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{{#Wiki_filter: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  
{{#Wiki_filter:A Edward Scherer I           EDISON SOUTHERN CALIFORNIA An EDISON INTERNATIONAL"' Compan.*
Manager of Nuclear Oversight and Regulatory Affairs April 23, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555


==Subject:==
==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:
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).
This letter provides the Annual Radioactive Effluent Release Report (ARERR) for 2001.
If you require additional information, please contact me or Mr. Clay Williams at (949) 368-6707.
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).
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
Ifyou require additional information, please contact me or Mr. Clay Williams at (949) 368-6707.
/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.
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                                                                     /Yoo Fax 949-368-6085
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%).
SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2001 January - December
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
I*          EDISON SOUTHERN CALIFORNIA An VIlSOA \I     R 17I10, I/,'" CUmlpan 7*I*\
...... ................
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.
-LIQUID EFFLUENTS  
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%),
-PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADl -RADWASTE SHIPMENTS
and the City of Riverside (1.79%).
..............   
R 0. Box 128 San Clementc, CA 92674-0128 Cl) m 0a z
-APPLICABLE LIMITS ...... ................
 
-ESTIMATION OF ERROR ..... ...............
TABLE OF CONTENTS SECTION A - INTRODUCTION   . . . . . . . . . . . . . . . . .         . . . . . . . . . . 1
-10 CFR 50 APPENDIX I REQUIREMENTS
                                                                    . . . . . . . . . . 2 SECTION B - GASEOUS EFFLUENTS ......               ................
..........
                                                                    . . . . . . .  . . . 8 SECTION C - LIQUID EFFLUENTS  ...............
-CHANGES TO OFFSITE DOSE CALCULATION MANUAL -CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS -MISCELLANEOUS
SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADlDENDUM ....           ....... 17 SECTION E - RADWASTE SHIPMENTS    ..............                   S. . . . . . . ..   . 21 SECTION F - APPLICABLE LIMITS ......               ................     . . . . . . ..   . 24 SECTION G - ESTIMATION OF ERROR .....               ...............     . . . . . . ..   . 26 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS ..........                 . . . . . . ..   . 27 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL                  . . . . . . ..   . 31 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS              . . . . . . ..   . 32 SECTION K - MISCELLANEOUS ........             .................       . . . . . . ..   . 33 SECTION L - S.O.N.G.S. 1 CONCLUSIONS          . . .               . . . . . . . . ..     . 35
........ .................
                                                  -ii-
..........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
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
...-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:
January - December SFfTTMN v*v .......................
: 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
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
: 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
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:
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.
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.
Listed for each of the four categories are:
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.
(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:
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.
fission gases,     iodines, and particulates.         The total radioactivity for each radionuclide is listed     for each quarterly   period by "continuous" mode of release.
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.
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 IC for continuous mode releases only.
As of 8/4/93, "batch" mode releases are no longer conducted because of the permanent shutdown of the reactor.
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 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 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
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
: 1. Particulates with half-lives  
S.O.N.G.S. 1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First  Second    Total Unit Quarter  Quarter 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, %
A. Fission and activation gases
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 1. Total release                             Ci     <LLD     <LLD   3.OOE+l
I TABLE 1A (Continued)
: 2. Average release rate for period       4Ci/sec O.OOE+O   O.OOE+O
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  
: 3. Percent of applicable limit             % MPC O.OOE+O   O.OOE+O
>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 hours. 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.
: 4. Percent Effluent Concentration Limit   % ECL O.OOE+O   O.OOE+O B. Iodines
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 1. Total iodine-131                           Ci     <LLD     <LLD   1.90E+1
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.
: 2. Average release rate for period       uCi/sec O.OOE+O   O.OOE+O
1, "BATCH MODE" releases are no longer conducted.
: 3. Percent of applicable limit             % MPC O.OOE+O   O.OOE+O
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 4. Percent Effluent Concentration Limit   % ECL O.OOE+O   O.OOE+O C. Particulates
1 TABLE ID GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (,uCi/cc)
: 1. Particulates with half-lives >8 days       Ci     <LLD     <LLD   1.60E+1
: 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.
: 2. Average release rate for period       gCi/sec O.OOE+O O.OOE+O
1, "BATCH MODE" longer conducted.
: 3. Percent of applicable limit             % MPC   O.OOE+O O.OOE+O
releases are no
: 4. Percent Effluent Concentration Limit   % ECL   O.OOE+O O.OOE+O
-- -- -- --- --U L ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 5. Gross alpha activity                     Ci   1.62E-7 5.43E-8 5.OOE+1 D. Tritium
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. Total release                             Ci   2.14E-1 3.51E-1 2.50E+1
: 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  
: 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
 
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
S.O.N.G.S. I TABLE 1A (Continued)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third    Fourth        Total Unit     Quarter   Quarter       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           __
(1) On 8/27/01, plant vent stack particulate and iodine samples were not collected for 7 hours. 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 OF DETECTION CONTINUOUS MODE 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" releases are no longer conducted.
 
                                                                                                  -- -- -- - -- --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==
==SUMMARY==
NOTE: Due to the permanent shutdown of S.O.N.G.S.
 
1, "BATCH MODE" releases are no longer conducted.
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:
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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)
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:
(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.
(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:
The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.
(1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)
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.
(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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
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.
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
Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B.
: 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.
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.
1 TABLE 2A (Continued)
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.
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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.
S.O.N.G.S. 1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second     Total Unit Quarter Quarter Error, %
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
A. Fission and activation products
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.
: 1. Total release (not including tritium, gases, alpha)                     Ci   2.47E-7 3.11E-6   1.90E+1
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 2. Average diluted concentration during period                                 gCi/ml 1.56E-13 1.93E-12
1 TABLE 2B (Continued)
: 3. Percent of applicable limit             % MPC 7.82E-7 9.66E-6
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.
: 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
I_ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 2. Average diluted concentration during period                                 ,uCi/ml 8.42E-9 3.25E-10
1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION-13-Radionuclides LLD (,uCi/cc)
: 3. Percent of applicable limit             % MPC 2.81E-4 1.08E-5
: 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.
: 4. Percent Effluent Concentration Limit     % ECL 8.42E-4 3.25E-5 C. Dissolved and entrained gases
1 TABLE 2C (Continued)
: 1. Total release                               Ci     <LLD   <LLD   1.90E+1
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-14-Radionuclides LLD (/uCi/cc)
: 2. Average diluted concentration during period                                   MCi/ml O.OOE+O O.OOE+O
: 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.
: 3. Percent of applicable limit               % MPC O.OOE+O O.OOE+O
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.
: 4. Percent Effluent Concentration Limit     % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity
I TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE  
: 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 Estimated Third      Fourth        Total Unit     Quarter     Quarter     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 (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 OF DETECTION CONTINUOUS MODE 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 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 1anthanum-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
 
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
S.O.N.G.S. I TABLE 2D LIQUI[ D EFFLUENTS-RADIATION DOSES AT THE LIOUID SITE BOLJNDARY 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==
==SUMMARY==
12 month period 1. Number of batch releases:
 
1 release 2. Total time period for batch releases:
12 month period
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:
: 1. Number of batch releases:                                       1 release
6650 gpm ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 2. Total time period for batch releases:                         1380 minutes
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.
: 3. Maximum time period for a batch release:                     1380 minutes
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.
: 4. Average time period for a batch release:                     1380 minutes
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.
: 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 Radionuclides Released      I            Unit                Fourth Quarter
: 1. 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
 
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.
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)
i I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
S.O.N.G.S. I SECTION D.     PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)
: 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
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
 
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
S.O.N.G.S. 1 SECTION D.      PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)
Section H.      10CFR50 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 NWsector.
: 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 NWsector.
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,                  m3        N/A evaporator bottoms Ci          N/A      N/A
: b. Dry active waste (DAW),                          m3      2.52E+3 compactable and non-compactable
* Ci
_________
1.29E+0-  3.00E+1
: c. Irradiated components,    control            m3          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 (2001)
S.O.N.G.S. I
: 3. Solid Waste Disposition 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.
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments          Mode of Transportation                Destination None                No shipments were made                      N/A
 
