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| number = ML031250233 | | number = ML031250233 | ||
| issue date = 04/29/2003 | | issue date = 04/29/2003 | ||
| title = | | title = Annual Radioactive Effluent Release Report for 2002 & Offsite Dose Calculation Manual, Pages 1 - 94 | ||
| author name = | | author name = | ||
| author affiliation = San Diego Gas & Electric Co, Southern California Edison Co | | author affiliation = San Diego Gas & Electric Co, Southern California Edison Co | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2002 January -December SOUTHERN CALIFORNIA EDISON An LDISO\'IVTR\ITIO.\L"' | {{#Wiki_filter:SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2002 January - December | ||
Company 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. | SOUTHERN CALIFORNIA EDISON An LDISO\\'IVTR\\ITIO.\\L"' Company 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%).P 0 Bo\ 128 San Clemente, CA 92674-0128 S.O.N.G Es.1 TABLE OF CONTENTS SECTION A -INTRODUCTION | 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. | ||
.............SECTION B -GASEOUS EFFLUENTS | It is owned by Southern California Edison (80%) and San Diego Gas and Electric (20%). | ||
...........SECTION C -LIQUID EFFLUENTS | 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. | ||
...........SECTION D -PREVIOUS RADIOACTIVE EFFLUENT RELEASE R SECTION E -RADWASTE SHIPMENTS | The twin units are owned by Southern California Edison (75.05%), San Diego Gas and Electric (20%), City of Anaheim (3.16%), | ||
..........SECTION F -APPLICABLE LIMITS ...........SECTION G -ESTIMATION OF ERROR ..........SECTION H -10 CFR 50 APPENDIX I REQUIREMENTS | and the City of Riverside (1.79%). | ||
...SECTION I -CHANGES TO OFFSITE DOSE CALCULATION MAN E | P 0 Bo\\ 128 San Clemente, CA 92674-0128 | ||
.............SECTION L -S.O.N.G.S. | |||
1 CONCLUSIONS | S.O.N.G Es. 1 | ||
: 5. Batch Release Summaries 6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments 8. 10 CFR 50 Appendix I Requirements | TABLE OF CONTENTS SECTION A - INTRODUCTION............. | ||
: 9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | SECTION B - GASEOUS EFFLUENTS........... | ||
1 SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories: | SECTION C - LIQUID EFFLUENTS........... | ||
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 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: | SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE R SECTION E - RADWASTE SHIPMENTS.......... | ||
SECTION F - APPLICABLE LIMITS........... | |||
SECTION G - ESTIMATION OF ERROR.......... | |||
SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS... | |||
SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MAN E | |||
1 2 | |||
8 PORT ADDENDUM....... | |||
16 | |||
.............. 17 | |||
.............. 22 | |||
.............. 24 25 IAL | |||
............ 29 YSTEMS.......... 30 | |||
.............. 31 U | |||
SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT S SECTION K - MISCELLANEOUS............. | |||
SECTION L - S.O.N.G.S. 1 CONCLUSIONS....... | |||
33 | |||
-ii- | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
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, 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 (2002) | |||
S.O.N.G.S. 1 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 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. | 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. | The total radioactivity for each radionuclide is listed for each quarterly period by "continuous" mode of release. | ||
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 1C 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. | Plant stack releases are considered to be "continuous" releases. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | As of 8/4/93, "batch" mode-releases are no longer conducted because of the permanent shutdown of the reactor. | ||
1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error-. %I~ ~ | 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 for continuous mode releases only. | ||
: 1. Particulates with half-lives | Table 1E; "Gaseous Effluents-Radiation-Doses at the Site Boundary," provides a quarterly summary of doses-at the site boundary for this report period. | ||
>8 days Ci <LLD <LLD 1.60E+1 2. Average release rate for period yCi/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 <LLD <LLD 5.OOE+1 D. Tritium 1. Total release Ci 1.64E-1 7.05E-1 2.50E+1 2. Average release rate for period pCi/sec 2.11E-2 8.97E-2 3. Percent of applicable limit % MPC 1.37E-4 5.83E-4 4. Percent Effluent Concentration Limit % ECL 2.74E-4 1.17E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | Table IF, "Gaseous Effluents-Batch Release Summary," has been deleted. | ||
1 TABLE 1A (Continued) | "Batch" mode releases are no longer conducted as of 8/4/93, due to the permanent shutdown of the reactor. | ||
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
>8 days Ci <LLD 1.89E-6 1.60E+1 2. Average release rate for period yCi/sec O.OOE+O 2.37E-7 3. Percent of applicable limit % MPC O.OOE+O 6.33E-7 4. Percent Effluent Concentration Limit % ECL O.OOE+O 1.70E-6 5. Gross alpha activity -Ci <LLD <LLD 5.OOE+1 D. Tritium 1. Total release Ci <LLD 5.55E-1 2.50E+1 2. Average release rate for period pCi/sec O.OOE+O 6.98E-2 3. Percent of applicable limit % MPC O.OOE+O 4.54E-4 4. Percent Effluent Concentration Limit % ECL O.OOE+O 9.08E-4 (1)On 7/9/2002, plant vent stack particulate and iodine samples were not collected Tor 4 nrs and 44 minutes.Prior and subsequent samples were <LLD. There were no dose consequences to the public as a result of this event which is documented in AR 020700464. | S.O.N.G.S. 1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error-. % | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | I~ ~ | ||
1 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS | I A. Fission and activation gases | ||
: 1. Total release Ci | |||
1, "BATCH MODE" releases are no longer conducted. | <LLD | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | <LLD 3.0OE+1 | ||
1 TABLE ID GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION 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. Iodines iodine-131 2.90E-13 iodine-133 2.80E-12 iodine-135 1.90E-10 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 cobalt-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 4. alpha 1.OOE-11 5. tritium 7.20E-8 NOTE: Due to the permanent shutdown of longer conducted. | : 2. Average release rate for period yCi/sec O.OOE+O O.OOE+O | ||
S.O.N.G.S. | : 3. Percent of applicable limit | ||
1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | % MPC O.OOE+O O.OOE+O | ||
1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE | : 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 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 C. Particulates | |||
: 1. Particulates with half-lives >8 days Ci | |||
<LLD | |||
<LLD 1.60E+1 | |||
: 2. Average release rate for period yCi/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 | |||
<LLD | |||
<LLD 5.OOE+1 D. Tritium | |||
: 1. Total release Ci 1.64E-1 7.05E-1 2.50E+1 | |||
: 2. Average release rate for period pCi/sec 2.11E-2 8.97E-2 | |||
: 3. Percent of applicable limit | |||
% MPC 1.37E-4 5.83E-4 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL 2.74E-4 1.17E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 TABLE 1A (Continued) | |||
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Estimated Fourth Total Quarter Error, % | |||
A. Fission and activation gases | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 3.OOE+1 | |||
: 2. Average release rate for period yCi/sec O.OOE+O O.OOE+O | |||
: 3. Percent of applicable limit | |||
% MPC O.OOE+O O.OOE+O | |||
: 4. Percent Effluent Concentration Limit I% ECL O.OOE+O O.OOE+O I B. Iodines (1) | |||
: 1. Total iodine-131 Ci | |||
<LLD | |||
<LLD 1.90E+1 | |||
: 2. Average release rate for period pCi/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 (l) | |||
: 1. Particulates with half-lives >8 days Ci | |||
<LLD 1.89E-6 1.60E+1 | |||
: 2. | |||
Average release rate for period yCi/sec O.OOE+O 2.37E-7 | |||
: 3. Percent of applicable limit | |||
% MPC O.OOE+O 6.33E-7 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL O.OOE+O 1.70E-6 | |||
: 5. | |||
Gross alpha activity | |||
-Ci | |||
<LLD | |||
<LLD 5.OOE+1 D. Tritium | |||
: 1. Total release Ci | |||
<LLD 5.55E-1 2.50E+1 | |||
: 2. | |||
Average release rate for period pCi/sec O.OOE+O 6.98E-2 | |||
: 3. | |||
Percent of applicable limit | |||
% MPC O.OOE+O 4.54E-4 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL O.OOE+O 9.08E-4 (1) | |||
On 7/9/2002, plant vent stack particulate and iodine samples were not collected Tor 4 nrs and 44 minutes. | |||
Prior and subsequent samples were <LLD. There were no dose consequences to the public as a result of this event which is documented in AR 020700464. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE l First Second Third Fourth Radionuclides Released Unit l Quarter I Quarter I Quarter l 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 2.34E-8 cesium-137 Ci | |||
<LLD | |||
<LLD | |||
<LLD 1.80E-6 cobalt-58 | |||
- Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cobalt-60 Ci | |||
<LLD | |||
<LLD | |||
<LLD 6.30E-8 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 (2002) | |||
S.O.N.G.S. 1 TABLE ID GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION | |||
: 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. Iodines iodine-131 2.90E-13 iodine-133 2.80E-12 iodine-135 1.90E-10 | |||
: 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 cobalt-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 | |||
: 4. alpha 1.OOE-11 | |||
: 5. tritium 7.20E-8 NOTE: | |||
Due to the permanent shutdown of longer conducted. | |||
S.O.N.G.S. 1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY l | |||
First l 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 6.69E-6 3.67E-5 O.OOE+O 3.61E-5 | |||
: 2. Percent Applicable Limit 8.92E-5 4.89E-4 O.OOE+O 4.81E-4 NOTE: | |||
Calculations performed in accordance with the ODCM utilizing the historical X/Q. | |||
TABLE 1F GASEOUS EFFLUENTS-BATCH RELEASE | |||
==SUMMARY== | ==SUMMARY== | ||
NOTE: Due to the permanent shutdown of S.O.N.G.S. | NOTE: | ||
1, "BATCH MODE" releases are no longer conducted. | Due to the permanent shutdown of S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT!(2002) | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT!(2002) | ||
S.O.N.G.S. | S.O.N.G.S. 1 SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: | ||
1 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. | ||
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. | Listed for each of the three categories are: | ||
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. | (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: | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution) | ||
1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Unit Quarter Second Quarter Estimated Total Error. %A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 1.OOE-5 3.52E-3 1.90E+1 2. Average diluted concentration during period yCi/ml 6.36E-12 2.09E-9 3. Percent of applicable limit % MPC 3.10E-5 1.35E-2 4. Percent Effluent Concentration Limit % ECL 6.03E-4 1.46E-1 B. Tritium 1. Total release Ci 1.81E-3 1.15E+O 1.90E+1 2. Average diluted concentration during period yCi/ml 1.15E-9 6.85E-7 3. Percent of applicable limit % MPC 3.82E-5 2.28E-2 4. Percent Effluent Concentration Limit % ECL 1.15E-4 6.85E-2 C. Dissolved and entrained gases 1. Total release Ci <LLD <LLD 1.90E+1 2. Average diluted concentration during period pCi/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 | (3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. | ||
: 1. Total release Ci <LLD 1.49E-5 5.0OE+1 E. Volume of waste released (batch &continuous, prior to dilution) liters 1.33E+6 9.OOE+5 5.OOE+O F. Volume of dilution water used during period liters 1.58E+9 1.68E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. | ||
1 TABLE 2A (Continued) | 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. | ||
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, %A. Fission and activation products 1. Total release (not including- | Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. | ||
-tritium,-gases, alpha) | 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. | ||
% MPC 2.35E-2 5.36E-5 4. Percent Effluent Concentration Limit % ECL 2.36E-1 1.07E-3 B. Tritium 1. Total release Ci 4.62E+0 5.83E-4 1.90E+1 2. Average diluted concentration during period yuCi/ml 3.10E-6 3.51E-10 3. Percent of applicable limit % MPC 1.03E-1 1.17E-5-4. Percent Effluent Concentration Limit % ECL 3.10E-1 3.51E-5 C. Dissolved and entrained gases 1. Total release Ci <LLD <LLD 1.90E+1 2. Average diluted concentration during period yCi/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 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. | ||
: 1. Total release E. Volume of waste released (batcl continuous, prior to dilution)F. Volume of dilution water used i period ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
1 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter 1. Fission and activation products | S.O.N.G.S. 1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Unit Quarter Second Quarter Estimated Total Error. % | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | A. Fission and activation products | ||
1 TABLE 2B (Continued) | : 1. Total release (not including tritium, gases, alpha) | ||
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 <LLD <LLD N/A cerium-141 Ci N/A <LLD <LLD N/A cerium-144 Ci N/A <LLD <LLD N/A cesium-134 Ci N/A 9.-93E-5 1.32E-4 N/A cesium-137 Ci N/A 1.79E-3 2.58E-3 N/A chromium-51 Ci N/A <LLD <LLD N/A cobalt-57 Ci N/A <LLD 1.69E-5 N/A cobalt-58 Ci N/A <LLD <LLD N/A cobalt-60 Ci N/A 1.54E-3 2.01E-3 N/A iodine-131 Ci N/A <LLD <LLD N/A iron-55 Ci N/A <LLD 2.84E-3 N/A iron-59 Ci N/A <LLD <LLD N/A lanthanum-140 Ci N/A <LLD <LLD N/A manganese-54 Ci N/A <LLD <LLD N/A molybdenum-99 Ci N/A <LLD <LLD N/A niobium-95 Ci N/A <LLD <LLD N/A strontium-89 Ci N/A 7.21E-5 1.67E-4 N/A strontium-90 Ci N/A 1.55E-5 2.38E-5 N/A technetium-99m Ci N/A <LLD <LLD N/A zinc-65 Ci N/A <LLD <LLD N/A zirconium-95 Ci N/A <LLD <LLD N/A Total for period Ci N/A 3.52E-3 7.77E-3 N/A 2. Dissolved and entrained -gases xenon-133 Ci N/A <LLD <LLD N/A xenon-135 Ci N/A <LLD <LLD N/A Total for period Ci N/A <LLD <LLD N/A N/A No releases conducted LLD Lower Limit of Detection; see Table 2C. | Ci 1.OOE-5 3.52E-3 1.90E+1 | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | : 2. Average diluted concentration during period yCi/ml 6.36E-12 2.09E-9 | ||
