3F0402-05, 2001 Radioactive Effluent Release Report
| ML021190616 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/23/2002 |
| From: | Roderick D Florida Power Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3F0402-05 | |
| Download: ML021190616 (18) | |
Text
Florida Power A Progress Energy Comrpanyn Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.36(a)(2)
ITS 5.7.1. 1(c)
April 23, 2002 3F0402-05 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - 2001 Radioactive Effluent Release Report
Dear Sir:
Florida Power Corporation hereby submits the 2001 Radioactive Effluent Release Report for Crystal River Unit 3 (CR-3) in accordance with 10 CFR 50.36(a)(2) and the CR-3 Improved Technical Specifications (ITS), Section 5.7.1.1(c).
The report, provided as Attachment A, includes a summary of the quantities of radioactive liquid and gaseous effluents, and solid waste released from the CR-3 site during 2001.
The material provided is consistent with the objectives outlined in the Off-Site Dose Calculation Manual (ODCM) and the Process Control Program (PCP), and is in conformance with 10 CFR 50, Appendix I, Section IV.B. 1.
ITS 5.6.2.3.3 requires submittal of licensee initiated changes to the ODCM as part of the Radioactive Effluent Release Report. A complete copy of the ODCM, provided as Attachment B, is included herewith with the affected pages appropriately marked with vertical bars in the left margin. The PCP, revised during 2001, is also included as part of this submittal.
The affected pages in the PCP are appropriately marked with vertical bars in the left margin.
If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Lic' and Regulatory Programs at (352) 563-4883.
D. L. Roderick Director Site Operations DLR/ff Attachments:
A.
2001 Radioactive Effluent Release Report B.
Off-Site Dose Calculation Manual, Revision 25 C.
Process Control Program, Revision 5 xc:
NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Crysal River Nuclear Plain
'5760 W, Pov. er Lae Street C vs~al River, FL 34428
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT A 2001 Radioactive Effluent Release Report
RADIOACTIVE EFFLUENT RELEASE REPORT 2001 FLORIDA POWER CORPORATION CRYSTAL RIVER - UNIT 3 Facility Operating License No. DPR-72 Docket No. 50-302 Prepared By:
6 -
(
- e Environmental Coordinator Approved By:
il k
I Superintendent Environmental and Chemistry Date:
'41 QAoz-
CONTENTS Introduction................................................................................................
1 Tabular Data Summaries Gaseous Effluents - Quarters 1 & 2........................................................
2 Gaseous Effluents - Quarters 3 & 4........................................................
4 Liquid Effluents - Quarters 1 & 2...........................................................
6 Liquid Effluents - Quarters 3 & 4...........................................................
9 Radwaste Shipments......................................................................................
12 Unplanned Releases......................................................................................
13 Radioactive Waste Treatment Systems...............................................................
13 Annual Land Use Census...............................................................................
13 Effluent Monitor Instrument Operability..............................................................
13 ODCM & PCP Changes.................................................................................
13 Emergency Feed Pump 2...............................................................................
13 Appendix I Dose Summary.............................................................................
14
INTRODUCTION This report is submitted as required by the Offsite Dose Calculation Manual, section 6.5.
The scope of this report includes:
"* A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.
"* Quarterly and annual dose summaries.
"* A list and description of unplanned releases to unrestricted areas.
"* A description of any changes to the:
Process Control Program (PCP), and Offsite Dose Calculation Manual (ODCM).
"* Significant changes to any radioactive waste treatment system.
"* A list of new dose calculation location changes identified by the annual land-use census.
"* Information relating to effluent monitors or required supporting instrumentation being inoperable for 30 or more days.
I
TABLE 1 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I1 1
2 Error %I A.
Fission and activation gases
- 1.
Total release Ci 2.31E-01 3.41E+02 30
- 2.
Average release rate for period jACi/sec 2.97E-02 4.34E+01
- 3.
Percent of technical specification limit 2.10E-04 6.10E-02 B.
lodines I.
Total Iodine-131 Ci 0.001E+00 9.84E-07 30
- 2.
Average release rate for period IMCi/sec 0.OOE+00 1.25E-07
- 3.
Percent of technical specification limit 0.00E+00 3.58E-02 C.
Particulates*
- 1.
Particulates with half-lives > 8 days Ci 7.58E-09 1.57E-07 30
- 2.
Average release rate for period j+/-Ci/sec 9.75E-10 1.99E-08
- 3.
Percent of technical specification limit 5.79E-03 3.58E-02
- 4.
Gross alpha radioactivity Ci 0.OOE+00 0.OOE+00 D.
