ML20059D921
| ML20059D921 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/30/1990 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20059D926 | List: |
| References | |
| NUDOCS 9009070230 | |
| Download: ML20059D921 (21) | |
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' ENCLOSURE 1~
3 SEQUOYAH NUCLEAR PLANT'.
EFFLUENT AND WASTE DIFPOSAL SEMIANNUAL REPORT-SUPPLEMENTAL INFORMATION January.1=to' June:30, 1990 (852 900822 853) l:
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION ist HALF 1990 1.
Regulatory Limits a.
Fission and Activation Gases Instantaneous - Radionuclide Dependant (all release points)
Administrative release rate limits per radionuclide have been established and are based upon the methodology in Section 1.2.3 of the Sequoyah Offsite Dose Calculation Manual for each vent based on design flowrate. Technical Specification will not be exceeded until the sum of individual radionuclide release rate to Technical Specification limit ratios exceed 1.0.
- b. and c. I-131. I-133, tritium, and particulates with half-lives 18 Dayst Instantaneous - Radionuclide Dependant Total plant release rate limits per radionuclide have been established and are based upon the methodology in Section 1.2.4 of the Sequoyah Offsite. Dose Calculation Manual.
d.
Liquid effluent:
IMPC51.0 (reference 10CFR20, Appendix B, note 30, Table II, column 2).
1-
EFFLUENT AND UASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION ist HALF 3990 2.
Maximum Permissible Concentrations a,
Fission and Activation Gases Not Applicable b.
Iodines: Noc Applicable c.
Particulates, half-lives E8 days Not Applicable d.
Liquid effluents:
sum of individual MPC ratios 51.0 (ref. 10CFR20 Appendix B. Note 1)
~
3.
Average Energy - Not Applicable 4.
Measurements and Approximations of. Total Radioactivity i
ei NOTE:
Every effort is made to ensure.that all effluents from Sequoyah are conducted such that all Technical Specification Lower Limits of Detection (LLDc) are mot. Whenever an analysis does not identify a radioisotope, a "0.00E-01 Ci" is recorded for the release.
This does not necessarily mean that no activity was released for that particular radionuclide, but that the concentration was below the Technical r
Specifications and analysis LLDs.
Refer to Tables A and B for
]l estimates of these typical LLD values.
a.
Fission and Activation Gases Airborne effluent gaseous activity is continuously monitored and recorded.
Additional grab samples from the shield building, auxiliary building, service building, and condenser vacuum exhausts are taken and analyzed at least monthly to determine the quantity of noble gas activity released for the month based on the average vent flowrates recorded for the sample period. Also, noble gas samples are collected and evaluated for the shield and auxiliary buildings following startup, shutdown, or rated thermal power change exceeding 15 percent within one hour (sampling only required if dose equivalent I-131 concentration in the primary coolant has increased more than a factor of 3 and the noble gas activity monitor shows that the containment activity has increased more than a factor of 3).
The vent flowrates for the shield building, auxiliary building, service building, and condenser vacuum exhausts are determined and recorded once a shift.
s
<v EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HALF 1990 s
4.
Measurements and Approximation of Total Radioactivity (continued) a.
Fission and Activation Gases (continued)
The quantity of noble gases released through the shield and auxiliary building exhausts due to purging or venting of containment and releases of waste gas decay tanks are also determined.
The total noble gas activity released for the month is then determined by summing all of the activity released from each vent for all sampling periods, the activity released from purging or venting of containment, and the activity released from waste gas decay tank (s).
- b. and c. Iodines and Particulates Iodine and particulate activity is continuously monitored and recorded.
Charcoal and particulate samples are taken from the shield and auxiliary building exhausts and analyzed at least weekly to determine the total activity released from the plant based on the average vent flowrates recorded for the sample period.
I Also, particulate and charcoal samples are taken from the auxiliary and shield building exhausts once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 2 days following startup, shutdown, or a rated thermal power change exceeding 15 percent within one hour. The quantity of lodine and particulate released from each vent during each sampling period is then determined i
using the average vent flowrates recorded for the sampling period and activity concentration.
The vent flowrates f rom the shield and auxiliary building exhausts are recorded once a shift.
The total particulate and iodine activity released for the month is then determined by summing all of the activity released from the shield and auxiliary building exhausts for all sampling periods.
d.
Liquid Effluents (1)
Batch (Radwaste and condensate regenerants to cooling tower blowdown)
Total gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release. The total activity of a released batch is determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during a month is then determined by summing the activity content of each batch discharged during the month.
r EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION let HALF 1990 4.
Measurements and Approximation of Total Radioactivity (continued)
(2)
Continuous Releases and Porlodic Continuous Releases (Condensate regenerants, turbine building sump and steam generater blowdown)
Total gamma isotopic activity concentration as determined daily on a composite sample from the condensate system and turbine building sump and weekly for steam generator blowdown.
The total activity of the continuous release is determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during the month is then determined by summing the activity content of each daily and weekly composite for the month.
5.
Batch Value Units Quarter qparter 1st 2nd a.
Liquid 1.
Number of batches released (Radwaste only) 130 131 Each 2.
Total time period for batch releases 18,413 18.050 Minutes 3.
Maximum time period for a batch release 210 200 Minutes 4.
Average time period for batch releases 142 138 Minutes 5.
Minimum monthly average stream flow during periods of effluent into a flowing stream 61,974 15.363 Cubic Feet Per Per Second b.
Caseous 1.
Number of batches released 214 159 Each 2.
Total time period for batch releases 39,140 20,461 Minutes 3.
Maximum time period for a batch release 3,329 757 Minutes 4.
Average time period for batch releases 183 129 Minutes 5.
Minimum time period for a batch release 29 15 Minutes
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT-StiPPLEMENTAL INFORMATION 1st HALF 1990 6.
Abnormal Releases Value Units Quarter Quarter 1st 2nd a.
Liquid (1)
Number of Releases 0
0 (2)
Total Activity Released 0.00E-01 0.00E-01 C1' b.
Gaseous (1)
Number of Releases 0-0' (2)
Total Activity Released 0.00E-01 0.00E-01
. Ci
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l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1990 LfQUID EFFLUENTS - SUMMATION OF ALL RELEASES ist 2nd A.
Fission and Activation Unit
_0tr
% Error Otr
% Error Products 1.
Total Released Curies 1.91E-01 1 8E+01 3.77E-01 1
1 1 8E+01 2.
Average Diluted Conc.
During Period of All Identified Isotopes pCi/mi 1.16E-07 3.24E-07 3.
Percent of Applicable Limit (IMPC51) 4.08E-02 4.57E-01 NOTE:
Percent of applicable limit is based on identified isotope concentration after dilution, related to their appropriate MPC concentration and sum of all the isotope fractions compared to 1.0.
B.
Tritium 1.
Total Released curies 2.75E+02 1.8E+01 2.36E+02 1 8E+01 1
2.
Average Diluted pCi/ml 1.66E-04 2.03E-04 Conc. During Period
)
3.
Percent of Applicable Limit (3.0E-03 pCi/ml) 5.55E+00 6.77E+00 C.
Dissolved and Entrained cases 1.
Total Released Curies 5.08E-01 13.9E+01 1.06E-01 1 9E+01 l
3 2.
Average Diluted pCi/mi 3.07E-07 9.13E-08 Cone. During Period 3.
Percent of Applicable l
Limit (2.0E-04 pCi/ml) 1.54E-01 4.56E-02 D.
Cross Alpha Radioactivity 1.
Total Released Curies 2.75E-04 2.0E+01 1.26E-04 2.0E+01 E.
Volume of Waste Released (Before Dilution)
Liters 3.07E+07 4
1 0E+00 2.35E+07 4
1 0E+00 F.
Volume of Dilution Liters 1.62E+09 1
1 1E+01 1.14E+09 1
1 1E+01 Water for Period EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REP 0kT ist-HALF 1990 LIQUID EFtLUENTS - TOTAL PLANT DISCHARGE 0.
Isotope Summary (Note Refer to Table A for values reported as 0.00E-01)
Required by Technical Specification /Others Fission and Activation Products Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter 1st 2nd let
__pnd 1.
Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.
Strontium-90 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3.
Iron-55 Ci 0.00E-01 0.00E-01 6.62E-04 1.33E-02 4.
Manganese-54 C1 0.00E-01 0.00E-01 1.00E-03 1.46E-03 5.
Cobalt-58 Ci 0.00E-01 0.00E-01 1.12E-01 2.37E-01 6.
Iron-59 Ci 0.00E-01 0.00E-01 3.73E-04 7.79E-04 7.
Cobalt-60 Ci 0.00E-01 0.00E-01
- 8. 73E ;..}
1.90E-02 8.
Zine-65 Ci 0.00E-01 0.00E-01 0,
'.J 1.46E-04 9.
Molybdenum-99 Ci 0.00E-01 0.00E-01
- 1. 74E-02 1.82E-02 10.
Iodine-131 Ci 0.00E-01 0.00E-01 1.49E-03 1.30E-03 11.
Cesium-134 Ci
,2.88E-06 1.45E-05 2.71E-04 6.43E-05 12.
Cesium-137 Ci 4.77E-05 1.41E-04 7.22E-04 4.03E-04
- 13. Cerium-141 Ci 0.00E-01 0.00E-01 9.70E-04 4.79E-04
- 14. Cerium-144 Ci 0.00E-01 0.00E-01 2.43E-05 1.52E-04 Others (Specify) t
- 15. Antimony-125 Ci 0.00E-01 0.00E-01 2.18E-03 3.06E-02 l
- 16. Cobalt-57 Ci 1.26E-06 0.00E-01 2.83E-04 8.31E-04
- 17. Chromium-51 Ci 0.00E-01 0.00E-01 1.58E-02 2.27E-02
- 18. Niobium-97 Ci 0.00E-01 0.00E-01 2.90E-05 5.11E-05
- 19. Niobium-95 Ci 0.00E-01 0.00E-01 2.02E-03 3.09E-03
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ist HALF 1990 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)
Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd 20.
Barium-140 Ci 0.00E-01 0.00E-01 1.48E-03 1.13E-03 21.
Iodine-133 Ci 0.00E-01 0 00E-01 6.08E-05 0.00E-01' 1
22.
Zirconium-95 Ci 0.00E-01 0.00E-01 8.65E-04 1.39E-03 23.
Technetium-99m Ci 0.00E-01 0.00E-01 1.76E-02 1.82E-02 24.
Ruthenium-103 Ci 0.00E-01 0.00E-01 4.77E-04 4.69E-04 25.
Tellurium-132 Ci 0.00E-01 0.00E-01 2.09E-06 0.00E-01 26.
Antimony-127 Ci 0.00E-01 0.00E-01 2.71E-05 0.00E-01 27.
Zine-69m Ci 0.00E-01 0.00E-01 1.25E-05 6.13E-06 28.
Lanthanum-140 Ci 0.00E-01 0.00E-01 4.53E-03 1.91E-03 29.
Cesium-138 Ci 0.00E-01 0.00E-01 0.00E-01 1.34E-05 30.
Bromine-84 Ci 0.00E-01~
0.00E-01 4.33E-05 4.26E-05
- 31. Antimony-124 Ci 0.00E-01 0.00E-01 0.00E-01 3.07E-03 32.
Yttrium-91m Ci 0.00E-01 0.00E-01 0.00E-01 6.68E-06 33.
Sodium-24 Ci 0.00E-01 0.00E-01 4.29E-06 1.73E-05 34.
Cerium-143 Ci 0.00E-01 0.00E-01 1.63E-04 0.00E-01 35.
Bromine-82 Ci 0.00E-01 0.00E-01 6.53E-06 0.00E-01 36.
Strontium-92 Ci 0.00E-01 0.00E-01 8.96E-06' O.00E-01 37.
Yttrium-91 Ci 0.00E-01 0.00E-01 1.25E 0.00E-01 Total for Period Ci 5.18E-05 1.56E-04 1.90E-01 3.76E i
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EFFLUENT AND k'ASTE DISPOSAL SEMIANNUAL REPORT ist HALF 1990 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)
G.
Isotope Summary (NOTE: Refer to Table A for values reported as 0.00E-01)
Required by Tecnnical Specification /Others.
Dissolved and Entrained Noble Gases Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter 1st 2nd let 2nd 1.
Krypton-87 Ci 0.00E-01 0.00E-01 7.47E-06 6.46E-06 2.
Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01
-0.00E-01 3.
Xenon-133 Ci 0.00E-01 0.00E-01 4.90E-01 1.02E 4.
Xenon-133m Ci 0.00E-01 0.00E-01 5.68E-03 6.52E-04 5.
Xenon-135 Ci 0.00E-01 0.00E-01 6.48E-03 1.36E-03 6.
Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify) 7.
Krypton-85m Ci 0.00E-01 0.00E-01 4.36E-05 2.41E-05 8.
Krypton-85 Ci 0.00E-01
'O.00E-01 0.00E-01 0.00E-01 9.
Xenon-131m Ci 0.00E-01 0.00E-01 5.62E-03 J.19E-03
- 10. Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 0.00E-01 5.08E-01 1.06E-01 I
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l EFFLUENT AND k'ASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1990 TABEE A LIQUID " TYPICAL LLD" EVALUATION (1) 4t(2)
Nuclide Tech. Spec. LLD 15 min 30 min I hr 2 br__
Manganese-54 5.0E-07 9.12E-09 9.12E-09 9.12E-09 9.12E-09 Cobalt-58 5.0E-07 8.21E-09 8.21E-39 8.21E-09 8.21E-09 Iron-59 5.0E-07 1.62E-08 1.62E-08 1.62E-08
Zinc-65 5.0E-07 2.14E-08 2.14E-08 2.14E-08 2.14E-08 Molybdenum-99 5.0E-07 5.24E-08 5.25E-08 5.28E-08 5.34E-08 Cesium-134 5.0E+07 9.82E-09 9.82E-09 9.82E-09 9.82E-09 Cesium-137 5.0E-07.
9.31E-09 9.31E-09 9.31E-09 9.31E-09 Cerium-141 5.0E-07 1.06E-08 1.06E-08 1.07E-08 1.07E-08 Cerium-144 5.0E-06 4.03E-08 4.03E-08 4.03E-08 4.03E-08 Iodine-131 1.0E-06 7.28E-09 7.28E-09 7.30E-09 7.32E-09 I
Krypton-87 1.0E-05 1.62E-08 1.85E-08 2.43E-08 4.20E-08 Krypton-88 1.0E-05 2.13E-08 2.27E-08 2.56E-08 3.27E-08 i
l Xenon-133 1.0E-05 2.03E-08 2 04E-08 2.04E-08 2.05E-08 3
Xenon-133m 1.0E-05 5.05E-08 5.07E-08 5.10E-08 5.17E-08 Xenon-135 1.0E-05 5.60E-09 5.70E-09 5.93E-09 6.40E-09 Xenon-138 1.0E-05 2.82E-08 5.87E-08 2.55E-07 4.79E-06 l
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y EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT let HALF 1990 TABLE A LIQUID " TYPICAL LLD" EVALUATION (1)
(Continued)
Nue11de-Tech. Spec LLD Typical LLD (Others) (s)
Tritium 1.0E-05 1.0E-06 Gross Alpha 1.0E-07 2.0E-08 Strontium-89 5.0E-08 2.0E-08 Strontium-90 5.0E-08 1.0E-08 Iron-55 1.0E-06 3.0E-07 NOTES:
(1)
All evaluations are in pCi/ml.
All analyses are performed to ensure that Technical Specification LLD limits are met, and these are typical LLD values.
1 (2)
At is the time between sample collection and counting time.
(s)
All of these analyses are required to meet Technical i
Specification LLD limits, and are individually evaluated to ensure compliance.
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l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1sj HALF 1990 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (CROUND LEVEL RELEASES) 1 Ist 2nd Summation of All Releases Unit Qtr 1 Error Qtr
% Error A.
Noble Cases 1.
Total Released Ci 3.27E+03 1 1E+01 9.72E+02 1
2 1E+01 1
2.
Average Release Rate of Period uCi/sec-4.21E+02 1.24E+02 3.
Percent of Technical Specification Limit 1.50E-01 4.41E-02 B.
Iodines 1.
Total Iodine-131 Ci 6.45E-06 11.3E+01 1.50E-05 2 3E+01 1
2.
Average Release Rate for Period uCi/sec 8.30E-07 1.90E-06 3.
Percent of Technical Specification Limit (1.60E-01 uCi/sec) 5.18E-04 1.19E-03 C.
Particulates 1.
Particulates with C1 3.63E-05 1
1 6E+01 3.64E-06 1.6E+01 half-lives 28 days 2.
Average Release Rate for Period uCi/sec 4.67E-06 4.63E-07 3.
Percent of Techni-cal Specification 2.43E-05 4.74E-07 Limit 4.
Gross Alpha Radio-Ci 0.00E-01 12.1E+01 0.00E-01 22.1E+01 activity D.
Tritium 1.
Total Release Ci 3.24E+00 1 5E+01 4.49E+00 1
1
!.5E+01 2.
Average Release Rate for Period uCi/sec 4.16E-01 5.71E-01 3.
Percent of Technical l
Specification Limit 4.91E-04 6.74E-04 (8.47E+04 uC1/sec)
V f
m EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1990 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)
Continuous Mode Batch Mode Unit Quarter Quarter Guarter Quarter 1st 2nd let 2nd E.
Noble Gases Required by Technical Specification /Others 1.
Krypton-87 Ci 0.00E-01 0.00E-01 1.23E-01 5.77E-04 2.
Krypton-88 Ci 0.00E-01 0.00E-01 3.04E+00 6.74E-01 3.
Xenon-133 Ci 4.71E+02 1.06E+00 3.11E+03 9.27E+02 4.
Xenon-133m Ci 0.00E-01 0.00E-01 4.77E+01 1.21E+01 5.
Xenon-135 Ci 0.00E-01 2.90E-02 6.61E+01 1.64E+01 6.
Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify) 7.
Krypton-85 C1 0.00E-01 0.00E-01 1.41E+00 2.51E+00 8.
Argon-41 Ci 0.00E-01 1.11E-01 5.04E+00 2.57E+00 9.
Krypton-85m Ci 0.00E-01 1.40E-02 4.15E+00 9.43E-01
- 10. Xenon-131m Ci 0.00E-01 0.00E-01 2.95E+01 9.92E+00 Total for Period Ci 4.71E+02 1.21E+00 3.27E+03 9.77E+02 i
F.
Iodines 1.
Iodine-131 Ci 6.45E-06 1.49E-05 2.
Iodine-133 Ci 6.62E-07 2.51E-06 3.
Iodine-135 Ci 0.00E-01 0.00E-01 I
I Total for Period Ci 7.11E-06 1.74E-05 NOTE: Refer to Table B for values reported as 0.00E-01.
. )
m
m EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1990 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)
C.
Particulates Reauired by Technical Specification /Othe Nuclide Unit
<uous Mode
.,.- t e r Quarter
_1st 2nd,_
1.
-Strontium-89 Ci 0.00E-01 0.00E-01 2.
Strontium-90 Ci 0.00E-01 0.00E-01 3.
Iron-59 Ci 0.006-01' O.00E-01 4.
Cobalt-60 Ci 5.23E-06 0.00E-01 5.
Zine-65 Ci 0.00E-01 0.00E-01 6.
Manganese-54 Ci 0.00E-01 0.00E-01 7.
Cobalt-58 Ci 3.07E-05 3.63E-06 8.
Molybdenum-99 Ci 1.74E-07 0.00E-01 9.
Cesium-134 Ci 0.00E-01' O.00E-01
- 10. Cesium-137 Ci 0.00E-01 0.00E-01
- 11. Cerium-141 Ci 0.00E-01 0.00E-01
- 12. Cerium-144 Ci 0.00E-01 0.00E-01 Others (Specify)
- 13. Technetium-99m Ci 1.74E-07 0.00E-01 14 Cobalt-57 Ci 0.00E-01 1.58E-09 Total for Period Ci 3.63E-05 3.63E-06 NOTE: Refer to Table B for values reported as 0.00E-01.
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ist HALF 1990 TABLE B GASEQUS " TYPICAL" LLD F. VALUATION (1)
Noble Gas at(8)
Nuclide Tech. Spec. LLD 15 min 30 min 1 hr 2 hr 3 hr.
Krypton-87 1.0E-04 2.91E-07 3.34E-07 4.39E-07 7.56E-07 Krypton-88 1.0E-04 3.59E-07 3.82E-07 4.
( -0 7 5.51E-07 Xenon-133 1.0E-04 1.97E-07 1.98E-07 1.98E-07 1.99E-07 Xenon-133m 1.0E-04 8.75E-07 8.78E-07 8.84E-07 8.95E-07 Xenon-135 1.0E-04 9.76E-08 9.95E-08 1.03E-07 1.12E-07 Xenon-138 1.0E-04 4.93E-07 1.03E-06 4.46E-06 8 38E-05 t
Particulate Sample Manganese-54 1.0E 3.88E-14 3.88E-14 3.88E-14 3.88E-14 3.88E-14 Cobalt-58 1.0E-10 3.49E-14 3.49E-14 3.49E-14 3.50E-14 3.50E-14 Iron-59 1.0E-10 7.25E-14 7.25E-14 7.25E-14 7.26E-14 7.26E-14 Cobalt-60 1.0E-10 4.95E-14 4.95E-14 4.95E-14 4.95E-14 4.95E-14 Zinc-65 1.0E-10 9.54E-14 9.54E-14 9.54E-14 9.54E-14 9.54E-14 Molybdenum-99 1.0E-10 2.49E-13 2.49E-13 2.51E-13 2.53E-13 2.56E-13 Cesium-134 1.0E-10 4.15E-14 4.15E-14 4.15E-14 4.15E-14 4.15E-14 f
Cesium-137 1.0E-10 3.85E-14 3.85E-14 3.85E-14 3.85E-14 3.85E-14 Cerium-141 1.0E-10 3.70E-14 3.70E-14 3.70E-14 3.70E-14 3.71E-14 Cerium-144 1.0E.10 1.32E-13 1.32E-13 1.32E-13 1.32E-13 1.32E-13 Iodine-131 1.0E-10 3.09E-14 3.09E-14 3.09E-14 3.11E-14 3.12E-14 Strontium-89(3) 1.0E-11 i
i Strontium-90 (3) 1.0E-11 Gross Alpha (3) 1.0E-11 )
i l
EFFLUENT AND WASTE DISPOSAL SENIANNUAL REP 02T let HALF 1990 SOLID W5STE (RADI0 ACTIVE SHIPMENTS)
A.
solid Waste shipped offsite for Burial or Disposal (not Irradiated Fuel) 6 Month Est. Tot.
1.
Type of Waste Unit Period Error %
i a.
spent resins, filter sludges, m3 1.04E+1 11.00E-1 evaporator bottoms, etc.
C1 1.29E+0 ti.50E+1 b.
Dry Active Waste, Compressible Waste m3 8.11E+1 11.00E-1 Contaminated Equipment, etc.
C1 6.64E+0 11.50E+1 c.
Irradiated Components, m3 None N/A control Rods, etc.
Ci None N/A d.
Other (describe) m3 None N/A Composite liners (containinE wet rage, Cl None N/A resin, mechanical filters and metal oxides in boric acid concentrates) and oil liners 2.
Estimate of Major Neelide Composition (by type of waste)
Spent resin, filter sludges, evaporator bottoms, etc.
a.
(nuclides determined by measurement)
Curies Percent 1.
Hydrogen-3 1.76E-2 1.37E+0 2.
Manganese-54 8.45E-2 6.56E+0 3.
Iron-55 2.08E-1
- 1. 6.t. +1 4.
Cobalt-58 3.84E-1 2.99E+1 5.
Cobalt-60 2.58E-1 2.00E+1 6.
Nickel-63 2.16E-1 1.67E+1 7.
Cesium-137 5.71E-2 4.44E+0 b.
Dry active waste, compressible waste, contaminated equipment etc.
(nuclides determined by estimate) 1.
Iron-55 4.71E+0 7.10E+1 2.
Cobalt-58 2.03E-1 3.06E+0 3.
Cobalt-60 1.12E+0 1.68E+1 4.
Nickel-63 5.06E-1 7.62E+0 c.
Irradiated. Components N/A N/A d
Other (describe)
N/A N/A
_17-s
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 18t HALF 1990 SOLID WASTE (RADIOACTIVE SHIPMENTS) 3.
Solid Waste Disposition Number of Shipments Type Quantity Mode of Transportation Destination a) Spent resin, filter sludges, evaporator bottoms, etc.
6 A-LSA Motor Freight Barnwell, SC 1
B-LSA Motor Frei ht Barnwell, SC t
Number of Shipments Type Quantity Mode of Transportation Destination b) Dry active waste, compressible waste, contaminated equipment, etc.
40 A-LSA Motor Freight Barnwell SC Number of Shipments Type Quantity Mode of Transportation Destination c) Irradiated components, control rods, etc.
None Number of Shipments Type Quantity Mode of Transportation Destination d) Composite liners (containing wet rags, resin, mechanical filters and oxides on
{
boric acid) and oil liners 2
A-LSA Motor Freight Barnwell, SC 1
A-LSA Motor Freight Richland, WA i
4 Irradiated Fuel Shipments (Disposition)
Number of Shipments Type Quantity Mode of Transportation Destination None N/A N/A N/A 5.
Solidification of Waste i
l Was solidification performed?
X Yes No l
If yes, solidification media:
Cement i
! l I
l
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT.
_1sj HALF 1990, ATTACHMENT l'
[
INOPERABLE INSTRUMENTATION-Pursuant to Technical Specification LCO 3.3.3.10, the following information
-is provided concerning radioactive effluent monitoring instrumentation which was inoperable for greater than 30 consecutive days during the period.
January 1, through July 31, 1990.
. Flow indicator 1-FI-30-242, which measures air flow rate through Unit 1 Shield Building Exhaust, was declared inoperable on October 31, 1987.for j
exhaust flow rates of less than 8,000 cubic feet'per minute and remains inoperable at-this time._ 2-FI-30-242, which measures air flow rate through Unit 2 Shield Building Exhaust, was declared inoperable for exhaust flow:
rates of less than 8,000 cubic. feet per minute on November 25, 1987, and remains inoperable.
It was determined that these two instruments cannot accurately measure exhaust flow rates that are less than 8,000 CFMl:they_are-considered operable for flows above 8000 CFM.
Current plans are to replace this instrumentation on both shield building exhausts.
In the interim, 8,000 CFM is.being used to conservatively estimate releases ';ia the Shield Building. Exhaust when flow rates are less than 8,000 CFM.
The Waste Gas analyzer oxygen channel (0-02 AN-43-5000) was declared inoperable on March 22, 1990. The oxygen channel had become erratic in its readings and out of tolerance when compared-to grab' samples.
Ichh1 investigation revealed that the instrument is sensitive:(cat aate) to changes in system pressure. Condition adverse to Quality k,
>rc, SQP 900170, was initiated on April 5, 1990.
Long term correctiv' acc'ons include designing a suitable replacement to replace the obs. aste equipr 4t.
Interim corrective actions include obtaining original vendr
- ~'e rvon' services to assist in stab 11 zing the analyzers oxygen chanrz-
'rh3 enable Sequoyah to continue operation to meet technical spe.
v m-3.11.2.5 and 3.3.3.10.
Current grab samplings will contir e.e instrr aent is made opert.ble or replaced. As of August 20,,
troubleshooting investigations are in progress to identify w
.rsv problems associated with instrument stabilization. '
4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT let HALF 1990 ATTACHMENT 2 i
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL.
The following changes were made to the Sequoyah Offsite Do;o fairs 12 tion Manual'(ODCM) during the period January 1, 1990, to June 30, 1990j and the affected pages (Revision 24) are attached. The purpos4 of this Revision was the implementation of Generic Letter 89-01 (Radiological Effluents transferred to the ODCM).
4 k
-l ENCLOSURE 2-Offsite Dose Calculation Manual (ODCM), Revision 24 In this revision there are two sets of changes, the first are corrections of typographical errors.
The second change adds a section to the ODCM (Section 6.0), which contains definitions of terms. These: terms are those that are defined in Technical Specification (TS) Section 1.0 ani are used -in the ODCM. - This change is in anticipation of TS Change 90-03 that implements NRC's Generic Letter (GL) 89-01.
This GL recommends the relocation of the Radioactive Effluent Technical Specifications (RETS) to the ODCM.
Prior to the TS change, the definitions need to be relocated to the ODCM so that the ODCM will be a sr?f-contained document upon the implementation of the TS change.
In addition.
ra the added Section 6.0, all terms that are defined in this section are highlighted in_the ODCM text by being capitalized.
The definitions are viuplicated in the ODCM verbatim.
The only systems potentially affected by this change-to the ODCM will be the liquid and gaseous effluent monitoring system (System 90) described in Section 11.4 of the Sequoyah Nuclear Plant Final Safety Analysis Report.
Since this revision does not change any calculational methodology or requirements, it will not have any effect on this system. lThis revision will in no way affect the methodology described in the ODCM; hence no setpoints will be changed because of this revision.
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SEQUOYAH NUCLEAR
~
PLANT OFFSITE DOSE CALCULATION MANUAL
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TENNESSEE VALLEY AUTHORITY L
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l SEQUOYAH NUCLEAR PLANT-0FFSITE DOSE CALCULATION MANUAL l
DATES OF REVISIONS Original ODCM 02/29/80*
Revision 1 04/15/80**
Revision 2 10/07/80**
Revision 3 11/03/80, 02/10/81 04/08/81, 06/04/81**
Revision 4 11/22/82 10/22/81, 11/28/81, 04/29/82**
Revision 5 10/21/82**
Revision 6 01/20/83**
Revision 7 03/23/83**
Revision 8 12/16/83**
Revision 9 03/07/84**
Revision 10 04/24/84**
Revision 11 08/21/84**
Revision 12 02/19/85**
Revision 13 12/02/85 Revision 14 04/14/86 l
Revision 15 11/05/86***
Revision 16 01/16/87**
{
Revision 17 10/28/87**
C Revision 18 01/05/88**
Revision 19 03/30/88**
Revision 20 07/19/88**
Revision 20A 12/14/88**
Revision 21 02/15/89**
Revision 22 06/01/89**
Revision 23 6/28/89 & 9/15/89****
l Revision 24 2/15/90**
l Approved by Date J/A2/90 RARC irr n
!N7!"[h' Approved b k
Date
( lanager, Chemistry & Radio'logi' cal
(
Services l'
Low Pouer license for Sequoyah unit 1 RARC Meeting date
- Date approved by RARC Chairman
- Revision 23 implements the Nuclear Data Effluent Management Software. This ODCM revision and the software will be implemented concurrently on October 9, 1989.
Releases made during the month of October prior to the software implementation 4will be backfitted to comply with this revision.
