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| issue date = 04/23/2002
| issue date = 04/23/2002
| title = Annual Radioactive Effluent Release Report - 2001, for San Onofre Nuclear Generating Station, Units 1, 2, and 3
| title = Annual Radioactive Effluent Release Report - 2001, for San Onofre Nuclear Generating Station, Units 1, 2, and 3
| author name = Scherer A E
| author name = Scherer A
| author affiliation = Southern California Edison Co
| author affiliation = Southern California Edison Co
| addressee name =  
| addressee name =  
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..........1 ..........2 ..........8 DENDUM .... ....... 17 S. ........ .21 S. ........ .24 S. ........ .26 S. ........ .27 S. ........ .31 S. ........ .32 S. ........ .33 S.. .......... .35 SECTION L -S.O.N.G.S.
..........1 ..........2 ..........8 DENDUM .... ....... 17 S. ........ .21 S. ........ .24 S. ........ .26 S. ........ .27 S. ........ .31 S. ........ .32 S. ........ .33 S.. .......... .35 SECTION L -S.O.N.G.S.
1 CONCLUSIONS  
1 CONCLUSIONS  
...-ii-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) January -December SFfTTMN A INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Unit 1. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:  
...-ii-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) January -December SFfTTMN A INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Unit 1. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:
: 1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release 2. Percent of Applicable Limits 3. Estimated Total Percent Error 4. Lower Limit of Detection Concentrations  
: 1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release 2. Percent of Applicable Limits 3. Estimated Total Percent Error 4. Lower Limit of Detection Concentrations
: 5. Batch Release Summaries  
: 5. Batch Release Summaries
: 6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments  
: 6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments
: 8. 10 CFR 50 Appendix I Requirements  
: 8. 10 CFR 50 Appendix I Requirements
: 9. Changes to Offsite Dose Calculation Manual-1-.......................
: 9. Changes to Offsite Dose Calculation Manual-1-.......................
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
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Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC for continuous mode releases only. Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period. Table IF, "Gaseous Effluents-Batch Release Summary," has been deleted. "Batch" mode releases are no longer conducted as of 8/4/93, due to the permanent shutdown of the reactor.
Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC for continuous mode releases only. Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period. Table IF, "Gaseous Effluents-Batch Release Summary," has been deleted. "Batch" mode releases are no longer conducted as of 8/4/93, due to the permanent shutdown of the reactor.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter A. Fission and activation gases 1. Total release Ci <LLD <LLD 3.OOE+l 2. Average release rate for period 4Ci/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O B. Iodines 1. Total iodine-131 Ci <LLD <LLD 1.90E+1 2. Average release rate for period uCi/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O C. Particulates  
1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter A. Fission and activation gases 1. Total release Ci <LLD <LLD 3.OOE+l 2. Average release rate for period 4Ci/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O B. Iodines 1. Total iodine-131 Ci <LLD <LLD 1.90E+1 2. Average release rate for period uCi/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O C. Particulates
: 1. Particulates with half-lives  
: 1. Particulates with half-lives  
>8 days Ci <LLD <LLD 1.60E+1 2. Average release rate for period gCi/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O 5. Gross alpha activity Ci 1.62E-7 5.43E-8 5.OOE+1 D. Tritium 1. Total release Ci 2.14E-1 3.51E-1 2.50E+1 2. Average release rate for period uCi/sec 2.75E-2 4.46E-2 3. Percent of applicable limit % MPC 1.79E-4 2.90E-4 4. Percent Effluent Concentration Limit % ECL 3.58E-4 5.80E-4-3-Second Quarter Estimated Total Error, %
>8 days Ci <LLD <LLD 1.60E+1 2. Average release rate for period gCi/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O 5. Gross alpha activity Ci 1.62E-7 5.43E-8 5.OOE+1 D. Tritium 1. Total release Ci 2.14E-1 3.51E-1 2.50E+1 2. Average release rate for period uCi/sec 2.75E-2 4.46E-2 3. Percent of applicable limit % MPC 1.79E-4 2.90E-4 4. Percent Effluent Concentration Limit % ECL 3.58E-4 5.80E-4-3-Second Quarter Estimated Total Error, %
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1, "BATCH MODE" releases are no longer conducted.
1, "BATCH MODE" releases are no longer conducted.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
1 TABLE ID GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (,uCi/cc)  
1 TABLE ID GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (,uCi/cc)
: 1. Fission and activation gases krypton-85 2.10E-5 krypton-85m 5.OOE-8 krypton-87 2.60E-7 krypton-88 1.80E-7 xenon-133 1.30E-7 xenon-133m 4.10E-7 xenon-135 5.30E-8 xenon-135m 2.OOE-6 xenon- 138 3.50E-6 2. lodines iodine-131 2.90E-13 iodine-133 2.80E-12 iodine-135 1.90E-1O 3. Particulates barium-140 5.90E-13 cerium-141 6.60E-14 cerium-144 2.60E-13 cesium-134 1.70E-13 cesium-137 1.40E-13 cobalt-58 1.50E-13 cobal t-60 2.40E-13 iron-59 3.80E-13 lanthanum-140 1.20E-12 manganese-54 1.50E-13 molybdenum-99 7.90E-14 strontium-89 1.OOE-14 strontium-90 1.OOE-15 zinc-65 4.OOE-13 NOTE: Due to the permanent shutdown of S.O.N.G.S.
: 1. Fission and activation gases krypton-85 2.10E-5 krypton-85m 5.OOE-8 krypton-87 2.60E-7 krypton-88 1.80E-7 xenon-133 1.30E-7 xenon-133m 4.10E-7 xenon-135 5.30E-8 xenon-135m 2.OOE-6 xenon- 138 3.50E-6 2. lodines iodine-131 2.90E-13 iodine-133 2.80E-12 iodine-135 1.90E-1O 3. Particulates barium-140 5.90E-13 cerium-141 6.60E-14 cerium-144 2.60E-13 cesium-134 1.70E-13 cesium-137 1.40E-13 cobalt-58 1.50E-13 cobal t-60 2.40E-13 iron-59 3.80E-13 lanthanum-140 1.20E-12 manganese-54 1.50E-13 molybdenum-99 7.90E-14 strontium-89 1.OOE-14 strontium-90 1.OOE-15 zinc-65 4.OOE-13 NOTE: Due to the permanent shutdown of S.O.N.G.S.
1, "BATCH MODE" longer conducted.
1, "BATCH MODE" longer conducted.
releases are no  
releases are no  
-- -- -- --- --U L ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
-- -- -- --- --U L ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas 1. Gamma Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O 2. Percent Applicable Limit O.OOE+O O.OOE+O O.OOE+O O.OOE+O 3. Beta Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O 4. Percent Applicable Limit % O.OOE+O O.OOE+O O.OOE+O O.OOE+O B. Tritium, Iodine, Particulates (at the nearest receptor)  
1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas 1. Gamma Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O 2. Percent Applicable Limit O.OOE+O O.OOE+O O.OOE+O O.OOE+O 3. Beta Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O 4. Percent Applicable Limit % O.OOE+O O.OOE+O O.OOE+O O.OOE+O B. Tritium, Iodine, Particulates (at the nearest receptor)
: 1. Organ Dose mrem 8.01E-6 1.43E-5 4.36E-5 1.31E-4 2. Percent Applicable Limit % 1.07E-4 1.91E-4 5.82E-4 1.74E-3 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE  
: 1. Organ Dose mrem 8.01E-6 1.43E-5 4.36E-5 1.31E-4 2. Percent Applicable Limit % 1.07E-4 1.91E-4 5.82E-4 1.74E-3 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE  


