ML12068A207
| ML12068A207 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/01/2012 |
| From: | Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12068A207 (58) | |
Text
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 1.0 PROGRAM DESCRIPTION 2.0 SUPPLEMENTAL INFORMATION 2.1 Abnormal Releases or Abnormal Discharges 2.2 Non-Routine Planned Discharges 2.3 Radioactive Waste Treatment System Changes 2.4 Annual Land Use Census Changes 2.5 Effluent Monitoring System Inoperability 2.6 Offsite Dose Calculation Manual Changes 2.7 Process Control Program Changes 2.8 Corrections to Previous Reports 2.9 Other 2.10 Groundwater Protection Program 3.0 TABLES 3.1 Gaseous Effluents 3.2 Liquid Effluents 3.3 Solid Waste Storage and Shipments 3.4 Dose Assessments
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1,2011 THROUGH DECEMBER 31, 2011 1.0 PROGRAM DESCRIPTION Regulatory Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin.
The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b. During, any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
Iodine-131, Iodine-133, Tritium, Carbon-14 and Radioactive Material in Particulate Form The dose rate due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500.mrem/yr to any organ.
The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, carbon-14 and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 gCi/ml total activity.
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
Total Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
Effluent Concentration Limits Gaseous Effluents For gaseous effluents, effluent concentration limits (ECL) values are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.
Liquid Effluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. A value of 2.0E-04 gtCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.
Measurements and Approximations of Total Radioactivity Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 4.11-1 and 4.11-2, respectively, of the St. Lucie ODCM. Estimates of errors are in accordance with Methodology Section 4.4, of the ODCM.
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 The estimate of errors associated with values reported are as follows:
LIQUID GASEOUS Error Topic Avg. % Max. %
Avg. % Max. %
Release Point Mixing 2
5 NA NA Sampling 1
5 2
5 Sample Preparation 1
5 1
5 Sample Analysis 3
10 3
10 Release Volume 2
5 4
15 Total %
9 30 10 35 (above values are examples only)
The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums. Nuclides that are near background relative to the predominant nuclides in a given sample could easily have errors greater than the above listed maximums.
Liquid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. Composite samples were analyzed monthly and quarterly for tritium and gross alpha radioactivity in the onsite laboratory using liquid scintillation and air ion chamber counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90, Fe-55 and C-14 by a contract laboratory. The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter.
The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.
Gaseous Radioactive Effluents Each gaseous batch, the release was sampled and analyzed for radioactivity prior to release. For releases from Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy. For releases from the Containment Buildings, samples were taken of noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode.
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 Gaseous Radioactive Effluents (continued)
For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively. Continuous release pathways were continuously sampled using radioiodine adsorbers and particulate filters. The radioiodine adsorbers and particulate filters were analyzed weekly for gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas and tritium grab samples, radioiodine adsorber and particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode. Monthly composites of particulate filters were analyzed for gross alpha activity, in the onsite laboratory using the air ion chamber counting technique. Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by a contract laboratory.
Meteorological Monitoring Program In accordance with ODCM Administrative Control 3.11.2.6.b., a summary of hourly meteorological data, collected during 2011, is retained onsite.
This data is available for review by the NRC upon request. During 2011, the goal of >90% joint data recovery was met.
Carbon-14 Dose Estimation The estimate of carbon-14 (C-14) released from the St. Lucie Nuclear Plant was derived from the EPRI document, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", Report 1021106, issued December 2010.
The site specific source term values used in the St. Lucie calculations were taken from Section 4-28 of the report, and employed the proxy generation rate values for a Combustion Engineering reactor. The actual 2011 operating data for the units was employed for the calculations to derive the total curies released for each unit.
The total amount of C-14 released in 2011 for Unit I was 8.64 Ci, and the total amount of C-14 released in 2011 for Unit 2 was 6.48 Ci. The highest calculated dose is found to be "Bone Dose" to a "Child" through "Inhalation". The total combined dose, including C-14, through this pathway is 1.08-01 mrem/yr.
Additionally, a "Child" consuming vegetables from the garden located at 2.0 miles in the WSW direction from the plant would have received a total combined "Bone Dose", including C-14, of 1.08E-1 mrem/yr.
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 Carbon-14 Dose Estimation (continued)
Using the, same release values, the dose to a visitor on site (Adult Lifeguard) is found to be 2.61E-03 mrem/yr.
All C-14 dose calculations are based on Regulatory Guide 1.109 values.
This is a small fraction of the 1 mrem annual whole body dose received to the. average US citizen from natural occurring Carbon-14, primarily generated through cosmogenesis in the terrestrial biosphere. (Reference National Council of Radiation Protection Report 45, Natural Background Radiation in the United States.)
2.0 SUPPLEMENTAL INFORMATION 2.1 Abnormal Releases or Abnormal Discharges There were no abnormal releases or discharges from the site during the report period.
2.2 Non-Routine Planned Discharges No non-routine planned discharges were made during the report period.
2.3 Radioactive Waste Treatment System Changes No changes were made to the waste treatment system during the report period.
2.4 Annual Land Use Census Changes There was one change to the Land Use Census during 2011. A new garden was identified at 2.0 miles WSW from the plant. This change was noted in the St. Lucie Corrective Action Program under AR 1688791.
2.5 Effluent Monitoring System Inoperability The liquid radioactive waste discharge monitor was declared out of service for greater than 30 days. Although the radiation monitor was functional, the automatic flow isolation valve associated with the radiation monitor was out of service due to a failed valve actuator. A new valve actuator assembly was purchased, installed and the liquid radioactive waste discharge monitor was restored to service.
2.6 Offsite Dose Calculation Manual Changes Two changes were made to the St. Lucie ODCM during the report period.
The first change was to add C-14 dose factors to comply with Revision 2 of Regulatory Guide 1.21. The second change was administrative in nature and revised several procedure reference numbers that had recently changed.
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 2.7 Process Control Program Changes There were no changes to the Process Control Program during the report period.
2.8 Corrections to Previous Reports None 2.9 Other Four batch releases were made from the South Settling Basin to the Intake Canal during the year to lower the water level due to approaching severe weather. All four releases were analyzed according to the ODCM and site procedural requirements and were found to have no alpha, gamma, tritium or hard to detect isotopes. The releases are listed below:
Release start date Volume of release August 24 7.98E6 gallons September 9 7.20E6 gallons October 31 3.29E7 gallons December 11 6.18E6 gallons
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 2.10 Groundwater Protection Program H3 Feb H3 Mar H3 Apr H3 May H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec Well ID H3 Jan 2011 H3 June2011 2011 2011 2011 2011 2011 2011 2011 2011 2011 2011 e 1,Ui
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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31,2011 2.10 Groundwater Protection Program (continued)
H3 Feb H3 Mar H3 Apr H3 May H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2011 2011 2011 2011 2011 2011 2011 2011 2011 2011
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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 3.0 TABLES 3.1 Gaseous Effluents 3.2 Liquid Effluents 3.3 Solid Waste Storage and Shipments 3.4 Dose Assessments Dose to a Member of the Public from Activities Inside the Site Boundary Assessment of radiation dose from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY assumes the VISITOR to be a lifeguard at the Walton Rocks Beach recreation area. The visitor is assumed to be onsite for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per day for 312 days per year at a distance of 1.6 kilometers in the South East Sector.
The VISITOR received exposure from each of the two reactors on the site.
Actual Met Data was used to calculate Visitor Dose for Calendar Year 2011.