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              (Re]      Rate)      (X/O) (100)
MPCeff where:    Rel Rate              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.
X/Q                    1.30E-5 sec/m 3 ; the annual average atmospheric dispersion defined in the Unit 1 ODCM.
1 MPCelf                              n      F.
                                          =1i MPC where:  Fj                      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.
n                      total number of radionuclides identified MPC,                    Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.
&    %ECL                            - (Rel    Rate)      (X/0) (100)
ECLeff where:    Rel Rate                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.
X/Q                      1.30E-5 sec/m 3 ; the annual average atmospheric dispersion defined in the Unit 1 ODCM.
1 0    ECLeuf                                n    F.
M1 ECL i where:    Fj                      fractional abundance of the i th radionuclide obtained by dividing the activity (curies) for each radionuclide,    C1 , by the sum of all the isotopic activity,  CT.
n                        total number of radionuclides identified ECL,                    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                (Dil  Conc)    (100)
MPCeff where:  Dil Conc                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 MPCeff i  MPC i where:  F,                      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,.
n                      total number of radionuclides identified MPCi                    Maximum Permissible Concentration (MPC) of the i t h radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.
0    % ECL                            (Dil Conc) (100)
ECLeff where:  Dil Conc                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.
ECLeff i~i 11  ECL
[CLIi where:  F7                      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.
n                      total  number of radionuclides identified ECLj                  Effluent Concentration Limit (ECL) of the i th 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+  Y3c+        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 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
* 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.
1 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. 1OCFR50 Appendix I Requirements TABLE 1 (1999) Dose * (millirems)
: 1. This value was calculated using the methodology of thie ODCM.
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
: 2. This value was calculated using the methodology of thie ODCM.
: 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
: 3. This value was calculated using the methodology of thie ODCM.
* 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.
: 4. This value was calculated using the methodology of thie ODCM.
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
: 5. This value was calculated using the methodology of thie ODCM.
* _________
 
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
(*) Material packaged in strong, tight containers of various sizes. N/A No shipment made.
S.O.N.G.S. I
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 6. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
1 2. Estimate of major nuclide composition (by type of waste) a. not applicable
: 7. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
_ N/A b. americium-241
: 8. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
% 4.37E-2 carbon-14
: 9. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
% 5.86E-1 cerium-144
: 10. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
_ 1.87E-2 cesium-134
: 11. The maximum organ dose was to a child's thyroid and was located in      the NW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
% 1.50E+O cesium-137
: 12. The maximum organ dose was to a child's thyroid and was located in the NW sector.       This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
% 1.24E+1 cobal t-60 % 4.19E+1 curium-242
: 13. The maximum organ dose was to a child's thyroid and was located in the NW sector.       This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
% 3.72E-3 curium-243/244
: 14. The maximum organ dose was to a child's thyroid and was located in the NW sector.       This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
% 1.04E-2 iron-55 % 2.92E+1 iron-59 % 7.22E-2 nickel-63
: 15. The maximum organ dose was to a child's thyroid and was located in the NW sector.       This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
% 1.24E+1 niobium-94
: 16. There was no activity detected during the release period,    therefore the reported air dose for gamma radiation was O.OOE+O mrad.
__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
: 17. There was no activity detected during the release period,    therefore the reported air dose for gamma radiation was O.OOE+O mrad.
__1.46E-1
: 18. There was no activity detected during the release period,    therefore the reported air dose for gamma radiation was O.OOE+O mrad.
: c. not applicable
: 19. There was no activity detected during the rel ease period,  therefore the reported air dose for gamma radiation was O.OOE+O mrad.
__N/A d. not applicable
: 20. There was no activity detected during the rel ease period,  therefore the reported air dose for gamma radiation was O.OOE+O mrad.
__N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT S.O.N.G.S.
: 21. There was no activity detected during the rel ease period, therefore the reported air dose for beta radiation was O.OOE+O mrad.
I Number of Shipments Mode of Transportation Destination 30
: 22. There was no activity detected during the rel ease period, therefore the reported air dose for beta radiation was O.OOE+O mrad.
* Hitman Trucking Company EnviroCare, UT Truck/Trailer 2 MHFLogistical Solutions EnviroCare, UT Truck/Trailer 96 MHFLogistical Solutions EnviroCare, UT Rail
: 23. There was no activity detected during the rel ease period,  therefore  the reported air dose for beta radiation was O.OOE+O mrad.
* SONGS maintains a contract with vendor (GTS) that provides volume reduction services.
: 24. There was no activity detected during the rel ease period,  therefore  the reported air dose for beta radiation was O.OOE+O mrad.
These shipments were made from their processing facility.
 
The thirty shipments made from this facility included waste from other generators.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
SCE's waste volume was a small fraction of the total waste volume of these shipments.
S.O.N.G.S. 1
IRRADIATED FUEL SHIPMENTS (Disposition)
: 25. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.
Number of Shipments Mode of Transportation Destination None No shipments were made N/A-23-3. Solid Waste Disposition B.(2001)
: 26. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the W sector.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the W sector.
1 SECTION F. APPLICABLE LIMITS Gaseous Effluents
: 28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the WSW sector.
-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.
: 29. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the WSW sector.
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.
: 30. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the W sector.
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.
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 Liquid Effluents
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
-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:
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:
% 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.
: 1. Removal of Sewage Treatment Plant as an effluent pathway,
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 2. Change to 6.3.3.1.a to require ODCM updates be made in accordance with applicable regulations rather than 10CFR50.59, {due to changes in the 10CFR50.59 program}
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
: 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
-batch releases are: (1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for gaseous effluents
: 4. Changes related to the Land Use Census update.
-continuous releases are: (1) fan flow rate (2) sampling (3) counting (4) calibration (5) differential pressure drop Sources of error for liquid effluents
Safety evaluations were provided for items 1 and 2.
-batch releases are: (1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for liquid effluents
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.
-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.  
Per NRC Generic Letter 89-01, no safety reviews were required or performed              for editorial changes or changes made to reflect actual plant operation.
.1I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations.       The level of radioactive effluent control required by IOCFR20, 40CFR190, 10CFR5O.36a, and Appendix I to 10CFR50 will be maintained.
1 SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table I in Section H presents the quarterly and annual maximum dose to an individual.
Throughout the document, change bars are marked in one of four ways as follows:
Six different categories are presented:
A       Addition D        Deletion F        Editorial/Format change R        Revision The following is a complete list of the changes:
(1) Liquid Effluents
PAGE        CHANGE                                                            REASON TOC        Renumbered pages as necessary based on changes in the body of the F ODCM.
-Whole Body (2) Liquid Effluents
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.
-Organ (3) Airborne Effluents
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.
-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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
Each portion of each category is footnoted to briefly describe each maximum individual dose presented.
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.
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.
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.
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.
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
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.
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)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS
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.
: 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
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.
: 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.
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.
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
This value was calculated using the methodology of the ODCM; the liver primarily by the saltwater fish pathway.
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 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.
This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
R-2101            05/18/01 - 08/16/01  Monitor failure      Monitor exhibited spurious readings Yard Drain Sump                        alarms              and intermittent inoperability.
This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
Monitor                                                      Investigationidentified solar heating of a junction box as the cause. Housing was constructed to correct the problem that is documented in AR 010701251.
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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 hours 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 hours 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 hours 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 hours 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 hours 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.
S.O.N.G.S. I SECTION L. S.OQ.N.G.S. 1 CONCLUSIONS S.O.N.G.S. I 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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
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.
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.
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.
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.
The radiation doses from liquid releases were: (a) total body: 1.56E-2 mrem,  (b) limiting organ: 3.45E-2 mrem.
None of the changes impact the accuracy or reliability of effluent dose or calculations.
The radioactive releases and resulting doses generated from Unit 1 were below the Applicable Limits for both gaseous and liquid effluents.
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.
Cl) z Cl)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
CL W.
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.
TABLE OF CONTENTS
R 5-24 Corrected mileage for PIC 57. R 6-3 Added word response to MGPI portion of Source Check definition.
                          ...........                                                    S. ..  . 36 SECTION A - INTRODUCTION SECTION B - GASEOUS EFFLUENTS .... ...........                                S. . . . . . . .. .     37 SECTION C - LIQUID EFFLUENTS        ..........                                S. . . . . . . ..    . 47
Was R inadvertently omitted previously.
                                                                                          ....... 56 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADD ENDUM ....
6-10 Changed "10CFR50.59" to "applicable regulations".
S. . . . . . . ..     . 63 SECTION E - RADWASTE SHIPMENTS          .........
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.
S. . . . . . . ..    . 66 SECTION F - APPLICABLE LIMITS .... ...........
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
S. . . . . . . ..     . 68 SECTION G - ESTIMATION OF ERROR .............
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.
S. . . . . . . ..     . 69 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS . .
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.
S. . . . . . . ..     . 73 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS S. . . . . . . .       . 75 S. . . . . . . ..     . 75 SECTION K - MISCELLANEOUS ......                 ...................
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.
S.O.N.G.S. 2 and 3 CONCLUSIONS                          ........  .. . . . . . . ..     . 77 SECTION L -
Therefore there were no dose consequences to members of the public as a result of this event that is documented in AR 010801574.
                                                          -iii-
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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.
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:
Monitor Investigationidentified solar heating of a junction box as the cause. Housing was constructed to correct the problem that is documented in AR 010701251.
: 1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 2. Percent of Applicable Limits
I SECTION L.S.OQ.N.G.S.
: 3. Estimated Total Percent Error
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.
: 4. Lower Limit of Detection Concentrations
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
: 5. Batch Release Summaries
: 6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments
: 6. Previous Radioactive Effluent Release Report Addendum
: 8. 10 CFR 50 Appendix I Requirements
: 7. Radwaste Shipments
: 9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 8.     10 CFR 50 Appendix I Requirements
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:
: 9. Changes to Offsite Dose Calculation Manual
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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.
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:
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.
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.
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.
Waste gas decay tank releases are considered to be "batch" 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.
Containment purges and plant stack releases are considered to be "continuous" releases.
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 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 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
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
: 1. Particulates with half-lives  
S.O.N.G.S. 2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First   Second   Total Unit  Quarter  Quarter Error, %
>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.
C. Fission and activation gases
2 and 3 TABLE 1A (Continued)
: 1. Total release                               Ci   3.22E+1 8.98E+O 3.OOE+1
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
: 2. Average release rate for period         4Ci/sec 4.14E+O 1.15E+O
: 1. Particulates with half-lives  
: 3. Percent of applicable limit               % MPC 9.94E-3 4.15E-3
>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.
: 4. Percent Effluent Concentration Limit     % ECL   1.89E-2 1.17E-2 D. Iodines
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.
: 1. Total iodine-131                           Ci   2.24E-3 1.77E-5 1.90E+1
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 2. Average release rate for period         4Ci/sec 2.88E-4 2.25E-6
2 and 3 TABLE IC (Continued)
: 3. Percent of applicable limit               % MPC 1.38E-3 1.08E-5
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.
: 4. Percent Effluent Concentration Limit     % ECL 6.91E-4 5.40E-6 E. Particulates
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 1. Particulates with half-lives >8 days       Ci   1.37E-3 4.78E-5 1.60E+1
2 and 3 TABLE IC (Continued)
: 2. Average release rate for period         uCi/sec 1.76E-4 6.08E-6
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.
: 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.
* 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)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
: 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
S.O.N.G.S. 2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionucl ides                                       LLD (/.tCi/cc)
: 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.
: 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 and 3 TABLE ID (Continued)
: 2. lodines iodine-132                                             6.OOE-1O iodine-135                                             1.70E-10
GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE-44-Radionuclides LLD (/,&#xfd;Ci/cc)
: 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
: 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)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
: 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.
S.O.N.G.S. 2 and 3 TABLE ID (Continued)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides                                       LLD (/,&#xfd;Ci/cc)
2 and 3 TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE  
: 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     Fourth Unit     Quarter     Quarter   Quarter     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==
==SUMMARY==
12 month period I. Number of batch releases:
 