1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides lLLD (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 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 (2002)S.O.N.G.S. | : 3. Percent of applicable limit | ||
1 TABLE 2C (Continued) | % MPC 3.10E-5 1.35E-2 | ||
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides l LLD (MCi/cc)1. Fission and activation products barium-140 3.30E-7 cerium-141 5.30E-8 cerium-144 2.30E-7 chromium | : 4. Percent Effluent Concentration Limit % ECL 6.03E-4 1.46E-1 B. Tritium | ||
: 1. Total release Ci 1.81E-3 1.15E+O 1.90E+1 | |||
1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First l Second Third | : 2. Average diluted concentration during period yCi/ml 1.15E-9 6.85E-7 | ||
1 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE | : 3. Percent of applicable limit | ||
% MPC 3.82E-5 2.28E-2 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 1.15E-4 6.85E-2 C. Dissolved and entrained gases | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 1.90E+1 | |||
: 2. Average diluted concentration during period pCi/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 1.49E-5 5.0OE+1 E. Volume of waste released (batch & | |||
continuous, prior to dilution) liters 1.33E+6 9.OOE+5 5.OOE+O F. Volume of dilution water used during period liters 1.58E+9 1.68E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 TABLE 2A (Continued) | |||
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, % | |||
A. Fission and activation products | |||
: 1. Total release (not including- | |||
- tritium,-gases, alpha) | |||
Ci 7.79E-3 1.78E-5 1.90E+1 | |||
: 2. Average diluted concentration during period pCi/ml 5.23E-9 1.07E-11 | |||
: 3. Percent of applicable'limit | |||
% MPC 2.35E-2 5.36E-5 | |||
: 4. Percent Effluent Concentration Limit % ECL 2.36E-1 1.07E-3 B. Tritium | |||
: 1. Total release Ci 4.62E+0 5.83E-4 1.90E+1 | |||
: 2. Average diluted concentration during period yuCi/ml 3.10E-6 3.51E-10 | |||
: 3. Percent of applicable limit | |||
% MPC 1.03E-1 1.17E-5 | |||
-4. Percent Effluent Concentration Limit % ECL 3.10E-1 3.51E-5 C. Dissolved and entrained gases | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 1.90E+1 | |||
: 2. Average diluted concentration during period yCi/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 E. Volume of waste released (batcl continuous, prior to dilution) | |||
F. Volume of dilution water used i period ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
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 9.26E-6 6.74E-6 1.95E-5 1.78E-5 chromium-51 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cobalt-58 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cobalt-60 Ci 7.86E-7 | |||
<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.OOE-5 6.74E-6 1.95E-5 1.78E-5 | |||
: 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 (2002) | |||
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 | |||
<LLD | |||
<LLD N/A cerium-141 Ci N/A | |||
<LLD | |||
<LLD N/A cerium-144 Ci N/A | |||
<LLD | |||
<LLD N/A cesium-134 Ci N/A 9.-93E-5 1.32E-4 N/A cesium-137 Ci N/A 1.79E-3 2.58E-3 N/A chromium-51 Ci N/A | |||
<LLD | |||
<LLD N/A cobalt-57 Ci N/A | |||
<LLD 1.69E-5 N/A cobalt-58 Ci N/A | |||
<LLD | |||
<LLD N/A cobalt-60 Ci N/A 1.54E-3 2.01E-3 N/A iodine-131 Ci N/A | |||
<LLD | |||
<LLD N/A iron-55 Ci N/A | |||
<LLD 2.84E-3 N/A iron-59 Ci N/A | |||
<LLD | |||
<LLD N/A lanthanum-140 Ci N/A | |||
<LLD | |||
<LLD N/A manganese-54 Ci N/A | |||
<LLD | |||
<LLD N/A molybdenum-99 Ci N/A | |||
<LLD | |||
<LLD N/A niobium-95 Ci N/A | |||
<LLD | |||
<LLD N/A strontium-89 Ci N/A 7.21E-5 1.67E-4 N/A strontium-90 Ci N/A 1.55E-5 2.38E-5 N/A technetium-99m Ci N/A | |||
<LLD | |||
<LLD N/A zinc-65 Ci N/A | |||
<LLD | |||
<LLD N/A zirconium-95 Ci N/A | |||
<LLD | |||
<LLD N/A Total for period Ci N/A 3.52E-3 7.77E-3 N/A | |||
: 2. Dissolved and entrained -gases xenon-133 Ci N/A | |||
<LLD | |||
<LLD N/A xenon-135 Ci N/A | |||
<LLD | |||
<LLD N/A Total for period Ci N/A | |||
<LLD | |||
<LLD N/A N/A No releases conducted LLD Lower Limit of Detection; see Table 2C. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides lLLD (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 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 (2002) | |||
S.O.N.G.S. 1 TABLE 2C (Continued) | |||
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides l | |||
LLD (MCi/cc) | |||
: 1. Fission and activation products barium-140 3.30E-7 cerium-141 5.30E-8 cerium-144 2.30E-7 chromium 4.20E-7 cobalt-57 2.90E-8 | |||
- cobalt-58 8.70E-8 iodine-131 6.OOE-8 iron-55 1.OOE-6 | |||
-iron-59 2.OOE-7 lanthanum-140 2.40E-7 X | |||
manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 technetium-99m 3.60E-8 zinc-65 2.20E-7 zirconium-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 (2002) | |||
S.O.N.G.S. 1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First l Second Third Fourth | |||
_ Unit Quarter J Quarter Quarter Quarter A. | |||
: 1. Total body dose mrem 1.03E-4 1.44E-2 5.38E-2 1.27E-4 | |||
: 2. Percent Applicable Limit 6.85E-3 9.62E-1 3.59E+0 8.46E-3 B. | |||
: 1. Limiting organ dose mrem 1.52E-4 3.32E-2 2.21E-1 1.94E-4 | |||
: 2. Percent Applicable Limit 3.05E-3 | |||
-6.63E-1 4.41E+O 3.88E-3 | |||
: 3. Limiting organ for period Liver GI-LLI Bone Li ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE | |||
==SUMMARY== | ==SUMMARY== | ||
12 month period 1. Number of batch releases: | 12 month period | ||
6 releases 2. Total time period for batch releases: | : 1. Number of batch releases: | ||
9229 minutes 3. Maximum time period for a batch release: 3008 minutes 4. Average time period for a batch release: 1538 minutes 5. Minimum time period for a batch release: 682 minutes 6. Average saltwater flow during batch releases: | 6 releases | ||
: 2. Total time period for batch releases: | |||
9229 minutes | |||
: 3. Maximum time period for a batch release: | |||
3008 minutes | |||
: 4. Average time period for a batch release: | |||
1538 minutes | |||
: 5. Minimum time period for a batch release: | |||
682 minutes | |||
: 6. Average saltwater flow during batch releases: | |||
6733 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None. | 6733 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
1 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, | S.O.N.G.S. 1 SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) | ||
* Ci 9.54E+2 3.OOE+1 c. Irradiated components (Excore | Estimated 12 month total | ||
*Ci 2.43E+O 3.OOE+1 d. Other: (High pressure garnet) # | : 1. Type of waste Unit period error (%) | ||
(*) Material packaged in Type A or strong tight containers of various sizes.(#) Material packaged in High Integrity Containers and shipped in Type B Cask.N/A No shipment made. | : a. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | Spent resins, filter sludges, m3 N/A evaporator bottoms Ci N/A N/A | ||
: b. Dry active waste (DAW), | |||
m3 1.10E+3 compactable and non-compactable (incl. demolition rubble) | |||
* Ci 9.54E+2 3.OOE+1 | |||
: c. | |||
Irradiated components (Excore m3 2.66E+O detectors and insulation) | |||
* Ci 2.43E+O 3.OOE+1 | |||
: d. Other: (High pressure garnet) # | |||
m3 3.13E+O Ci 1.18E+3 3.OOE+1 NOTE: Total curie content estimated. | |||
(*) Material packaged in Type A or strong tight containers of various sizes. | |||
(#) | |||
Material packaged in High Integrity Containers and shipped in Type B Cask. | |||
N/A No shipment made. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 | |||
: 2. Estimate of major nuclide composition (by type of waste) | |||
: a. not applicable N/A | |||
: b. americium-241 5.28E-2 carbon-14 1.02E-1 cerium-144 3.20E-2 cesium-134 9.81E-3 cesium-137 1.82E-1 cobalt-58 1.89E-3 cobalt-60 3.63E+1 curium-242 1.49E-5 curium-243/244 2.36E-2 iodine-129 2.21E-5 iron-55 2.76E+1 manganese-54 3.33E-3 nickel-59 5.61E-1 nickel-63 3.30E+1 niobium-94 8.11E-4 niobium-95 1.13E-4 plutonium-238 7.95E-2 plutonium-239/240 2.95E-2 plutonium-241 1.93E+O silver-llOm 4.27E-6 strontium-90 7.10E-2 technetium-99 3.41E-4 tritium 3.61E-2 uranium-233 7.89E-8 zirconium-95 1.32E-4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 | |||
: 2. Estimate of major nuclide composition (by type of waste) | |||
(Cont'd) | |||
: c. americium-241 8.58E-6 carbon-14 2.53E-2 cerium-144 2.82E-6 cesium-134 4.22E-4 cesium-137 2.79E-3 cobalt-60 6.56E+1 curium-242 4.60E-8 curium-243/244 2.92E-6 iron-55 1.61E+1 manganese-54 6.48E-3 nickel-59 1.40E-1 nickel-63 1.81E+1 niobium-94 5.34E-4 plutonium-238 1.51E-5 plutonium-239/240 5.55E-6 plutonium-241 3.48E-4 strontium-90 3.34E-5 technetium-99 1.35E-4 tritium 2.89E-5 uranium-233 3.40E-9 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 | |||
: 2. Estimate of major nuclide composition (by type of waste) | |||
(Cont'd) | |||
: d. americium-241 3.20E-8 carbon-14 4.30E-4 cerium-144 3.41E-8 cesium-137 5.95E-8 cobalt-58 9.56E-8 cobalt-60 4.46E-1 curium-242 1.99E-10 curium-243/244 1.86E-8 iron-55 2.48E-1 manganese-54 5.34E-5 nickel-59 2.19E-3 nickel-63 3.04E-1 niobium-94 6.57E-6 plutonium-238 5.31E-8 plutonium-239/240 1.44E-8 plutonium-241 9.90E-7 strontium-90 1.03E-7 technetium-99 1.40E-6 tritium 4.95E-9 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 | |||
: 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 21 R&R Trucking Company EnviroCare, UT | |||
_____Truck/Trailer 22 MHFLogistical Solutions EnviroCare, UT Rail 2 | |||
KTC/TAG Barnwell, SC Flatbed Trailer BrwlS 2* | |||
R&R Trucking Co. | |||
TN RAM Type B Cask Barnwell, SC These shipments were done in a NRC Type B shipping cask. | |||
IRRADIATED FUEL SHIPMENTS (Disposition) | |||
Number of Shipments Mode of Transportation Destination None No shipments were made N/A B. | |||
C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 qprTTnM P ADDI TrARI P I TMTTRZ I | |||
I | |||
I I. | |||
I - | |||
Gaseous Effluents - ADDlicable 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 0 | |||
MPCelf | |||
= | |||
(Rel Rate) (XIO) (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, pCi/sec. | |||
Number of Shipments Mode of Transportation Destination None No shipments were made N/A B.C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | = | ||
1 qprTTnM P ADDI TrARI P I TMTTRZ I | 1.30E-5 sec/m3; the annual average atmospheric dispersion defined in the Unit 1 ODCM. | ||
-ADDlicable 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: | 1 | ||
= Maximum Permissible Concentration (MPC) of the ijh radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.= (Rel Rate) (X/O) (100)ECLeff where: Fj n MPC, | = | ||
= Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1. | n F | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | 1=1 MPC i | ||
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: | 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. | ||
= | |||
= Effluent Concentration Limit (ECL) of the | total number of radionuclides identified | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)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 | Maximum Permissible Concentration (MPC) of the ijh radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1. | ||
-batch releases are: (1) tank volumes (2) sampling (3) counting (4) calibration Sources of error for gaseous effluents | = | ||
-continuous releases'are: | (Rel Rate) (X/O) (100) | ||
(1) fan flow rate (2) sampling (3) counting (4) calibration (5) differential pressure drop Sources of error for liquid effluents | ECLeff where: | ||
-batch releases are: (1) tank volumes (2) sampling (3)counting (4) calibration Sources of error for liquid effluents | Fj n | ||
: MPC, | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | % ECL where: | ||
1 SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual. | Rel Rate X/Q 0 | ||
ECLeff | |||
= | |||
total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, yCi/sec. | |||
= | |||
1.30E-5 sec/m3; the annual average atmospheric dispersion defined in the Unit 1 ODCM. | |||
1 n | |||
Fi o1l ECL 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, CT. | |||
where: | |||
Fi n | |||
: ECL, | |||
= | |||
total number of radionuclides identified | |||
= | |||
Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
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, ACi/ml. | |||
1 o | |||
MPCeff | |||
= | |||
E F, | |||
1-l 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, Cr. | |||
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 2. | |||
8 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, itCi/ml. | |||
1 | |||
= | |||
n F | |||
EL1 i=1 ECL 0 | |||
ECLef where: | |||
F. | |||
n ECLd | |||
= | |||
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 | |||
= | |||
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 (2002) | |||
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 a I,2 | |||
+ G2 + | |||
G3 +... | |||
G where: | |||
G, = | |||
Error associated with each component. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 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) Liquid Effluents | (1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases - | ||
-Whole Body (2) Liquid Effluents | 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. | ||
-Organ (3) Airborne Effluents | Categories 3, 4, and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) software, Regulatory Guide 1.109 methodology, and concurrent meteorology. | ||
-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). | ||
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. | 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. | ||
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 I-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.' ODCM Figures 2-1 & 2-2. | For members of the public who traverse the site boundary via highway I-5, the residency time shall be considered negligible and hence the dose "0". | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | Table 2 in Section H presents the percent of Applicable Limits for each dose presented in Table 1. | ||
1 TABLE 1 Dose * (millirems) | ' ODCM Figures 2-1 & 2-2. | ||
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
: 1) 2) 3) 4) 5)Whole Body 1.03E-4 1.44E-2 5.38E-2 1.27E-4 6.84E-2 6) 7) 8) 9) 10)Organ 1.52E-4 3.32E-2 2.21E-1 1.94E-4 2.33E-1 AIRBORNE EFFLUENTS | S.O.N.G.S. 1 TABLE 1 Dose * (millirems) | ||
: 11) 12) 13) 14) 15)Tritium, Iodines, and Particulates 2.17E-4 6.06E-4 O.OOE+O 7.42E-4 1.57E-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 1.37E-1 1.23E-1 7.60E-2 1.31E-1 4.67E-1 | First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS | ||
