. 3.84E-06 N895 6.22E-09 3.46E-09 1.86E-09 0. 3.42E-09 0. 2.10E-05 N897 5.22E-11 1.32E-11 4.82E-12 0. 1.54E-11 0. 4.87E-08 M093 0. 7.51E-06 2.03E-07 0. 2.13E-06 0. 1.22E-06 M099 0. 4.31E-06 8.20E-07 0. 9.766-06 0. 9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0. 1.06E-08 3.42E-10 4.13E-07 TC99 1.25E-07 1.86E-07 5.02E-08 0. 2.34E-06 1.58E-08 6.08E-06 TC101 2.54E-10 3.66E-10 3.59E-09 0. 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.16E-05 RU105 1.54E-08 0. 6.08E-09 0. 1."99E-07 0. 9.42E-06 RU106 2.75E-06 0. . 3.48E-07 0. 5.31E-06 0. 1.78E-04 RH105 1.21 E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41 E-05 PD107 0. 1.47E-07 9.40E-09 0. 1.32E-06 0. 9.11E-07 PD109 0. 1.77E-07 3.99E-08 0. 1.01 E-06 0. 1.96E-05 AG110M 1.60E-07 1.48E-07 8.79E-08 0. 2.91E-07 0. 6.04E-05 AG111 5.81E-08 2.43E-08 1.21 E-08 0. 7.84E-08 0. 4.46E-05 CD113M 0. 3.18E-06 1.02E-07 0. 3.50E-06 0. 2.56E-05 CD115M 0. 1.84E-06 5.87E-08 0. 1.46E-06 0. 7.74E~05 8N123 3.11E-05 5.15E-07 7.59E-07 4.38E-07 0. 0. 6.33E-05 8N125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0. 0. 1.04E-04 8N126 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05 88124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0. 2.18E-06 7.95E-05 88125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0. 1.38E-06 1.97E-05 88126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05 88127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 0. 1.53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0. 1.07E-05 TE125M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0. 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.156-08 4.48E-07 0. 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0. 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0. 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0. 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0. 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0. 7.71E-05 TE133M 4.62E-08 2.70E-08 2.60E-08 3.91E-08 2.676-07 0. 6.64E-08 TE134 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 0. 3.59E-11 1129 3.27E-06 2.81E-06 9.21E-06 7.23E-03 6.04E-06 0. 4.44E-07 1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0. 1.92E-06 1131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0. 1.57E-06
Proc No ODCM Attachment 8 Revision 26 Page 15of16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0. 1.02E-07 1133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0. 2.22E-06 1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51E-10 1135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0. 1.31 E-06 XE131M 0. 0. 0. 0. 0. 0. 0. XE133M o. 0. 0. 0. 0. 0. 0. XE133 0. 0. 0. 0. 0. 0. 0. XE135M 0. 0. 0. 0. 0. 0. 0. XE135 0. 0. 0. 0. 0. 0. 0. XE137 0. 0. 0. 0. 0. 0. 0. XE138 0. 0. 0. 0. 0. 0. 0. CS134M 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.58E-08 CS134 6.22E-05 1.48E-04 1.21E-04 0. 4.79E-05 1.59E-05 2.59E-06 CS135 1.95E-05 1.80E-05 7.99E-06 0. 6.81E-06 2.04E-06 4.21E-07 CS136 6.51E-06 2.57E-05 1.85E-05 0. 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.11 E-06 CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.01E-08 7.91E-09 4.65E-13 CS139 3.41 E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.10E-30 BA139 9.70E-08 6.91 E-11 2.84E-09 0. 6.46E-11 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11 1.59E-09 0. 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2.19E-11 1.34E~09 0. 1.85E-11 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10 0. 0. 0. 9.25E-05 LA141 3.19E-10 9.90E-11 1.62E-11 0. 0. 0. 1.18E-05 LA142 1.28E-10 5.82E-11 1.45E-11 0. 0. 0. 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 0. 5.37E-10 0. 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 0. 1.21 E-07 0. 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 0. 2.13E-09 0. 4.03E-05 PR144 3.01E-11 1.25E-11 1.53E-12 0. 7.05E-12 0. 4.33E-18 ND147 6.29E-09 7.27E-09 4.35E-10 0. 4.25E-09 0. 3.49E-05 PM147 7.54E-08 7.09E-09 2.87E-09 0. 1.34E-08 0. 8.93E-06 PM148M 3.07E-08 7.95E-09 6.QSE-09 0. 1.20E-08 0. 6.74E-05 PM148 7.17E-09 1.19E-09 5.99E-10 0. 2.25E-09 0. 9.35E-05 PM149 1.52E-09 2.15E-10 8.78E-11 0. 4.06E-10 0. 4.03E-05 PM151 6.97E-10 1.17E-10 5.91 E-11 0. 2.09E-10 0. 3.22E-05 SM151 6.90E-08 1.19E-08 2.85E-09 0. 1.33E-08 0. 5.25E-06 SM153 8.57E-10 7.15E-10 5.22E-11 0. 2.31E-10 0. 2.55E-05 EU152 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05 EU154 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05 EU155 8.60E-08 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.60E-06 EU156 1.37E-08 1.06E-08 1.71E-09 0. 7.08E-09 0. 7.26E-05 TB160 4.70E-08 0. 5.86E-09 0. 1.94E-08 0. 4.33E-05 H0166M 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0. W181 9.91E-09 3.23E-09 3.46E-10 0. 0. 0. 3.68E-07 W185 4.05E-07 1.35E-07 1.42E-08 0. 0. 0. 1.56E-05 W187 1.03E-07 8.61E-08 3.01E-08 0. 0. 0. 2.82E-05
Proc No ODCM Attachment 8 Revision 26 Page 16of16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.42E-05 81210 4.61E-07 3.18E-06 3.96E-08 0. 3.83E-05 0. 4.75E-05 P0210 3.56E-04 7.56E-04 8.59E-05 0. 2.52E-03 0. 6.36E-05 RN222 0. 0. 0. 0. 0. 0. 0. RA223 4.97E-03 7.65E-06 9.94E-04 0. 2.17E-04 0. 3.21E-04 RA224 1.61 E-03 3.90E-06 3.23E-04 0. 1.10E-04 0. 3.40E-04 RA225 6.56E-03 7.78E-06 1.31 E-03 0. 2.21E-04 0. 3.06E-04 RA226 3.02E-01 5.74E-06 2.20E-01 0. 1.63E-04 0. 3.32E-04 RA228 1.12E-01 3.12E-06 1.21E-01 0. 8.83E-05 0. 5.64E-05 AC225 4.40E-06 6.06E-06 2.96E-07 0. 6.90E-07 0. 4.07E-04 AC227 1.87E-03 2.48E-04 1.11E-04 0. 8.00E-05 0. 8.19E-05 TH227 1.37E-05 2.48E-07 3.95E-07 0. 1.41E-06 0. 5.40E-04 TH228 4.96E-04 8.40E-06 1.68E-05 0. 4.67E-05 0. 5.63E-04 TH229 7.98E-03 1.19E-04 3.91E-04 0. 5.75E-04 0. 5.12E-04 TH230 2.06E-03 1.17E-04 5.70E-05 0. 5.65E-04 0. 6.02E-05 TH232 2.30E-03 1.00E-04 1.50E-04 0. 4.82E-04 0. 5.12E-05 TH234 8.01E-08 4.71E-09 2.31E-09 0. 2.67E-08 0. 1.13E-04 PA231 4.10E-03 1.54E-04 1.59E-04 0. 8.64E-04 0. 7.17E-05 PA233 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. 1.64E-05 U232 4.13E-03 0. 2.95E-04 0. 4.47E-04 0. 6.78E-05 U233 8.71E-04 0. 5.28E-05 0. 2.03E-04 0. 6.27E-05 U234 8.36E-04 0. 5.17E-05 0. 1.99E-04 0. 6.14E-05 U235 8.01E-04 0. 4.86E-05 0. 1.87E-04 0. 7.81E-05 U236 8.01E-04 0. 4.96E-05 0. 1.91 E-04 0. 5.76E-05 U237 5.52E-8 0. 1.47E-08 0. 2.27E-07 0. 1.94E-05 U238 7.67E-04 0. 4.54E-05 0. 1.75E-04 0. 5.50E-05 NP237 1.37E-03 1.19E-04 5.54E-05 0. 4.12E-04 0. 7.94E-05 NP238 1.37E-08 3.69E-10 2.13E-10 0. 1.25E-09 0. 3.43E-05 NP239 1.19E-09 1.17E-10 6.45E-11 0. 3.65E-10 0. 2.40E-05 PU238 6.80E-04 9.58E-05 1.71E-05 0. 7.32E-05 0. 7.30E-05 PU239 7.87E-04 1.06E-04 1.91E-05 0. 8.11E-05 0. 6.66E-05 PU240 7.85E-04 1.06E-04 1.91E-05 0. 8.10E-05 0. 6.78E-05 PU241 1.65E-05 8.44E-07 3.32E-07 0. 1.53E-06 0. 1.40E-06 PU242 7.29E-04 1.02E-04 1.84E-05 0. 7.81E-05 0. 6.53E-05 PU244 8.52E-04 1.17E-04 2.11E-05 0. 8.95E-05 0. 9.73E-05 AM241 8.19E-04 2.88E-04 5.41E-05 0. 4.07E-04 0. 7.42E-05 AM242M 8.24E-04 2.78E-04 5.43E-05 0. 4.05E-04 0. 9.34E-05 AM243 8.18E-04 2.78E-04 5.30E-05 0. 3.99E-04 0. 8.70E-05 CM242 2.06E-05 2.10E-05 1.37E-06 0. 6.22E-06 0. 7.92E-05 CM243 6.39E-04 2.41E-04 3.75E-05 0. 1.75E-04 0. 7.81E-05 CM244 4.83E-04 2.07E-04 2.87E-05 0. 1.34E-04 0. 7.55E-05 CM245 1.02E-03 2.87E-04 5.76E-05 0. 2.69E-04 0. 7.04E-05 CM246 1.01 E-03 2.87E-04 5.75E-05 0. 2.68E-04 0. 6.91E-05 CM247 9.84E-04 2.83E-04 5.67E-05 0. 2.64E-04 0. 9.09E-05 CM248 8.18E-03 2.33E-03 4.67E-04 0. 2.18E-03 0. 1.47E-03 CF252 2.64E-04 0. 6.29E-06 0. 0. 0. 2.88E-04
Proc No ODCM Attachment 9 Revision 26 Page 1of1 PALISADES 10 YEAR X/Q- DIQ DATA USNRC COHPUTER CODE - .XOQDOQ, *v'ERS ION 2
- 0 RUN DATE: 28FEB14
- ~ PALISADES XOQDOQ82 **H* USING 01/01/2004 - l2/-31/20"13 HE.T' DATA **~***
GROUND LEVEL RELEAS.E - TO? OF :coN'.rAINl~NT BUILDING iSP15Cil!'lC POJ:NT.S OF J:'NTI!:RE.3:" REL.El1SE TYPE OF QIREC.TION DISTl\NCE XIQ X/.Q X/Q D/Q ID LOCATION F~OH SI'rE (MILES) (METERS) \ SEC°Jccs. ~lETER} (SE*::!/CUB.METER) (SEC/CUB.METER) (PER SQ.ME.TER) NO DECAY, 2.260 DAY DECAY. 8.000 DAY DECAY UNDEPLETED UfTDEPLETED DEPLETED A SITE BOUNDARY NNE 0 .50 805. l.58E-{)6 I. 5_7E-0:6 l -44J>-06 7. 61E,...09 A. SITE 'BOUNDARY NE 0. 65 1046. 1.23E-06 1.23E-06 l.llE-06 8.80E-09 A SITE BOUNDARY EN.f; 0.87 140.0. 5. 88E-07 5.86E:-07 5.* 19E-07 4 .* 27E-09 A SITE BOUNDARY E 0.82 1320. 6_.99E-07 6.96E-07 6;19E-07 5*. 29E-09
'A SITE BOUNDARY ESE 0.76 1223. 8.34E-07 8 *. 3.lE-07 7.* 42E-07 .6.**93E-09 A ~ITE ~qUNDARY *SE 0.63 1014 .* l. 39:£0:.06 l *. 3.BE-06 1.25E-06 L-25E-0,8.
A .SITE :soUNDARY S;5E 0-.<18 772. 2, 28E-OG '2', 28E.-.o*6 2. 09E-0.6 ':2 .* O}E-.08 A SITE BOUNDARY *s. 0 *. 42 676. 1. 96E-0..6 1. 95E'...06 L 89.E-06 1. llE-(i8 A SITE BOUNDARY SSW 0.48 772. 1. 26E-06 1. 25E,-06 l;15E-06 6.25E-09 A RE.SI DENCE NNE 1.68 ;;:704. 2. 59E-07 2.57E-07 2. HE-07 9 *. 83E-10
.A RE.SI DENCE NE l. l*l 1835. 5, 32E-0.7 5.30E-07 t,.61E-0-7 *3. 39E-0.9 A RESIDENCE ENE 1 .. I.Si 1915. 3.70E-07 3.67E-07 3.19E-07 '2 .. 50E-0.9 A RESIDENCE E 1.67 2688. 2. 43E-0.7 2.4fa..,.07 2 .ME-07 ; 1. 56E;..09 f.. REp!DENCE J;;SE 0.99 1593. 5 .60E-07 5-.58E-07 ~.!)OE-07 4. 43E.:...'a9. .A *RESIDE!~CE SE 0.90 1448
- a .'ozE-67 7 *. 98E-07 7. 06E-07 6.86E-09 A *RESIDENCE SSE 0;80 1287. 1.0SE-06 1.04E-06 9.28E-07 *8.64E-09 A JIBSIDENCE s p.77 1239. i. 87E.-Cr7 7. S<lE-07 6.99E-07 :4 .12E-09 A 'RESIQENCE SSW 0.49 7.89 - l.22E-06 l.21E-06 l .llE-06 6.04E-09 A .GARDEN NNE 1. 75 :2816. 2 .45E-0.7 2.43E-07 2 .. 0SE-07 9.16E-10 A QJ;RDEN *NE 1 .* 67 2688. 3.03E-07 3.0lE-o'7 2.54E_.:07 1. 76E-09 A GARDEN ENE 2.62 4216. l.16E-07 l.HE-07 9.*. 29E'-08 6.34E-10 A *GARDEN E :2.68 4313 *. l .21E-07 1. 20E-07 9.7QE-08 6.83E-10 A GARDEN *ESE 1. 83 2945. 2. 24E-07 2.22E-07 1.86E-07 1.54E-0.9 A Gl\RDEN SE 1.49 2398. 3. 7.7E-07 .3. 75E.-07 3 .. 20E-0.7 *i.a9E-<i9 A GARDEN SSE 0.69 11'10. l.JlE-06 L31E-06 LI 7E-06 l. llE-,08 A ,GARPEN SSW *4 :a2 7757. 4. 54E-08 *l .43E-08 3, 2'8E-08 1.17E"'l0 A GOAT ENE 2.62 4216. l .16E-07 1. 14E-07 '9.29E-08 6.34E-10 A GOAT E 4.25 6840. 6.* 17E-08 6'. 05E-0.8 t,.67E-08 3 .* 0lE...,10 A l3EE,F .CATTLE SE 4.27 6872. 8.0lE-08 7.85E-OB 6:. Q6E,...08 4.~3E'.'..lO
ODCM Appendix A Revision 18 Issued Date 11/17/14 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) IProcess Applicability Exclusion D CLJones I 11/13/14 Procedure Sponsor Date CLJones I 9/17/14 Technical Reviewer Date ALWilliams I 11/11/14 General Manager Plant Operations Date
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page i TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table of Contents I. INTRODUCTION ............................................................................................................ 1 II. DEFINITIONS ................................................................................................................. 1 A. CHANNEL CALIBRATION ............................................................................ 1 B. CHANNEL CHECK ........................................................................................ 1 C. CHANNEL FUNCTIONAL TEST .................................................................... 2 D. SOURCE CHECK .......................................................................................... 2 E. OFFSITE DOSE CALCULATION MANUAL. ................................................. 2 F. GASEOUS RADWASTE TREATMENT SYSTEM ......................................... 2 G. MEMBERS OF THE PUBLIC ......................................................................... 2 H. PROCESS CONTROL PROGRAM (PCP) ..................................................... 3 I. SITE BOUNDARY .......................................................................................... 3 J. UNRESTRICTED AREA ................................................................................ 3 K. VENTILATION EXHAUST TREATMENT SYSTEM ....................................... 3 Ill. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES ..................... 4 A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ..................................................................................... 4
- 1. Requirement ............................................................................ 4
- 2. Action ....................................................................................... 4
- 3. Surveillance Requirements .................................................... 4
- 4. Bases .*.......................*............................................................. 5 B. GASEOUS EFFLUENTS DOSE RATE ........................................................ 10
- 1. Requirement .......................................................................... 10
- 2. Action ..................................................................................... 10
- 3. Surveillance Requirements .....................*............................ 10
- 4. Bases ..................................................................................... 11 C. NOBLE GASES DOSE ................................................................................ 12
- 1. Requirement .......................................................................... 12
- 2. Action ..................................................................................... 12
- 3. Surveillance Requirements .................................................. 12
- 4. Bases ..................................................................................... 13
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page ii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table of Contents D. 1-131, 1-133, TRITIUM, AND PARTICULATES ....................................*....... 14
- 1. Requirement *......................................................................... 14
- 2. Action ..................................................................................... 14
- 3. Surveillance Requirements ............................................. '. .... 14
- 4. Bases ..................................................................................... 15 E. GASEOUS WASTE TREATMENT SYSTEM .........................................*..... 19
.1. Requirement .............................................*............................ 19
- 2. Action ..........................................................................*.......... 19
- 3. Surveillance Requirements .................................................. 19
- 4. Bases ............ ,........*......................*........................................ 20 F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 20
- 1. Requirement .......................................................................... 20
- 2. Action ........................................................................*............ 21
- 3. Surveillance Requirements .................................................. 21
- 4. Bases ..................................................................................... 21 G. LIQUID EFFLUENTS CONCENTRATION ................................................... 26
- 1. Requirement ......*................................................................... 26
- 2. Action ...................................................................................... 26
- 3. Surveillance Requirements .................................................. 26
- 4. Bases ..................................................................................... 27 H. LIQUID EFFLUENT DOSE .......................................................................... 30
- 1. Requirement .......................................................................... 30
- 2. Action ................*.................................................................... 30
- 3. Surveillance Requirements ..............................................*... 30
- 4. Bases .....*............................................................................... 31 I. TOTAL DOSE ..............................*............................................................... 32
- 1. Requirement .......................................................................... 32
- 2. Action ..................................................................................... 32
- 3. Surveillance Requirements .................................*................ 33
- 4. Bases ..................................................................................... 34
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page iii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table of Contents J. RADIOLOGICAL ENVIRONMENTAL MONITORING ................................. 35
- 1. Requirement .......................................................................... 35
- 2. Action ..................................................................................... 35
- 3. Surveillance Requirements .................................................. 36
- 4. Bases ..................................................................................... 37 K. SIRW OR TEMPORARY LIQUID STORAGE TANK ................................... 52
- 1. Requirement ................................................................,....... ,. 52
- 2. Action ..................................................................................... 52
- 3. Surveillance Requirement .................................................... 52
- 4. Bases ................................................................*.................... 53 L. SURVEILLANCE REQUIREMENT TIME INTERVALS ............................... 53
- 1. Requirement .......................................................................... 53
- 2. Action ............................................................*......................... 53
- 3. Surveillance Requirements .................................................. 54
- 4. Bases ..................................................................................... 54 M. SEALED SOURCE CONTAMINATION ....... ;............................................... 54
- 1. Requirement .......................................................................... 54
- 2. Action ..................................................................................... 54
- 3. Surveillance Requirements .................................................. 55
- 4. Bases ..................................................................................... 55 IV. REPORTING REQUIREMENTS .................................................................................. 56 A. RADIOLOGICAL EFFLUENT RELEASE REPORT .................................... 56 B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ................... 57 C. NONROUTINE REPORTS ........................................................................... 57 V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS ............................................................................................. 59 A. LICENSEE MODIFICATIONS ...................................................................... 59 B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION ............. 60 VI. ONSITE GROUND WATER MONITORING ................................................................. 61
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page iv TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table of Contents TABLES A-1 Radioactive Gaseous Effluent Monitoring Instrumentation A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 8-1 Radioactive Gaseous Waste Sampling and Analysis Program C-1 Radioactive Liquid Effluent Monitoring Instrumentation C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements D-1 Radioactive Liquid Waste Sampling and Analysis Program E-1 Radiological Environmental Monitoring Program E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples E-3 Detection Capabilities for Environmental Sample Analysis E-4 Radiological Environmental Monitoring Program Locations F-1 Environmental Radiological Monitoring Program Summary
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 1of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) I. INTRODUCTION The NRC, through 10CFR50.36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01, dated January 31, 1989, allowed relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 85, November 9, 1984). The relocated procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program, and associated procectural reporting requirements follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specification to satisfy the regulatory requirements of 10CFR50.36a. The Technical Specifications programmatic controls include requirements for the establishment, implementation, maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well as record retention and reporting requirements. II. DEFINITIONS A. CHANNEL CALIBRATION
- a Channel Calibration shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Function Test.