8 releases 2. Total time period for batch releases:
12 month period I. Number of batch releases:                                         8 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. Total time period for batch releases:                         2672 minutes
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:
: 3. Maximum time period for a batch release:                       468 minutes
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)
: 4. Average time period for a batch release:                       334 minutes
(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.
: 5. Minimum time period for a batch release:                         23 minutes
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)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
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:
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) 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. 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) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)
2 and 3 TABLE 2A (Continued)
(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.
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
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.
: 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.
Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B.
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.
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.
2 and 3 TABLE 2B (Continued)
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.
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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.
S.O.N.G.S. 2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First       Second   Total 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 and 3 TABLE 2C (Continued)
: 2. Average diluted concentration during period                                   4Ci/ml   9.62E-12   5.72E-12
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.
: 3. Percent of applicable limit               % MPC   1.36E-5     1.10E-5
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.
: 4. Percent Effluent Concentration Limit     % ECL   1.29E-4     1.06E-4 B. Tritium
2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE  
: 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
 
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
S.O.N.G.S. 2 and 3 TABLE 2A (Continued)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third   Fourth     Total Unit  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 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 LLD Lower Limit of Detection; see Table 2C.
 
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 OF DETECTION CONTINUOUS MODE 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 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==
==SUMMARY==
12 month period 1. Number of batch releases:
 
146 releases 2. Total time period for batch releases:
12 month period
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:
: 1. Number of batch releases:                                     146 releases
726000 gpm SECTION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 2. Total time period for batch releases:                     21855 minutes
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.
: 3. Maximum time period for a batch release:                     478 minutes
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)
: 4. Average time period for a batch release:                     150 minutes
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 5. Minimum time period for a batch release:                       7 minutes
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)
: 6. Average saltwater flow during batch releases:             726000   gpm
* 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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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.
S.O.N.G.S. 2 and 3 SECTION 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)
(cont'd)
PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM 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     1.00E-6 Sr-89 LLD      5.OOE-8 Sr-90 LLD      1.00E-8
 