VISITOR DOSE RESULTS FOR CALENDAR YEAR 2011 were:
Noble Gas Dose mrad Gamma Air Dose 3.56E-03 Beta Air Dose 3.56E-03 Gas, Particulate, Iodine, Carbon Dose mrem Bone 2.58E-03 Liver 3.80E-03 Thyroid 4.85E-03 Kidney 8.64E-04 Lung 3.75E-03 GI-LLI 3.74E-03 Total Body 4.48E-03
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 L-2012-080 ENCLOSURE 1 COMBINED ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 (47 PAGES)
Open EMS Efuerat Muagment Soffimare Page 1 of 2 Friday, February 10, 2012 10:32:06PM Florida Power & Light St. Lucie Power Plant Table 5A and 5B - Regulatory Guide 1.21 (2011)
Batch Release Summary Unit: Site A. Liquid Releases Units
- 1. Number of batch releases
- 2. Total time period for Batch releases (Minutes):
- 3. Maximum time period for a batch release (Minutes):
- 4. Average time period for a batch release (Minutes):
- 5. Minimum time period for a batch release (Minutes):
- 6. Average stream flow during periods of release of liquid Effluent into a flowing stream (LPM) 1st Quarter 18 9.85E+03 7.05E+02 5.47E+02 3.87E+02 2.07E+06 2nd Quarter 12 9.11E+03 1.15E+03 7.59E+02 4.92E+02 3.15E+06 3rd Quarter 20 4.20E+04 1.98E+04 2.10E+03 1.OOE+02 3.88E+06 4th Quarter Year Totals 27 77 4.13E+04 1.02E+05 2.05E+04 2.05E+04 1.53E+03 1.33E+03 5.OOE+02 1.00E+02 2.09E+06 3.65E+06 User: Al Locke Database: [Server]: PSLSA37
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Friday, February 10, 2012 10:32:06PM Page 2 of 2 B. Gaseous Releases Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Totals
- 1. Number of batch releases 18 28 38 31 115
- 2. Total time period for batch releases (Minutes):
9.05E+03 1.06E+04 8.36E+03 5.90E+03 3.39E+04
- 3. Maximum time period for a batch release ( Minutes):
1.24E+03 1.44E+03 6.00E+02 6.OOE+02 1.44E+03
- 4. Average time period for a batch release (Minutes):
5.03E+02 3.78E+02 2.20E+02 1.90E+02 2.95E+02
- 5. Minimum time period for a batch release (Minutes):
2.10E+01 4.80E+01 3.00E+01 3.OOE+01 2.10E+01 END OF BATCH RELEASE
SUMMARY
REPORT User: Al Locke Database: [Server]: PSLSA37
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Op EMS EfuatMuLigemenIt S~oftware Page 1 of 1 Friday, February 10, 2012 10:31:10PM Florida Power & Light St. Lucie Power Plant Table IA - Regulatory Guide ( 2011)
Gaseous Effluents - Summation Of All Releases Unit: Site Type of Effluent A. Fission And Activation Gases
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit B. Radiolodines
- 1. Total Iodine-131
- 2. Average Release rate for period
- 3. Percent of Applicable Limit C. Particulates
- 1. Particulates ( Half-Lives > 8 Days)
- 2. Average Release rate for period
- 3. Percent of Applicable Limit D. Tritium
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit E. Gross Alpha
- 1. Total Release
- 2. Average Release rate for period Units Curies uCi/sec Curies uCi/sec 1st Quarter 1.88E+01 2.39E+00 2.17E-05 2.75E-06 2nd Quarter 2.01E+01 2.54E+00 9.78E-07 1.24E-07 3rd Quarter 1.88E+00 2.39E-01 1.14E-05 1.45E-06 4th Quarter o/o Est. Total Error 7.32E+00 9.29E-01 1.35E-06 1.71E-07 Curies uCi/sec Curies uCi/sec Curies uCi/sec 8.23E-01 1.04E-01
- 4.42E+01 5.61E+00 2.50E-07 3.18E-08 2.21E-05 2.80E-06 5.41E-01 6.86E-02 1.32E-07 1.68E-08 1.55E-05 1.97E-06 1.61E-01 2.05E-02 2.42E-07 3.07E-08 8.20E-06 1.041E-06 5.28E-01 6.70E-02 1.77E-07 2.25E-08
- Applicable limits are expressed in terms of dose.
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1Open EMS Efuent Mmuugerment S~oftware Page 1 of 4 Friday, February 10, 2012 10:31:39PM Florida Power & Light St. Lucie Power Plant Table 1C*
Annual Radioactive Effluent Release Report (2011)
Gaseous Effluents - Ground Level Releases Reactor Unit: Site Continuous Mode Nuclides Released Fission Gases Kr-85m Kr-87 Kr-88 Xe-131m Xe-133m Xe-135 Xe-138 Total For Period Unit Curies Curies Curies Curies Curies Curies Curies Curies 1st Quarter O.OOE+00 1.24E-01 O.OOE+00 1.45E+01 2.80E+00 2.82E-02 4.86E-01 1.79E+01 2nd Quarter 3rd Quarter 4th Quarter 5.12E-02 O.OOE+00 7.08E-01 1.53E+01 1.98E+00 1.66E-01 1.58E+00 1.98E+01 2.10E-01 0.OOE+00 7.23E-01 0.00E+00 3.95E-01 0.OOE+00 0.OOE+00 1.33E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.83E+00 0.OOE+00 2.68E+00 4.51E+00 Iodines 1-131 1-133 Curies Curies Curies 2.17E-05 9.78E-07 0.OOE+00 0.OOE+00 2.17E-05 9.78E-07 1.14E-05 1.35E-06 2.07E-04 8.58E-06 2.19E-04 9.93E-06 Total For Period Particulates C-14 Cr-51 Co-60 Cs-137 Ce-141 Curies Curies Curies Curies Curies 8.23E-01 0.OOE+00 0.OOE+00 3.29E-06 2.70E-05 1.38E-05 9.87E-07 2.64E-06 5.66E-07 0.OOE+00 0.OOE+00 2.31E-06 8.23E-01 2.21E-05 0.OOE+00 0.OOE+00 1.26E-05 2.89E-06 0.OOE+00 0.OOE+00 1.55E-05 0.OOE+00 0.OOE+00 3.13E-06 5.07E-06 0.OOE+00 0.OOE+00 8.20E-06 Ce-144 Total For Period Curies Curies Tritium H-3 Curies 4.41E+01 O.OOE+00 O.OOE+00 O.OOE+00 User: Al Locke Database: [Server]: PSLSA37
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Friday, February 10, 2012 10:31:39PM Page 2 of 4 Gross Alpha G-Alpha Curies Curies 2.50E-07 2.50E-07 1.32E-07 1.32E-07 2.42E-07 2.42E-07 1.77E-07 1.77E-07 Total For Period User: Al Locke Database: [Server]: PSLSA37
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Friday, February 10, 2012 10:31:39PM Page 3 of 4 Table 1C*
Annual Radioactive Effluent Release Report (2011)
Gaseous Effluents - Ground Level Releases Reactor Unit: Site Batch Mode Nuclides Released Fission Gases Unit 1st Quarter 2nd Quarter Ar-41 Curies Kr-85m Curies Kr-85 Curies Kr-87 Curies Kr-88 Curies Kr-89 Curies Xe-131m Curies Xe-133m CuFies Xe-133 Curies Xe-135m Curies Xe-135 Curies Xe-137 Curies Xe-138 Curies Total For Period Curies lodines 5.54E-01 2.54E-01 2.86E-04 2.61E-05 9.02E-03 1.97E-02 0.OOE+00 3.56E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.07E-03 0.OOE+00 4.86E-03 0.OOE+00 3.17E-01 8.11E-03 0.OOE+00 1.49E-03 2.99E-02 5.47E-05 0.OOE+00 8.32E-03 0.OOE+00 1.09E-04 9.16E-01 2.91E-01 3rd Quarter 4.45E-01 1.09E-03 0.OOE+00 1.36E-04 1.04E-03 0.OOE+00 0.OOE+00 1.15E-03 8.40E-02 3.95E-04 1.84E-02 4.82E-03 0.OOE+00 5.56E-01 4th Quarter 2.60E+00 1.25E-05 0.OOE+00 0.OOE+00 9.71E-05 1.24E-02 0.OOE+00 1.75E-03 1.88E-01 2.08E-04 1.99E-03 2.20E-03 0.OOE+00 2.81E+00 No Nuclides Found Particulates No Nuclides Found Tritium N/A N/A N/A N/A N/A N/A N/A N/A Batch Mode Nuclides Released Unit 1st Quarter H-3 Curies 1.59E-01 2nd Quarter 5.41E-01 3rd Quarter 1.61E-01 4th Quarter 5.28E-01 Gross Alpha No Nuclides Found N/A N/A N/A N/A User: Al Locke Database: [Server]: PSLSA37
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Friday, February 10, 2012 10:31:39PM Page 4 of 4
- Zeroes in this table indicate that no radioactivity was present at detectable levels.
END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP
OpenEMS Eflent Mm~ugernett Software Friday, February Page 1 of 1 10, 2012 10:47:52PM Florida Power & Light St. Lucie Power Plant Table IA - Regulatory Guide ( 2011 )
Gaseous Effluents - Summation Of All Releases Unit: PSL1 Type of Effluent A. Fission And Activation Gases
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit B. Radioiodines
- 1. Total Iodine-131
- 2. Average Release rate for period
- 3. Percent of Applicable Limit C. Particulates
- 1. Particulates ( Half-Lives > 8 Days)
- 2. Average Release rate for period
- 3. Percent of Applicable Limit D. Tritium
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit E. Gross Alpha
- 1. Total Release
- 2. Average Release rate for period Units Curies uCi/sec 1st Quarter 1.06E+01 1.35E+00 2nd Quarter 1.12E+01 1.43E+00 3rd Quarter 5.92E-01 7.51E-02 4th Quarter
%/o Est. Total Error 7.14E+00 9.05E-01 Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies uCi/sec 1.01E-05 1.28E-06 2.78E-05 3.53E-06 2.68E+01 3.40E+00 1.44E-07 1.83E-08 8.51E-07 1.08E-07 1.64E-05 2.07E-06 2.36E-01 2.99E-02 5.57E-08 7.07E-09
- 1. 14E-05 1.45E-06 1.17E-05 1.49E-06 1.09E-01 1.38E-02 1.45E-07 1.84E-08 1.35E-06 1.71E-07 4.80E-06 6.088E-07 4.75E-01 6.03E-02 1.23E-07 1.56E-08
- Applicable limits are expressed in terms of dose.