The Channel Calibration may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. B. 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 instrumentation channels measuring the same parameter.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 2 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) C. CHANNEL FUNCTIONAL TEST
- a Channel Functional Test shall be:
- 1. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.
- 2. Bistable channels - the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functions.
D. SOURCE CHECK
- a source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
E. OFFSITE DOSE CALCULATION MANUAL
- (per Plant Technical Specifications) - the Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain: 1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by the Technical Specifications, and 2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by the Technical Specifications.
F. GASEOUS RADWASTE TREATMENT SYSTEM
- any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
G. MEMBERS OF THE PUBLIC
- all persons who are not occupationally associated with the Plant. This category does not include employees of the utility, its contractors, or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 3 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) H. PROCESS CONTROL PROGRAM (PCP)
- shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Part 20, 10CFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.
I. SITE BOUNDARY
- that line beyond which the land is neither owned nor otherwise controlled by the licensee.
J. UNRESTRICTED AREA
- any area at or beyond the Site Boundary access 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.
K. VENTILATION EXHAUST TREATMENT SYSTEM
- any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 4 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Ill. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
- 1. Requirement The radioactive gaseous effluent monitoring instrumentation channels shown in Table A-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of requirement 111.B.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
- 2. Action
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above requirement, without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Table A-1. Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in, the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- 3. Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check, Source Check, Channel Calibration, and Channel Functional Test operations at the frequencies shown in Table A-2.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 5 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR 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 10CFR Part 50.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 6 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) TableA-1 Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Operable Applicability Action Channels
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor (RIA 1113) Providing Alarm and Automatic Termination of Release (1) At All Times 1
- 2. CONDENSER EVACUATION SYSTEM (RIA 0631)
- a. Noble Gas Activity Monitor (1) Above 210°F 3 Modes 1, 2, 3, 4 Above 210°F
- b. Evacuation Flow Indicator (Fl-0631 or Fl-0632) (1 )*** Modes 1, 2, 3, 4
- 3. STACK GAS EFFLUENT SYSTEM
- a. Noble Gas Activity Monitor (RIA 2326)* (1) At All Times 3
- b. Iodine/Particulate/Sampler/Monitor {RIA 2325) (1) At All Times 6
- c. Sampler Flow Rate Monitor (FE-2346) (1) At All Times 2
- d. Hi Range Noble Gas (RIA 2327)* (1) Above 210°F 4 Modes 1, 2, 3, 4
- 4. STEAM GENERATOR SLOWDOWN VENT SYSTEM
- a. *Noble Gas Activity Monitor (RIA 2320) (1) Above 210°F 3 Modes 1, 2, 3, 4
- 5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE
- a. Gross Gamma Activity Monitor* 1 per Main Above 325°F 4 (RIA 2323 and 2324) Steam Line Modes 1, 2, 3
- 6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM
- a. Noble Gas Activity Monitor ** 1 per Room Above 210°F 5 (RIA 1810 and 1811) Modes 1, 2, 3, 4
- Setpomts for these instruments are exempted from 111.B.1 limits, but are governed by Emergency Implementing Procedures or Operating procedures.
- Setpoints for these instruments are exempted from 111.B.1 limits, but are governed by Technical Specifications SR 3.3.1 Q.3.
- Documentation of operability not required.
- Setpoints for these instruments are exempted from 111.B.1 limits, but are governed by Technical Specifications SR 3.3.1 Q.3.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 7 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table A-1 (Cont'd) TABLE NOTATION -ACTION STATEMENTS ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels requirements, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve line up; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 2 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 24 hours. ACTION 3 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. ACTION4 - With the number of operable channels less than required by the Minimum Operable Channels requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), Within 72 hours, and:
- a. Either restore the inoperable channel(s) to operable status within 7 days of the event, or
- b. Prepare and submit a Special Report to the NRC within 30 days following the event outlining the actions taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.
ACTION 5 - If either channel fails low or is otherwise inoperable, the ventilation dampers associated with that channel shall be closed immediately and action shall be taken to have the affected channel repaired. The dampers associated with the channel shall not be opened until the affected channel has been declared operable. (Reference Technical Specifications LCO 3.3.10.) ACTION 6 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table B-1.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 8 of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Modes in Which Channel Source Channel Instrument Functional Surveillance Check Check Calibration Required Test
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor-Providing Alarm and 0(4) p R(3) Q(1 )(2)
- Automatic Termination of Release *
- 2. CONDENSER EVACUATION SYSTEM
- a. Noble Gas Activity Monitor D M R(3) Q(2) Above 210°F
- b. Evacuation Flow Indicator (Fl-0632) or *** *** *** *** Modes 1, 2, 3, 4
- c. Evacuation Flow Indicator (Fl-0631) *** *** *** ***
- 3. STACK GAS EFFLUENT SYSTEM
- a. Noble Gas Activity Monitor D M R(3) Q(2) *
- b. Iodine Particulate Sampler/Monitor w M** R(3)** NA
- C. Sampler Flow Rate Monitor D NA R NA *
- d. Hi Range Noble Gas D M R(3) Q(2) Above 210°F Modes 1, 2, 3, 4
- 4. STEAM GENERATOR SLOWDOWN VENT SYSTEM Above 210°F
- a. Noble Gas Activity Monitor D M R(3) Q(2) Modes 1, 2, 3, 4
- 5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE Above 325°F D M R(3) Q(2) Modes 1, 2, 3
- a. Gross Gamma Activitv Monitor
- 6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION. SYSTEM
- a. Noble Gas Activity Monitor 12 hours 31 days 18 months (3) 31 days(1)(2) Above 210°F (Technical Specifications SR 3.3.1 O and Modes 1, 2, 3, 4 SR 3.7.13.1)
- At all times other than when the hne 1s valved out and locked.
- Sampler not applicable
- This type of Flowmeter doesn't have any surveillance requirements.
- Sampler not applicable
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 9 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table A-2 (Cont'd) Table Notation (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint. (2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists.
- a. Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3.d, Hi Range Noble Gas).
- b. Circuit failure.
(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.
- b. For subsequent Channel Calibration, sources that have been related to the (1) calibration may be used.
(4) Channel Check shall be made at least once per 24 hours on days on which continuous or batch releases are made. TABLE FREQUENCY NOTATION S At least once per 12 hours D At least once per 24 hours M At least once per 31 days P Prior to radioactive batch release Q At least_ once per 92 days R At least once per 18 months W At least once per week
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 10 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 8. GASEOUS EFFLUENTS DOSE RATE
- 1. Requirement The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For lodine-131, for lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
- 2. Action With the dose rate(s) averaged over a period of one hour exceeding the above limits, without delay, restore the release rate to within the above limit(s).
- 3. Surveillance Requirements
- a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of 8.1.a in accordance with the methodology and parameters in the ODCM.
- b. The dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits of 8.1.b in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 8-1.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CA LC ULATION MANUAL Appendix A Revision 18 Page 11 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This is provided to ensure that the dose at any time at and beyond the Site Boundary from gaseous effluents from all units on the site will be within 10 times the annual dose limits of 10CFR Part 20 to Unrestricted Areas. The annual dose limits are the doses associated with the concentrations of 10 times 10CFR Part 20, Appendix B, Table 2, Column 1. These restrictions provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either within or outside the Site Boundary, to annual exposure greater than design objectives of 10CFR 50, Appendix I, Section 11.B.1. For Members of the Public who may at times be within the Site Boundary, the occupancy of the Member of the Public will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the Site Boundary. Examples of calculations for such Members of the Public, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rate above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mrems/yr to the total body.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 12 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) C. NOBLE GASES DOSE
- 1. Requirement The air dose due to noble gases released in gaseous effluents to areas at and beyond the Site Boundary (see Figure 2-1) 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.
- 2. Action With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRG within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- 3. Surveillance Requirements Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 13 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to implement the requirements of Sections 11.B, Ill.A, and IV.A of Appendix I, 10CFR Part 50. The limiting Condition for Operation implements the guides set forth in Section 11.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 to assure that the releases of radioactive material in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the 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 10CFR 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 ODCM equations provided for determining the air doses at and beyond the Site Boundary are based upon the historical average atmospheric conditions.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 14 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) D. 1-131, 1-133, TRITIUM, AND PARTICULATES
- 1. Requirement The dose to a Member of the Public from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
- 2. Action With the calculated dose from the release of lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit and define(s) the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- 3. Surveillance Requirements Cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 15 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to implement the requirements of Sections 11.C, Ill.A, and IV.A of Appendix I, 10CFR Part 50. The requirements are the guides set forth in Section 11.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 to assure that the releases of radioactive materials in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section II.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials 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 10CFR 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. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate requirements for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 16 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table B-1 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Type Sampling Minimum Type of Lower Limit Frequency Analysis Activity Analysis Detection (LLD)a Frequency (µCi/ml) A. Waste Gas Storage Tank p Each Tank p 4 Grab Sample Each Tank Principal Gamma Emittersb 1 x 10 B. Containment PURGE p Each PURGE p 4 Grab Sample Each PURGE Principal Gamma Emittersb 1 x 10 C. Stack Gas Effluent \,J\f*e Continuousc Charcoal 1-131,1-133 1 x 10*12 Sample
\,/\f*e Continuousc Particulate Principal Gamma Emittersb 1x10*11 Sample Q
Composite Sr-89, Sr-90, and 11 Continuousc 1 x 10" Particulate Gross Alpha Sample Noble Gas Noble Gases 1E-06 Continuousc Monitor Gross Beta or Gamma
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 17 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Gaseous Release Type Sampling Minimum Type of Lower Limit Frequency Analysis Activity Analysis Detection (LLD)a Frequency (µCi/ml) D. Condenser Evacuation System Continuous Noble Gas Noble Gases 1 x 1o-6 Monitor wt Grab w Principal Gamma Emittersb 1 x 10 4
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 18 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table 8-1 (Cont'd) Table Notation a The LLD is defined, in Table E-3, note C. 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 gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report. c The ratio of the sample flow rate to the sample stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with requirements 111.B.1, 111.C.1, and 111.D.1. d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing or after removal from sampler. e With channels operable on iodine monitor RIA 2325 less than required per 111.A.1, sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, start-up or Thermal Power change exceeding 15 percent of Rated Thermal Power in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if, 1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3, and 2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. f Obtain and analyze a gas sample weekly for noble gas quantification.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 19 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) E. GASEOUS WASTE TREATMENT SYSTEM
- 1. Requirement When gaseous waste exceeds a Xe-133 concentration of 1E-05 µCi/cc, the Waste Gas Decay Tank System shall be used to reduce radioactive gaseous effluents by holding gaseous waste collected by the system for a minimum of 15 days.
- 2. Action
- a. If a waste gas decay tank is required to be released with less than 15 days holdup time, the system waste gas tank contents shall be evaluated and the waste gas decay tank with the lowest dose consequence shall be released.
- b. Gaseous waste may be discharged directly from the waste gas surge tank through a high-efficiency filter or from a waste gas decay tank with less than 15 days of holdup directly to the stack for a period not to exceed 7 days if the holdup system equipment is not available and the release rates meet requirements 111.B, C, and D.
- 3. Surveillance Requirements Not Applicable.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 20 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable" by meeting the design objectives given in Section 11.D of Appendix I to 10CFR50.
It is expected that releases of radioactive materials in effluents shall be kept at small fractions of the limits specified in 20.1302 of 10CFR20. At the same time the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in 111.B, C, and D. F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
- 1. Requirement The radioactive liquid effluent monitoring instrumentation channels shown in Table C-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of 111.G are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 21of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 2. Action
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels Operable, take the Action shown in Table C-1. Exert best efforts to return the instruments to Operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- 3. Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated Operable by performance of the Channel Check, Source Check, Channel Calibration, and Channel Functional Test operations at the frequencies shown in Table C-2.
- 4. Bases The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding 10 times the limits of 10CFR 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 10CFR Part 50.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 22 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-1 Radioactive Liquid Effluent Monitoring Instrumentation Minimum Instrument Operable Applicability Action Channels
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line (RIA 1049) (1) For Effluent Releases 1
- b. Steam Generator Slowdown Effluent Line (1) For Effluent Releases 2 (RIA 0707)
- 2. GROSS BETA OR GAMMA RADIOACTIVE MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent Line (RIA 0833) (1) For Effluent Releases 3
- b. Turbine Building (Floor Drains) Sumps Effluent (1) For Effluent Releases 3 Line (RIA 5211)
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line (FIC 1051 or (1) For Effluent Releases 4 1050)
- 4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip Setpoints are not applicable)
- a. Turbine Building Sumps Effluent Line (1) For Effluent Releases 3
- b. Service Water System Effluent (1) For Effluent Releases 3
- c. Steam Generator Slowdown Effluent (1) For Effluent Releases 3
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 23 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-1 (Cont'd) TABLE NOTATION ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with requirements and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 2- With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table D-1 for principle gamma emitters and 1-131 at least once per 12 hours. The Steam Generator blowdown monitor is normally used in a clean up closed NOTE: loop system instead of as an effluent monitor. The action statement only applies when the monitor is used as an effluent monitor. ACTION 3- With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided that, at least once per 24 hours, grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table D-1 for principle gamma emitters and 1-131. ACTION 4- With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves or tank levels may be used to estimate flow.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 24 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Channel Instrument Functional Check Check Calibration Test
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line (RIA 1049) p p R(3) Q(1)(2)
- b. Steam Generator Slowdown Effluent Line (RIA 0707) D M R(3) Q(1)(2)
- 2. GROSS GAMMA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Service Water System Effluent Line (RIA 0833) D M R(3) Q(2)
- b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211) D M R(3) Q(2)
- 3. FLOW RATE MEASUREMENT DEVICES (5)
- a. Liquid Radwaste Effluent Line (FIC 1051 or 1050) 0(4) NA R NA
- 4. TURBINE SUMP EFFLUENT COMPOSITER 0(4) NA NA NA
- 5. SERVICE WATER SYSTEM EFFLUENT COMPOSITE SAMPLER 0(4) NA NA NA
- 6. STEAM GENERATOR SLOWDOWN EFFLUENT COMPOSITER 0(4) NA NA NA
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 25 of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table C-2 (Cont'd) TABLE NOTATION (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint. (2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists:
- a. Instrument indicates measured levels above the alarm setpoint.
- b. Circuit failure.
(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.
- b. For subsequent Channel Calibration, sources that have been related to the (a) calibration may be used.
(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check shall be made at least once per 24 hours on days on which continuous or batch releases are made. (5) Turbine Sump Discharge Flow Meter FQl-5210 was calibrated at factory and doesn't require recalibration. TABLE FREQUENCY NOTATION D At least once per 24 hours Q At least once per 92 days M At least once per 31 days R At least once per 18 months p Prior to radioactive batch release w At least once per week
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 26 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) G. LIQUID EFFLUENTS CONCENTRATION
- 1. Requirement The concentration of radioactive material released in liquid effluents to Unrestricted Areas shall be limited to 10 times the concentrations specified in 10CFR Part 20, Appendix 8, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/ml total activity.
- 2. Action With the concentration of radioactive material released in liquid effluents to Unrestricted Areas exceeding the above limits, without delay, restore the concentration to within the above limits.
- 3. Surveillance Requirements
- a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table D-1.
- b. The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of G.1 above.
PALISADES NUCLEAR PLANT ODOM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 27 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to Unrestricted Areas will be less than 10 times the concentration levels specified in 10CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in Unrestricted Areas will result in exposures within the Section II.A design objectives of Appendix I, 10CFR Part 50, to a Member of the Public. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and 10 times the effluent concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination*_ Application to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 28 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table D-1 Radioactive Liquid Waste Sampling and Analysis Program Liquid Release Type Sampling Minimum Analysis Type of Activity Analysis Lower Limit Frequency Frequency Detection (LLD)a (µCi/ml) A. Batch Waste Release Tanksu p p Principal Gamma Emittersc 5x10"7 Each Batch Each Batch 1-131 1 x 10"6 p M Dissolved and Entrained Gases 5 1x10" One Batch/M (Gamma Emitters) p M H-3 1 x 10-5 Each Batch Composited Gross Alpha 1x10"7 p Q Sr-89, Sr-90 5 x 10"8 Each Batch Composited Fe-55, Ni-63 1x10"6 B. Continuous Releasese Continuous' w Principal Gamma Emittersc 5x10"7 1 6 (Turbine Sump, Steam Generator Composite 1-131 1x10" Slowdown, and Service Water) M M Dissolved and Entrained Gases Grab Sample (Gamma Emitters) 1 x 10"5 Continuous' M H-3 1 x 10"5 1 Composite Gross Alpha 1x10*7 Continuous' Q Sr-89, Sr-90 5 x 10" 8 Composite1 Frequency Notation P Prior to batch release M Calendar month Q Calendar quarter W Calendar week
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 29 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table D-1 (Cont'd) TABLE NOTATION a The LLD is defined, in Table E-3, Note C. b A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. c The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144*. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.
