LIC-20-0009, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report
| ML20121A092 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/30/2020 |
| From: | Blome B Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-20-0009 | |
| Download: ML20121A092 (573) | |
Text
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Omaha Public Power District April 30, 2020 LIC-20-0009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285
Subject:
Fort Calhoun Station (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report
References:
FCS Permanently Defueled Technical Specifications (PDTS) Sections 5.9.4(a) and 5.9.4(b)
Pursuant to Fort Calhoun Station (FCS), Unit No. 1, Permanently Defueled Technical Specifications (PDTS), Sections 5.9.4(a), and 5.9.4(b), Omaha Public Power District (OPPD) provides the Annual Radiological Effluent Release Report and the Annual Radiological Environmental Operating Report.
The Annual Radiological Effluent Release Report is submitted in accordance with PDTS 5.9.4(a) and encompasses the period of January 1, 2019 through December 31, 2019. The report is presented in the format outlined in Regulatory Guide 1.21, Revision 1. In addition, the report provides the results of quarterly dose calculations performed in accordance with the Offsite Dose Calculation Manual (ODCM). In accordance with PDTS Section 5.17(d), Section VII of the Annual Radiological Effluent Release Report includes the revisions to the ODCM made during this period.
Section VII of the Annual Radiological Effluent Release Report also includes Process Control Program (PCP) changes made during this period.
The Annual Radiological Environmental Operating Report is submitted in accordance with PDTS 5.9.4(b) and encompasses the period of January 1, 2019 through December 31, 2019.
No commitments to the NRC are contained in this letter.
444 SOUTH 16TH STREET MALL
- OMAHA, NE 68102-2247 EMPLO'fMENT WITH EQUAL OPPORTUNIT'(.
U. S. Nuclear Regulatory Commission LIC-20-0009 Page2 Please contact Mr. Bradley H. Blome at (402) 533-6041 if you should have any questions.
Respectfully, Bradley H. Blome Director, Licensing and Regulatory Assurance BHB/cac
Enclosures:
- 2. Annual Radiological Environmental Operating Report c: S. A. Morris, NRC Regional Administrator, Region IV J. D. Parrott, NRC Senior Project Manager C. D. Steely, NRC Senior Health Physicist, Region IV
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TABLE III.1 BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
JANUARY THROUGH DECEMBER 2019 A. Liquid Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
- 1. Number of Batch Releases: 5 4 12 2 23
- 2. Total Time Period for Batch Releases(min): 3,040 620 1,635 285 5,580
- 3. Maximum Time Period for Batch Releases(min): 2,558 160 167 145 2,558
- 4. Average Time Period for Batch Releases(min): 608 155 136 143 243
- 5. Minimum Time Period for Batch Releases(min): 100 150 100 140 100
- 6. Average Dilution Stream Flow During Periods of Release into the Missouri River(mls/min): 1.718E+07 2.739E+07 2.741E+07 2.741E+07 2.518E+07 B. Gaseous Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year
- 1. Number of Batch Releases:
- 2. Total Time Period for Batch Releases(min):
- 3. Maximum Time Period for Batch Releases(min):
- 4. Average Time Period for Batch Releases(min):
- 5. Minimum Time Period for Batch Releases(min):
III-2
TABLE III.2 ABNORMAL BATCH LIQUID AND GASEOUS RELEASE
SUMMARY
JANUARY THROUGH DECEMBER 2019 A. Liquid Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year Number of Releases: 0 0 0 0 0 Total Activity Releases(Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B. Gaseous Releases All Sources 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year Number of Releases: 0 0 0 0 0 Total Activity Releases (Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 III-3
TABLE III.3 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 2019 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activation Gases Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 9.86E-01 9.86E-01 Average Release Rate (uCi/sec): 0.00E+00 0.00E+00 0.00E+00 2.51E-02 2.51E-02 Total Error (%): 25.00 B. Iodines Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate (uCi/sec): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Error (%): 21.2 C. Particulates Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate (uCi/sec): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Error (%): 20.62 Gross Alpha:
Total Error (%): 20.62 3.52E-07 1.69E-06 9.57E-07 1.83E-06 4.83E-06 D. Tritium Total Release (Ci): 1.84E-01 1.16E-01 2.84E-01 2.96E-01 8.79E-01 Average Release Rate (uCi/sec): 1.84E-03 1.14E-03 2.77E-03 2.69E-03 2.11E-03 Total Error (%): 25.08 E. Carbon-14 Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Release Rate (uCi/sec): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Error (%): 20.62 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).
III-4
TABLE III.4 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 2019 Batch Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter YEAR Fission & Activation Gases Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium and Gross Alpha NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).
III-5
TABLE III.5 GASEOUS EFFLUENTS--GROUND LEVEL RELEASES JANUARY THROUGH DECEMBER 2019 Continuous Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases KR-85 0.00E+00 0.00E+00 0.00E+00 9.86E-01 9.86E-01 Totals for Period: 0.00E+00 0.00E+00 0.00E+00 9.86E-01 9.86E-01 Iodines Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Particulates Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium and Gross Alpha ALPHA 3.52E-07 1.69E-06 9.57E-07 1.83E-06 4.83E-06 H-3 1.84E-01 1.16E-01 2.84E-01 2.96E-01 8.79E-01 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).
III-6
TABLE III.6 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES JANUARY THROUGH DECEMBER 2019 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year A. Fission & Activiation Products Total Release (No H-3,Gas,Alpha) (Ci): 1.14E-04 2.45E-04 4.37E-04 1.35E-04 9.30E-04 Average Diluted Concentration (uCi/mL): 4.69E-08 5.76E-08 1.17E-07 3.45E-08 2.62E-07 10 CFR 20, App. B Limit 1.00E-06 (uCi/mL)
Percent of Limit (%): 4.69E+00 5.76E+00 1.17E+01 3.45E+00 2.62E+01 Total Error (%): 24.13 B. Tritium Total Release (Ci): 2.89E-02 4.55E-02 5.92E-01 2.74E-01 9.40E-01 Average Diluted Concentration (uCi/mL): 1.19E-05 1.07E-05 1.58E-04 7.02E-05 2.65E-04 10 CFR 20, App. B Limit 1.00E-03(uCi/mL)
Percent of Limit (%): 1.19E+00 1.07E+00 1.58E+01 7.02E+00 2.65E+01 Total Error (%): 25.08 C. Dissolved & Entrained Gases Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average Diluted Concentration (uCi/mL): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ODCM Limit 2.00E-04 (uCi/mL):
Percent of Limit (%): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Error (%): 18.14 D. Gross Alpha Radioactivity Total Release (Ci): 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Error (%): 27.22 E. Volume of Waste Released Prior to Dilution (Liters):
1.60E+05 8.51E+04 2.51E+05 4.36E+04 5.40E+05 F. Volume of Dilution Water During Releases (Liters): 1.04E+07 1.69E+07 4.46E+07 7.77E+06 7.96E+07 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).
III-7
TABLE III.7 LIQUID EFFLUENTS JANUARY THROUGH DECEMBER 2019 Batch Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Gases CS-137 5.14E-05 1.01E-04 1.94E-04 6.65E-05 4.13E-04 CS-134 0.00E+00 0.00E+00 1.58E-07 0.00E+00 1.58E-07 NI-63 5.56E-05 1.32E-04 1.97E-04 5.89E-05 4.43E-04 CO-60 7.02E-06 1.27E-05 4.50E-05 9.27E-06 7.39E-05 Totals for Period: 1.14E-04 2.45E-04 4.37E-04 1.35E-04 9.30E-04 Dissolved & Entrained Gases Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium and Gross Alpha H-3 2.89E-02 4.55E-02 5.92E-01 2.74E-01 9.40E-01 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD) values.
Reported Alpha activity was attributed to natural short-lived radionuclides. This was confirmed by quarterly offside vendor analysis.
III-8
TABLE III.8 LIQUID EFFLUENTS JANUARY THROUGH DECEMBER 2019 Continuous Mode Nuclides(Ci) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Fission & Activation Products Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dissolved & Entrained Gases Totals for Period: 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium and Gross Alpha H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).
III-9
TABLE III.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2019 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-1A Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-1B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-2 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-2A Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-2B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-3 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-3A Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 6.61E-01 0.00E+00 Total Gamma 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MW-3B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total Gamma 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MW-4A Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 6.15E-01 Total Gamma 0.00E+00 III-10
TABLE III.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2019 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-4B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-5A Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 5.09E-01 Total Gamma 0.00E+00 MW-6 Tritium 2.57E+02 0.00E+00 2.62E+02 0.00E+00 FE-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 8.50E-01 0.00E+00 0.00E+00 Total Gamma 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MW-5B Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-7 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-9 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-10 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-11 Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 0.00E+00 NI-63 0.00E+00 Sr-90 0.00E+00 Total Gamma 0.00E+00 MW-12A Tritium FE-55 NI-63 Sr-90 Total Gamma III-11
TABLE III.9 GROUNDWATER ANALYSIS RESULTS pCi/L JANUARY THROUGH DECEMBER 2019 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter MW-12B Tritium FE-55 NI-63 Sr-90 Total Gamma EAST LAGOON Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 0.00E+00 0.00E+00 WEST LAGOON Tritium 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NORTH STORMWATER HDR Tritium 0.00E+00 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 0.00E+00 SOUTH STORMWATER HDR Tritium 0.00E+00 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 0.00E+00 SW-8 NORTH PA Tritium 0.00E+00 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 0.00E+00 SW-6 ISFSI Tritium 0.00E+00 0.00E+00 0.00E+00 FE-55 NI-63 Sr-90 Total Gamma 0.00E+00 0.00E+00 0.00E+00 NOTE: Values reported as zero are determined to be below the Lower Limit of Detection (LLD).
Only Tritium and Gamma are required for each sampling event.
Hard to detect (HTD) nuclide sampling frequency is per station procedures.
Missed sampling events are covered in the executive summary.
III-12
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,9
TABLE IV-A- 1 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 1 RES AT 4.36 MILES N ANNUAL_BETA_AIR_DOSE = 4.69E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.14E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.71E-08 : 2.71E-08 : 2.71E-08 : 2.71E-08 : 2.71E-08 : 2.71E-08 : 7.21E-08 : 3.26E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 1.54E-06 : 1.54E-06 : 1.50E-08 : 1.54E-06 : 1.54E-06 : 1.54E-06 : 1.55E-06 : 1.54E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.56E-06 : 1.56E-06 : 2.01E-08 : 1.56E-06 : 1.56E-06 : 1.56E-06 : 1.57E-06 : 1.56E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.37E-06 : 1.37E-06 : 2.85E-08 : 1.37E-06 : 1.37E-06 : 1.37E-06 : 1.38E-06 : 1.37E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 7.90E-07 : 7.90E-07 : 1.18E-08 : 7.91E-07 : 7.90E-07 : 7.90E-07 : 7.97E-07 : 7.90E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 5
TABLE IV-A- 2 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 2 RES AT 1.93 MILES NNE ANNUAL_BETA_AIR_DOSE = 6.70E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 5.91E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.87E-08 : 3.87E-08 : 3.87E-08 : 3.87E-08 : 3.87E-08 : 3.87E-08 : 1.03E-07 : 4.65E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 2.20E-06 : 2.20E-06 : 2.29E-08 : 2.20E-06 : 2.20E-06 : 2.20E-06 : 2.21E-06 : 2.20E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.22E-06 : 2.22E-06 : 3.08E-08 : 2.22E-06 : 2.22E-06 : 2.22E-06 : 2.24E-06 : 2.22E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.96E-06 : 1.96E-06 : 4.36E-08 : 1.96E-06 : 1.96E-06 : 1.96E-06 : 1.98E-06 : 1.96E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.13E-06 : 1.13E-06 : 1.80E-08 : 1.13E-06 : 1.13E-06 : 1.13E-06 : 1.14E-06 : 1.13E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 6
TABLE IV-A- 3 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 3 RES AT 1.52 MILES NE ANNUAL_BETA_AIR_DOSE = 7.92E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.99E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.58E-08 : 4.58E-08 : 4.58E-08 : 4.58E-08 : 4.58E-08 : 4.58E-08 : 1.22E-07 : 5.50E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 2.60E-06 : 2.60E-06 : 2.83E-08 : 2.60E-06 : 2.60E-06 : 2.60E-06 : 2.61E-06 : 2.60E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.63E-06 : 2.63E-06 : 3.80E-08 : 2.63E-06 : 2.63E-06 : 2.63E-06 : 2.65E-06 : 2.63E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.32E-06 : 2.32E-06 : 5.38E-08 : 2.32E-06 : 2.32E-06 : 2.32E-06 : 2.34E-06 : 2.32E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.33E-06 : 1.33E-06 : 2.22E-08 : 1.34E-06 : 1.33E-06 : 1.33E-06 : 1.35E-06 : 1.33E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 7
TABLE IV-A- 4 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 4 RES AT 4.79 MILES ENE ANNUAL_BETA_AIR_DOSE = 7.92E-07 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.99E-09 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.58E-09 : 4.58E-09 : 4.58E-09 : 4.58E-09 : 4.58E-09 : 4.58E-09 : 1.22E-08 : 5.50E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 2.60E-07 : 2.60E-07 : 2.50E-09 : 2.60E-07 : 2.60E-07 : 2.60E-07 : 2.61E-07 : 2.60E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.63E-07 : 2.63E-07 : 3.36E-09 : 2.63E-07 : 2.63E-07 : 2.63E-07 : 2.64E-07 : 2.63E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.32E-07 : 2.32E-07 : 4.76E-09 : 2.32E-07 : 2.32E-07 : 2.32E-07 : 2.33E-07 : 2.32E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.33E-07 : 1.33E-07 : 1.96E-09 : 1.33E-07 : 1.33E-07 : 1.33E-07 : 1.35E-07 : 1.33E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 8
TABLE IV-A- 5 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 5 RES AT 4.67 MILES E ANNUAL_BETA_AIR_DOSE = 1.65E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.45E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 9.51E-09 : 9.51E-09 : 9.51E-09 : 9.51E-09 : 9.51E-09 : 9.51E-09 : 2.53E-08 : 1.14E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 5.41E-07 : 5.41E-07 : 5.20E-09 : 5.41E-07 : 5.40E-07 : 5.40E-07 : 5.43E-07 : 5.40E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.46E-07 : 5.45E-07 : 6.99E-09 : 5.46E-07 : 5.45E-07 : 5.45E-07 : 5.49E-07 : 5.45E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.82E-07 : 4.82E-07 : 9.90E-09 : 4.82E-07 : 4.82E-07 : 4.82E-07 : 4.85E-07 : 4.82E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.77E-07 : 2.77E-07 : 4.08E-09 : 2.77E-07 : 2.77E-07 : 2.77E-07 : 2.80E-07 : 2.77E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV- 9
TABLE IV-A- 6 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 6 RES AT 4.22 MILES ESE ANNUAL_BETA_AIR_DOSE = 1.77E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.56E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.02E-08 : 1.02E-08 : 1.02E-08 : 1.02E-08 : 1.02E-08 : 1.02E-08 : 2.72E-08 : 1.23E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 5.81E-07 : 5.81E-07 : 5.72E-09 : 5.81E-07 : 5.81E-07 : 5.81E-07 : 5.83E-07 : 5.81E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.86E-07 : 5.86E-07 : 7.68E-09 : 5.86E-07 : 5.86E-07 : 5.86E-07 : 5.90E-07 : 5.86E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.18E-07 : 5.17E-07 : 1.09E-08 : 5.18E-07 : 5.17E-07 : 5.17E-07 : 5.21E-07 : 5.17E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.98E-07 : 2.98E-07 : 4.49E-09 : 2.98E-07 : 2.98E-07 : 2.98E-07 : 3.00E-07 : 2.98E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-10
TABLE IV-A- 7 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 7 RES AT 1.67 MILES SE ANNUAL_BETA_AIR_DOSE = 2.80E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.47E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.62E-07 : 1.62E-07 : 1.62E-07 : 1.62E-07 : 1.62E-07 : 1.62E-07 : 4.31E-07 : 1.95E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 9.21E-06 : 9.21E-06 : 9.84E-08 : 9.22E-06 : 9.21E-06 : 9.21E-06 : 9.25E-06 : 9.21E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 9.29E-06 : 9.29E-06 : 1.32E-07 : 9.30E-06 : 9.29E-06 : 9.29E-06 : 9.36E-06 : 9.29E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 8.21E-06 : 8.21E-06 : 1.87E-07 : 8.22E-06 : 8.20E-06 : 8.20E-06 : 8.27E-06 : 8.20E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 4.72E-06 : 4.72E-06 : 7.72E-08 : 4.72E-06 : 4.72E-06 : 4.72E-06 : 4.77E-06 : 4.72E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-11
TABLE IV-A- 8 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 8 RES AT 0.65 MILES SSE ANNUAL_BETA_AIR_DOSE = 3.11E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.74E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.80E-06 : 1.80E-06 : 1.80E-06 : 1.80E-06 : 1.80E-06 : 1.80E-06 : 4.78E-06 : 2.16E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 1.02E-04 : 1.02E-04 : 1.18E-06 : 1.02E-04 : 1.02E-04 : 1.02E-04 : 1.03E-04 : 1.02E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.03E-04 : 1.03E-04 : 1.59E-06 : 1.03E-04 : 1.03E-04 : 1.03E-04 : 1.04E-04 : 1.03E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 9.10E-05 : 9.10E-05 : 2.25E-06 : 9.11E-05 : 9.10E-05 : 9.10E-05 : 9.17E-05 : 9.10E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 5.24E-05 : 5.23E-05 : 9.29E-07 : 5.24E-05 : 5.23E-05 : 5.23E-05 : 5.29E-05 : 5.23E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-12
TABLE IV-A- 9 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 9 RES AT 0.73 MILES S ANNUAL_BETA_AIR_DOSE = 3.90E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.44E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.25E-06 : 2.25E-06 : 2.25E-06 : 2.25E-06 : 2.25E-06 : 2.25E-06 : 5.99E-06 : 2.71E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 1.28E-04 : 1.28E-04 : 1.47E-06 : 1.28E-04 : 1.28E-04 : 1.28E-04 : 1.29E-04 : 1.28E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.29E-04 : 1.29E-04 : 1.97E-06 : 1.29E-04 : 1.29E-04 : 1.29E-04 : 1.30E-04 : 1.29E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.14E-04 : 1.14E-04 : 2.79E-06 : 1.14E-04 : 1.14E-04 : 1.14E-04 : 1.15E-04 : 1.14E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 6.57E-05 : 6.57E-05 : 1.15E-06 : 6.57E-05 : 6.57E-05 : 6.57E-05 : 6.64E-05 : 6.57E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-13
TABLE IV-A-10 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 10 RES AT 0.65 MILES SSW ANNUAL_BETA_AIR_DOSE = 1.65E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.45E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 9.51E-07 : 9.51E-07 : 9.51E-07 : 9.51E-07 : 9.51E-07 : 9.51E-07 : 2.53E-06 : 1.14E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 5.41E-05 : 5.41E-05 : 6.18E-07 : 5.41E-05 : 5.40E-05 : 5.40E-05 : 5.43E-05 : 5.40E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.46E-05 : 5.45E-05 : 8.30E-07 : 5.46E-05 : 5.45E-05 : 5.45E-05 : 5.50E-05 : 5.45E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.82E-05 : 4.82E-05 : 1.17E-06 : 4.82E-05 : 4.82E-05 : 4.82E-05 : 4.86E-05 : 4.82E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 2.77E-05 : 2.77E-05 : 4.85E-07 : 2.77E-05 : 2.77E-05 : 2.77E-05 : 2.80E-05 : 2.77E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-14
TABLE IV-A-11 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 11 RES AT 0.73 MILES SW ANNUAL_BETA_AIR_DOSE = 4.08E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.60E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.36E-07 : 2.36E-07 : 2.36E-07 : 2.36E-07 : 2.36E-07 : 2.36E-07 : 6.27E-07 : 2.83E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 1.34E-05 : 1.34E-05 : 1.53E-07 : 1.34E-05 : 1.34E-05 : 1.34E-05 : 1.35E-05 : 1.34E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.35E-05 : 1.35E-05 : 2.05E-07 : 1.35E-05 : 1.35E-05 : 1.35E-05 : 1.36E-05 : 1.35E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.20E-05 : 1.20E-05 : 2.90E-07 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 : 1.20E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 6.88E-06 : 6.87E-06 : 1.20E-07 : 6.88E-06 : 6.87E-06 : 6.87E-06 : 6.95E-06 : 6.87E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-15
TABLE IV-A-12 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 12 RES AT 1.06 MILES WSW ANNUAL_BETA_AIR_DOSE = 1.83E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.61E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.06E-07 : 1.06E-07 : 1.06E-07 : 1.06E-07 : 1.06E-07 : 1.06E-07 : 2.81E-07 : 1.27E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 6.01E-06 : 6.01E-06 : 6.95E-08 : 6.01E-06 : 6.01E-06 : 6.01E-06 : 6.03E-06 : 6.01E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 6.06E-06 : 6.06E-06 : 9.33E-08 : 6.07E-06 : 6.06E-06 : 6.06E-06 : 6.11E-06 : 6.06E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.36E-06 : 5.35E-06 : 1.32E-07 : 5.36E-06 : 5.35E-06 : 5.35E-06 : 5.40E-06 : 5.35E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 3.08E-06 : 3.08E-06 : 5.45E-08 : 3.08E-06 : 3.08E-06 : 3.08E-06 : 3.11E-06 : 3.08E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-16
TABLE IV-A-13 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 13 RES AT 1.20 MILES W ANNUAL_BETA_AIR_DOSE = 4.45E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.92E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.57E-07 : 2.57E-07 : 2.57E-07 : 2.57E-07 : 2.57E-07 : 2.57E-07 : 6.84E-07 : 3.09E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 1.46E-05 : 1.46E-05 : 1.63E-07 : 1.46E-05 : 1.46E-05 : 1.46E-05 : 1.47E-05 : 1.46E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.48E-05 : 1.47E-05 : 2.19E-07 : 1.48E-05 : 1.47E-05 : 1.47E-05 : 1.49E-05 : 1.47E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.30E-05 : 1.30E-05 : 3.10E-07 : 1.30E-05 : 1.30E-05 : 1.30E-05 : 1.31E-05 : 1.30E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 7.49E-06 : 7.49E-06 : 1.28E-07 : 7.50E-06 : 7.49E-06 : 7.49E-06 : 7.57E-06 : 7.49E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-17
TABLE IV-A-14 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 14 RES AT 2.60 MILES WNW ANNUAL_BETA_AIR_DOSE = 7.31E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.45E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.23E-08 : 4.23E-08 : 4.23E-08 : 4.23E-08 : 4.23E-08 : 4.23E-08 : 1.12E-07 : 5.08E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 2.40E-06 : 2.40E-06 : 2.50E-08 : 2.40E-06 : 2.40E-06 : 2.40E-06 : 2.41E-06 : 2.40E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.42E-06 : 2.42E-06 : 3.35E-08 : 2.43E-06 : 2.42E-06 : 2.42E-06 : 2.44E-06 : 2.42E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.14E-06 : 2.14E-06 : 4.75E-08 : 2.14E-06 : 2.14E-06 : 2.14E-06 : 2.16E-06 : 2.14E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.23E-06 : 1.23E-06 : 1.96E-08 : 1.23E-06 : 1.23E-06 : 1.23E-06 : 1.24E-06 : 1.23E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-18
TABLE IV-A-15 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 15 RES AT 2.40 MILES NW ANNUAL_BETA_AIR_DOSE = 1.89E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.67E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.09E-07 : 1.09E-07 : 1.09E-07 : 1.09E-07 : 1.09E-07 : 1.09E-07 : 2.90E-07 : 1.31E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 6.21E-06 : 6.21E-06 : 6.44E-08 : 6.21E-06 : 6.21E-06 : 6.21E-06 : 6.23E-06 : 6.21E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 6.26E-06 : 6.26E-06 : 8.64E-08 : 6.27E-06 : 6.26E-06 : 6.26E-06 : 6.31E-06 : 6.26E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.53E-06 : 5.53E-06 : 1.22E-07 : 5.54E-06 : 5.53E-06 : 5.53E-06 : 5.57E-06 : 5.53E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 3.18E-06 : 3.18E-06 : 5.05E-08 : 3.18E-06 : 3.18E-06 : 3.18E-06 : 3.21E-06 : 3.18E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-19
TABLE IV-A-16 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 16 RES AT 2.08 MILES NNW ANNUAL_BETA_AIR_DOSE = 4.20E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.71E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.43E-07 : 2.43E-07 : 2.43E-07 : 2.43E-07 : 2.43E-07 : 2.43E-07 : 6.46E-07 : 2.92E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : : : : : : : : :
ADULT : 1.38E-05 : 1.38E-05 : 1.47E-07 : 1.38E-05 : 1.38E-05 : 1.38E-05 : 1.39E-05 : 1.38E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.39E-05 : 1.39E-05 : 1.98E-07 : 1.40E-05 : 1.39E-05 : 1.39E-05 : 1.40E-05 : 1.39E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.23E-05 : 1.23E-05 : 2.80E-07 : 1.23E-05 : 1.23E-05 : 1.23E-05 : 1.24E-05 : 1.23E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 7.08E-06 : 7.08E-06 : 1.16E-07 : 7.09E-06 : 7.08E-06 : 7.08E-06 : 7.15E-06 : 7.08E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-20
TABLE IV-A-17 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 17 VEG AT 2.23 MILES NNE ANNUAL_BETA_AIR_DOSE = 4.27E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.76E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.47E-08 : 2.47E-08 : 2.47E-08 : 2.47E-08 : 2.47E-08 : 2.47E-08 : 6.56E-08 : 2.96E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 2.67E-06 : 2.59E-06 : 3.77E-06 : 2.80E-06 : 2.54E-06 : 2.54E-06 : 2.54E-06 : 2.54E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.10E-06 : 2.97E-06 : 5.82E-06 : 3.31E-06 : 2.90E-06 : 2.90E-06 : 2.90E-06 : 2.90E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 5.00E-06 : 4.56E-06 : 1.43E-05 : 5.28E-06 : 4.51E-06 : 4.51E-06 : 4.51E-06 : 4.51E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-21
TABLE IV-A-18 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 18 VEG AT 3.20 MILES NE ANNUAL_BETA_AIR_DOSE = 1.28E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.13E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 7.40E-09 : 7.40E-09 : 7.40E-09 : 7.40E-09 : 7.40E-09 : 7.40E-09 : 1.97E-08 : 8.88E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 7.97E-07 : 7.77E-07 : 1.06E-06 : 8.35E-07 : 7.62E-07 : 7.62E-07 : 7.62E-07 : 7.62E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 9.26E-07 : 8.89E-07 : 1.63E-06 : 9.86E-07 : 8.71E-07 : 8.71E-07 : 8.71E-07 : 8.71E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.49E-06 : 1.37E-06 : 4.01E-06 : 1.57E-06 : 1.35E-06 : 1.35E-06 : 1.35E-06 : 1.35E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-22
TABLE IV-A-19 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 19 VEG AT 4.79 MILES ENE ANNUAL_BETA_AIR_DOSE = 7.92E-07 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.99E-09 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.58E-09 : 4.58E-09 : 4.58E-09 : 4.58E-09 : 4.58E-09 : 4.58E-09 : 1.22E-08 : 5.50E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 4.84E-07 : 4.77E-07 : 3.77E-07 : 4.98E-07 : 4.71E-07 : 4.71E-07 : 4.71E-07 : 4.71E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.59E-07 : 5.46E-07 : 5.82E-07 : 5.80E-07 : 5.39E-07 : 5.39E-07 : 5.39E-07 : 5.39E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 8.86E-07 : 8.43E-07 : 1.43E-06 : 9.14E-07 : 8.37E-07 : 8.37E-07 : 8.37E-07 : 8.37E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-23
TABLE IV-A-20 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 20 VEG AT 4.22 MILES ESE ANNUAL_BETA_AIR_DOSE = 1.77E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.56E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.02E-08 : 1.02E-08 : 1.02E-08 : 1.02E-08 : 1.02E-08 : 1.02E-08 : 2.72E-08 : 1.23E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 1.09E-06 : 1.07E-06 : 1.21E-06 : 1.14E-06 : 1.05E-06 : 1.05E-06 : 1.05E-06 : 1.05E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.27E-06 : 1.22E-06 : 1.86E-06 : 1.33E-06 : 1.20E-06 : 1.20E-06 : 1.20E-06 : 1.20E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.02E-06 : 1.88E-06 : 4.58E-06 : 2.11E-06 : 1.87E-06 : 1.87E-06 : 1.87E-06 : 1.87E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-24
TABLE IV-A-21 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 21 VEG AT 2.15 MILES SE ANNUAL_BETA_AIR_DOSE = 1.40E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.24E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.10E-08 : 8.10E-08 : 8.10E-08 : 8.10E-08 : 8.10E-08 : 8.10E-08 : 2.15E-07 : 9.73E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 8.80E-06 : 8.54E-06 : 1.36E-05 : 9.28E-06 : 8.34E-06 : 8.34E-06 : 8.34E-06 : 8.34E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.02E-05 : 9.77E-06 : 2.10E-05 : 1.10E-05 : 9.54E-06 : 9.54E-06 : 9.54E-06 : 9.54E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.66E-05 : 1.50E-05 : 5.15E-05 : 1.76E-05 : 1.48E-05 : 1.48E-05 : 1.48E-05 : 1.48E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-25
TABLE IV-A-22 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 22 VEG AT 0.94 MILES SSE ANNUAL_BETA_AIR_DOSE = 1.40E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.24E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 8.10E-07 : 2.15E-06 : 9.73E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 8.85E-05 : 8.56E-05 : 1.51E-04 : 9.39E-05 : 8.34E-05 : 8.34E-05 : 8.34E-05 : 8.34E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.03E-04 : 9.80E-05 : 2.33E-04 : 1.12E-04 : 9.54E-05 : 9.54E-05 : 9.54E-05 : 9.54E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.68E-04 : 1.50E-04 : 5.73E-04 : 1.79E-04 : 1.48E-04 : 1.48E-04 : 1.48E-04 : 1.48E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-26
TABLE IV-A-23 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 23 VEG AT 0.73 MILES S ANNUAL_BETA_AIR_DOSE = 3.90E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.44E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.25E-06 : 2.25E-06 : 2.25E-06 : 2.25E-06 : 2.25E-06 : 2.25E-06 : 5.99E-06 : 2.71E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 2.45E-04 : 2.38E-04 : 3.77E-04 : 2.58E-04 : 2.32E-04 : 2.32E-04 : 2.32E-04 : 2.32E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.85E-04 : 2.72E-04 : 5.82E-04 : 3.07E-04 : 2.65E-04 : 2.65E-04 : 2.65E-04 : 2.65E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.61E-04 : 4.17E-04 : 1.43E-03 : 4.89E-04 : 4.12E-04 : 4.12E-04 : 4.12E-04 : 4.12E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-27
TABLE IV-A-24 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 24 VEG AT 0.99 MILES SSW ANNUAL_BETA_AIR_DOSE = 6.70E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 5.91E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.87E-07 : 3.87E-07 : 3.87E-07 : 3.87E-07 : 3.87E-07 : 3.87E-07 : 1.03E-06 : 4.65E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 4.18E-05 : 4.07E-05 : 5.81E-05 : 4.39E-05 : 3.99E-05 : 3.99E-05 : 3.99E-05 : 3.99E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.87E-05 : 4.66E-05 : 8.97E-05 : 5.20E-05 : 4.56E-05 : 4.56E-05 : 4.56E-05 : 4.56E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 7.84E-05 : 7.17E-05 : 2.20E-04 : 8.27E-05 : 7.09E-05 : 7.09E-05 : 7.09E-05 : 7.09E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-28
TABLE IV-A-25 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 25 VEG AT 1.43 MILES SW ANNUAL_BETA_AIR_DOSE = 7.92E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.99E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.58E-08 : 4.58E-08 : 4.58E-08 : 4.58E-08 : 4.58E-08 : 4.58E-08 : 1.22E-07 : 5.50E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 4.94E-06 : 4.81E-06 : 6.71E-06 : 5.18E-06 : 4.71E-06 : 4.71E-06 : 4.71E-06 : 4.71E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.74E-06 : 5.51E-06 : 1.04E-05 : 6.12E-06 : 5.39E-06 : 5.39E-06 : 5.39E-06 : 5.39E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 9.24E-06 : 8.47E-06 : 2.55E-05 : 9.74E-06 : 8.37E-06 : 8.37E-06 : 8.37E-06 : 8.37E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-29
TABLE IV-A-26 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 26 VEG AT 1.13 MILES WSW ANNUAL_BETA_AIR_DOSE = 1.52E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.34E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.80E-08 : 8.80E-08 : 8.80E-08 : 8.80E-08 : 8.80E-08 : 8.80E-08 : 2.34E-07 : 1.06E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 9.52E-06 : 9.26E-06 : 1.36E-05 : 1.00E-05 : 9.07E-06 : 9.07E-06 : 9.07E-06 : 9.07E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.11E-05 : 1.06E-05 : 2.10E-05 : 1.18E-05 : 1.04E-05 : 1.04E-05 : 1.04E-05 : 1.04E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.79E-05 : 1.63E-05 : 5.15E-05 : 1.89E-05 : 1.61E-05 : 1.61E-05 : 1.61E-05 : 1.61E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-30
TABLE IV-A-27 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 27 VEG AT 1.30 MILES W ANNUAL_BETA_AIR_DOSE = 3.53E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.12E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.04E-07 : 2.04E-07 : 2.04E-07 : 2.04E-07 : 2.04E-07 : 2.04E-07 : 5.43E-07 : 2.45E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 2.20E-05 : 2.14E-05 : 2.79E-05 : 2.30E-05 : 2.10E-05 : 2.10E-05 : 2.10E-05 : 2.10E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.55E-05 : 2.45E-05 : 4.31E-05 : 2.71E-05 : 2.41E-05 : 2.41E-05 : 2.41E-05 : 2.41E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 4.10E-05 : 3.77E-05 : 1.06E-04 : 4.30E-05 : 3.74E-05 : 3.74E-05 : 3.74E-05 : 3.74E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-31
TABLE IV-A-28 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 28 VEG AT 2.65 MILES WNW ANNUAL_BETA_AIR_DOSE = 6.70E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 5.91E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 3.87E-08 : 3.87E-08 : 3.87E-08 : 3.87E-08 : 3.87E-08 : 3.87E-08 : 1.03E-07 : 4.65E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 4.14E-06 : 4.05E-06 : 4.52E-06 : 4.30E-06 : 3.99E-06 : 3.99E-06 : 3.99E-06 : 3.99E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 4.80E-06 : 4.64E-06 : 6.99E-06 : 5.06E-06 : 4.56E-06 : 4.56E-06 : 4.56E-06 : 4.56E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 7.67E-06 : 7.15E-06 : 1.72E-05 : 8.01E-06 : 7.09E-06 : 7.09E-06 : 7.09E-06 : 7.09E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-32
TABLE IV-A-29 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 29 VEG AT 2.40 MILES NW ANNUAL_BETA_AIR_DOSE = 1.89E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.67E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.09E-07 : 1.09E-07 : 1.09E-07 : 1.09E-07 : 1.09E-07 : 1.09E-07 : 2.90E-07 : 1.31E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 1.17E-05 : 1.14E-05 : 1.28E-05 : 1.21E-05 : 1.12E-05 : 1.12E-05 : 1.12E-05 : 1.12E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.35E-05 : 1.31E-05 : 1.98E-05 : 1.43E-05 : 1.29E-05 : 1.29E-05 : 1.29E-05 : 1.29E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.16E-05 : 2.01E-05 : 4.87E-05 : 2.26E-05 : 2.00E-05 : 2.00E-05 : 2.00E-05 : 2.00E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-33
TABLE IV-A-30 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 30 VEG AT 3.73 MILES NNW ANNUAL_BETA_AIR_DOSE = 1.16E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.02E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 6.69E-08 : 6.69E-08 : 6.69E-08 : 6.69E-08 : 6.69E-08 : 6.69E-08 : 1.78E-07 : 8.04E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : : : : : : : : :
ADULT : 7.14E-06 : 7.00E-06 : 7.32E-06 : 7.40E-06 : 6.89E-06 : 6.89E-06 : 6.89E-06 : 6.89E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 8.26E-06 : 8.01E-06 : 1.13E-05 : 8.68E-06 : 7.88E-06 : 7.88E-06 : 7.88E-06 : 7.88E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.32E-05 : 1.23E-05 : 2.78E-05 : 1.37E-05 : 1.22E-05 : 1.22E-05 : 1.22E-05 : 1.22E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-34
TABLE IV-A-31 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 31 BEEF AT 4.72 MILES NNE ANNUAL_BETA_AIR_DOSE = 1.04E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 9.14E-09 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 5.99E-09 : 5.99E-09 : 5.99E-09 : 5.99E-09 : 5.99E-09 : 5.99E-09 : 1.59E-08 : 7.19E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : :
ADULT : 9.16E-08 : 8.99E-08 : 8.97E-08 : 9.48E-08 : 8.86E-08 : 8.86E-08 : 8.86E-08 : 8.86E-08 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.52E-08 : 5.36E-08 : 7.22E-08 : 5.79E-08 : 5.28E-08 : 5.28E-08 : 5.28E-08 : 5.28E-08 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.87E-08 : 6.45E-08 : 1.38E-07 : 7.14E-08 : 6.40E-08 : 6.40E-08 : 6.40E-08 : 6.40E-08 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-35
TABLE IV-A-32 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 32 BEEF AT 4.91 MILES E ANNUAL_BETA_AIR_DOSE = 1.52E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 1.34E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 8.80E-09 : 8.80E-09 : 8.80E-09 : 8.80E-09 : 8.80E-09 : 8.80E-09 : 2.34E-08 : 1.06E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : :
ADULT : 1.34E-07 : 1.32E-07 : 1.07E-07 : 1.38E-07 : 1.30E-07 : 1.30E-07 : 1.30E-07 : 1.30E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 8.06E-08 : 7.86E-08 : 8.63E-08 : 8.37E-08 : 7.76E-08 : 7.76E-08 : 7.76E-08 : 7.76E-08 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 9.97E-08 : 9.47E-08 : 1.65E-07 : 1.03E-07 : 9.41E-08 : 9.41E-08 : 9.41E-08 : 9.41E-08 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-36
TABLE IV-A-33 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 33 BEEF AT 0.66 MILES S ANNUAL_BETA_AIR_DOSE = 4.94E-04 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 4.35E-06 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.85E-06 : 2.85E-06 : 2.85E-06 : 2.85E-06 : 2.85E-06 : 2.85E-06 : 7.59E-06 : 3.43E-04 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : :
ADULT : 4.42E-05 : 4.31E-05 : 6.05E-05 : 4.64E-05 : 4.22E-05 : 4.22E-05 : 4.22E-05 : 4.22E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.68E-05 : 2.57E-05 : 4.86E-05 : 2.86E-05 : 2.52E-05 : 2.52E-05 : 2.52E-05 : 2.52E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 3.36E-05 : 3.08E-05 : 9.33E-05 : 3.55E-05 : 3.05E-05 : 3.05E-05 : 3.05E-05 : 3.05E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-37
TABLE IV-A-34 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 34 BEEF AT 0.76 MILES SW ANNUAL_BETA_AIR_DOSE = 3.72E-05 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.28E-07 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.15E-07 : 2.15E-07 : 2.15E-07 : 2.15E-07 : 2.15E-07 : 2.15E-07 : 5.71E-07 : 2.58E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : :
ADULT : 3.33E-06 : 3.24E-06 : 4.39E-06 : 3.48E-06 : 3.18E-06 : 3.18E-06 : 3.18E-06 : 3.18E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.01E-06 : 1.93E-06 : 3.53E-06 : 2.14E-06 : 1.89E-06 : 1.89E-06 : 1.89E-06 : 1.89E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.53E-06 : 2.32E-06 : 6.77E-06 : 2.66E-06 : 2.30E-06 : 2.30E-06 : 2.30E-06 : 2.30E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-38
TABLE IV-A-35 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 35 BEEF AT 3.25 MILES W ANNUAL_BETA_AIR_DOSE = 3.90E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 3.44E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.25E-08 : 2.25E-08 : 2.25E-08 : 2.25E-08 : 2.25E-08 : 2.25E-08 : 5.99E-08 : 2.71E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : :
ADULT : 3.45E-07 : 3.39E-07 : 3.41E-07 : 3.57E-07 : 3.34E-07 : 3.34E-07 : 3.34E-07 : 3.34E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 2.08E-07 : 2.02E-07 : 2.75E-07 : 2.18E-07 : 1.99E-07 : 1.99E-07 : 1.99E-07 : 1.99E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.59E-07 : 2.43E-07 : 5.27E-07 : 2.69E-07 : 2.41E-07 : 2.41E-07 : 2.41E-07 : 2.41E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-39
TABLE IV-A-36 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 36 BEEF AT 4.59 MILES WNW ANNUAL_BETA_AIR_DOSE = 2.86E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.53E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.66E-08 : 1.66E-08 : 1.66E-08 : 1.66E-08 : 1.66E-08 : 1.66E-08 : 4.40E-08 : 1.99E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : : : : : : : : :
ADULT : 2.52E-07 : 2.48E-07 : 1.95E-07 : 2.59E-07 : 2.45E-07 : 2.45E-07 : 2.45E-07 : 2.45E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.51E-07 : 1.48E-07 : 1.57E-07 : 1.57E-07 : 1.46E-07 : 1.46E-07 : 1.46E-07 : 1.46E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 1.87E-07 : 1.78E-07 : 3.01E-07 : 1.93E-07 : 1.77E-07 : 1.77E-07 : 1.77E-07 : 1.77E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-40
TABLE IV-A-37 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 37 GOAT AT 3.44 MILES S ANNUAL_BETA_AIR_DOSE = 9.75E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 8.60E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 5.63E-08 : 5.63E-08 : 5.63E-08 : 5.63E-08 : 5.63E-08 : 5.63E-08 : 1.50E-07 : 6.77E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GOATMILK : : : : : : : : :
ADULT : 4.01E-06 : 4.00E-06 : 4.09E-07 : 4.02E-06 : 4.00E-06 : 4.00E-06 : 4.00E-06 : 4.00E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 5.22E-06 : 5.21E-06 : 7.18E-07 : 5.25E-06 : 5.20E-06 : 5.20E-06 : 5.20E-06 : 5.20E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 8.30E-06 : 8.24E-06 : 1.80E-06 : 8.33E-06 : 8.24E-06 : 8.24E-06 : 8.24E-06 : 8.24E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 1.26E-05 : 1.25E-05 : 2.12E-06 : 1.26E-05 : 1.25E-05 : 1.25E-05 : 1.25E-05 : 1.25E-05 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-41
TABLE IV-A-38 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 38 GOAT AT 3.30 MILES SSW ANNUAL_BETA_AIR_DOSE = 3.29E-06 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 2.90E-08 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 1.90E-08 : 1.90E-08 : 1.90E-08 : 1.90E-08 : 1.90E-08 : 1.90E-08 : 5.06E-08 : 2.28E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GOATMILK : : : : : : : : :
ADULT : 1.35E-06 : 1.35E-06 : 1.33E-07 : 1.36E-06 : 1.35E-06 : 1.35E-06 : 1.35E-06 : 1.35E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 1.76E-06 : 1.76E-06 : 2.34E-07 : 1.77E-06 : 1.75E-06 : 1.75E-06 : 1.75E-06 : 1.75E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 2.80E-06 : 2.78E-06 : 5.88E-07 : 2.81E-06 : 2.78E-06 : 2.78E-06 : 2.78E-06 : 2.78E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 4.24E-06 : 4.22E-06 : 6.93E-07 : 4.26E-06 : 4.22E-06 : 4.22E-06 : 4.22E-06 : 4.22E-06 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-42
TABLE IV-A-39 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS SPECIAL LOCATION NO. 39 GOAT AT 4.20 MILES SW ANNUAL_BETA_AIR_DOSE = 7.31E-07 MILLRADS ANNUAL_GAMMA_AIR_DOSE = 6.45E-09 MILLRADS PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 4.23E-09 : 4.23E-09 : 4.23E-09 : 4.23E-09 : 4.23E-09 : 4.23E-09 : 1.12E-08 : 5.08E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GROUND : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 : 0.00E+00 :
+----------+----------+----------+----------+----------+----------+----------+----------+
GOATMILK : : : : : : : : :
ADULT : 3.01E-07 : 3.00E-07 : 2.79E-08 : 3.02E-07 : 3.00E-07 : 3.00E-07 : 3.00E-07 : 3.00E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
TEEN : 3.92E-07 : 3.90E-07 : 4.91E-08 : 3.93E-07 : 3.90E-07 : 3.90E-07 : 3.90E-07 : 3.90E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
CHILD : 6.22E-07 : 6.18E-07 : 1.23E-07 : 6.24E-07 : 6.18E-07 : 6.18E-07 : 6.18E-07 : 6.18E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
INFANT : 9.42E-07 : 9.38E-07 : 1.45E-07 : 9.46E-07 : 9.37E-07 : 9.37E-07 : 9.37E-07 : 9.37E-07 :
+----------+----------+----------+----------+----------+----------+----------+----------+
IV-43
TABLE IV-B-1 FORT CALHOUN 1 DOSE CONTRIBUTIONS FROM GASEOUS EFFLUENTS UNRESTRICTED AREA BOUNDARY REQUIRED BY TECHNICAL SPECIFICATION 5.9.4.a.
JANUARY 1, 2019 TO DECEMBER 31, 2019 MAXIMUM SITE BOUNDARY GAMMA AIR DOSE - 2.63E-05 MILLRADS MAXIMUM SITE BOUNDARY BETA AIR DOSE - 2.99E-03 MILLRADS IV-44
TABLE IV-C-1 FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS ALARA ANNUAL INTEGRATED POPULATION DOSE
SUMMARY
(PERSON-REM)
PATHWAY T.BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN
+----------+----------+----------+----------+----------+----------+----------+----------+
PLUME : 2.67E-06 : 2.67E-06 : 2.67E-06 : 2.67E-06 : 2.67E-06 : 2.67E-06 : 8.87E-06 : 4.48E-04 :
- 0.67% : 0.68% : 1.18% : 0.66% : 0.68% : 0.68% : 2.23% : 53.54% :
+----------+----------+----------+----------+----------+----------+----------+----------+
INHAL : 2.09E-04 : 2.09E-04 : 2.07E-06 : 2.09E-04 : 2.09E-04 : 2.09E-04 : 2.09E-04 : 2.09E-04 :
- 52.31% : 53.03% : 0.91% : 51.50% : 53.30% : 53.30% : 52.57% : 24.94% :
+----------+----------+----------+----------+----------+----------+----------+----------+
VEGET : 1.32E-04 : 1.28E-04 : 1.60E-04 : 1.36E-04 : 1.26E-04 : 1.26E-04 : 1.26E-04 : 1.26E-04 :
- 33.04% : 32.49% : 70.38% : 33.63% : 32.30% : 32.30% : 31.73% : 15.11% :
+----------+----------+----------+----------+----------+----------+----------+----------+
COW MILK : 2.63E-05 : 2.55E-05 : 3.45E-05 : 2.73E-05 : 2.52E-05 : 2.52E-05 : 2.52E-05 : 2.52E-05 :
- 6.60% : 6.47% : 15.18% : 6.73% : 6.43% : 6.43% : 6.32% : 3.01% :
+----------+----------+----------+----------+----------+----------+----------+----------+
MEAT : 2.94E-05 : 2.88E-05 : 2.80E-05 : 3.03E-05 : 2.85E-05 : 2.85E-05 : 2.85E-05 : 2.85E-05 :
- 7.38% : 7.32% : 12.35% : 7.48% : 7.28% : 7.28% : 7.15% : 3.41% :
+----------+----------+----------+----------+----------+----------+----------+----------+
- TOTAL* : 3.99E-04 : 3.93E-04 : 2.27E-04 : 4.05E-04 : 3.91E-04 : 3.91E-04 : 3.98E-04 : 8.36E-04 :
IV-45
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- EVALUATION OF RADIATION DOSES FROM RELEASES OF RADIACTIVITY *
- IN NUCLEAR POWER PLANTS LIQUID EFFLUENTS *
- REVISION DATE: PNL VAX - OCTOBER 1985 *
- FORT CALHOUN ANNUAL 2019, DOSE PROJECTIONS *
- RADIOLOGICAL ASSESSMENT BRANCH *
- DIVISION OF SYSTEMS INTEGRATION *
- U. S. NUCLEAR REGULATORY COMMISSION *
- WASHINGTON, D. C. *
- DATE OF RUN: 202003051
- V-5
LOCATION IS FRESHWATER INTAKE A D U L T D O S E S
______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________
PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.56E-02 1.97E-02 1.29E-02 1.10E-05 6.66E-03 2.22E-03 4.40E-04 DRINKING 1.62E-04 1.89E-04 1.58E-04 1.01E-04 1.28E-04 1.10E-04 1.09E-04 SHORELINE 2.69E-05 2.30E-05 2.30E-05 2.30E-05 2.30E-05 2.30E-05 2.30E-05 2.30E-05 SWIMMING 9.36E-08 9.36E-08 9.36E-08 9.36E-08 9.36E-08 9.36E-08 9.36E-08 BOATING 4.68E-08 4.68E-08 4.68E-08 4.68E-08 4.68E-08 4.68E-08 4.68E-08 TOTAL 2.69E-05 1.58E-02 1.99E-02 1.31E-02 1.35E-04 6.81E-03 2.35E-03 5.73E-04 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 21.0 7.3 24.00 DRINKING 730.0 30.8 18.60 SHORELINE 12.0 7.3 0.00 SWIMMING 12.0 7.3 0.00 BOATING 12.0 7.3 0.00 T E E N A G E R D O S E S
______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________
PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.66E-02 2.05E-02 7.16E-03 8.47E-06 6.95E-03 2.70E-03 3.36E-04 DRINKING 1.56E-04 1.55E-04 1.02E-04 7.11E-05 9.73E-05 8.13E-05 7.67E-05 SHORELINE 1.50E-04 1.29E-04 1.29E-04 1.29E-04 1.29E-04 1.29E-04 1.29E-04 1.29E-04 SWIMMING 5.23E-07 5.23E-07 5.23E-07 5.23E-07 5.23E-07 5.23E-07 5.23E-07 BOATING 2.61E-07 2.61E-07 2.61E-07 2.61E-07 2.61E-07 2.61E-07 2.61E-07 TOTAL 1.50E-04 1.69E-02 2.08E-02 7.39E-03 2.09E-04 7.17E-03 2.91E-03 5.42E-04 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 16.0 7.3 24.00 DRINKING 510.0 30.8 18.60 SHORELINE 67.0 7.3 0.00 SWIMMING 67.0 7.3 0.00 BOATING 67.0 7.3 0.00 V-6
C H I L D D O S E S
______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________
PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 2.10E-02 1.86E-02 2.80E-03 7.02E-06 6.03E-03 2.17E-03 1.37E-04 DRINKING 4.68E-04 3.15E-04 1.72E-04 1.37E-04 1.89E-04 1.56E-04 1.41E-04 SHORELINE 3.14E-05 2.69E-05 2.69E-05 2.69E-05 2.69E-05 2.69E-05 2.69E-05 2.69E-05 SWIMMING 1.09E-07 1.09E-07 1.09E-07 1.09E-07 1.09E-07 1.09E-07 1.09E-07 BOATING 5.46E-08 5.46E-08 5.46E-08 5.46E-08 5.46E-08 5.46E-08 5.46E-08 TOTAL 3.14E-05 2.15E-02 1.89E-02 3.00E-03 1.71E-04 6.24E-03 2.36E-03 3.05E-04 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 6.9 7.3 24.00 DRINKING 510.0 30.8 18.60 SHORELINE 14.0 7.3 0.00 SWIMMING 14.0 7.3 0.00 BOATING 14.0 7.3 0.00 I N F A N T D O S E S
______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________
PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 DRINKING 4.02E-04 3.53E-04 1.58E-04 1.34E-04 1.89E-04 1.56E-04 1.37E-04 SHORELINE 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL 0.00E+00 4.02E-04 3.53E-04 1.58E-04 1.34E-04 1.89E-04 1.56E-04 1.37E-04 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 0.0 7.3 24.00 DRINKING 330.0 30.8 18.60 V-7
LOCATION IS SITE DISCHG.
A D U L T D O S E S
______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________
PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.14E-01 1.44E-01 9.40E-02 8.05E-05 4.86E-02 1.62E-02 3.22E-03 DRINKING 5.00E-03 5.82E-03 4.86E-03 3.11E-03 3.95E-03 3.39E-03 3.37E-03 SHORELINE 1.97E-04 1.68E-04 1.68E-04 1.68E-04 1.68E-04 1.68E-04 1.68E-04 1.68E-04 SWIMMING 6.83E-07 6.83E-07 6.83E-07 6.83E-07 6.83E-07 6.83E-07 6.83E-07 BOATING 3.42E-07 3.42E-07 3.42E-07 3.42E-07 3.42E-07 3.42E-07 3.42E-07 TOTAL 1.97E-04 1.19E-01 1.50E-01 9.91E-02 3.36E-03 5.27E-02 1.98E-02 6.75E-03 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 21.0 1.0 24.00 DRINKING 730.0 1.0 12.00 SHORELINE 12.0 1.0 0.00 SWIMMING 12.0 1.0 0.00 BOATING 12.0 1.0 0.00 T E E N A G E R D O S E S
______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________
PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.21E-01 1.50E-01 5.23E-02 6.18E-05 5.07E-02 1.97E-02 2.45E-03 DRINKING 4.81E-03 4.78E-03 3.14E-03 2.19E-03 3.00E-03 2.50E-03 2.36E-03 SHORELINE 1.10E-03 9.39E-04 9.39E-04 9.39E-04 9.39E-04 9.39E-04 9.39E-04 9.39E-04 SWIMMING 3.82E-06 3.82E-06 3.82E-06 3.82E-06 3.82E-06 3.82E-06 3.82E-06 BOATING 1.91E-06 1.91E-06 1.91E-06 1.91E-06 1.91E-06 1.91E-06 1.91E-06 TOTAL 1.10E-03 1.27E-01 1.55E-01 5.63E-02 3.20E-03 5.46E-02 2.32E-02 5.76E-03 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 16.0 1.0 24.00 DRINKING 510.0 1.0 12.00 SHORELINE 67.0 1.0 0.00 SWIMMING 67.0 1.0 0.00 BOATING 67.0 1.0 0.00 V-8
C H I L D D O S E S
______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________
PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 1.53E-01 1.36E-01 2.04E-02 5.12E-05 4.40E-02 1.59E-02 9.97E-04 DRINKING 1.44E-02 9.70E-03 5.30E-03 4.21E-03 5.83E-03 4.79E-03 4.35E-03 SHORELINE 2.29E-04 1.96E-04 1.96E-04 1.96E-04 1.96E-04 1.96E-04 1.96E-04 1.96E-04 SWIMMING 7.97E-07 7.97E-07 7.97E-07 7.97E-07 7.97E-07 7.97E-07 7.97E-07 BOATING 3.99E-07 3.99E-07 3.99E-07 3.99E-07 3.99E-07 3.99E-07 3.99E-07 TOTAL 2.29E-04 1.68E-01 1.45E-01 2.59E-02 4.45E-03 5.00E-02 2.08E-02 5.55E-03 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 6.9 1.0 24.00 DRINKING 510.0 1.0 12.00 SHORELINE 14.0 1.0 0.00 SWIMMING 14.0 1.0 0.00 BOATING 14.0 1.0 0.00 I N F A N T D O S E S
______________________________________________DOSE__(MREM PER YEAR INTAKE)________________________________________
PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 DRINKING 1.24E-02 1.09E-02 4.87E-03 4.13E-03 5.82E-03 4.81E-03 4.22E-03 SHORELINE 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL 0.00E+00 1.24E-02 1.09E-02 4.87E-03 4.13E-03 5.82E-03 4.81E-03 4.22E-03 USAGE (KG/YR,HR/YR) DILUTION TIME(HR) SHOREWIDTH FACTOR=0.2 FISH 0.0 1.0 24.00 DRINKING 330.0 1.0 12.00 V-9
- *
- FISH CONSUMPTION POPULATION DOSES * *
- PERSON-REM
__________COMMERCIAL HARVEST__________
DOSE (PERSON-REM)-------------------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH ADULT 4.18E+06 5.14E-03 6.49E-03 4.25E-03 3.64E-06 2.20E-03 7.33E-04 1.45E-04 FISH TEENAGER 4.88E+05 8.41E-04 1.04E-03 3.62E-04 4.28E-07 3.51E-04 1.37E-04 1.70E-05 FISH CHILD 3.38E+05 1.71E-03 1.51E-03 2.27E-04 5.69E-07 4.89E-04 1.76E-04 1.11E-05 FISH TOTAL 5.01E+06 7.68E-03 9.04E-03 4.84E-03 4.63E-06 3.04E-03 1.05E-03 1.73E-04 LOCATION DILUTION CATCH TIME(HR)-INCLUDES FOOD PROCESSING TIME OF 2.40E+02 HR POPULATION=8.53E+05 7.30E+00 7.30E+04 2.41E+02 AVERAGE INDIVIDUAL CONSUMPTION (KG/YR) ADULT=6.90E+00 TEEN=5.20E+00 CHILD=2.20E+00
__________NEPA DOSES__________
NOTE--TOTAL NEPA DOSE INCLUDES SPORT CATCH
DOSE (PERSON-REM)-------------------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI FISH ADULT 1.22E+05 9.03E-02 1.14E-01 7.48E-02 6.39E-05 3.86E-02 1.29E-02 2.56E-03 FISH TEENAGER 1.42E+04 1.48E-02 1.82E-02 6.37E-03 7.53E-06 6.18E-03 2.40E-03 2.98E-04 FISH CHILD 9.85E+03 3.00E-02 2.65E-02 3.99E-03 1.00E-05 8.60E-03 3.10E-03 1.95E-04 FISH TOTAL 1.46E+05 1.35E-01 1.59E-01 8.51E-02 8.15E-05 5.34E-02 1.84E-02 3.05E-03 V-10
- *
- POPULATION WATER CONSUMPTION DOSES * *
- SUPPLIER-OMAHA
DOSE (PERSON-REM)-------------------------
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI DRINKING ADULT 1.39E+08 3.09E-02 3.60E-02 3.00E-02 1.92E-02 2.44E-02 2.09E-02 2.08E-02 DRINKING TEENAGER 1.51E+07 4.63E-03 4.61E-03 3.02E-03 2.11E-03 2.89E-03 2.41E-03 2.27E-03 DRINKING CHILD 2.48E+07 2.27E-02 1.53E-02 8.35E-03 6.63E-03 9.19E-03 7.55E-03 6.86E-03 DRINKING TOTAL 1.79E+08 5.82E-02 5.59E-02 4.14E-02 2.80E-02 3.65E-02 3.09E-02 2.99E-02 POPULATION=5.29E+05 DILUTION=3.08E+01 TRANSIT TIME=3.06E+01 HR (INCLUDING 24 HR FOR TREATMENT FACILITY)
AVERAGE INDIVIDUAL CONSUMPTION (L/YR) ADULT=3.70E+02 TEEN=2.60E+02 CHILD=2.60E+02
CUMULATIVE TOTAL-----
PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI DRINKING CUMUL TOTAL 2.08E+08 6.76E-02 6.49E-02 4.81E-02 3.25E-02 4.24E-02 3.59E-02 3.48E-02
__________HYDROSPHERE TRITIUM DOSE__________
AVERAGE INDIVIDUAL WATER CONSUMPTION = 3.0 L/DAY PATHWAY AGE GROUP USAGE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI WATER TOTAL 2.86E+11 0.00E+00 7.17E-06 7.17E-06 7.17E-06 7.17E-06 7.17E-06 7.17E-06 V-11
- *
- RECREATION POPULATION DOSES * *
- LOCATION- DOWN STREAM SWIMMING DILUTION= 7.30E+00 TRANSIT TIME= 6.70E-01 HR SWF= 0.2
________________DOSE (PERSON-REM)_____________
PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID SHORELINE TOTAL POPUL 4.10E+07 9.20E-02 7.87E-02 7.87E-02 LOCATION- DOWN STREAM SWIMMING DILUTION= 7.30E+00 TRANSIT TIME= 6.70E-01 HR
________________DOSE (PERSON-REM)_____________
PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID SWIMMING TOTAL POPUL 4.10E+07 3.20E-04 3.20E-04 LOCATION- DOWN STREAM BOATING DILUTION= 7.30E+00 TRANSIT TIME= 6.70E-01 HR
________________DOSE (PERSON-REM)_____________
PATHWAY AGE GROUP USAGE SKIN TOTAL BODY THYROID BOATING TOTAL POPUL 4.10E+07 1.60E-04 1.60E-04
- *
- DOSE TO BIOTA * *
- MRADS PER YEAR BIOTA DILUTION= 1.00E+00 TRANSIT TIME= 0.00E+00 HR INTERNAL EXTERNAL TOTAL FISH 3.16E-01 6.14E-01 9.31E-01 INVERTEBRATE 1.64E-01 1.23E+00 1.39E+00 ALGAE 8.49E-02 4.99E-04 8.54E-02 MUSKRAT 1.73E+00 4.10E-01 2.14E+00 RACCOON 6.42E-01 3.07E-01 9.49E-01 HERON 9.97E+00 4.10E-01 1.04E+01 DUCK 1.58E+00 6.15E-01 2.19E+00 V-12
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9I. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT January 1, 2019 through December 31, 2019 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED)
Month Number of Volume Curie Est. Total
- 1. Type of Waste Shipped Shipments Cu. Meter Content % Error
- a. Spent resins, filters, January 1 0.33 25.024 20 sludges, evaporator February 1 0.09 31.650 20 bottoms, etc. March 0 0 0 N/A April 0 0 0 N/A May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A September 0 0 0 N/A October 0 0 0 N/A November 0 0 0 N/A December 0 0 0 N/A Total (Type a) 2 0.42 56.674 20
- b. Dry compressible, January 1 281.02 3.922 20 contaminated equipment, February 1 39.98 0.037 20 etc. March 0 0 0 N/A April 0 0 0 N/A May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A September 0 0 0 N/A October 1 193.69 36.330 20 November 8 154.27 79.245 20 December 0 0 0 N/A Total (Type b) 11 668.96 119.534 20
9,
VI. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT (Continued)
Month Number of Volume Curie Est. Total
- 1. Type of Waste Shipped Shipments Cu. Meter Content % Error
- c. Irradiated components January 0 0 0 N/A and other categories. February 0 0 0 N/A March 0 0 0 N/A April 0 0 0 N/A May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A September 0 0 0 N/A October 0 0 0 N/A November 0 0 0 N/A December 0 0 0 N/A Total (Type c) 0 0 0 N/A
- d. Other January 0 0 0 N/A February 0 0 0 N/A March 0 0 0 N/A April 0 0 0 N/A May 0 0 0 N/A June 0 0 0 N/A July 0 0 0 N/A August 0 0 0 N/A September 0 0 0 N/A October 0 0 0 N/A November 0 0 0 N/A December 0 0 0 N/A Total (Type d) 0 0 0 N/A
9,
VI. RADIOACTIVE EFFLUENT RELEASE - SOLID RADIOACTIVE WASTE EFFLUENT AND WASTE DISPOSAL REPORT (Continued)
B. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (By Type of Waste) 1. Percentage of Curies from Represented Isotopes Isotope Percent Curies
- a. Ni-63 49.2 2.79E+01 Co-60 28.4 1.61E+01 Fe-55 13.7 7.78E+00 Ag-110m 2.9 1.64E+00 Ni-59 2.5 1.40E+00 All Other Nuclides Constitute Less than 1% Each for Type a
- b. Ni-63 64.51 7.71E+01 Co-60 23.72 2.84E+01 Cs-137 D 6.87 8.21E+00 Fe-55 1.99 2.37E+00 Ni-59 1.24 1.48E+00 All Other Nuclides Constitute Less than 1% Each for Type b
- c. None
- d. None C. SOLID WASTE (DISPOSITION)
Number of Shipments Transportation Mode Destination 7 Sole Use Vehicle Clive Disposal Site, Clive, UT 6 Sole Use Vehicle Energy Solutions, Bear Creek, TN D. IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shipments Transportation Mode Destination N/A N/A N/A
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Page 1 of 136 CH-ODCM-0001 Off-Site Dose Calculation Manual (ODCM)
Revision 29 Safety Classification: Usage Level:
Non-Safety Reference Change No.: EC 69954 Reason for Change: Revise site boundary, reduce the frequency of milk sampling and eliminate sediment sampling.
Preparer: J. Hoffman Fort Calhoun Station
CH-ODCM-0001 Reference Use Page 2 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table of Contents PART I 1.0 PURPOSE AND SCOPE ................................................................................................. 6 1.1 Purpose ..................................................................................................................... 6 1.2 Scope ........................................................................................................................ 6 2.0 DEFINITIONS .................................................................................................................. 6 3.0 INSTRUMENTATION .................................................................................................... 10 3.1 Radioactive Liquid Effluent Instrumentation ............................................................ 10 3.2 Radioactive Gaseous Effluent Instrumentation ....................................................... 13 4.0 RADIOACTIVE EFFLUENTS ........................................................................................ 17 4.1 Radioactive Liquid Effluents .................................................................................... 17 4.2 Radioactive Gaseous Effluents ............................................................................... 23 4.3 Uranium Fuel Cycle ................................................................................................. 29 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) .................. 30 5.1 Monitoring Program ................................................................................................. 30 5.2 Land Use Survey ..................................................................................................... 45 5.3 Interlaboratory Comparison Program ...................................................................... 46 6.0 ADMINISTRATIVE CONTROLS.................................................................................... 47 6.1 Responsibilities ....................................................................................................... 47 6.2 Radioactive Effluent Reporting Requirements......................................................... 47 6.3 Change Mechanism ................................................................................................ 52 6.4 Meteorological Data ................................................................................................ 52 6.5 References .............................................................................................................. 53 7.0 BASIS ............................................................................................................................ 55 7.1 Instrumentation ....................................................................................................... 55 7.2 Radioactive Effluents............................................................................................... 55 7.3 Radiological Environmental Monitoring ................................................................... 62 7.4 Abnormal Release or Abnormal Discharge Reporting ............................................. 63
CH-ODCM-0001 Reference Use Page 3 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 List of Tables PART I Table 1.2 - Frequency Notation ............................................................................................... 8 Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation .. 9 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation .................................... 11 Table 3.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ....................................................................................................... 12 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation ............................... 14 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .................................................................................. 16 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis ............................................. 19 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis ......................................... 24 Table 4.3 - Sampler Deposition/Transportation Correction Factors ....................................... 25 Table 5.1 - Radiological Environmental Monitoring Program ................................................. 32 Table 5.2 - Radiological Environmental Sampling Locations And Media ............................... 35 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ................................................................................................... 43 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples ...................................................................................... 44 List of Figures PART I Figure 1 - Environmental Radiological Sampling Points ....................................................... 41 Figure 2 - 40CFR190 Sampling Points ................................................................................. 42
CH-ODCM-0001 Reference Use Page 4 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table of Contents PART II 1.0 EFFLUENT MONITOR SETPOINTS ............................................................................. 66 1.1 Liquid Effluents ........................................................................................................ 66 1.2 Airborne Effluents .................................................................................................... 69 2.0 EFFLUENT CONCENTRATIONS ................................................................................. 80 2.1 Liquid Effluent Concentrations ................................................................................ 80 2.2 Airborne Effluent Concentrations ............................................................................ 80 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS ................................................... 82 3.1 Liquid Effluent Dose Calculations ............................................................................ 82 3.2 Airborne Effluent Dose Calculations ........................................................................ 86 4.0 LOWER LIMIT OF DETECTION (LLD) ....................................................................... 101
CH-ODCM-0001 Reference Use Page 5 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 List of Tables PART II Table 1 - Allocation Factors for Simultaneous Releases ....................................................... 74 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases ................... 102 Table 3 - Bioaccumulation Factors ...................................................................................... 103 Table 4 - Highest Potential Exposure Pathways for Estimating Dose.................................. 104 Table 5 - Stable Element Transfer Data .............................................................................. 105 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data................................................................. 106 Table 7 - Animal Consumption Rates .................................................................................. 106 Table 8 - External Dose Factors for Standing on Contaminated Ground ............................. 107 Table 9 - Inhalation Dose Factors for Adult ......................................................................... 110 Table 10 - Inhalation Dose Factors for Teenager ................................................................ 113 Table 11 - Inhalation Dose Factors for Child ....................................................................... 116 Table 12 - Inhalation Dose Factors for Infant ...................................................................... 119 Table 13 - Ingestion Dose Factors for Adult ........................................................................ 122 Table 14 - Ingestion Dose Factors for Teenager ................................................................. 125 Table 15 - Ingestion Dose Factors for Child ........................................................................ 128 Table 16 - Ingestion Dose Factors for Infant ....................................................................... 131 Table 17 - Recommended Values for Other Parameters ..................................................... 134 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure ........ 136 List of Figures PART II Figure 1 - Exclusion and Site Boundary Map ........................................................................ 75 Figure 2 - Liquid Radioactive Discharge Pathways ............................................................... 76 Figure 3 - Liquid Radioactive Waste Disposal System .......................................................... 77 Figure 4 - Airborne Effluent Discharge Pathways .................................................................. 78 Figure 5 - Airborne Radioactive Waste Disposal System ...................................................... 79
CH-ODCM-0001 Reference Use Page 6 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 Contains methodologies for and parameters necessary for calculating offsite doses, determination of gaseous and liquid radiation monitor set points, and administrative controls for effluent instrumentation, Radiological Effluent Tech Specs (RETS), and the Radiological Environmental Monitoring Program (REMP).
1.2 Scope 1.2.1 Radioactive effluents are generated from station activities. These controls provide methodologies ensuring these effluents are properly monitored and quantified to promote accurate dose reporting. Additional controls ensure station equipment and processes are used to minimize release to the environment. The combination of minimizing release, accurately reporting dose, and monitoring the facility environs provides the basis for ensuring that station activities are not negatively impacting public health and the environment.
2.0 DEFINITIONS 2.1 Abnormal Discharge - The unplanned or uncontrolled emission of an effluent (i.e.,
containing facility-related, licensed radioactive material) into the unrestricted area.
2.2 Abnormal Release - The unplanned or uncontrolled emission of an effluent (i.e.,
containing facility-related, licensed radioactive material).
2.3 Channel Check - A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
2.4 Channel Function Test - Injection of a simulated signal into the channel to verify that it is functional, including any alarm and/or trip initiating action.
2.5 Effluent Concentration Limit (ECL) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 1.
2.6 Member(s) of the Public - Member(s) of the Public means any individual except when that individual is receiving occupational dose.
CH-ODCM-0001 Reference Use Page 7 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 2.7 Functional-Functionality - A system, subsystem, train, component or device shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power sources, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
2.8 Residual Radioactivity - Residual radioactivity means radioactivity in structures, materials, soils, ground water, and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee, but it excludes background radiation. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site, even if those burials were made in accordance with the provisions of 10 CFR Part 20.
2.9 Site Boundary - The Site Boundary is the line beyond which the land is neither owned, or leased, nor controlled by the licensee.
2.10 Source Check - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
2.11 Special Liquid - Non-routine release pathway in which normally non-radioactive liquid streams (such as Raw Water) found to contain radioactive material, are non-routine, and will be treated on a case specific basis if and when this occurs.