User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
p0 EMIS P
EzTt Ivbit igLienweln 'ofrware Page 1 of 2 Friday, February 10, 2012 10:49:00PM Florida Power & Light St. Lucie Power Plant Table IC*
Annual Radioactive Effluent Release Report (2011)
Gaseous Effluents - Ground Level Releases Reactor Unit: PSLI Continuous Mode Nuclides Released Unit 1st Quarter 2nd Quarter Fission Gases Kr-87 Curies 1.24E-01 O.OOE+00 Kr-88 Curies O.OOE+00 7.08E-01 Xe-131m Curies 7.19E+00 7.18E+00 Xe-133m Curies 2.60E+00 1.60E+00 Xe-138 Curies 4.86E-01 1.58E+00 Total For Period Curies 1.04E+01 1.11E+01 Iodines 3rd Quarter O.OOE+00 O.OOE+00 O.OOE+00 3.95E-01 O.OOE+00 3.95E-01 4th Quarter O.OOE+00 O.OOE+00 O.OOE+00 1.83E+00 2.68E+00 4.51E+00 1-131 Curies 1.01E-05 8.51E-07 1-133 Curies O.OOE+00 O.OOE+00 Total For Period Curies 1.01E-05 8.51E-07
- 1. 14E-05 2.07E-04 2.19E-04 1.35E-06 8.58E-06 9.93E-06 Particulates Cr-51 Co-60 Cs-137 Ce-144 Curies Curies Curies Curies Curies Total For Period O.OOE+00 2.70E-05 8.29E-07 O.OOE+00 2.78E-05 2.67E+01 1.44E-07 1.44E-07 3.29E-06 8.79E-06 2.54E-06 1.73E-06 1.64E-05 O.OOE+00 1.15E-05 2.64E-07 O.OOE+00 1.17E-05 0.OOE+00 2.82E-06 1.98E-06 0.OOE+00 4.80E-06 Tritium H-3 Curies 0.OOE+00 -----
0.OOE-i00-O.OOE+00 Gross Alpha G-Alpha Total For Period Curies Curies 5.57E-08 5.57E-08 1.45E-07 1.45E-07 1.23E-07 1.23E-07 User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 10:49:00PM Page 2 of 2 Table 1C*
Annual Radioactive Effluent Release Report (2011)
Gaseous Effluents - Ground Level Releases Reactor Unit: PSL1 Batch Mode Nuclides Released Fission Gases Unit 1st Quarter Ar-41 Curies Kr-85m Curies Xe-133m Curies Xe-133 Curies Xe-135m Curies Xe-135 Curies Xe-137 Curies Total For Period Curies 2.15E-01 0.OOE+00 0.OOE+00 6.72E-03 0.OOE+00 1.67E-04 0.OOE+00 2.22E-01 2nd Quarter 1.64E-01 0.OOE+00 0.OOE+00 5.10E-03 1.49E-03 0.OOE+00 8.32E-03 1.79E-01 3rd Quarter 1.69E-01 0.OOE+00 1.60E-04 2.25E-02 3.95E-04 2.45E-04 4.82E-03 1.97E-01 4th Quarter 2.46E+00 1.25E-05 1.39E-03 1.63E-01 0.OOE+00 1.57E-03 2.20E-03 2.63E+00 Podines No Nuclides Found - - - - - - - - - - - - -
Particulates No Nuclides Found N/A N/A N/A N/A N/A N/A N/A N/A Tritium Batch Mode Nuclides Released Unit Curies 1st Quarter 1.59E-01 2nd Quarter 3rd Quarter 2.36E-01 1.09E-01 4th Quarter 4.75E-01 H-3 Gross Alpha No Nuclides Found N/A N/A N/A N/A
- Zeroes in this table indicate that no radioactivity was present at detectable levels.
END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Ar-th 1 A rJjpeinEMS~y.~
Efflue~nt Mvamiugetrwrt Softm are Page 1 of 1 Friday, February 10, 2012 10:50:15PM Florida Power & Light St. Lucie Power Plant Table IA - Regulatory Guide ( 2011 )
Gaseous Effluents - Summation Of All Releases Unit: PSL-2 Type of Effluent A. Fission And Activation Gases
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit B. Radioiodines
- 1. Total Iodine-131
- 2. Average Release rate for period
- 3. Percent of Applicable Limit C. Particulates
- 1. Particulates ( Half-Lives > 8 Days)
- 2. Average Release rate for period
- 3. Percent of Applicable Limit D. Tritium
- 1. Total Release
- 2. Average Release rate for period
- 3. Percent of Applicable Limit E. Gross Alpha
- 1. Total Release
- 2. Average Release rate for period Units 1st Quarter Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies uCi/sec Curies uCi/sec 8.21E+00 1.04E+00 1.16E-05 1.47E-06 8.23E-01 1.04E-01 2nd Quarter 8.80E+00
- 1. 12E+00 3rd Quarter 1.29E+00 1.64E-01 4th Quarter
%/a Est. Total Error 1.84E-01 2.33E-02 1.27E-07 1.62E-08 5.72E-06 7.26E-07 3.05E-01 3.87E-02 7.65E-08 9.70E-09 0.OOE+00 0.OOE+00 3.80E-06 4.82E-07 5.24E-02 6.64E-03 9.71E-08 1.23E-08 0.OOE+00 0.OOE+00 3.40E-06 4.317E-07 5.31E-02 6.74E-03 5.40E-08 6.85E-09
- 1.74E+01
- 2.21E+00 1.06E-07 1.35E-08
- Applicable limits are expressed in terms of dose.
User: AI Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP
OýpeiEMS Efuerat IMluugemcia SoffiAure Page 1 of 3 Friday, February 10, 2012 10:50:36PM Florida Power & Light St. Lucie Power Plant Table IC*
Annual Radioactive Effluent Release Report (2011)
Gaseous Effluents - Ground Level Releases Reactor Unit: P51-2 Continuous Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter Fission Gases Kr-85m Kr-88 Xe-131m Xe-133m Xe-135 Total For Period lodines 1-131 Total For Period Curies O.OOE+00 5.12E-02 Curies O.OOE+00 O.OOE+00 Curies 7.29E+00 8.10E+00 Curies 2.02E-01 3.77E-01 Curies 2.82E-02 1.66E-01 Curies 7.52E+00 8.69E+00 Curies Curies 1.16E-05 1.16E-05 1.27E-07 1.27E-07 2.10E-01 7.23E-01 0.OOE+00 0.OOE+00 0.OOE+00 9.32E-01 0.OOE+00 O.OOE-I-O 0.OOE+00 1.17E-06 2.63E-06 0.OOE+00 0.OOE+00 3.80E-06 4th Quarter O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+O0 0.OOE+00 O.OOE+O0 0.OOE+00
- 3. 1OE-07 3.09E-06 O.OOE+00 O.OOE+00 3.40E-06 Particulates C-14 Co-60 Cs-137 Ce-141 Ce-144 Curies 8.23E-01 O.OOE+00 Curies O.OOE+00 5.06E-06 Curies 1.58E-07 9.30E-08 Curies 5.66E-07 O.OOE+00 Curies O.OOE+00 5.71E-07 Curies 8.23E-01 5.72E-06 Total For Period Tritium H-3 Curies 1.74E+01 O.OOE+00 O.OOE+00 O.OOE+00 Gross Alpha G-Alpha Total For Period Curies Curies
- 1.06E-07 1.06E-07 7.65E-08 7.65E-08 9.71E-08 9.71E-08 5.40E-08 5.40E-08 User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 10:50:36PM Page 2 of 3 Table 1C*
Annual Radioactive Effluent Release Report (2011)
Gaseous Effluents - Ground Level Releases Reactor Unit: PSL2 Batch Mode Nuclides Released Fission Gases Ar-41 Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Total For Period Iodines No Nuclides Found Particulates No Nuclides Found Tritium Nuclides Released H-3 Gross Alpha No Nuclides Found Unit Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 1st Quarter 3.39E-01 2.86E-04 9.02E-03 0.OOE+00 0.OOE+00 0.OOE+00 1.07E-03 4.86E-03 3.10E-01 0.00E+00 2.98E-02 0.OOE+00 6.94E-01 2nd Quarter 8.99E-02 2.61E-05 1.97E-02 3.56E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.01E-03 O.OOE+00 5.47E-05 1.09E-04 1.13E-01 3rd Quarter 2.76E-01 1.09E-03 0.OOE+00 1.36E-04 1.04E-03 0.OOE+00 0.OOE+00 9.87E-04 6.15E-02 0.OOE+00 1.81E-02 0.OOE+00 3.59E-01 4th Quarter 1.45E-01 0.OOE+00 0.OOE+00 0.OOE+00 9.71E-05 1.24E-02 0.OOE+00 3.54E-04 2.48E-02 2.08E-04 4.22E-04 0.00E+00 1.84E-01 N/A N/A N/A N/A N/A N/A N/A N/A Batch Mode Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Curies 0.OOE+00 3.05E-01 5.24E-02 5.31E-02 N/A N/A N/A N/A User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEIVISP
Friday, February 10, 2012 10:50:36PM Page 3 of 3
- Zeroes in this table indicate that no radioactivity was present at detectable levels.