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)
* 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.
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.
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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.
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.
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.
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 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.
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)
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
S.O.N.G.S.       2 and 3 SECTION D.     PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)
: 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
Section H.       10CFR50 Appendix I Requirments TABLE 1 (1998)
* The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).
Dose * (millirems)
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.
SOURCE First         Second       Third       Fourth         Year Quarter       Quarter       Quarter     Quarter AIRBORNE EFFLUENTS               11)           12)           13)         14)             15)
: 17. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
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 NNWsector.
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.
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)
2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd) Section H. 1OCFR50 Appendix I Requirments TABLE 1 (1999) Dose * (millirems)
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 **
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
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
: 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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
: 18. The maximum air dose for gamma radiation was located in the ESE sector, at the exclusion area boundary.
S.O.N.G.S. 2 and 3 SECTION D.     PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)
: 19. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
Section H.       10CFR50 Appendix I Requirments TABLE 1 (1999)
: 20. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
Dose * (millirems)
: 21. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
SOURCE                             First           Second           Third           Fourth           Year Quarter         Quarter           Quarter         Quarter AIRBORNE EFFLUENTS                 11)             12)               13)               14)             15)
: 22. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
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)
23-25. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
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 including the The numbered footnotes below briefly explain how each maximum dose was calculated, organ and the predominant pathway (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.
Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose.
2 and 3 SECTION D.PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)Section H. 1OCFRSO Appendix I Requirements TABLE 1 (2000) Dose * (millirems)
11-25   These were calculated using the assumptions of USNRC Regulatory Guide 1.109.
SOURCE First Second Third Fourth Year Quarter Quarter Quarter Quarter AIRBORNE EFFLUENTS
: 11.     The maximum organ dose was to a child's thyroid and was located in the ESE sector.
: 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.
12-15. 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 ENE sector, at the exclusion area boundary.
area boundary.
The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
: 16.     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.
: 17.     The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion in  the  ESE  sector,  at  the  exclusion  area boundary.
The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
: 18.     The maximum air dose for gamma radiation was located at the   exclusion area boundary.
The maximum air dose for beta 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, exclusion   area boundary.
The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
: 20.     The maximum air dose for gamma radiation was located in the ENE sector, at the boundary.
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 E sector, at the exclusion area 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.
: 22.     The maximum air dose for beta located in the E sector, at the   exclusion area   boundary.
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*
23-25. The maximum air dose for beta radiation was TABLE 2 (1999)
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.
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
(*) 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)
2 and 3 2. Estimate of major nuclide composition (by type of waste) (Cont'd) a. not applicable  
S.O.N.G.S. 2 and 3 SECTION D.       PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)
% N/A b. americium-241 00 1.63E-3 antimony-124 0 2.78E-1 antimony-125  
Section H. 10CFRSO Appendix I Requirements TABLE 1 (2000)
% 7.49E-1 carbon-14 00 1.26E+O cerium-141  
Dose * (millirems)
%o 6.75E-2 cerium-144  
SOURCE First         Second         Third           Fourth       Year Quarter       Quarter       Quarter       Quarter AIRBORNE EFFLUENTS                 11)             12)           13)           14)           15)
% 8.97E-2 cesium-134  
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)
%- 1.85E+O cesium-137  
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),
%_ 1.64E+1 chromium-51 0 1.17E+1 cobalt-57  
Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose.
% 1.11E-I cobalt-58  
11-25     These were calculated using the assumptions of USNRC Regulatory Guide 1.109.
% 2.53E+1 cobalt-60  
11-12. The maximum organ dose was to a child's thyroid and was located in the NNW sector.
%o 7.O1E+O curium-242  
: 13.       The maximum organ dose was to a child's thyroid and was located in the E sector.
% 1.29E-3 curi um-243/244  
: 14.       The maximum organ dose was to a child's thyroid and was located in the ESE sector.
%o 2.06E-3 iodine-129  
: 15.      The maximum organ dose was to a child's thyroid and was located in the NNW sector.
% 3.34E-2 i ron-55 % 1.92E+I I ron-59 __ 1.17E+O manganese-54  
: 16.      The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
%o 1.32E+O nickel-63  
: 17.     The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary.
% 8.25E+O ni obi um-95 0 3.09E+O pl utonium-238  
18-20. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary.
% 1.12E-3 pl utonium-239/240  
: 21.      The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
%o 1.03E-3 pl utonium-241  
22-23. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
%o 1.06E-1 silver-110m 00 1.60E-2 strontium-89  
: 23.       The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
% 1.06E-2 strontium-90  
: 24.      The maximum air dose for beta radiation was located in   the E sector, at the exclusion area boundary.
-1.04E-2 technetium-99  
: 25.      The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
%_ 3.84E-3 tin-113 %o 2.60E-1 tritium %o 1.13E-1 zi rconium-95  
TABLE 2 (2000)
% 1.59E+O c. not applicable  
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
% 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
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
* SONGS maintains a contract with vendor (GTS) that provides volume reduction services.
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)
These shipments were made from their processing facility.
Estimated 12 month total error
The 4 shipments made from this facility included waste from other generators.
: 1. Type of waste                                       Unit         period     (%)
SCE's waste volume was a small fraction of the total waste volume of these shipments.
        .a. Spent resins, filter sludges,                   m3          N/A evaporator bottoms                           Ci           N/A       N/A
B. IRRADIATED FUEL SHIPMENTS (Disposition)
: b. Dry active waste (DAW),                       m3        1.29E+1 compactable and non-compactable*             Ci         2.30E-2   3.OOE+1
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.
: c. Irradiated components,     control           m3          N/A rods                                           Ci           N/A       N/A
2 and 3 SECTION F APPLICABLE LIMITS Gaseous Effluents  
: d. Other                                         m3          N/A Ci           N/A       N/A Note: Total curie content estimated.
-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.
(*)     Material packaged in strong, tight containers of various sizes.
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.
N/A     No shipment made.
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
2 and 3 Liquid Effluents  
S.O.N.G.S. 2 and 3
-Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations:
: 2. Estimate of major nuclide composition (by type of waste)     (Cont'd)
% Applicable Limit where: Dil Conc 0 MPCeff where: Fj n MPCG
: a. not applicable                               %               N/A
* 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.
: 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
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.
: c.     not applicable                             %             O.OOE+O
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: d.     not applicable                               0           O.OOE+O
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  
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
-continuous releases are: (1) fan flow rate (2) sampling (3) counting (4) calibration (5) differential pressure drop Sources of error for liquid effluents  
S.O.N.G.S. 2 and 3 A.       SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)
-batch releases are: (1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for liquid effluents  
: 3.       Solid Waste Disposition Number of Shipments           Mode of Transportation                 Destination 4                   Hitman Trucking Company             EnviroCare, UT Truck/Trailer
-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.
* 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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
B.       IRRADIATED FUEL SHIPMENTS (Disposition)
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.
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 Limits, tabulated in Sections A, B, C, and D of Table were calculated using the following equation:                                                     1A,
    % Applicable Limit                      (Rel Rate)       WX/O) (100)
MPCef epcff where:  Rel Rate                  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.
X/Q                        4.80E-6 sec/mr; the annual average atmospheric dispersion defined in the Units 2&3 0DCM.
1 0  MPCeff
                                    --           I~
1 MPC where:    F1                        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,.
n                          total number of radionuclides identified MPCj                       Maximum Permissible Concentration         (MPC) of the i t" radionuclide from 10 CFR 20 (20.1-20.602),      Appendix B, Table II, Column 1.
*  %ECL                                (Rel    Rate)   (X/O)   (100)
ECLeff where:   Rel Rate                 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.
X/Q                        4.80E-6 sec/mr; the annual average atmospheric dispersion defined in the Units 2&3 0DCM.
o  ECLeff F,
                                          - ECLI where:  F,                        fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, C*,
by the sum of all the isotopic activity, C,.
n                          total number of radionuclides identified ECL                =     Effluent Concentration Limit (ECL) of the i t' 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.       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                 (Dil Conc) (100)
MPCeff where:  Dil Conc                  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 0  MPCeff Mi MPC i where:  Fj                        fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, CT.
n                          total number of radionuclides identified MPCG                      Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.
* ECL                                (Dil Conc) (100)
ECLeff where:  Dil Conc                  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 0  ECLeff
* ECL where:  Fj                        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.
n                          total number of radionuclides identified ECL,                      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:
Six different categories are presented:
(1) (2) (3) (4) (5) (6)Liquid Effluents  
(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; 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.
-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, 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.
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".
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
Table 2 in Section H presents the percent of Applicable Limits for each dose presented in Table 1.
2 and 3 TABLE I The numbered footnotes below briefly explain how each the organ and the predominant pathway(s).
: 1. ODCM Figures 2-1 & 2-2.
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
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
: 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.
S.O.N.G.S. 2 and 3 TABLE I Dose * (millirems)
2 and 3 6. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
First          Second        Third          Fourth SOURCE                      Quarter      Quarter        Quarter        Quarter        Year LIQUID EFFLUENTS                I)          2)            3)             4)          5)
: 7. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
Whole Body                  2.68E-4      1.90E-4        2.68E-4        1.11E-3     1.83E-3
: 8. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
: 6)            7)            8)              9)          10)
: 9. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
Organ                        7.07E-4       2.82E-4        3.01E-4        1.25E-3      2.54E-3 AIRBORNE EFFLUENTS            11)           12)           13)             14)         15)
: 10. This value was calculated using the methodology of the ODCM; the GI-LLI primarily by the saltwater fish pathway.
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)
: 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.
Gamma                      2.43E-3        7.19E-4       1.73E-3        2.12E-3     6.18E-3
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
: 21)           22)           23)             24)         25)
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 hours 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 hours 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 hours 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 hours 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 hours 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.
Beta                        2.88E-3       6.13E-4        1.28E-3         2.95E-3     7.05E-3
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
: 26)           27)           28)             29)         30)
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.
DIRECT RADIATION                9.39E-2        1.24E-1       6.86E-2         1.11E-1      3.53E-1 The numbered footnotes below briefly explain how each maximum dose was calculated,      including the organ and the predominant pathway(s).
This change incorporated the following:
Noble gas doses due to airborne effluent are in units of mrad,    reflecting the air dose.
: 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. This value was calculated using the methodology of the ODCM.
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.
: 2. This value was calculated using the methodology of the ODCM.
: 3. This value was calculated using the methodology of the ODCM.
: 4. This value was calculated using the methodology of the ODCM.
: 5. This value was calculated using the methodology of the ODCM.
 
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 received the maximum dose primarily by the saltwater fish pathway.
dose
: 7. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum primarily by the saltwater fish pathway.
the maximum dose
: 8. This value was calculated using the methodology of the ODCM; the GI-LLI received primarily by the saltwater fish pathway.
: 9. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
dose
: 10. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum primarily by the saltwater fish pathway.
: 11. The maximum organ dose was to a child's thyroid and was located in the NNW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
was
: 12. The maximum organ dose was to a child's thyroid and was located in the NNW sector. This calculated using the assumptions of USNRC Regulatory Guide 1.109.
This was
: 13. The maximum organ dose was to a child's thyroid and was located in the NNW sector.
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 the ESE sector. This was 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 the NNW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
: 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 hours 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 hours 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 hours 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 hours 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 hours 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.
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.
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.
The level of radioactive effluent control required by 1OCFR20, 40CFR190, 1OCFR50.36a, and Appendix I to IOCFR50 will be maintained.
None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations.         The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.36a, 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.
Throughout the document, change bars are marked in one of four ways as follows:
F 1-14 Lined up equation definitions.
A     Addition D     Deletion F     Editorial/Format change R     Revision The following is a complete list of the changes:
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.
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
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
4-7 Added composite samplers to Table 4-2. 4-6 4-8 Added Note 5 for composite samplers.
S.O.N.G.S. 2 and 3 Old     New page CHANGE page 2-31             Updated Controlling Location Factors per LUC update.
4-7 4-9 Changed 4.2.1.c from Investigative Report to Corrective Action Program.
2-32             Renumbered Table page number due to deletion of one page.
5-2 Removed Table 5-5 as sample location per AR #000400602.
2-33             Moved San Mateo Pt Homes from Sector P to Sector Q. Page intentionally left blank.
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.
2-34             Renumbered Table page number due to deletion of one page.
6-10 Changed "IOCFR50.59" to "applicable regulations".
2-35             Renumbered Table page number due to addition of one page.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001) S.O.N.G.S.
2-36             Renumbered Table page number due to addition of one page.
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).
2-37             Renumbered Table page number due to addition of one page.
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.
2-38             Renumbered Table page number due to addition of one page.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
Section 2         Renumbered Section 2 pages from 2-39 on to reflect the addition of pages.
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.
2-39     Moved San Mateo Pt Homes from Sector P to Sector Q.
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.
2-39     2-40     Renumbered Table page number due to addition of one page.
This event is documented in ARs 000101252 and 1000400960.
2-40     2-41     Renumbered Table page number due to addition of one page.
S.O.N.G.S.
2-42     Added Outage Worker to Sector R.
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.
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.
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.
4-3     Added composite samplers to Table 4-1.
This event is documented in ARs 000101252 and 1000400960.
4-4     4-5     Added Action 33 for composite samplers.
S.O.N.G.S.
4-7     Added composite samplers to Table 4-2.
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.
4-6     4-8     Added Note 5 for composite samplers.
This event is documented in AR 010801138. S.01.N.G..
4-7     4-9     Changed 4.2.1.c from Investigative Report to Corrective Action Program.
2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)S.O.N.G.S.
5-2               Removed Table 5-5 as sample location per AR #000400602.
2 and 3 SECTION L. S.O.N.G.S.
5-14             Removed Table 5-5 as sample location per AR #000400602, 5-21             Corrected mileage for PIC S7.
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.
6-2               Deleted INVESTIGATIVE REPORT definition.
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.
6-10             Changed "IOCFR50.59" to "applicable regulations".
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
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
* 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)
S.O.N.G.S. 2 and 3 SECTION J- CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Units 2&3 Radioactive Waste Treatment Systems during the reporting period, January 1, 2001 to December 31, 2001.
Ci N/A N/A Note: (*) N/A Total curie content estimated.
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.
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  
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
% 2.78E-1 antimony-125 0 7.49E-1 carbon-14  
S.O.N.G.S.       2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2001 - December 31,           2001 S.01.N.G.. 2 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.
% 1.26E+O cerium-141  
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.
% 6.75E-2 cerium-144  
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.
% 8.97E-2 cesium-134 0 1.85E+O cesium-137 0 1.64E+1 chromium-51 0 1. 17E+I cobalt-57  
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.
% 1.11E-1 cobalt-58  
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.
% 2.53E+1 cobal t-60 -7.01E+O curium-242 0 1.29E-3 curi um-243/244  
 