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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
I SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories:
I SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories:
fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are: (1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists: (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)  
fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are: (1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists: (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)
(3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category.
(3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category.
The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.
The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.
Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period. Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Unit 1.
Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period. Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Unit 1.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Second Unit Quarter Quarter Estimated Total Error, %A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 2.47E-7 3.11E-6 1.90E+1 2. Average diluted concentration during period gCi/ml 1.56E-13 1.93E-12 3. Percent of applicable limit % MPC 7.82E-7 9.66E-6 4. Percent Effluent Concentration Limit % ECL 1.56E-5 1.93E-4 B. Tritium I. Total release Ci 1.33E-2 5.23E-4 1.90E+1 2. Average diluted concentration during period ,uCi/ml 8.42E-9 3.25E-10 3. Percent of applicable limit % MPC 2.81E-4 1.08E-5 4. Percent Effluent Concentration Limit % ECL 8.42E-4 3.25E-5 C. Dissolved and entrained gases 1. Total release Ci <LLD <LLD 1.90E+1 2. Average diluted concentration during period MCi/ml O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity  
1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Second Unit Quarter Quarter Estimated Total Error, %A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 2.47E-7 3.11E-6 1.90E+1 2. Average diluted concentration during period gCi/ml 1.56E-13 1.93E-12 3. Percent of applicable limit % MPC 7.82E-7 9.66E-6 4. Percent Effluent Concentration Limit % ECL 1.56E-5 1.93E-4 B. Tritium I. Total release Ci 1.33E-2 5.23E-4 1.90E+1 2. Average diluted concentration during period ,uCi/ml 8.42E-9 3.25E-10 3. Percent of applicable limit % MPC 2.81E-4 1.08E-5 4. Percent Effluent Concentration Limit % ECL 8.42E-4 3.25E-5 C. Dissolved and entrained gases 1. Total release Ci <LLD <LLD 1.90E+1 2. Average diluted concentration during period MCi/ml O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity
: 1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 8.31E+6 1.16E+6 5.OOE+O F. Volume of dilution water used during period liters 1.58E+9 1.61E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 8.31E+6 1.16E+6 5.OOE+O F. Volume of dilution water used during period liters 1.58E+9 1.61E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
1 TABLE 2A (Continued)
1 TABLE 2A (Continued)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, %A. Fission and activation products (1) 1. Total release (not including tritium, gases, alpha) Ci 3.37E-5 3.42E-3 1.90E+1 2. Average diluted concentration during period MCi/ml 2.03E-I1 1.89E-9 3. Percent of applicable limit % MPC 1.02E-4 1.67E-2 4. Percent Effluent Concentration Limit % ECL 2.03E-3 1.35E-1 B. Tritium 1. Total release Ci 1.48E-4 2.28E-0 1.90E+1 2. Average diluted concentration during period uCi/ml 8.92E-11 1.26E-6 3. Percent of applicable limit % MPC 2.97E-6 4.20E-2 4. Percent Effluent Concentration Limit % ECL 8.92E-6 1.26E-1 C. Dissolved and entrained gases 1. Total release Ci <LLD <LLD 1.90E+1 2. Average diluted concentration during period uCi/ml O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity  
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, %A. Fission and activation products (1) 1. Total release (not including tritium, gases, alpha) Ci 3.37E-5 3.42E-3 1.90E+1 2. Average diluted concentration during period MCi/ml 2.03E-I1 1.89E-9 3. Percent of applicable limit % MPC 1.02E-4 1.67E-2 4. Percent Effluent Concentration Limit % ECL 2.03E-3 1.35E-1 B. Tritium 1. Total release Ci 1.48E-4 2.28E-0 1.90E+1 2. Average diluted concentration during period uCi/ml 8.92E-11 1.26E-6 3. Percent of applicable limit % MPC 2.97E-6 4.20E-2 4. Percent Effluent Concentration Limit % ECL 8.92E-6 1.26E-1 C. Dissolved and entrained gases 1. Total release Ci <LLD <LLD 1.90E+1 2. Average diluted concentration during period uCi/ml O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity
: 1. Total release Ci <LLD 2.93E-5 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 6.88E+5 6.31E+6 5.OOE+O F. Volume of dilution water used during period liters 1.66E+9 1.81E+9 5.OOE+O-10-(1) The 10/29/01 grab samples for the Yard Drain Sump (YDS) and Reheater Pit Sump were collected but discarded prior to compositing.
: 1. Total release Ci <LLD 2.93E-5 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 6.88E+5 6.31E+6 5.OOE+O F. Volume of dilution water used during period liters 1.66E+9 1.81E+9 5.OOE+O-10-(1) The 10/29/01 grab samples for the Yard Drain Sump (YDS) and Reheater Pit Sump were collected but discarded prior to compositing.
The 10/23/01-10/29/01 composite for both sumps consisted of the two remaining grabs and were <LLD. The grab sample for the composite was not collected 12/28/01 for the YDS. The 12/25/01 12/31/01 composite was also <LLD. These events are documented in ARs 011001581 and 020100050.
The 10/23/01-10/29/01 composite for both sumps consisted of the two remaining grabs and were <LLD. The grab sample for the composite was not collected 12/28/01 for the YDS. The 12/25/01 12/31/01 composite was also <LLD. These events are documented in ARs 011001581 and 020100050.
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LIQUID EFFLUENTS BATCH MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation products barium-140 Ci N/A N/A N/A <LLD cerium-141 Ci N/A N/A N/A <LLD cerium-144 Ci N/A N/A N/A <LLD cesium-134 Ci N/A N/A N/A 9.86E-5 cesium-137 Ci N/A N/A N/A 1.71E-3 chromium-51 Ci N/A N/A N/A <LLD cobalt-58 Ci N/A N/A N/A <LLD cobalt-60 Ci N/A N/A N/A 1.56E-3 iodine-131 Ci N/A N/A N/A <LLD iron-55 Ci N/A N/A N/A <LLD iron-59 Ci N/A N/A N/A <LLD lanthanum-140 Ci N/A N/A N/A <LLD manganese-54 Ci N/A N/A N/A <LLD molybdenum-99 Ci N/A N/A N/A <LLD niobium-95 Ci N/A N/A N/A <LLD strontium-89 Ci N/A N/A N/A <LLD strontium-90 Ci N/A N/A N/A 4.58E-5 technetium-99m Ci N/A N/A N/A <LLD zinc-65 Ci N/A N/A N/A <LLD zirconium-95 Ci N/A N/A N/A <LLD Total for period Ci N/A N/A N/A 3.42E-3 2. Dissolved and entrained gases xenon-133 Ci N/A N/A N/A <LLD xenon-135 Ci N/A N/A N/A <LLD Total for period Ci N/A N/A N/A <LLD N/A No releases conducted LLD Lower Limit of Detection; see Table 2C.
LIQUID EFFLUENTS BATCH MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation products barium-140 Ci N/A N/A N/A <LLD cerium-141 Ci N/A N/A N/A <LLD cerium-144 Ci N/A N/A N/A <LLD cesium-134 Ci N/A N/A N/A 9.86E-5 cesium-137 Ci N/A N/A N/A 1.71E-3 chromium-51 Ci N/A N/A N/A <LLD cobalt-58 Ci N/A N/A N/A <LLD cobalt-60 Ci N/A N/A N/A 1.56E-3 iodine-131 Ci N/A N/A N/A <LLD iron-55 Ci N/A N/A N/A <LLD iron-59 Ci N/A N/A N/A <LLD lanthanum-140 Ci N/A N/A N/A <LLD manganese-54 Ci N/A N/A N/A <LLD molybdenum-99 Ci N/A N/A N/A <LLD niobium-95 Ci N/A N/A N/A <LLD strontium-89 Ci N/A N/A N/A <LLD strontium-90 Ci N/A N/A N/A 4.58E-5 technetium-99m Ci N/A N/A N/A <LLD zinc-65 Ci N/A N/A N/A <LLD zirconium-95 Ci N/A N/A N/A <LLD Total for period Ci N/A N/A N/A 3.42E-3 2. Dissolved and entrained gases xenon-133 Ci N/A N/A N/A <LLD xenon-135 Ci N/A N/A N/A <LLD Total for period Ci N/A N/A N/A <LLD N/A No releases conducted LLD Lower Limit of Detection; see Table 2C.
I_ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
I_ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION-13-Radionuclides LLD (,uCi/cc)  
1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION-13-Radionuclides LLD (,uCi/cc)
: 1. Fission and activation products barium-140 3.90E-7 cerium-141 5.80E-8 cerium-144 2.30E-7 cesium-134 1.OOE-7 chromium-51 4.60E-7 cobalt-58 9.OOE-8 cobalt-60 1.30E-7 iodine-131 8.OOE-8 iron-55 I.OOE-6 iron-59 2.1OE-7 1anthanum-140 7.20E-7 manganese-54 8.90E-8 mol ybdenum-99 7.50E-8 niobium-95 9.10E-8 strontium-89 5.OOE-8 stronti um-90 I.OOE-8 techneti um-99m 7.70E-8 zinc-65 2.20E-7 zi rconium-95 1.60E-7 2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 1. Fission and activation products barium-140 3.90E-7 cerium-141 5.80E-8 cerium-144 2.30E-7 cesium-134 1.OOE-7 chromium-51 4.60E-7 cobalt-58 9.OOE-8 cobalt-60 1.30E-7 iodine-131 8.OOE-8 iron-55 I.OOE-6 iron-59 2.1OE-7 1anthanum-140 7.20E-7 manganese-54 8.90E-8 mol ybdenum-99 7.50E-8 niobium-95 9.10E-8 strontium-89 5.OOE-8 stronti um-90 I.OOE-8 techneti um-99m 7.70E-8 zinc-65 2.20E-7 zi rconium-95 1.60E-7 2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
1 TABLE 2C (Continued)
1 TABLE 2C (Continued)
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-14-Radionuclides LLD (/uCi/cc)  
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-14-Radionuclides LLD (/uCi/cc)
: 1. Fission and activation products barium-140 3.30E-7 cerium-141 5.30E-8 cerium-144 2.30E-7 chromi um-51 4.20E-7 cobalt-58 8.70E-8 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 1 anthanum-140 2.40E-7 manganese-54 8.80E-8 mol ybdenum-99 3.50E-8 ni obi um-95 8.50E-8 stronti um-89 5.OOE-8 techneti um-99m 3.60E-8 zinc-65 2.20E-7 zi rconi um-95 1.50E-7 2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 LIQUI[ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 1. Fission and activation products barium-140 3.30E-7 cerium-141 5.30E-8 cerium-144 2.30E-7 chromi um-51 4.20E-7 cobalt-58 8.70E-8 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 1 anthanum-140 2.40E-7 manganese-54 8.80E-8 mol ybdenum-99 3.50E-8 ni obi um-95 8.50E-8 stronti um-89 5.OOE-8 techneti um-99m 3.60E-8 zinc-65 2.20E-7 zi rconi um-95 1.50E-7 2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 LIQUI[ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
I TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIOUID SITE BOL JNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. 1. Total body dose mrem 7.40E-5 3.33E-5 3.51E-4 1.51E-2 2. Percent Applicable Limit 4.93E-3 2.22E-3 2.34E-2 1.OIE+O B. I. Limiting organ dose mrem 7.54E-5 5.08E-5 5.36E-4 3.44E-2 2. Percent Applicable Limit % 1.51E-3 1.02E-3 1.07E-2 6.88E-1 3. Limiting organ for period Liver Liver Liver GI/LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
I TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIOUID SITE BOL JNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. 1. Total body dose mrem 7.40E-5 3.33E-5 3.51E-4 1.51E-2 2. Percent Applicable Limit 4.93E-3 2.22E-3 2.34E-2 1.OIE+O B. I. Limiting organ dose mrem 7.54E-5 5.08E-5 5.36E-4 3.44E-2 2. Percent Applicable Limit % 1.51E-3 1.02E-3 1.07E-2 6.88E-1 3. Limiting organ for period Liver Liver Liver GI/LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
I SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. IOCFR50 Appendix I Requirements TABLE 1 (1998) Dose * (millirems)
I SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. IOCFR50 Appendix I Requirements TABLE 1 (1998) Dose * (millirems)
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS  
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
: 11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 2.06E-4 O.OOE+O O.OOE+O 5.64E-4 7.70E-4 NOBLE GASES ** 16) 17) 18) .19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta 21) 22) 23) 24) 25) O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O
: 11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 2.06E-4 O.OOE+O O.OOE+O 5.64E-4 7.70E-4 NOBLE GASES ** 16) 17) 18) .19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta 21) 22) 23) 24) 25) O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O
* The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).
* The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).
Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-15 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the NW sector. 12-13 There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. 14. The maximum organ dose was to a child's thyroid and was located in the NW sector. 15. The maximum organ dose was to a child's thyroid and was located in the NW sector. 16-20 There was no activity detected during any of these release periods, therefore the reported air dose for gamma radiation was O.OOE+O mrad. 21-25 There was no activity detected during any of the release periods, therefore the reported air dose for beta radiation was O.OOE+O mrad. TABLE 2 (1998) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 2.75E-3 O.OOE+O O.OOE+O 7.52E-3 5.13E-3 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O-19-i I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-15 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the NW sector. 12-13 There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. 14. The maximum organ dose was to a child's thyroid and was located in the NW sector. 15. The maximum organ dose was to a child's thyroid and was located in the NW sector. 16-20 There was no activity detected during any of these release periods, therefore the reported air dose for gamma radiation was O.OOE+O mrad. 21-25 There was no activity detected during any of the release periods, therefore the reported air dose for beta radiation was O.OOE+O mrad. TABLE 2 (1998) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 2.75E-3 O.OOE+O O.OOE+O 7.52E-3 5.13E-3 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O-19-i I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
1 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. 1OCFR50 Appendix I Requirements TABLE 1 (1999) Dose * (millirems)
1 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. 1OCFR50 Appendix I Requirements TABLE 1 (1999) Dose * (millirems)
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS  
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
: 11) 12) 13) 14) 15) Tritium, lodines, and Particulates O.OOE+O 1.03E-4 6.85E-5 7.07E-4 8.79E-4 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta 21) 22) 23) 24) 25) O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O
: 11) 12) 13) 14) 15) Tritium, lodines, and Particulates O.OOE+O 1.03E-4 6.85E-5 7.07E-4 8.79E-4 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta 21) 22) 23) 24) 25) O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O
* The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s). Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-15 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. 12. The maximum organ dose was to a child's thyroid and was located in the NW sector. 13. The maximum organ dose was to a child's thyroid and was located in the NW sector. 14. The maximum organ dose was to a child's thyroid and was located in the NW sector. 15. The maximum organ dose was to a child's thyroid and was located in the NW sector. 16-20 There was no activity detected during any of these release periods, therefore the reported air dose for gamma radiation was O.OOE+O mrad. 21-25 There was no activity detected during any of these release periods, therefore the reported air dose for beta radiation was O.OOE+O mrad. TABLE 2 (1999) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates O.OOE+O 1.38E-3 9.13E-4 9.43E-3 5.86E-3 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
* The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s). Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-15 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. 12. The maximum organ dose was to a child's thyroid and was located in the NW sector. 13. The maximum organ dose was to a child's thyroid and was located in the NW sector. 14. The maximum organ dose was to a child's thyroid and was located in the NW sector. 15. The maximum organ dose was to a child's thyroid and was located in the NW sector. 16-20 There was no activity detected during any of these release periods, therefore the reported air dose for gamma radiation was O.OOE+O mrad. 21-25 There was no activity detected during any of these release periods, therefore the reported air dose for beta radiation was O.OOE+O mrad. TABLE 2 (1999) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates O.OOE+O 1.38E-3 9.13E-4 9.43E-3 5.86E-3 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
I SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated 12 month total 1. Type of waste Unit period error (%) a. Spent resins, filter sludges, m 3  N/A evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3  2.52E+3 compactable and non-compactable
I SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated 12 month total 1. Type of waste Unit period error (%) a. Spent resins, filter sludges, m 3  N/A evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3  2.52E+3 compactable and non-compactable
* _________
* _________
Ci 1.29E+0- 3.00E+1 c. Irradiated components, control m 3  N/A rods Ci N/A N/A d. Other mn 3  N/A Ci N/A N/A NOTE: Total curie content estimated.
Ci 1.29E+0- 3.00E+1 c. Irradiated components, control m 3  N/A rods Ci N/A N/A d. Other mn 3  N/A Ci N/A N/A NOTE: Total curie content estimated.
(*) Material packaged in strong, tight containers of various sizes. N/A No shipment made.
(*) Material packaged in strong, tight containers of various sizes. N/A No shipment made.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
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% 1.24E+1 niobium-94
% 1.24E+1 niobium-94
__6.24E-2 ni obi um-95 1.39E-1 pl utoni um-238 5.24E-2 plutonium-239/240 1.94E-2 pl utoni um-241 _ _1.22E+O pl utoni um-242 __8.55E-3 stronti um-90 __1.77E-1 techneti um-99 __2.20E-3 tritium __1.07E-1 urani um-233/234 96 1.32E-4 zi rconium-95
__6.24E-2 ni obi um-95 1.39E-1 pl utoni um-238 5.24E-2 plutonium-239/240 1.94E-2 pl utoni um-241 _ _1.22E+O pl utoni um-242 __8.55E-3 stronti um-90 __1.77E-1 techneti um-99 __2.20E-3 tritium __1.07E-1 urani um-233/234 96 1.32E-4 zi rconium-95
__1.46E-1  
__1.46E-1
: c. not applicable
: c. not applicable
__N/A d. not applicable
__N/A d. not applicable
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.1I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
.1I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
1 SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table I in Section H presents the quarterly and annual maximum dose to an individual.
1 SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table I in Section H presents the quarterly and annual maximum dose to an individual.
Six different categories are presented:  
Six different categories are presented:
(1) Liquid Effluents  
(1) Liquid Effluents  
-Whole Body (2) Liquid Effluents  
-Whole Body (2) Liquid Effluents  
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I TABLE 1* The numbered footnotes below briefly explain how each the organ and the predominant pathway(s).   
I TABLE 1* The numbered footnotes below briefly explain how each the organ and the predominant pathway(s).   
** Noble gas doses due to airborne effluent are in units 1. This value was calculated using the methodology of thi 2. This value was calculated using the methodology of thi 3. This value was calculated using the methodology of thi 4. This value was calculated using the methodology of thi 5. This value was calculated using the methodology of thi maximum dose was calculated, including of mrad, reflecting the air dose. e ODCM. e ODCM. e ODCM. e ODCM. e ODCM.-28-Dose * (millirems)
** Noble gas doses due to airborne effluent are in units 1. This value was calculated using the methodology of thi 2. This value was calculated using the methodology of thi 3. This value was calculated using the methodology of thi 4. This value was calculated using the methodology of thi 5. This value was calculated using the methodology of thi maximum dose was calculated, including of mrad, reflecting the air dose. e ODCM. e ODCM. e ODCM. e ODCM. e ODCM.-28-Dose * (millirems)
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS  
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS
: 1) 2) 3) 4) 5) Whole Body 7.40E-5 3.33E-5 3.51E-4 1.51E-2 1.56E-2 6) 7) 8) 9) 10) Organ 7.54E-5 5.08E-5 5.36E-4 3.44E-2 3.45E-2 AIRBORNE EFFLUENTS  
: 1) 2) 3) 4) 5) Whole Body 7.40E-5 3.33E-5 3.51E-4 1.51E-2 1.56E-2 6) 7) 8) 9) 10) Organ 7.54E-5 5.08E-5 5.36E-4 3.44E-2 3.45E-2 AIRBORNE EFFLUENTS
: 11) 12) 13) 14) 15) Tritium, lodines, and Particulates 7.17E-5 2.11E-4 5.65E-4 8.63E-4 1.71E-3 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O 21) 22) 23) 24) 25) Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O 26) 27) 28) 29) 30) DIRECT RADIATION 9.36E-2 1.24E-1 6.84E-2 1.11E-1 3.52E-1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 11) 12) 13) 14) 15) Tritium, lodines, and Particulates 7.17E-5 2.11E-4 5.65E-4 8.63E-4 1.71E-3 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O 21) 22) 23) 24) 25) Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O 26) 27) 28) 29) 30) DIRECT RADIATION 9.36E-2 1.24E-1 6.84E-2 1.11E-1 3.52E-1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
I 6. 7. 8. 9. 10. 11. 12. 13. 14. 15.calculated using the assumptions of USNRC Regulatory Guide 1.109.There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad.the release period, therefore the the the the the the the the release release rel ease rel ease rel ease rel ease rel ease rel ease period, period, period, period, period, period, period, period, therefore therefore therefore therefore therefore therefore therefore therefore This value was calculated using the methodology of the ODCM; the liver primarily by the saltwater fish pathway.
I 6. 7. 8. 9. 10. 11. 12. 13. 14. 15.calculated using the assumptions of USNRC Regulatory Guide 1.109.There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad.the release period, therefore the the the the the the the the release release rel ease rel ease rel ease rel ease rel ease rel ease period, period, period, period, period, period, period, period, therefore therefore therefore therefore therefore therefore therefore therefore This value was calculated using the methodology of the ODCM; the liver primarily by the saltwater fish pathway.
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2 and 3 CONCLUSIONS  
2 and 3 CONCLUSIONS  
........
........
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)January -December SECTION A. INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Units 2 and 3. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:  
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)January -December SECTION A. INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Units 2 and 3. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:
: 1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release 2. Percent of Applicable Limits 3. Estimated Total Percent Error 4. Lower Limit of Detection Concentrations  
: 1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release 2. Percent of Applicable Limits 3. Estimated Total Percent Error 4. Lower Limit of Detection Concentrations
: 5. Batch Release Summaries  
: 5. Batch Release Summaries
: 6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments  
: 6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments
: 8. 10 CFR 50 Appendix I Requirements  
: 8. 10 CFR 50 Appendix I Requirements
: 9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories:
2 and 3 SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories:
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Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and 1C. Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period. Table IF, "Gaseous Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.
Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and 1C. Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period. Table IF, "Gaseous Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter Estimated Second Total Quarter Error, %C. Fission and activation gases 1. Total release Ci 3.22E+1 8.98E+O 3.OOE+1 2. Average release rate for period 4Ci/sec 4.14E+O 1.15E+O 3. Percent of applicable limit % MPC 9.94E-3 4.15E-3 4. Percent Effluent Concentration Limit % ECL 1.89E-2 1.17E-2 D. Iodines 1. Total iodine-131 Ci 2.24E-3 1.77E-5 1.90E+1 2. Average release rate for period 4Ci/sec 2.88E-4 2.25E-6 3. Percent of applicable limit % MPC 1.38E-3 1.08E-5 4. Percent Effluent Concentration Limit % ECL 6.91E-4 5.40E-6 E. Particulates  
2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter Estimated Second Total Quarter Error, %C. Fission and activation gases 1. Total release Ci 3.22E+1 8.98E+O 3.OOE+1 2. Average release rate for period 4Ci/sec 4.14E+O 1.15E+O 3. Percent of applicable limit % MPC 9.94E-3 4.15E-3 4. Percent Effluent Concentration Limit % ECL 1.89E-2 1.17E-2 D. Iodines 1. Total iodine-131 Ci 2.24E-3 1.77E-5 1.90E+1 2. Average release rate for period 4Ci/sec 2.88E-4 2.25E-6 3. Percent of applicable limit % MPC 1.38E-3 1.08E-5 4. Percent Effluent Concentration Limit % ECL 6.91E-4 5.40E-6 E. Particulates
: 1. Particulates with half-lives  
: 1. Particulates with half-lives  
>8 days Ci 1.37E-3 4.78E-5 1.60E+1 2. Average release rate for period uCi/sec 1.76E-4 6.08E-6 3. Percent of applicable limit % MPC 6.36E-5 5.64E-6 4. Percent Effluent Concentration Limit % ECL 1.52E-4 1.41E-5 5. Gross alpha activity Ci 7.66E-6 2.41E-6 5.OOE+1 F. Tritium 1. Total release Ci 2.08E+1 1.89E+1 2.50E+1 2. Average release rate for period kiCi/sec 2.67E+O 2.40E+O 3. Percent of applicable limit % MPC 6.42E-3 5.77E-3 4. Percent Effluent Concentration Limit % ECL 1.28E-2 1.15E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
>8 days Ci 1.37E-3 4.78E-5 1.60E+1 2. Average release rate for period uCi/sec 1.76E-4 6.08E-6 3. Percent of applicable limit % MPC 6.36E-5 5.64E-6 4. Percent Effluent Concentration Limit % ECL 1.52E-4 1.41E-5 5. Gross alpha activity Ci 7.66E-6 2.41E-6 5.OOE+1 F. Tritium 1. Total release Ci 2.08E+1 1.89E+1 2.50E+1 2. Average release rate for period kiCi/sec 2.67E+O 2.40E+O 3. Percent of applicable limit % MPC 6.42E-3 5.77E-3 4. Percent Effluent Concentration Limit % ECL 1.28E-2 1.15E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
2 and 3 TABLE 1A (Continued)
2 and 3 TABLE 1A (Continued)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Quarter Quarter Error, %A. Fission and activation gases 1. Total release Ci 1.73E+1 2.84E+1 3.OOE+1 2. Average release rate for period f4Ci/sec 2.16E+O 3.57E+O 3. Percent of applicable limit % MPC 8.13E-3 9.11E-3 4. Percent Effluent Concentration Limit % ECL 2.32E-2 1.86E-2 B. Iodines 1. Total iodine-131 Ci 2.OOE-5 4.03E-4 1.90E+1 2. Average release rate for period yCi/sec 2.52E-6 5.07E-5 3. Percent of applicable limit % MPC 1.21E-5 2.43E-4 4. Percent Effluent Concentration Limit % ECL 6.04E-6 1.22E-4 C. Particulates  
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Quarter Quarter Error, %A. Fission and activation gases 1. Total release Ci 1.73E+1 2.84E+1 3.OOE+1 2. Average release rate for period f4Ci/sec 2.16E+O 3.57E+O 3. Percent of applicable limit % MPC 8.13E-3 9.11E-3 4. Percent Effluent Concentration Limit % ECL 2.32E-2 1.86E-2 B. Iodines 1. Total iodine-131 Ci 2.OOE-5 4.03E-4 1.90E+1 2. Average release rate for period yCi/sec 2.52E-6 5.07E-5 3. Percent of applicable limit % MPC 1.21E-5 2.43E-4 4. Percent Effluent Concentration Limit % ECL 6.04E-6 1.22E-4 C. Particulates
: 1. Particulates with half-lives  
: 1. Particulates with half-lives  
>8 days Ci 2.57E-4 9.21E-5 1.60E+1 2. Average release rate for period 4Ci/sec 3.23E-5 1.16E-5 3. Percent of applicable limit % MPC 3.03E-5 6.41E-6 4. Percent Effluent Concentration Limit % ECL 7.57E-5 1.91E-5 5. Gross alpha activity Ci 5.92E-6 7.03E-6 5.OOE+1 D. Tritium 1. Total release Ci 1.36E+1 2.76E+1 2.50E+1 2. Average release rate for period MCi/sec 1.71E+O 3.47E+O 3. Percent of applicable limit % MPC 4.11E-3 8.33E-3 4. Percent Effluent Concentration Limit % ECL 8.21E-3 1.67E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
>8 days Ci 2.57E-4 9.21E-5 1.60E+1 2. Average release rate for period 4Ci/sec 3.23E-5 1.16E-5 3. Percent of applicable limit % MPC 3.03E-5 6.41E-6 4. Percent Effluent Concentration Limit % ECL 7.57E-5 1.91E-5 5. Gross alpha activity Ci 5.92E-6 7.03E-6 5.OOE+1 D. Tritium 1. Total release Ci 1.36E+1 2.76E+1 2.50E+1 2. Average release rate for period MCi/sec 1.71E+O 3.47E+O 3. Percent of applicable limit % MPC 4.11E-3 8.33E-3 4. Percent Effluent Concentration Limit % ECL 8.21E-3 1.67E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
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* Iodines and particulates are not analyzed prior to release via batch mode.
* Iodines and particulates are not analyzed prior to release via batch mode.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionucl ides LLD (/.tCi/cc)  
2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionucl ides LLD (/.tCi/cc)
: 1. Fission and activation gases krypton-85 2.1IOE-5 krypton-85m 5,OOE-8 krypton-87 2.60E-7 krypton-88 1.80E-7 xenon-131m 1.70E-6 xenon-133m 4.1OE-7 xenon-135 5.30E-8 xenon-135m 2.OOE-6 xenon-138 3.50E-6 2. lodines iodine-132 6.OOE-1O iodine-135 1.70E-10 3. Particulates barium-140 2.70E-11 cerium-141 3.40E-12 cerium-144 1.40E-11 cesium-134 9.20E-12 chromi um-51 3.20E-11 cobalt-60 1.30E-11 iron-59 2.OOE-11 1anthanum-140 2.20E-11 manganese-54 8.20E-12 molybdenum-99  
: 1. Fission and activation gases krypton-85 2.1IOE-5 krypton-85m 5,OOE-8 krypton-87 2.60E-7 krypton-88 1.80E-7 xenon-131m 1.70E-6 xenon-133m 4.1OE-7 xenon-135 5.30E-8 xenon-135m 2.OOE-6 xenon-138 3.50E-6 2. lodines iodine-132 6.OOE-1O iodine-135 1.70E-10 3. Particulates barium-140 2.70E-11 cerium-141 3.40E-12 cerium-144 1.40E-11 cesium-134 9.20E-12 chromi um-51 3.20E-11 cobalt-60 1.30E-11 iron-59 2.OOE-11 1anthanum-140 2.20E-11 manganese-54 8.20E-12 molybdenum-99
: 2. 1OE-12 niobium-95 7.70E-12 sodium-24 3.30E-12 stronti um-89 1.OOE-13 stronti um-90 1.OOE-14 technetium-99m 1.20E-11 zinc-65 2.20E-11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 2. 1OE-12 niobium-95 7.70E-12 sodium-24 3.30E-12 stronti um-89 1.OOE-13 stronti um-90 1.OOE-14 technetium-99m 1.20E-11 zinc-65 2.20E-11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
2 and 3 TABLE ID (Continued)
