ML061380535
| ML061380535 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/15/2006 |
| From: | Constellation Generation Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML061380535 (25) | |
Text
2005 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244
TABLE OF CONTENTS 1.0 Introduction 1 2.0 Supplemental Information 1 2.1 Regulatory Limits 1 2.2 Maximum Permissible Concentrations 3 2.3 Release Rate Limits 3 2.4 Measurements and Approximations of Total Radioactivity 3 2.5 Batch Releases 4 2.6 Abnormal Releases 4 3.0 Summary of Gaseous Radioactive Effluents 5 4.0 Summary of Liquid Radioactive Effluents 5 5.0 Solid Waste 5 6.0 Lower Limit of Detection 6 7.0 Radiological Impact 6 8.0 Meteorological Data 7 9.0 Land Use Census Changes 7 10.0 Changes to the Offsite Dose Calculation Manual 8 11.0 Changes to the Process Control Program 8 12.0 Major Changes to Radwaste Treatment Systems 8 13.0 Inoperable Monitors 8
LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases ..................... . 9 Table 2A Liquid Effluents - Summation of all Releases ...................... . 11 Table 1B Gaseous Effluents - Continuous and Batch Releases ................................. 13 Table 2B Liquid Effluents - Continuous and Batch Releases ...................................... 15 Table 3 Solid Waste and Irradiated Fuel Shipments ................................................ 17 Table 4A Radiation Dose to Nearest Individual Receptor from Gaseous Releases ... 18 Table 4B Radiation Dose to Nearest Individual Receptor from Liquid Releases ........ 22
1.0 INTRODUCTION
This Annual Radioactive Effluent Release Report is for the R.E. Ginna Nuclear Power Plant and is submitted in accordance with the requirements of Technical Specification Section 5.6.3. The report covers the period from January 1, 2005 through December 31, 2005.
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.
All gaseous 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 SUPPLEMENTAL INFORMATION 2.1 Re-iulatorv Limits The ODCM limits applicable to the release of radioactive material in liquid and gaseous effluents are:
2.1.1 Fission and Activation Gases 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 if allowed 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.
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2.1.2 Radioiodine, Tritium 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 if allowed 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 Liquid Effluents 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, as explained in Section 1 of the ODCM. For dissolved or entrained noble gases the total activity due to dissolved or entrained noble gases shall not exceed 2E-04 uCi/ml.
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.
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2.2 Effluent Concentration Limit (ECL) 2.2.1 For gaseous effluents, effluent concentration limits are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary, in accordance with Technical Specification 5.5.4.g.
2.2.2 For liquid effluents, ten times the effluent concentration values specified in IOCFR20, 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. A value of 2E-04 uCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.
2.3 Release Rate Limits Based on Average Nuclide Energy The release rate limits for fission and activation gases from the R.E. Ginna Nuclear Power Plant are not based on the average energy of the radionuclide mixture in gaseous effluents; therefore, this value is not applicable. Howeverthe 2005 average beta/gamma energy of the radionuclide mixture in fission and activation gases released from Ginna is available for review upon request.
2.4 Measurements and Approximations of Total Radioactivity 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 performed 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.
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2.5 Batch Releases 2.5.1 Liquid
- 1. Number of batch releases: 9.9 E+01
- 2. Total time period for batch releases: 1.71 E+05min
- 3. Maximum time period for a batch release: 4.83 E+04 min
- 4. Average time period for batch releases: 1.72 E+03 min
- 5. Minimum time period for a batch release: 4.0 E+01 min
- 6. Average blowdown (LPM) during periods of effluent release into the discharge canal. 4.87 E+02 LPM 2.5.2 Gaseous
- 1. Number of batch releases: 3.3 E+01
- 2. Total time period for batch releases: 5.11 E+05 min
- 3. Maximum time period for a batch release: 4.46 E+04 min
- 4. Average time period for batch releases: 1.55 E+04 min
- 5. Minimum time period for a batch release: 1.08 E+02 min 2.6 Abnormal Releases There were no abnormal or unplanned releases in 2005. Examples of ventilation system deficiencies that could result in small quantities of air exiting controlled areas by pathways other than monitored vent exhaust have been documented by the corrective action process. Sampling did not result in any measured radioactivity.