- 1.
Total release Ci 1.81E+00
- 2.
Average release rate for period tLCi/sec 2.32E-01
- 3.
Percent of technical specification limit 5.79E-03 The sum of the particulates reported on this page may be less than the sum from Table 2, as Table 2 includes all particulates, while this table includes only those with half-lives greater than 8 days.
2
TABLE 2 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A.
Fission gases Argon-41 Ci Krypton-85 Ci 3.20E+01 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci 2.77E+00 3.93E+00 Xenon-133 Ci
- 1. 12E +02 2.16E-01 1.88E+02 Xenon-133m C i 9.96E-01 1.53E+00 Xenon-135 C i 1.53E-02 8.91E-02 Xenon-135m Ci Xenon-138 Ci Total for period Ci O.OOE+0O 1.16E+02 2.31E-01 2.25E+02 B.
Iodines; Iodine-131 Ci 5.40E-07 4.43E-07 Iodine-132 Ci Iodine-133 Ci Iodine-135 Ci Total for period Ci O.OOE+OO 5.40E-07 O.OOE+OO 4.43E-07 C.
Particulates Zinc-72 Ci Cobalt-58*
Ci
___________2.41E-08 Cobalt-6O*
Ci Strontium-89*
Ci Strontium-90*
Ci Niobium-95m Ci Technicium-99m Ci Tellurium-132 Ci Cesium-134*
Ci Cesium-137*
Ci 1.33E-07 7.58E-09 Cesium-138 Ci Barium-139 Ci Lanthanum-142 Ci Cerium-141*
Ci Cerium-144*
Ci Rhenium-188 Ci Total for period Ci O.OOE+OO 1.33E-07 7.58E-09 2.41E-08
- > 8 day half-life 3
TABLE3 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 11 3
1 4
Error %
A.
Fission and activation gases
- 1.
Total release
- 2.
Average release rate for period
- 3.
Percent of technical specification limit B.
lodines
- 1.
Total Iodine-131 Ci 2.88E-06 1.00E-05 30
- 2.
Average release rate for period jzCi/sec 3.63E-07 1.26E-06
- 3.
Percent of technical specification limit 3.06E-02 9.23E-02 C.
Particulates*
- 1.
Particulates with half-lives > 8 days Ci 0.OOE+00 I
1.28E-07
- 2.
Average release rate for period liCi/sec 0.OOE+00 1.61E-08 3-Percent of technical specification limit 0.OOE+00 9.23E-02
- 4.
Gross alpha radioactivity Ci 0.00E+00 0.00E+00 D.
- 1.
Total release Ci 1.89E+00
- 2.
Average release rate for period ItCi/sec 2.38E-01
- 3.
Percent of technical specification limit 3.06E-02 The sum of the particulates reported on this page may be less than the sum from Table 4, as Table 4 includes all particulates, while this table includes only those with half-lives greater than 8 days.
4
TABLE 4 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES A.
Fission gases Argon-41 Ci 6.48E-03 Kyton-85 Ci 1.38E+00 3.02E+00 Krypton-85m Ci 8.80E-04 Krypton-87 Ci Kyton-88 Ci Xenon-131m Ci 1_________
.39E-02 3.89E-01 Xenon-133 Ci 1.15E+01 4.92E+01 4.36E+00 7.62E+00 Xenon-133m Ci 7.56E-02 2.02E-01 1.95E-02 Xenon-135 Ci 3.22E-01 6.44E-01 6.48E-02 4.87E-02 Xenon-135m Ci Xenon-138
_Ci Total for period Ci 1.19E+01 5.OOE+O1 5.83E+00 1.11E+01 B.
Iodines Iodine-131 Ci 2.88E-06 1.OOE-05 Iodine-132 Ci Iodine-133 Ci 1.04E-06 Iodine-135 Ci Total for period Ci 3.93E-06 1.OOE-05 O.OOE+00 O.OOE+OO C.
Particulates Zinc-72 Ci Cobalt-58*
Ci Chromium-51 *Ci Strontium-89*
Ci Strontium-9O*
Ci Niobium-95m Ci Tin-113*
Ci Indium-1l3m Ci Barium-133m Ci 1.80E-07 1.67E-07 Cesium-137*
Ci
___________1.28E-07__________
Cesium-138 Ci Barium-139 Ci Lanthanum-142 Ci Cerium-143 Ci 1.54E-07 Cerium-l44*
Ci Rhenium-188 Ci Total for period Ci 1.80E-07 4.50E-07 O.OOE+00 O.OOE+OO
- > 8 day half-life 5
TABLE5 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Total 1 1 2
1Er~ror %
A.
