ML17264A885
| ML17264A885 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/31/1996 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17264A884 | List: |
| References | |
| NUDOCS 9705140391 | |
| Download: ML17264A885 (37) | |
Text
1996 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT R. E. GINNANUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244 9705i4039i 970509 PDR ADGCK 05000244 R
TABLEOF CONTENTS
1.0 INTRODUCTION
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Release Rate Limits 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0
SUMMARY
OF GASEOUS RADIOACTIVEEFFLUENTS 4.0
SUMMARY
OF LIQUIDRADIOACTIVEEFFLUENTS 5.0 SOLID WASTE 6.0 LOWER LIMITOF DETECTION 7.0 RADIOLOGICALIMPACT 8.0 METEOROLOGICALDATA 9.0 LAND USE CENSUS CHANGES 10.0 CHANGES TO THE OFFSITE DOSE CALCULATIONMANUAL 11.0 CHANGES TO THE PROCESS CONTROL PROGRAM 12.0 MAJOR CHANGES TO RADWASTE TREATMENTSYSTEMS
LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases Table 1B Gaseous Effluents - Continuous and Batch Releases Table 2A Liquid Effluents - Summation of all Releases Table 2B Liquid Effluents - Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments Table 4A Radiation Dose to Nearest Individual Receptor from Gaseous Releases Table 4B Radiation Dose to Nearest Individual Receptor from Liquid Releases Supplementary Table 4A - 1995 Radiation Dose to Nearest Individual Receptor from Gaseous Releases
Cl
~o INTRODUCTION This Annual Radioactive Effluent Release Report is for Rochester Gas and Electric Corporation R.E. Ginna plant and is submitted in accordance with the requirements of Technical Specification Section 5.6.3.
The report covers the period from January 1, 1996 through December 31, 1996.
This report includes. a summary of the quantities of radioactive gaseous and liquid effluents and solid waste released from the plant presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.
Allgaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the R.E. Ginna Technical Specifications as defined in the Offsite Dose Calculation Manual (ODCM).
2.0 2.1 SUPPLEMENTAL INFORMATION Re ulator Limits The ODCM limits applicable to release of radioactive material in liquid and gaseous effluents are:
Fission and Activation ases The instantaneous dose rate, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to a release rate which would yield < 500 mrem/yr to the total body and < 3000 mrem/yr to the skin ifallowed to continue for a full year.
The air dose, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to the following:
(I)
During any calendar quarter to < 5 mrad for gamma radiation and to
< 10 mrad for beta radiation.
(ii)
During any calendar year to < 10 mrad for gamma radiation and to
< 20 mrad for beta radiation.
2.1.2 Radioiodine Tritiu and Particulates The instantaneous dose rate, as calculated in the ODCM, due to radioactive materials released in gaseous effluents from the site as radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days shall be limited to a release rate which would yield < 1500 mrem/yr to any organ ifallowed to continue for a full year.
The dose to an individual, as calculated in the ODCM, from radioiodine, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days released with gaseous effluents from the site shall be limited to the following:
(I)
During any calendar quarter to < 7.5 mrem to any organ.
(ii)
During any calendar year to < 15 mrem to any organ.
2.1.3
~did dill The release of radioactive liquid effluents shall be such that the concentration in the circulating water discharge does not exceed the limits specified in accordance with Appendix B, Table II, Column 2 and notes thereto of 10CFR20.
For dissolved or entrained noble gases the total activity due to dissolved or entrained noble gases shall not exceed 2 E-4 uCi/ml.
Oi The dose or dose commitment to an individual as calculated in the ODCM from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
(I)
During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, and (ii)
During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.
2.2 Maximum Permissible oncentrations MP 2.2.1 For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary.
2.2.2 For liquid effluents, ten times the effluent concentration values specified in 10CFR20, Appendix B, Table II, column 2, are used to calculate release rates and permissible concentrations at the unrestricted area boundary as permitted by Technical Specification 5.5.4.b. Avalue of 2E-04 uCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.
Z3 Release Rate Limits The release rate limits for fission and activation gases from the R.E. Ginna plant are not based on the average energy of the radionuclide mixture in gaseous effluents; therefore, this value is not applicable.
However, the average 1996 beta/gamma energy of the radionuclide mixture was 0.221 Mev.
2.4 Measurements and A roximations of Total Radioactivit Gamma spectroscopy was the primary analysis method used to determine the radionuclide composition and concentration of gaseous and liquid effluents.
Composite samples were analyzed for Sr-89, Sr-90 and Fe-55 by a contract lab-oratory. Tritium and alpha analysis were done using liquid scintillation and gas flow proportional counting respectively.