2.12 Unrestricted Area - An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
2.13 Venting - VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
2.14 Water Effluent Concentration (WEC) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.
CH-ODCM-0001 Reference Use Page 8 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 1.2 - Frequency Notation The surveillance intervals are defined as follows:
Notation Title FrequencyA S Shift At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W Weekly At least once per 7 days BW Biweekly At least once per 14 days M Monthly At least once per 31 days Q Quarterly At least once per 92 days SA Semiannual At least once per 184 days A Annually At least once per 366 days R At least once per 18 months P Prior to Prior to each release (Performance within 24 hrs.)
A. Each surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
CH-ODCM-0001 Reference Use Page 9 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation Technical Specification ODCM Implementing Step 5.16.1.a 3.1.1, 3.2.1 5.16.1.b 4.1.1 5.16.1.c Table 4.1, Table 4.2 5.16.1.d 4.1.2 5.16.1.e 4.1.2B.1, 4.2.2B.1 5.16.1.f 4.1.3A, 4.2.4A 5.16.1.g 4.2.1 5.16.1.h 4.2.2 5.16.1.i 4.2.3 5.16.1.j 4.3.1 5.16.2.a 5.1.1 5.16.2.b 5.2.1 5.16.2.c 5.3.1 5.17 6.3, 6.2.1D
CH-ODCM-0001 Reference Use Page 10 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.0 INSTRUMENTATION 3.1 Radioactive Liquid Effluent Instrumentation 3.1.1 Limiting Condition for Operation A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.1.1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 3.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Part II of the Off-Site Dose Calculation Manual.
APPLICABILITY: At all times ACTION:
- 1. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive liquid effluents monitored by the affected channel or declare the channel non-functional.
- 2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels functional, take the action shown in Table 3.1.1. Restore non-functional effluent monitoring instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this non-functionality was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent stream: RM-055.
3.1.2 Surveillance Requirements A. Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.1.2.
CH-ODCM-0001 Reference Use Page 11 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrument Functional Action
- 1. Radioactivity Monitor Providing Alarm and Automatic Termination of Release.
1.1 Liquid Radwaste Effluent Line (RM-055) 1 1, 4
- 2. Flow Rate Measurement Device 2.1 Liquid Radwaste Effluent Line 1 2
- 3. Radioactivity Recorder 3.1 Liquid Radwaste Effluent Line 1 3 Table Notation ACTION 1 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided that prior to initiating a release:
- 1. At least two independent samples are analyzed in accordance with applicable chemistry procedures.
- 2. At least two qualified individuals independently verify the release rate calculations.
ACTION 2 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the flow rate is determined at least once per four hours during the actual release.
ACTION 3 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the radioactivity is recorded manually at least once per four hours during the actual release.
ACTION 4 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered non-functional. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. If the effluent radiation monitor fails the source check, carryout the action(s) of the Off-Site Dose Calculation Manual for the non-functional monitor or terminate the effluent release.
CH-ODCM-0001 Reference Use Page 12 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 3.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Function Check Calibration Check Test
- 1. Radioactivity Monitor Providing Alarm and Automatic Isolation 1.1 RM-055 ---- R Q P
CH-ODCM-0001 Reference Use Page 13 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2 Radioactive Gaseous Effluent Instrumentation 3.2.1 Limiting Condition for Operation A. The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.2.1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 3.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Part II of the Off-Site Dose Calculation Manual.
APPLICABILITY: At all times ACTION:
- 1. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive gaseous effluents monitored by the affected channel or declare the channel non-functional.
- 2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels functional, take the action shown in Table 3.2.1. Restore non-functional effluent monitoring instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this non-functionality was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent streams: RM-043, RM-062, and RM-052.
3.2.2 Surveillance Requirements A. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.2.2.
CH-ODCM-0001 Reference Use Page 14 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Channels Action Functional
- 1. Auxiliary Bldg. Exhaust Stack (RM-052, RM-062) 1.1 Noble Gas 1 1, 7, 8 1.2 Particulate 1 2, 7, 8
- 2. Laboratory and Radwaste Processing Building Stack (RM-043) 2.1 Noble Gas 1 3, 7 2.2 Particulate 1 4, 7
- 3. Flow Rate Measurement Devices 3.1 Auxiliary Building Exhaust Stack 1 5 3.2 Laboratory and Radwaste Processing Building Stack 1 5
- 4. Radioactivity Chart Recorders 4.1 Auxiliary Building Exhaust Stack 1 6
CH-ODCM-0001 Reference Use Page 15 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 3.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation Table Notation ACTION 1 If the Auxiliary Building Exhaust Stack Noble Gas Monitor is non-functional, ventilation of the auxiliary building via the Auxiliary Building Exhaust Stack may continue provided grab samples are taken once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (See Table 4.2)
ACTION 2 If the Auxiliary Building Exhaust Stack Particulate Sampler is non-functional, ventilation of the Auxiliary Building may continue through the Auxiliary Building Exhaust Stack provided sample collection in accordance with Table 4.2 using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the declaration of non-functionality by the Shift Manager.
ACTION 3 If the Noble Gas Monitor is non-functional, ventilation of the LRWPB may continue via the LRWPB stack provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (See Table 4.2)
ACTION 4 If the Particulate Sampler is non-functional, ventilation of the LRWPB may continue via the LRWPB Stack provided sample collection using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the declaration of non-functionality, by the Shift Manager, in accordance with Table 4.2.
ACTION 5 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the flowrate is estimated or recorded manually at least once per four hours during the actual release.
ACTION 6 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the radioactivity level is recorded manually at least once per four hours during the actual release.
ACTION 7 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered non-functional. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. If the effluent radiation monitor fails the source check, carryout the Action(s) of the Off-Site Dose Calculation Manual for the non-functional monitor or terminate the effluent release.
ACTION 8 During the ventilation of airborne effluents from the Auxiliary Building Exhaust Stack at least one Auxiliary Building Exhaust fan shall be in operation.
CH-ODCM-0001 Reference Use Page 16 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Calibration Function Check Check Test
- 1. Radioactivity Monitors Providing Alarm and Automatic Isolation 1.1 RM-043 D R Q M 1.2 RM-062 D R Q M 1.3 RM-052 D R Q M
- 2. Flowrate Monitors 2.1 RM-043 Sampler D R Q ----
2.2 RM-062 Sampler D R Q ----
2.3 RM-052 Sampler D R Q ----
2.4 Auxiliary Bldg Exhaust Stack D R Q ----
2.5 Laboratory and Radwaste Process Bldg Exhaust Stack D R Q ----
Operations Check Air Flow Calibration
- 3. Environmental Monitors 3.1 RM-023 - Sample Station #40 M A 3.2 RM-024 - Sample Station #41 M A 3.3 RM-025 - Sample Station #28 ---- ----
3.4 RM-026 - Sample Station #36 ---- ----
3.5 RM-027 - Sample Station #37 M A 3.6 RM-028 - Sample Station #38 ---- ----
3.7 RM-029 - Sample Station #39 ---- ----
3.8 RM-035 - Sample Station #1 ---- ----
3.9 RM-036 - Sample Station #2 M A 3.10 RM-037 - Sample Station #3 ---- ----
3.11 RM-038 - Sample Station #4 M A 3.12 RM-039 - Sample Station #5 ---- ----
3.13 RM-040 - Sample Station #32 M A
CH-ODCM-0001 Reference Use Page 17 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.0 RADIOACTIVE EFFLUENTS 4.1 Radioactive Liquid Effluents 4.1.1 Concentration A. Limiting Condition for Operation
- 1. The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides, other than dissolved or entrained noble gases, do not exceed the values specified in 10 CFR Part 20 for liquid effluents at site discharge. To support facility operations, RP/Chemistry supervision may increase this limit up to the limit specified in Technical Specifications 5.16.1.b. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/ml, total activity.
- 2. Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/ml total activity.
APPLICABILITY: At all times ACTION:
- a. When the concentration of radioactive material released at site discharge exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.
CH-ODCM-0001 Reference Use Page 18 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 B. Surveillance Requirements NOTE i Radioactive liquid waste includes water used for fire suppression in areas of the facility that may contain radioactivity. These liquids are required to be i monitored prior to release in accordance with SO-G-28.
- 1. Radioactive liquid waste shall be sampled and analyzed according to the sampling and analysis program in Table 4.1.
- 2. The results of the radioactivity analysis shall be used with the calculational methods in Part II of the Off-Site Dose Calculation Manual.
- 3. To assure that the concentration at the point of release is maintained within the limits of Technical Specification 5.16.1.b.
- 4. Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred. Analytical results shall be submitted to the Commission in accordance with Part I, Section 6.0 of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 19 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis A. Monitor, Hotel Waste Tanks & Special Liquid, Releases Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Each Batch Principal Gamma Emitters B 5.0E-07 Dissolved Noble Gases Each Batch (Gamma Emitters) B 1.0E-05 Monthly Composite C H-3 1.0E-05 Monthly Composite C Gross Alpha 1.0E-07 Quarterly Composite C Sr-89, Sr-90 5.0E-08 Quarterly Composite C Fe-55 1.0E-06 NOTES:
A. LLD is defined in Part II of the Off-Site Dose Calculation Manual.
B. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved or entrained gases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141 for fission and corrosion products. Ce-144 shall also be measured, but with a LLD of 5.0E-06.
C. To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples should be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite should be mixed in order for the composite sample to be representative of the average effluent release.
CH-ODCM-0001 Reference Use Page 20 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.1.2 Dose from Radioactive Liquid Effluents A. Limiting Condition for Operation
- 1. The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 1.5 mrem to the total body and 5 mrem to any organ; and
- b. During any calendar year: Less than or equal to 3 mrem to the total body and 10 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of radioactive materials in liquid effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual at least once per quarter.
CH-ODCM-0001 Reference Use Page 21 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.1.3 Liquid Radwaste Treatment A. Limiting Condition for Operation
- 1. The Liquid Radwaste Treatment System shall be FUNCTIONAL, and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.
APPLICABILITY: At all times ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to 10 CFR 50, Appendix I, a Special Report that includes the following information:
- 1) Explanation of why liquid radwaste was being discharged without treatment, identification of equipment or subsystem(s) not functional and reasons for non-functionality.
- 2) Action(s) taken to restore the non-functional equipment to functional status.
- 3) Summary description of action(s) taken to prevent a recurrence.
B. Surveillance Requirements
- 1. Dose due to liquid releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual, when Liquid Radwaste Treatment Systems are not fully FUNCTIONAL.
- 2. FUNCTIONAL is defined as follows:
- a. A filtration/ion exchange (FIX) system will be utilized for processing liquid radwaste. The system consists of a booster pump, charcoal pretreatment filter, and pressure vessels containing organic/inorganic resins, which can be configured for optimum performance. The effluent from the FIX system is directed to the monitor tanks for release.
CH-ODCM-0001 Reference Use Page 22 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.1.3B.2 (continued)
- b. Waste filters (WD-17A and WD-17B) are used only on those occasions when considered necessary, otherwise the flows from the low activity fluids may bypass the filters. No credit for decontamination factors (iodines, Cs, Rb, others) was taken for these filters during the 10 CFR Part 50 Appendix I dose design objective evaluation; therefore, the non-functionality of these filters does not affect the dose contributions to any individual in the unrestricted areas via liquid pathways. The non-functionality of waste filters will not be considered a reportable event in accordance with the Action listed above.
4.1.4 Liquid Holdup Tanks Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
A. Limiting Condition for Operation
- 1. The quantity of radioactive material contained in each unprotected outdoor liquid holdup tank shall not exceed 10 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times ACTION:
- a. When the quantity of radioactive material in any unprotected outdoor liquid holdup tank exceeds 10 curies, excluding tritium and dissolved or entrained noble gasses, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
B. Surveillance Requirements
- 1. The quantity of radioactive material contained in each outdoor liquid holdup tank shall be determined to be within the above limit by analyzing a representative sample of the tanks contents at least once per 7 days when radioactive material is being added to the tank.
CH-ODCM-0001 Reference Use Page 23 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.2 Radioactive Gaseous Effluents 4.2.1 Concentration A. Limiting Condition for Operation
- 1. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations of radionuclides does not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To support facility operations, RP/Chemistry supervision may increase this limit up to the limits specified in Technical Specification 5.16.1.g.
- 2. Technical Specification 5.16.1.g establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.
APPLICABILITY: At all times ACTION:
- a. When the concentration of radioactive material released to unrestricted areas exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.
B. Surveillance Requirements NOTE Radioactive gaseous wastes include atmospheres in areas where gaseous i fire suppression systems are utilized or where smoke is produced as a result of fire in areas of the facility that may contain radioactivity. These i atmospheres are required to be monitored prior to gaseous release to unrestricted areas in accordance with SO-G-28.
- 1. Radioactive gaseous wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.2. The results of the radioactivity analysis shall be used to assure the limits in Step 4.2.1A are not exceeded.
CH-ODCM-0001 Reference Use Page 24 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis A. Auxiliary Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly (Noble Gases) Principal Gamma Emitters B 1.0E-4 Weekly Tritium (H-3) 1.0E-06 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Samples) Sr-89, Sr-90 1.0E-11 B. Laboratory and Radwaste Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly (Noble Gases) Principal Gamma Emitters B 1.0E-4 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-89, Sr-90 1.0E-11 NOTES:
A. LLD is defined in Part II of the Off-Site Dose Calculation Manual.
B. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate releases.
C. Frequency requirement may be satisfied using weekly gross alpha results from particulate sampling media.
D. Particulate samples shall be corrected for sampler deposition/transportation efficiency by using the approved software programs or by multiplying the activity obtained by the associated sampler multiplication factor (See Table 4.3).
CH-ODCM-0001 Reference Use Page 25 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 4.3 - Sampler Deposition/Transportation Correction Factors Particulate Sampler Sample DF ACTMULT RM-062 AB 0.411 2.433 RM-052 AB 0.638 1.567 RM-043 LRWPB 0.809 1.236 ACRONYM DEFINITIONS:
AB - Auxiliary Building Exhaust Stack LRWPB - Laboratory and Rad Waste Processing Building DF - Deposition Factor ACTMULT - Activity multiplication factor to correct for sample loss.
CH-ODCM-0001 Reference Use Page 26 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.2.2 Dose - Noble Gases A. Limiting Condition for Operation
- 1. The dose or dose commitment to an individual at the site boundary from release of noble gases in airborne effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of noble gases in airborne effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from radioactive noble gases in airborne effluents shall be determined, in accordance with the methodologies and parameters of Part II of the Off-Site Dose Calculation Manual, on a quarterly basis.
4.2.3 Dose - H-3, C-14, and Radioactive Material in Particulate Form with Half-Lives Greater than 8 Days (Other than Noble Gases)
A. Limiting Condition for Operation
- 1. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of H-3, C-14, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ; and
CH-ODCM-0001 Reference Use Page 27 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.2.3A.1 (continued)
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of H-3, C-14, and radioactive materials in particulate form with half-lives greater than eight days, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from H-3, C-14 and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be determined, in accordance with the methodologies and parameters of Part II of the Off-Site Dose Calculation Manual, on a quarterly basis.
4.2.4 Gaseous Radwaste Treatment A. Limiting Condition for Operation
- 1. In accordance with Technical Specification 5.16.1.f, the Ventilation Exhaust Systems shall be FUNCTIONAL, and appropriate portions of these systems shall be used to reduce the releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed:
- a. 0.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC
CH-ODCM-0001 Reference Use Page 28 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.2.4A.1 (continued)
APPLICABILITY: At all times ACTION:
- a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit a report to the Nuclear Regulatory Commission within 30 days, pursuant to 10 CFR 50, Appendix I, a special report that includes the following information:
- 1) Identification of equipment or subsystem(s) not functional and reasons for non-functionality.
- 2) Action(s) taken to restore the non-functional equipment to functional status.
- 3) Summary description of action(s) taken to prevent a recurrence.
B. Surveillance Requirements
- 1. Dose due to gaseous releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual, when Ventilation Exhaust Systems are not fully FUNCTIONAL.
- 2. FUNCTIONAL is defined as follows:
- a. Ventilation Exhaust Systems
- 1) The radioactive effluents from the controlled access area of the auxiliary building are filtered by the HEPA filters in the auxiliary building ventilation system. If the radioactive effluents are discharged without the HEPA filters and it is confirmed that one half of the annual dose objective will be exceeded during the calendar quarter, a special report shall be submitted to the Commission pursuant to Section 4.2.4A.
CH-ODCM-0001 Reference Use Page 29 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.3 Uranium Fuel Cycle 4.3.1 Total Dose-Uranium Fuel Cycle A. Limiting Condition for Operation
- 1. The dose to any real individual from uranium fuel cycle sources shall be limited to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to 75 mrem) during each calendar year.
APPLICABILITY: At all times ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specifications 4.1.2A, 4.2.2A, or 4.2.3A, calculations shall be made including direct radiation contribution from the facility and outside storage tanks to determine whether the above limits have been exceeded. If such is the case, in lieu of any other report required by Section 6.2, prepare and submit a Special Report to the Commission pursuant to Technical Specification 5.16 that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report , as defined in 10 CFR Part 20.2203(a)(4) and 20.2203(b), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 or 10 CFR Part 72.104 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 or 10 CFR Part 72.104.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
CH-ODCM-0001 Reference Use Page 30 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.3.1 (continued)
B. Surveillance Requirements
- 1. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance requirements 4.1.2B, 4.2.2B and 4.2.3B and in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual.
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 5.1 Monitoring Program 5.1.1 Limiting Condition for Operation A. The Radiological Environmental Monitoring Program shall be conducted as specified in Table 5.1.
APPLICABILITY: At all times ACTION:
- 1. Analytical results of this program and deviations from the sampling schedule shall be reported to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 6.2).
- 2. If the level of radioactivity from calculated doses leads to a higher exposure pathway to individuals, this pathway shall be added to the Radiological Environmental Monitoring Program. Modifications to the program shall be reported in the Annual Radiological Environmental Operating Report to the Nuclear Regulatory Commission.
- 3. If the level of radioactivity in an environmental sampling medium exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.3). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 5.3 for Lower Level of Detection (LLD).
CH-ODCM-0001 Reference Use Page 31 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 5.1.1A (continued)
- 4. If the level of radioactivity in a sample from either an onsite or offsite well, performed per the Site Groundwater Protection Program, exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.3). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 5.3 for Lower Level of Detection (LLD). Copies of the Special Report will be forwarded to State/Local authorities.
[AR 39127]
- 5. If the level of radioactivity from either an onsite or offsite well, performed per the Site Groundwater Protection Program exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operations, state and local authorities shall be notified by the end of the next business day. NRC shall be notified per LS-FC-1020, Reportability Tables and Decision Tree. [AR 39127]
- 6. Radiological environmental sampling locations and the media that is utilized for analysis are presented in Table 5.2. Sampling locations are also illustrated on the map, Figure 1. Details of the quarterly emergency TLD locations are contained in surveillance test CH-ST-RV-0003, Environmental Sample Collection -
Quarterly/Environmental Dosimeters (TLDs). Each TLD sample location contains one dosimeter that is exchanged quarterly for REMP sampling and as needed for Emergency Planning Zone monitoring.
- 7. Deviations from the monitoring program, presented in this section and detailed in Table 5.2, are permitted if specimens are unobtainable due to mitigating circumstances such as hazardous conditions, seasonal unavailability, malfunction of equipment, or if a person discontinues participation in the program, etc. If the equipment malfunctions, corrective actions will be completed as soon as practicable. If a person no longer supplies samples, a replacement will be made if possible. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report, pursuant to Section 6.2.
5.1.2 Surveillance Requirements A. The Radiological Environmental Monitoring Program (REMP) samples shall be collected and analyzed in accordance with Tables 5.1, 5.2, and 5.3.
CH-ODCM-0001 Reference Use Page 32 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 1. Direct Radiation A. 14 TLD indicator stations, one Gamma dose Quarterly background stationF, total of 15.
B. An inner-ring of 16 stations, one in each cardinal sector in the Gamma dose Quarterly general area of the unrestricted area boundary and within 2.5 miles.
C. An outer-ring of 16 stations, one in each cardinal sector located Gamma dose Quarterly outside of the inner-ring, but no more distant than approximately 5 miles.
D. Other TLDs may be placed at Gamma dose Quarterly special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Omaha Public Power District employees have routine access.
- 2. Air Monitoring A. Indicator Stations Filter for Gross Beta C Weekly
- 1. Three stations in the general Filter for Gamma Isotopic Quarterly area of the unrestricted area composite boundary of weekly filters
- 2. City of Blair
- 3. Desoto Township B. One background station F
- 3. Water A. Missouri River at nearest Gamma Isotopic, H-3 Monthly for downstream drinking water Gamma intake. isotopic analysis.
B. Missouri River downstream near the mixing zone. Quarterly composite for C. Missouri River upstream of H-3 Analysis Facility intake (background)F.
- 4. Milk D A. Nearest milk animal (cow or Gamma Isotopic Monthly goat) within 5 miles B. Milk animal (cow or goat) between 5 miles and 18.75 miles (background)F.
- 5. Fish A. Four fish samples within vicinity Gamma Isotopic Once per of Facility discharge. season (May to B. One background sample October) upstream of Facility discharge.
CH-ODCM-0001 Reference Use Page 33 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 6. Vegetables or A. One sample in the highest Gamma Isotopic Once per Food Products E exposure pathway. season (May to B. One sample from onsite crop October) field C. One sample outside of 5 miles (background)F.
- 7. Groundwater A. Three samples from sources H3, Gross Beta, Gamma Quarterly potentially affected by facility Isotopic, Sr-90 operations.
B. One sample outside of 5 miles (background)F.
- 8. Vegetation in lieu A. One sample at the highest Gamma Isotopic Monthly (when of milk annual average D/Q offsite available) location.
B. One sample at the second highest annual average D/Q offsite location.
C. One sample outside of 5 miles (background) F.
CH-ODCM-0001 Reference Use Page 34 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 NOTES:
A. See Table 5.3 for required detection limits.
B. The Lower Limit of Detection (LLD) for analysis is defined in the Off-Site Dose Calculation Manual in accordance with the wording of NUREG-1301.
C. When a gross beta count indicates radioactivity greater than 2.5E-13 Ci/ml or 0.25 pCi/m3, (ten times the yearly mean), a gamma spectral analysis will be performed.
D. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II, Table 4 "Highest Potential Exposure Pathways for Estimating Dose")
E. Samples should be collected from garden plots of 500 ft2 or more. (Reference Reg. Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants," Dec. 1975).
F. This sample may not be located in the least prevalent wind direction. The Branch Technical Position paper, Table 1, subnote "d" says this regarding background information, or control locations. "The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted".
CH-ODCM-0001 Reference Use Page 35 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate Onsite Station, 110-meter weather 1 tower 0.53 293°/WNW P X Onsite Station, adjacent 2C,E to old plant access road 0.59 207°/SSW K X X Offsite Station, Intersection of Hwy. 75 3 and farm access road 0.94 145°/SE G X 4 Blair OPPD office 2.86 305°/NW Q X X 5A Fort Calhoun, NE City 6 Hall 5.18 150°/SSE H X Fence around intake gate, Desoto Wildlife 7 Refuge 2.07 102°/ESE F X Onsite Station, entrance to Plant Site 8 from Hwy. 75 0.55 191°/S J X Onsite Station, NW of 9 Plant 0.68 305°/NW Q X Onsite Station, WSW of 10 Plant 0.61 242°/WSW M X Offsite Station, SE of 11 Plant 1.07 39°/SE G X
CH-ODCM-0001 Reference Use Page 36 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate Metropolitan Utilities Dist., Florence Treatment Plant 12 North Omaha, NE 14.3 154°/SSE H X West bank Missouri River, downstream from 13 Plant discharge 0.45 108°/ESE F X X Upstream from Intake 14D Bldg, west bank of river 0.09 4°/N A X X 15 Smith Farm 1.99 134°/SE G X 16A 17A 18A 19A 20D Mohr Dairy 9.86 186°/S J B,F X X A
21 Fish Sampling Area, 0.08 22 Missouri River (R.M. 645.0) 6°/N A X Fish Sampling Area, 17.9 23D Missouri River (R.M. 666.0) 358°/N A X 24A 25A 26A 27A
CH-ODCM-0001 Reference Use Page 37 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 28A 29A 30A 31A 32D Valley Substation #902 19.6 221°/SW L X X A
33 34A 35 Onsite Farm Field 0.52 118°/ESE F X Offsite Station Intersection Hwy 75/Co.
36 Rd. P37 0.75 227°/SW L X Offsite Station Desoto 37 Township 1.57 144°/SE G X X A
38 39A 40A 41C Dowler Acreage 0.73 175°/S J X X B,C 42 Sector A-1 1.94 0°/NORTH A X 43 Sector B-1 1.97 16°/NNE B X 44 Sector C-1 1.56 41°/NE C X 45 Sector D-1 1.34 71°/ENE D X 46 Sector E-1 1.54 90°/EAST E X 47 Sector F-1 0.45 108°/ESE F X
CH-ODCM-0001 Reference Use Page 38 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 48 Sector G-1 1.99 134°/SE G X 49 Sector H-1 1.04 159°/SSE H X 50 Sector J-1 0.71 179°/SOUTH J X 51 Sector K-1 0.61 205°/SSW K X 52 Sector L-1 0.74 229°/SW L X 53 Sector M-1 0.93 248°/WSW M X 54 Sector N-1 1.31 266°/WEST N X 55 Sector P-1 0.60 291°/WNW P X 56 Sector Q-1 0.67 307°/NW Q X 57 Sector R-1 2.32 328°/NNW R X 58 Sector A-2 4.54 350°/NORTH A X 59 Sector B-2 2.95 26°/NNE B X 60 Sector C-2 3.32 50°/NE C X 61 Sector D-2 3.11 75°/ENE D X 62 Sector E-2 2.51 90°/EAST E X 63 Sector F-2 2.91 110°/ESE F X 64 Sector G-2 3.00 140°/SE G X 65 Sector H-2 2.58 154°/SSE H X 66 Sector J-2 3.53 181°/SOUTH J X 67 Sector K-2 2.52 205°/SSW K X 68 Sector L-2 2.77 214°/SW L X 69 Sector M-2 2.86 243°/WSW M X
CH-ODCM-0001 Reference Use Page 39 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 70 Sector N-2 2.54 263°/WEST N X 71 Sector P-2 2.99 299°/WNW P X 72 Sector Q-2 3.37 311°/NW Q X 73 Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X C B, C 75 Lomp Acreage 0.65 163°/SSE H X X X X 76 Stangl Farm 3.40 169°/S J X 77G River N-1 0.17 328°/NNW R X G
78 River S-1 0.14 85°/EAST E X G
79 Lagoon S-1 0.24 131°/SE G X G
80 Parking S-1 0.27 158°/SSE H X G
81 Training W-1 0.28 194°/SSW K X 82G Switchyard S-1 0.21 219°/SW L X 83G Switchyard SE-1 0.14 231°/SW L X G
84 Switchyard NE-1 0.18 256°/WSW M X G
85 Switchyard W-1 0.29 233°/WEST L X G
86 Switchyard N-1 0.24 262°/WEST N X G
87 Range S-1 0.20 286°/WNW P X 88G Mausoleum E-1 0.37 216°/SW L X
CH-ODCM-0001 Reference Use Page 40 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 NOTES:
A. Location is either not in use or currently discontinued and is documented in the table for reference only.
B. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II, Table 4 "Highest Potential Exposure Pathways for Estimating Dose")
C. Locations represent highest potential exposure pathways as determined by the biennial Land Use Survey, performed in accordance with Part I, Section 7.3.2, of the Off-Site Dose Calculation Manual and are monitored as such.
D. Background location (control). All other locations are indicators.
E. Location for monitoring Sector K High Exposure Pathway Resident Receptor for inhalation.
F. When broad leaf (pasture grasses) are being collected in lieu of milk, background broad leaf samples will be collected at a background locale.
G. Location for special interest monitoring general dose to the public per 40CFR190 (Figure 2)
CH-ODCM-0001 Reference Use Page 41 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Figure 1 - Environmental Radiological Sampling Points
(*) Locations currently discontinued are not illustrated.
CH-ODCM-0001 Reference Use Page 42 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Figure 2- 40CFR190 Sampling Points
CH-ODCM-0001 Reference Use Page 43 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) A, B, C Gross Co-58, Ba-140 Sample Units Beta H-3 Mn-54 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 La-140 Water pCi/L 4 2.0E+03 1.5E+01 3.0E+01 1.5E+01 3.0E+01 1.5E+01 1.5E+01 1.5E+01 1.8E+01 1.5E+01 pCi/kg Fish (wet) --- --- 1.3E+02 2.6E+02 1.3E+02 2.6E+02 --- --- 1.3E+02 1.5E+02 ---
Milk pCi/L --- --- --- --- --- --- --- --- 1.5E+01 1.8E+01 1.5E+01 Airborne Particulates or Gases pCi/m3 1.0E-02 --- --- --- --- --- --- --- 1.0E-02 1.0E-02 ---
pCi/kg Sediment (dry) --- --- --- --- --- --- --- --- 1.5E+02 1.8E+02 ---
Grass or Broad Leaf Vegetation/
Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 6.0E+01 8.0E+01 ---
A. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable as Facility effluents, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Part I, Section 6.2, of the Off-Site Dose Calculation Manual.
B. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
C. The LLD is defined in Part II of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 44 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples A Sample Units H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Water pCi/L 2.0E+04 1.0E+03 4.0E+02 1.0E+03 3.0E+02 3.0E+02 4.0E+02 4.0E+02 3.0E+01 5.0E+01 2.0E+02 Fish pCi/kg (wet) --- 3.0E+04 1.0E+04 3.0E+04 1.0E+04 2.0E+04 --- --- 1.0E+03 2.0E+03 ---
Milk pCi/L --- --- --- --- --- --- --- --- 6.0E+01 7.0E+01 3.0E+02 Airborne Particulates or pCi/m3 Gases --- --- --- --- --- --- --- --- 1.0E+01 2.0E+01 ---
Grass or Broad Leaf Vegetation/
Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 1.0E+03 2.0E+03 ---
A. A Non-routine report shall be submitted when more than one of the radionuclides listed above are detected in the sampling medium and:
1 2 3
.... 1.0 1 2 3 When radionuclides other than those listed above are detected and are the result of Facility effluents, this report shall be submitted if the potential annual dose to a member of the general public is equal to or greater than the dose objectives of Part I, Section 4.1 and 4.2, of the Off-Site Dose Calculation Manual. This report is not required if the measured level of radioactivity was not the result of Facility effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
CH-ODCM-0001 Reference Use Page 45 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 5.2 Land Use Survey 5.2.1 Limiting Condition for Operation A. A Land Use Survey shall identify the location of the nearest milk animal, nearest meat animal, nearest vegetable garden, nearest groundwater source and the nearest residence in each of the 16 cardinal sectors within a distance of five miles. The survey shall be conducted under the following conditions:
- 1. Within a one-mile radius from the Facility site, enumeration by door-to-door or equivalent counting techniques.
- 2. Within a Five-mile radius, enumeration may be conducted door-to-door or by using referenced information from county agricultural agents or other reliable sources.
APPLICABILITY: At all times ACTION:
- a. If it is learned from this survey that milk animals, vegetable gardens and resident receptors are present at a location which yields a calculated dose greater than 20% from previously sampled location(s), the new location(s) shall be added to the monitoring program. Milk and vegetable garden sampling location(s) having the lowest calculated dose may then be dropped from the monitoring program at the end of the grazing and/or growing season during which the survey was conducted and the new location added to the monitoring program.
Groundwater monitoring is based on a determination if source(s) are potentially affected by facility operations.
Modifications to the air monitoring locations, vegetable garden sampling locations, and milk sampling locations will be made as soon as practicable. The Nuclear Regulatory Commission shall be notified of modifications to the program in the Annual Radiological Environmental Operating Report (Section 6.2).
CH-ODCM-0001 Reference Use Page 46 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 5.2.1A.2 (continued)
- b. If it is learned from this survey that a pathway for dose to a MEMBER OF THE GENERAL PUBLIC no longer exists, an additional pathway has been identified or site specific factors affecting the dose calculations for a pathway have changed, then this information should be documented in the Land Use Survey, the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report.
This information can be used to increase the accuracy of the dose models for the Annual Radioactive Effluent Release Report as well as dose estimates performed during the reporting period (i.e., quarterly dose estimates).
5.2.2 Surveillance Requirements A. A land use survey shall be conducted once per 24 months between the dates of June 1 and October 1. The results of the land use survey shall be submitted to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 6.2) for the year it was performed.
5.3 Interlaboratory Comparison Program 5.3.1 Limiting Condition for Operation A. Analyses shall be performed on radioactive materials as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commission.
APPLICABILITY: At all times ACTION:
- 1. With analysis not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report (Section 6.2).
5.3.2 Surveillance Requirements A. The results of these analyses shall be included in the Annual Radiological Environmental Operating Report (Section 6.2).
CH-ODCM-0001 Reference Use Page 47 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibilities 6.1.1 FCS RP/Chemistry Department is responsible for the implementation and maintenance of the Off-Site Dose Calculation Manual.
6.1.2 FCS Operations Department is responsible for the compliance with the Off-Site Dose Calculation Manual in the operation of Fort Calhoun Station.
6.2 Radioactive Effluent Reporting Requirements The reporting requirements for radioactive effluents stated in this Section are to provide assurance that the limits set forth in Part I of the Off-Site Dose Calculation Manual are complied with. These reports will meet the requirements for documentation of radioactive effluents contained in 10 CFR Part 50.36a; Reg.
Guide 1.21, Rev. 2; Reg. Guide 4.8, Table 1; and Reg. Guide 1.109, Rev. 1.
6.2.1 Annual Radioactive Effluent Release Report A report covering the operation of the Fort Calhoun Station during the previous calendar year shall be submitted prior to May 1 of each year per the requirements of Technical Specifications 5.9.4.a. and 10 CFR Part 50.
The Radioactive Effluent Release Report shall include:
A. A summary of the quantities of radioactive liquid and airborne effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21, Revision 2.
B. A summary of the annual meteorological data that provides joint frequency distributions of wind direction and wind speed by atmospheric stability class will be included in the annual report. In addition, hourly meteorological data is recorded and retained on site as outlined in Regulatory Guide 1.21, Revision 2.
C. An assessment of radiation doses from the radioactive liquid and airborne effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21, Revision 2. The assessment of radiation doses shall be performed in accordance with calculational methodology of the Regulatory Guide 1.109, Revision 1.
D. Changes to the Process Control Program (PCP) or to the Offsite Dose Calculation Manual (ODCM) made during the reporting period. Each change shall be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed and shall indicate the date the change was implemented.
CH-ODCM-0001 Reference Use Page 48 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 6.2.1 (continued)
E. A list and description of abnormal releases or abnormal discharges from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.
F. An explanation of why instrumentation designated in Part I, Sections 3.1.1 and 3.2, of the Off-Site Dose Calculation Manual, was not restored to FUNCTIONAL status within 30 days.
G. A description of any major design changes or modifications made to the Liquid and/or Gaseous Radwaste Treatment Systems or Ventilation Exhaust Systems during the reporting period.
H. An explanation of why the liquid and/or gaseous radwaste treatment systems were not FUNCTIONAL, causing the limits of specifications 4.1.3A and 4.2.4A to be exceeded.
I. The results of sampling from offsite and onsite groundwater wells per the Site Groundwater Protection Plan. [AR 39127]
J. Non-routine planned discharges (e.g., discharges from remediation efforts like pumping contaminated groundwater from a leak).
6.2.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report for the previous one year of operation shall be submitted prior to May 1 of each year. This report contains the data gathered from the Radiological Environmental Monitoring Program. The content of the report shall include:
A. Summarized and tabulated results of the radiological environmental sampling/analysis activities following the format of Regulatory Guide 4.8, Table 1. In the event that some results are not available, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
B. Interpretations and statistical evaluation of the results, including an assessment of the observed impacts of the facility operation and environment.
C. The results of participation in a NRC approved Interlaboratory Comparison Program.
D. The results of land use survey required by Section 5.2.
E. A map of the current environmental monitoring sample locations.
CH-ODCM-0001 Reference Use Page 49 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 6.2.3 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report.
The Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report must be submitted within 60 days after the end of the 12-month monitoring period, per 10 CFR 72.44(d)(3).
A. A Summary of the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous 12 months and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent releases.
6.2.4 Special Report If the limits or requirements of Sections 4.1.2A, 4.1.3A, 4.2.2A, 4.2.3A, 4.2.4A, 4.3.1A, and/or 5.1.1A.3 and/or 5.1.1A.4 are exceeded, a Special Report shall be issued to the Commission, pursuant to Technical Specification 5.16. This report shall include: [AR 39127]
A. The results of an investigation to identify the causes for exceeding the specification.
B. Define and initiate a program of action to reduce levels to within the specification limits.
C. The report shall also include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the condition.
6.2.5 EPA 40 CFR Part 190 Reporting Requirements With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of dose from specifications 4.1.2A, 4.2.2A, or 4.2.3A, calculations shall be made including direct radiation calculations, to prepare and submit a special report to the Commission within 30 days and limit the subsequent releases such that the dose to any real individual from uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except thyroid, which is limited to 75 mrem) over the calendar year. This special report shall include an analysis which demonstrates that radiation exposures to any member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 standard. The submittal of the report is to be considered a timely request and a variance is granted pending the final action on the variance request from the Commission.
CH-ODCM-0001 Reference Use Page 50 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 6.2.5 ISFSI 10 CFR Part 72.104 Reporting Requirements The regulatory requirements of 10CFR20, 10CFR72 and 40CFR190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20, 10CFR72 and 40CFR190 not addressed by 10CFR50 Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public.
CH-ODCM-0001 Reference Use Page 51 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 The 10CFR72.104 dose limits are the same as those specified in 40CFR190.
ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. If the dose limits of 40CFR190 or 10CFR72.104 are exceeded, a special report to the NRC, as well as an appropriate request for exemption/variance, is required to be submitted to the NRC.
The requirement that the dose limits of 10CFR72.104 apply to any real individual is controlled for ISFSI activities in the ISFSI 72.212 report.
Therefore, for the purposes of analyzing dose from the ISFSI, the member of the public as defined in 40CFR190 is the same as for the real individual.
The external Total Body Dose is comprised of:
- 1) Total Body Dose due to noble gas radionuclides in gaseous effluents
- 2) Dose due to radioactive waste and the ISFSI
- 3) Total Body Dose due to radioactivity deposited on the ground (this dose is accounted for in the determination of the non-noble gas dose and is not considered here)
The Total Body Dose, external is given by:
D,ext = D,tb + D,osf Where D,ext is the external dose D,tb is the total body dose D,osf is the dose from on-site storage The Total Dose is then given by:
D,tot = D,ext + D,liq + D,nng Where D,tot is the total dose D,ext is the external dose D,liq is the dose from liquid effluents D,nng is the dose from non-noble gases Dose Limits Total Body, annual 25 mrem Thyroid, annual 75 mrem Other Organs, annual 25 mrem
CH-ODCM-0001 Reference Use Page 52 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 6.3 Change Mechanism The Off-Site Dose Calculation Manual is the controlling document for all radioactive effluent releases. It is defined as a procedure under the guidance of Technical Specification 5.8. It will be revised and reviewed by the Plant Operations Review Committee and approved by the Plant Manager in accordance with Technical Specification 5.17. All changes to the Off-Site Dose Calculation Manual will be forwarded to the Nuclear Regulatory Commission during the next reporting period for the Annual Radioactive Effluent Release Report in accordance with the requirements of Technical Specification 5.17.
6.4 Meteorological Data The Annual Average /Q is utilized to determine the concentrations of radionuclides at the unrestricted area boundary. It is also the factor used in conjunction with the parameters and methodologies in Part II, of the Off-Site Dose Calculation Manual to determine unrestricted area dose on a quarterly bases or as needed. It is based on an average of the highest calculated sector /Q values, using all 16 sectors for each of the three previous year Annual Radioactive Effluent Release Reports, and the XOQDOQ plume trajectory model. An additional 10 percent will be added to the average for unrestricted area dose estimates performed quarterly or as needed for conservatism. When calculating /Q data for the Annual Radiological Effluent Release Report, if the highest calculated /Q for the reporting period is observed to be greater than +/- 10% of the Annual Average /Q previously calculated, contact RP/Chemistry supervision for further instructions. This model conforms with the Nuclear Regulatory Commissions Regulatory Guide 1.111.
Current year meteorological data will be utilized in the preparation of the Annual Radioactive Effluent Release Report. This data is used to calculate the joint frequency table, the dispersion coefficients and deposition factors in all 16 sectors. These are used in the calculation of doses to individuals in unrestricted areas as a result of the operation of Fort Calhoun Station. The models used, GASPAR 2 and LADTAP 2, meet the intent of Nuclear Regulatory Commissions Reg. Guide 1.109 and 1.21 for the reporting of doses due to routine radioactive effluent releases.
CH-ODCM-0001 Reference Use Page 53 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 6.5 References 6.5.1 Regulatory Guide 1.109, Rev. 1 - Calculation of Annual Dose to man from Routine Releases of Reactor Effluents for the purpose of evaluation compliance with 10 CFR Part 50, Appendix I 6.5.2 Regulatory Guide 1.111, Rev. 1 - Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.
6.5.3 Regulatory Guide 1.113, Rev. 1 - Estimating Aquatic Dispersion of Effluents from Accidental and Routine Releases for the purpose of Implementing Appendix I.
6.5.4 Regulatory Guide 4.8, Environmental Technical Specification for Nuclear Power Plants.
6.5.5 NRC Branch Technical Position, March 1978 6.5.6 NUREG-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.
6.5.7 NUREG-1301 - Offsite Dose Calculation Manual Guidance.
6.5.8 Regulatory Guide 1.21, Rev. 2 - Measuring, Evaluating, and Reporting Radioactivity in solid wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.
6.5.9 Code of Federal Regulations, Title 10, Part 20 6.5.10 Code of Federal Regulations, Title 10, Part 50 6.5.11 Code of Federal Regulations, Title 10, Part 72 6.5.12 Code of Federal Regulations, Title 40, Part 190 6.5.13 Fort Calhoun Revised Environmental Report (Unit No. 1)-1972 6.5.14 Fort Calhoun Technical Specifications (Unit No. 1) 6.5.15 Defueled Safety Analysis Report 6.5.16 AR 12357, Implement Recommendations of Memo FC-0133-92, Part I, Table 3.2.1 Action 4, of the Off-Site Calculation Manual 6.5.17 AR 39127, NEI Industry Initiative on Groundwater Protection
CH-ODCM-0001 Reference Use Page 54 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 6.5.18 Regulatory Guide 4.1, Rev. 2 - Radiological Environmental Monitoring for Nuclear Power Plants 6.5.19 SO-G Station Fire Plan 6.5.20 FC-19-001, ODCM rev 29 Change Support Document
CH-ODCM-0001 Reference Use Page 55 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 7.0 BASIS 7.1 Instrumentation 7.1.1 Radioactive Liquid Effluent Instrumentation The Radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
7.1.2 Radioactive Gaseous Effluent Instrumentation The Radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
7.2 Radioactive Effluents 7.2.1 Radioactive Liquid Effluents A. Concentration NOTE: Xe-133 is remaining as the controlling isotope for noble gases, even though it is no longer present due to FCS no longer producing power, because it is more conservative than the remaining noble gases (e.g., Kr-85).
CH-ODCM-0001 Reference Use Page 56 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, and (2) the limits of 10 CFR Part 20.1001-20.2401 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-133 is the controlling isotope and its effluent concentration in air (submersion) was converted to an equivalent concentration in water.
B. Dose This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, with fresh water sites with drinking water supplies which can be potentially affected by facility operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in Part II of the Off-Site Dose Calculation Manual, implement the requirements in Section III.A that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Part II of the Off-Site Dose Calculation Manual, for calculating the doses due to the actual release rates of radioactive material in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
C. Liquid Waste Treatment System
CH-ODCM-0001 Reference Use Page 57 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 The FUNCTIONALITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective and in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified to ensure the design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents are not exceeded.
D. Liquid Holdup Tanks Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
7.2.2 Radioactive Gaseous Effluents A. Concentration This specification, in conjunction with Steps 4.2.2A and 4.2.3A, is provided to ensure that the dose at or beyond the Site Boundary from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for MEMBERS OF THE PUBLIC. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations for these radionuclides do not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To support facility operations, RP/Chemistry supervision may increase this limit up to the limits specified in Technical Specifications 5.16.1.g. Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. Because these concentrations are applied on an instantaneous basis and because of the overriding 10 CFR Part 50 Appendix I cumulative dose limitations, these limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the Site Boundary, to
CH-ODCM-0001 Reference Use Page 58 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR Part 20.1301(a).
B. Dose - Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the Off-Site Dose Calculation Manual, for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The Off-Site Dose Calculation Manual, equations provided for determining the air doses at the site boundary are consistent with Regulatory Guides 1.109 and 1.111.
CH-ODCM-0001 Reference Use Page 59 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 7.2.2 (continued)
C. Dose - Radioactive Material in Particulate Form with Half-Lives Greater than Eight Days (Other than Noble Gases) and Tritium This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the Off-Site Calculation Manual, for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The release rate specification for radioactive material in particulate form with half-lives greater than eight days (other than noble gases) and tritium are dependent on the existing radionuclide pathways to man in the areas at or beyond the site boundary. The pathways that were examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
CH-ODCM-0001 Reference Use Page 60 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 7.2.2 (continued)
D. Gaseous Waste Treatment The FUNCTIONALITY of the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable. This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective and in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified to ensure the design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded.
CH-ODCM-0001 Reference Use Page 61 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 7.2.2 (continued)
E. Total Dose - Uranium Fuel Cycle This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mRems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mRems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the facility remains within twice the dose design objectives of Appendix I, 10 CFR Part 50, and if direct radiation doses (including outside storage tanks, etc.) are kept small. The Special Report shall describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report, with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4) and 20.2203(b) is considered to be a timely request and fulfills the requirements 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. Demonstration of compliance with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301.
CH-ODCM-0001 Reference Use Page 62 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 7.3 Radiological Environmental Monitoring 7.3.1 Monitoring Program The radiological environmental monitoring program required by this specification provides measurements of radiation and radioactive materials in those exposure pathways and for radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program was effective for at least the first three years of commercial operation.
Following this period, program changes are initiated based on operational experience.
7.3.2 Land Use Survey This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this survey. The frequency of the Land Use Survey has been reduced to a biennial requirement in site procedures because persons knowledgeable in land use census monitor usage characteristics perform routine REMP sampling. This approach allows knowledge gained during sample collection to be integrated into the program, maintaining its effectiveness. The best survey information from door to door, aerial or consulting with local agricultural authorities, or equivalent, shall be used. This survey satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the survey to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m2.
For milk, the survey is restricted to only milk animals (cow or goat) producing milk for human consumption. Air monitoring stations are strategically located to monitor the resident receptors who could potentially receive the highest doses from airborne radioactive material. For groundwater, samples shall be taken when sources are determined to potentially be affected by facility operations, and when sources are tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. Guidance provided in the Branch Technical Position and Technical Specification 5.16.2 is used to meet the intent of NUREG-1301.
CH-ODCM-0001 Reference Use Page 63 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 7.3.3 Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
7.4 Abnormal Release or Abnormal Discharge Reporting 7.4.1 Specific information should be reported concerning abnormal (airborne and/or liquid) releases on site and abnormal discharges to the unrestricted area. The report should describe each event in a way that would enable the NRC to adequately understand how the material was released and if there was a discharge to the unrestricted area. The report should describe the potential impact on the ingestion exposure pathway involving surface water and ground water, as applicable. The report should also describe the impact (if any) on other affected exposure pathways (e.g., inhalation from pond evaporation).
7.4.2 The following are the thresholds for reporting abnormal releases and abnormal discharges in the supplemental information section:
A. Abnormal release or Abnormal Discharges that are voluntarily reported to local authorities under NEI 07-07, Industry Ground Water Protection Initiative. [AR 39127]
B. Abnormal release or Abnormal discharges estimated to exceed 100 gallons of radioactive liquid where the presence of licensed radioactive material is positively identified (either in the on-site environs or in the source of the leak or spill) as greater than the minimum detectable activity for the laboratory instrumentation.
C. Abnormal releases to on-site areas that result in detectable residual radioactivity after remediation.
D. Abnormal releases that result in a high effluent radiation alarm without an anticipated trip occurring.
E. Abnormal discharges to an unrestricted area.
CH-ODCM-0001 Reference Use Page 64 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 7.4.3 Information on Abnormal releases or Abnormal discharges should include the following, as applicable:
Date and duration Location Volume Estimated activity of each radionuclide Effluent monitoring results (if any)
On-site monitoring results (is any)
Depth to the local water table Classification(s) of subsurface aquifer(s) (e.g., drinking water, unfit for drinking water, not used for drinking water)
Size and extent of any ground water plume Expected movement/mobility of any ground water plume Land use characteristics (e.g., water used for irrigation)
Remedial actions considered or taken and results obtained Calculated member of the public dose attributable to the release Calculated member of the public dose attributable to the discharge Actions taken to prevent recurrence, as applicable Whether the NRC was notified, the date(s), and the contact organization
CH-ODCM-0001 Reference Use Page 65 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 PART II CALCULATIONS
CH-ODCM-0001 Reference Use Page 66 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents 1.1.1 There is one liquid discharge pathway to the Missouri River. The pathway originates with the radioactive liquid waste processing system (monitor or hotel tanks). This pathway empties into the circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathway and associated radiation monitor. Figure 3 depicts the methods of liquid effluent treatment.
1.1.2 The flowrate for dilution water varies with the number raw water pumps in service 1.1.3 Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2.
For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 Ci/ml total activity.
1.1.4 The liquid effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
1.1.5 The liquid effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
1.1.6 Cs-137 is used to calibrate the liquid effluent monitors.
CH-ODCM-0001 Reference Use Page 67 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.1.7 Liquid Effluent Radiation Monitor A. Overboard Discharge Header Monitor (RM-055)
- 1. This process radiation monitor provides control of the waste monitor tank effluent by monitoring the overboard header prior to its discharge into the circulating water discharge tunnel. The concentration of activity at discharge is controlled below ten times the 10 CFR Part 20 limit of 1.0E-06 Ci/ml at site discharge for unidentified isotopes by the high alarm setpoint which closes the overboard flow control valve.
- 2. The following calculations for maximum concentration and alarm setpoints are valid for radioactive liquid releases of monitor tank discharge.
- 3. The maximum allowable concentration in the overboard discharge header is:
1.0 05 Where:
1.0E-05 Ci/ml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2).
F = Total dilution flow in the discharge tunnel (gpm).
(Normal flow is based on 2 raw water pumps at 7,200 gpm total.)
f = Maximum monitor tank discharge flow rate (gpm).
(Normal monitor tank maximum flow is 15 gpm.)
CMAX = Maximum allowable activity in discharge header (Ci/ml).
CH-ODCM-0001 Reference Use Page 68 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.1.7A (continued)
The High Alarm Setpoint (CPM):
0.75 Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to account for the difference in detector sensitivity for the range of isotopes detected.
Sf = Detector sensitivity factor (CPM/Ci/ml). (Sensitivity based on Cs-137).
K3 = Allocation factor for Waste Liquid Releases (See Table 1)
CMAX = Maximum allowable concentration in discharge header (Ci/ml).
B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 69 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.2 Airborne Effluents 1.2.1 There are two air effluent discharge pathways at the Fort Calhoun Station:
Laboratory and Radioactive Waste Processing Building Exhaust Stack, and the Auxiliary Building Exhaust Stack. An airborne radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 4. The airborne waste disposal system is presented in Figure 5.
Auxiliary Building - The Auxiliary Building Exhaust Stack receives discharges from the auxiliary building ventilation system. Radiation Monitor RM-062 provides noble gas monitoring and particulate sampling for the Auxiliary Building Exhaust Stack. Backup noble gas monitoring and particulate sampling is provided by RM-052.
Laboratory and Radioactive Waste Processing Building (LRWPB) - Noble gas monitoring and particulate sampling is provided by RM-043. This radiation monitor/sampler does not serve a control function.
Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.
The airborne effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
The airborne effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than 5 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
CH-ODCM-0001 Reference Use Page 70 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.2.2 Airborne Effluent Radiation Monitors NOTE: Xe-133 is remaining as the controlling isotope for noble gases, even though it is no longer present due to FCS no longer producing power, because it is more conservative than the remaining noble gases (e.g., Kr-85).
A. Auxiliary Building Exhaust Stack Noble Gas Activity Monitor (RM-062/RM-052)
- 1. Either of these monitors may be used to measure the noble gas activity in the exhaust stack. The noble gas is monitored after passing through a particulate filter, and charcoal cartridge. The monitor controls airborne releases so that five times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.0E-07 Ci/cc, based upon Xe-133, is not exceeded.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from Auxiliary Building Exhaust Stack and the LRWPB Exhaust Stack.
- 3. The maximum allowable release rate for stack airborne activity is calculated as follows:
2.5 06 1.0 06 Where:
2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q sec/m3 = Annual average dispersion factor at the unrestricted area boundary from Part II Table 4, of the Off-Site Dose Calculation Manual.
1.0E+06 cc/m3 = Constant of unit conversion.
CH-ODCM-0001 Reference Use Page 71 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.2.2A (continued)
The High Alarm Setpoint (CPM):
60 0.75 28317 Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.
Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133)
K1 = Allocation factor for Auxiliary Building Exhaust Stack (See Table 1) 60 = Conversion (seconds to minutes).
28317 = Conversion factor (ft3 to cc).
Fv = Auxiliary Building Exhaust stack flow rate (SCFM).
(Default maximum flow rate is 72,500 cfm for 3 Auxiliary Building exhaust fans in operation. Other flow rates may be used, as required.)
RMAX = Maximum Allowable Release Rate in Ci/sec B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 72 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.2.2 (continued)
B. Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and Particulate Sampler (RM-043)
- 1. RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is based on five times the 10 CFR Part 20 limit for Xe-133 at the unrestricted area boundary.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from Auxiliary Building Exhaust Stack and the LRWPB Exhaust Stack.
2.5 06 sec 1.0 06 The maximum allowable release rate for RM-043 is as follows:
Where:
2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q = Annual average dispersion factor at the unrestricted area boundary from Part II of the Off-Site Dose Calculation Manual, Table 4.
1.0E+06 cc/m3 = Constant of unit conversion
CH-ODCM-0001 Reference Use Page 73 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 1.2.2B (continued) i i NOTE This monitor alarms in the Control Room. There are no automatic control functions associated with the actuation of the alarm.
The High Alarm Setpoint (CPM):
60 0.75 28317 Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.
Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133)
K2 = Allocation factor for LRWPB Exhaust Stack (See Table 1) 60 = Conversion (seconds to minutes).
28317 = Conversion factor (ft3 to cc).
Fv = LRWPB Exhaust stack flow rate (SCFM). (Default flow rate is 28,700 cfm. Other flow rates may be used if required.)
RMAX = Maximum Allowable Release Rate in Ci/sec.
B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 74 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 1 - Allocation Factors for Simultaneous Releases NOTE i The Fort Calhoun Station is capable of performing simultaneous airborne releases.
The factors below may be adjusted to meet release requirements, provided that the sum of the Unrestricted Area Fraction Sum for all airborne releases remains less i
than or equal to 1.0.
A. Allocation Factors for Simultaneous Airborne Releases
- 1. Auxiliary Building Exhaust Stack Total: 0.90 K1 Noble Gases (RM-062 or RM-052) 0.75 Particulate/Tritium 0.15 Contributing Pathways:
a) Auxiliary Building 0.90
- 2. Laboratory and Radioactive Waste Building Exhaust Total: 0.10 Stack K2 Noble Gases (RM-043) 0.05 Particulate 0.05 Contributing Pathways:
a) Laboratory and Radioactive Waste Building Exhaust Stack 0.10 Airborne Release Total 1.00 B. Allocation Factors for Simultaneous Liquid Releases
- 1. K3 Waste Liquid Releases (RM-055) 1.00 Liquid Release Total 1.00
CH-ODCM-0001 Reference Use Page 75 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Figure 1 - Exclusion and Site Boundary Map
CH-ODCM-0001 Reference Use Page 76 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Figure 2 - Liquid Radioactive Discharge Pathways
CH-ODCM-0001 Reference Use Page 77 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Figure 3 - Liquid Radioactive Waste Disposal System
CH-ODCM-0001 Reference Use Page 78 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Figure 4 - Airborne Effluent Discharge Pathways
CH-ODCM-0001 Reference Use Page 79 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Figure 5 - Airborne Radioactive Waste Disposal System
CH-ODCM-0001 Reference Use Page 80 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 2.0 EFFLUENT CONCENTRATIONS 2.1 Liquid Effluent Concentrations 2.1.1 The concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) will be limited to the concentrations as specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. For batch releases (Monitor and Hotel Waste Tanks) the analyses will be performed in accordance with Part I, Table 4.1, of the Off-Site Dose Calculation Manual, and the concentration of each radionuclide at site discharge will be calculated, based on the following equation:
1 Radionuclide concentration at site discharge:
Where:
Ai = concentration at site discharge for radionuclide (I), in Ci/ml.
ai = concentration of radionuclide (I) in the undiluted effluent, in Ci/ml.
f = undiluted effluent flowrate, in gpm.
F = total diluted effluent flowrate in gpm.
weci = water effluent concentration limit for radionuclide (I) per 10 CFR Part 20, Appendix B, Table 2, Column 2.
NOTE i In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable.
i 2.2 Airborne Effluent Concentrations 2.2.1 The concentration at the unrestricted area boundary, due to airborne effluent releases, will be limited to less than Appendix B, Table 2, Column 1, values.
Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event an airborne effluent release from the station result in an alarm setpoint being exceeded, an evaluation of the unrestricted area boundary concentration resulting from the release will be performed:
CH-ODCM-0001 Reference Use Page 81 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 2.2.2 To determine the concentration and air effluent concentration (aec) fraction summation at the unrestricted area boundary, the following equations will be used:
1 Where:
Ai = Concentration of radionuclide (I) at the unrestricted area boundary K0 = Constant of unit conversion. (1.0E-6 m3/cc)
ECLi = Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, Column 1 value for radionuclide(I))
Qi = The release rate of radionuclide (I) in airborne effluents from all vent releases (in Ci/sec.)
(/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from Part II, Table 4, of the Off-Site Dose Calculation Manual.
2.2.3 As appropriate, simultaneous releases from the Auxiliary Building Ventilation Stack and Laboratory and Radwaste Building Stack will be considered in evaluating compliance with the release rate limits of 10 CFR Part 20.
Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. Historical annual average dispersion parameters, as presented in Table 4, may be used for evaluating the airborne effluent dose rate.
2.2.4 For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding those more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding 10 CFR Part 20 limits. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based upon the above criteria, no further analyses are required for demonstrating compliance with 10 CFR Part 20.
CH-ODCM-0001 Reference Use Page 82 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS 3.1 Liquid Effluent Dose Calculations 3.1.1 Three pathways for human exposure to liquid releases from FCS to the Missouri River exists: 1) fish, 2) drinking water, and 3) Shoreline deposition.
Fish are considered to be taken from the vicinity of the facility discharge.
The drinking water for Omaha is located 19 miles downstream from FCS.
The dilution factors for these pathways are derived from the Revised Environmental Report for FCS, (1974), (page 4-29 and 4-31). This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be < 14% of the concentration at discharge from FCS and will average 3%. This equates to a dilution factor of 7.14, which is used to calculate the maximum dose to an individual from liquid pathways and a dilution factor of 33.33, for calculating the average dose. All pathways combine to give the dose to an individual in unrestricted areas.
3.1.2 10 CFR Part 50, Appendix I restricts the dose to individuals in the unrestricted areas from radioactive materials in liquid effluents from the Fort Calhoun Station to the following limits:
during any calendar quarter 1.5 mrem to total body 5.0 mrem to any organ and during any calendar year 3.0 mrem to total body 10.0 mrem to any organ The following calculational methods shall be used for determining the dose or dose commitment from liquid effluents.
CH-ODCM-0001 Reference Use Page 83 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.1.3 Doses from Liquid Effluent Pathways A. Potable Water 1100 exp Where:
Rapj = is the total annual dose to organ(j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr.
Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in
/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless.
(Table 17)
F = is the flow rate of the liquid effluent, in ft3/ sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Daipj = is the dose factor specific to a given age group (a),
radionuclide (I), pathway (p), and organ (j) which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = is the radiological decay constant of radionuclide (I), in hr 1.
tp = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the radionuclides and ingestion of water, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 84 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.1.3 (continued)
B. Aquatic Foods 1100 exp Where:
Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr.
Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in kg/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless. (Table 17)
F = is the flow rate of the liquid effluent, in ft3/sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Bip = is the equilibrium bioaccumulation factor for radionuclide (I) in pathway (p) expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in (pCi/kg)/(pCi/liter). (Table 3)
Daipj = is the dose factor specific to a given age group (a),
radionuclide (I), pathway (p), and organ (j), which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = is the radiological decay constant of radionuclide (I), in hr-1.
tp = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the radionuclides and ingestion of food, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 85 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.1.3 (continued)
C. Shoreline Deposits 110,000 exp 1 exp Where:
Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p),
in mrem/yr.
Uap = is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p),
in hr/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless. (Table 17)
W = is the shore-width factor, dimensionless. (Table 17)
F = is the flow rate of the liquid effluent, in ft3/sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Tip = is the radioactive half life of radionuclide (I), in days.
Daipj = is the dose factor specific radionuclide (I) which can be used to calculate the radiation dose from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the real radionuclide concentration (in pCi/m2). (Table 8) i = is the radiological decay constant of radionuclide (I), in hr-1.
tp = is the average transit time required for radionuclides to reach the point of exposure, in hours. (Table 17) tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours. (Table 17) 110,000 = Constant [(100
- pCi
- yr
- ft3)/(Ci
- sec
- L)]
CH-ODCM-0001 Reference Use Page 86 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2 Airborne Effluent Dose Calculations 3.2.1 Noble Gas 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from noble gases in airborne effluents from the Fort Calhoun Station to the following limits:
During any calendar quarter 5 mrad-gamma air dose 10 mrad-beta air dose and During any calendar year 10 mrad-gamma air dose 20 mrad-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses:
A. Doses from Noble Gases
- 1. Annual Gamma/Beta Air Dose from All Other Noble Gas Releases
, , 3.17 10 ,
Where:
DFi or DFi = are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide (I), in mrad-m3/pCi-yr. (Table 2)
D (r,) or D(r,) = are the annual gamma and beta air doses at distance r, in the sector at angle , from the discharge point, in mrad/yr.
Qi = is the annual release rate of radionuclide (I),
in Ci/yr.
[/Q]D(r,) = is the annual average gaseous dispersion factor at distance r, in the sector at angle , in sec/m3.
(Table 4) 3.17x104 = is the number of pCi per Ci divided by the number of seconds per year.
CH-ODCM-0001 Reference Use Page 87 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.1A (continued)
- 2. Annual Total Body Dose from All Other Noble Gas Releases Where:
DFBi = is the total body dose factor for a semi-infinite cloud of the radionuclide (I), which includes the attenuation of 5 g/cm2 of tissue, in mrem-m3/pCi-yr. (Table 2)
(r,) = is the annual total body dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle , in mrem/yr.
Xi(r,) = is the annual average ground-level concentration of radionuclide (I) at distance r, in the sector at angle , in pCi/m3. (Table 4)
Sf = Shielding Factor (Table 17)
CH-ODCM-0001 Reference Use Page 88 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29
- 3. Annual Skin Dose from All Other Noble Gas Releases
, 1.11 , ,
Where:
(r,) = is the annual skin dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle , in mrem/yr.
Xi(r,) = is the annual average ground-level concentration of radionuclide (I) at distance r, in the sector at angle , in pCi/m3. (Table 4)
Sf = Shielding Factor (Table 17)
DFSi = is the beta skin dose factor for a semiinfinite cloud of radionuclide (I), in mrem-m3/pCi-yr.
(Table 2)
= is the gamma skin dose factor for a semiinfinite cloud of radionuclide (I), in mrem-m3/pCi-yr.
(Table 2) 1.11 = is the average ratio of tissue to air energy absorption coefficients.
CH-ODCM-0001 Reference Use Page 89 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.2 Radioiodine, Tritium, and Particulates 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from radioactive materials in gaseous airborne from the Fort Calhoun Station to:
During any calendar quarter 7.5 mrem to any organ and During any calendar year 15 mrem to any organ The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in airborne effluents released to unrestricted areas should be determined by the following expressions:
CH-ODCM-0001 Reference Use Page 90 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.2 (continued)
NOTE i In all cases, for releases of tritium, use the dispersion parameter for inhalation (/Q).
i A. Annual Organ Dose from External Irradiation from Radioactivity Deposited on the Ground Plane The ground plane concentration of radionuclide (I) at distance r, in the sector at angle , with respect to the release point, may be determined by:
1.0 10 ,
, 1 exp Where:
CGI = is the ground plane concentration of the radionuclide (I) at distance r, in the sector at angle , from the release point, in pCi/m2.
Qi = is the annual release rate of radionuclide (I) to the atmosphere, in Ci/yr.
tb = is the time period over which the accumulation is evaluated, which is assumed to be 20 years (mid-point of plant operating life). (Table 17) i(r,) = is the annual average relative deposition of radionuclide (I) at distance r, in the sector at angle , considering depletion of the plume by deposition during transport, in m-2. Table 4 i = is the radiological decay constant for radionuclide (I), in yr-1.
1.0x1012 = is the number of pCi/Ci
CH-ODCM-0001 Reference Use Page 91 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.2A (continued)
The annual organ dose is then calculated using the following equation:
, 8760 ,
Where:
CGj(r,) = is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle , in pCi/m2.
DFGij = is the open field ground plane dose conversion factor for organ (j) from radionuclide (i), in mrem-m2/pCi-hr.
(Table 8)
DGj(r,) = is the annual dose to the organ (j) at distance r, in the sector at angle , in mrem/yr.
Sf = is the shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy, dimensionless. (Table 17) 8760 = is the number of hours in a year B. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide (i) at distance r, in the sector at angle , with respect to the release point, may be determined as:
, 3.17 10 ,
Where:
Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
[/Q]D (r,) = is the annual average atmosphere dispersion factor, in sec/m3 (see Reg Guide 1.111). This includes depletion (for radioiodines and particulates) and radiological decay of the plume. (Table 4) 3.17x104 = is the number of pCi/Ci divided by the number of sec/yr.
CH-ODCM-0001 Reference Use Page 92 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.2B (continued)
The annual dose associated with inhalation of all radionuclides to organ (j) of an individual in age group (a), is then:
Where:
DAja(r,) = is the annual dose to organ (j) of an individual in the age group (a) at distance r, in the sector at angle , due to inhalation, in mrem/yr.
Ra = is the annual air intake for individuals in the age group (a), in m3/yr. (Table 6) i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
DFAija = is the inhalation dose factor for radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 9-12)
CH-ODCM-0001 Reference Use Page 93 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.3 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases A. Parameters for Calculating Concentrations in Forage, Produce, and Leafy Vegetables, excluding Tritium 1 exp 1 exp
, , exp Where:
CVi(r,) = is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle , in pCi/kg.
di (r,) = is the deposition rate of radionuclide (i) at distance r, in the sector at angle , in pCi/m2 hr.
r = is the fraction of deposited activity retained on crops, dimensionless. (Table 17)
Ei = is the effective removal rate constant for radionuclide (i) from crops, in hr-1.
Ei = i + w w = 0.0021/hr. (Table 17) te = is the time period that crops are exposed to contamination during the growing season, in hours.
(Table 17)
Yv = is the agricultural productivity (yield) in kg (wet weight)/m2. (Table 17)
Biv = is the concentration factor for uptake of radionuclide (i) from soil by edible parts of crops, in pCi/ kg (wet weight) per pCi/kg dry soil. (Table 5) i = is the radiological decay constant of radionuclide (I), in hr-1 tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours (mid-point of plant life). (Table 17)
P = is the effective "surface density" for soil, in kg (dry soil)/m2. (Table 17) th = is the holdup time that represents the time interval between harvest and consumption of the food, in hours.
(Table 17)
Different values for the parameters te, Yv, and th, may be used to allow the use of the Equation for different purposes: estimating concentrations in produce consumed by man; in leafy vegetables consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or goats; and in forage consumed as stored feed by dairy cows, beef cattle or goats. See Table 17.
CH-ODCM-0001 Reference Use Page 94 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.3A (continued)
The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa. C-6):
, 1.1 10 ,
Where:
di(r,) = is the deposition rate of radionuclide (i).
i(r,) = is the relative deposition of radionuclide (i), considering depletion and decay, in m-2 (see Reg Guide 1.111).
(Table 4) 1.1x108 = is the number of pCi/Ci (1012) divided by the number of hours per year (8760).
Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
CH-ODCM-0001 Reference Use Page 95 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.3 (continued)
B. For radioiodines, the model considers only the elemental fraction of the effluent:
, 3.3 10 ,
Where:
di (r, ) = The deposition rate of radioiodine (i).
3.3 x 107 = The number of pCi/Ci (1012) divided by the number of hours per year (8760), then multiplied by the amount of radioiodine emissions considered to be elemental (0.5).
i (r, ) = The relative deposition of radioiodine (i), considering depletion and decay, in m-2. (Table 4)
Qi = The total (elemental and nonelemental) radioiodine (i) emission rate.
C. Parameters for Calculating the Concentration of Radionuclide (i) in the Animal's Feed (Milk Cow, Beef Cow, and Goat)
, , 1 , 1 ,
Where:
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
CPi(r,) = is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2.3A with th=0), in pCi/kg.
CSi(r,) = is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3A with th=90 days), in pCi/kg.
fp = is the fraction of the year that animals graze on pasture. (Table 17) fs = is the fraction of daily feed that is pasture grass while the animal grazes on pasture. (Table 17)
CH-ODCM-0001 Reference Use Page 96 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk
, , exp Where:
CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter.
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
Fm = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each liter of milk, in days/liter.
(Table 5)
QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) tf = is the average transport time of the radionuclide (i) from the feed to the milk and to the receptor (a value of 2 days is assumed). (Table 17) i = is the radiological decay constant of radionuclide (i), in days-1.
CH-ODCM-0001 Reference Use Page 97 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.5 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium
, , exp Where:
CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter.
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7)
Ff = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each kilogram of flesh, in days/kilogram. (Table 5) ts = is the average time from slaughter to consumption. (Table 17) 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.
, 0.75 0.5 ,
, 3.17 10 1.2 10 Where:
CVT(r, ) = is the concentration of tritium in vegetation grown at distance r, in the sector at angle , in pCi/kg.
H = is the absolute humidity of the atmosphere at distance r, in the sector at angle , in g/m3. H=8 gm/kg.
QT = is the annual release rate of tritium, in Ci/yr.
[/Q](r,) = is the atmospheric dispersion factor, in sec/m3. (Table 4) 0.5 = is the ratio of tritium concentration in facility water to tritium concentration in atmospheric water, dimensionless.
0.75 = is the fraction of total facility mass that is water, dimensionless.
CH-ODCM-0001 Reference Use Page 98 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ (j) of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by:
Where:
DDja(r,) = is the annual dose to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. Tables 13-16.