END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP
Page Iofi1 ip iEMVS odaPower ih Friday, February 10, 2012 10:51:44PM lieMx.e=nt Software Florida Power & Light St. Lucie Power Plant Friday, February 10, 2012 10:51:44PM Page 1 of 1 Table 2A - Regulatory Guide 1.21 (2011)
Liquid Effluents - Summation Of All Releases Unit: Site Type of Effluent Ui A. Fission And Activation Products
- 1. Total Release (not including tritium, gases, alpha)
Ci
- 2. Average diluted concentration during period u
- 3. Percent of Applicable Limit B. Tritium
- 1. Total Release C
- 2. Average diluted Concentration during period u(
- 3. Percent of Applicable Limit OX nits 1st Quarter uries Ci/ml uries Ci/ml 1.43E-02 7.02E-10 2nd Quarter 2.82E-02 9.83E-10 3rd Quarter 4.13E-02 2.53E-10
- k 4th Quarter
%/o Est. Total Error 9.02E-02 1.04E-09 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: Waste Vol Release (Pre-Dilution)
F. Volume of Dilution Water Used Curies uCi/ml 6.06E+01 2.97E-06 9.04E-03 4.44E-10 0.OOE+00 1.43E+06 2.04E+10 4.22E+01 1.47E-06 7.86E-05 2.75E-12 0.OOE+00 1.09E+02 6.67E-07 7.68E-03 4.71E-11 0.OOE+00 6.57E+01 7.61E-07 3.32E-02 3.85E-10 0.OOE+00 Liters Liters 1.04E+06 2.86E+10 5.88E+07 1.63E+11 1.50E+08 8.64E+10
- Applicable limits are expressed in terms of dose.
User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
.Page 1 of 4 Friday, February 10, 2012 10:52:01PM O p p E1 M~
S Florida Power & Light St. Lucie Power Plant Table 2B - Regulatory Guide 1.21 (2011)
Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: Site Continuous Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission & Activation Products No Nuclides Found N/A N/A N/A N/A Tritium No Nuclides Found N/A N/A N/A N/A Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 10:52:01PM Page 2 of 4 Table 2B - Regulatory Guide 1.21 (2011)
Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: Site Batch Mode 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Unit User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 10:52:01PM Page 3 of 4 Fission & Activation Products Sb-125 Cs-137 1-130 C-14 Ba-140 Cs-136 Ag-110m Fe-59 Mn-54 Zr-97 Br-82 1-135 Co-58 La-140 Ru-103 Zn-65 Nb-97 Co-57 Co-60 Sb-124 Cs-138 Cr-51 Rb-88 Te-129 Ni-63 Sb-122 Sr-91 Nb-95 Fe-55 1-131 Zr-95 Te-129m Sn-113 Total For Period Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 5.OOE-04 0.OOE+00 0.OOE+00 4.23E-03 0.OOE+00 5.19E-06 5.99E-04 9.50E-05 1.04E-04 1.78E-04 5.05E-06 1.37E-05 4.97E-03 0.OOE+00 0.OOE+00 5.45E-06 8.43E-05 0.OOE+00 7.16E-04 5.73E-06 9.67E-06 4.38E-04 0.OOE+00 5.24E-05 0.OOE+00 0.OOE+00 7.01E-06 6.96E-05 2.13E-03 5.28E-06 8.16E-05 0.OOE+00 5.89E-06 1.43E-02 5.18E-04 4.91E-06 2.84E-06 5.07E-03 9.06E-06 5.10E-06 3.47E-04 2.98E-04 8.76E-05 0.OOE+00 4.38E-06 0.OOE+00 1.48E-03 0.OOE+00 3.78E-06 4.54E-06 1.68E-04 6.24E-06 4.47E-04 7.18E-06 0.OOE+00 5.22E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.76E-05 1.96E-04 1.87E-02 0.OOE+00 1.48E-04 1.04E-04 2.01E-05 2.82E-02 5.71E-04 1.14E-05 0.OOE+00 2.80E-02 0.OOE+00 6.72E-06 5.37E-04 9.01E-05 2.17E-04 1.63E-04 0.OOE+00 0.OOE+00 1.93E-03 9.91E-05 0.OOE+00 0.OOE+00 6.46E-04 8.13E-06 1.66E-03 0.OOE+00 8.68E-06 1.48E-04 0.OOE+00 0.OOE+00 4.67E-04 0.OOE+00 0.OOE+00 2.77E-04 6.24E-03 0.OOE+00 1.37E-04 9.70E-05 0.OOE+00 4.13E-02 9.14E-04 1.47E-05 0.OOE+00 7.02E-02 1.90E-05 0.OOE+00 9.50E-04
- 8. lE-05 2.52E-04 3.25E-04 0.OOE+00 0.OOE+00 3.71E-03 3.38E-05 0.OOE+00 2.37E-05 1.64E-03 2.64E-06 2.48E-03 0.OOE+00 2.71E-05 3.12E-04 2.84E-04 0.OOE+00 8.90E-04 5.76E-06 0.OOE+00 2.30E-04 7.49E-03 0.00E+00 5.49E-05 2.69E-04 9.67E-06 9.02E-02 Tritium H-3 Curies 6.06E+01 4.22E+01 1.09E+02 6.57E+01 Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke
Friday, February 10, 2012 10:52:01PM Page 4 of 4 Dissolved And Entrained Gases Xe-133 Curies 8.96E-03 7.86E-05 7.63E-03 2.07E-02 Kr-88 Curies 0.OOE+00 0.OOE+00 0.OOE+00 9.09E-05 Kr-87 Curies 0.OOE+00 0.OOE+00 O.OOE+00 8.13E-06 Xe-133m Curies 7.44E-05 0.00E+00 2.72E-05 1.47E-04 Xe-135 Curies 3.43E-06 0.OOE+00 1.39E-05 1.33E-03 Ar-41 Curies 0.OOE+00 0.OOE+00 4.05E-06 1.09E-02 Kr-85m Curies 0.OOE+00 0.OOE+00 0.OOE+00 6.05E-05 Total For Period Curies 9.04E-03 7.86E-05 7.68E-03 3.32E-02 If Not Detected, Nuclide is Not Reported
- Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 2-7 for typical minimum detectable concentrations.
END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
0 Pent EMS Effluet uugenwtit Softwa~re Page 1 of 1 Friday, February 10, 2012 10:53:21PM Florida Power & Light St. Lucie Power Plant February 10, 2012 10:53:21PM Page 1 of 1
- Friday, Table 2A - Regulatory Guide 1.21 (2011)
Liquid Effluents - Summation Of All Releases Unit: PSL1 Type of Effluent U
A. Fission And Activation Products
- 1. Total Release (not including tritium, gases, alpha)
C
- 2. Average diluted concentration during period u
- 3. Percent of Applicable Limit 0/
B. Tritium
- 1. Total Release C
- 2. Average diluted Concentration during period u
- 3. Percent of Applicable Limit 0/
nits 1st Quarter uries Ci/ml uries Ci/ml 7.15E-03 7.02E-10 3.03E+01 2.97E-06 4.52E-03 4.44E-10 0.OOE+00 2nd Quarter 1.41E-02 9.83E-10 3rd Quarter 2.06E-02 2.53E-10 4th Quarter 0/6 Est. Total Error 4.51E-02 1.04E-09 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: Waste Vol Release (Pre-Dilution)
F. Volume of Dilution Water Used 2.11E+01 1.47E-06 3.93E-05 2.75E-12 0.OOE+00 Curies uCi/ml 5.44E+01 6.67E-07 3.84E-03 4.71E-11 0.OOE+00 2.94E+07 8.16E+10 3.29E+01 7.61E-07 1.66E-02 3.85E-10 0.OOE+00 7.51E+07 4.32E+10 Liters Liters 7.14E+05 1.02E+10 5.19E+05 1.43E+10
- Applicable limits are expressed in terms of dose.