2 and 3 TABLE ID (Continued)
GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-44-Radionuclides LLD (/,&#xfd;Ci/cc)  
GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-44-Radionuclides LLD (/,&#xfd;Ci/cc)
: 1. Fission and activation gases krypton-85 1.20E-3 krypton-85m 2.50E-6 krypton-87 1.20E-5 krypton-88 8.90E-6 xenon-133 5.70E-6 xenon-133m 2.30E-5 xenon-135 2.90E-6 xenon-135m 3.70E-5 xenon-138 5.50E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 1. Fission and activation gases krypton-85 1.20E-3 krypton-85m 2.50E-6 krypton-87 1.20E-5 krypton-88 8.90E-6 xenon-133 5.70E-6 xenon-133m 2.30E-5 xenon-135 2.90E-6 xenon-135m 3.70E-5 xenon-138 5.50E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
2 and 3 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Unit Quarter Quarter Quarter Fourth Quarter A. Noble Gas 1. Gamma Air Dose mrad 5.07E-3 2.81E-3 5.76E-3 5.02E-3 2.. Percent Applicable Limit % 5.07E-2 2.81E-2 5.76E-2 5.02E-2 3. Beta Air Dose mrad 6.20E-3 2.08E-3 4.02E-3 5.47E-3 4. Percent Applicable Limit 3.10E-2 1.04E-2 2.01E-2 2.74E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)  
2 and 3 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Unit Quarter Quarter Quarter Fourth Quarter A. Noble Gas 1. Gamma Air Dose mrad 5.07E-3 2.81E-3 5.76E-3 5.02E-3 2.. Percent Applicable Limit % 5.07E-2 2.81E-2 5.76E-2 5.02E-2 3. Beta Air Dose mrad 6.20E-3 2.08E-3 4.02E-3 5.47E-3 4. Percent Applicable Limit 3.10E-2 1.04E-2 2.01E-2 2.74E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)
: 1. Organ Dose mrem 3.10E-3 7.65E-4 1.06E-3 1.48E-3 2. Percent Applicable Limit % 2.07E-2 5.10E-3 7.09E-3 9.89E-3 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.
: 1. Organ Dose mrem 3.10E-3 7.65E-4 1.06E-3 1.48E-3 2. Percent Applicable Limit % 2.07E-2 5.10E-3 7.09E-3 9.89E-3 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
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2672 minutes 3. Maximum time period for a batch release: 468 minutes 4. Average time period for a batch release: 334 minutes 5. Minimum time period for a batch release: 23 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2672 minutes 3. Maximum time period for a batch release: 468 minutes 4. Average time period for a batch release: 334 minutes 5. Minimum time period for a batch release: 23 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories:
2 and 3 SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories:
fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are: (1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists: (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)  
fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are: (1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists: (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)
(3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category.
(3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category.
The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.
The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.
Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period. Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.
Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period. Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Second Unit Oua;;rter uate A. Fission and activation products I. Total release (not including tritium, gases, alpha) Ci 4.78E-3 3.58E-3 1.90E+1 2. Average diluted concentration during period 4Ci/ml 9.62E-12 5.72E-12 3. Percent of applicable limit % MPC 1.36E-5 1.10E-5 4. Percent Effluent Concentration Limit % ECL 1.29E-4 1.06E-4 B. Tritium 1. Total release Ci 1.02E+2 8.34E+1 1.90E+1 2. Average diluted concentration during period 4Ci/ml 2.05E-7 1.33E-7 3. Percent of applicable limit 0 MPC 6.84E-3 4.45E-3 4. Percent Effluent Concentration Limit % ECL 2.05E-2 1.33E-2 C. Dissolved and entrained gases 1. Total release Ci 4.51E-1 1.49E-2 1.90E+1 2. Average diluted concentration during period 4Ci/ml 9.07E-10 2.38E-11 3. Percent of applicable limit % MPC 4.53E-4 1.19E-5 4. Percent Effluent Concentration Limit % ECL 4.53E-4 1.19E-5 D. Gross alpha radioactivity  
2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Second Unit Oua;;rter uate A. Fission and activation products I. Total release (not including tritium, gases, alpha) Ci 4.78E-3 3.58E-3 1.90E+1 2. Average diluted concentration during period 4Ci/ml 9.62E-12 5.72E-12 3. Percent of applicable limit % MPC 1.36E-5 1.10E-5 4. Percent Effluent Concentration Limit % ECL 1.29E-4 1.06E-4 B. Tritium 1. Total release Ci 1.02E+2 8.34E+1 1.90E+1 2. Average diluted concentration during period 4Ci/ml 2.05E-7 1.33E-7 3. Percent of applicable limit 0 MPC 6.84E-3 4.45E-3 4. Percent Effluent Concentration Limit % ECL 2.05E-2 1.33E-2 C. Dissolved and entrained gases 1. Total release Ci 4.51E-1 1.49E-2 1.90E+1 2. Average diluted concentration during period 4Ci/ml 9.07E-10 2.38E-11 3. Percent of applicable limit % MPC 4.53E-4 1.19E-5 4. Percent Effluent Concentration Limit % ECL 4.53E-4 1.19E-5 D. Gross alpha radioactivity
: 1. Total release Ci 1.39E-5 <LLD 5.0OE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 7.56E+7 9.02E+7 5.OOE+O F. Volume of dilution water used during period liters 4.97E+11 6.25E+11 5.OOE+O Estimated Total ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 1. Total release Ci 1.39E-5 <LLD 5.0OE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 7.56E+7 9.02E+7 5.OOE+O F. Volume of dilution water used during period liters 4.97E+11 6.25E+11 5.OOE+O Estimated Total ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
2 and 3 TABLE 2A (Continued)
2 and 3 TABLE 2A (Continued)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Estimated Third Fourth Total Quarter Quarter Error, %A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 2.62E-3 5.01E-3 1.90E+1 2. Average diluted concentration during period uCi/ml 3.41E-12 6.77E-12 3. Percent of applicable limit % MPC 7.05E-6 1.25E-5 4. Percent Effluent Concentration Limit % ECL 7.64E-5 1.29E-4] B. Tritium 1. Total release Ci 1.42E+2 6.31E+2 1.90E+1 2. Average diluted concentration during period uCi/ml 1.85E-7 8.52E-7 3. Percent of applicable limit % MPC 6.16E-3 2.84E-2 4. Percent Effluent Concentration Limit % ECL 1.85E-2 8.52E-2 C. Dissolved and entrained gases 1. Total release Ci 1.46E-2 1.17E-1 1.90E+1 2. Average diluted concentration during period MCi/ml 1.90E-11 1.58E-10 3. Percent of applicable limit % MPC 9.51E-6 7.90E-5 4. Percent Effluent Concentration Limit % ECL 9.51E-6 7.90E-5 D. Gross alpha radioactivity  
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Estimated Third Fourth Total Quarter Quarter Error, %A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 2.62E-3 5.01E-3 1.90E+1 2. Average diluted concentration during period uCi/ml 3.41E-12 6.77E-12 3. Percent of applicable limit % MPC 7.05E-6 1.25E-5 4. Percent Effluent Concentration Limit % ECL 7.64E-5 1.29E-4] B. Tritium 1. Total release Ci 1.42E+2 6.31E+2 1.90E+1 2. Average diluted concentration during period uCi/ml 1.85E-7 8.52E-7 3. Percent of applicable limit % MPC 6.16E-3 2.84E-2 4. Percent Effluent Concentration Limit % ECL 1.85E-2 8.52E-2 C. Dissolved and entrained gases 1. Total release Ci 1.46E-2 1.17E-1 1.90E+1 2. Average diluted concentration during period MCi/ml 1.90E-11 1.58E-10 3. Percent of applicable limit % MPC 9.51E-6 7.90E-5 4. Percent Effluent Concentration Limit % ECL 9.51E-6 7.90E-5 D. Gross alpha radioactivity
: 1. Total release Ci 1.29E-5 1.21E-4 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 8.58E+7 1.09E+8 5.OOE+O F. Volume of dilution water used during period liters 7.68E+11 17.41E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 1. Total release Ci 1.29E-5 1.21E-4 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 8.58E+7 1.09E+8 5.OOE+O F. Volume of dilution water used during period liters 7.68E+11 17.41E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE LLD Lower Limit of Detection; see Table 2C.-50-First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 1.52E-4 5.01E-5 <LLD <LLD chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci 1.52E-4 5.01E-5 <LLD <LLD 2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE LLD Lower Limit of Detection; see Table 2C.-50-First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 1.52E-4 5.01E-5 <LLD <LLD chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci 1.52E-4 5.01E-5 <LLD <LLD 2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)Section H. 1OCFR50 Appendix I Requirments TABLE 1 (1998) Dose * (millirems)
2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)Section H. 1OCFR50 Appendix I Requirments TABLE 1 (1998) Dose * (millirems)
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS  
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
: 11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 1.58E-2 1.42E-3 2.02E-3 5.71E-4 1.88E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 6.64E-3 1.42E-3 2.44E-3 5.38E-3 1.46E-2 Beta 21) 22) 23) 24) 25) 1.23E-2 3.97E-3 6.92E-3 7.96E-3 2.95E-2
: 11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 1.58E-2 1.42E-3 2.02E-3 5.71E-4 1.88E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 6.64E-3 1.42E-3 2.44E-3 5.38E-3 1.46E-2 Beta 21) 22) 23) 24) 25) 1.23E-2 3.97E-3 6.92E-3 7.96E-3 2.95E-2
* The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).
* The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).
Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-25 These values were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 12. The maximum organ dose was to a child's thyroid and was located in the NNW sector. 13-15. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-25 These values were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 12. The maximum organ dose was to a child's thyroid and was located in the NNW sector. 13-15. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
: 17. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
: 17. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
18-20. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
18-20. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
: 21. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
: 21. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
: 22. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
: 22. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
23-25. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
23-25. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
TABLE 2 (1998) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, lodines, 1.05E-1 9.48E-3 1.35E-2 3.80E-3 6.25E-2 and Particulates NOBLE GASES ** Gamma 6.64E-2 1.42E-2 2.44E-2 5.38E-2 7.30E-2 Beta 6.13E-2 1.98E-2 3.46E-2 3.98E-2 7.37E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
TABLE 2 (1998) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, lodines, 1.05E-1 9.48E-3 1.35E-2 3.80E-3 6.25E-2 and Particulates NOBLE GASES ** Gamma 6.64E-2 1.42E-2 2.44E-2 5.38E-2 7.30E-2 Beta 6.13E-2 1.98E-2 3.46E-2 3.98E-2 7.37E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. 1OCFR50 Appendix I Requirments TABLE 1 (1999) Dose * (millirems)
2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. 1OCFR50 Appendix I Requirments TABLE 1 (1999) Dose * (millirems)
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS  
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
: 11) 12) 13) 14) 15) Tritium, lodines, and Particulates 1.35E-2 3.84E-3 8.62E-4 6.78E-3 1.94E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 5.59E-3 1.92E-3 1.06E-3 2.60E-3 1.04E-2 Beta 21) 22) 23) 24) 25) 1.07E-2 1.80E-3 1.16E-3 3.30E-3 1.67E-2 The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s). Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-25 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 12-15. The maximum organ dose was to a child's thyroid and was located in the NNW sector. 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
: 11) 12) 13) 14) 15) Tritium, lodines, and Particulates 1.35E-2 3.84E-3 8.62E-4 6.78E-3 1.94E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 5.59E-3 1.92E-3 1.06E-3 2.60E-3 1.04E-2 Beta 21) 22) 23) 24) 25) 1.07E-2 1.80E-3 1.16E-3 3.30E-3 1.67E-2 The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s). Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-25 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 12-15. The maximum organ dose was to a child's thyroid and was located in the NNW sector. 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
: 17. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
: 17. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
: 18. The maximum air dose for gamma radiation was located in the ESE sector, at the exclusion area boundary.
: 18. The maximum air dose for gamma radiation was located in the ESE sector, at the exclusion area boundary.
: 19. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
: 19. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
: 20. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
: 20. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
: 21. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
: 21. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
: 22. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
: 22. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
23-25. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
23-25. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
TABLE 2 (1999) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 9.03E-2 2.56E-2 5.74E-3 4.52E-2 6.45E-2 NOBLE GASES Gamma 5.59E-2 1.92E-2 1.06E-2 2.60E-2 5.18E-2 Beta 5.35E-2 9.02E-3 5.81E-3 1.65E-2 4.18E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
TABLE 2 (1999) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 9.03E-2 2.56E-2 5.74E-3 4.52E-2 6.45E-2 NOBLE GASES Gamma 5.59E-2 1.92E-2 1.06E-2 2.60E-2 5.18E-2 Beta 5.35E-2 9.02E-3 5.81E-3 1.65E-2 4.18E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 SECTION D.PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)Section H. 1OCFRSO Appendix I Requirements TABLE 1 (2000) Dose * (millirems)
2 and 3 SECTION D.PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)Section H. 1OCFRSO Appendix I Requirements TABLE 1 (2000) Dose * (millirems)
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS  
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
: 11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 6.13E-3 2.97E-3 3.66E-3 3.94E-3 1.58E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 1.51E-3 3.45E-3 1.82E-3 1.94E-3 7.18E-3 Beta 21) 22) 23) 24) 25) 1.39E-3 3.26E-3 1.56E-3 2.12E-3 8.08E-3 The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s), Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose.11-25 11-12. 13. 14. 15. 16. 17. 18-20. 21. 22-23. 23. 24. 25.These were calculated using the assumptions of USNRC Regulatory Guide 1.109. The maximum organ dose was to a child's thyroid and was located in the NNW sector. The maximum organ dose was to a child's thyroid and was located in the E sector. The maximum organ dose was to a child's thyroid and was located in the ESE sector. The maximum organ dose was to a child's thyroid and was located in the NNW sector. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
: 11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 6.13E-3 2.97E-3 3.66E-3 3.94E-3 1.58E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 1.51E-3 3.45E-3 1.82E-3 1.94E-3 7.18E-3 Beta 21) 22) 23) 24) 25) 1.39E-3 3.26E-3 1.56E-3 2.12E-3 8.08E-3 The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s), Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose.11-25 11-12. 13. 14. 15. 16. 17. 18-20. 21. 22-23. 23. 24. 25.These were calculated using the assumptions of USNRC Regulatory Guide 1.109. The maximum organ dose was to a child's thyroid and was located in the NNW sector. The maximum organ dose was to a child's thyroid and was located in the E sector. The maximum organ dose was to a child's thyroid and was located in the ESE sector. The maximum organ dose was to a child's thyroid and was located in the NNW sector. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
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TABLE 2 (2000)Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 4.09E-2 1.98E-2 2.44E-2 2.63E-2 5.27E-2 NOBLE GASES Gamma 1.51E-2 3.45E-2 1.82E-2 1.94E-2 3.59E-2 Beta 6.95E-3 1.63E-2 7.79E-3 1.06E-2 2.02E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
TABLE 2 (2000)Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 4.09E-2 1.98E-2 2.44E-2 2.63E-2 5.27E-2 NOBLE GASES Gamma 1.51E-2 3.45E-2 1.82E-2 1.94E-2 3.59E-2 Beta 6.95E-3 1.63E-2 7.79E-3 1.06E-2 2.02E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated 12 month total error 1. Type of waste Unit period (%) .a. Spent resins, filter sludges, m 3  N/A evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3  1.29E+1 compactable and non-compactable*
2 and 3 SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated 12 month total error 1. Type of waste Unit period (%) .a. Spent resins, filter sludges, m 3  N/A evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3  1.29E+1 compactable and non-compactable*
Ci 2.30E-2 3.OOE+1 c. Irradiated components, control m 3  N/A rods Ci N/A N/A d. Other m 3  N/A Ci N/A N/A Note: Total curie content estimated.
Ci 2.30E-2 3.OOE+1 c. Irradiated components, control m 3  N/A rods Ci N/A N/A d. Other m 3  N/A Ci N/A N/A Note: Total curie content estimated.
(*) Material packaged in strong, tight containers of various sizes. N/A No shipment made.
(*) Material packaged in strong, tight containers of various sizes. N/A No shipment made.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
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2 and 3 TABLE I The numbered footnotes below briefly explain how each the organ and the predominant pathway(s).
2 and 3 TABLE I The numbered footnotes below briefly explain how each the organ and the predominant pathway(s).
Noble gas doses due to airborne effluent are in units 1. This value was calculated using the methodology of the 2. This value was calculated using the methodology of the 3. This value was calculated using the methodology of the 4. This value was calculated using the methodology of the 5. This value was calculated using the methodology of the maximum dose was calculated, including of mrad, reflecting the air dose. ODCM. ODCM. ODCM. ODCM. ODCM.-70-Dose * (millirems)
Noble gas doses due to airborne effluent are in units 1. This value was calculated using the methodology of the 2. This value was calculated using the methodology of the 3. This value was calculated using the methodology of the 4. This value was calculated using the methodology of the 5. This value was calculated using the methodology of the maximum dose was calculated, including of mrad, reflecting the air dose. ODCM. ODCM. ODCM. ODCM. ODCM.-70-Dose * (millirems)
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS I) 2) 3) 4) 5) Whole Body 2.68E-4 1.90E-4 2.68E-4 1.11E-3 1.83E-3 6) 7) 8) 9) 10) Organ 7.07E-4 2.82E-4 3.01E-4 1.25E-3 2.54E-3 AIRBORNE EFFLUENTS  
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS I) 2) 3) 4) 5) Whole Body 2.68E-4 1.90E-4 2.68E-4 1.11E-3 1.83E-3 6) 7) 8) 9) 10) Organ 7.07E-4 2.82E-4 3.01E-4 1.25E-3 2.54E-3 AIRBORNE EFFLUENTS
: 11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 9.26E-3 3.09E-3 1.39E-3 7.99E-3 1.97E-2 NOBLE GASES 16) 17) 18) 19) 20) Gamma 2.43E-3 7.19E-4 1.73E-3 2.12E-3 6.18E-3 21) 22) 23) 24) 25) Beta 2.88E-3 6.13E-4 1.28E-3 2.95E-3 7.05E-3 26) 27) 28) 29) 30) DIRECT RADIATION 9.39E-2 1.24E-1 6.86E-2 1.11E-1 3.53E-1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 9.26E-3 3.09E-3 1.39E-3 7.99E-3 1.97E-2 NOBLE GASES 16) 17) 18) 19) 20) Gamma 2.43E-3 7.19E-4 1.73E-3 2.12E-3 6.18E-3 21) 22) 23) 24) 25) Beta 2.88E-3 6.13E-4 1.28E-3 2.95E-3 7.05E-3 26) 27) 28) 29) 30) DIRECT RADIATION 9.39E-2 1.24E-1 6.86E-2 1.11E-1 3.53E-1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
2 and 3 6. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
2 and 3 6. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 7. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 7. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 8. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 8. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 9. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 9. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 10. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 10. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 11. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 12. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 13. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 14. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 15. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109.received the maximum dose received the maximum dose received the maximum dose received the maximum dose received the maximum dose the NNW sector. This was the NNW sector. This was the NNW sector. This was the ESE sector. This was the NNW sector. This was 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 17. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 18. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 19. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 20. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 21. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 22. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 23. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 24. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
: 11. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 12. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 13. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 14. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 15. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109.received the maximum dose received the maximum dose received the maximum dose received the maximum dose received the maximum dose the NNW sector. This was the NNW sector. This was the NNW sector. This was the ESE sector. This was the NNW sector. This was 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 17. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 18. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 19. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 20. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 21. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 22. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 23. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 24. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 28, 2001, Revision 36 to the Units 2/3 Offsite Dose Calculation Manual was adopted and published.
2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 28, 2001, Revision 36 to the Units 2/3 Offsite Dose Calculation Manual was adopted and published.
This change incorporated the following:  
This change incorporated the following:
: 1. Update to SYF flowrates, 2. Addition of liquid composite samplers to Section 4, 3. Change to 6.3.1.a to require ODCM updates be made in accordance with applicable regulations rather than IOCFR50.59, {due to changes in the 10CFR50.59 program} 4. Deleted the Investigative Report definition, and 5. Changes related to the Land Use Census update. Safety Evaluations were provided for items 2 and 3. The requirement for an Investigative Report was added to the ODCM at the time that the RETS were transferred from the Technical Specifications.
: 1. Update to SYF flowrates, 2. Addition of liquid composite samplers to Section 4, 3. Change to 6.3.1.a to require ODCM updates be made in accordance with applicable regulations rather than IOCFR50.59, {due to changes in the 10CFR50.59 program} 4. Deleted the Investigative Report definition, and 5. Changes related to the Land Use Census update. Safety Evaluations were provided for items 2 and 3. The requirement for an Investigative Report was added to the ODCM at the time that the RETS were transferred from the Technical Specifications.
There existed a need to document each occurrence of failure to meet Surveillance Requirements and/or Action Statements related to the ODCM. The ODCM will now require performance of an evaluation based on the significance of the event in accordance with the site Corrective Action Program.
There existed a need to document each occurrence of failure to meet Surveillance Requirements and/or Action Statements related to the ODCM. The ODCM will now require performance of an evaluation based on the significance of the event in accordance with the site Corrective Action Program.
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2 and 3 CONCLUSIONS Gaseous releases totaled 1.68E+2 curies of which noble gases were 8.68E+1 curies, iodines were 4.56E-2 curies, particulates were 1.77E-3 curies, and tritium was 8.08E+1 curies. The radiation doses from gaseous releases were: (a) gamma air dose: 6.18E-3 mrad at the site boundary, (b) beta air dose: 7.05E-3 mrad at the site boundary, (c) organ dose: 1.96E-2 mrem at the nearest receptor.
2 and 3 CONCLUSIONS Gaseous releases totaled 1.68E+2 curies of which noble gases were 8.68E+1 curies, iodines were 4.56E-2 curies, particulates were 1.77E-3 curies, and tritium was 8.08E+1 curies. The radiation doses from gaseous releases were: (a) gamma air dose: 6.18E-3 mrad at the site boundary, (b) beta air dose: 7.05E-3 mrad at the site boundary, (c) organ dose: 1.96E-2 mrem at the nearest receptor.
Liquid releases totaled 9.59E+2 curies of which particulates and iodines were 1.60E-2 curies, tritium was 9.58E+2 curies, and noble gases were 5.98E-1 curies. The radiation doses from liquid releases were: (a) total body: 1.83E-3 mrem, (b) limiting organ: 2.54E-3 mrem. The radioactive releases and resulting doses generated from Units 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.
Liquid releases totaled 9.59E+2 curies of which particulates and iodines were 1.60E-2 curies, tritium was 9.58E+2 curies, and noble gases were 5.98E-1 curies. The radiation doses from liquid releases were: (a) total body: 1.83E-3 mrem, (b) limiting organ: 2.54E-3 mrem. The radioactive releases and resulting doses generated from Units 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.
COMMON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) COMMON COMMON RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated  
COMMON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) COMMON COMMON RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated
: 1. Type of waste Unit 12 month period total error (%) a. Spent resins, filter m3 N/A sludges, evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3  1.19E+1 compactable and non compactable
: 1. Type of waste Unit 12 month period total error (%) a. Spent resins, filter m3 N/A sludges, evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3  1.19E+1 compactable and non compactable
* Ci 9.OOE-3 3.OOE+1 c. Irradiated components, m 3  N/A control rods Ci N/A N/A m 3  N/A d. Other (filters)
* Ci 9.OOE-3 3.OOE+1 c. Irradiated components, m 3  N/A control rods Ci N/A N/A m 3  N/A d. Other (filters)
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==REFERENCES:==
==REFERENCES:==
: 1. Unit 1 Technical Specifications, section D6.13.2.
: 1. Unit 1 Technical Specifications, section D6.13.2.
: 2. Units 2 and 3 Licensee Controlled Specifications, Section 5.0.103.2.2.
: 2. Units 2 and 3 Licensee Controlled Specifications, Section 5.0.103.2.2.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON D. CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 (Continued)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON D. CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 (Continued)
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==SUBJECT:==
==SUBJECT:==
Process Control Program (PCP) Procedure Revision Health Physics is issuing a comprehensive revision of S0123-VII-8.5.1, Process Control Program. The purpose of this memorandum is to inform you, as required by procedure, of changes made to the PCP and their bases. Revision 7 of the PCP procedure contains changes that are only administrative in nature. Changes principally include: 1. A restatement of the procedure objective to more concisely link general objectives to specific references.
Process Control Program (PCP) Procedure Revision Health Physics is issuing a comprehensive revision of S0123-VII-8.5.1, Process Control Program. The purpose of this memorandum is to inform you, as required by procedure, of changes made to the PCP and their bases. Revision 7 of the PCP procedure contains changes that are only administrative in nature. Changes principally include: 1. A restatement of the procedure objective to more concisely link general objectives to specific references.
: 2. Updated and expanded references, including the Unit 1 DSAR. 3. Reorganized and restated procedure steps to more clearly link requirements to referenceg.
: 2. Updated and expanded references, including the Unit 1 DSAR. 3. Reorganized and restated procedure steps to more clearly link requirements to referenceg.
: 4. Revised statements of administrative controls that quote, rather than paraphrase, requirements imposed by the TQAM, LCSs, etc. 5. Deletion of record requirements duplicated in other Health Physics procedures and not required to meet PCP objectives.
: 4. Revised statements of administrative controls that quote, rather than paraphrase, requirements imposed by the TQAM, LCSs, etc. 5. Deletion of record requirements duplicated in other Health Physics procedures and not required to meet PCP objectives.
The changes made to the PCP procedure are justified as administrative in nature. The core PCP objective, ensuring all solid radioactive waste processing conform to form, stability, and free-standing water requirements, remains intact. With the core requirements of the procedure unchanged, overall conformance of SONGS solid radioactive waste products with applicable requirements is maintained.
The changes made to the PCP procedure are justified as administrative in nature. The core PCP objective, ensuring all solid radioactive waste processing conform to form, stability, and free-standing water requirements, remains intact. With the core requirements of the procedure unchanged, overall conformance of SONGS solid radioactive waste products with applicable requirements is maintained.