UVa = are the ingestion rates of produce (non-leafy vegetables, fruits, and grains) , respectively for individuals in age group (a).
(Table 6)
UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6)
UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6)
ULa = are the ingestion rates of leafy vegetables for individuals in age group (a), in kg/yr. (Table 6)
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter.
CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter.
CLI (r,) = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.
fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 99 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 3.2.7 (continued)
B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce)
Vegetation for Radionuclide (i) to Each Organ (j) and Age Group (a)
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i) to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in vegetation, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pci. Tables 13-16 ULa,UVa = are the ingestion rates of leafy vegetables and produce (non-leafy vegetables, fruits, and grains), for individuals in age group (a), in kg/yr. (Table 6)
CLi = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.
CVi = is the concentration of radionuclide (i) in and on produce, in pCi/kg.
fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 100 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 C. Calculation Determining the Ingested Dose from Cow Milk for Radionuclide (i), Organ (j), and Age Group (a)
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in cow milk, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16)
UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6)
CMi = is the radionuclide concentration in cow milk, in pCi/kg.
Equation 3.2.4 D. Calculation Determining the Ingested Dose from Meat for Radionuclide (i) to Organ (j) and Age Group (a)
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in meat, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16)
UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6)
CFi = is the radionuclide (i) concentration in meat, in pCi/kg.
3.2.8 Annual Dose from Carbon 14 A. This is a calculated value based on power generation and days of operation. Critical organ doses from C-14 were calculated using a ratio of 15% as CO2. This ratio was determined during an NRC in-plant source term study conducted at the Fort Calhoun Station between 1976 and 1977, NUREG/CR-0140.
CH-ODCM-0001 Reference Use Page 101 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 4.0 LOWER LIMIT OF DETECTION (LLD) 4.1 The lower limit of detection (LLD) for liquid and airborne effluent discharges and environmental samples referenced in Part I, Tables 4.1, 4.2 and 5.3, of the Off-Site Dose Calculation Manual, is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
4.2 For a particular measurement system, which may include radiochemical separation:
4.66 exp Where:
LLD = the lower limit of detection as defined above, in either picoCuries or microCuries, per unit mass or volume as a function of the value of D Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate, as counts per minute E = the counting efficiency, as counts per disintegration V = the sample size in units of mass or volume D = 2.22E+06 of disintegrations per minute per microCurie or 2.22 disintegrations per minute per picoCurie Y = the fractional radiochemical yield, when applicable
= the radioactive decay constant for the particular radionuclide t = the elapsed time between the midpoint of sample collection and time of counting Appropriate values of E, V, Y, and t should be used in the calculation.
4.3 It should be recognized that the LLD is defined as an A Priori limit representing the capability of a measurement system and not as a limit for a particular measurement.
4.4 LLD verifications will be performed on a periodic basis. This determination is to ensure that the counting system is able to detect levels of radiation at the LLD values for the specific type of analysis required. They will be performed with a blank (non-radioactive) sample in the same counting geometry as the actual sample.
CH-ODCM-0001 Reference Use Page 102 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Nuclide -Air1 (Dfi) -Skin2 (DFSi) -Air1 (Dfi) -Body2 (DFBi)
Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11E-03 4.67E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 1.
2.
CH-ODCM-0001 Reference Use Page 103 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 3 - Bioaccumulation Factors (pCi/kg per pCi/liter)
FRESHWATER Element Fish Invertebrate H 9.0E-01 9.0E-01 C 4.6E+03 9.1E+03 Na 1.0E+02 2.0E+02 P 1.0E+05 2.0E+04 Cr 2.0E+02 2.0E+03 Mn 4.0E+02 9.0E+04 Fe 1.0E+02 3.2E+03 Co 5.0E+01 2.0E+02 Ni 1.0E+02 1.0E+02 Cu 5.0E+01 4.0E+02 Zn 2.0E+03 1.0E+04 Br 4.2E+02 3.3E+02 Rb 2.0E+03 1.0E+03 Sr 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+03 Zr 3.3E+00 6.7E+00 Nb 3.0E+04 1.0E+02 Mo 1.0E+01 1.0E+01 Tc 1.5E+01 5.0E+00 Ru 1.0E+01 3.0E+02 Rh 1.0E+01 3.0E+02 Te 4.0E+02 6.1E+03 I 1.5E+01 5.0E+00 Cs 2.0E+03 1.0E+03 Ba 4.0E+00 2.0E+02 La 2.5E+01 1.0E+03 Ce 1.0E+00 1.0E+03 Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E+03 W 1.2E+03 1.0E+01 Np 1.0E+01 4.0E+02
CH-ODCM-0001 Reference Use Page 104 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 4 - Highest Potential Exposure Pathways for Estimating Dose NOTE i The Annual Radiological Effluent Report uses the highest calculated value from real time meteorological data obtained for the entire year for calculating i dose.
Distance
/Q A D/Q A Exposure from Location B Direction B {/Q (r,)} { (r,)}
Pathway Containment (sec/m3) (m-2)
(miles) B Direct Exposure Site SSE 0.60 1.30E-05 N/A Boundary Inhalation Site SSE 0.60 1.30E-05 N/A Boundary Ingestion Residence SSE 0.60 N/A 7.6E-08 A. These values are used for calculating quarterly dose estimates during the annual reporting period and are based on a 2 year average, updated only upon a +10%
change from the previous value. At least ten percent (10%) should be added to these values for dose estimates during the reporting periods.
B. The location is subject to change based on an annual evaluation and is utilized only for ingestion exposure pathway dose estimates. This location may differ from the highest ingestion exposure pathway for offsite air monitoring locations as determined by the Land Use Survey performed biennially in accordance with Part 1, Section 7.3.2, of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 105 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 5 - Stable Element Transfer Data Biv Fm (cow) Fm (goat) Ff Element Veg./Soil Milk (d/I) Milk (d/I) Meat (d/kg)
H 4.8E+00 1.0E-02 1.7E-01 1.2E-02 C 5.5E+00 1.2E-02 1.0E-01 3.1E-02 Na 5.2E-02 4.0E-02 ------ 3.0E-02 P 1.1E+00 2.5E-02 2.5E-01 4.6E-02 Cr 2.5E-04 2.2E-03 ------ 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 1.3E-04 4.0E-02 Co 9.4E-03 1.0E-03 ------ 1.3E-02 Ni 1.9E-02 6.7E-03 ------ 5.3E-02 Cu 1.2E-01 1.4E-02 1.3E-02 8.0E-03 Zn 4.0E-01 3.9E-02 ------ 3.0E-02 Rb 1.3E-01 3.0E-02 ------ 3.1E-02 Sr 1.7E-02 8.0E-04 1.4E-02 6.0E-04 Y 2.6E-03 1.0E-05 ------ 4.6E-03 Zr 1.7E-04 5.0E-06 ------ 3.4E-02 Nb 9.4E-03 2.5E-03 ------ 2.8E-01 Mo 1.2E-01 7.5E-03 ------ 8.0E-03 Tc 2.5E-01 2.5E-02 ------ 4.0E-01 Ru 5.0E-02 1.0E-06 ------ 4.0E-01 Rh 1.3E+1 1.0E-02 ------ 1.5E-03 Ag 1.5E-01 5.0E-02 ------ 1.7E-02 Sb 1.1E-02 1.5E-03 ------ 4.0E-03 Te 1.3E+00 1.0E-03 ------ 7.7E-02 I 2.0E-02 6.0E-03 6.0E-02 2.9E-03 Cs 1.0E-02 1.2E-02 3.0E-01 4.0E-03 Ba 5.0E-03 4.0E-04 ------ 3.2E-03 La 2.5E-03 5.0E-06 ------ 2.0E-04 Ce 2.5E-03 1.0E-04 ------ 1.2E-03 Pr 2.5E-03 5.0E-06 ------ 4.7E-03 Nd 2.4E-03 5.0E-06 ------ 3.3E-03 W 1.8E-02 5.0E-04 ------ 1.3E-03 Pu 2.5E-04 2.0E-06 ------ 1.4E-05 Np 2.5E-03 5.0E-06 ------ 2.0E-04 Am 2.5E-04 5.0E-06 ------ 2.0E-04 Cm 2.5E-03 5.0E-06 ------ 2.0E-04
CH-ODCM-0001 Reference Use Page 106 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data Pathway Infant Child Teen Adult Fruits, vegetables, & grain (kg/yr) --- 520 630 520 Leafy vegetables (kg/yr) --- 26 42 64 Milk (/yr) 330 330 400 310 Meat & poultry (kg/yr) --- 41 65 110 Fish (fresh or salt)(kg/yr) --- 6.9 16 21 Other Seafood (kg/yr) --- 1.7 3.8 5 Drinking water (/yr) 330 510 510 730 Shoreline recreation (hr/yr) --- 14 67 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table 7 - Animal Consumption Rates Animal QF Feed or Forage [Kg/day (wet weigh)] QAW Water (/day)
Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8
CH-ODCM-0001 Reference Use Page 107 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin H-3 --- ---
C-14 --- ---
Na-24 2.50E-08 2.90E-08 P-32 --- ---
Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 --- ---
Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-59 --- ---
Ni-63 --- ---
Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 --- ---
Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 --- ---
Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09
CH-ODCM-0001 Reference Use Page 108 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Sb-124 1.30E-08 1.50E-08 Sb-125 3.10E-09 3.50E-09 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 --- ---
Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09
CH-ODCM-0001 Reference Use Page 109 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin Pu-238 1.30E-12 1.80E-11 Pu-239 7.90E-13 7.70E-12 Pu-240 1.30E-12 1.80E-11 Pu-241 4.60E-12 6.80E-12 Np-239 9.50E-10 1.10E-09 Am-241 1.80E-10 2.60E-10 Cm-242 5.50E-12 2.30E-11 Cm-243 2.30E-09 2.90E-09 Cm-244 2.90E-12 1.80E-11
CH-ODCM-0001 Reference Use Page 110 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 --- --- --- 1.08E-05 Cr-51 --- --- 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 --- 4.95E-06 7.87E-07 --- 1.23E-06 1.75E-04 9.67E-06 Mn-56 --- 1.55E-10 2.29E-11 --- 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 --- --- 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 --- --- 1.27E-04 2.35E-05 Co-58 --- 1.98E-07 2.59E-07 --- --- 1.16E-04 1.33E-05 Co-60 --- 1.44E-06 1.85E-06 --- --- 7.46E-04 3.56E-05 Ni-59 4.06E-06 1.46E-06 6.77E-07 --- --- 8.20E-06 6.11E-07 Ni-63 5.40E-05 3.93E-06 1.81E-06 --- --- 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 --- --- 7.00E-07 1.54E-06 Cu-64 --- 1.83E-10 7.69E-11 --- 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 --- 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 --- 5.27E-12 1.15E-07 2.04E-09 Br-83 --- --- 3.01E-08 --- --- --- 2.90E-08 Br-84 --- --- 3.91E-08 --- --- --- 2.05E-13 Br-85 --- --- 1.60E-09 --- --- --- ---
Rb-86 --- 1.69E-05 7.37E-06 --- --- --- 2.08E-06 Rb-88 --- 4.84E-08 2.41E-08 --- --- --- 4.18E-19 Rb-89 --- 3.20E-08 2.12E-08 --- --- --- 1.16E-21 Sr-89 3.80E-05 --- 1.09E-06 --- --- 1.75E-04 4.37E-05 Sr-90 3.59E-03 --- 7.21E-05 --- --- 1.20E-03 9.02E-05 Sr-91 7.74E-09 --- 3.13E-10 --- --- 4.56E-06 2.39E-05 Sr-92 8.43E-10 --- 3.64E-11 --- --- 2.06E-06 5.38E-06 Y-90 2.61E-07 --- 7.01E-09 --- --- 2.12E-05 6.32E-05 Y-91M 3.26E-11 --- 1.27E-12 --- --- 2.40E-07 1.66E-10 Y-91 5.78E-05 --- 1.55E-06 --- --- 2.13E-04 4.81E-05 Y-92 1.29E-09 --- 3.77E-11 --- --- 1.96E-06 9.19E-06 Y-93 1.18E-08 --- 3.26E-10 --- --- 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 --- 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 --- 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 --- 9.67E-07 6.31E-05 1.30E-05 Mo-99 --- 1.51E-08 2.87E-09 --- 3.64E-08 1.14E-05 3.10E-05 Tc-99M 1.29E-13 3.64E-13 4.63E-12 --- 5.52E-12 9.55E-08 5.20E-07
CH-ODCM-0001 Reference Use Page 111 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 5.22E-15 7.52E-15 7.38E-14 --- 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 --- 8.23E-08 --- 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 --- 3.89E-11 --- 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 --- 1.09E-06 --- 1.67E-05 1.17E-03 1.14E-04 Ag-110M 1.35E-06 1.25E-06 7.43E-07 --- 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 --- 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 --- 2.18E-04 1.26E-05 Te-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 --- 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 --- 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 --- 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 --- 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 --- 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 --- 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 --- 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 --- 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 --- 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 --- 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 --- 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 --- 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 --- 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 --- 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 --- --- 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 --- --- 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 --- 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 --- 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 --- 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 --- 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 --- 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 --- 4.45E-07 2.76E-05 2.16E-05
CH-ODCM-0001 Reference Use Page 112 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.06E-09 8.85E-10 3.10E-10 --- --- 3.63E-06 1.94E-05 Pu-238 1.43E+00 9.71E-01 6.90E-02 --- 2.96E-01 1.82E-01 4.52E-05 Pu-239 1.66E+00 1.07E+00 7.75E-02 --- 3.30E-01 1.72E-01 4.13E-05 Pu-240 1.65E+00 1.07E+00 7.73E-02 --- 3.29E-01 1.72E-01 4.21E-05 Pu-241 3.42E-02 8.69E-03 1.29E-03 --- 5.93E-03 1.52E-04 8.65E-07 Np-239 2.87E-08 2.54E-08 1.55E-09 --- 8.75E-09 4.70E-06 1.49E-05 Am-241 1.68E+00 1.13E+00 6.71E-02 --- 5.04E-01 6.06E-02 4.60E-05 Cm-242 2.22E-02 1.77E-02 9.84E-04 --- 4.48E-03 3.92E-02 4.91E-05 Cm-243 1.10E+00 7.61E-01 4.61E-02 --- 2.15E-01 6.31E-02 4.84E-05 Cm-244 8.37E-01 5.88E-01 3.51E-02 --- 1.64E-01 6.06E-02 4.68E-05
CH-ODCM-0001 Reference Use Page 113 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 --- --- --- 1.16E-05 Cr-51 --- --- 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 --- 6.39E-06 1.05E-06 --- 1.59E-06 2.48E-04 8.35E-06 Mn-56 --- 2.12E-10 3.15E-11 --- 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 --- --- 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 --- --- 1.91E-04 2.23E-05 Co-58 --- 2.59E-07 3.47E-07 --- --- 1.68E-04 1.19E-05 Co-60 --- 1.89E-06 2.48E-06 --- --- 1.09E-03 3.24E-05 Ni-59 5.44E-06 2.02E-06 9.24E-07 --- --- 1.41E-05 6.48E-07 Ni-63 7.25E-05 5.43E-06 2.47E-06 --- --- 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 --- --- 1.17E-06 4.59E-06 Cu-64 --- 2.54E-10 1.06E-10 --- 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 --- 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 --- 7.53E-12 1.98E-07 3.56E-08 Br-83 --- --- 4.30E-08 --- --- --- ---
Br-84 --- --- 5.41E-08 --- --- --- ---
Br-85 --- --- 2.29E-09 --- --- --- ---
Rb-86 --- 2.38E-05 1.05E-05 --- --- --- 2.21E-06 Rb-88 --- 6.82E-08 3.40E-08 --- --- --- 3.65E-15 Rb-89 --- 4.40E-08 2.91E-08 --- --- --- 4.22E-17 Sr-89 5.43E-05 --- 1.56E-06 --- --- 3.02E-04 4.64E-05 Sr-90 4.14E-03 --- 8.33E-05 --- --- 2.06E-03 9.56E-05 Sr-91 1.10E-08 --- 4.39E-10 --- --- 7.59E-06 3.24E-05 Sr-92 1.19E-09 --- 5.08E-11 --- --- 3.43E-06 1.49E-05 Y-90 3.73E-07 --- 1.00E-08 --- --- 3.66E-05 6.99E-05 Y-91M 4.63E-11 --- 1.77E-12 --- --- 4.00E-07 3.77E-09 Y-91 8.26E-05 --- 2.21E-06 --- --- 3.67E-04 5.11E-05 Y-92 1.84E-09 --- 5.36E-11 --- --- 3.35E-06 2.06E-05 Y-93 1.69E-08 --- 4.65E-10 --- --- 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 --- 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 --- 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 --- 1.25E-06 9.39E-05 1.21E-05 Mo-99 --- 2.11E-08 4.03E-09 --- 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 --- 7.20E-12 1.44E-07 7.66E-07
CH-ODCM-0001 Reference Use Page 114 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 7.40E-15 1.05E-14 1.03E-13 --- 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 --- 1.12E-07 --- 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 --- 5.42E-11 --- 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 --- 1.55E-06 --- 2.38E-05 2.01E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-06 9.99E-07 --- 3.13E-06 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 --- 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 --- 3.42E-04 1.24E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 --- 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 --- 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 --- 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 --- 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 --- 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 --- 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 --- 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 --- 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 --- 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 --- 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 --- 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 --- 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 --- 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 --- 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 --- 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 --- --- 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 --- --- 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 --- 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 --- 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 --- 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 --- 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 --- 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 --- 6.28E-07 4.65E-05 2.28E-05
CH-ODCM-0001 Reference Use Page 115 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.50E-09 1.22E-09 4.29E-10 --- --- 5.92E-06 2.21E-05 Pu-238 1.50E+00 1.03E+00 7.22E-02 --- 3.10E-01 3.12E-01 4.79E-05 Pu-239 1.73E+00 1.12E+00 8.05E-02 --- 3.44E-01 2.93E-01 4.37E-05 Pu-240 1.72E+00 1.12E+00 8.04E-02 --- 3.43E-01 2.93E-01 4.46E-05 Pu-241 3.74E-02 9.56E-03 1.40E-03 --- 6.47E-03 2.60E-04 9.17E-07 Np-239 4.23E-08 3.60E-08 2.21E-09 --- 1.25E-08 8.11E-06 1.65E-05 Am-241 1.77E+00 1.20E+00 7.10E-02 --- 5.32E-01 1.05E-01 4.88E-05 Cm-242 3.17E-02 2.51E-02 1.41E-03 --- 6.40E-03 6.76E-02 5.21E-05 Cm-243 1.19E+00 8.30E-01 5.00E-02 --- 2.34E-01 1.09E-01 5.13E-05 Cm-244 9.19E-01 6.53E-01 3.88E-02 --- 1.81E-01 1.05E-01 4.96E-05
CH-ODCM-0001 Reference Use Page 116 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 --- --- --- 1.14E-05 Cr-51 --- --- 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 --- 1.16E-05 2.57E-06 --- 2.71E-06 4.26E-04 6.19E-06 Mn-56 --- 4.48E-10 8.43E-11 --- 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 --- --- 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 --- --- 3.43E-04 1.91E-05 Co-58 --- 4.79E-07 8.55E-07 --- --- 2.99E-04 9.29E-06 Co-60 --- 3.55E-06 6.12E-06 --- --- 1.91E-03 2.60E-05 Ni-59 1.66E-05 4.67E-06 2.83E-06 --- --- 2.73E-05 6.29E-07 Ni-63 2.22E-04 1.25E-05 7.56E-06 --- --- 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 --- --- 2.21E-06 2.27E-05 Cu-64 --- 5.39E-10 2.90E-10 --- 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 --- 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 --- 1.58E-11 3.84E-07 2.75E-06 Br-83 --- --- 1.28E-07 --- --- --- ---
Br-84 --- --- 1.48E-07 --- --- --- ---
Br-85 --- --- 6.84E-09 --- --- --- ---
Rb-86 --- 5.36E-05 3.09E-05 --- --- --- 2.16E-06 Rb-88 --- 1.52E-07 9.90E-08 --- --- --- 4.66E-09 Rb-89 --- 9.33E-08 7.85E-08 --- --- --- 5.11E-10 Sr-89 1.62E-04 --- 4.66E-06 --- --- 5.83E-04 4.52E-05 Sr-90 1.04E-02 --- 2.07E-04 --- --- 3.99E-03 9.28E-05 Sr-91 3.28E-08 --- 1.24E-09 --- --- 1.44E-05 4.70E-05 Sr-92 3.54E-09 --- 1.42E-10 --- --- 6.49E-06 6.55E-05 Y-90 1.11E-06 --- 2.99E-08 --- --- 7.07E-05 7.24E-05 Y-91M 1.37E-10 --- 4.98E-12 --- --- 7.60E-07 4.64E-07 Y-91 2.47E-04 --- 6.59E-06 --- --- 7.10E-04 4.97E-05 Y-92 5.50E-09 --- 1.57E-10 --- --- 6.46E-06 6.46E-05 Y-93 5.04E-08 --- 1.38E-09 --- --- 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 --- 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 --- 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 --- 2.33E-06 1.66E-04 1.00E-05 Mo-99 --- 4.66E-08 1.15E-08 --- 1.06E-07 3.66E-05 3.42E-05 Tc-99M 4.81E-13 9.41E-13 1.56E-11 --- 1.37E-11 2.57E-07 1.30E-06
CH-ODCM-0001 Reference Use Page 117 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.19E-14 2.30E-14 2.91E-13 --- 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 --- 2.90E-07 --- 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 --- 1.50E-10 --- 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 --- 4.57E-06 --- 4.97E-05 3.87E-03 1.16E-04 Ag-110M 4.56E-06 3.08E-06 2.47E-06 --- 5.74E-06 1.48E-03 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 --- 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 --- 6.27E-04 1.09E-05 Te-125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 --- 1.29E-04 9.13E-06 Te-127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 --- 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 --- 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 --- 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 --- 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 --- 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 --- 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 --- 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 --- 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 --- 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 --- 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 --- 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 --- 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 --- 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 --- 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 --- --- 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 --- --- 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 --- 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 --- 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 --- 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 --- 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 --- 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 --- 1.30E-06 8.87E-05 2.22E-05
CH-ODCM-0001 Reference Use Page 118 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 4.41E-09 2.61E-09 1.17E-09 --- --- 1.11E-05 2.46E-05 Pu-238 2.55E+00 1.60E+00 1.21E-01 --- 4.47E-01 6.08E-01 4.65E-05 Pu-239 2.79E+00 1.68E+00 1.28E-01 --- 4.78E-01 5.72E-01 4.24E-05 Pu-240 2.79E+00 1.68E+00 1.27E-01 --- 4.77E-01 5.71E-01 4.33E-05 Pu-241 7.94E-02 1.75E-02 2.93E-03 --- 1.10E-02 5.06E-04 8.90E-07 Np-239 1.26E-07 8.14E-08 6.35E-09 --- 2.63E-08 1.57E-05 1.73E-05 Am-241 2.97E+00 1.84E+00 1.24E-01 --- 7.63E-01 2.02E-01 4.73E-05 Cm-242 9.48E-02 5.68E-02 4.20E-03 --- 1.34E-02 1.31E-01 5.06E-05 Cm-243 2.32E+00 1.42E+00 9.95E-02 --- 3.74E-01 2.10E-01 4.98E-05 Cm-244 1.94E+00 1.18E+00 8.31E-02 --- 3.06E-01 2.02E-01 4.82E-05
CH-ODCM-0001 Reference Use Page 119 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 --- --- --- 1.15E-05 Cr-51 --- --- 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 --- 1.81E-05 3.56E-06 --- 3.56E-06 7.14E-04 5.04E-06 Mn-56 --- 1.10E-09 1.58E-10 --- 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 --- --- 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 --- --- 7.25E-04 1.77E-05 Co-58 --- 8.71E-07 1.30E-06 --- --- 5.55E-04 7.95E-06 Co-60 --- 5.73E-06 8.41E-06 --- --- 3.22E-03 2.28E-05 Ni-59 1.81E-05 5.44E-06 3.10E-06 --- --- 5.48E-05 6.34E-07 Ni-63 2.42E-04 1.46E-05 8.29E-06 --- --- 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 --- --- 5.80E-06 3.58E-05 Cu-64 --- 1.34E-09 5.53E-10 --- 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 --- 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 --- 2.87E-11 1.05E-06 9.44E-06 Br-83 --- --- 2.72E-07 --- --- --- ---
Br-84 --- --- 2.86E-07 --- --- --- ---
Br-85 --- --- 1.46E-08 --- --- --- ---
Rb-86 --- 1.36E-04 6.30E-05 --- --- --- 2.17E-06 Rb-88 --- 3.98E-07 2.05E-07 --- --- --- 2.42E-07 Rb-89 --- 2.29E-07 1.47E-07 --- --- --- 4.87E-08 Sr-89 2.84E-04 --- 8.15E-06 --- --- 1.45E-03 4.57E-05 Sr-90 1.11E-02 --- 2.23E-04 --- --- 8.03E-03 9.36E-05 Sr-91 6.83E-08 --- 2.47E-09 --- --- 3.76E-05 5.24E-05 Sr-92 7.50E-09 --- 2.79E-10 --- --- 1.70E-05 1.00E-04 Y-90 2.35E-06 --- 6.30E-08 --- --- 1.92E-04 7.43E-05 Y-91M 2.91E-10 --- 9.90E-12 --- --- 1.99E-06 1.68E-06 Y-91 4.20E-04 --- 1.12E-05 --- --- 1.75E-03 5.02E-05 Y-92 1.17E-08 --- 3.29E-10 --- --- 1.75E-05 9.04E-05 Y-93 1.07E-07 --- 2.91E-09 --- --- 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 --- 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 --- 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 --- 3.37E-06 3.42E-04 9.05E-06 Mo-99 --- 1.18E-07 2.31E-08 --- 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-11 --- 2.22E-11 5.79E-07 1.45E-06
CH-ODCM-0001 Reference Use Page 120 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 4.65E-14 5.88E-14 5.80E-13 --- 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 --- 4.85E-07 --- 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 --- 2.93E-10 --- 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 --- 7.77E-06 --- 7.61E-05 8.26E-03 1.17E-04 Ag-110M 7.13E-06 5.16E-06 3.57E-06 --- 7.80E-06 2.62E-03 2.36E-05 Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 --- 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 --- 1.17E-03 1.05E-05 Te-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 --- 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 --- 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 --- 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 --- 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 --- 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 --- 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 --- 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 --- 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 --- 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 --- 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 --- 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 --- 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 --- 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 --- 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 --- 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 --- --- 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 --- --- 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 --- 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 --- 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 --- 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 --- 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 --- 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 --- 2.25E-06 2.30E-04 2.23E-05
CH-ODCM-0001 Reference Use Page 121 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 9.26E-09 6.44E-09 2.23E-09 --- --- 2.83E-05 2.54E-05 Pu-238 2.69E+00 1.68E+00 1.27E-01 --- 4.64E-01 9.03E-01 4.69E-05 Pu-239 2.93E+00 1.76E+00 1.34E-01 --- 4.95E-01 8.47E-01 4.28E-05 Pu-240 2.93E+00 1.75E+00 1.34E-01 --- 4.94E-01 8.47E-01 4.36E-05 Pu-241 8.43E-02 1.85E-02 3.11E-03 --- 1.15E-02 7.62E-04 8.97E-07 Np-239 2.65E-07 2.13E-07 1.34E-08 --- 4.73E-08 4.25E-05 1.78E-05 Am-241 3.15E+00 1.95E+00 1.31E-01 --- 7.94E-01 4.06E-01 4.78E-05 Cm-242 1.28E-01 8.65E-02 5.70E-03 --- 1.69E-02 2.97E-01 5.10E-05 Cm-243 2.47E+00 1.52E+00 1.06E-01 --- 3.91E-01 4.24E-01 5.02E-05 CM-244 2.07E+00 1.27E+00 8.89E-02 --- 3.21E-01 4.08E-01 4.86E-05
CH-ODCM-0001 Reference Use Page 122 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 --- --- --- 2.17E-05 Cr-51 --- --- 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 --- 4.57E-06 8.72E-07 --- 1.36E-06 --- 1.40E-05 Mn-56 --- 1.15E-07 2.04E-08 --- 1.46E-07 --- 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 --- --- 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 --- --- 2.85E-06 3.40E-05 Co-58 --- 7.45E-07 1.67E-06 --- --- --- 1.51E-05 Co-60 --- 2.14E-06 4.72E-06 --- --- --- 4.02E-05 Ni-59 9.76E-06 3.35E-06 1.63E-06 --- --- --- 6.90E-07 Ni-63 1.30E-04 9.01E-06 4.36E-06 --- --- --- 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 --- --- --- 1.74E-06 Cu-64 --- 8.33E-08 3.91E-08 --- 2.10E-07 --- 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 --- 1.03E-05 --- 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 --- 1.28E-08 --- 2.96E-09 Br-83 --- --- 4.02E-08 --- --- --- 5.79E-08 Br-84 --- --- 5.21E-08 --- --- --- 4.09E-13 Br-85 --- --- 2.14E-09 --- --- --- ---
Rb-86 --- 2.11E-05 9.83E-06 --- --- --- 4.16E-06 Rb-88 --- 6.05E-08 3.21E-08 --- --- --- 8.36E-19 Rb-89 --- 4.01E-08 2.82E-08 --- --- --- 2.33E-21 Sr-89 3.08E-04 --- 8.84E-06 --- --- --- 4.94E-05 Sr-90 8.71E-03 --- 1.75E-04 --- --- --- 2.19E-04 Sr-91 5.67E-06 --- 2.29E-07 --- --- --- 2.70E-05 Sr-92 2.15E-06 --- 9.30E-08 --- --- --- 4.26E-05 Y-90 9.62E-09 --- 2.58E-10 --- --- --- 1.02E-04 Y-91M 9.09E-11 --- 3.52E-12 --- --- --- 2.67E-10 Y-91 1.41E-07 --- 3.77E-09 --- --- --- 7.76E-05 Y-92 8.45E-10 --- 2.47E-11 --- --- --- 1.48E-05 Y-93 2.68E-09 --- 7.40E-11 --- --- --- 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 --- 1.53E-08 --- 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 --- 5.12E-10 --- 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 --- 3.42E-09 --- 2.10E-05 Mo-99 --- 4.31E-06 8.20E-07 --- 9.76E-06 --- 9.99E-06 Tc-99M 2.47E-10 6.98E-10 8.89E-09 --- 1.06E-08 3.42E-10 4.13E-07
CH-ODCM-0001 Reference Use Page 123 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.54E-10 3.66E-10 3.59E-09 --- 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 --- 7.97E-08 --- 7.06E-07 --- 2.16E-05 Ru-105 1.54E-08 --- 6.08E-09 --- 1.99E-07 --- 9.42E-06 Ru-106 2.75E-06 --- 3.48E-07 --- 5.31E-06 --- 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 --- 2.91E-07 --- 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 --- 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 --- 1.38E-06 1.97E-05 Te-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 --- 1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 --- 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 --- 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 --- 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 --- 2.37E-08 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 --- 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 --- 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 --- 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 --- 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 --- 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 --- 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 --- 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 --- 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 --- 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 --- 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 --- 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 --- 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 --- 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 --- 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 --- 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 --- 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 --- 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 --- --- --- 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 --- --- --- 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 --- 2.94E-09 --- 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 --- 5.37E-10 --- 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 --- 1.21E-07 --- 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 --- 2.13E-09 --- 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 --- 7.05E-12 --- 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 --- 4.25E-09 --- 3.49E-05
CH-ODCM-0001 Reference Use Page 124 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.03E-07 8.61E-08 3.01E-08 --- --- --- 2.82E-05 Pu-238 6.30E-04 7.98E-05 1.71E-05 --- 7.32E-05 --- 7.30E-05 Pu-239 7.25E-04 8.71E-05 1.91E-05 --- 8.11E-05 --- 6.66E-05 Pu-240 7.24E-04 8.70E-05 1.91E-05 --- 8.10E-05 --- 6.78E-05 Pu-241 1.57E-05 7.45E-07 3.32E-07 --- 1.53E-06 --- 1.40E-06 Np-239 1.19E-09 1.17E-10 6.45E-11 --- 3.65E-10 --- 2.40E-05 Am-241 7.55E-04 7.05E-04 5.41E-05 --- 4.07E-04 --- 7.42E-05 Cm-242 2.06E-05 2.19E-05 1.37E-06 --- 6.22E-06 --- 7.92E-05 Cm-243 5.99E-04 5.49E-04 3.75E-05 --- 1.75E-04 --- 7.81E-05 Cm-244 4.56E-04 4.27E-04 2.87E-05 --- 1.34E-04 --- 7.55E-05
CH-ODCM-0001 Reference Use Page 125 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 -- 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 --- --- --- 2.32E-05 Cr-51 --- --- 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 --- 5.90E-06 1.17E-06 --- 1.76E-06 --- 1.21E-05 Mn-56 --- 1.58E-07 2.81E-08 --- 2.00E-07 --- 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 --- --- 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 --- --- 4.32E-06 3.24E-05 Co-58 --- 9.72E-07 2.24E-06 --- --- --- 1.34E-05 Co-60 --- 2.81E-06 6.33E-06 --- --- --- 3.66E-05 Ni-59 1.32E-05 4.66E-06 2.24E-06 --- --- --- 7.31E-07 Ni-63 1.77E-04 1.25E-05 6.00E-06 --- --- --- 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 --- --- --- 5.19E-06 Cu-64 --- 1.15E-07 5.41E-08 --- 2.91E-07 --- 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 --- 1.28E-05 --- 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 --- 1.83E-08 --- 5.16E-08 Br-83 --- --- 5.74E-08 --- --- --- ---
Br-84 --- --- 7.22E-08 --- --- --- ---
Br-85 --- --- 3.05E-09 --- --- --- ---
Rb-86 --- 2.98E-05 1.40E-05 --- --- --- 4.41E-06 Rb-88 --- 8.52E-08 4.54E-08 --- --- --- 7.30E-15 Rb-89 --- 5.50E-08 3.89E-08 --- --- --- 8.43E-17 Sr-89 4.40E-04 --- 1.26E-05 --- --- --- 5.24E-05 Sr-90 1.02E-02 --- 2.04E-04 --- --- --- 2.33E-04 Sr-91 8.07E-06 --- 3.21E-07 --- --- --- 3.66E-05 Sr-92 3.05E-06 --- 1.30E-07 --- --- --- 7.77E-05 Y-90 1.37E-08 --- 3.69E-10 --- --- --- 1.13E-04 Y-91M 1.29E-10 --- 4.93E-12 --- --- --- 6.09E-09 Y-91 2.01E-07 --- 5.39E-09 --- --- --- 8.24E-05 Y-92 1.21E-09 --- 3.50E-11 --- --- --- 3.32E-05 Y-93 3.83E-09 --- 1.05E-10 --- --- --- 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 --- 1.91E-08 --- 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 --- 7.11E-10 --- 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 --- 4.42E-09 --- 1.95E-05 Mo-99 --- 6.03E-06 1.15E-06 --- 1.38E-05 --- 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 --- 1.38E-08 5.14E-10 6.08E-07
CH-ODCM-0001 Reference Use Page 126 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 3.60E-10 5.12E-10 5.03E-09 --- 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 --- 1.09E-07 --- 8.99E-07 --- 2.13E-05 Ru-105 2.18E-08 --- 8.46E-09 --- 2.75E-07 --- 1.76E-05 Ru-106 3.92E-06 --- 4.94E-07 --- 7.56E-06 --- 1.88E-04 Ag-110M 2.05E-07 1.94E-07 1.18E-07 --- 3.70E-07 --- 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 --- 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 --- 2.18E-06 1.93E-05 Te-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 --- --- 1.13E-05 Te-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 --- 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 --- 1.22E-05 Te-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 --- 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 --- 2.45E-07 Te-131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 --- 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 --- 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 --- 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 --- 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 --- 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 --- 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 --- 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 --- 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 --- 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 --- 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 --- 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 --- 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 --- 1.10E-07 1.28E-08 4.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 --- 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 --- 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 --- 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 --- 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 --- --- --- 9.28E-05 La-142 1.79E-10 7.95E-11 1.98E-11 --- --- --- 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 --- 4.18E-09 --- 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 --- 7.67E-10 --- 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 --- 1.72E-07 --- 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 --- 3.04E-09 --- 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 --- 1.01E-11 --- 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 --- 5.99E-09 --- 3.68E-05
CH-ODCM-0001 Reference Use Page 127 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.46E-07 1.19E-07 4.17E-08 --- --- --- 3.22E-05 Pu-238 6.70E-04 8.58E-05 1.82E-05 --- 7.80E-05 --- 7.73E-05 Pu-239 7.65E-04 9.29E-05 2.01E-05 --- 8.57E-05 --- 7.06E-05 Pu-240 7.64E-04 9.27E-05 2.01E-05 --- 8.56E-05 --- 7.19E-05 Pu-241 1.75E-05 8.40E-07 3.69E-07 --- 1.71E-06 --- 1.48E-06 Np-239 1.76E-09 1.66E-10 9.22E-11 --- 5.21E-10 --- 2.67E-05 Am-241 7.98E-04 7.53E-04 5.75E-05 --- 4.31E-04 --- 7.87E-05 Cm-242 2.94E-05 3.10E-05 1.95E-06 --- 8.89E-06 --- 8.40E-05 Cm-243 6.50E-04 6.03E-04 4.09E-05 --- 1.91E-04 --- 8.28E-05 Cm-244 5.04E-04 4.77E-04 3.19E-05 --- 1.49E-04 --- 8.00E-05
CH-ODCM-0001 Reference Use Page 128 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 --- --- --- 2.28E-05 Cr-51 --- --- 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 --- 1.07E-05 2.85E-06 --- 3.00E-06 --- 8.98E-06 Mn-56 --- 3.34E-07 7.54E-08 --- 4.04E-07 --- 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 --- --- 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 --- --- 7.74E-06 2.78E-05 Co-58 --- 1.80E-06 5.51E-06 --- --- --- 1.05E-05 Co-60 --- 5.29E-06 1.56E-05 --- --- --- 2.93E-05 Ni-59 4.02E-05 1.07E-05 6.82E-06 --- --- --- 7.10E-07 Ni-63 5.38E-04 2.88E-05 1.83E-05 --- --- --- 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 --- --- --- 2.56E-05 Cu-64 --- 2.45E-07 1.48E-07 --- 5.92E-07 --- 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 --- 2.30E-05 --- 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 --- 3.84E-08 --- 3.99E-06 Br-83 --- --- 1.71E-07 --- --- --- ---
Br-84 --- --- 1.98E-07 --- --- --- ---
Br-85 --- --- 9.12E-09 --- --- --- ---
Rb-86 --- 6.70E-05 4.12E-05 --- --- --- 4.31E-06 Rb-88 --- 1.90E-07 1.32E-07 --- --- --- 9.32E-09 Rb-89 --- 1.17E-07 1.04E-07 --- --- --- 1.02E-09 Sr-89 1.32E-03 --- 3.77E-05 --- --- --- 5.11E-05 Sr-90 2.56E-02 --- 5.15E-04 --- --- --- 2.29E-04 Sr-91 2.40E-05 --- 9.06E-07 --- --- --- 5.30E-05 Sr-92 9.03E-06 --- 3.62E-07 --- --- --- 1.71E-04 Y-90 4.11E-08 --- 1.10E-09 --- --- --- 1.17E-04 Y-91M 3.82E-10 --- 1.39E-11 --- --- --- 7.48E-07 Y-91 6.02E-07 --- 1.61E-08 --- --- --- 8.02E-05 Y-92 3.60E-09 --- 1.03E-10 --- --- --- 1.04E-04 Y-93 1.14E-08 --- 3.13E-10 --- --- --- 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 --- 3.65E-08 --- 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 --- 1.45E-09 --- 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 --- 8.23E-09 --- 1.62E-05 Mo-99 --- 1.33E-05 3.29E-06 --- 2.84E-05 --- 1.10E-05 Tc-99M 9.23E-10 1.81E-09 3.00E-08 --- 2.63E-08 9.19E-10 1.03E-06
CH-ODCM-0001 Reference Use Page 129 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 1.07E-09 1.12E-09 1.42E-08 --- 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 --- 2.81E-07 --- 1.84E-06 --- 1.89E-05 Ru-105 6.45E-08 --- 2.34E-08 --- 5.67E-07 --- 4.21E-05 Ru-106 1.17E-05 --- 1.46E-06 --- 1.58E-05 --- 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91E-07 --- 6.78E-07 --- 4.33E-05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 --- 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 --- 3.99E-06 1.71E-05 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 --- --- 1.10E-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 --- 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 --- 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 --- 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 --- 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 --- 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 --- 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 --- 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 --- 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 --- 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 --- 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 --- 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 --- 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 --- 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 --- 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 --- 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 --- 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 --- 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 --- 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 --- 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 --- 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 --- 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 --- --- --- 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 --- --- --- 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 --- 8.68E-09 --- 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 --- 1.59E-09 --- 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 --- 3.61E-07 --- 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 --- 6.39E-09 --- 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 --- 2.11E-11 --- 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 --- 1.24E-08 --- 3.58E-05
CH-ODCM-0001 Reference Use Page 130 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 4.29E-07 2.54E-07 1.14E-07 --- --- --- 3.57E-05 Pu-238 1.19E-03 1.38E-04 3.16E-05 --- 1.15E-04 --- 7.50E-05 Pu-239 1.29E-03 1.38E-04 3.31E-05 --- 1.22E-04 --- 6.85E-05 Pu-240 1.28E-03 1.43E-04 3.31E-05 --- 1.22E-04 --- 6.98E-05 Pu-241 3.87E-05 1.58E-06 8.04E-07 --- 2.96E-06 --- 1.44E-06 Np-239 5.25E-09 3.77E-10 2.65E-10 --- 1.09E-09 --- 2.79E-05 Am-241 1.36E-03 1.17E-03 1.02E-04 --- 6.23E-04 --- 7.64E-05 Cm-242 8.78E-05 7.01E-05 5.84E-06 --- 1.87E-05 --- 8.16E-05 Cm-243 1.28E-03 1.04E-03 8.24E-05 --- 3.08E-04 --- 8.03E-05 Cm-244 1.08E-03 8.74E-04 6.93E-05 --- 2.54E-04 --- 7.77E-05
CH-ODCM-0001 Reference Use Page 131 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 --- --- --- 2.30E-05 Cr-51 --- --- 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 --- 1.99E-05 4.51E-06 --- 4.41E-06 --- 7.31E-06 Mn-56 --- 8.18E-07 1.41E-07 --- 7.03E-07 --- 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 --- --- 4.36E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 --- --- 1.59E-05 2.57E-05 Co-58 --- 3.60E-06 8.98E-06 --- --- --- 8.97E-06 Co-60 --- 1.08E-05 2.55E-05 --- --- --- 2.57E-05 Ni-59 4.73E-05 1.45E-05 8.17E-06 --- --- --- 7.16E-07 Ni-63 6.34E-04 3.92E-05 2.20E-05 --- --- --- 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 --- --- --- 4.05E-05 Cu-64 --- 6.09E-07 2.82E-07 --- 1.03E-06 --- 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 --- 3.06E-05 --- 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 --- 6.98E-08 --- 1.37E-05 Br-83 --- --- 3.63E-07 --- --- --- ---
Br-84 --- --- 3.82E-07 --- --- --- ---
Br-85 --- --- 1.94E-08 --- --- --- ---
Rb-86 --- 1.70E-04 8.40E-05 --- --- --- 4.35E-06 Rb-88 --- 4.98E-07 2.73E-07 --- --- --- 4.85E-07 Rb-89 --- 2.86E-07 1.97E-07 --- --- --- 9.74E-08 Sr-89 2.51E-03 --- 7.20E-05 --- --- --- 5.16E-05 Sr-90 2.83E-02 --- 5.74E-04 --- --- --- 2.31E-04 Sr-91 5.00E-05 --- 1.81E-06 --- --- --- 5.92E-05 Sr-92 1.92E-05 --- 7.13E-07 --- --- --- 2.07E-04 Y-90 8.69E-08 --- 2.33E-09 --- --- --- 1.20E-04 Y-91M 8.10E-10 --- 2.76E-11 --- --- --- 2.70E-06 Y-91 1.13E-06 --- 3.01E-08 --- --- --- 8.10E-05 Y-92 7.65E-09 --- 2.15E-10 --- --- --- 1.46E-04 Y-93 2.43E-08 --- 6.62E-10 --- --- --- 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 --- 5.41E-08 --- 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 --- 2.56E-09 --- 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 --- 1.24E-08 --- 1.46E-05 Mo-99 --- 3.40E-05 6.63E-06 --- 5.08E-05 --- 1.12E-05 Tc-99M 1.92E-09 3.96E-09 5.10E-08 --- 4.26E-08 2.07E-09 1.15E-06
CH-ODCM-0001 Reference Use Page 132 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.27E-09 2.86E-09 2.83E-08 --- 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 --- 4.95E-07 --- 3.08E-06 --- 1.80E-05 Ru-105 1.36E-07 --- 4.58E-08 --- 1.00E-06 --- 5.41E-05 Ru-106 2.41E-05 --- 3.01E-06 --- 2.85E-05 --- 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81E-07 --- 1.04E-06 --- 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 --- 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 --- 7.12E-06 1.64E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 --- --- 1.11E-05 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 --- 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 --- 2.10E-05 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 --- 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 --- 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 --- 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 --- 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 --- 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 --- 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 --- 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 --- 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 --- 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 --- 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 --- 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 --- 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 --- 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 --- 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 --- 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 --- 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 --- 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 --- 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 --- 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 --- --- --- 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 --- --- --- 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 --- 1.48E-08 --- 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 --- 2.86E-09 --- 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 --- 4.93E-07 --- 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 --- 1.13E-08 --- 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 --- 3.84E-11 --- 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 --- 2.19E-08 --- 3.60E-05
CH-ODCM-0001 Reference Use Page 133 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 9.03E-07 6.28E-07 2.17E-07 --- --- --- 3.69E-05 Pu-238 1.28E-03 1.50E-04 3.40E-05 --- 1.21E-04 --- 7.57E-05 Pu-239 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 6.91E-05 Pu-240 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 7.04E-05 Pu-241 4.25E-05 1.76E-06 8.82E-07 --- 3.17E-06 --- 1.45E-06 Np-239 1.11E-08 9.93E-10 5.61E-10 --- 1.98E-09 --- 2.87E-05 Am-241 1.46E-03 1.27E-03 1.09E-04 --- 6.55E-04 --- 7.70E-05 Cm-242 1.37E-04 1.27E-04 9.10E-06 --- 2.62E-05 --- 8.23E-05 Cm-243 1.40E-03 1.15E-03 8.98E-05 --- 3.27E-04 --- 8.10E-05 Cm-244 1.18E-03 9.70E-04 7.59E-05 --- 2.71E-04 --- 7.84E-05
CH-ODCM-0001 Reference Use Page 134 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol fg Fraction of ingested produce grown in garden 0.76 of interest.
f Fraction of leafy vegetables grown in garden of 1.0 interest.
P Effective surface density of soil (assumes a 240 kg/m2 15 cm plow layer, expressed in dry weight) r Fraction of deposited activity retained on crops, 0.25 leafy vegetables, or pasture grass 1.0 (iodines) 0.2 (other particulates)
Sf Attenuation factor accounting for shielding 0.7 (maximum individual) provided by residential structures 0.5 (general population) tb Period of long-term buildup for activity in 1.752E5 hr sediment or soil (20 years) te Period of crop, leafy vegetable, or pasture 30 days (grass-cow-milk-man grass exposure during growing season pathway) 60 days (crop/vegetation-man pathway) tf Transport time from animal feed-milk-man 2 days (maximum individual) provided by residential structures 4 days (general population) th Time delay between harvest of vegetation or crops and ingestion:
For ingestion of forage by animals Zero (pasture grass) 90 days (stored feed)
For ingestion of crops by man 1 day (leafy vegetables and max. individual feed) 60 days (produce and max.
individual) 14 days (general population) fs The fraction of daily feed that is pasture grass 1.0 while the animals graze on pasture.
Mp The mixing ratio at the point of withdrawal of Site Discharge 7.14 drinking water. M.U.D. Intake 30.8 fp Fraction of the year that animals graze on 0.5 pasture.
CH-ODCM-0001 Reference Use Page 135 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol tp Environmental transit time, release to receptor 12 hrs. (maximum)
(add time from release to exposure individual 1 day (maximum individual) point to minimums shown for distribution) 1 day (general population) 7 days (population--sport fish doses) 10 days (population--
commercial fish doses) ts Average time from slaughter of meat animal to 20 days consumption Yv Agricultural productivity by unit area (measured 0.7 kg/m2 (grass-cow-milk-man in wet weight) pathway) 2.0 kg/m2 (produce or leafy vegetable ingested by man)
W Shore-width factor for river shoreline 0.2 w Rate constant for removal of activity on plant or 0.0021 hr-1 leaf structures by weathering (corresponds to a 14-day half-life)
%CO2 Fraction of C-14 used for organ dose 0.15 calculations from gaseous releases.
CH-ODCM-0001 Reference Use Page 136 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 29 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure NOTE i The Dose Estimates are based on normal public activities conducted within the Fort Calhoun Station Site Boundary.
i Estimated Individual Dose Estimated Total Combined Distance Rate (mR/hour) Annual Dose (mRem)B from Direct Inhalation Direct Inhalation Containment Exposure (Critical Exposure (Critical Location Direction (miles) (Total Body) OrganA) (Total Body) OrganA)
Firing Range 200° 0.24 4.08E-05 9.67E-06 5.08E+00 1.20E+00 Burn Pad 241° 0.33 1.95E-05 4.63E-06 1.41E-01 3.34E-02 On-Site Farming 118° 0.52 2.12E-05 5.03E-06 2.38E-02 5.64E-03 On-Site Farming 200° 0.51 1.03E-05 2.45E-06 2.30E-02 5.50E-03 On-Site Farming 308° 0.50 2.77E-05 6.64E-06 4.66E-02 1.12E-02 Site Maintenance Admin Bldg 145° 0.20 1.18E-04 2.84E-05 5.50E-02 1.33E-02 Site Maintenance Training Center 180° 0.20 1.45E-04 3.50E-05 6.78E-02 1.64E-02 A. Critical organ doses are based on adult thyroid.
B. Estimated totals are based on summation of all individual doses for members of the General Public while within the Fort Calhoun Station site boundary.
Page 1 of 136 CH-ODCM-0001 Off-Site Dose Calculation Manual (ODCM)
Revision 30 Safety Classification: Usage Level:
Non-Safety Reference Change No.: EC 70009 Reason for Change: Revise site boundary.
Preparer: J. Hoffman Fort Calhoun Station
CH-ODCM-0001 Reference Use Page 2 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table of Contents PART I 1.0 PURPOSE AND SCOPE ................................................................................................. 6 1.1 Purpose ..................................................................................................................... 6 1.2 Scope ........................................................................................................................ 6 2.0 DEFINITIONS .................................................................................................................. 6 3.0 INSTRUMENTATION .................................................................................................... 10 3.1 Radioactive Liquid Effluent Instrumentation ............................................................ 10 3.2 Radioactive Gaseous Effluent Instrumentation ....................................................... 13 4.0 RADIOACTIVE EFFLUENTS ........................................................................................ 17 4.1 Radioactive Liquid Effluents .................................................................................... 17 4.2 Radioactive Gaseous Effluents ............................................................................... 23 4.3 Uranium Fuel Cycle ................................................................................................. 29 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) .................. 30 5.1 Monitoring Program ................................................................................................. 30 5.2 Land Use Survey ..................................................................................................... 45 5.3 Interlaboratory Comparison Program ...................................................................... 46 6.0 ADMINISTRATIVE CONTROLS.................................................................................... 47 6.1 Responsibilities ....................................................................................................... 47 6.2 Radioactive Effluent Reporting Requirements......................................................... 47 6.3 Change Mechanism ................................................................................................ 52 6.4 Meteorological Data ................................................................................................ 52 6.5 References .............................................................................................................. 53 7.0 BASIS ............................................................................................................................ 55 7.1 Instrumentation ....................................................................................................... 55 7.2 Radioactive Effluents............................................................................................... 55 7.3 Radiological Environmental Monitoring ................................................................... 62 7.4 Abnormal Release or Abnormal Discharge Reporting ............................................. 63
CH-ODCM-0001 Reference Use Page 3 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 List of Tables PART I Table 1.2 - Frequency Notation ............................................................................................... 8 Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation .. 9 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation .................................... 11 Table 3.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ....................................................................................................... 12 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation ............................... 14 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .................................................................................. 16 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis ............................................. 19 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis ......................................... 24 Table 4.3 - Sampler Deposition/Transportation Correction Factors ....................................... 25 Table 5.1 - Radiological Environmental Monitoring Program ................................................. 32 Table 5.2 - Radiological Environmental Sampling Locations And Media ............................... 35 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ................................................................................................... 43 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples ...................................................................................... 44 List of Figures PART I Figure 1 - Environmental Radiological Sampling Points ....................................................... 41 Figure 2 - 40CFR190 Sampling Points ................................................................................. 42
CH-ODCM-0001 Reference Use Page 4 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table of Contents PART II 1.0 EFFLUENT MONITOR SETPOINTS ............................................................................. 66 1.1 Liquid Effluents ........................................................................................................ 66 1.2 Airborne Effluents .................................................................................................... 69 2.0 EFFLUENT CONCENTRATIONS ................................................................................. 80 2.1 Liquid Effluent Concentrations ................................................................................ 80 2.2 Airborne Effluent Concentrations ............................................................................ 80 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS ................................................... 82 3.1 Liquid Effluent Dose Calculations ............................................................................ 82 3.2 Airborne Effluent Dose Calculations ........................................................................ 86 4.0 LOWER LIMIT OF DETECTION (LLD) ....................................................................... 101
CH-ODCM-0001 Reference Use Page 5 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 List of Tables PART II Table 1 - Allocation Factors for Simultaneous Releases ....................................................... 74 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases ................... 102 Table 3 - Bioaccumulation Factors ...................................................................................... 103 Table 4 - Highest Potential Exposure Pathways for Estimating Dose.................................. 104 Table 5 - Stable Element Transfer Data .............................................................................. 105 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data................................................................. 106 Table 7 - Animal Consumption Rates .................................................................................. 106 Table 8 - External Dose Factors for Standing on Contaminated Ground ............................. 107 Table 9 - Inhalation Dose Factors for Adult ......................................................................... 110 Table 10 - Inhalation Dose Factors for Teenager ................................................................ 113 Table 11 - Inhalation Dose Factors for Child ....................................................................... 116 Table 12 - Inhalation Dose Factors for Infant ...................................................................... 119 Table 13 - Ingestion Dose Factors for Adult ........................................................................ 122 Table 14 - Ingestion Dose Factors for Teenager ................................................................. 125 Table 15 - Ingestion Dose Factors for Child ........................................................................ 128 Table 16 - Ingestion Dose Factors for Infant ....................................................................... 131 Table 17 - Recommended Values for Other Parameters ..................................................... 134 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure ........ 136 List of Figures PART II Figure 1 - Exclusion and Site Boundary Map ........................................................................ 75 Figure 2 - Liquid Radioactive Discharge Pathways ............................................................... 76 Figure 3 - Liquid Radioactive Waste Disposal System .......................................................... 77 Figure 4 - Airborne Effluent Discharge Pathways .................................................................. 78 Figure 5 - Airborne Radioactive Waste Disposal System ...................................................... 79
CH-ODCM-0001 Reference Use Page 6 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 Contains methodologies for and parameters necessary for calculating offsite doses, determination of gaseous and liquid radiation monitor set points, and administrative controls for effluent instrumentation, Radiological Effluent Tech Specs (RETS), and the Radiological Environmental Monitoring Program (REMP).
1.2 Scope 1.2.1 Radioactive effluents are generated from station activities. These controls provide methodologies ensuring these effluents are properly monitored and quantified to promote accurate dose reporting. Additional controls ensure station equipment and processes are used to minimize release to the environment. The combination of minimizing release, accurately reporting dose, and monitoring the facility environs provides the basis for ensuring that station activities are not negatively impacting public health and the environment.
2.0 DEFINITIONS 2.1 Abnormal Discharge - The unplanned or uncontrolled emission of an effluent (i.e.,
containing facility-related, licensed radioactive material) into the unrestricted area.
2.2 Abnormal Release - The unplanned or uncontrolled emission of an effluent (i.e.,
containing facility-related, licensed radioactive material).
2.3 Channel Check - A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
2.4 Channel Function Test - Injection of a simulated signal into the channel to verify that it is functional, including any alarm and/or trip initiating action.
2.5 Effluent Concentration Limit (ECL) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 1.
2.6 Member(s) of the Public - Member(s) of the Public means any individual except when that individual is receiving occupational dose.
CH-ODCM-0001 Reference Use Page 7 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 2.7 Functional-Functionality - A system, subsystem, train, component or device shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power sources, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
2.8 Residual Radioactivity - Residual radioactivity means radioactivity in structures, materials, soils, ground water, and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee, but it excludes background radiation. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site, even if those burials were made in accordance with the provisions of 10 CFR Part 20.
2.9 Site Boundary - The Site Boundary is the line beyond which the land is neither owned, or leased, nor controlled by the licensee.
2.10 Source Check - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
2.11 Special Liquid - Non-routine release pathway in which normally non-radioactive liquid streams (such as Raw Water) found to contain radioactive material, are non-routine, and will be treated on a case specific basis if and when this occurs.
2.12 Unrestricted Area - An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
2.13 Venting - VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
2.14 Water Effluent Concentration (WEC) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.
CH-ODCM-0001 Reference Use Page 8 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 1.2 - Frequency Notation The surveillance intervals are defined as follows:
Notation Title FrequencyA S Shift At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W Weekly At least once per 7 days BW Biweekly At least once per 14 days M Monthly At least once per 31 days Q Quarterly At least once per 92 days SA Semiannual At least once per 184 days A Annually At least once per 366 days R At least once per 18 months P Prior to Prior to each release (Performance within 24 hrs.)
A. Each surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
CH-ODCM-0001 Reference Use Page 9 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation Technical Specification ODCM Implementing Step 5.16.1.a 3.1.1, 3.2.1 5.16.1.b 4.1.1 5.16.1.c Table 4.1, Table 4.2 5.16.1.d 4.1.2 5.16.1.e 4.1.2B.1, 4.2.2B.1 5.16.1.f 4.1.3A, 4.2.4A 5.16.1.g 4.2.1 5.16.1.h 4.2.2 5.16.1.i 4.2.3 5.16.1.j 4.3.1 5.16.2.a 5.1.1 5.16.2.b 5.2.1 5.16.2.c 5.3.1 5.17 6.3, 6.2.1D
CH-ODCM-0001 Reference Use Page 10 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.0 INSTRUMENTATION 3.1 Radioactive Liquid Effluent Instrumentation 3.1.1 Limiting Condition for Operation A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.1.1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 3.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Part II of the Off-Site Dose Calculation Manual.
APPLICABILITY: At all times ACTION:
- 1. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive liquid effluents monitored by the affected channel or declare the channel non-functional.
- 2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels functional, take the action shown in Table 3.1.1. Restore non-functional effluent monitoring instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this non-functionality was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent stream: RM-055.
3.1.2 Surveillance Requirements A. Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.1.2.
CH-ODCM-0001 Reference Use Page 11 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrument Functional Action
- 1. Radioactivity Monitor Providing Alarm and Automatic Termination of Release.
1.1 Liquid Radwaste Effluent Line (RM-055) 1 1, 4
- 2. Flow Rate Measurement Device 2.1 Liquid Radwaste Effluent Line 1 2
- 3. Radioactivity Recorder 3.1 Liquid Radwaste Effluent Line 1 3 Table Notation ACTION 1 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided that prior to initiating a release:
- 1. At least two independent samples are analyzed in accordance with applicable chemistry procedures.
- 2. At least two qualified individuals independently verify the release rate calculations.
ACTION 2 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the flow rate is determined at least once per four hours during the actual release.
ACTION 3 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the radioactivity is recorded manually at least once per four hours during the actual release.
ACTION 4 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered non-functional. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. If the effluent radiation monitor fails the source check, carryout the action(s) of the Off-Site Dose Calculation Manual for the non-functional monitor or terminate the effluent release.
CH-ODCM-0001 Reference Use Page 12 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 3.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Function Check Calibration Check Test
- 1. Radioactivity Monitor Providing Alarm and Automatic Isolation 1.1 RM-055 ---- R Q P
CH-ODCM-0001 Reference Use Page 13 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2 Radioactive Gaseous Effluent Instrumentation 3.2.1 Limiting Condition for Operation A. The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.2.1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 3.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Part II of the Off-Site Dose Calculation Manual.
APPLICABILITY: At all times ACTION:
- 1. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive gaseous effluents monitored by the affected channel or declare the channel non-functional.
- 2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels functional, take the action shown in Table 3.2.1. Restore non-functional effluent monitoring instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this non-functionality was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent streams: RM-043, RM-062, and RM-052.
3.2.2 Surveillance Requirements A. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.2.2.
CH-ODCM-0001 Reference Use Page 14 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Channels Action Functional
- 1. Auxiliary Bldg. Exhaust Stack (RM-052, RM-062) 1.1 Noble Gas 1 1, 7, 8 1.2 Particulate 1 2, 7, 8
- 2. Laboratory and Radwaste Processing Building Stack (RM-043) 2.1 Noble Gas 1 3, 7 2.2 Particulate 1 4, 7
- 3. Flow Rate Measurement Devices 3.1 Auxiliary Building Exhaust Stack 1 5 3.2 Laboratory and Radwaste Processing Building Stack 1 5
- 4. Radioactivity Chart Recorders 4.1 Auxiliary Building Exhaust Stack 1 6
CH-ODCM-0001 Reference Use Page 15 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 3.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation Table Notation ACTION 1 If the Auxiliary Building Exhaust Stack Noble Gas Monitor is non-functional, ventilation of the auxiliary building via the Auxiliary Building Exhaust Stack may continue provided grab samples are taken once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (See Table 4.2)
ACTION 2 If the Auxiliary Building Exhaust Stack Particulate Sampler is non-functional, ventilation of the Auxiliary Building may continue through the Auxiliary Building Exhaust Stack provided sample collection in accordance with Table 4.2 using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the declaration of non-functionality by the Shift Manager.
ACTION 3 If the Noble Gas Monitor is non-functional, ventilation of the LRWPB may continue via the LRWPB stack provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (See Table 4.2)
ACTION 4 If the Particulate Sampler is non-functional, ventilation of the LRWPB may continue via the LRWPB Stack provided sample collection using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the declaration of non-functionality, by the Shift Manager, in accordance with Table 4.2.
ACTION 5 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the flowrate is estimated or recorded manually at least once per four hours during the actual release.
ACTION 6 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the radioactivity level is recorded manually at least once per four hours during the actual release.
ACTION 7 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered non-functional. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. If the effluent radiation monitor fails the source check, carryout the Action(s) of the Off-Site Dose Calculation Manual for the non-functional monitor or terminate the effluent release.
ACTION 8 During the ventilation of airborne effluents from the Auxiliary Building Exhaust Stack at least one Auxiliary Building Exhaust fan shall be in operation.
CH-ODCM-0001 Reference Use Page 16 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Calibration Function Check Check Test
- 1. Radioactivity Monitors Providing Alarm and Automatic Isolation 1.1 RM-043 D R Q M 1.2 RM-062 D R Q M 1.3 RM-052 D R Q M
- 2. Flowrate Monitors 2.1 RM-043 Sampler D R Q ----
2.2 RM-062 Sampler D R Q ----
2.3 RM-052 Sampler D R Q ----
2.4 Auxiliary Bldg Exhaust Stack D R Q ----
2.5 Laboratory and Radwaste Process Bldg Exhaust Stack D R Q ----
Operations Check Air Flow Calibration
- 3. Environmental Monitors 3.1 RM-023 - Sample Station #40 M A 3.2 RM-024 - Sample Station #41 M A 3.3 RM-025 - Sample Station #28 ---- ----
3.4 RM-026 - Sample Station #36 ---- ----
3.5 RM-027 - Sample Station #37 M A 3.6 RM-028 - Sample Station #38 ---- ----
3.7 RM-029 - Sample Station #39 ---- ----
3.8 RM-035 - Sample Station #1 ---- ----
3.9 RM-036 - Sample Station #2 M A 3.10 RM-037 - Sample Station #3 ---- ----
3.11 RM-038 - Sample Station #4 M A 3.12 RM-039 - Sample Station #5 ---- ----
3.13 RM-040 - Sample Station #32 M A
CH-ODCM-0001 Reference Use Page 17 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.0 RADIOACTIVE EFFLUENTS 4.1 Radioactive Liquid Effluents 4.1.1 Concentration A. Limiting Condition for Operation
- 1. The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides, other than dissolved or entrained noble gases, do not exceed the values specified in 10 CFR Part 20 for liquid effluents at site discharge. To support facility operations, RP/Chemistry supervision may increase this limit up to the limit specified in Technical Specifications 5.16.1.b. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/ml, total activity.
- 2. Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/ml total activity.
APPLICABILITY: At all times ACTION:
- a. When the concentration of radioactive material released at site discharge exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.
CH-ODCM-0001 Reference Use Page 18 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 B. Surveillance Requirements NOTE i Radioactive liquid waste includes water used for fire suppression in areas of the facility that may contain radioactivity. These liquids are required to be i monitored prior to release in accordance with SO-G-28.
- 1. Radioactive liquid waste shall be sampled and analyzed according to the sampling and analysis program in Table 4.1.
- 2. The results of the radioactivity analysis shall be used with the calculational methods in Part II of the Off-Site Dose Calculation Manual.
- 3. To assure that the concentration at the point of release is maintained within the limits of Technical Specification 5.16.1.b.
- 4. Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred. Analytical results shall be submitted to the Commission in accordance with Part I, Section 6.0 of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 19 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis A. Monitor, Hotel Waste Tanks & Special Liquid, Releases Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Each Batch Principal Gamma Emitters B 5.0E-07 Dissolved Noble Gases Each Batch (Gamma Emitters) B 1.0E-05 Monthly Composite C H-3 1.0E-05 Monthly Composite C Gross Alpha 1.0E-07 Quarterly Composite C Sr-89, Sr-90 5.0E-08 Quarterly Composite C Fe-55 1.0E-06 NOTES:
A. LLD is defined in Part II of the Off-Site Dose Calculation Manual.
B. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved or entrained gases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141 for fission and corrosion products. Ce-144 shall also be measured, but with a LLD of 5.0E-06.
C. To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples should be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite should be mixed in order for the composite sample to be representative of the average effluent release.
CH-ODCM-0001 Reference Use Page 20 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.1.2 Dose from Radioactive Liquid Effluents A. Limiting Condition for Operation
- 1. The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 1.5 mrem to the total body and 5 mrem to any organ; and
- b. During any calendar year: Less than or equal to 3 mrem to the total body and 10 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of radioactive materials in liquid effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual at least once per quarter.
CH-ODCM-0001 Reference Use Page 21 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.1.3 Liquid Radwaste Treatment A. Limiting Condition for Operation
- 1. The Liquid Radwaste Treatment System shall be FUNCTIONAL, and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.
APPLICABILITY: At all times ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to 10 CFR 50, Appendix I, a Special Report that includes the following information:
- 1) Explanation of why liquid radwaste was being discharged without treatment, identification of equipment or subsystem(s) not functional and reasons for non-functionality.
- 2) Action(s) taken to restore the non-functional equipment to functional status.
- 3) Summary description of action(s) taken to prevent a recurrence.
B. Surveillance Requirements
- 1. Dose due to liquid releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual, when Liquid Radwaste Treatment Systems are not fully FUNCTIONAL.
- 2. FUNCTIONAL is defined as follows:
- a. A filtration/ion exchange (FIX) system will be utilized for processing liquid radwaste. The system consists of a booster pump, charcoal pretreatment filter, and pressure vessels containing organic/inorganic resins, which can be configured for optimum performance. The effluent from the FIX system is directed to the monitor tanks for release.
CH-ODCM-0001 Reference Use Page 22 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.1.3B.2 (continued)
- b. Waste filters (WD-17A and WD-17B) are used only on those occasions when considered necessary, otherwise the flows from the low activity fluids may bypass the filters. No credit for decontamination factors (iodines, Cs, Rb, others) was taken for these filters during the 10 CFR Part 50 Appendix I dose design objective evaluation; therefore, the non-functionality of these filters does not affect the dose contributions to any individual in the unrestricted areas via liquid pathways. The non-functionality of waste filters will not be considered a reportable event in accordance with the Action listed above.
4.1.4 Liquid Holdup Tanks Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
A. Limiting Condition for Operation
- 1. The quantity of radioactive material contained in each unprotected outdoor liquid holdup tank shall not exceed 10 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times ACTION:
- a. When the quantity of radioactive material in any unprotected outdoor liquid holdup tank exceeds 10 curies, excluding tritium and dissolved or entrained noble gasses, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
B. Surveillance Requirements
- 1. The quantity of radioactive material contained in each outdoor liquid holdup tank shall be determined to be within the above limit by analyzing a representative sample of the tanks contents at least once per 7 days when radioactive material is being added to the tank.
CH-ODCM-0001 Reference Use Page 23 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.2 Radioactive Gaseous Effluents 4.2.1 Concentration A. Limiting Condition for Operation
- 1. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations of radionuclides does not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To support facility operations, RP/Chemistry supervision may increase this limit up to the limits specified in Technical Specification 5.16.1.g.
- 2. Technical Specification 5.16.1.g establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.
APPLICABILITY: At all times ACTION:
- a. When the concentration of radioactive material released to unrestricted areas exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.
B. Surveillance Requirements NOTE Radioactive gaseous wastes include atmospheres in areas where gaseous i fire suppression systems are utilized or where smoke is produced as a result of fire in areas of the facility that may contain radioactivity. These i atmospheres are required to be monitored prior to gaseous release to unrestricted areas in accordance with SO-G-28.
- 1. Radioactive gaseous wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.2. The results of the radioactivity analysis shall be used to assure the limits in Step 4.2.1A are not exceeded.
CH-ODCM-0001 Reference Use Page 24 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis A. Auxiliary Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly (Noble Gases) Principal Gamma Emitters B 1.0E-4 Weekly Tritium (H-3) 1.0E-06 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Samples) Sr-89, Sr-90 1.0E-11 B. Laboratory and Radwaste Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly (Noble Gases) Principal Gamma Emitters B 1.0E-4 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-89, Sr-90 1.0E-11 NOTES:
A. LLD is defined in Part II of the Off-Site Dose Calculation Manual.
B. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate releases.
C. Frequency requirement may be satisfied using weekly gross alpha results from particulate sampling media.
D. Particulate samples shall be corrected for sampler deposition/transportation efficiency by using the approved software programs or by multiplying the activity obtained by the associated sampler multiplication factor (See Table 4.3).
CH-ODCM-0001 Reference Use Page 25 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 4.3 - Sampler Deposition/Transportation Correction Factors Particulate Sampler Sample DF ACTMULT RM-062 AB 0.411 2.433 RM-052 AB 0.638 1.567 RM-043 LRWPB 0.809 1.236 ACRONYM DEFINITIONS:
AB - Auxiliary Building Exhaust Stack LRWPB - Laboratory and Rad Waste Processing Building DF - Deposition Factor ACTMULT - Activity multiplication factor to correct for sample loss.