: 1) | |||
6.7.8.9.10.ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | : 2) | ||
1 This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.This value was calculated using the methodology of the ODCM; the bone received the maximum dose primarily by the saltwater fish pathway.This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.This value was calculated using the methodology of the ODCM; the bone 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.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.calculated using the assumptions of USNRC Regulatory Guide 1.109.13. There was no activity detected during the release period, therefore the reported organ O.OOE+O mrem.This was 14.15.16.17.18.19.20.21.22.23.The maximum organ dose was to a child's calculated using the assumptions of USNRC The maximum organ dose was to a child's calculated using the assumptions of USNRC There was no activity detected during the gamma radiation was O.OOE+O mrad.There was no activity detected during the gamma radiation was O.OOE+O mrad.There was no activity detected during the gamma radiation was O.OOE+O mrad.There was no activity detected during the gamma radiation was O.OOE+O mrad.There was no activity detected during the gamma radiation was O.OOE+O mrad.There was no activity detected during the beta radiation was O.OOE+O mrad.There was no activity detected during the beta radiation was O.OOE+O mrad.There was no activity detected during the beta radiation was O.OOE+O mrad.liver and was located in the NW sector.Regulatory Guide 1.109.liver and was located in the NW sector.Regulatory Guide 1.109.release period, therefore release release period, period, therefore therefore therefore therefore therefore release period, the the the the the the the the reported reported reported reported reported reported reported reported air air air air air air air air This dose This This dose dose dose dose dose dose dose dose was was was was for for for for for for for for release release release release period, period, period, therefore period, therefore 24. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad. | : 3) | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | : 4) 5) | ||
Whole Body 1.03E-4 1.44E-2 5.38E-2 1.27E-4 6.84E-2 | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | : 6) | ||
1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 28, 2002, Revision 19 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published. | : 7) | ||
Incorporated into this revision were: 1. A change to the requirement for reporting unplanned releases on a quarterly basis in the annual report, 2. Updates related to the recent Land Use Census, and 3. Changes to the Kelp and Shoreline Sediment environmental sample locations. | : 8) | ||
Item 1 is being changed in response to AR 011000482 to reflect the more generic language of NUREG 0472. An Effluent/ODCM Screen has been provided for item 1. Item 3 changes were made per email from Environmental Protection Group to Effluent Engineering dated 2/1/02.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. | : 9) 10) | ||
Organ 1.52E-4 3.32E-2 2.21E-1 1.94E-4 2.33E-1 AIRBORNE EFFLUENTS | |||
: 11) | |||
: 12) | |||
: 13) | |||
: 14) 15) | |||
Tritium, Iodines, and Particulates 2.17E-4 6.06E-4 O.OOE+O 7.42E-4 1.57E-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 1.37E-1 1.23E-1 7.60E-2 1.31E-1 4.67E-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 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. | |||
e ODCM. | |||
e ODCM. | |||
e ODCM. | |||
e ODCM. | |||
2 ODCM. | |||
6. | |||
7. | |||
8. | |||
9. | |||
10. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway. | |||
This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway. | |||
This value was calculated using the methodology of the ODCM; the bone received the maximum dose primarily by the saltwater fish pathway. | |||
This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway. | |||
This value was calculated using the methodology of the ODCM; the bone 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. | |||
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. | |||
calculated using the assumptions of USNRC Regulatory Guide 1.109. | |||
: 13. | |||
There was no activity detected during the release period, therefore the reported organ O.OOE+O mrem. | |||
This was 14. | |||
15. | |||
16. | |||
17. | |||
18. | |||
19. | |||
20. | |||
21. | |||
22. | |||
23. | |||
The maximum organ dose was to a child's calculated using the assumptions of USNRC The maximum organ dose was to a child's calculated using the assumptions of USNRC There was no activity detected during the gamma radiation was O.OOE+O mrad. | |||
There was no activity detected during the gamma radiation was O.OOE+O mrad. | |||
There was no activity detected during the gamma radiation was O.OOE+O mrad. | |||
There was no activity detected during the gamma radiation was O.OOE+O mrad. | |||
There was no activity detected during the gamma radiation was O.OOE+O mrad. | |||
There was no activity detected during the beta radiation was O.OOE+O mrad. | |||
There was no activity detected during the beta radiation was O.OOE+O mrad. | |||
There was no activity detected during the beta radiation was O.OOE+O mrad. | |||
liver and was located in the NW sector. | |||
Regulatory Guide 1.109. | |||
liver and was located in the NW sector. | |||
Regulatory Guide 1.109. | |||
release period, therefore release release | |||
: period, period, therefore therefore therefore therefore therefore release period, the the the the the the the the reported reported reported reported reported reported reported reported air air air air air air air air This dose This This dose dose dose dose dose dose dose dose was was was was for for for for for for for for release release release release | |||
: period, period, period, therefore period, therefore | |||
: 24. | |||
There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
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 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 W 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 W 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 6.85E-3 9.62E-1 3.59E+O 8.46E-3 2.28E+O Organ 3.05E-3 6.63E-1 4.41E+O 3.88E-3 2.33E+O AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 2.89E-3 8.08E-3 O.OOE+O 9.90E-3 1.04E-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 (2002) | |||
S.O.N.G.S. 1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 28, 2002, Revision 19 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published. | |||
Incorporated into this revision were: | |||
: 1. | |||
A change to the requirement for reporting unplanned releases on a quarterly basis in the annual report, | |||
: 2. | |||
Updates related to the recent Land Use Census, and | |||
: 3. | |||
Changes to the Kelp and Shoreline Sediment environmental sample locations. | |||
Item 1 is being changed in response to AR 011000482 to reflect the more generic language of NUREG 0472. An Effluent/ODCM Screen has been provided for item 1. Item 3 changes were made per email from Environmental Protection Group to Effluent Engineering dated 2/1/02. | |||
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. | 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 10CFR50 will be maintained. | The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.36a, 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 2-21 Updated CLF due to Land Use Census Update. R 2-31 Updated Dose Parameters in Table 2-11, Outage Workers due to Land Use Census R Update.5-22 Removed distances from titles of Shoreline Sediment locations for San Onofre State R Beach (Southeast) | Throughout the document, change bars are marked in one of four ways as follows: | ||
Changed dashes to the word "to" in the distance and directions for Local Crops -F Oceanside (CONTROL). | A Addition D | ||
Deletion F | |||
Editorial/Format change R | |||
Revision The following is a complete list of the changes: | |||
PAGE CHANGE REASON 2-21 Updated CLF due to Land Use Census Update. | |||
R 2-31 Updated Dose Parameters in Table 2-11, Outage Workers due to Land Use Census R | |||
Update. | |||
5-22 Removed distances from titles of Shoreline Sediment locations for San Onofre State R | |||
Beach (Southeast) | |||
Changed dashes to the word "to" in the distance and directions for Local Crops - | |||
F Oceanside (CONTROL). | |||
5-23 Deleted Kelp sample Laguna Beach (CONTROL) | 5-23 Deleted Kelp sample Laguna Beach (CONTROL) | ||
D Added Kelp sample Salt Creek (CONTROL) 11 to 13 miles WNW to NW A Deleted Ocean Sediment sample Unit 1 Outfall D Added Ocean Sediment sample SONGS Upcoast 0.9 miles WSW A 5-26 thru New maps reflecting changes to sample locations R 5-30 6-9 Changed the time frame for unplanned releases reporting in the annual report by R replacing "on a quarterly basis" with "during the reporting period" per AR 011000482. | D Added Kelp sample Salt Creek (CONTROL) 11 to 13 miles WNW to NW A | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | Deleted Ocean Sediment sample Unit 1 Outfall D | ||
1 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, 2002 to December 31, 2002. | Added Ocean Sediment sample SONGS Upcoast 0.9 miles WSW A | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | 5-26 thru New maps reflecting changes to sample locations R | ||
1 SECTION K. MISCELLANEOUS Yard Drain Sump Overflow The Unit 1 Yard Drain sump overflowed to the PMF Catch Basin due to heavy rainfall three times in 2002. 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 Estimated Start Stop Duration Activity Release Whole Body Organ Dose Date/Time Date/Time (min) (pCi/ml) (Curies) Dose (mrem) (mrem)11/29/02 @ 2047 11/29/02 @ 2053 6 <MDA 0.OOE+o o.OOE+O o.OOE+O 12/16/02 @ 1712 12/16/02 @ 1745 33 <MDA O.OOE+O O.OOE+O O.OOE+O 12/20/02 @ 0502 12/20/02 @ 0640 98 <MDA O.OOE+0 O.OOE+0 0.00E+O Airborne Particulate Release During Large Component Removal In October 2002, penetrations were cut into the Containment sphere to allow large component removal (LCR) as a continuation of the decommissioning process.The Unit 1 containment sphere was breached on 10/7/2002 with the removal of the opening above the reactor vessel. The final sphere opening cap was installed 12/10/2002. | 5-30 6-9 Changed the time frame for unplanned releases reporting in the annual report by R | ||
replacing "on a quarterly basis" with "during the reporting period" per AR 011000482. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 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, 2002 to December 31, 2002. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 1 SECTION K. MISCELLANEOUS Yard Drain Sump Overflow The Unit 1 Yard Drain sump overflowed to the PMF Catch Basin due to heavy rainfall three times in 2002. | |||
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 Estimated Start Stop Duration Activity Release Whole Body Organ Dose Date/Time Date/Time (min) | |||
(pCi/ml) | |||
(Curies) | |||
Dose (mrem) | |||
(mrem) 11/29/02 @ 2047 11/29/02 @ 2053 6 | |||
<MDA 0.OOE+o o.OOE+O o.OOE+O 12/16/02 @ 1712 12/16/02 @ 1745 33 | |||
<MDA O.OOE+O O.OOE+O O.OOE+O 12/20/02 @ 0502 12/20/02 @ 0640 98 | |||
<MDA O.OOE+0 O.OOE+0 0.00E+O Airborne Particulate Release During Large Component Removal In October 2002, penetrations were cut into the Containment sphere to allow large component removal (LCR) as a continuation of the decommissioning process. | |||
The Unit 1 containment sphere was breached on 10/7/2002 with the removal of the opening above the reactor vessel. The final sphere opening cap was installed 12/10/2002. | |||
Continuous air sampling was performed at each of the roof openings. | Continuous air sampling was performed at each of the roof openings. | ||
The sample analyses indicated trace amounts of Cs-137 and occasionally Co-60 and Cs-134. The resultant curies and dose are included in the Unit 1 release data (Section B and H) of this report. There were minimal dose consequences to members of the public as a result of this event that is documented in AR 021100412. | The sample analyses indicated trace amounts of Cs-137 and occasionally Co-60 and Cs-134. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | The resultant curies and dose are included in the Unit 1 release data (Section B and H) of this report. | ||
1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 -December 31, 2002 S.O.N.G.S. | There were minimal dose consequences to members of the public as a result of this event that is documented in AR 021100412. | ||
1 Monitor Inoperability Period Inoperability Cause Explanation R-2100 04/24/02 -06/22/02 Corrosion in Corrosion on the Local Processing Reheater Pit Sump electronics and Unit (LPU) caused monitor to fail.Monitor detector -The LPU and detector were replaced.Upon returning to service, the monitor experienced frequent alarms. This event is documented in ARs 020401433 and 020501438. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
09/25/02 -10/29/02 Low sample flow Investigation of flow problems identified debris in canister which was blocking flow. Thorough cleaning of detector restored normal sample flow. This event is documented in AR 020901269. | S.O.N.G.S. 1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 - December 31, 2002 S.O.N.G.S. 1 Monitor Inoperability Period Inoperability Cause Explanation R-2100 04/24/02 - 06/22/02 Corrosion in Corrosion on the Local Processing Reheater Pit Sump electronics and Unit (LPU) caused monitor to fail. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | Monitor detector | ||
1 SECTION L.S.O.N.G.S. | - The LPU and detector were replaced. | ||
1 CONCLUSIONS | Upon returning to service, the monitor experienced frequent alarms. This event is documented in ARs 020401433 and 020501438. | ||
09/25/02 - 10/29/02 Low sample flow Investigation of flow problems identified debris in canister which was blocking flow. Thorough cleaning of detector restored normal sample flow. This event is documented in AR 020901269. | |||
S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
2 and 3 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 SECTION L-INTRODUCTION | S.O.N.G.S. 1 SECTION L. | ||
............-GASEOUS EFFLUENTS | S.O.N.G.S. 1 CONCLUSIONS Gaseous releases totaled 1.42E+O curies'of which noble gases were O.OOE+O curies, iodines were O.OOE+O curies, particulates were 1.89E-6 curies, and tritium was 1.42E+O curies. | ||
..........-LIQUID EFFLUENTS | 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: 1.57E-3 mrem at the nearest receptor. | ||