Gaseous release permit methodology is conservative against small deviations in flow direction, if activity were present.
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3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS 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. In 2005, Ginna revised gaseous release procedures to remove the unrealistically conservative step of including sample activity that was less than the Minimum Detectable Activity, MDA, (which is the calculated a posteriori LLD for each sample counted), as if it were actually a measured value. This conservatism had been included in procedures years ago to account for sample purges and valve leaks which have since been demonstrated to be dramatically lower than the conservative estimate.
Any leaks or purges with measurable activity are now included in release permits by integration of RMS data. This change has resulted in lower total reported activity in gaseous effluents for 2005 as compared to previous years.
4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 2B.
5.0 SOLID WASTE 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.
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6.0 LOWER LIMIT OF DETECTION The required Lower Limit of Detection, (LLD), as defined in the ODCM, was met for all samples used in reporting effluent releases for 2005.
The following samples failed to meet the a posteriori MDA for high background activity in the samples.
"A" Monitor Tank release #2005014, 2/9/05:
Cs-137 5.57E-7 uCi/mL "A" Monitor Tank release #2005017, 2/12/05:
Cs-137 7.87E-7 uCi/mL, Fe-59 6.17E-7 uCi/mL, Zn-65 6.13E-7 uCi/mL "A" Monitor Tank rlease #2005018, 2/14/05:
Cs-137 1.12E-6 uCi/mL, Cs-134 5.42E-7 uCi/mL, Fe-59 9.65E-7 uCi/mL, Zn-65 9.09E-7 uCi/mL "A" Monitor Tank release #2005027, 2/23/05:
Cs-137 7.12E-7 uCi/mL, Fe-59 5.17E-7 uCi/mL, Zn-65 5.39E-7 uCi/mL 7.0 RADIOLOGICAL IMPACT An assessment of doses to the maximally exposed individual from gaseous and liquid effluents was performed for locations representing the maximum calculated dose in occupied sectors. Meteorological sectors from WNW through ENE are entirely over Lake Ontario. In all cases, doses were well below Technical Specification limits as defined in the ODCM. Doses were assessed based upon historical meteorological conditions considering the noble gas exposure, inhalation, ground plane exposure, and ingestion pathways. The ingestion pathways considered were the fruit, vegetable, fish, drinking water, goat's milk, cows milk and cow meat pathways. Results of this assessment are presented in Tables 4A and 4B.
Since the events of September 11, 2001, Ginna Security has been augmented by full-time presence of the New York State Police and the New York National Guard.
These personnel have posts within the site boundary. For this reason, the exposure and uptake pathways for 2005 are calculated using maximum meteorological dispersion and deposition parameters at on-site posts, as well as at the site boundary.
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7.1 Total Dose 40CFRI90 limits the total dose to members of the public due to radiation and radioactivity from uranium fuel cycle sources to:
<25 mrem total body or any organ and;
<75 mrem thyroid for a calendar year.
Using the maximum exposure and uptake pathways, the maximum liquid pathways, and the direct radiation measurements onsite in the vicinity of the National Guard outpost, yield the following dose summaries to the hypothetical maximally exposed individual member of the public on-site.
7.6 mrem total body (7.6 mrem direct radiation plus 6.32E-3 mrem all other pathways).
6.14E-3 mrem thyroid (maximum organ dose).
Using the maximum exposure and uptake pathways, the maximum liquid pathways, and the maximum direct radiation measurements at the site boundary, yields the following dose summaries to the hypothetical maximally exposed individual member of the public off-site. This dose conservatively bounds any real member of the public.
5.2 mrem total body (5.2 mrem direct radiation plus 6.32E-3 mrem all other pathways).
6.14E-3 mrem thyroid, maximum organ dose.
8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 2005 is not included with this report, but can be made available at the R. E. Ginna Nuclear Power Plant.
9.0 LAND USE CENSUS 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 are being built at an increasing rate compared to past years.