The total radioactivity in effluent releases was determined from the measured concentration of each radionuclide present and the total volume of effluents released.
2.5 Batch Releases 2.5.1 Liquid
- 1. Number of batch releases:
- 2. Total time eriod for batch releases:
- 3. Maximum time eriod for a batch release:
- 4. Avera e time eriod for batch releases:
- 5. Minimum time eriod for a batch release:
- 6. Average stream flow (LPM) during periods of release effluent into a flowin stream:
1.75 E+02 3.51 E+04 min 6.12 E+02 min 2.00 E+02 min 2.1 E+01 min 1.18 E+02 2.5.2 Gaseous
- 1. Number of batch releases:
- 2. Total time eriod for batch releases:
- 3. Maximum time eriod for a batch release:
- 4. Avera e time eriod for batch releases:
- 5. Minimum time eriod for a batch release:
2.6 E+01 7.23 E+03 min 5.56 E+02 min 2.77 E+02 min 7.8 E+01 min
26 bnorma Releases 1
There were no abnormal releases of liquid or gaseous effluents during the reporting period.
3.0
SUMMARY
OF GASEOUS RADIOACTIVEEFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in tables 1A and 1B. Plant vent and Containment Vent releases are modeled as mixed mode and Air Ejector is modeled as ground level release.
4.0
SUMMARY
OF LIQUIDRADIOACTIVEEFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 2B.
5.0 SOLID WASTES i
The quantities of radioactive material released in shipments of solid waste transported from the site during the reporting period are summarized in table 3.
Principal nuclides were determined by gamma spectroscopy and non-gamma emitters were calculated from scaling factors determined by an independent laboratory from representative samples of that waste type. The majority of Dry Active Waste is processed utilizing an off-site processor who reduces the volume and then sends the waste for burial.
6.0 LOWER LIMITOF DETECTION NOT MET There were no liquid or gaseous releases for which the LLD for specified gamma emitting nuclides was not met.
~
~
7.0 RADIOLOGICALIMPACT An assessment of doses to the maximally exposed individual from gaseous and liquid effluents was performed for locations representing the maximum dose.
In all cases, doses were well below Technical Specification limits as defined in the ODCM. Doses were assessed based upon actual meteorological conditions considering the noble gas exposure, inhalation, ground plane and ingestion pathways.
The ingestion pathways considered were the fruit, vegetable, fish, drinking water, goat's milk, cow's milk and meat pathway.
The results of this assessment are presented in Tables 4A and 4B.
A review of 1995 data revealed that when the data was entered into the computer program only the final week of data for each month was used to calculate effluent releases during the month for continuous releases.
This meant that the dose to the general population was undercalculated for gaseous releases during the outage period and other months.
The data for 1995 was reentered and the calculation rerun. The new calculation results are included with this report.
All results still indicate that the maximally exposed adult received less than 2E-5 Rem total body dose and the maximally exposed child received <5E-5 Rem to the thyroid. These calculated doses are < 1% of the allowed maximum of 10CFR50, Appendix I exposures.
8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 1996 is not included with this report, but can be made available at the RGKE Ginna Plant.
9.0 LAND USE CHANGES There were no changes in critical receptor location for dose calculations during the reporting period. There were no large changes in land use within 5 miles of the plant. Additional new homes were built.
10.0 CHANGES TO THE OFFSITE DOSE CALCULATIONMANUAL (ODCM)
The ODCM was totally rewritten for the implementation of Amendment 61 to R.E. Ginna Technical Specifications.
The change became effective 2/24/96.
Changes were made to the ODCM to clarify wording on the Modes when specific effluent monitors are required to be operable and to add ACTION statements based on MODE changes.
For the steam generator replacement project, wording was added to describe actions after holes are cut through the containment dome.
Typos were corrected and non-required environmental sample points were removed from applicable tables.
11.0 CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)
P The change to the PCP for the implementation of Amendment 61 to the R.E.
Ginna Technical Specifications was the removal of the reference to R.E. Ginna Technical Specifications.
No other changes were required.
<2O MAJOR CHANGES TO RADWASTE TREATMENTSYSTEMS There were no major change's to the Radwaste Treatment Systems during the reporting period.