..........-PREVIOUS RADIOACTIVE EFFLUENT RELEASE-RADWASTE SHIPMENTS | Liquid releases totaled 5.79E+O curies of which particulates and iodines were 1.13E-2 curies, tritium was 5.78E+O curies, and noble gases were O.OOE+O curies. | ||
.........-APPLICABLE LIMITS ..........-ESTIMATION OF ERROR .........-10 CFR 50 APPENDIX I REQUIREMENTS | The radiation doses from liquid releases were: (a) total body: 6.84E-2 mrem, (b) limiting organ: 2.33E-1 mrem. | ||
..-CHANGES TO OFFSITE DOSE CALCULATION M,... | 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. 2 and 3 | |||
2 | |||
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 SECTION L | |||
- INTRODUCTION............ | |||
: | - GASEOUS EFFLUENTS.......... | ||
- LIQUID EFFLUENTS.......... | |||
- PREVIOUS RADIOACTIVE EFFLUENT RELEASE | |||
- RADWASTE SHIPMENTS......... | |||
- APPLICABLE LIMITS.......... | |||
- ESTIMATION OF ERROR......... | |||
- 10 CFR 50 APPENDIX I REQUIREMENTS.. | |||
2 | - CHANGES TO OFFSITE DOSE CALCULATION M, REPORT 34 35 45 ADDENDUM....... | ||
53 54 57 59 60 | |||
............ 64 MS.......... 65 | |||
2 | ............ 66 | ||
............ 69 lANUAL | |||
- | - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTE | ||
- MISCELLANEOUS............... | |||
S.O.N.G.S. 2 and 3 CONCLUSIONS...... | |||
-iii- | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | 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: | ||
2 and 3 TABLE | : 1. | ||
GASEOUS EFFLUENTS- | Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release | ||
: 2. | |||
Percent of Applicable Limits | |||
- | : 3. | ||
2 | Estimated Total Percent Error | ||
: 4. | |||
Lower Limit of Detection Concentrations | |||
2 | : 5. | ||
Batch Release Summaries | |||
2 and 3 TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE | : 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 (2002) | |||
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 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 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 IC. | |||
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 (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error, e A. Fission and activation gases | |||
: 1. Total release Ci 8.23E+O 3.32E+1 3.OOE+1 | |||
: 2. Average release rate for period yCi/sec 1.06E+O 4.22E+O | |||
: 3. Percent of applicable limit | |||
% MPC 2.57E-3 1.11E-2 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 4.97E-3 2.32E-2 B. lodines | |||
: 1. Total iodine-131 Ci 2.03E-5 1.73E-2 1.90E+1 | |||
: 2. Average release rate for period pCi/sec 2.61E-6 2.20E-3 | |||
: 3. Percent of applicable limit | |||
% MPC 1.25E-5 1.06E-2 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 6.27E-6 5.28E-3 C. Particulates | |||
: 1. Particulates with half-lives >8 days Ci 8.10E-5 1.17E-4 1.60E+1 | |||
: 2. Average release rate for period AtCi/sec 1.04E-5 1.48E-5 | |||
: 3. Percent of applicable limit | |||
% MPC 9.75E-6 6.76E-6 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 2.43E-5 1.57E-5 | |||
: 5. Gross alpha activity Ci 5.58E-6 | |||
<LLD 5.OOE+1 D. Tritium | |||
: 1. Total release Ci 1.26E+1 1.51E+1 2.50E+1 | |||
: 2. Average release rate for period uCi/sec 1.62E+O 1.92E+O | |||
: 3. Percent of applicable limit | |||
% MPC 3.89E-3 4.61E-3 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 7.78E-3 9.22E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 1A (Continued) | |||
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, % | |||
A. Fission and activation gases | |||
: 1. Total release Ci 1.33E+1 8.81E+O 3.00E+1 | |||
: 2. Average release rate for period ptCi/sec 1.67E+O 1.11E+O | |||
: 3. Percent of applicable limit | |||
% MPC 1.10E-2 4.40E-3 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 3.92E-2 -1.29E-2 B. Iodines | |||
: 1. Total iodine-131 Ci 1.70E-5 1.27E-5 1.90E+1 | |||
: 2. Average release rate for period yCi/sec 2.14E-6 1.60E-6 3: Percent of applicable limit l% MPC 1.03E-5 7.67E-6 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 5.13E-6 3.83E-6 C. Particulates | |||
: 1. Particulates with half-lives >8 days Ci 5.16E-5 6.42E-5 1.60E+1 | |||
: 2. Average release rate for period pCi/sec 6.49E-6 8.07E-6 | |||
: 3. Percent of applicable limit | |||
% MPC 3.89E-6 7.31E-6 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 9.35E-6 1.82E-5 | |||
: 5. Gross alpha activity Ci | |||
<LLD | |||
<LLD 5.0OE+1 D. Tritium | |||
: 1. Total release Ci 1.08E+1 5.78E+O 2.50E+1 | |||
: 2. Average release rate for period iCi/sec 1.36E+O 7.27E-1 | |||
: 3. Percent of applicable limit | |||
% MPC 3.26E-3 1.75E-3 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 6.52E-3 3.49E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE 1 First Second F Third Fourth Radionuclides Released Unit Quarter Quarter I Quarter Quarter | |||
: 1. Fission and activation gases argon-41 Ci 6.58E-1 3.16E+O 6.35E+O 2.01E+O krypton-85 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD krypton-85m Ci | |||
<LLD 2.54E-2 | |||
<LLD | |||
<LLD krypton-87 Ci | |||
<LLD | |||
<1.22E-3 LLD | |||
<LLD krypton-88 Ci | |||
<LLD 3.46E-3 | |||
<LLD | |||
<LLD xenon-133 Ci 6.86E+O 2.82E+1 6.19E+O 6.50E+O xenon-133m Ci | |||
<LLD 4.95E-1 | |||
<LLD | |||
<LLD xenon-135 Ci | |||
<LLD 3.79E-1 | |||
<LLD | |||
<LLD xenon-135m Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD xenon-138 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD Total for period Ci 7.52E+O 3.23E+1 1.25E+1 8.52E+O | |||
: 2. Iodines iodine-131 Ci 2.03E-5 1.73E-2 1.70E-5 1.27E-5 iodine-132 Ci | |||
<LLD 1.08E-2 | |||
<LLD 1.16E-7 iodine-133 Ci 3.03E-5 6.42E-4 5.84E-6 1.87E-5 iodine-135 Ci | |||
<LLD | |||
<LLD | |||
<LLD 1.36E-6 Total for period Ci 5.05E-5 2.87E-2 2.29E-5 I 3.28E-5 LLD Lower Limit of Detection; see Table 1D. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 1C (Continued) | |||
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I | |||
First Second Third Fourth Radionuclides Released Unit | |||
'Quarter I Quarter Quarter Quarter | |||
: 3. Particulates barium-140 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD bromine-82 Ci 2.70E-5 9.70E-5 9.39E-5 4.73E-5 cerium-141 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cerium-144 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cesium-134 Ci 8.40E-8 4.61E-8 | |||
<LLD | |||
<LLD cesium-137 Ci 7.82E-5 3.49E-5 2.58E-5 | |||
-5.93E-5 cobalt-58 Ci 2.67E-6 8.17E-5 2.58E-5 4.86E-6 cobalt-60 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 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. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 1C (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 7.10E-1 7.56E-1 6.21E-1 2.99E-1 krypton-85m Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD krypton-87 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD krypton-88 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD xenon-131m Ci | |||
<LLD 3.25E-2 | |||
<LLD | |||
<LLD xenon-133 Ci 1.69E-3 1.09E-1 1.02E-1 | |||
<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 7.11E-1 8.98E-1 7.23E-1 2.99E-1 LLD Lower Limit of Detection; see Table 1D. | |||
Iodines and particulates are not analyzed prior to release via batch mode. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (yCi/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-133m 4.10E-7 xenon-135 5.30E-8 xenon-135m 2.OOE-6 xenon-138 3.50E-6 | |||
: 2. Iodines iodine-132 6.OOE-10 iodine-135 1.70E-10 | |||
: 3. Particulates bar um-140 2.70E-11 cerium-141 3.40E-12 cerium-144 1.40E-11 cesium-134 9.20E-12 cobalt-60 1.30E-11 iron-59 2.OOE-11 lanthanum-140 2.20E-11 manganese-54 8.20E-12 molybdenum-99 2.10E-12 strontium-89 1.OOE-13 strontium-90 1.OOE-14 zinc-65 2.20E-11 | |||
: 4. alpha 1.OOE-11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE iD (Continued) | |||
GASEOUS EFFLUENTS-LOWER LIMIT BATCH MODE OF DETECTION Radionuclides lLLD (yCi/cc) | |||
: 1. Fission and activation gases krypton-85m 2.50E-6 krypton-87 1.20E-5 krypton-88 8.90E-6 xenon-131m 1.70E-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 (2002) | |||
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 1.30E-3 6.14E-3 9.35E-3 3.18E-3 | |||
: 2. Percent Applicable Limit 1.30E-2 6.14E-2 9.35E-2 3.18E-2 | |||
: 3. Beta Air Dose mrad 1.64E-3 6.60E-3 4.43E-3 2.06E-3 | |||
: 4. | |||
Percent Applicable Limit 8.18E-3 3.30E-2 2.21E-2 1.03E-2 B. Tritium, Iodine, Particulates (at the nearest receptor) | |||
: 1. Organ Dose mrem 7.85E-4 1.46E-2 6.21E-4 4.59E-4 | |||
: 2. Percent Applicable Limit I 5.24E-3 9.74E-2 4.14E-3 3.06E-3 NOTE: | |||
Calculations performed in accordance with the ODCM utilizing the historical X/Q. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE | |||
==SUMMARY== | ==SUMMARY== | ||
12 month period 1. Number of batch releases: | 12 month period | ||
10 releases 2. Total time period for batch releases: | : 1. Number of batch releases: | ||
4340 minutes 3. Maximum time period for a batch release: 582 minutes 4. Average time period for a batch release: 434 minutes 5. Minimum time period for a batch release: 145 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | 10 releases | ||
2 and 3 SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: | : 2. Total time period for batch releases: | ||
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. | 4340 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. | : 3. Maximum time period for a batch release: | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | 582 minutes | ||
2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Unit Quarter Second Quarter Estimated Total Error, %A. Fission and activation products 1. Total release (not including tritium, gases, alpha) Ci 1.03E-3 5.81E-3 1.90E+1 2. Average diluted concentration during period pCi/ml 1.37E-12 9.15E-12 3. Percent of applicable limit % MPC 2.62E-6 2.10E-5 4. Percent Effluent Concentration Limit % ECL 2.01E-5 1.64E-4 B. Tritium 1. Total release Ci 4.26E+1 6.54E+2 1.90E+1 2. Average diluted concentration during period uCi/ml 5.70E-8 1.03E-6 3. Percent of applicable limit % MPC 1.90E-3 3.44E-2 4. Percent Effluent Concentration Limit % ECL 5.70E-3 1.03E-1 C. Dissolved and entrained gases 1. Total release Ci <LLD 2.40E-1 1.90E+1 2. Average diluted concentration during period yCi/ml O.OOE+O 3.78E-10 3. Percent of applicable limit % MPC O.OOE+O 1.89E-4 4. Percent Effluent Concentration Limit % ECL O.OOE+O 1.89E-4 D. Gross alpha radioactivity | : 4. Average time period for a batch release: | ||
: 1. Total release Ci <LLD <LLD 5.0OE+1 E. Volume of waste released (batch &continuous, prior to dilution) liters 1.12E+8 9.03E+7 5.OOE+O F. Volume of dilution water used during period liters 7.47E+11 6.34E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | 434 minutes | ||
2 and 3 TABLE 2A (Continued) | : 5. Minimum time period for a batch release: | ||
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Third -Fourth Unit Quarter Quarter Estimated Total Error, %A. Fission and activation products 1. Total release (not including-tritium, gases, alpha) Ci 3.06E-3 6.69E-3 1.90E+1 2. Average diluted concentration during period | 145 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
% ECL 8.37E-5 2.47E-4 B. Tritium 1. -Total release Ci 1.16E+2 6.76E+2 1.90E+1 2. Average diluted concentration during period yCi/ml 1.56E-7 8.80E-7 3. -Percent of applicable limit % MPC 5.20E-3 2.93E-2 4. Percent Effluent Concentration Limit % ECL 1.56E-2 8.80E-2 C. Dissolved and entrained gases | 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: | ||
: 1. Total release Ci 2.15E-5 <LLD 5.OOE+1 E. Volume of waste released (batch &continuous, prior to dilution) liters 1.17E+8 1.06E+8 5.OOE+O F. Volume of dilution water used during period liters 7.43E+11 7.68E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | fission and activation products, tritium, and dissolved and entrained gases. | ||
2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE I First Second Third Fourth Radionuclides Released l Unit l Quarter l Quarter l Quarter l 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 | 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) | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | (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. | ||
2 and 3 TABLE 2B (Continued) | 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. | ||
LIQUID EFFLUENTS BATCH | Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides'not detected in Table 2B. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)'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 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides lLLD (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 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-go 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 (2002)S.O.N.G.S. | 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. | ||
2 and 3 TABLE 2C (Continued) | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
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 cesium-134 9.90E-8 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 molybdenum-99 3.50E-8 niobium-95 8.50E-8 niobium-97 2.OOE-7 silver-110m 1.30E-7 strontium-89 5.OOE-8 strontium-90 1.OOE-8 strontium-92 | S.O.N.G.S. 2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Unit Quarter Second Quarter Estimated Total Error, % | ||
-7.80E-5 technetium-99m 3.60E-8 tin-113 7.50E-8 tungsten-187 4.90E-7 zinc-65 2.20E-7 zirconium-95 1.50E-7 2. Dissolved and entrained gases krypton-85 4.20E-5 xenon-131m 4.OOE-6 xenon-133 3.10E-7 xenon-133m 9.20E-7 xenon-135 1.20E-7 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | A. Fission and activation products | ||
2 and 3 TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOL LIQUI1 | : 1. Total release (not including tritium, gases, alpha) | ||
2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE | Ci 1.03E-3 5.81E-3 1.90E+1 | ||
: 2. Average diluted concentration during period pCi/ml 1.37E-12 9.15E-12 | |||
: 3. Percent of applicable limit | |||
% MPC 2.62E-6 2.10E-5 | |||
: 4. Percent Effluent Concentration Limit % ECL 2.01E-5 1.64E-4 B. Tritium | |||
: 1. Total release Ci 4.26E+1 6.54E+2 1.90E+1 | |||
: 2. Average diluted concentration during period uCi/ml 5.70E-8 1.03E-6 | |||
: 3. Percent of applicable limit | |||
% MPC 1.90E-3 3.44E-2 | |||
: 4. Percent Effluent Concentration Limit % ECL 5.70E-3 1.03E-1 C. Dissolved and entrained gases | |||
: 1. Total release Ci | |||
<LLD 2.40E-1 1.90E+1 | |||
: 2. Average diluted concentration during period yCi/ml O.OOE+O 3.78E-10 | |||
: 3. Percent of applicable limit | |||
% MPC O.OOE+O 1.89E-4 | |||
: 4. Percent Effluent Concentration Limit % ECL O.OOE+O 1.89E-4 D. Gross alpha radioactivity | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 5.0OE+1 E. Volume of waste released (batch & | |||