- LLD - 5E-06 because of low gamma yields.
d A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. e A continuous release is the discharge of liquid wastes of a nondiscrete volume; eg, from a volume of a system that has an input flow during the continuous release. f To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in a series of aliquots of constant volume collected at regular time intervals and combined to form a single sample. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 30 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) H. LIQUID EFFLUENT DOSE
- 1. Requirement The dose or dose commitment to a Member of the Public from radioactive materials in liquid effluents released from each reactor unit to Unrestricted Areas shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
- 2. Action With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include the results of radiological analyses of the drinking water source.
- 3. Surveillance Requirements 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 the ODCM at least once every 31 days.
- PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 31of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix I, 10CFR 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 to Unrestricted Areas will be kept "as low as is reasonably achievable." Also, for freshwater sites with drinking water supplies that 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 40CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials 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 10CFR 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 32 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) I. TOTAL DOSE
- 1. Requirement The annual (calendar year) dose or dose commitment to any Member of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
- 2. Action With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of 111.C.1.a, 111.C.1.b, 111.D.1.a, 111.D.1.b, 111.H.1.a, or 111.H.1.b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of 111.1.1 have been exceeded. If such is the case, prepare and submit to the NRC within 30 days a Special Report 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 10CFR Part 20.2203, 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 concentrations of radioactive material involved and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR Part 190. Submittal of the report is considered a timely request and a variance is granted until staff action on the request is complete.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 33 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 750~0)
- 3. Surveillance Requirements
- a. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with 111.C.1, 111.D.1, and 111.H.1 and in accordance with the methodology and parameters in the ODCM.
- b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Action 1.2 above.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 34 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement is provided to meet the dose limitations of 40CFR Part 190 that have been incorporated into 10CFR Part 20 by 46 FR 18525. It also requires the preparation and submittal of a Special Report whenever the calculated doses from Plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except for thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a Member of the Public will exceed the dose limits of 40CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a Member of the Public to within the 40CFR Part 190 limits. For the 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 40CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR Part 190 have not already been corrected), in accordance with the provisions of 40CFR Part 190.11 and 10CFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10CFR 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 35 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) J. RADIOLOGICAL ENVIRONMENTAL MONITORING
- 1. Requirement The radiological environmental monitoring program shall be conducted as specified in Table E-1.
- 2. Action
- a. With the radiological environmental monitoring program not being conducted as specified in Table E... 1, prepare and submit to the NRG, in the Annual Radiological Environmental Operating Report a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity as the result of Plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table E-2 when averaged over any calendar quarter, prepare and submit to the NRG within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents. When more than one of the radionuclides in Table E-2 are detected in the sampling medium, this report shall be submitted if:
Concentration (1) + Concentration (2) + .... ~ 1.0 Reporting Level (1) Reporting Level (2) When radionuclides other than those in Table E-2 are detected and are the result of Plant effluents, this report shall be submitted if the potential annual dose to a Member of the Public is equal to or greater than the calendar year limits of 111.C.1, 111.D.1, and 111.H.1. 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.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 36 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table E-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radiological Environmental Report.
- 3. Surveillance Requirements
- a. The radiological environmental monitoring samples shall be collected pursuant to Table E-1 and shall be analyzed pursuant to the requirements of Table E-1 and the detection capabilities required by Table E-3.
- b. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 9 overland meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 tt2) producing broad leaf vegetation.
- c. The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report and shall be included in a revision of the ODCM for use in the following calendar year.
- d. Analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program that has been approved by the NRC.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 37 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- e. A summary of the results obtained as part of the above required lnterlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.
- f. The environmental air samplers shall be operationally checked monthly and airflow verified annually.
- 4. Bases
- a. Monitoring Program The radiological environmental monitoring program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of Members of the Public resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR Part 50 and 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 the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table E-3 are considered optimum for routine environmental measurements in industrial laboratories. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40, 586-92 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-15 (June 1975).
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CA LC ULATION MANUAL Appendix A Revision 18 Page 38 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- b. Land Use Census:
This requirement is provided to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the radiological environmental monitoring program are made if required by results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR Part 50. Restricting the census to gardens of greater than 50 m2 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 (16 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (ie, similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2 .
- c. lnterlaboratory Comparison Program:
The requirement for participation in an approved lnterlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10CFR Part 50.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 39 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-1 Radiological Environmental Monitoring Program Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locations 3 Collection Frequency of Analysis
- 1. DIRECT RADIATIONb 23 routine monitoring stations either with two or Quarterly Gamma dose quarterly more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
One on site TLD in the vicinity of the Plant. An inner ring of stations, one in each overland meteorological sector (9) in the general area of the Site Boundary and one additional location near the State Park camping area in the NE sector. An outer ring of stations, one in each overland meteorological sector (9) within the 12 km range from the site. The balance of the stations (3) to be placed to serve as control stations.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 40 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis
- 2. AIRBORNE Radioiodine and Samples from 5 locations. Continuous sample Radioiodine Canister:
Particulates operation with sample 1-131 analysis weekly for 3 samples from within 6 km of the Site Boundary collection weekly or more each filter change. in different sectors (2.5 km-SSW, 5.8 km-ESE frequently if required by and .96 km-NE). dust loading. Particulate Sam12ler: Gross beta radioactivity 1 sample from the vicinity of a community having analysis following filter the highest calculated annual average ground changed. Gamma isotopice level D/Q (Covert-6.2 km-SE). analysis on quarterly composite 1 sample from a control location in the least prevalent wind directionc (Grand Rapids 82 km-NE)h.
- 3. WATERBORNE
- a. Lake (surface) Plant lake water inlet. Composite sample over Gamma isotopice and tritium 1-month periodt. analyses monthly.
- b. Lake (drinking) 1 sample of South Haven drinking water supply. Composite sample over Gamma isotopice, gross 1-month periodt. beta, and tritium analyses
'- monthly.
1 sample from a control location (Ludington Composite sample over Gamma isotopice, gross Pumped Storage 201 km N) 1-month periodt. beta, and tritium analyses monthly.
- c. Well (drinking) 1 grab sample per month when Palisades Park 1 grab sample per month Gamma isotopice and tritium community drinking water well is in operation when operational analyses monthly when (Park is seasonal in operations and is only open Park is operational.
for the summer months)
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 41 of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis
- d. Sediment from 1 sample from between north boundary and Van Semiannually Gamma isotopice analysis shoreline Buren State Park beach, approximately Yz mile semiannually.
north of the Plant discharge.
- 4. INGESTION 0
- a. Milk Samples from milking animals in 3 locations Monthly Gamma isotopic and 1-131 between 5-8 km distance. analyses monthly.
0 1 sample from milking animals at a control location, Monthly Gamma isotopic and 1-131 15-30 km distance. analyses monthly. 0
- b. Broad leaf Samples of 3 different kinds of broad leaf vegetation Monthly during growing Gamma isotopic and 1-131 vegetation grown nearest each of two different offsite locations season analyses of highest predicted annual average ground level D/Q if milk sample is not performed. (SE or SSE sectors near site.)
0 1 sample of each of the similar broad leaf vegetation Monthly during growing Gamma isotopic and 1-131 grown 15-30 km distance in the least prevalent wind season analyses direction if milk sampling is not performed. (NNE or NE sectors.) 0
- c. Fish Sample 2 species of commercially and/or Sample in season or Gamma isotopic analysis recreationally important species in vicinity of Plant semiannually if they are discharge area. 1 sample of same species in areas not seasonal.
not influenced by Plant discharge.
- d. Food Products 1 sample each of two principal fruit crops At time of harvest9 0 Gamma isotopic and 1-131 (blueberries and apples). analyses.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page42 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-1 (Cont'd) Table Notation a Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. b One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors or phosphor readout zones in a packet are considered as two or more dosimeters. c 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 that provide valid background data may be substituted. d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. e Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. f A composite sample is one in which the .quantity (aliquot) of liquid samples is proportional to the quantity of liquid discharged and in which the method of sampling employed results in a specimen that is representative of the liquid released {continuous composites or daily grab composites which meet this criteria are acceptable). g If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. h The Control Air sample results from Cook Nuclear Plant, except Coloma, may be used as a backup of the Grand Rapids control.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 43 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 {TAC NO 75060) Table E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Reporting Levels Water Airborne Particulates Fish Milk Food Products Analysis 3 (pCi/I) or Gases (pCi/m ) (pCi/kg, Wet) (pCi/I) (pCi/kg, Wet) H-3 20,000* Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
- For drinking water samples. This is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 44 of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)bc Water Airborne Particulates Fish Milk Food Products Sediment Analysis 3 (pCi/I) or Gases (pCi/m ) (pCi/kg, Wet) (pCi/I) (pCi/kg, Wet) (pCi/kg, Dry) Gross Beta 4 0.01 H-3 2,000* Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1d 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15
- If no drinking water pathway exists, a value of 3,000 pCi/I may be used.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 45 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 (Cont'd) TABLE NOTATION a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. c The LLD 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% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD= 4.66 x Sb Ex V x 2.22 x Y x Exp(-A-M) Where: LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume. sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute. E is the counting efficiency, as counts per disintegration. V is the sample size in units of mass or volume. 2.22 is the number of disintegrations per minute per picocurie. Y is the fractional radiochemical yield, when applicable. A is the radioactive decay constant for the particular radionuclide. LH for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting. Typical values of E, V, Y, and Lit should be used in the calculation.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 46 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-3 (Cont'd) Table Notation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 47 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table E-4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS Seven Mile Map
*.. ' *{~_ 'J. ***. ' ~
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 48 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS Four Mile Map
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 49 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER89-01 (TAC NO 75060) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS TLDs Location Coordinates Distance (miles) DeQrees Sector Stack N 42 19 22.5 w 86 18 50.8 1 N 42 19 20.5 0.213 100.36 E w 86 18 36.1 Inner Ring 13 N 42 19 47.2 0.530 26.56 NNE w 86 18 34.1 8 N 42 19 46.8 0.602 39.19 NE w 861824.0 14 N 42 19 41.1 0.551 49.64 NE w 8618 21.2 15 N 42 19 41.7 0.834 63.76 ENE w 86 17 58.1 16 N 42 19 28.0 0.804 82.45 E w 86 17 54.6 17 N 42 19 10.5 0.572 113.74 ESE w 86 18 13.9 18 N 42 19 4.2 0.469 138.49 SE w 86 18 28.9 19 N42190.9 0.443 159.19 SSE w 86 18 39.7 20 N 42 19 1.1 0.412 176.05 s w 86 18 48.8 21 N42193.4 0.382 196.40 SSW w 86 18 58.4 Outer Ring - Displayed on 7 mile map 7 N 42 22 40.8 4.115 22.35 NNE w 86 17 0.4 6 N 42 22 30.6 5.314 47.18 NE w 86 14 15.9 23 N 42 20 44.6 3.189 60.37 ENE w 8615 35.4 24 N 42 19 59.5 6.021 83.19 E w 86 11 49.4 5 N 42 18 27.6 3.475 107.63 ESE w 8614 57.5 4 N 42 17 10.8 3.668 133.54 SE w 86 15 43.5 3 N 42 14 37.9 5.684 163.92 SSE w 86 16 60.0
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 50 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS TLDs Location Coordinates Distance (miles) Degrees Sector 2 N 42 14 33.4 S.560 183.7S s W861916.4 9 N 4218 1.73 1.670 201.86 SSW W8619 34.6 Control TLDs 10 N 42 53 16.7 S0.746 39.49 NE was 40 3S.9 11 N 42 1S 24.S 39.472 96.39 E was 32 49.3 12 N 41 S6 54.3 27.971 1S7.61 SSE W86 6 24.S TLD 10 is located within the Consumers Energy Grand Rapids service facility attached to a pole located adjacent to the south fence. TLD 11 is located within Consumers Energy Kalamazoo service facility attached to a pole in the far NE corner of the facility, past the employee parking lot. TLD 12 is located approximately 30 yards from the road, NE and next to a private residence located at S8399 Wilbur Road, Dowagiac, Ml. ' A"Ir SampleI Sta1ons f Location Coordinates Distance (miles) Degrees Sector AB (State Park) N 42 19 46.8 O.S95 38.34 NE w 86 18 24.8 A9 (Township N42184.6 1.S2S 191.38 SSW Park) w 86 19 12.0 A4 (Covert) N421712.1 3.882 130.12 SE w 861S 21.7 AS (Rood) N 42 18 30.5 3.590 106.12 ESE W861447.8 A10 (Grand N 42 S3 16.7 S0.765 39.S2 NE Rapids) was 40 33.8 Air Sample Station 10 is located within Consumers Energy Grand Rapids service facility, south side, next to a small service building and due east of TLD 10. Control fish and water samples are normally obtained from the Consumers Energy Pump Storage Facility located in Ludington, Ml or another location not influenced by Palisades plant discharges.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 51of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Palisade Park Wells Location Coordinates Distance (miles) Degrees Sector Community Well N 42 18 47.5 0.729 203.63 SSW w 86 19 11.4 Commercial Well N 42 18 48.5 .652 175.06 s w 86 18 46.8 The Community Well services the community residents with well water to their homes; the Commercial Well services the community gardens and drinking fountains on the east side of the property.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 52 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) K. SIRW OR TEMPORARY LIQUID STORAGE TANK
- 1. Requirement The concentration of radioactive material (excluding tritium and noble gases) contained in the SIRW tank or any unprotected outside temporary tank* shall be limited such that the mixture radionuclides do not exceed 1,000 times the effluent concentration (EC) as listed in 10CFR Part 20, Appendix B, Table 2, Column 2 .
.Qg + ~ ... + ~ = < 1000 ECa ECb ECi
- 2. Action With the quantity of radioactive material in any of the above listed tanks exceeding the above concentration, immediately suspend all additions of radioactive material to the tank, within 48 hours reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radiological Effluent Release Report.
- 3. Surveillance Requirement The concentration of radioactive material contained in each of the above listed tanks 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 materials are being added to the tank.
A calculational methodology performed prior to the material being transferred may be used to show compliance with the requirement of this section if a representative sample cannot be obtained at least once per seven days. A representative sample of the radioactive material to be added to the SIRW or Temporary Liquid Storage Tank shall be analyzed and a calculation performed to show compliance with the 1000 EC limit.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 53 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 4. Bases This requirement will provide reasonable assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10CFR Part 20, Appendix B; Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an Unrestricted Area.
(The dilution between Palisades and the South Haven drinking water supply has been established as 1000.)
*Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
NOTE: The limit for the SIRW Tank may be exceeded for operational flexibility if the conditions of this section are met. L. SURVEILLANCE REQUIREMENT TIME INTERVALS
- 1. Requirement 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.
- 2. Action Failure to perform a Surveillance Requirement within the allowed surveillance interval shall constitute noncompliance with the operability requirements. The time limits of the action requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The action requirements may be delayed for up to 24 hours to permit the completion of the surveillance when the allowed outage time limits of the action requirements are less than 24 hours.
Surveillance Requirements do not have to be performed on inoperable equipment.
PALISADES NUCLEAR PLANT ODCM CFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 54 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 3. Surveillance Requirements The applicable surveillance interval frequencies are specified in Tables A-2 and C-2. The applicable sampling and/or analysis frequencies are specified in Tables A-1, B-1, C-1, D-1, and E-1.
Extendable surveillance requirements are limited to Channel Checks, Source Checks, Channel Calibrations, Channel Functional Checks, sampling frequencies and/or analysis frequencies.
- 4. Bases The maximum allowable extension for a surveillance interval *is consistent with the surveillance requirements specified in the Technical Specifications, Section 4.0. Until relocated in the ODCM, all of the effluent surveillances were subject to these same requirements.
M. SEALED SOURCE CONTAMINATION
- 1. Requirement Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.
- 2. Action
- a. With a sealed source having removable contamination in excess of 0.005 microcuries, immediately withdraw the sealed source from use and either:
(1) Decontaminate and repair the sealed source, or (2) Dispose of the sealed source in accordance with applicable regulations.
- b. A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 55 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 3. Surveillance Requirements
- a. Each category of sealed sources as described in the requirement with a half-life greater than 30 days (excluding Hydrogen-3), and in any other form than gas, shall be tested for leakage and/or contamination at intervals not to exceed 6 months.
- b. The test shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
- c. The test sample shall be taken from the sealed source or, in the case of permanently mounted sources, from the surfaces of the mounting device on which contamination would be expected to accumulate.
- d. The periodic leak test does not apply to sealed sources that are stored and not being used. These sources shall be tested prior to use or transfer to another licensee, unless tested within the previous 6 months. Sealed sources which ari continuously enclosed within a shielded mechanism (ie, sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
- e. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed in use.
- 4. Bases The requirement, actions, and surveillance requirements are the same as contained in the Technical Specifications 6.21 prior to relocation to the ODCM and will provide assurance that sealed sources are tested to demonstrate that source integrity is being maintained.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 56 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) IV. REPORTING REQUIREMENTS A. RADIOLOGICAL EFFLUENT RELEASE REPORT The Radioactive Effluent Release Report (RERR) shall be submitted in accordance with 10CFR 50.36a prior to May 1 of each year. The report shall include a summary of the quantities of liquid and gaseous effluents and solid waste released as outlined in Regulatory Guide 1.21, R1, Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants, with data summarized on a quarterly basis following the format of Appendix B, thereof. The following information shall also be included in the RERR:
- Assessment of the radiation doses due to the liquid and gaseous effluents released during the previous year
- Inoperable effluent radiation monitors that exceeded 30 continuous days; explain causes of inoperability and actions taken to prevent reoccurrence
- Evaluation to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation
- Unplanned releases of radioactive materials in gaseous or liquid effluents to unrestricted areas on a quarterly basis
- Any changes to this procedure made during the reporting period
- Groundwater monitoring results taken in support of the Groundwater Protection Initiative, but are not part of the REMP Solid radioactive waste data shall be reported as follows:
- Type of waste (example: spent resin, dry waste. Irradiated components)
- Volume in cubic meters, include estimated error
- Curie quantity per type of waste, include estimated error
- Principal radionuclides in each category
- Disposition of waste shipments and irradiated fuel shipments (identify number of shipments mode of transport and destination)
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 57 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in: (1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix 1 to 10CFR50. The Annual Radiological Environmental Operating Reports shall include summaries, interpretation and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the Plant operation on the environment. The reports shall also include the results of land use census pursuant to 111.J.3.c. The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results in the format of Table F-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, 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. The reports shall also include the following; a summary description of the radiological environmental monitoring program, including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by 111.J.3.c and results of the lnterlaboratory Comparison Program required by 111.J.3.e. C. NONROUTINE REPORTS A report shall be submitted to the NRC in the event that: 1) the Radiological Environmental Monitoring Programs are not substantially conducted as described in Section 111.J, or 2) an unusual or important event occurs from Plant operation that causes a significant environmental impact or affects a potential environmental impact. Reports shall be submitted within 30 days.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 58 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) Table F-1 Environmental Radiological Monitoring Program Summarv Name of Facility Docket No Location of Facility Reporting Period _ _ _ _ _ __ (County, State Type/Total Lower Limit All Indicator Medium or Pathway Control Locations Number of Number of of Locations Name Mean (~b Sampled Mean<!t REPORTABLE Analyses Detectiona Mean (~b Distance & Direction Range (Unit of Measure) Range OCCURRENCES Performed (LLD) Range Air Particulates Gross r.. 416 0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/104)- 1 (pCi/m 3 ) (200/312) 5 miles 340° (0.08-2.0) (0.05-1.40) y-Spec 32 (0.05-2.0) Cs-137 0.003 0.05 (4/24) Smithville 0.08 (2/4) <LLD 4 (0.03-0.13) 2.5 miles 160° (0.03-0.13) Ba-140 0.003 0.03 (2/24) Podunk 0.05 (2/4) 0.02 (1/8) 1 (0.01-0.08) 4 miles 270° (0.01-0.08) Sr-89 40 0.002 <LLD -- -- <LLD 0 Sr-90 40 0.0003 <LLD -- -- <LLD 0 Fish y-Spec 8 pCi/kg (dry weight) <LLD Cs-137 80 -- <LLD 90 (1/4) 0
<LLD Cs-134 80 -- <LLD <LLD 0 120 (3/4)
Co-60 80 (90-200) River Mile 35 See <LLD 0 Podunk River Column 4 a Nominal Lower Limit of Detection (LLD) as defined in table notation c.ofTable E-3. b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is indicated in parentheses (f). NOTE: The example data are provided for illustrative purposes only.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 59 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060) V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS A. LICENSEE MODIFICATIONS Licensee initiated major modifications to the radioactive liquid and gaseous waste systems.