% 2.06E-3 iodine-129  
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
% 3.34E-2 iron-55 0 1.92E+1 iron-59 % 1.17E+O manganese-54 0 1.32E+O nickel-63  
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.
% 8.25E+O niobium-95  
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.
% 3.09E+O pl utoni um-238 % 1.12E-3 pl utonium-239/240  
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.
% 1.03E-3 pl utonium-241 0 1.06E-1 silver-110m  
The radiation doses from liquid releases were: (a) total body: 1.83E-3 mrem, (b) limiting organ: 2.54E-3 mrem.
% 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  
The radioactive releases and resulting doses generated from Units 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.
% 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.
COMMON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
1, 2, and 3) Number of Shipments Mode of Transportation Destination Kindrick Trucking Company EnviroCare, UT 2 Flatbed Trailer IRRADIATED FUEL SHIPMENTS (Disposition)
COMMON COMMON RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)
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.
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),             m3          1.19E+1 compactable and non compactable
* Ci         9.OOE-3       3.OOE+1
: c. Irradiated components,               m3            N/A control rods                         Ci             N/A           N/A m3            N/A
: d. Other (filters)
Ci             N/A           N/A Note: Total curie content estimated.
(*)  Material packaged in strong, tight containers of various sizes.
N/A  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)
: 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 B. 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:==
==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)
 
February 28, 2001 RUSS KRIEGER, Site Manager and VP Nuclear DARYL DICK, Supervisor of Effluent Engineering BILL STROM, Nuclear Safety Group Supervisor  
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:==
==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.
: 2. Updated and expanded references, including the Unit 1 DSAR. 3. Reorganized and restated procedure steps to more clearly link requirements to referenceg.
Revision 7 of the PCP procedure contains changes that are only administrative in nature. Changes principally include:
: 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.
: 1.     A restatement of the procedure objective to more concisely link general objectives to specific references.
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.
: 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.
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.
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.
JIM MADIGAN Health Physics Manager MLewis:PCP:mjk cc:     E. Goldin P. Elliott ITA File 95-325 CDM Files
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
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.
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.
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.
Dose Category                                 Units             Year
1, 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.
: 1. Total Body
S.O.N.G.S.
: a. Total Body Dose                           mrem           3.90E-1
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.
: 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 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.
Meteorological dispersion was good 30% of the time, fair 47% of the time and poor 23% of the time.
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.
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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
S10 mrad for gamma radiation and S20 mrad for beta radiation.
COMMON APPENDIX A GASEOUS EFFLUENTS - APPLICABLE LIMITS A. Table 1A lists the total curies released and the release rate. The percent of applicable limit compares the released concentrations to the concentration limits of 10 CFR 20, Appendix B, Table II, Column 1.
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.
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:
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)COMMON APPENDIX A (Continued)
: 1. During any calendar quarter:         S5 mrad for gamma radiation and S10 mrad for beta radiation.
LIQUID EFFLUENTS  
: 2. During any calendar year:          S10 mrad for gamma radiation and S20 mrad for beta radiation.
-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.
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:
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
: 1. During any calendar quarter:           *7.5 mrem to any organ.
* 5 mrem to any organ. <3 mrem to the total body and <10 mrem to any organ.
: 2. During any calendar year:            S15 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.
 
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:       <   1.5 mrem to the total body and
* 5     mrem to any organ.
: 2. During any calendar year:          <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.
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
 
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 A EXTREMELY UNSTABLE (DT/DZ < -1.9    oC/100  METERS)
WIND      .22    .51      .76    1.1    1.6      2.1-  3 .I  5.1      7.1  10.1  13.1   

Revision as of 05:22, 24 November 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
Southern California Edison Co
To:
Document Control Desk, NRC/FSME
References
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Download: ML021160114 (111)


Text

A Edward Scherer I EDISON SOUTHERN CALIFORNIA An EDISON INTERNATIONAL"' Compan.*

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).

Ifyou 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 /Yoo Fax 949-368-6085

SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2001 January - December

I* EDISON SOUTHERN CALIFORNIA An VIlSOA \I R 17I10, I/,'" CUmlpan 7*I*\

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 0a z

TABLE OF CONTENTS SECTION A - INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

. . . . . . . . . . 2 SECTION B - GASEOUS EFFLUENTS ...... ................

. . . . . . . . . . 8 SECTION C - LIQUID EFFLUENTS ...............

SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADlDENDUM .... ....... 17 SECTION E - RADWASTE SHIPMENTS .............. S. . . . . . . .. . 21 SECTION F - APPLICABLE LIMITS ...... ................ . . . . . . .. . 24 SECTION G - ESTIMATION OF ERROR ..... ............... . . . . . . .. . 26 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS .......... . . . . . . .. . 27 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL . . . . . . .. . 31 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS . . . . . . .. . 32 SECTION K - MISCELLANEOUS ........ ................. . . . . . . .. . 33 SECTION L - S.O.N.G.S. 1 CONCLUSIONS . . . . . . . . . . . .. . 35

-ii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)

January - December SFfTTMN v*v .......................

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

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 Estimated First Second Total Unit Quarter Quarter Error, %

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)

S.O.N.G.S. I TABLE 1A (Continued)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit Quarter Quarter 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 __

(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 OF DETECTION CONTINUOUS MODE 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" releases are no longer conducted.

-- -- -- - -- --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 Estimated First Second Total Unit Quarter Quarter 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 Estimated Third Fourth Total Unit Quarter Quarter 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 (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 OF DETECTION CONTINUOUS MODE 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 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 1anthanum-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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)

S.O.N.G.S. I TABLE 2D LIQUI[ D EFFLUENTS-RADIATION DOSES AT THE LIOUID SITE BOLJNDARY 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 Radionuclides Released I Unit Fourth Quarter

1. 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

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.

i I 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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)

S.O.N.G.S. 1 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM (cont'd)

Section H. 10CFR50 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 NWsector.
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 NWsector.

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, m3 N/A evaporator bottoms Ci N/A N/A
b. Dry active waste (DAW), m3 2.52E+3 compactable and non-compactable
  • Ci

_________

1.29E+0- 3.00E+1

c. Irradiated components, control m3 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 (2001)

S.O.N.G.S. I

3. Solid Waste Disposition 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.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A

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 (Re] Rate) (X/O) (100)

MPCeff where: Rel Rate 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.

X/Q 1.30E-5 sec/m 3 ; the annual average atmospheric dispersion defined in the Unit 1 ODCM.

1 MPCelf n F.

=1i MPC where: Fj 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.

n total number of radionuclides identified MPC, Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.

& %ECL - (Rel Rate) (X/0) (100)

ECLeff where: Rel Rate 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.

X/Q 1.30E-5 sec/m 3 ; the annual average atmospheric dispersion defined in the Unit 1 ODCM.

1 0 ECLeuf n F.

M1 ECL i where: Fj fractional abundance of the i th radionuclide obtained by dividing the activity (curies) for each radionuclide, C1 , by the sum of all the isotopic activity, CT.

n total number of radionuclides identified ECL, 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 (Dil Conc) (100)

MPCeff where: Dil Conc 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 MPCeff i MPC i where: F, 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,.

n total number of radionuclides identified MPCi Maximum Permissible Concentration (MPC) of the i t h radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.

0  % ECL (Dil Conc) (100)

ECLeff where: Dil Conc 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.