L 00101-I
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SEQUOYAH NUCLEAR ~ PLANT C
OFFSITE DOSE CALCULATION MANUAL
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EFFECTIVE ~PAGE LISTING REVISION 24 4
P.a11 Revision Listing of Dates of Revisions Revision 24 i
Table of Contents Page 1 through-10 Revision 24 Pages 1 through 156 Revision 24 I
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TABLE OF CONTENTS Revision 24 L-page 1.0 CASEOUS EFFLUENTS 1
1.1 RELEASE POINTS DESCRIPTION 1
1.2 DOSE BATE 3
1.2.1 Rt0VIREMENTS 3
1.2.2 REPORTING LIMITS 4
1.2.3 HQBLE CAS DOSE RAIE1 4
1.2.3.1 Total Body Dose Rate 4
1.2.3.2 Skin Dose Rate 5
1.2.4 I-131. 1-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF CREATER THAN 8 DAYS - ORGAN DOSE RATE 6
1.3 RADICAC"IVE CASEOUS EFFLUENT MONITORING IN5ikUMENTATION
()
7 1.3.1 RE0VIREMENT 7
1.3.2 RELEASE SAMPLING 8
1.3.3 INSTRUMENT SETPOINTS 9
1.3.3.1 Expected Monitor Resoonse 9
1.3.3.2 Calculated Maxi== Setoolnt
- 9 1.3.3.3 Normal Default Setooint 10 1.3.3.4 Actual Monitor setooints 11 1.4 DOSE - NOBLE CASES 12 1.4.1 REQUIREMENTS 12 TOC-1
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OFFSITE DOSE eAf>'ULATION MANUAL TABLE OF CONTENTS Revision 24 Page 1.4.2 CUMULATIVE DOSE CALCULATIONS - WOBLE CASES 13 1.4.2.1 Cama dose to air 13
-1.4.2.2 Beta dose to air 14 1.4.2.3 Cusa 1stive' Dose - Noble cas 14 1.4.2.4 Comparison to Limits 14 1.5 CUMULATIVE DOSE - I-131. I-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM 15 1.5.1 REQUIREMENTS 15 1.5.2 DOSE DUE TO I-131. I-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES OF CREATER THAN 8 DAYS 17 1.5.2.1 Orman dose Calculation 17
(
1.5.2.2 Cumulative Doses 18 1.5.2.3.Comoarison to Limits 18 1.6 CASE 0VS RADWASTE TREATMENT 19 1.6.1 BEQUIREMENTS 19 1.6.2 DOSE PROJECTIONS 20 1.6.3 CASEOUS RADWASTE TREATMENT SYS' TEM DESCRIPTION 20
-l 1.7 OUARTERLY DOSE CALCULATIONS 21 1
1.7.1 N0BLE CAS - CAMMA AIR DOSE 21 1.7.2 NOBLE CAS - BETA AIR DOSE 21' 1.7.3 RADI0 IODINE. PARTICULATE AND TRITIUM - MAXIMUM ORCAN DOSE
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l TABLE OF CONTENTS Revision 24 page.
t 1.7.4 POPULATION DOSES 23 1.7.5 REPORTING OF DOSES 25 1.8 CASE 0US RELEASES - Dose Factors 26 1.8.1 FASTURE CRASS-DOW/C0AT-MILE INCESTION DOSE FACTORS - Repi 26 1.8.2 STORED FEED-COW /C0AT-MILK INCESTION DOSE FACTORS - RCSi 27-1.8.3 R&EIEME GRASS-BEEF INCESTION DOSE FACTORS - Ryyg 28 1.8.4 STORED FEED-BEEP INCESTION DOSE FACTORS - Rgst 29 1.8.5 FRESH LEAFY VEGETABLE INCESTION DOSE FACTORS - Ryyt 30 i
1.8.6 STORED VECETABLE INCESTION DOSE FACTORS - Rygt 31 1.8.7 TRITIUM-PASTURE GRASS-COW / COAT-MILK DOSE FACTOR - R
(
CTP 32 1.B.8 TRITIUM-STORED FEED-COW / COAT-MILK DOSE FACTOR - RCTS 33 1.8.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR - RNT 34 1.8.10 TRITIUM-STORED FEED-BEEF DOSE FACTOR - RgTS 35 i
1.8.11 TRITIUM-FRESH LEAFY VICUTABLES DOSE FACTOR - R VTF 36 1.8.12 TRITIUM-STORED VECETABLES DOSE FACTOR - RVTS 37 1.8.13 INNALATION DOSE FACTORS-Rgg 38 1.8.14 GROUND PLANE DOSE FACTORS - Rgt 38-1.9 DISFERSION NETHODOLOGY 39 1.9.1 AIR CONCENTRATION - 1 (yCi/a')
39 1.9.2 RELATIVE CONCENTRATION - r/0 (sec/m')
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SEOUOYAH NUCLEAR PLANT 0FFSITE DOSE CA!.CULATION MANU6k.
TABLE OF CONTENTS Revision 24 Page 1.9.3 RELATIVE DEPOSITION-D/0 (m's) 41 2.0 LIQUID EFFLUENTS 42 2.1 RELEASE POINTS 42 2.2 CONCENTRATION 44 2.2.1 REQUIPEMENTS 44 2.2.2 MPC-SUM OF THE RATIOS 45 2.3 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION 46 2.3.1 REQUIREMENTS i
46 2.3.2 RELFASE SAMPLING 47 2.3.3 IESIRUFENT SETPOINTS 48 2.3.3.1 Ewooeted Monitor Res'Lgggt.
48 2.3.3.2 Calculated Max!_== Aonitor Setpoint 48 2.3.3.3 Wormal Default Set 22iILt 50 2.3.3.4 Actual Monitor Seteoints 50
)
2.3.4 Post-Release Analysis 51 i'
l 2.4 2 2I.E 52 l
2.4.1 REQUIREMENTS 52 2.4.2 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS 54 2.4.2.2 Monthiv Dose Calculations 55 2.4.2.3 Cumulative Doses 55 1
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i SEQUOYAH FJCLEAR PLANT C
0FFSITE DOSE CALCULATION M TABLE OF CONTENTS Revision 24 Page 2.4.2.4 Comparison to Limits 55 2.5 LIOUID WASTE TREATMENT 56 2.5.1 REQUIREMENT 56 2.5.2 LIOUID RADWASTE TREATMENT SYSTEM 57 2.5.3 pose PROJECTIONS 57 2.6 OUARTERLY DOSE CALCULATIONS 58 2.6.1 WATER INCESTION 58 2.6.2 FISH INCESTION 59-2.6.3 SHORELINE RECREE LQE 59-l 2.6.4 TOTAL MAKIMUM INDIVIDUAL DOSE 60 2.6.5 POPULATION DOSES 61 2.7 LIOU1D DOSE FACTOR EQUATIONS 63 2.7.1 WATER INCESTION - AWit (area /hr per pC1/al)-
63 2.7.2 FISH INCESTION - AFit (area /hr per pCi/ml) 63 2.7.3 SHORELINE RECREATION - ARit (arem/hr per pCi/ml).
63-3.0 Radiological Environmental Monitorint 65 3.1 MINIMUM REOUIRED MONITORINC PROGRAM 65 i
3.1.1 REQUIREMENT 65 3.1.2 ][QElTORINC PROGRAM 66 3.1.3 DETECiION CAPABILITIES 67
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C SEOUOYAH NUCLEAR PLANT 0FFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Revision 24 page 3.2 LAND USE CENSUS 68' 3.2.1 REQUIREMENT 68 3.2.2 LAND USE CENSUJ-69 3.3 INTERLABORATORY COMPARISON PROCRAM 70 3.3.1 REQUIREMENT 70 3.3.2 INTERLABORATORY COMPARISON PROGRAM 70 4.0 TOTAL DOSE 73 4.1 REQUIREMENT 73 4.2 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE 72 5.0 REPORTING REOUIREMENTS 73 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 73 5.2 SFMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 73 6.0 DEFINITIONS 75-6.1 CHANNEL CALIBRATION 75 6.2 CHANNEL CHECK 75 6.3 CHANNEL FUNCTIONAL TEST 75 6.4 CASEOUS RADWASTE TREATMENT SYSTEM 75 6.5 DOSE EQUIVALENT T-131
,76 6.6 NEMBER(S) 0F THE PUBLIC 76 6.6 OPERABLE - OPERABILITY 76 TOC-6
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6.9 PURGE - FURCING 76 6.10 RATED THERMAL POWER 77 6.11 SITE BOUNDARY 77 6.12 SOURCE CHECK 77 6.13 UNRESTRICTED AREA 77 6.14 VENTILATION EKMAUST TREATMENT S M 77 6.15 VENTING 77 I
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SE000YAH NUCLtAR PLANT s
OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES 1
Revision 24-Pa8e 1.1 RADICACTIVE GASEOUS WASTE MONITORING SAIO VM AND ANALYSIS l
PROGRAM 78 1.2
.101NT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED I
FOR DIFFERENT STABILITY CLASSES 82' q
1.3 SQN - 0FFSITE RECEPTOR LOCATION DATA-89 1.4 DOSE FACTORS FOR SUBMERSION IN NOBLE CASES 90 x
1.5 RADI0 ACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION 91 1.6 RADI0 ACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 93 1.7 SECTOR ELEMENTS CONSIDERED FOR POPULATXON DOSES 95 1.8 POPULATION WITHIN EACH SECTOR ELEMENT 96 1.9 INGESTION DOSE FACTORS
(
98 1.10 RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA 105 i
1.11 DOSE CALCULATION FACTORS
-108 1.12 INMALATION DOSE FACTORS 110 1
1.13 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 118 2.1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 120 2.2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 124 2.3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INRTRUMENTATION SURVEILLANCE REQUIREMENTS 127 2;4 RECEPTORS FOR LIQUID DOSE CALCULATIONS 129 2.5 BI0 ACCUMULATION FACTORS FOR FRESHWATER FISH 130 TOC-8 00101
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C SEOUOYAN NUCLFA8 PLANT 0FFSITE DOSS cA_LG1LATION MANUAL LIST OF 1g],31 Revision 24 l'
Page 3.1 RADIOLOGICAL ENVIRONNEnitAL NONITORING t30 CRAN 131 3.2 NAKINUM VALUES FOR THE LOWER. LIMITS OF DETECTION-(LLD)134 3 '. 3 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN i
RNVIROWNENTAL SAMPLES 136 3.4 RADIOLOGICAL ENVIRONMENTAL NONITORINC FROGRAN 137 l
3.5 SEQUOYAH nut, LEAR PLANT - ENVIRONMENTAL RADIOLOGICAL MONITORING l
PROGRAM - SAMPLING LOCATIONS 141' 3.6 SEQUOYAH NUCLEAR PLANT - THERMOLUh.)ESCENT DOSIMETRY LOCATIO 143 t
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SEOUOYAH NUCLEAR PLANT OFFSITE DOSE-CALCULATION MANUAL LIST OF FIGURES
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Revision 24 Page 1.1 CASEOUS EFFLUENT RELEASE POINTS 145 1.2 AUKILIARY AND SHIELD BUILDING VENTS (DETAIL) 146 1.3 SQN LAND SITE SOUNDARY 147 1.4 GASECUS RADWASTE TREATMENT SYSTEM.
148 1.5 PLUME DEPLETION EFFECT FOR CROUND LEVEL RELEASES 149 1.6 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 150 1.7 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES 151 2.1 LIQUID EFFLUENT RELEASE POINTS 152 2.2 LIQUID RADWASTE SYSTEM 153 3.1. RADIOLOGICAL ENVIRONMENTAL SAr.< LING LOCATIONS - WITHIN 1 MILE OF PLANT 154 3.2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - WITHIN 1 TO 5 MILES OF PLANT 155.
3.3 RADIOLOCICAL ENVIRONMENTAL SAMPLING LOCATIONS -
CRF.ATER TMAN 5 MILE? 0F PLANT 156 i
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SQN ODCM Revision 24 Page 1 of 156 1.0 GA310ML EFFLVt HS 1.1 RELEASE PQTVTS DtSCRIPTION There are six exhausts at Sequoyah Wuclear Plant that are monitored a
for airborne ef fluents. These are a condenser Vacuum Exhaust for each unit, a service Building Exhaust, an Auxiliary Building Exhaust and a shield Building Exhaust for each unit.
Figure 1.1 provides an outline of the airborne affluent release and discharge points with associatt.d radiation monitor identifications.
Condenser Vacuum Exhaust The Condenser Vacuum Exhausts (CVEs) are located in the turbine bulliing. They exhaust at a maximum design flow rate of 45 cubic feet per minute. They are monitored by radiation monitors (1)- and (2)-RM-90-99, -119.
Service Building Vent, 4
The Titration Room, Chemistry Lab, Not Shop, and Health Physics Lab all exhaust to the Service Building Vent. This exhausts at approximately 14,950 efs and is monitored by radiation monitor 0-RM-9 0 -132.
Auxiliary Buildinz Exhaust (see Figure 1.2 for detail)
The annulus vacuum priming system exhausts through the containment
(,'
vent to the Auxiliary Building. The Auxiliary Building exhaust mixes with the General Exhaust System and they cumulatively exhaust at a maximum design flow of 228,000 cfm. The exhaust is monitored by radiation monitor 0-RM-90-101.
Shield Buildina' Vent (see Figure 1.2 for detail)
The Auxiliary Building Gas Treatment System (ABCTS) draws from the Auxiliary Building and exhausts to the waste gas header. There are nine Waste Gas Decay Tanks (WGDTs) that also mapty into this. header.
Either ABGTS or the' Emergency'Cas Treatment System (ECTS) is run to release a WCDT.
Each WGDT has a design capacity of 600 cubic feet and a design release rate of 22.5 cfa. Both the Containment Purge and the Incore Instrument Room Purge from each unit tie into the waste gas header. The Containment Purge exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors (1)- (2)-BM-90-130. -131.
If the-Incore Instrument Room Purge is operating exclusively, it exhausts at 800 cfm. 'Under emergency conditions, and sometimes during normal operation, the ECTS is used to draw a vacuum in the annulus and exhaust to the Shield ~ Building Vent. Auxiliary Building Isolation starts both the ABGTS and ECTS. The common header exhausts to the
-p Reformatting / Repagination changes only o1441 fN ~ '
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SQN ODCM R3visicn 24 Page 2 of 156 Shield Building Exhaust. There is one exhaust for each unit. This exhausts at a maximum design flow of 28,000 cfm and is monitored by radiation monitors (1)- (2)-RM-90-100.
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Revision 24
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Page 3 of 156 1.2 DOSE RATE 1.2.1 goVlRDfEHL1 The dose rate due to radioactive materials released in gaseous etfluents to areas at or beyond the SITE BOUNDARY (UNRESTRICTED AREA) 124 -
j (see Figure 1.3) shall be limited to the following:
a.
For noble gases: Less than or equal to 500 area /yr to the total body and less than or equal to 3000 area /yr to the skin, and b.
For Iodine-131. Iodine-133. Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less i
than or equal to 1500 area /yr to any organ.
l This requirement is applicable at all times.
This requirement is provided to ensure that the dose at s'ny time at the SITE BOUNDARY from gaseous effluents from all units on the site R24-will be within the annual dose limits of 10 CFR Part 20.
'15e annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B. Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, R24 either within or outside the SITE BOUNDARY, to annual average-R24 concentrations exceeding the limits specified in Appendix B. Table II of 10 CFR part 20 (10 CFR Part 20.106(b)).
For MEMBERS OF THE PUBLIC R24
(
who may at times be within the SITE BOUNDARY, the occupancy of the R24 l
individual will be sufficiently low to compensate for any increase in l
the atmospheric diffusion factor above that for the SITE BOUNDARY.
R24 The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE B0UNDARY to less than or equal to R24 500 mesm/yr to the total body or to less than or equal to 3000 mrem /yr to the skim These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via-the cow-milk-inf ant pathway to less than or equal to 1500 meem/yr for the nearest cow to the plant. This requirement applies to'the release of gaseous effluents from all reactors at the site. For units with-shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system.
If this requirement is not met, the following action will be -
performed:.
With dose rate (s) exceeding the above limits, without delay restore the release rate to within the above lialt(s).
Lc 01441 ngh!"'IC d;F MMP ~~WS*O m~- - a
SQW ODCM Revision 24 To ensure that this requirement is met:
page 4 of 156
(
The dose rate due to noble gases in gaseous offluents shall be detemined to be within the above limits in accordance with the methodology and parameterni in Section 1.2.3, and The dose este due to I-131. I-133. Tritiuss, and for all radionuelides in particulate form with half-lives greater than i
8 days in gaseous effluents shall be determined to be within the l
above limits in accordance with the methodology and parameters in Section 1.2.4 and by obtaining representative samples and perfo ming analyses in accordance with the sasqpling and analysis program specified in Table 1.1.
1.2.2 REFORTINC 1,1 NITS 10 CFR 50.73 requires that any airborne radioactivity release that exceeds 2 times the applicable concentrations of the limits specifled in Appendix B. Table II cf 10 CFR 20 in VNRESTRICTED AREAS when averaged over a period of one hour be reported to the NRC.within R24 30 days.
For the purposes of meeting this requirement, it is assumed that the dose rate limits stated above are the result of offsite concentrations equal to those listed in Appendix B. Table II of 10 CFR 20.
1.2.3 WOBt.E CAS DOSE RATES Dose rates are calculated for total body and skin due to submersion within a cloud of noble gases using a semi-infinite cloud model.
1.2.3.1 Total Body Dose Rate The dose rate to the total body, DRTB in trea/ year, is calculated using the following equation:
DRTB = (K/Q) F 1 Ci DFBI i
(1 1) where X/Q relative concentration, s/a. Relative air
=
s concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in section 1.9.2 using the historical meteorological data for the period
'1972-1975 given in Table 1.2.
For dose rate calculations, the highest value from.the sixteen land-site boundary locations is used.
5.12E-06 s/as (from Table 1.3).
=
y a flowrate of effluent stream cc/s.
Ci concentration of noble gas n,uclide i in effluent stream, a
vCi/cc.
DFBI 4
nuclide 1, aram/y per pC1/atotal body dose factor due to gamma radiation
=
s (Table 1.4).
01441 Q
~~
a.
SQN ODCM Revision 24 1.2.3.2 skin Dose Rate
[
The dose rate to the skin, DRs in pres / year, is calculated using the i
i A
f011cwing equation:
DRs = (X/Q) F I C (DFsi + 1.11 DFyi)
(1.2) i i
where X/Q relative concentration, s/a'.
Relative air-
=
concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period 1972-1975 given in Table 1.2.
For dose rate calculations, the highest value from the sixteen land-site boundary locations is used.
5.12E-06 s/ms (from Table 1.3).
=
F flowrote of effluent stream, cc/s.
=
Ci concentration of noble gas nuclide i in effluent stream,
=
WCi/cc.
DFS1 skin dose factor due to beta radiation for noble gas
=
nuclide i. arem/y per pCi/m* (Table 1.4).
1.11 the average ratio of tissue to air energy absorption
=
coefficients, arem/arad.
DFyi dose conversion factor for external samma for noble gas-
=
nuclide i, mrad / year per pCi/m8 (Table 1.4)..
1
.M c i
(
Reformatting / Repagination changes only
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01441 1
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=
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Revision 24 Page 6 of 156 1.2.4 I-131. 1-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM 3
WITH MALF-LIVES OF CREATER THAN 8 DAYS - ORGAN DOSE RATE Organ dose rates due to I-131. I-133. Tritium and all radionuclides in particulate form with half-lives of greater than 8 days, DR rt in o
= rem / year, are calculated for all age groups (adult, teen, child, and Infant) and all organs Coone, liver, tetel body thyroid, kidney, lung, and CI tract) using the following equation:
{
DRors= F[ C (A/Q)IRIT+RCTpl+1C [(X/Q)Rgi+(D/Q)[Repi+ Rat))]
(1.3) R24 T
i i
where F
= flowrate of affluent stream, cc/s.
= concentration of tritium in effluent stream, pCi/cc.
1/Q
=_ relative concentration, s/m8 Relative air concentrations are calculated for the land-site boundary in I
each of the sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period 1972-1975 given in Table 1.2.
For dose rate calculations, the highest value from the sixteen land-site boundary locations is used.
(
= 5.12E-06 a/as (from Table 1.3).
RIT
= inhalation dose factor for tritium, arem/ year per pCL/ms.
Dose factor is calculated as described in Section 1.8.13.
RCTp
= Grass-cow-milk dose factor for tritium, mrom/ year per
(
pCi/m8 Dose factor is calculated as described in-Section 1.8.7.
Ci
= concentration of nuclide i in effluent stream, pCi/cc.
Rgi
= inhalation dose factor for each identified nuclide 1, arem/ year per pCi/m*.
Dose factors are calculated as described in Section 1.8.13.
D/Q
= relative deposition, 1/m8 Relative deposition is calculated for the land-site boundary in each of the sixteen sectors as described in section 1.9.3 using the historical meteorological data for the, period 1972-1975 given in Table 1.2.
For dose rate calculations,'the highest value from the sixteen land-site boundary locations is used.
= 1.29E-08 1/ma (from Table 1.3).
Rept a crass-cow-milk dose factor for each identified nuclide i, a
m -area / year per pCi/s. Dose factors are calculated as described in Section 1.8.1.
Roi
=. ground plane dose factor for each identified nuclide 1, a
m -area / year per pCi/s. Dose factors are calculated as described in section 1.8.14.
The maximum organ dose este is selected from among the dose rates calculated for all the organs and all age groups.
M 01441 er n
.i SQN ODCH Revision 24 j
page 7 of 156 1.3 RADI0 ACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION C
1.3.1 REQUIREMENT e
The radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.5 shall be OPERABLE with their alara/ trip setpoints R24 set to ensure that the limits of Section 1.2 are not exceeded. The i
alarm / trip satpoints of these channele shall be detemined in accordance with the methodology and parameters in Section 1.3.3.
This requirement is applicable as shown in Table 1.5.
The radioactive gaseous affluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous affluents during actual or potential releases of gaseous effluents. The alam/ trip motpoints for these instruments i
shall be calculated in accordance with the procedures in Section 1.3.3 to ensure that the alam/ trip will occur prior to exceeding the limits i
of 10 CFR part 20.
The OptRABILITY and use of this instrumentation is R24 1
consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR part 50.
If this requirement is not met, the appropriate following action (s)l will be performed:
With a radioactive gaseous effluent monitoring instrumentation a.
1
(
channel alam/ trip setpoint less conservative than required above, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, declare the channel inoperable, or chLnste the setpoint so it is acceptably conservative.
b.
With less than the minimum number of radioactive gaseous effluent monitoring instnamentation channels OPERABLE take the action shown R24 in Table 1.5.
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in R24 the next seal-Annual Effluent Report why the inoperability could not be corrected within 30 days
- To ensure that this requirement is met.
\\
(
Bach radioactive gaseous affluent monitoring instrumentation channel shall be demonstrated OptRABLE by performance of the R24 CHANNEL CHECK, SOURCE CHECK, CHANNEL' CALIBRATION, and CHANNEL R24 FUNCTIONAL TEST operations at the frequencies shown in Table 1.6.
R24
- sa 01441 l
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SQN ODCN Revision 24 i
Page 8 of 156 1.3.2 RELEASE SAMPLING
(
Prior to each celease (excluding an Incore Instrument Room Purge),
a grab sample is taken and analyzed to determine the concentration.
WCi/ce, of each noble gas nuclide. On at least a weekly basis, filters are analyzed to determine the amount of iodines and particulates released. Composite samples are maintained (as required by Table 1.1) to determine the concentration of certain nuelldes (Sr-89 Sr-90, and alpha emitters).
For those nuclides whose activities are determined from composite samples the concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations in Sections 1.2, 1.4, 1.5 and 1.6.
The actual measured concentrations will be used for the dose calculations described in Section 1.7.
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Reformatting / Repagination changes only s
01441 4
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e
SQM VDCK Revis.on 24 page 9 of 156 1.3.3 INSTRUMENT SETp0IFTS 1.3.3.1 troected Monitor Response For each release, the expected monitor response,=R in cym, is calculated using the following equation:
R=
8 + ! ef ft C1 (1.4) f i
where B
= monitor background, cym.
effi efficiency factor for the monitor for nuclide i, a
cpm per pC1/ce._
i Ci
= measuced concentration of nuclide 1, pC1/ce.
For the noble gas response, the sumation in the above equation will be performed over all measured noble gases.
Similarly, the responses for iodines and particulates would sum over all measured iodine and particulate nuclides respectively.
1.3.3.2 Calculated Maximum Seteoint For each release from a release point, a calculated maximum setpoint is detemined for the appropriate monitor which corresponds to the most restrictive dose rate limit.- This maximum setpoint is calculated as follows:
(
1.
The ratio, r, of the dose rate limit to the calculated dose rate for the release is obtained using the following equation:
r=
(1.5)
DR where DRiim
= the dose rate limit, arem/ year.
= 500 mram/ year to the tot;al body for noble Bases.
= 3000 mrom/ year to the skin for noble gases, and
= 1500 meem/ year to the maximum organ for iodines and particulates.
DR
= the calculated dose rate for the release, arem/ year.
= DR73 for total body (as described in Section 1.2.3.1),
= DRs for skin (as described in Section 1.2.3.2), and
= DRort for maximum organ (as described in
, SectIon 1.2.4).
.' e c Reformatting / Repagination changes only 01441
(
}-
_^
The calculated maxLaum monitor response R11m in epm, corresponding to the dose rate limit is determined using the
(
following equation:
Rlia * (r(R - B)) + B (1.6) where r a ratio of dose rate limit to calculated dose rate for the release, as calculated above. For noble gases, the smaller-of the two ratios for total body or skin is used.
R = expected monitor response (as calculated in Section 1.3.3.1),
epm.
b = monitet background, eps.
3.
The calculated maximum setpoint, Smax in epm, corresponding to
~'
the dose rate limit is calculated using the following equation:
Smax = ((A*ST)(R11a - 8)) + B (1.7) where A
= dose rate allocation factor for the release point, dimensionless. The does rate allocation factors for release points are defined in approved plant procedures.
SF
= safety factor for the monitor, dimensionless. Safety factors for each monitor are defined in approved plant
(
procedures.
R11m
= the calculated monitor response, as calculated above, cym.
B
= the monitor background, cym.
- l 1.3.J.3 Wormal Default Seteoint I
A normal default setpoint is determined for each monitor. The default setpoints for each monitor are defined and documented in approved plant procedures. The default setpoints should be set high enough such that, in most cases,.the value will not need to be changed for each release. ~The default setpoints should be low enough, however..to ensure that the limite given in Section 1.2.1 are not violated, and to ensure that unexpected releases are identified.
.% c Reformatting / Repagination changes only 01441 I
E
SQW ODCM Revision 24 1.3.3.4 Actual Monitor setooints
(
The setpoint chosen for a monitor for each release is determined as follows:
1 1.
IF the calcu;;tv1 maximum setpoint is lhes than the normal default. TKi/ tht-setpoint shall be set equal to the c61culates miainta -'tpoint.
4 2.
IF the calculat<1 m >> mun setpoint is greater than the normal default, MG K1 Lin'es the expected monitor response is less than the oc". mal default setpoint THEN the setpoint shall be set equsi to tne normal default setpoint.
3.
IF the calculated maximus setpcint is' greater than the normal I
default, AND Il times the expected monitor response is greater than the normal default setpoint. THEN the setpoint.
j shall be set equal to Il times the expected response, i
1 I is an administrative factor designed to account for expected variations in monitor response. It will be defined in approved plant instructions.
i
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1 Reformatting / Repagination changes only og447 CPa%E]Qr? - Ed JidhhSsk*%3Tih$C'l
SQN ODCM Revision 24 page 12 of 156 1.4 DOSE - NOBLE CASES ^
(
1.4.1 REQUTRp;MENTS The sie dose due to noble gases released in gaseous affluents from each reactor unit to areas at er beyond the gITE SOUNDARY' (see R24
' Figure 1.3) shall be limited to the following:
a.
During any calendar quarter: Less than or equal to 5 arad for genua radiation and less than or equal to 10 arad for beta radiation and b.
During any calendar year: Less than or equal to 10 mrad for sanna radiation and less than or equal' to 20 arad for beta radiation.
This requirement is applicable at all times.
This requirement is provided to implement the requirements of sections II.B.III. A arl IV. A of Appendix I,10 CFR part 50. The requirement implements the guides set forth in section II.B of Appendix 1.
The action to be taken provide the required operating flexibility and at the same time implements the guides set forth in section IV. A of Appendix I to assure that the releases of radioactive material in gaseous of fluents will be kept "as low a reasonably achievable." The survelliance implements the requirements in section III. A of Appendix I that conformance with the guides of Appendix I be shown by
(
calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately modelod R24 L
pathways is unlikely to be substantially underestimated.
The dose calculations established in Section 1.4.2 for calculating the doses-due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the purposes of Evaluatina, Compliance with 10 CFR part 50 Appendix I," Revision 1, Octobar 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of caseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1. July 1977. The CDCM equations provided for detemining the air doses at the SITE BOUNDARY are based upon the R24 historical average atmospheric conditions.
If this requirement is not met, the following action will be performed:.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical specification 6.9.2, a special Report which identifiert the e:
01441
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SQN ODCN Revision 24 page 13 of 156 i
cause(s) for ancoeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
To ensure that this requirement is mots i
j Cmistive dose contributions for the surrent salendar quarter and j
current calendar year for noble gases shall be detemined in j
tecordance with the anthodology and parameters in Section 1.4.2 at least ente yet 31 days.
1 1.4.2 lMfVLATIVE 'J0SE CALCULATIONS - BOBLE GASES Doses tc be calculated are gasuna and beta air doses due to exposure to an infinite cloud of noble gases. These doses will be calculated at the land-site boundary location with the highest annual-average K/Q based on 1972-1975 meteorological data (Table 1.2).
This location is chosen from the SITE SOUNDARY locations listed in R24 Table 1.3.
Di9persion factors are calculated using the methodology described in Section 1.9.2.
No credit is taken for radioactive decay.
1.4.2.1 Cama dose to air The gama air dose D in mead, is calculated for each release y
using the following equation:
Dy = 1.9E-06 (K/Q) ! Qi Dr i T (1.8) y i
where:
1.9E-06 conversion factor, years per minute.
=
K/Q highest land-site boundary annual-average relative
=
I cc,ncentration 5.12x10-* s/m' (from Table 1.3).
l Qi a rolesee rate for nuclide i, pci/s.
Dr i y
dose conversion factor for external gema for nuclide i a
(Table 1.4), arad/yett per pCi/m,
i s
T
= duration of release, minutes.
l The sama-air dose calculated by this method will be used in the l
cumulative. dose calculations discussed in Section 1.4.2.3.
1 h *.
____ M V Ck*',6 fr)" n **dfk ",%%DW L
g
SQW ODCM Revision 24 Page 14 of 156 1.4.2.2 Beta dose to air l
The beta air dese. Dg in arad is calculated for each release using the following *quation:
Dg = 1.9E-06 (1/Q) ! Qi DFgi T (1.9) where:
1.9E-06. conversion f actor, years per minute.
1/9
. highest land-site bound 6ry annual-everage relative concentration. 5.12x10-* s/m' (from Table 1.3).
Qt
= release rate for nuclide 1, wCL/s.
Dr i dose conversion factor for arternal beta for nuclide 1 e
a arad/ year per wCi/me (from Table 1.4).
T
. duration of release, minutes.
The beta-air dose calculated by this method will be used in the cumulative dos 6 calculations discussed in Section 1.4.2.3.
i 1.i.2.3 Cueulative Dose - Noble Cas Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in Section 1.4.1.
For noble gases, cumulative doses are calculated for samaa and beta air doses. Doses due to each release are summed with the doser for
(
all previous release in the quarter or year to obtain cumulative quarterly and annual doses.
1.4.2.4 Comearison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance.
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.a Reformatting / Repagination changes only 01441
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0 se,*
SQN ODCM Revision 24 Page 15 of 156 1
1.5 CUNULATIVE Dost - f-131. I-133. TRITIUM AND RADIONUCLIDES TV I
PARTICVLATE.F0PM l
C 1.5.1 REQUIREMENTS l
The dose to a MEMBER OF THE PUBLIC from I-131, 1-133 Tritium and all R24 i
radionuclides in Particulate form with half-lives greater than 8 days a'
in gaseous offluents released to areas at er beyond the SITE ROUNDARY R24
^*
j (see Figure 1.3) shall be lialted to the following from each reactor l
unit
~
a.
During any calender quarter Less than er ogual to 7.5 s 9 to j
any organ and, i
i b.
During any calendar years Less than or equal to 15 area to any organ.
I This requirement is applicable at all times.
This requirement is yrovided to implement the requirements of Sections II.C.III.A and IV.A of Appendix I, 10 CFR part 50.
The requirement implements the guides set forth in Section II.C of Appendix I.
The estion to be taken provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will bo kept "as low as ressenably achievable."
i tection 1.5.2 calculational methods implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational pre.edures based on models and data such that the actual exposure of a NEM8tR OF THE PUBLIC through R24 i
appropriately modeled pathways is unlikely to be substantially underestimated. Section 1.5.2 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREC/CR-1004, "A Statistical Analysis of Selected Parsmeters for Predicting Food Chain Transport and Internal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CPR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. "Nothods for Estiasting Atmospheric Transport and Dispersion of Caseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1 July 19??. These equations also provide for determining the actual doses based upon the historical,everage atmospheric conditions. The release rate specifications.for I-131 I-133 tritium and all radionuclides in particulate fore with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the SITE BOUNDARY.
R24 The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides.
- p.
01441
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)
SQW CDCM Revision 24 page 16 of 156
- 2) deposition of radionuclides onto green leafy vegetation with subsequent consuniption by man, 3) deposition onto grassy areas where C
milk animals and meat producing animals graze with consumption of the milk an( seat by man, and 4) deposition on the ground with subsequent exposure of man.
l If this requirement is not met, perfom the following sction:
1 i
With the calculated dose from the release of I-131, 1-133 tritium and all radionuelides in particulate fem with half-lives exceeding 8 days, in gaseous effluents asceeding any of the above limits, prepare and submit to the commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which 4
l identifies the cause(s) for asceeding the 1 Lait (s) and defines the torrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
i
)
To ensure that this requirement is sett t'
Cumulative dose t ontributions for the current calendar quarter and current calendar year for 2-131, 1-133 tritium and all radionuclides.in particulate form with half-lives exceeding a days shall be detemined in accordance with the methodology and i
parameters in section 1.5.2 at least once per 31 days.
l
%4
..fo mattin.,,e,s.ina,1on e,an,es on1,
&26
'. MSh - 5N' DWE - ---
~
sQW oocM Revision 24
)
page 17 of 156 1.5.2 D0st DUE TO I-131. 1-133. TRITIUM AND At.L RADIONUCLIDES TV ggIICULATE FORM WITH MALF-LIVES OF GRF.ATER THAN 8 DAYS I
1.5.2.1 organ dose calculation 1
i Organ doses due to I-131, 1-133, tritium and all radionuclides in i
particulate form with half lives of greater than 8 days are calculated j
g for each release for the critical receptor. The critical receptor is defined as the land-site boundary in the sector with the highest l
annual average R/Q. The annual average X/Q and D/Q are calculated using the methodology in sections 1.9.2 and 1.9.3 using the historical 1972-1975 meteorological data (Table 1.2).
pathways considered to exist at this location are inhalation, ground plano 4
exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant). Dose factors for these age groups and pathways are calculated as described in Section 1.0.