Fission and activation products Total release (not including tritium, gases, alpha)
Average diluted concentration during period Percent of applicable limit Ci 4.53E-02 4.49E-02 zCi/rnl 8.71E-11 7.50E-11 I4.54E-02 2.36E-02 B.
Tritium I.
Total release
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit C.
Dissolved and entrained gases
- 1.
Total release
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit D.
Gross alpha radioactivity
- 1.
Total release Ci 0.OOE+00 0.OOE+0O 30 E.
Volume of waste released (prior to dilution)
I 1.
Batch and continuous modes Liters 5.60E+06 9.01E+06 10 F.
Volume of dilution water used during period
- 1.
Batch and continuous modes Liters 5.20E+11 5.99E+11
- 10 6
I.
- 2.
3.
25
TABLE 6 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 LIQUID EFFLUENTS CONTINOUS MODE BATCH MODE Fission and activation products Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Sodium-24 Ci 3.51E-06 Chromium-5i Ci 3.13E-04 6.90E-03 Manganese-54 Ci 4.82E-05 3.63E-04 Manganese-56 Ci Iron-55 Ci 2.14E-04 1.ilOE-03 Iron-59 Ci 1.41E-03 Cobalt-57 Ci Cobalt-58 Ci 6.8713-05 1.46E-03 1.50E-02 Cobalt-60 Ci 1_________
.11E-03 1.26E-03 Zinc-72 Ci Strontium-85 Ci
__________8.03E-06 Strontium-89 Ci Strontium-90 Ci Yttrium-91m Ci Yttrium-92 Ci Yttrium-93 Ci Niobium-95 Ci 5.4513-05 2.04E-03 Niobium-95m Ci Niobium-97 Ci
__________2.77E-04 Zirconium-95 Ci 1.9613-04 1.68E-03 Zirconium-97 Ci 1.01E-03 1.04E-04 Molybdinum-99 Ci 2.55E-04 Technetium-99m Ci 3.73E-04 4.85E-04 Technetium-101 Ci Ruthenium 103 Ci 1.26E-05 2.87E-05 Ruthen~ium-106 Ci 2.52E-03 Silver-1l0m Ci 2.03E-02 1.78E-03 Tin-1 13 Ci
__________1.23E-04 Indium-113m Ci 1.75E-04 Antimony-122 Ci Antimony-124 Ci 4.30E-04 2.35E-05 Antimony-125 Ci 8.07E-03 3.86E-04 Tellurium-129 Ci 3.26E-05 Tellurium-132 Ci 4.93E-05 Iodine-131 Ci
- 3. 18E-03 6.4613-03 Iodine-133 Ci 3.56E-03 2.12E-03 Iodine-135 Ci 1.71E-04 2.22E-04 Cesium 134 Ci 6.13E-06 1.24E-04 Cesium-137 Ci 6.OOE-05 1.22E-05 8.46E-05 Cesium 138 Ci Barium-139 Ci 1.80E-05 Barium-140 Ci 2.55E-04 Lanthanum 140 Ci 2.1113-03 1.98E-03 Cerium-143 Ci 4.56E-06 Cerium-144 Ci 6.76E-05 Rhenium-188 Ci 3.29E-05 Tungsten-187 Ci 5.91E-05 Neptunium--239 Ci 2.68E-05 Total for period Ci 0.00E+00 1.29E-04 4.53E-02 4.49E-02 7
TABLE 6 (CONTINUED)
EFFLUENT AND WASTE DISPOSAL REPORT - 2001 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved and entrained gases Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Argon-41 Ci Krypton-85 Ci 1.88E-03 Krypton-85m Ci Krypton-87 Ci 2.00E-07 Krypton-88 Ci Xenon-131m Ci 3.54E-04 6.63E-03 Xenon-133 Ci 1.27E-01 1.70E-01 Xenon-133m Ci 4.86E-03 3.88E-03 Xenon-135 Ci 5.41E-02 2.80E-02 Xenon-135m Ci 1.77E-05 3.74E-05 Total for period Ci 0.00E+00 O.OOE+00 1.86E-01 2.10E-01 Tritium Ci 0.00E+00 3.24E-02 1.57+02 9.32E+01 8
TABLE 7 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 11 3
1 4
Error %
A.
Fission and activation products
- 1.
Total release (not including tritium, gases, alpha)
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit B.
- 1.
Total release
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit C.
Dissolved and entrained gases
- 1.
Total release
- 2.