ECLeff i~i 11 ECL

[CLIi where: F7 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.

n total number of radionuclides identified ECLj Effluent Concentration Limit (ECL) of the i th 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+ Y3c+ 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 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

  • 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.
1. This value was calculated using the methodology of thie ODCM.
2. This value was calculated using the methodology of thie ODCM.
3. This value was calculated using the methodology of thie ODCM.
4. This value was calculated using the methodology of thie ODCM.
5. This value was calculated using the methodology of thie ODCM.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)

S.O.N.G.S. I

6. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
7. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
8. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
9. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
10. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
11. The maximum organ dose was to a child's thyroid and was located in the NW sector. This was 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 the NW sector. This was 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 the NW sector. This was 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 the NW sector. This was 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 the NW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
16. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.
17. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.
18. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.
19. There was no activity detected during the rel ease period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.
20. There was no activity detected during the rel ease period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.
21. There was no activity detected during the rel ease period, therefore the reported air dose for beta radiation was O.OOE+O mrad.
22. There was no activity detected during the rel ease period, therefore the reported air dose for beta radiation was O.OOE+O mrad.
23. There was no activity detected during the rel ease period, therefore the reported air dose for beta radiation was O.OOE+O mrad.
24. There was no activity detected during the rel ease period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

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 10CFR50.59, {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 setpoint calculations. The level of radioactive effluent control required by IOCFR20, 40CFR190, 10CFR5O.36a, and Appendix I to 10CFR50 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:

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 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 S.O.N.G.S. I 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.

Cl) z Cl)

CL W.

TABLE OF CONTENTS

........... S. .. . 36 SECTION A - INTRODUCTION SECTION B - GASEOUS EFFLUENTS .... ........... S. . . . . . . .. . 37 SECTION C - LIQUID EFFLUENTS .......... S. . . . . . . .. . 47

....... 56 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADD ENDUM ....

S. . . . . . . .. . 63 SECTION E - RADWASTE SHIPMENTS .........

S. . . . . . . .. . 66 SECTION F - APPLICABLE LIMITS .... ...........

S. . . . . . . .. . 68 SECTION G - ESTIMATION OF ERROR .............

S. . . . . . . .. . 69 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS . .

S. . . . . . . .. . 73 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS S. . . . . . . . . 75 S. . . . . . . .. . 75 SECTION K - MISCELLANEOUS ...... ...................

S.O.N.G.S. 2 and 3 CONCLUSIONS ........ .. . . . . . . .. . 77 SECTION L -

-iii-

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 Estimated First Second Total Unit Quarter 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 OF DETECTION CONTINUOUS MODE 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 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 Fourth Unit Quarter Quarter Quarter 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 Estimated First Second Total 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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)

S.O.N.G.S. 2 and 3 TABLE 2A (Continued)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit 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 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 LLD Lower Limit of Detection; see Table 2C.

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 OF DETECTION CONTINUOUS MODE 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 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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)

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

(cont'd)

PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM 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 1.00E-6 Sr-89 LLD 5.OOE-8 Sr-90 LLD 1.00E-8

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. 10CFR50 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 NNWsector.

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. 10CFR50 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 including the The numbered footnotes below briefly explain how each maximum dose was calculated, 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.

area boundary.

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

23-25. The maximum air dose for beta radiation was 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. 10CFRSO 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 These were calculated using the assumptions of USNRC Regulatory Guide 1.109.

11-12. The maximum organ dose was to a child's thyroid and was located in the NNW sector.

13. The maximum organ dose was to a child's thyroid and was located in the E sector.
14. The maximum organ dose was to a child's thyroid and was located in the ESE sector.
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.

18-20. The maximum air dose for gamma 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.

22-23. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.

23. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary.
24. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary.
25. 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, m3 N/A evaporator bottoms Ci N/A N/A

b. Dry active waste (DAW), m3 1.29E+1 compactable and non-compactable* Ci 2.30E-2 3.OOE+1
c. Irradiated components, control m3 N/A rods Ci N/A N/A
d. Other m3 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 Limits, tabulated in Sections A, B, C, and D of Table were calculated using the following equation: 1A,

% Applicable Limit (Rel Rate) WX/O) (100)

MPCef epcff where: Rel Rate 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.

X/Q 4.80E-6 sec/mr; the annual average atmospheric dispersion defined in the Units 2&3 0DCM.

1 0 MPCeff

-- I~

1 MPC where: F1 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,.

n total number of radionuclides identified MPCj Maximum Permissible Concentration (MPC) of the i t" radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.

  • %ECL (Rel Rate) (X/O) (100)

ECLeff where: Rel Rate 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.

X/Q 4.80E-6 sec/mr; the annual average atmospheric dispersion defined in the Units 2&3 0DCM.

o ECLeff F,

- ECLI where: F, fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, C*,

by the sum of all the isotopic activity, C,.

n total number of radionuclides identified ECL = Effluent Concentration Limit (ECL) of the i t' 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. 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 (Dil Conc) (100)

MPCeff where: Dil Conc 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 0 MPCeff Mi MPC i where: Fj fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, CT.

n total number of radionuclides identified MPCG Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.

  • ECL (Dil Conc) (100)

ECLeff where: Dil Conc 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 0 ECLeff

  • ECL where: Fj 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.

n total number of radionuclides identified ECL, 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) 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; 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 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. 2 and 3 TABLE I 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 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.

1. This value was calculated using the methodology of the ODCM.
2. This value was calculated using the methodology of the ODCM.
3. This value was calculated using the methodology of the ODCM.
4. This value was calculated using the methodology of the ODCM.
5. This value was calculated using the methodology of the ODCM.

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 received the maximum dose primarily by the saltwater fish pathway.

dose

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

the maximum dose

8. This value was calculated using the methodology of the ODCM; the GI-LLI received primarily by the saltwater fish pathway.
9. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.

dose

10. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum primarily by the saltwater fish pathway.
11. The maximum organ dose was to a child's thyroid and was located in the NNW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.

was

12. The maximum organ dose was to a child's thyroid and was located in the NNW sector. This calculated using the assumptions of USNRC Regulatory Guide 1.109.

This was

13. The maximum organ dose was to a child's thyroid and was located in the NNW sector.

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 the ESE sector. This was 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 the NNW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
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 10CFR20, 40CFR190, 10CFR50.36a, 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 no changes to the Units 2&3 Radioactive Waste Treatment Systems during the reporting period, January 1, 2001 to December 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 S.01.N.G.. 2 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.

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), m3 1.19E+1 compactable and non compactable
  • Ci 9.OOE-3 3.OOE+1
c. Irradiated components, m3 N/A control rods Ci N/A N/A m3 N/A
d. Other (filters)

Ci N/A N/A Note: Total curie content estimated.

(*) Material packaged in strong, tight containers of various sizes.

N/A 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)

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 B. 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 released and the release rate. The percent of applicable limit compares the released concentrations to the concentration limits of 10 CFR 20, Appendix B, 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: S5 mrad for gamma radiation and S10 mrad for beta radiation.
2. During any calendar year: 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: *7.5 mrem to any organ.
2. During any calendar year: 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: < 1.5 mrem to the total body and
  • 5 mrem to any organ.
2. During any calendar year: <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 PASQUILL A EXTREMELY UNSTABLE (DT/DZ < -1.9 oC/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1- 3 .I 5.1 7.1 10.1 13.1 >18 TOIAL DIR .50 .75 1.0 2.0 1.5 UNSTABLE 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 EXTREMELY 0 0 0 0 0 0 0 0 1 NNE 0 0 0 2 0 0 0 0 0 0 0 4 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 1 6 1 0 0 0 0 8 0

SSE 0 0 0 0 5 10 8 1 0 0 0 24 0

S 0 0 0 2 4 13 18 7 0 0 1 0 45 SSW 0 0 0 5 5 11 12 0 0 0 0 0 33 SW 0 0 1 3 7 15 13 1 0 1 0 0 41 WSW 0 0 0 3 13 29 19 5 0 0 0 0 69 W 0 0 0 0 5 43 57 3 1 0 0 0 109 WNW 0 0 0 0 4 9 28 11 0 0 0 0 52 NW 0 0 0 0 1 0 4 0 0 0 0 0 5 NNW 0 0 0 0 0 0 0 0 0 0 0 0 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 8 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2160