User: Al Locke PSLSA37
[Database]: NEOEMSP Database: [Server]:
o-,penEMS Eflent M~uugemei t Sofmu~re Page 1 of 4 Friday, February 10, 2012 10:53:44PM Florida Power & Light St. Lucie Power Plant Table 2B - Regulatory Guide 1.21 (2011)
Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSLI Continuous Mode Nuclides Released Fission & Activation Products Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter No Nuclides Found N/A N/A N/A N/A Tritium No Nuclides Found N/A N/A N/A Dissolved And Entrained Gases N/A No Nuclides Found N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server): PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 10:53:44PM Page 2 of 4 Table 2B - Regulatory Guide 1.21 (2011)
Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSL1 Batch Mode 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Unit User: Al Locke Database: [Server]: PSLSA37
[Database]: N EOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 10:53:44PM Page 3 of 4 Fission & Activation Products Cs-138 Ba-140 Te-129m 1-135 Fe-59 Sb-125 Sr-91 Co-60 Nb-95 Zr-95 Co-57 Nb-97 Ag-110m Cs-137 Cs-136 Zr-97 Te-129 Cr-51 La-140 Sb-122 C-14 Zn-65 Fe-55 1-130 Mn-54 Co-58 Sn-113 Rb-88 Sb-124 Ru-103 Br-82 Ni-63 1-131 Total For Period Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 4.83E-06 0.OOE+00 0.OOE+00 6.86E-06 4.75E-05 2.50E-04 3.51E-06 3.58E-04 3.48E-05 4.08E-05 0.00E+00 4.22E-05 2.99E-04 0.00E+00 2.59E-06 8.90E-05 2.62E-05 2.19E-04 0.OOE+00 0.OOE+00 2.11E-03 2.73E-06 1.06E-03 0.OOE+00 5.20E-05 2.48E-03 2.95E-06 0.OOE+00 2.87E-06 0.OOE+00 2.53E-06 0.OOE+00 2.64E-06 7.15E-03 0.OOE+00 4.53E-06 5.22E-05 0.OOE+00 1.49E-04 2.59E-04 8.81E-06 2.24E-04 9.82E-05 7.40E-05 3.12E-06 8.42E-05 1.74E-04 2.46E-06 2.55E-06 0.OOE+00 0.OOE+00 2.61E-04 0.00E+00 0.OOE+00 2.53E-03 2.27E-06 9.35E-03 1.42E-06 4.38E-05 7.40E-04 1.OOE-05 0.OOE+00 3.59E-06 1.89E-06 2.19E-06 0.OOE+00 0.OOE+00 1.41E-02 4.34E-06 0.OOE+00 4.85E-05 0.00E+00 4.50E-05 2.86E-04 0.OOE+00 8.32E-04 1.38E-04 6.85E-05 4.07E-06 3.23E-04 2.68E-04 5.71E-06 3.36E-06 8.17E-05 0.OOE+00 7.42E-05 4.96E-05 0.OOE+00 1.40E-02 0.OOE+00 3.12E-03 0.00E+00 1.09E-04 9.66E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.33E-04 0.OOE+00 2.06E-02 1.36E-05 9.52E-06 1.34E-04 0.OOE+00 4.05E-05 4.57E-04 0.OOE+00 1.24E-03
- 1. 15E-04 2.74E-05 1.32E-06 8.22E-04 4.75E-04 7.37E-06 0.OOE+00 1.62E-04 0.OOE+00 1.56E-04 1.69E-05 2.88E-06 3.51E-02 1.18E-05 3.75E-03 0.OOE+00 1.26E-04 1.85E-03 4.83E-06 1.42E-04 0.OOE+00 0.OOE+00 0.OOE+00 4.45E-04 0.OOE+00 4.51E-02 Tritium H-3 Curies 3.03E+01 2.11E+01 5.44E+01 3.29E+01 Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke
Friday, February 10, 2012 10:53:44PM Page 4 of 4 Dissolved And Entrained Gases Kr-88 Curies 0.OOE+00 0.00E+00 0.OOE+00 4.55E-05 Xe-135 Curies 1.71E-06 0.OOE+00 6.97E-06 6.63E-04 Kr-87 Curies O.OOE+00 0.OOE+00 0.OOE+00 4.06E-06 Xe-133 Curies 4.48E-03 3.93E-05 3.82E-03 1.03E-02 Kr-85m Curies 0.OOE+00 0.OOE+00 0.OOE+00 3.03E-05 Ar-41 Curies 0.OOE+00 0.OOE+00 2.03E-06 5.46E-03 Xe-133m Curies 3.72E-05 0.OOE+00 1.36E-05 7.33E-05 Total For Period Curies 4.52E-03 3.93E-05 3.84E-03 1.66E-02 If Not Detected, Nuclide is Not Reported
- Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 2-7 for typical minimum detectable concentrations.
END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
OpeiaiEMS Efuent Mnaigemient Software Page 1 of 1 Friday, February 10, 2012 11:02:57PM Florida Power & Light St. Lucie Power Plant Friday, February 10, 2012 11:02:57PM Page 1 of 1 Table 2A - Regulatory Guide 1.21 (2011)
Liquid Effluents - Summation Of All Releases Unit: PSL2 Type of Effluent U
A. Fission And Activation Products
- 1. Total Release (not including tritium, gases, alpha)
C
- 2. Average diluted concentration during period u
- 3. Percent of Applicable Limit OX B. Tritium
- 1. Total Release C
- 2. Average diluted Concentration during period u
- 3. Percent of Applicable Limit
°/
nits 1st Quarter uries Ci/ml uries Ci/ml 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: Waste Vol Release (Pre-Dilution)
F. Volume of Dilution Water Used 7.15E-03 7.02E-10 3.03E+01 2.97E-06 4.52E-03 4.44E-10 0.00E+00 7.14E+05 1.02E+10 2nd Quarter 1.41E-02 9.83E-10 3rd Quarter 2.06E-02 2.53E-10 Curies uCi/ml 2.11E+01 1.47E-06 3.93E-05 2.75E-12 0.OOE+00 5.19E+05 1.43E+10 5.44E+01 6.67E-07 3.84E-03 4.71E-11 0.OOE+00 2.94E+07 8.16E+10 4th Quarter
%/o Est. Total Error 4.51E-02 1.04E-09 3.29E+01 7.61E-07 1.66E-02 3.85E-10 0.OOE+00 7.51E+07 4.32E+10 Liters Liters
- Applicable limits are expressed in terms of dose.
User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
QOCTIEMS
.1 Effluent Mmuugement Softwire Friday, February Page 1 of 4 10, 2012 11:03:10PM Florida Power & Light St. Lucie Power Plant Table 2B - Regulatory Guide 1.21 (2011)
Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSL2 Continuous Mode Nuclides Released Fission & Activation Products No Nuclides Found Tritium No Nuclides Found Dissolved And Entrained Gases No Nuclides Found Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 11:03:10PM Page 2 of 4 Table 2B - Regulatory Guide 1.21 (2011)
Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSL2 Batch Mode 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Unit User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: AI Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 11:03:10PM Page 3 of 4 Fission & Activation Products Ba-140 Nb-95 Sr-91 Br-82 Ru-103 Cs-136 Sb-122 Cr-51 Sb-125 Te-129m Fe-55 La-140 Fe-59 Co-60 Ni-63 Cs-137 Zn-65 Te-129 1-135 1-131 Sn-113 Mn-54 Rb-88 Nb-97 Zr-95 1-130 Co-58 Ag-110m Cs-138 Zr-97 C-14 Co-57 Sb-124 Total For Period Tritium H-3 Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 0.OOE+00 3.48E-05 3.51E-06 2.53E-06 0.OOE+00 2.59E-06 0.OOE+00 2.19E-04 2.50E-04 0.00E+00 1.06E-03 0.OOE+00 4.75E-05 3.58E-04 O.OOE+00 0.OOE+00 2.73E-06 2.62E-05 6.86E-06 2.64E-06 2.95E-06 5.20E-05 0.OOE+00 4.22E-05 4.08E-05 0.OOE+00 2.48E-03 2.99E-04 4.83E-06 8.90E-05 2.11E-03 0.OOE+00 2.87E-06 7.15E-03 4.53E-06 9.82E-05 8.81E-06 2.19E-06 1.89E-06 2.55E-06 0.00E+00 2.61E-04 2.59E-04 5.22E-05 9.35E-03 0.00E+00 1.49E-04 2.24E-04 0.O0E+00 2.46E-06 2.27E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.OOE-05 4.38E-05 0.OOE+00 8.42E-05 7.40E-05 1.42E-06 7.40E-04 1.74E-04 0.OOE+00 0.00E+00 2.53E-03 3.12E-06 3.59E-06 1.41E-02 0.00E+00 1.38E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.36E-06 0.OOE+00 7.42E-05 2.86E-04 4.85E-05 3.12E-03 4.96E-05 4.50E-05 8.32E-04 2.33E-04 5.71E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.09E-04 0.OOE+00 3.23E-04 6.85E-05 0.OOE+00 9.66E-04 2.68E-04 4.34E-06 8.17E-05 1.40E-02 4.07E-06 0.OOE+00 2.06E-02 5.44E+01 9.52E-06 1.15E-04 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 2.88E-06 1.56E-04 4.57E-04 1.34E-04 3.75E-03 1.69E-05 4.05E-05 1.24E-03 4.45E-04 7.37E-06 1.18E-05 0.OOE+00 0.OOE+00 0.OOE+00 4.83E-06 1.26E-04 1.42E-04 8.22E-04 2.74E-05 0.OOE+00 1.85E-03 4.75E-04 1.36E-05 1.62E-04 3.51E-02 1.32E-06 0.OOE+00 4.51E-02 Curies 3.03E+01 2.11E+01 3.29E+01 User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
Friday, February 10, 2012 11:03:10PM Page 4 of 4 Dissolved And Entrained Gases Xe-133 Curies 4.48E-03 3.93E-05 3.82E-03 1.03E-02 Kr-85m Curies O.OOE+00 O.OOE+00 O.OOE+00 3.03E-05 Xe-133m Curies 3.72E-05 O.OOE+00 1.36E-05 7.33E-05 Xe-135 Curies 1.71E-06 O.OOE+00 6.97E-06 6.63E-04 Ar-41 Curies O.OOE+00 O.OOE+00 2.03E-06 5.46E-03 Kr-87 Curies O.OOE+00 O.OOE+00 O.OOE+00 4.06E-06 Kr-88 Curies O.OOE+00 O.OOE+00 O.OOE+00 4.55E-05 Total For Period Curies 4.52E-03 3.93E-05 3.84E-03 1.66E-02 If Not Detected, Nuclide is Not Reported
- Zeroes in this table indicate that no radioactivity was present at detectable levels.
See Table 2-7 for typical minimum detectable concentrations.