Average diluted concentration during period
- 3.
Percent of applicable limit D.
Gross alpha radioactivity
- 1.
Total release E.
Volume of waste released (prior to dilution)
- 1.
Batch and continuous modes F.
Volume of dilution water used during period
- 1.
Batch and continuous modes 25 I
Ci 3.52E-02 4.13E-02 14Ci/ml 5.57E-11 8.65E-11 2.44E-03 1.60E-03 Ci 0.OOE+00 6.67E-04
=30 Liters 8.28E+06 7.56E+06 10 Liters 6.3213+11 4.77E +11 7
170:
9 1
TABLE 8 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Fission and activation products Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Sodium-24 Ci
__________1.95E-06 8.47E-06 Chromium-51 Ci 9.01E-04 1.05E-03 Manganese-54 Ci 2.77E-05 5.46E-05 Manganese-56 Ci Iron-55 Ci 1.89E-03 3.9313-03 Iron-59 Ci 8.78E-07 Cobalt-57 Ci Cobalt-58 Ci 3.18E-03 6.93E-04 Cobalt-60 Ci 5.47E-04 2.50E-04 Zinc-69 Ci 6.70E-06 Zinc-72 Ci Strontium-85 Ci 5.95E-06 2.8413-05 Strontium-89 Ci Strontium-90 Ci Strontium-92 Ci Yttrium-91 Ci 2.60E-04 Yttrium-92 Ci 7.74E-06 Yttrium-93 Ci Rubidium-88 Ci Niobium-95 Ci 8.56E-05 9.65E-05 Zirconium-95 Ci 3.23E-05 3.79E-05 Zirconium-97 Ci 9.36E-06 Molybdinum-99 Ci Technetium-99m Ci Technetium 101 Ci Rutheniuin-106 Ci 2.43E-05 Silver-i l0i Ci 6.69E-04 8.15E-06 Tin-113 Ci 5.15E-07 Indium-113m Ci 8.71E-07 Antimony-122 Ci 1.51E-07 2.1 IE-07 Antimony-124 Ci 1.55E-05 1.391304 Antimony-125 Ci 2.78E-02 3.19E-02 Tellurium-129 Ci Tellurium-132 Ci 6.75E-06 2.1713-04 Iodine-131 Ci 5.05E-06 1.3313-04 Iodine-132 Ci 1.80E-04 Iodine-133 Ci
_1
.96E-07 Iodine-135 Ci Cesium-134 Ci 3.78E-06
- 7. 18E-05 Cesium-136 Ci Cesium 137 Ci 9.83E-06 8.87E-05 Barium-133m Ci 6.69E-06.
Barium-139 Ci Barium-140 Ci 5.36E-07 Lanthanum-140 Ci Cerium-143 Ci 5.38E-05 Cerium-144 Ci Praseodymium-144 Ci 1.95E-03 Tungsten-187 Ci Rhenium-188 Ci 2.8313-05 Total for period Ci O.OOE+00 5.38E-05 3.5213-02 4.13E-02 10
TABLE 8 (CONTINUED)
EFFLUENT AND WASTE DISPOSAL REPORT - 2001 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved and entrained gases Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Argon-41 Ci Krypton-85 Ci 1.39E-03 6.65E-03 Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-131m Ci 7.18E-04 7.50E-03 Xenon-133 Ci 2.41E-04 6.68E-02 2.37E-01 Xenon-133m Ci 9.28E-05 1.55E-03 Xenon-135 Ci 8.91E-04 2.41E-04 Xenon-135m Ci 9.36E-06 Total for period Ci 2.41E-04 0.00E+00 6.99E-02 2.53E-01 Tritium Ci 2.66E-02 1.74E-02 4.77E+01 3.6lE+01 11 I
TABLE9 EFFLUENT AND WASTE DISPOSAL REPORT - 2001 SOLID WASTE AND IRRADIATED FUEL SIHPMENTS A.
SOLID WASTE SHIPPED OFFSITE FOR PROCESSING OR BURIAL (Non-irradiated fuel)
Type of waste Unit 12 month period Est. Total Error %
m3 2.79E+01 25
- a.
Spent resins, filter sludges, evaporator bottoms, etc.
Ci I.38E+01 25 m3 7.06E+02 25
- b.
Dry compressible waste, contaminated equipment, etc.
Ci 2.17E+00 25 m3 0.17E+00 25
- c.
Irradiated components, control rods, etc.
Ci 0.OOE+00 25 m3 0.OOE+00 25
- d.
Other (describe):
Expended charcoal C3 O.OOE+00 Ci 0.00E+00
- 2.