Revision as of 07:34, 14 July 2019

Annual Radioactive Effluent Release Report - 2001, for San Onofre Nuclear Generating Station, Units 1, 2, and 3
ML021160114
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 04/23/2002
From: Scherer A
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I SOUTHERN CALIFORNIA EDISON An EDISON INTERNATIONAL"' A Edward Scherer Manager of Nuclear Oversight and Regulatory Affairs April 23, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Docket Nos. 50-206, 50-361 and 50-362 Annual Radioactive Effluent Release Report -2001 San Onofre Nuclear Generating Station, Units 1, 2 and 3 Gentlemen:

This letter provides the Annual Radioactive Effluent Release Report (ARERR) for 2001. The ARERR is required to be submitted by 10 CFR 50.36a, Unit 1 Technical Specification D6.9.1.4, and Units 2 and 3 Technical Specification 5.7.1.3. Also enclosed are Revision 18 to the Unit 1 and Revision 36 to Units 2/3 Offsite Dose Calculation Manuals (ODCMs).

If you require additional information, please contact me or Mr. Clay Williams at (949) 368-6707.

Sincerely, Enclosures cc: E. W. Merschoff, Regional Administrator, NRC Region IV D. G. Holland, NRC Project Manager, San Onofre Unit 1 A. B. Wang, NRC Project Manager, San Onofre Units 2, and 3 C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 & 3 P. O. Box 128 San Clemente, CA 92674-0128 949-368-7501 Fax 949-368-6085

/Yoo SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2001 January -December SOUTHERN CALIFORNIA EDISON An VIlSOA \ I 7 R 17I 10, I/,'" CUmlpan PREFACE San Onofre Nuclear Generating Station is located next to San Onofre State Beach, adjoining Camp Pendleton Marine Corps Base, in San Diego County, 64 miles south of Los Angeles, California.

There are two operating pressurized water reactors with a total rated capacity of 2254 net megawatts electrical.

Unit 1, rated at 410 net megawatts electrical, was supplied by Westinghouse Electric Company and began commercial operation on January 1, 1968. The unit was permanently shutdown on November 30, 1992. It is owned by Southern California Edison (80%) and San Diego Gas and Electric (20%). Unit 2 and Unit 3 were supplied by Combustion Engineering, Inc., with turbine generators supplied by G.E.C. Turbine Generators, Ltd., of England. The units began commercial operation on August 18, 1983, and April 1, 1984, respectively and are rated at 1127 net megawatts electrical each. The twin units are owned by Southern California Edison (75.05%), San Diego Gas and Electric (20%), City of Anaheim (3.16%), and the City of Riverside (1.79%).

R 0. Box 128 San Clementc, CA 92674-0128 Cl) m 0 a z TABLE OF CONTENTS SECTION A SECTION B SECTION C SECTION D SECTION E SECTION F SECTION G SECTION H SECTION I SECTION J SECTION K-INTRODUCTION

................. -GASEOUS EFFLUENTS

...... ................

-LIQUID EFFLUENTS

...............

-PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADl -RADWASTE SHIPMENTS

..............

-APPLICABLE LIMITS ...... ................

-ESTIMATION OF ERROR ..... ...............

-10 CFR 50 APPENDIX I REQUIREMENTS

..........

-CHANGES TO OFFSITE DOSE CALCULATION MANUAL -CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS -MISCELLANEOUS

........ .................

..........1 ..........2 ..........8 DENDUM .... ....... 17 S. ........ .21 S. ........ .24 S. ........ .26 S. ........ .27 S. ........ .31 S. ........ .32 S. ........ .33 S.. .......... .35 SECTION L -S.O.N.G.S.

1 CONCLUSIONS

...-ii-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) January -December SFfTTMN A INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Unit 1. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:

1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release 2. Percent of Applicable Limits 3. Estimated Total Percent Error 4. Lower Limit of Detection Concentrations
5. Batch Release Summaries
6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments
8. 10 CFR 50 Appendix I Requirements
9. Changes to Offsite Dose Calculation Manual-1-.......................

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 SECTION B. GASEOUS EFFLUENTS Table IA, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories:

fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.

Listed for each of the four categories are: (1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total error In addition, the particulate category lists the gross alpha radioactivity released for each quarter.

The methodology used to calculate the percent of Applicable Limit is presented in Section F of this report. The methodology used in Table 1A to calculate the estimated total error is presented in Section G of this report. Table IB, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Unit 1 does not conduct elevated releases.

Table IC, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in three categories:

fission gases, iodines, and particulates.

The total radioactivity for each radionuclide is listed for each quarterly period by "continuous" mode of release.

Plant stack releases are considered to be "continuous" releases.

As of 8/4/93, "batch" mode releases are no longer conducted because of the permanent shutdown of the reactor.

Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC for continuous mode releases only. Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period. Table IF, "Gaseous Effluents-Batch Release Summary," has been deleted. "Batch" mode releases are no longer conducted as of 8/4/93, due to the permanent shutdown of the reactor.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter A. Fission and activation gases 1. Total release Ci <LLD <LLD 3.OOE+l 2. Average release rate for period 4Ci/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O B. Iodines 1. Total iodine-131 Ci <LLD <LLD 1.90E+1 2. Average release rate for period uCi/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O C. Particulates

1. Particulates with half-lives

>8 days Ci <LLD <LLD 1.60E+1 2. Average release rate for period gCi/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O 5. Gross alpha activity Ci 1.62E-7 5.43E-8 5.OOE+1 D. Tritium 1. Total release Ci 2.14E-1 3.51E-1 2.50E+1 2. Average release rate for period uCi/sec 2.75E-2 4.46E-2 3. Percent of applicable limit % MPC 1.79E-4 2.90E-4 4. Percent Effluent Concentration Limit % ECL 3.58E-4 5.80E-4-3-Second Quarter Estimated Total Error, %

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

I TABLE 1A (Continued)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, A. Fission and activation gases 1. Total release Ci <LLD <LLD 3.OOE+1 2. Average release rate for period pLCi/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O B. Iodines (1) 1. Total iodine-131 Ci <LLD <LLD 1.90E+1 2. Average release rate for period MCi/sec O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O C. Particulates (1) 1. Particulates with half-lives

>8 days Ci 1.63E-6 1.21E-5 1.60E+1 2. Average release rate for period uCi/sec 2.05E-7 1.52E-6 3. Percent of applicable limit % MPC 8.89E-7 6.60E-6 4. Percent Effluent Concentration Limit % ECL 5.33E-6 3.96E-5 5. Gross alpha activity Ci 4.95E-8 6.01E-8 5.OOE+1 D. Tritium 1. Total release Ci 8.19E-1 1.36E+O 2.50E+1 2. Average release rate for period yCi/sec 1.03E-1 1.71E-1 3. Percent of applicable limit % MPC 6.70E-4 1.11E-3 4. Percent Effluent Concentration Limit % ECL 1.34E-3 2.22E-3 __-4-(1) On 8/27/01, plant vent stack particulate and iodine samples were not collected for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. The weekly sample had very low levels of activity with minimal dose impact to the public. Prior and subsequent samples were <LLDo. This event is documented in AR 010801535.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation gases krypton-85 Ci <LLD <LLD <LLD <LLD krypton-85m Ci <LLD <LLD <LLD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci <LLD <LLD <LLD <LLD xenon-133m Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD 2. lodines iodine-131 Ci <LLD <LLD <LLD <LLD iodine-133 Ci <LLD <LLD <LLD <LLD iodine-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD 3. Particulates barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci <LLD <LLD <LLD 7.66E-11 cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD 1.63E-6 1.21E-5 iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 1D. NOTE: Due to the permanent shutdown of S.O.N.G.S.

1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 TABLE ID GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (,uCi/cc)

1. Fission and activation gases krypton-85 2.10E-5 krypton-85m 5.OOE-8 krypton-87 2.60E-7 krypton-88 1.80E-7 xenon-133 1.30E-7 xenon-133m 4.10E-7 xenon-135 5.30E-8 xenon-135m 2.OOE-6 xenon- 138 3.50E-6 2. lodines iodine-131 2.90E-13 iodine-133 2.80E-12 iodine-135 1.90E-1O 3. Particulates barium-140 5.90E-13 cerium-141 6.60E-14 cerium-144 2.60E-13 cesium-134 1.70E-13 cesium-137 1.40E-13 cobalt-58 1.50E-13 cobal t-60 2.40E-13 iron-59 3.80E-13 lanthanum-140 1.20E-12 manganese-54 1.50E-13 molybdenum-99 7.90E-14 strontium-89 1.OOE-14 strontium-90 1.OOE-15 zinc-65 4.OOE-13 NOTE: Due to the permanent shutdown of S.O.N.G.S.

1, "BATCH MODE" longer conducted.

releases are no

-- -- -- --- --U L ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas 1. Gamma Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O 2. Percent Applicable Limit O.OOE+O O.OOE+O O.OOE+O O.OOE+O 3. Beta Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O 4. Percent Applicable Limit % O.OOE+O O.OOE+O O.OOE+O O.OOE+O B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem 8.01E-6 1.43E-5 4.36E-5 1.31E-4 2. Percent Applicable Limit % 1.07E-4 1.91E-4 5.82E-4 1.74E-3 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

NOTE: Due to the permanent shutdown of S.O.N.G.S.

1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

I SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories:

fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are: (1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists: (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)

(3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category.

The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.

Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period. Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Unit 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Second Unit Quarter Quarter Estimated Total Error, %A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 2.47E-7 3.11E-6 1.90E+1 2. Average diluted concentration during period gCi/ml 1.56E-13 1.93E-12 3. Percent of applicable limit % MPC 7.82E-7 9.66E-6 4. Percent Effluent Concentration Limit % ECL 1.56E-5 1.93E-4 B. Tritium I. Total release Ci 1.33E-2 5.23E-4 1.90E+1 2. Average diluted concentration during period ,uCi/ml 8.42E-9 3.25E-10 3. Percent of applicable limit % MPC 2.81E-4 1.08E-5 4. Percent Effluent Concentration Limit % ECL 8.42E-4 3.25E-5 C. Dissolved and entrained gases 1. Total release Ci <LLD <LLD 1.90E+1 2. Average diluted concentration during period MCi/ml O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 8.31E+6 1.16E+6 5.OOE+O F. Volume of dilution water used during period liters 1.58E+9 1.61E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 TABLE 2A (Continued)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, %A. Fission and activation products (1) 1. Total release (not including tritium, gases, alpha) Ci 3.37E-5 3.42E-3 1.90E+1 2. Average diluted concentration during period MCi/ml 2.03E-I1 1.89E-9 3. Percent of applicable limit % MPC 1.02E-4 1.67E-2 4. Percent Effluent Concentration Limit % ECL 2.03E-3 1.35E-1 B. Tritium 1. Total release Ci 1.48E-4 2.28E-0 1.90E+1 2. Average diluted concentration during period uCi/ml 8.92E-11 1.26E-6 3. Percent of applicable limit % MPC 2.97E-6 4.20E-2 4. Percent Effluent Concentration Limit % ECL 8.92E-6 1.26E-1 C. Dissolved and entrained gases 1. Total release Ci <LLD <LLD 1.90E+1 2. Average diluted concentration during period uCi/ml O.OOE+O O.OOE+O 3. Percent of applicable limit % MPC O.OOE+O O.OOE+O 4. Percent Effluent Concentration Limit % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity

1. Total release Ci <LLD 2.93E-5 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 6.88E+5 6.31E+6 5.OOE+O F. Volume of dilution water used during period liters 1.66E+9 1.81E+9 5.OOE+O-10-(1) The 10/29/01 grab samples for the Yard Drain Sump (YDS) and Reheater Pit Sump were collected but discarded prior to compositing.

The 10/23/01-10/29/01 composite for both sumps consisted of the two remaining grabs and were <LLD. The grab sample for the composite was not collected 12/28/01 for the YDS. The 12/25/01 12/31/01 composite was also <LLD. These events are documented in ARs 011001581 and 020100050.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD -<LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 2.47E-7 3.11E-6 3.37E-5 8.29E-6 chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zi nc-65 Ci <LLD <LLD <LLD <LLD zi rconi um-95 Ci <LLD <LLD <LLD <LLD Total for period Ci 2.47E-7 3.11E-6 3.37E-5 8.29E-6 2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 TABLE 2B (Continued)

LIQUID EFFLUENTS BATCH MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation products barium-140 Ci N/A N/A N/A <LLD cerium-141 Ci N/A N/A N/A <LLD cerium-144 Ci N/A N/A N/A <LLD cesium-134 Ci N/A N/A N/A 9.86E-5 cesium-137 Ci N/A N/A N/A 1.71E-3 chromium-51 Ci N/A N/A N/A <LLD cobalt-58 Ci N/A N/A N/A <LLD cobalt-60 Ci N/A N/A N/A 1.56E-3 iodine-131 Ci N/A N/A N/A <LLD iron-55 Ci N/A N/A N/A <LLD iron-59 Ci N/A N/A N/A <LLD lanthanum-140 Ci N/A N/A N/A <LLD manganese-54 Ci N/A N/A N/A <LLD molybdenum-99 Ci N/A N/A N/A <LLD niobium-95 Ci N/A N/A N/A <LLD strontium-89 Ci N/A N/A N/A <LLD strontium-90 Ci N/A N/A N/A 4.58E-5 technetium-99m Ci N/A N/A N/A <LLD zinc-65 Ci N/A N/A N/A <LLD zirconium-95 Ci N/A N/A N/A <LLD Total for period Ci N/A N/A N/A 3.42E-3 2. Dissolved and entrained gases xenon-133 Ci N/A N/A N/A <LLD xenon-135 Ci N/A N/A N/A <LLD Total for period Ci N/A N/A N/A <LLD N/A No releases conducted LLD Lower Limit of Detection; see Table 2C.

I_ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION-13-Radionuclides LLD (,uCi/cc)

1. Fission and activation products barium-140 3.90E-7 cerium-141 5.80E-8 cerium-144 2.30E-7 cesium-134 1.OOE-7 chromium-51 4.60E-7 cobalt-58 9.OOE-8 cobalt-60 1.30E-7 iodine-131 8.OOE-8 iron-55 I.OOE-6 iron-59 2.1OE-7 1anthanum-140 7.20E-7 manganese-54 8.90E-8 mol ybdenum-99 7.50E-8 niobium-95 9.10E-8 strontium-89 5.OOE-8 stronti um-90 I.OOE-8 techneti um-99m 7.70E-8 zinc-65 2.20E-7 zi rconium-95 1.60E-7 2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 TABLE 2C (Continued)

LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-14-Radionuclides LLD (/uCi/cc)

1. Fission and activation products barium-140 3.30E-7 cerium-141 5.30E-8 cerium-144 2.30E-7 chromi um-51 4.20E-7 cobalt-58 8.70E-8 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 1 anthanum-140 2.40E-7 manganese-54 8.80E-8 mol ybdenum-99 3.50E-8 ni obi um-95 8.50E-8 stronti um-89 5.OOE-8 techneti um-99m 3.60E-8 zinc-65 2.20E-7 zi rconi um-95 1.50E-7 2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 LIQUI[ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

I TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIOUID SITE BOL JNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. 1. Total body dose mrem 7.40E-5 3.33E-5 3.51E-4 1.51E-2 2. Percent Applicable Limit 4.93E-3 2.22E-3 2.34E-2 1.OIE+O B. I. Limiting organ dose mrem 7.54E-5 5.08E-5 5.36E-4 3.44E-2 2. Percent Applicable Limit % 1.51E-3 1.02E-3 1.07E-2 6.88E-1 3. Limiting organ for period Liver Liver Liver GI/LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

I TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period 1. Number of batch releases:

1 release 2. Total time period for batch releases:

1380 minutes 3. Maximum time period for a batch release: 1380 minutes 4. Average time period for a batch release: 1380 minutes 5. Minimum time period for a batch release: 1380 minutes 6. Average saltwater flow during batch releases:

6650 gpm ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM I. The fourth quarter 2000 values for composite Sr-89, Sr-90 and Fe-55 were incomplete due to data not available at report time. Information is presented below. All values were <LLD, and therefore, no other data tables as earlier reported were affected.

TABLE iC (2000) GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE Radionuclides Released Unit Fourth Quarter 3. Particulates strontium-89 Ci <LLD strontium-90 Ci <LLD Sr-89 LLD = 1.0OE-14 Sr-90 LLD = 1.00E-15 TABLE 2B (2000) LIQUID EFFLUENTS CONTINUOUS MODE Fe-55 LLD = 1.OOE-6 Sr-89 LLD = 5.OOE-8 Sr-90 LLD = 1.OOE-8-17-Radionuclides Released I Unit Fourth Quarter 1. Fission an activation products iron-55 Ci <LLD strontium-89 Ci <LLD strontium-90 Ci <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

I SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) 2. Dose calculations for Table 1 Airborne Effluents and Noble Gases of this report are performed using concurrent meteorological data. On 10/27/00, it was determined a conversion factor of 2 had incorrectly been applied to wind speeds collected from 07/27/98 to 12/31/99 subsequent to a hard drive failure. This event is documented in AR 001002318.

The dose data have been reprocessed for the years 1998 and 1999. In no case did the percent of the dose limit exceed 1%. The revised data are provided in the following tables.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

I SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. IOCFR50 Appendix I Requirements TABLE 1 (1998) Dose * (millirems)

SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS

11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 2.06E-4 O.OOE+O O.OOE+O 5.64E-4 7.70E-4 NOBLE GASES ** 16) 17) 18) .19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta 21) 22) 23) 24) 25) O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O
  • The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).

Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-15 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the NW sector. 12-13 There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. 14. The maximum organ dose was to a child's thyroid and was located in the NW sector. 15. The maximum organ dose was to a child's thyroid and was located in the NW sector. 16-20 There was no activity detected during any of these release periods, therefore the reported air dose for gamma radiation was O.OOE+O mrad. 21-25 There was no activity detected during any of the release periods, therefore the reported air dose for beta radiation was O.OOE+O mrad. TABLE 2 (1998) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 2.75E-3 O.OOE+O O.OOE+O 7.52E-3 5.13E-3 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O-19-i I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. 1OCFR50 Appendix I Requirements TABLE 1 (1999) Dose * (millirems)

SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS

11) 12) 13) 14) 15) Tritium, lodines, and Particulates O.OOE+O 1.03E-4 6.85E-5 7.07E-4 8.79E-4 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta 21) 22) 23) 24) 25) O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O
  • The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s). Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-15 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. 12. The maximum organ dose was to a child's thyroid and was located in the NW sector. 13. The maximum organ dose was to a child's thyroid and was located in the NW sector. 14. The maximum organ dose was to a child's thyroid and was located in the NW sector. 15. The maximum organ dose was to a child's thyroid and was located in the NW sector. 16-20 There was no activity detected during any of these release periods, therefore the reported air dose for gamma radiation was O.OOE+O mrad. 21-25 There was no activity detected during any of these release periods, therefore the reported air dose for beta radiation was O.OOE+O mrad. TABLE 2 (1999) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates O.OOE+O 1.38E-3 9.13E-4 9.43E-3 5.86E-3 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

I SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated 12 month total 1. Type of waste Unit period error (%) a. Spent resins, filter sludges, m 3 N/A evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3 2.52E+3 compactable and non-compactable

  • _________

Ci 1.29E+0- 3.00E+1 c. Irradiated components, control m 3 N/A rods Ci N/A N/A d. Other mn 3 N/A Ci N/A N/A NOTE: Total curie content estimated.

(*) Material packaged in strong, tight containers of various sizes. N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 2. Estimate of major nuclide composition (by type of waste) a. not applicable

_ N/A b. americium-241

% 4.37E-2 carbon-14

% 5.86E-1 cerium-144

_ 1.87E-2 cesium-134

% 1.50E+O cesium-137

% 1.24E+1 cobal t-60 % 4.19E+1 curium-242

% 3.72E-3 curium-243/244

% 1.04E-2 iron-55 % 2.92E+1 iron-59 % 7.22E-2 nickel-63

% 1.24E+1 niobium-94

__6.24E-2 ni obi um-95 1.39E-1 pl utoni um-238 5.24E-2 plutonium-239/240 1.94E-2 pl utoni um-241 _ _1.22E+O pl utoni um-242 __8.55E-3 stronti um-90 __1.77E-1 techneti um-99 __2.20E-3 tritium __1.07E-1 urani um-233/234 96 1.32E-4 zi rconium-95

__1.46E-1

c. not applicable

__N/A d. not applicable

__N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT S.O.N.G.S.

I Number of Shipments Mode of Transportation Destination 30

  • Hitman Trucking Company EnviroCare, UT Truck/Trailer 2 MHFLogistical Solutions EnviroCare, UT Truck/Trailer 96 MHFLogistical Solutions EnviroCare, UT Rail
  • SONGS maintains a contract with vendor (GTS) that provides volume reduction services.

These shipments were made from their processing facility.

The thirty shipments made from this facility included waste from other generators.

SCE's waste volume was a small fraction of the total waste volume of these shipments.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A-23-3. Solid Waste Disposition B.(2001)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 SECTION F. APPLICABLE LIMITS Gaseous Effluents

-Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, C.3, and D.3 of Table 1A, was calculated using the following equation:% Applicable Limit where: Rel Rate X/Q MPCelf where: Fj n MPC,& %ECL (Re] Rate) (X/O) (100) MPCeff total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, 4Ci/sec.

1.30E-5 sec/m 3; the annual average atmospheric dispersion defined in the Unit 1 ODCM. 1 n F. =1i MPC fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT. total number of radionuclides identified Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.-(Rel Rate) (X/0) (100) ECLeff where: Rel Rate X/Q 0 ECLeuf where: Fj n ECL, total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, yCi/sec.

1.30E-5 sec/m 3; the annual average atmospheric dispersion defined in the Unit 1 ODCM. 1 n F. M1 ECL i fractional abundance of the i th radionuclide obtained by dividing the activity (curies) for each radionuclide, C 1 , by the sum of all the isotopic activity, CT. total number of radionuclides identified Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 Liquid Effluents

-Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, and C.3 of Table 2A, were calculated using the following equations:

% Applicable Limit where: Dil Conc MPCeff where: F, n MPCi 0 % ECL (Dil Conc) (100) MPCeff total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, pCi/ml. I i MPC i fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C,, by the sum of all the isotopic activity, C,. total number of radionuclides identified Maximum Permissible Concentration (MPC) of the i t h radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.(Dil Conc) (100) ECLeff where: Dil Conc ECLeff where: F7 n ECLj total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, ACi/ml. 11 [CLI i~i ECL i fractional abundance of the i t" radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT. total number of radionuclides identified Effluent Concentration Limit (ECL) of the i t h radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made. Sources of error for gaseous effluents

-batch releases are: (1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for gaseous effluents

-continuous releases are: (1) fan flow rate (2) sampling (3) counting (4) calibration (5) differential pressure drop Sources of error for liquid effluents

-batch releases are: (1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for liquid effluents

-continuous releases are: (1) dilution flow rate (2) sampling (3) counting (4) calibration These sources of error are independent, and thus, the total error is calculated according to the following formula: Total Error r , + aYcte + w Y 3c+ 2Y where: G= Error associated with each component.