END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP User: A[ Locke Database: [Server]: PSLSA37
[Database]: NEOEMSP
0 uL1,.,'nEMtS~fw Friday, February 10, 2012 11:14:59PM Florida Power & Light St. Lucie Power Plant Table A-2B, Liquid Effluents - Continuous Mode Unit: Site Starting: 1-Jan-2011 Ending: 31-Dec-2011 Nuclides Released A. Particulates and Iodines No Nuclides Found B. Dissolved and Entrained Gase No Nuclides Found C. Tritium No Nuclides Found D. Gross Alpha Activity No Nuclides Found Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Total Ci Ci Ci Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.
User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP
Opep EMS Efuent Mm.ug-emcnt Software Page 1 of 2 Friday, February 10, 2012 11:06:11PM Florida Power & Light St. Lucie Power Plant Table 6A and 6B - Regulatory Guide 1.21 Annual Liquid Effluents - Abnormal Release Summary No Data Found for Selected Search Criteria User: Al Locke
[Server]: PSLSA37
[Database]: NEOEMSP User: Al Locke
[Server]: PSLSA37
[Database]: NEOEMSP
NRC Regulatory Guide 1.21 Reports Page 1
Report Date :
2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff:
1 Waste Stream : Resins, Filters, and Evap Bottoms Waste Volume Curies
% Error Class FtA3 MA3 Shipped (Ci)
A 3.39E+02 9.60E+00 2.12E+01
+/-25%
B 2.67E+02 7.56E+00 8.65E+01
+/- 25%
C 0.OOE+00 0.OOE+00 0.OOE+00
+/- 25%
All 6.06E+02 1.72E+01 1.08E+02
+/-25%
Waste Stream : DryActive Waste DAW 20' Sealand DAW 40' Sealand DAW 8-120 Liner Waste Volume Curies
%Error Class FtA3 MA3 Shipped (Ci)
A 4.07E+04 1.15E+03 1.61E+01
+/-25%
B 0.OOE+00 0.00E+00 0.OOE+00
+/-25%
C 0.OOE+00 0.OOE+00 0.OOE+00
+/-25%
All 4.07E+04 1.15E+03 1.61E+01
+/-25%
Waste Stream : Irradiated Components Waste Volume Curies
% Error Class FtA3 MA3 Shipped (Ci)
A 0.OOE+00 0.OOE+00 0.OOE+00
+/-25%
B 0.OOE+00 0.OOE+00 0.OOE+00
+/-25%
C 0.OOE+00 0.OOE+00 0.00E+00
+/-25%
All 0.00E+00 0.OOE+00 0.OOE+00
+/-25%
NRC Regulatory Guide 1.21 Reports Page 2
Report Date :
2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff:
1 Waste Stream : Other Waste Combined Packages Oil 07-01 Waste Volume Curies
% Error Class FtA3 MA3 Shipped (Ci)
A 5.49E+03 1.55E+02 2.27E+00
+/-25%
B 0.OOE+00 0.OOE+00 0.00E+00
+/-25%
C 0.OOE+00 0.OOE+00 0.OOE+00
+/-25%
All 5.49E+03 1.55E+02 2.27E+00
+/-25%
Waste Stream : Sum of All 4 Categories Combined Packages DAW 20' Sealand DAW 8-120 Liner DAW 40' Sealand Oil 07-01 Waste Volume Curies
% Error Class FtA3 MA3 Shipped (Ci)
A 4.66E+04 1.32E+03 3.96E+01
+/-25%
B 2.67E+02 7.56E+00 8.65E+01
+/-25%
C 0.OOE+00 0.OOE+00 0.OOE+00
+/-25%
All 4.68E+04 1.33E+03 1.26E+02
+/-25%
-Combined Waste Type Shipment, Major Volume Waste Type Shown
NRC Regulatory Guide 1.21 Reports Page 1
Report Date :
2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Number of Shipments Mode of Transportation Destination 25 Hittman Transport (TN)
EnergySolutions Bear Creek 4
Hittman Transport (SC)
EnergySolutions LLC.
1 Hittman Transport (TN)
EnergySolutions LLC.
2 Hittman Transport (SC)
Studsvik Processing Facility LLC -
Erwin
NRC Regulatory Guide 1.21 Reports Page 1
Report Date :
2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff:
1 Resins, Filters, and Evap Bottom Waste Class A Nuclide Name Percent Abundance Curies H-3 4.109%
8.72E-01 C-14 4.000%
8.49E-01 Cr-51 1.404%
2.98E-01 Mn-54 1.690%
3.59E-01 Fe-55 17.859%
3.79E+00 Co-58 39.157%
8.31 E+00 Co-60 9.829%
2.09E+00 Ni-63 16.492%
3.50E+00 Sb-125 2.563%
5.44E-01 Resins, Filters, and Evap Bottom Waste Class B Nuclide Name Percent Abundance Curies H-3 2.646%
2.29E+00 Mn-54 4.836%
4.18E+00 Fe-55 14.337%
1.24E+01 Co-58 6.813%
5.89E+00 Co-60 11.586%
1.OOE+01 Ni-63 43.009%
3.72E+01 Cs-137 13.299%
1.15E+01 Resins, Filters, and Evap Bottom Waste Class All Nuclide Name Percent Abundance Curies H-3 2.934%
3.16E+00 C-14 1.423%
1.53E+00 Mn-54 4.216%
4.54E+00 Fe-55 15.031%
1.62E+01 Co-58 13.186%
1.42E+01 Co-60 11.240%
1.21E+01 Ni-63 37.785%
4.07E+01 Cs-137 10.748%
1.16E+01 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 1.614%
2.60E-01 Cr-51 2.338%
3.77E-01 Mn-54 1.617%
2.61 E-01 Fe-55 35.046%
5.66E+00 Co-58 19.183%
3.1OE+00 Co-60 10.756%
1.74E+00 Ni-63 12.754%
2.06E+00 Zr-95 2.101%
3.39E-01 Nb-95 3.568%
5.76E-01 Sn-113 1.176%
1.90E-01 Sb-125 1.434%
2.31E-01
NRC Regulatory Guide 1.21 Reports Page 2
Report Date:
2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff:
1 Cs-137 2.845%
4.59E-01 Ce-144 3.789%
6.11E-01 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 1.614%
2.60E-01 Cr-51.
2.338%
3.77E-01 Mn-54 1.617%
2.61E-01 Fe-55 35.046%
5.66E+00 Co-58 19.183%
3.1OE+00 Co-60 10.756%
1.74E+00 Ni-63 12.754%
2.06E+00 Zr-95 2.101%
3.39E-01 Nb-95 3.568%
5.76E-01 Sn-113 1.176%
1.90E-01 Sb-125 1.434%
2.31E-01 Cs-1 37 2.845%
4.59E-01 Ce-144 3.789%
6.11E-01 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 16.734%
3.80E-01 C-14 9.782%
2.22E-01 Fe-55 27.002%
6.13E-01 Co-58 9.417%
2.14E-01 Co-60 6.348%
1.44E-01 Ni-63 23.105%
5.25E-01 Ag-110m 1.055%
2.40E-02 Sb-125 2.639%
5.99E-02 Cs-137 1.480%
3.36E-02 Other Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 16.734%
3.80E-01 C-14 9.782%
2.22E-01 Fe-55 27.002%
6.13E-01 Co-58 9.417%
2.14E-01 Co-60 6.348%
1.44E-01 Ni-63 23.105%
5.25E-01 Ag-110m 1.055%
2.40E-02 Sb-125 2.639%
5.99E-02 Cs-137 1.480%
3.36E-02 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 3.816%
1.51 E+00 C-14 2.703%
1.07E+00
NRC Regulatory Guide 1.21 Reports Page 3
Report Date :
2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff:
1 Cr-51 1.704%
6.75E-01 Mn-54 1.598%
6.33E-01 Fe-55 25.381%
1.01E+01 Co-58 29.320%
1.16E+01 Co-60 10.007%
3.97E+00 Ni-63 15.349%
6.08E+00 Nb-95 1.774%
7.03E-01 Sb-125 2.108%
8.35E-01 Cs-137 1.431%
5.67E-01 Ce-144 1.699%
6.73E-01 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 2.646%
2.29E+00 Mn-54 4.836%
4.18E+00 Fe-55 14.337%
1.24E+01 Co-58 6.813%
5.89E+00 Co-60 11.586%
1.00E+01 Ni-63 43.009%
3.72E+01 Cs-137 13.299%
1.15E+01 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 3.013%
3.80E+00 C-14 1.391%
1.75E+00 Mn-54 3.819%
4.82E+00 Fe-55 17.807%
2.25E+01 Co-58 13.886%
1.75E+01 Co-60 11.090%
1.40E+01 Ni-63 34.318%
4.33E+01 Cs-137 9.570%
1.21 E+01
NRC Regulatory Guide 1.21 Reports Page 1
Report Date :