For the I
ground exposure pathway, which has no age or organ specific dose i
factors, the total body dose will be added to the internal organ doses for all age groups.,No credit is taken for radioactive decay.
The general equation for the calculation of organ dose ist f
Dors = 3.173-08 T I I Rpt ( Wp Qi )
(1,10) ip where:
3.17E-08 = conversion factor, year /second T
= duration of release, seconds.
Rpt
= dose factor for pathway p for each identified nuclide i, l
s a -area / year per pC1/s for ground plane, grass-cow-milk, grass-cow-meat, and vegetation pathways, and arem/ year per pCL/m' for inhalation and tritium ingestion pathways, squations for calculating these dose facters are given in Section 1.8.
Wp dispersion factor for the location and pathway, a
1/Q for the inhalation a'nd tritium ingestion a
- pathways, 5.123-06 s/a'.
a D/Q for the food and ground plane pathways, 1.293-08 a-a
=
release rate for radionuclide i wC1/s Qi
=
From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The organ doses for the critical age group will be used in the eunulative doses discussed in section 1.5.2.2.
Reformatting / Repagination changes only
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J SQW CDCN Revision 24 l
1.5.2.2 Cumu1stive Doses age 8 of 156
(
Quarterly and annual suas of all doses are calculated for each.elease as desc0ibed below to compare to the limits listed in Section 1.5.1.
For maximum organ dose, cumulative quarterly and annual desas are maintained for each of the eight organs considered. The emulative dose is obtained by sununing the doses for each organ of the critical l
age group (as calculated in Section 1.5.2.1) as detonainevi for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of doses belonging to various age groups depending on the mix of radionuclides. The highest of these cumistive organ doses is used for the comparison to the limits described in Section 1.5.1.
1.5.2.3 Comcarison to Limits The cumulative calender quarter and calendar year doses are compared to their respective limits once per 31 days to detemine compliance.
1 i
i e:
Reformatting / Repagination changes only 01441 ge.ia: J).W ?' 1142. _
__ _ _____ __ ____ _ _ _. %, 7 L
i sQN ODeu Revision 24 page 19 of 156 1.6 CASE 0US RADWASTE TREATMENT 1.6.1 REQUIREMENTS The GAst0US RADWASTE TREATIRENT SYSTEM and the VENTILATION EEHAUST R24 TREATHENT SYSTEM shall be used to reduce radioactive asterials in R24 i
8
' gaseous waste prior to their discharge when the projected gaseous i
effluent doses due to gaseous effluent releases to areas at or beyond l
The SITE SOUNDARY (see pigure 1.3), when averaged over 31 days, would R24 encoed 0.2 arad per unit for gassna radiation, and 0.4 arad per unit i
for beta radiation. The appropriate portions of the VENTILATION R24 EEHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials 124 l
in gaseous waste prior to their discharge when the projected doses due to gaseous offluents to areas at er beyond the SITE 80UNDARY (see 124 a
pisure 1.3) when averaged over 31 days would exceed 0.3 area per unit j
to any organ.
This requirement is applicable at all times.
j This requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous offluents will be kept "as low as reasonably achievable." This requirement implementi the requirements of 10 CFR part 50.36a. General Design Criteria 60 of Appendix A to 4
10 CFR part 50, and the design objectives given 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 as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR part 50, for gaseous effluents.
If this requirement is not met, perform the following action l
With the gaseous waste being discharged without treatment for more than 31 days and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2 a special Report which includes the following info 3ations 1.
Identification of the inoperable equipment or subsystems and the reason for inoperability.
2.
Action (s) taken to restore the inoperable equipment'to OPERABLE status, and R24 3.
Bussnary description of action (s) taken to prevent a recurrence.
To ensure that this requirement is met:
Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in Section 1.6.2.
fs c 01441 1
0 l
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i 3
I SQW CDCM Revision 24 Page 20 of 156 1.6.2 DOSE. PROJECTIONS C
In accordance with &wction 1.6.1, dose projections will be performed.
This will be done by a.aintaining running 31-day tt.tals for the gamma
-l dese, the beta dose and the maxLaun organ dose. Once per 31 days, i
these 31-day running totals will be compared to the limits given in Section 1.6.1 to determine compliance.
If the projected doses exceed any of these limits, the Cast 005 R24 RADWASTE TREATMENT SYSTEM and the VtWTILATION EKMAUST TREATMENT SYSTEM R24 shall be used to reduce radioactive seterials in gaseous effluents to I
areas at or beyond the SITE 90VWDARY.
124 l
1.6.3 CASE 0VS PADWASTE TRtf'tMENT SYSTEM DESCRIPTIDW The CASE 0VS RADWASTE TREATMENT SYSTEM (CRTS) described below shall be R24 I
maintained and c,perated to keep releases ALARA.
A flow diagram for the CRTi is given in Figure 1.4.
The system convists of two waste-gas Ampressor packages, nine gas decay tanks,
- nd the associated piping, valves. and instrumentation. Gaseous wastes are received from the following desassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header, tnd boron recycle process operation.
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l SQW ODcM Revision 24 1.7 OUARTrtLY DOSE CALCULATIONS page 21 of 156
(<
A complete dose analysis utilising the total estimated gaseous releases for each calendar quarter will be performed and reported as required in gection 5.2.
Methodology for this analysis is that which is described in this section using the. quarterly release values reported by the plant personnel. All real pathways and receptor locations identified by the most recent land use survey are considered.
In addition, actual meteorological data representntive of a ground level release for each corresponding calendar quarter will be used. For iodine releases, it is assumed that half the iodine released is in organic form. Organic iodine causes a dose only by inhalation. For cow-milk and beef ingestion doses, the fraction of the time the animals are on stored food (identified in the survey) is used in the calculation.
The highest organ dose for a real receptor is determined by suming the dose contribution from all identified pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow and/or goat mi?.k ingestion (if a cow or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors).
1.7.1 EQBLE CAS - CAMMA AIR DOSE Camma air doses due to exposure to nob?
jasas D in area, are y
calculated using the following equati %.
Dy = Ala DFyl (l*11) where:
Kim
- concentration of nuclide i at location a, WC1/a8 Air concentrations are calculated as described by squation 1.16.
DTyt dose conv;rsion factor for external sama for nuclide i,
=
arad/ year per pci/a* (Table 1.4).
1.7.2 NOBLE CAS - BETA AIR DoSt Beta air doses due to exposure to noble gases Da in area, are calculated using the following equation:
Dg'e Xia DFgi (1.12)
.here Ala
- concentration of nuclide i at location a, pC1/a'. Air concentrations are calculated as described by Equation 1.16.
DF61
- dose conversion f actor for external beta for nuclide i, mead / year per WC1/me (Table 1.4).
Reformatting / Repagination changes only 01441 Il w m a e.s ts;. 4.":.
N
+
gQW 00cu Revision 24 page 22 of 156 1.7.3 RDJOIODINE. PARTICULATE AND TRITIUM - MAXINUM ORGAN DOSE organ doses due to radiolodine, particulate and tritium releases, Dorg in arem, are calculated using the following equation:
Dorg
- 3.173-08((K/Q)!RptQTIII /9)IRPi+(D g}p(x/Q)Rgg)Qt)
(1.13) R24 f
P i
p whoret 3.173-08 = conversion factor, year /second.
1/Q Relative concentration for location under consideration,
=
e s/m. Relative concentrations are calculated as described by squation 1.17.
Rpy ingestion dose factor for pathway p for tritium, e
as-area / year per WCi/s.
Ingestion pathways available for consideration are the same as those listed above for Rpi. squations for calculating ingestion dose factors for tritium are given in Sections 1.8.7 through 1.8.12.
QT
= adjusted release rate for tritium for location under consideration, wCi/s. Calculated in the same manner as Qi above.
Rpi ingestion dose f actor for pathway p for each identified e
nuclide 1 (except tritium), m8-area / year per WC1/s.
Ingestion pathways available for consideration includet pasture grass-cow-milk ingestion
(
stored feed-cow-milk ingestion pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in sections 1.8.1 through 1.4.6.
D/Q
. Relative deposition for location under consideration, i
a-a.
Relative deposition 'is calculated as described in squation 1.18.
RCi
= Dose factor for standing on contaminated ground, a8-area / year per wCi/s. The equation for calculating the ground plane dose factor is given in Section 1.8.14.
Rg1
= Inhalation dose factor, area / year per wCi/m8 The equation for calculating the inhalation dose factor is given in section 1.8.13.
D 01441 t
.g l
- Il
,A 4
4 gen - %
- ,I 9'
I sQu oDen Revision 24 page 23 of 156 i
Qt
= adjusted release rate for nuclide i for location under
(
consideration, WCi/s. The initial release rate is adjusted to secount for decay between the release point und the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equal to the actual release rate decayed g
for an average travel time during the period.
9 Qgo t f3 exp(-ki x/uj)
(1.14) j=1 where Qio
= initial average release rate for nuclide i over the period, WCi/s.
fj
= joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, i
expressed as a fraction.
I kt
= radiological decay constant for nuclide 1, s-1 x
= downwind distance, meters, uj a nidpoint value of wind speed class interval j, m/s.
1.7.4 POPUt.ATION DOSE),
For determining population doses to the 50-mile population around the
(
plant, each compass sector is broken down into elem4nts. These elements are defined in Table 1.7.
For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the x.idpoint of each sector element (see Table 1.7).
For population doses resulting from ingestion, it is conservatively assumed that',til food eaten by the average individual is grown locally.
The general equation used for calculating the population dose in a given sector element is pop = PI RATI0p
- P0pN
- ACg
- 0.001
- DOSEp (1.15)
Doso where RAT 10p
= ratio of average to maximum dose for pathway P.
(Average ingestion rates are obtained from Regulatory Guide 1.109, l
Table E-4.)
l e 0.5 for submersion and ground exposure pathways, a shielding / occupancy factor.
Reformatting / Repagination changes only l
/
01441 g n = N u e n niin v e s N L
_ x, -
a'
- h
o l
i SQW ODCM l
Revision 24 page 24 of 156 1.0 for the inhalation pathway.
=
l 0.515, 0.515. 0.5, and 0.355'for milk. for infant, child,
=
i ta'en and adult. respectively.
(It is assumed that the l
ratio of average to maximus infant milk ingestion rates is the same as that for child.)
i
{
1.0. 0.90. 0.91, 0.46 for beef ingestion, for infant,
=
child, teen and adult, respectively, i
i 1.0, 0.38. 0.38, 0.37 for vegetable ingestion, for infant,
=
child, toen and adult, respectively.
(It is assumed that the average individual sato no fresh leafy vegetables, only stored vegetables.)
POPN the population of the sector element, persons (Table 1.8).
=
i ACE
= fraction of the population belonging to each age group.
0.015, 0.168, 0.153, 0.665 for infant, child, teen and
=
adult, respectively (fractions taken from NUREG/CR-1004, l
Table 3.39).
0.001
= conversion from area to rom.
i DOSEp the dose for pathway p to the maximum individual at the a
location under consideration, mrom.
For ine,estion i
]
pathways, this dose is multiplied by an average decay i
correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as follows:
For milk and vegetables. ADC = exp(-A t) t where 11 decay constant for nuclide 1. seconds,
=
i
[
t distribution time for food product under consideration
=
l
(
(values from Regulatory Guide 1.109. Table D-1).
1.21t+06 seconds (14 days) for vegetables.
l
=
3.46t+05 seconde (4 days) for milk.
=
exp(-A t) K ti ch t
For meat. ADC
=
1 - exp(-k teb) i where Ai decay constant for nuclide 1, seconds, e
t
= additional distribution time for meat, over and above the time for slaughter to consumption described in Section 1.8.3, 7 days.
tcb
= time to consume a whole beef, as described in Section 1.8.3.
For be'ef ingestion, the additional factors in the calculation of ADC negate the integration of the dose ters over the period during which a whole beef is consumed. for the calculation of population dose. In other words, this assumes that the maximaa individual freeses and eats a whole beef, while the average individual buys smaller portions at a time.
[.d.*.
Reformatting / Repagination changes only ggg,g ll l
y D
I SQN ODCM Revision 24 page 25 of 156 C
population, doses are pusumed over all sector elements to obtain a total population dose for the 50-mile population.
A 1.7.5 REPORTING OF DOSES The calculated quarterly doses and calculated population doses described in this section are reported in the semi-Annual Effluent Release, Report submitted to the IfRC for the period ending December 31 d
of each year.
l l
5 4
i I
s-4 l
2.a u R8fo N tting/ Repagination changes only 01441
~
I 1
IJ * ' 7 M*f."&C*RM.:4',47".
.4 j
SQW ODCM Revision 24
(
page 26 of 156 1.3 g g tEAtts - Dose Factors a
1.8.1 PASTURE CRAIS-COW /00AT-MILE IBCERTION Dost FACTORS - Rept (m8-aren/ year per microcuries/second) f r(1-amp (-Agtep))
S y(1-owp(-k t )) I t
ib Rept.10*DrL e,V,p gQgerp(-1 t alf l i
r 1f p
+
1, x, y gg where:
los
= conversion factor, pleocurie/ microcurie.
Drliao ingestion dose conversion factor for nuclide 1 e
age group a ergan o, area /picoeurie (Table 1.9).
V a milk ingestion rate for age group a. liters / year.
ap ymi
- transfer factor for nuclide i from animal's feed to milk.
days / liter (Table 1.10).
Og animal's consumption rate, kg/ day.
a Kg a decay constant for nuclide i, seconds-a (Table 1.10).
tm transport time from milking to receptor, seconds.
f a
fp fraction of time animal opends on pasture, dimensionless.
a fraction of activity retained on pasture grass, r
a dimensionless.
ig a the effective decay constant, due to radioactive decay and weathering, seconds ** equal to At+k.
w A
a weathering decay constant for leaf and plant surfaces, w
seconds-1
(
t a
op time pasture is exposed to deposition, seconds.
Yp
= agricultural productivity by unit area of pasture grass, kg/m8 Bv transfer factor for nuclide i from soil to vegetation, i
=
picoeuries/kg (wat weight of vegetation) per picoeuries/kg (dry soil).
tb o time period over which accumulation on the ground is evaluated, seconds.
p
= effective surface density of soil kg/m'.
NOTE: yactors defined above which do not reference a table for their numerical values are given in Table 1.11.
1 Refomatting/ Repagination changes only.
01441
((
f t.c *
- dia, 2$$$ 'F.r.:xbv$ * '
SQN ODCN Revision 24 page 27 of 156 1.3.2 STORED Pttb-COW / COAT-MIt.K INCERTION Dott FACTORE - R C
CSi (m*-area / year per microcuries/second)
J (1-erp(-k t,g))
ie ACSi
- 10' DFL ao U Imi Qf fs arp(-k ti fm) _
i sp gq i
r(1-owp(-kgtest))
8 v(1-owp(-k t ))
1 ib
(-
+
)
Yst i t P11 i
where:
10' conversion factor, picoeurie/ microcurie.
=
DFL.,
ingestion dose conversion factor for nuclide 1, i
e age group a, organ o, aren/picoeurie (Table 1.9).
U,p
= milk ingestion rate for age group a, liters / year.
F,g transfer factor for nuclide i from animal's feed to milk, a
days / liter (Table 1.10).
Qg animal's consumption rate, kg/ day.
i
=
f,
= fraction of time animal spends on stored feed, dimensionless, ki decay constant for nuclida 1. seconds ** (Table 1.10).
e tfm
= transport time from milking to receptor, seconds, test
= time between harvest of stored feed and consumption by animal, seconds.
= fraction of activity retained on pasture grass, r
dimensionless.
kg the effective decay constant, due to radioactive decay ar.d
(
a weathering, seconds-1, equal to ki+K.
w kw
= weathering decay constant for leaf and plant surfaces, seconds-4 tesf time stored feed is exposed to deposition, seconds.
a Ygg agricultural productivity by unit area of stored, feed,
=
kg/m8 By transfer factor for nuclide i from soil to vegetation.
i a
picoeuries/kg (wet weight of vegetation) por picoeuries/kg (dry soil).
tb
= time period over which, accumulation on the ground is
(
evaluated, seconds.
l p
= effective surface density of soil, kg/m8 NOTtt Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
keformatting/ Repagination changes only M4 01441 (m
I ne. -
- . m;W:9W __-
A
4 i
i SQW CDCM Revision 24 page 28 of 156 i
1.s.3 LASTVPt. CRASS-BEEF INCESTION DOSE FACTORS - Rgpi (as-area / year per microcuries/second)
(1-owp(-k teb))
i I pi = 10' DFL ao Uns Fgt Qt owp(-k ts)
M i
i
, tg r(1-owp(-katep))
Biy(1-owp(-k t )) )
ib fl p
+
i Tp At F Al i
where 10'
= conversion f actor, picoeurie/ microcurie.
DrL e
= ingestion dose conversion factor for nuclide 1, i
age group a, organ o, ares /pisoturie (Table 1.9).
V.,
a meet ingestion rate for age group a, kg/ year.
Fri
= transfer factor for nuclide i from cow's feed to meat, days /kg (Table 1.10)~.
Og cow's consumption rate, kg/ day.
=
11 decay constant for nuclide i, seconds-1 (Table 1.10).
=
ted time for receptor to consume a whole beef, seconds.
a t
transport time from slaughter to consumer, seconds.
s
=
f
= fraction of time ecw spends on pasture, dimensionless, p
fraction of activity retained on pasture grass, r
a dimensionless.
Kg the effective decay constant, due to radioactive decay and
=
weathering, seconds-1, equal to Ki+k.
w I
K
= weathering decay constant for leaf and plant surfaces, w
seconds-1
(
t,p
= time pasture is owposed to deposition, seconds.
Y
= agricultural productivity by unit area of pasture stass, p
kg/m.
s By
= transfer factor for nuclide i from soil to vegetation, i
picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soil),
tb
= time over which accumulation on the ground is evaluated,
- seconds, p
= effective surface density of soil, kg/m*.
NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
Reformatting / Repagination changes only J.,. c 01441 I
((
N h ?. !.4 A W ; -
L Q ;>
y :., +
l l
sov ODCN l
Revision 24
(
1.8.4 STOPfD PttD-strF isctsTror Dost FACTORS - Rggg (n -ares / year por microcuries/second) a (1-4wp(-k teb))
i Ensi
- 108 DFL e, Van If1 Of 88p(-1 ts) i 1
qg (1-owP(-k test)) ( f(1-awp(-kgtest))
i 8 v(1-owp(-i t )))
1 tb a
+
gg g,,g y,g gg y gg i
where:
10'
= conversion factor, picoeurle/ microcurie.
I DFLgeo
= ingestion dose senversion factor for nuclide 1, age group a, organ o, area /picoeurie (Table 1.9).
U e meet ingestion rate for age group a, kg/ year.
na Pgt
. transfer factor for nuclide i from cow's feed to meat, dayc/kg (Table 1.10).
Og
= cow's consumption rate, kg/esy.
11
. doesy constant for nuclide i, seconds-1 (Table 1.10).
te t.
. time for receptor to consume a whole beef, seconds.
t a
g transport time from slaughter to consumer, seconds.
is fraction of time cow spends on stored feed, dimensionless.
teeg a time between harvest of stored feed and consumption by cow, seconds.
fraction of activity retained on pasture grass, i
r a
i dimensionless.
teng time stored feed is owposed to deposition, seconds.
a Yst
- agricultural productivity by unit area of stored feed, kg/m,
a K E
- the effective decay constant, due to radioactive decay and weathering, seconds-1, equal to kt + 1,.
k
= weathering decay constant for leaf and plant surfaces, w
seconds-a.
Sty
. transfer factor for nuclide i from soli to vegetation, picoeuries/kg (wat weight of vegetation) per picoeuries/kg (dry soil).
tb
- time over which accumulation on the ground is evaluated.
seconds.
p
. effective surface density of soil, kg/m.
s NOTE: Factors defined above Which do not reference a table for their numerical values are given in Table 1.11.
l l
Reformatting / Repagination changes only 01441 l
i
' w w.-u. : MwsMc
~
h G~
c
4 SQW CDCM Revision 24 page 30 of 156 C
1.0.$ FRESH LEAFY VECETABLE INCESTIDW DOSE FACTORS - R ri V
(m8-ares / year per microcuries/second)
R ri = 10' DrL., e(-k t e) UyLaf (r(1-e(-kgt.))
R v(1-e(-k t ))I i
ib V
t ih L
+
y, x, r At where:
10'
= conversion f actor, picoeurie/ microcurie.
DFL.,
= ingestion dose conversion factor for nuclide i, t
age group a, organ o, mren/picoeurie (Table 1.9).
Ki e doesy constant for nuclide i, seconds ** (Table 1.10).
te
- average time between harvest of vegetables and their h
consumption and/or storage, seconds.
Urt.
= consumption rate of fresh leafy vegetables by the receptor in age group a, kg/ year.
ft
= fraction of fresh leafy vegetables grown locally, dimensionless.
fraction of deposited activity retained on vegetables.
r a
l dimensionless.
KE
= the effective decay constant, due to radioactive decay and weathering, seconds-1
=ki + A, k
= decay constant for removal of activity on leaf and plant w
surfaces by weathering, seconds-4 t,
= orposure time in garden for fresh leafy and/or stored l
vegetables, seconds.
Yr
= agricultural yield for fresh leafy vegetables, kg/m,
s Bv
= transfer factor for nuclide i from soil to vegetables, i
picoeuries/kg (wet weight of vegetation) per picocuries/kg (dry soil).
tb
- time period over which accumulation on the ground is evaluated, seconds.
p
= effective surface density of soil, kg/m8 NOTE: rectors defined above which do not reference a table for their numerical values are given in' Table 1.11.
l l
Refomatting/Repetination changes only 01441
, W$$Y: LRW'.W.O.-
3 __-_ _. W o:: '$.n; 4
i SQW CDCN i
Revision 24 page 31 of 156 C
1.0.6 IIstDp_IMEIARLLIMMIION DOSE TACTORS - Rygt at-erea/ year per microcuries/second)
(1-e(-A tsv))
t Rygg = 10' DFL ao *NP(~k t e) Uggfg i
ih y
I
{r(1-e(-kate)) + 8 v(1-*(-l t )))
1 ib
)
Y,y At Pki where:
10'
= conversion factor, picoeurio/ microcurie.
ingestion dose conversion factor for nuclide 1 DFL.,
e t
age group a organ o, meen/picoeurie (Table 1.9).
decay constant for nuclide i, secondo-a (Table 1.10).
kg
=
te
= average time between harvest of vegetables and their h
consumption and/or storage, seconds.
consumption rate of stored vegetables by the receptor in Us, a
age group a. kg/ year.
fraction of stored vegetables grown locally, dimensionless.
f
=
g time between storage of vegetables and their consumption.
t,y
=
i seconds.
r
= fraction of deposited activity retained on vegetables, dimensionless.
the effective decay constant, due to radioactive decay and KE
=
weathering, seconds-1
(
kg + kw
=
decay constant for removal of activity on leaf and plant kw
=
surfaces by weathering, seconds-a, exposure time in garden for fresh leafy and/or stored t,
=
vegetables, seconds.
i agricultural yield for stored vegetables, kg/m*.
Ysv
=
transfer factor for nuclide i from soil to vegetables, giv
=
picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soil).
time period over which accumulation on the ground is tb
=
evaluated, seconds.
effective surface density of soil 'kg/a*.
p
=
NOTE Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
l Reformatting / Repagination changes only 01441
((
2
-h
- I
.M 7
Y y.*
b SQW ODCN Revision 24 j
Page 32 of 156 1.8.7 TRITIUM-PARTVRE CRASS-COW / COAT-MILK DOSE FACTOR - R C
CTP l
(area / year per microcuries/a8)
RCTP = 108 10* DFL;.. Fat Of Usp [0.75(0.5/H)) fp exp(-k tT fa) where 108
= conversion factor, st*sms/kg.
l 108
= conversion f actor, picoeuries/microcuries.
DFLy..
= ingestion dose conversion factor for tritium for age group a, organ o, mres/picoeurie (Table 1.9).
FmT
= transfer factor for tritium from animal's feed to milk, days / liter (Table 1.10).
Og animal's consumption rate, kg/ day.
=
U.,5 e allk ingestion rate for age group a liters / year.
0.7 the fraction of total feed that is water.
=
0.5 the ratio of the specific activity of the feed grass water
=
to the atmospheric water.
H
= absolute humidity of the atmosphere, g/m8 f
=
p fraction of time animal spends on pasture, dimensionless.
kr decay constant for tritium, seconds-1 (Table 1.10).
=
tfm transport time from milking to receptor, seconds.
a NOTg: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
1
'l J
l i
Reformatting / Repagination changes only
~*4 01441 t
(
4 1
-25cqt.c.ia mus.*z s wim._
~~
)
(
page 33 of 156 1.8.8 TRITTUM-STORED FttD-COW / COAT-MILK DOSE FACTOR - RCTS (mes.a/ year per microcuries/me)
Uap 10.75(0.5/H)) fs (1-e#p(-k tT egg))
l RCTS = 108 105 DFL ao FmT Of T
- P(*k tT im) qg where:
los conversion factor, grams /kg.
e 108
= conversion factor, picoeuries/microcuries.
DFLTao
" ingestion dose conversion factor for tritium for age group a, organ o, area /picoeurie (Table 1.9).
F,7
= transfer factor for tritium from animal's food to milk.
days / liter (Table 1.10).
Qg
= animal's consumption rate, kg/ day.
Up
= milk ingestion rate for age group a liters / year.
0.75 the fraction of total food that is water.
=
0.5
= the ratio of the specific activity of the feed grass water to the atmospheric water.
H
= absolute humidity of the atmosphere, g/m.
8 f,
fraction of time animal spends on stored feed,
=
dimensionless.
k decay constant for tritium, seconds-1 (Table 1.10).
T e
teeg time between harvest of stored feed and consumption by
=
animal, seconds, tfm
- transport time from allking to receptor, seconds, i
WOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
ea Reformatting / Repagination changes only 01441
/
\\s m qu 4.,-;v0 M ' 6.+.6: E 4 s J'MW J
sou opes Revision 24 1.g.9 TRITTUM-PARTURE crass-sttr Dost FACTOR - Rg7 page 34 of 156 (area / year per microcuries/sts n ;p = 108 10' DFLyo, Fff Of Van to.73(0.5/M)) fp exp(-k ts) n T
(1-owp(-k ley))
(1-emp(-k tT eb))
f where:
- T "*P AT teb 108
= conversion factor, grams /kg.
10'
= conversion factor, picoeuries/microcuries.
- DFLyo,
= ingestion dose conversion f actor for M-3 for age group a, organ o. aroa/picoeurie (Table 1.9).
Pff
- transfer factor for N-3 from cow's feed to meat, days /kg (Table 1.10).
Qg
= cow's consumption rate, kg/ day.
U
- meat ingestion rate for age group a. kg/ year.
am 0.75
= the fraction of total food that is water.
0.5
= the ratio of the specific activity of the feed grass water to the atmospheric water.
H absolute humidity of the atmosphere, g/m,
=
e fp fraction of time cow spends on pasture dimensionless.
=
kg
= decay constant for tritium, seconds-1 (Table 1.10).
i t
transport time from slaughter to consumer, seconds, s
a t,p time pasture is owposed to deposition, seconds.
=
tcb
= time for receptor to consume a whole beef, seconds.
NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
l Reformatting / Repagination changes only 4
01441 i
L IL mam.a,unmu.
i.w.-
i
.l sov 00cu Revision 24 page 35 of 156 1.3.10 TRTTIUM-2TORED PttD-Sttr Dost FACTOR - R NTS l
(area / year per microcuries/me)
RNTS = 108 105 DFLTao Fff Of Van (0.75(0.5/H)) f, exp(- h t )
(1-emp(-k hep))
(1**"P(*A heb))
T T
t where:
AT tcp kT teb 10'
= conversion factor, grams /kg.
10' e conversion factor, picoeuries/microcuries.
)
DFL eo ingestion dose conversion factor for H-3 for age group a, T
e organ o, nrea/picoeurie (Table 1.9).
Fff a transfer factor for N-3 from cow's food to meat, days /kg (Table 1.10).
Og
= cow's consumption rate, kg/ day.
i U
- meat ingestion rate for age group a, kg/ year.
se 0.75
= the fra. tion of total feed that is water, j
0.5
= the ratio of the specific activity of the food grass water to the atmospheric water.
H
= absolute humidity of the atmosphere, s/m,
e fs
= fraction of time cow spends on stored feed, dimensionless.
tT
= decay constant for tritiuse, seconds-1 (Table 1.10).
ts
= transport time from slaughter to consumer, seconds, top
= time pasture is exposed to deposition, seconds.
teb
= time for receptor to consume a whole beef, seconds.
(
NOTE! Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
\\
- a Reformatting / Repagination changes only 01441
^
1...
"~~
^
-.~
I l-i 30W CDen gevision 24
(
page 36 of 156 1.g.11 TRITWM-FRERN LgAFY YtCETnt.22 Dost FACTOR - RYTF (area / year per microcuries/as) a fF
- 108 los DrLg., to.75(0.5/N)) U,a f. *NP(*k tT he) l v
FI t
where:
10'
= conversion factor, grams /kg.
10'
= conversion factor, picoeuries/alerocuries.
DN,
e ingestion dose conversion factor for tritium for age group a, organ o, area /picoeurie (Table 1.9).
0.75 the fraction of total vegetation that is water.
=
0.5
= the ratio of the specific activity of the vegetables water to the stasepherie wetsr.
l H
= absolute humidity of the staoephere, g/n,
e Vy.,.
consumption rate of fresh leafy vegetables by the receptor
=
in age group a, kg/ year.
f.
fraction of fresh leafy vegetables grown locally, t
dimensionless, 1
decay constant for tritium, seconds ** (Table 1.10).
7
=
the a time between harvest of vegetables and their consumption j
and/or storage, seconds.
I NOTE: Factors defined above which do not reference a table for their i
numerical values are given in Table 1.11.
l i
.% c Reformatting / Repagination changes only 01H1 1
.4i WZE.h*.RisWC A$$'.'d' n L *..:. A
iib E'" ' *
- A
- 4 M,
-- - ' ~
=
SQW ODCM Revision 24
(
page 37 of 156 1.8.12 Tritium-s?0 RED vtetTABLt3 D0tt FACTOR - RYTS (aren/ year por microcuries/me)
(1-exp(-k tsv))
T RYTS = los los pyL ao 10.75(0.5/H)) Usafs qg T
orp(-kyt e) h where:
10'
= conversion factor, grams /kg.
10' e conversion factor, picoeuries/microcuries.
DFLTao
- ingestion dose conversion factor for tritium for age group a, organ o, aren/picoeurie (Table 1.9).
0.75 the fraction of total vegetation that is water.
1 0.5 e the ratio of the specific activity of the vegetation water to the atmospheric water.
H
. absolute humidity of the atmosphere, s/m,
e U
consumption rate of stored vegetables by the receptor in e
Sa age group a, kg/ year.
fg fraction of stored vegetables grown locally, dimensionless.
=
kr
= decay constant for tritium, seconds-1 (Table 1.10).
time between harvest of stored vegetables and their toy 6
consumption and/or storage, seconds.
the time between harvest of vegetables and their storage,
=
seconds.
NOTE: yactors defined above which do not reference a table for their
(
numerical values are given in Table 1.11.
l l
Reformatting / Repagination changes only 01441 l
l 4
..me k? - *
- s
- u
- ' '* 5 * * &
e e
SQW ODCM Revision 24 page 38 of 156
(
1.8.13 ImiA1.ATION DOSE FACTORS-Rgg (area / year per microcuries/m )
e 108 Rgt = DFAiso 884 wheret inhalation dose conversion factor for nuclide 1, DFA n, i
e age group a and organ o, ares /picoeurie (Table 1.12).
bra
= breathing rate for ass group a, a8/ year (Table 1.11).
10e
= conversion fustor, picoeurio/ microcurie.
1.8.14 CROUND pt.ANE DOSE FACTORS - Rgt (m -area / year per altrocuries/second) a RCi " DFCio 1/kg 108 8760 (1 - exp(-A t ))
tb wheret DFCio dose conversion factor for standing on contaminated ground a
for nuclide i and organ o (total body and skin), arem/hr per picoeurle/a8 (Table 1.13).
11 e decay constant of nuclide i, seconds ** (Table 1.10).
los conversion factor, picoeurie/ microcurie.
=
4760 conversion factor, hours / year.
=
tb
. time period over which the ground accumulation is evaluated.