continuous, prior to dilution) liters 1.12E+8 9.03E+7 5.OOE+O F. Volume of dilution water used during period liters 7.47E+11 6.34E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 2A (Continued) | |||
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Third | |||
-Fourth Unit Quarter Quarter Estimated Total Error, % | |||
A. Fission and activation products | |||
: 1. Total release (not including-tritium, gases, alpha) | |||
Ci 3.06E-3 6.69E-3 1.90E+1 | |||
: 2. Average diluted concentration during period A | |||
Ci/ml 4.12E-12 8.71E-12 | |||
: 3. Percent of applicable limit | |||
% MPC 7.21E-6 2.07E-5 | |||
: 4. Percent Effluent Concentration-Limit % ECL 8.37E-5 2.47E-4 B. Tritium | |||
: 1. -Total release Ci 1.16E+2 6.76E+2 1.90E+1 | |||
: 2. Average diluted concentration during period yCi/ml 1.56E-7 8.80E-7 | |||
: 3. -Percent of applicable limit | |||
% MPC 5.20E-3 2.93E-2 | |||
: 4. Percent Effluent Concentration Limit % ECL 1.56E-2 8.80E-2 C. Dissolved and entrained gases 1.- Total release Ci 6.82E-3 4.81E-2 1.90E+1 | |||
: 2. Average diluted concentration during period MCi/ml 9.19E-12 6.25E-11 | |||
: 3. -Percent of applicable limit | |||
% MPC 4.59E-6 3.13E-5 | |||
: 4. Percent Effluent Concentration Limit % ECL 4.59E-6 3.13E-5 D. Gross alpha radioactivity | |||
: 1. Total release Ci 2.15E-5 | |||
<LLD 5.OOE+1 E. Volume of waste released (batch & | |||
continuous, prior to dilution) liters 1.17E+8 1.06E+8 5.OOE+O F. Volume of dilution water used during period liters 7.43E+11 7.68E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE I | |||
First Second Third Fourth Radionuclides Released l Unit l Quarter l Quarter l Quarter l 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 | |||
<LLD | |||
<LLD | |||
<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 | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD | |||
: 2. Dissolved and entrained gases xenon-133 Ci | |||
<LLD | |||
<LD | |||
<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 (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 2B (Continued) | |||
LIQUID EFFLUENTS BATCH MODE l First l Second 1 Third Fourth Radionuclides Released Unit l Quarter Quarter l Quarter Quarter | |||
: 1. Fission and activation products antimony-125 Ci 3.14E-4 1.94E-3 1.01E-3 3.13E-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 | |||
<LLD 1.32E-4 7.39E-5 2.98E-4 cesium-137 Ci 2.41E-5 5.66E-4 4.21E-4 1.25E-3 chromium-51 Ci | |||
<LLD 3.35E-4 3.12E-4 2.13E-5 cobalt-58 Ci 3.22E-4 2.24E-3 5.64E-4 8.53E-4 cobalt-60 Ci 2.50E-4 3.47E-4 1.20E-4 4.29E-4 iodine-131 Ci | |||
<LLD 8.73E-6 | |||
<LLD | |||
<LLD iron-55 Ci | |||
<LLD | |||
<LLD 3.44E-4 | |||
<LLD iron-59 Ci | |||
<LLD | |||
<LLD 2.55E-5 | |||
<LLD lanthanum-140 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD manganese-54 Ci 2.38E-5 3.63E-5 2.90E-5 8.43E-5 molybdenum-99 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD niobium-95 Ci | |||
<LLD 4.07E-5 8.27E-5 3.96E-4 niobium-97 Ci | |||
<LLD 9.33E-6 | |||
<LLD | |||
<LLD silver-110m Ci 9.30E-5 1.17E-4 2.68E-5 | |||
<LLD strontium-89 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD strontium-90 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD strontium-92 Ci | |||
<LLD 2.10E-6 2.06E-6 | |||
<LLD technetium-99m Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD tin-113 Ci | |||
<LLD | |||
<LLD 4.27E-6 | |||
<LLD tungsten-187 Ci | |||
<LLD 8.59E-6 | |||
<LLD | |||
<LLD zinc-65 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD zirconium-95 Ci | |||
<LLD 1.98E-5 4.57E-5 2.26E-4 Total for period Ci 1.03E-3 5.81E-3 3.06E-3 6.69E-3 | |||
: 2. Dissolved and entrained gases krypton-85 Ci | |||
<LLD 5.82E-2 5.89E-3 2.36E-2 (xenon-131m Ci | |||
<LLD-7.03E-3 | |||
<LLD 1.01E-3 xenon-133 Ci | |||
<LLD 1.74E-1 9.37E-4 2.34E-2 xenon-133m Ci | |||
<LLD 5.02E-4 | |||
<LLD | |||
<LLD xenon-135 Ci | |||
<LLD | |||
<LLD | |||
<LLD 1.11E-5 Total for period Ci | |||
<LLD 2.40E-1 6.82E-3 4.81E-2 LLD Lower Limit of Detection; see Table 2C. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)' | |||
S.O.N.G.S. 2 and 3 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides lLLD (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 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-go 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 (2002) | |||
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 cesium-134 9.90E-8 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 molybdenum-99 3.50E-8 niobium-95 8.50E-8 niobium-97 2.OOE-7 silver-110m 1.30E-7 strontium-89 5.OOE-8 strontium-90 1.OOE-8 strontium-92 | |||
-7.80E-5 technetium-99m 3.60E-8 tin-113 7.50E-8 tungsten-187 4.90E-7 zinc-65 2.20E-7 zirconium-95 1.50E-7 | |||
: 2. Dissolved and entrained gases krypton-85 4.20E-5 xenon-131m 4.OOE-6 xenon-133 3.10E-7 xenon-133m 9.20E-7 xenon-135 1.20E-7 | |||
: 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOL LIQUI1 INDARY First l Second I Third 1 Fourth Unit Quarter Quarter Quarter Quarter A. | |||
: 1. Total body dose mrem 8.16E-5 1.16E-3 2.56E-4 1.23E-3 | |||
: 2. Percent Applicable Limit I | |||
2.72E-3 3.87E-2 8.54E-3 4.11E-2 B. | |||
: 1. Limiting organ dose mrem 4.47E-4 1.74E-3 5.14E-4 1.36E-3 | |||
: 2. Percent Applicable Limit 4.47E-3 1.74E-2 5.14E-3 1.36E-2 | |||
: 3. Limiting organ for period GI-LLI GI-LLI GI-LLI GI-LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE | |||
==SUMMARY== | ==SUMMARY== | ||
12 month period 1. Number of batch releases: | 12 month period | ||
170 releases 2. Total time period for batch releases: | : 1. Number of batch releases: | ||
26435 minutes 3. Maximum time period for a batch release: 510 minutes 4. Average time period for a batch release: 156 minutes 5. Minimum time period for a batch release: 5 minutes 6. Average saltwater flow during batch releases: | 170 releases | ||
: 2. Total time period for batch releases: | |||
26435 minutes | |||
: 3. Maximum time period for a batch release: | |||
510 minutes | |||
: 4. Average time period for a batch release: | |||
156 minutes | |||
: 5. Minimum time period for a batch release: | |||
5 minutes | |||
: 6. Average saltwater flow during batch releases: | |||
735000 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None. | 735000 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
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, | 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) | ||
Ci 3.31E+2 3.0OE+1 c. Irradiated components, control m3 N/A rods Ci N/A N/A d. Other | Estimated 12 month total error | ||
(*) Material packaged in Type A or strong tight containers of various sizes.N/A No shipment made. | : 1. Type of waste Unit period | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | (%) | ||
2 and 3 2. Estimate of major nuclide composition (by type of waste)a. not applicable | : a. Spent resins, filter sludges, m3 N/A evaporator bottoms Ci N/A N/A | ||
: b. Dry active waste (DAW), | |||
m3 2.09E+2 compactable and non-compactable* | |||
Ci 3.31E+2 3.0OE+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 Type A or strong tight containers of various sizes. | |||
N/A No shipment made. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
__3.40E-5 iodine-129 3.95E-11 iron-55 | S.O.N.G.S. 2 and 3 | ||
: 2. Estimate of major nuclide composition (by type of waste) | |||
: a. not applicable N/A | |||
: b. americium-241 3.56E-5 antimony-124 5.67E-8 antimony-125 1.18E-2 carbon-14 2.13E-2 cerium-144 1.43E-7 cesium-134 8.76E-3 cesium-137 6.73E-2 chromium-51 7.87E-2 cobalt-57 2.31E-8 cobalt-58 3.33E-1 cobalt-60 1.25E-1 curium-242 | |||
__1.36E-2 c. not applicable | _1.05E-5 curium-243/244 | ||
__O.OOE+O d. not applicable | __3.40E-5 iodine-129 3.95E-11 iron-55 1.63E-1 iron-59 6.64E-3 manganese-54 2.51E-2 nickel-59 6.22E-6 nickel-63 1.19E-1 niobium-94 1.47E-6 niobium-95 2.05E-2 plutonium-238 2.07E-5 plutonium-239/240 1.99E-5 plutonium-241 1.65E-3 ruthenium-103 2.74E-7 silver-llOm 1.30E-5 strontium-90 2.03E-4 technetium-99 5.85E-5 tin-113 1.28E-8 tritium 3.19E-3 uranium-233/234 2.62E-9 uranium-238 8.90E-12 zirconium-95 | ||
__O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | __1.36E-2 | ||
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 None No shipments were made N/A B. IRRADIATED FUEL SHIPMENTS (Disposition) | : c. | ||
Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers l Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | not applicable | ||
2 and 3 SECTION F. APPLICABLE LIMITS Gaseous Effluents | __O.OOE+O | ||
-Applicable Limits -The percent of Applicable Limits, tabulated in Sections A, B, C, and D of Table 1A, were calculated using the following equation:* % Applicable Limit where: Rel Rate X/Q o MPCeff where: | : d. | ||
= Effluent Concentration Limit (ECL) of the | not applicable | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | __O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
2 and 3 Liquid Effluents | S.O.N.G.S. 2 and 3 A. | ||
-Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations: | SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) | ||
* % Applicable Limit where: Dil Conc o MPCeff= (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, 4Ci/ml.1= n F i.1 MPC where: F, n | : 3. | ||
= Maximum Permissible Concentration (MPC) of the iih 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, uCi/ml.1= n F 121 ECL° ECLeff where: F.n ECL,= fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Cr, by the sum of all the isotopic activity, CT.= total number of radionuclides identified | Solid Waste Disposition Number of Shipments Mode of Transportation Destination None No shipments were made N/A B. | ||
= Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2. | IRRADIATED FUEL SHIPMENTS (Disposition) | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. | ||
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 | DEWATERING Number of Containers l Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
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 1A, were calculated using the following equation: | |||
* % Applicable Limit where: | |||
Rel Rate X/Q o | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | MPCeff where: | ||
2 and 3 SECTION H.10 CFR 50 APPENDIX I REQUIREMENTS | F1 | ||
= | |||
(Rel Rate) (X/Q) (100) | |||
MPCe~f | |||
= | |||
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. | |||
= | |||
4.80E-6 sec/r3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM. | |||
1 | |||
_n Fi 1=. | |||
MPC 1 | |||
= | |||
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 MPC1 Maximum Permissible Concentration (MPC) radionuclide from 10 CFR 20 (20.1-20.602), | |||
Table II, Column 1. | |||
of the i t | |||
Appendix B, | |||
% ECL where: | |||
Rel Rate X/Q | |||
° ECLeff where: | |||
F1 | |||
= | |||
(Rel Rate) (X/Q) (100) | |||
ECLeff | |||
= | |||
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, pCi/sec. | |||
= | |||
4.80E-6 sec/n3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM. | |||
1 | |||
=n F | |||
E 1 | |||
1=1 ECL s | |||
= | |||
fractional abundance of the ij radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, CT. | |||
n | |||
: ECL, total number of radionuclides identified | |||
= | |||
Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 Liquid Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations: | |||
* % Applicable Limit where: | |||
Dil Conc o | |||
MPCeff | |||
= | |||
(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, 4Ci/ml. | |||
1 | |||
= | |||
n F | |||
i.1 MPC where: | |||
F, n | |||
MPC1 | |||
* % ECL where: | |||
Dil Conc | |||
= | |||
fractional abundance of the i t | |||
radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, CT. | |||
= | |||
total number of radionuclides identified | |||
= | |||
Maximum Permissible Concentration (MPC) of the iih 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, uCi/ml. | |||
1 | |||
= | |||
n F | |||
121 ECL | |||
° ECLeff where: | |||
F. | |||
n | |||
: ECL, | |||
= | |||
fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Cr, 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 2. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
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 | |||
= | |||
+ | |||
G2 + | |||
22 | |||
+ | |||
where: | |||
Error associated with each component. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
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) | ||
-Whole Body Liquid Effluents | (2) | ||
-Organ Airborne Effluents | (3) | ||
-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. | (4) | ||
Table IE 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. | (5) | ||
Each portion of each category is footnoted to briefly describe each maximum individual dose presented. | (6) | ||
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 ODCM Figures 2-1 & 2-2. | Liquid Effluents - Whole Body Liquid Effluents - Organ Airborne Effluents - Tritium, Iodines and Particulates Noble Gases - Gamma Noble Gases - Beta Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; these data are also presented in Table 2D. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | Categories 3, 4, and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) software, Regulatory Guide 1.109 methodology, and concurrent meteorology. Table IE 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). | ||
2 and 3 TABLE 1 Dose * (millirems) | 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. | |||
: 1) 2) 3) 4) 5)Whole Body 8.16E-5 1.16E-3 2.56E-4 1.23E-3 2.73E-3 6) 7) 8) 9) 10)Organ 4.47E-4 1.74E-3 5.14E-4 1.36E-3 4.06E-3 AIRBORNE EFFLUENTS | 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". | ||
: 11) 12) 13) 14) 15)Tritium, Iodines, and Particulates 5.98E-3 1.18E-2 2.93E-3 -5.10E-4 1.35E-2 NOBLE GASES ** 16) 17) 18) 19) 20)Gamma 3.48E-4 1.30E-3 5.71E-3 3.82E-3 9.18E-3 21) 22) 23) 24) 25)Beta 7.58E-4 1.30E-3 2.68E-3 2.02E-3 6.37E-3 26) 27) 28) 29) 30)DIRECT RADIATION 1.37E-1 1.23E-1 7.60E-2 1.31E-1 4.67E-1 | Table 2 in Section H in Table 1. | ||
presents the percent of Applicable Limits for each dose presented ODCM Figures 2-1 & 2-2. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
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.7. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.8. This value was calculated using the methodology of the ODCM; the GI-LLI 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 NNW 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 ENE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.13. The maximum organ dose was to a child's liver and was located in the NNW 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 NNW 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 ENE 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 E 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 E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. | S.O.N.G.S. 2 and 3 TABLE 1 Dose * | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | (millirems) | ||