ROCHESTER GAS ELECTRIC CORPORATION Table 1A EFFLUENT AND WASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES JANUARY - JUNE 1996 A. Fission 5 activation gases
- 1. Total release
- 2. Average release rate for period
- 3. Percent of technical specification limit Unit Ci uCi/sec Quarter 1st 1.38E+ 01 1.75E+ 00 2.78E-04 Quarter 2nd 3.67E+ 01 4.67E+ 00 7.42E-04 Est. Total Error, %
5.90E+ 00 B. Iodines
- 1. Total iodine-131
- 2. Average release rate for period
- 3. Percent of technical specification limit C. Particulates
- 1. Particulates with half-lives ) 8days
- 2. Average release rate for period
- 3. Percent of technical specification limit
- 4. Gross alpha radioactivity Ci uCi/sec Ci uCi/sec Ci 2.51E-05 3.'I 9E-06 7.01 E-03 1.46E-06 1.86E-07 1.40E-05 1
~ 11E-04 6.60E+ 00 1.41 E-05 3.09E-02 5.27E-04 4.00E+ 01 6.71E-05 5.04E-03 D. Tritium
- 1. Total release Ci 8.59E+ 00 2.06E+ 01 3.20E+ 00
- 2. Average release rate for period
- 3. Percent-of technical specification limit uCi/sec 1.09E+ 00 1.28E-04 2.62E+ 00 3.09E-04 Note:
Isotope for which no value is given were not identified in applicable releases.
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ROCHESTER GAS ELECTRIC CORPORATION Table 1A EFFLUENT AND WASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES JULY - DECEMBER 1996 A. Fission 8c activation gases Unit Quarter 3rd Quarter 4th Est. Total Error, %
1
~ Total release
- 2. Average release rate for period
- 3. Percent of technical specification limit Ci uCi/sec 2.76E+ 01 7.50E+ 00 7.90E+ 00 3.47E+ 00 9.44E-01 5.51E-04 1.50E-04 B. Iodines
- 1. Total iodine-131 Ci 1.77E-05 1.09E-05 2.10E+ 01
- 2. Average release rate for period
- 3. Percent of technical specification limit 3.00E-03 4.89E-03 uCi/sec 2.23E-06 1.37E-06 C. Particulates
- 1. Particulates with half-lives ) 8days
- 2. Average release rate for period
- 3. Percent of technical specification limit
- 4. Gross alpha radioactivity D. Tritium
- 1. Total release
- 2. Average release rate for period
- 3. Percent of technical specification limit Ci uCi/sec Ci Ci uCi/sec 1.29E-06 1.63E-07 1.22E-05
- 6. 59E+ 00 8.29E-01 9.76E-05 5.77E-12 7.26E-13 5.46E-11 5.26E+ 00 6.62E-01 7.79E-05 4.00E+ 01 3.20E+ 00 Note:
Isotope for which no value is given were not identified in applicable releases.
ROCHESTER GAS ELECTRIC CORPORATION Table 1B EFFLUENT AND WASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - ELEVATED RELEASE Nuclides released 1.
Fission gases Unit Continuous Mode Quarter Quarter 1st 2nd Batch Mode Quarter Quarter 1st 2nd argon-41
~
krypton-85 krypton-85m krypton-87 Ci Ci Ci Ci 8.67E-01 9.1 5E-02 1.'1 9E-01 5.16E-03 3.55E-04 4.32E-04 2.37E-02 1.92E-02 8.08E-02 1.19E+00 3.36E-05 krypton-88 xenon-131m xenon-133 Ci Ci Ci 1.63E-01 5.84E-04 1
~ 13E-01 4.68E-03 6.27E+.00 4.70E+ 00 7.51E-01 3.00E+ 01 xenon-133m Ci 3.19E-02 1.31 E-04 8.66E-04 2.07E-02 xenon-135 xenon-135m xenon-1 38 others (specify)
Ci Ci
. Ci Ci Ci 7.11E-01 1.44E-03 3.18E+ 00 6.05E-01 1.47E+ 00 4.19E-03 2.02E-02 3.88E-02 1.03E-02 Total for period 2.
Iodines iodine-131 Ci Ci Ci 2.32E-05 1.08E-04 1.88E-06 2.20E-06 1.29E+01 5.32E+00 8.81E-01 3.14E+01 iodine-133 iodine-1 35 Total for period 3.
Particulates strontium-89 strontium-90 cesium-134 cesium-137 Nb-95 cobalt-58 cobalt-60 Total for period unidentified Ci Ci Ci.
Ci Ci Ci Ci Ci Ci Ci Ci Ci 9.01E-05 1.13E-04 1.46E-06 1.46E-06 4.65E-06 1.13E-04 5.60E-05 2.70E-04 2.01E-04 5.27E-04 1
~ 18E-06 3.06E-06 5.35E-07 2.73E-06 Note:
Isotope for which no value is given were not identified in applicable releases.