CH-ODCM-0001 Reference Use Page 26 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.2.2 Dose - Noble Gases A. Limiting Condition for Operation
- 1. The dose or dose commitment to an individual at the site boundary from release of noble gases in airborne effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of noble gases in airborne effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from radioactive noble gases in airborne effluents shall be determined, in accordance with the methodologies and parameters of Part II of the Off-Site Dose Calculation Manual, on a quarterly basis.
4.2.3 Dose - H-3, C-14, and Radioactive Material in Particulate Form with Half-Lives Greater than 8 Days (Other than Noble Gases)
A. Limiting Condition for Operation
- 1. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of H-3, C-14, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ; and
CH-ODCM-0001 Reference Use Page 27 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.2.3A.1 (continued)
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of H-3, C-14, and radioactive materials in particulate form with half-lives greater than eight days, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from H-3, C-14 and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be determined, in accordance with the methodologies and parameters of Part II of the Off-Site Dose Calculation Manual, on a quarterly basis.
4.2.4 Gaseous Radwaste Treatment A. Limiting Condition for Operation
- 1. In accordance with Technical Specification 5.16.1.f, the Ventilation Exhaust Systems shall be FUNCTIONAL, and appropriate portions of these systems shall be used to reduce the releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed:
- a. 0.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC
CH-ODCM-0001 Reference Use Page 28 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.2.4A.1 (continued)
APPLICABILITY: At all times ACTION:
- a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit a report to the Nuclear Regulatory Commission within 30 days, pursuant to 10 CFR 50, Appendix I, a special report that includes the following information:
- 1) Identification of equipment or subsystem(s) not functional and reasons for non-functionality.
- 2) Action(s) taken to restore the non-functional equipment to functional status.
- 3) Summary description of action(s) taken to prevent a recurrence.
B. Surveillance Requirements
- 1. Dose due to gaseous releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual, when Ventilation Exhaust Systems are not fully FUNCTIONAL.
- 2. FUNCTIONAL is defined as follows:
- a. Ventilation Exhaust Systems
- 1) The radioactive effluents from the controlled access area of the auxiliary building are filtered by the HEPA filters in the auxiliary building ventilation system. If the radioactive effluents are discharged without the HEPA filters and it is confirmed that one half of the annual dose objective will be exceeded during the calendar quarter, a special report shall be submitted to the Commission pursuant to Section 4.2.4A.
CH-ODCM-0001 Reference Use Page 29 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.3 Uranium Fuel Cycle 4.3.1 Total Dose-Uranium Fuel Cycle A. Limiting Condition for Operation
- 1. The dose to any real individual from uranium fuel cycle sources shall be limited to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to 75 mrem) during each calendar year.
APPLICABILITY: At all times ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specifications 4.1.2A, 4.2.2A, or 4.2.3A, calculations shall be made including direct radiation contribution from the facility and outside storage tanks to determine whether the above limits have been exceeded. If such is the case, in lieu of any other report required by Section 6.2, prepare and submit a Special Report to the Commission pursuant to Technical Specification 5.16 that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report , as defined in 10 CFR Part 20.2203(a)(4) and 20.2203(b), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 or 10 CFR Part 72.104 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 or 10 CFR Part 72.104.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
CH-ODCM-0001 Reference Use Page 30 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.3.1 (continued)
B. Surveillance Requirements
- 1. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance requirements 4.1.2B, 4.2.2B and 4.2.3B and in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual.
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 5.1 Monitoring Program 5.1.1 Limiting Condition for Operation A. The Radiological Environmental Monitoring Program shall be conducted as specified in Table 5.1.
APPLICABILITY: At all times ACTION:
- 1. Analytical results of this program and deviations from the sampling schedule shall be reported to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 6.2).
- 2. If the level of radioactivity from calculated doses leads to a higher exposure pathway to individuals, this pathway shall be added to the Radiological Environmental Monitoring Program. Modifications to the program shall be reported in the Annual Radiological Environmental Operating Report to the Nuclear Regulatory Commission.
- 3. If the level of radioactivity in an environmental sampling medium exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.3). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 5.3 for Lower Level of Detection (LLD).
CH-ODCM-0001 Reference Use Page 31 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 5.1.1A (continued)
- 4. If the level of radioactivity in a sample from either an onsite or offsite well, performed per the Site Groundwater Protection Program, exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.3). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 5.3 for Lower Level of Detection (LLD). Copies of the Special Report will be forwarded to State/Local authorities.
[AR 39127]
- 5. If the level of radioactivity from either an onsite or offsite well, performed per the Site Groundwater Protection Program exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operations, state and local authorities shall be notified by the end of the next business day. NRC shall be notified per LS-FC-1020, Reportability Tables and Decision Tree. [AR 39127]
- 6. Radiological environmental sampling locations and the media that is utilized for analysis are presented in Table 5.2. Sampling locations are also illustrated on the map, Figure 1. Details of the quarterly emergency TLD locations are contained in surveillance test CH-ST-RV-0003, Environmental Sample Collection -
Quarterly/Environmental Dosimeters (TLDs). Each TLD sample location contains one dosimeter that is exchanged quarterly for REMP sampling and as needed for Emergency Planning Zone monitoring.
- 7. Deviations from the monitoring program, presented in this section and detailed in Table 5.2, are permitted if specimens are unobtainable due to mitigating circumstances such as hazardous conditions, seasonal unavailability, malfunction of equipment, or if a person discontinues participation in the program, etc. If the equipment malfunctions, corrective actions will be completed as soon as practicable. If a person no longer supplies samples, a replacement will be made if possible. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report, pursuant to Section 6.2.
5.1.2 Surveillance Requirements A. The Radiological Environmental Monitoring Program (REMP) samples shall be collected and analyzed in accordance with Tables 5.1, 5.2, and 5.3.
CH-ODCM-0001 Reference Use Page 32 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 1. Direct Radiation A. 14 TLD indicator stations, one Gamma dose Quarterly background stationF, total of 15.
B. An inner-ring of 16 stations, one in each cardinal sector in the Gamma dose Quarterly general area of the unrestricted area boundary and within 2.5 miles.
C. An outer-ring of 16 stations, one in each cardinal sector located Gamma dose Quarterly outside of the inner-ring, but no more distant than approximately 5 miles.
D. Other TLDs may be placed at Gamma dose Quarterly special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Omaha Public Power District employees have routine access.
- 2. Air Monitoring A. Indicator Stations Filter for Gross Beta C Weekly
- 1. Three stations in the general Filter for Gamma Isotopic Quarterly area of the unrestricted area composite boundary of weekly filters
- 2. City of Blair
- 3. Desoto Township B. One background station F
- 3. Water A. Missouri River at nearest Gamma Isotopic, H-3 Monthly for downstream drinking water Gamma intake. isotopic analysis.
B. Missouri River downstream near the mixing zone. Quarterly composite for C. Missouri River upstream of H-3 Analysis Facility intake (background)F.
- 4. Milk D A. Nearest milk animal (cow or Gamma Isotopic Monthly goat) within 5 miles B. Milk animal (cow or goat) between 5 miles and 18.75 miles (background)F.
- 5. Fish A. Four fish samples within vicinity Gamma Isotopic Once per of Facility discharge. season (May to B. One background sample October) upstream of Facility discharge.
CH-ODCM-0001 Reference Use Page 33 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 6. Vegetables or A. One sample in the highest Gamma Isotopic Once per Food Products E exposure pathway. season (May to B. One sample from onsite crop October) field C. One sample outside of 5 miles (background)F.
- 7. Groundwater A. Three samples from sources H3, Gross Beta, Gamma Quarterly potentially affected by facility Isotopic, Sr-90 operations.
B. One sample outside of 5 miles (background)F.
- 8. Vegetation in lieu A. One sample at the highest Gamma Isotopic Monthly (when of milk annual average D/Q offsite available) location.
B. One sample at the second highest annual average D/Q offsite location.
C. One sample outside of 5 miles (background) F.
CH-ODCM-0001 Reference Use Page 34 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 NOTES:
A. See Table 5.3 for required detection limits.
B. The Lower Limit of Detection (LLD) for analysis is defined in the Off-Site Dose Calculation Manual in accordance with the wording of NUREG-1301.
C. When a gross beta count indicates radioactivity greater than 2.5E-13 Ci/ml or 0.25 pCi/m3, (ten times the yearly mean), a gamma spectral analysis will be performed.
D. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II, Table 4 "Highest Potential Exposure Pathways for Estimating Dose")
E. Samples should be collected from garden plots of 500 ft2 or more. (Reference Reg. Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants," Dec. 1975).
F. This sample may not be located in the least prevalent wind direction. The Branch Technical Position paper, Table 1, subnote "d" says this regarding background information, or control locations. "The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted".
CH-ODCM-0001 Reference Use Page 35 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate Onsite Station, 110-meter weather 1 tower 0.53 293°/WNW P X Onsite Station, adjacent 2C,E to old plant access road 0.59 207°/SSW K X X Offsite Station, Intersection of Hwy. 75 3 and farm access road 0.94 145°/SE G X 4 Blair OPPD office 2.86 305°/NW Q X X 5A Fort Calhoun, NE City 6 Hall 5.18 150°/SSE H X Fence around intake gate, Desoto Wildlife 7 Refuge 2.07 102°/ESE F X Onsite Station, entrance to Plant Site 8 from Hwy. 75 0.55 191°/S J X Onsite Station, NW of 9 Plant 0.68 305°/NW Q X Onsite Station, WSW of 10 Plant 0.61 242°/WSW M X Offsite Station, SE of 11 Plant 1.07 39°/SE G X
CH-ODCM-0001 Reference Use Page 36 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate Metropolitan Utilities Dist., Florence Treatment Plant 12 North Omaha, NE 14.3 154°/SSE H X West bank Missouri River, downstream from 13 Plant discharge 0.45 108°/ESE F X X Upstream from Intake 14D Bldg, west bank of river 0.09 4°/N A X X 15 Smith Farm 1.99 134°/SE G X 16A 17A 18A 19A 20D Mohr Dairy 9.86 186°/S J B,F X X A
21 Fish Sampling Area, 0.08 22 Missouri River (R.M. 645.0) 6°/N A X Fish Sampling Area, 17.9 23D Missouri River (R.M. 666.0) 358°/N A X 24A 25A 26A 27A
CH-ODCM-0001 Reference Use Page 37 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 28A 29A 30A 31A 32D Valley Substation #902 19.6 221°/SW L X X A
33 34A 35 Onsite Farm Field 0.52 118°/ESE F X Offsite Station Intersection Hwy 75/Co.
36 Rd. P37 0.75 227°/SW L X Offsite Station Desoto 37 Township 1.57 144°/SE G X X A
38 39A 40A 41C Dowler Acreage 0.73 175°/S J X X B,C 42 Sector A-1 1.94 0°/NORTH A X 43 Sector B-1 1.97 16°/NNE B X 44 Sector C-1 1.56 41°/NE C X 45 Sector D-1 1.34 71°/ENE D X 46 Sector E-1 1.54 90°/EAST E X 47 Sector F-1 0.45 108°/ESE F X
CH-ODCM-0001 Reference Use Page 38 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 48 Sector G-1 1.99 134°/SE G X 49 Sector H-1 1.04 159°/SSE H X 50 Sector J-1 0.71 179°/SOUTH J X 51 Sector K-1 0.61 205°/SSW K X 52 Sector L-1 0.74 229°/SW L X 53 Sector M-1 0.93 248°/WSW M X 54 Sector N-1 1.31 266°/WEST N X 55 Sector P-1 0.60 291°/WNW P X 56 Sector Q-1 0.67 307°/NW Q X 57 Sector R-1 2.32 328°/NNW R X 58 Sector A-2 4.54 350°/NORTH A X 59 Sector B-2 2.95 26°/NNE B X 60 Sector C-2 3.32 50°/NE C X 61 Sector D-2 3.11 75°/ENE D X 62 Sector E-2 2.51 90°/EAST E X 63 Sector F-2 2.91 110°/ESE F X 64 Sector G-2 3.00 140°/SE G X 65 Sector H-2 2.58 154°/SSE H X 66 Sector J-2 3.53 181°/SOUTH J X 67 Sector K-2 2.52 205°/SSW K X 68 Sector L-2 2.77 214°/SW L X 69 Sector M-2 2.86 243°/WSW M X
CH-ODCM-0001 Reference Use Page 39 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 70 Sector N-2 2.54 263°/WEST N X 71 Sector P-2 2.99 299°/WNW P X 72 Sector Q-2 3.37 311°/NW Q X 73 Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X C B, C 75 Lomp Acreage 0.65 163°/SSE H X X X X 76 Stangl Farm 3.40 169°/S J X 77G River N-1 0.17 328°/NNW R X G
78 River S-1 0.14 85°/EAST E X G
79 Lagoon S-1 0.24 131°/SE G X G
80 Parking S-1 0.27 158°/SSE H X G
81 Training W-1 0.28 194°/SSW K X 82G Switchyard S-1 0.21 219°/SW L X 83G Switchyard SE-1 0.14 231°/SW L X G
84 Switchyard NE-1 0.18 256°/WSW M X G
85 Switchyard W-1 0.29 233°/WEST L X G
86 Switchyard N-1 0.24 262°/WEST N X G
87 Range S-1 0.20 286°/WNW P X 88G Mausoleum E-1 0.37 216°/SW L X
CH-ODCM-0001 Reference Use Page 40 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 NOTES:
A. Location is either not in use or currently discontinued and is documented in the table for reference only.
B. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II, Table 4 "Highest Potential Exposure Pathways for Estimating Dose")
C. Locations represent highest potential exposure pathways as determined by the biennial Land Use Survey, performed in accordance with Part I, Section 7.3.2, of the Off-Site Dose Calculation Manual and are monitored as such.
D. Background location (control). All other locations are indicators.
E. Location for monitoring Sector K High Exposure Pathway Resident Receptor for inhalation.
F. When broad leaf (pasture grasses) are being collected in lieu of milk, background broad leaf samples will be collected at a background locale.
G. Location for special interest monitoring general dose to the public per 40CFR190 (Figure 2)
CH-ODCM-0001 Reference Use Page 41 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Figure 1 - Environmental Radiological Sampling Points
(*) Locations currently discontinued are not illustrated.
CH-ODCM-0001 Reference Use Page 42 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Figure 2- 40CFR190 Sampling Points
CH-ODCM-0001 Reference Use Page 43 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) A, B, C Gross Co-58, Ba-140 Sample Units Beta H-3 Mn-54 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 La-140 Water pCi/L 4 2.0E+03 1.5E+01 3.0E+01 1.5E+01 3.0E+01 1.5E+01 1.5E+01 1.5E+01 1.8E+01 1.5E+01 pCi/kg Fish (wet) --- --- 1.3E+02 2.6E+02 1.3E+02 2.6E+02 --- --- 1.3E+02 1.5E+02 ---
Milk pCi/L --- --- --- --- --- --- --- --- 1.5E+01 1.8E+01 1.5E+01 Airborne Particulates or Gases pCi/m3 1.0E-02 --- --- --- --- --- --- --- 1.0E-02 1.0E-02 ---
pCi/kg Sediment (dry) --- --- --- --- --- --- --- --- 1.5E+02 1.8E+02 ---
Grass or Broad Leaf Vegetation/
Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 6.0E+01 8.0E+01 ---
A. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable as Facility effluents, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Part I, Section 6.2, of the Off-Site Dose Calculation Manual.
B. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
C. The LLD is defined in Part II of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 44 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples A Sample Units H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Water pCi/L 2.0E+04 1.0E+03 4.0E+02 1.0E+03 3.0E+02 3.0E+02 4.0E+02 4.0E+02 3.0E+01 5.0E+01 2.0E+02 Fish pCi/kg (wet) --- 3.0E+04 1.0E+04 3.0E+04 1.0E+04 2.0E+04 --- --- 1.0E+03 2.0E+03 ---
Milk pCi/L --- --- --- --- --- --- --- --- 6.0E+01 7.0E+01 3.0E+02 Airborne Particulates or pCi/m3 Gases --- --- --- --- --- --- --- --- 1.0E+01 2.0E+01 ---
Grass or Broad Leaf Vegetation/
Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 1.0E+03 2.0E+03 ---
A. A Non-routine report shall be submitted when more than one of the radionuclides listed above are detected in the sampling medium and:
1 2 3
.... 1.0 1 2 3 When radionuclides other than those listed above are detected and are the result of Facility effluents, this report shall be submitted if the potential annual dose to a member of the general public is equal to or greater than the dose objectives of Part I, Section 4.1 and 4.2, of the Off-Site Dose Calculation Manual. This report is not required if the measured level of radioactivity was not the result of Facility effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
CH-ODCM-0001 Reference Use Page 45 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 5.2 Land Use Survey 5.2.1 Limiting Condition for Operation A. A Land Use Survey shall identify the location of the nearest milk animal, nearest meat animal, nearest vegetable garden, nearest groundwater source and the nearest residence in each of the 16 cardinal sectors within a distance of five miles. The survey shall be conducted under the following conditions:
- 1. Within a one-mile radius from the Facility site, enumeration by door-to-door or equivalent counting techniques.
- 2. Within a Five-mile radius, enumeration may be conducted door-to-door or by using referenced information from county agricultural agents or other reliable sources.
APPLICABILITY: At all times ACTION:
- a. If it is learned from this survey that milk animals, vegetable gardens and resident receptors are present at a location which yields a calculated dose greater than 20% from previously sampled location(s), the new location(s) shall be added to the monitoring program. Milk and vegetable garden sampling location(s) having the lowest calculated dose may then be dropped from the monitoring program at the end of the grazing and/or growing season during which the survey was conducted and the new location added to the monitoring program.
Groundwater monitoring is based on a determination if source(s) are potentially affected by facility operations.
Modifications to the air monitoring locations, vegetable garden sampling locations, and milk sampling locations will be made as soon as practicable. The Nuclear Regulatory Commission shall be notified of modifications to the program in the Annual Radiological Environmental Operating Report (Section 6.2).
CH-ODCM-0001 Reference Use Page 46 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 5.2.1A.2 (continued)
- b. If it is learned from this survey that a pathway for dose to a MEMBER OF THE GENERAL PUBLIC no longer exists, an additional pathway has been identified or site specific factors affecting the dose calculations for a pathway have changed, then this information should be documented in the Land Use Survey, the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report.
This information can be used to increase the accuracy of the dose models for the Annual Radioactive Effluent Release Report as well as dose estimates performed during the reporting period (i.e., quarterly dose estimates).
5.2.2 Surveillance Requirements A. A land use survey shall be conducted once per 24 months between the dates of June 1 and October 1. The results of the land use survey shall be submitted to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 6.2) for the year it was performed.
5.3 Interlaboratory Comparison Program 5.3.1 Limiting Condition for Operation A. Analyses shall be performed on radioactive materials as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commission.
APPLICABILITY: At all times ACTION:
- 1. With analysis not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report (Section 6.2).
5.3.2 Surveillance Requirements A. The results of these analyses shall be included in the Annual Radiological Environmental Operating Report (Section 6.2).
CH-ODCM-0001 Reference Use Page 47 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibilities 6.1.1 FCS RP/Chemistry Department is responsible for the implementation and maintenance of the Off-Site Dose Calculation Manual.
6.1.2 FCS Operations Department is responsible for the compliance with the Off-Site Dose Calculation Manual in the operation of Fort Calhoun Station.
6.2 Radioactive Effluent Reporting Requirements The reporting requirements for radioactive effluents stated in this Section are to provide assurance that the limits set forth in Part I of the Off-Site Dose Calculation Manual are complied with. These reports will meet the requirements for documentation of radioactive effluents contained in 10 CFR Part 50.36a; Reg.
Guide 1.21, Rev. 2; Reg. Guide 4.8, Table 1; and Reg. Guide 1.109, Rev. 1.
6.2.1 Annual Radioactive Effluent Release Report A report covering the operation of the Fort Calhoun Station during the previous calendar year shall be submitted prior to May 1 of each year per the requirements of Technical Specifications 5.9.4.a. and 10 CFR Part 50.
The Radioactive Effluent Release Report shall include:
A. A summary of the quantities of radioactive liquid and airborne effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21, Revision 2.
B. A summary of the annual meteorological data that provides joint frequency distributions of wind direction and wind speed by atmospheric stability class will be included in the annual report. In addition, hourly meteorological data is recorded and retained on site as outlined in Regulatory Guide 1.21, Revision 2.
C. An assessment of radiation doses from the radioactive liquid and airborne effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21, Revision 2. The assessment of radiation doses shall be performed in accordance with calculational methodology of the Regulatory Guide 1.109, Revision 1.
D. Changes to the Process Control Program (PCP) or to the Offsite Dose Calculation Manual (ODCM) made during the reporting period. Each change shall be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed and shall indicate the date the change was implemented.
CH-ODCM-0001 Reference Use Page 48 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 6.2.1 (continued)
E. A list and description of abnormal releases or abnormal discharges from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.
F. An explanation of why instrumentation designated in Part I, Sections 3.1.1 and 3.2, of the Off-Site Dose Calculation Manual, was not restored to FUNCTIONAL status within 30 days.
G. A description of any major design changes or modifications made to the Liquid and/or Gaseous Radwaste Treatment Systems or Ventilation Exhaust Systems during the reporting period.
H. An explanation of why the liquid and/or gaseous radwaste treatment systems were not FUNCTIONAL, causing the limits of specifications 4.1.3A and 4.2.4A to be exceeded.
I. The results of sampling from offsite and onsite groundwater wells per the Site Groundwater Protection Plan. [AR 39127]
J. Non-routine planned discharges (e.g., discharges from remediation efforts like pumping contaminated groundwater from a leak).
6.2.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report for the previous one year of operation shall be submitted prior to May 1 of each year. This report contains the data gathered from the Radiological Environmental Monitoring Program. The content of the report shall include:
A. Summarized and tabulated results of the radiological environmental sampling/analysis activities following the format of Regulatory Guide 4.8, Table 1. In the event that some results are not available, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
B. Interpretations and statistical evaluation of the results, including an assessment of the observed impacts of the facility operation and environment.
C. The results of participation in a NRC approved Interlaboratory Comparison Program.
D. The results of land use survey required by Section 5.2.
E. A map of the current environmental monitoring sample locations.
CH-ODCM-0001 Reference Use Page 49 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 6.2.3 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report.
The Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report must be submitted within 60 days after the end of the 12-month monitoring period, per 10 CFR 72.44(d)(3).
A. A Summary of the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous 12 months and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent releases.
6.2.4 Special Report If the limits or requirements of Sections 4.1.2A, 4.1.3A, 4.2.2A, 4.2.3A, 4.2.4A, 4.3.1A, and/or 5.1.1A.3 and/or 5.1.1A.4 are exceeded, a Special Report shall be issued to the Commission, pursuant to Technical Specification 5.16. This report shall include: [AR 39127]
A. The results of an investigation to identify the causes for exceeding the specification.
B. Define and initiate a program of action to reduce levels to within the specification limits.
C. The report shall also include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the condition.
6.2.5 EPA 40 CFR Part 190 Reporting Requirements With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of dose from specifications 4.1.2A, 4.2.2A, or 4.2.3A, calculations shall be made including direct radiation calculations, to prepare and submit a special report to the Commission within 30 days and limit the subsequent releases such that the dose to any real individual from uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except thyroid, which is limited to 75 mrem) over the calendar year. This special report shall include an analysis which demonstrates that radiation exposures to any member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 standard. The submittal of the report is to be considered a timely request and a variance is granted pending the final action on the variance request from the Commission.
CH-ODCM-0001 Reference Use Page 50 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 6.2.5 ISFSI 10 CFR Part 72.104 Reporting Requirements The regulatory requirements of 10CFR20, 10CFR72 and 40CFR190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20, 10CFR72 and 40CFR190 not addressed by 10CFR50 Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public.
CH-ODCM-0001 Reference Use Page 51 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 The 10CFR72.104 dose limits are the same as those specified in 40CFR190.
ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. If the dose limits of 40CFR190 or 10CFR72.104 are exceeded, a special report to the NRC, as well as an appropriate request for exemption/variance, is required to be submitted to the NRC.
The requirement that the dose limits of 10CFR72.104 apply to any real individual is controlled for ISFSI activities in the ISFSI 72.212 report.
Therefore, for the purposes of analyzing dose from the ISFSI, the member of the public as defined in 40CFR190 is the same as for the real individual.
The external Total Body Dose is comprised of:
- 1) Total Body Dose due to noble gas radionuclides in gaseous effluents
- 2) Dose due to radioactive waste and the ISFSI
- 3) Total Body Dose due to radioactivity deposited on the ground (this dose is accounted for in the determination of the non-noble gas dose and is not considered here)
The Total Body Dose, external is given by:
D,ext = D,tb + D,osf Where D,ext is the external dose D,tb is the total body dose D,osf is the dose from on-site storage The Total Dose is then given by:
D,tot = D,ext + D,liq + D,nng Where D,tot is the total dose D,ext is the external dose D,liq is the dose from liquid effluents D,nng is the dose from non-noble gases Dose Limits Total Body, annual 25 mrem Thyroid, annual 75 mrem Other Organs, annual 25 mrem
CH-ODCM-0001 Reference Use Page 52 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 6.3 Change Mechanism The Off-Site Dose Calculation Manual is the controlling document for all radioactive effluent releases. It is defined as a procedure under the guidance of Technical Specification 5.8. It will be revised and reviewed by the Plant Operations Review Committee and approved by the Plant Manager in accordance with Technical Specification 5.17. All changes to the Off-Site Dose Calculation Manual will be forwarded to the Nuclear Regulatory Commission during the next reporting period for the Annual Radioactive Effluent Release Report in accordance with the requirements of Technical Specification 5.17.
6.4 Meteorological Data The Annual Average /Q is utilized to determine the concentrations of radionuclides at the unrestricted area boundary. It is also the factor used in conjunction with the parameters and methodologies in Part II, of the Off-Site Dose Calculation Manual to determine unrestricted area dose on a quarterly bases or as needed. It is based on an average of the highest calculated sector /Q values, using all 16 sectors for each of the three previous year Annual Radioactive Effluent Release Reports, and the XOQDOQ plume trajectory model. An additional 10 percent will be added to the average for unrestricted area dose estimates performed quarterly or as needed for conservatism. When calculating /Q data for the Annual Radiological Effluent Release Report, if the highest calculated /Q for the reporting period is observed to be greater than +/- 10% of the Annual Average /Q previously calculated, contact RP/Chemistry supervision for further instructions. This model conforms with the Nuclear Regulatory Commissions Regulatory Guide 1.111.
Current year meteorological data will be utilized in the preparation of the Annual Radioactive Effluent Release Report. This data is used to calculate the joint frequency table, the dispersion coefficients and deposition factors in all 16 sectors. These are used in the calculation of doses to individuals in unrestricted areas as a result of the operation of Fort Calhoun Station. The models used, GASPAR 2 and LADTAP 2, meet the intent of Nuclear Regulatory Commissions Reg. Guide 1.109 and 1.21 for the reporting of doses due to routine radioactive effluent releases.
CH-ODCM-0001 Reference Use Page 53 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 6.5 References 6.5.1 Regulatory Guide 1.109, Rev. 1 - Calculation of Annual Dose to man from Routine Releases of Reactor Effluents for the purpose of evaluation compliance with 10 CFR Part 50, Appendix I 6.5.2 Regulatory Guide 1.111, Rev. 1 - Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.
6.5.3 Regulatory Guide 1.113, Rev. 1 - Estimating Aquatic Dispersion of Effluents from Accidental and Routine Releases for the purpose of Implementing Appendix I.
6.5.4 Regulatory Guide 4.8, Environmental Technical Specification for Nuclear Power Plants.
6.5.5 NRC Branch Technical Position, March 1978 6.5.6 NUREG-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.
6.5.7 NUREG-1301 - Offsite Dose Calculation Manual Guidance.
6.5.8 Regulatory Guide 1.21, Rev. 2 - Measuring, Evaluating, and Reporting Radioactivity in solid wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.
6.5.9 Code of Federal Regulations, Title 10, Part 20 6.5.10 Code of Federal Regulations, Title 10, Part 50 6.5.11 Code of Federal Regulations, Title 10, Part 72 6.5.12 Code of Federal Regulations, Title 40, Part 190 6.5.13 Fort Calhoun Revised Environmental Report (Unit No. 1)-1972 6.5.14 Fort Calhoun Technical Specifications (Unit No. 1) 6.5.15 Defueled Safety Analysis Report 6.5.16 AR 12357, Implement Recommendations of Memo FC-0133-92, Part I, Table 3.2.1 Action 4, of the Off-Site Calculation Manual 6.5.17 AR 39127, NEI Industry Initiative on Groundwater Protection
CH-ODCM-0001 Reference Use Page 54 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 6.5.18 Regulatory Guide 4.1, Rev. 2 - Radiological Environmental Monitoring for Nuclear Power Plants 6.5.19 SO-G Station Fire Plan 6.5.20 FC-19-001, ODCM rev 29 Change Support Document
CH-ODCM-0001 Reference Use Page 55 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 7.0 BASIS 7.1 Instrumentation 7.1.1 Radioactive Liquid Effluent Instrumentation The Radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
7.1.2 Radioactive Gaseous Effluent Instrumentation The Radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
7.2 Radioactive Effluents 7.2.1 Radioactive Liquid Effluents A. Concentration NOTE: Xe-133 is remaining as the controlling isotope for noble gases, even though it is no longer present due to FCS no longer producing power, because it is more conservative than the remaining noble gases (e.g., Kr-85).
CH-ODCM-0001 Reference Use Page 56 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, and (2) the limits of 10 CFR Part 20.1001-20.2401 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-133 is the controlling isotope and its effluent concentration in air (submersion) was converted to an equivalent concentration in water.
B. Dose This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, with fresh water sites with drinking water supplies which can be potentially affected by facility operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in Part II of the Off-Site Dose Calculation Manual, implement the requirements in Section III.A that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Part II of the Off-Site Dose Calculation Manual, for calculating the doses due to the actual release rates of radioactive material in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
C. Liquid Waste Treatment System
CH-ODCM-0001 Reference Use Page 57 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 The FUNCTIONALITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective and in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified to ensure the design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents are not exceeded.
D. Liquid Holdup Tanks Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
7.2.2 Radioactive Gaseous Effluents A. Concentration This specification, in conjunction with Steps 4.2.2A and 4.2.3A, is provided to ensure that the dose at or beyond the Site Boundary from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for MEMBERS OF THE PUBLIC. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations for these radionuclides do not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To support facility operations, RP/Chemistry supervision may increase this limit up to the limits specified in Technical Specifications 5.16.1.g. Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. Because these concentrations are applied on an instantaneous basis and because of the overriding 10 CFR Part 50 Appendix I cumulative dose limitations, these limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the Site Boundary, to
CH-ODCM-0001 Reference Use Page 58 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR Part 20.1301(a).
B. Dose - Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the Off-Site Dose Calculation Manual, for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The Off-Site Dose Calculation Manual, equations provided for determining the air doses at the site boundary are consistent with Regulatory Guides 1.109 and 1.111.
CH-ODCM-0001 Reference Use Page 59 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 7.2.2 (continued)
C. Dose - Radioactive Material in Particulate Form with Half-Lives Greater than Eight Days (Other than Noble Gases) and Tritium This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the Off-Site Calculation Manual, for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The release rate specification for radioactive material in particulate form with half-lives greater than eight days (other than noble gases) and tritium are dependent on the existing radionuclide pathways to man in the areas at or beyond the site boundary. The pathways that were examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
CH-ODCM-0001 Reference Use Page 60 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 7.2.2 (continued)
D. Gaseous Waste Treatment The FUNCTIONALITY of the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable. This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective and in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified to ensure the design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded.
CH-ODCM-0001 Reference Use Page 61 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 7.2.2 (continued)
E. Total Dose - Uranium Fuel Cycle This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mRems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mRems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the facility remains within twice the dose design objectives of Appendix I, 10 CFR Part 50, and if direct radiation doses (including outside storage tanks, etc.) are kept small. The Special Report shall describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report, with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4) and 20.2203(b) is considered to be a timely request and fulfills the requirements 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. Demonstration of compliance with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301.
CH-ODCM-0001 Reference Use Page 62 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 7.3 Radiological Environmental Monitoring 7.3.1 Monitoring Program The radiological environmental monitoring program required by this specification provides measurements of radiation and radioactive materials in those exposure pathways and for radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program was effective for at least the first three years of commercial operation.
Following this period, program changes are initiated based on operational experience.
7.3.2 Land Use Survey This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this survey. The frequency of the Land Use Survey has been reduced to a biennial requirement in site procedures because persons knowledgeable in land use census monitor usage characteristics perform routine REMP sampling. This approach allows knowledge gained during sample collection to be integrated into the program, maintaining its effectiveness. The best survey information from door to door, aerial or consulting with local agricultural authorities, or equivalent, shall be used. This survey satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the survey to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m2.
For milk, the survey is restricted to only milk animals (cow or goat) producing milk for human consumption. Air monitoring stations are strategically located to monitor the resident receptors who could potentially receive the highest doses from airborne radioactive material. For groundwater, samples shall be taken when sources are determined to potentially be affected by facility operations, and when sources are tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. Guidance provided in the Branch Technical Position and Technical Specification 5.16.2 is used to meet the intent of NUREG-1301.
CH-ODCM-0001 Reference Use Page 63 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 7.3.3 Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
7.4 Abnormal Release or Abnormal Discharge Reporting 7.4.1 Specific information should be reported concerning abnormal (airborne and/or liquid) releases on site and abnormal discharges to the unrestricted area. The report should describe each event in a way that would enable the NRC to adequately understand how the material was released and if there was a discharge to the unrestricted area. The report should describe the potential impact on the ingestion exposure pathway involving surface water and ground water, as applicable. The report should also describe the impact (if any) on other affected exposure pathways (e.g., inhalation from pond evaporation).
7.4.2 The following are the thresholds for reporting abnormal releases and abnormal discharges in the supplemental information section:
A. Abnormal release or Abnormal Discharges that are voluntarily reported to local authorities under NEI 07-07, Industry Ground Water Protection Initiative. [AR 39127]
B. Abnormal release or Abnormal discharges estimated to exceed 100 gallons of radioactive liquid where the presence of licensed radioactive material is positively identified (either in the on-site environs or in the source of the leak or spill) as greater than the minimum detectable activity for the laboratory instrumentation.
C. Abnormal releases to on-site areas that result in detectable residual radioactivity after remediation.
D. Abnormal releases that result in a high effluent radiation alarm without an anticipated trip occurring.
E. Abnormal discharges to an unrestricted area.
CH-ODCM-0001 Reference Use Page 64 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 7.4.3 Information on Abnormal releases or Abnormal discharges should include the following, as applicable:
Date and duration Location Volume Estimated activity of each radionuclide Effluent monitoring results (if any)
On-site monitoring results (is any)
Depth to the local water table Classification(s) of subsurface aquifer(s) (e.g., drinking water, unfit for drinking water, not used for drinking water)
Size and extent of any ground water plume Expected movement/mobility of any ground water plume Land use characteristics (e.g., water used for irrigation)
Remedial actions considered or taken and results obtained Calculated member of the public dose attributable to the release Calculated member of the public dose attributable to the discharge Actions taken to prevent recurrence, as applicable Whether the NRC was notified, the date(s), and the contact organization
CH-ODCM-0001 Reference Use Page 65 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 PART II CALCULATIONS
CH-ODCM-0001 Reference Use Page 66 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents 1.1.1 There is one liquid discharge pathway to the Missouri River. The pathway originates with the radioactive liquid waste processing system (monitor or hotel tanks). This pathway empties into the circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathway and associated radiation monitor. Figure 3 depicts the methods of liquid effluent treatment.
1.1.2 The flowrate for dilution water varies with the number raw water pumps in service 1.1.3 Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2.
For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 Ci/ml total activity.
1.1.4 The liquid effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
1.1.5 The liquid effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
1.1.6 Cs-137 is used to calibrate the liquid effluent monitors.
CH-ODCM-0001 Reference Use Page 67 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.1.7 Liquid Effluent Radiation Monitor A. Overboard Discharge Header Monitor (RM-055)
- 1. This process radiation monitor provides control of the waste monitor tank effluent by monitoring the overboard header prior to its discharge into the circulating water discharge tunnel. The concentration of activity at discharge is controlled below ten times the 10 CFR Part 20 limit of 1.0E-06 Ci/ml at site discharge for unidentified isotopes by the high alarm setpoint which closes the overboard flow control valve.
- 2. The following calculations for maximum concentration and alarm setpoints are valid for radioactive liquid releases of monitor tank discharge.
- 3. The maximum allowable concentration in the overboard discharge header is:
1.0 05 Where:
1.0E-05 Ci/ml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2).
F = Total dilution flow in the discharge tunnel (gpm).
(Normal flow is based on 2 raw water pumps at 7,200 gpm total.)
f = Maximum monitor tank discharge flow rate (gpm).
(Normal monitor tank maximum flow is 15 gpm.)
CMAX = Maximum allowable activity in discharge header (Ci/ml).
CH-ODCM-0001 Reference Use Page 68 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.1.7A (continued)
The High Alarm Setpoint (CPM):
0.75 Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to account for the difference in detector sensitivity for the range of isotopes detected.
Sf = Detector sensitivity factor (CPM/Ci/ml). (Sensitivity based on Cs-137).
K3 = Allocation factor for Waste Liquid Releases (See Table 1)
CMAX = Maximum allowable concentration in discharge header (Ci/ml).
B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 69 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.2 Airborne Effluents 1.2.1 There are two air effluent discharge pathways at the Fort Calhoun Station:
Laboratory and Radioactive Waste Processing Building Exhaust Stack, and the Auxiliary Building Exhaust Stack. An airborne radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 4. The airborne waste disposal system is presented in Figure 5.
Auxiliary Building - The Auxiliary Building Exhaust Stack receives discharges from the auxiliary building ventilation system. Radiation Monitor RM-062 provides noble gas monitoring and particulate sampling for the Auxiliary Building Exhaust Stack. Backup noble gas monitoring and particulate sampling is provided by RM-052.
Laboratory and Radioactive Waste Processing Building (LRWPB) - Noble gas monitoring and particulate sampling is provided by RM-043. This radiation monitor/sampler does not serve a control function.
Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.
The airborne effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
The airborne effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than 5 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
CH-ODCM-0001 Reference Use Page 70 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.2.2 Airborne Effluent Radiation Monitors NOTE: Xe-133 is remaining as the controlling isotope for noble gases, even though it is no longer present due to FCS no longer producing power, because it is more conservative than the remaining noble gases (e.g., Kr-85).
A. Auxiliary Building Exhaust Stack Noble Gas Activity Monitor (RM-062/RM-052)
- 1. Either of these monitors may be used to measure the noble gas activity in the exhaust stack. The noble gas is monitored after passing through a particulate filter, and charcoal cartridge. The monitor controls airborne releases so that five times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.0E-07 Ci/cc, based upon Xe-133, is not exceeded.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from Auxiliary Building Exhaust Stack and the LRWPB Exhaust Stack.
- 3. The maximum allowable release rate for stack airborne activity is calculated as follows:
2.5 06 1.0 06 Where:
2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q sec/m3 = Annual average dispersion factor at the unrestricted area boundary from Part II Table 4, of the Off-Site Dose Calculation Manual.
1.0E+06 cc/m3 = Constant of unit conversion.
CH-ODCM-0001 Reference Use Page 71 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.2.2A (continued)
The High Alarm Setpoint (CPM):
60 0.75 28317 Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.
Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133)
K1 = Allocation factor for Auxiliary Building Exhaust Stack (See Table 1) 60 = Conversion (seconds to minutes).
28317 = Conversion factor (ft3 to cc).
Fv = Auxiliary Building Exhaust stack flow rate (SCFM).
(Default maximum flow rate is 72,500 cfm for 3 Auxiliary Building exhaust fans in operation. Other flow rates may be used, as required.)
RMAX = Maximum Allowable Release Rate in Ci/sec B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 72 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.2.2 (continued)
B. Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and Particulate Sampler (RM-043)
- 1. RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is based on five times the 10 CFR Part 20 limit for Xe-133 at the unrestricted area boundary.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from Auxiliary Building Exhaust Stack and the LRWPB Exhaust Stack.
2.5 06 sec 1.0 06 The maximum allowable release rate for RM-043 is as follows:
Where:
2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q = Annual average dispersion factor at the unrestricted area boundary from Part II of the Off-Site Dose Calculation Manual, Table 4.
1.0E+06 cc/m3 = Constant of unit conversion
CH-ODCM-0001 Reference Use Page 73 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 1.2.2B (continued) i i NOTE This monitor alarms in the Control Room. There are no automatic control functions associated with the actuation of the alarm.
The High Alarm Setpoint (CPM):
60 0.75 28317 Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.
Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133)
K2 = Allocation factor for LRWPB Exhaust Stack (See Table 1) 60 = Conversion (seconds to minutes).
28317 = Conversion factor (ft3 to cc).
Fv = LRWPB Exhaust stack flow rate (SCFM). (Default flow rate is 28,700 cfm. Other flow rates may be used if required.)
RMAX = Maximum Allowable Release Rate in Ci/sec.
B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 74 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 1 - Allocation Factors for Simultaneous Releases NOTE i The Fort Calhoun Station is capable of performing simultaneous airborne releases.
The factors below may be adjusted to meet release requirements, provided that the sum of the Unrestricted Area Fraction Sum for all airborne releases remains less i
than or equal to 1.0.
A. Allocation Factors for Simultaneous Airborne Releases
- 1. Auxiliary Building Exhaust Stack Total: 0.90 K1 Noble Gases (RM-062 or RM-052) 0.75 Particulate/Tritium 0.15 Contributing Pathways:
a) Auxiliary Building 0.90
- 2. Laboratory and Radioactive Waste Building Exhaust Total: 0.10 Stack K2 Noble Gases (RM-043) 0.05 Particulate 0.05 Contributing Pathways:
a) Laboratory and Radioactive Waste Building Exhaust Stack 0.10 Airborne Release Total 1.00 B. Allocation Factors for Simultaneous Liquid Releases
- 1. K3 Waste Liquid Releases (RM-055) 1.00 Liquid Release Total 1.00
CH-ODCM-0001 Reference Use Page 75 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Figure 1 - Exclusion and Site Boundary Map
CH-ODCM-0001 Reference Use Page 76 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Figure 2 - Liquid Radioactive Discharge Pathways
CH-ODCM-0001 Reference Use Page 77 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Figure 3 - Liquid Radioactive Waste Disposal System
CH-ODCM-0001 Reference Use Page 78 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Figure 4 - Airborne Effluent Discharge Pathways
CH-ODCM-0001 Reference Use Page 79 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Figure 5 - Airborne Radioactive Waste Disposal System
CH-ODCM-0001 Reference Use Page 80 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 2.0 EFFLUENT CONCENTRATIONS 2.1 Liquid Effluent Concentrations 2.1.1 The concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) will be limited to the concentrations as specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. For batch releases (Monitor and Hotel Waste Tanks) the analyses will be performed in accordance with Part I, Table 4.1, of the Off-Site Dose Calculation Manual, and the concentration of each radionuclide at site discharge will be calculated, based on the following equation:
1 Radionuclide concentration at site discharge:
Where:
Ai = concentration at site discharge for radionuclide (I), in Ci/ml.
ai = concentration of radionuclide (I) in the undiluted effluent, in Ci/ml.
f = undiluted effluent flowrate, in gpm.
F = total diluted effluent flowrate in gpm.
weci = water effluent concentration limit for radionuclide (I) per 10 CFR Part 20, Appendix B, Table 2, Column 2.
NOTE i In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable.
i 2.2 Airborne Effluent Concentrations 2.2.1 The concentration at the unrestricted area boundary, due to airborne effluent releases, will be limited to less than Appendix B, Table 2, Column 1, values.
Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event an airborne effluent release from the station result in an alarm setpoint being exceeded, an evaluation of the unrestricted area boundary concentration resulting from the release will be performed:
CH-ODCM-0001 Reference Use Page 81 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 2.2.2 To determine the concentration and air effluent concentration (aec) fraction summation at the unrestricted area boundary, the following equations will be used:
1 Where:
Ai = Concentration of radionuclide (I) at the unrestricted area boundary K0 = Constant of unit conversion. (1.0E-6 m3/cc)
ECLi = Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, Column 1 value for radionuclide(I))
Qi = The release rate of radionuclide (I) in airborne effluents from all vent releases (in Ci/sec.)
(/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from Part II, Table 4, of the Off-Site Dose Calculation Manual.
2.2.3 As appropriate, simultaneous releases from the Auxiliary Building Ventilation Stack and Laboratory and Radwaste Building Stack will be considered in evaluating compliance with the release rate limits of 10 CFR Part 20.
Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. Historical annual average dispersion parameters, as presented in Table 4, may be used for evaluating the airborne effluent dose rate.
2.2.4 For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding those more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding 10 CFR Part 20 limits. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based upon the above criteria, no further analyses are required for demonstrating compliance with 10 CFR Part 20.
CH-ODCM-0001 Reference Use Page 82 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS 3.1 Liquid Effluent Dose Calculations 3.1.1 Three pathways for human exposure to liquid releases from FCS to the Missouri River exists: 1) fish, 2) drinking water, and 3) Shoreline deposition.
Fish are considered to be taken from the vicinity of the facility discharge.
The drinking water for Omaha is located 19 miles downstream from FCS.
The dilution factors for these pathways are derived from the Revised Environmental Report for FCS, (1974), (page 4-29 and 4-31). This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be < 14% of the concentration at discharge from FCS and will average 3%. This equates to a dilution factor of 7.14, which is used to calculate the maximum dose to an individual from liquid pathways and a dilution factor of 33.33, for calculating the average dose. All pathways combine to give the dose to an individual in unrestricted areas.
3.1.2 10 CFR Part 50, Appendix I restricts the dose to individuals in the unrestricted areas from radioactive materials in liquid effluents from the Fort Calhoun Station to the following limits:
during any calendar quarter 1.5 mrem to total body 5.0 mrem to any organ and during any calendar year 3.0 mrem to total body 10.0 mrem to any organ The following calculational methods shall be used for determining the dose or dose commitment from liquid effluents.
CH-ODCM-0001 Reference Use Page 83 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.1.3 Doses from Liquid Effluent Pathways A. Potable Water 1100 exp Where:
Rapj = is the total annual dose to organ(j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr.
Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in
/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless.
(Table 17)
F = is the flow rate of the liquid effluent, in ft3/ sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Daipj = is the dose factor specific to a given age group (a),
radionuclide (I), pathway (p), and organ (j) which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = is the radiological decay constant of radionuclide (I), in hr 1.
tp = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the radionuclides and ingestion of water, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 84 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.1.3 (continued)
B. Aquatic Foods 1100 exp Where:
Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr.
Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in kg/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless. (Table 17)
F = is the flow rate of the liquid effluent, in ft3/sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Bip = is the equilibrium bioaccumulation factor for radionuclide (I) in pathway (p) expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in (pCi/kg)/(pCi/liter). (Table 3)
Daipj = is the dose factor specific to a given age group (a),
radionuclide (I), pathway (p), and organ (j), which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = is the radiological decay constant of radionuclide (I), in hr-1.
tp = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the radionuclides and ingestion of food, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 85 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.1.3 (continued)
C. Shoreline Deposits 110,000 exp 1 exp Where:
Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p),
in mrem/yr.
Uap = is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p),
in hr/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless. (Table 17)
W = is the shore-width factor, dimensionless. (Table 17)
F = is the flow rate of the liquid effluent, in ft3/sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Tip = is the radioactive half life of radionuclide (I), in days.
Daipj = is the dose factor specific radionuclide (I) which can be used to calculate the radiation dose from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the real radionuclide concentration (in pCi/m2). (Table 8) i = is the radiological decay constant of radionuclide (I), in hr-1.
tp = is the average transit time required for radionuclides to reach the point of exposure, in hours. (Table 17) tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours. (Table 17) 110,000 = Constant [(100
- pCi
- yr
- ft3)/(Ci
- sec
- L)]
CH-ODCM-0001 Reference Use Page 86 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2 Airborne Effluent Dose Calculations 3.2.1 Noble Gas 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from noble gases in airborne effluents from the Fort Calhoun Station to the following limits:
During any calendar quarter 5 mrad-gamma air dose 10 mrad-beta air dose and During any calendar year 10 mrad-gamma air dose 20 mrad-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses:
A. Doses from Noble Gases
- 1. Annual Gamma/Beta Air Dose from All Other Noble Gas Releases
, , 3.17 10 ,
Where:
DFi or DFi = are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide (I), in mrad-m3/pCi-yr. (Table 2)
D (r,) or D(r,) = are the annual gamma and beta air doses at distance r, in the sector at angle , from the discharge point, in mrad/yr.
Qi = is the annual release rate of radionuclide (I),
in Ci/yr.
[/Q]D(r,) = is the annual average gaseous dispersion factor at distance r, in the sector at angle , in sec/m3.
(Table 4) 3.17x104 = is the number of pCi per Ci divided by the number of seconds per year.
CH-ODCM-0001 Reference Use Page 87 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.1A (continued)
- 2. Annual Total Body Dose from All Other Noble Gas Releases Where:
DFBi = is the total body dose factor for a semi-infinite cloud of the radionuclide (I), which includes the attenuation of 5 g/cm2 of tissue, in mrem-m3/pCi-yr. (Table 2)
(r,) = is the annual total body dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle , in mrem/yr.
Xi(r,) = is the annual average ground-level concentration of radionuclide (I) at distance r, in the sector at angle , in pCi/m3. (Table 4)
Sf = Shielding Factor (Table 17)
CH-ODCM-0001 Reference Use Page 88 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30
- 3. Annual Skin Dose from All Other Noble Gas Releases
, 1.11 , ,
Where:
(r,) = is the annual skin dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle , in mrem/yr.
Xi(r,) = is the annual average ground-level concentration of radionuclide (I) at distance r, in the sector at angle , in pCi/m3. (Table 4)
Sf = Shielding Factor (Table 17)
DFSi = is the beta skin dose factor for a semiinfinite cloud of radionuclide (I), in mrem-m3/pCi-yr.
(Table 2)
= is the gamma skin dose factor for a semiinfinite cloud of radionuclide (I), in mrem-m3/pCi-yr.
(Table 2) 1.11 = is the average ratio of tissue to air energy absorption coefficients.
CH-ODCM-0001 Reference Use Page 89 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.2 Radioiodine, Tritium, and Particulates 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from radioactive materials in gaseous airborne from the Fort Calhoun Station to:
During any calendar quarter 7.5 mrem to any organ and During any calendar year 15 mrem to any organ The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in airborne effluents released to unrestricted areas should be determined by the following expressions:
CH-ODCM-0001 Reference Use Page 90 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.2 (continued)
NOTE i In all cases, for releases of tritium, use the dispersion parameter for inhalation (/Q).
i A. Annual Organ Dose from External Irradiation from Radioactivity Deposited on the Ground Plane The ground plane concentration of radionuclide (I) at distance r, in the sector at angle , with respect to the release point, may be determined by:
1.0 10 ,
, 1 exp Where:
CGI = is the ground plane concentration of the radionuclide (I) at distance r, in the sector at angle , from the release point, in pCi/m2.
Qi = is the annual release rate of radionuclide (I) to the atmosphere, in Ci/yr.
tb = is the time period over which the accumulation is evaluated, which is assumed to be 20 years (mid-point of plant operating life). (Table 17) i(r,) = is the annual average relative deposition of radionuclide (I) at distance r, in the sector at angle , considering depletion of the plume by deposition during transport, in m-2. Table 4 i = is the radiological decay constant for radionuclide (I), in yr-1.
1.0x1012 = is the number of pCi/Ci
CH-ODCM-0001 Reference Use Page 91 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.2A (continued)
The annual organ dose is then calculated using the following equation:
, 8760 ,
Where:
CGj(r,) = is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle , in pCi/m2.
DFGij = is the open field ground plane dose conversion factor for organ (j) from radionuclide (i), in mrem-m2/pCi-hr.
(Table 8)
DGj(r,) = is the annual dose to the organ (j) at distance r, in the sector at angle , in mrem/yr.
Sf = is the shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy, dimensionless. (Table 17) 8760 = is the number of hours in a year B. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide (i) at distance r, in the sector at angle , with respect to the release point, may be determined as:
, 3.17 10 ,
Where:
Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
[/Q]D (r,) = is the annual average atmosphere dispersion factor, in sec/m3 (see Reg Guide 1.111). This includes depletion (for radioiodines and particulates) and radiological decay of the plume. (Table 4) 3.17x104 = is the number of pCi/Ci divided by the number of sec/yr.
CH-ODCM-0001 Reference Use Page 92 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.2B (continued)
The annual dose associated with inhalation of all radionuclides to organ (j) of an individual in age group (a), is then:
Where:
DAja(r,) = is the annual dose to organ (j) of an individual in the age group (a) at distance r, in the sector at angle , due to inhalation, in mrem/yr.
Ra = is the annual air intake for individuals in the age group (a), in m3/yr. (Table 6) i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
DFAija = is the inhalation dose factor for radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 9-12)
CH-ODCM-0001 Reference Use Page 93 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.3 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases A. Parameters for Calculating Concentrations in Forage, Produce, and Leafy Vegetables, excluding Tritium 1 exp 1 exp
, , exp Where:
CVi(r,) = is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle , in pCi/kg.
di (r,) = is the deposition rate of radionuclide (i) at distance r, in the sector at angle , in pCi/m2 hr.
r = is the fraction of deposited activity retained on crops, dimensionless. (Table 17)
Ei = is the effective removal rate constant for radionuclide (i) from crops, in hr-1.
Ei = i + w w = 0.0021/hr. (Table 17) te = is the time period that crops are exposed to contamination during the growing season, in hours.
(Table 17)
Yv = is the agricultural productivity (yield) in kg (wet weight)/m2. (Table 17)
Biv = is the concentration factor for uptake of radionuclide (i) from soil by edible parts of crops, in pCi/ kg (wet weight) per pCi/kg dry soil. (Table 5) i = is the radiological decay constant of radionuclide (I), in hr-1 tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours (mid-point of plant life). (Table 17)
P = is the effective "surface density" for soil, in kg (dry soil)/m2. (Table 17) th = is the holdup time that represents the time interval between harvest and consumption of the food, in hours.
(Table 17)
Different values for the parameters te, Yv, and th, may be used to allow the use of the Equation for different purposes: estimating concentrations in produce consumed by man; in leafy vegetables consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or goats; and in forage consumed as stored feed by dairy cows, beef cattle or goats. See Table 17.
CH-ODCM-0001 Reference Use Page 94 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.3A (continued)
The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa. C-6):
, 1.1 10 ,
Where:
di(r,) = is the deposition rate of radionuclide (i).
i(r,) = is the relative deposition of radionuclide (i), considering depletion and decay, in m-2 (see Reg Guide 1.111).
(Table 4) 1.1x108 = is the number of pCi/Ci (1012) divided by the number of hours per year (8760).
Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
CH-ODCM-0001 Reference Use Page 95 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.3 (continued)
B. For radioiodines, the model considers only the elemental fraction of the effluent:
, 3.3 10 ,
Where:
di (r, ) = The deposition rate of radioiodine (i).
3.3 x 107 = The number of pCi/Ci (1012) divided by the number of hours per year (8760), then multiplied by the amount of radioiodine emissions considered to be elemental (0.5).
i (r, ) = The relative deposition of radioiodine (i), considering depletion and decay, in m-2. (Table 4)
Qi = The total (elemental and nonelemental) radioiodine (i) emission rate.
C. Parameters for Calculating the Concentration of Radionuclide (i) in the Animal's Feed (Milk Cow, Beef Cow, and Goat)
, , 1 , 1 ,
Where:
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
CPi(r,) = is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2.3A with th=0), in pCi/kg.
CSi(r,) = is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3A with th=90 days), in pCi/kg.
fp = is the fraction of the year that animals graze on pasture. (Table 17) fs = is the fraction of daily feed that is pasture grass while the animal grazes on pasture. (Table 17)
CH-ODCM-0001 Reference Use Page 96 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk
, , exp Where:
CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter.
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
Fm = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each liter of milk, in days/liter.
(Table 5)
QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) tf = is the average transport time of the radionuclide (i) from the feed to the milk and to the receptor (a value of 2 days is assumed). (Table 17) i = is the radiological decay constant of radionuclide (i), in days-1.
CH-ODCM-0001 Reference Use Page 97 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.5 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium
, , exp Where:
CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter.
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7)
Ff = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each kilogram of flesh, in days/kilogram. (Table 5) ts = is the average time from slaughter to consumption. (Table 17) 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.
, 0.75 0.5 ,
, 3.17 10 1.2 10 Where:
CVT(r, ) = is the concentration of tritium in vegetation grown at distance r, in the sector at angle , in pCi/kg.
H = is the absolute humidity of the atmosphere at distance r, in the sector at angle , in g/m3. H=8 gm/kg.
QT = is the annual release rate of tritium, in Ci/yr.
[/Q](r,) = is the atmospheric dispersion factor, in sec/m3. (Table 4) 0.5 = is the ratio of tritium concentration in facility water to tritium concentration in atmospheric water, dimensionless.
0.75 = is the fraction of total facility mass that is water, dimensionless.
CH-ODCM-0001 Reference Use Page 98 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ (j) of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by:
Where:
DDja(r,) = is the annual dose to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. Tables 13-16.
UVa = are the ingestion rates of produce (non-leafy vegetables, fruits, and grains) , respectively for individuals in age group (a).
(Table 6)
UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6)
UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6)
ULa = are the ingestion rates of leafy vegetables for individuals in age group (a), in kg/yr. (Table 6)
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter.
CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter.
CLI (r,) = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.
fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 99 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 3.2.7 (continued)
B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce)
Vegetation for Radionuclide (i) to Each Organ (j) and Age Group (a)
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i) to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in vegetation, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pci. Tables 13-16 ULa,UVa = are the ingestion rates of leafy vegetables and produce (non-leafy vegetables, fruits, and grains), for individuals in age group (a), in kg/yr. (Table 6)
CLi = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.
CVi = is the concentration of radionuclide (i) in and on produce, in pCi/kg.
fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 100 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 C. Calculation Determining the Ingested Dose from Cow Milk for Radionuclide (i), Organ (j), and Age Group (a)
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in cow milk, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16)
UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6)
CMi = is the radionuclide concentration in cow milk, in pCi/kg.
Equation 3.2.4 D. Calculation Determining the Ingested Dose from Meat for Radionuclide (i) to Organ (j) and Age Group (a)
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in meat, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16)
UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6)
CFi = is the radionuclide (i) concentration in meat, in pCi/kg.
3.2.8 Annual Dose from Carbon 14 A. This is a calculated value based on power generation and days of operation. Critical organ doses from C-14 were calculated using a ratio of 15% as CO2. This ratio was determined during an NRC in-plant source term study conducted at the Fort Calhoun Station between 1976 and 1977, NUREG/CR-0140.
CH-ODCM-0001 Reference Use Page 101 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 4.0 LOWER LIMIT OF DETECTION (LLD) 4.1 The lower limit of detection (LLD) for liquid and airborne effluent discharges and environmental samples referenced in Part I, Tables 4.1, 4.2 and 5.3, of the Off-Site Dose Calculation Manual, is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
4.2 For a particular measurement system, which may include radiochemical separation:
4.66 exp Where:
LLD = the lower limit of detection as defined above, in either picoCuries or microCuries, per unit mass or volume as a function of the value of D Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate, as counts per minute E = the counting efficiency, as counts per disintegration V = the sample size in units of mass or volume D = 2.22E+06 of disintegrations per minute per microCurie or 2.22 disintegrations per minute per picoCurie Y = the fractional radiochemical yield, when applicable
= the radioactive decay constant for the particular radionuclide t = the elapsed time between the midpoint of sample collection and time of counting Appropriate values of E, V, Y, and t should be used in the calculation.
4.3 It should be recognized that the LLD is defined as an A Priori limit representing the capability of a measurement system and not as a limit for a particular measurement.
4.4 LLD verifications will be performed on a periodic basis. This determination is to ensure that the counting system is able to detect levels of radiation at the LLD values for the specific type of analysis required. They will be performed with a blank (non-radioactive) sample in the same counting geometry as the actual sample.
CH-ODCM-0001 Reference Use Page 102 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Nuclide -Air1 (Dfi) -Skin2 (DFSi) -Air1 (Dfi) -Body2 (DFBi)
Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11E-03 4.67E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 1.
2.
CH-ODCM-0001 Reference Use Page 103 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 3 - Bioaccumulation Factors (pCi/kg per pCi/liter)
FRESHWATER Element Fish Invertebrate H 9.0E-01 9.0E-01 C 4.6E+03 9.1E+03 Na 1.0E+02 2.0E+02 P 1.0E+05 2.0E+04 Cr 2.0E+02 2.0E+03 Mn 4.0E+02 9.0E+04 Fe 1.0E+02 3.2E+03 Co 5.0E+01 2.0E+02 Ni 1.0E+02 1.0E+02 Cu 5.0E+01 4.0E+02 Zn 2.0E+03 1.0E+04 Br 4.2E+02 3.3E+02 Rb 2.0E+03 1.0E+03 Sr 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+03 Zr 3.3E+00 6.7E+00 Nb 3.0E+04 1.0E+02 Mo 1.0E+01 1.0E+01 Tc 1.5E+01 5.0E+00 Ru 1.0E+01 3.0E+02 Rh 1.0E+01 3.0E+02 Te 4.0E+02 6.1E+03 I 1.5E+01 5.0E+00 Cs 2.0E+03 1.0E+03 Ba 4.0E+00 2.0E+02 La 2.5E+01 1.0E+03 Ce 1.0E+00 1.0E+03 Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E+03 W 1.2E+03 1.0E+01 Np 1.0E+01 4.0E+02
CH-ODCM-0001 Reference Use Page 104 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 4 - Highest Potential Exposure Pathways for Estimating Dose NOTE i The Annual Radiological Effluent Report uses the highest calculated value from real time meteorological data obtained for the entire year for calculating i dose.
Distance
/Q A D/Q A Exposure from Location B Direction B {/Q (r,)} { (r,)}
Pathway Containment (sec/m3) (m-2)
(miles) B Direct Exposure Site NW 0.29 4.90E-05 N/A Boundary Inhalation Site NW 0.29 4.90E-05 N/A Boundary Ingestion Residence SSE 0.60 N/A 7.6E-08 A. These values are used for calculating quarterly dose estimates during the annual reporting period and are based on a 2 year average, updated only upon a +10%
change from the previous value. At least ten percent (10%) should be added to these values for dose estimates during the reporting periods.