2 and 3 25. 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 1.109.26. 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 W 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 W 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 2.72E-3 3.87E-2 8.54E-3 4.11E-2 4.56E-2 Organ 4.47E-3 1.74E-2 5.14E-3 1.36E-2 2.03E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 3.99E-2 7.84E-2 1.95E-2 3.40E-3 4.50E-2 NOBLE GASES Gamma 3.48E-3 1.30E-2 5.71E-2 3.82E-2 4.59E-2 Beta 3.79E-3 6.51E-3 1.34E-2 1.01E-2 1.59E-2 NOTE: Direct Radiation is hot specifically addressed in the Applicable Limits. | First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | : 1) | ||
2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 28, 2002, Revision 37 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. | : 2) | ||
This change incorporated the following: | : 3) | ||
: 1. A change to the requirement for reporting unplanned releases on a quarterly basis in the annual report, 2. Updates related to the recent Land Use Census, and 3. Changes to Kelp and Shoreline Sediment environmental sample locations. | : 4) 5) | ||
Item 1 is being changed in response to AR 011000482 to reflect the more generic language of NUREG 0472. An Effluent/ODCM Screen has been provided for item 1. Item 3 changes were made per email from Environmental Protection Group to Effluent Engineering dated 2/1/02.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. | Whole Body 8.16E-5 1.16E-3 2.56E-4 1.23E-3 2.73E-3 | ||
: 6) | |||
: 7) | |||
: 8) | |||
: 9) 10) | |||
Organ 4.47E-4 1.74E-3 5.14E-4 1.36E-3 4.06E-3 AIRBORNE EFFLUENTS | |||
: 11) | |||
: 12) | |||
: 13) | |||
: 14) 15) | |||
Tritium, Iodines, and Particulates 5.98E-3 1.18E-2 2.93E-3 | |||
-5.10E-4 1.35E-2 NOBLE GASES ** | |||
: 16) | |||
: 17) | |||
: 18) | |||
: 19) 20) | |||
Gamma 3.48E-4 1.30E-3 5.71E-3 3.82E-3 9.18E-3 | |||
: 21) | |||
: 22) | |||
: 23) | |||
: 24) 25) | |||
Beta 7.58E-4 1.30E-3 2.68E-3 2.02E-3 6.37E-3 | |||
: 26) | |||
: 27) | |||
: 28) | |||
: 29) 30) | |||
DIRECT RADIATION 1.37E-1 1.23E-1 7.60E-2 1.31E-1 4.67E-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 th( | |||
: 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 th( | |||
: 5. This value was calculated using the methodology of thE maximum dose was calculated, including of mrad, reflecting the air dose. | |||
e ODCM. | |||
? ODCM. | |||
2 ODCM. | |||
a ODCM. | |||
a ODCM. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
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. | |||
: 7. | |||
This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway. | |||
: 8. | |||
This value was calculated using the methodology of the ODCM; the GI-LLI 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 NNW 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 ENE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109. | |||
: 13. The maximum organ dose was to a child's liver and was located in the NNW 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 NNW 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 ENE 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 E 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 E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 | |||
: 25. 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. | |||
: 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 W 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 W 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 2.72E-3 3.87E-2 8.54E-3 4.11E-2 4.56E-2 Organ 4.47E-3 1.74E-2 5.14E-3 1.36E-2 2.03E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 3.99E-2 7.84E-2 1.95E-2 3.40E-3 4.50E-2 NOBLE GASES Gamma 3.48E-3 1.30E-2 5.71E-2 3.82E-2 4.59E-2 Beta 3.79E-3 6.51E-3 1.34E-2 1.01E-2 1.59E-2 NOTE: | |||
Direct Radiation is hot specifically addressed in the Applicable Limits. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 28, 2002, Revision 37 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated the following: | |||
: 1. | |||
A change to the requirement for reporting unplanned releases on a quarterly basis in the annual report, | |||
: 2. | |||
Updates related to the recent Land Use Census, and | |||
: 3. | |||
Changes to Kelp and Shoreline Sediment environmental sample locations. | |||
Item 1 is being changed in response to AR 011000482 to reflect the more generic language of NUREG 0472. An Effluent/ODCM Screen has been provided for item 1. Item 3 changes were made per email from Environmental Protection Group to Effluent Engineering dated 2/1/02. | |||
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 calculations. | None of the changes impact calculations. | ||
The level 40CFR190, | The level 40CFR190, 10CFR50.36a, and the accuracy or reliability of effluent dose or setpoint of radioactive effluent control required by 10CFR20, Appendix I to 10CFR50 will be maintained. | ||
Throughout the document, change bars are marked in one of four ways as follows: A D F R Addition Deletion Editorial/Format change Revision The following is a complete list of the changes: PAGE CHANGE TOC Renumbered pages as necessary based on changes in the body of the ODCM.2-39 Format change for numbers 2-31 Updated CLF due to Land Use Census Update.2-33 Removed previously blank page.2-41 Updated Dose Parameters in Table 2-9, Outage Workers due to Land Use Census Update.Sect. 2 Renumbered Section 2 pages from 2-33 on to reflect the addition of pages.5-19 Removed distances from titles of Shoreline Sediment locations for San Onofre State Beach (Southeast) | Throughout the document, change bars are marked in one of four ways as follows: | ||
Removed a previously deleted line 5-20 Deleted Kelp sample Laguna Beach (CONTROL)Added Kelp sample Salt Creek (CONTROL) 11 to 13 miles WNW to NW Deleted Ocean Sediment sample Unit 1 Outfall Removed distance and direction from title of Ocean Sediment location for Unit 1 Outfall Added Ocean Sediment sample SONGS Upcoast 0.9 miles WSW | A D | ||
2 and 3 5-23 thru 5-27 6-9 New maps reflecting changes to sample locations Changed the time frame for unplanned releases reporting in the annual report by replacing "on a quarterly basis" with "during the reporting period" per AR 011000482. | F R | ||
R R SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS | Addition Deletion Editorial/Format change Revision The following is a complete list of the changes: | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | PAGE CHANGE TOC Renumbered pages as necessary based on changes in the body of the ODCM. | ||
2 and 3 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 2001 with trace amounts of tritium). | 2-39 Format change for numbers 2-31 Updated CLF due to Land Use Census Update. | ||
The valves were repaired during the Unit 2 refueling outage in May 2002. This event is documented in AR 001200733. | 2-33 Removed previously blank page. | ||
Waste Gas System leakage in the Radwaste Building In May 2002, while venting the volume control tank through the waste gas system, equipment failure lead to a system leak into the radwaste building.Samples were collected in the vicinity of the leak for release evaluation. | 2-41 Updated Dose Parameters in Table 2-9, Outage Workers due to Land Use Census Update. | ||
The dose was included in the monthly dose data. The dose received by the public as a result of this event was bounded by the dose received from the site for the month. This event is documented in AR 020501046. | Sect. 2 Renumbered Section 2 pages from 2-33 on to reflect the addition of pages. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | 5-19 Removed distances from titles of Shoreline Sediment locations for San Onofre State Beach (Southeast) | ||
2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 -December 31, 2002 S.O.N.G.S. | Removed a previously deleted line 5-20 Deleted Kelp sample Laguna Beach (CONTROL) | ||
2 Monitor Inoperability Period Inoperability Cause Explanation 2RT-7870 04/17/00 -present -Inoperable process Design-deficiency causes process Condenser Air | Added Kelp sample Salt Creek (CONTROL) 11 to 13 miles WNW to NW Deleted Ocean Sediment sample Unit 1 Outfall Removed distance and direction from title of Ocean Sediment location for Unit 1 Outfall Added Ocean Sediment sample SONGS Upcoast 0.9 miles WSW REASON F | ||
This event is documented in ARs 000101252 and 000400960. | F R | ||
2RT-7817 05/20/02 --07/08/02 Monitor failure Investigation identified detector BPS/FFCPD with low flow was non-functional and was Discharge Monitor replaced. | F R | ||
The flow switch was found to be slightly degraded but still functional. | F R | ||
This event is documented in AR 020501134. | F D | ||
09/21/02 -10/26/02 Shorted circuitry Investigation identified the with corrosion detector had been shorted and the forming connector was corroded due to water intrusion into the detector. | A D | ||
An overhead floor plug was found to leak excessively and was repaired.This event is documented in AR 020901084. | R A | ||
2RT-7865 09/23/02 -11/21/02 Isokinetic flow Major inspection and repair-of the Plant Vent Stack probe inspection isokinetic flow probes. This event (Containment is documented in AR 011100588. | |||
Purge) Monitor ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 -December 31, 2002 S.O.N.G.S. | S.O.N.G.S. 2 and 3 5-23 thru 5-27 6-9 New maps reflecting changes to sample locations Changed the time frame for unplanned releases reporting in the annual report by replacing "on a quarterly basis" with "during the reporting period" per AR 011000482. | ||
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. | R R | ||
This event is documented in ARs 000101252 and 000400960. | 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, 2002 to December 31, 2002. | ||
3RT-7865 04/29/02 -07/02/02 Isokinetic flow Major inspection, repair and Plant Vent Stack probes calibration of the isokinetic flow (Containment probes. This event is documented Purge) Monitor in AR 020500049. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
3RT-7817 06/04/02 -current Failure due to low Monitor has had low sample flow BPS/FFCPD sample flow. problems since installation. | S.O.N.G.S. 2 and 3 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 2001 with trace amounts of tritium). | ||
The Discharge Monitor piping was replaced in 2000 with marginal improvement. | The valves were repaired during the Unit 2 refueling outage in May 2002. | ||
The long lengths of pipe and low motive force are the cause of this problem. Corrective actions currently in progress include a simplified piping design. This event is documented in ARs 010600960 and 020701020. | This event is documented in AR 001200733. | ||
S.O.N.G.S. | Waste Gas System leakage in the Radwaste Building In May 2002, while venting the volume control tank through the waste gas system, equipment failure lead to a system leak into the radwaste building. | ||
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. | Samples were collected in the vicinity of the leak for release evaluation. The dose was included in the monthly dose data. | ||
This event is documented in AR 010801138. | The dose received by the public as a result of this event was bounded by the dose received from the site for the month. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)S.O.N.G.S. | This event is documented in AR 020501046. | ||
2 and 3 SECTION L.S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | ||
2 and 3 CONCLUSIONS | S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 - December 31, 2002 S.O.N.G.S. 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. | |||
COMMON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)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), | Flow Monitor vacuum pump is Substitute flow value is running. | ||
* Ci 1.42E+1 3.OOE+1 c. Irradiated components, 3 (incl. excore detectors and m 1.93E+O heated junction thermocouple) | 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 000400960. | ||
* Ci 4.59E+1 3.0OE+1 m3 N/A d. Other (filters)Ci N/A N/A Note: Total curie content estimated. | 2RT-7817 05/20/02 --07/08/02 Monitor failure Investigation identified detector BPS/FFCPD with low flow was non-functional and was Discharge Monitor replaced. The flow switch was found to be slightly degraded but still functional. This event is documented in AR 020501134. | ||
(*) Material packaged in Type A or strong tight containers of various sizes.N/A No shipment made. I | 09/21/02 - | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)COMMON 2. Estimate of major nuclide composition (by type of waste)a. not applicable | 10/26/02 Shorted circuitry Investigation identified the with corrosion detector had been shorted and the forming connector was corroded due to water intrusion into the detector. An overhead floor plug was found to leak excessively and was repaired. | ||
This event is documented in AR 020901084. | |||
2RT-7865 09/23/02 - | |||
11/21/02 Isokinetic flow Major inspection and repair-of the Plant Vent Stack probe inspection isokinetic flow probes. | |||
This event (Containment is documented in AR 011100588. | |||
Purge) Monitor ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 - December 31, 2002 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 000400960. | |||
3RT-7865 04/29/02 - | |||
07/02/02 Isokinetic flow Major inspection, repair and Plant Vent Stack probes calibration of the isokinetic flow (Containment probes. This event is documented Purge) Monitor in AR 020500049. | |||
3RT-7817 06/04/02 - | |||
current Failure due to low Monitor has had low sample flow BPS/FFCPD sample flow. | |||
problems since installation. The Discharge Monitor piping was replaced in 2000 with marginal improvement. The long lengths of pipe and low motive force are the cause of this problem. Corrective actions currently in progress include a simplified piping design. This event is documented in ARs 010600960 and 020701020. | |||
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 (2002) | |||
S.O.N.G.S. 2 and 3 SECTION L. | |||
S.O.N.G.S. 2 and 3 CONCLUSIONS Gaseous | |||
: curies, tritium releases totaled 1.08E+2 curies of which noble gases were 6.35E+1 iodines were 1.74E-2 curies, particulates were 3.14E-4 curies, and was 4.42E+1 curies. | |||