- 1. Shall be reported to the NRC pursuant to 10CFR 50.59. The discussion of each modification shall contain:
- a. A summary of the evaluation that led to the determination that the modification could be made in accordance with 10CFR Part 50.59.
- b. A description of the equipment, components and processes involved, and the interfaces with other Plant systems.
- c. Documentation of the fact that the modification was reviewed and found acceptable by the PRC.
- 2. Shall become effective upon review and acceptance by the General Manager Plant Operations.
PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 60 of 61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
- 8. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION 1.
Purpose:
The purpose of this definition is to assure that this requirement will be satisfied under clearly identifiable circumstances, and with the objective that current radwaste system capabilities are not jeopardized.
- 2. Definition:
A major radwaste system modification is a modification which would remove (either by bypassing for greater than 7 days or physical removal) or replace with less efficient equipment, any components of the radwaste system:
- a. Letdown filters or demineralizers.
- b. Vacuum degassifier (not applicable when the reactor is in cold shutdown and depressurized).
- c. Miscellaneous or clean waste evaporators.
- d. The present waste gas compressor/decay tank system.
- e. Fuel Pool filters/demineralizers.
- f. Radwaste polishing demineralizers.
- g. Radwaste Solidification system.
Improvements or additions to improve efficiency will not be considered major modifications unless a complete substitution of equipment or systems is made with equipment of unrelated design. Examples would be: 1) replacement of mechanical degassifier with steam, jet degassifier, 2) replacement of waste gas system with cryogenic system, 3) replacement of asphalt solidification with cement system, and 4) change from deep bead resins to Powdex, etc.
- PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 18 Page 61of61 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)
VI. ONSITE GROUND WATER MONITORING Palisades installed 5 ground water monitoring wells in 2007 and added an additional 9 wells in 2008. These wells were installed in response to NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document. These wells are strategically placed within the Owner Controlled Area, both inside and outside the Protected Area to allow detection of radioactive contamination of ground water due to leaks or spills from plant systems.
ODCM Appendix B DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR 20.302 Revision 0 August 1, 1991 Approved KM Haas 8/20/91 MRN Manager - ~adiological Services Date TP Neal 8/1/91 RMC Administrator Date ML Grogan 8/14/91 Tech Review Date PF Bruce 9l-082d 8/14/91 Date Applicability Reviewed: ---'Tu...P.u.:Ne=aw....l_-=5~/~5/~9~3_ _ Gerald B. Slade 11/30/93 Pl ant General Manager .. Date Applicability Reviewed: ~ s-,/(ffe-
ODCK Appendix B Page 1 Request to Retain Soil in Accordance with 10CFR 20.302 Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose of contaminated soil in place as specified by 10CFR 20.302. The area known as the South Radwaste Area has been contaminated by numerous cooling tower overflows and contamination was redistributed by heavy rain showers. Although the majority of the radioactive material has been packed for waste shipment, a large volume of very low activity radioactive material remains. This volume of material would be very expensive to ship as waste. The specific area contaminated is noted as Area B on the attached survey grid map in reference 1. The entire area is fenced and is about 12,000 sq ft of soil exposed with the remainder buildings and asphalt. The inhalation pathway is for breathing suspended soil from this area. The radworker could receive 8.03E-04 mRem/50-year maximum organ (liver) dose and the infant could receive 3.16E-05 mRem/50-year maximum organ (liver) dose, both of which are insignificant. Direct dose to a radworker is less than 2E-03 mRem/hr. Occupancy in this area should not average more than 2 hours/week or 100 hours/year, which would result in a dose of <1 mRem/year. The radwaste activities which caused the contamination of the soil were completely relocated to a new east radwaste area. The South Building has been deconned and is being used for non-radwaste activities. Some fixed contamination is present in floor cracks and vaults. This has been documented for plant decommissioning. No further contamination will be added to the south area from the South Radwaste Building. In spite of this commitment, revocation of Michigan shipping privileges in November 1990 require the use of this area to store packaged low level radioactive waste (LLW). Use of this building is addressed in CPCo's letter to NRC Document_ Control Desk, April 24, 1991 which is entered as reference 6. This LLW, in the form of dry active waste (DAW) will be packaged in metal boxes and labeled, ready for future shipment to burial sites. The DAW metal shipping boxes will be stored off the floor to prevent water damage. The metal shipping boxes are strong, tight containers designed to prevent any leakage of radioactive material during transportation. Incidental water contact will not result in the spread of contamination. Radioactive waste will not be processed in the South Radwaste Building and the bullding will be maintained as a normally clean (radiologically) area. Rev 0 8-1-91
ODCH Appendix B Page 2 References (1) CPCo's letters, T.C. Bordine to NRC Document Control Desk, November 12, 1987 and January 25, 1988. (2) Memorandum from L.J. Cunningham, DREP to T.R. Quay, T.V. Vambach, "Request for Additional Information (RAI)", March 15, 1988, April 7, 1989, and January 12, 1990. * (3) CPCo's supplement to Reference (1), J.L. Kuemin to NRC Document Control Desk, June 27, 1988. (4) CPCo's supplement to References (1, 2), G.B. Slade to NRC Document Control Desk, August 31, 1990. (5) CPCo's letter, T.P. Neal to B. Holian, October 23, 1990. (Typo of 10/13/90 in original reference). (6) CPCo's letter, G.B. Slade to NRC Document Control Desk, April 24, 1991.
"Use of South Storage Building as an Interim Radi6active Yaste Storage Building".
(7) NRC Letter, Brian Holian to G.B. Slade, CPCo, June 7, 1991, "Approval and Conditions to Retain Soil in Place". Rev O 8-1-91
ODCM - APPENDIX B REFERENCE 1 consumers Power POWERING MICHlliAN'S l'IUIGllES5 General Offlc.. : 1945 Wen Pernell Roed, Jackson, Ml 49201 * (5171 788-0550 November 12, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH IOCFR20.302 The Code of Federal Regulations, Title IO, section 20.302 allows for approval of proposed procedures to dispose of licensed material in a manner not other-wise authorized in the regulations. Flooding of the South Radwaste Building has caused contamination of 4,173 cubic feet of soil with 2,992.6 µCi of N Cs-137 and 79.3 µCi of Co-60. The area is approximately 30 meters from Lake Michigan. Site hydrology (Attachment 2, FSAR 2.2) indicates most of the activity will ~!grate to Lake Michigan in a few years. In July, 1986 a two-fold evaluation began to identify and map the extent of the ground contamination in the flood plain. The initial findings and evaluation were provided to NRC and the Michigan Department of Public Health by internal letter dated September 26, 1986, to LHueter, NRC, Region III. Consumers Power Company requests authorization to dispose of this soil inplace as the costs of disposal at a burial ground is estimated at $270,000 while radiological consequences to the general public and site employees is very low. The activities in the contaminated soil were input as a single radio-active liquid release to Lake Michigan into the NRC LADTAP Code. The output indicated an estimated wholebody dose to the general public (50 mile radius population l.05E06) of I.69E-02 manRem or I.6E-OS millirem per person. The maximum estimated wholebody dose to an individual would be 5.13E-03 millirem and maximum organ dose (teenage liver) would be 8.67E-03 millirem. The maximum whole body dose rate was assumed to be at 18 inches from contaminated soil. The maximum whole body dose rate calculated using the Microshield Code was I.02E-02 mR/hr. Occupancy of this area is controlled by the Radiological Safety Department and secured by a locked fence. Average yearly occupancy is approximately 8 hours per week per individual for 4 to 5 individuals. *A radiation worker should not exceed an additional wholebody dose of 4.08 millirem/year. Flooding of the South Radwaste Building as a result of the cooling tower overflows is being addressed in two stages. "For the short term the cooling tower bypass valve is now electrically isolated during cooling tower opera-tion. Most previous flooding has been due to instrument failures that cause the valve to open during normal operation. In addition the South Radwaste Building has been decontaminated to eliminate ~r minimize contamination that TPN-HPOl-~01 Rev O 8-1-9"1
Nuclear Regulatory Commission 2 Palisades Plant 10CFR20.302 Request November 12, 1987 could be transported to the environment. A long term solution to remove radwaste activities from this area is being included in the Five-Year Plan. The activity released to the environment from a flooding release prior to 1986 was estimated and added to the liquid section of the Semi-Annual Radiological Effluent Release Report dated February 28, 1986. Following approval of this application, it is proposed .to account for current activity as an abnormal liquid release included in the semi-annual effluent report. A background, evaluation and survey results discussion follows in Attachment A. Attachment 1 is the Microshield Code output and Attachment 2 is FSAR section 2.2 (including referenced tables and figures) on site hydrology. Pursuant to 10CFR170.12(c) a check in the amount of $150 is attached. Thomas C Bordine (Signed) Thomas C Bordine Administrator, Nuclear Licensing ('"'. CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment TPN-HPOl-NLOl Rev 0 8-1-91
ATTACHMENT A Consumers Power Company Palisades Plant Docket 50-255 EVALUATION AND SURVEY RESULTS November 12, 1987 10 Pages TPN-HPOl-NLOl Rev O 8-1-91
1
Background
In 1986, a soil survey was conducted south of the Turbine Building which included the South Radwaste area. The survey was conducted due to the South Radwaste Building being in the main flowpath of 'A' Cooling Tower, which has overflowed on three separate occasions in 8 years. The survey found that radioactive material was deposited in the soil due to the flooding of contami-nation and radioactive material areas inside the South Radwaste Building. Other areas sampled that were not in the flood plain were; liquid radwaste storage tanks, T-90, T-91, storm drains, the beach and the sand dunes. The survey included a survey grid, surface sample results and core sample results. All contaminated areas found in Are~ A (Figure 1) were packaged as radwaste. In addition, the highest activity areas adjoining the South Radwaste Building were also packaged. A total of 16-98 cubic foot boxes were packaged containing over 85 percent of the estimated activity.
- Evaluation In August of 1987, the survey was conduc.ted again to prepare this report and to verify the location of the ground contamination and if any contamination migrated further into the ground since the 1986 su~ey. The survey was a two phase evaluation with the first phase being a mapped area consisting of 25' x 25' ~quares south of the Turbine Building. Once mapped out, surface samples were taken in this area. The intent of this phase was to accurately map the location and determine the activity in µCi/gram of all ground surface contami~
nation. Each surface sample consisted of approximately 20 grams of soil taken Rev 0 MI0987-0066A-NL02 8-1-91
2 from the top l / 211 of gr*ound and placed in a petri dish for analysis on the Multi-Channel Analyzer (MCA). Over 275 samples were collected and analyzed with two surface samples being taken in each sector. All.samples were counted on MCA, Intrinsic Detector #1. Figure 2 shows the sector where activity was detected and their highest levels in µCi/gram. Phase II was initiated after completion of the "surface" sample analysis. This consisted of taking core samples in 6" increments where activity was detected. Core samples were taken until two consecutive core ~amples reflected no activ-ity. Core samples were also taken below the activity levels found in the 1986 soil survey until two consecutive core samples revealed no activity. Figure 3 indicates the depth level where activity was no longer detectable. For example, 6 inches is indicated in H-10 on Figure 3. This indicates that activity was only detected on the surface. H-9 and I-10 indicate 18" which tn means activity was detected only at 12 11
- Table 1 shows the results summary in
µCi/gram of the highest activity at all sample locations. The sector numbers respond to grid coordinates shown on Figures 1, 2 and 3.
In addition to the sample sectors shown on Figure 1, 25 samples were collected at various locations on site. These include surface and core samples around T-90, and T-91 on the Northwest side of the Turbine Building (location not shown on figures). Surface samples were taken under the asphalt around the South Radwaste Building. These are indicated by a hexagon on Figure 1 in F-11, I-12 and K-10 sectors. Core samples taken under the South Radwaste Building are indicated by circles on Figure 1. Of the areas sampled above activity was Rev a* MI0987-0066A-NL02 8-1-91
3 found only under the East side of the So.uth Radwaste Building in sector I-9 (Table 1). In *the 1986 soil survey other areas were sampled that were not in the flood plain of the South Radwaste Building. Those included Feedwater Purity Build-ing, North Storage Building, beach areas North and South of Plant, North and Northeast sand *dunes and various storm drains. In all of these areas no activity was detected. Therefore, they were not sampled in the 1987 soil survey as they were not in *the flood plain. Since the 1986 soil survey, asphalt has been placed over various locations in the protected area. Asphalt was placed around all storm drains and approx!- mately 50% of the South end of the Turbine Building. Before asphalt was laid down. about 3-6" of the top soil was removed and taken offsite. The soil before leaving site was sampled and counted with no activity detected. !.n Results To quantify activity and determine impact, the areas of ground contamination were separated into two areas. Area A which contains all the sectors (A-L, 1-8) North of the "black top" to the Turbine Building. Area B contains all sectors (C-L. 9-14) South of "black top" in the vicinity of the South Radwaste Build.ing. In Area A no activity was detected, therefore it was not used in determining activity or impact. Rev 0 MI0987-0066A-NL02 8-1-91
4 In *Area B activity was detected in almost all sectors to the East of the South Ra_dwaste Building (Figur'e 2). Activities r~nged from 2 .07E-6 µCi/gram (E-11) to 3.75E-5 µCi/gram (H-11). Cs-137 was the primary radionuclide present in all samples with two other samples containing Co~60 l.12E-5 µCi/gram at 6" and 5.80E-6 µCi/gram at 12" (I-9 East Figure 2). The greatest depth where activity was detected was in sector H..:11 at 18" and when compared to the 1986 soil survey the activity has migrated down into the soil 6" inches further. Activity was detected at the surf~ce in sectors E-11, E-13, J-12 and L-9 and at 6" in L-9. This was a result of moving the sand deposited on the asphalt during the flood to these sectors and the movement of soil during the grading and dumping during the asphalting of the South Radwaste area. Activity in µCi was calculated for each sector (Table 2) by the following formula: sector ft 2 x depth of activity ft x *48144 grams/ft 3 x activity (µCi/gram) ~ µCi. *Average liter of soil weighed 1700 grams x 28.32 L/ft 3
- tn 48144 grams/ft 3
- The first level at which no activity was detected was used to
~ determine depth of activity. In a few sectors, activity was only detected on the first 1/2" of soil, but for determining cubic feet and activity a depth of 6" was use_d. For example, activity for .H-10 was calculated as follows: 625 ft 2 x .5 ft. depth x 48144 grams/ft 3 x 2.6E-6 µCi/gram activity of surface sample equals 39.12 µCi.
Total volume in cubic feet and total activity in µC~ were calculated for each sector of Area B. For sectors with activity, the highest activity detected per sector was used in* the µCi calculation. Total contaminated area in Area B is Rev 0 MI0987-0066A-NL02 8-1-91
5 4173 ft 3 , total activity is 3071.9 µCi. Sector H-11 contains 73.5% of the
- total activity which comprises 14.5% of the total contaminated area of Area B.
To quantify the dose to the population projections, 2992.6 µCi of Cs-137 and 79.3 µCi of Co-60 was entered into the LADTAP computer program. Assuming that the total 3071.9 µCi was eventually released to Lake Michigan thru the water table, and the uptake pathways which included fish, drinking, swimming, boating and shoreline the 50 mile population estimated at l.05E6 would receive a total body dose of l.69E-2 manRem, or l.61E-5 millirem per person. The maximum wholebody do.se to an individual* would be 5 .13E-3 millirem and maximum organ dose (teenage liver) would be 8.67E-03 millirem. Direct dose to an individual working in the affected areas was calculated using the MICROSHIELD code. The activities from sec;ors H-11 and I-9 were used for a dose 18 inches above the surface. The dose rates from H-11 and I-9 are tn 8.75E-06 R/hr .and l.02E*05 R/hr respectively (Attachment 1). Therefore, a 50 hour occupancy in one week could result in a maximum exposure of 0.51 millirem. Normal occupancy of this area is on an as needed bases and averages less than 8 hours/week per individual in contact with contaminated soil. Rev O MI0987-0066A-NL02 8-1-91
Table 1 Soil Sample Core Results Cuci/gram) Sector Surf ace 6.. 12 11 18 11 24 30 11 36 11 42" 48" E-11 E-13
' 2.07£-6 4.39E-6
<HDA
<HDA
<HDA
<HDA
<HDA
<HDA H-9 4 .19E-6 <HDA 4.79E-6 <HDA <HDA <HDA H-10 2.60£-6 <HDA <HDA H-11 3. 75E-5 <HDA <HDA 8.45E-6 <HDA <HDA <HDA I-9 1.24£-5 <HDA <HDA I-10 <HDA <HDA 5.39£-6 <HDA <HDA <HDA <HDA <HDA J-9 5.39E-6 <HDA <HDA J-12 6.39E-6 <HDA <HDA L-9 * <HDA 6. 77£-6 <HDA <HDA T-90 <HDA <H~A 0 T-91 <HDA <HDA
**I-9 #1 <HDA <HDA <HDA' <HDA <Hl>A <HDA <HDA
<HDA <HDA
'°'N **I-9 #2
**I-10 #3
**I-11 #4
<HDA
<HOA
<HDA l.40E-5* 5.80E-6+
<HDA
<HDA
<HDA <HDA 0
***K-10 <HDA
>h'n':J-12 <HDA
*>""F-11 <HDA
+ Activity is all Co-60
- Includes l.12E-5 µCi/gram of Co-60. All other activities listed were identified as Cs-137.
'°'* Core samples unde.r foundation of the South Radwaste Building.