B. The location is subject to change based on an annual evaluation and is utilized only for ingestion exposure pathway dose estimates. This location may differ from the highest ingestion exposure pathway for offsite air monitoring locations as determined by the Land Use Survey performed biennially in accordance with Part 1, Section 7.3.2, of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 105 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 5 - Stable Element Transfer Data Biv Fm (cow) Fm (goat) Ff Element Veg./Soil Milk (d/I) Milk (d/I) Meat (d/kg)
H 4.8E+00 1.0E-02 1.7E-01 1.2E-02 C 5.5E+00 1.2E-02 1.0E-01 3.1E-02 Na 5.2E-02 4.0E-02 ------ 3.0E-02 P 1.1E+00 2.5E-02 2.5E-01 4.6E-02 Cr 2.5E-04 2.2E-03 ------ 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 1.3E-04 4.0E-02 Co 9.4E-03 1.0E-03 ------ 1.3E-02 Ni 1.9E-02 6.7E-03 ------ 5.3E-02 Cu 1.2E-01 1.4E-02 1.3E-02 8.0E-03 Zn 4.0E-01 3.9E-02 ------ 3.0E-02 Rb 1.3E-01 3.0E-02 ------ 3.1E-02 Sr 1.7E-02 8.0E-04 1.4E-02 6.0E-04 Y 2.6E-03 1.0E-05 ------ 4.6E-03 Zr 1.7E-04 5.0E-06 ------ 3.4E-02 Nb 9.4E-03 2.5E-03 ------ 2.8E-01 Mo 1.2E-01 7.5E-03 ------ 8.0E-03 Tc 2.5E-01 2.5E-02 ------ 4.0E-01 Ru 5.0E-02 1.0E-06 ------ 4.0E-01 Rh 1.3E+1 1.0E-02 ------ 1.5E-03 Ag 1.5E-01 5.0E-02 ------ 1.7E-02 Sb 1.1E-02 1.5E-03 ------ 4.0E-03 Te 1.3E+00 1.0E-03 ------ 7.7E-02 I 2.0E-02 6.0E-03 6.0E-02 2.9E-03 Cs 1.0E-02 1.2E-02 3.0E-01 4.0E-03 Ba 5.0E-03 4.0E-04 ------ 3.2E-03 La 2.5E-03 5.0E-06 ------ 2.0E-04 Ce 2.5E-03 1.0E-04 ------ 1.2E-03 Pr 2.5E-03 5.0E-06 ------ 4.7E-03 Nd 2.4E-03 5.0E-06 ------ 3.3E-03 W 1.8E-02 5.0E-04 ------ 1.3E-03 Pu 2.5E-04 2.0E-06 ------ 1.4E-05 Np 2.5E-03 5.0E-06 ------ 2.0E-04 Am 2.5E-04 5.0E-06 ------ 2.0E-04 Cm 2.5E-03 5.0E-06 ------ 2.0E-04
CH-ODCM-0001 Reference Use Page 106 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data Pathway Infant Child Teen Adult Fruits, vegetables, & grain (kg/yr) --- 520 630 520 Leafy vegetables (kg/yr) --- 26 42 64 Milk (/yr) 330 330 400 310 Meat & poultry (kg/yr) --- 41 65 110 Fish (fresh or salt)(kg/yr) --- 6.9 16 21 Other Seafood (kg/yr) --- 1.7 3.8 5 Drinking water (/yr) 330 510 510 730 Shoreline recreation (hr/yr) --- 14 67 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table 7 - Animal Consumption Rates Animal QF Feed or Forage [Kg/day (wet weigh)] QAW Water (/day)
Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8
CH-ODCM-0001 Reference Use Page 107 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin H-3 --- ---
C-14 --- ---
Na-24 2.50E-08 2.90E-08 P-32 --- ---
Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 --- ---
Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-59 --- ---
Ni-63 --- ---
Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 --- ---
Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 --- ---
Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09
CH-ODCM-0001 Reference Use Page 108 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Sb-124 1.30E-08 1.50E-08 Sb-125 3.10E-09 3.50E-09 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 --- ---
Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09
CH-ODCM-0001 Reference Use Page 109 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin Pu-238 1.30E-12 1.80E-11 Pu-239 7.90E-13 7.70E-12 Pu-240 1.30E-12 1.80E-11 Pu-241 4.60E-12 6.80E-12 Np-239 9.50E-10 1.10E-09 Am-241 1.80E-10 2.60E-10 Cm-242 5.50E-12 2.30E-11 Cm-243 2.30E-09 2.90E-09 Cm-244 2.90E-12 1.80E-11
CH-ODCM-0001 Reference Use Page 110 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 --- --- --- 1.08E-05 Cr-51 --- --- 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 --- 4.95E-06 7.87E-07 --- 1.23E-06 1.75E-04 9.67E-06 Mn-56 --- 1.55E-10 2.29E-11 --- 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 --- --- 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 --- --- 1.27E-04 2.35E-05 Co-58 --- 1.98E-07 2.59E-07 --- --- 1.16E-04 1.33E-05 Co-60 --- 1.44E-06 1.85E-06 --- --- 7.46E-04 3.56E-05 Ni-59 4.06E-06 1.46E-06 6.77E-07 --- --- 8.20E-06 6.11E-07 Ni-63 5.40E-05 3.93E-06 1.81E-06 --- --- 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 --- --- 7.00E-07 1.54E-06 Cu-64 --- 1.83E-10 7.69E-11 --- 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 --- 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 --- 5.27E-12 1.15E-07 2.04E-09 Br-83 --- --- 3.01E-08 --- --- --- 2.90E-08 Br-84 --- --- 3.91E-08 --- --- --- 2.05E-13 Br-85 --- --- 1.60E-09 --- --- --- ---
Rb-86 --- 1.69E-05 7.37E-06 --- --- --- 2.08E-06 Rb-88 --- 4.84E-08 2.41E-08 --- --- --- 4.18E-19 Rb-89 --- 3.20E-08 2.12E-08 --- --- --- 1.16E-21 Sr-89 3.80E-05 --- 1.09E-06 --- --- 1.75E-04 4.37E-05 Sr-90 3.59E-03 --- 7.21E-05 --- --- 1.20E-03 9.02E-05 Sr-91 7.74E-09 --- 3.13E-10 --- --- 4.56E-06 2.39E-05 Sr-92 8.43E-10 --- 3.64E-11 --- --- 2.06E-06 5.38E-06 Y-90 2.61E-07 --- 7.01E-09 --- --- 2.12E-05 6.32E-05 Y-91M 3.26E-11 --- 1.27E-12 --- --- 2.40E-07 1.66E-10 Y-91 5.78E-05 --- 1.55E-06 --- --- 2.13E-04 4.81E-05 Y-92 1.29E-09 --- 3.77E-11 --- --- 1.96E-06 9.19E-06 Y-93 1.18E-08 --- 3.26E-10 --- --- 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 --- 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 --- 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 --- 9.67E-07 6.31E-05 1.30E-05 Mo-99 --- 1.51E-08 2.87E-09 --- 3.64E-08 1.14E-05 3.10E-05 Tc-99M 1.29E-13 3.64E-13 4.63E-12 --- 5.52E-12 9.55E-08 5.20E-07
CH-ODCM-0001 Reference Use Page 111 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 5.22E-15 7.52E-15 7.38E-14 --- 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 --- 8.23E-08 --- 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 --- 3.89E-11 --- 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 --- 1.09E-06 --- 1.67E-05 1.17E-03 1.14E-04 Ag-110M 1.35E-06 1.25E-06 7.43E-07 --- 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 --- 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 --- 2.18E-04 1.26E-05 Te-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 --- 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 --- 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 --- 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 --- 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 --- 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 --- 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 --- 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 --- 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 --- 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 --- 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 --- 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 --- 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 --- 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 --- 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 --- --- 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 --- --- 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 --- 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 --- 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 --- 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 --- 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 --- 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 --- 4.45E-07 2.76E-05 2.16E-05
CH-ODCM-0001 Reference Use Page 112 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.06E-09 8.85E-10 3.10E-10 --- --- 3.63E-06 1.94E-05 Pu-238 1.43E+00 9.71E-01 6.90E-02 --- 2.96E-01 1.82E-01 4.52E-05 Pu-239 1.66E+00 1.07E+00 7.75E-02 --- 3.30E-01 1.72E-01 4.13E-05 Pu-240 1.65E+00 1.07E+00 7.73E-02 --- 3.29E-01 1.72E-01 4.21E-05 Pu-241 3.42E-02 8.69E-03 1.29E-03 --- 5.93E-03 1.52E-04 8.65E-07 Np-239 2.87E-08 2.54E-08 1.55E-09 --- 8.75E-09 4.70E-06 1.49E-05 Am-241 1.68E+00 1.13E+00 6.71E-02 --- 5.04E-01 6.06E-02 4.60E-05 Cm-242 2.22E-02 1.77E-02 9.84E-04 --- 4.48E-03 3.92E-02 4.91E-05 Cm-243 1.10E+00 7.61E-01 4.61E-02 --- 2.15E-01 6.31E-02 4.84E-05 Cm-244 8.37E-01 5.88E-01 3.51E-02 --- 1.64E-01 6.06E-02 4.68E-05
CH-ODCM-0001 Reference Use Page 113 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 --- --- --- 1.16E-05 Cr-51 --- --- 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 --- 6.39E-06 1.05E-06 --- 1.59E-06 2.48E-04 8.35E-06 Mn-56 --- 2.12E-10 3.15E-11 --- 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 --- --- 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 --- --- 1.91E-04 2.23E-05 Co-58 --- 2.59E-07 3.47E-07 --- --- 1.68E-04 1.19E-05 Co-60 --- 1.89E-06 2.48E-06 --- --- 1.09E-03 3.24E-05 Ni-59 5.44E-06 2.02E-06 9.24E-07 --- --- 1.41E-05 6.48E-07 Ni-63 7.25E-05 5.43E-06 2.47E-06 --- --- 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 --- --- 1.17E-06 4.59E-06 Cu-64 --- 2.54E-10 1.06E-10 --- 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 --- 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 --- 7.53E-12 1.98E-07 3.56E-08 Br-83 --- --- 4.30E-08 --- --- --- ---
Br-84 --- --- 5.41E-08 --- --- --- ---
Br-85 --- --- 2.29E-09 --- --- --- ---
Rb-86 --- 2.38E-05 1.05E-05 --- --- --- 2.21E-06 Rb-88 --- 6.82E-08 3.40E-08 --- --- --- 3.65E-15 Rb-89 --- 4.40E-08 2.91E-08 --- --- --- 4.22E-17 Sr-89 5.43E-05 --- 1.56E-06 --- --- 3.02E-04 4.64E-05 Sr-90 4.14E-03 --- 8.33E-05 --- --- 2.06E-03 9.56E-05 Sr-91 1.10E-08 --- 4.39E-10 --- --- 7.59E-06 3.24E-05 Sr-92 1.19E-09 --- 5.08E-11 --- --- 3.43E-06 1.49E-05 Y-90 3.73E-07 --- 1.00E-08 --- --- 3.66E-05 6.99E-05 Y-91M 4.63E-11 --- 1.77E-12 --- --- 4.00E-07 3.77E-09 Y-91 8.26E-05 --- 2.21E-06 --- --- 3.67E-04 5.11E-05 Y-92 1.84E-09 --- 5.36E-11 --- --- 3.35E-06 2.06E-05 Y-93 1.69E-08 --- 4.65E-10 --- --- 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 --- 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 --- 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 --- 1.25E-06 9.39E-05 1.21E-05 Mo-99 --- 2.11E-08 4.03E-09 --- 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 --- 7.20E-12 1.44E-07 7.66E-07
CH-ODCM-0001 Reference Use Page 114 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 7.40E-15 1.05E-14 1.03E-13 --- 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 --- 1.12E-07 --- 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 --- 5.42E-11 --- 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 --- 1.55E-06 --- 2.38E-05 2.01E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-06 9.99E-07 --- 3.13E-06 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 --- 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 --- 3.42E-04 1.24E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 --- 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 --- 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 --- 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 --- 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 --- 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 --- 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 --- 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 --- 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 --- 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 --- 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 --- 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 --- 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 --- 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 --- 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 --- 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 --- --- 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 --- --- 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 --- 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 --- 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 --- 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 --- 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 --- 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 --- 6.28E-07 4.65E-05 2.28E-05
CH-ODCM-0001 Reference Use Page 115 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.50E-09 1.22E-09 4.29E-10 --- --- 5.92E-06 2.21E-05 Pu-238 1.50E+00 1.03E+00 7.22E-02 --- 3.10E-01 3.12E-01 4.79E-05 Pu-239 1.73E+00 1.12E+00 8.05E-02 --- 3.44E-01 2.93E-01 4.37E-05 Pu-240 1.72E+00 1.12E+00 8.04E-02 --- 3.43E-01 2.93E-01 4.46E-05 Pu-241 3.74E-02 9.56E-03 1.40E-03 --- 6.47E-03 2.60E-04 9.17E-07 Np-239 4.23E-08 3.60E-08 2.21E-09 --- 1.25E-08 8.11E-06 1.65E-05 Am-241 1.77E+00 1.20E+00 7.10E-02 --- 5.32E-01 1.05E-01 4.88E-05 Cm-242 3.17E-02 2.51E-02 1.41E-03 --- 6.40E-03 6.76E-02 5.21E-05 Cm-243 1.19E+00 8.30E-01 5.00E-02 --- 2.34E-01 1.09E-01 5.13E-05 Cm-244 9.19E-01 6.53E-01 3.88E-02 --- 1.81E-01 1.05E-01 4.96E-05
CH-ODCM-0001 Reference Use Page 116 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 --- --- --- 1.14E-05 Cr-51 --- --- 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 --- 1.16E-05 2.57E-06 --- 2.71E-06 4.26E-04 6.19E-06 Mn-56 --- 4.48E-10 8.43E-11 --- 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 --- --- 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 --- --- 3.43E-04 1.91E-05 Co-58 --- 4.79E-07 8.55E-07 --- --- 2.99E-04 9.29E-06 Co-60 --- 3.55E-06 6.12E-06 --- --- 1.91E-03 2.60E-05 Ni-59 1.66E-05 4.67E-06 2.83E-06 --- --- 2.73E-05 6.29E-07 Ni-63 2.22E-04 1.25E-05 7.56E-06 --- --- 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 --- --- 2.21E-06 2.27E-05 Cu-64 --- 5.39E-10 2.90E-10 --- 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 --- 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 --- 1.58E-11 3.84E-07 2.75E-06 Br-83 --- --- 1.28E-07 --- --- --- ---
Br-84 --- --- 1.48E-07 --- --- --- ---
Br-85 --- --- 6.84E-09 --- --- --- ---
Rb-86 --- 5.36E-05 3.09E-05 --- --- --- 2.16E-06 Rb-88 --- 1.52E-07 9.90E-08 --- --- --- 4.66E-09 Rb-89 --- 9.33E-08 7.85E-08 --- --- --- 5.11E-10 Sr-89 1.62E-04 --- 4.66E-06 --- --- 5.83E-04 4.52E-05 Sr-90 1.04E-02 --- 2.07E-04 --- --- 3.99E-03 9.28E-05 Sr-91 3.28E-08 --- 1.24E-09 --- --- 1.44E-05 4.70E-05 Sr-92 3.54E-09 --- 1.42E-10 --- --- 6.49E-06 6.55E-05 Y-90 1.11E-06 --- 2.99E-08 --- --- 7.07E-05 7.24E-05 Y-91M 1.37E-10 --- 4.98E-12 --- --- 7.60E-07 4.64E-07 Y-91 2.47E-04 --- 6.59E-06 --- --- 7.10E-04 4.97E-05 Y-92 5.50E-09 --- 1.57E-10 --- --- 6.46E-06 6.46E-05 Y-93 5.04E-08 --- 1.38E-09 --- --- 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 --- 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 --- 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 --- 2.33E-06 1.66E-04 1.00E-05 Mo-99 --- 4.66E-08 1.15E-08 --- 1.06E-07 3.66E-05 3.42E-05 Tc-99M 4.81E-13 9.41E-13 1.56E-11 --- 1.37E-11 2.57E-07 1.30E-06
CH-ODCM-0001 Reference Use Page 117 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.19E-14 2.30E-14 2.91E-13 --- 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 --- 2.90E-07 --- 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 --- 1.50E-10 --- 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 --- 4.57E-06 --- 4.97E-05 3.87E-03 1.16E-04 Ag-110M 4.56E-06 3.08E-06 2.47E-06 --- 5.74E-06 1.48E-03 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 --- 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 --- 6.27E-04 1.09E-05 Te-125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 --- 1.29E-04 9.13E-06 Te-127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 --- 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 --- 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 --- 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 --- 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 --- 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 --- 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 --- 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 --- 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 --- 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 --- 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 --- 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 --- 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 --- 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 --- 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 --- --- 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 --- --- 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 --- 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 --- 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 --- 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 --- 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 --- 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 --- 1.30E-06 8.87E-05 2.22E-05
CH-ODCM-0001 Reference Use Page 118 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 4.41E-09 2.61E-09 1.17E-09 --- --- 1.11E-05 2.46E-05 Pu-238 2.55E+00 1.60E+00 1.21E-01 --- 4.47E-01 6.08E-01 4.65E-05 Pu-239 2.79E+00 1.68E+00 1.28E-01 --- 4.78E-01 5.72E-01 4.24E-05 Pu-240 2.79E+00 1.68E+00 1.27E-01 --- 4.77E-01 5.71E-01 4.33E-05 Pu-241 7.94E-02 1.75E-02 2.93E-03 --- 1.10E-02 5.06E-04 8.90E-07 Np-239 1.26E-07 8.14E-08 6.35E-09 --- 2.63E-08 1.57E-05 1.73E-05 Am-241 2.97E+00 1.84E+00 1.24E-01 --- 7.63E-01 2.02E-01 4.73E-05 Cm-242 9.48E-02 5.68E-02 4.20E-03 --- 1.34E-02 1.31E-01 5.06E-05 Cm-243 2.32E+00 1.42E+00 9.95E-02 --- 3.74E-01 2.10E-01 4.98E-05 Cm-244 1.94E+00 1.18E+00 8.31E-02 --- 3.06E-01 2.02E-01 4.82E-05
CH-ODCM-0001 Reference Use Page 119 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 --- --- --- 1.15E-05 Cr-51 --- --- 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 --- 1.81E-05 3.56E-06 --- 3.56E-06 7.14E-04 5.04E-06 Mn-56 --- 1.10E-09 1.58E-10 --- 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 --- --- 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 --- --- 7.25E-04 1.77E-05 Co-58 --- 8.71E-07 1.30E-06 --- --- 5.55E-04 7.95E-06 Co-60 --- 5.73E-06 8.41E-06 --- --- 3.22E-03 2.28E-05 Ni-59 1.81E-05 5.44E-06 3.10E-06 --- --- 5.48E-05 6.34E-07 Ni-63 2.42E-04 1.46E-05 8.29E-06 --- --- 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 --- --- 5.80E-06 3.58E-05 Cu-64 --- 1.34E-09 5.53E-10 --- 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 --- 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 --- 2.87E-11 1.05E-06 9.44E-06 Br-83 --- --- 2.72E-07 --- --- --- ---
Br-84 --- --- 2.86E-07 --- --- --- ---
Br-85 --- --- 1.46E-08 --- --- --- ---
Rb-86 --- 1.36E-04 6.30E-05 --- --- --- 2.17E-06 Rb-88 --- 3.98E-07 2.05E-07 --- --- --- 2.42E-07 Rb-89 --- 2.29E-07 1.47E-07 --- --- --- 4.87E-08 Sr-89 2.84E-04 --- 8.15E-06 --- --- 1.45E-03 4.57E-05 Sr-90 1.11E-02 --- 2.23E-04 --- --- 8.03E-03 9.36E-05 Sr-91 6.83E-08 --- 2.47E-09 --- --- 3.76E-05 5.24E-05 Sr-92 7.50E-09 --- 2.79E-10 --- --- 1.70E-05 1.00E-04 Y-90 2.35E-06 --- 6.30E-08 --- --- 1.92E-04 7.43E-05 Y-91M 2.91E-10 --- 9.90E-12 --- --- 1.99E-06 1.68E-06 Y-91 4.20E-04 --- 1.12E-05 --- --- 1.75E-03 5.02E-05 Y-92 1.17E-08 --- 3.29E-10 --- --- 1.75E-05 9.04E-05 Y-93 1.07E-07 --- 2.91E-09 --- --- 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 --- 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 --- 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 --- 3.37E-06 3.42E-04 9.05E-06 Mo-99 --- 1.18E-07 2.31E-08 --- 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-11 --- 2.22E-11 5.79E-07 1.45E-06
CH-ODCM-0001 Reference Use Page 120 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 4.65E-14 5.88E-14 5.80E-13 --- 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 --- 4.85E-07 --- 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 --- 2.93E-10 --- 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 --- 7.77E-06 --- 7.61E-05 8.26E-03 1.17E-04 Ag-110M 7.13E-06 5.16E-06 3.57E-06 --- 7.80E-06 2.62E-03 2.36E-05 Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 --- 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 --- 1.17E-03 1.05E-05 Te-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 --- 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 --- 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 --- 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 --- 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 --- 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 --- 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 --- 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 --- 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 --- 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 --- 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 --- 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 --- 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 --- 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 --- 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 --- 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 --- --- 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 --- --- 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 --- 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 --- 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 --- 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 --- 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 --- 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 --- 2.25E-06 2.30E-04 2.23E-05
CH-ODCM-0001 Reference Use Page 121 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 9.26E-09 6.44E-09 2.23E-09 --- --- 2.83E-05 2.54E-05 Pu-238 2.69E+00 1.68E+00 1.27E-01 --- 4.64E-01 9.03E-01 4.69E-05 Pu-239 2.93E+00 1.76E+00 1.34E-01 --- 4.95E-01 8.47E-01 4.28E-05 Pu-240 2.93E+00 1.75E+00 1.34E-01 --- 4.94E-01 8.47E-01 4.36E-05 Pu-241 8.43E-02 1.85E-02 3.11E-03 --- 1.15E-02 7.62E-04 8.97E-07 Np-239 2.65E-07 2.13E-07 1.34E-08 --- 4.73E-08 4.25E-05 1.78E-05 Am-241 3.15E+00 1.95E+00 1.31E-01 --- 7.94E-01 4.06E-01 4.78E-05 Cm-242 1.28E-01 8.65E-02 5.70E-03 --- 1.69E-02 2.97E-01 5.10E-05 Cm-243 2.47E+00 1.52E+00 1.06E-01 --- 3.91E-01 4.24E-01 5.02E-05 CM-244 2.07E+00 1.27E+00 8.89E-02 --- 3.21E-01 4.08E-01 4.86E-05
CH-ODCM-0001 Reference Use Page 122 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 --- --- --- 2.17E-05 Cr-51 --- --- 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 --- 4.57E-06 8.72E-07 --- 1.36E-06 --- 1.40E-05 Mn-56 --- 1.15E-07 2.04E-08 --- 1.46E-07 --- 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 --- --- 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 --- --- 2.85E-06 3.40E-05 Co-58 --- 7.45E-07 1.67E-06 --- --- --- 1.51E-05 Co-60 --- 2.14E-06 4.72E-06 --- --- --- 4.02E-05 Ni-59 9.76E-06 3.35E-06 1.63E-06 --- --- --- 6.90E-07 Ni-63 1.30E-04 9.01E-06 4.36E-06 --- --- --- 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 --- --- --- 1.74E-06 Cu-64 --- 8.33E-08 3.91E-08 --- 2.10E-07 --- 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 --- 1.03E-05 --- 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 --- 1.28E-08 --- 2.96E-09 Br-83 --- --- 4.02E-08 --- --- --- 5.79E-08 Br-84 --- --- 5.21E-08 --- --- --- 4.09E-13 Br-85 --- --- 2.14E-09 --- --- --- ---
Rb-86 --- 2.11E-05 9.83E-06 --- --- --- 4.16E-06 Rb-88 --- 6.05E-08 3.21E-08 --- --- --- 8.36E-19 Rb-89 --- 4.01E-08 2.82E-08 --- --- --- 2.33E-21 Sr-89 3.08E-04 --- 8.84E-06 --- --- --- 4.94E-05 Sr-90 8.71E-03 --- 1.75E-04 --- --- --- 2.19E-04 Sr-91 5.67E-06 --- 2.29E-07 --- --- --- 2.70E-05 Sr-92 2.15E-06 --- 9.30E-08 --- --- --- 4.26E-05 Y-90 9.62E-09 --- 2.58E-10 --- --- --- 1.02E-04 Y-91M 9.09E-11 --- 3.52E-12 --- --- --- 2.67E-10 Y-91 1.41E-07 --- 3.77E-09 --- --- --- 7.76E-05 Y-92 8.45E-10 --- 2.47E-11 --- --- --- 1.48E-05 Y-93 2.68E-09 --- 7.40E-11 --- --- --- 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 --- 1.53E-08 --- 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 --- 5.12E-10 --- 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 --- 3.42E-09 --- 2.10E-05 Mo-99 --- 4.31E-06 8.20E-07 --- 9.76E-06 --- 9.99E-06 Tc-99M 2.47E-10 6.98E-10 8.89E-09 --- 1.06E-08 3.42E-10 4.13E-07
CH-ODCM-0001 Reference Use Page 123 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.54E-10 3.66E-10 3.59E-09 --- 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 --- 7.97E-08 --- 7.06E-07 --- 2.16E-05 Ru-105 1.54E-08 --- 6.08E-09 --- 1.99E-07 --- 9.42E-06 Ru-106 2.75E-06 --- 3.48E-07 --- 5.31E-06 --- 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 --- 2.91E-07 --- 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 --- 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 --- 1.38E-06 1.97E-05 Te-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 --- 1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 --- 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 --- 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 --- 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 --- 2.37E-08 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 --- 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 --- 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 --- 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 --- 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 --- 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 --- 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 --- 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 --- 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 --- 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 --- 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 --- 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 --- 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 --- 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 --- 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 --- 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 --- 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 --- 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 --- --- --- 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 --- --- --- 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 --- 2.94E-09 --- 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 --- 5.37E-10 --- 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 --- 1.21E-07 --- 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 --- 2.13E-09 --- 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 --- 7.05E-12 --- 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 --- 4.25E-09 --- 3.49E-05
CH-ODCM-0001 Reference Use Page 124 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.03E-07 8.61E-08 3.01E-08 --- --- --- 2.82E-05 Pu-238 6.30E-04 7.98E-05 1.71E-05 --- 7.32E-05 --- 7.30E-05 Pu-239 7.25E-04 8.71E-05 1.91E-05 --- 8.11E-05 --- 6.66E-05 Pu-240 7.24E-04 8.70E-05 1.91E-05 --- 8.10E-05 --- 6.78E-05 Pu-241 1.57E-05 7.45E-07 3.32E-07 --- 1.53E-06 --- 1.40E-06 Np-239 1.19E-09 1.17E-10 6.45E-11 --- 3.65E-10 --- 2.40E-05 Am-241 7.55E-04 7.05E-04 5.41E-05 --- 4.07E-04 --- 7.42E-05 Cm-242 2.06E-05 2.19E-05 1.37E-06 --- 6.22E-06 --- 7.92E-05 Cm-243 5.99E-04 5.49E-04 3.75E-05 --- 1.75E-04 --- 7.81E-05 Cm-244 4.56E-04 4.27E-04 2.87E-05 --- 1.34E-04 --- 7.55E-05
CH-ODCM-0001 Reference Use Page 125 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 -- 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 --- --- --- 2.32E-05 Cr-51 --- --- 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 --- 5.90E-06 1.17E-06 --- 1.76E-06 --- 1.21E-05 Mn-56 --- 1.58E-07 2.81E-08 --- 2.00E-07 --- 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 --- --- 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 --- --- 4.32E-06 3.24E-05 Co-58 --- 9.72E-07 2.24E-06 --- --- --- 1.34E-05 Co-60 --- 2.81E-06 6.33E-06 --- --- --- 3.66E-05 Ni-59 1.32E-05 4.66E-06 2.24E-06 --- --- --- 7.31E-07 Ni-63 1.77E-04 1.25E-05 6.00E-06 --- --- --- 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 --- --- --- 5.19E-06 Cu-64 --- 1.15E-07 5.41E-08 --- 2.91E-07 --- 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 --- 1.28E-05 --- 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 --- 1.83E-08 --- 5.16E-08 Br-83 --- --- 5.74E-08 --- --- --- ---
Br-84 --- --- 7.22E-08 --- --- --- ---
Br-85 --- --- 3.05E-09 --- --- --- ---
Rb-86 --- 2.98E-05 1.40E-05 --- --- --- 4.41E-06 Rb-88 --- 8.52E-08 4.54E-08 --- --- --- 7.30E-15 Rb-89 --- 5.50E-08 3.89E-08 --- --- --- 8.43E-17 Sr-89 4.40E-04 --- 1.26E-05 --- --- --- 5.24E-05 Sr-90 1.02E-02 --- 2.04E-04 --- --- --- 2.33E-04 Sr-91 8.07E-06 --- 3.21E-07 --- --- --- 3.66E-05 Sr-92 3.05E-06 --- 1.30E-07 --- --- --- 7.77E-05 Y-90 1.37E-08 --- 3.69E-10 --- --- --- 1.13E-04 Y-91M 1.29E-10 --- 4.93E-12 --- --- --- 6.09E-09 Y-91 2.01E-07 --- 5.39E-09 --- --- --- 8.24E-05 Y-92 1.21E-09 --- 3.50E-11 --- --- --- 3.32E-05 Y-93 3.83E-09 --- 1.05E-10 --- --- --- 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 --- 1.91E-08 --- 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 --- 7.11E-10 --- 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 --- 4.42E-09 --- 1.95E-05 Mo-99 --- 6.03E-06 1.15E-06 --- 1.38E-05 --- 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 --- 1.38E-08 5.14E-10 6.08E-07
CH-ODCM-0001 Reference Use Page 126 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 3.60E-10 5.12E-10 5.03E-09 --- 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 --- 1.09E-07 --- 8.99E-07 --- 2.13E-05 Ru-105 2.18E-08 --- 8.46E-09 --- 2.75E-07 --- 1.76E-05 Ru-106 3.92E-06 --- 4.94E-07 --- 7.56E-06 --- 1.88E-04 Ag-110M 2.05E-07 1.94E-07 1.18E-07 --- 3.70E-07 --- 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 --- 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 --- 2.18E-06 1.93E-05 Te-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 --- --- 1.13E-05 Te-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 --- 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 --- 1.22E-05 Te-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 --- 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 --- 2.45E-07 Te-131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 --- 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 --- 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 --- 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 --- 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 --- 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 --- 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 --- 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 --- 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 --- 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 --- 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 --- 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 --- 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 --- 1.10E-07 1.28E-08 4.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 --- 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 --- 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 --- 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 --- 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 --- --- --- 9.28E-05 La-142 1.79E-10 7.95E-11 1.98E-11 --- --- --- 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 --- 4.18E-09 --- 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 --- 7.67E-10 --- 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 --- 1.72E-07 --- 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 --- 3.04E-09 --- 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 --- 1.01E-11 --- 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 --- 5.99E-09 --- 3.68E-05
CH-ODCM-0001 Reference Use Page 127 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.46E-07 1.19E-07 4.17E-08 --- --- --- 3.22E-05 Pu-238 6.70E-04 8.58E-05 1.82E-05 --- 7.80E-05 --- 7.73E-05 Pu-239 7.65E-04 9.29E-05 2.01E-05 --- 8.57E-05 --- 7.06E-05 Pu-240 7.64E-04 9.27E-05 2.01E-05 --- 8.56E-05 --- 7.19E-05 Pu-241 1.75E-05 8.40E-07 3.69E-07 --- 1.71E-06 --- 1.48E-06 Np-239 1.76E-09 1.66E-10 9.22E-11 --- 5.21E-10 --- 2.67E-05 Am-241 7.98E-04 7.53E-04 5.75E-05 --- 4.31E-04 --- 7.87E-05 Cm-242 2.94E-05 3.10E-05 1.95E-06 --- 8.89E-06 --- 8.40E-05 Cm-243 6.50E-04 6.03E-04 4.09E-05 --- 1.91E-04 --- 8.28E-05 Cm-244 5.04E-04 4.77E-04 3.19E-05 --- 1.49E-04 --- 8.00E-05
CH-ODCM-0001 Reference Use Page 128 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 --- --- --- 2.28E-05 Cr-51 --- --- 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 --- 1.07E-05 2.85E-06 --- 3.00E-06 --- 8.98E-06 Mn-56 --- 3.34E-07 7.54E-08 --- 4.04E-07 --- 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 --- --- 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 --- --- 7.74E-06 2.78E-05 Co-58 --- 1.80E-06 5.51E-06 --- --- --- 1.05E-05 Co-60 --- 5.29E-06 1.56E-05 --- --- --- 2.93E-05 Ni-59 4.02E-05 1.07E-05 6.82E-06 --- --- --- 7.10E-07 Ni-63 5.38E-04 2.88E-05 1.83E-05 --- --- --- 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 --- --- --- 2.56E-05 Cu-64 --- 2.45E-07 1.48E-07 --- 5.92E-07 --- 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 --- 2.30E-05 --- 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 --- 3.84E-08 --- 3.99E-06 Br-83 --- --- 1.71E-07 --- --- --- ---
Br-84 --- --- 1.98E-07 --- --- --- ---
Br-85 --- --- 9.12E-09 --- --- --- ---
Rb-86 --- 6.70E-05 4.12E-05 --- --- --- 4.31E-06 Rb-88 --- 1.90E-07 1.32E-07 --- --- --- 9.32E-09 Rb-89 --- 1.17E-07 1.04E-07 --- --- --- 1.02E-09 Sr-89 1.32E-03 --- 3.77E-05 --- --- --- 5.11E-05 Sr-90 2.56E-02 --- 5.15E-04 --- --- --- 2.29E-04 Sr-91 2.40E-05 --- 9.06E-07 --- --- --- 5.30E-05 Sr-92 9.03E-06 --- 3.62E-07 --- --- --- 1.71E-04 Y-90 4.11E-08 --- 1.10E-09 --- --- --- 1.17E-04 Y-91M 3.82E-10 --- 1.39E-11 --- --- --- 7.48E-07 Y-91 6.02E-07 --- 1.61E-08 --- --- --- 8.02E-05 Y-92 3.60E-09 --- 1.03E-10 --- --- --- 1.04E-04 Y-93 1.14E-08 --- 3.13E-10 --- --- --- 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 --- 3.65E-08 --- 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 --- 1.45E-09 --- 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 --- 8.23E-09 --- 1.62E-05 Mo-99 --- 1.33E-05 3.29E-06 --- 2.84E-05 --- 1.10E-05 Tc-99M 9.23E-10 1.81E-09 3.00E-08 --- 2.63E-08 9.19E-10 1.03E-06
CH-ODCM-0001 Reference Use Page 129 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 1.07E-09 1.12E-09 1.42E-08 --- 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 --- 2.81E-07 --- 1.84E-06 --- 1.89E-05 Ru-105 6.45E-08 --- 2.34E-08 --- 5.67E-07 --- 4.21E-05 Ru-106 1.17E-05 --- 1.46E-06 --- 1.58E-05 --- 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91E-07 --- 6.78E-07 --- 4.33E-05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 --- 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 --- 3.99E-06 1.71E-05 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 --- --- 1.10E-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 --- 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 --- 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 --- 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 --- 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 --- 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 --- 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 --- 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 --- 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 --- 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 --- 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 --- 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 --- 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 --- 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 --- 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 --- 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 --- 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 --- 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 --- 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 --- 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 --- 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 --- 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 --- --- --- 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 --- --- --- 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 --- 8.68E-09 --- 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 --- 1.59E-09 --- 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 --- 3.61E-07 --- 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 --- 6.39E-09 --- 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 --- 2.11E-11 --- 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 --- 1.24E-08 --- 3.58E-05
CH-ODCM-0001 Reference Use Page 130 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 4.29E-07 2.54E-07 1.14E-07 --- --- --- 3.57E-05 Pu-238 1.19E-03 1.38E-04 3.16E-05 --- 1.15E-04 --- 7.50E-05 Pu-239 1.29E-03 1.38E-04 3.31E-05 --- 1.22E-04 --- 6.85E-05 Pu-240 1.28E-03 1.43E-04 3.31E-05 --- 1.22E-04 --- 6.98E-05 Pu-241 3.87E-05 1.58E-06 8.04E-07 --- 2.96E-06 --- 1.44E-06 Np-239 5.25E-09 3.77E-10 2.65E-10 --- 1.09E-09 --- 2.79E-05 Am-241 1.36E-03 1.17E-03 1.02E-04 --- 6.23E-04 --- 7.64E-05 Cm-242 8.78E-05 7.01E-05 5.84E-06 --- 1.87E-05 --- 8.16E-05 Cm-243 1.28E-03 1.04E-03 8.24E-05 --- 3.08E-04 --- 8.03E-05 Cm-244 1.08E-03 8.74E-04 6.93E-05 --- 2.54E-04 --- 7.77E-05
CH-ODCM-0001 Reference Use Page 131 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 --- --- --- 2.30E-05 Cr-51 --- --- 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 --- 1.99E-05 4.51E-06 --- 4.41E-06 --- 7.31E-06 Mn-56 --- 8.18E-07 1.41E-07 --- 7.03E-07 --- 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 --- --- 4.36E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 --- --- 1.59E-05 2.57E-05 Co-58 --- 3.60E-06 8.98E-06 --- --- --- 8.97E-06 Co-60 --- 1.08E-05 2.55E-05 --- --- --- 2.57E-05 Ni-59 4.73E-05 1.45E-05 8.17E-06 --- --- --- 7.16E-07 Ni-63 6.34E-04 3.92E-05 2.20E-05 --- --- --- 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 --- --- --- 4.05E-05 Cu-64 --- 6.09E-07 2.82E-07 --- 1.03E-06 --- 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 --- 3.06E-05 --- 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 --- 6.98E-08 --- 1.37E-05 Br-83 --- --- 3.63E-07 --- --- --- ---
Br-84 --- --- 3.82E-07 --- --- --- ---
Br-85 --- --- 1.94E-08 --- --- --- ---
Rb-86 --- 1.70E-04 8.40E-05 --- --- --- 4.35E-06 Rb-88 --- 4.98E-07 2.73E-07 --- --- --- 4.85E-07 Rb-89 --- 2.86E-07 1.97E-07 --- --- --- 9.74E-08 Sr-89 2.51E-03 --- 7.20E-05 --- --- --- 5.16E-05 Sr-90 2.83E-02 --- 5.74E-04 --- --- --- 2.31E-04 Sr-91 5.00E-05 --- 1.81E-06 --- --- --- 5.92E-05 Sr-92 1.92E-05 --- 7.13E-07 --- --- --- 2.07E-04 Y-90 8.69E-08 --- 2.33E-09 --- --- --- 1.20E-04 Y-91M 8.10E-10 --- 2.76E-11 --- --- --- 2.70E-06 Y-91 1.13E-06 --- 3.01E-08 --- --- --- 8.10E-05 Y-92 7.65E-09 --- 2.15E-10 --- --- --- 1.46E-04 Y-93 2.43E-08 --- 6.62E-10 --- --- --- 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 --- 5.41E-08 --- 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 --- 2.56E-09 --- 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 --- 1.24E-08 --- 1.46E-05 Mo-99 --- 3.40E-05 6.63E-06 --- 5.08E-05 --- 1.12E-05 Tc-99M 1.92E-09 3.96E-09 5.10E-08 --- 4.26E-08 2.07E-09 1.15E-06
CH-ODCM-0001 Reference Use Page 132 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.27E-09 2.86E-09 2.83E-08 --- 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 --- 4.95E-07 --- 3.08E-06 --- 1.80E-05 Ru-105 1.36E-07 --- 4.58E-08 --- 1.00E-06 --- 5.41E-05 Ru-106 2.41E-05 --- 3.01E-06 --- 2.85E-05 --- 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81E-07 --- 1.04E-06 --- 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 --- 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 --- 7.12E-06 1.64E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 --- --- 1.11E-05 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 --- 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 --- 2.10E-05 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 --- 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 --- 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 --- 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 --- 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 --- 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 --- 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 --- 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 --- 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 --- 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 --- 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 --- 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 --- 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 --- 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 --- 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 --- 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 --- 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 --- 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 --- 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 --- 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 --- --- --- 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 --- --- --- 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 --- 1.48E-08 --- 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 --- 2.86E-09 --- 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 --- 4.93E-07 --- 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 --- 1.13E-08 --- 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 --- 3.84E-11 --- 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 --- 2.19E-08 --- 3.60E-05
CH-ODCM-0001 Reference Use Page 133 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 9.03E-07 6.28E-07 2.17E-07 --- --- --- 3.69E-05 Pu-238 1.28E-03 1.50E-04 3.40E-05 --- 1.21E-04 --- 7.57E-05 Pu-239 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 6.91E-05 Pu-240 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 7.04E-05 Pu-241 4.25E-05 1.76E-06 8.82E-07 --- 3.17E-06 --- 1.45E-06 Np-239 1.11E-08 9.93E-10 5.61E-10 --- 1.98E-09 --- 2.87E-05 Am-241 1.46E-03 1.27E-03 1.09E-04 --- 6.55E-04 --- 7.70E-05 Cm-242 1.37E-04 1.27E-04 9.10E-06 --- 2.62E-05 --- 8.23E-05 Cm-243 1.40E-03 1.15E-03 8.98E-05 --- 3.27E-04 --- 8.10E-05 Cm-244 1.18E-03 9.70E-04 7.59E-05 --- 2.71E-04 --- 7.84E-05
CH-ODCM-0001 Reference Use Page 134 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol fg Fraction of ingested produce grown in garden 0.76 of interest.
f Fraction of leafy vegetables grown in garden of 1.0 interest.
P Effective surface density of soil (assumes a 240 kg/m2 15 cm plow layer, expressed in dry weight) r Fraction of deposited activity retained on crops, 0.25 leafy vegetables, or pasture grass 1.0 (iodines) 0.2 (other particulates)
Sf Attenuation factor accounting for shielding 0.7 (maximum individual) provided by residential structures 0.5 (general population) tb Period of long-term buildup for activity in 1.752E5 hr sediment or soil (20 years) te Period of crop, leafy vegetable, or pasture 30 days (grass-cow-milk-man grass exposure during growing season pathway) 60 days (crop/vegetation-man pathway) tf Transport time from animal feed-milk-man 2 days (maximum individual) provided by residential structures 4 days (general population) th Time delay between harvest of vegetation or crops and ingestion:
For ingestion of forage by animals Zero (pasture grass) 90 days (stored feed)
For ingestion of crops by man 1 day (leafy vegetables and max. individual feed) 60 days (produce and max.
individual) 14 days (general population) fs The fraction of daily feed that is pasture grass 1.0 while the animals graze on pasture.
Mp The mixing ratio at the point of withdrawal of Site Discharge 7.14 drinking water. M.U.D. Intake 30.8 fp Fraction of the year that animals graze on 0.5 pasture.
CH-ODCM-0001 Reference Use Page 135 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol tp Environmental transit time, release to receptor 12 hrs. (maximum)
(add time from release to exposure individual 1 day (maximum individual) point to minimums shown for distribution) 1 day (general population) 7 days (population--sport fish doses) 10 days (population--
commercial fish doses) ts Average time from slaughter of meat animal to 20 days consumption Yv Agricultural productivity by unit area (measured 0.7 kg/m2 (grass-cow-milk-man in wet weight) pathway) 2.0 kg/m2 (produce or leafy vegetable ingested by man)
W Shore-width factor for river shoreline 0.2 w Rate constant for removal of activity on plant or 0.0021 hr-1 leaf structures by weathering (corresponds to a 14-day half-life)
%CO2 Fraction of C-14 used for organ dose 0.15 calculations from gaseous releases.
CH-ODCM-0001 Reference Use Page 136 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 30 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure NOTE i The Dose Estimates are based on normal public activities conducted within the Fort Calhoun Station Site Boundary.
i Estimated Individual Dose Estimated Total Combined Distance Rate (mR/hour) Annual Dose (mRem)B from Direct Inhalation Direct Inhalation Containment Exposure (Critical Exposure (Critical Location Direction (miles) (Total Body) OrganA) (Total Body) OrganA)
Firing Range 200° 0.24 4.08E-05 9.67E-06 5.08E+00 1.20E+00 Burn Pad 241° 0.33 1.95E-05 4.63E-06 1.41E-01 3.34E-02 On-Site Farming 118° 0.52 2.12E-05 5.03E-06 2.38E-02 5.64E-03 On-Site Farming 200° 0.51 1.03E-05 2.45E-06 2.30E-02 5.50E-03 On-Site Farming 308° 0.50 2.77E-05 6.64E-06 4.66E-02 1.12E-02 Site Maintenance Admin Bldg 145° 0.20 1.18E-04 2.84E-05 5.50E-02 1.33E-02 Site Maintenance Training Center 180° 0.20 1.45E-04 3.50E-05 6.78E-02 1.64E-02 A. Critical organ doses are based on adult thyroid.
B. Estimated totals are based on summation of all individual doses for members of the General Public while within the Fort Calhoun Station site boundary.
Page 1 of 136 CH-ODCM-0001 Off-Site Dose Calculation Manual (ODCM)
Revision 31 Safety Classification: Usage Level:
Non-Safety Reference Change No.: EC 70234 Reason for Change: Revise Goat milk location Preparer: J. Hoffman Fort Calhoun Station
CH-ODCM-0001 Reference Use Page 2 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table of Contents PART I 1.0 PURPOSE AND SCOPE ................................................................................................. 6 1.1 Purpose ..................................................................................................................... 6 1.2 Scope ........................................................................................................................ 6 2.0 DEFINITIONS .................................................................................................................. 6 3.0 INSTRUMENTATION .................................................................................................... 10 3.1 Radioactive Liquid Effluent Instrumentation ............................................................ 10 3.2 Radioactive Gaseous Effluent Instrumentation ....................................................... 13 4.0 RADIOACTIVE EFFLUENTS ........................................................................................ 17 4.1 Radioactive Liquid Effluents .................................................................................... 17 4.2 Radioactive Gaseous Effluents ............................................................................... 23 4.3 Uranium Fuel Cycle ................................................................................................. 29 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) .................. 30 5.1 Monitoring Program ................................................................................................. 30 5.2 Land Use Survey ..................................................................................................... 45 5.3 Interlaboratory Comparison Program ...................................................................... 46 6.0 ADMINISTRATIVE CONTROLS.................................................................................... 47 6.1 Responsibilities ....................................................................................................... 47 6.2 Radioactive Effluent Reporting Requirements ......................................................... 47 6.3 Change Mechanism ................................................................................................ 52 6.4 Meteorological Data ................................................................................................ 52 6.5 References .............................................................................................................. 53 7.0 BASIS ............................................................................................................................ 55 7.1 Instrumentation ....................................................................................................... 55 7.2 Radioactive Effluents............................................................................................... 55 7.3 Radiological Environmental Monitoring ................................................................... 62 7.4 Abnormal Release or Abnormal Discharge Reporting ............................................. 63
CH-ODCM-0001 Reference Use Page 3 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 List of Tables PART I Table 1.2 - Frequency Notation ............................................................................................... 8 Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation .. 9 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation .................................... 11 Table 3.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ....................................................................................................... 12 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation ............................... 14 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .................................................................................. 16 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis ............................................. 19 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis ......................................... 24 Table 4.3 - Sampler Deposition/Transportation Correction Factors ....................................... 25 Table 5.1 - Radiological Environmental Monitoring Program ................................................. 32 Table 5.2 - Radiological Environmental Sampling Locations And Media ............................... 35 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ................................................................................................... 43 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples ...................................................................................... 44 List of Figures PART I Figure 1 - Environmental Radiological Sampling Points ....................................................... 41 Figure 2 - 40CFR190 Sampling Points ................................................................................. 42
CH-ODCM-0001 Reference Use Page 4 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table of Contents PART II 1.0 EFFLUENT MONITOR SETPOINTS ............................................................................. 66 1.1 Liquid Effluents ........................................................................................................ 66 1.2 Airborne Effluents .................................................................................................... 69 2.0 EFFLUENT CONCENTRATIONS ................................................................................. 80 2.1 Liquid Effluent Concentrations ................................................................................ 80 2.2 Airborne Effluent Concentrations ............................................................................ 80 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS ................................................... 82 3.1 Liquid Effluent Dose Calculations ............................................................................ 82 3.2 Airborne Effluent Dose Calculations ........................................................................ 86 4.0 LOWER LIMIT OF DETECTION (LLD) ....................................................................... 101
CH-ODCM-0001 Reference Use Page 5 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 List of Tables PART II Table 1 - Allocation Factors for Simultaneous Releases ....................................................... 74 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases ................... 102 Table 3 - Bioaccumulation Factors ...................................................................................... 103 Table 4 - Highest Potential Exposure Pathways for Estimating Dose .................................. 104 Table 5 - Stable Element Transfer Data .............................................................................. 105 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data................................................................. 106 Table 7 - Animal Consumption Rates .................................................................................. 106 Table 8 - External Dose Factors for Standing on Contaminated Ground ............................. 107 Table 9 - Inhalation Dose Factors for Adult ......................................................................... 110 Table 10 - Inhalation Dose Factors for Teenager ................................................................ 113 Table 11 - Inhalation Dose Factors for Child ....................................................................... 116 Table 12 - Inhalation Dose Factors for Infant ...................................................................... 119 Table 13 - Ingestion Dose Factors for Adult ........................................................................ 122 Table 14 - Ingestion Dose Factors for Teenager ................................................................. 125 Table 15 - Ingestion Dose Factors for Child ........................................................................ 128 Table 16 - Ingestion Dose Factors for Infant ....................................................................... 131 Table 17 - Recommended Values for Other Parameters ..................................................... 134 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure ........ 136 List of Figures PART II Figure 1 - Exclusion and Site Boundary Map ........................................................................ 75 Figure 2 - Liquid Radioactive Discharge Pathways ............................................................... 76 Figure 3 - Liquid Radioactive Waste Disposal System .......................................................... 77 Figure 4 - Airborne Effluent Discharge Pathways .................................................................. 78 Figure 5 - Airborne Radioactive Waste Disposal System ...................................................... 79
CH-ODCM-0001 Reference Use Page 6 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.0 PURPOSE AND SCOPE 1.1 Purpose 1.1.1 Contains methodologies for and parameters necessary for calculating offsite doses, determination of gaseous and liquid radiation monitor set points, and administrative controls for effluent instrumentation, Radiological Effluent Tech Specs (RETS), and the Radiological Environmental Monitoring Program (REMP).
1.2 Scope 1.2.1 Radioactive effluents are generated from station activities. These controls provide methodologies ensuring these effluents are properly monitored and quantified to promote accurate dose reporting. Additional controls ensure station equipment and processes are used to minimize release to the environment. The combination of minimizing release, accurately reporting dose, and monitoring the facility environs provides the basis for ensuring that station activities are not negatively impacting public health and the environment.
2.0 DEFINITIONS 2.1 Abnormal Discharge - The unplanned or uncontrolled emission of an effluent (i.e.,
containing facility-related, licensed radioactive material) into the unrestricted area.
2.2 Abnormal Release - The unplanned or uncontrolled emission of an effluent (i.e.,
containing facility-related, licensed radioactive material).
2.3 Channel Check - A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
2.4 Channel Function Test - Injection of a simulated signal into the channel to verify that it is functional, including any alarm and/or trip initiating action.
2.5 Effluent Concentration Limit (ECL) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 1.
2.6 Member(s) of the Public - Member(s) of the Public means any individual except when that individual is receiving occupational dose.
CH-ODCM-0001 Reference Use Page 7 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 2.7 Functional-Functionality - A system, subsystem, train, component or device shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power sources, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
2.8 Residual Radioactivity - Residual radioactivity means radioactivity in structures, materials, soils, ground water, and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee, but it excludes background radiation. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site, even if those burials were made in accordance with the provisions of 10 CFR Part 20.
2.9 Site Boundary - The Site Boundary is the line beyond which the land is neither owned, or leased, nor controlled by the licensee.
2.10 Source Check - A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
2.11 Special Liquid - Non-routine release pathway in which normally non-radioactive liquid streams (such as Raw Water) found to contain radioactive material, are non-routine, and will be treated on a case specific basis if and when this occurs.
2.12 Unrestricted Area - An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
2.13 Venting - VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
2.14 Water Effluent Concentration (WEC) - Radionuclide limits listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.
CH-ODCM-0001 Reference Use Page 8 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 1.2 - Frequency Notation The surveillance intervals are defined as follows:
Notation Title FrequencyA S Shift At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W Weekly At least once per 7 days BW Biweekly At least once per 14 days M Monthly At least once per 31 days Q Quarterly At least once per 92 days SA Semiannual At least once per 184 days A Annually At least once per 366 days R At least once per 18 months P Prior to Prior to each release (Performance within 24 hrs.)
A. Each surveillance requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
CH-ODCM-0001 Reference Use Page 9 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 1.3 - Radiological Effluent Controls Program Technical Specification Implementation Technical Specification ODCM Implementing Step 5.16.1.a 3.1.1, 3.2.1 5.16.1.b 4.1.1 5.16.1.c Table 4.1, Table 4.2 5.16.1.d 4.1.2 5.16.1.e 4.1.2B.1, 4.2.2B.1 5.16.1.f 4.1.3A, 4.2.4A 5.16.1.g 4.2.1 5.16.1.h 4.2.2 5.16.1.i 4.2.3 5.16.1.j 4.3.1 5.16.2.a 5.1.1 5.16.2.b 5.2.1 5.16.2.c 5.3.1 5.17 6.3, 6.2.1D
CH-ODCM-0001 Reference Use Page 10 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.0 INSTRUMENTATION 3.1 Radioactive Liquid Effluent Instrumentation 3.1.1 Limiting Condition for Operation A. The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.1.1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 3.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Part II of the Off-Site Dose Calculation Manual.
APPLICABILITY: At all times ACTION:
- 1. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive liquid effluents monitored by the affected channel or declare the channel non-functional.
- 2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels functional, take the action shown in Table 3.1.1. Restore non-functional effluent monitoring instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this non-functionality was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent stream: RM-055.
3.1.2 Surveillance Requirements A. Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.1.2.
CH-ODCM-0001 Reference Use Page 11 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 3.1.1 - Radioactive Liquid Effluent Monitoring Instrumentation Minimum Channels Instrument Functional Action
- 1. Radioactivity Monitor Providing Alarm and Automatic Termination of Release.
1.1 Liquid Radwaste Effluent Line (RM-055) 1 1, 4
- 2. Flow Rate Measurement Device 2.1 Liquid Radwaste Effluent Line 1 2
- 3. Radioactivity Recorder 3.1 Liquid Radwaste Effluent Line 1 3 Table Notation ACTION 1 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided that prior to initiating a release:
- 1. At least two independent samples are analyzed in accordance with applicable chemistry procedures.
- 2. At least two qualified individuals independently verify the release rate calculations.
ACTION 2 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the flow rate is determined at least once per four hours during the actual release.
ACTION 3 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the radioactivity is recorded manually at least once per four hours during the actual release.
ACTION 4 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered non-functional. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. If the effluent radiation monitor fails the source check, carryout the action(s) of the Off-Site Dose Calculation Manual for the non-functional monitor or terminate the effluent release.
CH-ODCM-0001 Reference Use Page 12 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 3.1.2 - Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Function Check Calibration Check Test
- 1. Radioactivity Monitor Providing Alarm and Automatic Isolation 1.1 RM-055 ---- R Q P
CH-ODCM-0001 Reference Use Page 13 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2 Radioactive Gaseous Effluent Instrumentation 3.2.1 Limiting Condition for Operation A. The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.2.1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the limits of Specification 3.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Part II of the Off-Site Dose Calculation Manual.
APPLICABILITY: At all times ACTION:
- 1. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the releases of radioactive gaseous effluents monitored by the affected channel or declare the channel non-functional.
- 2. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels functional, take the action shown in Table 3.2.1. Restore non-functional effluent monitoring instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Annual Radiological Effluent Release Report why this non-functionality was not corrected in a timely manner. The reporting requirement is limited to the following instrumentation that monitors effluent streams: RM-043, RM-062, and RM-052.
3.2.2 Surveillance Requirements A. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.2.2.
CH-ODCM-0001 Reference Use Page 14 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 3.2.1 - Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Channels Action Functional
- 1. Auxiliary Bldg. Exhaust Stack (RM-052, RM-062) 1.1 Noble Gas 1 1, 7, 8 1.2 Particulate 1 2, 7, 8
- 2. Laboratory and Radwaste Processing Building Stack (RM-043) 2.1 Noble Gas 1 3, 7 2.2 Particulate 1 4, 7
- 3. Flow Rate Measurement Devices 3.1 Auxiliary Building Exhaust Stack 1 5 3.2 Laboratory and Radwaste Processing Building Stack 1 5
- 4. Radioactivity Chart Recorders 4.1 Auxiliary Building Exhaust Stack 1 6
CH-ODCM-0001 Reference Use Page 15 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 3.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation Table Notation ACTION 1 If the Auxiliary Building Exhaust Stack Noble Gas Monitor is non-functional, ventilation of the auxiliary building via the Auxiliary Building Exhaust Stack may continue provided grab samples are taken once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (See Table 4.2)
ACTION 2 If the Auxiliary Building Exhaust Stack Particulate Sampler is non-functional, ventilation of the Auxiliary Building may continue through the Auxiliary Building Exhaust Stack provided sample collection in accordance with Table 4.2 using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the declaration of non-functionality by the Shift Manager.
ACTION 3 If the Noble Gas Monitor is non-functional, ventilation of the LRWPB may continue via the LRWPB stack provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (See Table 4.2)
ACTION 4 If the Particulate Sampler is non-functional, ventilation of the LRWPB may continue via the LRWPB Stack provided sample collection using auxiliary sample collection equipment is initiated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the declaration of non-functionality, by the Shift Manager, in accordance with Table 4.2.
ACTION 5 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the flowrate is estimated or recorded manually at least once per four hours during the actual release.
ACTION 6 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases may continue provided the radioactivity level is recorded manually at least once per four hours during the actual release.
ACTION 7 During the performance of source checks the effluent radiation monitor is unable to respond, hence is considered non-functional. Effluent releases may continue uninterrupted during the performance of source checks provided the operator is stationed at the monitor during the check. If the effluent radiation monitor fails the source check, carryout the Action(s) of the Off-Site Dose Calculation Manual for the non-functional monitor or terminate the effluent release.
ACTION 8 During the ventilation of airborne effluents from the Auxiliary Building Exhaust Stack at least one Auxiliary Building Exhaust fan shall be in operation.
CH-ODCM-0001 Reference Use Page 16 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 3.2.2 - Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Channel Channel Source Instrument Calibration Function Check Check Test
- 1. Radioactivity Monitors Providing Alarm and Automatic Isolation 1.1 RM-043 D R Q M 1.2 RM-062 D R Q M 1.3 RM-052 D R Q M
- 2. Flowrate Monitors 2.1 RM-043 Sampler D R Q ----
2.2 RM-062 Sampler D R Q ----
2.3 RM-052 Sampler D R Q ----
2.4 Auxiliary Bldg Exhaust Stack D R Q ----
2.5 Laboratory and Radwaste Process Bldg Exhaust Stack D R Q ----
Operations Check Air Flow Calibration
- 3. Environmental Monitors 3.1 RM-023 - Sample Station #40 M A 3.2 RM-024 - Sample Station #41 M A 3.3 RM-025 - Sample Station #28 ---- ----
3.4 RM-026 - Sample Station #36 ---- ----
3.5 RM-027 - Sample Station #37 M A 3.6 RM-028 - Sample Station #38 ---- ----
3.7 RM-029 - Sample Station #39 ---- ----
3.8 RM-035 - Sample Station #1 ---- ----
3.9 RM-036 - Sample Station #2 M A 3.10 RM-037 - Sample Station #3 ---- ----
3.11 RM-038 - Sample Station #4 M A 3.12 RM-039 - Sample Station #5 ---- ----
3.13 RM-040 - Sample Station #32 M A
CH-ODCM-0001 Reference Use Page 17 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.0 RADIOACTIVE EFFLUENTS 4.1 Radioactive Liquid Effluents 4.1.1 Concentration A. Limiting Condition for Operation
- 1. The release rate of radioactive material in liquid effluents shall be controlled such that the instantaneous concentrations for radionuclides, other than dissolved or entrained noble gases, do not exceed the values specified in 10 CFR Part 20 for liquid effluents at site discharge. To support facility operations, RP/Chemistry supervision may increase this limit up to the limit specified in Technical Specifications 5.16.1.b. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/ml, total activity.
- 2. Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 Ci/ml total activity.
APPLICABILITY: At all times ACTION:
- a. When the concentration of radioactive material released at site discharge exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.
CH-ODCM-0001 Reference Use Page 18 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 B. Surveillance Requirements NOTE i Radioactive liquid waste includes water used for fire suppression in areas of the facility that may contain radioactivity. These liquids are required to be i monitored prior to release in accordance with SO-G-28.
- 1. Radioactive liquid waste shall be sampled and analyzed according to the sampling and analysis program in Table 4.1.
- 2. The results of the radioactivity analysis shall be used with the calculational methods in Part II of the Off-Site Dose Calculation Manual.
- 3. To assure that the concentration at the point of release is maintained within the limits of Technical Specification 5.16.1.b.
- 4. Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred. Analytical results shall be submitted to the Commission in accordance with Part I, Section 6.0 of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 19 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 4.1 - Radioactive Liquid Effluent Sampling and Analysis A. Monitor, Hotel Waste Tanks & Special Liquid, Releases Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Each Batch Principal Gamma Emitters B 5.0E-07 Dissolved Noble Gases Each Batch (Gamma Emitters) B 1.0E-05 Monthly Composite C H-3 1.0E-05 Monthly Composite C Gross Alpha 1.0E-07 Quarterly Composite C Sr-89, Sr-90 5.0E-08 Quarterly Composite C Fe-55 1.0E-06 NOTES:
A. LLD is defined in Part II of the Off-Site Dose Calculation Manual.
B. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for dissolved or entrained gases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141 for fission and corrosion products. Ce-144 shall also be measured, but with a LLD of 5.0E-06.
C. To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples should be collected in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite should be mixed in order for the composite sample to be representative of the average effluent release.
CH-ODCM-0001 Reference Use Page 20 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.1.2 Dose from Radioactive Liquid Effluents A. Limiting Condition for Operation
- 1. The dose or dose commitment to an individual in unrestricted areas from radioactive materials in liquid effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 1.5 mrem to the total body and 5 mrem to any organ; and
- b. During any calendar year: Less than or equal to 3 mrem to the total body and 10 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of radioactive materials in liquid effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual at least once per quarter.
CH-ODCM-0001 Reference Use Page 21 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.1.3 Liquid Radwaste Treatment A. Limiting Condition for Operation
- 1. The Liquid Radwaste Treatment System shall be FUNCTIONAL, and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.
APPLICABILITY: At all times ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Nuclear Regulatory Commission within 30 days, pursuant to 10 CFR 50, Appendix I, a Special Report that includes the following information:
- 1) Explanation of why liquid radwaste was being discharged without treatment, identification of equipment or subsystem(s) not functional and reasons for non-functionality.
- 2) Action(s) taken to restore the non-functional equipment to functional status.
- 3) Summary description of action(s) taken to prevent a recurrence.
B. Surveillance Requirements
- 1. Dose due to liquid releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual, when Liquid Radwaste Treatment Systems are not fully FUNCTIONAL.
- 2. FUNCTIONAL is defined as follows:
- a. A filtration/ion exchange (FIX) system will be utilized for processing liquid radwaste. The system consists of a booster pump, charcoal pretreatment filter, and pressure vessels containing organic/inorganic resins, which can be configured for optimum performance. The effluent from the FIX system is directed to the monitor tanks for release.
CH-ODCM-0001 Reference Use Page 22 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.1.3B.2 (continued)
- b. Waste filters (WD-17A and WD-17B) are used only on those occasions when considered necessary, otherwise the flows from the low activity fluids may bypass the filters. No credit for decontamination factors (iodines, Cs, Rb, others) was taken for these filters during the 10 CFR Part 50 Appendix I dose design objective evaluation; therefore, the non-functionality of these filters does not affect the dose contributions to any individual in the unrestricted areas via liquid pathways. The non-functionality of waste filters will not be considered a reportable event in accordance with the Action listed above.
4.1.4 Liquid Holdup Tanks Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
A. Limiting Condition for Operation
- 1. The quantity of radioactive material contained in each unprotected outdoor liquid holdup tank shall not exceed 10 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times ACTION:
- a. When the quantity of radioactive material in any unprotected outdoor liquid holdup tank exceeds 10 curies, excluding tritium and dissolved or entrained noble gasses, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
B. Surveillance Requirements
- 1. The quantity of radioactive material contained in each outdoor liquid holdup tank shall be determined to be within the above limit by analyzing a representative sample of the tanks contents at least once per 7 days when radioactive material is being added to the tank.
CH-ODCM-0001 Reference Use Page 23 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.2 Radioactive Gaseous Effluents 4.2.1 Concentration A. Limiting Condition for Operation
- 1. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations of radionuclides does not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To support facility operations, RP/Chemistry supervision may increase this limit up to the limits specified in Technical Specification 5.16.1.g.
- 2. Technical Specification 5.16.1.g establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.
APPLICABILITY: At all times ACTION:
- a. When the concentration of radioactive material released to unrestricted areas exceeds the above limits, appropriate corrective actions shall be taken immediately to restore concentrations within the above limits.
B. Surveillance Requirements NOTE Radioactive gaseous wastes include atmospheres in areas where gaseous i fire suppression systems are utilized or where smoke is produced as a result of fire in areas of the facility that may contain radioactivity. These i atmospheres are required to be monitored prior to gaseous release to unrestricted areas in accordance with SO-G-28.
- 1. Radioactive gaseous wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.2. The results of the radioactivity analysis shall be used to assure the limits in Step 4.2.1A are not exceeded.
CH-ODCM-0001 Reference Use Page 24 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 4.2 - Radioactive Airborne Effluent Sampling and Analysis A. Auxiliary Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly (Noble Gases) Principal Gamma Emitters B 1.0E-4 Weekly Tritium (H-3) 1.0E-06 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Samples) Sr-89, Sr-90 1.0E-11 B. Laboratory and Radwaste Building Exhaust Stack D Lower Limit of Detection Sampling Frequency Type of Activity Analysis (LLD) (Ci/ml) A Weekly (Particulate Sample) Principal Gamma Emitters B 1.0E-11 Weekly (Noble Gases) Principal Gamma Emitters B 1.0E-4 Monthly Composite C Gross Alpha 1.0E-11 Quarterly Composite (Particulate Sample) Sr-89, Sr-90 1.0E-11 NOTES:
A. LLD is defined in Part II of the Off-Site Dose Calculation Manual.
B. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate releases.
C. Frequency requirement may be satisfied using weekly gross alpha results from particulate sampling media.
D. Particulate samples shall be corrected for sampler deposition/transportation efficiency by using the approved software programs or by multiplying the activity obtained by the associated sampler multiplication factor (See Table 4.3).
CH-ODCM-0001 Reference Use Page 25 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 4.3 - Sampler Deposition/Transportation Correction Factors Particulate Sampler Sample DF ACTMULT RM-062 AB 0.411 2.433 RM-052 AB 0.638 1.567 RM-043 LRWPB 0.809 1.236 ACRONYM DEFINITIONS:
AB - Auxiliary Building Exhaust Stack LRWPB - Laboratory and Rad Waste Processing Building DF - Deposition Factor ACTMULT - Activity multiplication factor to correct for sample loss.
CH-ODCM-0001 Reference Use Page 26 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.2.2 Dose - Noble Gases A. Limiting Condition for Operation
- 1. The dose or dose commitment to an individual at the site boundary from release of noble gases in airborne effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of noble gases in airborne effluents, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC, per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from radioactive noble gases in airborne effluents shall be determined, in accordance with the methodologies and parameters of Part II of the Off-Site Dose Calculation Manual, on a quarterly basis.
4.2.3 Dose - H-3, C-14, and Radioactive Material in Particulate Form with Half-Lives Greater than 8 Days (Other than Noble Gases)
A. Limiting Condition for Operation
- 1. The dose to an individual or dose commitment to any organ of an individual in unrestricted areas due to the release of H-3, C-14, and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ; and
CH-ODCM-0001 Reference Use Page 27 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.2.3A.1 (continued)
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. If the dose contribution, due to the cumulative release of H-3, C-14, and radioactive materials in particulate form with half-lives greater than eight days, exceeds the annual or quarterly dose objectives, submit a Special Report to the NRC per Section 6.2.3, within 30 days.
B. Surveillance Requirements
- 1. The radiation dose contributions from H-3, C-14 and radioactive materials in particulate form with half-lives greater than eight days (excluding noble gases) in airborne effluents shall be determined, in accordance with the methodologies and parameters of Part II of the Off-Site Dose Calculation Manual, on a quarterly basis.
4.2.4 Gaseous Radwaste Treatment A. Limiting Condition for Operation
- 1. In accordance with Technical Specification 5.16.1.f, the Ventilation Exhaust Systems shall be FUNCTIONAL, and appropriate portions of these systems shall be used to reduce the releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed:
- a. 0.2 mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC
CH-ODCM-0001 Reference Use Page 28 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.2.4A.1 (continued)
APPLICABILITY: At all times ACTION:
- a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit a report to the Nuclear Regulatory Commission within 30 days, pursuant to 10 CFR 50, Appendix I, a special report that includes the following information:
- 1) Identification of equipment or subsystem(s) not functional and reasons for non-functionality.
- 2) Action(s) taken to restore the non-functional equipment to functional status.
- 3) Summary description of action(s) taken to prevent a recurrence.
B. Surveillance Requirements
- 1. Dose due to gaseous releases shall be projected frequently and at least once per quarter, in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual, when Ventilation Exhaust Systems are not fully FUNCTIONAL.
- 2. FUNCTIONAL is defined as follows:
- a. Ventilation Exhaust Systems
- 1) The radioactive effluents from the controlled access area of the auxiliary building are filtered by the HEPA filters in the auxiliary building ventilation system. If the radioactive effluents are discharged without the HEPA filters and it is confirmed that one half of the annual dose objective will be exceeded during the calendar quarter, a special report shall be submitted to the Commission pursuant to Section 4.2.4A.
CH-ODCM-0001 Reference Use Page 29 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.3 Uranium Fuel Cycle 4.3.1 Total Dose-Uranium Fuel Cycle A. Limiting Condition for Operation
- 1. The dose to any real individual from uranium fuel cycle sources shall be limited to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to 75 mrem) during each calendar year.
APPLICABILITY: At all times ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specifications 4.1.2A, 4.2.2A, or 4.2.3A, calculations shall be made including direct radiation contribution from the facility and outside storage tanks to determine whether the above limits have been exceeded. If such is the case, in lieu of any other report required by Section 6.2, prepare and submit a Special Report to the Commission pursuant to Technical Specification 5.16 that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report , as defined in 10 CFR Part 20.2203(a)(4) and 20.2203(b), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentration of radioactive material involved, and the cause of exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 or 10 CFR Part 72.104 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 or 10 CFR Part 72.104.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
CH-ODCM-0001 Reference Use Page 30 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.3.1 (continued)
B. Surveillance Requirements
- 1. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance requirements 4.1.2B, 4.2.2B and 4.2.3B and in accordance with the methodology and parameters in Part II of the Off-Site Dose Calculation Manual.
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 5.1 Monitoring Program 5.1.1 Limiting Condition for Operation A. The Radiological Environmental Monitoring Program shall be conducted as specified in Table 5.1.
APPLICABILITY: At all times ACTION:
- 1. Analytical results of this program and deviations from the sampling schedule shall be reported to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 6.2).
- 2. If the level of radioactivity from calculated doses leads to a higher exposure pathway to individuals, this pathway shall be added to the Radiological Environmental Monitoring Program. Modifications to the program shall be reported in the Annual Radiological Environmental Operating Report to the Nuclear Regulatory Commission.
- 3. If the level of radioactivity in an environmental sampling medium exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.3). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 5.3 for Lower Level of Detection (LLD).
CH-ODCM-0001 Reference Use Page 31 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 5.1.1A (continued)
- 4. If the level of radioactivity in a sample from either an onsite or offsite well, performed per the Site Groundwater Protection Program, exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operation, a Special Report shall be prepared and submitted to the Nuclear Regulatory Commission within 30 days (Section 6.2.3). The detection capabilities of the equipment used for the analysis of environmental samples must meet the requirements of Table 5.3 for Lower Level of Detection (LLD). Copies of the Special Report will be forwarded to State/Local authorities.
[AR 39127]
- 5. If the level of radioactivity from either an onsite or offsite well, performed per the Site Groundwater Protection Program exceeds the reporting level specified in Table 5.4, and the activity is attributable to facility operations, state and local authorities shall be notified by the end of the next business day. NRC shall be notified per LS-FC-1020, Reportability Tables and Decision Tree. [AR 39127]
- 6. Radiological environmental sampling locations and the media that is utilized for analysis are presented in Table 5.2. Sampling locations are also illustrated on the map, Figure 1. Details of the quarterly emergency TLD locations are contained in surveillance test CH-ST-RV-0003, Environmental Sample Collection -
Quarterly/Environmental Dosimeters (TLDs). Each TLD sample location contains one dosimeter that is exchanged quarterly for REMP sampling and as needed for Emergency Planning Zone monitoring.
- 7. Deviations from the monitoring program, presented in this section and detailed in Table 5.2, are permitted if specimens are unobtainable due to mitigating circumstances such as hazardous conditions, seasonal unavailability, malfunction of equipment, or if a person discontinues participation in the program, etc. If the equipment malfunctions, corrective actions will be completed as soon as practicable. If a person no longer supplies samples, a replacement will be made if possible. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report, pursuant to Section 6.2.
5.1.2 Surveillance Requirements A. The Radiological Environmental Monitoring Program (REMP) samples shall be collected and analyzed in accordance with Tables 5.1, 5.2, and 5.3.
CH-ODCM-0001 Reference Use Page 32 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 1. Direct Radiation A. 14 TLD indicator stations, one Gamma dose Quarterly background stationF, total of 15.
B. An inner-ring of 16 stations, one in each cardinal sector in the Gamma dose Quarterly general area of the unrestricted area boundary and within 2.5 miles.
C. An outer-ring of 16 stations, one in each cardinal sector located Gamma dose Quarterly outside of the inner-ring, but no more distant than approximately 5 miles.
D. Other TLDs may be placed at Gamma dose Quarterly special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Omaha Public Power District employees have routine access.
- 2. Air Monitoring A. Indicator Stations Filter for Gross Beta C Weekly
- 1. Three stations in the general Filter for Gamma Isotopic Quarterly area of the unrestricted area composite boundary of weekly filters
- 2. City of Blair
- 3. Desoto Township B. One background station F
- 3. Water A. Missouri River at nearest Gamma Isotopic, H-3 Monthly for downstream drinking water Gamma intake. isotopic analysis.
B. Missouri River downstream near the mixing zone. Quarterly composite for C. Missouri River upstream of H-3 Analysis Facility intake (background)F.
- 4. Milk D A. Nearest milk animal (cow or Gamma Isotopic Monthly goat) within 5 miles B. Milk animal (cow or goat) between 5 miles and 18.75 miles (background)F.
- 5. Fish A. Four fish samples within vicinity Gamma Isotopic Once per of Facility discharge. season (May to B. One background sample October) upstream of Facility discharge.
CH-ODCM-0001 Reference Use Page 33 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.1 - Radiological Environmental Monitoring Program Exposure Pathway Collection Site A Type of Analysis B Frequency and/or Sample
- 6. Vegetables or A. One sample in the highest Gamma Isotopic Once per Food Products E exposure pathway. season (May to B. One sample from onsite crop October) field C. One sample outside of 5 miles (background)F.
- 7. Groundwater A. Three samples from sources H3, Gross Beta, Gamma Quarterly potentially affected by facility Isotopic, Sr-90 operations.
B. One sample outside of 5 miles (background)F.
- 8. Vegetation in lieu A. One sample at the highest Gamma Isotopic Monthly (when of milk annual average D/Q offsite available) location.
B. One sample at the second highest annual average D/Q offsite location.
C. One sample outside of 5 miles (background) F.
CH-ODCM-0001 Reference Use Page 34 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 NOTES:
A. See Table 5.3 for required detection limits.
B. The Lower Limit of Detection (LLD) for analysis is defined in the Off-Site Dose Calculation Manual in accordance with the wording of NUREG-1301.
C. When a gross beta count indicates radioactivity greater than 2.5E-13 Ci/ml or 0.25 pCi/m3, (ten times the yearly mean), a gamma spectral analysis will be performed.
D. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II, Table 4 "Highest Potential Exposure Pathways for Estimating Dose")
E. Samples should be collected from garden plots of 500 ft2 or more. (Reference Reg. Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants," Dec. 1975).
F. This sample may not be located in the least prevalent wind direction. The Branch Technical Position paper, Table 1, subnote "d" says this regarding background information, or control locations. "The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted".
CH-ODCM-0001 Reference Use Page 35 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate Onsite Station, 110-meter weather 1 tower 0.53 293°/WNW P X Onsite Station, adjacent 2C,E to old plant access road 0.59 207°/SSW K X X Offsite Station, Intersection of Hwy. 75 3 and farm access road 0.94 145°/SE G X 4 Blair OPPD office 2.86 305°/NW Q X X 5A Fort Calhoun, NE City 6 Hall 5.18 150°/SSE H X Fence around intake gate, Desoto Wildlife 7 Refuge 2.07 102°/ESE F X Onsite Station, entrance to Plant Site 8 from Hwy. 75 0.55 191°/S J X Onsite Station, NW of 9 Plant 0.68 305°/NW Q X Onsite Station, WSW of 10 Plant 0.61 242°/WSW M X Offsite Station, SE of 11 Plant 1.07 39°/SE G X
CH-ODCM-0001 Reference Use Page 36 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate Metropolitan Utilities Dist., Florence Treatment Plant 12 North Omaha, NE 14.3 154°/SSE H X West bank Missouri River, downstream from 13 Plant discharge 0.45 108°/ESE F X X Upstream from Intake 14D Bldg, west bank of river 0.09 4°/N A X X 15 Smith Farm 1.99 134°/SE G X 16A 17A 18A 19A 20B,D,F Mohr Dairy 9.86 186°/S J X X X 21A Fish Sampling Area, 0.08 22 Missouri River (R.M. 645.0) 6°/N A X Fish Sampling Area, 17.9 23D Missouri River (R.M. 666.0) 358°/N A X 24A 25A 26A 27A
CH-ODCM-0001 Reference Use Page 37 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 28A 29A 30A 31A 32D Valley Substation #902 19.6 221°/SW L X X 33A 34A 35 Onsite Farm Field 0.52 118°/ESE F X Offsite Station Intersection Hwy 75/Co.