(
seconds (Table 1.11).
i Reformatting / Repagination changes only 01441 1
1 I'
gm.m "Qu=
rew.2,
+
..wa w tw i n J d
SQN ODCM Revision 24 1.9 DISPERSION METHOD 01.0CY page 39 of 156 Dispersion factors are calculated for radioactive effluent releases using hourly everose meteorological data consisting of wind speed and direction measurements at 10m and temperature teessurements at to and 46m.
A sector-average dispersion equation consistent with Regulatory cuide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 1.5), and building wake effects.
Terrain effects en dispersion are not considered.
Hourly average meteorological data are empressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability. The joint-frequency distribution which represents the historical meteorological data for the period January 1972 to December 1975 is given in Table 1.2.
The wind speed classes that are used are as follows:
Number Rante (a/s)
Midsoint (m/s) 1
<0.3 0.13 2
0.3-0.6 0.45 3
0.7-1.5 1.10 4
1.6-2.4 1.99
)
5 2.5-3.3 2.sg
(
6 3.4-5.5 4.45 7
5.6-3.2 6.91 8
8.3-10.9 9.59 9
>10.9 10.95 The stability classes that will be used att the standard A through C classifications. The stability classes 1-7 will correspond to A=1, 8 2,.... Ca?.
1.9.1 AIR CONCENTRATION - t ( yC1/m')
Air concentrations of nuclides at downwind locations are calculated using the following equation xi e I I (2/s)s/s Uk II P emp(-Ag x/uj)
(1.16) jel kel tag u3 (2ew/n) where fjk
- joint relative frequency of occurrence of winds in windipeed class j, stability class k, blowing toward this exposure point, orpressed as a fraction.
Refomatting/ Repagination changes only og4gg
- ..., a.@ M h t.-
- ~ _ - - - _ _ _ - - _ - _ - - -. -
i j
j gou ODcM Revision 24
(
pass 40 of 156 gg
= average annual release rate of radionuclide 1, vCi/s.
p
= fraction of radionuclide remaining in plume (Figure 1.5).
tak
= vertical dispersion coefficient for stability class k which includes a building wake adjustment.
l
= (ejk + CA/')"#8, I
or = v3 e k, whichever is smaller.
s where e g is the vertical dispersion coefficient for stability g
class k (a) (Figure 1.6),
e is a building shape factor (c=0.5),
A is the mintaus building cross-sectional area (1800 a8).
i uj
= miepoint value of wind speed class interval j, m/s.
m
= downwind distance, s.
n
= number of sectors, 16.
11
= radioactive decay coefficient t.
radionuclide 1 s-1 2vz/n
= sector width at point of interest, m.
1.9.2 RELATIVE CONCENTRAff0N - t/0 (sec/a8)
Relative concentrations of nuclides at downwind locations are calculated using the following equation:
9 7
A/Q
=I I (2/v)1/8 3
(1.17) jel k=1 Isk uj (2rx/n) where
(
fjk
= joint relative frequency of occurrence of win % iti eir.4;pesa class j, stability class k, blowing toward this exposure point, expressed as a fraction.
(
!sk
= vertical dispersion coefficient for stability class k which includes a building wake adjustment.
i
= (ejk + CA#')*#8' or = v3 e k, whichever is smaller.
s where ek is the vertical dispe,rsion coefficient for stability s
class k (a) (Figure 1.6),
e is a building shape factor (c=0.5),
A is the minimum building cross-sectional area (1800 a8).
uj
= midpoint value of wind speed class interval j, s/s.
x
= downwind distance, m.
n
= number of sectors, 16.
2rx/n
= sector width at point of interest, m.
Refomatting/Repsgination changes only 01441 L
I i
.. $k NMMN
$W%.
f 5.R: lA?&$Lc" _s.__.__._:We___b,
. a
- -.. ~ _. _ -
SQN ODCM Revision 24 page 41 of 156 1.9.3 RELATIVE DEPOSITION-D/0 (m*8)
Relative deposition of nuclides at downwind locations is calculated using ths following equation:
9 7
fjk DR I
I (1.1a)
D/0 =j=l k=1 (2n/n) where ik
- joint relative frequency of occurrence of winds in windspeed class j en4 ntability class k, blowing toward this exposure point, expressed as a fraction.
DR
= relative deposition rate, a-*
(from Figure 1.7).
x
. downwind dist.ance, m.-
n a number of sectors, 16.
2rx/n a sector width at point of-interest, m.
f(
l l
.'.* c Reformatting / Repagination changes only 01441 i
4
$.'" '%ffARE
_?,
Y ?_ Q,..., =
... L%ta:. bdd% fu':,
. f. ;..
.k
- - - - ~ -. - -
L 3
(.
l l
SQN ODCM Revision 24 page 42 of 156 2.0 LIQUID EFTLURWTS l
2.1 RELEASE p01RTS There are four systems from which liquid ef fluents are released to the environment. These are the Liquid Radweste System, the Condensate Domineraliser System, the Turbine Building Sump, and the Units 1 and 2 Steam Generator 310wdown. Figure 2.1 provides an outline of the liquid release paths and discharge points with associated flow rates and radiation monitors.
All liquid effluents are ultimately sischarged to the Diffuser pond which roles.ses to the Tennessee River. The gesential Raw Cooling Water (ERCW) provides dilution for liquid ef fluents at a minimum flow rate of 15,000 syn. ERCW flow is monitored by radiation monitors 0-RM.133. -134. -140, -141.
The inlet of the Diffuser pond is monitored by radiation monitor 0-RM-90-211.
Liculd'Radwaste System j
The Liquid Radwaste System processes liquid from the Reactor Building and Auxiliary Building Floor Drains and the laundry / hot shower and chemical drain tanks. Figure 2.2 provides a schematic of the Liquid I
Radweste System, showing the liquid pathways, flow rate and radiation monitors. The normal release points for liquid rad inste are the Monitor Tank and the cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is released' routinely at a flow rate of 125 spm. The CDCT has a capacity of 15,000 gal and is also released routinely at a flow rate of 125 spm. The Monitor Tank and CDC discharge to the Cooling Tower Blowdown (CTBD) line as a batch release and are monitored by radiation monitor 0-RM-90-122.
Condensate Domineralizar System The Condensate Domineraliser System processes liquid wastes coming from the High Crud Tanks-(HCT-1 and -2), the Neutralisation Tank, and the Non-Reclaimable Waste Tank (NRWT). The HCTs have a capacity of 20,000 gal and a maximum discharge' flow rate of.245 spm. The Neutralization Tank has a capacity of 19,000 gal and a maximus discharge flow rate of 245 gym. The NRWT has a capacity of 11,000 gal and a maximum discharge flow rate of 245 spa.. The Condensate Domineraliser System is routinely released to the CTBD line and is j
monitored by radiation monitor 0-RM-90-225.
Turbine Buildina sumo The Turbine Building Sump (TSS) normally releases to the Low Volume Weste Treetaent pond (LVWTP) but can be released to the-Yard pond.
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A-----
A^
" ^ ~ *
~
^ ' - -
a
SQW ODCM Revision 24 C
page 43 of 156 The TBS has a capacity of 30,000 gal and a design discharge release rate of 1,750 spa per pump. TBS releases are monitored by radiation monitor 0-RN-90-212.
Steam Generator Blo g The Steam Generator Slowdown (SCBD) is processed-in the steam Generator Draindown Flash Tanks or SCBD Heat Exchangers. The SGBD discharge has s'anximum flow rate of 40 spa per steam generator. SG8D discharges to the CTBD line are continuous and are monitored by radiation monitors (1) (2)-BM-90-120. -121.
l r.
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.QEggagly"%i1gj%+:
. al= '% UW
1 SQW ODCM Revision 24 Page 44 of 156 C
2.2 CONCENTRATION 2.2.1 REOUIREMENTS The concentration of radioactive material released to UNRESTRICTED R24 ARIAS (see Figure-1.3) shall be lialted to the concentrations R24 specified in 10 CFR Part 20 Appendix 3. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases..For dissolved or entrained noble gases, the concentration shall be limited to 2210** alcrocuries/a1 total activity.-
This requirement is' applicable at all times.
This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to' i
UNRESTRICTED AREAS will be less than the concentration levels R24 specifled 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 in UWRESTRICTED AREAS will R24 result in exposures within (1) the Section II. A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC and (2) the limits of R24 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Ie-135 is the controlling radioisotope and its MPC in air (submersion) was converted' to an equivalent concentration in water using the methods described in Int:<s. 'inal Conunission of Radiological Protection (ICRP) Publi L
e.
(
If this req"irement la..,
the following action will be performed:
With the concentration of radioactive material released to UNRESTRICTED AREAS axceeding the above lialts, without delay, R24 restore the concentration to within the above lialts.
To ensure that this requirement is sett Radioactive liquid wastes shall be sampled and analysed according to the sampling and analysis pr'ogram of Table 2.1 and The results of the radioactivity analysis shall be used in accordance with the methods in Section 2.2.2 to assure that the concentration at the point of release is maintained within the limits stated above.
I a-01441 L
j MMgMjitM2%dtr* %
N & E C
SQW 0DCM Revision 24 page 45 of 156 2.2.2 MPC-SUM OF THE RATIOS C
The sua of the ratios (R ) for each release point will be calculated J
by the following relationship.
Ct Rj =
gpg -
(2.1).
where RJ
= the sum of-the ratios for release point j.
WCg the Nec of r.sdionuclide 1, as specified in Section 2.2.1, a
yCi/mL.
Ci
. concentration of radionuclide 1, yC1/mL.
The sum of the NPC ratios must be i 1 due to the releases from any or all of the release points described above.
The following relationship is used to ensure that this criterion is met fgR1+fR23+fR33+fR44 (2.2).
RTBS +
1 1.0 F
where
(
RTBS
= sum of the ratios of the turbine building sump as determined by equation 2.1.
f.f *f *f4 = effluent flow rate for radweste, condensate t 2 3 domineraliser system and each of the steam generators, respectively, gym.
R,R,R,R4 = sum of ratios for radweste, condensate 1 2 3 domineraliser system and each of the steam generators, respectively, as determined by equation 2.1.
F e mininum dilution flow rate for CTBD,15,000 gym.
Reformatting /Repsginetion changes only
.'764 01441 L
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-- 2 <- Q n -
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'14'*7* *!
'8
l SQN ODCM Revision 24-page 46 of 156 2.3 RADI0 ACTIVE LIOUID EFFLUENT MONITORINC INSTRUMENTATION 2.3.1 RE0VIREMENTS The radioactive liquid' effluent monitoring instrumentation channels shown in Table 2.2 shall be OPERABLE with their alarm / trip setpoints R24 set to ensure that the lialts of Section 2.2.1 are not exceeded. The
'alare/ trip setpoints of these channels shall'be determined in l
I accordance with the methodology and parameters in section 2.3.3.
This requirement is applicable during all releases via these pathways.
The radioactive liquid effluent instrumentation is provided to monitor.
l and control, as applicable, the releases of radioactive materials in liquid offluents during actual or potential releases of liquid offluents. The alare/ trip setpointe for these instruments shall be i
calculated in accordance with the procedures in Section 2.3.3 to -
ensure -that the alara/ trip will occur prior te exceeding the limits of.
10 CFR part 20.
The OPERABILITY and use of this instrumentation is R24 consistent with the requirements of General Design criteria 60, 63, and 64 of Appendix A to 10 CFR part 30.
If this requirement is not met, the appropriate following action (s) will be performed; s.
With a radioactive liquid effluent monitoring instivaentation channel alars/ trip setpoint less conservative than required above, t
without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inopers' ole, or change the setpoint so that it is acceptably conservative, i
b.
With less than the minianen number of radioactive liquid offluent monitoring instrumentation channels OptRABLE, take the action R24 shown in Table 2.2.
Exert best effort to return the instruments to OptRABLE status within 30 days and, if unsuccessful, explain in R24 the next Seal-Annual Rffluent Release Report why the inoperability could not be corrected within 30 days.
To ensure that this requirement is met:
Each radioactive liquid offluent monitoring channel shall be demonstrated OpKRABLE by performance of the CHANNEL CHECK, CHANNEL R24 CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the R24 frequencies shown in Table 2.3.
1
,M 01441 M W J4 % 2*tfc N v w c::e
,,4..
SQW CDCM Revision 24 page 47 of 156 2.3.2 Rg y.SE SAMPLUfg Radweste tanks will be recirculated through two volume changes prior to aampling to ensure that a representative sample is obtained. The i
condensate domineraliser waste evaporator blowdown tanks cannot be recirculated. However, the contents will be transferred to the waste-distillate tanks prior to release.
Condensate domineraliser tanks are routinely continuously releaseda
.I and ut111:e a composite sampler to obtain a representative saarple while being discharged.. In the event of an inoperable effluent radiation monitor or composite sampler, a two volume recirculation and two independent samples and analyses will be performed. Releases from the steam generator blowdown and turbine building sump a are considered continuous and grab sampled daily.
prior to a batch release, a grab sample will be taken and analysed to determine the concentration, yci/m1, of each gansna-emitting nuclide. For continuous releases, daily grab or composite samples will be taken and analysed to determine the concentration, pCi/m1, of each ganuna-emitting nuclide nuclide. Composite samples are maintained (as required by 'lable 2.1) to determine the concentration of certain nuclides (H-3, Fe-55, Sr-89, Sr-90, and alpha emitters).
For those nuclides whose activities are determined from composite samples (i.e. Sr-89, Sr-90, Fe-55 and H-3) the concentrations for the.
previous, composite period will be assumed as the cencontration for the
(
next period to perform the calculations in Sections 2.2, 2.3, 2.4 and 2.5.
The actual measured concentrations will be used for the dose calculations described in Section 2.6.
a Sampling requirements for those release points are applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of s 18-06 vC17mr and allowing for background radiation during periods when primary to secondary leakage is occurring.
sa Reformatting / Repagination changes only 01441 I
F_ Z **/ M4;EMMXW.;
M 3 Nh"~
pate 48 of 156 2.3.3 XFSTRUMEFT 3 ETPOINTS Liquid effluent monitor setpoints are detemined to ensure that the concentration of radioactive material released at any. time from the site to UVRESTRICTED AREAS does not exceed the NPC limits referenced R24 in Section 2.2.1.
2.3.3.1 ggp,ggted Monitor Resoonse For each release, the expected monitor response, R in epm, is calculated using the following equation:
R = B + 2 Effi*C1 (2.3)
I where B
= monitor background, cym.
Effi
= monitor ef ficiency for nuclide 1, cpm per WC1/cc.
Ci
= tank concentration of nuclide i, WCi/cc.
2.3.3.2 Calculated Maximum Monitor Setcoint For each release from a release point, a setpoint is calculated for the appropriate monitor which corresponds to the MPC limit for that
- release, j
The calculated maximum monitor setpoint, S in epm, is given by max the following equation i
Smax = (SAF*(R - B))'+ B (2.4) where SAF
= setpoint adjustment factor as calculated below.
R
= expected monitor response, cym, as calculated by equation 2.3-in Section 2.3.3.1..
B
= background, cym.
Setcoint Adiustment Factor - SAF The SAF is detemined by calculating,the required dilution factor for the waste stream which will ensure that the MPC limits are met at the UVRESTRICTED AREA boundary. If no dilution is required, then there is R24 no need for a BAF.
If dilution is required to meet the MPC limits, l
the SAF adjusts the monitor to account for any additional dilution over the required amount. The methodology for determining the SAF is given below.
l l
l
? a s' 01441
,L f
a g
V sQW ODCu Revision 24
(
page 49 of 156 1.
A required dilution factor. DF is calculated using the
-l r
following equation:
R3 I
DFr=
(2.5)'
sF where
.c.
RJ sum of the NPC ratios for release point j as calculated in e
section 2.2.2.
sF a safety factor for the monitor.
2.
The following criteria will be applie3 to the required dilution factor to determine the sAF i
A.
If the required dilution factor DFr is less than or equal to 1 then the sAF = 0.
B.
If the required dilution factor DF.. is greater than 1 sAF r
is calculated using the following equation. This accounts for-the downstream dilution of the waste flow over and above the required dilution.
i 1
DFr where 1
(
DF e the required dilution factor as calculated above.
r Dr
= the actual dilution factor, calculated using the j
a following equation:
l FLOWw + ( A e FLOW il )
d DFa" (2.6)
FLOWw where FLOW
= flow of waste stream, gym.
w FLOWdil
. flow of the dilution stream, gym.
A
= fraction of dil'ition flow allocated to this release point. For the TBS, this fraction is sero. The fractions for the remaining 4 release points are defined as the ratio of the allocated minimum CTBD flow for that release point to the.
total minimum CTBD flow. The minimum CTBD flow allocation for these release points is as follows; i
Radweste 9000 spa Condensate domineraliser-3000 gym steam generator blow down (U1) 1500 gym steam generator blow down (U2) 1500 spa Reformatting / Repagination changes only ac OW
~
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page 50 of 156 C
2.3.3.3 Normal Default Setooint A normal default setpoint may be determined for each monitor. A def ault setpoint for a monitor will be defined and documented in-
=
approved plant procedures. A default setpoint should be low enough to l'
ensure that concentration limits defined in Section 2.2.1 are not violated and to ensure that unexpected releases are identified.
2.3.3.4 Actual Monitor Setooints i
l The maximum calculated monitor setpoint is determined for each monitor using the methodology in Section 2.3.3.2.
The default setpoint is defined in Section 2.3.3.3.
The monitor setpoint for the release is detennined as described below.
The setpoint chosen for a monitor for each release is determined as follows:
1.
IF the calculated maximum setpoint is less than the normal-def ault, THEN the setpoint shall be set equal to the calculated maximaan setpoint.
2.
IF the calculated maximum setpoint is greater than the normal default, AND X1 times the expected monitor response is less than the normal def ault setpoint THEN the setpoint shall be set equal to the normal glefault setpoint.
l 3.
IF the calculated maximum setpoint is greater than the normal default, AND X1 times the expected monitor response is l
greater than the normal def ault setpoint, THEN the setpoint shall be set equal to It times the expected response.
'l l
I is an administrative factor designed to account for expected varir.tions in monitor response.
It will be defined in approved plant instructions.
Reformatting / Repagination changes only
[
01441
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'O'
' 9 b
- - - - - - - - - - - ^ - ^ ^ ^ - - - - - - "
E.
b SQW CDCM Revision 24 Page 51 of 156 2.3.4 Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in section 2.2.1 were not exceeded.
1 A composite list of concentrations (C ), by isotope, will be used t
with the actual waste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.2 to
-demonstrate compliance with.the limits in section 2.2.1.
This data
.{
and setpoints will be recorded in auditable records by plant personnel.
l l
l e
l r
i l
l l
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- - - : 'm " '
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SQW ODcM Revision 24 page $2 of 156 2.4 pgH.
2.4.1 REQUIR MENTS The dose or dose commitment to a MEMBER OF THE PUBLIC from R24 radioactive materials in liquid effluents released to UNRESTRICTED R24 AREAS shall be limited from each reactor unit Rf4 a.
During any calendar quarter to less than or equal to 1.5 aren to the total body and to less than or equal to 5 arem to any organ, and b.
During any calendar year to less than or equal to a area to the total body and to less-than or equal to 10 arem to any organ.
This requirement is applicable at all times.
This requirement is provided to implement the requirements of Sections II. A. III. A. and IV. A of Appendix I,10 CFR Part 50.
The requirement implements the guide 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 materials in liquid effluents will be kept "as low as reasonable schievable."
Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in
(
radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in this section implement the requirements in Section III.A of Appendix I that confotinance with the guides of Appendix I be shown_by calculational procedures based on models and data,' such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately R24 modeled pathways is unlikely to substantially underestimated._ The equations specified in this section for calculating the doses due to the actual release rates of radioactive materials in liquid affluents -
are-consistent with the methodology, provided in Regulatory Cuide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Etfluents for the Purposes of Evaluating Compliance with 10 CFR Part 50 Appendix I," Revision 1, October 1977 and Regulatory Guide ~1.113 "gstinating Aquatic Dispersion of Effluents from-Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This requirement applies to the release of liquid effluents from each reactor-at the site. For units with shared redweste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing that system.
sa 01441 4
i A4C69.w y? MM$m9hnM.fdW b
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[.
SQN CDCM Ravision 24-page 53 of 156 C
If this requirement is not met, the following action will be performed:.
i Eth the calculated dose from the release of radioactive asterials i
in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective.
I actions that have been taken to reduce the releases and the-proposed corrective actions to be taken to assure that subsequent releases will be in compliance:with the above limits. This i
special Report shall also include (1) the results of radiological analyses of the:Arinking-water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141 (applicable only if drinking water supply.is taken from the receiving water body within three miles downstream of the plant discharge).
To ensure that this requirement is mots cumulative dose contributions from liquid effluents for the i
current calendar quarter and current. calendar year shall be determined in accordance with-the methodology and parameters'in Section 2.4.2 at least once per 31 days.
Reformatting /Wspagination changes only 0144
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~l SQN ODCM Revision 24-Page 54 of 156
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2.4.2 ggEMTIVE LIOUID EFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for all age groups (adult, teen, child and infant) and orgons (bone. liver, i
total body, thyroid, skin, kidney, lung and CI tract). Pathways considered are ingestion of drinking water, fish consumption and l
. recreation-shoreline. The maximum individual dose from drinking water is assumed to be that calculated at the location Lamediately downstrema from the diffuser (see Table 1.1).
The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream das (Chickamauga Dam). The maximum potential recreation dose is calculated for a location insediately downstream of the plant outfall. Dose f actors for thase age groups and pathways are calculated as described in section 2.7.
For pathways with no age or organ specific dose factors (i.e. shoreline recreation), the total body dose will be added to the internal organ doses for all age groups.
The general equation for the dose calculations ist I
4 Dose = 1 Agg T Cg D (2.7) i where:
Ag
= the total dose factor to the total body or any organ t for i
nuclide i, mrom/hr per WCL/ml. The total dose factor is the sum of the dose factors for water ingestion, fish ingestion.
and shoreline recreation, as defined in Section 2.7.
(
T
= the length of time period over which the concentrations and the flows are averaged for the liquid release, hours.
Ci
= the average concentration cf radionuclide i, in undiluted liquid effluent during the time period T feon any liquid release. WCi/ml.
D e the near field average dilution f actor for Ci during any effluent release. D is calculated by the following equation:
FLOWw D*
. RF 0.60
(
where:
- FLOW,
= maximum un611uted liquid waste flow during the release, cfs. For TBS releases, this term is the diluted waste flow into the pond.
0.60 a mixing factor of effluent in river, defined as the percentage of the riverflow which is available for dilution of the release.
RF
= default riverflow, cfs. For each release, this value is set to 7900 cfs (the lowest average quarterly riverflow recorded from the period 1978-1988).
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1 l%WM&ihk??N&'MsW ---------- - --- ----- --- -
h*
i SQW 0DCM s
Revision 24
~
page 55 of 156 From the four age groups considered, the maximum is determined by
(
comparing,all organ doses for all age groups. The age group with the a
highest single organ dose is selected as the critical age group. The tot:1 body and maximum organ doses for the critical age group are used in the calculation of the monthly dose described in Section 2.4.2.2.
q 2.4.2.2 Monthly Dose calculations I
At the and of each month, the actual average riverflow for the month is used to recalculate the liquid doses. The monthly cunnalative dose is defined as the sua of the doses for the critical age group for each release during the month. Thus, the monthly cumulative dose will be a i
conservative value, consisting of doses belonging to various age groups depending on the six of radionuclides. These doses are
-multiplied by the ratio of the default riverflow 0 900 cfs) to the i
actual monthly everage riverflow to obtain the monthly dose. The total body and maximum organ doses' determined in this manner are then used to determine the cumulative quarterly and annual doses described in Section 2.4.2.3, and for the dose projections described in 1
Section 2.5.3.
2.4.2.3 Cumulative Doses Quarterly and annual sums of all doses are determined at the end of each month to compare to the limits given in Section 2.4.1.
These quarterly and ar.nual sums will be the sum of the monthly cumulative doses described in Section 2.4.2.2 for the appropriate months in the quarter or year. These doses will be used in the comparison to the limits.
(
2.4.2.4 Comearison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in Section 2.4.1 once per 31 days to determine compliance.
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o e=
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SQW ODCH Revision 24 page $6 of 156
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2.5 LIQUID' WASTE TREATMENT 2.5.1 REQUIREMENT The liquid radweste treatment systen shall be used to reduce the radioactive asterials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS R24 (see Figure 1.3) would exceed 0.06 area per reactor unit to the total body or 0.2 area per reactor unit to any organ.in a 31-day period.
This requirement is applicable at all times.
The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive asterials in liquid effluents will be kept "as low as reasonable achievable." This requirement implements the requirements of 10 CFR part 50.36a, Cereral Design Criteria 60 of Appendix A to 10 CFR part 50 and the design objective given in section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropri.ite portions of the liquid redweste system were specified as a suitable fraction of the dose design objectives set forth in section II.A of Appendix I, 10 CFR part 50, for liquid effluents.
If this requirement is not met, the following action will be l
Performed:
With radioactive liquid waste being discharged without treatment
(
and in excess of the above lialts, prepare and submit to the Comission within 30 days pursuant to Technical -
l specification 6.9.2, a special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and R24 3.
Sununary description of action (s) taken to prevent a recurrence.
To ensure that this requirement is met:
Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the methodology and parameters in Section 2.5.3.
a9 e
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SQN CDCM Revision 24
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page 57 of 156 2.5.2 }.70pID RADWASTE TREATNENT SYSTEM l
The liquid radwesta treatment system described below shall be
'l asintained and operated to keep releaces ALARA.
A flow diagram for the 1.ETS is given in Figure 2.2. The system consists of one reactor coolant drain tank with two pumps and a floor and equipment drain sump inside the containment of each unit and the following shared equipment inside the auxiliary buildings one sump tank and pumps, one tritiated drain collector tank with two pumps and' one f11ter, one floor drain collector tank with two pumps and one l
filter, a waste condensate tank filter, three waste condensate tanks and two pumps, a chemical draia tank and pump, two ' laundry and hot i
shower tanks and pump, a spent resin storspe tank, a cask decontamination tank with two pumps and two filters.' Auxiliary Building floor and equiFment drain cump and pumps. and evaporator with two distillate tanks, a Mobile Weste Domineraliser System (if needed) and the associated piping, valves and instrumentation.
2.5.3 DOSE PROJECTIONS In accordance with section 2.5.1, dose projections will be performed by averaging the two previous month's doses as determined in Section 2.4.2.2.
To detemine compliance with the limits..these averages are assigned as the dose projections for the upcoming month.
The projected doses are compared to the limits of section 2.5.1.
If C
the projected doses exceed either of these limits, the liquid radweste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge to UNRESTRICTED AREAS.-
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SQW CDCM Revision 24 page 58 of 156 i
2.6 0UARTERLY DOSE CALCULATIONS
(
A complete dose analysis utilizing the total estimated liquid releases i
for each calendar quarter will be performed and reported as required in Section 5.2.
Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.
The average dilution factor. D used for the quarterly calculations ist 1
D=
(for receptors upstream (2.7)
RF
- 0.60 of Chickamauga Dam)
I and
.g D=
(for receptors downstream (2.8)
RF of Chickamauga Dam)-
j where:
RF
= the average actual riverflow for the location at which the dose is being determined, cfs.
0.60 = the fraction of the riverflow available for dilution in the near field, dimensionless.
2.6.1 WATER INCESTION Water ingestion doses are calculated for each water supply identified
(
within a 50 mile radius downstream of SQN (Table 2.4).
Water ingestion doses are calculated for the total body and each internal organ as described below:
Dorg = los 9.80g.og N it Q1 D exp(-8.64E+04 11t)
(2.9) d where I
108
= conversion factor. WCi/C1.
9.80E-09 = conversion factor, cfs per al/ hour.
%it
= Dose factor for water ingestion for nuclide i, age group t, ares / hour per vC1/m1, as calculated in section 2.7.1.
Qt
= Quantity of nuclide i released during the quarter. Curies.
D
= dilution factor, as described above, cis-1 11
= radiological decay constant of nuclide 1. seconds-1 (Table 1.10).
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s SQN ODCN-Revision 24 C
page 59 of~156 I
decay tLas for water ingestion, equal to the travel time td a
from the plant to the water supply plus one day to account for the tLae of processing at the water supply (per Regulatory Guide 1.109), days.
8.64E+04 ccaversion f actor, seconds per day.
=
2.6.2 FISH IWGESTION Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of SQN (Table 2.4). ~ Individual fish ingestion doses are calculated for the total body and each internal organ as described below:
Dorg
- 10' 9.80E-09 0.25 AFit Qi D amp (-8.64t&04 11 t)
(2.10) d where 10*-
conversion factor, WCi/C1.
a 9.80E-09 conversion factor, cfs per ml/ hour.
a 0.25
= fraction of the yearly fish consumption eaten in one quarter, dimensionless.
Arit Dose factor for fish ingestion for nuclide i, age group t,
=
mesm/ hour per vCi/ml, as calculated in section 2.7.2.
Qi Quantity of nuclide i released during the quarter, Curies.
=
D dilution factor, as described above, cfs-1
=
Ai radiological decay constant of nuclide i, seconds =
(
(Table 1.10).
td
= decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), days.
8.64E+04 conversion factor, seconds per day.
e 2.6.3 SHORELINE RECREATION Recreation doses are calculated for each identified recch within a 50 l
nile radius downstream of'SQN (Table 12.4).
It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year on the shoreline i
at a' location immediately downstream from the diffusers. Individual tetreation shoreline doses are calculated for the total body and skin as described below:
(
j Dorg. 108 9.80E-09 ef ARit Qi D exp(-8.64E+04 11 t)
(2.11) d l.
where 10' conversion factor, pCi/Ci.
=
9.80E-09 conversion f actor, cfs per al/ hour.
a
? *.;
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.- -. a A
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.._..)
1 SQW ODCM Revision 24
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Page 60 of-156 rf recreation factor, used to account for the fact that the a
same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are:
1 let quarter - 0 1 2nd quarter - 0.3 3rd quarter - 0.4 4th quarter - 0.2.
?
Aggg Dose factor for shoreline recreation for nuclide i, age j
=
group t, area / hour per WC1/m1, as calculated in i
Section 2.7.3.-
Qi e quantity of nuclide i released during the quarter, curies, i
D
= dilution factor, as described above, cis-1 kg radiological decay constant of nuclide i, seconds-1 a
(Table 1.10).
i to
- decay time for recreation, equal to the travel time from the plant to the center of the reach, days.
8.64E+04 = conversion factor, seconds per day.
2.6.4 TOTAL MAX 7 MUM INDIVIDUAL DOSE The total maximum individual total body dose is obtained by suming the following for each age groups the highest total body water ingestion dose from among all the public water-supplies; the highest total body fish ingestion dose from among all the reaches; and the total body maxinum shoreline recreation dose.- The total maximum individual organ dose.is obtained by summing the following for each
(
organ and each age groups that organ's highest water ingestion dose.
from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; and the total _ body maximum shoreline recreation dose. The total maxinum individual skin dose is that skin dose calculated for the maximum shoreline dose.'
2.6.5 POPULATION DOSES For determining population doses to,the 50-mile population around the Plant, an average dose is calculated for each aga group and each pathway and then multiplied by the population.
- For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is 4
POPVfRg = 10-e I P0P, I POP, ATMW, TWDosamt (2.12) a=1 aal where:
POPWIRg a water ingestion population dose to organ t, man-rem, bc Reformatting / Repagination changes only-
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01441 d'
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i SQW ODCN Revision 24
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Page 61 of 156
- POP,
= fraction of population in each age group a (from i
L NURgG CR-1004, table 3.39).
Adult = 0.665 Child = 0.168 Infant = 0.015 o
Teen
=
0.153 PCP a Population at'PWS m.
The 4 PW8s and their populations a
are listed in Table 2.4 ATNW
- ratio of average to maximum water ingestion rates for a
each age group a.
Maximum water ingestion rates are given in Table 1.11.. Average water ingestion rates, in L/ year, (from R.G.1.109 Table E-4) are:
Adult = 370 child = 260 Infant
- m. 260 Teen
= 260 TWDOSamt
= total-individual' water ingestion dose to organ t at PWS m, to the age group a, as described in Section 2.6.1,
(
mrom.
10-s
= conversion factor for ren/aren.
For population doses resulting from fish ingestion the calculation I
assumes that all fish caught within a 50-mile radius downstream of SQW are consumed by local population. An additional. 7-day decay term is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion.
(
of all fish caught within a 50-mile radius downstream is:
l 453.6 NVST APR 4
3 TFDOSart POPa l
POPFt.
I I
(2.13) los los rol a=1 FISH
- PCP, a
where:
POPFt
= total fish ingestion population dose to organ t, man-rem.
HVST
= fish harve?t for the, Tennessee River, 3.04 lbs/ acre / year.
APR size of reach, acres (Table 2.4)..
a TFDOSart
- total fish ingestion dose to organ t for reach r, for the age group a, as described in Section 2.6.2, mrom.
POP
= fraction of population in each age group a, as given a
above.