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10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The ODCM was revised March 29, 2005, to allow selected liquid and gaseous effluent monitors to be removed from service for short periods of time for monthly/quarterly testing without being declared inoperable, and to provide a replacement control sample point on Lake Ontario. No major changes were made to requirements or to methodology used in calculation of offsite dose. See attached ODCM, Revision 20.
11.0 CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Process Control Program during the reporting period.
12.0 MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS There were no major changes to the Radwaste Treatment Systems during the reporting period. However, a major effort to reconfigure and optimize the Liquid Radwaste Treatment System was undertaken by Engineering in 2005.
Improvements in procedures for processing water are in place and reductions in effluent activity have been achieved.
13.0 INOPERABLE MONITORS
- RM-15A, Out of service for water trap repair, 10/4/05 - 10/11/05.
- R-10B, Out of service for failed source check, 2/11/05 - 2/24/05
- R-1OB skid out of service for high sample flow, 8/5/05 - 9/3/05.
- R-13 out of service for high sample flow, 8/13/05 - 8/25/05.
14.0 CHANGES TO PREVIOUS ANNUAL EFFLUENT OPERATING REPORTS None 8
R. E. Ginna Nuclear Power Plant Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES January -June 2005 Unit Quarter Quarter Est. Total A. Fission & activation gases I 1st 2nd Error, %
- 1. Total release Ci 4.40E+00 2.30E-01 1.50E+01
- 2. Average release rate for period uCi/sec 5.85E-01 3.05E-02
- 3. Percent of technical specification limit % 9.29E-05 4.84E-06 B. lodines
- 1. Total iodine-131 Ci 6.69E-06 1.50E+01
- 2. Average release rate for period uCi/sec 8.90E-07
- 3. Percent of technical specification limit _ 1.93E-03 C. Particulates
- 1. Particulates with half-lives > 8days Ci l l l
- 2. Average release rate for period j uCi/sec
- 3. Percent of technical specification limit %
- 4. Gross alpha radioactivity Ci D. Tritium
- 1. Total release l Ci 1.32E+01 1.01E+01 9.20E+00
- 2. Average release rate for period uCi/sec 1.76E+00 4.36E-01
- 3. Percent of technical specification limit % 2.07E-02 1.71 E-02 Note: Isotope for which no value is given were not identified in applicable releases.
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R. E. Ginna Nuclear Power Plant Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2005 Unit Quarter Quarter Est. Total A. Fission & activation gases 3rd 4th Error, %
- 1. Total release J Ci 9.38E-02 1.03E-01 1.50E+01
- 2. Average release rate for period uCi/sec 1.24E-02 1.36E-02
- 3. Percent of technical specification limit _ 1.97E-06 2.16E-06 B. lodines
- 1. Total iodine-131 Ci
- 2. Average release rate for period uCi/sec
- 3. Percent of technical specification limit __
C. Particulates
- 1. Particulates with half-lives > 8days Ci 9.37E-1 0 2.00E+01
- 2. Average release rate for period uCi/sec 1.26E-1 0
- 3. Percent of technical specification limit l _% 1.19E-08
- 4. Gross alpha radioactivity Ci D. Tritium
- 1. Total release Ci 1.68E+01 1.67E+01 9.20E+00
- 2. Average release rate for period uCi/sec 2.22E+00 2.21 E+00
- 3. Percent of technical specification limit % 2.67E-02 I 2.66E-02 Note: Isotope for which no value is given were not identified in applicable releases.
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R. E. Ginna Nuclear Power Plant Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January - June 2005 Unit Quarter Quarter Est.Total A. Fission and activation products 1St 2nd Error, %
- 1. Total release (not including tritium, gases, alpha) Ci 3.43E-03 5.83E-04 9.90E+00
- 2. Average diluted concentration during period uCi/mi 9.20E-12 1.02E-12
- 3. Percent of applicable limit ___ 7.67E-05 8.50E-06 B. Tritium
- 1. Total release Ci 1.36E+02 2.97E+01 9.20E+00
- 2. Average diluted concentration during period uCi/ml 3.65E-07 5.22E-08
- 3. Percent of applicable limit _ 3.65E-03 5.22E-04 C. Dissolved and entrained gases
- 1. Total release Ci 2.53E-04 2.88E-05 9.90E+00
- 2. Average diluted concentration I I during period uCi/ml 6.78E-13 5.05E-14
- 3. Percent of applicable limit j 3.39E-07 2.53E-08 D. Gross alpha radioactivity
- 1. Total release Ci E. Vol. of waste released (prior to dilution) Liters 8.06E+07 8.25E+07 F. Vol. of dilution water used during period Liters 3.74E+1 1 5.68E+1 1 Note: Isotope for which no value is given were not identified in applicable releases.