2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Manifest Number Date Shipped Waste Volume Used Burial volume Used FPL/PSL 11-147 12/8/2011 Yes FPL/PSL 11-146 11/9/2011 Yes FPL/PSL 11-138 10/20/2011 Yes FPL/PSL 11-124 7/27/2011 Yes FPL/PSL 11-123 7/22/2011 Yes FPL/PSL 11-122 7/19/2011 Yes FPL/PSL 11-119 6/30/2011 Yes FPL/PSL 11-116 6/22/2011 Yes FPL/PSL 11-115 6/17/2011 Yes FPL/PSL 11-114 6/16/2011 Yes FPL/PSL11-113 6/9/2011 Yes FPL/PSL 11-111 6/6/2011 Yes FPL/PSL 11-110 6/2/2011 Yes FPL/PSL 11-109 6/1/2011 Yes FPL/PSL 11-106 5/26/2011 Yes FPL/PSL 11-105 5/26/2011 Yes FPL/PSL 11-102 5/12/2011 Yes FPL/PSL 11-101 5/11/2011 Yes FPL/PSL 11-100 5/10/2011 Yes FPL/PSL 11-85 4/7/2011 Yes FPL/PSL 11-68 3/17/2011 Yes FPL/PSL 11-61 3/3/2011 Yes FPL/PSL 11-54 2/23/2011 Yes FPL/PSL 11-55 2/22/2011 Yes FPL/PSL 11-48 2/15/2011 Yes FPL/PSL 11-40 2/14/2011 Yes FPL/PSL 11-26 2/7/2011 Yes FPL/PSL 11-25 1/27/2011 Yes FPL/PSL 11-22 1/24/2011 Yes PSL/FPL-11-13 1/19/2011 Yes FPL/PSL 11-6 1/7/2011 Yes FPL/PSL-11-163 1/5/2011 Yes
Gas Status Summary Report Tuesday, February 14, 2012 04:26 Page 12 of 13 Period:
Ann, 2011 Site/Unit/Discharge Point:
Site Site Boundary NNG Doserate Summary - Note: All Doses in mRem/yr Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin WNW Site Boundary - I Infant 1.573E-05 1.573E-05 1.573E-05 1.573E-05 1.573E-05 1.573E-05 1.573E-05 0.OOOE+00 NW Site Boundary - In Infant 6.510E-03 9.302E-03 9.170E-03 1.164E-02 2.042E-03 9.178E-03 9.159E-03 0.OOOE+00 Maximum Doserate by Organ:
Maximum Organ Doserate (mRem/yr):
6.510E-03
- 1. 164E-02 9.302E-03 9.170E-03 1.164E-02 2.042E-03 9.178E-03 9.159E-03 O.O00E+00 Maximum Total Body Doserate (mRem/yr):
9.170E-03 Site Boundary NG Doserate Summary Gas Receptor Location WNW Site Boundary NW Site Boundary Gamma (mRad/yr) 1.103E-03 1.280E-03 Beta (mRad/yr) 1.103E-03 1.280E-03 Total Body (mRem/yr) 1.034E-03 1.200E-03 Skin (mRem/yr) 1.784E-03 2.071E-03 User: A[ Locke
[Server]: PSLSA37 [Database]: NEOEMSP
Gas Status Summary Report Tuesday, February 14, 2012 04:26 Page 13 of 13 Period:
Ann, 2011 Site/Unit/Discharge Point:
Site Maximum Individual NNG Dose Summary - Note: All Doses in mRem Receptor SE Nearest Res - Adult SE Nearest Res -
SE Nearest Res -
SE Nearest Res -
SE Visitor - Adult SSW Near Garden SSW Near Garden SSW Near Garden WSW Near Milk -
WSW Near Milk -
WSW Near Milk -
WSW Near Milk -
Child Infant Teenager
- Adult
- Child Adult Child Infant Teenager Agegroup Adult Child Infant Teenager Adult Adult Child Teenager Adult Child Infant Teenager Bone 1.170E-04 1.170E-04 1.169E-04 1.169E-04 5.432E705 9.060E-06 9.060E-06 9.054E-06 2.515E-05 3.851E-05 5.770E-05 7.474E-06 Liver 1.170E-04 1.170E-04 1.170E-04 1.170E-04 5.431E-05 9.059E-06 9.059E-06 9.059E-06 2.672E-05 3.801E-05 6.227E-05 1.013E-05 Total Body 1.168E-04 1.168E-04 1.167E-04 1.168E-04 5.425E-05 9.049E-06 9.045E-06 9.046E-06 2.468E-05 2.399E-05 2.443E-05 3.775E-06 Thyroid 1.365E-04 1.474E-04 1.450E-04 1.415E-04 6.285E-05 1.040E-05 1.115E-05 1.074E-05 1.211E-04 3.194E-04 7.350E-04 1.524E-04 Kidney 1.169E-04 1.168E-04 1.167E-04 1.169E-04 5.429E-05 9.054E-06 9.046E-06 9.054E-06 2.331E-05 2.346E-05 2.345E-05 3.175E-06 Lung 1.234E-04 1.246E-04 1.232E-04 1.264E-04 5.713E-05 9.501E-06 9.583E-06 9.708E-06 2.233E-05 2.375E-05 2.640E-05 2.450E-06 GI-Ili
- 1. 171 E-04 1.168E-04 1.167E-04 1.170E-04 5.435E-05 9.065E-06 9.048E-06 9.062E-06 2.117E-05 2.114E-05 2.114E-05 9.531E-07 Skin 0.OOOE+O0 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+0Q 0.OOOE+00 Maximum Dose by Organ:
1.
Maximum Organ Dose (mRem):
7.35C Maximum Total Body Dose (mRem):
1.168 Maximum Individual NG Dose Summary Gas Receptor Location 170E-04 1.170E-04 1.168E-04 7.350E-04 1.169E-04 1.264E-04 1.171E-04 0.OOOE+00
)E-04 3E-04 WSW Near Milk 3.43 mi 248 deg SE Visitor SE Nearest Res 1.52 mi 142 deg SSW Near Gard 4.4 mi 207 deg Gamma (mRad)
Beta (mRad)
Total Body (mRem) 3.352E-04 2.620E-04 3.143E-04 1.078E-03 8.426E-04 1.011E-03 2.489E-03 1.946E-03 2.334E-03 1.888E-04 1.476E-04 1.771E-04 Skin (mRem) 5.422E-04 1.743E-03 4.027E-03 3.055E-04 User: Al Locke
[Server]: PSLSA37 [Database]: NEOEMSP
Gas Status Summary Report Tuesday, February 14, 2012 03:51 Page 6 of 7 Period:
Ann, 2011 Site/Unit/Discharge Point:
PSL1 Site Boundary NNG Doserate Summary - Note: All Doses in mRem/yr Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin WNW Site Boundary - I Infant 2.955E-05 2.955E-05 2.955E-05 2.955E-05 2.955E-05 2.955E-05 2.955E-05 0.OOOE+00 NW Site Boundary - In Infant 2.723E-04 3.970E-03 3.829E-03 7.578E-03 1.749E-03 3.838E-03 3.815E-03 0.OOOE+00 Maximum Doserate by Organ:
Maximum Organ Doserate (mRem/yr):
2.723E-04 7.578E-03 3.970E-03 3.829E-03 7.578E-03 1.749E-03 3.838E-03 3.815E-03 O.OOOE+00 Maximum Total Body Doserate (mRem/yr):
3.829E-03 Site Boundary NG Doserate Summary Gas Receptor Location NW Site Boundary WNW Site Boundary Gamma (mRad/yr) 2.212E-03 1.906E-03 Beta (mRad/yr) 2.212E-03 1.906E-03 Total Body (mRem/yr) 2.086E-03 1.797E-03 Skin (mRem/yr) 3.545E-03 3.054E-03 User: Al Locke
[Server]: PSLSA37 [Database]: NEOEMSP
Gas Status Summary Report Tuesday, February 14, 2012 03:51 Page 7 of 7 Gas Status Summary Report Tuesday, February 14, 2012 03:51 Page 7 of 7 Period:
Ann, 2011 Site/Unit/Discharge Point:
PSL1 Maximum Individual NNG Dose Summary - Note: All Doses in mRem Receptor Agegroup Bone SE Nearest Res - Adult Adult 9.923E-05 SE Nearest Res -
SE Nearest Res -
SE Nearest Res -
SE Visitor - Adult SSW Near Garden SSW Near Garden SSW Near Garden WSW Near Milk -
WSW Near Milk -
WSW Near Milk -
WSW Near Milk -
Child Infant Teenager
- Adult
- Child Adult Child Infant Teenager Child Infant Teenager Adult Adult Child Teenager Adult Child Infant Teenager 9.922E-05 9.918E-05 9.917E-05 4.608E-05 7.686E-06 7.685E-06 7.681E-06 1.985E-05 2.646E-05 3.597E-05 3.705E-06 Liver 9.923E-05 9.922E-05 9.921E-05 9.922E-05 4.608E-05 7.685E-06 7.685E-06 7.685E-06 2.063E-05 2.624E-05 3.828E-05 5.053E-06 Total Body 9.912E-05 9.909E-05 9.907E-05 9.910E-05 4.603E-05 7.678E-06 7.676E-06 7.676E-06 1.960E-05 1.937E-05 1.971E-05 1.942E-06 Thyroid 1.163E-04 1.264E-04 1.243E-04 1.208E-04 5.351E-05 8.853E-06 9.546E-06 9.165E-06 8.716E-05 2.257E-04 5.144E-04 1.058E-04 Kidney 9.921E-05 9.911E-05 9.906E-05 9.921E-05 4.607E-05 7.684E-06 7.677E-06 7.684E-06 1.902E-05 1.910E-05 1.909E-05 1.698E-06 Lung 1.049E-04 1.060E-04 1.047E-04 1.076E-04 4.857E-05 8.076E-06 8.147 E-06 8.257E-06 1.875E-05 1.949E-05 2.071E-05 1.651E-06 GI-Ili 9.936E-05 9.915E-05 9.907E-05 9.932E-05 4.613E-05 7.694E-06 7.680E-06 7.691E-06 1.792E-05 1.790E-05 1.790E-05 7.743E-07 Skin 0.000E+00 0.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.000E+00 O.OOOE+00 0.OOOE+00 0.000E+00 O.000E+00 Maximum Dose by Organ:
9.