Estimate of major nuclide composition (by type of waste in %)*
Co-58 33.8 Co-60 8.2 Ni-63 3.1
- a.
Nb-95 27.4 Ag-ll0m 3.6 Zr-95 3.1 Fe-55 16.8 Mn-54 3.2 Fe-55 35.5 Co-60 11.6 Mn-54 2.8
- b.
Cs-137 15.4 Co-58 11.5 Nb-95 2.0 Ni-63 13.0 Ag-I 10m 3.3 C.
d.
- 3.
Solid Waste Disposition Number of Shipments Mode of Transportation 1
Exclusive use truck 4
Exclusive use truck 5
Exclusive use truck 5
Exclusive use truck 1
Exclusive use truck 1
Exclusive use truck B.
IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination Barnwell Waste Mngmt (SC)
Alaron Corp. (SC)
Duratek (TN)
ATG Nuclear Services (TN)
ATG Richland Corp (WA)
Envirocare (UT)
Destination 0
N/A N/A Curie values and principle radionuclides are estimates based on a combination of direct and indirect methods.
12
Unplanned Releases There was one unplanned releases during 2001.
The release was documented in NCR 52926.
An estimated 4.4E-06 Curies of gamma emitters and 3.6E-02 Curies of tritium were released. The release path was from Nuclear Services Closed Cycle Cooling System (SW) to the Nuclear Services and Decay Seawater System (RW) by way of leaks in two heat exchangers. The RW system discharges to the site discharge canal. The SW system contains residual contaminated due to a primary coolant leak into the system earlier in 2001, prior to Refuel 12.
Radioactive Waste Treatment Systems There were no significant changes to the radioactive waste treatment systems.
Annual Land Use Census The July 2001 land-use census did not identify any new dose calculation locations.
Effluent Monitor Instrument Operability Required effluent monitor instrumentation was not out of service for more than 30 days during 2001.
ODCM & PCP Changes The PCP was revised during 2001. The entire PCP underwent a significant rewrite. The main reason for the revision was to clarify that only qualified vendors, and not station personnel, will perform solidification activities when required.
The ODCM was revised during 2001. The affected pages are ii, 1, 2, 3, 24, 29, 40, 51, 58, 68, 101, 109, 117. The changes were made primarily to make the ODCM consistent with the technical specification 5.6.2.3.g and 5.6.2.3.i language pertaining to 1-133. ODCM definitions that were also in technical specifications were deleted from the ODCM.
Emergency Feed Pump 2 Emergency Feed Pump 2 (EFP-2) overspeed testing is performed quarterly using steam from CR-3's steam generators. Due to a small primary to secondary leak, an evaluation was performed to estimate the quantity of radioactive material which was released during 2001 due to operation of this pump. The results of this evaluation are given below in units of Curies/year.
Xe-133 2.23E-07 1-131 1.64E-08 Cs-137 1.00E-08 Xe-135 6.91E-08 1-133 8.91E-08 Cs-137 8.48E-09 H-3 1.90E-03 These values are not included in Tables 1 through 4.
13
2001 Appendix I Dose Summary Maximum Hypothetical Individual Liquid Effluent Dose Limits 1.5 mrem/quarter, 3 mrem/year 5 mrem/quarter, 10 mrem/year Liquid Effluent Dose Summary Total Body Dose (mrem)
Maximum Organ Dose (mrem)
Maximum Organ was GI Gaseous Effluent Dose Limits Gamma Air Dose:
Beta Air Dose:
Any Organ:
Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total 1.55E-05 4.77E-05 6.74E-06 2.39E-05 9.39E-05 2.27E-03 1.18E-03 1.22E-04 7.43E-05 3.65E-03 5 mrad/quarter, 10 mrad/year 10 mrad/quarter, 20 mrad/year 7.5 mrem/quarter, 15 mrem/year Gaseous Release Dose Summary Quarter 1 Quarter 2 Gamma Air Dose (mrad)
Beta Air Dose (mrad)
Total Body Dose (mrem)
Maximum Organ Dose (mrem)
Maximum Organ was Thyroid Quarter 3 Quarter 4 Annual Total 8.37E-06 2.90E-04 5.32E-04 1.71E-03 2.54E-03 2.1OE-05 6.1OE-03 1.62E-03 5.39E-03 1.31E-02 4.34E-04 2.06E-03 4.57E-04 5.46E-04 4.34E-04 2.69E-03 2.29E-03 6.92E-03 14 Total Body:
Any Organ:
3.50E-03 1.23E-02