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R. E. Ginna Nuclear Power Plant Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2005 Unit Quarter Quarter Est.Total A. Fission and activation products 3rd 4th Error, %
- 1. Total release (not including tritium, gases, alpha) Ci 2.36E-04 2.83E-04 9.90E+00
- 2. Average diluted concentration during period uCVmI 5.02E-13 5.82E-13
- 3. Percent of applicable limit % 4.18E-06 4.85E-06 B. Tritium =
- 1. Total release Ci 6.11E+01 3.32E+01 9.20E+00
- 2. Average diluted concentration during period uCi/ml 1.30E-07 6.28E-08
- 3. Percent of applicable limit % 1.39E-03 6.28E-04 C. Dissolved and entrained gases
- 1. Total release Ci 2.97E-04 9.90E+00
- 2. Average diluted concentration during period uCi/ml 6.32E-13
- 3. Percent of applicable limit % 3.16E-07 D. Gross alpha radioactivity
- 1. Total release Ci E. Vol. of waste released (prior ro dilution) Liters 9.80E+07 1.06E+08 F. Vol. of dilution water used during period Liters 4.69E+11 4.84E+1 1 Note: Isotope for which no value is given were not identified in applicable releases.
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R. E. Ginna Nuclear Power Plant Table 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES January - June 2005 Continuous Mode Batch Mode Nuclides released I Unit Quarter lQuarter Quarter Quarter 1st 2nd l st 2nd
- 1. Fission gases, argon-41 Ci 3.73E-02 2.88E-01 5.40E-02 krypton-85 Ci krypton-85m Ci 1.29E-03 1.65E-04 krypton-87 Ci krypton-88 Ci 2.20E-03 xenon-131 m Ci 5.73E-03 xenon-133 Ci 2.76E+00 1.03E+00 1.68E-01 xenon-1 33m Ci 1.26E-02 7.12E-04 xenon-135 Ci 2.04E-01 2.19E-02 6.62E-03 xenon-135m Ci 3.01 E-02 xenon-1 38 Ci others (specify) Ci Ci Ci Ci Total for period Ci
- 2. lodines iodine-131 Ci 5.09E-06 l_2.34E-07 l iodine-132 Ci 9.78E-07 iodine-133 Ci 2.50E-07 Total for period Ci 1.60E-06 iodine-135 Ci 1.40E-07
- 3. Particulates strontium-89 Ci strontium-90 Ci cesium-134 Ci cesium-137 Ci niobium-95 Ci cobalt-58 Ci cobalt-60 Ci Total for period Ci unidentified Ci Note: Isotope for which no value is given were not identified in applicable releases.
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R. E. Ginna Nuclear Power Plant Table 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES July - December 2005 Continuous Mode Batch Mode Nuclides released l Unit Quarter Quarter Quarter Quarter 3rd 4th3rd 4th
- 1. Fission gases argon-41 Ci 5.14E-02 4.85E-02 krypton-85 Ci krypton-85m Ci krypton-87 Ci krypton-88 Ci xenon-131 m Ci xenon-133 Ci 4.18E-02 5.98E-02 xenon-1 33m Ci xenon-135 Ci _ 4.07E-03 5.42E-02 xenon-135m Ci xenon-138 Ci others (specify) Ci Ci Ci Ci
_Total for period Ci I
- 2. Iodines iodine-1 31 Ci iodine-133 Ci iodine-1 35 Ci Total for period Ci
- 3. Particulates strontium-89 Ci 9.37E-10 strontium-90 Ci zirconium-95 Ci silver- I lOm Ci niobium-95 Ci cobalt-58 Ci cobalt-60 Ci _ _
Total for period Ci unidentified Ci Note: Isotope for which no value is given were not identified in applicable releases.