Maximum Organ Dose (mRem):
5.14*
Maximum Total Body Dose (mRem):
9.91 Maximum Individual NG Dose Summary Gas Receptor Location
.923E-05 9.923E-05 9.912E-05 5.144E-04 9.921E-05 1.076E-04 9.936E-05 0.OOOE+00 IE-04 2E-05 SSW Near Gard 4.4 mi 207 deg SE Nearest Res 1.52 mi 142 deg WSW Near Milk 3.43 mi 248 deg SE Visitor Gamma (mRad) 1.500E-04 1.978E-03 2.663E-04 8.563E-04 Beta (mRad) 1.055E-04 1.391E-03 1.873E-04 6.023E-04 Total Body (mRem) 1.415E-04 1.865E-03 2.511E-04 8.074E-04 Skin (mRem) 2.405E-04 3.170E-03 4.268E-04 1.372E-03 User: Al Locke
[Server]: PSLSA37
[Database]: NEOEMSP
Gas Status Summary Report Tuesday, February 14, 2012 03:52 Page 7 of 8 Period:
Ann, 2011 Site/Unit/Discharge Point:
PSL2 Site Boundary NNG Doserate Summary - Note: All Doses in mRem/yr Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin WNW Site Boundary - I Infant 3.965E-06 3.965E-06 3.965E-06 3.965E-06 3.965E-06 3.965E-06 3.965E-06 0.OOOE+00 NW Site Boundary - In Infant 1.182E-02 1.384E-02 1.371E-02 1.511E-02 2.291E-03 1.372E-02 1.371E-02 0.OOOE+00 Maximum Doserate by Organ:
Maximum Organ Doserate (mRem/yr):
1.182E-02 1.511E-02 1.384E-02 1.371E-02 1.511E-02 2.291E-03 1.372E-02 1.371E-02 0.000E+00 Maximum Total Body Doserate (mRem/yr):
1.371E-02 Site Boundary NG Doserate Summary Gas Receptor Location NW Site Boundary WNW Site Boundary Gamma (mRad/yr) 4.869E-04 4.194E-04 Beta (mRad/yr) 4.869E-04 4.194E-04 Total Body (mRem/yr) 4.468E-04 3.849E-04 Skin (mRem/yr) 8.157E-04 7.026E-04 User: Al Locke
[Server]: PSLSA37
[Database]: NEOEMSP
Gas Status Summary Report Tuesday, February 14, 2012 03:52 Page 8 of 8 Period:
Ann, 2011 Site/Unit/Discharge Point:
PSL2 Maximum Individual NNG Dose Summary - Note: All Doses in mRem Receptor SE Nearest Res - Adult SE Nearest Res - Child SE Nearest Res - Infant SE Nearest Res - Teenager SE Visitor - Adult SSW Near Garden - Adult SSW Near Garden - Child SSW Near Garden -
WSW Near Milk - Adult WSW Near Milk - Child WSW Near Milk - Infant WSW Near Milk - Teenager Agegroup Adult Child Infant Teenager Adult Adult Child Teenager Adult Child Infant Teenager Bone 1.775E-05 1.776E-05 1.774E-05 1.773E-05 8.239E-06 1.374E-06 1.375E-06 1.373E-06 5.306E-06 1.205E-05 2.173E-05 3.768E-06 Liver 1.774E-05 1.775E-05 1.774E-05 1.775E-05 8.238E-06 1.374E-06 1.374E-06 1.374E-06 6.089E-06 1.178E-05 2.398E-05 5.077E-06 Total Body 1.771E-05 1.767E-05 1.766E-05 1.769E-05 8.221E-06 1.371E-06 1.369E-06 1.370E-06 5.075E-06 4.614E-06 4.715E-06 1.833E-06 Thyroid 2.027E-05 2.104E-05 2.075E-05 2.071E-05 9.340E-06 1.547E-06 1.600E-06 1.577E-06 3.393E-05 9.366E-05 2.205E-04 4.660E-05 Kidney 1.770E-05 1.767E-05 1.766E-05 1.770E-05 8.217E-06 1.371E-06 1.369E-06 1.371E-06 4.285E-06 4.357E-06 4.355E-06 1.477E-06 Lung 1.848E-05 1.865E-05 1.849E-05 1.887E-05 8.560E-06 1.424E-06 1.436E-06 1.45 1E-06 3.580E-06 4.260E-06 5.695E-06 7.990E-07 GI-Lli 1.770E-05 1.767E-05 1.766E-05 1.769E-05 8.217E-06 1.371E-06 1.368E-06 1.370E-06 3.249E-06 3.240E-06 3.242E-06 1.788E-07 Skin
- 0. 000E+00 0.OOaE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+O0 0.OOOE+00 0.0001E+00 0.OOOE+00 Maximum Dose by Organ:
2 Maximum Organ Dose (mRem):
2.20!
Maximum Total Body Dose (mRem):
1.77.
Maximum Individual NG Dose Summary
.173E-05 2.398E-05 1.771E-05 2.205E-04 1.770E-05 1.887E-05 1.770E-05 0.OOOE+00 5E-04 1E-05 Gas Receptor Location WSW Near Milk 3.43 mi 248 deg SE Visitor SE Nearest Res 1.52 mi 142 deg SSW Near Gard 4.4 mi 207 deg Gamma (mRad) 6.889E-05 2.215E-04 5.116E-04 3.881E-05 Beta (mRad) 7.474E-05 2.403E-04 5.550E-04 4.211E-05 Total Body (mRem) 6.322E-05 2.033E-04 4.694E-04 3.561E-05 Skin (mRem) 1.154E-04 3.711E-04 8.570E-04 6.501E-05 User: Al Locke
[Server]: PSLSA37
[Database]: NEOEMSP
Liquid Status Summary Report Tuesday, February 14, 2012 03:51 Page 6 of 6 Period:
Ann, 2011 Site/Unit/Discharge Point:
Site Liquid Dose Summary - Note: All Doses in mRem Receptor AaearouD Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin Liquid Recptor - Child Child 3.003E-02 1.068E-01 3.500E-02 8.364E-03 2.524E-03 1.217E-01 6.432E-02 O.OOOE+00 Liquid Receptor - Teenager Teenager 5.679E-02 2.300E-01 6.638E-02 6.786E-03 5.823E-03 2.632E-01 1.369E-01 O.OOOE+00 Maximum Dose by Organ:
5.679E-02 2.300E-01 6.638E-02 8.364E-03 5.823E-03 2.632E-01 1.369E-01 O.OOOE+00 Maximum Organ Dose (mRem):
Maximum Total Body Dose (mRem):
2.632E-01 6.638E-02 User: Al Locke
[Server]: PSLSA37
[Database]: NEOEMSP
Liquid Status Summary Report Tuesday, February 14, 2012 03:54 Page 6 of 6 Period:
Ann, 2011 Site/Unit/Discharge Point:
PSL1 Liquid Dose Summary - Note: All Doses in mRem Receptor AaearouD Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin Liquid Recptor - Child Child 1.502E-02 5.340E-02 1.750E-02 4.182E-03 1.262E-03 6.085E-02 3.216E-02 0.OOOE+00 Liquid Receptor - Teenager Teenager 2.839E-02 1.150E-01 3.319E-02 3.393E-03 2.912E-03 1.316E-01 6.843E-02 0.000E+00 Maximum Dose by Organ:
2.839E-02 1.150E-01 3.319E-02 4.182E-03 2.912E-03 1.316E-01 6.843E-02 0.000E+00 Maximum Organ Dose (mRem):
Maximum Total Body Dose (mRem):
1.316E-01 3.319E-02 User: Al Locke
[Server]: PSLSA37
[Database]: NEOEMSP
Liquid Status Summary Report Tuesday, February 14, 2012 03:55 Page 6 of 6 Period:
Ann, 2011 Site/Unit/Discharge Point:
PSL2 Liquid Dose Summary - Note: All Doses in mRem Receptor AaearouD Bone Liver Total Body Thyroid Kidne kjn GI-Lli Skin Liquid Recptor - Child Child 1.502E-02 5.340E-02 1.750E-02 4.182E-03 1.262E-03 6.085E-02 3.216E-02 O.OOOE+00 Liquid Receptor - Teenager Teenager 2.839E-02 1.150E-01 3.319E-02 3.393E-03 2.912E-03 1.316E-01 6.843E-02 O.OOOE+00 Maximum Dose by Organ:
2.839E-02 1.150E-01 3.319E-02 4.182E-03 2.912E-03 1.316E-01 6.843E-02 0.000E+00 Maximum Organ Dose (mRem):
Maximum Total Body Dose (mRem):
1.316E-01 3.319E-02 User: Al Locke
[Server]: PSLSA37
[Database]: NEOEMSP