ROCHESTER GAS ELECTRIC CORPORATION Table 1B EFFLUENT AND WASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - ELEVATED RELEASE Nuclides released Unit Continuous Mode Quarter Quarter Batch Mode Quarter Quarter 3rd 4th 3rd 4th 1.
Fission gases argon-41 krypton-86 krypton-85m krypton-87 krypton-88 xenon-131m Ci Ci Ci Ci Ci Ci 3.19E-05 2.75E-01 2.56E-01 4.18E-03 1.11E-03 2.75E-03 1.57E-03 5.00E-02 6.05E-02 1.32E-04 xenon-133 xenon-133m xenon-135 xenon-135m xenon-138 others (specify)
Ci Ci Ci Ci Ci Ci Ci 1.97E+ 00 3.1 5E+ 00 1.33E-01 2.46E-03 3.94E-06 5.64E-03 2.15E+01 3.95E+00 3.46E+00 2.83E-01 1.19E-02 1.36E-03 Total for period 2.
Iodines Ci Ci 2.34E+ 01 7.10E+ 00 4.1 5E+ 00 4.01E-01 iodine-1 31 iodine-133 iodine-135 Total for period Ci Ci Ci Ci 1.54E-05 1.51E-01 1.51E-01 1.08E-05 1.08E-05 2.16E-05 2.35E-06 2.45E-07 2.60E-06 1.17E-08 1.1.7E-08 3.
Particulates strontium-89 strontium-90 cesium-134 cesium-1 37 Nb-95 cobalt-58 cobalt-60 Total for period unidentified Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.29E-06 1.29E-06 5.77E-12 5.77E-12 Note:
Isotope for which no value is given were not identified in applicable releases.
ROCHESTER GAS ELECTRIC CORPORATION Table 2A EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID EFFLUENTS - SUMMATIONOF ALLRELEASES JANUARY - JUNE 1996 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. Tritium Unit Ci uCi/ml Quarter 1st 8.16E-02 5.93E-10 6.20E-02 Quarter 2nd 3.18E-02 5.02E-10 1.56E-02 Est. Total Error, %
6.60E+ 00
- 1. Total release Ci 4.35E+01 3.59E+01 3.20E+ 00
- 2. Average diluted concentration during period
- 3. Percent of applicable limit C. Dissolved and entrained gases uCi/ml 3.16E-07 1.05E-02 5.66E-07 1,89E-02
- 1. Total release Ci 9.51 E-03 2.02E-03 3.50E+ 01
- 2. Average diluted concentration during period
- 3. Percent of applicable limit D. Gross alpha radioactivity 1
~ Total release uCi/ml Ci 6.91E-11 3.45E-05 N/A 3.20E-11 1.60E-05 N/A E. Vol. of waste released (prior to dilution)
Liters 4.64E+07 1.30E+07 5.00E+00 F. Vol. of dilution water used during period Liters 1.38E+11 6.33E+10 5.00E+00 Note:
Isotope for which no value is given were not identified in applicable releases.
ROCHESTER GAS ELECTRIC CORPORATION Table 2A EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID EFFLUENTS - SUMMATIONOF ALLRELEASES JULY - DECEMBER 1996 A. Fission and activation products Unit Quarter 3rd Quarter 4th Est. Total Error, %
- 1. Total release (not including tritium,
- gases, alpha)
Ci 3.87E-03 6.08E-04 8.50E+00
- 2. Average diluted concentration during period
- 3. Percent of applicable limit B. Tritium
- 1. Total release uCi/ml Ci 2.40E-11 1.18E-04 4.18E-12 1.22E-05 2.24E+01 1.72E+01 3.20E+00
- 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 uCi/ml Ci uCi/ml Ci 1.39E-07 4.64E-03 N/A 1.19E-07 3.95E-03 N/A E. Vol. of waste released (prior to dilution)
F. Vol. of dilution water used during period Liters 4.20E+ 07 5.64E+ 07 5.00E+ 00 Liters 1.61E+ 11 1.45E+ 11 5.00E+ 00 Note:
Isotope for which no value is given were not identified in applicable releases.