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R. E. Ginna Nuclear Power Plant Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS January-June 2005 I Continuous Mode I B itch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 11st 2nd chromium-51 Ci manganese-54 Ci 5.66E-06 iron-55 Ci iron-59 Ci cobalt-58 Ci 2.27E-03 2.22E-04 cobalt-60 Ci 7.32E-04 1.21 E-05 zinc-65 Ci strontium-89 Ci strontium-90 Ci zirconium/niobium-95 Ci 1.03E-05 molybdenum-99 Ci silver-110m Ci 6.74E-05 antimony-122 Ci antimonv-124 Ci antimony-125 Ci 3.28E-05 8.51 E-06 iodine-131 Ci iodine-132 Ci 1.50E-04 2.44E-04 iodine-i35 Ci cesium-1 34 Ci cesium-I 36 Ci cesium-1 37 Ci barium/lanthanum-140 Ci cerium-141 Ci Te-132 Ci 1 .40E-04 1.04E-04 Sn-1 13 Ci __ __ __ _ _ _ _
Co-57 Ci _ 3.03E-05 Total for period (above) - Ci unidentified Ci lxenon-133 l Ci I I I 2.53E-04 I 2.00E-05 lxenon-135 I Ci I I 8.73E-06 Note: Isotope for which no value is given were not identified in applicable releases.
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R. E. Ginna Nuclear Power Plant Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS July - December 2005 I Continuous Mode I Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th chromium-51 Ci manganese-54 Ci iron-55 Ci 2.45E-04 1.01 E-04 iron-59 Ci cobalt-58 Ci 2.04E-04 1.26E-04 cobalt-60 Ci 3.19E-05 1.38E-04 zinc-65 Ci _
strontium-89 Ci strontium-90 Ci niobium-95 Ci molybdenum-99 Ci i silver-11 Om Ci 1.21 E-05 antimony-122 Ci antimony-124 Ci antimony-125 Ci iodine-131 Ci iodine-1 32 Ci iodine-135 Ci cesium-134 Ci cesium-1 36 Ci cesium-137 Ci _
barium/lanthanum-140 Ci cerium-141 Ci Te-132 Ci Zr-95 Ci Co-57 Ci 3.36E-06 Total for period (above) Ci unidentified Ci Ixenon-133 l Ci I I I 2.79E 5.01E-06 l Ixenon-135 Ci I I I1.86E-05 I Note: Isotope for which no value is given were not identified in applicable releases.
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Table 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 2005 - December 31, 2005 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL - (Not irradiated fuel)
- 1. Type of waste Unit 12 month period Est. total Error %
- a. Spent resins, filter sludges, m3 5.88 7.0 E+00 evaporator bottoms, etc. Ci 0.607 1.4 E+01
- b. Dry compressible waste, m3 33.02 7.0 E+00 contaminated equip, etc. Ci 0.268 1.4 E+01
- c. Irradiated components, control m3 N/A N/A rods, etc. Ci N/A N/A
- d. Other: m3 N/A N/A Ci N/A N/A 2.Estimate of major nuclide composition (by type of waste)
- a. b. l d. (None)
Co-58 % 48.27 Fe-55 % 28.26 %
Ni-63 % 12.77 Co-58 % 19.88 _ %
Cs-1 37 % 3.56 Cr-51 % 9.82 l__%