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 U U U 5 I 4 2 U 0 0 0 0 18 NNE 0 2 1 8 7 9 2 0 0 0 0 0 29 NE 0 0 0 3 3 2 1 0 0 0 0 10 ENE 0 0 0 0 1 2 1 0 0 0 0 0 4 E 0 2 1 2 0 3 7 2 0 0 0 0 17 ESE 0 0 2 1 1 13 23 10 6 0 0 0 56 SE 0 0 0 1 3 23 56 41 24 2 1 0 151 SSE 0 1 1 6 10 22 26 19 7 7 2 0 101 S 0 2 0 4 10 13 12 5 2 1 0 0 49 SSW 0 1 5 2 10 12 6 1 1 0 0 0 38 SW 0 0 2 8 7 9 1 4 2 0 0 0 33 WSW 0 0 2 6 1 4 3 3 3 2 0 0 24 W 0 0 0 3 7 2 6 6 5 1 0 0 30 WNW 0 0 1 2 8 3 12 4 2 0 0 32 NW 0 0 1 1 3 1 13 5 5 0 0 0 29 0 0 NNW 0 0 1 7 0 10 5 0 0 0 TOTALS 0 9 0 0 23 17 61 76 144 168 101 52 13 3 0 64-4 NUMBER OF VALID HOURS 644 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 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 SLIGHTL Y STABLE (-0.5 < DT/DZ 5 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 4 7 9 4 0 0 0 0 0 24 NNE 0 1 2 10 9 16 8 0 0 0 0 0 46 NE 0 0 6 6 5 5 3 0 0 0 0 0 25 ENE 0 3 1 2 2 3 0 1 0 1 0 0 13 E 2 0 2 5 4 9 4 1 0 0 0 0 27 ESE 0 0 2 3 3 9 5 1 0 0 0 0 23 SE 0 0 0 3 2 2 9 2 0 0 0 0 18 SSE 0 0 1 0 1 0 2 4 1 0 0 0 9 S 0 1 1 4 0 0 1 3 0 0 0 0 10 SSW 0 0 1 1 1 0 0 0 0 0 0 0 3 SW 0 0 0 1 1 0 0 0 0 0 0 0 2 1 2 0 0 0 0 0 0 0 0 3 WSW 0 0 W 0 0 0 0 1 3 1 0 0 0 0 0 5 WNW 0 0 0 2 2 3 5 0 2 0 0 0 14 NW 0 1 0 4 1 4 3 1 0 0 0 0 14 NNW 0 2 1 2 10 5 3 0 0 0 0 0 14 2 8 18 49 68 48 13 3 1 0 0 250 TOTALS 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 281 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 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 6 0 1 0 1 7 12 0 0 0 0 0 27 NNE 0 1 0 6 20 163 128 3 0 0 0 0 321 NE 5 0 1 8 11 15 8 3 0 0 0 0 51 ENE 0 2 1 4 0 2 6 0 0 0 0 0 15 E 0 0 1 1 0 1 0 0 0 0 0 0 3 ESE 0 0 1 0 2 1 0 0 0 0 0 0 4 SE 0 0 0 1 0 1 1 0 0 0 0 0 3 SSE 0 0 0 0 1 0 0 0 0 0 0 0 1 S 0 0 1 0 0 0 0 0 0 0 0 0 1 SSW 0 0 2 0 1 2 0 0 0 0 0 0 0 SW 0 0 1 0 0 0 0 0 0 0 0 0 1 WSW 0 0 1 0 1 1 0 0 0 0 0 0 3 W 0 0 0 1 1 0 0 0 0 0 0 3 WNW 0 0 0 2 2 4 7 0 0 0 0 0 15 NW 0 0 0 0 0 2 0 0 0 0 0 0 2 NNW 0 0 0 0 1 2 10 0 0 0 0 0 13 TOTALS 11 3 23 6 n ArQ 41 202 172 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 NUMBER OF VALID HOURS 2159 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 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 PASQUILL A EXTREMELY UNSTABLE (DT/DZ < 1.9 'C/100 METERS)

WIND .22 .51 .7b 1.1 1.6 2.1- 5.1 METERS) 3*.1 °C/100 7.1 10.1 13.1 >18 TOTAL

.50 .75 1.0 1.5 2.0 3.0 5P.0 7.0 10.0 13.0 18.0 DIR 0 0 0 0 0 0 0 0 0 N 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 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 1 0 0 0 1 0 0 0 0 0 ESE 0 0 0 0 0 0 1 1 1 2 0 0 0 0 SE 0 0 0 0 3 5 17 3 2 0 0 0 30 SSE 0 0 1 3 7 22 49 18 2 0 0 0 102 S 0 0 2 2 6 17 27 3 0 0 0 0 57 SSW 0 0 0 2 9 58 42 1 1 0 0 0 113 SW 0 0 3 22 106 52 0 0 0 0 0 183 WSW 0 0 0 3 15 83 99 0 0 0 0 0 200 W 0 0 0 0 2 8 43 5 0 0 0 0 58 WNW 0 0 0 0 0 0 1 3 1 0 0 0 0 5 NW 0 0 0 0 1 0 0 0 0 0 0 1 NNW 0 0 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 3 NUMBER OF CALMS 0 0 TOTAL HOURS FOR THE PERIOD 2184 NUMBER OF INVALID HOURS

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 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 1U.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 3.0 0 i 0 0 0 0 0 0 0 1 NNE 0 0 0 1 1 1 1 0 0 0 0 0 4 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 2 2 2 0 0 0 0 0 6 SSE 0 0 1 0 3 2 11 4 1 0 0 0 22 S 0 0 1 1 1 4 10 5 6 2 0 0 30 SSW 0 0 0 0 2 6 3 0 3 0 0 0 14 SW 0 0 0 2 7 8 9 2 0 0 0 0 28 WSW 0 0 0 3 7 9 2 1 0 0 0 0 22 W 0 0 0 3 4 7 4 1 0 0 0 0 19 WNW 0 0 0 3 5 2 5 3 0 0 0 0 18 NW 0 0 0 0 0 0 6 0 0 0 0 0 6 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 U 2 2 5 13 4 1 0 0 0 0 0 27 NNE 0 0 2 10 9 15 0 0 0 0 0 0 36 NE 0 0 2 11 10 0 0 0 0 0 0 23 0

ENE 0 0 2 3 1 4 0 0 0 0 0 0 10 E 0 1 3 1 1 14 7 0 0 0 0 27 0

ESE 0 1 3 6 5 11 15 0 0 0 0 0 41 SE 0 0 2 5 15 26 31 6 0 0 0 0 85 SSE 0 1 1 11 21 25 44 11 3 0 0 0 117 S 0 1 5 10 30 37 26 13 0 0 0 0 122 SSW 0 1 4 10 13 20 27 1 0 0 0 0 76 SW 0 3 6 14 15 20 12 3 1 0 0 0 74 WSW 0 0 2 11 10 7 3 2 0 0 0 0 35 W 1 1 3 17 5 2 5 2 1 0 0 0 37 WNW 0 0 6 7 6 7 12 5 0 0 0 0 43 NW 1 2 0 5 3 15 13 1 2 0 0 0 42 NNW 1 1 4 5 6 4 2 0 0 0 0 3 14 0 23 TOTALS 47 131 163 211 198 44 7 0 0 818 0 00 NUMBER OF VALID HOURS 818 NUMBER OF CALMS NUMBER OF INVALID HOURS 0 0 TOTAL HOURS FOR THE PERIOD 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 PASQUILL E SLIGHTLY STABLE (-0.5 < 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 1 3 0 3 1 0 0 0 0 0 8 NNE 0 1 5 15 16 8 7 1 0 0 0 0 53 NE 0 2 3 4 2 1 1 0 0 0 0 0 13 ENE 0 0 1 2 1 0 0 0 0 0 0 0 4 E 0 0 1 2 2 2 0 0 0 0 0 0 7 ESE 1 0 2 1 0 0 0 0 0 0 0 5 SE 0 0 0 1 1 3 0 0 0 0 0 0 5 SSE 0 0 0 1 0 1 0 0 0 0 0 0 2 0 1 0 1 0 0 0 0 0 5 S 1 0 2 0 1 0 0 0 0 0 0 0 1 SSW 0 0 0 SW 0 0 0 2 1 1 0 0 0 0 0 0 4 WSW 0 2 0 0 0 0 0 0 0 0 0 0 2 0 0 0 3 1 0 0 0 0 0 4 W 0 0 0 0 0 1 5 2 0 0 0 0 9 WNW 1 0 NW 0 0 0 0 1 3 0 1 0 0 0 0 5 NNW 0 0 2 1 2 1 0 0 0 0 0 0 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 145 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 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 PASQUILL G EXTREMELY STABLE (DT/DZ > 4 .0 *C/100 METERS) _____

WIND .22 .51 .76- 1.1- 1.6 2.1 .1 °C/lO0 5.1 METERS) 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 .0 7.0 10.0 13.0 18.0 N 0 0 1 0 2 1 5 0 0 0 0 0 9 NNE 0 0 0 3 10 73 43 3 0 0 0 0 132 NE 0 0 1 1 2 4 1 0 0 0 0 0 9 ENE 0 0 1 0 0 1 0 0 0 0 0 0 2 E 0 0 0 0 1 0 0 0 0 0 0 0 1 ESE 0 1 0 0 0 0 0 0 0 0 0 0 1 SE 0 0 0 0 0 1 0 0 0 0 0 0 1 SSE 0 0 0 0 1 0 0 0 0 0 0 0 1 S 0 0 0 1 0 0 0 0 0 0 0 0 1 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 0 0 0 1 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 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 1 3 5 16 50 3 0 0 81