PISH
- amount of fish ingested by each age group a, kg/ year.
a Average fish ingestion rates (R.G. 1.109 Table R-A) ares Adult
= 6.9 Child
'2.2
=
Teen 5.2
.=
453.6 a conversion factor, s/lb.
10'
= conversion factor, mesm/ rem.
'C' a conversion factor, s/kg.
'e:
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Page 62 of 156 For recreation shoreline, the general equation used for calculating the population doses. POPR in man-ram ist REQFRA 4
POPRg a 1 TSKDOSrt 8KVI3r NRSVISr (2'14) 108 8760 rol where i
POPRt
- total recreation population dose for all reaches to organ t, man-rem.
REQFRA
= fraction of yearly recreation Which occurs in that quarter, as given in Section 2.6.3.
TSKDOSrt
- total shoreline dose rate for organ t in reach r, mesm/h.
I SHVIS
- shoreline visits per year at each reach r. (Table 2.4).
r MRSVISr length of shoreline-recreation visit at reach r. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
108 conversion factor, arem/ rem.
8760
. conversion factor, hours / year.
,i f
%e c Reformatting / Repagination changes only 01441 l
1
- A m ~e., A m w.
, a -:1.n- :.c
i SQN ODCM Revision'24 lf page 63 of 156' 2.7 LIOUID DOSE FACTOR EQUATIONS
(
2.7.1 WATER INCESTION - Att (aren/hr per pCi/mi)
DFList Uwe 108 los Nit
- 8760
'where ingestion dose conversion factor for nuclide i, age group DFList
=
a, organ t, ares /pci, (Table 1.9).
U, water consumption rata for age group a L/ year.
=
w (Table 1.11).
10' conversion factor, PCi/pci.
=
10' conversion factor, al/L.
=
8760 conversion factor, hours per year.
=
2.7.2 FISH INCESTION - Apig (area /hr per pC1/ml)
DFLiakUa81 108 108 f
AFit "
i 8760 where t
DFLiat
= ingestion dose conversion factor for nuclide i, age group a, organ t, mrom/pci, (Table 1.9).
(
Ufa
= fish consumption rate for age group a,-kg/ year, (Table 1.11).
Bt
= bicacaumulation f actoc for nuclide i. PCi/kg per pCi/L, (Table 2.5).
10*
conversion factor, PCi/pci.
a los
= conversion factor, al/L.
8760
= conversion factor, hours per year.
2.7.3 SHORELINE RECREATION - ARit (mrom/hr per pCi/ml).
DFCit Ke M W los too u 8760
- 3600 kg where:
DFCit
= dose conversion. factor for standing on contaminated ground for nuclide i and organ t (total body-and skin), aces /hr per
. pCi/m8, (Table 1.13).
e transfer coefficient from water to shoreline sediment.
K a
L/kg-hr, (Table 1.11).
M
= mass density of sediment, kg/m, (Table 1.11).
8 l
M4 l
Reformatting / Repagination changes only
~
01441 l
5
. shim >'s% ~fGmfat K -Mr%'5 -
~.~%.h w e,.-
2 e
SQW 0DCH Revision 24-(
Page 64 of 156 i
K
= fransfer coefficient from water to shoreline sediment.
e L/kg-hr. (Table 1.11).
M e mass density of sediment, kg/m. (' table 1.11).
a W
. shoreline width factor, dimensior.lests. (Table 1.11).
108 conversion factor, al/L.
10'
= conversion factor, pci/pci.
3600 conversion factor, seconds / hour.
a 11
. decay constant for nuclide 1. seconds-1 (Table 1.10).
tb time shoreline is exposed to the concentration on the water.
=
seconds. (Table 1.11).
U e usage factor. 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year.
i 8760 conversion factor, hours / year.
i r
i Refo N tting/ Repagination changes only 01441 i
32n.':,e w noenas-w w m:
a -,- h e w = -
c ~ 1 = ~4
SQW ODCM Revision 24 page 65 of 156
(
3.0 Radiolonical Environmental Monitorinz 3.1 MININVil RE0VTRED MOVITORING PROGRAN 3.1.1 RE0VIRNENT The radiological environmental monitoring program shall be conducted as specified in Table 3.1.
This requirensnt is applicable at all times.
The radiological environmental monitoring program required by this section provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiatien exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological offluent monitoring program by verifying that the measurable. ton?.entration of radioactive materials and levels of radiation are A Migher than expected on the basis of the effluent measurements and edn'.ing of the environmen;.a1 exposure pathwayc.. The initially specified monitoring program will' be effective for at least the first three years of connercial operation. Following this period,'
program changes may be initiated based on operational experience.
i The LLDs required by Table 3.2 are considered optimum for routine l
environments 1 measurements in industrial laboratories. It should be recognized that the LLD is defined as an a ari.ori (before the fact)
(
limit representing the capability of a measurement system and not as 3-oosteriori (af ter the f act) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sises, the. presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unschievable. In such cases, the contributing" circumstances will be identified and described in the Annual Radiological Environmental Operating Report.
If this requirement is not met, the. appropriate following action (s) will be performed With the radiological environmental monitoring progran not being a.
conducted as specified in Table 3.1, prepare and submit to the Ceaunission, in the Annual Radiological Environmental Operating Report,'a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, b.
Wititlie level of radioactivity in an en' a' sampling medium exceeding the reporting levels of hen averaged over any calendar quarter, prepare and se a casumission within 30 days from the end of the affe.
ir, pursuant to Reformatting / Repagination changes only l
01441 y 'l MA.p. r
.1,.
- wi d N kfakid3Wem w aiMU MMV
l l
{(
Ter.hnical specification 6.9.2, a Special Report that identifies the page 66 of 156-a 3
cause(s) for exceeding the limit (s) and-defines the corrective actions l
to be taken to reduce radicactive affluents so that the potential-l annual dose to a member of the public is less than the calendar year limits of sections 1.4.1, 1.5.1 and 2.4.1.
When one or more of the radionuclides in Table 3.3 is detected in the sampling medium, this report shall be subaltted ift
~ concentration (i) concentration (2)
+
g l'. 0
+.
limit level (1) limit level (2)
When radionuclides other thn.those in Table 3.3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE pVBLIC is equal to R24 or greater than the calendar year limits of Sections 1.4.1, 1.5.1 and 2.4.1.
This report is not required if the measured level of radioactivity.was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental-Operating Report.
c.
With allk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The
(
specified locations from which samples were unavailable may then.
be deleted from the monitoring program. pursuant to Section 5.1, identify the new locations for obtaining replacement samples in the Annual Radiological Environmental Operating Report. A revised figure (s) and table (s) for the ODCM reflecting the new location (s) shall be included-in the next Semi-Annual Effluent Release Report pursuant to section 5.2.
To ensure that this requirement is met:
The radiological environmental. monitoring samples shall be collected pursuant to Table 3.1 from the_ locations given in the tables and figures listed below and shall be rialysed pursuant. to the requirements of Table 3.1 and the detection capabilities required by Table 3.2.
3.1.2 MONITORING PROGRAM An envir'oninental radiological monitoring program shall be conducted in accordance with the above requirement. The monitoring program described in Tables 3.4, 3.5, and 3.6, and in Figures 3.1.- 3.2 and 3.3 shall be conducted. Results of this program shall be reported in 01'.41 1
.3N/fN. ?*A 9 I N Iel @ ?J I 4.m
.. ma
@%k? 1 %"'
.. - -. ~. -
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Page 67 of 156 3
accordance'with Section 5.1.-
i The atmospheric environmental radiological monitoring program shall-consist of monitoring stations from which samples of air particulates and atmospheric radiciodine shall be. collected.
The terrestrial monitoring program shall. consist of the callection of milk, soil, ground water, drinking water, and food crops. In addition, direct samma radiation levels will be measured in the
. vicinity of the plant.
The reservoir sampling program shall censist of the collection of samples of surf ace water, sediment, class, and fish.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hasardeus conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.
3.1.3 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 3.2 are achieved.
l l
l l
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<.,s.99 i
SQu ODCH Revision 24
(
3.2 tJ.ND USE CEWSUS
\\
3.2.1 BfaVIREMENT l
& Land Use consus shall be conducted and shall identify within a distance of 8 km (5 alles) the location in each of the 16 astoorological sectors of the nearest allk animal, the nearest i
residence, and the nearest gardene of greater then 50 as (500 f ts) produeleg fresh leafy vegetables..
3 This requirement is applicable at all times.
j This requirement 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 that const-The best survey information from the door-to-door, aerial, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.8.3 of Appendix I to 10 CFR Part 50.
Restricting the census to gardens of greater than 500 fta provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the mininua required to provide the guantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used.1) that 20% (J 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,
a
(
The results obtained in the Land Use Census will be evaluated in accordance with the following appropriate actions:
I With a Land Uso Census identifying a location (s) that yields a a.
calculated dose or dose comaltaant 20% greater than the values currently being calculated in Sections 1.4 and 1.5. identify.the new location (s) in the next Semi-Annual Effluent Release Report pursuant to Section 5.2.
b.
With a Land Use Census identifying a location (s) that yields a calculated dose or dose cosaltaent (via the same pathway) 20%
greater than at a location from which samples are currently being obtained in accordance with the requirements of Section 3.1.1, add the new location (s) within 30 days to the radiological environmental monitoring program given in Section 3.1.2, if samples are available. The sampling location (s), excluding the-control station location, having the losest calculated dose or dose commitaant(s), via the same exposure pathway may be deleted froa this monitoring program after October 31 of the year in which this Land Use Census was conducted. pursuant to Technical Specification 6.14, submit in the next Seal-Annual Effluent Reformatting / Repagination changes only 01441 a,
.d '
d
.'E-MA
1 son oDen Revision 24 Release Report documentation for a thange in the ODCM including a
{
page 69 of 156 revised figure (s) and table (s) for the ODCE reflesting the now location (s) with the information supporting the thansa in sampling locations.
To ensure that this requirement is mett at least ense por 12 asnths using ht infornation that willh Land provide N boot results, such as by a door-to-door survey, mail agricultural authorities. survey, telephone survey, serial survey, or by sensulting local k
N results of h Land Use census shall be included in N Annual Radiological Bavironaestal Operating Report pursuant to gestien 5.1.
N 6
3.2.2 1.AND USt CENSUR A land use survey shall be sonducted in accordance with the requirements above.
the Annual Radiologiaal gnvircamental Operating Report.The results of the su 3
Broad leaf vegetation sampling of at least three different kinds different'ditoction sectora with the highest predicted D/Qs ino R24 lieu of the garden conses.
g Specifications for broad leaf analysis of control samples. vegetation sampling in table 3.1.4c shall be followed, inc
'.yc 01441 l
y h., pew u.,.
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-1 4
._ e
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3.3 INTERLARORATORY COMPARISON PROCRAM 3.3.1 REQUIREMENT Analyses shall be performed on radioactive materials supplied as part of an Interlsboratory Comparisen program whiah has been approved by the Commission.
y This requirement is appliaable at all tinos.
The requirement for participation in an Interlaboratory Comparison progran is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive asterial in environmental sample matrices are performed as part of the quality 1
assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
If this requirement is not met, the followims action will be performed:
With analyses not being performed as required above, report the corrective actions being taken to prevent a recurrence to the Cosnission in the Annual Radiological Environmental Operating Report.
To ensure that this requirasent is mots f
L susunary of the reeukte obtained as a part - the above required Interlaboratory Comparison program and in fx m aance with the q
guidance below shall be included in the Ann,44 Radiological Environmental Operating Report.
l 3.3.2 INTERt.ABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Interleboratory Comparison program which has been approved by the VRC. A suustery of thi results bbtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the RpA progran code designation may be provided).
If analyses are not perforned as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.
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Revision 2a page 71 of 156
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0 M Mt 4.1 Rt0VTPtMENT l
The annual (eglendar year) dose or dose sessaltaant to any MEMBER OF THE R24 I
i pURLIC, due to releases of radioactivity from uranius fuel cycle R24 sources, shall be limited to less than or equal to 25 area to the total body or any organ (except the thyroid, which shall be limited to t
less than or equal to 75 area).
This requirement is applicable at all times.
This requirement is provided to meet the dose limitations of 40 CFR 190. The action requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive i '
effluents exceed twice the design objective doses of Appendix 1.
For i
sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits R24 of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of 1
action which should result in the limitation of dose to a MEMBER OF R24 THE PUBLIC for 12 consecutive months to within the 40 CFR 190 limits.
R24 For the purposes of the special Report, it may be assumed tnat the dose comitment to the MEMBER OF THE PUBLIC from other uranium fuel R24 cycle sources is negligible, with the exception that dose centributions from otter nuclear fuel cycle f acilities at the same
(
site or within a radius of 5 miles must be considered.
9 If this requirement is not met, the following action will be performed:
,With the calculated doses from the release of radioactive materials in liquid or gaseous effluents om.eeding twice the limits of Section 1.4.1, 1.5.1, or 2.4.1, calculations should be made to determine if the above limits have been violated. If em,h is the case, prepare and submit a special Report to the Director, Nuclear Reactor Regulation. U.S. Regulatorp Cosmission, Washington D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits above. This 3 rectal Report, as defined in 10 Crt Fort 20.405e.
R24 shall include an analysis which estimates the radiation exposure (dose) to a MINWER OF THE pURLIC free uraniue fuel eyele sources R24 (including all offisent pathways and direct radiation) for a salendar year that includes the release (s) covered by this report. If the estimated. dose (s) exceeds the above limits and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the special Report shall include a request for a, variance in accordance with the provisions of 40 CFR 190 and including the specified inforntion of section 190.11(b). Rubmittal of the report 4
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Page 72 of 156 is considered a tiacly request, and a variance is granted until the staff action on the request is coupleted.'
R24 to ensure that this requirement is met:
Cumulative dose contributions from liquid and gaseous offluents shall be determined in accordance with the methodology and parameters in i
Sections 1.4.2. 1.5.2, and 2.4.2.
4.2 ANNUAL MAXIWM INDIVIDUAL D08tB - TOTAL REUJtIflLitfdl To determine compliance with 40 CFR 190 as required in Section 5.2 the annual dose contributions to the maximum individual from SQN radioactive offluents and all other nearby urar.Lun fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first sunening the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterly total body dose from liquid effluents, the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sua for each guarter and sunning over the four quarters.
l d
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page 73 of 156 5.0 Rtp0RTING..REQUIRENEF U l
5.1 ANWUAL RADIOLOCICAL INVIRONMENTAL OPERATINC REPORT
{
The annual radiological environmental operating reports shall include susnaries, interpretstions, and an analysis of tramde of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, i
eperational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 3.2 and a listing
)
of the new locations for dose calculations and/or environmental monitoring identified by the land use census. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarised and tabulated results in the format of Regulatory 4
cuide 4.8. December 1975 of all radiologiesi environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
l The reports shall also include the following a susunary description of the radiological environmental monitoring program; a rap of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison program required by Section 3.3.
i
$.2 SEMI-ANNUAL RADI0 ACTIVE EFFLUtWT RELEASE REPORT semiannual radioactive release reports shall include a sununary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21
" Measuring. Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Caseous Effluents from Light-Water-Cooled Nuclear power plants." Revision 1. hne 1974, with data summarized on a quarterly basis following the format of Appendix 5 thereof.
The senlannual radioactive release report shall include unplanned releases from the site to unrestricted areas on a quarterly basis and l
shall also include any thanges ande to the CDCM pursuant to Technical Specification 6.14.
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30W CDCu Revision 24 page 74 of 156
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The somlannual radioactive release report shall include information for solid waste as outlined in the process Control program, and shall also include any changes made to the PCP during the reporting period.
The annual radioactive :,ffluent release report (Radiological tapact) to be submitted 60 days after January 1 of each year shall include an annual runnary of hourly astoorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, staoepheric stability, and precipitation (if measured) on magnetic tape, or in the fem of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the annual radioactive affluent release report, this summary of required meteorological data may be retained in site in a file that shall be provided to WRC upon request). This same report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents released from the unit or station during the previous calender year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the R24 SITE BOUNDARY (rigure 1.3) during the report period. All assumptions R24 used in making these assessments (i.e., specific activity. exposure time, and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as detemined by sampling frequency and measurement) shall be used for detemining the gaseous pathway doses. The assessment of radiation doses shall be perfomed in accordance with sections 1.7 and 2.6.
(
The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation doses to the likely most awposed MRMBERS OF THE Pull.1C from reactor R24 releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show confomance with 40 CFR 190. Environmental Radiation Protection Standards for Nuclear power Operation, in accordance with Section d.2.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory cuide 1.109. Revision 1.
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Revision 24 I
page ?$ of 156 6.0 g /INITIONS The dsfined terms in this section appear in capitalised type in the text and are applicable throughout this ODCN.
6.1 CHANNEL CAL 18tATION
& CHANNEL CALIBRATION shall be the adjustaant, as necessary, of the thannel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire thannel including the sensor and alars and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIDEATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
6.1 CHANNEL CHECK A channel check shall be the qualitative assessement of channel J
behavior during operation by observation. This detemination I
shall include, where possible, comparison of the channel indication and/or status with other indications and/or status i
derir,ed from independent instrument channels measuring the same parameter.
6.3 CMANNEL FUNCTIONAL TEST A CMANNEL FUNCTIONAL TEST shall bet a.
Analog channels - the injection of a sisaalated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alam and/or trip functions, b.
31 stable channel - the injection of a staulated signal into the sensor to verify OPERA 3!LITY including alare and/or trip function.
4.4 CAST 0US RADWASTE TREATMENT SYST'EM A Cast 0US RADWASTE TREA1 MENT SYSTEM is any system designed and instelled to reduce radioactive Baseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environement.
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SQW CDen Revision 24 page 76 of 156 6.5 DOSE EQUIVALENT I-131
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DO8E EQUIVALENT,I-131 shall be that concentration of I-131 (Sci / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132,1-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for power and Test Reactor sites.
6.6 MEMBER (5) 0F THE PUBLIC MEMBER (S) 0F THE PUBLIC shall include all individuels who are not occupationally associated with the plant. This category sha11 include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category does not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter en area that is controlled by the licensee for purposes of protectbn of individuals from exposure to radiation and i
radioactive materials.
6.7 OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation,
) (
controls, a normal and an emergengy electrical power source, cooling or seal water, lubrication or other auxiliary equipar.nt that are required for the system, subsystem, train, componer.t. or device to perfom its function (s) are also capable of perfr.rming their related support function.
6.8 MODE j
A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and everage reactor codcr.c temperature specified in Table 4.1 of the SQN Technical Specifications.
6.9 PURCE - PURCING NRCE or pVRGIpc is the controlled process of discharging air or be from a confinement to maintain temperature, pressure, humudity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement, page Added i
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squ ODCM Revision 24
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page 77 of 156 6.10 RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.
6.11 SITE SOUNDARY The SITE 80VWDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee (see Figure 1.3) 6.12 SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
6.13 UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area, at or beyond the SITE 80VWDARY to which access is not controlled by the licensee for purposed of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, consnercial, institutional, and/or recreational purposes.
6.14 VENTILATION EKHAUST TREATMENT SYSTEM A VENTILATION EKMAUST TRGTHENT SYSTEM is any systes designed and installed to reduce gaseous radiciodine or radioactive material in particulate fosin in affluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stessa prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). D gineered Safety Feature (EST) atmospheric cleanup systems are not considered to be VENTILATION EIHAUST TREATHENT SYSTEM component 3.
6.15 VENTING VENTINC is the controlled process of discharging air or gas from a confinement to maintain temperan.ure, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air gas is not provided or required during VENTINC.
Vent, used in systen names, does not imply a VENTING process.
page Added
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SQN ODCM Revision 24 Table 1.1 (Page 1 of 4)
RADI,CACTIVE CASE 0t's WASTE MONITORING SAMPLING AND ANALYSIS FROGRAM Caseous Minimum Type of 1.ower Limit of Release Sampling Analysis Activity Detection (1.1.D)
Type Frequency Trequency Analysis (pCi/ml)*
A. Waste Gas P
P Storage Each Tank Each Tank Principal lx10**
Tank Crab Gamma Enitters B. Containment
- 1. PURCE P'
D' Principal 1x10**
R24 Each PURCE Each PURCE Gamma R24 Crab Esitters8 Sample B-3 1x10*'
DJ DJ Principal 1x10**
- 2. Vent Each Day Each Day Gamuna Crab Emitters:
Sample R-3 1x10*'
C. Noble cases and M
M Principal 1x10**
Tritium Grab Camens Sample taitters:
- 1. Condenser
(
Vacuum E-3 1x10**
Exhaust"
- 2. Auxiliary Building Exhaust
- 3. Service Bldg.
Exhaust
- 4. Shield Bldg.
Exhaust'"
r
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SQN ODCM Revision 24 Page 79 of 156 Table 1.1 (Page 2 of 4)
ILAD10 ACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROCRAM Gaseous Minimum Type of Lower Limit of Release Sampling Analysis Activitv Detection -LLD Type Frequency Frequency Analyst (pci/ml)*
D. Iodine and W'
I-131 1x10*
Particulates Continuous' Charcoal Sampler Sample
- 1. Auxiliary W'
Principal 1x10
Building Continuous' Particulate Gamma Exhaus t Sampler Sample Esitters8
(!-131,
- 2. Shield Others )
Building Exhaust M
Gross Alpha 1x10
~
Continuous' Composite Sampler Particulate Sample Q
Sr-89 lx10*
Continuous' Composite Sr-90 Sampler Particulate Sample
(
E. Noble Cases Continuous' Noble cas Noble Cases 1x10*'
all Rele6se Monitor Monitor Cross Beta i
types as or Gamma l
listed in C
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Page 80 of 156 Table 1.1 (Page 3 of 4)
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RADICACTIVE CASE 0US WASTE MONITORING SAMPLING AND ANALYSIS PROG TABLE NOTATION P = Completed prior to each release.
D = At 2 east once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = At least once per 31 days W = At least ou:* Per 7 days Q = At least once per 92 days a The LLD is defined, for the purpose of these specification:, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only a 51 probability of falsely concluding that a black observation represents a "real" signal.
For s. particular measurement system (which may include radiochemical R24 separation):
i 4.66s.
LLD =
i E
V 2.22x10' Y
exp (-1 At)
Where LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume,
- s. is the standard deviation of the background counting rate or of
(
the counting rate of a blank sample as appropriate (as counts per minu t.-).
E is the counting efficiency as counts per disintegration, V is the sample sise in units of mass or volume, 2.22x10' is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable).
A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (midpoint).
It should be noted that the LLD is defined as an p priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (af ter the fact) limit for a particular esasurement.
b Sampling and analysis shall also be performed following shutdown, l
startup, or a thermal power change exceeding 15% of RATED TBERMAL R24 POWER within i hour unless (1) analysis shows that the DOSE R24 EQUIVALENT I-131 concentration in the primary coolant has not R24 increased more than a factor of 3 and (2) the containment noble gas activity monitor (RE-90-106 or RE-90-112) shows that the radioactivity has not increased by more than a factor of 3.
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Page 81 of 156 Table 1.1 (Page 4 of 4) f RADI0 ACTIVE CASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM l
TABLE NOTATION e Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
d Samples shall be changed at least once per 7 days and analyses shall be completed within 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days following each shutdown from 115% RATED R24 TEERMAL POWER, startup of 115% RATED TIERMAL POWER or HEAMAL POWER R24 change exceeding 15% of RATED TIERMAL POWER in one hour and analyses R24 i
shall be completed within &g hours of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analysed,'the corresponding LLD's may be increased by a factor of 10.
e Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
f The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation ande in accordance with sections 1.2, 1.4, and 1.5.
g The principal gansna emitters for which the LLD specification applies exclusively are the following radionuclides Kr-87, Kr-68, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gases and Mn-54. Te-59, I-131 Co-58, co-60, In-65, Mo-99, Cs-134. Cs-137. Ce-141 and Ce-144 for
(
particulate principal gasuna emitters. This list does not mean that only these nuclides are to be detected and reported. Other gamma peaks which are measurable and identifiable, together with the above nuclides, shall also be analysed and reported in the Semi-annual Radioactive Effluent Release Report pursuant to Section 5.2.
h During teleases via this exhaust system.
1 PURGING - Applicable in MODES 1, 2, 3 and 4, the upper and lower R24 compartments of the containment shall be sampled prior to PURGING.
R24 Prior to breaking containment ihtegrity in MODE 5 or 6, the upper R24 and lower compartmenta of the containment shall be sampled. The incere instrument room purge sample shall be obtained at the shield building exhaust between 20 and 25 minutes following initiation of I
the incore instrument room PURGE.
R24 j VENTING - App 1,8 able in MODES 1, 2, 3, and 41 the containment will R24 b.e VENTED to the containment annulus and then to the auxiliary R24 building via containment annulus fans. The lower containment l
compartment shall be sampled daily when Vt.NTING is to occur to R24 account for the radioactivity being discharged from the VENTING R24 process.
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SQN ODCM Revision 24 Page 82 of 156 C
Table 1.2 (1 of 7)
JOINT PERCENTAGE TREQUENCIES OT WIND DIRECTION AND WIND SPEED TOR D1TTERENT STABII,ITY CLASSES
- 4 Sequoyah Nuclear Plant Meteorological Tacility*
Jan. 1. 72 - Dec. 31. 75 Stability Class A Delta T1-1.9 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.6 3.4
_ 5. 4 7.4 11.h 11.,)_ -26.4
>24.5 Total N
0.01 0.01 0.01 0.03 0.04 0.04 0.0 0.0 0.0 0.13 NNE 0.0 0.0 0.04 0.19 0.20 0.16 0.01 0.0 0.0 0.60 NE 0.0 0.0 0.08 0.20 0.15 0.13 0.0 0.0 0.0 0.56 ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 E
0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 ESE 0.0 0.0 0.01 0.01 0.0 0.C 0.01 0.0 0.0 0.03 SE 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.03 SSE 0.0 0.0 0.01 0.03 0.02 0.02 0.01 0.0 0.0 0.09 S
0.0 0.0 0.01 0.04 0.06 0.05 0.01-0.0 0.0 0.17 SSW 0.0 0.0 0.01 0.09 0.18 0.16 0.01 0.0 0.0 0.45 SW 0.0 0.0 0.04 0.12 0.10 0.09 0.02 0.0 0.0 0.37 WSW 0.0 0.0 0.02 0.03 0.03 0.02 0.02 0.0 0.0 0.12 W
0.0 0.0 0.01 0.0 0.01 0.02 0.0 0.0 0.0 0.04 kW 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02
(
NW 0.0 0.0 0.01 0.01 0.01 0.05 0.01 0.0 0.0 0.09 NNW 0.0 0.0 0.01 0.0 0.02 0.08 0.01 0.0 0.0 0.12 Sub-total 0.01 0.01 0.31 0.80 0.83 0.83 0.12 0.0 0.0 2.90 958 stability class A occurrences out of total 32723 valid temperature difference readings.
934 valid wind direction / wind speed readings out of total 958 stability class A occurrences.
All columns and calm total 100 percent of net valid readings
- Meteorological Tacility located 0.74 miles SW of Seguoyah Nuclear Plant.
Temperature Instruments 33 and 150 feet above ground.
Wind instrumenta 33 feet above ground.
neformatting/n pagination cheeses only 01461 j
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SQN ODCM Revision 24 Page 83 of 156 Table 1.2 (2 of 7)
J0!hT PERCEh7 AGE TREQUENCIES OF WIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan. 1. 72 - Dec. 31. 75 Stability Class 8
-1.9 < delta 71-1.7 dvs. C/100m Wind Speed (eph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 h 18.4 24.4
>24.5 h
N 0.0 0.0 0.01 0.01 0.02 0.03 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.23 0.20 0.18 0.01 0.0 0.0 0.67 NE 0.01 0.0 0.08 0.29 0.09 0.06 0.0 0.0 0.0 0.52 ENE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 E
0.0 0.0 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.03 ESE 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.01 0.02 0.0 0.01 0.0 0.0 0.0 0.04 SSE 0.0 0.0 0.01 0.03 0.0 0.02 0.0 0.0 0.0 0.06 S
0.0 0.0 0.03 0.03 0.07 0.04 0.01 0.0 0.0 0.18 SSV 0.0 0.0 0.04 0.09 0.20 0.20 0.03 0.0 0.0 0.56 SW 0.0 0.0 0.03 0.11 0.14 0.10 0.02 0.0 0.0 0.40' WSW 0.0 0.0 0.01 0.01 0.03 0.02 0.01 0.01 0.0 0.09 i
W 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 t
WNW 0.0 0.0 0.0 0.01 0.01 0.03 0.0 0.0 0.0 0.05 NW 0.0 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.0 0.06
(
NNW 0.0 0.0 0.01 0.02 0.02 0.06 0.01 0.0 0.0 0.12 SUB-TOTAL 0.01 0.0 0.33 0.90 0.81 0.81 0.09 0.01 0.0 2.95 969 stability class B occurrences out of total 32723 valid temperature difference readings.
953 valid wind direction / wind speed readings out of total 969 stability class B occurrences.
All columns and calm total 100 percent of not valid readings.
- Meteorological facility located 0.74 miles SW of Seguoyah Nuclear Plant.
Temperature instrumenta 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Page 84 of 156 C
J0!h7 PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED Table 1.2 (3 of 7)
FOR DIFTEREhi STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorologica'l Facility
- Jan.1, 72 - Dec. 31, 75 Stability Class C
-1.7 < delta T1-1.5 deg. C/100m Wind Speed (eph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 h h 24.4 124.5 MT N
0.0 0.0 0.01 0.02 0.02 0.02 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.12 0.11 0.11 0.0 0.0 0.0 0.39 NE 0.0 0.0 0.05 0.14 0.05 0.03 0.0 0.0 0.0 0.27 LNE 0.0 0.0 0.03 0.02 0.0 0.0 0.0 0,0 0.0 0.0F E
0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 ESE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 l
SSE 0.0 0.0 0.01 0.02 0.0 0.02 0.0 0.0 0.0 0.05 S
0.0 0.0 0.03 0.04 0.06 0.05 0.0 0.0 0.0 0.18 SSW 0.0 0.0 0.01 0.11 0.14 0.13 0.02 0.0 0.0 0.41' SW 0.0 0.0 0.03 0.08 0.12 0.07 0.01 0.0 0.0 0.31 WSW 0.0 0.0 0.01 0.02 0.03 0.02 0.0 0.01 0.0 0.08 W
0.0 0.0 0.0 0.01 0.0 0.01 0.01 0.0 0.0 0.03 WNW 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 i (
NW 0.0 0.0 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.06 NNW 0.0 0.0 0.0 0.02 0.02 0.05 0.0 0.0 0.0 0.09 SUS-TOTAL 0.0 0.0 0.26 0.64 0.58 0.55 0.05 0.0 0.0 2.08 584 stability class C occurrences out of total 32723 valid temperature difference readings.
672 valid wind direction / wind speed readings out of total 684 stability class C occurrences.
All columns and calm total 100 percent of not valid readings.
- Meteorological facility located 0.74 alles SW of Sequoyah Nuclear /lant.
Temperature instrumente 33 and 150 feet above Bround.
Wind instrumenta 33 feet above ground.
l
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i SQN ODCM Revision 24 Page 85 of 156 Table 1.2 (4 of 7)
(
JOINT PERCENTACE TREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DITTERENT STABILITY C1. ASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan. 1. 72 - Dec. 31. 75 Stability Class D
-1.5 < delta T1-0.5 deg. C/100m Wind Speed (aph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-i Calm _
1.4 3.4 5.4 7.4 12 d. 18.4 24.4
>24.5 M
N 0.003 0.01 0.24 0.22 0.16 0.17 0.0 0.0 0.0 0.80 NNE 0.017 0.06 0.73 1.03 0.84 0.78 0.07 0.0 0.0 3.51 NE 0.006 0.02 0.76 0.88 0.42 0.42 0.05 0.0 0.0 2.55 ENE 0.003 0.01 0.21 0.11 0.03 0.0 0.0 0.0 0.0 0.36 E
0.003 0.01 0.12 0.03 0.02 0.01 0.0 0.0 0.0 0.19 ESE 0.003 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.0 0.99 SE 0.0 0.0 0.12 0.08 0.0 0.0 0.0 0.3 0.0 0.20
$$E 0.0 0.0 0.15 0.15 0.05 0.06 0.01 0.01 0.0 9.43 0.003 0.01 0.31 0.53 0.38 0.25 0.02 0.0 0.0 1.50 SSW 0.003 0.01 0.44 1.25 0.95 0.70 0.07 0.0 0.0 3.42 SW 0.003 0.01 0.47 1.17 1.03 0.52 0.03 0.01 0.0 3.24 WSW 0.0 0.0 0.22 0.34 0.18 0.21 0.07 0.01 0.0 1.03 W
0.003 0.01 0.06 0.08 0.10 0.19 0.02 0.01 0.0 0.47 WNW 0.003 0.01 0.06 0.05 0.11 0.18 0.01 0.0 0.0 0.42 NW 0.0 0.0 0.08 0.08 0.22 0.31 0.03 0.0 0.0 0.72
(
NNW 0.003 0.01 0.15 0.14 0.25 0.36 0.02 0.0 0.0 0.93 SUB-TOTAL 0.05 0.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.96 6567 stability class D occurrences out of total 32723 valid temperature difference r1adings.