Sb-125 % 2.39 Ni-95 % 5.46 %
Cr-51 % 1.17 Zr-95 % 4.31 %
Ce-144 % 0.45 Ag-1 Om % 2.79 __%
Mn-54 % 0.82 Cs-1 37 % 0.55 %
Ag-110m % 0.76 Sb-125 % 0.53 %
l Total - 96.84 Total 98.25 J Total 0 I
- 3. Solid Waste Disposition _
Number of Shipments : Mode of Transportation Destination' 2 Sole Use Truck RACE, TN 1 Sole Use Truck Duratek, TN 1 Sole Use Truck Bamwell, SC B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments -; Mode ofTransportation Destination None _ _ _ __
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R. E. Ginna Nuclear Power Plant Table 4A Radiation Dose to Maximum Individual Receptor First Quarter 2005 (Units In rem)
_ Noble Gas Noble Gas Thyroid Thyroid Thyoid Thyroid Air Gamma Air Beta N 1.89E-08 3.58E-08 NNE, 1.60E-08 3.04E-08 NE 1.84E-08 3.50E-08 ENE 2.39E-08 4.53E-08 E 4.27E-08 8.1 E-08 6.01 E-07 7.11 E-07 1.08E-06 1.19E-06 ESE 5.43E-08 1.03E-07 8.70E-07 1.03E-06 1.57E-06_ 1.73E-06 SE 3.28E-08 6.23E-08 4.86E-07 5.76E-07 8.78E-07 9.76E-07 SSE 1.35E-08 2.56E-08 1.64E-07 1.94E-07 2.97E-07 3.27E-07 S 2.36E-08 4.49E-08 2.61 E-07 2.99E-07 4.55E-07 5.02E-07 SSW 2.26E-08 4.39E-08 3.02E-07 3.57E-07 5.45E-07 6.01 E-07 SW 2.33E-08 4.44E-08 3.38E-07 4.01 E-07 6.11 E-07 6.73E-07 WSW 2.52E-08 4.79E-08 2.59E-07 3.07E-07 4.68E-07 5.16E-07 W 1.59E-08 3.04E-08 1.21 E-07 1.43E-07 2.18E-07 2.40E-07 WNW 1.35E-09 2.57E-09 NW 4.45E-09 8.44E-09 NNW 1.39E-08 2.63E-08 MAX. 5.43E-08 1.03E-07 8.70E-07 1.03E-06 1.57E-06 1.73E-06 Page 18 __
R. E. Ginna Nuclear Power Plant Table 4A Radiation Dose to Maximum Individual Receptor Second Quarter 2005 (Units In rem)
_____ .I I I I_ I Noble Gas Noble Gas Thyroid Thyroid Thyroid Thyroid Air Gamma Air Beta NI .54E-09 9.95E-10 NNE 1.31 E-09 8.44E-10 NE 1.51 E-09 9.72E-10 ENE 1.95E-09 1.25E-09 E 3.48E-09 2.25E-09 2.59E-07 2.84E-07 3.90E-07 1.70E-07 ESE 4.43E-09 2.86E-09 3.76E-07 4.11 E-07 5.65E-07 2.47E-07 SE 2.66E-09 1.73E-09 2.1 OE-07 2.30E-07 3.16E-07 1.38E-07 SSE 1.1OE-09 7.12E-10 7.07E-08 7.73E-08 1.06E-07 4.64E-08 S 1.93E-09 1.25E-09 1.09E-07 1.19E-07 1.64E-07 7.16E-08 SSW 1.86E-09 1.20E-09 1.30E-07 1.43E-07 1.96E-07 8.57E-08 SW 1.90E-09 1.23E-09 1.46E-07 1.60E-07 2.20E-07 9.61 E-08 WSW 2.06E-09 1.33E-09 1.12E-07 1.22E-07 1.68E-07 7.36E-08 W 1.31 E-09 8.47E-10 4.58E-08 5.30E-08 7.29E-08 3.19E-08 WNW 1.11E-t0 7.15E-10 NW 3.63E-10 2.35E-10 NNW 1.13E-09 7.32E-10 MAX. 4.43E-09 2.86E-09 3.76E-07 4.11 E-07 5.65E-07 2.47E-07
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R. E. Ginna Nuclear Power Plant Table 4A Radiation Dose to Maximum Individual Receptor Third Quarter 2005 (Units In rem)