.1I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

1 SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table I in Section H presents the quarterly and annual maximum dose to an individual.

Six different categories are presented:

(1) Liquid Effluents

-Whole Body (2) Liquid Effluents

-Organ (3) Airborne Effluents

-Tritium, Iodines and Particulates (4) Noble Gases -Gamma (5) Noble Gases -Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; this data is also presented in Table 2D. Categories 3, 4, and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) software, Regulatory Guide 1.109 methodology, and concurrent meteorology.

Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters.

Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

For members of the public, per the ODCM, who may at times be within the site boundary', the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

For members of the public who traverse the site boundary via highway 1-5, the residency time shall be considered negligible and hence the dose "0". Table 2 in Section H presents the percent of Applicable Limits for each dose presented in Table 1. 1. ODCM Figures 2-1 & 2-2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

I TABLE 1* The numbered footnotes below briefly explain how each the organ and the predominant pathway(s).

    • Noble gas doses due to airborne effluent are in units 1. This value was calculated using the methodology of thi 2. This value was calculated using the methodology of thi 3. This value was calculated using the methodology of thi 4. This value was calculated using the methodology of thi 5. This value was calculated using the methodology of thi maximum dose was calculated, including of mrad, reflecting the air dose. e ODCM. e ODCM. e ODCM. e ODCM. e ODCM.-28-Dose * (millirems)

First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS

1) 2) 3) 4) 5) Whole Body 7.40E-5 3.33E-5 3.51E-4 1.51E-2 1.56E-2 6) 7) 8) 9) 10) Organ 7.54E-5 5.08E-5 5.36E-4 3.44E-2 3.45E-2 AIRBORNE EFFLUENTS
11) 12) 13) 14) 15) Tritium, lodines, and Particulates 7.17E-5 2.11E-4 5.65E-4 8.63E-4 1.71E-3 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O 21) 22) 23) 24) 25) Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O 26) 27) 28) 29) 30) DIRECT RADIATION 9.36E-2 1.24E-1 6.84E-2 1.11E-1 3.52E-1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

I 6. 7. 8. 9. 10. 11. 12. 13. 14. 15.calculated using the assumptions of USNRC Regulatory Guide 1.109.There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during gamma radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad. There was no activity detected during beta radiation was O.OOE+O mrad.the release period, therefore the the the the the the the the release release rel ease rel ease rel ease rel ease rel ease rel ease period, period, period, period, period, period, period, period, therefore therefore therefore therefore therefore therefore therefore therefore This value was calculated using the methodology of the ODCM; the liver primarily by the saltwater fish pathway.

This value was calculated using the methodology of the ODCM; the liver primarily by the saltwater fish pathway.

This value was calculated using the methodology of the ODCM; the liver primarily by the saltwater fish pathway.

This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.

This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.

The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. The maximum organ dose was to a child's thyroid and was located in-29-received the maximum dose received the maximum dose received the maximum dose received the maximum dose received the maximum dose the NW sector. This was the NW sector. This was the NW sector. This was the NW sector. This was the NW sector. This was the reported air dose for the reported air dose for the reported air dose for the reported air dose for the reported air dose for the reported air dose for the reported air dose for the reported air dose for the reported air dose for 16. 17. 18. 19. 20. 21. 22. 23. 24.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 25. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad. 26. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector. 27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector. 28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the WSW sector. 29. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the WSW sector. 30. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector. TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 4.93E-3 2.22E-3 2.34E-2 1.OIE+O 5.19E-1 Organ 1.51E-3 1.02E-3 1.07E-2 6.88E-1 3.45E-1 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 9.56E-4 2.82E-3 7.53E-3 1.15E-2 1.14E-2 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 SECTION I.CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 21, 2001, revision 18 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published.

Incorporated into this revision were: 1. Removal of Sewage Treatment Plant as an effluent pathway, 2. Change to 6.3.3.1.a to require ODCM updates be made in accordance with applicable regulations rather than 1OCFR50.59, {due to changes in the 10CFR50.59 program} 3. Updated note 6 to Table 4-1, concerning MGPI monitors, by removing "When turned over to station, the" as all of the monitors have been turned over, and 4. Changes related to the Land Use Census update. Safety evaluations were provided for items 1 and 2. Minor format changes, correction of typographical errors, and removal of previously blank pages have been made and are described in the attached List of Affected Pages. Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

None of the changes impact the accuracy or reliability of effluent dose or calculations.

The level of radioactive effluent control required by 40CFR190, 1OCFR5O.36a, and Appendix I to 1OCFR50 will be maintained.

setpoint IOCFR20, Throughout the document, change bars are marked in one of four ways as follows: A Addition D Deletion F Editorial/Format change R Revision The following is a complete list of the changes: PAGE CHANGE REASON TOC Renumbered pages as necessary based on changes in the body of the F ODCM. 1-3 Removed Sewage Treatment Plant from Table 1-1. D 2-21 Updated Controlling Location Factors per LUC update. R 2-22 Renumbered table page number due to deletion of one page. F 2-23 Renumbered table page number due to deletion of one page. F 2-24 Moved San Mateo Pt Homes from Sector P to Sector Q. Page D intentionally left blank. 2-25 Renumbered table page number due to addition of one page. F 2-26 Renumbered table page number due to addition of one page. F 2-27 Moved San Mateo Pt Homes from Sector P to Sector Q to reflect land A use update.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

I Section 2 Renumbered Section 2 pages from 2-28 on to reflect the addition of F pages 2-30 Renumbered table page number due to addition of one page. Was page F 2-29. 2-31 Added Outage Worker to Sector B A 4-6 Removed "When turned over to station, the" from note 6, as all MGPI R monitors have been turned over to station.

5-17 Removed Table 5-5 as sample location per AR #000400602.

R 5-24 Corrected mileage for PIC 57. R 6-3 Added word response to MGPI portion of Source Check definition.

Was R inadvertently omitted previously.

6-10 Changed "10CFR50.59" to "applicable regulations".

R SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Unit 1 Radioactive Waste Treatment Systems during the reporting period, January 1, 2001 to December 31, 2001.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 SECTION K. MISCELLANEOUS Yard Drain Sump Overflow The Unit I Yard Drain sump overflowed to the PMF Catch Basin due to heavy rainfall twice in 2001. Since there was no detectable activity in the grab samples taken during the overflows, there were no dose consequences as a result of these unplanned, unmonitored releases.

Estimated Estimated Start Stop Duration Activity Release Whole Body Estimated Organ Date/Time Date/Time (min) (kLCi/ml) (Curies) Dose (mrem) Dose (mrem) 01/11/01 @ 0310 01/11/01 @ 0321 11 <LLD 0.00E+0 O.OOE+O O.OOE+O 11/24/01 @ 1555 11/24/01 @ 1638 43 <LLD O.OOE+O 0.AOE+O O.OOE+O PVS Monitor SamDle Line Leak On 8/30/01 during a routine Channel Functional Test, the flexible line for R-1254 particulate and iodine sampling skid was found in a degraded condition.

Evaluation of sample results from the monitor and an auxiliary sampler during this time period revealed there was minimal or no in-leakage during normal operation.

Therefore there were no dose consequences to members of the public as a result of this event that is documented in AR 010801574.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2001 -December 31, 2001 S.O.N.G.S.

1-34-Monitor Inoperability Period Inoperability Cause Explanation R-1218 09/17/00 -05/19/01 Radmonitor upgrade Design change upgrade modification Liquid Radwaste design change installed a new instrument and Discharge Line connected to Plant Information Monitor Monitoring System (PIMS) in conjunction with relocation of the Control Room. R-2101 05/18/01 -08/16/01 Monitor failure Monitor exhibited spurious readings Yard Drain Sump alarms and intermittent inoperability.

Monitor Investigationidentified solar heating of a junction box as the cause. Housing was constructed to correct the problem that is documented in AR 010701251.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

I SECTION L.S.OQ.N.G.S.

1 CONCLUSIONS Gaseous releases totaled 2.75E+O curies of which noble gases were O.OOE+O curies, iodines were O.OOE+O curies, particulates were 1.37E-5 curies, and tritium was 2.75E+O curies. The radiation doses from gaseous releases were: (a) gamma air dose: O.OOE+O mrad at the site boundary, (b) beta air dose: O.OOE+O mrad at the site boundary, organ dose: 1.71E-3 mrem at the nearest receptor.

Liquid releases totaled 2.29E+O curies of which particulates and iodines were 3.46E-3 curies, tritium was 2.29E+O curies, and noble gases were O.OOE+O curies. The radiation doses from liquid releases were: (a) total body: 1.56E-2 mrem, (b) limiting organ: 3.45E-2 mrem. The radioactive releases and resulting doses generated from Unit 1 were below the Applicable Limits for both gaseous and liquid effluents. S.O.N.G.S.

I CONCLUSIONS Cl) z Cl) CL W.

TABLE OF CONTENTS SECTION A -INTRODUCTION

...........

-GASEOUS EFFLUENTS

.... ...........

-LIQUID EFFLUENTS

..........

-PREVIOUS RADIOACTIVE EFFLUENT RELEASE -RADWASTE SHIPMENTS

.........

-APPLICABLE LIMITS .... ...........

-ESTIMATION OF ERROR .............

-10 CFR 50 APPENDIX I REQUIREMENTS

.. -CHANGES TO OFFSITE DOSE CALCULATION M REPORT ADD SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION B C D E F G H I J K L S. ........ .37 S. ........ .47 ENDUM .... ....... 56 S. ........ .63 S. ........ .66 S. ........ .68 S. ........ .69 S. ........ .73 S. ........75 S. ........ .75 .......... .77-iii-S. .. .36 ANUAL-CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS -MISCELLANEOUS

...... ...................

-S.O.N.G.S.

2 and 3 CONCLUSIONS

........

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)January -December SECTION A. INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Units 2 and 3. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:

1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release 2. Percent of Applicable Limits 3. Estimated Total Percent Error 4. Lower Limit of Detection Concentrations
5. Batch Release Summaries
6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments
8. 10 CFR 50 Appendix I Requirements
9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories:

fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.

Listed for each of the four categories are: (1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total error In addition, the particulate category lists the gross alpha radioactivity released for each quarter.

The methodology used to calculate the percent of Applicable Limit is presented in Section F of this report. The methodology used in Table 1A to calculate the estimated total error is presented in Section G of this report. Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Units 2 and 3 do not conduct elevated releases.

Table 1C, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in three categories:

fission gases, iodines, and particulates.

The total radioactivity for each radionuclide is listed for each quarterly period by both "continuous" and "batch" modes of release.

Waste gas decay tank releases are considered to be "batch" releases.

Containment purges and plant stack releases are considered to be "continuous" releases.

Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and 1C. Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period. Table IF, "Gaseous Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter Estimated Second Total Quarter Error, %C. Fission and activation gases 1. Total release Ci 3.22E+1 8.98E+O 3.OOE+1 2. Average release rate for period 4Ci/sec 4.14E+O 1.15E+O 3. Percent of applicable limit % MPC 9.94E-3 4.15E-3 4. Percent Effluent Concentration Limit % ECL 1.89E-2 1.17E-2 D. Iodines 1. Total iodine-131 Ci 2.24E-3 1.77E-5 1.90E+1 2. Average release rate for period 4Ci/sec 2.88E-4 2.25E-6 3. Percent of applicable limit % MPC 1.38E-3 1.08E-5 4. Percent Effluent Concentration Limit % ECL 6.91E-4 5.40E-6 E. Particulates

1. Particulates with half-lives

>8 days Ci 1.37E-3 4.78E-5 1.60E+1 2. Average release rate for period uCi/sec 1.76E-4 6.08E-6 3. Percent of applicable limit % MPC 6.36E-5 5.64E-6 4. Percent Effluent Concentration Limit % ECL 1.52E-4 1.41E-5 5. Gross alpha activity Ci 7.66E-6 2.41E-6 5.OOE+1 F. Tritium 1. Total release Ci 2.08E+1 1.89E+1 2.50E+1 2. Average release rate for period kiCi/sec 2.67E+O 2.40E+O 3. Percent of applicable limit % MPC 6.42E-3 5.77E-3 4. Percent Effluent Concentration Limit % ECL 1.28E-2 1.15E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE 1A (Continued)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Quarter Quarter Error, %A. Fission and activation gases 1. Total release Ci 1.73E+1 2.84E+1 3.OOE+1 2. Average release rate for period f4Ci/sec 2.16E+O 3.57E+O 3. Percent of applicable limit % MPC 8.13E-3 9.11E-3 4. Percent Effluent Concentration Limit % ECL 2.32E-2 1.86E-2 B. Iodines 1. Total iodine-131 Ci 2.OOE-5 4.03E-4 1.90E+1 2. Average release rate for period yCi/sec 2.52E-6 5.07E-5 3. Percent of applicable limit % MPC 1.21E-5 2.43E-4 4. Percent Effluent Concentration Limit % ECL 6.04E-6 1.22E-4 C. Particulates

1. Particulates with half-lives

>8 days Ci 2.57E-4 9.21E-5 1.60E+1 2. Average release rate for period 4Ci/sec 3.23E-5 1.16E-5 3. Percent of applicable limit % MPC 3.03E-5 6.41E-6 4. Percent Effluent Concentration Limit % ECL 7.57E-5 1.91E-5 5. Gross alpha activity Ci 5.92E-6 7.03E-6 5.OOE+1 D. Tritium 1. Total release Ci 1.36E+1 2.76E+1 2.50E+1 2. Average release rate for period MCi/sec 1.71E+O 3.47E+O 3. Percent of applicable limit % MPC 4.11E-3 8.33E-3 4. Percent Effluent Concentration Limit % ECL 8.21E-3 1.67E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation gases argon-41 Ci 2.47E+O 1.76E+O 3.56E+O 2.56E+0 krypton-85 Ci 3.91E-2 <LLD <LLD 1.78E-1 krypton-85m Ci <LLD <LLD 6.47E-4 <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD 5.54E-4 <LLD xenon-131m Ci 2.92E-3 <LLD 1.22E-2 7.10E-2 xenon-133 Ci 2.86E+1 6.28E+O 1.32E+1 2.53E+1 xenon-133m Ci <LLD <LLD 4.85E-3 2.60E-1 xenon-135 Ci 4.58E-2 <LLD 3.34E-2 8.10E-2 xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci 3.12E+1 8.05E+O 1.68E+1 2.84E+I 2. Iodines iodine-131 Ci 2.24E-3 1.77E-5 2.OOE-5 4.03E-4 iodine-132 Ci 4.27E-2 1.03E-6 <LLD 4.61E-5 iodine-133 Ci 1.13E-4 1.76E-5 1.79E-5 4.72E-5 iodine-135 Ci <LLD <LLD <LLD 1.59E-5 Total for period Ci 4.50E-2 3.64E-5 3.80E-5 5.13E-4 LLD Lower Limit of Detection; see Table ID.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE IC (Continued)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter I Quarter Quarter 3. Particulates barium-140 Ci <LLD <LLD <LLD <LLD bromine-82 Ci 6.39E-5 2.75E-5 4.85E-5 7.66E-5 cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD 1.52E-7 cesium-137 Ci 1.99E-4 4.56E-5 2.49E-4 2.93E-5 chromium-51 Ci 8.36E-6 <LLD <LLD <LLD cobalt-58 Ci 1.13E-3 2.21E-6 7.84E-6 5.71E-5 cobalt-60 Ci 1.57E-5 <LLD <LLD 5.58E-6 iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 1.47E-5 <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 1.43E-6 <LLD <LLD <LLD sodium-24 Ci <LLD <LLD <LLD 4.93E-6 strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD 6.17E-7 zinc-65 Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table ID.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE IC (Continued)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE *First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation gases krypton-85 Ci 9.93E-1 9.34E-1 3.77E-1 <LLD krypton-85m Ci <LLD <LLD <LLD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci 2.03E-3 <LLD 7.54E-2 <LLD xenon-133m Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD 5.79E-4 <LLD xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci 9.95E-1 9.34E-1 4.53E-1 <LLD LLD Lower Limit of Detection; see Table ID.

  • Iodines and particulates are not analyzed prior to release via batch mode.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionucl ides LLD (/.tCi/cc)

1. Fission and activation gases krypton-85 2.1IOE-5 krypton-85m 5,OOE-8 krypton-87 2.60E-7 krypton-88 1.80E-7 xenon-131m 1.70E-6 xenon-133m 4.1OE-7 xenon-135 5.30E-8 xenon-135m 2.OOE-6 xenon-138 3.50E-6 2. lodines iodine-132 6.OOE-1O iodine-135 1.70E-10 3. Particulates barium-140 2.70E-11 cerium-141 3.40E-12 cerium-144 1.40E-11 cesium-134 9.20E-12 chromi um-51 3.20E-11 cobalt-60 1.30E-11 iron-59 2.OOE-11 1anthanum-140 2.20E-11 manganese-54 8.20E-12 molybdenum-99
2. 1OE-12 niobium-95 7.70E-12 sodium-24 3.30E-12 stronti um-89 1.OOE-13 stronti um-90 1.OOE-14 technetium-99m 1.20E-11 zinc-65 2.20E-11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE ID (Continued)

GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-44-Radionuclides LLD (/,ýCi/cc)

1. Fission and activation gases krypton-85 1.20E-3 krypton-85m 2.50E-6 krypton-87 1.20E-5 krypton-88 8.90E-6 xenon-133 5.70E-6 xenon-133m 2.30E-5 xenon-135 2.90E-6 xenon-135m 3.70E-5 xenon-138 5.50E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Unit Quarter Quarter Quarter Fourth Quarter A. Noble Gas 1. Gamma Air Dose mrad 5.07E-3 2.81E-3 5.76E-3 5.02E-3 2.. Percent Applicable Limit % 5.07E-2 2.81E-2 5.76E-2 5.02E-2 3. Beta Air Dose mrad 6.20E-3 2.08E-3 4.02E-3 5.47E-3 4. Percent Applicable Limit 3.10E-2 1.04E-2 2.01E-2 2.74E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem 3.10E-3 7.65E-4 1.06E-3 1.48E-3 2. Percent Applicable Limit % 2.07E-2 5.10E-3 7.09E-3 9.89E-3 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period I. Number of batch releases:

8 releases 2. Total time period for batch releases:

2672 minutes 3. Maximum time period for a batch release: 468 minutes 4. Average time period for a batch release: 334 minutes 5. Minimum time period for a batch release: 23 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories:

fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are: (1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists: (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)

(3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category.

The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.

Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period. Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Second Unit Oua;;rter uate A. Fission and activation products I. Total release (not including tritium, gases, alpha) Ci 4.78E-3 3.58E-3 1.90E+1 2. Average diluted concentration during period 4Ci/ml 9.62E-12 5.72E-12 3. Percent of applicable limit % MPC 1.36E-5 1.10E-5 4. Percent Effluent Concentration Limit % ECL 1.29E-4 1.06E-4 B. Tritium 1. Total release Ci 1.02E+2 8.34E+1 1.90E+1 2. Average diluted concentration during period 4Ci/ml 2.05E-7 1.33E-7 3. Percent of applicable limit 0 MPC 6.84E-3 4.45E-3 4. Percent Effluent Concentration Limit % ECL 2.05E-2 1.33E-2 C. Dissolved and entrained gases 1. Total release Ci 4.51E-1 1.49E-2 1.90E+1 2. Average diluted concentration during period 4Ci/ml 9.07E-10 2.38E-11 3. Percent of applicable limit % MPC 4.53E-4 1.19E-5 4. Percent Effluent Concentration Limit % ECL 4.53E-4 1.19E-5 D. Gross alpha radioactivity

1. Total release Ci 1.39E-5 <LLD 5.0OE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 7.56E+7 9.02E+7 5.OOE+O F. Volume of dilution water used during period liters 4.97E+11 6.25E+11 5.OOE+O Estimated Total ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE 2A (Continued)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Estimated Third Fourth Total Quarter Quarter Error, %A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 2.62E-3 5.01E-3 1.90E+1 2. Average diluted concentration during period uCi/ml 3.41E-12 6.77E-12 3. Percent of applicable limit % MPC 7.05E-6 1.25E-5 4. Percent Effluent Concentration Limit % ECL 7.64E-5 1.29E-4] B. Tritium 1. Total release Ci 1.42E+2 6.31E+2 1.90E+1 2. Average diluted concentration during period uCi/ml 1.85E-7 8.52E-7 3. Percent of applicable limit % MPC 6.16E-3 2.84E-2 4. Percent Effluent Concentration Limit % ECL 1.85E-2 8.52E-2 C. Dissolved and entrained gases 1. Total release Ci 1.46E-2 1.17E-1 1.90E+1 2. Average diluted concentration during period MCi/ml 1.90E-11 1.58E-10 3. Percent of applicable limit % MPC 9.51E-6 7.90E-5 4. Percent Effluent Concentration Limit % ECL 9.51E-6 7.90E-5 D. Gross alpha radioactivity

1. Total release Ci 1.29E-5 1.21E-4 5.OOE+1 E. Volume of waste released (batch & continuous, prior to dilution) liters 8.58E+7 1.09E+8 5.OOE+O F. Volume of dilution water used during period liters 7.68E+11 17.41E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE LLD Lower Limit of Detection; see Table 2C.-50-First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 1.52E-4 5.01E-5 <LLD <LLD chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci 1.52E-4 5.01E-5 <LLD <LLD 2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 TABLE 2B (Continued)

LIQUID EFFLUENTS BATCH MODE I First Second Third Fourth Radionuclides Released Unit Quarter Quarter I Quarter Quarter 1. Fission and activation products antimony-125 Ci 1.1OE-3 2.35E-3 1.92E-3 3.41E-3 barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci 7.55E-5 8.23E-5 9.38E-5 1.76E-4 cesium-137 Ci 1.14E-4 3.74E-4 3.54E-4 6.OOE-4 chromium-51 Ci 4.56E-4 4.33E-5 <LLD 1.59E-4 cobalt-58 Ci 8.37E-4 1.30E-4 4.87E-5 5.89E-4 cobalt-60 Ci 5.35E-4 1.68E-4 1.85E-4 3.46E-5 iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci 1.12E-3 3.40E-4 <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 6.18E-5 5.07E-6 <LLD 7.13E-6 molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 1.51E-4 3.02E-6 1.38E-5 <LLD niobium-97 Ci 5.30E-6 9.05E-6 4.83E-6 6.15E-6 silver-lOrm Ci 6.10E-5 <LLD <LLD 3.19E-5 strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD tin-117m Ci <LLD 2.27E-5 <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci 1.12E-4 <LLD <LLD <LLD Total for period Ci 4.63E-3 3.53E-3 2.62E-3 5.01E-3 2. Dissolved and entrained gases krypton-85 Ci 1.42E-1 1.49E-2 1.16E-2 9.63E-2 xenon-131m Ci 1.77E-2 <LLD <LLD 5.17E-3 xenon-133 Ci 2.91E-1 <LLD 3.01E-3 1.56E-2 xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci 4.51E-1 1.49E-2 1.46E-2 1.17E-1 LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION-52-Rad ionucl ides LLD (4Ci/cc) I. Fission and activation products bariurn-140 3.90E-7 cerium-141 5.80E-8 cerium-144 2.30E-7 cesium-134 1.00E-7 cesium-137 8.60E-8 chromium-51 4.60E-7 cobalt-58 9.OOE-8 cobalt-60 1.30E-7 iodine-131 8.OOE-8 iron-55 1.OOE-6 iron-59 2.10E-7 lanthanum-140 7.20E-7 manganese-54 8.90E-8 molybdenum-99 7.50E-8 niobium-95 9.10E-8 strontium-89 5.OOE-8 strontium-90 1.OOE-8 technetium-99m 7.70E-8 zinc-65 2.20E-7 zirconium-95 1.60E-7 2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE 2C (Continued)

LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-53-Radionuclides LLD (gCi/cc) 1. Fission and activation products barium-140 3.30E-7 cerium-141 5.30E-8 cerium-144 2.30E-7 chromium-51 4.20E-7 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 lanthanum-140 2.40E-7 manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 silver-llOm 1.30E-7 strontium-89 5.OOE-8 strontium-90 1.OOE-8 technetium-99m 3.60E-8 tin-ll7m 3.10E-8 zinc-65 2.20E-7 zirconium-95 1.50E-7 2. Dissolved and entrained gases xenon-131m 4.OOE-6 xenon-133 3.10E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A.1. Total body dose mrem 2.68E-4 1.90E-4 2.68E-4 1.11E-3 2. Percent Applicable Limit O 8.95E-3 6.32E-3 8.92E-3 3.69E-2 B. 1. Limiting organ dose mrem 7.07E-4 2.82E-4 3.01E-4 1.25E-3 2. Percent Applicable Limit % 7.07E-3 2.82E-3 3.01E-3 1.25E-2 3. Limiting organ for period GI/LLI GI/LLI GI/LLI GI/LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period 1. Number of batch releases:

146 releases 2. Total time period for batch releases:

21855 minutes 3. Maximum time period for a batch release: 478 minutes 4. Average time period for a batch release: 150 minutes 5. Minimum time period for a batch release: 7 minutes 6. Average saltwater flow during batch releases:

726000 gpm SECTION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM 1. The fourth quarter 2000 values for composite Sr-89, Sr-90 and Fe-55 were incomplete due to data not available at report time. The values are as follows: TABLE IC (2000) GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE Radionuclides Released Unit Fourth Quarter 3. Particulates strontium-89 Ci <LLD strontium-90 Ci <LLD Sr-89 LLD = 1.OOE-13 Sr-90 LLD = 1.OOE-14 Table 2A (2000) LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Fourth Unit Quarter A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 4.42E-2 2. Average diluted concentration during period 4Ci/ml 7.09E-11 3. Percent of applicable limit % MPC 7.66E-5 4. Percent of Effluent Concentration Limit % ECL 5.93E-4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION D.PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)TABLE 2B (2000) LIQUID EFFLUENTS CONTINUOUS MODE Radionuclides Released Unit Fourth Quarter 2. Fission an activation products iron-55 Ci <LLD strontium-89 Ci <LLD strontium-90 Ci <LLD Fe-55 LLD = 1.OOE-6 Sr-89 LLD = 5.OOE-8 Sr-90 LLD = 1.OOE-8 TABLE 2B (2000) LIQUID EFFLUENTS BATCH MODE Radionuclides Released Unit Fourth Quarter 2. Fission an activation products iron-55 Ci 9.77E-3 strontium-89 Ci <LLD strontium-90 Ci <LLD Total for period Ci 4.42E-2 Fe-55 LLD Sr-89 LLD Sr-90 LLD 1.00E-6 5.OOE-8 1.00E-8-57-PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) 2. The following information was not included in the 2000 report. SECTION K. MISCELLANEOUS (2000)

  • Non-isokinetic Particulate and Iodine Sampling on Condenser Air Eiector Monitors On 1/21/00, it was determined that the Unit 2 and Unit 3 Condenser Air Ejector (CAE) radiation monitoring systems' sample flow was outside the design range for isokinetic flow (11.3-18.7 scfm). The process flow was immediately adjusted to ensure sampling within the allowable range. Based on testing of the actual plant configuration and equipment, it was determined that isokinetic flow could actually be maintained between 7.0 scfm to 22.5 scfm. From 2/21/99 to 1/21/00, Unit 2 CAE monitor sample flow was outside the allowable range 30% of the time while Unit 3, from 5/6/99, was outside 80% of the time. For the entire year, no particulate and iodine sample showed any detectable activity.

The noble gas monitor was in service for the entire time period. This event is documented in AR 000101252.

0 Missed Process Flow Estimate On 5/2/00 the Unit 3 Full Flow Condensate Polishing Demineralizer Holdup Tank was released with the process flow instrument, 3FQ13772, out of service. The one hour flow check required by the ODCM under these conditions was missed. The flow estimate was completed at 66 minutes. There were no dose consequences to the public as a result of this event that is documented in AR 000500145.

  • Loss of Heat Tracing on Plant Vent Stack Monitor (2RT-7865)

On 5/10/00, the heat tracing for the sample lines for 2RT-7865 was identified as inoperable due to a failed breaker. The last time the heat tracing had been verified operable was on 3/7/00 during a Channel Functional Test. During the period of 3/7/00 to 5/10/00, particulate and iodine samples from 2RT-7865 were only used for dose calculations from 3/15/00 to 3/29/00. Sample results of the weeks previous and following this time period, from different monitors, showed similar or lower iodine activity.

There was no particulate activity during this time. There were no dose consequences to the public as a result of this event that is documented in AR 000400609.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) 3. Dose calculations for Table 1 Airborne Effluents and Noble Gases of this report are performed using concurrent meteorological data. On 10/27/00, it was determined a conversion factor of 2 had incorrectly been applied to wind speeds collected from 07/27/98 to 12/31/99 subsequent to a hard drive failure. This event is documented in AR 001002318.

On 12/7/01, it was determined the computer program used to perform airborne dose calculations did not have the current controlling location receptor parameters.

In August 1998, during system repair, the file was replaced but the contents were not verified prior to use. This event is documented in AR 010201705.

The operating procedure has been revised to verify file data prior to use. The dose data have been reprocessed for the years 1998, 1999 and 2000. In no case did the percent of the dose limit exceed 1%. The revised data are provided in the following tables.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)Section H. 1OCFR50 Appendix I Requirments TABLE 1 (1998) Dose * (millirems)

SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS

11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 1.58E-2 1.42E-3 2.02E-3 5.71E-4 1.88E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 6.64E-3 1.42E-3 2.44E-3 5.38E-3 1.46E-2 Beta 21) 22) 23) 24) 25) 1.23E-2 3.97E-3 6.92E-3 7.96E-3 2.95E-2
  • The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).

Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-25 These values were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 12. The maximum organ dose was to a child's thyroid and was located in the NNW sector. 13-15. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.

17. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.

18-20. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.

21. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
22. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.

23-25. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.

TABLE 2 (1998) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, lodines, 1.05E-1 9.48E-3 1.35E-2 3.80E-3 6.25E-2 and Particulates NOBLE GASES ** Gamma 6.64E-2 1.42E-2 2.44E-2 5.38E-2 7.30E-2 Beta 6.13E-2 1.98E-2 3.46E-2 3.98E-2 7.37E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. 1OCFR50 Appendix I Requirments TABLE 1 (1999) Dose * (millirems)

SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS

11) 12) 13) 14) 15) Tritium, lodines, and Particulates 1.35E-2 3.84E-3 8.62E-4 6.78E-3 1.94E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 5.59E-3 1.92E-3 1.06E-3 2.60E-3 1.04E-2 Beta 21) 22) 23) 24) 25) 1.07E-2 1.80E-3 1.16E-3 3.30E-3 1.67E-2 The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s). Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose. 11-25 These were calculated using the assumptions of USNRC Regulatory Guide 1.109. 11. The maximum organ dose was to a child's thyroid and was located in the ESE sector. 12-15. The maximum organ dose was to a child's thyroid and was located in the NNW sector. 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
17. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
18. The maximum air dose for gamma radiation was located in the ESE sector, at the exclusion area boundary.
19. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
20. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
21. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
22. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.

23-25. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.

TABLE 2 (1999) Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 9.03E-2 2.56E-2 5.74E-3 4.52E-2 6.45E-2 NOBLE GASES Gamma 5.59E-2 1.92E-2 1.06E-2 2.60E-2 5.18E-2 Beta 5.35E-2 9.02E-3 5.81E-3 1.65E-2 4.18E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION D.PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)Section H. 1OCFRSO Appendix I Requirements TABLE 1 (2000) Dose * (millirems)

SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS

11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 6.13E-3 2.97E-3 3.66E-3 3.94E-3 1.58E-2 NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 1.51E-3 3.45E-3 1.82E-3 1.94E-3 7.18E-3 Beta 21) 22) 23) 24) 25) 1.39E-3 3.26E-3 1.56E-3 2.12E-3 8.08E-3 The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway (s), Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose.11-25 11-12. 13. 14. 15. 16. 17. 18-20. 21. 22-23. 23. 24. 25.These were calculated using the assumptions of USNRC Regulatory Guide 1.109. The maximum organ dose was to a child's thyroid and was located in the NNW sector. The maximum organ dose was to a child's thyroid and was located in the E sector. The maximum organ dose was to a child's thyroid and was located in the ESE sector. The maximum organ dose was to a child's thyroid and was located in the NNW sector. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.

The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.

The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.

The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.

The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.

The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.

The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.

The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.

TABLE 2 (2000)Percent Applicable Limit SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 4.09E-2 1.98E-2 2.44E-2 2.63E-2 5.27E-2 NOBLE GASES Gamma 1.51E-2 3.45E-2 1.82E-2 1.94E-2 3.59E-2 Beta 6.95E-3 1.63E-2 7.79E-3 1.06E-2 2.02E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated 12 month total error 1. Type of waste Unit period (%) .a. Spent resins, filter sludges, m 3 N/A evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3 1.29E+1 compactable and non-compactable*

Ci 2.30E-2 3.OOE+1 c. Irradiated components, control m 3 N/A rods Ci N/A N/A d. Other m 3 N/A Ci N/A N/A Note: Total curie content estimated.

(*) Material packaged in strong, tight containers of various sizes. N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 2. Estimate of major nuclide composition (by type of waste) (Cont'd) a. not applicable

% N/A b. americium-241 00 1.63E-3 antimony-124 0 2.78E-1 antimony-125

% 7.49E-1 carbon-14 00 1.26E+O cerium-141

%o 6.75E-2 cerium-144

% 8.97E-2 cesium-134

%- 1.85E+O cesium-137

%_ 1.64E+1 chromium-51 0 1.17E+1 cobalt-57

% 1.11E-I cobalt-58

% 2.53E+1 cobalt-60

%o 7.O1E+O curium-242

% 1.29E-3 curi um-243/244

%o 2.06E-3 iodine-129

% 3.34E-2 i ron-55 % 1.92E+I I ron-59 __ 1.17E+O manganese-54

%o 1.32E+O nickel-63

% 8.25E+O ni obi um-95 0 3.09E+O pl utonium-238

% 1.12E-3 pl utonium-239/240

%o 1.03E-3 pl utonium-241

%o 1.06E-1 silver-110m 00 1.60E-2 strontium-89

% 1.06E-2 strontium-90

-1.04E-2 technetium-99

%_ 3.84E-3 tin-113 %o 2.60E-1 tritium %o 1.13E-1 zi rconium-95

% 1.59E+O c. not applicable

% O.OOE+O d. not applicable 0 O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 4 Hitman Trucking Company EnviroCare, UT Truck/Trailer

  • SONGS maintains a contract with vendor (GTS) that provides volume reduction services.

These shipments were made from their processing facility.

The 4 shipments made from this facility included waste from other generators.

SCE's waste volume was a small fraction of the total waste volume of these shipments.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 SECTION F APPLICABLE LIMITS Gaseous Effluents

-Applicable Limits The percent of Applicable were calculated using the % % Applicable Limit where: Rel Rate X/Q 0 MPCeff where: F1 n Limits, tabulated in Sections A, B, C, and D of Table 1A, following equation: (Rel Rate) WX/O) (100) MPCef epcff total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, uCi/sec.

4.80E-6 sec/mr; the annual average atmospheric dispersion defined in the Units 2&3 0DCM. 1 -- I~ 1 MPC fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C,, by the sum of all the isotopic activity, C,. total number of radionuclides identified MPCj Maximum Permissible Concentration (MPC) radionuclide from 10 CFR 20 (20.1-20.602), Table II, Column 1.of the i t" Appendix B, (Rel Rate) (X/O) (100) ECLeff where: Rel Rate X/Q o ECLeff where: F, n ECL total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, uCi/sec.

4.80E-6 sec/mr; the annual average atmospheric dispersion defined in the Units 2&3 0DCM. F, -ECLI fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, by the sum of all the isotopic activity, C,. total number of radionuclides identified

= Effluent Concentration Limit (ECL) of the i t' radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.-66-* %ECL ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 Liquid Effluents

-Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations:

% Applicable Limit where: Dil Conc 0 MPCeff where: Fj n MPCG

  • ECL where: Dil Conc 0 ECLeff where: Fj n ECL, (Dil Conc) (100) MPCeff total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, juCi/ml.

1 Mi MPC i fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C 1 , by the sum of all the isotopic activity, CT. total number of radionuclides identified Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2. (Dil Conc) (100) ECLeff total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, yCi/ml. 1 ECL fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT. total number of radionuclides identified Effluent Concentration Limit (ECL) of the it' radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made. Sources of error for gaseous effluents

-batch releases are: (1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for gaseous effluents

-continuous releases are: (1) fan flow rate (2) sampling (3) counting (4) calibration (5) differential pressure drop Sources of error for liquid effluents

-batch releases are: (1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for liquid effluents

-continuous releases are: (1) dilution flow rate (2) sampling (3) counting (4) calibration These sources of error are independent, and thus, the total error is calculated according to the following formula: Total Error -2 a + U2 + ... 02 1I,, 2 3 where: o = Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual.

Six different categories are presented:

(1) (2) (3) (4) (5) (6)Liquid Effluents

-Whole Body Liquid Effluents

-Organ Airborne Effluents

-Tritium, Iodines and Particulates Noble Gases -Gamma Noble Gases -Beta Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; these data are also presented in Table 2D. Categories 3, 4, and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) software, Regulatory Guide 1.109 methodology, and concurrent meteorology.

Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters.

Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

For members of the public, per the ODCM, who may at times be within the site boundary', the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

For members of the public who traverse the site boundary via highway 1-5, the residency time shall be considered negligible and hence the dose "0".Table 2 in Section H in Table 1.presents the percent of Applicable Limits for each dose presented 1. ODCM Figures 2-1 & 2-2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 TABLE I The numbered footnotes below briefly explain how each the organ and the predominant pathway(s).

Noble gas doses due to airborne effluent are in units 1. This value was calculated using the methodology of the 2. This value was calculated using the methodology of the 3. This value was calculated using the methodology of the 4. This value was calculated using the methodology of the 5. This value was calculated using the methodology of the maximum dose was calculated, including of mrad, reflecting the air dose. ODCM. ODCM. ODCM. ODCM. ODCM.-70-Dose * (millirems)

First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS I) 2) 3) 4) 5) Whole Body 2.68E-4 1.90E-4 2.68E-4 1.11E-3 1.83E-3 6) 7) 8) 9) 10) Organ 7.07E-4 2.82E-4 3.01E-4 1.25E-3 2.54E-3 AIRBORNE EFFLUENTS

11) 12) 13) 14) 15) Tritium, Iodines, and Particulates 9.26E-3 3.09E-3 1.39E-3 7.99E-3 1.97E-2 NOBLE GASES 16) 17) 18) 19) 20) Gamma 2.43E-3 7.19E-4 1.73E-3 2.12E-3 6.18E-3 21) 22) 23) 24) 25) Beta 2.88E-3 6.13E-4 1.28E-3 2.95E-3 7.05E-3 26) 27) 28) 29) 30) DIRECT RADIATION 9.39E-2 1.24E-1 6.86E-2 1.11E-1 3.53E-1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 6. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.

7. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
8. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
9. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
10. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
11. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 12. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 13. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 14. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109. 15. The maximum organ dose was to a child's thyroid and was located in calculated using the assumptions of USNRC Regulatory Guide 1.109.received the maximum dose received the maximum dose received the maximum dose received the maximum dose received the maximum dose the NNW sector. This was the NNW sector. This was the NNW sector. This was the ESE sector. This was the NNW sector. This was 16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 17. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 18. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 19. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 20. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 21. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 22. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 23. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 24. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 25. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. 26. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector. 27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector, 28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the WSW sector. 29. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the WSW sector. 30. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector. TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 8.95E-3 6.32E-3 8.92E-3 3.69E-2 3.05E-2 Organ 7.07E-3 2.82E-3 3.01E-3 1.25E-2 1.27E-2 AIRBORNE EFFLUENTS Tritium, lodines, and Particulates 6.17E-2 2.06E-2 9.28E-3 5.33E-2 6.57E-2 NOBLE GASES Gamma 2.43E-2 7.19E-3 1.73E-2 2.12E-2 3.09E-2 Beta 1.44E-2 3.06E-3 6.39E-3 1.48E-2 1.76E-2 NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 28, 2001, Revision 36 to the Units 2/3 Offsite Dose Calculation Manual was adopted and published.

This change incorporated the following:

1. Update to SYF flowrates, 2. Addition of liquid composite samplers to Section 4, 3. Change to 6.3.1.a to require ODCM updates be made in accordance with applicable regulations rather than IOCFR50.59, {due to changes in the 10CFR50.59 program} 4. Deleted the Investigative Report definition, and 5. Changes related to the Land Use Census update. Safety Evaluations were provided for items 2 and 3. The requirement for an Investigative Report was added to the ODCM at the time that the RETS were transferred from the Technical Specifications.

There existed a need to document each occurrence of failure to meet Surveillance Requirements and/or Action Statements related to the ODCM. The ODCM will now require performance of an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

Minor format changes, correction of typographical errors, and removal of previously blank pages have been made and are described in the attached List of Affected Pages. None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations.

The level of radioactive effluent control required by 1OCFR20, 40CFR190, 1OCFR50.36a, and Appendix I to IOCFR50 will be maintained.

Throughout the document, change bars are marked in one of four ways as follows: A Addition D Deletion F Editorial/Format change R Revision The following is a complete list of the changes: Old New page CHANGE REASON page TOC Renumbered pages as necessary based on changes in the body of the ODCM. F 1-10 Lined up equation definitions.

F 1-14 Lined up equation definitions.

F 1-25 Changed procedure reference name. R 2-8 Added placeholder for Step 2.5 which was previously deleted. F 2-21 Updated SYF process flow rates per NEDO Calculation N-0320-007.

R ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 Old New page CHANGE page 2-31 Updated Controlling Location Factors per LUC update. 2-32 Renumbered Table page number due to deletion of one page. 2-33 Moved San Mateo Pt Homes from Sector P to Sector Q. Page intentionally left blank. 2-34 Renumbered Table page number due to deletion of one page. 2-35 Renumbered Table page number due to addition of one page. 2-36 Renumbered Table page number due to addition of one page. 2-37 Renumbered Table page number due to addition of one page. 2-38 Renumbered Table page number due to addition of one page. Section 2 Renumbered Section 2 pages from 2-39 on to reflect the addition of pages. 2-39 Moved San Mateo Pt Homes from Sector P to Sector Q. 2-39 2-40 Renumbered Table page number due to addition of one page. 2-40 2-41 Renumbered Table page number due to addition of one page. 2-42 Added Outage Worker to Sector R. 4-1 Changed 4.1.1.c from Investigative Report to Corrective Action Program Section 4 Renumbered Section 4 pages from 4-3 on to reflect the addition of pages. 4-3 Added composite samplers to Table 4-1. 4-4 4-5 Added Action 33 for composite samplers.

4-7 Added composite samplers to Table 4-2. 4-6 4-8 Added Note 5 for composite samplers.

4-7 4-9 Changed 4.2.1.c from Investigative Report to Corrective Action Program.

