ML11160A215
| ML11160A215 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 02/07/2011 |
| From: | Pacific Gas & Electric Co |
| To: | NRC/FSME |
| References | |
| HBL-11-006 | |
| Download: ML11160A215 (2) | |
Text
Enclosure 1 PG&E Letter HBL-1 1-006 INTRUDER DOSE CALCULATION SPREADSHEET (1 PAGE)
Construction Scenario Dose to Inadvertent Intruder ATTACHMENT 4 USEI Inadvertant Intruder Dose Calculation Worksheet Customer: PG&E Humboldt Bay Power Plant Project: Alternate Disposal Request #2 - Unit 3 Date:
2/7/2011 Dose Calculation per NUREG-0782 G-57 Isotope PCDF Half Life Cw f
f f
% of year for Dose (Sv/Bq)
(years)
(Ci/M 3)
_Exposure (mrem/year)
Cs-137 8.63E-09 30.1 1.32E-05 0.501 1
1 2.84E-10 5.70%
3.42E-15 Co-60 5.91E-08 5.3 4.40E-06 0.019 1
1 2.84E-10 5.70%
3.02E-16 Sr-90 3.51E-07 28.9 8.80E-07 0.487 1
1 2.84E-10, 5.70%
9.01E-15 H-3 1.73E-11 12.3 8.80E-05 0.185 1
1 2.84E-10 5.70%
1.69E-17 C-14 6.36E-12 5730.0 8.80E-07 0.996 1
1 2.84E-10 5.70%
3.34E-19 Air Fe-55 7.26E-10 2.7 8.80E-07 0.000 1
1 2.84E-10 5.70%
1.73E-20 Ni-63 1.70E-09 100.1 8.80E-06 0.812 1
1 2.84E-10 5.70%
7.28E-16 Eu-152 5.97E-08 13.5 8.80E-07 0.215 1
1 2.84E-10 5.70%
6.76E-16 Eu-154 7.73E-08 8.6 8.80E-07 0.089 1
1 2.84E-10 5.70%
3.62E-16 Aa-108m 7.66E-08 418.0 8.80E-08 0.951 1
1 2.84E-10 5.70%
3.84E-16 Cs-137 4.02E-21 30.1 1.32E-05 0.501 1
1 0.057 1.77E-04 Co-60 8.68E-17 5.3 4.40E-06 0.019 1
1 0.057 4.93E-02 Sr-90 3.77E-21 28.9 8.80E-07 0.487 1
1 0.057 1.08E-05 H-3 0
12.3 8.80E-05 0.185 1
1 0.057 0.OOE+00 Direct C-14 7.20E-23 5730.0 8.80E-07 0.996 1
1 0.057 N/A 4.20E-07 Gamma Fe-55 0
2.7 8.80E-07 0.000 1
1 0.057 0.OOE+00 Ni-63 0
100.1 8.80E-06 0.812 1
1 0.057 0.OOE+00 Eu-152 3.75E-17 13.5 8.80E-07 0.215 1
1 1 0.057 4.72E-02 Eu-154 4.11E-17 8.6 8.80E-07 0.089 1
1 0.057 2.14E-02 Ag-108m 5.16E-17 418.0 8.80E-08 0.951 1
1 0.057 2.88E-02 Tota 1.47E-01 The total dose to the inadvertent intruder is estimated using the following equation:
H =
(fOfdfwfs),
C, PDCF3 + I (fOfdfWfS)Di eG.
a Cw PDCF5 n
n Explanation of calculation and terms:
Radionuclide Specific Pathway Dose Conversion Factor for Inhalation PDCF 3 Source: FGR 11, Table 2.1 - "Inhalation Doses (Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Inhalation). Slowest transport class used.
Radionuclide Specific,Pathway Dose Conversion Factor for direct Gamma Exposure PDCF5 Source: FGR 12, Table 111.7 - "External Exposure to Radionuclides in Air, Water and Soil". Doses for submersion and from a plane source of infinite depth were summed to obtain the total direct gamma dose.
Cw Radionuclide Concentration in Waste Activity fraction remaining after decay f"
4
-l]ere t is the the time period between the end of activ6 disposal and the initiation of the scenario; the site closure plan fjVSEI ensures maintenance for 30 years after closure.
Dilution factor due to particular disposal practices fd 0.5 for random, 0.75 for stacked, or 0.5 for decontainerized. Fd set to 1 for this evaluation as USEI is not taking credit for dilution of these wastes as part of the Intruder scenario.
f, Waste form and Package Factor - No credit is taken for waste form or solidification Site Selection Factor T. x JxposureFitor T7 =2.53x10-'0 x(tO/v)x(s/30)x(501PE) =2.81xlO-'0 fs where:
v = 4.47 m/s (average annual wind speed at Boise, ID Airport) s = 50% (default silt content of soil)
PE = 91 (default precipitation-evaporation index)