*** Surface ~amples ~nder asphalt in South Radwaste area.
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7 Table 2 Activity Calculations per Sector Area B Sector IJ Sq.ft. x Depth ::z ft 3 x g/ft 3 X uCi/g = Total uCi. E-11 375 0.5 187.5 48144 2. 07E-6 18.7 E-13 375 0.5 187.5 48144 4.39E-6 39.6 H-9 625 1.5 937.5 48144 4. 79E-6 216.2 H-10 625 o.s 312.5 48144 2.60E-6 39.l H-11 625 2.0 1250.0* 48144 3.75E-5 2256.8* I-9 527 0.5 263.5 48144 l.24E-5 157.3 I-10 275 1.5 412.5 48144 5 .39E-6 107 .o J-9 450 0 .5 225 48144 5*.39E-6 58.4 J-12 200 0.5 100 48144 6.39E-6 30.8 L-9 150 1.0 150 48144 6.77E-6 48.9 I-9 east 98 1.5 147 48144 l.40E-5 . 99.1 4325 4173 3071.9 '° N
*1250 = *2256.8 =
0 73.5% of total activity Ln 'q" 1' ~ Rev 0 HI0986-0062A-HP01 8-1-91
FIGURE~ SURVEY ...- GRID I. LEGEND ~ ASPHALT AREAS LI . 21*
- 21* SECTORS 0 ARE.\ *s*
µ (f=l AREA "" ():) !:O I <D I-'~ I AUGUST 1987
\0 o.
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AUGUST 1987 =1GURE 2 SURFACE ASPHALT AREAS ():> !:ti *EXAMPLE . ONLY I CD I-' < I
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. UNDER FOUNDATION .
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ATTACHMENT l Consumers Power Company Palisades Plant Docket 50-255 r.n ..o. N MICROSHIELD CODE OUTPUT November 12, 1987 8 Pages TPN-HPOl-NLOl Rev O 8-1-91
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ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 FSAR SECTION 2.2 - SITE HYDROLOGY November 12, 1987 r..n
~
10 Pages Rev 0 TPN-HPOl-NLOl 8-1-91
2.2 HYDROLOGY The Palisades Plant site is surrounded on the north, east and south sides by sand dunes. The west side of the site is the Lake Michigan shoreline. As a result of this local topography, the site drainage is independent of the Brandywine Creek drainage basin which drains the hinterland. All sur-face water runoff drains directly to the lake and the percolating runoff also discharges to the lake (see Reference 3). There are no data available to verify the amount of surface runoff from the site; however, the flow from the Brandywine Creek drainage basin should be useful for the putpose of comparison: Data obtained to establish base flow.figures for Van Buren County streams indicate that the Brandywine Cree~drainage basin is about 17 square miles (see Reference 4). The average annual rainfall for the area is 34 inches. During the period September 1962 to O~tober 1963, the base flow measure-ments varied from a minimum of 0.90 cubic feet per second (ft 3 /s) to a maximum of 11.4 ft 3 /s. This resulted in a mean annual 7-day minimum flow of 1.6 ft 3 /s or 0.094 ft 3 /s/sq mi (cubic feet per second per square mile). The period of stream measurements was representatiye of drought conditions. The deposits of Brandywine Creek drainage basin are of low permeability which results in ~ nearly total runoff to Lake Michigan. This runoff prob-ably occurs soon after precipitation. Minor groundwater storage in the oLd beach and reworked older.sandy lake deposits observed on the surface to the east of the site area probably maintain Brandywine Creek during periods of low rainfall *. 2.2.1 GROUNDWATER Almost all the water used in Van Buren County is obtained from wells. r.n Exceptions are the City of South Haven that obtains its municipal suppiy from Lake Mi;chigan and some irrigation supplies th.a.t are obtained from streams, lakes and local ditches (see Reference 4). The glacial drift.is the only known source of fresh groundwater in the county. All the glacial deposits are capable of yielding some water to wells, but the sand and gravel outwash deposits yield the largest quantities (see Reference 4). The area of sand dunes along Lake Michigan is not generally favorable for obtaining large supplies of groundwater. Probably most of the dune sand is above the water table and most wells must be drilled into the underlying,, lake deposits (see Reference 4). *
- 1. General Groundwater levels were established by the 1966 Geology and Groundwater Investigation conducted by Bechtel Company for Consumers Power Company (see Reference 3). The results of the investigation are shown on Figure 2-9.
It is rea*dily apparent that subsurface drainage is generally westward fsl281-129la-09-72 2.2-1 Rev 0 8-1-91
ATTACH.'1E~T ' toward the lake (see Profile A-A). Minor variations; ie, flow toward surface streams, may exist but are not considered significant. An average hydraulic gradient toward the lake of about 13 feet per mile was obtained along Profile A*A as shown on Figure 2*9. This gradient repre-sents only the upper surface of unconfined groundwater. Water released on the surface would move toward the lake at an estimated rate of 650 feet per year (see Reference 3). The nearest domestic wells to the site are located one-half mile to the east and south. The data indicates that groundwater in the vicinity of the eastern wells is flowing west toward the site. Local groundwater in the area of the southern wells is also flowing west toward the lake, perpendic-ular to the shoreline. There are no major sources of groundwater withdrawal, eg, large-scale industrial or agricultural pumping, that might reverse the direction of groundwater flow and cause groundwater to flow from the Plant area toward any existing domestic wells. Without such pumping, it is difficult to envis1on a condition which would cause sufficient groundwater lowering at any of the domestic wells such that the direction of flow might be reversed.
- 2. Plant Site Groundwater levels in the vicinity of the site are shown on Figure 2-9.
The water table generally slopes toward the lake. During the site inve~ti gations, groundwater elevations averaged 580 feet MSL beneath the building site. This elevation corresponds to the approximate mean level of Lake Michigan. As shown by water levels measured during drilling, groundwater levels rise *to the east to approximately 604 feet MSL beneath the switch* yard and 601 fee~ MSL near the eastern site boundary (see Reference 3). Field permeability tests performed during the 1965 exploratory drilling yielded values ranging from 30 to 1,720 feet per year in the site area, Table 2-11. In Drill Hole S, located approximately 500 feet northwest of the containment ~uilding, the permeability values ranged from 30.4 feet per year to 143 feet per year. In Drill Hole 7, located approximately 650 feet south of the containment building,- the permeability values ranged from 156 feet per year to 1,720 feet per year.
- 3. Groundwater Movement An unconfined aquifer is present in the dune area with groundwater levels controlled by the level of Lake Michigan. The rate of movement of ground-water downward into material underlying the dunes appears to be very slow.
Nine samples from Drill Hole 22 in the site area were tested (or sodium ab-sorption ratio (SAR), Table 2*12. A high SAR indicates poor downward per-colation of water due to sodium deposition on and between soil particles. At the Plant site, the SAR is considered to be high between elevations 596 and 566 feet MSL and low between 566 and 555 feet MSL (see Reference 3). fsl281-129la-09-72 2.2-2 Rev 0 8-1-91
Groundwater levels and permeability data from the sandy lake deposits underlying the dunes indicate a slow rate of discharge into Lake ~ichigan .
. 4. Conclusions
- a. Groundwater in the unconfined aquifer moves westerly from the Brandywine Creek basin to Lake Michigan.
- b. The hydraulic gradient is approximately 13 feet per mile and flow is essentially perpendicular to the shoreline.
- c. Water discharged on the ground surface at the Plant site will percolate downward at a slow rate and mix with groundwater moving toward Lake Michigan.
- d. Infiltration of surface water from the site to domestic wells offsite does not appear to be possible under present groundwater conditions.
2.2.2 GENERAL LAI<E HYDROLOGY
- 1. Lake Levels The level of Lake Michigan is cyclic and is expected to fluctuate with time and is dependent on long*term above-normal or below-normal amounts of pre-
- cipitation. The highest monthly mean stage of Lake Michigan was 583.68 feet MSL in 1886. Subsequent modifications in the St Clair River and the opening of the diversion out of the basin at Chicago have tended to reduce the maximum level attainable. During the recent period of record (1900 to present), the highest recorded monthly mean stage was 582.6 feet MSL in July 1974, and the lowest monthly mean stage was 576.91 feet MSL in March and April 1964 (see Reference 5). Great Lakes levels are reported t.n using International Great Lakes Datwn which is converted to MSL at the Palisades site by adding 1.558 feet. The l.558*foot correction factor is taken from the reference point at St Joseph, Michigan.
Short*time variations in lake levels (seiches), caused by meteorological factors and measured in hours rath.er than days, occur occasionally. The greatest level change of this type on record over a 105*year period in* volved a sudden.rise of 6 feet at Michigan City, Indiana (8:10 AM, June 26, 1954) and a rise of 8 feet at Montrose Harbor, Chicago (9:30 AM on the same date) (see Reference 6). These seiches were reported in the "Science" article by Ewing, Press and Donn (Vol 120, Page 684). On passing into tGe shallow water at Michigan City, the wave was reflected and refracted to reach the Chicago shore of the lake. The US Lake Survey gauge at Holland, Michigan, which is 30 miles north of the Palisades site and has similar lake geometry to the site, indicated no surge on June 26, 1954. As part of the Syst.ematic Evaluation Program (SEP Topic II-3.B), the maxi-mum probable surge elevation, was reevaluated. The offshore sur.ge value was reevaluated to produce an onshore surge height of 10.9 feet. The maximum monthly mean level was also* reduced from 583.6 feet MSL to 582.6 feet MSL. fs1281-1291a-09-72 2.2*3 Rev 0 8-1-91
This resulted in a probable maximum flood protection level for the Palisades Plant of 593.5 *feet MSL. The service water pump motors at 594.7 feet MSL provide the basis for determining the minimum flood protection requirements for the Plant. Therefore, the resultant wave surges from Lake Michigan do not present a problem at Palisades.
- 2. Water Movements Conclusions from a study of lake hydrology in the Palisades Park, Michigan area by Dr J L Hough (see Reference 6) indicate that surface currents gen-erated by wind conditions and .modified by the earth's rotation and lake configuration will provide adequate mixing of Plant liquid effluents into the lake. The study included actual measurements of lake water movement in the area near the.Plant site, and water mixing where the Black River enters Lake Michigan at South Haven.
A summary of the study is as follows: Lake water is almost constantly moving past the Palisades site, with an appreci~ble velocity of flow, under the influence of winds. It is es-timated, on the basis of wind records, that an alongshore current flows northward about 33\ o*f the time and an alongshore current flows south-ward about 23% of the time. Offshore drift of surface water should occur about 38% of the time, according to frequency of offshore winds, but these would have a minimal effect close to shore, which is bordered by a high dune ridge. It is likely, therefore, that the alongshore currents would tend to persist, once set up, while offshore winds were blowing. Thus, the frequency of alongshore current flow is probably greater* than the 33% and 23% based on wind directions. Under the procedure of taking water from a depth of about 20 feet, 3,500 feet offshore, raising its temperature as it is used for service water and dilution of c~oling tower blowdown, and returning the efflu~ ent to the lake near shore, the effluent water will almost always be warmer than the lake water into which it is discharged. This is because- a sin-gle take Michigan water mass is involved during most. of the year. When the effluent is warmer, it will tend to float at the surface, to drift with the surface current, and to be mixed by surface turbulence due to wave action. On rare occasions, during the spring wa~ing period when the upper layer of lake water is less than 20 feet deep, and during the summer when strong offshore winds *cause a thinning of the normally deep surface mass to less* than 20 feet, the intake
- water coming from a colder layer may not be warmed in the Plant suf fic-iently to have a temperature higher than that of the surface lake water. At such times, the effluent water will tend to sink to the thermocline and it will not be subject to vigorous turbulence caused by surface wave action. It will tend to mix more slowly.
Surveys of the performance of Black River water, entering Lake Michigan at South Haven under various weather conditions, have indicated that fsl281-129la-09-72 2.2-4 Rev 0 8-l-9l
the river water is diluted rapidly, reaching a concentration of ab~ut only 1% in ~he lake witbin a mile of the river mouth. The disch~rge of the Black River was evaluated because the rate was deter-mined to be nearly the same as the discharge* rate from the Palisades Plant with once-through coolidg. Since th~ Plant is now operated with cooling towers, the discharge to the lake has been reduced to approximately 60,000 gpm or about 1/7 the original rate. The mixing and dilution factors are considered to be as great as during the higher discharge periods and the discharge concentrations should be diluted at least 1,000 times by the time the discharge could reach the public water intake at South Haven, Michigan.
- 3. Conclusions
- a. The level of Lake Michigan is cyclic; howeve.r, the recorded high of 1886 is unlikely to be exceeded. High lake levels are not expected to present a problem at the Plant site.
- b. There is no recorded evidence of short-time variations in lak*e levels (s.eiches) along the eastern shore of Lake Michigan which would be expected to affect the Plant site.
- c. Surface currents generated by wind conditions and modified by the earth's rotation and lake c~.nfiguration will provide adequate mixing of Plant liquid effluents into the lake.
r.n fs128l-1291a-09*72 2.2-S Rev 0 B-1-91
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TABU 2-U FIELD PERMEABILITY TEST RESULTS Drill Hole Elevation Flow "Q" Head "H" Permeabil ity 3"K" Number of Test ( G12m) (Feet) (ft/Yr) (cm /s) 5 576 0.0029 12.3 30.4 0.3 x 10-_,4 570 0.0101 12.3 106.0 l. 1 l( 10 '+ 4 565 0.0088 12.3 92.0 0.89 l( 10-560 0.0035 12.3 36.8 0.36 x 10-~ 555 0.0136 12.3 143.0 1.4 x 10-... 4 550 0.0064 12.3 67.0 0.65 x 10- 4 545 0.0033 12.3 34.6 0.34 l( 10-4 Average 72.8 0. 72 x 10 "' 4 0 7 580 0.0303 25 156 1.5 x l0- 4 575 0.0477 25 246 2. 4 l( 10"' 4 Q) 570 0.0588 25 303 2.9 l( 10- 4 565 0.0588 25 303 2.9 l( 10- 4
- 't 560 0.0834 25 430 4.2 x 10- 4
,,.... 550 0.3333 25 1,720 16.7 x 10- 4 545 0.0677 25 350 3.4 x lo"' 4 540 0.2500 25 1,290 12.5 l< lo-* 4 535 0.2000 25 11035 10. 1 l( 10-4 Average 648 6.3 x 10"' t.n
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TABLE 2*12 ANALYSES OF SOIL SA...'1PLES Saturation Extract Values Millieguivalents Eer Liter Sample Sample No ....£!L ECe Caldwn Magnesium Sodium SAR DescriEtion 1 8.2S 1.2 0.5 Trace 11. 7 23.5 DH 22 El 596
*2 8.4 1.4 0.5 Trace 13.0 26 DH 22 El 59 l.
J 8.3 1.3 o.s Trace 12.3 24.5 DH 22 El 586 4 8.45 1.4 0.5 Trace 14.4 29 DH 22 El 581 5 8.5 1.5 0.5 0.1 14.8 27 DH 22 El 576 6 8.3 1.5 0.5 Trace 14.8 29.5 DH 22 El 571
*7 8.5 1.3 0.5 0.05 12: 7 24 DH 22 El 566 N
8 8.2 0.5 J,O 0.4 1. 1 1 DH 22 El 561 9 8.1 0.6 3.4 0.7 2.4 1.5 DH 22 El 555 ECe ~ Millimhos per centimeter SAR = Sodium adsorption ratio on saturation extract tn . ,.., v fsl281-129lo-09-72 Rev 0 8-1-91
LEGEllD I SITE PROPERTY BOUMDARY & EXCLUSION AREA 2 l'GWER BLOCK PUN 3 CIRCULATING WATER COOLIMG TOWERS
' SITE COllTOUR INTERVALS Of 20' IMCREHENTS 5 3300 FOOT INTAKE PIPE TO CRIB Ii DISCHARGE STRUCTURE 1 PARllllG
- 8. TOl'OGllAPlllC ELEVATIONS IN FEET ABOVE MUI SU LEVEL N
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'-,, 10 COOl llN (A.E.P.) CO CONSUMERS POWER COMPANY PALISADES PLANT FSAR UPDATE
. *' --* . SITE LAYOUT 677 METEIS IEAREST ACCESS ROAD 19UIOARY POllT TO COllTA1114ENT f IGURE 110 2-2 CP ~
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- FSAR UPDATE SITE TOPOGKAfHY,
- r; CllllltO. . IHllWALI a' IOl116 LOCATIOllS, AID SEISMIC PllOFILU tn*
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.arug!!.A=A_PAll'ilLLEL TO 241h 51. LOCAJEll .:I UIL[5 SOUTH.
ANO AREA GRADIENTS FIGURE 110 2-9 REVISION NO . 0 CX> :::0 I CD f--' < I
'00 f--' ATTACllMENT 2
consumers Power POWERING MICHlliAN"S PROGRESS General Offices: 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788*0550 January 25, 1988 Nuclear Regulatory Co1m11ission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR.20.302 Consumers Power Company letter dated November 12, 1987, requested authori-zation to dispose of soil in place as specified by 10CFR.20.302. The letter
*included the results of a survey and evaluation performed in*August, 1987.
Following submittal of that letter, a cooling tower overflow on November 13, 1987 again flooded the South Radwaste Building. The flooding caused additional activity that necessitated Consumers Power Company to request placing our November 12, 1987 request on hold until further evaluation and surveys could be completed. This letter includes the results of our evaluation and survey of the November 13, 1987 flooding incident and is intended to supplement our original November 12, 1987 request. Following the cooling tower overflow, a survey indicated additional activity ' had been released from the building. The building was being maintained in a non~contaminated condition to prevent this type of occurrence; however, during this period a destructive testing program on waste packages was being con-ducted in a small area of the building. The survey clearly showed the release of activ~ty from the building adjoining the testing area, The top six inches of soil from the sectors adjoining the building were removed"and packaged (588 cubic feet) to prevent additional dispersion of radioactivity. The area was then completely resurveyed. An evaluation of the August 1987 and November 1987 (post packaging) activities is att.ached. The survey indicates a drop of 49% in activities between the August and.November surveys. We propose the activities specified in the November 12, 1987 submittal be used ~s jµstification for the request because they are consei::vative. In addition since the November 13, 1987 flooding and following the most recent survey the area was subject to.heavy rains which could have diluted some activities to below minimum detectable activity (MDA is nominally lE-06 µCi/g), Rev 0 OC0188-0018-NL02 8-1-91
- Nuclear Regulatory Commission 2 Palisades Nuclear Plant Retain Soil in Accord. with 10CFR20.302 January 25, 1988 The one non-conservative value from our August survey and evaluation is* the maximum dose rate at 18 inches above the surface. The November survey value from MICROSHIELD is 1.17 mR/hr as opposed to 1.02 mR/hr. This small increase only slightly changes the radiation workers' conservative dose estimate from 4.08 mR/year to 4.7 mR/year.
*Following approval of this application, it is p*roposed to account for the most conservative values of activity, which was stated in the November 12, 1987 submittal, as an abnormal release in the semi-annual report. In order to prevent recurrence of these releases to the environment, Consumers Power Company is also committing to transfer radwaste activities from this area, except for high level vault use which is not a potential flooding release problem.