- 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 u 2 1u 17 9 10 0 0 0 0 0 52 NNE 0 3 9 48 69 144 55 4 0 0 0 0 332 NE 0 3 10 21 16 5 2 0 0 0 0 0 57 ENE 0 0 5 9 2 7 0 0 0 0 0 0 23 E 0 2 4 4 4 16 7 0 0 0 0 0 37 ESE 1 2 4 9 6 12 15 0 0 0 0 0 49 SE 0 0 2 7 19 33 35 8 0 0 0 0 104 SSE 0 1 2 12 28 34 72 18 6 0 0 0 173 S 1 1 9 15 39 63 86 36 8 2 0 0 260 SSW 0 1 6 13 23 43 57 4 3 0 0 0 150 SW 0 3 6 20 32 87 63 6 2 0 0 0 219 WSW 0 2 2 18 40 123 57 3 0 0 0 0 245 W 1 1 3 24 24 96 109 3 1 0 0 0 262 WNW 1 0 6 10 14 18 65 15 0 0 0 0 129 NW 1 2 0 6 4 20 23 3 2 0 0 0 61 NNW 1 1 7 6 8 6 2 0 0 0 0 0 31 TOTALS 6 24 79 232 100 2184 345 716 658 22 2 0 0

NUMBER OF VALID HOURS 2184 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184

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 37 NUMBER OF CALMS 2 2 TOTAL HOURS FOR THE PERIOD 2208 NUMBER OF INVALID HOURS

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 1036 NUMBER OF CALMS 2 NUMBER OF INVALID HOURS 2 TOTAL HOURS FOR THE PERIOD 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 E SLIGHTLY STABLE (-0 .5 < 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 3 1 10 8 15 2 0 0 0 0 0 40 NNE 1 5 8 19 25 20 4 0 0 0 0 0 82 NE 0 1 4 9 2 0 0 0 0 0 0 0 16 2 3 2 2 0 0 0 0 0 0 0 9 ENE 0 E 01 1 1 3 1 1 2 0 0 0 0 0 10 ESE 1 3 4 0 0 2 0 0 0 0 0 11 SE 0 2 2 3 1 10 1 2 1 0 0 0 22 SSE 0 0 2 3 7 10 2 0 0 0 0 0 24 S 0 2 0 3 5 1 0 0 0 0 0 0 11 2 0 0 0 0 0 5 SSW 0 1 1 0 0 1 SW 0 0 0 0 0 2 0 0 0 0 0 0 2 WSW 0 2 3 1 2 0 0 0 0 0 0 9 W 0 0 1 2 2 0 0 0 0 0 0 0 5 WNW 00 1 1 0 0 3 6 0 0 0 0 0 11 NW 0 1 1 2 2 4 2 0 0 0 0 12 0

NNW 0 3 6 1 1 0 0 0 0 0 0 11 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 91 NUMBER OF CALMS 2 NUMBER OF INVALID HOURS 2 TOTAL HOURS FOR THE PERIOD 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 18.0 114 5 4 21 29 4 0 0 0 0 0 104 NNE 1 6 11 45 64 100 16 1 0 0 0 0 244 NE 0 3 8 28 15 11 0 0 0 0 0 0 65 ENE 0 2 6 4 4 8 0 0 0 0 0 0 24 E 2 3 7 6 12 4 0 0 0 0 0 35 ESE 1 1 3 7 3 7 4 0 0 0 0 0 26 SE 2 21 4 8 11 44 30 3 1 0 0 0 105 SSE 0 1 4 15 31 63 47 1 0 0 0 0 162 S 0 3 3 19 30 56 66 9 0 0 0 0 186 SSW 1 2 6 16 34 48 45 1 0 0 0 0 153 SW 0 1 15 19 43 76 38 0 0 0 0 0 192 WSW 1 2 11 24 35 112 75 1 0 0 0 0 261 W 0 1 28 34 11 88 169 1 0 0 0 0 332 WNW 0 2 6 13 24 54 87 5 0 0 0 2 0 191 NW 0 3 16 15 16 27 5 0 0 0 0 84 NNW 0 1 6 20 9 5 1 0 0 0 0 10 35 0 42 TOTALS 104 308 379 729 613 27 1 0 0 0 2206 0 0 2206 NUMBER OF VALID HOURS 2206 NUMBER OF CALMS 2 NUMBER OF INVALID HOURS 2 TOTAL HOURS FOR THE PERIOD 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 43 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2208

II 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 C SLIGHTLY UNSTABLE (-1 .7 < DT/DZ < -1.5 °C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 7...1.- 7.1-5, 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 0 1 0 0 0 0 0 2 NE 0 0 0 0 0 0 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 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 1 0 0 0 0 1 SSE 0 0 0 0 0 0 1 0 0 0 0 1 0

S 0 0 0 0 1 4 0 0 0 0 0 0 5 SSW 0 0 0 0 1 1 4 1 0 0 0 0 7 SW 0 0 0 0 1 1 0 1 0 0 0 0 3 WSW 0 0 0 1 0 2 1 0 0 0 0 0 4 W 0 0 0 0 2 1 0 0 0 0 0 0 3 WNW 0 0 0 0 0 0 3 0 0 0 0 0 3 NW 0 0 0 1 0 1 1 0 1 0 0 0 4 NNW 0 0 0 0 0 0 0 0 0 0 0 0 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 416 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2208

-100-

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 < 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 1 2 4 17 13 23 6 1 0 0 0 0 67 NNE 2 2 8 12 29 28 27 2 0 0 0 0 110 NE 0 1 8 4 5 6 2 0 2 0 0 0 28 ENE 0 3 2 5 2 4 0 0 0 0 0 0 16 E 0 0 2 4 2 5 0 0 0 0 0 0 13 ESE 1 0 2 2 2 5 3 2 0 0 0 0 17 SE 0 1 0 5 8 24 19 6 1 0 0 0 64 SSE 1 1 2 6 11 14 5 1 1 0 1 0 43 S 0 1 3 3 5 7 4 0 0 0 0 0 23 SSW 0 0 3 4 2 0 2 0 3 0 0 0 14 SW 0 0 2 4 2 3 0 2 1 0 0 0 14 WSW 0 2 1 3 2 2 0 0 1 0 0 0 11 W 0 2 3 1 3 3 1 1 2 0 0 0 16 WNW 1 0 4 9 2 8 3 8 0 0 0 0 35 NW 0 2 1 6 5 12 9 3 0 0 0 0 38 NNW 0 1 2 6 4 12 5 0 0 0 0 0 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 275 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2208

-101-

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 EXTREMELY STABLE (DT/DZ > 4.0 'C/100 METERS)

WIND .22 .51 i 76- 1.1- 1.6 2.1 3.1 4.0 5.1 METERS)

°C/lO0 7.1 lU.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 1 2 1 13 8 0 0 0 0 0 25 NNE 0 0 1 4 25 181 206 14 0 0 0 0 431 NE 0 0 1 4 7 9 5 0 0 0 0 0 26 ENE 0 0 0 2 2 1 0 0 0 0 0 0 5 E 0 0 0 1 1 0 0 0 0 0 0 0 2 ESE 0 0 0 1 1 0 0 0 0 0 0 2 0

SE 0 0 0 0 0 0 0 0 0 0 0 0 0

SSE 0 0 0 0 1 2 1 0 0 0 0 4 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 0

W 0 0 0 0 0 0 0 0 0 0 0 0 0 WNW 0 0 0 0 1 2 1 0 0 0 0 4 0

NW 0 0 0 1 1 0 0 0 0 0 0 0 2 NNW 0 0 0 0 1 1 0 0 0 0 0 0 0 0 2 TOTALS 3 15 41 209 221 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 NNE 1 2 1U 29 26 51 25 2 0 0 0 0 146 NE 2 3 13 46 100 271 264 22 1 0 0 0 722 ENE 0 4 17 17 26 21 11 3 2 0 0 0 101 0 4 3 10 5 8 0 0 0 0 0 0 30 E 0 3 2 10 4 5 0 0 0 0 0 0 24 ESE 1 3 2 3 4 10 4 2 1 0 0 0 51 SE 0 2 0 8 9 34 36 10 4 0 0 0 103 SSE 1 1 3 15 25 40 33 7 4 0 1 0 130 S 0 2 5 11 17 37 24 3 0 0 0 0 99 SSW 0 0 4 16 13 27 20 1 3 0 0 0 84 SW 0 1 4 14 20 35 7 3 1 0 0 0 85 WSW 0 2 2 11 30 40 16 0 1 0 0 0 102 W 0 3 5 11 24 115 51 6 2 1 0 0 218 WNW 1 1 5 17 12 54 73 20 0 0 0 0 183 NW 0 2 2 9 12 25 27 8 1 0 0 0 86 NNW 0 2 3 12 12 25 9 1 0 0 0 0 64 TOTALS 6 35 80 600 0 2207 239 339 798 88 20 1 1 T NUMBER OF VALID HOURS 2207 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS I TOTAL HOURS FOR THE PERIOD 2208 102-