6345 valid wind direction / wind speed readings out of total 6567 stability class D occurrences.
All columns and calm total 100 percent of net valid readings.
l
- Meteorological facility located 0.74 miles SW of sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above 8round.
Wind instruments 33 feet above 8round.
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SQN CDCM Revision 24 Page 86 of 156
(
Table 1.2 (5 of 7)
JOINT PERCENTAGE FREQ1'ENCIES OF WIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan. 1, 72 - Dec. 31, 75 J
Stability Class E
-0.5 < delta Ti 1.5 deg. C/100m Wind Speed (sph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 11 4 18.4_
24.4
>24.5 I2t11 N
0.017 0.23 1.26 0.83 0.39 0.27 0.0 0.0 0.0
' 98 NNE 0.023 0.31 2.83 2.46 1.07 0.92 0.03 0.0 0.0 t.62 i
NE 0.011 0.15 1.03 0.71 0.31 0.18 0.01 0.0 0.0 2.39 ENE 0.009 0.12 0.48 0.16 0.04 0.0 0.0 0.0 0.0 0.80 E
0.010 0.14 0.24 0.05 0.01 0.01 0.0 0.0 0.0 0.45 ESE 0.007 0.09 0.11 0.01 0.01 0.01 0.01 0.0 0.0 0.24 i
SE 0.007 0.10 0.37 0.06 0.01 0.01 0.0 0.0 0.0 0.55 I
SSE 0.008 0.11 0.58 0.24 0.13 0.23 0.04 0.02 0.0 1.35 S
0.013 0.17 1.33 1.49 0.91 1.05 0.08 0.0 0.0 5.03 SSW 0.007 0.10 1.67 2.32 1.67 1.45 0.11 0.0 0.0 7.32 SW 0.013 0.17 1.59 2.07 1.30 0.99 0.10 0.0 0.0 6.22 WSW 0.010 0.13 0.87 0.55 0.35 0.40 0.06 0.0 0.0 2.36 l
W 0.007 0.10 0.42 0.28 0.21 0.22 0.03 0.0 0.0 1.26
(
WNW 0.010 0.14 0.37 0.22 0.19 0.27 0.02 0.0 0.0 1.21 NW 0.007 0.10 0.50 0.37 0.43 0.38 0.02 0.0 0.0 1.80 NNW 0.011 0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61 Sub-total 0.17 2.31 14.45 12.50 7.60 6.79 0.52 0.02 0.0 LA.19 14624 stability class E occurrences out of total 32723 valid temperature difference readings.
14146 valid wind direction / wind speed rea',ings out of total 14624 stability class E occurrences.
All columns and calm total 100 percent of net valid readings.
i
- Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature instrumenta 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Table 1.2 (6 of 7)
(
JOINT FERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DITTERENT STABILITY CALSSES*
Sequoyah Nuclear Plant Meteorological Facility
- Jan. 1. 72 - Dec. 31. 75 Stability Class T 1.5 < delta Ti 4.0 deg. C/100m Wind Speed (sph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 h h 24.4
>24.5 Dtst N
0.011 0.21 1.37 0.44 0.04 0.0 0.0 0.0 0.0 2.06 NNE 0.018 0.35 3.61 0.84 0.05 0.0 0.0 0.0 0.0 4.85 NE 0.011 0.21 1.15 0.28 0.01 0.0 0.0 0.0 0.0 1.65 ENE 0.008 0.16 0.39 0.03 0.0 0.0 0.0 0.0 0.0 0.58 L
0.010 0.20 0.22 0.0 0.0 0.0 0.0 0.0 0.0 0.42 ESE 0.007 0.13 0.18 0.02 0.0 0.0 0.0 0.0 0.0 0.33 SE 0.007 0.14 0.23, 0.02 0.0 0.0 0.0 0.0 0.0 0.39 SSE 0.008 0.15 0.37 0.07 0.03 0.01 0.0 0.0 0.0 0.63 0.009 0.17 0.77 0.30 0.10 0.06 0.0 0.0 0.0 1.40 SSW 0.006 0.12 1.13 0.71 0.26 0.11 0.0 0.0 0.0 2.33 SW 0.005 0.10 0.99 0.66 0.27 0.13 0.0 0.0 0.0 2.35 WSW 0.005 0.09 0.46 0.19 0.04 0.0.
0.0 0.0 0.0 0.79 W
0.004 0.07 0.20 0.07 0.01 0.0 0.0 0.0 0.0 0.35 WNW 0.005 0.10 0.26 0.07 0.01 0.0 0.0 0.0 0.0 0.42
(
NW 0.003 0.05 0.29 0.15 0.05 0.01 0.0 0.0 0.0 0.55 NNW 0.005 0.09 0.52 0.34 0.05 0.01 0.0 0.0 0.0 1.01 SUB-TOTAL 0.12 2.34 12.12
- . 39 0.92 0.34 0.0 0.0 0.0 20.11 6542 stability class r occurrences out of total 32723 valid temperature difference readings.
i 6461 valid wind directie.i/ wind speed readings out of total 6542 stability class T occurrences.
All columns and cals total 100 percent of net valid readings.
- Meteorological facility located 0.74 alles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
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SQN ODCM Revision 24 Table 1.2 (7 of 7)
(
JOINT PERCENTACE TREQUENCIES OF WIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan. 1. 72 - Dec. 31. 75 Stability Class 0 Delta T > 4.0 de8. C/100m Wind Speed (sph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm
_1.4 3.4 5.4 7.4 h 18.4 24.4
>24.5 Igg,11 N
0.003 0.06 0.33 0.09 0.0 0.0 0.0 0.0 0.0 0.48 NNE 0.005 0.10 1.03 0.20 0.0 0.0 0.0 0.0 0.0 1.33 NE 0.005 0.09 0.74 0.12 0.0 0.0 0.0 0.0 0.0 0.95 ENE 0.007 0.13 0.42 0.02 0.0 0.0 0.0 0.0 0.0 0.57 E
0.007 0.14 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.33 ESE 0.006 0.11 0.08 0.01 0.0 0.0 0.0 0.0 0.0 0.20 SE 0.005 0.09 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 SSE 0.008 0.16 0.21 0.0 0.01 0.0 0.0 0.0 0.0 0.37 S
0.006 0.11 0.39 0.04 0.02 0.0 0.0 0.0 0.0 0.55 SSW 0.003 0.06 0.48 0.32 0.06 0.01 0.0 0.0 0.0 0.89 SW 0.002 0.03 0.44 0.42 0.0 0.0 0.0 0.0 0.0 0.95 WSW 0.001 0.01 0.11 0.07 0.0 0.0 0.0 0.0 0.0 0.19 W
0.002 0.03 0.08 0.02 0.0 0.0 0.0 0.0 0.0 0.13 WNW 0.001 0.01 0.03 0.01 0.0 0.01 0.0 0.0 0.0 0.06 NW 0.001 0.02 0.06 0.03 0.0 0.0 0.0 0.0 0.0 0.11
(
NNW 0.001 0.02 0.08 0.03 0.0 0.0 0.0 0.0 0.0 0.13 SUB-TOTAL 0.06 1.17 4.74 1.39 0.09 0.2 0.0 0.0 0.0 7.41 2379 stability class G occurrences out of total 32723 valid temperature difference readings.
1378 valid wind direction / wind speed readings out of total 2379 stability class G occurrences.
All columns and calm total 100 percent of not valid readings.
- Meteorological facility located 0.74 Miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
'dind instruments 33 feet above ground.
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Aevision 24
(
Page 89 of 156 Table 1.3 SQN - OTTSITE RECEFTOR LOCATION DATA DISTANCE x/Q D/Q POINT from plant (s/m')
(1/m')
(e)
Site Soundary N
950 5.12E-06 1.29E-08 Site Boundary NNE 2260 1.93E-06 5.28E-09 Site boundary NE 1910
- 2. 32E-06 6.33E-09 Site boundary ENE 1680 1.12E-06 2.64E-09 Site Boundary E
1570 7.10E-07 1.46E-09 Site Soundary ESE 1460 7.91E-07 1.58E-09 81te Boundary SE 1460 9.14E-07 2.41E-09 Site Soundary SSE 1550 1.34E-06 3.23E-09 Site Soundary 5
1570 2.37E-06 4.18E-09
$1te Boundary SSW 1840 4.51E-06 9.26E-09 Site Boundary SW 2470 1 38E-06 2.63E-09 Site Boundary WSW 910 2.93E-06 3.86E-09 Site Boundary W
670 3.63E-06 3.74E-09 Site Boundary WNW 660 2.49E-06 2.44E-09 Site Boundary NW 660 2.85E-06 3.67E-09 Site Boundary NNW 730 3.95E-06 6.59E-09 Liquid Discharge S
870 N/A N/A i
NOTE: For quarterly airborne dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.
a l
l l
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SQN ODCM Revision 24 Page 90 of 156 Table 1.4 i
DOSE TACTORS FOR SUBMERSION IN NOB 1.E CASES A
Submersion dose Air dose t
ares /yr per pCi/m' arad/yr per pC1/m' DFBi DTS.
DFyi DT3i Kr-83m 7.56 E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 l
Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Reference Regulatory Guide 1.109. Table B-1.
Reformatting / Repagination changes only 01461 O
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SQN ODCM Revision 24 Table 1.5 (Page 1 of 2)
(
RADIDACTIVE CASEQUS EFTLUENT MONITORING INSTRUMENTATION Minimum Channels Applic-Instrument OPERABLE ability Action 1.
WASTE GAS DISPOSAL SYSTEM s.
Noble Gas Activity Monitor 1
40 b.
Effluent System Tiow Rate Measuring Device 1
41 2.
CONDENSER VACUUM EXEAUST SYSTEM a.
Noble Gas Activity Monitor 1
42 b.
Flow Rate Monitor 1
41 3.
$!!! ELD BUILDING EXHAUST SYSTLM a.
Noble cas Activity Monitor 1
42 b.
todine Sampler 1
44 c.
Particulate Sampler 1
44 d.
Flow Rate Monitor 1
41 e.
Sampler Flow Rate Monitor 1
41 4.
AUXILIARY SUILDING VENT!!ATION SYSTLM a.
Noble Gas Activity Monitor 1
42
(
b.
Iodine Sampler 1
44 c.
Particulate Sampler 1
44 d.
Tiow Rate Monitor 1
41 e.
Sampler Flow Rate Monitor 1
41 6.
SERVICE BUILDING VENTILATICN SYSTLM a.
Noble Gas Activity Monitor 1
42 b.
Tiow Rate Monitor 1
41 i
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SQN ODCM Revition 24 Page 92 of 156
(
Table 1.5 (Page 2 of 2)
RAD 10 ACTIVE CASEOUS EFTLUENT MONITORING INSTRLY.ENTATION TABLE NOTATION R24 At all times.
R24
- e During shield building exhaust system operation.
ACTION 40 - With the number of channels OPERABLE less than required by R24 the Minimum Channels OPERABLE requirement, the contents of R24 the tank (s) may be released to the envirorument provided that prior to initiating the releases
- a. At least two independent samples of the tank's contents are analysed, and
- b. At least two technically qualified members of the Tacility Staff independently verify the release rate calculations and discharge valve lineupt otherwise, suspend release of radioactive effluents via this pathway.
ACTION 41 - With the number of channels OPERABLE less than required by R24 the Minimum Channels OPERABLE requirement, effluent R24 releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 42 - With the number of channels OPERABLE less than required by
(
R24 the Minimum Channels OPERABLE requirement, of fluent R2h releases via this pathway may continue provided grab samples are tabn at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analysed for noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 44 - With the number of channels OPERABLE less than required by R24 the Minimum Channels CPERABLE requirement, ef fluent R24 releases via the affected pathway may continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> af ter the channel has been declared inoperable samples art continuously collected with auxiliary sampling equipment as required in Table 1.1.
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.L A
SQN ODCM Revision 24 Table 1.6 (Page 1 of 2)
(
RADICACTIVE CASEOUS ETTLUENT MONITORING INSTRUMENTATION SURVEILIANCE REQUIREMENTS MODES CHANNEL in which CHANNEL TUNC-surveil-CRANNIL SOURCE CALIBRA-TIONAL lance jnstrument
$ HECK CHECK T10N TEST Recuired
- 1. WASTE GAS DISPOSAL SYSTEM
- a. Noble ces Activity Monitor P
P R(3)
Q(1)
- b. Flow Rate Monitor D
N.A.
R Q
- 2. CONDENSER VACUUM EXHAUST SYSTEM
- a. Noble Cas Activity Monitor D
M R(3)
Q(2)
- b. Flow Rate Monitor D
N.A.
R Q
- 3. SHIELD BUILDING EXHAUST SYSTEM
- a. Noble Cas Activity Monitor D
M R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
R Q
- 4. AUXILIARY BUILDING VENTILATION SYSTEM
(
- a. Noble Gas Activity Monitor D
M R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler k
N.A.
N.A.
N.A.
- d. Tiow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
R Q
- 5. SERVICE BUILDING VENTILATION SYSTEM
- a. Noble cas Activity Monitor. D M
R(3)
Q(2)
- b. Tiow Rate Monitor D
N.A.
R Q
i l
l l
l
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-:] N'M - -
ENM
SQN ODCM Revision 24 Page 94 of 156 Table 1.6 (Page 2 of 2)
(
RADI0 ACTIVE CASE 00S EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLt. NOTATION P = Completed prior to each release R e At least once per 18 months Q = At lease once per 92 days i
D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A. = Not Applicable M = At least once per 31 days At all times.
R24 During shield building exhaust system operation.
- During waste gas releases.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic R24 isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Downscale failure.
(2) The CHANNEL TUNCTION TEST shall also demonstrate that control room R24 alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levela above the alarm
(
setpoint.
- 2. Circuit failure.
)
- 3. Downscale failure.
For the auxiliary building ventilation system, at least once every 18 months, the CHANNEL TUNCTIONAL TEST shall also demonstrate R24 automatic isolation of this pathway if the following condition exists:
Instrument indicates measured levels above the alarm / trip setpoint.
(3) The initial CHANNEL CALIBRATION shall be performed usirig one or R24 l
more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in seasurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CRANNEL CALIBRATION, sources _that have been related to R24 i
'the initial calibration shall be used.
R24 R24 R24 R24
\\
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e
Pese 95 of 156
(
Table 1.7 SECTOR E1.EMENTS CONSIDERED FOR POPULATION DOSES Range of Midpoint of Sector Element Sector Element Site boundary - 1 mile 0.8 mile 1-2 miles 1.5 miles 2-3 miles 2.5 miles 3-4 miles 3.5 miles 4-5 miles 4.5 miles 5 - 10 miles 7.5 miles I
10 - 20 miles 15 miles 20 - 30 miles 25 miles 30 - 40 miles 35 miles 40 - 50 miles 45 miles I
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l SQN ODCM Revision 24 Fage 96 of 156
(
Tcble 1.8 POPULATION WITHIN EACH SECTOR ELLMEhT Sector Midpoint (miles) 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N
20 41 213 129 66 1784 5453 3470 2610 11145 NNE O
30 123 182 62 600 10628 4910 8250 10625 NE O
O 67 67 94 581 2884-6998 7047 18080 ENE 0
11 24 222 300 773 4707 3747 29477 18679 E
O 70 11 191 137 918 17440 6808 5072 4129
)
ESE O
118 113 194 137 1849 46521 5044 1896 13624 SE O
179 322 168 205 1507 6005 5461 15641 3417 SSE O
125 370 750 601 2347 13242 8596 34279 11640 S
0 67 143 229 811 3930 28008 26690 19642 11622 SSW 0
82 140 400 170 8927 96966 55597 21349 11978 SV 0
10 306 634 194 9787 94225 23455 11641 11109
(
i WSW 20 190 642 1124 1669 19089 28405 4106 15071 9548 W
10 20 233 657 657 5225 1580 6350 5699 7707 WNW 10 30 365 598 598 2622 6540 4920 6699 2450 NW 50 80 292 569 336 2696 1410 1750 1217 15856 NNW 10 263 80 75, 213 1610 471 3130 2835 5719
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SQN ODCM Revision 24 Page 97 of 156
(
Table 1.9 (1 of 8)
INCEST 10N DOSE TACTORS (ares /pci in8ested)
ADULT bone liver t body thyroid kidney lung 31-111 j
g k.05E 1.05E-07 l1.05E-07 '1.05E-07 B-3 1.0$E-07 1.0$E-07 1.05E-07 C-14 2.84E-06 5.68E-07: 5.48E-071 5.68E-07 5.68E-0? 5.68E-07 5.68E Na-24 1.70E-06 !1.70E-06: 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 l
P-32 1.93E-04!1.20E-05 7.46E-06 0.00E+00 0.00E*00 0.00E+00 2.17E-05 j
Cr-51 0.00E+00 l0.00E+00! 2.66E-09 1.59E-09.5.86E-10 3.53E 6.69E-07 Mn-54 0.00E+00 :4.57E-06l 8.72E-07: 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Mn-56 0.00E+00 1.15E-07i2.04E-08 0.00E+00 1.46E 0.00E+00 L3.67E-06
?
Te-5:i 2.75E-06 1.90E-06I 4.43E-07.0.00E+00 -0.00E+00 1.06E-06 1.09E-06 Te-59 4.34E-06 1.02E-05 3.91E-06' O.00E+00 0.00E+00 2.85E-06 3.40E-05 Co-57.
0.00E+00 1.75E-07 12.91E-07l 0.00E+00 0.00E+00' O.00E+00 4.44E-06 Co-58 0.00E+00 7.45E-07l1.67E-06' O.00E+00 0.00E+00 0.00E+00 1.51E-05 u
Co-60 _.0.00E+00.2.14E-04.14J 2E-06; 0.00E+00 0.00E+00 -0.00E+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 Ni-65 5.2BE-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Cu-64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.8LE-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00- 9.70E-06 2n-69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00. 2.96E-09
\\
Zn-69m 1.70E-07 4.08E-07 3.73E-08 0.00E+00 2.470 07 0.00E+00 2.49E-05
\\
Br-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00h00. 0.00E+00.2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 ~ 0.00E+00 5.79E-08 Br-84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13
(
Br-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-08 3.21E 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 Sr-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Fr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.00E+00 2.20*-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.6*E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91m 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00' O.00E+00 2.67E-10 Y-91 1.41E-07' O.00E+00 3.7)E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 '1.48E-05' Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 -8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 '5.12E-10 0.00E+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-49 0.00E+00 3.42E-09 0.00E+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-1F 0.00E+00 4.87E-08 30-99 0.00E+00 4.31E-06 ' 8.20E-07 ' O.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.03E+00 1.06E 48 3.42E-10' 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.39E 'J9 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08.0.00E+00 6.08E-09 0.00E+00' 1.99E-07 0.00E+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 As-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 Sb-124 2.80E-06 5.29E-08 1.11E-06 6.799-09 0.00E-00 2.18E-06 7.95E-05 Reformatting / Repagination changes only 01461 e
N
- y. _~ _ _ y f*
SQN ODCM Revision 24 Page 98 of 156 Table 1.9 (2 of 8)
(
E ESTION DC,95 FACTORS (ares /pci ingested)
ADULT bone 14ecc t body thyroid kidney
. lung 31-111-Sb-125
- 1. 79E-06 2.00E-Cd 4.26E-07 1.82E-09 0.00E-00 1.38E-06 1.97E-C5 Te-125m
- 2. 68E-06 9.71E-07 3 59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E Te-127 1.10E-07 3.95E-08= 2.38E-08 8.15E-08 4.48E-07' O.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09. 2.41E-02 1.32E-07 0.00E+00- 2.37E-CS Te-131m
- 1. 73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E<00 8.40E-C5 Te-131
- 1. 9 7E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I-130 7.56E-07. 2.23E-06 8.80E-07 1.8 9E-04 3.48E-06 0.00E+00 1.92E-06 I-131-4.16E-06 5.95E-06 3.41E-06. 1.95E-03' 1.02E-05 0.00E+00 1.57E-C6 I-132 2.03E-07 5.43E-07 1.90E-07
- 1. 90E-05 8.65E-07 0.00E+00 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 I-134 1.06E-07 2.38E-07 1.03E-07. 4.99E-06 4.58E-07 0.00E+00 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.4BE-04 1.21E-04 0.00E+00 4.79E-05 1.59E 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-Oi 0.00E +00 3.70E-05 1.23E-05'- 2.11E-06 Cs-138 5.52E-08 1.09E-07 5'.~40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05
(
Ba-141
- 4. 71E-08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11. 3.00E-26 14-140 2.50E-09 1.26E-09.3.33E-10 0.00E+00 'O.00E+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 0.00E+00 0.00E+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 ' 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09
- 7. 27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E 08~ 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10. 0.00E+00 2.40E-05 Referencess Regulatory cuide 1.109 Table E-11.
l~
Dose Factors for Co-57. En-69e, Br-82 Nb-97, $b-124 and Sb-125 are from NUREG-0172 Aae Soecific Radiation Dose Counitment Factors for a One Year ghronic Intake., November, 1977, Table 4 I
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
.M.::.
Reformatting / Repagination changes only 01461 L
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1 SQN ODCM Revision 24 Page 99 of 156 Table 1.9 (3 of 8)
(
INCEST 10N DOSE TACTORS l
(ares /pCi ingested)
TEEN bone-liver t body thyroid kidney lung 31-111 E-3 1.06E-07 1.06E-07 1.06E-07 l.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 1
Na 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 1.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 0.00E+00 0.00E+00 3.60E-09 1.00E-09 7.89E-10 5.14E-09 6.05E-07
-Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00.1.76E-06 0.00E+00 1.21E-05 Mn-56 0.00E+00 1.58E-07 1.81E-08 -0.00E+00 2.00E-07 0.00E+00 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 0.0CE+00 0.00E+00 1.70E-06 1.16E-06 Te-59 5.87E 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 Co-57 0.00E+00 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 Co-60 0.00E+00,t.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 i
Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00: 0.00E+00 1.99E-06 N1-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E '
Cu-64 0.00E+00 -1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E 0.00E+00 8.47E-06 2n-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16 E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00 3.11E-05 Br-82 0.00E+00 0.00E+00 -3.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00. 0.00E+00 0.00E+00 l
Br-85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Rb-86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E Rb-88 0.00E+00. 8.52E-08 4.54E-08 0.00E+00~ 0.00E+00 0.00E+00 7.30E Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 Sr-89 4.40E-04 0.00E+00 -1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00~ 2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00. 0.00E+00 3.66E-05 Sr-92 3.0$E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y-90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00. 0.00E+00 1.13E-04 Y-91m 1.29E-10 0.00E+00. 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09.0.00E+00 0.00E+00- 0.00E+00. 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.0!E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 2r-97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12. 0.00E+00 2.14E-11 0.00E+00 4.37E-07 Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 Te-99s 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Te-101 3.60E-10 '5.12E-10 5.03E-09 0.00E+00 9.26E 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00
- 8. 99F.-07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.00E+00 5.45E-05 l
Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78J-09 0.00E-00 3.38E-06 7.80E-05 Reformatting / Repagination changes only 01461
~
.i M W G iU ~?? M % d hfaW 4 7 -
.. mM.c
- Wik, a
~a-
SQN ODCM Revision 24 Page 98 of 156 i
Table 1.9 (2 of 8)
(
INOESTION DOSE FACTORS (aree/pci ingested)
ADULT bone liver t body thyroid kidney lung gi-111 Sb-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.00E-00 1.38E-06 1.97E-C5 Te-125m 2.68E-0A 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 S.15E-08 4.48E-07 0.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 Te-129 L.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07' O.00E+00 2.37E-CS Te-131m
- 1. 73E-06 8.46E-07 7.05 E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-C5 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 i
Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 1-130 7.56E-07 2.23E-06 8.f?E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 1-131-4.16E-06 5.95E-06 3.41E-04_ 1.957-03 1.02E-05 0.00E+00 1.57E-C6-1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E.00 1.02E-07 1-133 1.42E-06 2.47E-06.7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 6
1-134 1.06E-07 2.88E-07 -1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10' I-135 4.43E-07 1.16E-06 4.28E-07.-7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06. 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-01 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138
'5.52E-08 1.09E-07 5'.10 E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84 E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05
(
Ba-141
- 4. 71E-08 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.07E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09. 0.00E+00 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E 0.00E+00 0.00E+00 0.00E+00.4.25E Ce-141 9.36E-09 6.33E-09 7.18E-10 0.00E+00 - 2.94E 0.00E+00. 2.42E-05 a
Ce-143 1.65E-09 1.22E-06 1.35E-10 0.00E+CO. 5.37E-10 0.00E+00 4.56E-05 i
Ce-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04
~ l Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09: 0.00E+00 4.03E-05 i
Pr-144 3.01E-11 1.25E-11 1.53E-12 0.00E+00.7,05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09
- 7. 27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00. 0.00E+00 2.82E Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 Referencest Regulatory Guide 1.109. Table E-11.
Dose Factors for Co-57. En-69m. Br-82, Nb-97 Sb-124 and Sb-125 are from NUREG-0172 Ane-Specific Radiation Dose Commitment Factors for e One Year Chronic Intake., November,1977. Table 4 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
- -s e Reformatting / Repagination changes only 01461 N_
l
=
O *
- 4 e
.. ~
L Revision 24 Page 99 of 156 Table 1.9 (3 of A)'
INCESTION DOSE FACTORS l
(ares /pC1 ingested)-
l TEEN bone liver t body thyroid
-kidney lung 31-111 l
E-3 1.06E-07 '1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E 8.12E-07 8.12E-07l 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 0.00E+00 0.00E+00 0.00E+00 2..' 005 Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.b; 07 Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.211 **
Mn-56 0.00E+00' 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00- 1.04E-u.
Fe-55 3.78E 2.68E-06.6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 i
Te-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06_ 3.24E-05 Co-57 0.00E+00 2.38E-07 -3.99E 0.00E40 0.00E+00 -0.00E+00 4.44E-06 Co-58 0.00E+00- 9.72E-07 '2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E -Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 i
N1-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 N1-65
-7.49E-07 9.57E-08 4.36E-08 0.00E+00 v.00E+00 0.00E+00 5.19E-06 Cu-64~
0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00- 8.92E-06 2n-65 5.76E-06 2.00E-05 9.33E-06: 0.00E+00 1.28E-05 0.00E+00 8.47E-06 2n-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 2n-69m 2.40E-07 5.66E-07 5.19E-08 0.00E+00 3.44E-07 0.00E+00- 3.11E-05 Br-82 0.00E+00 0.00E+00 '3.04E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 - 0.00E+00 Br-84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Br-85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0 00E+00 4.41E-06 Rb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00' 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00- 5.24E-05 Sr-90 8.30E-03 0.00E+00 2.0$E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04
(
Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 '3.66E-05 Sr-92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y-90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00- 0.00E+00' O.00E+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 0.00E40 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.0$E-10 0.00E+00 0.00E+00 0.00E4 0 1.17E-04 2r-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 l-2r-97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00!.+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7.37E-11 1.83E-11 6.68E-12 0.00H+00 2.14E-11 0.00E+00 4.37E-07 Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00 b00 1.36E-05 0.00E40 1.08E-05 Tc-99a 3.32E-10 9.26t-10 1.20E-08 0.00.t+00 1.38'!-08 5.14E-10 6.08E-07 l
Te-101 3.60E-10 % 12E-10 5.03E-09 0.fiOL+00 9.ME-09 3.12E-10' 8.75E-17 tu-103 2.55E-07 0.00E+00 1-09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 0.0CE+00 2.75E-07 0.00E+00 1.76E-05 Ru-106 3.92E 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00E+00 1.88E-C4 Ag-110m 2.05E-07 1.94E-07 1.18E-07 0.00E40 3.70E-07 0.00E+00 5.4b5-05 Sb-124 3.87E-06 7.13E-08 1.51E-06 8.78J-09 0.00E-00 3.38E-06 7.80E-05 Reformatting / Repagination changes only 01451 b
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1 SQN ODCM Revision 24 Page 100 of 156
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Table 1.9 (4 of 8)
INGESTION DOSE FACTORS (arem/pci ingested)
TEEN bone liver t body thyroid kidney lung 31-111-j Sb-125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.00E+00 2.1EE-3G 1.93E-05 i
Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.00E+00 2.41E-05 3'
Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.00E+.'O 1.22E-05 i
Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.00Ed90 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E 0.00E~00 ' 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05.0.00E 00 9.39E-05 i
Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.00E+00 7.00E-05 1-130-1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.00E+00 2.29E-06 I-131 5.85E-06 8.19E 4.40E-06 2.39E-03 1.41E-05 0.00E+00 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.00E+00 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 -0.00E+00 2.58E-06 1-134 1 ~. 46 E-0 7 3.87E-07 1.39E-07 6.45E 6.10E-07 0.00E+00 -5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.2 7E-05 0.00E+00 1.8&E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 0.00E+00 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.19E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ba-140
- 2. uke-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4.38E-05
(
Ba-141 6.71E-08 5.01E 2.24E-09 0.00E+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.00E+00 0.00E+00 0.00E+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 0.00E+00 0.00E*00 0.00E+00 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 0.00E+00 4.18E-09.0.00E+00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07.0.00E+00' 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 0.00E+00 3.04E-09 0.00E+00 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01E-11.0.00E+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 -5.99E-09 0.00E+00 3.6LE-05 W-187 1.46E-07 1.19E-07 4.17E-08 0.00E+00 0.00E+00 0.00E+00 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 0.00E+00 2.67E-05
References:
Regulatory Guide 1.109, Table E-12.
Dose Factors for Co-57, 2n-69s, Br-82, Nb-97, Sb-124 and Sb-125 are f rom.
NUREG-0172 Are Specific Radiation Dose Commitment Factors for a One Year Chronic Intake., November, 1977, Table 4 NOTE: The tritium dose factor for bone is assumed to-be equal to the total body dose factor.
I su Reformatting / Repagination changes only 01461
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SQN'0DCM.
Revision 24 Page 101 of 156:
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Table 1.9 (5 of 8)
_ INCESTION DOSE TACTORS (ares /pCl ingested)
CHILD bone liver t body thyroid kidney lung gi-111 I-3 2.03E-07 2.03E-07 2,03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-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 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Or-51 0.00E+00 0.00E+00 8.90E-Oa 4.94E-09 1.35E-09 9.02E-09 -4.72E-07 Mn 0.00E+00 1.07E-05 '2.85E-06 0.00E+00 3.00E-06 0.00E+00 8.98E-06 3
Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00- 4.84E-05 Te-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 '1.13E-06 Fe-59 1.65E-05. 2.67E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E-06 5.51E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co-60 0.00%+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E+00 0.00E+00' O.00E+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E+00 1.15E-05 2n-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 i
2n-69 4.38E-08 6.33E-08 5.85E-09 0.00E+00 3.84E-08 0.00E+00 3.991-06 2n-69m 7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.e ;+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0 ;5+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00
(
Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00~ 4.31E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09' Rb-09 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 l
Sr-89 1,12E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 Sr-90 1.70E-02 0.00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04 i
Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 5.30E-05 Sr-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00. 1.71E-04.
Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 7.48 E-0 7 Y-91 6.02E-07 0.00E+00
- 1. ele-08 0.00E+00 0.00E+00 0.00E+00 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E-10 '0.00E+00 0.00E+00 0.00E+00 1.04E.l Y-93 1.14 E-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 2r-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00.2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.25E-08
- 8. 76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E )
Nb-97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 '4.35E-11 0.00E+00 1.21E-05 j
Mo-99 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 Tc-99s 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 -1.82E-04 l
As-110m 5.39E-07 3.64E-07 2.91E-07 0.00E+00 6.78E-07 0.00E+00. 4.33E 05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.455-08 0.00E+00 6.16E-06 6.94E-05 Reformatting / Repagination changes only 01461 o
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Revision 24 1
Page 102 of 156 j
Table 1.9 (6 of 8)
(
INCEST!0N-DOSE TACTORS l-(ares /pci ingested)1 CHILD bone liver t body thyroid kidney lung 31-111 l
i Sb-125 7.16E-06' 5.52E-C8 1.50E-06. 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 -3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 'O.00E+00 2.34E-05 Te-127 4.71E-07 1.27E-07 ~1.01E-07 3.26E-07' 1.34E-06 0.00E+00 1.S4E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00: 8.34E-06 Te-131m 7.20E-06 2.49E-06. 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00: 4.36E-07 Te-132' 1.01E-05 4.47E-06 ~ 5.40E-06 -6.51E-06 4.15E-05 0.00E+00.4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E 8.82E-06 0.00E+00 2.7)E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 I-132 8.00E-07. 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E 1.22E-05 0.00E+00 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 1-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04' 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E 3.67E-05 1.96E-06 t
Cs-138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E 2.40E-08 1.46E-07 l
Ba-139
-4.14E-07 2.21E-10 1.20E-08 -0.00E+00 l.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.00E+00'.2.37E-08 4.34E-08 4.21E-05
(
Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00%
5.09E-11. 3.70E-11 l.' 14E-0 9 La-140 1.01E-08 3.53E-09 1.19E-09. 0.00.sv 0.00E+00 0.00E+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.00E+00 0.00E+00 3.31E-05 Ce-141 3 97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E 0.00E+00~ 1.59E-09 0.00E+00 5.55E-05 i
Ce-144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 '6.49E-12.0.00E+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 l0.00E+00 0.00E+00 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 References i
l Regulatory Guide 1.109. Table E-13.