5-2 Removed Table 5-5 as sample location per AR #000400602.

5-14 Removed Table 5-5 as sample location per AR #000400602, 5-21 Corrected mileage for PIC S7. 6-2 Deleted INVESTIGATIVE REPORT definition.

6-10 Changed "IOCFR50.59" to "applicable regulations".

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.

2 and 3 SECTION J- CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were during the no changes to the Units 2&3 Radioactive Waste reporting period, January 1, 2001 to December Treatment Systems 31, 2001.SECTION K. MISCELLANEOUS Leaking Unit 2 Steam Generator Blowdown Valves In December 2000, Unit 2 Steam Generators were estimated to be leaking past their blowdown isolation valves to the outfall at 1 gpm, with a maximum leak rate of 2 gpm. Compensatory sampling was performed all year (samples indicated no detectable gamma activity for the year with trace amount of tritium).

Valve repair is planned for the outage in 2002. A recent engineering evaluation has determined there is minimal leakage, less than can be accurately measured (less than 1 gpm). This event is documented in AR 001200733.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2001 -December 31, 2001 Monitor Inoperability Period Inoperability Cause Explanation 2RT-7870 04/17/00 -present Inoperable process Design deficiency causes process Condenser Air flow measuring flow instrument to be inoperable Ejector Process device whenever while the vacuum pump is running.

Flow Monitor vacuum pump is Substitute flow value is running. automatically inserted whenever the vacuum pump is running as high flow values are not sensed. Flow monitor works properly during normal operations.

This event is documented in ARs 000101252 and 1000400960.

S.O.N.G.S.

3 Monitor Inoperability Period Inoperability Cause Explanation 3RT-7870 04/17/00 -present Inoperable process Design deficiency causes process Condenser Air flow measuring flow instrument to be inoperable Ejector Process device whenever while the vacuum pump is running.

Flow Monitor vacuum pump is Substitute flow value is running, automatically inserted whenever the vacuum pump is running as high flow values are not sensed. Flow monitor works properly during normal operations.

This event is documented in ARs 000101252 and 1000400960.

S.O.N.G.S.

2/3 Monitor Inoperability Period Inoperability Cause Explanation 2/3FIT-7202 08/22/01 -01/12/02 Suspected process Investigation during two subsequent Waste Gas Holdup flow measuring releases showed no instrument or System Process device component error. The system was Flow Rate verified to be properly Monitoring Device functioning.

This event is documented in AR 010801138. S.01.N.G..

2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.

2 and 3 SECTION L. S.O.N.G.S.

2 and 3 CONCLUSIONS Gaseous releases totaled 1.68E+2 curies of which noble gases were 8.68E+1 curies, iodines were 4.56E-2 curies, particulates were 1.77E-3 curies, and tritium was 8.08E+1 curies. The radiation doses from gaseous releases were: (a) gamma air dose: 6.18E-3 mrad at the site boundary, (b) beta air dose: 7.05E-3 mrad at the site boundary, (c) organ dose: 1.96E-2 mrem at the nearest receptor.

Liquid releases totaled 9.59E+2 curies of which particulates and iodines were 1.60E-2 curies, tritium was 9.58E+2 curies, and noble gases were 5.98E-1 curies. The radiation doses from liquid releases were: (a) total body: 1.83E-3 mrem, (b) limiting organ: 2.54E-3 mrem. The radioactive releases and resulting doses generated from Units 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.

COMMON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) COMMON COMMON RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) Estimated

1. Type of waste Unit 12 month period total error (%) a. Spent resins, filter m3 N/A sludges, evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), m 3 1.19E+1 compactable and non compactable
  • Ci 9.OOE-3 3.OOE+1 c. Irradiated components, m 3 N/A control rods Ci N/A N/A m 3 N/A d. Other (filters)

Ci N/A N/A Note: (*) N/A Total curie content estimated.

Material packaged in strong, tight containers of various sizes. No shipment made.

.1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) COMMON 2. Estimate of major nuclide composition (by type of waste) (Cont'd) a. not applicable 0 N/A b. americium-241 0 1.63E-3 antimony-124

% 2.78E-1 antimony-125 0 7.49E-1 carbon-14

% 1.26E+O cerium-141

% 6.75E-2 cerium-144

% 8.97E-2 cesium-134 0 1.85E+O cesium-137 0 1.64E+1 chromium-51 0 1. 17E+I cobalt-57

% 1.11E-1 cobalt-58

% 2.53E+1 cobal t-60 -7.01E+O curium-242 0 1.29E-3 curi um-243/244

% 2.06E-3 iodine-129

% 3.34E-2 iron-55 0 1.92E+1 iron-59 % 1.17E+O manganese-54 0 1.32E+O nickel-63

% 8.25E+O niobium-95

% 3.09E+O pl utoni um-238 % 1.12E-3 pl utonium-239/240

% 1.03E-3 pl utonium-241 0 1.06E-1 silver-110m

% 1.60E-2 strontium-89 0 1.06E-2 stronti um-90 % 1.04E-2 technetium-99 0 3.84E-3 tin-113 % 2.60E-1 tritium % 1.13E-1 zirconium-95

% 1.59E+O c. not applicable 0 d. not applicable 0

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)B.3. Solid Waste Disposition (S.O.N.G.S.

1, 2, and 3) Number of Shipments Mode of Transportation Destination Kindrick Trucking Company EnviroCare, UT 2 Flatbed Trailer IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING See Units 2/3 section of this report. D. CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 During the reporting period January 1, 2001 through December 31, 2001, a change to the Process Control Program (PCP) procedure S0123-VII-8.5.1 was issued but did not result in a change to the PCP itself. The following page has an explanation of the administrative changes and the justification of their nature.

REFERENCES:

1. Unit 1 Technical Specifications, section D6.13.2.
2. Units 2 and 3 Licensee Controlled Specifications, Section 5.0.103.2.2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON D. CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 (Continued)

February 28, 2001 RUSS KRIEGER, Site Manager and VP Nuclear DARYL DICK, Supervisor of Effluent Engineering BILL STROM, Nuclear Safety Group Supervisor

SUBJECT:

Process Control Program (PCP) Procedure Revision Health Physics is issuing a comprehensive revision of S0123-VII-8.5.1, Process Control Program. The purpose of this memorandum is to inform you, as required by procedure, of changes made to the PCP and their bases. Revision 7 of the PCP procedure contains changes that are only administrative in nature. Changes principally include: 1. A restatement of the procedure objective to more concisely link general objectives to specific references.

2. Updated and expanded references, including the Unit 1 DSAR. 3. Reorganized and restated procedure steps to more clearly link requirements to referenceg.
4. Revised statements of administrative controls that quote, rather than paraphrase, requirements imposed by the TQAM, LCSs, etc. 5. Deletion of record requirements duplicated in other Health Physics procedures and not required to meet PCP objectives.

The changes made to the PCP procedure are justified as administrative in nature. The core PCP objective, ensuring all solid radioactive waste processing conform to form, stability, and free-standing water requirements, remains intact. With the core requirements of the procedure unchanged, overall conformance of SONGS solid radioactive waste products with applicable requirements is maintained.

Implementing procedures, such as those controlling the actual processing and packaging of radioactive wastes, are unaffected.

Please contact me if I can be of assistance.

JIM MADIGAN Health Physics Manager MLewis:PCP:mjk cc: E. Goldin P. Elliott ITA File 95-325 CDM Files ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON COMMON 40 CFR 190 REQUIREMENTS Table I below presents the annual site-wide doses and percent of ODCM Specification limits to members of the public. These values were calculated utilizing doses resulting from all effluent pathways and direct radiation.

The different categories presented are: (1) Total Body, (2) Limiting Organ, and (3) Thyroid.

Dose Category Units Year 1. Total Body a. Total Body Dose mrem 3.90E-1 b. Percent ODCM Specification Limit % 1.56E+O 2. Limiting Organ a. Organ Dose (GI-LLI) mrem 4.36E-2 b. Percent ODCM Specification Limit 1.75E-1 3. Thyroid a. Thyroid Dose mrem 8.71E-3 b. Percent ODCM Specification Limit % 1.16E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S.

1, 2 and 3 totaled 1.71E+2 curies of which noble gases were 8.68E+1 curies, iodines were 4.56E-2 curies, particulates were 2.OOE-3 curies, and tritium was 8.36E+1 curies. Liquid releases form S.O.N.G.S.

1, 2 and 3 totaled 9.61E+2 curies of which particulates and iodines were 1.95E-2 curies, tritium was 9.60E+2 curies, and noble gases were 5.98E-1 curies. Radioactive releases and resulting doses generated from S.O.N.G.S.

1, 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.

S.O.N.G.S.

1, 2 and 3 made 134 radwaste shipments to Envirocare, UT. Total volume was 2.54E+3 cubic meters containing 1.32E+O curies of radioactivity.

Meteorological conditions during the year were typical for S.O.N.G.S.

Meteorological dispersion was good 30% of the time, fair 47% of the time and poor 23% of the time. The net result from the analysis of these effluent releases indicates that the operation of S.O.N.G.S.

1, 2 and 3 has met all the requirements of the applicable regulations and therefore has not resulted in any detrimental effects to a member of the public.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON APPENDIX A GASEOUS EFFLUENTS

-APPLICABLE LIMITS A. Table 1A lists the total curies of applicable limit compares the limits of 10 CFR 20, Appendix B, released and the release rate. The percent released concentrations to the concentration Table II, Column 1.B. Table 1E lists the air doses as calculated using the historical X/Q. The air dose due to noble gases released in gaseous effluents from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values: 1. During any calendar quarter: 2. During any calendar year: S5 mrad for gamma radiation and S10 mrad for beta radiation.

S10 mrad for gamma radiation and S20 mrad for beta radiation.

C. The dose to a Member of the Public from iodines, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values: 1. During any calendar quarter: 2. During any calendar year:7.5 mrem to any organ. S15 mrem to any organ.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON APPENDIX A (Continued)

LIQUID EFFLUENTS

-APPLICABLE LIMITS A. Table 2A lists the total curies released, the diluted concentration, and percent of the applicable limit. The percent of applicable limit compares the diluted concentration of radioactive material released to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration is limited to 2.OOE-4 pCi/ml. B. Table 2D lists doses due to liquid releases.

The dose commitment to a Member of the Public from radioactive materials in liquid effluents released from S.O.N.G.S. (per reactor) to unrestricted areas shall be limited to the following values: 1. During any calendar quarter: 2. During any calendar year:< 1.5 mrem to the total body and

  • 5 mrem to any organ. <3 mrem to the total body and <10 mrem to any organ.

METEOROLOGY METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2001 is described in this section. Meteorological measurements have been made according to the guidance provided in USNRC Regulatory Guide 1.23, "Onsite Meteorological Programs." A summary report of the meteorological measurements taken during each calendar quarter are presented in Table 4A as joint frequency distribution (JFD) of wind direction and wind speed by atmospheric stability class. Hourly meteorological data for batch releases have been recorded for the periods of actual release. These data are available, as well as the hourly data for the Annual Report, but have not been included in this report because of the bulk of data records.

Table 4A lists the joint frequency distribution for each quarter, 2001. Each page of Table 4A represents the data for the individual stability classes: A, B, C, D, E, F, and G. The last page of each section is the JFD for all the stability classes. The wind speeds have been measured at the 10-meter level, and the stability classes are defined by the temperature differential between the 10-meter and 40-meter levels.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY January -March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00123124-01033123 WIND SPEED (M/S) AT 10 METER LEVEL.22.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.51.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 EXTREMELY UNSTABLE 1.1 1.5 0 2 0 0 0 0 0 0 2 5 3 3 0 0 0 0 1.6 2.0 0 0 0 0 0 0 0 0 4 5 7 13 5 4 1 0.76 1.0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 PASQUILL A (DT/DZ < 2.1- 3 3.0 5 0 0 0 0 1 5 13 11 15 29 43 9 0 0-1.9 .I.0 0 0 0 0 0 0 6 10 18 12 13 19 57 28 4 0 oC/100 5.1 7.0 0 0 0 0 0 0 1 8 7 0 1 5 3 11 0 0 METERS) 7.1 10.0 0 0 0 0 0 0 0 1 0 0 0 0 1 0 0 0 10.1 13.0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 13.1 18.0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0>18 TOIAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 4 0 0 0 0 8 24 45 33 41 69 109 52 5 0 TOTALS 0 0 1 15 40 128 167 36 2 1 1 0 391 NUMBER OF VALID HOURS 391 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2160 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ : -1.7 °C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 1 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 1 0 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 1 0 0 0 0 0 1 SW 0 0 0 0 0 1 0 0 0 0 0 0 1 WSW 0 0 0 0 1 0 0 0 0 0 0 0 1 W 0 0 0 0 1 0 0 0 0 0 0 0 1 WNW 0 0 0 0 0 1 1 0 0 0 0 0 2 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 0 2 3 3 0 0 0 0 0 8 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 8 1 NUMBER OF CALMS TOTAL HOURS FOR-87-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW THE PERIOD 0 2160 EXTREMELY UNSTABLE IIl ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) METEOROLOGY January -March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00123124-01033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ _< -1.5 'C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 4 0 0 0 1 0 0 0 0 0 0 0 5 NNE 0 0 0 0 1 0 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 1 0 0 0 0 0 1 ESE 0 0 0 0 0 0 2 1 0 0 0 0 3 SE 0 0 0 0 0 1 2 6 1 0 0 0 10 SSE 0 0 0 0 2 2 4 6 0 0 0 0 14 S 0 0 0 0 2 4 4 2 1 0 0 0 13 SSW 0 0 0 1 1 2 4 1 0 0 0 0 9 SW 0 1 1 1 3 7 0 0 0 0 0 0 13 WSW 0 0 1 2 3 5 2 0 1 0 0 0 14 W 0 0 0 2 5 6 1 0 0 0 0 0 14 WNW 0 0 0 0 2 1 6 1 0 0 0 0 10 NW 0 0 0 0 1 2 3 1 0 0 0 0 7 NNW 0 0 0 0 1 1 0 0 0 0 0 0 2 TOTALS 4 1 2 6 22 31 30 18 3 0 0 0 117 NUMBER OF VALID HOURS 117 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS I TOTAL HOURS FOR THE PERIOD 2160 PASQUILL D NEUTRAL (-1.5 < DT/DZ _< -0.5 'C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 11 NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS U 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 U 2 0 0 2 0 0 1 2 1 0 0 0 0 1 0 9 U 5 1 8 0 3 0 0 1 2 2 1 0 1 1 6 0 4 5 2 2 8 2 6 0 3 1 2 1 3 1 7 17 61 I 7 3 1 0 1 3 10 10 10 7 1 7 8 1 0 4 9 2 2 3 13 23 22 13 12 9 4 2 3 13 10 2 2 1 7 23 56 26 12 6 1 3 6 12 5 5 U 0 1 0 2 10 41 19 5 1 4 3 6 4 5 0 0 0 0 0 0 6 24 7 2 1 2 3 5 2 0 0 0 0 0 0 0 0 2 7 1 0 0 2 1 0 0 0 0 0 0 0 0 0 1 2 0 0 0 0 0 0 0 0 0 23 76 144 168 101 52 13 3 0 64-4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 18 29 10 4 17 56 151 101 49 38 33 24 30 32 29 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 644 1 NUMBER OF CALMS TOTAL HOURS FOR-88-THE PERIOD 0 2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY January -March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00123124-01033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E Y STABLE (-0.5 < DT/DZ 5 1.5 1.1 1.5 4 10 6 2 5 3 3 0 4 1 1 2 0 2 4 2 49 1.6 2.0 7 9 5 2 4 3 2 1 0 1 1 0 1 2 1 10 2.1 3.0 9 16 5 3 9 9 2 0 0 0 0 0 3 3 4 5 68 3.1 5.0 4 8 3 0 4 5 9 2 1 0 0 0 1 5 3 3 48-C/100 METERS) 5.1- 7.1 7.0 10.0 0 0 0 0 0 0 1 0 1 0 1 0 2 0 4 1 3 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 13 3 NUMBER OF VALID HOURS 250 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2160 PASQUILL F MODERATELY STABLE (1.5 g DT/DZ 4.0 °C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 4 4 11 2 0 0 0 0 0 21 NNE 0 0 6 17 43 64 26 2 0 0 0 0 158 NE 0 0 3 5 12 4 5 4 0 0 0 0 33 ENE 0 0 2 5 2 1 0 0 0 0 0 0 10 E 0 1 1 1 2 1 1 0 0 0 0 0 7 ESE 0 0 0 4 1 0 1 0 0 0 0 0 6 SE 0 0 1 1 1 2 5 0 0 0 0 0 10 SSE 0 1 0 2 0 1 0 0 0 0 0 0 4 S 2 0 1 1 2 0 0 0 0 0 0 0 6 SSW 0 1 0 0 0 1 0 0 0 0 0 0 2 SW 0 0 0 1 0 0 0 0 0 0 0 0 1 WSW 0 0 0 1 0 0 0 0 0 0 0 0 1 W 0 0 0 2 2 2 2 0 0 0 0 0 8 WNW 0 0 0 0 1 0 0 0 0 0 0 0 1 NW 1 0 0 2 4 0 1 0 0 0 0 0 8 NNW 0 0 1 1 0 1 2 0 0 0 0 0 5 TOTALS 3 3 15 47 74 88 45 6 0 0 0 0 281 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 281 1 NUMBER OF CALMS TOTAL HOURS FOR-89-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS>18 TOTAL.22.50 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 2.51.75 0 1 0 3 0 0 0 0 1 0 0 0 0 0 1 2 8 SLIGHTL .76 1.0 0 2 6 1 2 2 0 1 1 1 0 1 0 0 0 1 18 10.1 13.0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 1 13.1 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 24 46 25 13 27 23 18 9 10 3 2 3 5 14 14 14 250 THE PERIOD 0 2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY January -March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00123124-01033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 'C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS 6 0 5 0 0 0 0 0 0 0 0 0 0 0 0 0 11 0 1 0 2 0 0 0 0 0 0 0 0 0 0 0 0 3 1 0 1 1 1 1 0 0 1 2 1 1 0 0 0 0 0 6 8 4 1 0 1 0 0 0 0 0 1 2 0 0 23 1 20 11 0 0 2 0 1 0 1 0 1 2 0 1 41 7 163 15 2 1 1 1 0 0 2 0 1 1 4 2 2 202 12 128 8 6 0 0 1 0 0 0 0 0 0 7 0 10 172 0 3 3 0 0 0 0 0 0 0 0 0 0 0 0 0 6 NUMBER OF VALID HOURS 468 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2160 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 10 0 1 13 20 32 20 0 0 0 0 0 96 NNE 0 4 9 43 81 253 165 5 0 0 0 0 560 NE 5 0 10 22 31 26 18 8 0 0 0 0 120 ENE 0 5 4 11 5 8 7 1 0 1 0 0 42 E 2 3 5 9 6 14 13 3 0 0 0 0 55 ESE 0 0 5 8 7 23 31 12 6 0 0 0 92 SE 0 0 1 6 6 31 79 50 25 2 1 0 201 SSE 0 2 2 8 14 30 42 37 9 7 2 0 153 S 2 3 3 11 18 30 35 17 3 1 1 0 124 SSW 0 2 8 9 18 28 23 2 1 0 0 0 91 SW 0 1 5 14 18 32 14 5 2 1 0 0 92 WSW 0 0 5 14 19 39 24 8 4 2 0 0 115 W 0 0 0 8 22 57 67 9 6 1 0 0 170 WNW 0 0 1 6 19 21 59 16 4 0 0 0 126 NW 1 2 1 9 8 21 16 7 0 0 0 0 65 NNW 0 2 3 10 3 19 20 0 0 0 0 0 57 TOTALS 20 24 63 201 295 664 633 180 60 15 4 0 2159 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 n 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 27 321 51 15 3 4 3 1 1 0 1 3 3 15 2 13 ArQ NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2159 1 NUMBER OF CALMS TOTAL HOURS FOR-90-THE PERIOD 0 2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY April -June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01033124-01063023 WIND SPEED (M/S) AT 10 METER LEVEL EXTREMELY UNSTABLE.7b 1.0 0 0 0 0 0 0 0 0 1 2 0 0 0 0 0 0 1.1 1.5 0 0 0 0 0 0 0 0 3 2 2 3 3 0 0 0 1.6 2.0 0 0 0 0 0 0 1 3 7 6 9 22 15 2 0 0 PASQUILL A (DT/DZ < 2.1- 3 3.0 5 0 1 0 0 0 1 1 5 22 17 58 106 83 8 1 1 1.9 *.1 P.0 0 0 0 0 0 0 1 17 49 27 42 52 99 43 3 0'C/100 METERS)5.1 7.0 0 0 0 0 0 0 2 3 18 3 1 0 0 5 1 0 7.1 10.0 0 0 0 0 0 0 0 2 2 0 1 0 0 0 0 0 10.1 13.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>18 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 30 102 57 113 183 200 58 5 1 TOTALS 0 0 3 13 65 304 333 33 5 0 0 0 756 NUMBER OF VALID HOURS 756 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 'C/100 WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 1 0 0 0 0 0 0 0 0 1 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 0 1 0 0 0 0 0 0 1 W 0 0 0 1 0 0 0 0 0 0 0 0 1 WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 2 0 1 0 0 0 0 0 0 3 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 3 0 NUMBER OF CALMS TOTAL HOURS FOR-91-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW.22.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.51.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 THE PERIOD 0 2184°C/100 METERS)

II ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) METEOROLOGY April -June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01033124-01063023 WIND SPEED (M/S) AT 10 METER LEVEL UNSTABLE (-1 1.1 1.5 0 1 0 0 0 0 0 0 1 0 2 3 3 3 0 1.6 2.0 i 1 0 0 0 0 2 3 1 2 7 7 4 5 0 PASQUILL C .7 < DT/DZ : -1.5 °C/100 METERS)2.1-3.0 0 1 0 0 0 0 2 2 4 6 8 9 7 2 0 3.1 5.0 0 1 0 0 0 0 2 11 10 3 9 2 4 5 6 5.1 7.0 0 0 0 0 0 0 0 4 5 0 2 1 1 3 0 7.1 10.0 0 0 0 0 0 0 0 1 6 3 0 0 0 0 0 1U.1 13.0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 13.1 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>18 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 2 13 33 41 53 16 10 2 0 0 170 NUMBER OF VALID HOURS 170 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 'C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 1 4 0 0 0 0 6 22 30 14 28 22 19 18 6 2 5 2 10 2 11 2 3 3 1 3 6 2 5 1 11 5 10 4 10 6 14 2 11 3 17 6 7 0 5 4 5 47 131 13 9 10 1 1 5 15 21 30 13 15 10 5 6 3 6 163 4 1 0 15 0 0 0 0 0 4 0 0 14 7 0 11 15 0 26 31 6 25 44 11 37 26 13 20 27 1 20 12 3 7 3 2 2 5 2 7 12 5 15 13 1 4 2 0 211 198 44 0 0 0 0 0 0 0 3 0 0 1 0 1 0 2 0 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 27 36 23 10 27 41 85 117 122 76 74 35 37 43 42 23 818 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 818 0 NUMBER OF CALMS TOTAL HOURS FOR-92-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW.22.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.51.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 SLIGHTLY .76 1.0 0 0 0 0 0 0 0 1 1 0 0 0 0 0 0 NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS U 0 0 0 0 0 0 0 0 0 0 0 1 0 1 1 3 2 0 0 0 1 1 0 1 1 1 3 0 1 0 2 1 14 THE PERIOD 0 2184 0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY April -June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01033124-01063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5.76 1.0 1 5 3 1 1 0 0 2 0 0 0 0 0 0 2 1.1 1.5 3 15 4 2 2 2 1 1 0 0 2 0 0 0 0 1 1.6 2.0 0 16 2 1 2 1 1 0 1 1 1 0 0 0 1 2< DT/DZ 2.1 3.0 3 8 1 0 2 0 3 1 0 0 1 0 3 1 3 1< 1.5 3.1 5.0 1 7 1 0 0 0 0 0 1 0 0 0 1 5 0 0°C/100 METERS) 5.1- 7.1 7.0 10.0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 1 0 0 0 10.1 13.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>18 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 53 13 4 7 5 5 2 5 1 4 2 4 9 5 6 TOTALS 3 5 16 33 29 27 16 4 0 0 0 0 133 NUMBER OF VALID HOURS 133 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 PASQUILL F MODERATELY STABLE (1.5 DT/DZ 4.0 °C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 2 1 1 3 0 0 0 0 0 7 NNE 0 2 2 19 33 46 4 0 0 0 0 0 106 NE 0 1 4 5 2 0 0 0 0 0 0 0 12 ENE 0 0 1 4 0 2 0 0 0 0 0 0 7 E 0 1 0 1 0 0 0 0 0 0 0 0 2 ESE 0 0 0 1 0 0 0 0 0 0 0 0 1 SE 0 0 0 1 0 0 1 0 0 0 0 0 2 SSE 0 0 0 0 0 1 0 0 0 0 0 0 1 S 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 1 0 0 0 0 0 0 0 1 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 1 1 0 0 0 0 0 0 0 2 W 0 0 0 0 0 0 0 0 0 0 0 0 0 WNW 0 0 0 0 1 0 0 0 0 0 0 0 1 NW 0 0 0 1 0 1 0 0 0 0 0 0 2 NNW 0 0 1 0 0 0 0 0 0 0 0 0 1 TOTALS 0 4 8 35 39 51 8 0 0 0 0 0 145 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 145 0 NUMBER OF CALMS TOTAL HOURS FOR-93-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW.22.50 0 0 0 0 0 1 0 0 1 0 0 0 0 1 0 0.51.75 0 1 2 0 0 0 0 0 0 0 0 2 0 0 0 0 THE PERIOD 0 2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) METEOROLOGY April -June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01033124-01063023 WIND SPEED (M/S) AT 10 METER LEVEL EXTREMELY STABLE .76- 1.1- 1.6 1.0 1.5 2.0 1 0 2 0 3 10 1 1 2 1 0 0 0 0 1 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 5 16 PASQUILL G (DT/DZ > 4 2.1 3.0 1 73 4 1 0 0 1 0 0 0 0 0 1 0 0 0 81.0 *C/100 METERS) _____.1 5.0 5 43 1 0 0 0 0 0 0 0 0 0 0 0 1 0 50 5.1 7.0 0 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 7.1 10.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.1 13.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0-3 00 159 NUMBER OF VALID HOURS 159 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0>18 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 9 132 9 2 1 1 1 1 1 0 0 0 1 0 1 0 NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS u 0 0 0 0 1 0 0 1 0 0 0 1 1 1 1 6 2 3 3 0 2 2 0 1 1 1 3 2 1 0 2 1 24 9 10 5 4 4 2 2 9 6 6 2 3 6 0 7 79 1u 48 21 9 4 9 7 12 15 13 20 18 24 10 6 6 232 17 69 16 2 4 6 19 28 39 23 32 40 24 14 4 8 345 9 10 144 55 5 2 7 0 16 7 12 15 33 35 34 72 63 86 43 57 87 63 123 57 96 109 18 65 20 23 6 2 716 658 0 4 0 0 0 0 8 18 36 4 6 3 3 15 3 0 100 0 0 0 0 0 0 0 6 8 3 2 0 1 0 2 0 22 0 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 52 332 57 23 37 49 104 173 260 150 219 245 262 129 61 31 2184 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2184 0 NUMBER OF CALMS TOTAL HOURS FOR-94-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS.22.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.51.75 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1 THE PERIOD 0 2184.0 °C/lO0 METERS)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY July -September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01063024-00093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ < -1.9 -C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 1 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 2 0 2 0 0 0 0 0 4 S 0 0 0 0 2 12 17 2 0 0 0 0 33 SSW 0 0 0 1 2 10 18 0 0 0 0 0 31 SW 0 0 0 0 10 35 14 0 0 0 0 0 59 WSW 0 0 1 3 13 76 66 1 0 0 0 0 160 W 0 0 0 0 7 62 157 1 0 0 0 0 227 WNW 0 0 0 0 3 22 65 4 0 0 0 0 94 NW 0 0 0 0 1 3 5 1 0 0 0 0 10 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 1 4 40 221 344 9 0 0 0 0 619 NUMBER OF VALID HOURS 619 NUMBER OF CALMS 2 NUMBER OF INVALID HOURS 2 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 °C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 1 1 0 0 0 0 2 SSW 0 0 0 0 3 0 0 0 0 0 0 0 3 SW 0 0 0 0 0 5 0 0 0 0 0 0 5 WSW 0 0 0 0 1 8 1 0 0 0 0 0 10 W 0 0 0 1 3 6 1 0 0 0 0 0 11 WNW 0 0 0 0 1 2 1 1 0 0 0 0 5 NW 0 0 0 0 0 0 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 1 8 21 5 2 0 0 0 0 37 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 37 2 NUMBER OF CALMS TOTAL HOURS FOR-95-THE PERIOD 2 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) METEOROLOGY July -September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01063024-01093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ < -1.5 °C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 1 1 0 0 0 0 0 0 2 NE 0 0 0 0 0 1 0 0 0 0 0 0 1 ENE 0 0 0 0 0 1 0 0 0 0 0 0 1 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 1 0 0 0 0 0 0 1 SSE 0 0 0 0 1 2 2 0 0 0 0 0 5 S 0 0 1 2 0 3 0 2 0 0 0 0 8 SSW 0 0 0 1 2 6 2 0 0 0 0 0 11 SW 0 0 0 1 1 10 7 0 0 0 0 0 19 WSW 0 0 0 2 1 7 2 0 0 0 0 0 12 W 0 0 0 2 3 7 2 0 0 0 0 0 14 WNW 0 0 0 0 2 6 2 0 0 0 0 0 10 NW 0 0 0 0 0 2 4 0 0 0 0 0 6 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 1 8 11 47 21 2 0 0 0 0 90 NUMBER OF VALID HOURS 90 NUMBER OF CALMS 2 NUMBER OF INVALID HOURS 2 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 'C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 2 24 9 6 0 0 0 0 0 0 42 NNE 0 1 2 19 21 22 2 0 0 0 0 0 67 NE 0 1 4 16 13 8 0 0 0 0 0 0 42 ENE 0 0 2 2 2 6 0 0 0 0 0 0 12 E 1 0 2 3 5 11 2 0 0 0 0 0 24 ESE 0 0 0 3 3 7 2 0 0 0 0 0 15 SE 1 0 2 5 10 32 29 1 0 0 0 0 80 SSE 0 1 2 12 20 50 41 1 0 0 0 0 127 S 0 0 2 13 23 39 48 4 0 0 0 0 129 SSW 1 1 5 14 27 30 24 1 0 0 0 0 103 SW 0 1 14 18 31 24 17 0 0 0 0 0 105 WSW 0 2 8 16 19 19 6 0 0 0 0 0 70 W 0 1 9 23 19 11 9 0 0 0 0 0 72 WNW 0 1 5 10 18 20 12 0 0 0 0 0 66 NW 0 2 2 15 10 9 12 2 0 0 0 0 52 NNW 0 1 3 13 8 4 1 0 0 0 0 0 30 TOTALS 3 13 64 206 238 298 205 9 0 0 0 0 1036 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 1036 2 NUMBER OF CALMS TOTAL HOURS FOR-96-THE PERIOD 2 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY July -September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01063024-01093023 WIND SPEED (M/S) AT 10 METER LEVEL SLIGHTLY STABLE (-0.76 1.0 1 8 4 3 1 3 2 2 0 1 0 2 1 1 1 3 1.1 1.5 10 19 9 2 3 4 3 3 3 0 0 3 2 0 1 6 1.6 2.0 8 25 2 2 1 0 1 7 5 0 0 1 2 0 2 1 PASQUILL E .5 < DT/DZ 2.1- 3 3.0 5 15 20 0 0 1 0 10 10 1 2 2 2 0 3 2 1 1.5 .1.0 2 4 0 0 2 2 1 2 0 1 0 0 0 6 4 0-C/100 METERS) 5.1- 7.1 7.0 10.0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 TOTALS 5 19 33 68 57 69 24 4 1 0 0 0 280 NUMBER OF VALID HOURS 280 NUMBER OF CALMS 2 NUMBER OF INVALID HOURS 2 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 'C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 1 1 1 5 4 7 1 0 0 0 0 0 20 NNE 0 0 1 7 10 28 1 0 0 0 0 0 47 NE 0 1 0 1 0 2 0 0 0 0 0 0 4 ENE 0 0 1 0 0 1 0 0 0 0 0 0 2 E 0 0 0 1 0 0 0 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 1 0 0 0 0 0 0 0 0 0 0 0 1 SSE 0 0 0 0 1 1 0 0 0 0 0 0 2 S 0 1 0 1 0 1 0 0 0 0 0 0 3 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 1 0 1 0 0 0 0 0 0 0 2 WSW 0 0 0 0 0 0 0 0 0 0 0 0 0 W 0 0 0 0 0 2 0 0 0 0 0 0 2 WNW 0 0 0 2 0 1 1 0 0 0 0 0 4 NW 0 0 0 0 2 0 1 0 0 0 0 0 3 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 2 3 4 17 18 43 4 0 0 0 0 0 91 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 91 2 NUMBER OF CALMS TOTAL HOURS FOR-97-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW.22.50 1 0 0 0 1 0 0 0 0 0 0 0 0 0>18 TOTAL.51.75 3 5 1 2 1 1 2 0 2 1 0 0 0 1 0 0 10.1 13.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 40 82 16 9 10 11 22 24 11 5 2 9 5 11 12 11 THE PERIOD 2 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) METEOROLOGY July -September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01063024-01093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 -C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 1 1 0 0 0 0 0 2 NNE 0 0 0 0 7 28 9 1 0 0 0 0 45 NE 0 0 0 2 0 0 0 0 0 0 0 0 2 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 1 0 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 0 0 0 0 0 0 W 0 0 1 0 0 0 0 0 0 0 0 0 1 WNW 0 0 0 1 0 0 0 0 0 0 0 0 1 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 1 0 0 0 0 0 0 0 0 1 TOTALS 0 0 1 4 7 30 10 1 0 0 0 0 53 NUMBER OF VALID HOURS 53 NUMBER OF CALMS 2 NUMBER OF INVALID HOURS 2 TOTAL HOURS FOR THE PERIOD 2208 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 1 0 0 2 1 2 0 0 1 0 1 0 0 0 0 10 5 6 3 2 1 1 2 1 3 2 1 2 1 2 2 1 35 4 11 8 6 3 3 4 4 3 6 15 11 11 6 3 6 104 45 28 4 7 7 8 15 19 16 19 24 28 13 16 20 308 21 29 4 0 64 100 16 1 15 11 0 0 4 8 0 0 6 12 4 0 3 7 4 0 11 44 30 3 31 63 47 1 30 56 66 9 34 48 45 1 43 76 38 0 35 112 75 1 34 88 169 1 24 54 87 5 15 16 27 5 9 5 1 0 379 729 613 27 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2206 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 104 244 65 24 35 26 105 162 186 153 192 261 332 191 84 42 2206 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2206 2 NUMBER OF CALMS TOTAL HOURS FOR-98-114 NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS THE PERIOD 2 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY October -December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01093024-01123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ < -1.9 °C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0. NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 1 1 0 0 0 0 0 2 SSE 0 0 0 1 3 2 1 1 0 0 0 0 8 S 0 0 0 1 3 8 6 1 0 0 0 0 19 SSW 0 0 0 4 3 5 2 0 0 0 0 0 14 SW 0 0 0 6 10 13 3 0 0 0 0 0 32 WSW 0 0 0 3 20 32 12 0 0 0 0 0 67 W 0 0 0 2 14 102 45 2 0 0 0 0 165 WNW 0 0 0 0 2 21 53 10 0 0 0 0 86 NW 0 0 0 0 2 0 0 1 0 0 0 0 3 NNW 0 0 1 0 0 0 0 0 0 0 0 0 1 TOTALS 0 0 1 17 57 184 123 15 0 0 0 0 397 NUMBER OF VALID HOURS 397 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ g -1.7 'C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 2 1 0 0 0 0 0 3 S 0 0 0 0 0 3 1 0 0 0 0 0 4 SSW 0 0 0 0 0 4 3 0 0 0 0 0 7 SW 0 1 0 0 1 4 0 0 0 0 0 0 6 WSW 0 0 0 0 4 0 0 0 0 0 0 0 4 W 0 0 1 0 0 4 2 0 0 0 0 0 7 WNW 0 0 0 1 2 5 3 1 0 0 0 0 12 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 1 1 1 7 22 10 1 0 0 0 0 43 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 43 1 NUMBER OF CALMS TOTAL HOURS FOR-99-THE PERIOD 0 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) METEOROLOGY October -December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01093024-01123123 WIND SPEED (M/S) AT 10 METER LEVEL UNSTABLE (-1 1.1 1.5 0 0 0 0 0 0 0 0 0 0 0 1 0 0 1 0 1.6 2.0 0 1 0 0 0 0 0 0 1 1 1 0 2 0 0 0 PASQUILL C .7 < DT/DZ < -1.5 °C/100 METERS)2.1 3.0 0 0 0 0 0 0 0 0 4 1 1 2 1 0 1 0 3.1 5.0 0 1 0 0 0 0 1 0 4 0 1 0 3 1 0 5, 7,.1.- 7.1- 10.1- 13.1.0 10.0 13.0 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0>18 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 0 0 0 1 1 5 7 3 4 3 3 4 0 TOTALS 0 0 0 2 6 10 12 3 1 0 0 0 34 NUMBER OF VALID HOURS 34 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 °C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 2 4 6 2 3 1 0 0 0 0 18 NNE 0 1 0 4 4 7 9 2 0 0 0 0 27 NE 0 0 1 1 2 2 1 1 0 0 0 0 8 ENE 0 0 1 1 0 1 0 0 0 0 0 0 3 E 0 2 0 2 0 0 0 0 0 0 0 0 4 ESE 0 2 0 0 1 2 1 0 1 0 0 0 7 SE 0 0 0 0 1 9 13 3 3 0 0 0 29 SSE 0 0 1 6 10 19 23 5 3 0 0 0 67 S 0 1 2 7 7 15 13 2 0 0 0 0 47 SSW 0 0 1 7 7 17 9 0 0 0 0 0 41 SW 0 0 2 4 6 14 4 0 0 0 0 0 30 WSW 0 0 1 3 4 4 3 0 0 0 0 0 15 W 0 1 1 7 4 4 2 3 0 0 0 0 22 WNW 0 1 1 7 5 16 10 1 0 0 0 0 41 NW 0 0 1 1 4 11 16 4 0 0 0 0 37 NNW 0 0 0 3 5 7 4 1 0 0 0 0 20 TOTALS 0 8 14 57 66 130 111 23 7 0 0 0 416 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 416 1 NUMBER OF CALMS TOTAL HOURS FOR-100-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW.22.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.51.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 SLIGHTLY .76 1.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 THE PERIOD 0 2208. 7.I I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY October -December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01093024-01123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 .51- .76- 1.1- 1.6.75 1.0 1.5 2.0 2 4 17 13 2 8 12 29 1 8 4 5 3 2 5 2 0 2 4 2 0 2 2 2 1 0 5 8 1 2 6 11 1 3 3 5 0 3 4 2 0 2 4 2 2 1 3 2 2 3 1 3 0 4 9 2 2 1 6 5 1 2 6 4< DT/DZ 1.5 2.1 3.0 23 28 6 4 5 5 24 14 7 0 3 2 3 8 12 12 3.1 5.0 6 27 2 0 0 3 19 5 4 2 0 0 1 3 9 5-C/100 METERS) 5.1- 7.1 7.0 10.0 1 0 2 0 0 2 0 0 0 0 2 0 6 1 1 1 0 0 0 3 2 1 0 1 1 2 8 0 3 0 0 0 10.1 13.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1 18.0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0>18 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 67 110 28 16 13 17 64 43 23 14 14 11 16 35 38 30 TOTALS 6 18 47 91 97 156 86 26 11 0 1 0 539 NUMBER OF VALID HOURS 539 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 °C/100 METERS) WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 3 6 6 13 8 0 0 0 0 0 36 NNE 0 0 4 26 41 55 21 4 1 0 0 0 152 NE 0 3 7 8 12 4 2 2 0 0 0 0 38 ENE 0 1 0 2 1 2 0 0 0 0 0 0 6 E 0 1 0 3 1 0 0 0 0 0 0 0 5 ESE 0 1 0 0 0 3 0 0 0 0 0 0 4 SE 0 1 0 3 0 0 3 0 0 0 0 0 7 SSE 0 0 0 2 0 1 1 0 0 0 0 0 4 S 0 0 0 0 1 0 0 0 0 0 0 0 1 SSW 0 0 0 1 0 0 0 0 0 0 0 0 1 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 1 0 0 0 0 0 0 0 0 1 W 0 0 0 1 1 1 1 0 0 1 0 0 5 WNW 0 0 0 0 0 2 0 0 0 0 0 0 2 NW 0 0 0 0 0 1 1 0 0 0 0 0 2 NNW 0 1 0 3 2 5 0 0 0 0 0 0 11 TOTALS 0 8 14 56 65 87 37 6 1 1 0 0 275 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 275 1 NUMBER OF CALMS TOTAL HOURS FOR-101-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW.22.50 1 2 0 0 0 1 0 1 0 0 0 0 0 1 0 0 THE PERIOD 0 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)METEOROLOGY October -December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01093024-01123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G 1 EXTREMELY STABLE 76- 1.1- 1.6.0 1.5 2.0 1 2 1 1 4 25 1 4 7 0 2 2 0 1 1 0 1 1 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 1 0 0 1 3 15 41 (DT/DZ > 2.1 3.0 13 181 9 1 0 0 0 2 0 0 0 0 0 2 0 1 209 4.0 'C/100 METERS)3.1 5.0 8 206 5 0 0 0 0 1 0 0 0 0 0 1 0 0 221 5.1 7.0 0 14 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7.1 10.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S14. 0 0 0 0 03 NUMBER OF VALID HOURS 503 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2208 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 lU.1 13.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.1 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS 1 2 0 0 0 1 0 1 0 0 0 0 0 1 0 0 6 2 3 4 4 3 3 2 1 2 0 1 2 3 1 2 2 35 1U 13 17 3 2 2 0 3 5 4 4 2 5 5 2 3 80 29 46 17 10 10 3 8 15 11 16 14 11 11 17 9 12 239 26 100 26 5 4 4 9 25 17 13 20 30 24 12 12 12 339 51 271 21 8 5 10 34 40 37 27 35 40 115 54 25 25 798 25 264 11 0 0 4 36 33 24 20 7 16 51 73 27 9 600 2 22 3 0 0 2 10 7 3 1 3 0 6 20 8 1 88 0 1 2 0 0 1 4 4 0 3 1 1 2 0 1 0 20 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T 146 722 101 30 24 51 103 130 99 84 85 102 218 183 86 64 2207 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2207 I NUMBER OF CALMS TOTAL HOURS FOR 102-WIND DIR N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTALS.22.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.51.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0>18 TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 25 431 26 5 2 2 0 4 0 0 0 0 0 4 2 2 THE PERIOD 0 2208 4.0 °C/lO0 METERS)i

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