Al 77Al dlt TenC 7 nfn Noble Gas Noble Gas Thyroid Thyroid Thyroid Thyroid Air Gamma Air Beta ___ _
N 1.33E-09 5.74E-10 NNE 1.12E-09 4.87E-10 NE 1.30E-09 5.61E-10 ENE 1.68E-09 7.26E-10 E 2.99E-09 1.30E-09 4.13E-07 4.52E-07 6.20E-07 2.71 E-07 ESE 3.81 E-09 1.65E-09 5.98E-07 6.55E-07 8.99E-07 3.93E-07 SE 2.31 E-09 9.98E-10 3.34E-07 3.66E-07 5.03E-07 2.20E-07 SSE 9.49E-10 4.19E-10 1.06E-07 1.17E-07 1.60E-07 7.20E-08 S 1.66E-09 7.29E-10 1.73E-07 1.90E-07 2.61 E-07 1.14E-07 SSW 1.60E-09 6.93E-10 2.08E-07 2.27E-07 3.12E-07 1.36E-07 SW 1.64E-09 7.IOE-10 2.33E-07 2.55E-07 3.50E-07 1.53E-07 WSW 1.77E-09 7.67E-10 1.78E-07 1.95E-07 2.68E-07 1.17E-07 W 1.13E-09 4.91 E-10 7.71 E-08 8.45E-08 1.16E-07 5.07E-08 WNW 9.53E-11 4.13E-11 NW 3.12E-10 1.35E-10 NNW 9.73E-10 4.22E-10 MAX. 3.81 E-09 1.65E-09 5.98E-07 6.55E-07 8.99E-07 3.93E-07
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R. E. Ginna Nuclear Power Plant Table 4A Radiation Dose to Maximum Individual Receptor Fourth Quarter 2005 (Units In rem)
Noble Gas Noble Gas Thyroid Thyroid Thyroid Thyroid Air Gamma Air Beta N 1.26E-09 5.85E-10 NNE 1.07E-09 4.96E-10 NE 1.23E-09 5.71 E-10 ENE 1.60E-09 7.39E-10 .
E 2.85E-09 1.32E-09 4.12E-07 4.52E-07 6.90E-07 2.70E-07 ESE 3.63E-09 1.68E-09 5.97E-07 6.55E-07 8.97E-07 3.92E-07 SE 2.20E-09 1.02E-09 3.34E-07 3.66E-07 5.01 E-07 2.19E-07 SSE 9.04E-10 4.18E-10 1.06E-07 1.17E-07 1.60E-07 6.98E-08 S 1.58E-09 7.32E-10 1.73E-07 1.90E-07 2.60E-07 1.14E-07 SSW 1.52E-09 7.06E-10 2.07E-07 2.27E-07 3.11 E-07 1.36E-07 SW 1.56E-09 7.22E-10 2.32E-07 2.55E-07 3.49E-07 1.52E-07 WSW 1.69E-09 7.81 E-10 1.78E-07 1.95E-07 2.67E-07 1.17E-07 W 1.07E-09 4.97E-10 7.70E-08 8.45E-08 1.16E-07 5.06E-08 WNW 1.05E-10 4.70E-11 NW 2.98E-10 1.38E-10 NNW 9.29E-10 4.30E-10 MAX. 3.63E-09 1.68E-09 5.97E-07 6.55E-07 8.97E-07 3.92E-07
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R. E. Ginna Nuclear Power Plant Table 4B Radiation Dose To Maximum Individual Receptor From Liquid Release 2005 (Units in rem) lAdult lTeen Child lnfant First Quarter l T. Body 1.13E-06 7.95E-07 1.50E-06 1.45E-06 Bone 1.16E-09 1.20E-09 1.97E-09 6.15E-1O0 Thyroid 1.12E-06 7.90E-07 1.49E-06 1.44E-06 Second Quarter I T. Body 1.83E-07 1.29E-07 2.43E-07 2.36E-07 Bone 1.52E-10 1.60E-10 2.21E-10 <1.OOE-10 Thyroid 1.83E-07 1.29E-07 2.43E-07 2.36E-07 Third Quarter _ _ __ __ _
T. Body 3.55E-07 2.51 E-07 4.73E-07 4.59E-07 Bone 1.41E-10 1.45E-10 2.50E-10 <1.OE-10 Thyroid 3.54E-07 2.50E-07 4.71 E-07 4.59E-07 Fourth Quarter T. Body 2.07E-07 1.46E-07 2.75E-07 2.67E-07 Bone <1.OOE-10 <1.OOE-10 <1.OOE-10 <1.OOE-1 0 Thyroid 2.05E-07 1.45E-07 2.73E-07, 2.67E-0O 22