36 Rd. P37 0.75 227°/SW L X Offsite Station Desoto 37 Township 1.57 144°/SE G X X 38A 39A 40A 41B,C Dowler Acreage 0.73 175°/S J X X 42 Sector A-1 1.94 0°/NORTH A X 43 Sector B-1 1.97 16°/NNE B X 44 Sector C-1 1.56 41°/NE C X 45 Sector D-1 1.34 71°/ENE D X 46 Sector E-1 1.54 90°/EAST E X 47 Sector F-1 0.45 108°/ESE F X
CH-ODCM-0001 Reference Use Page 38 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 48 Sector G-1 1.99 134°/SE G X 49 Sector H-1 1.04 159°/SSE H X 50 Sector J-1 0.71 179°/SOUTH J X 51 Sector K-1 0.61 205°/SSW K X 52 Sector L-1 0.74 229°/SW L X 53 Sector M-1 0.93 248°/WSW M X 54 Sector N-1 1.31 266°/WEST N X 55 Sector P-1 0.60 291°/WNW P X 56 Sector Q-1 0.67 307°/NW Q X 57 Sector R-1 2.32 328°/NNW R X 58 Sector A-2 4.54 350°/NORTH A X 59 Sector B-2 2.95 26°/NNE B X 60 Sector C-2 3.32 50°/NE C X 61 Sector D-2 3.11 75°/ENE D X 62 Sector E-2 2.51 90°/EAST E X 63 Sector F-2 2.91 110°/ESE F X 64 Sector G-2 3.00 140°/SE G X 65 Sector H-2 2.58 154°/SSE H X 66 Sector J-2 3.53 181°/SOUTH J X 67 Sector K-2 2.52 205°/SSW K X 68 Sector L-2 2.77 214°/SW L X 69 Sector M-2 2.86 243°/WSW M X
CH-ODCM-0001 Reference Use Page 39 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Approximate Air Distance Sample Direction Monitoring Vegetables Approximate from Center Sedi- Ground-Station (degrees Sector TLD Water Milk Fish and Food Collection Sites of ment water No. from true Products Containment Airborne north)
(miles) Particulate 70 Sector N-2 2.54 263°/WEST N X 71 Sector P-2 2.99 299°/WNW P X 72 Sector Q-2 3.37 311°/NW Q X 73 Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X 75B,C Lomp Acreage 0.65 163°/SSE H X X X X 76A 77G River N-1 0.17 328°/NNW R X 78G River S-1 0.14 85°/EAST E X 79G Lagoon S-1 0.24 131°/SE G X 80G Parking S-1 0.27 158°/SSE H X 81G Training W-1 0.28 194°/SSW K X 82G Switchyard S-1 0.21 219°/SW L X 83G Switchyard SE-1 0.14 231°/SW L X 84G Switchyard NE-1 0.18 256°/WSW M X 85G Switchyard W-1 0.29 233°/WEST L X 86G Switchyard N-1 0.24 262°/WEST N X 87G Range S-1 0.20 286°/WNW P X 88G Mausoleum E-1 0.37 216°/SW L X 89 C, Miller 3.30 210°/SSW K X
CH-ODCM-0001 Reference Use Page 40 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 NOTES:
A. Location is either not in use or currently discontinued and is documented in the table for reference only.
B. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II, Table 4 "Highest Potential Exposure Pathways for Estimating Dose")
C. Locations represent highest potential exposure pathways as determined by the biennial Land Use Survey, performed in accordance with Part I, Section 7.3.2, of the Off-Site Dose Calculation Manual and are monitored as such.
D. Background location (control). All other locations are indicators.
E. Location for monitoring Sector K High Exposure Pathway Resident Receptor for inhalation.
F. When broad leaf (pasture grasses) are being collected in lieu of milk, background broad leaf samples will be collected at a background locale.
G. Location for special interest monitoring general dose to the public per 40CFR190 (Figure 2)
CH-ODCM-0001 Reference Use Page 41 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Figure 1 - Environmental Radiological Sampling Points
(*) Locations currently discontinued are not illustrated.
CH-ODCM-0001 Reference Use Page 42 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Figure 2- 40CFR190 Sampling Points
CH-ODCM-0001 Reference Use Page 43 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.3 - Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) A, B, C Gross Co-58, Ba-140 Sample Units Beta H-3 Mn-54 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 La-140 Water pCi/L 4 2.0E+03 1.5E+01 3.0E+01 1.5E+01 3.0E+01 1.5E+01 1.5E+01 1.5E+01 1.8E+01 1.5E+01 pCi/kg Fish (wet) --- --- 1.3E+02 2.6E+02 1.3E+02 2.6E+02 --- --- 1.3E+02 1.5E+02 ---
Milk pCi/L --- --- --- --- --- --- --- --- 1.5E+01 1.8E+01 1.5E+01 Airborne Particulates or Gases pCi/m3 1.0E-02 --- --- --- --- --- --- --- 1.0E-02 1.0E-02 ---
pCi/kg Sediment (dry) --- --- --- --- --- --- --- --- 1.5E+02 1.8E+02 ---
Grass or Broad Leaf Vegetation/
Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 6.0E+01 8.0E+01 ---
A. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable as Facility effluents, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Part I, Section 6.2, of the Off-Site Dose Calculation Manual.
B. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
C. The LLD is defined in Part II of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 44 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5.4 - Reporting Levels for Radioactivity Concentrations in Environmental Samples A Sample Units H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Water pCi/L 2.0E+04 1.0E+03 4.0E+02 1.0E+03 3.0E+02 3.0E+02 4.0E+02 4.0E+02 3.0E+01 5.0E+01 2.0E+02 Fish pCi/kg (wet) --- 3.0E+04 1.0E+04 3.0E+04 1.0E+04 2.0E+04 --- --- 1.0E+03 2.0E+03 ---
Milk pCi/L --- --- --- --- --- --- --- --- 6.0E+01 7.0E+01 3.0E+02 Airborne Particulates or pCi/m3 Gases --- --- --- --- --- --- --- --- 1.0E+01 2.0E+01 ---
Grass or Broad Leaf Vegetation/
Vegetables or pCi/kg Food Products (wet) --- --- --- --- --- --- --- --- 1.0E+03 2.0E+03 ---
A. A Non-routine report shall be submitted when more than one of the radionuclides listed above are detected in the sampling medium and:
1 2 3
+ + + . . . . 1.0 1 2 3 When radionuclides other than those listed above are detected and are the result of Facility effluents, this report shall be submitted if the potential annual dose to a member of the general public is equal to or greater than the dose objectives of Part I, Section 4.1 and 4.2, of the Off-Site Dose Calculation Manual. This report is not required if the measured level of radioactivity was not the result of Facility effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
CH-ODCM-0001 Reference Use Page 45 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 5.2 Land Use Survey 5.2.1 Limiting Condition for Operation A. A Land Use Survey shall identify the location of the nearest milk animal, nearest meat animal, nearest vegetable garden, nearest groundwater source and the nearest residence in each of the 16 cardinal sectors within a distance of five miles. The survey shall be conducted under the following conditions:
- 1. Within a one-mile radius from the Facility site, enumeration by door-to-door or equivalent counting techniques.
- 2. Within a Five-mile radius, enumeration may be conducted door-to-door or by using referenced information from county agricultural agents or other reliable sources.
APPLICABILITY: At all times ACTION:
- a. If it is learned from this survey that milk animals, vegetable gardens and resident receptors are present at a location which yields a calculated dose greater than 20% from previously sampled location(s), the new location(s) shall be added to the monitoring program. Milk and vegetable garden sampling location(s) having the lowest calculated dose may then be dropped from the monitoring program at the end of the grazing and/or growing season during which the survey was conducted and the new location added to the monitoring program.
Groundwater monitoring is based on a determination if source(s) are potentially affected by facility operations.
Modifications to the air monitoring locations, vegetable garden sampling locations, and milk sampling locations will be made as soon as practicable. The Nuclear Regulatory Commission shall be notified of modifications to the program in the Annual Radiological Environmental Operating Report (Section 6.2).
CH-ODCM-0001 Reference Use Page 46 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 5.2.1A.2 (continued)
- b. If it is learned from this survey that a pathway for dose to a MEMBER OF THE GENERAL PUBLIC no longer exists, an additional pathway has been identified or site specific factors affecting the dose calculations for a pathway have changed, then this information should be documented in the Land Use Survey, the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report.
This information can be used to increase the accuracy of the dose models for the Annual Radioactive Effluent Release Report as well as dose estimates performed during the reporting period (i.e., quarterly dose estimates).
5.2.2 Surveillance Requirements A. A land use survey shall be conducted once per 24 months between the dates of June 1 and October 1. The results of the land use survey shall be submitted to the Nuclear Regulatory Commission in the Annual Radiological Environmental Operating Report (Section 6.2) for the year it was performed.
5.3 Interlaboratory Comparison Program 5.3.1 Limiting Condition for Operation A. Analyses shall be performed on radioactive materials as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commission.
APPLICABILITY: At all times ACTION:
- 1. With analysis not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report (Section 6.2).
5.3.2 Surveillance Requirements A. The results of these analyses shall be included in the Annual Radiological Environmental Operating Report (Section 6.2).
CH-ODCM-0001 Reference Use Page 47 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibilities 6.1.1 FCS RP/Chemistry Department is responsible for the implementation and maintenance of the Off-Site Dose Calculation Manual.
6.1.2 FCS Operations Department is responsible for the compliance with the Off-Site Dose Calculation Manual in the operation of Fort Calhoun Station.
6.2 Radioactive Effluent Reporting Requirements The reporting requirements for radioactive effluents stated in this Section are to provide assurance that the limits set forth in Part I of the Off-Site Dose Calculation Manual are complied with. These reports will meet the requirements for documentation of radioactive effluents contained in 10 CFR Part 50.36a; Reg.
Guide 1.21, Rev. 2; Reg. Guide 4.8, Table 1; and Reg. Guide 1.109, Rev. 1.
6.2.1 Annual Radioactive Effluent Release Report A report covering the operation of the Fort Calhoun Station during the previous calendar year shall be submitted prior to May 1 of each year per the requirements of Technical Specifications 5.9.4.a. and 10 CFR Part 50.
The Radioactive Effluent Release Report shall include:
A. A summary of the quantities of radioactive liquid and airborne effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21, Revision 2.
B. A summary of the annual meteorological data that provides joint frequency distributions of wind direction and wind speed by atmospheric stability class will be included in the annual report. In addition, hourly meteorological data is recorded and retained on site as outlined in Regulatory Guide 1.21, Revision 2.
C. An assessment of radiation doses from the radioactive liquid and airborne effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21, Revision 2. The assessment of radiation doses shall be performed in accordance with calculational methodology of the Regulatory Guide 1.109, Revision 1.
D. Changes to the Process Control Program (PCP) or to the Offsite Dose Calculation Manual (ODCM) made during the reporting period. Each change shall be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed and shall indicate the date the change was implemented.
CH-ODCM-0001 Reference Use Page 48 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 6.2.1 (continued)
E. A list and description of abnormal releases or abnormal discharges from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.
F. An explanation of why instrumentation designated in Part I, Sections 3.1.1 and 3.2, of the Off-Site Dose Calculation Manual, was not restored to FUNCTIONAL status within 30 days.
G. A description of any major design changes or modifications made to the Liquid and/or Gaseous Radwaste Treatment Systems or Ventilation Exhaust Systems during the reporting period.
H. An explanation of why the liquid and/or gaseous radwaste treatment systems were not FUNCTIONAL, causing the limits of specifications 4.1.3A and 4.2.4A to be exceeded.
I. The results of sampling from offsite and onsite groundwater wells per the Site Groundwater Protection Plan. [AR 39127]
J. Non-routine planned discharges (e.g., discharges from remediation efforts like pumping contaminated groundwater from a leak).
6.2.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report for the previous one year of operation shall be submitted prior to May 1 of each year. This report contains the data gathered from the Radiological Environmental Monitoring Program. The content of the report shall include:
A. Summarized and tabulated results of the radiological environmental sampling/analysis activities following the format of Regulatory Guide 4.8, Table 1. In the event that some results are not available, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
B. Interpretations and statistical evaluation of the results, including an assessment of the observed impacts of the facility operation and environment.
C. The results of participation in a NRC approved Interlaboratory Comparison Program.
D. The results of land use survey required by Section 5.2.
E. A map of the current environmental monitoring sample locations.
CH-ODCM-0001 Reference Use Page 49 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 6.2.3 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report.
The Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report must be submitted within 60 days after the end of the 12-month monitoring period, per 10 CFR 72.44(d)(3).
A. A Summary of the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous 12 months and such other information as may be required by the Commission to estimate maximum potential radiation dose commitment to the public resulting from effluent releases.
6.2.4 Special Report If the limits or requirements of Sections 4.1.2A, 4.1.3A, 4.2.2A, 4.2.3A, 4.2.4A, 4.3.1A, and/or 5.1.1A.3 and/or 5.1.1A.4 are exceeded, a Special Report shall be issued to the Commission, pursuant to Technical Specification 5.16. This report shall include: [AR 39127]
A. The results of an investigation to identify the causes for exceeding the specification.
B. Define and initiate a program of action to reduce levels to within the specification limits.
C. The report shall also include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the condition.
6.2.5 EPA 40 CFR Part 190 Reporting Requirements With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of dose from specifications 4.1.2A, 4.2.2A, or 4.2.3A, calculations shall be made including direct radiation calculations, to prepare and submit a special report to the Commission within 30 days and limit the subsequent releases such that the dose to any real individual from uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except thyroid, which is limited to 75 mrem) over the calendar year. This special report shall include an analysis which demonstrates that radiation exposures to any member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 standard. Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 standard. The submittal of the report is to be considered a timely request and a variance is granted pending the final action on the variance request from the Commission.
CH-ODCM-0001 Reference Use Page 50 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 6.2.5 ISFSI 10 CFR Part 72.104 Reporting Requirements The regulatory requirements of 10CFR20, 10CFR72 and 40CFR190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20, 10CFR72 and 40CFR190 not addressed by 10CFR50 Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public.
CH-ODCM-0001 Reference Use Page 51 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 The 10CFR72.104 dose limits are the same as those specified in 40CFR190.
ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. If the dose limits of 40CFR190 or 10CFR72.104 are exceeded, a special report to the NRC, as well as an appropriate request for exemption/variance, is required to be submitted to the NRC.
The requirement that the dose limits of 10CFR72.104 apply to any real individual is controlled for ISFSI activities in the ISFSI 72.212 report.
Therefore, for the purposes of analyzing dose from the ISFSI, the member of the public as defined in 40CFR190 is the same as for the real individual.
The external Total Body Dose is comprised of:
- 1) Total Body Dose due to noble gas radionuclides in gaseous effluents
- 2) Dose due to radioactive waste and the ISFSI
- 3) Total Body Dose due to radioactivity deposited on the ground (this dose is accounted for in the determination of the non-noble gas dose and is not considered here)
The Total Body Dose, external is given by:
D,ext = D,tb + D,osf Where D,ext is the external dose D,tb is the total body dose D,osf is the dose from on-site storage The Total Dose is then given by:
D,tot = D,ext + D,liq + D,nng Where D,tot is the total dose D,ext is the external dose D,liq is the dose from liquid effluents D,nng is the dose from non-noble gases Dose Limits Total Body, annual 25 mrem Thyroid, annual 75 mrem Other Organs, annual 25 mrem
CH-ODCM-0001 Reference Use Page 52 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 6.3 Change Mechanism The Off-Site Dose Calculation Manual is the controlling document for all radioactive effluent releases. It is defined as a procedure under the guidance of Technical Specification 5.8. It will be revised and reviewed by the Plant Operations Review Committee and approved by the Plant Manager in accordance with Technical Specification 5.17. All changes to the Off-Site Dose Calculation Manual will be forwarded to the Nuclear Regulatory Commission during the next reporting period for the Annual Radioactive Effluent Release Report in accordance with the requirements of Technical Specification 5.17.
6.4 Meteorological Data The Annual Average /Q is utilized to determine the concentrations of radionuclides at the unrestricted area boundary. It is also the factor used in conjunction with the parameters and methodologies in Part II, of the Off-Site Dose Calculation Manual to determine unrestricted area dose on a quarterly bases or as needed. It is based on an average of the highest calculated sector /Q values, using all 16 sectors for each of the three previous year Annual Radioactive Effluent Release Reports, and the XOQDOQ plume trajectory model. An additional 10 percent will be added to the average for unrestricted area dose estimates performed quarterly or as needed for conservatism. When calculating /Q data for the Annual Radiological Effluent Release Report, if the highest calculated /Q for the reporting period is observed to be greater than +/- 10% of the Annual Average /Q previously calculated, contact RP/Chemistry supervision for further instructions. This model conforms with the Nuclear Regulatory Commissions Regulatory Guide 1.111.
Current year meteorological data will be utilized in the preparation of the Annual Radioactive Effluent Release Report. This data is used to calculate the joint frequency table, the dispersion coefficients and deposition factors in all 16 sectors. These are used in the calculation of doses to individuals in unrestricted areas as a result of the operation of Fort Calhoun Station. The models used, GASPAR 2 and LADTAP 2, meet the intent of Nuclear Regulatory Commissions Reg. Guide 1.109 and 1.21 for the reporting of doses due to routine radioactive effluent releases.
CH-ODCM-0001 Reference Use Page 53 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 6.5 References 6.5.1 Regulatory Guide 1.109, Rev. 1 - Calculation of Annual Dose to man from Routine Releases of Reactor Effluents for the purpose of evaluation compliance with 10 CFR Part 50, Appendix I 6.5.2 Regulatory Guide 1.111, Rev. 1 - Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.
6.5.3 Regulatory Guide 1.113, Rev. 1 - Estimating Aquatic Dispersion of Effluents from Accidental and Routine Releases for the purpose of Implementing Appendix I.
6.5.4 Regulatory Guide 4.8, Environmental Technical Specification for Nuclear Power Plants.
6.5.5 NRC Branch Technical Position, March 1978 6.5.6 NUREG-0133 - Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.
6.5.7 NUREG-1301 - Offsite Dose Calculation Manual Guidance.
6.5.8 Regulatory Guide 1.21, Rev. 2 - Measuring, Evaluating, and Reporting Radioactivity in solid wastes and Releases of Radioactivity Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.
6.5.9 Code of Federal Regulations, Title 10, Part 20 6.5.10 Code of Federal Regulations, Title 10, Part 50 6.5.11 Code of Federal Regulations, Title 10, Part 72 6.5.12 Code of Federal Regulations, Title 40, Part 190 6.5.13 Fort Calhoun Revised Environmental Report (Unit No. 1)-1972 6.5.14 Fort Calhoun Technical Specifications (Unit No. 1) 6.5.15 Defueled Safety Analysis Report 6.5.16 AR 12357, Implement Recommendations of Memo FC-0133-92, Part I, Table 3.2.1 Action 4, of the Off-Site Calculation Manual 6.5.17 AR 39127, NEI Industry Initiative on Groundwater Protection
CH-ODCM-0001 Reference Use Page 54 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 6.5.18 Regulatory Guide 4.1, Rev. 2 - Radiological Environmental Monitoring for Nuclear Power Plants 6.5.19 SO-G Station Fire Plan 6.5.20 FC-19-001, ODCM rev 29 Change Support Document
CH-ODCM-0001 Reference Use Page 55 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 7.0 BASIS 7.1 Instrumentation 7.1.1 Radioactive Liquid Effluent Instrumentation The Radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
7.1.2 Radioactive Gaseous Effluent Instrumentation The Radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip setpoints for these instruments shall be calculated in accordance with Part II of the Offsite Dose Calculation Manual to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
7.2 Radioactive Effluents 7.2.1 Radioactive Liquid Effluents A. Concentration NOTE: Xe-133 is remaining as the controlling isotope for noble gases, even though it is no longer present due to FCS no longer producing power, because it is more conservative than the remaining noble gases (e.g., Kr-85).
CH-ODCM-0001 Reference Use Page 56 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, and (2) the limits of 10 CFR Part 20.1001-20.2401 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-133 is the controlling isotope and its effluent concentration in air (submersion) was converted to an equivalent concentration in water.
B. Dose This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, with fresh water sites with drinking water supplies which can be potentially affected by facility operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in Part II of the Off-Site Dose Calculation Manual, implement the requirements in Section III.A that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Part II of the Off-Site Dose Calculation Manual, for calculating the doses due to the actual release rates of radioactive material in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
C. Liquid Waste Treatment System
CH-ODCM-0001 Reference Use Page 57 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 The FUNCTIONALITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective and in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified to ensure the design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents are not exceeded.
D. Liquid Holdup Tanks Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.
7.2.2 Radioactive Gaseous Effluents A. Concentration This specification, in conjunction with Steps 4.2.2A and 4.2.3A, is provided to ensure that the dose at or beyond the Site Boundary from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for MEMBERS OF THE PUBLIC. The release rate of radioactive material in airborne effluents shall be controlled such that the instantaneous concentrations for these radionuclides do not exceed the values specified in 10 CFR Part 20 for airborne effluents at the unrestricted area boundary. To support facility operations, RP/Chemistry supervision may increase this limit up to the limits specified in Technical Specifications 5.16.1.g. Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. Because these concentrations are applied on an instantaneous basis and because of the overriding 10 CFR Part 50 Appendix I cumulative dose limitations, these limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the Site Boundary, to
CH-ODCM-0001 Reference Use Page 58 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 annual average concentrations that would result in exceeding the annual total effective dose equivalent limit specified in 10 CFR Part 20.1301(a).
B. Dose - Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the Off-Site Dose Calculation Manual, for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The Off-Site Dose Calculation Manual, equations provided for determining the air doses at the site boundary are consistent with Regulatory Guides 1.109 and 1.111.
CH-ODCM-0001 Reference Use Page 59 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 7.2.2 (continued)
C. Dose - Radioactive Material in Particulate Form with Half-Lives Greater than Eight Days (Other than Noble Gases) and Tritium This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition For Operation implements the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept as low as is reasonably achievable. The surveillance requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in Part II of the Off-Site Calculation Manual, for calculating the doses due to actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. The release rate specification for radioactive material in particulate form with half-lives greater than eight days (other than noble gases) and tritium are dependent on the existing radionuclide pathways to man in the areas at or beyond the site boundary. The pathways that were examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
CH-ODCM-0001 Reference Use Page 60 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 7.2.2 (continued)
D. Gaseous Waste Treatment The FUNCTIONALITY of the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable. This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective and in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified to ensure the design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50 for gaseous effluents are not exceeded.
CH-ODCM-0001 Reference Use Page 61 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 7.2.2 (continued)
E. Total Dose - Uranium Fuel Cycle This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mRems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mRems. It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the facility remains within twice the dose design objectives of Appendix I, 10 CFR Part 50, and if direct radiation doses (including outside storage tanks, etc.) are kept small. The Special Report shall describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report, with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4) and 20.2203(b) is considered to be a timely request and fulfills the requirements 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. Demonstration of compliance with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR Part 20.1301.
CH-ODCM-0001 Reference Use Page 62 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 7.3 Radiological Environmental Monitoring 7.3.1 Monitoring Program The radiological environmental monitoring program required by this specification provides measurements of radiation and radioactive materials in those exposure pathways and for radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program was effective for at least the first three years of commercial operation.
Following this period, program changes are initiated based on operational experience.
7.3.2 Land Use Survey This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this survey. The frequency of the Land Use Survey has been reduced to a biennial requirement in site procedures because persons knowledgeable in land use census monitor usage characteristics perform routine REMP sampling. This approach allows knowledge gained during sample collection to be integrated into the program, maintaining its effectiveness. The best survey information from door to door, aerial or consulting with local agricultural authorities, or equivalent, shall be used. This survey satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the survey to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m 2.
For milk, the survey is restricted to only milk animals (cow or goat) producing milk for human consumption. Air monitoring stations are strategically located to monitor the resident receptors who could potentially receive the highest doses from airborne radioactive material. For groundwater, samples shall be taken when sources are determined to potentially be affected by facility operations, and when sources are tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. Guidance provided in the Branch Technical Position and Technical Specification 5.16.2 is used to meet the intent of NUREG-1301.
CH-ODCM-0001 Reference Use Page 63 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 7.3.3 Interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
7.4 Abnormal Release or Abnormal Discharge Reporting 7.4.1 Specific information should be reported concerning abnormal (airborne and/or liquid) releases on site and abnormal discharges to the unrestricted area. The report should describe each event in a way that would enable the NRC to adequately understand how the material was released and if there was a discharge to the unrestricted area. The report should describe the potential impact on the ingestion exposure pathway involving surface water and ground water, as applicable. The report should also describe the impact (if any) on other affected exposure pathways (e.g., inhalation from pond evaporation).
7.4.2 The following are the thresholds for reporting abnormal releases and abnormal discharges in the supplemental information section:
A. Abnormal release or Abnormal Discharges that are voluntarily reported to local authorities under NEI 07-07, Industry Ground Water Protection Initiative. [AR 39127]
B. Abnormal release or Abnormal discharges estimated to exceed 100 gallons of radioactive liquid where the presence of licensed radioactive material is positively identified (either in the on-site environs or in the source of the leak or spill) as greater than the minimum detectable activity for the laboratory instrumentation.
C. Abnormal releases to on-site areas that result in detectable residual radioactivity after remediation.
D. Abnormal releases that result in a high effluent radiation alarm without an anticipated trip occurring.
E. Abnormal discharges to an unrestricted area.
CH-ODCM-0001 Reference Use Page 64 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 7.4.3 Information on Abnormal releases or Abnormal discharges should include the following, as applicable:
Date and duration Location Volume Estimated activity of each radionuclide Effluent monitoring results (if any)
On-site monitoring results (is any)
Depth to the local water table Classification(s) of subsurface aquifer(s) (e.g., drinking water, unfit for drinking water, not used for drinking water)
Size and extent of any ground water plume Expected movement/mobility of any ground water plume Land use characteristics (e.g., water used for irrigation)
Remedial actions considered or taken and results obtained Calculated member of the public dose attributable to the release Calculated member of the public dose attributable to the discharge Actions taken to prevent recurrence, as applicable Whether the NRC was notified, the date(s), and the contact organization
CH-ODCM-0001 Reference Use Page 65 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 PART II CALCULATIONS
CH-ODCM-0001 Reference Use Page 66 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.0 EFFLUENT MONITOR SETPOINTS 1.1 Liquid Effluents 1.1.1 There is one liquid discharge pathway to the Missouri River. The pathway originates with the radioactive liquid waste processing system (monitor or hotel tanks). This pathway empties into the circulating water system which discharges to the Missouri River (see Figure 1). Figure 2 depicts the liquid discharge pathway and associated radiation monitor. Figure 3 depicts the methods of liquid effluent treatment.
1.1.2 The flowrate for dilution water varies with the number raw water pumps in service 1.1.3 Technical Specification 5.16.1.b establishes the administrative control limit on concentration of radioactive material, other than dissolved or entrained noble gases, released in liquid effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2.
For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 Ci/ml total activity.
1.1.4 The liquid effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
1.1.5 The liquid effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in liquid effluents at site discharge will be less than 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.
1.1.6 Cs-137 is used to calibrate the liquid effluent monitors.
CH-ODCM-0001 Reference Use Page 67 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.1.7 Liquid Effluent Radiation Monitor A. Overboard Discharge Header Monitor (RM-055)
- 1. This process radiation monitor provides control of the waste monitor tank effluent by monitoring the overboard header prior to its discharge into the circulating water discharge tunnel. The concentration of activity at discharge is controlled below ten times the 10 CFR Part 20 limit of 1.0E-06 Ci/ml at site discharge for unidentified isotopes by the high alarm setpoint which closes the overboard flow control valve.
- 2. The following calculations for maximum concentration and alarm setpoints are valid for radioactive liquid releases of monitor tank discharge.
- 3. The maximum allowable concentration in the overboard discharge header is:
(1.0 05 ) ()
=
Where:
1.0E-05 Ci/ml = Ten times 10 CFR Part 20 Limit for unidentified radionuclides at site discharge (10 CFR Part 20, Appendix B, Note 2).
F = Total dilution flow in the discharge tunnel (gpm).
(Normal flow is based on 2 raw water pumps at 7,200 gpm total.)
f = Maximum monitor tank discharge flow rate (gpm).
(Normal monitor tank maximum flow is 15 gpm.)
CMAX = Maximum allowable activity in discharge header (Ci/ml).
CH-ODCM-0001 Reference Use Page 68 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.1.7A (continued)
The High Alarm Setpoint (CPM):
= 0.75 [((3 )( )( )) + ]
Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to account for the difference in detector sensitivity for the range of isotopes detected.
Sf = Detector sensitivity factor (CPM/Ci/ml). (Sensitivity based on Cs-137).
K3 = Allocation factor for Waste Liquid Releases (See Table 1)
CMAX = Maximum allowable concentration in discharge header (Ci/ml).
B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one tenth (1/10) the value of the high alarm setpoint value so that significant increases in activity will be identified prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 69 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.2 Airborne Effluents 1.2.1 There are two air effluent discharge pathways at the Fort Calhoun Station:
Laboratory and Radioactive Waste Processing Building Exhaust Stack, and the Auxiliary Building Exhaust Stack. An airborne radioactive waste flow diagram with the applicable, associated radiation monitoring instrumentation and controls is presented as Figure 4. The airborne waste disposal system is presented in Figure 5.
Auxiliary Building - The Auxiliary Building Exhaust Stack receives discharges from the auxiliary building ventilation system. Radiation Monitor RM-062 provides noble gas monitoring and particulate sampling for the Auxiliary Building Exhaust Stack. Backup noble gas monitoring and particulate sampling is provided by RM-052.
Laboratory and Radioactive Waste Processing Building (LRWPB) - Noble gas monitoring and particulate sampling is provided by RM-043. This radiation monitor/sampler does not serve a control function.
Technical Specification 5.16.1.g. establishes the administrative control limit on the concentration resulting from radioactive material, other than noble gases, released in gaseous effluents to unrestricted areas conforming to ten times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1. For noble gases, the concentration shall be limited to five times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 1.
The airborne effluent monitoring instrumentation ALERT setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
The airborne effluent monitoring instrumentation HIGH ALARM setpoints shall be established low enough to ensure that the concentration of radioactive material released in air effluents at site discharge will be less than 5 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 1.
CH-ODCM-0001 Reference Use Page 70 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.2.2 Airborne Effluent Radiation Monitors NOTE: Xe-133 is remaining as the controlling isotope for noble gases, even though it is no longer present due to FCS no longer producing power, because it is more conservative than the remaining noble gases (e.g., Kr-85).
A. Auxiliary Building Exhaust Stack Noble Gas Activity Monitor (RM-062/RM-052)
- 1. Either of these monitors may be used to measure the noble gas activity in the exhaust stack. The noble gas is monitored after passing through a particulate filter, and charcoal cartridge. The monitor controls airborne releases so that five times the 10 CFR Part 20 limit at the unrestricted area boundary of 5.0E-07 Ci/cc, based upon Xe-133, is not exceeded.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from Auxiliary Building Exhaust Stack and the LRWPB Exhaust Stack.
- 3. The maximum allowable release rate for stack airborne activity is calculated as follows:
2.5 06
= ( ) 1.0 + 06 3 3
Where:
2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q sec/m3 = Annual average dispersion factor at the unrestricted area boundary from Part II Table 4, of the Off-Site Dose Calculation Manual.
1.0E+06 cc/m3 = Constant of unit conversion.
CH-ODCM-0001 Reference Use Page 71 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.2.2A (continued)
The High Alarm Setpoint (CPM):
( )( )(60)
= 0.75 [1 ( ) + ]
( )(28317)
Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.
Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133)
K1 = Allocation factor for Auxiliary Building Exhaust Stack (See Table 1) 60 = Conversion (seconds to minutes).
28317 = Conversion factor (ft3 to cc).
Fv = Auxiliary Building Exhaust stack flow rate (SCFM).
(Default maximum flow rate is 72,500 cfm for 3 Auxiliary Building exhaust fans in operation. Other flow rates may be used, as required.)
RMAX = Maximum Allowable Release Rate in Ci/sec B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 72 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.2.2 (continued)
B. Laboratory and Radioactive Waste Processing Building Exhaust Stack Noble Gas Activity Monitor and Particulate Sampler (RM-043)
- 1. RM-043 is located in the Radwaste Building and samples the LRWPB Exhaust Stack. The monitor alarm setpoint is based on five times the 10 CFR Part 20 limit for Xe-133 at the unrestricted area boundary.
- 2. The following calculations for maximum release rate and alarm setpoint are valid for simultaneous airborne releases from Auxiliary Building Exhaust Stack and the LRWPB Exhaust Stack.
2.5 06 sec = ( ) 1.0 + 06 3 3
The maximum allowable release rate for RM-043 is as follows:
Where:
2.5E-06 Ci/cc = 5 times the 10 CFR Part 20 Limit at the unrestricted area boundary (based upon Xe-133).
/Q = Annual average dispersion factor at the unrestricted area boundary from Part II of the Off-Site Dose Calculation Manual, Table 4.
1.0E+06 cc/m3 = Constant of unit conversion
CH-ODCM-0001 Reference Use Page 73 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 1.2.2B (continued)
NOTE i This monitor alarms in the Control Room. There are no automatic control functions associated with the actuation of i
the alarm.
The High Alarm Setpoint (CPM):
( )( )(60)
= 0.75 [2 ( ) + ]
( )(28317)
Where:
0.75 = An administrative correction factor which includes the following:
25% tolerance to allow for the contribution of noble gases other than Xe-133 towards the total ECL fraction sum.
Sf = Detector sensitivity factor (CPM/Ci/cc). (Sensitivity based on Xe-133)
K2 = Allocation factor for LRWPB Exhaust Stack (See Table 1) 60 = Conversion (seconds to minutes).
28317 = Conversion factor (ft3 to cc).
Fv = LRWPB Exhaust stack flow rate (SCFM). (Default flow rate is 28,700 cfm. Other flow rates may be used if required.)
RMAX = Maximum Allowable Release Rate in Ci/sec.
B = Background (CPM)
The Alert Setpoint will be chosen less than or equal to one fifth (1/5) the value of the high alarm setpoint value so that significant increases in activity will be identified, prior to exceeding an Unrestricted Area fractional sum of 1.0. It will also provide additional time for corrective actions prior to exceeding the Alarm Setpoint.
CH-ODCM-0001 Reference Use Page 74 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 1 - Allocation Factors for Simultaneous Releases NOTE i The Fort Calhoun Station is capable of performing simultaneous airborne releases.
The factors below may be adjusted to meet release requirements, provided that the sum of the Unrestricted Area Fraction Sum for all airborne releases remains less i
than or equal to 1.0.
A. Allocation Factors for Simultaneous Airborne Releases
- 1. Auxiliary Building Exhaust Stack Total: 0.90 K1 Noble Gases (RM-062 or RM-052) 0.75 Particulate/Tritium 0.15 Contributing Pathways:
a) Auxiliary Building 0.90
- 2. Laboratory and Radioactive Waste Building Exhaust Total: 0.10 Stack K2 Noble Gases (RM-043) 0.05 Particulate 0.05 Contributing Pathways:
a) Laboratory and Radioactive Waste Building Exhaust Stack 0.10 Airborne Release Total 1.00 B. Allocation Factors for Simultaneous Liquid Releases
- 1. K3 Waste Liquid Releases (RM-055) 1.00 Liquid Release Total 1.00
CH-ODCM-0001 Reference Use Page 75 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Figure 1 - Exclusion and Site Boundary Map
CH-ODCM-0001 Reference Use Page 76 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Figure 2 - Liquid Radioactive Discharge Pathways
CH-ODCM-0001 Reference Use Page 77 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Figure 3 - Liquid Radioactive Waste Disposal System
CH-ODCM-0001 Reference Use Page 78 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Figure 4 - Airborne Effluent Discharge Pathways
CH-ODCM-0001 Reference Use Page 79 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Figure 5 - Airborne Radioactive Waste Disposal System
CH-ODCM-0001 Reference Use Page 80 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 2.0 EFFLUENT CONCENTRATIONS 2.1 Liquid Effluent Concentrations 2.1.1 The concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) will be limited to the concentrations as specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. For batch releases (Monitor and Hotel Waste Tanks) the analyses will be performed in accordance with Part I, Table 4.1, of the Off-Site Dose Calculation Manual, and the concentration of each radionuclide at site discharge will be calculated, based on the following equation:
=
+
1
=1 Radionuclide concentration at site discharge:
Where:
Ai = concentration at site discharge for radionuclide (I), in Ci/ml.
ai = concentration of radionuclide (I) in the undiluted effluent, in Ci/ml.
f = undiluted effluent flowrate, in gpm.
F = total diluted effluent flowrate in gpm.
weci = water effluent concentration limit for radionuclide (I) per 10 CFR Part 20, Appendix B, Table 2, Column 2.
NOTE i In addition to the above defined method, Notes 1 through 4 of 10 CFR Part 20, Appendix B, will also be applicable.
i 2.2 Airborne Effluent Concentrations 2.2.1 The concentration at the unrestricted area boundary, due to airborne effluent releases, will be limited to less than Appendix B, Table 2, Column 1, values.
Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event an airborne effluent release from the station result in an alarm setpoint being exceeded, an evaluation of the unrestricted area boundary concentration resulting from the release will be performed:
CH-ODCM-0001 Reference Use Page 81 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 2.2.2 To determine the concentration and air effluent concentration (aec) fraction summation at the unrestricted area boundary, the following equations will be used:
= 0 ( )
1
=1 Where:
Ai = Concentration of radionuclide (I) at the unrestricted area boundary K0 = Constant of unit conversion. (1.0E-6 m3/cc)
ECLi = Effluent concentration limit (10 CFR Part 20, Appendix B, Table 2, Column 1 value for radionuclide(I))
Qi = The release rate of radionuclide (I) in airborne effluents from all vent releases (in Ci/sec.)
(/Q) = Annual Average Dispersion Factor at the Unrestricted Area Boundary from Part II, Table 4, of the Off-Site Dose Calculation Manual.
2.2.3 As appropriate, simultaneous releases from the Auxiliary Building Ventilation Stack and Laboratory and Radwaste Building Stack will be considered in evaluating compliance with the release rate limits of 10 CFR Part 20.
Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. Historical annual average dispersion parameters, as presented in Table 4, may be used for evaluating the airborne effluent dose rate.
2.2.4 For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding those more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding 10 CFR Part 20 limits. Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based upon the above criteria, no further analyses are required for demonstrating compliance with 10 CFR Part 20.
CH-ODCM-0001 Reference Use Page 82 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.0 RADIOACTIVE EFFLUENT DOSE CALCULATIONS 3.1 Liquid Effluent Dose Calculations 3.1.1 Three pathways for human exposure to liquid releases from FCS to the Missouri River exists: 1) fish, 2) drinking water, and 3) Shoreline deposition.
Fish are considered to be taken from the vicinity of the facility discharge.
The drinking water for Omaha is located 19 miles downstream from FCS.
The dilution factors for these pathways are derived from the Revised Environmental Report for FCS, (1974), (page 4-29 and 4-31). This report states that during Low-Low river conditions, the concentration at Omaha's water intake will be < 14% of the concentration at discharge from FCS and will average 3%. This equates to a dilution factor of 7.14, which is used to calculate the maximum dose to an individual from liquid pathways and a dilution factor of 33.33, for calculating the average dose. All pathways combine to give the dose to an individual in unrestricted areas.
3.1.2 10 CFR Part 50, Appendix I restricts the dose to individuals in the unrestricted areas from radioactive materials in liquid effluents from the Fort Calhoun Station to the following limits:
during any calendar quarter 1.5 mrem to total body 5.0 mrem to any organ and during any calendar year 3.0 mrem to total body 10.0 mrem to any organ The following calculational methods shall be used for determining the dose or dose commitment from liquid effluents.
CH-ODCM-0001 Reference Use Page 83 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.1.3 Doses from Liquid Effluent Pathways A. Potable Water
= 1100 exp( )
=1 Where:
Rapj = is the total annual dose to organ(j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr.
Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in
/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless.
(Table 17)
F = is the flow rate of the liquid effluent, in ft3/ sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Daipj = is the dose factor specific to a given age group (a),
radionuclide (I), pathway (p), and organ (j) which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = is the radiological decay constant of radionuclide (I), in hr 1.
tp = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the radionuclides and ingestion of water, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 84 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.1.3 (continued)
B. Aquatic Foods
= 1100 exp( )
=1 Where:
Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p), in mrem/yr.
Uap = is a usage factor that specifies the intake rate for an individual of age group (a) associated with pathway (p), in kg/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless. (Table 17)
F = is the flow rate of the liquid effluent, in ft3/sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Bip = is the equilibrium bioaccumulation factor for radionuclide (I) in pathway (p) expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in (pCi/kg)/(pCi/liter). (Table 3)
Daipj = is the dose factor specific to a given age group (a),
radionuclide (I), pathway (p), and organ (j), which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. (Tables 13-16) i = is the radiological decay constant of radionuclide (I), in hr-1.
tp = is the average transit time required for radionuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the radionuclides and ingestion of food, in hours. (Table 17) 1100 = Constant (pCi
- yr
- ft3/Ci
- sec
- L)
CH-ODCM-0001 Reference Use Page 85 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.1.3 (continued)
C. Shoreline Deposits
= 110,000 [exp( )] [1 exp( )]
=1 Where:
Rapj = is the total annual dose to organ (j) of individuals of age group (a) from all of the radionuclides (I) in pathway (p),
in mrem/yr.
Uap = is a usage factor that specifies the exposure time for an individual of age group (a) associated with pathway (p),
in hr/yr. (Table 6)
Mp = is the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless. (Table 17)
W = is the shore-width factor, dimensionless. (Table 17)
F = is the flow rate of the liquid effluent, in ft3/sec.
Qi = is the annual release rate of radionuclide (I), in Ci/yr.
Tip = is the radioactive half life of radionuclide (I), in days.
Daipj = is the dose factor specific radionuclide (I) which can be used to calculate the radiation dose from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the real radionuclide concentration (in pCi/m2). (Table 8) i = is the radiological decay constant of radionuclide (I), in hr-1.
tp = is the average transit time required for radionuclides to reach the point of exposure, in hours. (Table 17) tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours. (Table 17) 110,000 = Constant [(100
- pCi
- yr
- ft3)/(Ci
- sec
- L)]
CH-ODCM-0001 Reference Use Page 86 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2 Airborne Effluent Dose Calculations 3.2.1 Noble Gas 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from noble gases in airborne effluents from the Fort Calhoun Station to the following limits:
During any calendar quarter 5 mrad-gamma air dose 10 mrad-beta air dose and During any calendar year 10 mrad-gamma air dose 20 mrad-beta air dose The following general equations shall be used to calculate the gamma-air and beta-air doses:
A. Doses from Noble Gases
- 1. Annual Gamma/Beta Air Dose from All Other Noble Gas Releases
(, ) (, ) = 3.17 104 [] (, )( )
=1 Where:
DFi or DFi = are the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide (I), in mrad-m3/pCi-yr. (Table 2)
D (r,) or D(r,) = are the annual gamma and beta air doses at distance r, in the sector at angle , from the discharge point, in mrad/yr.
Qi = is the annual release rate of radionuclide (I),
in Ci/yr.
[/Q]D(r,) = is the annual average gaseous dispersion factor at distance r, in the sector at angle , in sec/m3.
(Table 4) 3.17x104 = is the number of pCi per Ci divided by the number of seconds per year.
CH-ODCM-0001 Reference Use Page 87 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.1A (continued)
- 2. Annual Total Body Dose from All Other Noble Gas Releases
(,
) = (, )
=1 Where:
DFBi = is the total body dose factor for a semi-infinite cloud of the radionuclide (I), which includes the attenuation of 5 g/cm2 of tissue, in mrem-m3/pCi-yr. (Table 2)
(r,) = is the annual total body dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle , in mrem/yr.
Xi(r,) = is the annual average ground-level concentration of radionuclide (I) at distance r, in the sector at angle , in pCi/m3. (Table 4)
Sf = Shielding Factor (Table 17)
CH-ODCM-0001 Reference Use Page 88 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31
- 3. Annual Skin Dose from All Other Noble Gas Releases
(,
) = 1.11 (, ) + (, )
=1 =1 Where:
(r,) = is the annual skin dose due to immersion in a semi-infinite cloud at distance r, in the sector at angle , in mrem/yr.
Xi(r,) = is the annual average ground-level concentration of radionuclide (I) at distance r, in the sector at angle , in pCi/m3. (Table 4)
Sf = Shielding Factor (Table 17)
DFSi = is the beta skin dose factor for a semiinfinite cloud of radionuclide (I), in mrem-m3/pCi-yr.
(Table 2)
= is the gamma skin dose factor for a semiinfinite cloud of radionuclide (I), in mrem-m3/pCi-yr.
(Table 2) 1.11 = is the average ratio of tissue to air energy absorption coefficients.
CH-ODCM-0001 Reference Use Page 89 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.2 Radioiodine, Tritium, and Particulates 10 CFR Part 50, Appendix I, restricts the dose to individuals in the unrestricted areas from radioactive materials in gaseous airborne from the Fort Calhoun Station to:
During any calendar quarter 7.5 mrem to any organ and During any calendar year 15 mrem to any organ The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in airborne effluents released to unrestricted areas should be determined by the following expressions:
CH-ODCM-0001 Reference Use Page 90 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.2 (continued)
NOTE i In all cases, for releases of tritium, use the dispersion parameter for inhalation (/Q).
i A. Annual Organ Dose from External Irradiation from Radioactivity Deposited on the Ground Plane The ground plane concentration of radionuclide (I) at distance r, in the sector at angle , with respect to the release point, may be determined by:
[1.01012 ][ (, ) ]
(, ) = [1 exp( )]
Where:
CGI = is the ground plane concentration of the radionuclide (I) at distance r, in the sector at angle , from the release point, in pCi/m2.
Qi = is the annual release rate of radionuclide (I) to the atmosphere, in Ci/yr.
tb = is the time period over which the accumulation is evaluated, which is assumed to be 20 years (mid-point of plant operating life). (Table 17) i(r,) = is the annual average relative deposition of radionuclide (I) at distance r, in the sector at angle , considering depletion of the plume by deposition during transport, in m-2. Table 4 i = is the radiological decay constant for radionuclide (I), in yr-1.
1.0x1012 = is the number of pCi/Ci
CH-ODCM-0001 Reference Use Page 91 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.2A (continued)
The annual organ dose is then calculated using the following equation:
(, ) = 8760 (, )
=1 Where:
CGj(r,) = is the ground plane concentration of radionuclide (i) at distance r, in the sector at angle , in pCi/m2.
DFGij = is the open field ground plane dose conversion factor for organ (j) from radionuclide (i), in mrem-m2/pCi-hr.
(Table 8)
DGj(r,) = is the annual dose to the organ (j) at distance r, in the sector at angle , in mrem/yr.
Sf = is the shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy, dimensionless. (Table 17) 8760 = is the number of hours in a year B. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide (i) at distance r, in the sector at angle , with respect to the release point, may be determined as:
(, ) = 3.17 104 [] (, )
Where:
Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
[/Q]D (r,) = is the annual average atmosphere dispersion factor, in sec/m3 (see Reg Guide 1.111). This includes depletion (for radioiodines and particulates) and radiological decay of the plume. (Table 4) 3.17x104 = is the number of pCi/Ci divided by the number of sec/yr.
CH-ODCM-0001 Reference Use Page 92 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.2B (continued)
The annual dose associated with inhalation of all radionuclides to organ (j) of an individual in age group (a), is then:
(, ) = (, )
=1 Where:
DAja(r,) = is the annual dose to organ (j) of an individual in the age group (a) at distance r, in the sector at angle , due to inhalation, in mrem/yr.
Ra = is the annual air intake for individuals in the age group (a), in m3/yr. (Table 6) i(r,) = is the annual average ground-level concentration of radionuclide (i) in air at distance r, in the sector at angle
, in pCi/m3.
DFAija = is the inhalation dose factor for radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 9-12)
CH-ODCM-0001 Reference Use Page 93 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.3 Concentrations of Radionuclides in Foods and Vegetation from Atmospheric Releases A. Parameters for Calculating Concentrations in Forage, Produce, and Leafy Vegetables, excluding Tritium
[1 exp( )] [1 exp( )]
(, ) = (, ) [ + ] exp( )
Where:
CVi(r,) = is the concentration of radionuclide (i) in and on vegetation at distance r, in the sector at angle , in pCi/kg.
di (r,) = is the deposition rate of radionuclide (i) at distance r, in the sector at angle , in pCi/m2 hr.
r = is the fraction of deposited activity retained on crops, dimensionless. (Table 17)
Ei = is the effective removal rate constant for radionuclide (i) from crops, in hr-1.
Ei = i + w w = 0.0021/hr. (Table 17) te = is the time period that crops are exposed to contamination during the growing season, in hours.
(Table 17)
Yv = is the agricultural productivity (yield) in kg (wet weight)/m2. (Table 17)
Biv = is the concentration factor for uptake of radionuclide (i) from soil by edible parts of crops, in pCi/ kg (wet weight) per pCi/kg dry soil. (Table 5) i = is the radiological decay constant of radionuclide (I), in hr-1 tb = is the period of time for which sediment or soil is exposed to the contaminated water, in hours (mid-point of plant life). (Table 17)
P = is the effective "surface density" for soil, in kg (dry soil)/m2. (Table 17) th = is the holdup time that represents the time interval between harvest and consumption of the food, in hours.
(Table 17)
Different values for the parameters te, Yv, and th, may be used to allow the use of the Equation for different purposes: estimating concentrations in produce consumed by man; in leafy vegetables consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or goats; and in forage consumed as stored feed by dairy cows, beef cattle or goats. See Table 17.
CH-ODCM-0001 Reference Use Page 94 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.3A (continued)
The deposition rate from the plume is defined by (Reg. Guide 1.109, Rev. 1, Page 1.109-26, Equa. C-6):
(, ) = 1.1 108 (, )
Where:
di(r,) = is the deposition rate of radionuclide (i).
i(r,) = is the relative deposition of radionuclide (i), considering depletion and decay, in m-2 (see Reg Guide 1.111).
(Table 4) 1.1x108 = is the number of pCi/Ci (1012) divided by the number of hours per year (8760).
Qi = is the annual release rate of radionuclide (i) to the atmosphere, in Ci/yr.
CH-ODCM-0001 Reference Use Page 95 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.3 (continued)
B. For radioiodines, the model considers only the elemental fraction of the effluent:
(, ) = 3.3 107 (, )
Where:
di (r, ) = The deposition rate of radioiodine (i).
3.3 x 107 = The number of pCi/Ci (1012) divided by the number of hours per year (8760), then multiplied by the amount of radioiodine emissions considered to be elemental (0.5).
i (r, ) = The relative deposition of radioiodine (i), considering depletion and decay, in m-2. (Table 4)
Qi = The total (elemental and nonelemental) radioiodine (i) emission rate.
C. Parameters for Calculating the Concentration of Radionuclide (i) in the Animal's Feed (Milk Cow, Beef Cow, and Goat)
(, ) = (, ) + (1 ) (, ) + (1 ) (, )
Where:
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
CPi(r,) = is the concentration of radionuclide (i) on pasture grass (calculated using Equation 3.2.3A with th=0), in pCi/kg.
CSi(r,) = is the concentration of radionuclide (i) in stored feeds (calculated using Equation 3.2.3A with th=90 days), in pCi/kg.
fp = is the fraction of the year that animals graze on pasture. (Table 17) fs = is the fraction of daily feed that is pasture grass while the animal grazes on pasture. (Table 17)
CH-ODCM-0001 Reference Use Page 96 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.4 Parameters for Calculating Radionuclide Concentration in Cow and Goat Milk
(, ) = (, ) exp( )
Where:
CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter.
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
Fm = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each liter of milk, in days/liter.
(Table 5)
QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7) tf = is the average transport time of the radionuclide (i) from the feed to the milk and to the receptor (a value of 2 days is assumed). (Table 17) i = is the radiological decay constant of radionuclide (i), in days-1.
CH-ODCM-0001 Reference Use Page 97 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.5 Parameters for Calculating Radionuclide Concentration in Cow Meat, excluding Tritium
(, ) = (, ) exp( )
Where:
CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter.
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
QF = is the amount of feed consumed by the animal per day, in kg/day. (Table 7)
Ff = is the average fraction of the animal's daily intake of radionuclide (i) which appears in each kilogram of flesh, in days/kilogram. (Table 5) ts = is the average time from slaughter to consumption. (Table 17) 3.2.6 Parameters for Calculating Tritium Concentrations in Vegetation The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.
[](, )(0.75)(0.5) [](, )
(, ) = 3.17 107 = 1.2 107 Where:
CVT(r, ) = is the concentration of tritium in vegetation grown at distance r, in the sector at angle , in pCi/kg.
H = is the absolute humidity of the atmosphere at distance r, in the sector at angle , in g/m3. H=8 gm/kg.
QT = is the annual release rate of tritium, in Ci/yr.
[/Q](r,) = is the atmospheric dispersion factor, in sec/m3. (Table 4) 0.5 = is the ratio of tritium concentration in facility water to tritium concentration in atmospheric water, dimensionless.
0.75 = is the fraction of total facility mass that is water, dimensionless.
CH-ODCM-0001 Reference Use Page 98 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.7 Annual Dose from Atmospherically Released Radionuclides in Foods A. The total annual dose to organ (j) of an individual in age group (a) resulting from ingestion of all radionuclides in produce, milk, and leafy vegetables is given by:
(
, ) = [ (, ) + (, ) + (, ) + (, )]
Where:
DDja(r,) = is the annual dose to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. Tables 13-16.
UVa = are the ingestion rates of produce (non-leafy vegetables, fruits, and grains) , respectively for individuals in age group (a).
(Table 6)
UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6)
UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6)
ULa = are the ingestion rates of leafy vegetables for individuals in age group (a), in kg/yr. (Table 6)
CVi (r,) = is the concentration of radionuclide (i) in the animal's feed, in pCi/kg.
CMi (r,) = is the concentration of radionuclide (i) in milk, in pCi/liter.
CFi (r,) = is the concentration of radionuclide (i) in meat, in pCi/liter.
CLI (r,) = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.
fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 99 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 3.2.7 (continued)
B. Calculating the Ingested Dose from Leafy and Non-Leafy (produce)
Vegetation for Radionuclide (i) to Each Organ (j) and Age Group (a)
(, ) = [ (, ) + (, )]
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i) to organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in vegetation, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pci. Tables 13-16 ULa,UVa = are the ingestion rates of leafy vegetables and produce (non-leafy vegetables, fruits, and grains), for individuals in age group (a), in kg/yr. (Table 6)
CLi = is the concentration of radionuclide (i) in and on leafy vegetation, in pCi/kg.
CVi = is the concentration of radionuclide (i) in and on produce, in pCi/kg.
fg = Fraction of ingested produce grown in garden of interest (Table 17) f = Fraction of leafy vegetables grown in garden of interest (Table 17)
CH-ODCM-0001 Reference Use Page 100 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 C. Calculation Determining the Ingested Dose from Cow Milk for Radionuclide (i), Organ (j), and Age Group (a)
(, ) = [ (, )]
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in cow milk, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16)
UMa = is the ingestion rate of cow milk for individuals in age group (a), in /yr. (Table 6)
CMi = is the radionuclide concentration in cow milk, in pCi/kg.
Equation 3.2.4 D. Calculation Determining the Ingested Dose from Meat for Radionuclide (i) to Organ (j) and Age Group (a)
(, ) = [ (, )]
Where:
DDja(r,) = is the annual dose from the ingestion of radionuclide (i), organ (j) of an individual in age group (a) from dietary intake of atmospherically released radionuclides in meat, in mrem/yr.
DFIija = is the dose conversion factor for the ingestion of radionuclide (i), organ (j), and age group (a), in mrem/pCi. (Tables 13-16)
UFa = is the ingestion rate of meat for individuals in age group (a), in kg/yr. (Table 6)
CFi = is the radionuclide (i) concentration in meat, in pCi/kg.
3.2.8 Annual Dose from Carbon 14 A. This is a calculated value based on power generation and days of operation. Critical organ doses from C-14 were calculated using a ratio of 15% as CO2. This ratio was determined during an NRC in-plant source term study conducted at the Fort Calhoun Station between 1976 and 1977, NUREG/CR-0140.
CH-ODCM-0001 Reference Use Page 101 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 4.0 LOWER LIMIT OF DETECTION (LLD) 4.1 The lower limit of detection (LLD) for liquid and airborne effluent discharges and environmental samples referenced in Part I, Tables 4.1, 4.2 and 5.3, of the Off-Site Dose Calculation Manual, is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
4.2 For a particular measurement system, which may include radiochemical separation:
4.66
=
exp()
Where:
LLD = the lower limit of detection as defined above, in either picoCuries or microCuries, per unit mass or volume as a function of the value of D Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate, as counts per minute E = the counting efficiency, as counts per disintegration V = the sample size in units of mass or volume D = 2.22E+06 of disintegrations per minute per microCurie or 2.22 disintegrations per minute per picoCurie Y = the fractional radiochemical yield, when applicable
= the radioactive decay constant for the particular radionuclide t = the elapsed time between the midpoint of sample collection and time of counting Appropriate values of E, V, Y, and t should be used in the calculation.
4.3 It should be recognized that the LLD is defined as an A Priori limit representing the capability of a measurement system and not as a limit for a particular measurement.
4.4 LLD verifications will be performed on a periodic basis. This determination is to ensure that the counting system is able to detect levels of radiation at the LLD values for the specific type of analysis required. They will be performed with a blank (non-radioactive) sample in the same counting geometry as the actual sample.
CH-ODCM-0001 Reference Use Page 102 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 2 - Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Nuclide -Air1 (Dfi) -Skin2 (DFSi) -Air1 (Dfi) -Body2 (DFBi)
Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11E-03 4.67E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 3
1.
3 2.
CH-ODCM-0001 Reference Use Page 103 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 3 - Bioaccumulation Factors (pCi/kg per pCi/liter)
FRESHWATER Element Fish Invertebrate H 9.0E-01 9.0E-01 C 4.6E+03 9.1E+03 Na 1.0E+02 2.0E+02 P 1.0E+05 2.0E+04 Cr 2.0E+02 2.0E+03 Mn 4.0E+02 9.0E+04 Fe 1.0E+02 3.2E+03 Co 5.0E+01 2.0E+02 Ni 1.0E+02 1.0E+02 Cu 5.0E+01 4.0E+02 Zn 2.0E+03 1.0E+04 Br 4.2E+02 3.3E+02 Rb 2.0E+03 1.0E+03 Sr 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+03 Zr 3.3E+00 6.7E+00 Nb 3.0E+04 1.0E+02 Mo 1.0E+01 1.0E+01 Tc 1.5E+01 5.0E+00 Ru 1.0E+01 3.0E+02 Rh 1.0E+01 3.0E+02 Te 4.0E+02 6.1E+03 I 1.5E+01 5.0E+00 Cs 2.0E+03 1.0E+03 Ba 4.0E+00 2.0E+02 La 2.5E+01 1.0E+03 Ce 1.0E+00 1.0E+03 Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E+03 W 1.2E+03 1.0E+01 Np 1.0E+01 4.0E+02
CH-ODCM-0001 Reference Use Page 104 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 4 - Highest Potential Exposure Pathways for Estimating Dose NOTE i The Annual Radiological Effluent Report uses the highest calculated value from real time meteorological data obtained for the entire year for calculating i dose.
Distance
/Q A D/Q A Exposure from Location B Direction B {/Q (r,)} { (r,)}
Pathway Containment (sec/m3) (m-2)
(miles) B Direct Exposure Site NW 0.29 4.90E-05 N/A Boundary Inhalation Site NW 0.29 4.90E-05 N/A Boundary Ingestion Residence SSE 0.60 N/A 7.6E-08 A. These values are used for calculating quarterly dose estimates during the annual reporting period and are based on a 2 year average, updated only upon a +10%
change from the previous value. At least ten percent (10%) should be added to these values for dose estimates during the reporting periods.
B. The location is subject to change based on an annual evaluation and is utilized only for ingestion exposure pathway dose estimates. This location may differ from the highest ingestion exposure pathway for offsite air monitoring locations as determined by the Land Use Survey performed biennially in accordance with Part 1, Section 7.3.2, of the Off-Site Dose Calculation Manual.