The radiation doses from gaseous releases were: (a) gamma air dose: 9.18E-3 mrad at the site boundary, (b) beta air dose: 6.37E-3 mrad at the site boundary, (c) organ dose: 1.35E-2 mrem at the nearest receptor. | |||
Liquid releases totaled 1.49E+3 curies of which particulates and iodines were 1.66E-2 curies, tritium was 1.49E+3 curies, and noble gases were 2.95E-1 curies. | |||
The radiation doses from liquid releases were: (a) total body: 2.73E-3 mrem, (b) limiting organ: 4.06E-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 (2002) | |||
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 9.47E+1 compactable and non-compactable | |||
* Ci 1.42E+1 3.OOE+1 | |||
: c. Irradiated components, 3 | |||
(incl. excore detectors and m | |||
1.93E+O heated junction thermocouple) | |||
* Ci 4.59E+1 3.0OE+1 m3 N/A | |||
: d. Other (filters) | |||
Ci N/A N/A Note: Total curie content estimated. | |||
(*) Material packaged in Type A or strong tight containers of various sizes. | |||
N/A No shipment made. | |||
I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
COMMON | |||
: 2. | |||
Estimate of major nuclide composition (by type of waste) | |||
: a. not applicable N/A | |||
: b. americium-241 5.72E-2 antimony-124 2.85E-3 antimony-125 6.05E-1 carbon-14 1.17E+O ceri um-144 4.12E-2 cesium-134 6.36E-1 cesium-137 7.31E+O chromium-51 2.70E-1 cobalt-57 2.05E-2 cobalt-58 1.44E+O cobalt-60 3.07E+1 curium-242 8.89E-4 curium-243/244 | |||
__2.97E-2 iodine-129 | __2.97E-2 iodine-129 | ||
__4.92E-9 iron-55 | __4.92E-9 iron-55 3.13E+1 iron-59 1.66E-2 manganese-54 6.18E-1 nickel-59 1.05E-1 nickel-63 2.37E+1 niobium-94 3.28E-2 niobium-95 6.83E-2 plutonium-238 8.43E-2 plutonium-239/240 2.63E-2 plutonium-241 1.66E+O ruthenium-106 4.83E-6 silver-llOm 2.82E-2 strontium-90 1.67E-1 technetium-99 5.33E-3 tritium | ||
__1.27E-1 uranium-233 1.56E-4 uranium-235 3.19E-7 uranium-238 | |||
__1.74E-10 zirconium-95 5.05E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
COMMON | |||
: 2. | |||
Estimate of major nuclide composition (by type of waste) | |||
__1.74E-10 zirconium-95 | (Cont'd) | ||
: c. americium-241 l_% | |||
l 6.91E-7 antimony-124 1.66E-4 antimony-125 | |||
__2.66E-2 carbon-14 | __2.66E-2 carbon-14 | ||
__4.75E-3 cerium-144 | __4.75E-3 cerium-144 1.35E+O cesium-137 4.60E+O chromium-51 2.38E-5 cobalt-57 2.53E-3 cobalt-58 6.56E-2 cobal t-60 1.38E+l curium-242 6.21E-7 curium-243/244 2.53E-6 iron-55 6.30E+1 iron-59 | ||
-6.95E-5 manganese-54 7.56E-1 nickel-59 3.73E-4 nickel-63 2.38E+O niobium-95 1.41E-5 plutonium-238 2.59E-7 plutonium-239/240 1.66E-7 plutonium-241 3.12E-5 promethium-147 2.51E+O silver-llOm 5.84E-4 strontium-89 3.36E-6 strontium-90 4.56E+O tin-113 7.28E-4 tritium 6.67E-4 uranium-233 5.19E-7 uranium-235 7.99E-5 zinc-65 7.04E+O zirconium-95 1.23E-4 | |||
: d. not applicable N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
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 39* | |||
Hitman Trucking Company EnviroCare, UT | |||
1, 2, and 3)Number of Shipments Mode of Transportation Destination 39* Hitman Trucking Company EnviroCare, | _Truck/Trailer 1 | ||
The 39 shipments made from these facilities included waste from other generators. | KTC/TAG Evr~rU | ||
SCE's waste volume was a small fraction of the total waste volume of these shipments. | ____________________Flatbed Trailer Evr~rU SONGS maintains a contract with vendors (ATG/Duratek) that provide volume reduction services. | ||
B. IRRADIATED FUEL SHIPMENTS (Disposition) | These shipments were made from the ATG/Duratek processing facilities to EnviroCare. | ||
Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A D. CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 None. | The 39 shipments made from these facilities 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 D. | |||
CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 None. | |||
==REFERENCES:== | ==REFERENCES:== | ||
: 1. Unit 1 Technical Specifications, section D6.13.2. | |||
: 2. Units 2 and 3 License Controlled Specifications, section 5.0.103.2.2. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
COMMON COMMON 40 CFR 190 REQUIREMENTS Table 1 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 5.58E-1 | |||
: b. Percent ODCM Specification Limit 2.23E+O | |||
: 2. Limiting Organ | |||
: a. Organ Dose (Bone) mrem 2.50E-1 | |||
: b. Percent ODCM Specification Limit 1.OOE+O | |||
: 3. Thyroid | |||
: a. Thyroid Dose mrem 2.01E-2 | |||
: b. | |||
Percent ODCM Specification Limit 2.68E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 1.09E+2 curies of which noble gases were 6.35E+1 curies, iodines were 1.74E-2 curies, particulates were 3.16E-4 curies, and tritium was 4.56E+1 curies. | |||
Liquid releases from S.O.N.G.S. 1, 2 and 3 totaled 1.49E+3 curies of which particulates and iodines were 2.79E-2 curies, tritium was 1.49E+3 curies, and noble gases were 2.95E-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 83 radwaste shipments to Envirocare, UT and 4 shipments to Barnwell, SC. | |||
Total volume was 1.41E+3 cubic meters containing 2.53E+3 curies of radioactivity. | |||
Meteorological conditions during the year were typical for S.O.N.G.S. | |||
Meteorological dispersion was good 33% of the time, fair 43% of the time and poor 24% 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 (2002) | |||
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 dose due to noble reactor) to areas following values: | |||
air doses as calculated using the historical X/Q. | |||
The air gases released in gaseous effluents from S.O.N.G.S. (per at and beyond the site boundary shall be limited to the | |||
: 1. During any calendar quarter: | |||
: 2. During any calendar year: | |||
5 mrad for gamma radiation and | |||
* 10 mrad for beta radiation. | |||
5 10 mrad for gamma radiation and | |||
* 20 mrad for beta radiation. | |||
C. | |||
The dose to a Member of the Public from iodines, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values: | |||
: 1. During any calendar quarter: | |||
: 2. During any calendar year: | |||
I 7.5 mrem to any organ. | |||
* 15 mrem to any organ. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
COMMON APPENDIX A (Continued) | |||
LIQUID EFFLUENTS - APPLICABLE LIMITS A. | |||
Table 2A lists the total curies released, the diluted concentration, and percent of the applicable limit. The percent of applicable limit compares the diluted concentration of radioactive material released to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration is limited to 2.OOE-4 pCi/ml. | |||
B. | |||
Table 2D lists doses due to liquid releases. The dose commitment to a Member of the Public from radioactive materials in liquid effluents released from S.O.N.G.S. (per reactor) to unrestricted areas shall be limited to the following values: | |||
: 1. During any calendar quarter: | |||
: 2. During any calendar year: | |||
< 1.5 mrem to the total body and | |||
* 5 mrem to any organ. | |||
< 3 mrem to the total body and | |||
< 10 mrem to any organ. | |||
METEOROLOGY | |||
METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2002 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, 2002. | |||
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 (2002) | |||
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01123124-02033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILI EXTREMELY UNSTABLE (DT/DZ WIND DIR N | |||
NNE NE ENE E | |||
ESE SE SSE S | |||
SSW SW WSW W | |||
WNW NW NNW | |||
.22- | |||
.50 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 | |||
.51- | |||
.75 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 | |||
.76-1.0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 1.1-1.5 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 2 | |||
1 6 | |||
7 0 | |||
0 0 | |||
0 1.6-2.0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 3 | |||
2 17 19 11 1 | |||
0 0 | |||
2.1-3.0 0 | |||
0 0 | |||
0 0 | |||
0 1 | |||
3 10 15 19 43 82 20 0 | |||
1 L A | |||
< -1.9 3.1-5.0 0 | |||
0 0 | |||
0 0 | |||
0 2 | |||
0 14 5 | |||
18 21 57 51 1 | |||
0 | |||
°C/100 5.1-7.0 1 | |||
1 3 | |||
0 0 | |||
0 1 | |||
1 4 | |||
0 0 | |||
3 4 | |||
20 1 | |||
0 METERS) 7.1-10.0 1 | |||
0 2 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
5 0 | |||
0 10.1-13.0 0 | |||
0 0 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 | |||
- -A n | |||
T 13.1-18.0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 | |||
>1l8 TOAL 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 2 | |||
1 5 | |||
2 0 | |||
0 4 | |||
4 33 24 60 93 154 97 2 | |||
1 TOTALS 0 | |||
0 1 | |||
16 53 194 169 39 9 | |||
1 0 | |||
0 482 NUMBER OF VALID HOURS 482 NUMBER OF CALMS 0 | |||
NUMBER OF INVALID HOURS 0 | |||
TOTAL HOURS FOR THE PERIOD 2160 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -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 1 | |||
0 1 | |||
0 0 | |||
0 0 | |||
2 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 | |||
1 1 | |||
0 0 | |||
0 2 | |||
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 2 | |||
1 0 | |||
0 0 | |||
0 4 | |||
SSE 0 | |||
0 0 | |||
1 0 | |||
3 2 | |||
2 0 | |||
0 0 | |||
0 8 | |||
S 0 | |||
0 1 | |||
0 1 | |||
1 3 | |||
1 0 | |||
0 0 | |||
0 7 | |||
SSW 0 | |||
0 0 | |||
0 1 | |||
1 1 | |||
0 0 | |||
0 0 | |||
0 3 | |||
SW 0 | |||
0 0 | |||
2 2 | |||
1 1 | |||
0 0 | |||
0 0 | |||
0 6 | |||
WSW 0 | |||
0 0 | |||
1 2 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 4 | |||
W 0 | |||
0 0 | |||
2 3 | |||
4 0 | |||
1 0 | |||
0 0 | |||
0 10 WNW 0 | |||
0 0 | |||
0 1 | |||
4 2 | |||
0 1 | |||
0 0 | |||
0 8 | |||
NW 0 | |||
0 0 | |||
0 0 | |||
0 1 | |||
0 0 | |||
0 0 | |||
0 1 | |||
NNW 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
1 0 | |||
0 0 | |||
0 1 | |||
TOTALS 0 | |||
0 1 | |||
6 10 17 12 8 | |||
2 0 | |||
0 0 | |||
56 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 56 0 | |||
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0 | |||
2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01123124-02033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -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 0 | |||
2 1 | |||
0 0 | |||
0 0 | |||
0 3 | |||
NE 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
ENE 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 1 | |||
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 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
SSE 0 | |||
0 0 | |||
0 0 | |||
0 4 | |||
1 0 | |||
0 0 | |||
0 5 | |||
S 0 | |||
0 0 | |||
0 1 | |||
1 3 | |||
0 0 | |||
0 0 | |||
0 5 | |||
SSW 0 | |||
0 0 | |||
0 2 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 3 | |||
SW 0 | |||
0 0 | |||
3 1 | |||
1 3 | |||
1 1 | |||
0 0 | |||
0 10 WSW 0 | |||
0 0 | |||
1 0 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 2 | |||
W 0 | |||
0 0 | |||
1 0 | |||
1 1 | |||
0 0 | |||
0 0 | |||
0 3 | |||
WNW 0 | |||
0 0 | |||
2 2 | |||
3 4 | |||
0 0 | |||
0 0 | |||
0 11 NW 0 | |||
0 0 | |||
1 0 | |||
1 2 | |||
0 0 | |||
0 0 | |||
0 4 | |||
NNW 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
TOTALS 0 | |||
0 0 | |||
8 6 | |||
11 18 2 | |||
2 0 | |||
0 0 | |||
47 NUMBER OF VALID HOURS 47 NUMBER OF CALMS 0 | |||
NUMBER OF INVALID HOURS 0 | |||
TOTAL HOURS FOR THE PERIOD 2160 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -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 | |||
0 2 | |||
5 7 | |||
2 0 | |||
0 0 | |||
0 0 | |||
16 NNE 0 | |||
1 2 | |||
5 4 | |||
5 4 | |||
1 0 | |||
0 0 | |||
0 22 NE 0 | |||
0 0 | |||
1 0 | |||
2 1 | |||
2 1 | |||
0 0 | |||
0 7 | |||
ENE 0 | |||
0 0 | |||
1 0 | |||
0 0 | |||
2 1 | |||
0 0 | |||
0 4 | |||
E 0 | |||
0 1 | |||
1 0 | |||
4 2 | |||
0 0 | |||
0 0 | |||
0 8 | |||
ESE 0 | |||
0 0 | |||
1 4 | |||
9 5 | |||
1 0 | |||
0 0 | |||
0 20 SE 0 | |||
0 1 | |||
3 12 26 35 9 | |||
0 0 | |||
0 0 | |||
86 SSE 0 | |||
1 1 | |||
7 8 | |||
17 23 13 1 | |||
1 0 | |||
0 72 S | |||
0 0 | |||
1 6 | |||
5 4 | |||
8 4 | |||
6 0 | |||
0 0 | |||
34 SSW 0 | |||
1 1 | |||
6 2 | |||
6 3 | |||
2 1 | |||
2 0 | |||
0 24 SW 0 | |||
0 1 | |||
2 4 | |||
4 0 | |||
2 1 | |||
0 0 | |||
0 14 WSW 0 | |||
1 1 | |||
3 0 | |||
4 1 | |||
2 0 | |||
0 0 | |||
0 12 W | |||
0 1 | |||
2 4 | |||
7 7 | |||
6 5 | |||
0 0 | |||
0 0 | |||
32 WNW 0 | |||
1 2 | |||
0 3 | |||
16 11 10 1 | |||
0 0 | |||
0 44 NW 0 | |||
0 1 | |||
4 6 | |||
12 23 6 | |||
1 0 | |||
0 0 | |||
53 NNW 0 | |||
0 2 | |||
1 7 | |||
6 2 | |||
0 0 | |||
0 0 | |||
0 18 TOTALS 0 | |||
6 16 47 67 129 126 59 13 3 | |||
0 0 | |||
: 466, NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 466 0 | |||
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0 | |||
2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002) | |||
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01123124-02033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ s 1.5 WIND) | |||
DIR N | |||
NNE NE ENE E | |||
ESE SE SSE S | |||
SSW SW WSW W | |||
WNW NW NNW | |||
.22- | |||
.50 1 | |||
0 0 | |||
0 0 | |||
1 0 | |||
0 1 | |||
0 1 | |||
0 0 | |||
0 0 | |||
0 | |||
.51- | |||
.75 0 | |||
2 0 | |||
1 2 | |||
0 0 | |||
0 1 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 | |||
.7b-1.0 2 | |||
5 0 | |||
2 6 | |||
0 0 | |||
1 1 | |||
2 1 | |||
0 1 | |||
0 1 | |||
1 1.1-1.5 3 | |||
15 9 | |||
4 3 | |||
5 4 | |||
6 2 | |||
3 6 | |||
1 3 | |||
1 2 | |||
5 1.6b-2.0 6 | |||
14 4 | |||
4 4 | |||
2 4 | |||
1 1 | |||
1 0 | |||
0 3 | |||
3 1 | |||
6 Z.1-3.0 12 20 1 | |||
2 7 | |||
6 8 | |||
2 1 | |||
0 0 | |||
0 2 | |||
4 5 | |||
8 S.1-5.0 3 | |||
14 4 | |||
3 8 | |||
1 10 1 | |||
0 0 | |||
0 0 | |||
1 11 2 | |||
7 CC/100 METERS) 5.1-7.1-10.1-7.0 10.0 13.0 0 | |||
1 0 | |||
1 1 | |||
0 1 | |||
4 0 | |||
2 1 | |||
0 O | |||
0 0 | |||
O 0 | |||
0 O | |||
0 0 | |||
O 0 | |||
0 O | |||
0 0 | |||
O 0 | |||
0 O | |||
0 0 | |||
1 0 | |||
0 1 | |||
0 0 | |||
2 0 | |||
0 3 | |||
0 0 | |||
1 0 | |||
0 13.1-18.0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 | |||
>18 TOTAL 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 28 72 23 19 30 15 26 11 7 | |||
7 8 | |||
2 11 21 14 28 TOTALS 4 | |||
7 23 72 54 78 65 12 7 | |||
0 0 | |||
0 322 NUMBER OF VALID HOURS 322 NUMBER OF CALMS 0 | |||
NUMBER OF INVALID HOURS 0 | |||
TOTAL HOURS FOR THE | |||
Latest revision as of 10:07, 16 January 2025
| ML031250233 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 04/29/2003 |
| From: | San Diego Gas & Electric Co, Southern California Edison Co |
| To: | NRC/FSME |
| References | |
| -RFPFR | |
| Download: ML031250233 (102) | |
Text
SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2002 January - December
SOUTHERN CALIFORNIA EDISON An LDISO\\'IVTR\\ITIO.\\L"' Company 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%).