ROCHESTER GAS ELECTRIC CORPORATION k
Table 2B EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released chromium-51 manganese-54 iron-55 iron-59 cobalt-58 Unit Ci Ci Ci Ci Ci Quarter 1st 5.22E-05 Quarter 2nd 3.77E-05 9.14E-04 Quarter 1st 1.72E-05 5.07E-04 6.61 E-06 Quarter 2nd 4.1 1E-04 9.75E-05 cobalt-60 zinc-65 strontium-89 strontium-90 zirconium/niobium-95 molybdenum-99 silver-110m antimony-122 antimony-124 antimony-125 iodine-131 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.36E-05 3.90E-05 5.62E-05 6.19E-03 1.86E-03 7.48E-05 1.26E-05 4.33E-05 2.86E-04 7.43E-03 1.74E-03 1.50E-02 3.29E-05 5.78E-03 9.75E-06 6.21E-05 1.64E-06 iodine-133 Ci 1.95E-02 2.56E-03 1.98E-02 iodine-135 cesium-134 cesium-1 36 Ci Ci Ci 4.53E-03 1.24E-03 3.78E-04 3.64E-04 5.01E-05 4.23E-05 1.82E-02 2.15E-03 3.81E-04 1.76E-04 cesium-137 barium/lanthanum-140 cerium-141 Te-123m Ru-103 Ci Ci Ci Ci Ci 7.37E-05 3.49E-04 2.27E-05 2.30E-03 3.36E-04 1.72E-04 Total for period (above) unidentified Ci Ci 3.08E-02 7.51E-03 5.08E-02 2 43E-02 xenon-133 xenon-1 35 Ci Ci 1.19E-03 5.99E-04 1.34E-03 1.03E-03 3.41 E-03 3.95E-04 3.58E-03 Note:
Isotope for which no value is given were not identified in applicable releases.
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ROCHESTER GAS ELECTRIC CORPORATION Table 2B EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Quarter Quarter Quarter Quarter Unit 3rd 4th 4th 3rd Ci chromium-51 Ci manganese-54 iron-55 iron-59 Ci Ci 8.09E-06 Ci cobalt-58 3.92E-05 7.21E-05 Ci cobalt-60 zinc-65 strontium-89 Ci Ci Ci strontium-90 2.49E-06 Ci zirconium/niobium-95 molybdenum-99 1.03E-05 Ci 1.82E-05 Ci silver-110m antimony-122 Ci Ci 3.66E-05 4.36E-05 2.53E-04 antimony-124 antimony-1 25 iodine-131 Ci Ci Ci iodine-133 Ci iodine-135 cesium-134 cesium-136 Ci Ci 3.72E-03 2.07E-04 5.05E-05 Ci 1.87E-05 cesium-137 Ci barium/lanthanum-140 cerium-141 Ru-106 Ci Ci Ci Ru-103 1
~ 52E-04 4.01E-04 3.72E-03 2.07E-04 Ci Total for period (above) unidentified Ci Ci xenon-133 xenon-135 Ci Note:
Isotope for which no value is given were not identified in applicable releases.
Table 3 EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS January 1, 1996 - December 31, 1996 A.
SOLID WASTE SHIPPED OFFSITE FOR BURIALOR DISPOSAL -
(Not irradiated fuel) 1.
T e of waste a.
Spent resins, filter sludges, eva orator bottoms, etc.
b.
Dry compressible waste, contaminated e ui, etc.
c.
Irradiated components, control rods, etc.
d.
Other:
Unit m'i m'i m
Ci fn Ci 12 month eriod 1.24 E+01 6.3 E+01 1.16 E+01 2.57 E-01 2.8 E-03 2.32 E+01 Est. total Error%
2 E+00 2 E+00 2 E+00 2 E+00 5 E+00 2 E+00 2.
Estimate of major nuclide corn osition b
t e of waste
- a. Ni-63 4.54 E+01
- b. Fe-55 3.32 E+01 c.
Fe-59 9.02 E+01 Co-60 Fe-55 Cs-1 37 Sb-125 Cs-1 34 Ce-144 Mn-54 PU-241 3.29 E+01 9.0 E+00 5.7 E+00 3.2 E+00 9 E-01 7 E-01 6 E-01 1 E-01 Co-58 Co-60 Cs-1 37 Ni43 Sb-124 Cr-51 Nb-95 Ce-144 Sb-125 Zr-95 Cs-1 34 Mn-54 PU-241 1.27 E+01 1 04 E+01 8.0 E+00 6.5 E+00 5.2 E+00 5.1 E+00 4.6 E+00 3.2 E+00 2.9 E+00 2.8 E+00 1.9 E+00 1.4 E+00 8 E-01 Co-60 Mn-54 4.9 E+00 4.7 E+00 3.
Solid Waste Dis osition Numb'er of::Shi ments':....