CH-ODCM-0001 Reference Use Page 105 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 5 - Stable Element Transfer Data Biv Fm (cow) Fm (goat) Ff Element Veg./Soil Milk (d/I) Milk (d/I) Meat (d/kg)
H 4.8E+00 1.0E-02 1.7E-01 1.2E-02 C 5.5E+00 1.2E-02 1.0E-01 3.1E-02 Na 5.2E-02 4.0E-02 ------ 3.0E-02 P 1.1E+00 2.5E-02 2.5E-01 4.6E-02 Cr 2.5E-04 2.2E-03 ------ 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 1.3E-04 4.0E-02 Co 9.4E-03 1.0E-03 ------ 1.3E-02 Ni 1.9E-02 6.7E-03 ------ 5.3E-02 Cu 1.2E-01 1.4E-02 1.3E-02 8.0E-03 Zn 4.0E-01 3.9E-02 ------ 3.0E-02 Rb 1.3E-01 3.0E-02 ------ 3.1E-02 Sr 1.7E-02 8.0E-04 1.4E-02 6.0E-04 Y 2.6E-03 1.0E-05 ------ 4.6E-03 Zr 1.7E-04 5.0E-06 ------ 3.4E-02 Nb 9.4E-03 2.5E-03 ------ 2.8E-01 Mo 1.2E-01 7.5E-03 ------ 8.0E-03 Tc 2.5E-01 2.5E-02 ------ 4.0E-01 Ru 5.0E-02 1.0E-06 ------ 4.0E-01 Rh 1.3E+1 1.0E-02 ------ 1.5E-03 Ag 1.5E-01 5.0E-02 ------ 1.7E-02 Sb 1.1E-02 1.5E-03 ------ 4.0E-03 Te 1.3E+00 1.0E-03 ------ 7.7E-02 I 2.0E-02 6.0E-03 6.0E-02 2.9E-03 Cs 1.0E-02 1.2E-02 3.0E-01 4.0E-03 Ba 5.0E-03 4.0E-04 ------ 3.2E-03 La 2.5E-03 5.0E-06 ------ 2.0E-04 Ce 2.5E-03 1.0E-04 ------ 1.2E-03 Pr 2.5E-03 5.0E-06 ------ 4.7E-03 Nd 2.4E-03 5.0E-06 ------ 3.3E-03 W 1.8E-02 5.0E-04 ------ 1.3E-03 Pu 2.5E-04 2.0E-06 ------ 1.4E-05 Np 2.5E-03 5.0E-06 ------ 2.0E-04 Am 2.5E-04 5.0E-06 ------ 2.0E-04 Cm 2.5E-03 5.0E-06 ------ 2.0E-04
CH-ODCM-0001 Reference Use Page 106 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 6 - Recommended Values for Uap to Be Used for the Maximum Exposed Individual in Lieu of Site Specific Data Pathway Infant Child Teen Adult Fruits, vegetables, & grain (kg/yr) --- 520 630 520 Leafy vegetables (kg/yr) --- 26 42 64 Milk (/yr) 330 330 400 310 Meat & poultry (kg/yr) --- 41 65 110 Fish (fresh or salt)(kg/yr) --- 6.9 16 21 Other Seafood (kg/yr) --- 1.7 3.8 5 Drinking water (/yr) 330 510 510 730 Shoreline recreation (hr/yr) --- 14 67 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table 7 - Animal Consumption Rates Animal QF Feed or Forage [Kg/day (wet weigh)] QAW Water (/day)
Milk Cow 50 60 Beef Cattle 50 50 Goats 6 8
CH-ODCM-0001 Reference Use Page 107 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin H-3 --- ---
C-14 --- ---
Na-24 2.50E-08 2.90E-08 P-32 --- ---
Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 --- ---
Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-59 --- ---
Ni-63 --- ---
Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 --- ---
Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 --- ---
Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09
CH-ODCM-0001 Reference Use Page 108 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Sb-124 1.30E-08 1.50E-08 Sb-125 3.10E-09 3.50E-09 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 --- ---
Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09
CH-ODCM-0001 Reference Use Page 109 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 8 - External Dose Factors for Standing on Contaminated Ground (mrem/hr per pCi/m2)
Element Total Body Skin Pu-238 1.30E-12 1.80E-11 Pu-239 7.90E-13 7.70E-12 Pu-240 1.30E-12 1.80E-11 Pu-241 4.60E-12 6.80E-12 Np-239 9.50E-10 1.10E-09 Am-241 1.80E-10 2.60E-10 Cm-242 5.50E-12 2.30E-11 Cm-243 2.30E-09 2.90E-09 Cm-244 2.90E-12 1.80E-11
CH-ODCM-0001 Reference Use Page 110 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 8.98E-08 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 --- --- --- 1.08E-05 Cr-51 --- --- 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 --- 4.95E-06 7.87E-07 --- 1.23E-06 1.75E-04 9.67E-06 Mn-56 --- 1.55E-10 2.29E-11 --- 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 --- --- 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 --- --- 1.27E-04 2.35E-05 Co-58 --- 1.98E-07 2.59E-07 --- --- 1.16E-04 1.33E-05 Co-60 --- 1.44E-06 1.85E-06 --- --- 7.46E-04 3.56E-05 Ni-59 4.06E-06 1.46E-06 6.77E-07 --- --- 8.20E-06 6.11E-07 Ni-63 5.40E-05 3.93E-06 1.81E-06 --- --- 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 --- --- 7.00E-07 1.54E-06 Cu-64 --- 1.83E-10 7.69E-11 --- 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 --- 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 --- 5.27E-12 1.15E-07 2.04E-09 Br-83 --- --- 3.01E-08 --- --- --- 2.90E-08 Br-84 --- --- 3.91E-08 --- --- --- 2.05E-13 Br-85 --- --- 1.60E-09 --- --- --- ---
Rb-86 --- 1.69E-05 7.37E-06 --- --- --- 2.08E-06 Rb-88 --- 4.84E-08 2.41E-08 --- --- --- 4.18E-19 Rb-89 --- 3.20E-08 2.12E-08 --- --- --- 1.16E-21 Sr-89 3.80E-05 --- 1.09E-06 --- --- 1.75E-04 4.37E-05 Sr-90 3.59E-03 --- 7.21E-05 --- --- 1.20E-03 9.02E-05 Sr-91 7.74E-09 --- 3.13E-10 --- --- 4.56E-06 2.39E-05 Sr-92 8.43E-10 --- 3.64E-11 --- --- 2.06E-06 5.38E-06 Y-90 2.61E-07 --- 7.01E-09 --- --- 2.12E-05 6.32E-05 Y-91M 3.26E-11 --- 1.27E-12 --- --- 2.40E-07 1.66E-10 Y-91 5.78E-05 --- 1.55E-06 --- --- 2.13E-04 4.81E-05 Y-92 1.29E-09 --- 3.77E-11 --- --- 1.96E-06 9.19E-06 Y-93 1.18E-08 --- 3.26E-10 --- --- 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 --- 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 --- 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 --- 9.67E-07 6.31E-05 1.30E-05 Mo-99 --- 1.51E-08 2.87E-09 --- 3.64E-08 1.14E-05 3.10E-05 Tc-99M 1.29E-13 3.64E-13 4.63E-12 --- 5.52E-12 9.55E-08 5.20E-07
CH-ODCM-0001 Reference Use Page 111 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 5.22E-15 7.52E-15 7.38E-14 --- 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 --- 8.23E-08 --- 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 --- 3.89E-11 --- 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 --- 1.09E-06 --- 1.67E-05 1.17E-03 1.14E-04 Ag-110M 1.35E-06 1.25E-06 7.43E-07 --- 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 --- 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 --- 2.18E-04 1.26E-05 Te-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 --- 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 --- 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 --- 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 --- 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 --- 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 --- 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 --- 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 --- 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 --- 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 --- 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 --- 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 --- 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 --- 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 --- 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 --- --- 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 --- --- 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 --- 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 --- 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 --- 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 --- 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 --- 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 --- 4.45E-07 2.76E-05 2.16E-05
CH-ODCM-0001 Reference Use Page 112 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 9 - Inhalation Dose Factors for Adult (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.06E-09 8.85E-10 3.10E-10 --- --- 3.63E-06 1.94E-05 Pu-238 1.43E+00 9.71E-01 6.90E-02 --- 2.96E-01 1.82E-01 4.52E-05 Pu-239 1.66E+00 1.07E+00 7.75E-02 --- 3.30E-01 1.72E-01 4.13E-05 Pu-240 1.65E+00 1.07E+00 7.73E-02 --- 3.29E-01 1.72E-01 4.21E-05 Pu-241 3.42E-02 8.69E-03 1.29E-03 --- 5.93E-03 1.52E-04 8.65E-07 Np-239 2.87E-08 2.54E-08 1.55E-09 --- 8.75E-09 4.70E-06 1.49E-05 Am-241 1.68E+00 1.13E+00 6.71E-02 --- 5.04E-01 6.06E-02 4.60E-05 Cm-242 2.22E-02 1.77E-02 9.84E-04 --- 4.48E-03 3.92E-02 4.91E-05 Cm-243 1.10E+00 7.61E-01 4.61E-02 --- 2.15E-01 6.31E-02 4.84E-05 Cm-244 8.37E-01 5.88E-01 3.51E-02 --- 1.64E-01 6.06E-02 4.68E-05
CH-ODCM-0001 Reference Use Page 113 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 9.06E-08 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 --- --- --- 1.16E-05 Cr-51 --- --- 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 --- 6.39E-06 1.05E-06 --- 1.59E-06 2.48E-04 8.35E-06 Mn-56 --- 2.12E-10 3.15E-11 --- 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 --- --- 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 --- --- 1.91E-04 2.23E-05 Co-58 --- 2.59E-07 3.47E-07 --- --- 1.68E-04 1.19E-05 Co-60 --- 1.89E-06 2.48E-06 --- --- 1.09E-03 3.24E-05 Ni-59 5.44E-06 2.02E-06 9.24E-07 --- --- 1.41E-05 6.48E-07 Ni-63 7.25E-05 5.43E-06 2.47E-06 --- --- 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 --- --- 1.17E-06 4.59E-06 Cu-64 --- 2.54E-10 1.06E-10 --- 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 --- 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 --- 7.53E-12 1.98E-07 3.56E-08 Br-83 --- --- 4.30E-08 --- --- --- ---
Br-84 --- --- 5.41E-08 --- --- --- ---
Br-85 --- --- 2.29E-09 --- --- --- ---
Rb-86 --- 2.38E-05 1.05E-05 --- --- --- 2.21E-06 Rb-88 --- 6.82E-08 3.40E-08 --- --- --- 3.65E-15 Rb-89 --- 4.40E-08 2.91E-08 --- --- --- 4.22E-17 Sr-89 5.43E-05 --- 1.56E-06 --- --- 3.02E-04 4.64E-05 Sr-90 4.14E-03 --- 8.33E-05 --- --- 2.06E-03 9.56E-05 Sr-91 1.10E-08 --- 4.39E-10 --- --- 7.59E-06 3.24E-05 Sr-92 1.19E-09 --- 5.08E-11 --- --- 3.43E-06 1.49E-05 Y-90 3.73E-07 --- 1.00E-08 --- --- 3.66E-05 6.99E-05 Y-91M 4.63E-11 --- 1.77E-12 --- --- 4.00E-07 3.77E-09 Y-91 8.26E-05 --- 2.21E-06 --- --- 3.67E-04 5.11E-05 Y-92 1.84E-09 --- 5.36E-11 --- --- 3.35E-06 2.06E-05 Y-93 1.69E-08 --- 4.65E-10 --- --- 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 --- 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 --- 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 --- 1.25E-06 9.39E-05 1.21E-05 Mo-99 --- 2.11E-08 4.03E-09 --- 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 --- 7.20E-12 1.44E-07 7.66E-07
CH-ODCM-0001 Reference Use Page 114 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 7.40E-15 1.05E-14 1.03E-13 --- 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 --- 1.12E-07 --- 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 --- 5.42E-11 --- 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 --- 1.55E-06 --- 2.38E-05 2.01E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-06 9.99E-07 --- 3.13E-06 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 --- 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09 --- 3.42E-04 1.24E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 --- 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 --- 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 --- 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 --- 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 --- 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 --- 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 --- 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 --- 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 --- 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 --- 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 --- 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 --- 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 --- 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 --- 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 --- 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 --- --- 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 --- --- 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 --- 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 --- 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 --- 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 --- 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 --- 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 --- 6.28E-07 4.65E-05 2.28E-05
CH-ODCM-0001 Reference Use Page 115 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 10 - Inhalation Dose Factors for Teenager (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.50E-09 1.22E-09 4.29E-10 --- --- 5.92E-06 2.21E-05 Pu-238 1.50E+00 1.03E+00 7.22E-02 --- 3.10E-01 3.12E-01 4.79E-05 Pu-239 1.73E+00 1.12E+00 8.05E-02 --- 3.44E-01 2.93E-01 4.37E-05 Pu-240 1.72E+00 1.12E+00 8.04E-02 --- 3.43E-01 2.93E-01 4.46E-05 Pu-241 3.74E-02 9.56E-03 1.40E-03 --- 6.47E-03 2.60E-04 9.17E-07 Np-239 4.23E-08 3.60E-08 2.21E-09 --- 1.25E-08 8.11E-06 1.65E-05 Am-241 1.77E+00 1.20E+00 7.10E-02 --- 5.32E-01 1.05E-01 4.88E-05 Cm-242 3.17E-02 2.51E-02 1.41E-03 --- 6.40E-03 6.76E-02 5.21E-05 Cm-243 1.19E+00 8.30E-01 5.00E-02 --- 2.34E-01 1.09E-01 5.13E-05 Cm-244 9.19E-01 6.53E-01 3.88E-02 --- 1.81E-01 1.05E-01 4.96E-05
CH-ODCM-0001 Reference Use Page 116 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 1.73E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 --- --- --- 1.14E-05 Cr-51 --- --- 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 --- 1.16E-05 2.57E-06 --- 2.71E-06 4.26E-04 6.19E-06 Mn-56 --- 4.48E-10 8.43E-11 --- 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 --- --- 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 --- --- 3.43E-04 1.91E-05 Co-58 --- 4.79E-07 8.55E-07 --- --- 2.99E-04 9.29E-06 Co-60 --- 3.55E-06 6.12E-06 --- --- 1.91E-03 2.60E-05 Ni-59 1.66E-05 4.67E-06 2.83E-06 --- --- 2.73E-05 6.29E-07 Ni-63 2.22E-04 1.25E-05 7.56E-06 --- --- 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 --- --- 2.21E-06 2.27E-05 Cu-64 --- 5.39E-10 2.90E-10 --- 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 --- 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 --- 1.58E-11 3.84E-07 2.75E-06 Br-83 --- --- 1.28E-07 --- --- --- ---
Br-84 --- --- 1.48E-07 --- --- --- ---
Br-85 --- --- 6.84E-09 --- --- --- ---
Rb-86 --- 5.36E-05 3.09E-05 --- --- --- 2.16E-06 Rb-88 --- 1.52E-07 9.90E-08 --- --- --- 4.66E-09 Rb-89 --- 9.33E-08 7.85E-08 --- --- --- 5.11E-10 Sr-89 1.62E-04 --- 4.66E-06 --- --- 5.83E-04 4.52E-05 Sr-90 1.04E-02 --- 2.07E-04 --- --- 3.99E-03 9.28E-05 Sr-91 3.28E-08 --- 1.24E-09 --- --- 1.44E-05 4.70E-05 Sr-92 3.54E-09 --- 1.42E-10 --- --- 6.49E-06 6.55E-05 Y-90 1.11E-06 --- 2.99E-08 --- --- 7.07E-05 7.24E-05 Y-91M 1.37E-10 --- 4.98E-12 --- --- 7.60E-07 4.64E-07 Y-91 2.47E-04 --- 6.59E-06 --- --- 7.10E-04 4.97E-05 Y-92 5.50E-09 --- 1.57E-10 --- --- 6.46E-06 6.46E-05 Y-93 5.04E-08 --- 1.38E-09 --- --- 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 --- 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 --- 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 --- 2.33E-06 1.66E-04 1.00E-05 Mo-99 --- 4.66E-08 1.15E-08 --- 1.06E-07 3.66E-05 3.42E-05 Tc-99M 4.81E-13 9.41E-13 1.56E-11 --- 1.37E-11 2.57E-07 1.30E-06
CH-ODCM-0001 Reference Use Page 117 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.19E-14 2.30E-14 2.91E-13 --- 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 --- 2.90E-07 --- 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 --- 1.50E-10 --- 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 --- 4.57E-06 --- 4.97E-05 3.87E-03 1.16E-04 Ag-110M 4.56E-06 3.08E-06 2.47E-06 --- 5.74E-06 1.48E-03 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 --- 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 --- 6.27E-04 1.09E-05 Te-125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 --- 1.29E-04 9.13E-06 Te-127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 --- 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 --- 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 --- 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 --- 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 --- 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 --- 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 --- 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 --- 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 --- 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 --- 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 --- 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 --- 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 --- 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 --- 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 --- --- 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 --- --- 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 --- 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 --- 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 --- 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 --- 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 --- 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 --- 1.30E-06 8.87E-05 2.22E-05
CH-ODCM-0001 Reference Use Page 118 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 11 - Inhalation Dose Factors for Child (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 4.41E-09 2.61E-09 1.17E-09 --- --- 1.11E-05 2.46E-05 Pu-238 2.55E+00 1.60E+00 1.21E-01 --- 4.47E-01 6.08E-01 4.65E-05 Pu-239 2.79E+00 1.68E+00 1.28E-01 --- 4.78E-01 5.72E-01 4.24E-05 Pu-240 2.79E+00 1.68E+00 1.27E-01 --- 4.77E-01 5.71E-01 4.33E-05 Pu-241 7.94E-02 1.75E-02 2.93E-03 --- 1.10E-02 5.06E-04 8.90E-07 Np-239 1.26E-07 8.14E-08 6.35E-09 --- 2.63E-08 1.57E-05 1.73E-05 Am-241 2.97E+00 1.84E+00 1.24E-01 --- 7.63E-01 2.02E-01 4.73E-05 Cm-242 9.48E-02 5.68E-02 4.20E-03 --- 1.34E-02 1.31E-01 5.06E-05 Cm-243 2.32E+00 1.42E+00 9.95E-02 --- 3.74E-01 2.10E-01 4.98E-05 Cm-244 1.94E+00 1.18E+00 8.31E-02 --- 3.06E-01 2.02E-01 4.82E-05
CH-ODCM-0001 Reference Use Page 119 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 2.63E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 --- --- --- 1.15E-05 Cr-51 --- --- 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 --- 1.81E-05 3.56E-06 --- 3.56E-06 7.14E-04 5.04E-06 Mn-56 --- 1.10E-09 1.58E-10 --- 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 --- --- 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 --- --- 7.25E-04 1.77E-05 Co-58 --- 8.71E-07 1.30E-06 --- --- 5.55E-04 7.95E-06 Co-60 --- 5.73E-06 8.41E-06 --- --- 3.22E-03 2.28E-05 Ni-59 1.81E-05 5.44E-06 3.10E-06 --- --- 5.48E-05 6.34E-07 Ni-63 2.42E-04 1.46E-05 8.29E-06 --- --- 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 --- --- 5.80E-06 3.58E-05 Cu-64 --- 1.34E-09 5.53E-10 --- 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 --- 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 --- 2.87E-11 1.05E-06 9.44E-06 Br-83 --- --- 2.72E-07 --- --- --- ---
Br-84 --- --- 2.86E-07 --- --- --- ---
Br-85 --- --- 1.46E-08 --- --- --- ---
Rb-86 --- 1.36E-04 6.30E-05 --- --- --- 2.17E-06 Rb-88 --- 3.98E-07 2.05E-07 --- --- --- 2.42E-07 Rb-89 --- 2.29E-07 1.47E-07 --- --- --- 4.87E-08 Sr-89 2.84E-04 --- 8.15E-06 --- --- 1.45E-03 4.57E-05 Sr-90 1.11E-02 --- 2.23E-04 --- --- 8.03E-03 9.36E-05 Sr-91 6.83E-08 --- 2.47E-09 --- --- 3.76E-05 5.24E-05 Sr-92 7.50E-09 --- 2.79E-10 --- --- 1.70E-05 1.00E-04 Y-90 2.35E-06 --- 6.30E-08 --- --- 1.92E-04 7.43E-05 Y-91M 2.91E-10 --- 9.90E-12 --- --- 1.99E-06 1.68E-06 Y-91 4.20E-04 --- 1.12E-05 --- --- 1.75E-03 5.02E-05 Y-92 1.17E-08 --- 3.29E-10 --- --- 1.75E-05 9.04E-05 Y-93 1.07E-07 --- 2.91E-09 --- --- 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 --- 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 --- 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 --- 3.37E-06 3.42E-04 9.05E-06 Mo-99 --- 1.18E-07 2.31E-08 --- 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-11 --- 2.22E-11 5.79E-07 1.45E-06
CH-ODCM-0001 Reference Use Page 120 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 4.65E-14 5.88E-14 5.80E-13 --- 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 --- 4.85E-07 --- 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 --- 2.93E-10 --- 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 --- 7.77E-06 --- 7.61E-05 8.26E-03 1.17E-04 Ag-110M 7.13E-06 5.16E-06 3.57E-06 --- 7.80E-06 2.62E-03 2.36E-05 Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 --- 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 --- 1.17E-03 1.05E-05 Te-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 --- 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.40E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 --- 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 --- 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 --- 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 --- 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 --- 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 --- 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 --- 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 --- 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 --- 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 --- 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 --- 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 --- 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 --- 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 --- 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 --- --- 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 --- --- 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 --- 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 --- 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 --- 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 --- 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 --- 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 --- 2.25E-06 2.30E-04 2.23E-05
CH-ODCM-0001 Reference Use Page 121 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 12 - Inhalation Dose Factors for Infant (mrem per pCi Inhaled)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 9.26E-09 6.44E-09 2.23E-09 --- --- 2.83E-05 2.54E-05 Pu-238 2.69E+00 1.68E+00 1.27E-01 --- 4.64E-01 9.03E-01 4.69E-05 Pu-239 2.93E+00 1.76E+00 1.34E-01 --- 4.95E-01 8.47E-01 4.28E-05 Pu-240 2.93E+00 1.75E+00 1.34E-01 --- 4.94E-01 8.47E-01 4.36E-05 Pu-241 8.43E-02 1.85E-02 3.11E-03 --- 1.15E-02 7.62E-04 8.97E-07 Np-239 2.65E-07 2.13E-07 1.34E-08 --- 4.73E-08 4.25E-05 1.78E-05 Am-241 3.15E+00 1.95E+00 1.31E-01 --- 7.94E-01 4.06E-01 4.78E-05 Cm-242 1.28E-01 8.65E-02 5.70E-03 --- 1.69E-02 2.97E-01 5.10E-05 Cm-243 2.47E+00 1.52E+00 1.06E-01 --- 3.91E-01 4.24E-01 5.02E-05 CM-244 2.07E+00 1.27E+00 8.89E-02 --- 3.21E-01 4.08E-01 4.86E-05
CH-ODCM-0001 Reference Use Page 122 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 5.99E-08 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 --- --- --- 2.17E-05 Cr-51 --- --- 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 --- 4.57E-06 8.72E-07 --- 1.36E-06 --- 1.40E-05 Mn-56 --- 1.15E-07 2.04E-08 --- 1.46E-07 --- 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 --- --- 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 --- --- 2.85E-06 3.40E-05 Co-58 --- 7.45E-07 1.67E-06 --- --- --- 1.51E-05 Co-60 --- 2.14E-06 4.72E-06 --- --- --- 4.02E-05 Ni-59 9.76E-06 3.35E-06 1.63E-06 --- --- --- 6.90E-07 Ni-63 1.30E-04 9.01E-06 4.36E-06 --- --- --- 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 --- --- --- 1.74E-06 Cu-64 --- 8.33E-08 3.91E-08 --- 2.10E-07 --- 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 --- 1.03E-05 --- 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 --- 1.28E-08 --- 2.96E-09 Br-83 --- --- 4.02E-08 --- --- --- 5.79E-08 Br-84 --- --- 5.21E-08 --- --- --- 4.09E-13 Br-85 --- --- 2.14E-09 --- --- --- ---
Rb-86 --- 2.11E-05 9.83E-06 --- --- --- 4.16E-06 Rb-88 --- 6.05E-08 3.21E-08 --- --- --- 8.36E-19 Rb-89 --- 4.01E-08 2.82E-08 --- --- --- 2.33E-21 Sr-89 3.08E-04 --- 8.84E-06 --- --- --- 4.94E-05 Sr-90 8.71E-03 --- 1.75E-04 --- --- --- 2.19E-04 Sr-91 5.67E-06 --- 2.29E-07 --- --- --- 2.70E-05 Sr-92 2.15E-06 --- 9.30E-08 --- --- --- 4.26E-05 Y-90 9.62E-09 --- 2.58E-10 --- --- --- 1.02E-04 Y-91M 9.09E-11 --- 3.52E-12 --- --- --- 2.67E-10 Y-91 1.41E-07 --- 3.77E-09 --- --- --- 7.76E-05 Y-92 8.45E-10 --- 2.47E-11 --- --- --- 1.48E-05 Y-93 2.68E-09 --- 7.40E-11 --- --- --- 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 --- 1.53E-08 --- 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 --- 5.12E-10 --- 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 --- 3.42E-09 --- 2.10E-05 Mo-99 --- 4.31E-06 8.20E-07 --- 9.76E-06 --- 9.99E-06 Tc-99M 2.47E-10 6.98E-10 8.89E-09 --- 1.06E-08 3.42E-10 4.13E-07
CH-ODCM-0001 Reference Use Page 123 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.54E-10 3.66E-10 3.59E-09 --- 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 --- 7.97E-08 --- 7.06E-07 --- 2.16E-05 Ru-105 1.54E-08 --- 6.08E-09 --- 1.99E-07 --- 9.42E-06 Ru-106 2.75E-06 --- 3.48E-07 --- 5.31E-06 --- 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 --- 2.91E-07 --- 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 --- 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 --- 1.38E-06 1.97E-05 Te-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 --- 1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 --- 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 --- 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 --- 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 --- 2.37E-08 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 --- 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 --- 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 --- 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 --- 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 --- 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 --- 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 --- 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 --- 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 --- 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 --- 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 --- 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 --- 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 --- 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 --- 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 --- 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 --- 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 --- 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 --- --- --- 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 --- --- --- 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 --- 2.94E-09 --- 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 --- 5.37E-10 --- 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 --- 1.21E-07 --- 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 --- 2.13E-09 --- 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 --- 7.05E-12 --- 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 --- 4.25E-09 --- 3.49E-05
CH-ODCM-0001 Reference Use Page 124 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 13 - Ingestion Dose Factors for Adult (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.03E-07 8.61E-08 3.01E-08 --- --- --- 2.82E-05 Pu-238 6.30E-04 7.98E-05 1.71E-05 --- 7.32E-05 --- 7.30E-05 Pu-239 7.25E-04 8.71E-05 1.91E-05 --- 8.11E-05 --- 6.66E-05 Pu-240 7.24E-04 8.70E-05 1.91E-05 --- 8.10E-05 --- 6.78E-05 Pu-241 1.57E-05 7.45E-07 3.32E-07 --- 1.53E-06 --- 1.40E-06 Np-239 1.19E-09 1.17E-10 6.45E-11 --- 3.65E-10 --- 2.40E-05 Am-241 7.55E-04 7.05E-04 5.41E-05 --- 4.07E-04 --- 7.42E-05 Cm-242 2.06E-05 2.19E-05 1.37E-06 --- 6.22E-06 --- 7.92E-05 Cm-243 5.99E-04 5.49E-04 3.75E-05 --- 1.75E-04 --- 7.81E-05 Cm-244 4.56E-04 4.27E-04 2.87E-05 --- 1.34E-04 --- 7.55E-05
CH-ODCM-0001 Reference Use Page 125 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 -- 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 6.04E-08 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 --- --- --- 2.32E-05 Cr-51 --- --- 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 --- 5.90E-06 1.17E-06 --- 1.76E-06 --- 1.21E-05 Mn-56 --- 1.58E-07 2.81E-08 --- 2.00E-07 --- 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 --- --- 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 --- --- 4.32E-06 3.24E-05 Co-58 --- 9.72E-07 2.24E-06 --- --- --- 1.34E-05 Co-60 --- 2.81E-06 6.33E-06 --- --- --- 3.66E-05 Ni-59 1.32E-05 4.66E-06 2.24E-06 --- --- --- 7.31E-07 Ni-63 1.77E-04 1.25E-05 6.00E-06 --- --- --- 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 --- --- --- 5.19E-06 Cu-64 --- 1.15E-07 5.41E-08 --- 2.91E-07 --- 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 --- 1.28E-05 --- 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 --- 1.83E-08 --- 5.16E-08 Br-83 --- --- 5.74E-08 --- --- --- ---
Br-84 --- --- 7.22E-08 --- --- --- ---
Br-85 --- --- 3.05E-09 --- --- --- ---
Rb-86 --- 2.98E-05 1.40E-05 --- --- --- 4.41E-06 Rb-88 --- 8.52E-08 4.54E-08 --- --- --- 7.30E-15 Rb-89 --- 5.50E-08 3.89E-08 --- --- --- 8.43E-17 Sr-89 4.40E-04 --- 1.26E-05 --- --- --- 5.24E-05 Sr-90 1.02E-02 --- 2.04E-04 --- --- --- 2.33E-04 Sr-91 8.07E-06 --- 3.21E-07 --- --- --- 3.66E-05 Sr-92 3.05E-06 --- 1.30E-07 --- --- --- 7.77E-05 Y-90 1.37E-08 --- 3.69E-10 --- --- --- 1.13E-04 Y-91M 1.29E-10 --- 4.93E-12 --- --- --- 6.09E-09 Y-91 2.01E-07 --- 5.39E-09 --- --- --- 8.24E-05 Y-92 1.21E-09 --- 3.50E-11 --- --- --- 3.32E-05 Y-93 3.83E-09 --- 1.05E-10 --- --- --- 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 --- 1.91E-08 --- 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 --- 7.11E-10 --- 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 --- 4.42E-09 --- 1.95E-05 Mo-99 --- 6.03E-06 1.15E-06 --- 1.38E-05 --- 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 --- 1.38E-08 5.14E-10 6.08E-07
CH-ODCM-0001 Reference Use Page 126 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 3.60E-10 5.12E-10 5.03E-09 --- 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 --- 1.09E-07 --- 8.99E-07 --- 2.13E-05 Ru-105 2.18E-08 --- 8.46E-09 --- 2.75E-07 --- 1.76E-05 Ru-106 3.92E-06 --- 4.94E-07 --- 7.56E-06 --- 1.88E-04 Ag-110M 2.05E-07 1.94E-07 1.18E-07 --- 3.70E-07 --- 5.45E-05 Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 --- 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 --- 2.18E-06 1.93E-05 Te-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 --- --- 1.13E-05 Te-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 --- 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 --- 1.22E-05 Te-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 --- 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 --- 2.45E-07 Te-131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 --- 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 --- 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 --- 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 --- 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 --- 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 --- 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 --- 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 --- 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 --- 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 --- 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 --- 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 --- 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 --- 1.10E-07 1.28E-08 4.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 --- 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 --- 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 --- 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 --- 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 --- --- --- 9.28E-05 La-142 1.79E-10 7.95E-11 1.98E-11 --- --- --- 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 --- 4.18E-09 --- 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 --- 7.67E-10 --- 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 --- 1.72E-07 --- 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 --- 3.04E-09 --- 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 --- 1.01E-11 --- 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 --- 5.99E-09 --- 3.68E-05
CH-ODCM-0001 Reference Use Page 127 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 14 - Ingestion Dose Factors for Teenager (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 1.46E-07 1.19E-07 4.17E-08 --- --- --- 3.22E-05 Pu-238 6.70E-04 8.58E-05 1.82E-05 --- 7.80E-05 --- 7.73E-05 Pu-239 7.65E-04 9.29E-05 2.01E-05 --- 8.57E-05 --- 7.06E-05 Pu-240 7.64E-04 9.27E-05 2.01E-05 --- 8.56E-05 --- 7.19E-05 Pu-241 1.75E-05 8.40E-07 3.69E-07 --- 1.71E-06 --- 1.48E-06 Np-239 1.76E-09 1.66E-10 9.22E-11 --- 5.21E-10 --- 2.67E-05 Am-241 7.98E-04 7.53E-04 5.75E-05 --- 4.31E-04 --- 7.87E-05 Cm-242 2.94E-05 3.10E-05 1.95E-06 --- 8.89E-06 --- 8.40E-05 Cm-243 6.50E-04 6.03E-04 4.09E-05 --- 1.91E-04 --- 8.28E-05 Cm-244 5.04E-04 4.77E-04 3.19E-05 --- 1.49E-04 --- 8.00E-05
CH-ODCM-0001 Reference Use Page 128 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 --- --- --- 2.28E-05 Cr-51 --- --- 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 --- 1.07E-05 2.85E-06 --- 3.00E-06 --- 8.98E-06 Mn-56 --- 3.34E-07 7.54E-08 --- 4.04E-07 --- 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 --- --- 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 --- --- 7.74E-06 2.78E-05 Co-58 --- 1.80E-06 5.51E-06 --- --- --- 1.05E-05 Co-60 --- 5.29E-06 1.56E-05 --- --- --- 2.93E-05 Ni-59 4.02E-05 1.07E-05 6.82E-06 --- --- --- 7.10E-07 Ni-63 5.38E-04 2.88E-05 1.83E-05 --- --- --- 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 --- --- --- 2.56E-05 Cu-64 --- 2.45E-07 1.48E-07 --- 5.92E-07 --- 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 --- 2.30E-05 --- 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 --- 3.84E-08 --- 3.99E-06 Br-83 --- --- 1.71E-07 --- --- --- ---
Br-84 --- --- 1.98E-07 --- --- --- ---
Br-85 --- --- 9.12E-09 --- --- --- ---
Rb-86 --- 6.70E-05 4.12E-05 --- --- --- 4.31E-06 Rb-88 --- 1.90E-07 1.32E-07 --- --- --- 9.32E-09 Rb-89 --- 1.17E-07 1.04E-07 --- --- --- 1.02E-09 Sr-89 1.32E-03 --- 3.77E-05 --- --- --- 5.11E-05 Sr-90 2.56E-02 --- 5.15E-04 --- --- --- 2.29E-04 Sr-91 2.40E-05 --- 9.06E-07 --- --- --- 5.30E-05 Sr-92 9.03E-06 --- 3.62E-07 --- --- --- 1.71E-04 Y-90 4.11E-08 --- 1.10E-09 --- --- --- 1.17E-04 Y-91M 3.82E-10 --- 1.39E-11 --- --- --- 7.48E-07 Y-91 6.02E-07 --- 1.61E-08 --- --- --- 8.02E-05 Y-92 3.60E-09 --- 1.03E-10 --- --- --- 1.04E-04 Y-93 1.14E-08 --- 3.13E-10 --- --- --- 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 --- 3.65E-08 --- 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 --- 1.45E-09 --- 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 --- 8.23E-09 --- 1.62E-05 Mo-99 --- 1.33E-05 3.29E-06 --- 2.84E-05 --- 1.10E-05 Tc-99M 9.23E-10 1.81E-09 3.00E-08 --- 2.63E-08 9.19E-10 1.03E-06
CH-ODCM-0001 Reference Use Page 129 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 1.07E-09 1.12E-09 1.42E-08 --- 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 --- 2.81E-07 --- 1.84E-06 --- 1.89E-05 Ru-105 6.45E-08 --- 2.34E-08 --- 5.67E-07 --- 4.21E-05 Ru-106 1.17E-05 --- 1.46E-06 --- 1.58E-05 --- 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91E-07 --- 6.78E-07 --- 4.33E-05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 --- 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 --- 3.99E-06 1.71E-05 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 --- --- 1.10E-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 --- 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 --- 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 --- 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 --- 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 --- 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 --- 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 --- 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 --- 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 --- 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 --- 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 --- 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 --- 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 --- 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 --- 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 --- 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 --- 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 --- 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 --- 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 --- 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 --- 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 --- 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 --- --- --- 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 --- --- --- 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 --- 8.68E-09 --- 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 --- 1.59E-09 --- 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 --- 3.61E-07 --- 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 --- 6.39E-09 --- 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 --- 2.11E-11 --- 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 --- 1.24E-08 --- 3.58E-05
CH-ODCM-0001 Reference Use Page 130 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 15 - Ingestion Dose Factors for Child (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 4.29E-07 2.54E-07 1.14E-07 --- --- --- 3.57E-05 Pu-238 1.19E-03 1.38E-04 3.16E-05 --- 1.15E-04 --- 7.50E-05 Pu-239 1.29E-03 1.38E-04 3.31E-05 --- 1.22E-04 --- 6.85E-05 Pu-240 1.28E-03 1.43E-04 3.31E-05 --- 1.22E-04 --- 6.98E-05 Pu-241 3.87E-05 1.58E-06 8.04E-07 --- 2.96E-06 --- 1.44E-06 Np-239 5.25E-09 3.77E-10 2.65E-10 --- 1.09E-09 --- 2.79E-05 Am-241 1.36E-03 1.17E-03 1.02E-04 --- 6.23E-04 --- 7.64E-05 Cm-242 8.78E-05 7.01E-05 5.84E-06 --- 1.87E-05 --- 8.16E-05 Cm-243 1.28E-03 1.04E-03 8.24E-05 --- 3.08E-04 --- 8.03E-05 Cm-244 1.08E-03 8.74E-04 6.93E-05 --- 2.54E-04 --- 7.77E-05
CH-ODCM-0001 Reference Use Page 131 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 --- 1.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 1.76E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 --- --- --- 2.30E-05 Cr-51 --- --- 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 --- 1.99E-05 4.51E-06 --- 4.41E-06 --- 7.31E-06 Mn-56 --- 8.18E-07 1.41E-07 --- 7.03E-07 --- 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 --- --- 4.36E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 --- --- 1.59E-05 2.57E-05 Co-58 --- 3.60E-06 8.98E-06 --- --- --- 8.97E-06 Co-60 --- 1.08E-05 2.55E-05 --- --- --- 2.57E-05 Ni-59 4.73E-05 1.45E-05 8.17E-06 --- --- --- 7.16E-07 Ni-63 6.34E-04 3.92E-05 2.20E-05 --- --- --- 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 --- --- --- 4.05E-05 Cu-64 --- 6.09E-07 2.82E-07 --- 1.03E-06 --- 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 --- 3.06E-05 --- 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 --- 6.98E-08 --- 1.37E-05 Br-83 --- --- 3.63E-07 --- --- --- ---
Br-84 --- --- 3.82E-07 --- --- --- ---
Br-85 --- --- 1.94E-08 --- --- --- ---
Rb-86 --- 1.70E-04 8.40E-05 --- --- --- 4.35E-06 Rb-88 --- 4.98E-07 2.73E-07 --- --- --- 4.85E-07 Rb-89 --- 2.86E-07 1.97E-07 --- --- --- 9.74E-08 Sr-89 2.51E-03 --- 7.20E-05 --- --- --- 5.16E-05 Sr-90 2.83E-02 --- 5.74E-04 --- --- --- 2.31E-04 Sr-91 5.00E-05 --- 1.81E-06 --- --- --- 5.92E-05 Sr-92 1.92E-05 --- 7.13E-07 --- --- --- 2.07E-04 Y-90 8.69E-08 --- 2.33E-09 --- --- --- 1.20E-04 Y-91M 8.10E-10 --- 2.76E-11 --- --- --- 2.70E-06 Y-91 1.13E-06 --- 3.01E-08 --- --- --- 8.10E-05 Y-92 7.65E-09 --- 2.15E-10 --- --- --- 1.46E-04 Y-93 2.43E-08 --- 6.62E-10 --- --- --- 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 --- 5.41E-08 --- 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 --- 2.56E-09 --- 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 --- 1.24E-08 --- 1.46E-05 Mo-99 --- 3.40E-05 6.63E-06 --- 5.08E-05 --- 1.12E-05 Tc-99M 1.92E-09 3.96E-09 5.10E-08 --- 4.26E-08 2.07E-09 1.15E-06
CH-ODCM-0001 Reference Use Page 132 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Tc-101 2.27E-09 2.86E-09 2.83E-08 --- 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 --- 4.95E-07 --- 3.08E-06 --- 1.80E-05 Ru-105 1.36E-07 --- 4.58E-08 --- 1.00E-06 --- 5.41E-05 Ru-106 2.41E-05 --- 3.01E-06 --- 2.85E-05 --- 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81E-07 --- 1.04E-06 --- 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 --- 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 --- 7.12E-06 1.64E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 --- --- 1.11E-05 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 --- 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 --- 2.10E-05 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 --- 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 --- 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 --- 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 --- 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 --- 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 --- 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 --- 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 --- 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 --- 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 --- 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 --- 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 --- 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 --- 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 --- 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 --- 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 --- 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 --- 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 --- 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 --- 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 --- --- --- 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 --- --- --- 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 --- 1.48E-08 --- 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 --- 2.86E-09 --- 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 --- 4.93E-07 --- 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 --- 1.13E-08 --- 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 --- 3.84E-11 --- 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 --- 2.19E-08 --- 3.60E-05
CH-ODCM-0001 Reference Use Page 133 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 16 - Ingestion Dose Factors for Infant (mrem per pCi Ingested)
Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI W-187 9.03E-07 6.28E-07 2.17E-07 --- --- --- 3.69E-05 Pu-238 1.28E-03 1.50E-04 3.40E-05 --- 1.21E-04 --- 7.57E-05 Pu-239 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 6.91E-05 Pu-240 1.38E-03 1.55E-04 3.54E-05 --- 1.28E-04 --- 7.04E-05 Pu-241 4.25E-05 1.76E-06 8.82E-07 --- 3.17E-06 --- 1.45E-06 Np-239 1.11E-08 9.93E-10 5.61E-10 --- 1.98E-09 --- 2.87E-05 Am-241 1.46E-03 1.27E-03 1.09E-04 --- 6.55E-04 --- 7.70E-05 Cm-242 1.37E-04 1.27E-04 9.10E-06 --- 2.62E-05 --- 8.23E-05 Cm-243 1.40E-03 1.15E-03 8.98E-05 --- 3.27E-04 --- 8.10E-05 Cm-244 1.18E-03 9.70E-04 7.59E-05 --- 2.71E-04 --- 7.84E-05
CH-ODCM-0001 Reference Use Page 134 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol fg Fraction of ingested produce grown in garden 0.76 of interest.
f Fraction of leafy vegetables grown in garden of 1.0 interest.
P Effective surface density of soil (assumes a 240 kg/m2 15 cm plow layer, expressed in dry weight) r Fraction of deposited activity retained on crops, 0.25 leafy vegetables, or pasture grass 1.0 (iodines) 0.2 (other particulates)
Sf Attenuation factor accounting for shielding 0.7 (maximum individual) provided by residential structures 0.5 (general population) tb Period of long-term buildup for activity in 1.752E5 hr sediment or soil (20 years) te Period of crop, leafy vegetable, or pasture 30 days (grass-cow-milk-man grass exposure during growing season pathway) 60 days (crop/vegetation-man pathway) tf Transport time from animal feed-milk-man 2 days (maximum individual) provided by residential structures 4 days (general population) th Time delay between harvest of vegetation or crops and ingestion:
For ingestion of forage by animals Zero (pasture grass) 90 days (stored feed)
For ingestion of crops by man 1 day (leafy vegetables and max. individual feed) 60 days (produce and max.
individual) 14 days (general population) fs The fraction of daily feed that is pasture grass 1.0 while the animals graze on pasture.
Mp The mixing ratio at the point of withdrawal of Site Discharge 7.14 drinking water. M.U.D. Intake 30.8 fp Fraction of the year that animals graze on 0.5 pasture.
CH-ODCM-0001 Reference Use Page 135 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 17 - Recommended Values for Other Parameters Parameter Definition Values Symbol tp Environmental transit time, release to receptor 12 hrs. (maximum)
(add time from release to exposure individual 1 day (maximum individual) point to minimums shown for distribution) 1 day (general population) 7 days (population--sport fish doses) 10 days (population--
commercial fish doses) ts Average time from slaughter of meat animal to 20 days consumption Yv Agricultural productivity by unit area (measured 0.7 kg/m2 (grass-cow-milk-man in wet weight) pathway) 2.0 kg/m2 (produce or leafy vegetable ingested by man)
W Shore-width factor for river shoreline 0.2 w Rate constant for removal of activity on plant or 0.0021 hr-1 leaf structures by weathering (corresponds to a 14-day half-life)
%CO2 Fraction of C-14 used for organ dose 0.15 calculations from gaseous releases.
CH-ODCM-0001 Reference Use Page 136 of 136 Off-Site Dose Calculation Manual (ODCM) Revision 31 Table 18 - Estimated Doses Received by the General Public from On-Site Exposure NOTE i The Dose Estimates are based on normal public activities conducted within the Fort Calhoun Station Site Boundary.
i Estimated Individual Dose Estimated Total Combined Distance Rate (mR/hour) Annual Dose (mRem)B from Direct Inhalation Direct Inhalation Containment Exposure (Critical Exposure (Critical Location Direction (miles) (Total Body) OrganA) (Total Body) OrganA)
Firing Range 200° 0.24 4.08E-05 9.67E-06 5.08E+00 1.20E+00 Burn Pad 241° 0.33 1.95E-05 4.63E-06 1.41E-01 3.34E-02 On-Site Farming 118° 0.52 2.12E-05 5.03E-06 2.38E-02 5.64E-03 On-Site Farming 200° 0.51 1.03E-05 2.45E-06 2.30E-02 5.50E-03 On-Site Farming 308° 0.50 2.77E-05 6.64E-06 4.66E-02 1.12E-02 Site Maintenance Admin Bldg 145° 0.20 1.18E-04 2.84E-05 5.50E-02 1.33E-02 Site Maintenance Training Center 180° 0.20 1.45E-04 3.50E-05 6.78E-02 1.64E-02 A. Critical organ doses are based on adult thyroid.
B. Estimated totals are based on summation of all individual doses for members of the General Public while within the Fort Calhoun Station site boundary.
SECTION VII ATTACHMENT 2 JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA (Regulatory Guide 1.21)
January 1, 2019 - December 31, 2019 VII-2
JOINT FREQUENCY DISTRIBUTION WIND DIRECTION VS. WIND SPEED BY STABILITY CLASS AND METEOROLOGICAL DATA A. Meteorological Data Recovery Data availability from the on-site weather tower for the period January 1, 2019 through December 31, 2019 had a cumulative recovery rate of 0.00% from the meteorological tower with the remaining 100.00%
provided by Eppley Airfield Weather Station, a branch of the National Weather Service. The following table is a summary of the parameters and their respective recovery rates for the period.
The tabulations of the Weather Tower Data for the period January 1, 2019 through December 31, 2019 look appropriate for the season indicated.
The Pasquill Classes observed for the twelve-month period are detailed below.
Pasquill Class A B C D E F G Total
% Obs. 0.16 1.44 10.45 70.62 6.76 7.25 3.33 100 On the basis of the data and its cross-checks, the weather data as amended is completely valid for use in tabulating atmospheric releases.
VII-3
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY UNSTABLE (delta T/ delta z <= -1.9)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL A WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 0 0 2 1 0 0 0 0 0 0 11 NNE 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 1 0 0 0 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 1 0 0 0 0 0 0 1 S 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 0 0 0 0 0 Total 0 0 1 2 2 0 0 0 0 0 0 5 Number of Calms 9 Number of Invalid Hours 0 Number of Valid Hours 14 VII-4
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY UNSTABLE (-1.9 < delta T/ delta z <= -1.7)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL B WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 13 8 10 3 2 0 0 0 0 0 51 NNE 0 1 2 0 0 0 0 0 0 0 0 3 NE 0 0 0 1 0 0 0 0 0 0 0 1 ENE 0 0 1 1 0 0 0 0 0 0 0 2 E 0 1 2 3 0 0 0 0 0 0 0 6 ESE 0 2 1 0 0 0 0 0 0 0 0 3 SE 0 0 0 3 0 1 0 0 0 0 0 4 SSE 0 3 2 6 0 1 1 0 0 0 0 13 S 0 0 1 5 3 5 1 0 0 0 0 15 SSW 0 1 1 2 1 1 0 0 0 0 0 6 SW 0 1 0 0 1 0 0 0 0 0 0 2 WSW 0 0 0 0 0 1 0 0 0 0 0 1 W 0 0 1 0 2 0 0 0 0 0 0 3 WNW 0 1 1 1 1 1 0 0 0 0 0 5 NW 0 1 2 2 1 0 0 0 0 0 0 8 NNW 0 0 1 2 0 0 0 0 0 0 0 3 Total 0 24 23 36 12 12 2 0 0 0 0 109 Number of Calms 17 Number of Invalid Hours 0 Number of Valid Hours 126 VII-5
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL C WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 33 36 45 13 14 4 0 0 0 0 235 NNE 0 10 9 16 5 1 0 0 0 0 0 43 NE 0 3 5 6 0 0 1 0 0 0 0 15 ENE 0 3 4 5 0 2 0 0 0 0 0 15 E 0 5 10 16 3 0 0 0 0 0 0 36 ESE 0 8 9 9 3 1 0 0 0 0 0 31 SE 0 13 21 33 10 3 0 0 0 0 0 81 SSE 0 14 24 30 10 8 3 0 0 0 0 92 S 0 10 8 12 21 23 7 0 0 0 0 85 SSW 0 5 3 11 10 6 3 0 0 0 0 41 SW 0 3 7 4 3 3 1 0 0 0 0 23 WSW 0 3 3 7 4 0 0 0 0 0 0 25 W 0 8 10 11 4 5 1 0 0 0 0 44 WNW 0 3 3 6 3 9 3 1 0 0 0 33 NW 0 4 10 15 7 7 4 0 0 0 0 55 NNW 0 6 12 22 5 6 5 0 0 0 0 61 Total 0 131 174 248 101 88 32 1 0 0 0 775 Number of Calms 140 Number of Invalid Hours 0 Number of Valid Hours 915 VII-6
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS NEUTRAL (-1.5 < delta T/ delta z <= -0.5)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL D WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 38 23 134 213 269 109 62 31 0 0 1033 NNE 0 13 20 44 83 82 25 6 0 1 0 283 NE 0 9 4 26 32 14 4 3 2 0 0 94 ENE 0 10 12 20 35 14 6 2 2 0 0 103 E 0 16 32 62 89 58 19 12 5 1 0 298 ESE 0 15 14 55 95 87 16 10 4 0 0 300 SE 0 11 11 102 185 150 66 21 21 0 0 578 SSE 0 6 19 103 259 311 137 49 23 0 0 910 S 0 11 13 57 171 258 127 74 29 0 0 745 SSW 0 8 7 22 32 42 15 11 4 0 0 142 SW 0 1 8 11 48 33 8 6 2 0 0 118 WSW 0 6 5 10 19 20 8 4 1 0 0 74 W 0 5 1 25 38 45 16 19 10 0 0 161 WNW 0 6 5 15 36 53 40 26 20 0 0 201 NW 0 11 14 29 94 104 78 54 87 7 1 486 NNW 0 11 16 42 135 184 105 71 81 8 0 660 Total 0 177 204 757 1564 1724 779 430 322 17 1 5975 Number of Calms 211 Number of Invalid Hours 0 Number of Valid Hours 6186 VII-7
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL E WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 0 0 7 29 14 5 0 0 0 0 55 NNE 0 0 0 8 12 2 0 0 0 0 0 22 NE 0 0 0 1 2 0 0 0 0 0 0 3 ENE 0 0 0 2 3 0 0 0 0 0 0 5 E 0 0 0 7 14 2 0 0 0 0 0 23 ESE 0 0 0 9 20 2 0 0 0 0 0 31 SE 0 0 0 24 32 9 0 0 0 0 0 65 SSE 0 0 0 38 103 31 0 0 0 0 0 172 S 0 0 0 7 33 40 2 0 0 0 0 82 SSW 0 0 0 0 3 1 0 0 0 0 0 4 SW 0 0 0 1 3 1 0 0 0 0 0 5 WSW 0 0 0 2 3 0 0 0 0 0 0 5 W 0 0 0 2 7 2 0 0 0 0 0 11 WNW 0 0 0 1 8 6 3 0 0 0 0 18 NW 0 0 0 5 21 9 4 0 0 0 0 39 NNW 0 0 0 13 18 10 8 3 0 0 0 52 Total 0 0 0 127 311 129 22 3 0 0 0 592 Number of Calms 0 Number of Invalid Hours 0 Number of Valid Hours 592 VII-8
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL F WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 12 11 20 10 2 0 0 0 0 0 125 NNE 0 5 0 7 0 0 0 0 0 0 0 12 NE 0 1 1 1 0 1 0 0 0 0 0 4 ENE 0 1 1 0 1 0 0 0 0 0 0 5 E 0 10 6 5 0 0 0 0 0 0 0 21 ESE 0 8 10 16 2 0 0 0 0 0 0 39 SE 0 12 14 32 15 1 0 0 0 0 0 75 SSE 0 8 7 54 66 5 0 0 0 0 0 142 S 0 3 3 15 15 6 0 0 0 0 0 42 SSW 0 0 3 3 0 0 0 0 0 0 0 7 SW 0 1 1 3 1 0 0 0 0 0 0 6 WSW 0 2 1 2 2 0 0 0 0 0 0 7 W 0 4 3 9 9 2 0 0 0 0 0 28 WNW 0 3 1 8 12 4 0 0 0 0 0 29 NW 0 3 2 13 12 4 0 0 0 0 0 36 NNW 0 5 12 16 16 6 0 0 0 0 0 57 Total 0 78 76 204 161 31 0 0 0 0 0 550 Number of Calms 85 Number of Invalid Hours 0 Number of Valid Hours 635 VII-9
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY EVENTS EXTREMELY STABLE (delta T/ delta z > 4.0)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL G WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0 8 6 6 0 0 0 0 0 0 0 68 NNE 0 3 2 1 0 0 0 0 0 0 0 6 NE 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 E 0 3 0 1 0 0 0 0 0 0 0 7 ESE 0 4 2 4 0 0 0 0 0 0 0 12 SE 0 15 9 12 0 0 0 0 0 0 0 41 SSE 0 9 20 26 0 0 0 0 0 0 0 59 S 0 4 3 6 0 0 0 0 0 0 0 15 SSW 0 3 1 1 0 0 0 0 0 0 0 5 SW 0 1 2 0 0 0 0 0 0 0 0 3 WSW 0 1 4 3 0 0 0 0 0 0 0 8 W 0 2 6 5 0 0 0 0 0 0 0 15 WNW 0 3 2 4 0 0 0 0 0 0 0 11 NW 0 5 9 5 0 0 0 0 0 0 0 26 NNW 0 1 9 5 0 0 0 0 0 0 0 16 Total 0 62 75 79 0 0 0 0 0 0 0 216 Number of Calms 76 Number of Invalid Hours 0 Number of Valid Hours 292 Hours Accounted For: 8760 VII-10
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY UNSTABLE (delta T/ delta z <= -1.9)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL A WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0.00 0.00 0.00 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.13 NNE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ENE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 E 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 ESE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSE 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.01 S 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SSW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 SW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 WSW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 W 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 WNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 NW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 NNW 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Total 0.00 0.00 0.01 0.02 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.06 Percent of Calms 0.10 Percent of Invalid Hours 0.00 Percent of Valid Hours 0.16 VII-11
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY UNSTABLE (-1.9 < delta T/ delta z <= -1.7)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL B WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0.00 0.15 0.09 0.11 0.03 0.02 0.00 0.00 0.00 0.00 0.00 0.58 NNE 0.00 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 NE 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.01 ENE 0.00 0.00 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.02 E 0.00 0.01 0.02 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 ESE 0.00 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 SE 0.00 0.00 0.00 0.03 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.05 SSE 0.00 0.03 0.02 0.07 0.00 0.01 0.01 0.00 0.00 0.00 0.00 0.15 S 0.00 0.00 0.01 0.06 0.03 0.06 0.01 0.00 0.00 0.00 0.00 0.17 SSW 0.00 0.01 0.01 0.02 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.07 SW 0.00 0.01 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.02 WSW 0.00 0.00 0.00 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.01 W 0.00 0.00 0.01 0.00 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.03 WNW 0.00 0.01 0.01 0.01 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.06 NW 0.00 0.01 0.02 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.09 NNW 0.00 0.00 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 Total 0.00 0.27 0.26 0.41 0.14 0.14 0.02 0.00 0.00 0.00 0.00 1.24 Percent of Calms 0.19 Percent of Invalid Hours 0.00 Percent of Valid Hours 1.44 VII-12
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY UNSTABLE (-1.7 < delta T/ delta z <= -1.5)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL C WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0.00 0.38 0.41 0.51 0.15 0.16 0.05 0.00 0.00 0.00 0.00 2.68 NNE 0.00 0.11 0.10 0.18 0.06 0.01 0.00 0.00 0.00 0.00 0.00 0.49 NE 0.00 0.03 0.06 0.07 0.00 0.00 0.01 0.00 0.00 0.00 0.00 0.17 ENE 0.00 0.03 0.05 0.06 0.00 0.02 0.00 0.00 0.00 0.00 0.00 0.17 E 0.00 0.06 0.11 0.18 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.41 ESE 0.00 0.09 0.10 0.10 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.35 SE 0.00 0.15 0.24 0.38 0.11 0.03 0.00 0.00 0.00 0.00 0.00 0.92 SSE 0.00 0.16 0.27 0.34 0.11 0.09 0.03 0.00 0.00 0.00 0.00 1.05 S 0.00 0.11 0.09 0.14 0.24 0.26 0.08 0.00 0.00 0.00 0.00 0.97 SSW 0.00 0.06 0.03 0.13 0.11 0.07 0.03 0.00 0.00 0.00 0.00 0.47 SW 0.00 0.03 0.08 0.05 0.03 0.03 0.01 0.00 0.00 0.00 0.00 0.26 WSW 0.00 0.03 0.03 0.08 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.29 W 0.00 0.09 0.11 0.13 0.05 0.06 0.01 0.00 0.00 0.00 0.00 0.50 WNW 0.00 0.03 0.03 0.07 0.03 0.10 0.03 0.01 0.00 0.00 0.00 0.38 NW 0.00 0.05 0.11 0.17 0.08 0.08 0.05 0.00 0.00 0.00 0.00 0.63 NNW 0.00 0.07 0.14 0.25 0.06 0.07 0.06 0.00 0.00 0.00 0.00 0.70 Total 0.00 1.50 1.99 2.83 1.15 1.00 0.37 0.01 0.00 0.00 0.00 8.85 Percent of Calms 1.60 Percent of Invalid Hours 0.00 Percent of Valid Hours 10.45 VII-13
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT NEUTRAL (-1.5 < delta T/ delta z <= -0.5)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL D WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0.00 0.43 0.26 1.53 2.43 3.07 1.24 0.71 0.35 0.00 0.00 11.79 NNE 0.00 0.15 0.23 0.50 0.95 0.94 0.29 0.07 0.00 0.01 0.00 3.23 NE 0.00 0.10 0.05 0.30 0.37 0.16 0.05 0.03 0.02 0.00 0.00 1.07 ENE 0.00 0.11 0.14 0.23 0.40 0.16 0.07 0.02 0.02 0.00 0.00 1.18 E 0.00 0.18 0.37 0.71 1.02 0.66 0.22 0.14 0.06 0.01 0.00 3.40 ESE 0.00 0.17 0.16 0.63 1.08 0.99 0.18 0.11 0.05 0.00 0.00 3.42 SE 0.00 0.13 0.13 1.16 2.11 1.71 0.75 0.24 0.24 0.00 0.00 6.60 SSE 0.00 0.07 0.22 1.18 2.96 3.55 1.56 0.56 0.26 0.00 0.00 10.39 S 0.00 0.13 0.15 0.65 1.95 2.95 1.45 0.84 0.33 0.00 0.00 8.50 SSW 0.00 0.09 0.08 0.25 0.37 0.48 0.17 0.13 0.05 0.00 0.00 1.62 SW 0.00 0.01 0.09 0.13 0.55 0.38 0.09 0.07 0.02 0.00 0.00 1.35 WSW 0.00 0.07 0.06 0.11 0.22 0.23 0.09 0.05 0.01 0.00 0.00 0.84 W 0.00 0.06 0.01 0.29 0.43 0.51 0.18 0.22 0.11 0.00 0.00 1.84 WNW 0.00 0.07 0.06 0.17 0.41 0.61 0.46 0.30 0.23 0.00 0.00 2.29 NW 0.00 0.13 0.16 0.33 1.07 1.19 0.89 0.62 0.99 0.08 0.01 5.55 NNW 0.00 0.13 0.18 0.48 1.54 2.10 1.20 0.81 0.92 0.09 0.00 7.53 Total 0.00 2.02 2.33 8.64 17.85 19.68 8.89 4.91 3.68 0.19 0.01 68.21 Percent of Calms 2.41 Percent of Invalid Hours 0.00 Percent of Valid Hours 70.62 VII-14
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT SLIGHTLY STABLE (-0.5 < delta T/ delta z <= 1.5)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL E WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0.00 0.00 0.00 0.08 0.33 0.16 0.06 0.00 0.00 0.00 0.00 0.63 NNE 0.00 0.00 0.00 0.09 0.14 0.02 0.00 0.00 0.00 0.00 0.00 0.25 NE 0.00 0.00 0.00 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.03 ENE 0.00 0.00 0.00 0.02 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.06 E 0.00 0.00 0.00 0.08 0.16 0.02 0.00 0.00 0.00 0.00 0.00 0.26 ESE 0.00 0.00 0.00 0.10 0.23 0.02 0.00 0.00 0.00 0.00 0.00 0.35 SE 0.00 0.00 0.00 0.27 0.37 0.10 0.00 0.00 0.00 0.00 0.00 0.74 SSE 0.00 0.00 0.00 0.43 1.18 0.35 0.00 0.00 0.00 0.00 0.00 1.96 S 0.00 0.00 0.00 0.08 0.38 0.46 0.02 0.00 0.00 0.00 0.00 0.94 SSW 0.00 0.00 0.00 0.00 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.05 SW 0.00 0.00 0.00 0.01 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.06 WSW 0.00 0.00 0.00 0.02 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.06 W 0.00 0.00 0.00 0.02 0.08 0.02 0.00 0.00 0.00 0.00 0.00 0.13 WNW 0.00 0.00 0.00 0.01 0.09 0.07 0.03 0.00 0.00 0.00 0.00 0.21 NW 0.00 0.00 0.00 0.06 0.24 0.10 0.05 0.00 0.00 0.00 0.00 0.45 NNW 0.00 0.00 0.00 0.15 0.21 0.11 0.09 0.03 0.00 0.00 0.00 0.59 Total 0.00 0.00 0.00 1.45 3.55 1.47 0.25 0.03 0.00 0.00 0.00 6.76 Percent of Calms 0.00 Percent of Invalid Hours 0.00 Percent of Valid Hours 6.76 VII-15
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT MODERATELY STABLE (1.5 < delta T/ delta z <= 4.0)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL F WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0.00 0.14 0.13 0.23 0.11 0.02 0.00 0.00 0.00 0.00 0.00 1.43 NNE 0.00 0.06 0.00 0.08 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 NE 0.00 0.01 0.01 0.01 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.05 ENE 0.00 0.01 0.01 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.06 E 0.00 0.11 0.07 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.24 ESE 0.00 0.09 0.11 0.18 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.45 SE 0.00 0.14 0.16 0.37 0.17 0.01 0.00 0.00 0.00 0.00 0.00 0.86 SSE 0.00 0.09 0.08 0.62 0.75 0.06 0.00 0.00 0.00 0.00 0.00 1.62 S 0.00 0.03 0.03 0.17 0.17 0.07 0.00 0.00 0.00 0.00 0.00 0.48 SSW 0.00 0.00 0.03 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.08 SW 0.00 0.01 0.01 0.03 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.07 WSW 0.00 0.02 0.01 0.02 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.08 W 0.00 0.05 0.03 0.10 0.10 0.02 0.00 0.00 0.00 0.00 0.00 0.32 WNW 0.00 0.03 0.01 0.09 0.14 0.05 0.00 0.00 0.00 0.00 0.00 0.33 NW 0.00 0.03 0.02 0.15 0.14 0.05 0.00 0.00 0.00 0.00 0.00 0.41 NNW 0.00 0.06 0.14 0.18 0.18 0.07 0.00 0.00 0.00 0.00 0.00 0.65 Total 0.00 0.89 0.87 2.33 1.84 0.35 0.00 0.00 0.00 0.00 0.00 6.28 Percent of Calms 0.97 Percent of Invalid Hours 0.00 Percent of Valid Hours 7.25 VII-16
Omaha Public Power District Fort Calhoun Nuclear Station JOINT FREQUENCY DISTRIBUTION BY PERCENT EXTREMELY STABLE (delta T/ delta z > 4.0)
PERIOD OF RECORD: JAN 2019 - DEC 2019 PASQUILL G WIND SPEED (m/s) AT 10-m LEVEL Wind < 0.5- 1.1- 1.6- 2.1- 3.1- 4.1- 5.1- 6.1- 8.1- >
Direct 0.5 1.0 1.5 2.0 3.0 4.0 5.0 6.0 8.0 10.0 10.0 Total N 0.00 0.09 0.07 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.78 NNE 0.00 0.03 0.02 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.07 NE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ENE 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 E 0.00 0.03 0.00 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.08 ESE 0.00 0.05 0.02 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.14 SE 0.00 0.17 0.10 0.14 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.47 SSE 0.00 0.10 0.23 0.30 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.67 S 0.00 0.05 0.03 0.07 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.17 SSW 0.00 0.03 0.01 0.01 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.06 SW 0.00 0.01 0.02 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.03 WSW 0.00 0.01 0.05 0.03 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.09 W 0.00 0.02 0.07 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.17 WNW 0.00 0.03 0.02 0.05 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.13 NW 0.00 0.06 0.10 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.30 NNW 0.00 0.01 0.10 0.06 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.18 Total 0.00 0.71 0.86 0.90 0.00 0.00 0.00 0.00 0.00 0.00 0.00 2.47 Percent of Calms 0.87 Percent of Invalid Hours 0.00 Percent of Valid Hours 3.33 Percent of Hours Accounted For: 100.00 VII-17
LIC-20-0009 Enclosure 2 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TECHNICAL SPECIFICATION 5.9.4.b January 01, 2019 - December 31, 2019
Annual Radiological Environmental Operating Report This report is submitted in accordance with Section 5.9.4.b of the Technical Specifications of Fort Calhoun Station Unit No. 1, Facility Operating License DPR-40 for the period January 01, 2019 through December 31, 2019.
In addition, this report provides any observations and anomalies that occurred during the monitoring period.
Reviewed by: Approved by:
RP/Chem Supervisor Manager-RP/Chemistry Plant Manager Decommissioning Senior Director of Nuclear Decommissioning
Annual Radiological Environmental Operating Report In accordance with Technical Specification 5.9.4.b, herein is the Fort Calhoun Station (FCS) Annual Radiological Environmental Operating Report for year 2019. The data provided is consistent with the objectives as specified in Section 6.2.2 of the Offsite Dose Calculation Manual (ODCM), Annual Radiological Environmental Operating Report. The report is presented as follows:
- 1) An introductory discussion of the implementation of the Radiological Environmental Monitoring Program (REMP), including program observations and environmental impact relevant to the operation of FCS.
- 2) The sample class, sample collection frequency, number of sample locations, and the number of samples collected this reporting period for each parameter is delineated in Table 1.0.
- 3) A statistical evaluation of REMP data is summarized in Table 2.0, in accordance with Regulatory Guide 4.8, Table 1. For each type of sample media and analysis, Table 2.0 presents data separately for all indicator locations, all control (background) locations, and the location having the highest annual mean result. For each of these classes, Table 2.0 specifies the following:
- a. The total number of analyses,
- b. The fraction of analyses yielding detectable results (i.e., results above the highest Lower Limit of Detection (LLD) for this period),
- c. The maximum, minimum, and average results,
- d. Locations with the highest annual mean are specified by code, name, and by distance and direction from the center of plant reactor containment building.
- 4) Table 3.0 is a listing of missed samples and explanations
- 5) Table 4.0 is the 2018 Land Use Survey
- 6) Review of Environmental Inc. Quality Assurance Program
- 7) Appendix A describes the Interlaboratory Comparison Program
- 8) Appendix B describes the vendor Data Reporting Conventions utilized
- 9) Appendix C is the Sample Location Maps Page 1 of 13
INTRODUCTION Radiological Environmental Monitoring Program (REMP) - 2019 This report gives the results of the Radiological Environmental Monitoring Program (REMP) for the year 2019.
The REMP is a requirement of the Fort Calhoun Station (FCS) operating license. It was initiated prior to plant operation in 1973.
The main purpose of the REMP is to ensure public safety by monitoring plant discharges and assessing the effect, if any, of plant operations on the environment. Samples are collected that would account for various exposure pathways such as ingestion, inhalation, adsorption and direct exposure. Samples collected on a regular basis include: air, surface water, ground water, milk, vegetation, fish, sediment, and food crops. Direct radiation is measured by thermoluminescent dosimeters (TLDs). These samples and TLDs are sent to an independent vendor laboratory for analysis. The vendor uses analytical methods that are sensitive enough to detect a level of activity far below that which would be considered harmful. Locations for sample collection are based on radiological and meteorological data from the Annual Effluent Release Report and information obtained from the Environmental Land Use Survey.
Most samples, particularly indicator samples, are collected in a circular area within a five-mile radius of plant containment. (However, control locations are usually outside of five miles.) This circle is divided into sixteen equal sectors, each assigned an identification letter A through R (note: letters I and O are not used, as they may be mistaken for the numbers 1 and 0). Sector A is centered on North or zero degrees. Sectors are also given directional labels such as West-Southwest (WSW). Sample locations are listed by number along with their respective distances and direction from plant containment, in the Offsite Dose Calculation Manual (ODCM).
When assessing sample results, data from indicator locations (those most likely to be affected by plant operations) are compared to those from control locations (those least or not likely to be affected). Results from an indicator location which were significantly higher than those from a control location could indicate a plant-attributable effect and could require additional investigation.
The results of the sample analyses, as required by the FCS Offsite Dose Calculation Manual (ODCM), are presented in the attached statistical tables in accordance with Table 1 of Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants. Sample collection was conducted by plant chemistry/environmental staff. A contract vendor (Environmental Inc., Northbrook, Illinois) performed sample analyses, preparation of monthly reports and the statistical evaluation of sample results. All vendor analysis techniques met the sensitivity requirements as stated in the ODCM.
Results for 2019 were within expected ranges and compared closely with historical results. The result details and exceptions are listed in the following sections.
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- 1) Ambient Gamma Radiation Ambient gamma radiation is measured by thermoluminescent dosimeters (TLDs) provided by the vendor laboratory. These dosimeters contain calcium sulfate phosphors and are processed quarterly.
Four incident condition reports were documented in the Corrective Action Program in 2019 related to TLD sampling. Two TLDs were not retrieved due to potentially unsafe river conditions in the first quarter due to high water and flooding prevented access by land. These TLDs were retrieved, and their data noted as having 2 quarters of exposure. Three TLDs were lost and could not be located; TLD OTD-1F was flooded twice, and TLD OTD-1D once. The samples were added to Table 3.0 to help reviewers of this report since the vendor attachments show that not all TLDs were collected/read.
All sample results are within the range of historical data and displayed less than 11% difference when compared to historical averages. All results were less than 3 sigma standard deviations from historical means. No discrepancy between released effluents and resultant radiation dose measured was observed. No changes in plant operation/procedures are required based upon observed impacts to the environment to date.
Twelve TLDs were added to the stations ODCM. These TLDs were placed within the owner controlled area to assist with determination of 40 CFR 190 doses. These locations are not included in Table 1.0, but are being described to assist reviewers of vendor analysis records.
10-Year Trend Comparison of TLD Locations Location Avg. Dose (mr/week) 2019 Avg. Dose (mr/week)
A 1.31 1.23 B 1.40 1.38 C 1.35 1.30 D 1.19 1.13 F 1.35 1.40 G 1.31 1.23 H 1.34 1.25 I 1.46 1.40 J 1.53 1.55 K 1.43 1.35 N 1.48 1.63 O 1.44 1.48 P 1.49 1.55 S 1.52 1.60 L (Control) 1.26 1.28 Page 3 of 13
- 2) Milk/Pasture Milk samples or pasture grasses, if milk is temporarily unavailable, are collected every two weeks during the pasture season from the beginning of May through September, and monthly the rest of the calendar year. Indicator samples are collected from a herd of milk goats at a family farm located approximately 3.3 miles from the plant in Sector K (Southwest). The control samples are collected from a commercial dairy cow herd located approximately 9.9 miles from the plant in Sector J (South). The indicator station and control location changed from last year. No indicator milk samples were available until spring (May) due to the dairy owners suspending operations. Late fall samples were not performed due to the does drying up before birthing. Pasture grass in lieu of milk was collected at the indicator location due to unavailability.
All sample results for Cesium-134, Cesium-137 and other gammas were at the LLD for both indicator and control locations. No plant-related effects were observed.
- 3) Fish Fish are collected on an annual basis. Control samples are collected at a location approximately twenty miles upstream of the plant (river miles 665 - 667). Indicator samples are collected in the immediate vicinity of the power plant (river miles 644 - 646). Several species of fish, important to commercial and recreational interest, representing all levels of the aquatic food chain are collected at both locations.
All sample results are within the range of historical data. Results from both control and indicator locations were less than LLD for all gamma emitters, indicating no plant-related effects.
- 4) Food Crop Based on the results of the biennial Land Use Survey, the nearest high deposition pathway for food crops is the Alvin Pechnik Farm in Sector H (0.94 miles, 163°). Accordingly, vegetable samples were collected at Alvin Pechnik Farm for the purposes of the 2019 REMP. Table 5.2 lists Lomp Acreage as the food crop sample locale. During the 2018 LUS, Penchnik Farm relayed their intention not to continue planting a garden. ODCM Table 5.2 was updated after the LUS, but not before samples were obtained from the garden listed in the 2016 LUS.
Samples were comparable with historical results and within the range of results reported from the control location garden at Mohr Dairy. The additional special interest samples were not obtained from on-site farm fields per plant Technical Specifications due to no crops being planted because of flooding, documented in CR 2019-00768. This sample is documented in Table 3.0.
All results were at the LLD for all non-naturally occurring radionuclides. No plant-related effects were observed.
- 5) Sediment River sediment samples were deleted from the program due to shoreline sediment not being a significant pathway and reduced volume of effluent release and activity.
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- 6) Air Monitoring Air sample results for 2019 were well within historical limits for all locations. Additionally, all indicator locations showed results very similar to the control locations.
All sample results are within the range of historical data. All indicator locations displayed less than 15%
difference when compared to historical average. All 2019 results when compared to historical averages are within the stated vendor error acceptance tolerance.
Results from both control and indicator locations were less than LLD for gamma emitters and iodine.
No changes in plant operation/procedures are required based upon observed impacts to the environment to date.
10-Year Trend Comparison of Air Sampling Locations Location Avg. Beta (pCi/m3) 2019 Avg. Beta (pCi/m3)
Sector B 0.027 0.026 Sector D 0.027 0.021 Sector I 0.024 0.019 Sector J 0.025 0.021 Sector K 0.026 0.020 Sector F (Control) 0.028 0.023
- 7) Surface Water Water samples are collected upstream of the plant (control location) as well as half-mile downstream and at a municipal water treatment plant on the north edge of Omaha.
Results for Cs-134, Cs-137, and other gammas were all less than LLD. All tritium results were less than LLD. No plant-related effects were detected.
- 8) Ground Water Quarterly residential well water samples are collected at the following four locations: Station No. 15:
Smith Farm, Station No. 20: Mohr Dairy, Station No. 74: D. Miller Farm and Station No. 75: Lomp Acreage. All sample results to date have been at the LLD except gross beta due to naturally occurring radionuclides. Gross beta results have ranged from a low of 2.2 pCi/liter to a high of 7.4 pCi/liter, with an average gross beta for the year of 3.7 pCi/liter for indicator locations. Strontium-90 analysis is being conducted on wells as part of the stations groundwater protection program. No plant-related effects were detected.
Page 5 of 13
Table 1.0 Sample Collection Program Collection Number of Samples Sample Class Frequency Sample Collected this Locations Period Background Radiation (TLDs) Quarterly 474 1815 Air Particulates Weekly 6 312 Airborne Iodine Weekly6 6 6 Biweekly Milk May thru Sept 2 271 Surface Water Monthly 3 36 Ground Water Quarterly 4 16 Fish Annually 2 52 Sediment Semi-annually 2 0 Food Crops Annually 2 83 TOTAL 919 Note 1: Milk sample collection total includes 9 vegetation samples performed for milk unavailability. Milk samples are collected every two weeks May-Sept. and monthly the rest of the year.
Note 2: Includes one background sample.
Note 3: Variety of samples collected during period Note 4: Twelve sample locations were added for assessing 40 CFR 190 doses. The results are not included in REMP program totals.
Note 5: See table of missed samples for explanations.
Note 6: Collection was terminated on 1/9/19.
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Reporting Table 2.0 Radiological Environmental Monitoring Program Summary Period January-December, 2019 Name of Facility Fort Calhoun Nuclear Power Station - Unit 1 Docket No. 50-285 Location of Facility Washington, Nebraska
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Number Mean (F)c Type of LLDb Mean (F)c Mean (F)c Routine Rangec (Units) Analysesa Rangec Locationd Rangec Resultse Background Gamma 181 0.5 1.4 (170/177) OTD-1K-(I), 1.7 (4/4) 1.3 (4/4) 0 Radiation ( 1.1-1.8) 0.61 mi. @ 205° 1.6-1.8 (1.2-1.4)
(TLD) 1.8 (1/1)
(mR/week) 0.021 Airborne GB 312 0.005 (260/260) OAP-B-(I) 0.025 (52/52) 0.023 (52/52) 0 Particulates (0.019-0.025) 0.6 miles SW (0.011-0.050) (0.007-0.067)
(pCi/m3) GS 24 Cs-134 0.001 < LLD - - < LLD 0 Cs-137 0.001 < LLD - - < LLD 0 Other Gammas 0.001 < LLD - - < LLD 0 Airborne I-131 6 0.07 < LLD - - < LLD 0 Iodine (pCi/m3)
Milk I-131 18 0.5 < LLD - - < LLD 0 (pCi/L)
GS 18 K-40 150 1793 (4/4) C. Miller Farm 1793 (4/4) 1328 (6/6) 0 (1665-1937) 3.3 mi. @ 210 ° (1665-1937) (1250-1385)
Cs-134 15 < LLD - - < LLD 0 Cs-137 15 < LLD - - < LLD 0 Other Gammas 15 < LLD - - < LLD 0 Ground Water GB 16 3.7 (10/12) Lomp Acreage 4.3 (3/4) 3.2 (4/4) 0 (pCi/L) (2.2-7.4) 0.65 mi.@163° (2.8-5.7) (2.2-4.0)
H-3 16 300 < LLD - - < LLD 0 Sr-90 16 0.7 < LLD - - < LLD 0 GS 16 (pCi/L) Cs-134 15 < LLD - - < LLD 0 Cs-137 18 < LLD - - < LLD 0 Other Gammas 15 < LLD - - < LLD 0 Surface Water GS 36 (pCi/L) Cs-134 15 < LLD - - < LLD 0 Cs-137 18 < LLD - - < LLD 0 Other Gammas 15 < LLD - - < LLD 0 H-3 12 300 < LLD - - < LLD 0 Page 7 of 13
Table 2.0 Radiological Environmental Monitoring Program Summary Reporting Period January-December, 2019 Name of Facility Fort Calhoun Nuclear Power Station - Unit 1 Docket No. 50-285 Location of Facility Washington, Nebraska
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Location d Rangec Rangec Resultse Fish GS 5 (pCi/g wet) Mn-54 0.022 < LLD - - < LLD 0 Co-58 0.023 < LLD - - < LLD 0 Co-60 0.019 < LLD - - < LLD 0 Fe-59 0.057 < LLD - - < LLD 0 Zn-65 0.042 < LLD - - < LLD 0 Ru-103 0.038 < LLD - - < LLD 0 Cs-134 0.019 < LLD - - < LLD 0 Cs-137 0.022 < LLD - - < LLD 0 Sediment GS 0 pCi/g dry Mn-54 0.000 < LLD - - < LLD 0 Co-58 0.000 < LLD - - < LLD 0 Co-60 0.000 < LLD - - < LLD 0 Fe-59 0.000 < LLD - - < LLD 0 Zn-65 0.000 < LLD - - < LLD 0 Cs-134 0.000 < LLD - - < LLD 0 Cs-137 0.000 < LLD - - < LLD 0 Food Crops GS 8 (pCi/g wet) Mn-54 0.014 < LLD - - < LLD 0 Co-58 0.020 < LLD - - < LLD 0 Co-60 0.022 < LLD - - < LLD 0 Fe-59 0.042 < LLD - - < LLD 0 Zn-65 0.056 < LLD - - < LLD 0 Zr-Nb-95 0.023 < LLD - - < LLD 0 Cs-134 0.023 < LLD - - < LLD 0 Cs-137 0.024 < LLD - - < LLD 0 Ba-La-140 0.019 < LLD - - < LLD 0 a
GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 95% confidence level.
c Mean and range are based on detectable measurements only (i.e., >LLD) Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by code, (2) by name, and (3) by distance and direction relative to the Reactor Containment Building.
e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds the typical pre-operational value for the medium or location.
Page 8 of 13
Table 3.0 Listing of Missed Samples (samples scheduled but not collected)
Sample Date Location Reason Type TLD 03-31-19 OTD-1D The TLD was not recovered after searching the area. (Condition Report 2019-00359)
TLD 03-31-19 OTD-1A The TLD was not retrieved due to potentially unsafe river conditions due to high water and flooding prevented access by land. (Condition Report 2019-00359) Read the next quarter TLD 03-31-19 OTD-1F The TLD was not retrieved due to potentially unsafe river conditions due to high water and flooding prevented access by land. (Condition Report 2019-00359)
TLD 03-31-19 OTD-2D The TLD was not retrieved due to potentially unsafe river conditions due to high water and flooding prevented access by land. (Condition Report 2019-00359) Read the next quarter TLD 06-30-19 OTD-1F The TLD was not retrieved due to potentially unsafe river conditions due to high water and flooding prevented access by land. (Condition Report 2019-00696)
Food 08-05-19 OVG The Food Crop (Field Corn) was not retrieved due flooding Crop prevented crop from being planted. (Condition Report 2019-00768)
TLD 09-30-19 OTD-1F The TLD was not retrieved due to potentially unsafe river conditions due to high water and flooding prevented access by land. (Condition Report 2019-00946)
TLD 12-31-19 OTD-1F The TLD was not retrieved due to potentially unsafe river conditions due to high water and flooding prevented access by land. (Condition Report 2020-00013)
Page 9 of 13
Table 4.0 - 2018 Land Use Survey Page 10 of 13
Table 4.0 - 2018 Land Use Survey Page 11 of 13
Table 4.0 - 2018 Land Use Survey Page 12 of 13
Review of Environmental Inc., Quality Assurance Program Fort Calhoun Station contracts with Environmental Inc., Midwest Laboratory (vendor lab) to perform radioanalysis of environmental samples. Environmental Inc. participates in inter-laboratory comparison (cross-check) programs as part of its quality control program. These programs are operated by such agencies as the Department of Energy, which supply blind-spike samples such as milk or water containing concentrations of radionuclides unknown to the testing laboratory. This type of program provides an independent check of the analytical laboratorys procedures and processes, and provides indication of possible weaknesses. In addition, Environmental Inc. has its own in-house QA program of blind-spike and duplicate analyses.