Relocation of these activities to a new radwaste facility is currently scheduled to.be completed in 1988. A check in the amount of $150.00 was attached to our November 12, 1987 submittal pursuant to 10CFR170.12(c). Thomas C Bordine (Signed) Thomas C Bordine Administrator, Nuclear Licensing CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment Rev O 8-1-9.1 OC0188-0018-NL02
Attachment A Consumers Power Company Palisades Nuclear Plant Docket 50-255 Evaluation and Survey Results Comparison Post November I .. Flood and Packaging Versus the November 12, i987 Submittal 1*:* Rev 0 8-1-91* MI0188-0001A-HP01
,.A' Cooling Tower - South Radwaste Flood In August of 1987, a resurvey was conducted of the soil at the South Radwaste Building and its adjacent areas. The resurvey was conducted to verify the location of ground contamination and i f any .contamination migrated further into the ground since the 1986 survey.
After submittal of the 1987 soil results and request to retain, in accordance with 10CFR20.302, 'A' Cooling Tower Basin overflowed again flooding the South Radwaste Building and outlying areas. Immediately following the occurrence, one liter sample was taken with no activity detected on the Multi-Channel Analyzer (MCA). Then, another complete survey was conducted which included at least two surface samples and core samples in every sector (Figures 1 and 2). Surface sample results showed that activities have increased as well as new sectors contaminated. The most heavily affected sectors were I-10, I-11, J-9 and K-9 (Figure lA). To keep these areas from spreading, the top 6" of each of these sectors was removed and placed in 6 LSA boxes (approx. 588 cu.ft) and ,. stored for disposition at a later date. ,. After removal of soil, the sectors were resurveyed (Figure lB) and core samples were taken in each sector in 6-inch increments. Core samples were taken as far down as in the 1986 and August 1987 surveys, and in some instances even further in this survey. *Results showed that no activity was detected below 6 inches as shown in Figure 2. Table 1 and Table 2 show comparisons between the August and November 1987 soil surveys. Table 1 compares the depths, the activities, the total cu.ft. and total µCi per sector. After the removal of soil, the November 1987 soil survey results showed approximately a 49.3% drop in total contaminated soil (cu.ft.) ' and a 51.1% drop in total µCi in comparison to the August 1987 survey results. In Table 2 the comparison is between sectors affected in each survey and the depth at which each of these sectors were sampled. No activity was detected past 6 inches in the November 1987 soil survey, in comparison to that of 18 inches detected in August 1987. Direct dose to an individual working in the affected areas was calculated using the MICROSHIELD code. The activities from sectors H-9 and J-9 were used for a dose at 18" inches above the surface. The dose rates from H-9 and J-9 are
*9.97E-6 R/hr and l.17E-5 R/hr, respectively. Therefore, a SO-hour occupancy in one week could result in a maximum exposure of .59 millirem. Normal occupancy of this are~ is on an "as needed basis" and averages less than 8 hours/week per individual in contact with the contaminated soil.
In reviewing the soil results between August and November 1987, the August 1987 soil survey remains more conservative based on the information shown on Tables 1 and 2. Therefore, the August 1987 soil survey is still valid in support of our request to retain the soil in accordance with 10CFR20.302. Rev 0 S-1-91 MI0188-0001A-HP01
Table 1 Comparison Table Between Total Cu. Ft. and Total µCi August 1987 Sector fl sg.ft. *X DeEth = ft 3 x g/ft 3 x µCi/g . Total µCi E-11 375 0.5 187.5 48144 2.07E-6 18.7 E-13 375 0.5 187.5 48144 4.39E-6 39.6 H-9 625 1.5 937.5 48144 ~.79E-6 216.2 H-10 625 0.5 312.5 48144 2.60E-6 39.1 H-11 625 2.0 1250* 48144 3.75E-5 2256.8 I-9 527 0.5 263.5 48144 l.24E-5 157.3 I-10 275 1.5 412.5 48144 5.39E-6 107.0 J-9 450 0.5 225 48144 5.39E-6 58.4 J-12 200 0.5 100 48144 6.39E-6 30.8 L-9 150 1.0 150 48144 6.77E-6 48.9 I-9 East 98 1.5 147 48144 l .40E-5 99.1 4325 4173 3011.2 ~
*1250 *2256.8 m
) 73.5% of total activity November 1987 E-11 375 0.5 187.5 48144 l.80E-6 16.25 H-9 625 0.5 312.5 48144 4.35E-5 654.46 H-10 625 0.5 312.5 48144 3.20E-6 48.14 r H-11 625 0.5 312.5 48144 3.22E-5 484.45 ,. H-12 I-9 250
*527 0.5 0.5 125 263.5 48144 48144 2.20E-6 6.79E-6 13.24 86.14 I-12 220 0.5 110 48144 3.0E-6 15.89 J-9 450 0.5 225 48144 2.05E-5 222.06
- l. J-1*2 200 0.5 100 48144 2.60E-6 12.52 K-9 216 0.5 108 48144 3.39E-6 17.63 iUl 20~6!5 1570.78 Rev 0 8-l-9l MI0188-0001A-HP01
Table 2 Survey Comparison Between August and November 1987 Soil Surveys August 1987 November 1987 Sector Surface 6" 12 11 18" 24 11 30 11 36 11 42" E-11 2.07E-6 <MDA <MDA <MDA l.SOE-6 <MDA <MDA <MDA E-13 4.39E-6 <MDA <MDA <MDA
<MDA H/A <MDA <MDA H-9 4.19E-6 <MDA 4.79E-6 <MDA <HDA <HDA 4.JSE-5 <MDA <MDA <MDA <MDA <HDA H-10 2.60E-6 <MDA <MDA 3*.20E-6 <MDA <MDA H-11 J.75E-5 <MDA <MDA 8.45E-6 <MDA <MDA <HDA 3.22E-5 <MDA <MDA <MDA <MDA <MDA <MDA H-12 <MDA Nf A 2.20E-6 N/A I-9 l.24E~5 <HOA <MDA 6.79E-6 <MDA <MDA I-10 <MDA <MDA 5.39E-6 <MDA <MDA <MDA <MDA <MDA
<MDA <MDA <MDA <MDA <MDA <MDA <MDA <HDA I-11 <MDA Nf A
<MDA <MDA <MDA <MDA I-12 <MDA N/A 3.00E-6 N/A J-9 5.39E-6 <MDA <MDA 2.0SE-5 <MDA <MDA
. J-12 6.39E-6 <MDA <MDA*
2.60E-6 N/A <MDA lC-9 <MDA Nf A 3.J9E-6 <MDA <MDA <MDA <MDA <MDA <MDA L-9 <MDA 6. 77E-6 <MDA <MDA a:> ?:d <MDA N/A <MDA <MDA I CD I-'< I \00 I-' MI0188-0001A-HP01
Microshield 3.02
===;=============
(ConsuMer's Power CoMpany - #037) Page 1 File SOIL1 .MSH Run date: January 18, 1988 Run tiMe: 4:17 p.M. CASE: CONTAMINATED SOIL@ H-9 LOCATION <6 INCHES DEEP> GEOMETRY 11: Rectangular solid source. - slab shields Distance to detector ......................... x 60.960 CM, Source width*
- t
- I C II II II I' 11 II 11 11 11 II I II I I 11 °1 11 I I
- II II S II
- II
- w 762. II Source length ... I.*.* I . ** * * * * ** *
- I I I *********** I L 762. "
Rectangular solid, thickness toward dose pt ** Tl 15.240 " Thickness ci f second ~hield .................... T2 45.720 " Source Volul'le: B.84901e+6 cubic centit11eters MATERIAL DENSITIES (g/cc>: Material Source Shield 2 ., Air .001220 .001220 Alut11inuP1 Carbon 1. 70 Concrete Hydrogen Iron Lead LithiuPI Nickel Tin Ti taniul"I Tungsten o* Urania UraniuPI Water 1.0 Zirconiul"I Rev O 8-1-91
Page 2 File: SOIL1 .MSH CASE: CONTAMINATED SOIL@ H-9 LOCATION (6 INCHES DEEP> BUILDUP FACTOR: based on TAYLOR Method. Using the characteristics of the Materials in shield 1
- INTEGRATION PARAMETERS:
NuMber or lateral angle segPlents (Nthetal..... 5 NuMber of aziMuthal angle segMents <Npsi)..... 5 NuP1ber of radial segMents (Nradius)........... 5 SOURCE NUCLIDES: Ba-137M: 3.8493e-04 curies RESULTS: Group Energy Activity Do3e point flux Dose rate -; # <MeVl (photons/sec) MeV/(sq cpi)/sec ( l'lr/hr > 1 .664 I. 282e+07 4.908e+00 9.969e-03 2 3
- r: 4 5
6 7 8 9 10
. 11
, 12 13 14 15
- '.). 16 17 18 19 20 TOTALS: 1. 282e+07 4.808e+00 9.969e-03 Rev 0 8-1-91
Microshield 3.02
=================
(ConsuMer's Power CoMpany - #037) Page 1 File SOIL2.MSH Run date: January 18, 1988 Run tiMe: 4:26 p.M. CASE: CONTAMINATED SOIL@ J-9 LOCATION {6 INCHES DEEP> GEOMETRY 11: Rectangular solid source - slab shields Distance to detector ..*.. ,.,.* ***.*. ~ .**....* , .)( 60.960 CM, II Source width ........... , ...................... lJ 762. Source length ..................*.............. L 548.640 Rectangular solid, thickness toward dose pt *. Tl 15.240 II Thickness of second shield', ..*..*.***...**** , T2 45.720 II Source VoluMe: 6.37129e+6 cubic centi111eters MATERIAL DENSITIES (g/cc): Material Source Shield 2 Air .001220 .001220 Alu111inufll Carbon f. 70 ,. Concrete Hydrogen
- r *Iron Lead Li thiul'I Ni'ckel Tin T1taniuP1 Tungsten
,.. Urania Uraniu111 Water 1.0 ' Zirconiul"I Rev O 8-1-9],
Page 2 File: SOIL2.MSH CASE: CONTAMINATED SOIL @ J~g LOCATION CS INCHES DEEPl BUILDUP FACTOR: based on TAYLOR Method. Using the characteristics of the Materials in shield 1. INTEGRATION PARAMETERS: NuMber of lateral angle segMents CNthetal..... 5 NuMber of aziMuthal angle segMents (Npsil..... 5 NuMber of radial segl'lents (Nradius).. ......... 5
. SOURCE NUCLIDES:
Co-80: 8.9198e-05 curies RESULTS: Group *Energy Activity Dose point Hux Dose rate
# <MeV) (photons/sec) MeV/(sq cP1)/sec; <Mr/hr>
1 1 .336 . 3 .300e+06 3.411 e+00 6 .1 SSe-03 ., 2 3 1
- 180
.695 3.300e+~6 5.303e+02 2.958e+00 2.aase-04 5.497e-03 5.950e-07 l'" 4 5
6 7 a 9 ,.. 10 11 , 12 13 14 15 ~. 16 17 10 19 20 TOTALS: 6.S01e+06 6.370e+00 1 .165e-02 Rev 0 8-1-91
- 1GURE 1A SURFACE
~ESULTS
. . .ACE ACTMTYOFSECTOR ASPHALT AMAS
*1xA11PLI: ONLY rl 00\
I ID I rl P'.i <X)
- 1GURE 1B .
SURFACE . L I. i.EGEND
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- IURMCI! AMA IN>ER ASPHALT 't/'"" . * .
&J CORE SAMPLE UNDER FOUNDATION. *
/~
SURFACE ACTIVITY OF SECTOR ASPHALT AflEAS
*EXAMPLE: ONLY 00\
ri (°
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L c. I . .Ei~END
- -I Lat IUt llJ-cawr.tN
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~ OIPTM 1.DIL AT.WllCll NO Ll ICllVlirWAIMNCTID ~ _AINIALT A~ J ,.--.,,..-~ i1
ODCM - APPENDIX B REFERENCE 2
/>woa/OB>eg
~-
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 15, 1988 MAN 1 fi ,988 NUCt!AI uaNSING Mr. Kenneth W. Berry Director, Nuclear Licensing Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201
Dear Mr. Berry:
SUBJECT:
PALISADES PLANT - REQUEST TO .RETAIN CONTAMINATED SOIL IN ACCORDANCE WITH 10 CF.R 20.302 (TAC NO. 67408) The subject request submitted by Consumers Power Company by letter dated November 12, 1987 and supp1emented by information forwarded by letter dated January 25, 1988 contains detailed information evaluating the radiation doses via the liquid pathways for very low levels of contamination presently in areas of soil near the Palisades Plant South Radwaste Building. Detailed evaluations are also presented of potential occupational doses from this contaminated so.i l . One additional dose pathway should, however,*be evaluated to complete the analysis of the impact viz., the inhalation pathway. In your submittals, you have presented diagrams showing areas in which contamination has been detected. It appears that for some of these areas 611 of soil has been removed, others are now covered by black top, and still others have not been disturbed. In order for the staff to complete the evaluation under 10 CFR 20.302, we ask that you submit a diagram indicating all contaminated soil surface areas included in this request, the condition of this soil surface, and an evaluation of the radiation dose.s via the inhalation pathway associated with these soil surfaces. The request in this letter affects fewer than ten respondents; therefore, OMB clearance is not required under PL 96-511. Sincerely,
~1(~
Thomas V. Wambach, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V
&Special Projects cc; Sse* *Next. -Rage
I
*Mr. Kenneth W. Berry Consumers Power Company Palisades Plant cc:
M. I. Miller, Esquire Isham, Ljncoln &Beale Nuclear Facilities and Slst Floor Environmental Monitoring Three First National Plaza Section Office Chicago, Illinois 60602 Division of Radiological Health Mr. Thomas A. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Michigan 48909 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire
- Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator. Region III U.S. Nuclear Regulatory Commission 799 Roos*eve 1t Road Glen Ellyn, Illinois 60137 Jerry Sarno Township Supervisor Covert Townsh1 p 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building
,. Lansing, Michigan 48913 , Mr. David P. Hoffman Plant General Manager Palisades Plant
- l. 27780 Blue Star Memorial Hwy.
Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Commission Palisades Plant 27782 Blue Star Memorial Hwy. Covert, Michigan 49043 Rev O 8-'l-91
Lt# 5ooe89 llEt:c;1vED UNITED STATES NUCLEAR REGULATORY COMMISSION JAN 1 ~ f93~ WASHINGTON, D. C. 20555 January 12, 1990 11r.1 FL\O ~ :FN~INn Docket No. 50-255 Serial No. PAL 90-002 Mr. Kenneth W. Berry Director, Nuclear Licensing Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201
Dear Mr. Berry:
SUBJECT:
PALISADES PLANT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10 CFR 20.302 (TAC NO. 67408) By letters dated November 12, 1987 and January 25 1 1988, Consumers Power Company requested authorization under the provisions of 10 CFR 20.302 to dispose . contaminated soil in place. The NRC staff replied with a request for additional information which was forwarded to you on March 15 1 1988. * * ~* By letter dated June 27, 1988, Consumers Power Company provided additional*~ 1 information in response to ou.r request. Howeve.r, in that response, CPCo expanded the original request to include the entire South Radwaste area as a contingency against future spread of co.ntamination and to obviate the* need for additional requests under 10 CFR 20.302. For the staff to complete its review of this request, additional specific information is required. This is because NRC approval under 10 CFR 20.302 is for the disposa'l of specifically identified and characterized slightly contaminated material by the applicant. We request that you provide a revised submittal describing the licensed material for disposal and the analysis and evaluation called for under 10 CFR 20.302. The attached request for additional information provides additional detail for the content of the revised submittal. The reporting and/or recordkeepfng requirements of this letter affect fewer
*than ten respondents; therefore, OMB clearance under Pl 96-511 is not required.
Sincerely,
~/~
Albert W. De Ag;~-a,-~;:ject Manager Project Directorate III-1 . Division of Reactor Projects - III, IV, V &Special Projects Office of Nuclear Reactor Regulation cc: See next page Rev 0 8-1-91
r' Mr. Kenneth w. Berry Palisades Plant Consumers Power Company cc: M. I. Miller, Esquire Sidley &Austin Nuclear Facilities and 54th Floor Environmental Monitoring One First National Plaza Section Office Chicago, Illinois 60603 Division of Radiological Health Mr. Thomas A. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Mfch1gan 48909 212 West Michigan Avenue
*Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Con111ission 799 Roosevelt Road Glen El~yn, Illinois 60137 Jerry Sarno Township Supervisor Covert Township 36197 M*140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. Gerald B. Slade Plant General Manager Palisades Plant 27780 Blue Star Memorial Hwy.
Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Conmiss1on Pa 1i sades Pl ant 27782 Blue Star Memorial Hwy. Covert, Michigan 49043 Rev 0 8-1-91
I ENCLOSURE SECOND REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE CONSUM.ERS POWER COMPANY PALISADES PLANT REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10 CFR 20.302 The subject request submitted by Consumers Power Company (licensee) by letter dated November 12, 1987 and supplemented by information forwarded by letter dated January 25, 1988 contained detailed infor~ation evaluating the radiation doses via the liquid pathways for very low levels of contamination presently in areas of soil near the Palisades Plant South R.adwaste Building. Detailed evaluations were also presented of potential occup~tional doses from this contaminated soil. Three significant questions arose during the staff evaluation of this request:
- 1. The inhalation pathway for doses from the contaminated soil was not addressed.
- 2. The proposals contain no delineation of the specific contaminated areas covered by the disposal request.
- 3. The licensee's Technical Specifications for radiological environmental
-1 1 3 7 Cs monitoring require an LLD of 2 x 10 µCi/gm for determinations in sediment - yet all of the measurements reported in the request were made with equipment 5 to 10 times less sensitive for these gamma radiations.
Re-v 0 8-1-91
By letter dated June 27, 1988 the licensee submitted additional information in response to the staff's RAI of March 15, 1988. This submittal was unacceptable in that it addressed potentially contaminated areas and hypothetical maximum contamination parameters rather than measured licensed material to be disposed of under the regulations. It is requested that. the licensee submit a complete, revised 20.302 request incorporating the dose evaluation information of the measured contamination considered in the No.vember 12, 1987 and January 25, 1988 submissionsand updated if appropriate with dose evaluations of the inhalation pathway based on the same measured contamination. As part of the proposal the licensee should record exactly what areas of measured contamination are covered by the request for which disposal under 10 CFR 20.302 is proposed. Rev O 2 8-l-9l
.ODCM - APPENDIX B REFERENCE 3 consumers Power POWERING MICHlliAN-S PROGRSS General Offices: 1945 West Parn11ll Road, Jackson, Ml 49201 * (517) 788-0550 June 27, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR-20-- PALISADES PLANT -
SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302 , Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose contaminated soil inplace as specified r by 10 CFR 20.302. The area, known as the South Radwaste Area, has been contaminated by numerous cooling tower overflows and redistributed by heavy rain showers. Although the majority of the radioactive material has been packaged for waste *shipment, a large volume of very low ac_tivity radioactive material remains. This volume of material would be very expensive to ship as waste. The NRC, by letter of March 15, 1988 to Consumers Power Company, requested additional inhalation dose information and clarification of the contaminated area
- A generic inhalation dose evaluation is described in Attachment A. Conserva-tive assumptions have been made to get the maximum organ dose possible from inhalation of contaminated soil. The inhalation doses are not significant.