' Dose Factors ' for Co-57, Zn-69m, Br-82. Nb-97. Sb-124 and Sb-125 are f rom l
NUREG-0172 Are Specific Radiation Dose Commitment Factors for a One Year Chronic Intake., November,1677. Table 4 NOTE: The tritium' dose factor for bone is assumed to be equal to the total body dose factor.
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Page-103 of 156 Table 1.9 (7 of 8)
INGESTION DOSE TACTORS-(ares /pci ingested).
INTANT bone' liver t body thyroid kidney lung 31-111 i
E-3 3.08E-07 3.08E-07 3.08E-07 3.08E-07.3.08E-07. 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E 5.06E-06 5.06E-06 5.06E-06.5.06E-06 Ne-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 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr-51 0.00E+00 0.00E+00 1,41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.311-06 Mn-56 0.00E+00 8.18E-07 1.41E-07. 0.00E+00 - 7.03E-07 0.00E+00. 7.43E Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E 1 Te-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05. 2.57E-05 4>
Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00' O.00E+00- 0.00E+00- 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E 0.00E+00 0.00E +00 0.00E+0018.97E-06 Co-60 0.00E+00 1.08E-05 2.55E-05 0.00E+00 -0.00E+00 0.00E+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 -2.20E-05 0.00E+00 0.00E+00 0.00E+00. 1.95E-06 Ni 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.0!E-05 l
Co-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00F.+00 1.25E-05 2n-65 1~.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00.5.35E-05 i
In-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 '1.37E-05 Zn-69m 1.50E-06 3.06E-06 2.79E-07 0.00E+00- 1.24E-06 0.00E+00 4.24E-05 Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00. 0.00E+00
'Br-83 0.00E+00- 0.00E+00 3.63E-07.0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
Br-84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00-A I
Br-85 0.00E+00 0.00E+00 1.94E-Of 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
g Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00- 4.35E-06 Rb-88 0.00E+00 4.9BE-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07. 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 Sr-90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00. 0.00E+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00- 0.00E+00 0.00E+00.5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E-11 '0.00E+00 0.00E+00 0.00E+00~ 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 ' O.00E+00 0.00E+00 0.00E+00 8.10E-05.
Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00' O.00E+00 0.00E+00 1.92E-04 2r-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+C0 2.50E-05 2r-97 1.481-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00- 1.46E-05 Mb-97 4.09E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11. 0.00E+00 3.09E-05 Mo-9'9 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00= 1.12E-05 Tc-99m' ' 1.925-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 -2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Ru-105
- 1. 36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 Ru-106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E* 08 0.00E+00 1.34E 6.60E-05 Reformatting / Repagination changes only 01461 j
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-l Revision 24 l
Page 104 of 156 Table 1.9 (8 of 8).
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INCEST!0N DOSE TACTORS (area /pci in6ested) j INFANT I
bone liver t body thyroid kidney lung 3 -111 1
Sb-125 1.23E-05. 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 1.00E-06
- 3. 35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 l
Te-129s 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 ' 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+00 2.27E-05 Te-131m 1.52E-05: 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E 4.94E-08 1.5?E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 I-131-3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 1-132' 1.66E-06 3.37E-06 1.20E-06 '1.58E-04 -3.76E-06 0.00E+00 2.73E-06
- l I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03: 2.14E-05 0.00E+00 3.08E-06 I-134 8.69E-07
- 1. 78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06
}
I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.voE+00 2.62E-06' Cs-134 3.77E-04 7.03E-04 7.10E-05 0.00E+00 1.81E-04 7.42E-05 '1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E -05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1=.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 0.00E400 3.90E-07 6.C9E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E 0.00E+00 - 3.51E-101 3.54E-10 -5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05
(
Ba-141 4.25E-07 2.91E-10 1.34E-08 0.00E+00 '1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06K-09 0.00E+00 8.81E-11 -9.26E-11 7.59E-07 La-140 2.11E-Og m.322-Gy-2.14E-09 0.00E+00. 0.00E+00 - 0.00E+00. 9.77E-05 La-142 1.10E-09 4.041-1C 9.67E-11. 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 a.80E-08 5.65E-09. 0.00E+00 1.48E-OS 0.00E+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00' 5.73E-05 Ce-144 2.98E-06
- 1. 22E-06 1.67E 0.00E+00 4.93E-07 0.00E+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 i
Pr-144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 0.00E+00 4.93E-06 i
Nd-147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 -0.00E+00 3.60E-05 W-187 9.03E-07
- 6. 28E-07 2.17,E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00,2.87E-05 Refs'rences Re8ulatory Guide 1.109. Table E-14.
Dese Factors for Co-57. En-69m. Br-82. Nb-97. Sb-124 and Sb-125 are f rom NUREG-0172 Aae Specific Radiation Dose Comunitment Factors for a One Year Chronic Intake.. November, 1977, Table 4.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
las a Reformatting / Repagination chan8es only 01461 A_
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SQN ODCM Revision 24 Page 105 of 156
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Table 1.10 (1 of 3)
RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSTER' DATA 7
Balf-Life A
Bv F=i Foi Fri i
(minutes) (1/s)
E-3 6.46E+06 1.79E-09.
(cow)
(goat)
(beef)-
4.80E+00 1.00E-02
- 1. 70E-01 1.20E-02 l
r C-14 3.01E+09 3.8&E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06 t+04. 5. 61 E-0 7 -
1.10E+00-2.50E 2.50E-01 4.60E-02 Cr-51 3.99E+04
- 2. 90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02.
Fe-59 6.43E+04 1.80E-07 6.60E-04 1,. 20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09=
9.40E 1.00E-03 1.00E-03 1.30 -02 Ni-63 5.27E+07 2.19E-10 1.90E-02
- 6. 70E 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E 1.90E-02 6.70E-03 6.70E-03 5.30E,
Cu-64 7.62E+02 1.52E-05
'1.20E-01 1.40E-02 1.30E-02 9.70E-04 l
Zn-65 3.52E+05 3.28E-08 4.00E 3.90E 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.00E 3.90E-02
- 3. 90E-02 3.00E-02 In-69 5.56E+01 2.08E-04 4.00E-01' 3.90E-02 3 90E-02 3.00E-02 Br-82 2.12E+03 '5.45E-06
~7.60E-01 5.00E-02 6.00E-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-84 3.18E+01' 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86
'2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02
(
Rb-88 1.78E+01 6.49E-04.
1.30E-01 3.00E-02 3.00E 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 St-89 7.28E+04 1.59E-07
.1.70E-02
'1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 St-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 2r-95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 ' 2.80E-01 Nb-97 7.21E+01 1.60E-04
-9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03
/.50E-03 1.10E-03' Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Ru-103 5.67t+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E 4.00E-01 As-110m.3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 1,.;
Reformatting / Repagination changes only 01461 9g 3 g,,,,
_ ggjpgw, 4%[
_m.
SQN ODCM Revision 24 Page 106 of 156
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=
Table 1.10 (2 of 3)
" RADIONUCLIDE DECAY AND' STABLE ELEMENT TRANSFER DATA
-Balf-Life K
Bv Fi F.i Fe s :
i (minutes)
(1/s)
(cow)
(goat)
(beef)
Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46 E+06 7.91E-09 N/A 1.50E 1.50E-03 N/A' Te 125m 8.35E+04
- 1. 38E-0 7 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03
-1.00E-03
'.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-031 1.00E-03 1.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00-1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80E+03~ 6.42E-06 1.30E+00 1.00E-03
~1.00E-03 7.70E-02 Te-131 2.50E+01 4.62E-04.
1.30E+00 1.00E-03 1.00E-03.
7.70E-02 Te-132 4.69E+03.
2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 i
'!-130 7.42E+02 1.56E-05 2.00E 1.20E-02 4.30E-01 2.90E-03 1-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 14.30E-01.
2.90E-03' I-134 5.26E+01 2.20E-04 2.00E-02
.1.20E-02 4.30E-01 2.90E-03 I-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03
-3.00E-01 1.50E-02 Cs-136 1.90E+04 6.08E-07 1.00E-02 8.00E-03.
3.00E-01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.00E '3.00E-01 1.50E-02 Cs-138 3.22E+01 3.59E 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31E+01 1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-140- 1.84E+04
- 6. 28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E-04 4.00E 3.20E-03
(
Ba-14 2 -
1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03.12-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E 5.00E 2.00E-04 Co-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-143 1.9BE+03 5.83E-06 2.50E-03 1 ~. 00 E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E 4.70E-03 Nd-147 1.58E+04
- 7. 31E-0 7 2.40E-03 5.00E-06.
5.00E-06
.3.30E-03 l
W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E '
Np-239 3.39E+03 3.41E-06 2.30E-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A.
N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A' N/A Er-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 N/A N/A
- N/A N/A Kr-88
- 1. 70E+02 6.79E-05 N/A N/A N/A N/A Kr-8.9 - _3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90_..5.39E-01 2.14E-02 N/A N/A.
N/A N/A Xe-131m 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-133m 3.15E+03 3.67E-06 N/A N/A
-N/A N/A
,~ c Reformatting / Repagination changes only 01461
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..i
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" 4 %.*d1%. " ' -
Page=107 of 156 Table 1.10 (3 of 3)
., (
" RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSTER DATA Ealf-Life K
Biv F.i Fi Fri (sin.ites ) -
(1/s)
(cow)
(goat)
(beef) i I Ke-133 7.55E+03
~1.53E-06 N/A N/A-N/A N/A' i-Ke-135m 1.54E+0L 7.50E-04 N/A N/A N/A N/A1 Xe-135 5.47Es02 2.11E-05 N/A N/A N/A
-N/A Xe-137 3.83E+00 3.02E N/A N/A N/A N/A Ae-138 1.41E+01 8.19E-04 N/A N/A N/A N/A References Balf lives for all nuclides: DOE-TIC-11026. " Radioactive Decay Data Tables - A handbook of Decay Data for Application to Radiation Desimetry and Radiological Assessment," D. C. Kocher, 1981.
Transfer factors for Sb-isotopes are from ORNL 4992, " Methodology--
for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.
Cow-milk transfer factors for. Iodine;' Strontium, and Cesium nuclides are from NUREC/CR-1004,-Table 3.17.
coat-milk transfer factors for Iodine nuclides are from NUREG/CR-1004, Table 3.17.
(
Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides.are from NUREG/CR-1004. Table 3.18.
All other nuclides' transfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2.
~
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SQN ODCM Revision 24 Page 108 of 156 Table 1.11 (1 of 2)
(
DOSE CALCULATION FACTORS.
Tactor Value Units Reference BR. (infant) 1400 m*/ year _
ICRP 23 BR. (child) 5500.
m'/ year ICRP 23 BR. (teen) 8000 m*/ year ICRP 23 l
BR. fedult) 8100 m*/ year ICRP 23 f-1 TVA Assumption.
ft 1
R. C.1.109 (Table E-15 )
f, 1
TVA u sumption f.
O TVA Assumption-B 9
g/m' TVA Value i
K.
0.072
.L/kg2hr R. G.1.109 (Section 2.C. )
M 40 kg/m R. G.1.109 (Section 2.C. )
P 240 kg/m' R. C.1.109 '(Table E-15):
Qr (cow) 64 kg/ day NUREG/CR-1004 (Sect. 3.4)
Qr (goat) 08 kg/ day NUREG/CR-1004 (Sect. 3.4) r 0.47 NUREC/CR-1004 (Sect. 3.2) t.
4.73E+08' seconds R. G.1.109 (Table E-15 )
(15 years).
t..
7.78E+06 seconds.
SQN TSAR Section 11.3.9.1 (90 days) tear 1.56E+07 seconds
- SQN TSAR Section 11.3.9.'1 (180 days) t.
5.18E+06 seconds.
R. C.1.109 (Table E-15)
(60 days)
(
t.,
2.59E+06 seconds R..G. 1.109 (Table E-15)
(30 days) t..r 7.78E+06 seconds R. G.1.109 (Table E-15 )
(90 days) tr.
8.64E+04 seconds SQN TSAR Section 11.3.9.1 (1 day) tn.
8.64E+04 seconds NUREC/CR-1004 Table 3.40 (1 day) t.
1.12E+06 seconds NUREC/CR-1004. Table 3.40' (13 days) tav 2.38E+07 seconds SQN TSAR Section 11.3.9.1 (275 days)
U.. (infant) 0 kg/ year R. G. 1.109-(Table E-5)
U.. (child) 41 kg/ year R. G.1.109 (Table E-5 )
U.. (teen) 65 kg/ year R. G. 1.109 (Table E-5)
U.. (adult) 110 kg/ year R. G. 1.109 (Table'E-5) l U., (infant) 330 L/ year R. C. 1.109 (Table E-5)
'O.,(child) 330 L/ year R. G. 1.109 (Table E-5)
U.,(teen) 400 L/ year R. C. 1.109 (Table E-5)
U.,(adul-t) 310 L/ year ~
R. G.1.109 (Table E-5)
Reformatting / Repagination changes only
-01461 4
= -- Y M%4gMm&irc%Wm -
1-
SQN OCCM Revision 24 '-
Page 109 of 156 Table 1.11 (2 of 2)
(
DOSE CALCULATION FACTORS Tactor Value Units Reference Ur.(infant) 0 kg/ year R. C. 1.109 (Table E-5).
Ur.(child) 6.9:
kg/ year
.R. C. 1.109 (Table E-5)
Ur.(teen) 16 kg/ year R. C. 1.109 (Table E-5),
Ur.(adult) 21 kg/ year R. C. 1.109 (Table E-5)
Urt.'(infant) 0 kg/ year.
R. C. 1.109 (Table E-5)
.Urt. (child) 26 kg/ year R. C. 1.109 (Table E-5)
Urt. (teen)-
42 kg/ year R. C. 1.109 (Table E-5)
{
Urt. (adult)-
64 kg/ year R. C. 1.10 9 ('.'ab l e E-5 )
Us. (infant) 0 kg/ year R. C. 1.109-(Teble E-5)
Us. (child) 520 kg/ year R. C.-1.109 (Tablv E-5)
Us. (teen) 630
'kg/ year R. O.~1.109 (Table E-5)
Us. (adult) 520 kg/ year R. C. 1.109 (Table E-5)
U..(infant) 330 L/ year R. C. 1.109 (7able E-5)
'U..(child) 510 L/ year R. C.1.109 (T sble E-5 )-
U..(teen) 510-L/ year
- R. C. 1.109 (Table - E-5 )
U..(adult) 730 L/ year R. C. 1.109 (Table I-5)
W 0.3, none-
-R. C. 1.109 (Table A-2)'
Yr 1.85-kg/m NUREC/CR-1004 (Table 3.4) 3 Y,
1.18 kg/m' NUREC/CR-1004 (Table 3.3)
Yr 0.64 kg/m' NUREC/CR-1004 (Table 3.3) i Y.,
0.57 kg/m NUREC/CR-1004 (Table 3.4) 3 (value selected is for non-leafy vegetables)
- 1. (iodines) 7.71E-07 sec '
NUREG/CR-1004 (Table 3.10)
(
(10.4 d half-life)
R24 K. (particulates) 5.21E-07 see '
NUREC/CR-1004 (Table 3.10)
(15.4 d half-life)
R24 l
~l l
- .a Reformatting / Repagination changes only 01461 (U
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SQN ODCM Revision 24 Page 110 of 156 4
Table 1.12 (1 of 8) l C
INEALATION DOSE TACTORS i
(ares /pCi' inhaled)-
ADULT bone liver t body ~
thyroid kidney lung 31-111-B-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 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 1.2SE-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00- 0.00E+00 0.00E+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04' 9.67E-06 Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E-10-.1.18E-06 2.53E-06 Te-55 3.07E-06 2.12E-06 4.93E-07= 0.00E+00 0.00E+00 9.01E-06 7.54E Te-59 1.47E-06 3.47E-06 -1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 0.00E+00. 5.78E-10 8.48E-07 6.12E-06 l
2n-65 4.05E-06 1.29E-05 5.82E 0.00E+00 8.62E-06 1.08E-04 6.68E-06 i
2n-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 -1.15E-07 ' 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.38E-06 1.71E-05 Br-82 0.00E+00 0.00E+00. 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00. 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00r 00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13
(
Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1
Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19
'Rb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 -1.16E-21 Sr F.9 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 11.75E-04 4.37E-05 Sr 90 1.24E-02 0.00E+00 7.62E-04 0.00E+00. 0.00E+00 1.20E-03 9.02E-05
$r-91 7.74E-09 0.00E+00 3.13E-10 0.00E+004 0.00E+00.'4.56E-06 2.39E-05 Y
Sr 92 8.43E-10 0.00E+00 '3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09.0.00E+00' O.00E+00 2.12E-05 6.32E-05 f-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00. 0.00E+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 'O.00E+00' 0.00E+00 2.13E-04 4.81E-05 Y-92 1.29E-09 0.00E+00 3.77E-11'.0.00E+00 0.00E+00: -1.96E-06 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 ~6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6.77E-06. 2.21E-04 1.88E-05 2r-97 1.21E-08 2.45E-09 1.13E-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 '9.67E-07 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12. 2.56E-12 0.00E+00 8.18E-12 3.00E-07 3.02E-08
'Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99a 1.29E-13 3.64E-13 4.63E-12 0.00E +00 5.52E-12 9.55E-08. 5.20E-07 Tc-101' ' 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 '1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 A8-110m 1.35E-06 1.25E-06 7.43E-07 0.00E +00 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.4}E-09 0.00E+00 3.10E-04 5.08E-05 Reformatting / Repagination changes only
~
01461 (t
- _mmemm.mmase
' im J
..... ~.
. Revision 24 Page 111 of 156 i
Table 1.12 (2 of 8) i INHALATION DOSE TACTORS (mres/pci inhaled)-
ADULT j
bone liver t body thyroid kidney lung g1-111' j
5b-125 6.67E-06 7.44E 1458E-06 6475E-09 0.00t+00 2.18E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07' 5.84E-08 1.31E 1.55E-06 3.92E-05 8.83E-061 l
Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E 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 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 1.42E-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 b
Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E 47 2.30E-09
'i 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 0.00E+00 9.61E ;
I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 i
~
1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07. 0.00E+00.5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07' 2.69E-04 '3.23E-06 0.00E+00 1.11E-06 l
1-134' 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 '1.22E 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.0$E-06
'l Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 -0.00E+00. 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E-15 2.42E-07 1.45E-17
(
Ba-142 3.29E-12' 3.38E-15 2.07E-13 0.00;+00 2.8tt '.; 1.49E-07-'1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-G G.00E+00 0.00S+0C~ 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11' 9.65E-12 0.00E+00 0.0Ci+00 7.91E-07 2.64E-07 Ce-141 2.492-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-'143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 0.00E+00. 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.15E-09L0.00E+00 8i75E-09 4.70E-06 1.49E,
Reference Regulatory Guide 1.109. Table E-7.
Dose Factors for Co-57, 2n-69m. Br-82. Nb-97. Sb-124 and Sb-125 are from NUREG-0172 Aae Soecific Radiation Dose Commitment Feetors for a One Year i
' Chronic Intake. November 1977. Table 8.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
Reformatting / Repagination changes only 01461
(-
_ _ _ _ _. -...Rh ~ N '
- M - * -
5' 'O
f I
Revision 24 Page 112 of 156
(
Table 1.12 (3 of 8)
INHALATION DOSE FACTORS (ares /pci inhaled)
TEEN i
bone liver t body thyroid kidney lung g1-111 h
I-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 i
[
- 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 1.72E-06 1.72E-06 l
P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09' 2.62E-06 3.75E-07 Mo-54 0.00E+00' 6.39E-06 1.05E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+002 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 '7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E ;
Fe-59 1.99E-06 '4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.68E-04 1.19E-05 Co-60 0.00E+00 1.89E-06 2.48E-06 0.00E+00 0.00E+00' 1.09E-03 '3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00- 0.00E+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00' 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.68E-06 2n-65 4.82E-06 1.6 7E-05 7.80E-06 0.00E+00 1.08E-05' 1.55E-04 5.83E-06 2n-69 6.04E-12 1.15E-11 8.07E-13 0.00E+00 -7.53E-12 1.98E-07 3.56E-08 2n-69m 1.44E-09 -3.39E-09 3.11E-10 0.00E+00 2.06E-09 3.92E-06 ' 2.14E-05 Br-82 0.00E+00 0.00E+00 2.2BE-06. 0.00E+00 0.00E+00. 0.00E+00 0.00E+00 i
Br-83 0.00E+00 0.00E+00. 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Be-84 0.00E+00 0.00E+00' 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00
(
Br-85 0.00E+00. 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-88 0.00E+00 6.82E-08 3.40E-08 0.00E+00 ~0.00E+00 0.00E+00 3.65E-15 Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 - 0.00E+00 0.00E+00 4.22E-17 St-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04.0.00E+00 0.00E+00 2.06E 9.56E-05 Sr-91 1.10E-08 0.00E+00 4.39E 0.00E+00- 0.00E+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 '5.08E-11 0.00E+00 0.00E+00 '3.43E 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08. 0.00E+00 0.00E+00 3.66E-05 6.99E-05 Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.2IE-06 0.00E+00 ' 0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00- 5.36E-11 0.00E+00 0.00E+00 3'.35E-06 2.06E-05' Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 2r-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 2r-97 1.72E-08 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Nb-97
'3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-9.9 0.00E+00 2.11E-08 4.03E 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m., 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Te-101 7.40E-15 1.05E-14.1.03E-13 0.00E+00 1.00E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 0.00E+00 5.42E-11 0.00E+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 0.00E+00 1.55E-06 0.00E+00 2.38E-05 2.01E-03 1.20E-04 As-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-06 2.10E-06 1.22Er08 0.00E+00 4.81F-04 4.98E-05 Reformatting / Repagination changes only 01461
/...,
SQN ODCM Revision 24 Page 113 of 156 Table 1.12 (4 of 6)
(
INHALATION DOSE FACTORS (ares /pCi inhaled)
TEEN bone liver t body thyroid kidney lung 31-111 Sb-125 9.23E-06 1.01E-07 2.15E-06 8.80E-09. 0.00E+00 3.1.2E-04 1.24E-05 Te-125m 16.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 0.70E-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 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07= 2.02E-07 l
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 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00' 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06.0.00E+00 8.69E-07 Cs-134 6.28E-05.1.41E-04 6.86E-05 0.00E+00 4.69E-05: 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E 1.71E-05 0.00E+00 1.38E-05 2.22E 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 l
Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 -4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 I
Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14
(
Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6 09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-041 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E +00 3.86E-07 6.04E-05 ~2.67E-05 Pr-144 5.37E-12 2.20E 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 10.00E+00 6.28E-07 '4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.2'1E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05
Reference:
Regulatory cuide 1.109. Table E-8.
Dose Factors for Co-57. En-69s Br-82. Nb-97. Sb-124 and $b-125 are from
. NUREG-0172 Aae Specific Radiatir.n Dose Commitment Factors for a One Year Chronic Intake. November 1977. Table 8.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
,g Reformatting / Repagination chan6es only 01461 L
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SQN ODCM Revision 24 Table 1.12 (5 of 8)
(
INHA1.ATION DOSE TACTORS (aren/pci inhaled)
CHII.D bone liver t body thyroid kidney lung gi-111' H-3 3.04E-07 3.04E 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.0LE-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 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 -4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 L
Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 l
Mn-56 0.00E+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10 3.55E-06 3.33E-05=
Te-55 1.28E-05 6.80E-06 2.10E-06 0.00E+00 0.00E+00 3.00E-05 7.75E-07 Te-59 5.59E-06' 9.04E-06 4.51E 0.00E+00 0.00E+00 3.43E-04 1.91Z-05 Co 0.00E+00 2.44E-07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 0.00E+00' 4.79E-07 8.55E-07 0.00E+00 0.00E+00 2.99E-04 9.29E-06 Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 I
Ni-63 2.22E-04 1.25E-05 7.56E-00 0.00E+00 0.00E+00 7.43E-05
- 1. 71E-06 Ni 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu-64 0.00E+00 5.39E-10 2.90E-10 0.00E+00 1.63E-09 2.59E-06 9.92E-06 2n-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 -1.93E-05 2.69E-04 4.41E-06 2n-69 1.81E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E 2.75E-06 i
2n-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 i
Br-82 0.00E+00 0.00E+00- 5.66E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 Br-84 0.00E+00 0.00E+00 1.48E-07' O.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00
(
Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 -2.16E-06 I
Rb-88 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 0.00E+00 0.00E+00 5.11E St-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73 E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E 6.55E-05 Y-90 1.11E-06 0.00E+00- 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00- 7.60E 4.64E-07 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00 6.46E-06 6.46E-05 Y-93 5.04E-08 0.00E+00 1.38E-09 0.00E+00 0.00E+00 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.0$E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1.66E 1.00E-05' Nb-97 1.16E-10 2.08E-11 9.74E-12 0.00E+00 2.31E-11.9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 -0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 - 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00. 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 0.00E+00 4 57E-06 0.00E+00. 4.97E-05 3.87E-03 1.16E-04 As-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 a
Reformatting / Repagination changes only 01461 (m
19
~ ~.5 55 '
SQN ODCM Revision 24 Page 115'.of 156 Table 1.12 (6 of 8)
(
INHALATION DOSE FACTORS (arem/pci inhaled)-
CHILD bone-liver t body thyroid kidney lung 31-111 Sb-125 2.66E-05 2.05E-07c 5.59E-06 2.46E-08' O.0CE+00 6.27E 1.09E-05 Te-125m 1.82E-06 6.29E-07 '2.47E-07 5.20E-07 0.00E+00- 1.29E-04 9.13E-06 Te-127a 6.72E 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. t.65E-10. 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129a 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-131a 3.63E-08 1.60E-08 1.37E-08 2.64E-08.1.08E 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 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' O.00E+00 1.38E-06' I-131 1.30E-05' 1.30E-05 7.37E-06' 4.39E-03 2.13E-05 0.00E+00 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E 5.23E-05 1.69E-06. 0.00E+00' 8.65E-07 I-133-4.48E-06
- 5. 4 9E-06 ' 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.00E+00 2.5BE-07 I-135 1.33E-06 2.36E-06.1.12E-06 2.14E-04 3.62E-06 0.00E+00 11.20E-06 Cs-134 1.76E-04 2.74E-04 16.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E Cs-136-1.76E-05 4.62E-05 3.14E-05 0.00E+00 -2.58E-05 3.93E-06 '1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05= 9.78E Cs-138 1.71E-07 2.27E-071 1.50E-07 0.00E+00. 1.68E-07 1.84E-08 -7.29E-08
~
Ba-139 4.98E-10 2.66E 1.45E-11 0.00E+00- 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09. 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.00E+00 2.56E-14 7.89E-07.7.44E-08
(
Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15' 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 -0.00E+00' O.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E +00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 ~7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E <
Ce-143 9.89E-08 5.37E-08 7.77E-09 0.00E+00- 2.26E-08 3.12E-05: 3.44E Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12--8.10E-13 0.00E+00.2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 0.00E+00 1.30E-06' 8.87E-05 2.22E-05 i
W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00. 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.~ 57E-05 1.73E-05 k erence Regulatory Guide 1.109. Table E-9.
Dose Factors for Co-57, 2n-69m. Br-82 Nb-97, Sb-124 and Sb-125 are from
.NUREG-0172 Aae Soecific Radiation Dose Consnitment Factors for a One Year Chronic Intake. November 1977. Table 8.-
NOTE: The tritium dose factor for bone is assumed to be equal ~to the total body dose factor.
Reformatting / Repagination changes only 01461
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SQN ODCM_
Revision 24
'l Page 116 of 156 Table 1.12 (7 of 8)
C INEALATION DOSE FACTORS (area /pci' inhaled)
INFANT l
liver t body thyroid kidney lung ~
31-111 H-3 4.62E-07 4.62E-07 4.62E-07 4.62E-07. 4.62E-07 4.62E 4.62E-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 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 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr-51 0.00E+00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10 >09 1.58E-10.0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.382-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 0.00E+00 0.90E+00 7.25E-04 '1.77E-05 l
Co-57 0.00E+00 4.65E-07 4.58E-07 0.00Edo 0.0CE+00 2.71E-04 3.47E Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E40 0.00Ev00 5.55E-04 7.95E-06 Co 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 N1-65 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00- 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05~ 4.62E-04 '3.67E-05 2n-69 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 Zn-69m 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 Br-82 0.00E+00 0.00E+00' 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07.0.00E+00 0.00E+00 0.00E+00 0.00E+00
(
Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.00E+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.98E-07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 '2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89 2.84E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E-03 ~0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09.0.00E+00 2.79E-10 0.00E+00 0.00E+00_ 1.70E-05 1.00E-04 l
Y-90 2.35E-06 0.00E+00 '6.30E-08 0.00E+00 0.00E+00.1.92E-04 7.43E-05 Y-91m 2.91E-10 0.00E+00 9.90E-12.0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 'O.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E-08 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05.9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00- 5.46E-05 1.19E-04 Zr 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1;00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04' 9.05E-06 Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 i
Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101' 4.65E-14 5.88E-04 -5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 c
Ru-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 0.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 0.00E+00 2.93E-10. 0.00E+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 As-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 Sb-124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0.00E+00 1.89E-03 4.22E-05 Reformatting / Repagination changes only 01461
(
\\_
' ' ' ' ~
4 SQN ODCM Revision 24 Table 1.12 (8 of 8)
(
LNEALATION DOSE FACTORS (ares /pci inhaled)
INFANT-bone liver t body thyroid kidney lung g1-111
-Sb-125 3.69E 3.41E-07 7.78E-06 4.45E-08 0.00E+00 1.17E-03 1.0$E-05 i.
Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 Te-1273 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 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 l
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 2.5 9E-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 0.00E+00 1.42E-06 I-131 2.71E-05 3.17E 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00- 9.21E-07 I-135 -
2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137' 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-06 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14' 2.12E-06 3.39E-06
(
Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E La-140 3.61E-07 1.43E-07 ~ 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00: 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 '1.41E-06 -3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E-06. 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 -2.54E-03 Np-239 2.65 E-07 ~2.37E-08 1.34E-08.0.00E+00 4.73E-08 4.25E-05 1.78E-J5
Reference:
Regulatory Guide 1.109. Table E-10.
Dose Factors for Co-57, 2n-693,.Br-82. Nb-97, $b-124 and Sb-125 are from
' NUREG-0172 Are Specific Radiation Dose Conseitsent Factors for a One Year Chronic' Intake. November 1977, Table 8.
NOTE: The tritium dose factor for bone.is assumed to be equal to the total body dose factor.
Reformatting / Repagination changes only
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SQN ODCM Revision.24 Page 118 of 156 Table 1.13 (1 of 2)
(
,, EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED CROUht l
(ares /h per pCL/m*)
Nuclide
-Total Body Skin H-3 0.0 0.0 s
C-14 0.0 0.0 1
Na-24 2.50E-08 2.90E-08 L
P-32 0.0 0.0 i
Cr-51 2.20E 2.60E-10 Mn-54 5.80E-09 6.80E-09 Hn-56 1.10E-08 1.30E Fe-55 0.0.
0.0 Fe-59 8.00E-09 9.40E-09 A}
Co-57 1.77E-09 2.21E-09 Co-58' 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09.
4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09, 4.60E-09 2n-69' O.0 0.0 2n-69m 5.50E-09 6.59E-09.
Br-82 3.18E 3.90E-08, Be-83 6,40E-11 9.30E Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0
(
Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09
-4.00E-09 Rb-89~
1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09' l
Sr-92
.9.00E-09 1.00E-08 Y-90
.2.20E-12 2.60E i 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 2r-95 5.00E-09 5.80E-09 3r-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09' Tc-99m 9.60E-10 1.10E-09
.Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E Ag-110m 1.80E-08 2.10E-08 Sb-124 2.17E-08 2.57E-08
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SQN ODCM Revision 24 Page 119 of 156 Table 1.13 (2 of 2)-
(
EXTERNAL DOSE TACTORS TOR STANDING ON CONTAMINATED CROUND-(area /h per PCi/m')
Nuclide Total Body Skin Sb-125 5.48E-09 6.80E-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 Co-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09.
1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09
References:
Regulatory Guide 1.109. Table E-6.
l lDose Factors for Co-57, En-69u, Br-82. Nb-97, Sb-124 and ' Sb-125 are from i
Dose-Rate Conversion Factors for External Exposure to Photon and Electron I
Radiation f rom Radionuclides Occurrina in Routine Releases f rom Nuclear Fuel l
Cycle Facilities. D. C. Kocher, Bealth Physics Volume 38. April 1980.
s.'.