- .Mode.of.Trans ortation Hi hwa Vehicle Hi hwa Vehicle Hi hwa Vehicle Destinatiori OakRid e, TN Mem his, TN Barnwell, SC B.
IRRADIATEDFUEL SHIPMENTS (Disposition)
.. Number:of Shi ments:,.
None Mode. of.Traris or'tation Destination
TabIe 4A Radiation Doses to Maximally Exposed Individual Receptor From Gaseous Releases in Rem First Quarter 1996 P4i$+~."-4<i"ADULT,:,@pl<~- ':"'+""""'~ +~~-"a-'.,')v '4>>TEEN".-4~~~$'-"~~%i@ <~44~."'jX~'.:x@lCHILDp'V>'"'g"'W<$:
NNE NE ENE ESE SE SSE SSW SW WSW W
WNW NW NNW T.BODY THYRD SKIN T.BODY 1.6E-07 1.6E-07 8.7E-07 1.6E-07 1.6E-07 1.6E-07 5.9E-07 1.6E-07 1.1E-07 1.1E-07 5.6E-07 1.1E-07 1.4E-07 1.4E-07 7.3E-07 1.4E-07 2.2E-06 2.2E-06 5.4E-06 2.2E-06 1.5E-06 1.5E-06 3.6E-06 1.5E-06 3.0E-06 3.1E-06 7.9E-06 3.0E-06 2.6E-06 2.6E-06 6.7E-06 2.6E-06 2.8E-06 2.8E-06 6.9E-06 2.8E-06 3.5E-06 3.5E-06 8.1E-06 3.5E-06 7.6E-06 7.6E-06 1.7E-05 7.6E-06 2.6E-06 2.6E-06 5.7E-06 2.6E-06 2.3E-06 2.3E-06 4.5E-06 2.3E-06 1.1E-06 1.1E-06 2.0E-06 1.1E-06 4.9E-08 5.0E-08 2.7E-07 4.9E-08 1.1E-07 1.1E-07 6.0E-07 1.1E-07 THYRD 1.6E-07 1.6E-07 1.1E-07 1.4E-07 2.2E-06 1.6E-06 3.1E-06 2.6E-06 2.8E-06 3.5E-06 7.7E-06 2.6E-06 2.3E-06 1.1E-06 5.1E-08 1.1E-07 SKIN T.BODY 8.7E-07 1.6E-07 5.9E-07 1.6E-07 5.6E-07 1.0E-07 7.3E-07 1.3E-07 5.4E-06 2.1E-06 3.6E-06 1.5E-06 7.9E-06 3.0E-06 6.7E-07 2.6E-06 6.9E-06 2.8E-06 8.1E-06 3.5E-06 1.7E-05 7.6E-06 5.7E-06 2.6E-06 4.5E-06 2.3E-06 2.0E-06 1.1E-06 2.7E-07 4.7E-08 6.0E-07 1.0E-07 THYRD SKIN 1.6E-07 8.7E-07 1.6E-07 5.9E-07 1.1E-07 5.6E-07 1.4E-07 7.3E-07 2.2E-06 5.4E-06 1.5E-06 3.6E-06 3.0E-06 7.9E-06 2.6E-06 6.7E-06 2.8E-06 6.9E-06 3.5E-06 8.1E-06 7.6E-06
'.7E-05 2.6E-06 5.7E-06 2.3E-06 4.5E-06 1.1E-06 2.0E-46 4.9E-08 2.7E-07 1.1E-07 6.0E-07 T.BODY THYRD SKIN 1.4E-07 1.4E-07 8.7E-07 1.4E-07 1.5E-07 5.9E-07 9.1E-08 9.4E-08 5.6E-07 1.2E-07 1.2E-07 7.3E-07 2.1E-06 2.1E-06 5.4E-06 1.5E-06 1.5E-06 3.6E-06 2.9E-06 2.9E-06 7.9E-06 2.5E-06 2.5E-06 6.7E-06 2.7E-06 2.7E-06 6.9E-06 3.4E-06 3.5E-06 8.1E-06 7 4E-06 7 5E-06 1 7E-05 2.5E-06 2.6E-06 5.7E-06 2.3E-06 2.3E-06 4.5E-06 1.1E-06 1.1E-06 2.0E-06 4.2E-08 4.3E-08 2.7E-07 9.0E-08 9.3E-08 6.0E-07 7.6E-06 7.6E-06 1.7E-05 7.6E-06 7.7E-06 1.7E-05 7.6E-06
. 7.6E-06 1.7E-05 7.4E-06 7.5E-06 1.7E-05
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Table 4A Radiation Doses to Maximally Exposed Individual Receptor From Gaseous Releases in Rem Third Quarter 1996 ADULT