Consumers Power Comp*any requests to expand this 10 CFR 20.302 request to _include the entire South Radwaste Area * . Periodic cooling tower overflows and occasional heavy rains have caused redistribution of radioactive material to
-areas which were below Lower Limits of Detection (LLD) during previous evalua-tions. Expanding the area would eliminate the need for a new 10 CFR 20.302 submittal if radioactive material is redistributed within the South Radwaste Area. The South Radwaste Are~ is completely fenced and located directly South of tpe Plant South Security fence. Area fence is shown in dark outline on Figure 1.
As desc~ibed in our January 25, 1988, letter we intend to transfer the radwaste activities which caused the contamination of soil from the South Radwaste Area, except for the high level* vault use which is not a potential flooding release problem. Rev 0 OC0688-0049-NL02 8-1-91
Nuclear Regulatory Commission 2 Palisades Nuclear Plant Retain Soil in Accordance w/10CFR20.302 June 27, 1988 Consumers Power Company requests approval to dispose of inplace low level radioactive materials which meet the following conditions ~ithout further 10 CFR 20.302 submittals.
- 1. Material contained in the fenced area described as South Radwaste Area.
- 2. Direct dose to a radiation worker would not exceed SE-02 mRem/hour.from contaminated soil. *
- 3. Average gross beta/gamma concentration not to exceed SE-05 µCi/gm so in~alation doses to a radiation worker or at the site boundary would not exceed the values contained in Attachment 1.
- 4. Additional radioactive material releases shall be identified in liquid Semi-Annual Effluents Reports as an 'Abnormal Release'.
') Sampling, analyses and Semiannual Effluent Report inclusions of 'Abnormal 'l Release' will be performed only when further flooding of the area occurs. James L Kuemin (Signed) James L Kuemin Staff Licensing Engineer CC Administrator, Region III,° NRC ' NRC Resident Inspector - Palisades ~.. Attachment Rev 0 OC0688-0049-NL02 8-1-91
Attachment 1 The inhalation doses have been calculated on a generic worst case basis. A generic basis has been selected to compensate for the elevated Lower Limit of Detection (LLD) in analysis and also to address movement of radioactivity within the South Radwaste Area. The assumptions made are the worst case Dose Conversion Factor (DCF) used (see Table 3), a total average activity concentra-tion.of 5E-05 µCi/gram and the entire area (500 m2 ) used instead of the indi-cated contaminated area (117 m2 ). Increasing the area is self-explanatory. The total average activity concentra-tion is being used il!tstead of actual to account for dose important isotopes which may be present near the analysis LLD of lE-0~ µCi/gm, but not detected. The worst case D9F is used to demonstrate a maximum organ dose. A variation in isotope mixes could shift the maximum dose to a different organ but could not 0 exceed the dose indicated. 0 Radworker and site boundary inhalation dose calculat~ons are attached. T
.Rev 0 OC0688-0049-NL02 8-1-91
*Table 1 Inhalation Dose From Contaminated Soil -
Adult Radiation Worker* Where: CS = concentration of waste: 5.0E04 pCi/Kg. Ef .. occupancy factor: 2080 worker hours + 8760 hrs/yr = 0.2.37 f =areal mass available for resuspension (top 1 cm of soil): 16 18 Kg/m2 ... f 1 = resuspension. factor: 8.5E-9/m 4 ., f = adult annual inhalation rate: 7300 m3 (RG 1.109) 15 r DCFi =- 7 .46E-04 mRem/ (50 yr
- pCi): adult lung (RG 1.109)
- Substituting: DW = 8.78E-03 mRem/50 yr: maxim.um organ dose
Reference:
AIF/NESP-035 Evaluation of the Potential for De-Regulated*Disposal of Very Low Level Wastes From Nuclear Power Plants Rev O OC0688-0049-NL02 8-1-91
Table 2 Inhalation Dose At Site Boundary.- Infant Most Limiting X/Q µ A Where: Terms are identified in Table 1 and F 16
= 2045 ms: infant annual breathing rate (RG 1.109)
X/Q ~ 1.4 E-6 sec/ms: actual 5 year site average
µ = 3.8 m/sec averag~ wind speed: actual 1986
, A = 500 m2 : contaminated area DCFi = 3.22E-03 mR/(50 yr. pCi): infant lung (RG 1.109) T - Subs t i tu ting DSB = 1.19E-04 mRem/50 yr: ~aximum organ dose Rev O OC0688-0049-NL02 8-1-91
Table 3 Dose Conversion Factors for Inhalation: Committed dose (mRem) over 50 years per pCi inhaled, per Regulatory Guide 1.109. Onsite - Radiation Worker Bone Liver Kidney Lung GI Cs-134 4.66E-05 l .06E-04 3.59E-05 l.22E-05 l.30E-06 Cs-137 5.98E-05 7.76E-05 2.78E-05 9.40E-06 l.05E-06 Ba.:..140+D 4.88E-06 6.13E-09 2.09E-09 l.59E-04 2.73E-05 Sr-90* l.24E-02 0.0 o.o l.20E-Ol 9.02E-05 Co-60** o.o l.44E-06 o.o 7.46E-04 3.56E-05
- Sr-90 is a factor of 5E-Ol lower than Cs-137 based upon 10 CFR 61 sampling analysis and cannot be limiting. Cs-137 was present in all samples where activity was identified.
** Given the concentration restriction on Sr-90 noted above, Co-60 lung dose is
-* most limiting. Offsite ,.. Infant Most Limiting for Inhalation Cs-134 2.83E-04 5.02E-04 . l.36E-04 5.69E-05 9.53E-07 Cs-137 3.92E-04 4.37E-04 l.23E-04 5.09E-05 9.53E-07 Ba-140 4.00E-05 4.00E-08 9.59E-09 l.14E-03 2.74E-05 Sr-90* 2.92E-02 o.o o.o 8.03E-03 9.36E-05 Co-60** 0.0 5.73E-06 o.o 3.22E-Ol 2.28E-5
- Sr-90 is a factor of 5E-03 lower than Cs-137 based upon 10 CFR 61 sampling analy~is and cannot be limiting. Cs-137 was present in all samples where activity was identified. *
** Given the concentration restriction on Sr-90 noted above, Co-60 lung dose is most limiting.
Rev 0 OC0688-0049-NL02 8-1-91
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ODCM - APPENDIX B REF~CE 4. consumers Power G BSlade General Managft POWERING M.IClllGAN"S l'llll&llUS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert. Ml 49043 August 31, 1990 Nuclear Regulatory Commission Document Control Desk Washington, D C 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR 20.302 Consumers Power Company correspondence dated November 12, 1987 and January 25, 1988 requested authorization to dispose of contaminated soil in place as specified by 10CFR 20.302. The area known as the South Radwaste Area has been contaminated by numerous cooling tower overflows and contamination was
- redistributed by heavy rain showers. Although the majority of the radioactive material has-been packed for waste shipment, a large volume of very low activity radioactive material remains. This volume of material would be very expensive to ship as waste. The NRC, by letter of March 15, 1988 to Consumers Power Company, requested additional inhalation dose information and clarification of the contaminated area.
After discussions with the NRC reviewer, a supplement was submitted on June 2.7, 1988 which was based on generic approval. It proposed that further submittals would not be required if flooding moved activity from an identified to an unidentified sector. Subsequently, on January 12, 1990, the NRC Staff requested additional information. The information request required the licensee to submit a revised proposal incorporating the dose evaluation information of the measured contamination considered in the November 12, 1987 and January 25, 1988 submittals and updated, if appropriate, with dose evaluations of the inhalation pathway based on the same measured contamination. As part of the proposal, the licensee was asked to record exactly what areas of measured contamination are covered by the request for which disposal under 10CFR 20.302 is proposed, The attached material supplie~ the requested information. The specific area contaminated is noted as Area Bon the attached survey grid map. The entire area is fenced* and is about 12 ,000 sq ft of soil exposed with the remainder buildings and asphalt. The inhalation pathway is for breathing suspended soil from this area. Table 2 addresses a radworker in Area B, and Table 3 addresses an infant on the site boundary. The radworker could receive 8.03E-04 mRem/50-year maximum organ (liver) dose and the infant could receive 3.16E-05 mRem/50-year maximum organ (liver) dose, both of which are insignif-icant. Rev O 8-1-91 OC0890-0074A-NL03 .
4 . When the flooding problem was discovered and planning for a formal survey was done, the environmental sediment LLD was not considered, as this was a nuclear plant site. We attempted.to get the best LLDj we could usi~g our equipment and the number of samples we were going to have to run. With the hundreds of samp*les run, we felt rn . . 06 uCi/gm was adequate. To be conservative, we . expanded the August and November 1987 surveys to use l.OE-06 uci/gm Cs-137 in any sector which showed LLD. This will increase the radioactivity to 5,006 uCi from 4,643 uCi, an increase of 8%. The activities are on Table 1 and lA. If this submittal is approved, we will add the released activity to the Liquid Semi-annual Effluent Report as an aQnormal release, and the approval to retain the soil in place will be documented in the FSAR. In summation, Consumers Power Company requests approval to dispose of i~ place the low-level radioactive materials which are contaminated soil contained* in the fenced area described as South Radwaste Area (Area B). Direct dose to a radiation worker would not exceed l.7E-02 mRem/hour from this contaminated soil. Inhalation doses to a radiation worker or at the site boundary would. not exceed 8.03E-04 mRem/50-year. Tables 1 and lA radioactive material release shall be identified in liquid Semi-an~ual Effluent Reports as an
'abnormal release'. The disposal in place would be documented in the FSAR.
The radwaste activities which caused the contamination of the soil have bee*n completely relocated to a new east radwaste area. The South Building has been deconned and is being useQ. for non-radwaste activities. Some fixed contamination is present in floor cracks and vaults. This has been documented for plant decommissioning. No further contamination will be added to the south area from the South Radwaste Building. Gerald B Slade (Signed) Gerald B Slade General Manager pc: Administrator, Regio~ III, USNRC NRC Resident Inspector, Palisades Rev 0 8-1-91 OC0890-0074A-NL03
Attachment A Consumers Power Company Palisades Nuclear Plant Docket 50-255
- Tables l and lA,. Survey Results Microshield Direct Dose Calculation Table 2 - Radworker Inhalation Dose Table 3 - Site Boundary Inhalation Dose Figure l - Survey Crid Figure 2 - Survey Results Rev 0 8-1-91 MI0890-00 74A-liPOl
, I Table 1 August 1987 Survey Sector (} S9.ft. x De 2th = ft) x g/ ft l x ~Ci/g = Total ~Ci E-11 375 o.5 187.5 48144 2.07E-6 18.7 E-13 375 0.5 187.5 48144 4.39E-6 39.6 H-9 625 1.5 937.5 48144 4.79E-6 216.2 H-10 625 o.5 312.5 48144 2.60E-6 39.l H-11 6*25 2.0 1250* 48144 3.75E-5 2256.8 I-9 527 0.5 263.5 48144 l.24E-5 15 7 .3 I-10 275 1.5 412.5 48144 5.39E-6 107.0 J-9 450 0.5 225 48144 5* .39E-6 58.4 J-12 200 0.5 100 48144 6.39E-6 30.8 l.-9 150 1.0 150 48144 *6.77E-6 48.9 1.5 147 48144 l.40E-5 99.l I-9 East ~ Subtotals 4325 4173 3071.9 Remainder 7613 0.5 3807 48144 l .OE-06 183 i: Section TOTAL 11, 938 3,255. Rev 0 a..:.1-91 MI0890-0074A-HP01
Table lA November 1987 SurveI Sector ~ Sg. ft. x Deeth = ft J x ~)ft J x ~Ci/g = Total ~Ci B-9 125 0.5 62.5 48144 lE-06 3 C-9 625 0.5 312 *.5 48144 lE-06 15 c-10 500 0.5 250 48144 lE-06 12 D-9 500 0.5 250 48144 lE-06 12
.D-10 625 0.5 312.5 48144 lE-06 15 D-11 550 o.5 275 48144 lE-0"6 13 D~l2 75 0.5 37.5 48144 lE-06 2 E-10 125 0.5 62.5 48144 lE-06 3 E-11 375 0.5 187.5 48144 l.8E-06 16 E-12 625 0.5 312.5 48144 l.E-06 15 E-13 550 0.5 275 48144 lE-06 13 F-12 300 0.5 150 48144 lE-06 7 F-13 625 0.5 312.5 48144 lE-06 15 G-12 750 0.5 125 48144 lE-06 6 C-13 625 0.5 312.5 48144 lE-06 15 H-9 625 0.5 312.5 48144 4.4E-05 662 H-10 625 0.5 312.5 48144" 3.2E-06 48 H-11 600 0.5 300 48144 3.2E-05 462 H-12 250 0.5 125 48144 2.2E-06 13 H-13 625 0.5 312.5 48144 1. OE-06 15 I-9 527 0.5 263.5 48144 6.8E-06 86 I-10 275 0.5 137. 5 48144 l.OE-06 7 I-11 250 0.5 125 48144 l.OE-06 6 I-12 220 0.5 110 48144 3.0E-06 16 J-9 450 0.5 225 48144 2. lE-05* 227.
J-12 200 0.5 100 48144 2.6E-06 13 K-9 216 0.5 108 48144 3.4E-06 18 L-9 150 0.5 75 48144 *i.oE-06 4 L-10 150 0.5 75 48144 l.OE-06 4 L-11 150 0.5 75 48144 l.OE-06 4 L-12 150 0.5 75 48144 l.OE-06 4
\
Subtotals 11,938 ft 2 5,969 ft 3 Maximum 4.4E-05 1751 Average 6. lE-06 Re-v 0 8-l-91 HI0890-0074A-HP01
Microsh1eld 3.~2
<Consu111er's Power Co111pany - #037l Page I File SOIL! .MSH Run date: January 19, 1999 Run ti111e: 4:17 p.111.
CASE: CONTAMINATED SOIL ~ H-9 LOCATION (6 INCHES DEEP> GEOMETRY 11: Rectangular solid !ource - !lab shields Distance to detector ************************* X 60.960 CPI, Source widtti .*.**.. , ....**..*........ ~ ....... W 762. Source length ..*...*.....*........*.......... L 762. Rectangular solid, th1cknese toward dose pt ** ft 15.240 Thickness o.f second shield ****.**.**..*.**..* TZ 45.720 " Source Volul'le: 8.84901e+6 cubic centil'leters MATERIAL DENSITIES Cgicc): Materh! Source Sh1e!d 2 Air .001220 .001220 Alul!linul'I Carbon !. 70 Concrete Hydrogen Iron Lead. L1 tl"liUl'I Nickel Tin TitaniuPI Tungsten Urania Uraniul'I Water 1.0 Zi.rconiu111 Rev 0 8-1-9.1
8U[L0UP FACrCR: oased on rAvLOR Met~od.
!J!lnQ tlie clier-acte1"15t1cs or* tl'le l'li!ter-lcds tn 9h1eld I*
INrEGRAT[ON PARAMErERS: Nul'lber or later-al angle seQMent5 <Ntnetal,,, .. 5
!\Ju111cer- or ~Zll"lutnal angle segMenh <Npul..... 5 Nul'lt1er- or '.ad1 al seg111ent ! <Nrad11.Js l., ... ,.,,., 5 SOURCE NUCUOES:
Sa-137,.,,:
- 3. S493e-04 cur us .Actual 6.SlE-04.Ci (4 *.4E-05 uCi/gm)
RESULTS: Gr-ou~ Energy l'ict1111ty Dose point rlux Dose rate
# (MeVl <gnotonstsecJ MeV/(s~ cll\Jtsec f
.664 I .282e+07 4.S08e+00 (I'll'"/ hr-)
z 9.969e-03 3 4 s s 7 s s 10 1I 12 13 14 15 rs 17 I8 19 ZI TOTALS: --------- I. 282e+07 --------- 4.8081+00 9.969e-03 6.51 Ci
- Ratio of 3.85 Ci= 1.69 x 9.969E-03 = l.7E-02 ?:lR/hr Rev 0 8-1-91
Table 2 Inhalation Dose From Contaminated Soil - Adult Radiation Worker Dw = Cg f14 Where: Cs = concentrati.on of waste - 4.4E04 pCi/Kg Cs-137 (actual max concentration) Ef = occupancy factor - 2080 worker hours ~ 8760 hrs/yr = 0.237 f18 = a real/mass available for resuspension (top l cm of soil) - 16 Kg/m 2 f14 = resuspension factor - 8.SE-9/m f15 = adult 3 annual inhalation rate - 7300 m (RC 1.109) DCFi = 7.76E-o5* mRem/50 yr* pCi - Cs-137 adult liver (RG 1.109)
- substituting:
Ow = 8.03E-04 mRem/50 yr - maximum organ dose
* ~ference: AIF/NESP-035 Evaluation of the Potential for De-regulated Disposal of Very Low Level Wastes From Nuclear Power Plants Rev O 8-l-91 HI0890-0Q74A-HP0l
Table 3 Inhalation Dose At Site Boundary - Infant Most Limiting Dse = cs f18 X/Q µ A DCFi Where: Terms are identified in Table 1 and F16 = 2045 ml - infant annual breathing rate (RG 1.109) X/Q = 1.4 E-6 sec/ml - actual 5 year site average
µ = 3.8 m/sec average wind speed -'actual 1986 A - 1110 m2 - contaminated area DCFi - 4.37E-04 mR/50 yr
- pCi - Cs-137 infant liver (RG 1.109)
>stituting:
Dss = 3.16E-05 mRem/50 yt - maximum organ dose Rev 0 B-1-91 MI0890-0074A-HP01
FIGUIE ~B ' SURFACE RESULTS AINALT MEAS
-EXAMPLI : ONLY rl 0.0\
I
> rl
- DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
- 0l) which required implementation of actions to prevent future flooding. In 1988 it was decided to relocate the radwaste processing functions performed in the South Radwaste Building to a new addition at the East Radwaste Building to prevent the spread of contamination in the event of future cooling tower overflows. All radwaste processing equipment was relocated to the East Radwaste Building and the South Radwaste Building was decontaminated. The South Radwaste Building (then re-named the South Storage Building) has since been used for non-radiological m.aterial storage.
- 1. \
- LI I
- I.
Dear Mr. Slade:
SUBJECT:
REQUEST UNDER 10 CFR 20.302 TO RETAIN CONTAMINATED SOIL ONSITE AT PALISADES PLANT (TAC NO. 67408) By letters dated N*avember 12, 1987, and January 25, 1988, (Reference 1 of the enclosed Safety Evaluation (SE)), Consumers Power Company submitted a request pursuant to 10 CFR 20.302(a) for the disposal of contaminated soil onsite at the Palisades Plant. We have completed our review of the request and find your procedures, (~,!,th. comnitmeJJt~. -~.~ dQc.~m~o~~cl.~lP-"~~f e.r:-ence l) to be acceptable. Ttf'ls:' a.* ._
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.. Also-:~fir ure Minucfl':;(r .A mo shall'be"reporte(:f tottie NRC. in accordance with the applicable ODCM. change protocol. We fu.rther find that the radiological environmental impact of the proposed action meets the staff criteria as reflected in Reference 6 of the enclosed Safety Evaluation.