Vendor in-house spike sampling was performed with one failure and in-house blank analyses were performed within acceptable ranges. The failure was within the cross check program tolerances, but not the vendor internal administrative limits. Routine FCS REMP duplicates samples were performed by the vendor to verify reproducibility of results. All duplicates were within acceptance criteria.
Environmental resource cross check samples ERW-75 and ERW-1141 for Total Uranium failed the acceptance criteria. Due to 2018 Uranium failures a Uranium study was conducted by the lab. New tracer standard with known NIST standards was performed with U-238 solution. This produced acceptable results upon reanalysis for ERW-75. This U-238 tracer had an interference issue with U-232 analysis, this led to the high result on ERW-1141 in April. After performing U-isotopic chemistry on the NIST-Uranium solution to remove interferences, a more accurate U-232 tracer concentration was obtained. A duplicate analysis was performed with acceptable results. .An ERW-2477 sample for total Uranium was perform successfully in July. ERA MRAD-30 cross check sample ERAP 846 failed on Uranium isotopes. These failures and the ERW-2563 failure from the 2018 report were based on the U-232 tracer interference issue. The subsequent ERA PT study was deemed acceptable.
Two DOE MAPEP cross check sample failed in 2019. DOE cross check sample MAAP-611 sample for Sr-90, U-234/233, and U-238 failed the acceptance criteria due to an erroneous volume conversion utilized. If the conversion was performed correctly acceptable results would be obtained. MAW-613 sample for PU-238 failed the acceptance criteria and the investigation is in progress to determine cause for failure. None of these analyses are performed as part of the FCS REMP program.
The vendor had one failure identified during the third quarter of 2019. The ERW-2479 sample for H-3 results were understated by half due to a wrong count time utilized. Errors were identified (extra blank sample) and the reanalysis was within control limits. FCS vendor does perform tritium analyses for the REMP program, however this error would not impact FCS results.
No test results failed both the ERA and DOE methodologies for a given sample type. Reanalysis produced acceptable results. The ordering of additional tests and successful testing after corrections were applied, visibly demonstrates the vendor's commitment to reporting and resolving deficiencies.
These results indicate the vendors ability to self-identify and correct any deviations from acceptable or expected results. The test results had no impact on Fort Calhoun samples and were documented as such by the vendor. No changes are deemed necessary to the FCS REMP program due to vendor performance.
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APPENDIX A INTERLABORATORY AND INTRALABORATORY COMPARISON PROGRAM RESULTS NOTE: Appendix A is updated four times a year. The complete appendix is included in March, June, September and December monthly progress reports only.
October, 2018 through September, 2019
Appendix A Interlaboratory/ Intralaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratorys analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-1 were obtained through participation in the RAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Table A-2 lists results for thermoluminescent dosimeters (TLDs), via irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.
Table A-3 lists results of the analyses on in-house spiked samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house blank samples for the past twelve months. Data for previous years available upon request.
Table A-5 lists analytical results from the in-house duplicate program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory acceptance criteria for various analyses.
Out-of-limit results are explained directly below the result.
A-1
Attachment A ACCEPTANCE CRITERIA FOR SPIKED SAMPLES Analysis Ratio of lab result to known value.
Gamma Emitters 0.8 to 1.2 Strontium-89, 0.8 to 1.2 Strontium-90 Potassium-40 0.8 to 1.2 Gross alpha 0.5 to 1.5 Gross beta 0.8 to 1.2 Tritium 0.8 to 1.2 Radium-226, 0.7 to 1.3 Radium-228 Plutonium 0.8 to 1.2 Iodine-129, 0.8 to 1.2 Iodine-131 Nickel-63, 0.7 to 1.3 Technetium-99, Uranium-238 Iron-55 0.8 to 1.2 Other Analyses 0.8 to 1.2 A-2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) a.
RAD study Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance ERW-71 1/7/2019 Ba-133 97.9 +/- 4.5 99.5 84.1 - 109 Pass ERW-71 1/7/2019 Cs-134 45.4 +/- 3.1 49.1 39.5 - 54.0 Pass ERW-71 1/7/2019 Cs-137 129 +/-6 125 112 - 140 Pass ERW-71 1/7/2019 Co-60 98.1 +/- 4.1 96.4 86.8 - 108 Pass ERW-71 1/7/2019 Zn-65 80.4 +/- 7.8 77.4 69.5 +/- 93.2 Pass ERW-73 1/7/2019 Gr. Alpha 22.2 +/- 1.6 21.8 10.9 - 29.5 Pass ERW-73 1/7/2019 Gr. Beta 46.4 +/- 1.4 55.7 38.1 - 62.6 Pass ERW-75 1/7/2019 Ra-226 7.19 +/- 0.30 7.37 5.55 +/- 8.72 Pass ERW-75 1/7/2019 Ra-228 4.02 +/- 0.70 4.28 2.48 - 5.89 Pass ERW-75 1/7/2019 Uranium 50.2 +/- 2.9 68.2 55.7 - 75.0 Failb ERW-77 1/7/2019 H-3 2,129 +/- 158 2,110 1,740 - 2,340 Pass ERW-397 2/11/2019 I-131 27.2 +/- 1.0 25.9 25.1 - 30.6 Pass ERW-1141 4/8/2019 Ra-226 7.58 +/- 0.53 7.15 5.39 - 8.48 Pass ERW-1141 4/8/2019 Ra-228 2.64 +/- 0.79 2.94 1.54 - 4.35 Pass ERW-1141 4/8/2019 Uranium 67.0 +/- 0.9 55.9 45.6 - 61.5 Failc ERW-2471 7/8/2019 Ba-133 66.5 +/- 4.0 66.9 55.8 - 73.6 Pass ERW-2471 7/8/2019 Cs-134 29.6 +/- 2.6 32.0 25.1 - 35.2 Pass ERW-2471 7/8/2019 Cs-137 21.3 +/- 3.6 21.4 17.6 - 26.7 Pass ERW-2471 7/8/2019 Co-60 99.9 +/- 4.4 95.1 85.6 - 107.0 Pass ERW-2471 7/8/2019 Zn-65 43.7 +/- 6.2 41.2 35.3 - 51.4 Pass ERW-2473 7/8/2019 Gr. Alpha 41.7 +/- 2.1 70.6 37.1 - 87.1 Pass ERW-2473 7/8/2019 Gr. Beta 57.0 +/- 1.6 63.9 44.2 - 70.5 Pass ERW-2477 7/8/2019 Ra-226 16.2 +/- 0.5 18.5 13.8 - 21.1 Pass ERW-2477 7/8/2019 Ra-228 6.2 +/- 0.8 8.2 5.2 - 10.3 Pass ERW-2477 7/8/2019 Uranium 63.8 +/- 3.6 68.3 55.8 - 75.1 Pass ERW-2479 7/8/2019 H-3 8,630 +/- 200 16,700 14,600 - 18,400 Faild ERW-2475 7/8/2019 I-131 33.6 +/- 1.3 29.6 24.6 - 34.6 Pass a
Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resource Associates (ERA).
b In order to get to the root cause of the above "Fail" resolution the U-232 tracer was standardized using a known concentration of NIST U-238 solution. A duplicate analysis was performed and the results obtained were well within the acceptance range (Known value for Total Uranium=68.2 pCi/L, acceptance range of (55.7-75 pCi/L). The results obtained were 63.3 pCi/L and 66.0 pCi/L respectively.
c The standardized U-232 value utilized on ERA sample ERW-75 (see footnote "b" above was found to be estimated high due to interferences in the U-238 solution causing the ERW-1141 Uranium PT failure above. After performing U-isotopic chemistry on the NIST-Uranium solution to remove interferences a more accurate U-232 tracer concentration was obtained. The subsequent ERA PT study was acceptable. See ERW-2477 Uranium result above.
d H-3 analysis was performed using the ERA provided blank sample. Pairing the ERA supplied blank and the lab routine blank with standard vials created confusion and resulted in the standard total count time being mistallied by half.
The resulting batch efficiency was overstated by a factor of two and the reported ERA results were understated by half.
The result of reanalysis, (17,400 pCi/L), is within the control limits for the study.
A-3
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).a mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P)
Environmental, Inc. Group 1 2018-1 11/15/2018 Spike 1 97.0 81.6 -0.16 2018-1 11/15/2018 Spike 2 97.0 88.5 -0.09 2018-1 11/15/2018 Spike 3 97.0 87.9 -0.09 2018-1 11/15/2018 Spike 4 97.0 85.6 -0.12 2018-1 11/15/2018 Spike 5 97.0 86.5 -0.11 2018-1 11/15/2018 Spike 6 97.0 89.0 -0.08 2018-1 11/15/2018 Spike 7 97.0 85.1 -0.12 2018-1 11/15/2018 Spike 8 97.0 90.6 -0.07 2018-1 11/15/2018 Spike 9 97.0 91.3 -0.06 2018-1 11/15/2018 Spike 10 97.0 84.5 -0.13 2018-1 11/15/2018 Spike 11 97.0 90.8 -0.06 2018-1 11/15/2018 Spike 12 97.0 93.8 -0.03 2018-1 11/15/2018 Spike 13 97.0 85.3 -0.12 2018-1 11/15/2018 Spike 14 97.0 85.5 -0.12 2018-1 11/15/2018 Spike 15 97.0 86.9 -0.10 2018-1 11/15/2018 Spike 16 97.0 88.6 -0.09 2018-1 11/15/2018 Spike 17 97.0 83.1 -0.14 2018-1 11/15/2018 Spike 18 97.0 85.4 -0.12 2018-1 11/15/2018 Spike 19 97.0 83.3 -0.14 2018-1 11/15/2018 Spike 20 97.0 85.5 -0.12 Mean (Spike 1-20) 86.9 -0.10 Passd Standard Deviation (Spike 1-20) 3.1 0.03 Passd a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.
b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)K a = 1.20 . mrem/cGy = 1000.
c Performance Quotient (P) is calculated as ((reported dose - conventially true value) ÷ conventially true value) where the conventially true value is the delivered dose.
d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.
A-4
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).a mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P)
Environmental, Inc. Group 2 2018-2 11/15/2018 Spike 21 143.0 130.3 -0.09 2018-2 11/15/2018 Spike 22 143.0 128.1 -0.10 2018-2 11/15/2018 Spike 23 143.0 134.4 -0.06 2018-2 11/15/2018 Spike 24 143.0 129.0 -0.10 2018-2 11/15/2018 Spike 25 143.0 132.5 -0.07 2018-2 11/15/2018 Spike 26 143.0 126.1 -0.12 2018-2 11/15/2018 Spike 27 143.0 126.2 -0.12 2018-2 11/15/2018 Spike 28 143.0 122.4 -0.14 2018-2 11/15/2018 Spike 29 143.0 118.8 -0.17 2018-2 11/15/2018 Spike 30 143.0 123.2 -0.14 2018-2 11/15/2018 Spike 31 143.0 137.2 -0.04 2018-2 11/15/2018 Spike 32 143.0 144.4 0.01 2018-2 11/15/2018 Spike 33 143.0 137.8 -0.04 2018-2 11/15/2018 Spike 34 143.0 140.2 -0.02 2018-2 11/15/2018 Spike 35 143.0 143.8 0.01 2018-2 11/15/2018 Spike 36 143.0 146.7 0.03 2018-2 11/15/2018 Spike 37 143.0 150.0 0.05 2018-2 11/15/2018 Spike 38 143.0 126.1 -0.12 2018-2 11/15/2018 Spike 39 143.0 136.2 -0.05 2018-2 11/15/2018 Spike 40 143.0 144.8 0.01 Mean (Spike 21-40) 133.9 -0.06 Passd Standard Deviation (Spike 21-40) 9.0 0.06 Passd a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.
b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(10)K a = 1.20 . mrem/cGy = 1000.
c Performance Quotient (P) is calculated as ((reported dose - conventially true value) ÷ conventially true value) where the conventially true value is the delivered dose.
d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.
A-5
TABLE A-3. In-House "Spiked" Samples Concentrationa Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known SPW-3991 10/1/2018 H-3 15,614 +/- 369 16,507 13,206 - 19,808 Pass 0.95 SPW-4105 10/5/2018 H-3 15,669 +/- 370 16,507 13,206 - 19,808 Pass 0.95 W-101118 4/29/2016 Cs-134 33.5 +/- 3.1 36.2 29.0 - 43.4 Pass 0.92 W-101118 4/29/2016 Cs-137 79.7 +/- 3.2 71.9 57.5 - 86.3 Pass 1.11 SPW-4205 10/12/2018 H-3 15,821 +/- 372 16,507 13,206 - 19,808 Pass 0.96 SPW-4274 10/17/2018 H-3 15,575 +/- 369 16,507 11,555 - 21,459 Pass 0.94 SPW-4596 10/31/2018 H-3 15,650 +/- 369 16,507 13,206 - 19,808 Pass 0.95 SPW-4682 11/1/2018 H-3 15,742 +/- 371 16,507 13,206 - 19,808 Pass 0.95 SPW-4684 11/1/2018 Sr-90 19.1 +/- 1.2 17.9 14.3 - 21.5 Pass 1.07 SPW-4790 11/9/2018 H-3 15,887 +/- 373 16,507 13,206 - 19,808 Pass 0.96 SPW-4839 11/13/2018 Ni-63 381 +/- 43 465 326 - 605 Pass 0.82 SPW-4863 11/16/2018 H-3 15,610 +/- 370 16,507 13,206 - 19,808 Pass 0.95 W-111618 4/29/2016 Cs-134 38.0 +/- 12.4 36.2 25.3 - 47.1 Pass 1.05 W-111618 4/29/2016 Cs-137 83.8 +/- 13.8 71.9 57.5 - 86.3 Pass 1.17 SPW-5049 11/30/2018 H-3 15,370 +/- 366 16,507 13,206 - 19,808 Pass 0.93 SPW-5148 12/7/2018 H-3 15,522 +/- 368 16,507 13,206 - 19,808 Pass 0.94 W-121118 4/29/2016 Cs-134 39.4 +/- 7.9 36.2 29.0 - 43.4 Pass 1.09 W-121118 4/29/2016 Cs-137 78.5 +/- 7.7 71.9 57.5 - 86.3 Pass 1.09 W-121218 4/29/2016 Cs-134 42.0 +/- 13.8 36.2 25.3 - 47.1 Pass 1.16 W-121218 4/29/2016 Cs-137 79.2 +/- 13.1 71.9 57.5 - 86.3 Pass 1.10 W-121318 4/29/2016 Cs-134 35.1 +/- 7.8 36.2 25.3 - 47.1 Pass 0.97 W-121318 4/29/2016 Cs-137 77.5 +/- 8.4 71.9 50.3 - 93.5 Pass 1.08 SPW-5279 12/14/2018 H-3 15,686 +/- 370 16,507 13,206 - 19,808 Pass 0.95 W-121418 4/29/2016 Cs-134 34.5 +/- 8.2 36.2 29.0 - 43.4 Pass 0.95 W-121418 4/29/2016 Cs-137 82.7 +/- 8.0 71.9 57.5 - 86.3 Pass 1.15 W-121718 4/29/2016 Cs-134 34.9 +/- 10.5 36.2 29.0 - 43.4 Pass 0.96 W-121718 4/29/2016 Cs-137 80.3 +/- 8.1 71.9 57.5 - 86.3 Pass 1.12 SPW-5351 12/19/2018 H-3 15,855 +/- 375 16,507 13,206 - 19,808 Pass 0.96 SPW-5404 12/31/2018 H-3 15,179 +/- 365 16,507 13,206 - 19,808 Pass 0.92 SPW-5450 12/31/2018 Gr. Alpha 56.5 +/- 2.6 72.4 36.2 - 108.6 Pass 0.78 SPW-5450 12/31/2018 Gr. Beta 45.1 +/- 1.4 54.8 43.8 - 65.8 Pass 0.82 SPW-5615 12/31/2018 Fe-55 831.0 +/- 43.5 732.6 586.0 - 879.1 Pass 1.13 SPW-5619 12/31/2018 Tc-99 99.0 +/- 1.7 107.8 86.2 - 129.4 Pass 0.92 SPW-61 11/5/2018 Ra-226 13.4 +/- 0.4 12.3 8.6 - 16.0 Pass 1.09 SPW-118 1/14/2019 H-3 15,463 +/- 369 16,507 13,206 - 19,808 Pass 0.94 SPW-178 1/16/2019 Ra-228 17.7 +/- 2.1 15.1 10.58 - 19.66 Pass 1.17 SPW-199 1/18/2019 Sr-90 17.6 +/- 1.2 17.9 14.3 - 21.5 Pass 0.98 SPW-250 1/24/2019 Ni-63 356.3 +/- 44.5 465 326 - 605 Pass 0.77 SPW-256 1/15/2019 Ra-226 12.0 +/- 0.4 12.3 8.6 - 16.0 Pass 0.98 SPW-271 3/18/2019 H-3 22,035 +/- 450 21,700 17,360 - 26,040 Pass 1.02 SPW-281 1/25/2019 Ra-226 11.6 +/- 0.4 12.3 8.6 - 16.0 Pass 0.94 W-012119 4/29/2016 Cs-134 37.3 +/- 10.6 36.2 29.0 - 43.4 Pass 1.03 W-012119 4/29/2016 Cs-137 82.7 +/- 8.0 71.9 57.5 - 86.3 Pass 1.15 W-012319 4/29/2016 Cs-134 33.4 +/- 10.1 36.2 25.3 - 47.1 Pass 0.92 W-012319 4/29/2016 Cs-137 79.1 +/- 9.6 71.9 57.5 - 86.3 Pass 1.10 W-012519 4/29/2016 Cs-134 35.0 +/- 7.7 36.2 29.0 - 43.4 Pass 0.97 W-012519 4/29/2016 Cs-137 79.2 +/- 7.9 71.9 57.5 - 86.3 Pass 1.10 W-012919 4/29/2016 Cs-134 32.3 +/- 8.3 36.2 29.0 - 43.4 Pass 0.89 W-012919 4/29/2016 Cs-137 82.3 +/- 8.3 71.9 57.5 - 86.3 Pass 1.14 A-6
TABLE A-3. In-House "Spiked" Samples Concentrationa Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known SPW-370 3/19/2019 H-3 21,689 +/- 444 21,700 17,360 - 26,040 Pass 1.00 SPW-400 1/31/2019 Ra-226 11.6 +/- 0.4 12.3 8.6 - 16.0 Pass 0.95 SPW-461 2/12/2019 Ra-226 11.1 +/- 0.4 12.3 8.6 - 16.0 Pass 0.90 W-020619 4/26/2016 Cs-134 35.0 +/- 14.9 36.2 29.0 - 43.4 Pass 0.97 W-020619 4/29/2016 Cs-137 72.8 +/- 8.9 71.9 57.5 - 86.3 Pass 1.01 W-020819 4/26/2016 Cs-134 36.7 +/- 8.6 36.2 29.0 - 43.4 Pass 1.01 W-020819 4/29/2016 Cs-137 76.7 +/- 8.7 71.9 57.5 - 86.3 Pass 1.07 SPW-568 2/21/2019 Ra-226 10.3 +/- 0.3 12.3 8.6 - 16.0 Pass 0.84 W-021319 4/29/2016 Cs-134 37.7 +/- 11.5 36.2 29.0 - 43.4 Pass 1.04 W-021319 4/26/2016 Cs-137 75.8 +/- 9.6 71.9 57.5 - 86.3 Pass 1.05 SPW-469 3/19/2019 H-3 21,696 +/- 447 21,700 17,360 - 26,040 Pass 1.00 SPW-600 3/6/2019 H-3 20,710 +/- 425 21,700 17,360 - 26,040 Pass 0.95 SPW-837 3/21/2019 Ra-228 11.7 +/- 1.5 15.1 10.58 - 19.66 Pass 0.78 SPW-709 3/19/2019 H-3 20,369 +/- 421 21,700 17,360 - 26,040 Pass 0.94 SPW-818 3/19/2019 H-3 20,457 +/- 424 21,700 17,360 - 26,040 Pass 0.94 SPW-844 3/22/2019 U-234 15.1 +/- 0.5 13.6 9.5 - 17.7 Pass 1.11 SPW-844 3/22/2019 U-238 15.3 +/- 0.5 13.1 9.2 - 17.0 Pass 1.17 SPW-934 3/19/2019 H-3 20,487 +/- 421 21,700 17,360 - 26,040 Pass 0.94 SPW-1061 3/1/2019 Ra-226 10.6 +/- 0.3 12.3 8.6 - 16.0 Pass 0.86 SPW-1091 4/10/2019 H-3 20,323 +/- 421 21,700 17,360 - 26,040 Pass 0.94 SPW-1093 4/8/2019 Ra-228 14.9 +/- 1.9 15.1 10.6 - 19.6 Pass 0.98 SPW-1267 4/16/2019 H-3 20,302 +/- 421 21,700 17,360 - 26,040 Pass 0.94 SPW-1339 4/18/2019 H-3 19,924 +/- 417 21,700 17,360 - 26,040 Pass 0.92 SPW-1403e 4/25/2019 Gr. Alpha 56.7 +/- 2.6 72.4 36.2 - 108.6 Pass 0.78 SPW-1403e 4/25/2019 Gr. Beta 43.2 +/- 1.4 54.8 43.8 - 65.8 Fail 0.79 SPW-1427 4/26/2019 H-3 20,119 +/- 418 21,700 15,190 - 28,210 Pass 0.93 SPW-1537 5/6/2019 Sr-90 19.9 +/- 1.2 17.9 14.3 - 21.5 Pass 1.11 W-050719 4/29/2016 Cs-134 38.5 +/- 9.0 36.2 29.0 - 43.4 Pass 1.06 W-050719 4/26/2016 Cs-137 85.2 +/- 8.5 71.9 57.5 - 86.3 Pass 1.18 SPW-1582 5/9/2019 H-3 20,492 +/- 423 21,700 15,190 - 28,210 Pass 0.94 W-050919 4/29/2016 Cs-134 37.4 +/- 8.9 36.2 29.0 - 43.4 Pass 1.03 W-050919 4/26/2016 Cs-137 81.5 +/- 7.8 71.9 57.5 - 86.3 Pass 1.13 SPW-1596 5/8/2019 Ra-228 14.1 +/- 1.7 15.1 10.6 - 19.6 Pass 0.94 W-051419 4/29/2016 Cs-134 36.2 +/- 11.7 36.2 29.0 - 43.4 Pass 1.00 W-051419 4/26/2016 Cs-137 75.8 +/- 10.0 71.9 57.5 - 86.3 Pass 1.05 SPW-1676 5/17/2019 H-3 20,233 +/- 420 21,700 15,190 - 28,210 Pass 0.93 SPW-1799 5/20/2019 H-3 20,428 +/- 422 21,700 15,190 - 28,210 Pass 0.94 SPW-1858 5/28/2019 H-3 20,367 +/- 522 21,700 15,190 - 28,210 Pass 0.94 SPW-1890 5/30/2019 H-3 20,206 +/- 419 21,700 15,190 - 28,210 Pass 0.93 SPW-2014 5/31/2019 Ra-226 11.9 +/- 0.3 12.3 8.6 - 16.0 Pass 0.97 SPW-2030 6/12/2019 Ni-63 377 +/- 45 464.8 325 - 604 Pass 0.81 SPW-2093 6/18/2019 H-3 20,158 +/- 418 21,700 15,190 - 28,210 Pass 0.93 W-062419 4/29/2016 Cs-134 33.0 +/- 12.4 36.2 29.0 - 43.4 Pass 0.91 W-062419 4/26/2016 Cs-137 66.0 +/- 10.4 71.9 57.5 - 86.3 Pass 0.92 SPW-2338 6/26/2019 H-3 20,032 +/- 417 21,700 15,190 - 28,210 Pass 0.92 A-7
TABLE A-3. In-House "Spiked" Samples Concentrationa b
Lab Code Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known W-072619 4/29/2016 Cs-134 36.3 +/- 9.2 36.2 29.0 - 43.4 Pass 1.00 W-072619 4/26/2016 Cs-137 79.7 +/- 7.6 71.9 57.5 - 86.3 Pass 1.11 SPW-3188 7/30/2019 Ra-226 11.9 +/- 0.3 12.3 8.6 - 16.0 Pass 0.97 SPW-2925 8/6/2019 Sr-90 10.7 +/- 1.0 SPW-2947 8/9/2019 H-3 20,128 +/- 425 21,700 15,190 - 28,210 Pass 0.93 SPW-3003 8/14/2019 H-3 20,588 +/- 435 21,700 15,190 - 28,210 Pass 0.95 W-081519 4/26/2019 Cs-134 36.2 +/- 9.2 36.2 29.0 - 43.4 Pass 1.00 W-081519 4/26/2019 Cs-137 78.1 +/- 8.4 71.9 57.5 - 86.3 Pass 1.09 W-082119 4/26/2019 Cs-134 32.8 +/- 9.1 36.2 29.0 - 43.4 Pass 0.91 W-082119 4/26/2019 Cs-137 79.1 +/- 7.9 71.9 57.5 - 86.3 Pass 1.10 SPW-3151 8/26/2019 H-3 20,329 +/- 428 21,700 15,190 - 28,210 Pass 0.94 W-082619 4/26/2019 Cs-134 33.3 +/- 17.8 36.2 29.0 - 43.4 Pass 0.92 W-082619 4/26/2019 Cs-137 82.6 +/- 13.2 71.9 57.5 - 86.3 Pass 1.15 W-082719 4/26/2019 Cs-134 33.9 +/- 7.0 36.2 29.0 - 43.4 Pass 0.94 W-082719 4/26/2019 Cs-137 81.4 +/- 6.0 71.9 57.5 - 86.3 Pass 1.13 SPW-3359 8/30/2019 Gr. Alpha 54.2 +/- 0.3 72.4 36.2 - 108.6 Pass 0.75 SPW-3359 8/30/2019 Gr. Beta 59.7 +/- 0.2 54.8 43.8 - 65.8 Pass 1.09 SPW-3323 9/6/2019 Ra-228 12.7 +/- 1.8 15.1 10.6 - 19.6 Pass 0.84 W-091019 4/26/2019 Cs-134 31.0 +/- 11.3 36.2 29.0 - 43.4 Pass 0.86 W-091019 4/26/2019 Cs-137 80.5 +/- 10.0 71.9 57.5 - 86.3 Pass 1.12 SPW-3349 9/10/2019 H-3 19,851 +/- 422 21,700 15,190 - 28,210 Pass 0.91 SPW-3410 9/13/2019 H-3 20,267 +/- 431 21,700 15,190 - 28,210 Pass 0.93 W-091719 4/26/2019 Cs-134 39.3 +/- 12.6 36.2 29.0 - 43.4 Pass 1.09 W-091719 4/26/2019 Cs-137 81.1 +/- 9.9 71.9 57.5 - 86.3 Pass 1.13 SPW-3450 9/17/2019 H-3 20,036 +/- 427 21,700 15,190 - 28,210 Pass 0.92 W-091919 9/19/2019 Cs-134 40.0 +/- 10.7 36.2 29.0 - 43.4 Pass 1.10 W-091919 9/19/2019 Cs-137 71.0 +/- 8.7 71.9 57.5 - 86.3 Pass 0.99 SPW-3569 8/28/2019 Ra-226 11.9 +/- 0.3 12.3 8.6 - 16.0 Pass 0.97 SPW-3571 9/27/2019 H-3 21,026 +/- 440 21,700 15,190 - 28,210 Pass 0.97 a
Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b Laboratory codes : W & SPW (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
c Results are based on single determinations.
d Control limits are listed in Attachment A of this report.
e The LCS sample was prepared from an Environmental Resource Associates (ERA) sample of known activity. While the analysis did satisfy the acceptance criteria of the ERA study from which it was sourced, it did not satisfy EIML's internal LCS acceptance criteria. All of the original solution had been consumed in the analysis. Subsequent gross alpha and beta PT and LCS sample results were acceptable.
NOTE: For fish, gelatin is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.
A-8
TABLE A-4. In-House "Blank" Samples Concentrationa b c Lab Code Sample Date Analysis Laboratory results (4.66V) Acceptance Type LLD Activityd Criteria (4.66 V)
SPW-3990 Water 10/1/2018 H-3 153 -6 +/- 71 200 SPW-4105 Water 10/5/2018 H-3 150 7 +/- 71 200 SPW-4565 Water 10/11/2018 Ra-228 0.86 -0.26 +/- 0.36 2 SPW-4205 Water 10/12/2018 H-3 154 -9 +/- 71 200 SPW-4273 Water 10/17/2018 H-3 153 67 +/- 76 200 SPW-4595 Water 10/30/2018 H-3 150 75 +/- 74 200 SPW-4681 Water 11/1/2018 H-3 152 19 +/- 72 200 SPW-4683 Water 11/1/2018 Sr-89 0.64 0.25 +/- 0.45 5 SPW-4683 Water 11/1/2018 Sr-90 0.51 -0.10 +/- 0.22 1 SPW-4789 Water 11/9/2018 H-3 148 27 +/- 73 200 SPW-4799 Water 11/9/2018 I-131 0.43 -0.01 +/- 0.20 1 SPW-4838 Water 11/13/2018 Ni-63 62 34 +/- 38 200 SPW-4862 Water 11/16/2018 H-3 154 15 +/- 77 200 SPW-5028 Water 11/19/2018 Ra-226 0.04 -0.14 +/- 0.03 2 SPW-5028 Water 11/19/2018 Ra-228 0.96 -0.11 +/- 0.43 2 SPW-5048 Water 11/30/2018 H-3 151 -6 +/- 69 200 SPW-5147 Water 12/7/2018 H-3 151 14 +/- 71 200 SPW-5278 Water 12/14/2018 H-3 153 83 +/- 76 200 SPW-5350 Water 12/19/2018 H-3 153 71 +/- 75 200 SPW-5403 Water 12/31/2018 H-3 156 51 +/- 75 200 SPW-5614 Water 12/31/2018 Fe-55 612 -68 +/- 368 1000 SPW-5618 Water 12/31/2018 Tc-99 11 7 +/-7 100 SPW-34 Water 1/7/2019 I-131 0.36 0.13 +/- 0.18 1 SPW-60 Water 11/5/2019 Ra-226 0.03 0.15 +/- 0.03 2 SPW-119 Water 1/14/2019 H-3 148 42 +/- 80 200 SPW-177 Water 1/16/2019 Ra-228 0.93 -0.10 +/- 0.42 2 SPW-198 Water 1/18/2019 Sr-89 0.67 0.25 +/- 0.50 5 SPW-198 Water 1/18/2019 Sr-90 0.67 -0.16 +/- 0.29 1 SPW-249 Water 1/24/2019 Ni-63 67 31 +/- 41 200 SPW-255 Water 1/15/2019 Ra-226 0.04 0.16 +/- 0.03 2 SPW-280 Water 1/25/2019 Ra-226 0.06 -0.09 +/- 0.14 2 SPW-399 Water 1/31/2019 Ra-226 0.03 0.15 +/- 0.03 2 SPW-460 Water 2/12/2019 Ra-226 0.03 0.15 +/- 0.02 2 SPW-567 Water 2/21/2019 Ra-226 0.03 0.13 +/- 0.02 2 SPW-844 Water 3/22/2019 U-234 0.19 0.04 +/- 0.14 1 SPW-844 Water 3/22/2019 U-238 0.19 0.00 +/- 0.11 1 SPW-836 Water 3/21/2019 Ra-228 0.74 0.53 +/- 0.41 2 SPW-1060 Water 3/31/2019 Ra-226 0.04 -0.02 +/- 0.03 2 a
Liquid sample results are reported in pCi/Liter, air filters ( pCi/m 3), charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b Laboratory codes : W & SPW (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
c I-131(G); iodine-131 as analyzed by gamma spectroscopy.
d Activity reported is a net activity result.
A-9
TABLE A-4. In-House "Blank" Samples Concentrationa b c Lab Code Sample Date Analysis Laboratory results (4.66V) Acceptance Type LLD Activityd Criteria (4.66 V)
SPW-1090 Water 4/10/2019 H-3 155 -14 +/- 72 200 SPW-1092 Water 4/8/2019 Ra-228 0.82 0.75 +/- 0.46 2 SPW-1266 Water 4/16/2019 H-3 152 67 +/- 74 200 SPW-1338 Water 4/18/2019 H-3 152 66 +/- 79 200 SPW-1386 Water 4/8/2019 Ra-226 0.03 0.09 +/- 0.03 2 SPW-1426 Water 4/26/2019 H-3 156 34 +/- 75 200 SPW-1536 Water 5/6/2019 Sr-89 0.66 -0.07 +/- 0.45 5 SPW-1536 Water 5/6/2019 Sr-90 0.59 -0.10 +/- 0.26 1 SPW-1581 Water 5/9/2019 H-3 147 73 +/- 77 200 SPW-1644 Water 4/22/2019 Ra-226 0.02 0.15 +/- 0.02 2 SPW-1675 Water 5/17/2019 H-3 154 -30 +/- 71 200 SPW-1798 Water 5/20/2019 H-3 149 24 +/- 73 200 SPW-1857 Water 5/28/2019 H-3 150 54 +/- 74 200 SPW-1889 Water 5/30/2019 H-3 152 45 +/- 73 200 SPW-2013 Water 5/31/2019 Ra-226 0.01 0.13 +/- 0.02 2 SPW-2029 Water 6/12/2019 Ni-63 66 10 +/- 40 200 SPW-2092 Water 6/18/2019 H-3 154 -42 +/- 70 200 SPW-2237 Water 6/26/2019 H-3 150 -9 +/- 69 200 SPW-2107 Water 6/18/2019 I-131 0.16 0.04 +/- 0.09 1 SPW-2152 Water 6/19/2019 I-131 0.16 0.04 +/- 0.09 1 SPW-3187 Water 7/30/2019 Ra-226 0.02 0.17 +/- 0.02 2 SPW-2924 Water 8/6/2019 Sr-89 0.71 -0.06 +/- 0.57 5 SPW-2924 Water 8/6/2019 Sr-90 0.59 0.08 +/- 0.28 1 SPW-2946 Water 8/9/2019 H-3 152 33 +/- 72 200 SPW-3002 Water 8/14/2019 H-3 152 -22 +/- 74 200 SPW-3150 Water 8/26/2019 H-3 151 115 +/- 77 200 SPW-3358 Water 8/30/2019 Gr. Alpha 0.44 -0.08 +/- 0.30 2 SPW-3358 Water 8/30/2019 Gr. Beta 0.72 -0.31 +/- 0.49 4 SPW-3568 Water 8/28/2019 Ra-226 0.03 0.16 +/- 0.03 2 SPW-3348 Water 9/10/2019 H-3 150 107 +/- 76 200 SPW-3409 Water 9/13/2019 H-3 154 133 +/- 79 200 SPW-3449 Water 9/17/2019 H-3 147 102 +/- 79 200 SPW-3570 Water 9/27/2019 H-3 151 70 +/- 77 200 a
Liquid sample results are reported in pCi/Liter, air filters ( pCi/m 3), charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b Laboratory codes : W & SPW (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
c I-131(G); iodine-131 as analyzed by gamma spectroscopy.
d Activity reported is a net activity result.
A-10
TABLE A-5. In-House "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance DW-90173,90174 10/24/2018 Ra-226 1.13 +/- 0.15 1.38 +/- 0.17 1.26 +/- 0.11 Pass DW-90173,90174 10/24/2018 Ra-228 5.09 +/- 0.84 6.59 +/- 0.89 5.84 +/- 0.61 Pass SW-4782,4783 11/7/2018 H-3 192 +/- 82 238 +/- 84 215 +/- 59 Pass WW-4959,4960 11/13/2018 H-3 330 +/- 88 286 +/- 86 308 +/- 61 Pass SG-4850,4851 11/14/2018 Pb-214 15.0 +/- 0.4 14.7 +/- 0.4 14.9 +/- 0.3 Pass SG-4850,4851 11/14/2018 Ac-228 17.5 +/- 0.7 16.7 +/- 0.6 17.1 +/- 0.5 Pass VE-4917,4918 11/20/2018 K-40 4.54 +/- 0.45 4.05 +/- 0.46 4.30 +/- 0.32 Pass VE-4917,4918 11/20/2018 Be-7 9.42 +/- 0.45 9.42 +/- 0.46 9.42 +/- 0.32 Pass SO-5024,5025 11/14/2018 K-40 6.60 +/- 0.54 6.26 +/- 0.58 6.43 +/- 0.40 Pass SG-5046,5047 11/21/2018 K-40 8.65 +/- 1.18 9.12 +/- 1.02 8.88 +/- 0.78 Pass SG-5046,5047 11/21/2018 Cs-137 0.18 +/- 0.06 0.10 +/- 0.05 0.14 +/- 0.04 Pass SG-5046,5047 11/21/2018 Gr. Alpha 22.8 +/- 5.6 17.5 +/- 4.8 20.2 +/- 3.7 Pass SG-5046,5047 11/21/2018 Gr. Beta 31.8 +/- 3.5 26.8 +/- 3.1 29.3 +/- 2.4 Pass SG-6286,6287 12/1/2018 Pb-214 11.3 +/- 0.4 10.7 +/- 0.5 11.0 +/- 0.3 Pass SG-6286,6287 12/1/2018 Ac-228 13.5 +/- 0.9 13.2 +/- 1.0 13.4 +/- 0.7 Pass SWU-5132,5133 12/4/2018 H-3 159 +/- 82 204 +/- 80 181 +/- 57 Pass SWU-5132,5133 12/4/2018 Gr. Beta 1.32 +/- 0.56 1.33 +/- 0.57 1.32 +/- 0.40 Pass AP-5499,5500 1/2/2019 Fe-55 941 +/- 220 1027 +/- 226 984 +/- 158 Pass AP-5499,5500 1/2/2019 Sr-89 20.2 +/- 7.3 14.9 +/- 5.7 17.5 +/- 4.7 Pass AP-5499,5500 1/2/2019 Ni-63 12.1 +/- 8.5 15.6 +/- 8.5 13.8 +/- 6.0 Pass CF-20,21 1/2/2019 Gr. Beta 10.0 +/- 0.2 10.7 +/- 0.2 10.3 +/- 0.2 Pass CF-20,21 1/2/2019 Sr-90 0.005 +/- 0.002 0.005 +/- 0.002 0.005 +/- 0.001 Pass CF-20,21 1/2/2019 Be-7 0.27 +/- 0.09 0.29 +/- 0.08 0.28 +/- 0.06 Pass CF-20,21 1/2/2019 K-40 6.69 +/- 0.34 6.83 +/- 0.34 6.76 +/- 0.24 Pass SG-211,212 1/21/2019 Ra-226 7.94 +/- 1.15 8.50 +/- 1.11 9.79 +/- 0.19 Pass SG-211,212 1/21/2019 Ac-228 4.46 +/- 0.37 4.63 +/- 0.43 4.55 +/- 0.28 Pass WW-324,325 2/4/2019 Gr. Alpha 0.68 +/- 0.44 0.49 +/- 0.46 0.59 +/- 0.32 Pass WW-324,325 2/4/2019 Gr. Beta 1.80 +/- 0.55 2.95 +/- 0.63 2.37 +/- 0.42 Pass W-345,346 2/4/2019 H-3 245 +/- 84 277 +/- 85 261 +/- 60 Pass WW-797,798 3/5/2019 H-3 165 +/- 80 222 +/- 83 193 +/- 58 Pass WW-648,649 3/8/2019 H-3 587 +/- 101 630 +/- 102 608 +/- 72 Pass SW-713,714 3/14/2019 H-3 326 +/- 90 254 +/- 86 290 +/- 62 Pass AP-1241,1242 4/2/2019 Be-7 0.097 +/- 0.018 0.108 +/- 0.020 0.103 +/- 0.013 Pass AP-1285,1286 4/3/2019 Be-7 0.080 +/- 0.014 0.078 +/- 0.012 0.079 +/- 0.009 Pass AP-1306,1307 4/3/2019 Be-7 0.085 +/- 0.009 0.096 +/- 0.011 0.090 +/- 0.007 Pass AP-1327,1328 4/3/2019 Be-7 0.078 +/- 0.010 0.079 +/- 0.011 0.078 +/- 0.007 Pass AP-1327,1328 4/3/2019 K-40 0.012 +/- 0.007 0.021 +/- 0.010 0.017 +/- 0.006 Pass AP-2119,2120 4/3/2019 Be-7 0.276 +/- 0.098 0.265 +/- 0.116 0.270 +/- 0.076 Pass A-11
TABLE A-5. In-House "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance AP-2225,2226 4/3/2019 Be-7 0.231 +/- 0.128 0.208 +/- 0.123 0.220 +/- 0.089 Pass CF-820,821 4/3/2019 K-40 6.39 +/- 0.30 6.63 +/- 0.37 6.51 +/- 0.24 Pass WW-648,649 4/5/2019 H-3 587 +/- 101 630 +/- 102 608 +/- 72 Pass WW-1043,1044 4/5/2019 H-3 666 +/- 121 662 +/- 121 664 +/- 86 Pass SW-1087,1088 4/8/2019 H-3 9,997 +/- 300 10,330 +/- 305 10,164 +/- 214 Pass WW-1198,1199 4/9/2019 H-3 562 +/- 99 640 +/- 102 601 +/- 71 Pass LW-1503,1504 4/25/2019 Gr. Beta 1.09 +/- 0.55 1.46 +/- 0.57 1.27 +/- 0.39 Pass WW-1789,1790 5/7/2019 H-3 366 +/- 90 400 +/- 92 383 +/- 64 Pass SG-2269,2270 5/7/2019 Pb-214 39.1 +/- 0.5 40.3 +/- 0.5 39.7 +/- 0.4 Pass SG-2269,2270 5/7/2019 Ac-228 53.2 +/- 1.0 57.1 +/- 1.0 55.2 +/- 0.7 Pass DW-10049,10050 5/7/2019 Ra-226 1.31 +/- 0.13 1.66 +/- 0.15 1.49 +/- 0.10 Pass DW-10049,10050 5/7/2019 Ra-228 1.24 +/- 0.52 1.33 +/- 0.53 1.29 +/- 0.37 Pass WW-1690A,B 5/8/2019 H-3 325 +/- 89 303 +/- 93 314 +/- 64 Pass S-1812,1813 5/16/2019 K-40 21.95 +/- 0.92 23.26 +/- 0.95 22.61 +/- 0.66 Pass S-1812,1813 5/16/2019 Cs-137 0.05 +/- 0.03 0.07 +/- 0.04 0.06 +/- 0.02 Pass DW-10053,10054 5/22/2019 Gr. Alpha 0.93 +/- 0.63 1.14 +/- 0.72 1.04 +/- 0.48 Pass DW-10053,10054 5/22/2019 Gr. Beta 1.43 +/- 0.62 1.13 +/- 0.59 1.28 +/- 0.43 Pass W-2053,2054 5/29/2019 H-3 1572 +/- 135 1470 +/- 131 1521 +/- 94 Pass G-1989,1990 6/3/2019 Be-7 0.80 +/- 0.18 0.72 +/- 0.15 0.76 +/- 0.12 Pass G-1989,1990 6/3/2019 K-40 6.15 +/- 0.51 5.98 +/- 0.46 6.065 +/- 0.34 Pass G-1989,1990 6/3/2019 Gr. Beta 7.24 +/- 0.19 7.00 +/- 0.19 7.12 +/- 0.13 Pass WW-2204,2205 6/6/2019 H-3 3861 +/- 194 3722 +/- 191 3792 +/- 136 Pass S-2031,2032 6/10/2019 Pb-214 5.16 +/- 0.19 4.75 +/- 0.22 4.96 +/- 0.15 Pass S-2031,2032 6/10/2019 Ac-228 3.81 +/- 0.31 3.63 +/- 0.33 3.72 +/- 0.23 Pass S-2010,2011 6/10/2019 Pb-214 1.48 +/- 0.10 1.05 +/- 0.11 1.27 +/- 0.07 Pass F-2140,2141 6/12/2019 K-40 1.01 +/- 0.28 1.39 +/- 0.32 1.20 +/- 0.21 Pass S-2162,2163 6/12/2019 Pb-214 0.65 +/- 0.06 0.54 +/- 0.05 0.60 +/- 0.04 Pass S-2162,2163 6/12/2019 Ac-228 0.46 +/- 0.10 0.44 +/- 0.08 0.45 +/- 0.07 Pass S-2162,2163 6/12/2019 K-40 4.22 +/- 0.49 3.81 +/- 0.41 4.02 +/- 0.32 Pass S-2162,2163 6/12/2019 Tl-208 0.09 +/- 0.02 0.10 +/- 0.02 0.09 +/- 0.01 Pass S-2162,2163 6/12/2019 Pb-212 0.34 +/- 0.03 0.26 +/- 0.03 0.30 +/- 0.02 Pass SWT-2355,2356 6/25/2019 Gr. Beta 1.12 +/- 0.57 1.24 +/- 0.56 1.18 +/- 0.40 Pass AP-2689,2690 6/28/2019 Be-7 0.089 +/- 0.020 0.075 +/- 0.018 0.082 +/- 0.013 Pass AP-2710,2711 7/1/2019 Be-7 0.091 +/- 0.010 0.097 +/- 0.010 0.094 +/- 0.007 Pass AP-2731,2732 7/2/2019 Be-7 0.073 +/- 0.013 0.072 +/- 0.011 0.072 +/- 0.009 Pass DW-10062,10063 7/5/2019 Ra-226 4.10 +/- 0.30 4.03 +/- 0.30 4.07 +/- 0.21 Pass DW-10062,10063 7/5/2019 Ra-228 1.95 +/- 0.60 2.31 +/- 0.62 2.13 +/- 0.43 Pass AP-70818,70819 7/8/2019 Gr. Beta 0.021 +/- 0.004 0.023 +/- 0.004 0.022 +/- 0.003 Pass XW-2459,2460 7/10/2019 H-3 304 +/- 92 234 +/- 89 269 +/- 64 Pass VE-2516,2517 7/10/2019 Be-7 0.63 +/- 0.16 0.52 +/- 0.19 0.58 +/- 0.12 Pass A-12
TABLE A-5. In-House "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance VE-2516,2517 7/10/2019 K-40 6.50 +/- 0.47 6.81 +/- 0.54 6.66 +/- 0.36 Pass AP-71518A,B 7/15/2019 Gr. Beta 0.022 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.003 Pass VE-2668,2669 7/16/2019 K-40 3.84 +/- 0.27 3.74 +/- 0.26 3.79 +/- 0.19 Pass DW-10076,10077 7/16/2019 Gr. Alpha 3.01 +/- 0.92 4.13 +/- 0.91 3.57 +/- 0.65 Pass DW-10073,10074 7/16/2019 Ra-226 1.57 +/- 0.18 1.51 +/- 0.21 1.54 +/- 0.14 Pass DW-10073,10074 7/16/2019 Ra-228 1.29 +/- 0.56 1.48 +/- 0.57 1.385 +/- 0.40 Pass AP-72218A,B 7/22/2019 Gr. Beta 0.013 +/- 0.004 0.016 +/- 0.004 0.015 +/- 0.003 Pass G-2752,2753 7/23/2019 K-40 4.53 +/- 0.42 4.47 +/- 0.46 4.50 +/- 0.31 Pass G-2752,2753 7/23/2019 Be-7 1.98 +/- 0.29 1.96 +/- 0.29 1.97 +/- 0.20 Pass AP-2800,2801 7/25/2019 Be-7 0.208 +/- 0.090 0.321 +/- 0.147 0.264 +/- 0.086 Pass AP-72918A,B 7/29/2019 Gr. Beta 0.026 +/- 0.005 0.025 +/- 0.005 0.025 +/- 0.003 Pass VE-2840,2841 7/31/2019 K-40 3.94 +/- 0.38 3.99 +/- 0.47 3.96 +/- 0.30 Pass AP-2903,2904 8/1/2019 Be-7 0.198 +/- 0.102 0.228 +/- 0.102 0.213 +/- 0.072 Pass P-2882,2983 8/1/2019 H-3 265 +/- 85 327 +/- 88 296 +/- 61 Pass SG-2926,2927 8/5/2019 Pb-214 9.07 +/- 0.39 8.82 +/- 0.39 8.95 +/- 0.28 Pass SG-2926,2927 8/5/2019 Ac-228 9.00 +/- 0.76 8.58 +/- 0.72 8.79 +/- 0.52 Pass AV-2993,2994 8/9/2019 Gr. Beta 1.22 +/- 0.19 1.28 +/- 0.21 1.25 +/- 0.14 Pass AV-2993,2994 8/9/2019 K-40 3.12 +/- 0.36 3.14 +/- 0.35 3.13 +/- 0.25 Pass DW-10088,10089 8/9/2019 Ra-228 0.60 +/- 0.50 1.20 +/- 0.50 0.90 +/- 0.35 Pass DW-10088,10089 8/9/2019 Ra-226 1.40 +/- 0.20 0.94 +/- 0.20 1.17 +/- 0.14 Pass VE-3016,3017 8/12/2019 Be-7 0.39 +/- 0.12 0.47 0.28 0.43 0.15 Pass VE-3016,3017 8/12/2019 K-40 6.13 +/- 0.41 6.24 0.64 6.18 0.38 Pass G-3600,3601 8/12/2019 Be-7 4.42 +/- 0.33 4.35 0.27 4.39 0.21 Pass WW-3100,3101 8/14/2019 H-3 480 +/- 96 401 +/- 92 441 +/- 66 Pass MI-3211,3212 8/27/2019 K-40 1862 +/- 131 1923 +/- 136 1893 +/- 94 Pass MI-3211,3212 8/27/2019 Sr-90 0.90 +/- 0.33 0.56 +/- 0.29 0.73 +/- 0.22 Pass LW-3512,3513 8/30/2019 Gr. Beta 0.79 +/- 0.50 1.39 +/- 0.58 1.09 +/- 0.38 Pass F-3379,3380 9/3/2019 K-40 2.98 +/- 0.40 3.04 +/- 0.37 3.01 +/- 0.27 Pass P-3278,3279 9/3/2019 H-3 1110 +/- 123 1076 +/- 121 1093 +/- 86 Pass VE-3309,3310 9/4/2019 K-40 2.23 +/- 0.26 1.72 +/- 0.25 1.98 +/- 0.18 Pass DW-10100,10101 9/5/2019 Ra-226 0.50 +/- 0.11 0.57 0.12 0.54 +/- 0.08 Pass DW-10100,10101 9/5/2019 Ra-228 3.38 +/- 0.82 2.54 1.03 2.96 +/- 0.66 Pass VE-3400,3401 9/10/2019 Be-7 1.68 +/- 0.22 1.45 +/- 0.41 1.57 +/- 0.24 Pass VE-3400,3401 9/12/2019 K-40 4.63 +/- 0.42 5.09 +/- 0.41 4.86 +/- 0.30 Pass VE-3488,3489 9/17/2019 K-40 22.9 +/- 0.8 24.1 +/- 1.4 23.5 +/- 0.8 Pass VE-3488,3489 9/17/2019 Be-7 4.33 +/- 0.35 4.09 +/- 0.50 4.21 +/- 0.31 Pass WW-3467,3468 9/18/2019 H-3 211 +/- 85 209 +/- 85 210 +/- 60 Pass WW-3730,3731 9/18/2019 H-3 229 +/- 83 256 +/- 85 242 +/- 59 Pass AP-3533,3534 9/19/2019 Be-7 0.217 +/- 0.093 0.261 +/- 0.112 0.239 +/- 0.073 Pass WW-3554,3555 9/23/2019 Gr. Beta 1.62 +/- 1.10 1.93 +/- 1.07 1.77 +/- 0.77 Pass A-13
TABLE A-5. In-House "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance DW-10111,10112 9/23/2019 Gr. Alpha 1.72 +/- 0.73 1.41 +/- 0.68 1.57 +/- 0.50 Pass DW-10115,10116 9/25/2019 Ra-228 3.65 +/- 0.80 2.76 +/- 0.68 3.21 +/- 0.52 Pass DW-10115,10116 9/25/2019 Ra-226 2.99 +/- 0.23 2.74 +/- 0.25 2.87 +/- 0.17 Pass G-3600,3601 9/26/2019 K-40 5.19 +/- 0.46 5.48 +/- 0.41 5.33 +/- 0.31 Pass AP-3921,3922 10/1/2019 Be-7 0.074 +/- 0.011 0.070 +/- 0.012 0.072 +/- 0.008 Pass AP-3986,3987 10/2/2019 Be-7 0.060 +/- 0.009 0.066 +/- 0.011 0.063 +/- 0.007 Pass WW-3793,3794 10/8/2019 Gr. Beta 3.75 +/- 1.18 4.34 1.20 4.05 +/- 0.84 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil and sediment (pCi/g).
b Laboratory codes: AP (Air Particulate), AV (Aquatic Vegetation), BS (Bottom Sediment), CF (Cattle Feed),
CH (Charcoal Canister), DW (Drinking Water), E (Egg), F (Fish), G (Grass), LW (Lake Water), P (Precipitation),
PM (Powdered Milk), S, (Solid), SG (Sludge), SO (Soil), SS (Shoreline Sediment), SW (Surface Water),
SWT (Surface Water Treated), SWU (Surface Water Untreated), VE (Vegetation), W Water (Water), WW (Well Water).
A-14
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentrationa Reference Known Control b c Lab Code Date Analysis Laboratory result Activity Limits Acceptance MASO-3638 8/1/2018 Cs-134 688.7 +/- 26.2 781 547 - 1015 Pass MASO-3638 8/1/2018 Cs-137 605.9 +/- 22.7 572 400 - 744 Pass MASO-3638 8/1/2018 Co-57 976.7 +/- 37.6 958 671 - 1245 Pass MASO-3638 8/1/2018 Co-60 604.5 +/- 24.9 608 426 - 790 Pass MASO-3638 8/1/2018 Mn-54 5.2 +/- 5.2 0 NA c Pass MASO-3638 8/1/2018 K-40 630 +/- 31 566 396 - 736 Pass MASO-3638 8/1/2018 Zn-65 556.4 +/- 26.8 500 350 - 650 Pass MAAP-3636 8/1/2018 Cs-134 0.37 +/- 0.04 0.444 0.311 - 0.577 Pass MAAP-3636 8/1/2018 Cs-137 0.34 +/- 0.05 0.345 0.242 - 0.449 Pass MAAP-3636 8/1/2018 Co-57 0.56 +/- 0.04 0.592 0.414 - 0.770 Pass MAAP-3636 8/1/2018 Co-60 0.28 +/- 0.03 0.294 0.206 - 0.382 Pass MAAP-3636 8/1/2018 Mn-54 0.26 +/- 0.05 0.266 0.186 - 0.346 Pass MAAP-3636 8/1/2018 Zn-65 0.22 +/- 0.07 0.201 NA d Pass MAVE-3640 8/1/2018 Cs-134 1.87 +/- 0.10 1.94 1.36 - 2.52 Pass MAVE-3640 8/1/2018 Cs-137 2.69 +/- 0.15 2.36 1.65 - 3.07 Pass MAVE-3640 8/1/2018 Co-57 3.90 +/- 0.12 3.31 2.32 - 4.30 Pass MAVE-3640 8/1/2018 Co-60 1.76 +/- 0.09 1.68 1.18 - 2.18 Pass MAVE-3640 8/1/2018 Mn-54 2.91 +/- 0.16 2.53 1.77 - 3.29 Pass MAVE-3640 8/1/2018 Zn-65 1.53 +/- 0.21 1.37 0.96 - 1.78 Pass MAW-3480 8/1/2018 H-3 336.0 +/- 10.7 338 237 - 439 Pass MAW-3480 8/1/2018 Cs-134 7.86 +/- 0.31 8.7 6.1 - 11.3 Pass MAW-3480 8/1/2018 Cs-137 7.55 +/- 0.33 6.9 4.8 - 9.0 Pass MAW-3480 8/1/2018 Co-57 15.67 +/- 0.36 14.9 10.4 - 19.4 Pass MAW-3480 8/1/2018 Co-60 0.12 +/- 0.12 0 NA c Pass MAW-3480 8/1/2018 Mn-54 13.38 +/- 0.44 12.5 8.8 - 16.3 Pass MAW-3480 8/1/2018 Zn-65 7.80 +/- 0.53 7.53 5.27 - 9.79 Pass MAW-3634 8/1/2018 I-129 1.32 +/- 0.08 1.62 1.13 - 2.11 Pass MAAP-609 2/1/2019 Gross Alpha 0.16 +/- 0.03 0.528 0.158 - 0.898 Pass MAAP-609 2/1/2019 Gross Beta 1.09 +/- 0.07 0.948 0.474 - 1.422 Pass MAW-550 2/1/2019 Gross Alpha 0.73 +/- 0.06 0.84 0.25 - 1.43 Pass MAW-550 2/1/2019 Gross Beta 2.26 +/- 0.06 2.33 1.17 - 3.50 Pass MASO-605 2/1/2019 Am-241 38.89 +/- 5.92 49.9 34.9 +/- 64.9 Pass MASO-605 2/1/2019 Cs-134 0.45 +/- 2.52 0.0 NA c Pass MASO-605 2/1/2019 Cs-137 1273.1 +/- 13.0 1164 815 - 1513 Pass MASO-605 2/1/2019 Co-57 0.46 +/- 1.1 0.0 NA c Pass MASO-605 2/1/2019 Co-60 857.96 +/- 8.52 855.0 599 - 1112 Pass MASO-605 2/1/2019 Mn-54 1,138.0 +/- 13.5 1027 719 - 1335 Pass MASO-605 2/1/2019 Zn-65 730.92 +/- 16.48 668 468 - 868 Pass MASO-605 2/1/2019 K-40 676 +/- 47 585 410 - 761 Pass MASO-605 2/1/2019 Sr-90 0.0007 +/- 0.0007 0.000 NA c Pass A-15
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentrationa Reference Known Control b c Lab Code Date Analysis Laboratory result Activity Limits Acceptance MASO-605 2/1/2019 Pu-238 78.15 +/- 6.11 71.0 49.7 - 92.3 Pass MASO-605 2/1/2019 Pu-239/240 65.00 +/- 5.4 59.8 41.9 - 77.7 Pass MASO-605 2/1/2019 U-234 65 +/- 13 56 39 - 73 Pass MASO-605 2/1/2019 U-238 237 +/- 23 205 144 - 267 Pass MAW-613 2/1/2019 Am-241 0.46 +/- 0.03 0.582 0.407 - 0.757 Pass MAW-613 2/1/2019 Cs-134 5.49 +/- 0.18 5.99 4.19 - 7.79 Pass MAW-613 2/1/2019 Cs-137 0.089 +/- 0.080 0 NA c Pass MAW-613 2/1/2019 Co-57 10.87 +/- 0.24 10.00 7.0 - 13.0 Pass MAW-613 2/1/2019 Co-60 6.78 +/- 0.19 6.7 4.7 - 8.7 Pass MAW-613 2/1/2019 Mn-54 8.98 +/- 0.17 8.4 5.9 - 10.9 Pass MAW-613 2/1/2019 Zn-65 0.096 +/- 0.141 0 NA c Pass MAW-613 2/1/2019 Fe-55 0.004 +/- 4.00 0 NA c Pass MAW-613 2/1/2019 Ni-63 5.54 +/- 1.52 5.8 4.1 - 7.5 Pass MAW-613 2/1/2019 Sr-90 6.02 +/- 0.53 6.35 4.45 +/- 8.26 Pass MAW-613 2/1/2019 Pu-238 0.315 +/- 0.088 0.451 0.316 - 0.586 Faile MAW-613 2/1/2019 Pu-239/240 0.07 +/- 0.07 0.005 NA d Pass MAW-613 2/1/2019 U-234 0.96 +/- 0.07 0.800 0.56 +/- 1.04 Pass MAW-613 2/1/2019 U-238 0.94 +/- 0.07 0.810 0.57 +/- 1.05 Pass MAAP-611 2/1/2019 Cs-134 0.185 +/- 0.025 0.216 0.151 - 0.281 Pass MAAP-611 2/1/2019 Cs-137 0.288 +/- 0.045 0.290 0.203 - 0.377 Pass MAAP-611 2/1/2019 Co-57 0.369 +/- 0.033 0.411 0.288 - 0.534 Pass MAAP-611 2/1/2019 Co-60 0.333 +/- 0.045 0.340 0.238 - 0.442 Pass MAAP-611 2/1/2019 Mn-54 0.546 +/- 0.058 0.547 0.383 - 0.711 Pass MAAP-611 2/1/2019 Zn-65 0.025 +/- 0.0348 0 NA c Pass MAAP-611 2/1/2019 Sr-90 1.34 +/- 0.13 0.662 0.463 - 0.861 Failf MAAP-611 2/1/2019 U-234/233 4.14 +/- 0.97 0.106 0.074 - 0.138 Failf MAAP-611 2/1/2019 U-238 3.89 +/- 0.94 0.110 0.077 - 0.143 Failf MAVE-607 2/1/2019 Cs-134 2.33 +/- 0.10 2.44 1.71 - 3.17 Pass MAVE-607 2/1/2019 Cs-137 2.62 +/- 0.13 2.30 1.61 - 2.99 Pass MAVE-607 2/1/2019 Co-57 2.39 +/- 0.11 2.07 1.45 - 2.69 Pass MAVE-607 2/1/2019 Co-60 0.046 +/- 0.04 0 NA c Pass MAVE-607 2/1/2019 Mn-54 0.031 +/- 0.04 0 NA c Pass MAVE-607 2/1/2019 Sr-90 0.013 +/- 0.022 0 NA c Pass MAW-601 2/1/2019 I-129 0.56 +/- 0.08 0.616 0.431 - 0.801 Pass a
Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil) and MAVE (vegetation).
c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
d Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.
e An investigation is in progress to determine the reason for the failure of the Pu-239 study.
f An erroneous volume conversion caused some incorrect values to be submitted. If the conversion had been performed properly the results in Bq/sample would have been (Sr-90: 0.671 +/- 0.066 ) and (U-234: 0.153 +/- 0.036) and (U-238: 0.144 +/- 0.035).
This result had been included in the Uranium investigation. See footnote "C" on Table A-1.
A-16
TABLE A-7. Interlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) a.
MRAD-30 Study Concentration a Lab Code b Date Analysis Laboratory ERA Control Result Value c Limits d Acceptance ERAP-846 3/18/2019 Am-241 19.1 18.7 13.3 - 24.9 Pass ERAP-846 3/18/2019 Cs-134 612 721 468 - 884 Pass ERAP-846 3/18/2019 Cs-137 679 634 521 - 832 Pass ERAP-846 3/18/2019 Co-60 93.7 93.8 79.7 - 119 Pass ERAP-846 3/18/2019 Fe-55 612 718 262 - 1150 Pass ERAP-846 3/18/2019 Mn-54 < 0.5 < 50.0 0.00 - 50.0 Pass ERAP-846 3/18/2019 Zn-65 1500 1380 1130 - 2110 Pass ERAP-846 3/18/2019 Pu-238 34.0 33.8 25.5 - 41.5 Pass ERAP-846 3/18/2019 Pu-239 64.9 67.0 50.1 - 80.8 Pass ERAP-846 3/18/2019 Sr-90 199 181 114 - 246 Pass ERAP-846 3/18/2019 U-234e 29.0 18.2 13.5 - 21.3 Fail ERAP-846 3/18/2019 U-238e 28.6 18.1 13.7 - 21.6 Fail ERAP-848 3/18/2019 Gross Alpha 48.4 50.3 26.3 - 82.9 Pass ERAP-848 3/18/2019 Gross Beta 95.5 78.6 47.7 - 119 Pass a
Results obtained by Environmental, Inc., Midwest Laboratory (EIML) as a participant in the crosscheck program for proficiency testing administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory code ERAP (air filter). Results are reported in units of (pCi/Filter).
c The ERA Assigned values for the air filter standards are equal to 100% of the parameter present in the standard as determined by the gravimetric and/or volumetric measurements made during standard preparation as applicable. The acceptance limits are established per the guidelines contained in the Department of Energy (DOE) d The acceptance limits are established per the guidelines contained in the Department of Energy (DOE) report EML-56 Analysis of Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP)Data Determination of Operational Criteria and Control Limits for Performance Evaluation Purposes or ERA's SOP for the generation of Performance Acceptance Limits.
e Failure due to an over-estimated U-232 tracer value. Tracer has been re-standardized. (See footnote "c" on Table A-1.
A-17
APPENDIX B DATA REPORTING CONVENTIONS
Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows: x+/-s where: x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x1 +/- s1 and x2 +/- s2 2 2 Reported result: x +/- s; where x = (1/2) (x1 + x2) and s = (1/2) s1 + s2 3.2. Individual results: <L1 , <L2 Reported result: <L, where L = lower of L1 and L2 3.3. Individual results: x +/- s, <L Reported result: x +/- s if x L; <L otherwise.
4.0. Computation of Averages and Standard Deviations B-2
4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2 . . . xn are defined as follows:
1 (x- x )2 x =n x s= n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.445 is rounded off to 11.45.
4.6 Composite samples which overlap the next month or year are reported for the month or year in which most of the sample is collected.
B-3
APPENDIX C SAMPLE LOCATION MAPS C-1
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Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate Onsite Station, 1 110-meter weather tower 0.53 293°/WNW P X Onsite Station, adjacent 2C,E to old plant access road 0.59 207°/SSW K X X Offsite Station, Intersection of Hwy. 75 3 and farm access road 0.94 145°/SE G X 4 Blair OPPD office 2.86 305°/NW Q X X 5A Fort Calhoun, NE City 6 Hall 5.18 150°/SSE H X Fence around intake gate, Desoto Wildlife 7 Refuge 2.07 102°/ESE F X C-3
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate Onsite Station, entrance to Plant Site from Hwy.
8 75 0.55 191°/S J X Onsite Station, NW of 9 Plant 0.68 305°/NW Q X Onsite Station, WSW of 10 Plant 0.61 242°/WSW M X Offsite Station, SE of 11 Plant 1.07 39°/SE G X Metropolitan Utilities Dist., Florence Treatment Plant 12 North Omaha, NE 14.3 154°/SSE H X West bank Missouri River, downstream from 13 Plant discharge 0.45 108°/ESE F X X C-4
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate Upstream from Intake 14D Bldg, west bank of river 0.09 4°/N A X X 15 Smith Farm 1.99 134°/SE G X 16A 17A 18A 19A 20B,D,F Mohr Dairy 9.86 186°/S J X X X 21A Fish Sampling Area, 0.08 Missouri River 22 (R.M. 645.0) 6°/N A X Fish Sampling Area, 17.9 Missouri River 23D (R.M. 666.0) 358°/N A X C-5
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate 24A 25A 26A 27A 28A 29A 30A 31A 32D Valley Substation #902 19.6 221°/SW L X X 33A 34A 35 Onsite Farm Field 0.52 118°/ESE F X C-6
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate Offsite Station Intersection Hwy 75/Co.
36 Rd. P37 0.75 227°/SW L X Offsite Station Desoto 37 Township 1.57 144°/SE G X X 38A 39A 40A 41B,C Dowler Acreage 0.73 175°/S J X X 42 Sector A-1 1.94 0°/NORTH A X 43 Sector B-1 1.97 16°/NNE B X 44 Sector C-1 1.56 41°/NE C X 45 Sector D-1 1.34 71°/ENE D X 46 Sector E-1 1.54 90°/EAST E X C-7
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate 47 Sector F-1 0.45 108°/ESE F X 48 Sector G-1 1.99 134°/SE G X 49 Sector H-1 1.04 159°/SSE H X 50 Sector J-1 0.71 179°/SOUTH J X 51 Sector K-1 0.61 205°/SSW K X 52 Sector L-1 0.74 229°/SW L X 53 Sector M-1 0.93 248°/WSW M X 54 Sector N-1 1.31 266°/WEST N X 55 Sector P-1 0.60 291°/WNW P X 56 Sector Q-1 0.67 307°/NW Q X 57 Sector R-1 2.32 328°/NNW R X 58 Sector A-2 4.54 350°/NORTH A X C-8
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate 59 Sector B-2 2.95 26°/NNE B X 60 Sector C-2 3.32 50°/NE C X 61 Sector D-2 3.11 75°/ENE D X 62 Sector E-2 2.51 90°/EAST E X 63 Sector F-2 2.91 110°/ESE F X 64 Sector G-2 3.00 140°/SE G X 65 Sector H-2 2.58 154°/SSE H X 66 Sector J-2 3.53 181°/SOUTH J X 67 Sector K-2 2.52 205°/SSW K X 68 Sector L-2 2.77 214°/SW L X 69 Sector M-2 2.86 243°/WSW M X C-9
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate 70 Sector N-2 2.54 263°/WEST N X 71 Sector P-2 2.99 299°/WNW P X 72 Sector Q-2 3.37 311°/NW Q X 73 Sector R-2 3.81 328°/NNW R X 74 D. Miller Farm 0.65 203°/SSW K X 75B,C Lomp Acreage 0.65 163°/SSE H X X X X 76A 77G River N-1 0.17 328°/NNW R X 78G River S-1 0.14 85°/EAST E X 79G Lagoon S-1 0.24 131°/SE G X 80G Parking S-1 0.27 158°/SSE H X 81G Training W-1 0.28 194°/SSW K X C-10
Radiological Environmental Sampling Locations and Media Table 5.2 - Radiological Environmental Sampling Locations And Media Approximate Air Approximate Distance Monitoring Sample Direction Vegetables Approximate Collection from Center Station (degrees Sector TLD Water Milk Sedi-ment Fish and Food Ground-water Sites of No. from true Products Containment Airborne north)
(miles) Particulate 82G Switchyard S-1 0.21 219°/SW L X 83G Switchyard SE-1 0.14 231°/SW L X 84G Switchyard NE-1 0.18 256°/WSW M X 85G Switchyard W-1 0.29 233°/WEST L X 86G Switchyard N-1 0.24 262°/WEST N X 87G Range S-1 0.20 286°/WNW P X 88G Mausoleum E-1 0.37 216°/SW L X 89 C, Miller 3.30 210°/SSW K X C-11
Radiological Environmental Sampling Locations and Media NOTES:
A. Location is either not in use or currently discontinued and is documented in the table for reference only.
B. If milk samples are temporarily not available at a sampling site due to mitigating circumstances, then vegetation (broadleaf, pasture grass, etc.) shall be collected as an alternate sample at the site. If there are no milk producers within the entire 5-mile radius of the facility, then vegetation shall be collected monthly, when available, at two offsite locations having the highest calculated annual average ground level D/Q and a background locale. (Reference Off-Site Dose Calculation Manual, Part II, Table 4 "Highest Potential Exposure Pathways for Estimating Dose")
C. Locations represent highest potential exposure pathways as determined by the biennial Land Use Survey, performed in accordance with Part I, Section 7.3.2, of the Off-Site Dose Calculation Manual and are monitored as such.
D. Background location (control). All other locations are indicators.
E. Location for monitoring Sector K High Exposure Pathway Resident Receptor for inhalation.
F. When broad leaf (pasture grasses) are being collected in lieu of milk, background broad leaf samples will be collected at a background locale.
G. Location for special interest monitoring general dose to the public per 40CFR190 (Figure 2)
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