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'HILD jNFANT N
NNE ENE ESE SE SSE SSW SW WSW W
WNW NW NNW T.BODY 1.3E-07 1.20E-07 1.3E-07 6.7E-08 1.3E-06 2.4E-06 9.4E-07 3.3E-07 5.9E-07 3.7E-07 5.8E-07 5.6E-07 3.8E-07 2.4E-08 3.6E-08 6.3E-08 THYRD SKIN T.BODY THYRD 2.1E-07 1.6E-07 1.3E-07 2.8E-07 2.1E-07 1.6E-07 1.3E-07 2.8E-07 2.1E-07 1.6E-07 1.3E-07 2.9E-07 1.1E-06 8.6E-08 6.8E-08 1.5E-06 3.7E-05 1.1E-06 1.4E-06 4.2E-05 8.6E-05 2.2E-06 2.6E-06 9.5E-05 2.2E-05 7.9E-07 1.0E-06 2.5E-05 7.0E-06 2.1E-07 3.5E-07 8.2E-06 1.0E-05 3.3E-07 6.4E-07 1.2E-05 3.6E-06 1.2E-07 4.1E-07 4.7E-06 3.3E-06 2.1E-07 6.4E-07 4.2E-06 2.5E-06 2.0E-07 6.3E-07 3.3E-06 1.2E-06 1.0E-07 4.3E-07 1.5E-06 6.4E-07 1.7E-08 2.6E-08 6.3E-07 5.9E-07 4.5E-08 3.7E-08 7.9E-07 1.1E-06 8.3E-08 6.4E-08 1.5E-06 SKIN T.BODY 1.6E-07 1.2E-07 1.6E-07 1.2E-07 1.6E-07 1.2E-07 8.6E-08 6.5E-08 1.1E-06 1.8E-06 2.2E-06 3.1E-06 7.9E-07 1.2E-06 2.1E-07 4.5E-07 3.3E-07 8.0E-07 1.2E-07 5.5E-07 2.1E-07 8.6E-07 2.0E-07 8.6E-07 1.0E-07 6.1E-07 1.7E-08 3.2E-08 4.5E-08 3.5E-08 8.3E-08 6.1E-08 THYRD SKIN 3.7E-07 1.6E-07 3.6E-07 1.6E-07 3.7E-07 1.6E-07 2.0E-06 8.6E-08 7.1E-05 1.1E-06 1.7E-04 2.2E-06 4.2E-05 7.9E-07 1.4E-05 2.1E-07 2.0E-05 3.3E-07 9.1E-06 1.2E-07 8.0E-06 2.1E-07 5.9E-06 2.0E-07 2.2E-06 1.0E-07 1.0E-06 1.7E-08 1.0E-06 4.5E-08 2.0E-06 8.3E-08 T.BODY THYRD 9.5E-07 3.4E-07 9.4E-07 3.3E-07 9.7E-07 3.4E-07 5.2E-08 1.8E-06 1.1E-06 6.5E-05 1.9E-06 1.5E-04 7.7E-07 4.2E-05 3.2E-07 1.6E-05 4.0E-07 1.7E-05 3.8E-07 1.5E-05 6.3E-07 1.3E-05 6.1E-07 9.3E-06 3.5E-07 2.3E-06 1.1E-08 2.6E-07 2.8E-08 9.5E-07 4.9E-08 1.8E-06 SKIN 1.6E-07 1.6E-07 1.6E-07 8.6E-08 1.1E-06 2.2E-06 7.9E-07 2.1E-07 3.3E-07 1.2E-07 2.1E-07 2.0E-07 1.0E-07 1.7E-08 4.5E-08 8.3E-08 2.4E-06 8.6E-05 2.2E-06 2.6E-06 9.5E-05 2.2E-06 3.1E-06 1.7E-04 2.2E-06 1.9E-06 1.5E-04 2.2E-06
Table 4A Radiation Doses to Maximally Exposed Individual Receptor From Gaseous Releases in Rem Fourth Quarter 1996
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NNE NE ENE ESE SE SSE SSW SW WSW W