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Page 120 of 156.
Table 2.1 (Page-1 of 4)
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM J
Liquid Minimum Type of Lower Limit of Release Sampling Analysis Activity-Detection (LLD)
Type Frequency Frequency Analysis (pci/ml)*
A. Batch Waste P
P Release Each Batch Each Batch Principal 5x10*'
Tanks *'
Casuna Emitters'
- 1. Waste Con-densate I-131 1X10" Tanks (3)
- 2. Cask Decon-P M
Dissolved /
1x10-'
tamination One Batch /M Entrained Tank Cases (Camma Emitters)
- 3. Laundry-Tanks (2)
P M
H-3 1x10' Each Batch Composite *
- 4. Chemical Cross 1x10~'
Drain Tank Alpha
- 5. Monitor Tank
- 6. Distillate l
Tanks (2)
P Q
- 7. Condensate Each Batch Composite
- S r-P 9, 5x10
Domineraliser
' SrdJ Waste-Evaporator fe-55 1x10" Blowdown Tank (1)
B. Continucus D
W Principal 5x10-'
Releases' Grab Sample Composite
- Gamma Emitters'
- 1. Steam.
Generator"
'I-131 1x10*'
Blowdown M
M.
Dissolved /
1x10"
- 2. Turbine Grab Sample Entrained Cases-(Gamma Building" Emitters)
Sump -
D Composite
- M
.B-3 1x10" Grab Sample Gross Alpha 1x10
l D
Q Sr-89, 5x10" l
Crab Sample Composite *_ "
Sr-90 l-l Te-55 1x10" Reformatting / Repagination changes only 01461
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Revision 24 Page 121 of 156 Table 2.1 (Page 2 of 4)
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 3
Liquid Minimum Type.of Lower. Limit of Release Samp1!.ng Analysis.
Activity Detection (LLD).
Type Trequency Frequen'y Analysis (pCi/ml)*
C. Periodic W
Principal 5x10-'
Continuous Continuouss Composite
- Gasuna Releases
Emi t te rs '-
i I-131 1x10-*
- 1. Non-Reclaim-able Waste M8 M
Dissolved 1x10
Tank Grab Sample and Entrained Gases
- 2. High Crud (Cansna -
Tanks (2)
Emitters)-
M H-3 1x10
- 3. Neutralizer Continuous 8 Composite
- Tank Gross 1x10
Alpha Q
Sr-89, 5x10-'
Continuous 8 Composite
- Sr-90 Fe 1x10
s i
1 i
i
{
l.
l
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SQN ODCM Revision 24 Table 2.1 (Page 3 of 4)
Page 122 of 156--
(
RADICACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PRO TABLE NOTATION i
P = Completed prior to each release Q = At least once per 92 days D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A. = Not Applicable M = At least once per.31 days a The LLD is defined'for the purpose of these specifications as the smallest concentration'of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only a 51 probability of ' falsely concluding-that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
R24 4.66s.
LLD =
E V
2.22x10' Y
exp (-AAt)
Where:
in microcurie per unit mass or volume,LLD is the "a priori" lowe
- s. is the standard deviation of the background counting rate
(
or of the counting rate of a blank sample as appropriate (as counts per minute),
V is the sample size in units of mass or volume.E is the co microcurie,2.21x10' is ths number of disintegrations per minute per Y is the fractional radiochemical yield (when applica$le),
X is the radioactive decay constant for the particular radionuclide, and 61 from plant offluents is the elapsed time between aidpoint of sample collection and tipe of counting (midpoint).
It should be recognised that the LLD is defined as an a oriori (before the fact) limit representing the espability of a t measurement system and not an a costeriori (after tLe-limit for a particulate measurement.
fact) b
.is proportional to the quantity of liquid' waste. discharg which the method of sampling employed results in a specimen which is representative of the liquids released.
~
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SQN ODCM Revision 24 Table f. 1 (Page 4 of 6) kAD!0 ACTIVE LIQUID WASTE SAMPLING AND ANALYS!$ PROCRAM TABLE NOTATION e Prior to analyses, all su plan taken for the composite shall be throughly mixed in order..or the composite sample to be representative of the offluent release.
i l
d A batch release is tLe distharge of liquid wastes of a discrete vclume. Prior to sampl#.ng be analyses, each batch shall be isolated, end then thoroughly mixed, by the method described in Ser. tion 2.3.2, to assure representative sampling.
e /. conticuous release is the discharge of liquid wastes of a
-nondiscrete volumet e.g., from a volume of system that has an input flow during the continuous release.
i f The principal samma emitters for which th LLD specification applies d usively are the following radionuclits: Mn-54, ye-59, Co-58, j
Co-46, 2n-65 Mo-99, Cs-134. Cs-13 7, Ce4141. Co-144 shall also be measured with an LLD of 5x10**.
This list does not mean that only these nuclides are to be detected and reporten, Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
g ReleMes from these tanks are continuously coa. posited during releases. With the composite sampler or the sampler flow monitor inoperable, the sampling frequency shall be changed to require representative batch samples from each tank to be released to be taken prior to release and manually composite for these analyses, h Applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent radiation j
monitor previded the radiation monitor setpoint is at a LLD of i
11x10*' pCi/ml and allowing for bacsground radiation during periods when primary to secondary leakage is not occurring.
I-s S
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Revision 24 Page 124 of 156 Table 2.2 (Page 1 of 3)
RADICACTIVE LIQUID EFFLUENT MONITORINC INST 1tUMENTATION
(
Minimum i
Channels l
Instrument OPERABLE Action 1.
CROSS RADICACTIVITY MONITORS PROVIDING AUTOMATIC l
TERMINATION OF RELEASE a.
Liquid Radweste Effluent Line 1
30 b.
Steam Generator Slowdown Effluent Line 1
31 c.
Condensate Domineraliser Effluent Line 1
30 2.
CROSS RADICACTIVITY MON! TORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Essential Raw Cooling Water E! fluent Bender **
1 32 b.
Turbine Building Sump Ef fluent Line 1
32 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radweste Effluent Line 1
33 b.
Condensate Domineraliser Effluent Line 1
33 c.
Steam Generator Blowdown Effluent Line 1
33 l
d.
Cooling Tower Blowdown Effluent Line 1
33 4.
TANK LEVEL INDICATING DEVICE.*
l a.
Condensate Storage Tank 1
34 b.
Steam Generator layup Tank
- 1 34 5.
CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR a.
Condensate Demineraliser Regenerant Effluent Line 1
35 1
- Required when connected to the secondary system
- Requires minimum of 1 Channel / Reader to be OPERABLE.
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l SQN ODCM Revision 24 Table 2.2 (Page 2 of 3)
RAD 10 ACTIVE LIQUID EyyLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement ef** 'at releases may continue provided that priot to / clat a
releases
- a. At least two independent sas*ples are analya accordance with Section 2.3.2 and
- b. At least two technically qualified members of the Facility Staf f independently verify the release rate calculations and discharge line valvingt otherwise, suspend release of radioactive affluents via this pathway.
ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement offluent releases via this pathway any continue provided grab samples are analysed for gross radioactivity gansna at a limit of detection of at least 10*' microcuries/gramt
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
(
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than er equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
ACTION 32
- With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement offluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analysed for gross radioactivity gansna at a limit of detection of at least 10 microcuries/ml.
ACTION 33
- With the number of channels OPERABLE less than requ! red by the Minimum Channels CPERABLE requirement effluent releases via this pathway may continued provided the flow rate is estiasted at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
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i i
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i
$QN ODCM i
Revision 24 j
j Page 126 of 156 l
Table 2.2 (Page 3 of 3)
RAD 10 ACTIVE LIQUID ETTLUENT MONITORING INSTRUMEh7ATION TABLE NOTATION ACTION 34 With the number of chant.s OPERABLE less than required by the Minimum Chan'
. OPERABLE requirement, liquid additions to this tank any continued provided the tank liquid level is estimated during all liquid additions to the tank.
ACTION 35 With the number of channels CPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided representative batch samples of each tank to be released are taken prior to release and composited for analysis according to Table 2.1. footnote 3 I
l l
l t
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SQN CDCM Revision 2l.
Table 2.3 (Page 1 of 2)
(
RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CRANNEL FUNCTIONAL Instrument CHECK CHECK CAL!SRATION TEST 1.
CROSS BETA OR CAPt4A RADICACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluents Line D
P R(3)
Q(1) b.
Steam Generator'81owdown Effluent Line D
M R(3)
Q($)
c.
Condensate Domineraliser Effluent Line-D M
R(3)
Q($)
2.
CROSS BETA OR CAMMA RAD 10ACT!VITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Essential Raw Cooling Water Elfluent Line D
M R(3)
Q(2) b.
Turbine Building Sump Effluent Line D
M R(3)
Q(2) 3.
TLOW RATE MEASUREMENT DEVICES
(
a.
Liquid Radweste Effluent Line D(4)
N.A.
R Q
b.
Steam Generator Blowdown l
Effluent Line D(4)
N.A.
R Q
c.
Condensate Domineraliser Effluent Line D(4)
N.A.
R Q
d.
Cooling Tower Blowdown Effluent Line D(4)
N.A.
R Q
4 TANK LEVEL INDICATING DEVICES.
a.
Condensate Storage Tank De N.A.
R Q
b.
Steam Generator layup Tank D*
N.A.
R N.A.
5.
CONTINUOUS COMPOSITE SAMPLER AND SAMPLE FLOW MONITOR
.a.
Condensate Domineraliser i
Regenerant Effluent Line P
N.A.
R N.A.
sa Reformatting /nepagination changes only 01461
. i a r,s,.9 J,
c.
j SQN CDCM Revision 24 i
Page 128 of 156
(
Table 2.3 (Page 2 of 2)
RAD 10 ACTIVE LIQUID EFTLUENT MONITORING INSTRUMENTATION j
$URVE!LIANCE REQUIREMENTS TABLE NOTATION P = Completed prior to each release R = At least once per 18 months i'
Q = At least once per 92 days D e At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A. = Not Applicable M = At least once per 31 days t
- During liquid additions to the tank.
i (1) The CRANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this patbvey and control room alars annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Downscale failure.
(2) The CHANNEL yVNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. Downscale failure.
4 (3) The initial CRANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau
(
of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system
)
i over its intended range of energy and measurement range. yor subsequent CHANNEL CALIBRATION, sources that have been relatvd to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CRECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous periodic, or batch releases are made.
(5) The CRANNEL FUNCTIONAL TEST ahall also demonstrate that automatic isolation of this pathway and control room alare annunciation occurs if any of the following conditions occurt
- 1. Instrument indicates measured levels above the alars/ trip.
setpoint.
- 2. Circuit failure.
The CRANNEL FUNCTIONAL TEST shall also demonstrate that control rose annunciation occurs if the following condition occurst
- 1. Downscale failure.
sa Reformatting / Repagination changes only 01461 e
,c T
m
SQN ODCM Revision 24 Page 129 of 156
(
Table 2.4 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of SQN Name loginning Ending Sise Recreation TRM TRM (acres) visits / year Chickamauga Lake 484.0 471.0 9939 5.226.700 belcw SQN Nickajack Lake 471.0 435.0 5604 240.700 (Part 1)
Nickajacktake 435.0 425.0 5326 607.600 (Part 2)
Cuntersville lake 425.0 400.0 6766 104.000 Public Water Supplies Within 50 Mile Radius Downstream of SQN Name TRM Population E. I. DuPont 469.9 1.400 Chattanooga. TN 465.3 224.000 South Pittsburg. TN 418.0 4.898 Bridgeport. AL 413.6 4.650' Refor. steins /Repasination channes only q
01461 4
>=.g i
SCN ODCM Revision 24 Page 130 of 156
(
. Table 2.5 B10ACCUMU1.ATION TACTORS FOR FRESHWATER FISH R-3 9.0E-01 Tc-99m 1.5E+01 C-14 4.6E+03 Tc-101 1.5E+01 Ns-24 1.0E+02 Au-103 1.0E+01 P-32 1.0E+05 Ru-105 1.0E+01 p
Cr-51 2.0E+02 Ru-106 1.0E+01 Mn-54 4.0E+02 A4-110m 0.0E+00 Mn-56 4.0E+02 Sb-124 1.0E+00 Fe-55 1.0E+02 Sb-125 1.0E+00 Fe-59 1.0E+02 Te-125m 4.0E+02 Co-57 5.0E+01 Te-127m 4.0t+02 Co-58 5.0E+01 Te-127 4.0E+02 Co-60 5.0E+01 Te-129s 4.0E+02 N1-63 1.0E+02 Te-129 4.0E+02 Ni-65 1.0E+02 73-131m 4.0E+02 Cu-64 5.0E41 Te-131 4.0E+02 Zn-65 2.0E+03 Te-132 4.0E+02 In-69 2.0E+03 2-130 4.0E+01 In-69m 2.0E+03 1-131 4.0E+01 Br-82 4.2E+02 1-132 4.0E+01 Br-83 4.2E+02 1-133 4 0E+01 Br-84 4.2E+02 I-134 4.0E+01 Br-85 4.2E+02 1-135 4.0E+01 Rb-86 2.0E+03 Cs-134 1.9t+03 Rb-88 2.0E+03 Cs-136 1.9E+03 Rb-89 2.0E+03 Cs-137 1.9E+03
(
Sr-89 5.6E+01 Cs-138 1.9E+03 Sr-90 5.6t+01 Ba-139 4 0E+00 Sr-91 5.6t+01 Ba-140 4.0E+00 Sr-92 5.6E+01 Ba-141 4.0E+00 Y-90 2.5E+01 Ba-142 4.0E+00 Y-91m 2.5E+01 1.a-140 2 5E+01 Y-91 2.5E+01 1.a-142 2.5E+01 Y-92 2.5E+01 Co.141 1.0E+00 Y-93 2.5E+01 Co-143 1.0E+00 Zr-95 3.3E+00 Ce-144 1.0E+00 Zr-97 3.3E+00 Pr-143 2.5E+01 Nb-95 3.0E+04 Pr-144 2.5E+01 Nb-97 3.0E+04 Nd-147 2.5E+01 Mo-99 1.0E+01 W-187 1.2E+03
References:
Bioaccumulation factors for Sb-nuclides are from ORNIA 992, "A Methodology for, Calculating Radiation Doses from Radioactivity 2eleased to the Environment March 1976. Table 4.11A.
Bioaccumulation factors for Iodine Cesium, and Strontium nuclides are from NURE0/CR-1004. Table 3.2./..
All other nuclides' bio 4.ccumulation factors are from Regulatory Guide 1.109 Table A-1.
J sc Reformatting / Repagination changes only 01461
SQN ODCM Revision 24 Page 131 of 156 Table 3.1 (Page 1 of 3)
MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTA1. MONITORING PROGRAM Exposure Pathway Number of Samples and/or and Sampling and' Type and Trequency
)ppi, Sample Locations ** Collection Frecuency of Analysis
- 1. AIRBORNE Radiciodine and minimum of 5 Continuous operation Radiciodine canister:
Particulates locations of sampler with Analyse at least once sample collection as per 7 days for I-131.
required by dust loading but at least Particulate samplert once per 7 days.
Analyse for gross beta radioactivity 1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> fc11owing filter change.
Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of control samples.
Perform gamma isotopic analysis on
(
composite (by location) sample at least once per 92 days.
- 2. DIRECT 35'to 40 At least once per Camma Dose. At least RADIATION locations with 92 days, once per 92 days.
1 2 dosimeters for continuously measuring and j
recording dose rate at each location.
- sample locations are given in Table 3.4 bc Reformatting / Repagination changes only 01461 9
M*
- Ja%2Mi n hL1-m2:&%4N15:hM & w_n my $
.~
Page 132 of 156
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Table 3.1 (Page 2 of 3)
MINIMUM REQUIRED RADIOLOGICA1, ENVIRONMENTAL MONITORING PROGRAM i
Exposure 1
Pathway Number of Samples i
and/or and Sampling and Type and Frequency IM21g Samole Locations ** Collection Frecuency of Analysis i
r
- 3. WATER 30RNE
- a. Surface 3 locations Composite
- sample Gamma isotopic collected over a analysis of each period of 1 31 days. composite sample.
Tritium analysis of composite sample at least once per 92 days.
b.Cround 2 locations At least once per Canna isotopic and 92 days.
tritium analyses of each sample.
- c. Drinking Minimum of 1 Composite
- samplit Cross beta and gansna location collected over a isotopic analysis of period of 1 31 days. each composite sample.
2 locations Monthly single Tritium analysis of
(
sample.
composite sample at least once per 92 days.
- d. Sediment Minimum of 2 At least once per Camma isotopic from locations.
184 days analysis l
Shoreline of each sample.
l locations
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- Sample locations are given In Table 3.4.
t 9
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(
Table 3.1 (Page 3 of 3)
MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PA0 GRAM Exposure i
Pathway Number of Samples i
and/or and Sampling and Type and Frequency j
),3311 Sample Locations ** Collection Frecuency of Analysis I
\\
1
- 4. INGEST 10N t
- a. Milk 3 locations At least once per 15 Gamma isotopic and Samples of broad days when aniasis I-131 analysis leaf vegetation are on pastures of each sample.
t at offsite.
at least once per location of 31 days at other highest D/Q if times.
milk sample is not available.
L 1
b.rish and 3 locations One sample in Gamma isotopic 2
Invertebrates season, or at least analysis on edible once per 184 days portions.
l if not seasonal.
One sample of each of the following species:
1.
Channel Catfish 2.
White Crappie 3.
Smallmouth Buffalo c.Tood Products Minimum of 2 At time of harvest.
Gamma isotopic locations One sample of each analysis on edible of the following portion.
classes of food products.
1.
Lettuce and/or cabbage 2.
Corn 3.
Seans
- 4.
Tomatoes
- sample locations are given in Table 3.4.
1 1
)
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SQN ODCM Revision 24 Pe.ge 134 of 156 Table 3.2 (Page 1 of 2)
(
MAXIMUM VALUES FOR THE LOWER LIMITS OF CETECTION (LLD)***
a Airborne Particulate Water or Cases Tish Milk Tood Products SediM nt Analysis (DCi/L) {pC1/m*L (DCi/Ka. wet ) (DCi/L)
(DCi/Kr. vet) (TCi/Ka d gross beta 4
1x10
N.A.
N.A N.A.
N.h.
E-3 2000*
N.A N.A N.A N.A.
?<. A.
Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
Te-59 30 N.A.
260 N.A.
N.A.
N.A.
Co-58,60 15 N.A.
130 N.A.
N.A.
N.A.
Zia-65 30 N.A.
260 N.A.
N.A.
N.A.
Zr-95 30 N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95 15 N.A.
N.A.
N.A.
N.A.
N.A.
1-131 1**
7x10**
N.A.
1 60 N.A.
Cs-134 15 5x10
130 15 60 150 Cs-137 18 6x10**
150 18 80 180 Ba-140 60 N.A.
N.A.
60 N.A.
N.A.
La-140 15 N.A.
N.A.
15 N.A.
N.A.
- If no drinking water pathway exists, a value of 3000 poi /L may be used.
- If no drinking water pathway exists, a value of 15 pCL/L may be used.
i
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Revision 24 Table 3.2 (Page 2 of 2)
Page 135 of 156
" MAXIMUM VALUES y0R THE LOWER LIMITS OF DLTECTION (L TABLE NOTATION a The LLD is defined, for the purpose of these specifications yield a net count above systes background : hat will
. as the that a blank observation represents a "real" signal 951 with u ng For a particular measurement system (which may include radioche i separation):
m cal 4.66s.
LLD = -
E V
2.22 Y
exp( 4 t)
Where in picoeurie per unit mass or volume,LLD is the "a priori" low above of the counting rate of a blank sample as appropria per minute).
s E is the counting efficiency as counts per disintegrati V is the sample size in units of mass or volume on.
(
2.22 is the number of disintegrations per minute per pi Y is the fractional radiochemical yield (when applicabl )
coeurie.
K is the radioactive decay constant for the particular e.
radionuclide, and et for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
(before the fact) limit representing the capabilitIt should orfort particular measurement. system and not an a costeriori (af ter the fact) limit fo that the stated LLDs will be achieved under routine cAnalys'is will be perfor onditions, b Other peaks which are esasurable and identifiable radionuclides in Table 3.2. shall be identifind and reported together with the a
Reformatting / Repagination changes only 01461 m
4 SQN ODCM Revision 24 Page 136 of 156
(
Table 3.3 REPORTING LEVELS TOR RAD 10 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Water or gases Fish Milk Tood Products Analysis (DCi/L) infd,/m. ')_,, (DCi/Kr. wet),
(DCi/L)
(DC1/Kr. vet) 1 E-3 2 x 10* '"
N.A N.A N.A.
N.A.
8 Mn-54 1 x 10 N.A.
3 x 10' N.A.
N.A.
8 Te-59 4 x 10 N.A.
1 x 10' N.A.
N.A.
Co-58 1 x 10' N.A.
3 x 10' N.A.
N.A.
8 Co-60 3 x 10 N.A.
1 x 10' N.A.
N.A.
8 2n-65 3 x 10 N.A.
2 x 10' N.A.
N.A.
8 Zr-Nb-95 4 x 10 N.A.
N.A.
N.A.
N.A.
82" 0.9
'N.A.
3 1 x 10
-!-131 8
Cs-134 30 10 1 x 10 60 1 x 10' 8
Cs-137 50 20 2 x 10*
70 2 x 10' 8
Ba-La-140 2 x 10 N.A.
N.A.
3 x 10 N.A.
8 (a) Tor drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 PCi/L may be used.
(b) If no drinking water pathway exists, a value of 20 pCi/L may be used.
l la.:.
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SQN CDCM Revision 24
(
Page 137 of 156 Table 3.4 (Sheet.1 of 4)
~
RADIOLOGICAL ENVIRONMENTAL MON!TORING PLOCP.AM Exposure Pathway Sampling and Type and Trequency and/or Samole Samola Loestions*
Collection Trecuency of Analysis AIRBORNE Particulates a samples from loca-Continuous sampler Analyse for stess tions (in different operation with beta radioactivity sectors) at or near sample collection 1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> follow.
the site boundary once per 7 days ing filter change.
(LM-2,3,4.and 5)
(more frequently Perf orm samma iso-if required by dust topic analysis on 4 samples from com-loading) each sample if munities approx-gross beta > 10 imately 6-10 miles times yearly mean distance from the of control sample.
q plant. (rn-e.3.6 and 9)
Composite at least once per 31 days (by location for gamma scan).
4 samples from control locations greater than 10 miles from the plant (RM-1,2,3,and 4) 4 Radiciodine Samples from same Continuous sampler I-131 at least location as air operation with fil-once per 7 days l
particulates.
ter collettion once per 7 days i
Soil Samples from same once per year Canna scan. Sr-89 l
locations as air Sr-90 once per l
particulates year i
DIRECT 2 or more dosimeters Once per 92 days Camma dose at RADIATION placed at locations least once per (in different sectors 92 days at or near the site boundary in <.ach of the 16 sectsrs.
2 or acre dosimeters placed
',t stations locatea >5 alles from the plant in each of the 16 sectors
- Sample locations are listed in Tables 3.5 and 3.6 and shown on rigures 3.1 3.2 and 3.3
- -s a Reformatting / Repagination changes only 01461 ty R
fi 4 } \\*
- I
'*'*t.
e r.*. $Y" N ~
'O s-
Page 138 of 156
(
Table 3.4 (Sheet 2 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Trequency and/or Samole Samole Locations
- Collection Frecuency of Analysis DIRECT 2 or more dosimeters RADIATION in at least 8 additional (continued) locations of special interest.
WATERBORNE surface TRM 497.0 Collected by auto-Cama scan of each TRM 483.4 metic sequential-composite sample.
TAM 473.2 type sampler ** with Composite for M-3 composite samples analysis at least collected at least once per 92 days once per 31 days Cround 1 sample adjacent to At least once per Gross beta and plant (location W-6) 92 days gansna scan. St-89 Sr-90 and E-3 an-1 sample from ground analysis at least water source up-once per 92 days gradient Drinking 1 sample at the first Collected by auto-Cross beta and potable surface water matic sequential gansna scan of each supply downstream type sampler ** with composite sample.
(
from the plant composite sample Composite for R-3 (TRM 473.0) collected at least
$r-89, Sr-90 at once per 31 days least once per 92 days.
1 sample at the next Grab sample once 2 downstream potable per 31 days surf ace water sup-l pliers (greater than 10 miles downstream)
(TRM 470.5 and 465,.3) 2 samples at control Samples collected by locations (TRM 497.0 automatic sequential and 503.8)***
type sampler with com-posite sample collected at least once per 31 days.
- Sample locations are listed in Tables 3.5 and 3.6 and shown on Tiguru 1.1 3.2 and 3.3
- Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- The surface water sample collected at TRM 497.0 is considered a control f or the raw drinking water sample.
.%sc Reformatting / Repagination changes only 01461
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& %,Mv:,.c...w&.. t: ;..
. & s u N $ W. &, n. e --r & O 2 A
SQN ODCM Revision 24 Page 139 of 156
(
Table 3.4 (Sheet 3 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM t.mposure Pathway Sampling and Type and Trequency
_and/or Sample Sample Locations
- Collection Frecuency of Analysis WATERBORNE (continued)
Sediment TRM 496.$ TRM 483.4 At least once per Gansna scan of each TRM 480.8, TRM 472.8 184 days sample.
Shoreline TRM 485, TRM 478 At least once per Gaasna scan of each TRM 477 184 days sample.
INCESTION Milk 1 sample from milk At least once per Gaasna isotopic and producing animals in 15 days 1-131 analysis of each of 1-3 areas in-each sample. St-89 dicated by the cow
$r-90 once per census where doses are quarter calculated to be highest.
If samples are not avail-able from a milk animal location, doses to that area will be estimated by projecting the doses from concentrations detected in alik from other sectors or
(
samples of vegetation will be taken monthly where milk is not available (Table 3.1, ad)
At least 1 sample from a control location Fish 1 sample each from At least once per Gamma scan on Nickajack, Chicka-184 days. One sam-edible portion mauga, and Watts,
pie of each of the Bar Reservoirs following species:
L Channel Catfish Crappie smallmouth Buffato
- sample locations are listed in Tables 3.$ and 3.6 and shown on Figures 3.1, 3.2 and 3.3 i
- e9 Reformatting / Repagination changes only 01461 4
_.g, w,.., n., a
+n, :n _.
.-:.a
SQN ODCM Revision 24 Page 160 of 156
(
Table 3.4 (Sheet 4 of 4)
RADIOLOGICAL ENVIRONMT.NTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Samole Sample Locations
- Collection Frecuenev of Analysis INCESTION (continued)
Invertebrates 2 samples downstream At least once per Camma scan on (Asiatic Class) from plant discharge ** 184 days edible portion 1 sample upstream from the plant **
Tood 1 sample each of At least onca per Gamma scan on Products principal food 365 days at tLee of edible portion products grown at harvest. The types private gardens of foods available for and/or farms in the sampling will vary.
immediate vicinity Following is a list of of the plant typical foods which may be available a
s Cabbage and/or Lettuce g
Corn
\\
Green Beans Potatoes Tomatoes Vegetation Samples f rom f arms At least once per 1-131 and gamma
(
producing milk 31 days scan at least once but not providing per 31 days, a milk sample Sr-89, Sr-90 anal-(Fara Em) ysis at lesst once per 92 days.
- Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1, 3.2 and 3.3
- No permanent stations established. Locations depend on availability of cl ams.
q Reformatting / Repagination changes only 01461 C.o1 6@
- ." W ci.r.r.iz
- c 5 m m.- L...
. a4.ut9 h a...
I SQN ODCM Revision 24 Page 141 of 156 Table 3.5 (1 of 2)
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (!)
Location Distance or Samples Number
- Station jg3,gt (Miles)
Control (C)
Collected' 2
IJi-2 N
0.8 1
LM-3
IM-4 NE 1.5 1
IJi-5 NNE 1.8 I
PM-2 SW 3.8 I
PM-3 W
5.6 I
PM-8
'JSW 2.6 I
-RM-1 SW 16.7 C
ESE 11.3 C
M 16 Tarm C NE 16.0 C
M 17 Tarm S NNE 12.0 C
M 18 Tarm J WNW 1.1 1
M 19 Tarm HW NW 1.2 I
M. W' 20 Tars EM N
2.6 1
V 24 Well No. 6 NNE 0.15 I
W 31 TRM' 473.0 11.5*
I PW
(
(C. T. Industries) 32 TRM 470.5 14.0' 1
PW (E. 1. DuPont) 33 TRM 465.3 19.2' I
PW (Chattanooga) 34 TRM 497.0 12.5' C'
PW (Dayton) 36 TRM 496.5 12.0' C
SS 38
'I1tM 483.4 1.1' I
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" ~'i$$$AIN' ' N Db'
'd
SQN ODCM Revision 24 Page 142 of 156
(
Table 3.5 (2 of 2) 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (1)
Location Distance or Samples Number
- Station h
(Miles)
_Cor; trol (C)
Collected"
?
45 3 M 425-471 1
F (Nickajack) a Reservoir) 46 TRM 471-530 1
F. CL (Chickamauga Reservoir) 47 TRM $30-602 C
T (Watts Bar Reservoir) 48 Tars E NE 4.2 1
M
- See figures 3.1, 3.2, and 3.3
(
M = Milk PW = Public water R = Rainwater S = Soil SD = Sediment SS = Shoreline sediment SW = Surf ace water V = Vegetation I
W = Well water
- A control for well water.
- Distance from plant discharge (TRM 484.5) l l
' Surface water sample also used as a control for public water.
l
.% c Reformatting / Repagination changes only 01461 4I Y f
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E
SQN ODCM Revision 24 Table 3.6 (1 of 2)
(
THERM 01.tMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)*
Location Distance or Number Station Sector (Miles)
Offsite (Off) 3
$$W-1A SSW 1.2 On 4
NE-1A NE 1.5 On l
5 NNE-1 NNE 1.8 On i
7 SW-2 SW 3.8 Off i
8 W-3 W
5.6 Off
(
9
$5W-3 SSW 8.7 off 10 WSW-2A WSW 2.6 Off 11 SW-3 SW 16.7 Off 12 NNE-4 NNE 17.8 Off l
13 ESE-3 ESE 11.3 off i
14 WWW-3 WNW 18.9 Off 49 N-1 N
0.6 On 50 N-2 N
2.1 off i
l 51 N-3 N
5.2 off 52 N-4 N
10.0 off I
$3 NNE-2 NNE 4.5 off
$4 NNE-3 NNE 12.1 off 55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off 57 ENE-1 ENE 0.4 on 58 ENE-2 ENE 5.1 off
(
59 E-1 E
1.2 On 60 E-2 E
5.2 Off 61 ESE-A ESE 0.4 on 62 ESE-1 ESE 1.2 On 63 ESE-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 SE-B SE 0.4 On 66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE, 5.2 Off 69
$$E-1 SSE 1.6 On 70 SSE-2 SSE 4.6 Off 4
71 5-1 8
1.5 On l
72 S-2 8
4.7 Off 73 SSW-1 SSW 0.6 on 74
$$W-2 SSW 4.0 off 75 SW-1 SW 0.9 on 76 WSW-1 WSW 0.9 On l
N.:.
Reformatting / Repagination changes only 01461
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SQN ODCM Revision 24 Page lek of 156 l
Table 3.6 (2 of 2) g 71IERM0 LUMINESCENT DOSIMITRY LOCATIONS l
Map Approximate Onsite (On)*
1.oestion Distance or i
Number Station
{g,eler (Miles)
Offsite (Off) e
)
l 77 WSW-2 WSW 2.5 off 1
78 WSW-3 WSW 5.7 Off i
i 79 WSW-4 WSW 7.8 Off 60 WSW-5 WSW 10.1 off.
81 W-1 W
0.8 On-3 82 W-2 W
4.3' Off 83 WNW-1 WNW
'O.4 On 84 WNW-2 WNW
$.3 Off 85 W-1 W
0.4 on j
86 W-2 W
5.2 Off l
87 NNW-1 NW 0.6 On i
88 NW-2 NW 1.7 On J
l 89 NW-3 NW 5.3 off l
TLDs designated onsite are those located two miles or less from the plant.
a.
TLDs designated offsite are those located more than tem miles from the plant.
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som Deen Revision 24 Page 145 of 156
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I Figure 1.1 GAst0US EFFLUENT RELEAst POINTS
+
s Condenser Vacuum Exhausti Shield Building Vent (one per unn) i (one per unit) 1 L j p l
(ews.i..tr) l 1.2-RW-so-100 C1 I
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TURent jg, E
Y PURot WCORE NsT.
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CONDENSER I""El R00W PURet,
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Revision 24
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Page 146 of 1$6 Figure 1.2 AUKILIARY AlfD SHIELD BUILDING VENTS (DETAIL)
Shleid j
Building Vent Cl 1,2-Ru-90-100 honnewnt ine ment Rooreg i%
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Purge kahouet O'"I I
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