Sincerely, Brian Holian, Project Manager Project Directorate JII .. 1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated Rev o 8-1-91
Mr. Gerald B. Slade Consumers Power Company Palisades Plant cc: M. I. Miller, Esquire Sidley & Austin Nuclear Facilities and 54th Floor Environmental Monitoring One First National Plaza Section Office Chicago, Illinois 60603 Division of Radiological Health Mr. Thomas ~. McNish, Secretary P.O. Box 30035 Consumers Power Company Lansing, Michigan 48909 212 West Michigan Avenue Jackson, Michigan 49201 Gerald Charnoff, P.C. Shaw, Pittman, Potts & Trowbridge Judd L. Bacon, Esquire 2300 N. Street, N.W. Consumers Power Company Washington, D.C. 20037 212 West Michigan Avenue Jackson, Michigan 49201 Hr. David L. Brannen Vice President Regional Administrator, Region III Palisades Generating Company U.S. Nuclear Regulatory Conmission c/o Bechtel Power Corporation 799 Roosevelt Road 15740 Shady Grove Road Glen Ellyn, Illinois 60137. Gaithersburg, Maryland 20877 Jerry Sarno Roy w. Jones Township Supervisor Manager, Strategic Program Covert Township Development 36197 M-140 Highway Westinghouse Electric Corporation Covert, Michigan 49043 4350 Northern Pike Monroeville, Pennsylvania 15146 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. Patrick M. Donnelly Director, Safety and Licensing Palisades Plant 27780 Blue Star Memorial Hwy. Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Conmission Pa 11 sades Plant 27782 Blue Star Memorial Hwy. Covert, Michigan 49043 Rev 0 8-1-91
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 SAFETY EVALUATION RELATED TO THE PALISADES NUCLEAR PLANT RETENTION OF CONTAMINATED SOIL ONSITE INTRODUCTION In reference (1). Consumers Power Company {CPCo) requested approval pursuant to Section 20.302 of Title 10 of the Code of Federal Regulations {CFR) for the disposal of licensed material not previously considered by the NRC in the Palisades Final Environmental Statement (FES). dated June 1972. The petition submitted contains a detailed description of the licensed material {i.e ** contaminated so;1) subject to this 10 CFR 20.302 request. The 6,000 cubic feet of onsite contaminated soil contains a total radionuclide inventory of 5.1 mCi. based on radioactive material that was deposited in the soil due to the flooding of the South Radwaste Building. The contaminated area is located inside the security fences, and is on company controlled land. This area {South Radwaste Area) is fenced in, within the plant's south security fences. Thus it*is inaccessible to the public {see Figures 1 and 2). In the submittals (References 1-5), the licensee addressed specific information requested in accordance with 10 CFR 20.302(a), provided a detailed description of the licensed material, thoroughly analyzed and evaluated the environmental effects relative to retention of the contaminated soil onsite, and coD111itted to follow specific procedures to minimize the risk of unexpected exposures. Although the environmental impact of the proposed action is well within the dose criteria contained in the Conmission's Below Regulatory Concern {BRC) Policy Statement, dated July 3, 1990. the licensee has not requested. and the staff has not considered, the act.tons described:-herein to be exempt from NRC regulation. CPCo plans to dispose of the 6,000 cubic feet of contaminated soil ons;te pursuant to 10 CFR 20.302. The area, known as thd South Radwaste Area, has been contaminated by several cooling tower overflows (three times in an eight-year period), and has subsequently been redistributed by heavy rain showers. The cooling tower overflows were caused by instrument failures that opened the cooling tower bypass valve during.normal operation. This valve is now electri-cally isolated during cooling tower operation. The licensee conducted a soil survey because the South Radwaste Building was in the main path of the water overflows from the cooling tower. Survey results indicated that radioactive material was deposited in the soil. Although the majority of the radioactive material has been packaged as radwaste and will be subsequently shipped offsite (16 boxes each having a volume of 98 cubic feet, containing 85% of the estimated activity), a large volume of. low level contaminated soil is contained in the fenced area described as the South Radwaste Area. Rev 0 8-1-91
The specific area contaminated is noted as Area B on the survey grid map (sed Figure 2). The total activity of this area (5.1 mCi) is based on 6,000 cubic feet of soil contaminated with the spoils from the South Radwaste Building. Table 1 lists the principal nuclides identified in the contaminated soil. The activity in this table is based on measurements in 1987; see data from a recent submittal (Reference 5) shows that activity concentrations in the contaminated area have decreased by approximately 10 percent. The radionuclide half-lives, which are dominated by 30.-year Cs-137, meet the staff's 10 CFR 20.302 guidelines (Reference 6, which applies to radionuclides with half-lives less than 35 years). Tab le 1 Average Nuclide Concentration (pCi/g) Total Activity (mCi) Co-60 0.05 0.079 Cs-137 30 5.0 Total r.n7§ RADIOLOGICAL IMPACTS The licensee has evaluated the following potential exposure pathways to members of the general public from the radionuclides in the contaminated soil: (1) external exposure caused by direct radiation from radionuclides in the soil; and (2) internal exposure from inhalation of resuspended radionuclides. The staff has reviewed the licensee's calculational methods and assumptions and finds that they are consistent with NRC 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, 11 Revision 1, October 1977. The staff finds the assessment methodology_acceptable. The dose assessments are based on the following:
- 1. 5.1 mCi of contaminated soil distributed over 12,000 square foot planar source having a thickness of 0.5 feet {6000 cubic feet source volume).
- 2. Direct radiation exposure of 2000 hours per year.
- 3. Inhalation exposure based on 2000 hours per year is minimized due to six-inch layer of gravel {which inhibits wind erosion.)
- 4. Groundwater not considered because there are no domestic wells in the area down~gradient from the plant.
Doses calculated from these pathways are shown in Table 2. The total dose of 0.85 mrem per year is within the staff's guideline of 1 mrem per year {Reference 6). Rev 0 8-l-9l
Table 2 Whole Body Dose Received by Maximally Exposed Individual Pathway (mrem/year} Groundshine 0.85 Inhalation 0.00081 Groundwater Ingestion o.o TOTAL 0.85 The above doses are a small fraction of the 300 mrem received annually by members of the general public in the United States and Canada from sources of natural background radiation (Reference 7}. Based on our review of the proposed disposal of contaminated soil onsite, we conclude that: (l} The radioactive material will be disposed in a manner such that it is unlikely that the material will be recycled; (2} Doses to the total whole body and any body organ of a maximally exposed individual (a member of the general public or a non-occupationally exposed member} from the probable pathways of exposure to the disposed material will be less than l mrem per year; (3} Doses to the total whole body and any body organ of an inadvertent intruder from the probable pathways*of exposure will be less than 5 mrem per year since the burial location is on company-controlled land; (4} The radiation exposures to the nuclear station workers are small compared to the routine occupational exposures at the Palisades Plant; (5} The possible radiation risks to members of the general public as a result of such disposal are well below regulatory limits and small in comparison to the doses they receive each year from natural background radiation. The licensee's procedures and conmitments as documented in the submittal are acceptable, provided that they are permanently incorporated into the licensee ~ffsite Dose Calculation Manual (ODCM} as an Appendix, and that future modifications be reported to NRC in accordance with the applicable ODCH change protocol. Rev 0 8-1-91
REFERENCES 1 (1) CPC0 s letters, T. C. Berdine to NRC Document Control Desk, November 12, 1987 and January 25, 1 988. (2) Memorandum from L. J. Cunningham, DREP to T. R. Quay, T. V. Wambach, 11 Request for Additiona 1 Information (RAI), March 15, 1988, Apri 1 7, 11 1989, and January 12, 1990. (3) CPCo's supplement to Reference (1), J. L. Kuemin to NRC Document Control Desk, June 27, 1988. (4) CPCo's supplement to References (1, 2), G. B. Slade to NRC Document Control Desk, August 31, 1990. ( 5) CPCo's letter, T. P. Neal to B. Holian, October 13, 1990. (6) E. F. Branagan, Jr. and F. J. Congel, "Disposal of Slightly Contaminated Radioacthe Wastes from Nuclear Power Plants," presented at CONF-860203, Health Physics Considerations Decontamination Deconmissioning, Knoxville, TN, February, 1986. (7) National Counci 1 on Radiation Protection and Measurements, "Exposure of the Population in the United States and Canada from Natural Background Radiatfon, NCRP Report No. 94, Bethesda, MD. Deceni>er 30, 11 1987. Principal Contributor: J. L. Minns Rev O 8-1-91
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ATTACHMENT 2 BIG ROCK POINT INDEPENDENT SPENT FUEL STORAGE INSTALLATION 2015 RADIOACTIVE EFFLUENT RELEASE REPORT This report provides information relating to radioactive effluent releases and solid radioactive waste disposal at Big Rock Point (BRP) for the year 2015. The report format is detailed in the BRP Offsite Dose Calculation Manual (ODCM). Effluent releases from BRP are controlled by the Defueled Technical Specifications and the ODCM requirements. The ODCM was not revised in 2015. 2015 Operating History On January 8, 2007, the Nuclear Regulatory Commission (NRC) approved release of the former BRP nuclear plant property for unrestricted use in accordance with the BRP License Termination Plan 1
- On April 11, 2007, the license for BRP, DPR-06, was transferred to Entergy Nuclear Operations, Inc.
During 2015, normal independent spent fuel storage installation (ISFSI) operations continued. There were no operational activities that generated any solid radioactive waste. Liquid and gaseous effluent monitoring is no longer conducted as the former BRP nuclear plant property has been released from the license. Short-lived radionuclides, including iodine and noble gas, are neither expected nor reported.
- 1. Supplemental Information A. Batch Releases There were no batch releases of gaseous or liquid effluents during 2015. All batch releases of radioactive liquids as described in the ODCM ceased in 2004.
B. Abnormal Releases There were no abnormal releases from BRP during 2015. C. Radioactive Effluent Monitoring Instrumentation BRP ODCM currently specifies required actions when less than the minimum numbers of radioactive effluent monitoring instrument channels are operable. The ODCM also specifies these actions be taken when installed effluent monitoring systems are removed from service for decommissioning. All plant-installed liquid and gaseous radioactive effluent monitoring instrument channels have been permanently removed and dismantled. 1 Letter from the USN RC dated January B, 2007, "Release of Land from Part 50 License for Unrestricted Use" Page 1 of 2
- 2. Gaseous Effluents Although there were no gaseous effluents released during 2015, Table 2 provides a summary of all gaseous radioactive effluent monitoring conducted during the reporting period as required by the ODCM.
- 3. Liquid Effluents There were no liquid effluent batch releases during 2015. Table 3 lists and summarizes liquid effluent releases in accordance with the ODCM.
- 4. Solid Waste There was no solid radioactive waste generated or shipped during 2015.
- 5. Summary of Radiological Impact on Man The ODCM specifies that the annual effluent release report provide potential dose calculations based on measured effluent to liquid and gaseous pathways, if estimates of dose exceed one millirem to an organ or total body of any individual or more than one person-rem to the population within 50 miles. During 2015, there were no releases. Therefore, no calculations were required.
- 6. Offsite Dose Calculation Manual The ODCM describes the radiological release requirements for the BRP site.
There were no revisions to the ODCM in 2015.
- 7. Process Control Program (PCP)
The Process Control Program (PCP) describes solid waste processing and disposal methods utilized at the BRP site. The PCP was not revised during 2015. Page 2 of 2
TABLE 1 Big Rock Point Batch Releases January 1, 2015 to December 31, 2015 A.GASEOUS Units 1ST QTR 2NDQTR 3RD QTR 4TH QTR Number of Releases N/A N/A N/A N/A Total Release Time Minutes N/A N/A N/A N/A Maximum Release Time Minutes N/A N/A N/A N/A Average Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A B. LIQUID Units 1ST QTR 2NDQTR 3RD QTR 4TH QTR Number of Releases N/A N/A N/A N/A Total Release Time Minutes N/A N/A N/A N/A Maximum Release Time Minutes N/A N/A N/A N/A Average Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A Page 1 of 1
TABLE 2 Big Rock Point Gaseous Effluent Releases January 1, 2015 to December 31, 2015 1ST 2ND 3RD 4TH Es!Total A. FISSION AND ACTIVATION GASES Units QTR QTR QTR QTR Error%
- 1. Total release Ci N/A N/A N/A N/A
- 2. Average release rate for period µCi/sec N/A N/A N/A N/A N/A
- 3. Percent of annual ava EC % N/A N/A N/A N/A B. IODINES
- 1. Total iodine Ci N/A N/A N/A N/A
- 2. Averaqe release rate for period µCi/sec N/A N/A N/A N/A N/A
- 3. Percent of annual avi:i EC % N/A N/A N/A N/A C. PARTICULATES
- 1. Particulates with half-life >8 dav Ci N/A N/A N/A N/A
- 2. Averaae release rate for period uCi/sec NIA NIA NIA NIA NIA
- 3. Percent of annual avi:i EC % NIA NIA NIA NIA
- 4. Gross alpha radioactivity Ci NIA NIA NIA NIA D. TRITIUM
- 1. Total Release Ci NIA NIA NIA NIA
- 2. Averaae release rate for period uCi/sec NIA NIA NIA NIA
- 3. Percent of annual avi:i EC % NIA NIA NIA NIA E. WHOLE BODY DOSE
- 1. Beta Air dose at Site Boundary due to Noble Gases (ODCM Section 1, 1.3.2 a (1) (2)) mrads NIA NIA NIA NIA
- 2. Percent limit % NIA NIA N/A NIA
- 3. Gamma Air dose at Site Boundary due to Noble Gas (ODCM Section 1, 1.3.2 a (1) (2)) mrads NIA NIA NIA NIA
- 4. Percent limit % N/A N/A NIA NIA F. ORGAN DOSE (ODCM Section 1, 1.3.2b (1) (2))
- 1. Maximum organ dose to pubic based on Critical Receptors (child bone) mrem NIA NIA NIA NIA
- 2. Percent of limit (7.5 mrem/quarter) % N/A NIA NIA NIA Page 1 of 3
TABLE 2 Big Rock Point Gaseous Effluent Releases January 1, 2015 to December31, 2015
- 1. FISSION GASES Units 1STQTR 2ND QTR 3RDQTR 4TH QTR Krypton-85m Ci N/A N/A N/A N/A Krvoton-87 Ci N/A N/A N/A N/A Krvoton-88 Ci N/A N/A N/A N/A Xenon-133 Ci N/A N/A N/A N/A Xenon-133m Ci N/A N/A N/A N/A Xenon-135 Ci N/A N/A N/A N/A Xenon-135m Ci N/A N/A N/A N/A Xenon-138 Ci N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A
- 2. IODINES lodine-131 Ci N/A N/A N/A N/A lodine-132 Ci N/A N/A N/A N/A lodine-133 Ci N/A N/A N/A N/A lodine-134 Ci N/A N/A N/A N/A lodine-135 Ci N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A Page 2 of 3
TABLE 2 Big Rock Point Gaseous Effluent Releases January 1, 2015 to December 31, 2015
- 3. PARTICULATES* Units 1STQTR 2NDQTR 3RDQTR 4TH QTR Chromium-51 Ci N/A N/A N/A N/A Manrianese-54 Ci N/A N/A N/A N/A Cobalt-58 Ci N/A N/A N/A N/A lron-59 Ci N/A N/A N/A N/A Cobalt-60 Ci N/A N/A N/A N/A Zinc-65 Ci N/A N/A N/A N/A Silver-11 Om Ci N/A N/A N/A N/A Cesium-134 Ci N/A N/A N/A N/A Cesium-137 Ci N/A N/A N/A N/A Barium-140 Ci N/A N/A N/A N/A Europium-152 Ci N/A N/A N/A N/A Strontium-89 Ci N/A N/A N/A N/A Stronlium-90 Ci N/A N/A N/A N/A Net unidentified beta Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A
- Particulates with half-life >8 days Page 3 of 3
TABLE 3 Big Rock Point Liquid Effluent Releases January 1, 2015 to December 31, 2015 Es!Total A. FISSION AND ACTIVATION PRODUCTS Units 1STQTR 2ND QTR 3RD QTR 4TH QTR Error%
- 1. Total release (not includina tritium, aases, aloha) Ci N/A N/A N/A N/A N/A
- 2. Averaae diluted concentration durina period uCi/ml N/A N/A N/A N/A
- 3. Percent of EC % N/A N/A N/A N/A B TRITIUM
- 1. Total release Ci N/A N/A N/A N/A N/A
- 2. Averaae diluted concentration durina oeriod uCi/ml N/A N/A N/A N/A
- 3. Percent of EC % N/A N/A N/A N/A C DISSOLVED AND ENTRAINED GASES
- 1. Total release Ci N/A N/A N/A N/A N/A
- 2. Averaae diluted concentration durina period uCi/ml N/A N/A N/A N/A
- 3. Percent of EC % N/A N/A N/A N/A D. GROSS ALPHA RADIOACTIVITY Ci N/A N/A N/A N/A E. VOLUME OF WASTE RELEASED (Prior to dilution) Liters N/A N/A N/A N/A F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters N/A N/A N/A N/A G. MAXIMUM DOSE COMMITMENT WHOLEBODY mrem N/A N/A N/A N/A Percent of ODCM Section 1, 2.3.2 a (1.5 mrem) % N/A N/A N/A N/A H. MAXIMUM DOSE COMMITMEtilT - ORGAN Mrem N/A N/A N/A N/A Percent of ODCM Section 1, 2.3.2 b (3.0 mrem) % N/A N/A N/A N/A Page 1 of 2
TABLE 3 Big Rock Point Liquid Effluent Releases January 1, 2015 to December 31, 2015
- 1. NUCLIDES RELEASED Units 1STQTR 2NDQTR 3RD QTR 4THQTR Chromium-51 Ci -- -- -- --
Manoanese 54 Ci -- -- -- -- Cobalt-58 Ci -- -- -- -- lron-59 Ci -- -- -- -- Cobalt-60 Ci -- -- -- -- Zinc-65 Ci -- -- -- -- Strontium-89 Ci -- -- -- -- Strontium-90 Ci -- -- -- -- Molvbdenum-99 Ci -- -- -- -- Silver-110m Ci -- -- -- -- lodine-131 Ci -- -- -- -- Cesium-134 Ci -- -- -- -- Cesium-137 Ci -- -- -- -- Antimony-125 Ci -- -- -- -- Tin-113 Ci -- -- -- -- Net Unidentified Beta Ci -- -- -- -- Fission & Activation Product Total Ci -- -- -- -- Xenon-133 Ci -- -- -- -- Tritium Ci -- -- -- -- Grand Total Ci -- -- -- -- Page 2 of 2}}