WNW NW NNW T.BODY 4.2E-08 4.2E-08 3.6E-08 3.7E-08 1.5E-07 2.8E-07 2.3E-07 7.9E-08 4.3E-07 3.0E-07 3.4E-07 2.2E-07 1.3E-07 5;8E-09 1.3E-08 3.0E-08 THYRD SKIN T.BODY THYRD SKIN T.BODY 4.2E-08 4.5E-08 4.2E-08 4.2E-08 4.5E-08 3.9E-08 4.2E-08 4.5E-08 4.2E-08 4.3E-08 4.5E-08 3.9E-08 3.6E-08 3.5E-08 3.6E-08 3.7E-08 3.5E-08 3.3E-08 3.8E-08 3.7E-08 3.7E-08 3.8E-08 3.7E-08 3.5E-08 1.5E-07 1.3E-07 1.6E-07 1.6E-07 1.3E-07 1.9E-07 3.0E-07 2.8E-07 2.9E-07 3.2E-07 2.8E-07 3.3E-07 2.4E-07 2.5E-07 2.4E-07 2.5E-07 2.5E-07 2.6E-07 8.6E-08 7.9E-08 8.3E-08 9.0E-08 7.9E-08 9.2E-08 4.7E-07 4.1E-07 4.5E-07 4.9E-07 4.1E-07 5.3E-07 3.2E-07 3.0E-07 3.2E-07 3.5E-07 3.0E-07 3.7E-07 3.7E-07 3.3E-07 3.6E-07 4.0E-07 3.3E-07 4.2E-07 2.4E-07 2.1E-07 2.3E-07 2.5E-07 2.1E-07 2.7E-07 1.3E-07 1.0E-07 1.4E-07 1.4E-07 1.0E-07 1.7E-07 6.2E-09 5.4E-09 6.1E-09 6.5E-09 5.4E-09 7.2E-09 1.3E-08 1.2E-08 1.3E-08 1.3E-08 1.2E-08 1.2E-08 3.0E-08 2.9E-08 3.0E-08 3.1E-08 2.9E-08 2.8E-08 THYRD SKIN 4.0E-08 4.5E-08 3.9E-08 4.5E-08 3.4E-08 3.5E-08 3.6E-08 3.7E-08 2.0E-07 1.3E-07 3.7E-07 2.8E-07 2.8E-07 2.5E-07 1.1E-07 7.9E-08 5.9E-07 4.1E-07 4.1E-07 3.0E-07 4.8E-07 3.3E-07 3.0E-07 2.1E-07 1.8E-07 1.0E-07 7.8E-09 5.4E-09 1.2E-08 1.2E-08 2.9E-08 2.9E-08 T.BODY THYRD 3.0E-08 3.0E-08 2.9E-08 3.0E-08 2.5E-08 2.5E-08 2.6E-08 2.7E-08 1.2E-07 1.2E-07 2.0E-07 2.6E-07 1.6E-07 1.9E-07 5.6E-08 7.5E-08 2.7E-07 3.4E-07 2.0E-07 2.5E-07 2.6E-07 3.5E-07 1.6E-07 2.1E-07 1.0E-07 1.2E-07 2.9E-09 3.0E-09 8.6E-09 8.9E-09 2.1E-08 2.1E-08 SKIN 4.5E-08 4.5E-08 3.5E-08 3.7E-08 1.3E-07 2.8E-07 2.5E-07 7.9E-08 4.1E-07 3.0E-07 3.3E-07 2.1E-07 1.0E-07 5.4E-09 1.2E-08 2.9E-08 4.3E-07
'.7E-07 4.1E-07 4.5E-07 4.9E-07 4.1E-07 5.3E-07 5.9E-07 4.1E-07 2.7E-07 3.5E-07 4.1E-07
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Table 4B Radiation Doses to Maximally Exposed Individual Receptor Radiation Dose To Maximally Exposed Individual From Liquid Release in Rem 1996 T. Body Bone Thyroid T. Body Bone Thyroid T. Body Bone Thyroid T. Body Bone Thyroid Adult 3.50E-07 2.55E-08 3.92E-07 8.86E-06 1.28E-07 9.01E-06 1.87E-06 9.06E-07 8.01E-05 2.86E-07 1.52E-08 3.23E-07 Teen First Quarter 3.52E-07 2.55E-08 4.04E-07 Second Quarter 9.44E-06 1.46E-07 9.59E-06 Third Quarter 1.97E-06 9.55E-07 8.50E-05 Fourth Quarter 3.08E-07 1.83E-08 3.44E-07 Child 3.14E-07 2.54E-08 3.77E-07 1.11E-05 2.11E-07 1.13E-05 2.40E-06 1.25E-06 1.43E-04 3.83E-07 2.96E-08 4.45E-07 Infant 1.91E-07 2.55E-08 2.49E-07 4.75E-06 1.17E-07 5.04E-06 1.21E-06 9.63E-07 9.88E-05 1.30E-07 1.40E-08 1.82E-07
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