P 0 Bo\\ 128 San Clemente, CA 92674-0128
S.O.N.G Es. 1
TABLE OF CONTENTS SECTION A - INTRODUCTION.............
SECTION B - GASEOUS EFFLUENTS...........
SECTION C - LIQUID EFFLUENTS...........
SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE R SECTION E - RADWASTE SHIPMENTS..........
SECTION F - APPLICABLE LIMITS...........
SECTION G - ESTIMATION OF ERROR..........
SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS...
SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MAN E
1 2
8 PORT ADDENDUM.......
16
.............. 17
.............. 22
.............. 24 25 IAL
............ 29 YSTEMS.......... 30
.............. 31 U
SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT S SECTION K - MISCELLANEOUS.............
SECTION L - S.O.N.G.S. 1 CONCLUSIONS.......
33
-ii-
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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, 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 (2002)
S.O.N.G.S. 1 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 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 1C 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 (2002)
S.O.N.G.S. 1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error-. %
I~ ~
I A. Fission and activation gases
- 1. Total release Ci
<LLD
<LLD 3.0OE+1
- 2. Average release rate for period yCi/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 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 C. Particulates
- 1. Particulates with half-lives >8 days Ci
<LLD
<LLD 1.60E+1
- 2. Average release rate for period yCi/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
<LLD
<LLD 5.OOE+1 D. Tritium
- 1. Total release Ci 1.64E-1 7.05E-1 2.50E+1
- 2. Average release rate for period pCi/sec 2.11E-2 8.97E-2
- 3. Percent of applicable limit
% MPC 1.37E-4 5.83E-4
- 4.
Percent Effluent Concentration Limit
% ECL 2.74E-4 1.17E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 TABLE 1A (Continued)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Estimated Fourth Total Quarter Error, %
A. Fission and activation gases
- 1. Total release Ci
<LLD
<LLD 3.OOE+1
- 2. Average release rate for period yCi/sec O.OOE+O O.OOE+O
- 3. Percent of applicable limit
% MPC O.OOE+O O.OOE+O
- 1. Total iodine-131 Ci
<LLD
<LLD 1.90E+1
- 2. Average release rate for period pCi/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 (l)
- 1. Particulates with half-lives >8 days Ci
<LLD 1.89E-6 1.60E+1
- 2.
Average release rate for period yCi/sec O.OOE+O 2.37E-7
- 3. Percent of applicable limit
% MPC O.OOE+O 6.33E-7
- 4.
Percent Effluent Concentration Limit
% ECL O.OOE+O 1.70E-6
- 5.
Gross alpha activity
-Ci
<LLD
<LLD 5.OOE+1 D. Tritium
- 1. Total release Ci
<LLD 5.55E-1 2.50E+1
- 2.
Average release rate for period pCi/sec O.OOE+O 6.98E-2
- 3.
Percent of applicable limit
% MPC O.OOE+O 4.54E-4
- 4.
Percent Effluent Concentration Limit
% ECL O.OOE+O 9.08E-4 (1)
On 7/9/2002, plant vent stack particulate and iodine samples were not collected Tor 4 nrs and 44 minutes.
Prior and subsequent samples were <LLD. There were no dose consequences to the public as a result of this event which is documented in AR 020700464.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE l First Second Third Fourth Radionuclides Released Unit l Quarter I Quarter I Quarter l 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 2.34E-8 cesium-137 Ci
<LLD
<LLD
<LLD 1.80E-6 cobalt-58
- Ci
<LLD
<LLD
<LLD
<LLD cobalt-60 Ci
<LLD
<LLD
<LLD 6.30E-8 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 (2002)
S.O.N.G.S. 1 TABLE ID GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION
- 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. Iodines iodine-131 2.90E-13 iodine-133 2.80E-12 iodine-135 1.90E-10
- 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 cobalt-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
- 4. alpha 1.OOE-11
- 5. tritium 7.20E-8 NOTE:
Due to the permanent shutdown of longer conducted.
S.O.N.G.S. 1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY l
First l 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 6.69E-6 3.67E-5 O.OOE+O 3.61E-5
- 2. Percent Applicable Limit 8.92E-5 4.89E-4 O.OOE+O 4.81E-4 NOTE:
Calculations performed in accordance with the ODCM utilizing the historical X/Q.
TABLE 1F 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!(2002)
S.O.N.G.S. 1 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 (2002)
S.O.N.G.S. 1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Unit Quarter Second Quarter Estimated Total Error. %
A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 1.OOE-5 3.52E-3 1.90E+1
- 2. Average diluted concentration during period yCi/ml 6.36E-12 2.09E-9
- 3. Percent of applicable limit
% MPC 3.10E-5 1.35E-2
- 1. Total release Ci 1.81E-3 1.15E+O 1.90E+1
- 2. Average diluted concentration during period yCi/ml 1.15E-9 6.85E-7
- 3. Percent of applicable limit
% MPC 3.82E-5 2.28E-2
- 4. Percent Effluent Concentration Limit
% ECL 1.15E-4 6.85E-2 C. Dissolved and entrained gases
- 1. Total release Ci
<LLD
<LLD 1.90E+1
- 2. Average diluted concentration during period pCi/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 1.49E-5 5.0OE+1 E. Volume of waste released (batch &
continuous, prior to dilution) liters 1.33E+6 9.OOE+5 5.OOE+O F. Volume of dilution water used during period liters 1.58E+9 1.68E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 TABLE 2A (Continued)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, %
A. Fission and activation products
- 1. Total release (not including-
- tritium,-gases, alpha)
Ci 7.79E-3 1.78E-5 1.90E+1
- 2. Average diluted concentration during period pCi/ml 5.23E-9 1.07E-11
- 3. Percent of applicable'limit
% MPC 2.35E-2 5.36E-5
- 1. Total release Ci 4.62E+0 5.83E-4 1.90E+1
- 2. Average diluted concentration during period yuCi/ml 3.10E-6 3.51E-10
- 3. Percent of applicable limit
% MPC 1.03E-1 1.17E-5
-4. Percent Effluent Concentration Limit % ECL 3.10E-1 3.51E-5 C. Dissolved and entrained gases
- 1. Total release Ci
<LLD
<LLD 1.90E+1
- 2. Average diluted concentration during period yCi/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 E. Volume of waste released (batcl continuous, prior to dilution)
F. Volume of dilution water used i period ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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 9.26E-6 6.74E-6 1.95E-5 1.78E-5 chromium-51 Ci
<LLD
<LLD
<LLD
<LLD cobalt-58 Ci
<LLD
<LLD
<LLD
<LLD cobalt-60 Ci 7.86E-7
<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.OOE-5 6.74E-6 1.95E-5 1.78E-5
- 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 (2002)
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
<LLD
<LLD N/A cerium-141 Ci N/A
<LLD
<LLD N/A cerium-144 Ci N/A
<LLD
<LLD N/A cesium-134 Ci N/A 9.-93E-5 1.32E-4 N/A cesium-137 Ci N/A 1.79E-3 2.58E-3 N/A chromium-51 Ci N/A
<LLD
<LLD N/A cobalt-57 Ci N/A
<LLD 1.69E-5 N/A cobalt-58 Ci N/A
<LLD
<LLD N/A cobalt-60 Ci N/A 1.54E-3 2.01E-3 N/A iodine-131 Ci N/A
<LLD
<LLD N/A iron-55 Ci N/A
<LLD 2.84E-3 N/A iron-59 Ci N/A
<LLD
<LLD N/A lanthanum-140 Ci N/A
<LLD
<LLD N/A manganese-54 Ci N/A
<LLD
<LLD N/A molybdenum-99 Ci N/A
<LLD
<LLD N/A niobium-95 Ci N/A
<LLD
<LLD N/A strontium-89 Ci N/A 7.21E-5 1.67E-4 N/A strontium-90 Ci N/A 1.55E-5 2.38E-5 N/A technetium-99m Ci N/A
<LLD
<LLD N/A zinc-65 Ci N/A
<LLD
<LLD N/A zirconium-95 Ci N/A
<LLD
<LLD N/A Total for period Ci N/A 3.52E-3 7.77E-3 N/A
- 2. Dissolved and entrained -gases xenon-133 Ci N/A
<LLD
<LLD N/A xenon-135 Ci N/A
<LLD
<LLD N/A Total for period Ci N/A
<LLD
<LLD N/A N/A No releases conducted LLD Lower Limit of Detection; see Table 2C.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides lLLD (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 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 (2002)
S.O.N.G.S. 1 TABLE 2C (Continued)
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides l
LLD (MCi/cc)
- 1. Fission and activation products barium-140 3.30E-7 cerium-141 5.30E-8 cerium-144 2.30E-7 chromium 4.20E-7 cobalt-57 2.90E-8
- cobalt-58 8.70E-8 iodine-131 6.OOE-8 iron-55 1.OOE-6
-iron-59 2.OOE-7 lanthanum-140 2.40E-7 X
manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 technetium-99m 3.60E-8 zinc-65 2.20E-7 zirconium-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 (2002)
S.O.N.G.S. 1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First l Second Third Fourth
_ Unit Quarter J Quarter Quarter Quarter A.
- 1. Total body dose mrem 1.03E-4 1.44E-2 5.38E-2 1.27E-4
- 2. Percent Applicable Limit 6.85E-3 9.62E-1 3.59E+0 8.46E-3 B.
- 1. Limiting organ dose mrem 1.52E-4 3.32E-2 2.21E-1 1.94E-4
- 2. Percent Applicable Limit 3.05E-3
-6.63E-1 4.41E+O 3.88E-3
- 3. Limiting organ for period Liver GI-LLI Bone Li ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE
SUMMARY
12 month period
- 1. Number of batch releases:
6 releases
- 2. Total time period for batch releases:
9229 minutes
- 3. Maximum time period for a batch release:
3008 minutes
- 4. Average time period for a batch release:
1538 minutes
- 5. Minimum time period for a batch release:
682 minutes
- 6. Average saltwater flow during batch releases:
6733 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 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 1.10E+3 compactable and non-compactable (incl. demolition rubble)
- Ci 9.54E+2 3.OOE+1
- c.
Irradiated components (Excore m3 2.66E+O detectors and insulation)
- Ci 2.43E+O 3.OOE+1
- d. Other: (High pressure garnet) #
m3 3.13E+O Ci 1.18E+3 3.OOE+1 NOTE: Total curie content estimated.
(*) Material packaged in Type A or strong tight containers of various sizes.
(#)
Material packaged in High Integrity Containers and shipped in Type B Cask.
N/A No shipment made.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1
- 2. Estimate of major nuclide composition (by type of waste)
- a. not applicable N/A
- b. americium-241 5.28E-2 carbon-14 1.02E-1 cerium-144 3.20E-2 cesium-134 9.81E-3 cesium-137 1.82E-1 cobalt-58 1.89E-3 cobalt-60 3.63E+1 curium-242 1.49E-5 curium-243/244 2.36E-2 iodine-129 2.21E-5 iron-55 2.76E+1 manganese-54 3.33E-3 nickel-59 5.61E-1 nickel-63 3.30E+1 niobium-94 8.11E-4 niobium-95 1.13E-4 plutonium-238 7.95E-2 plutonium-239/240 2.95E-2 plutonium-241 1.93E+O silver-llOm 4.27E-6 strontium-90 7.10E-2 technetium-99 3.41E-4 tritium 3.61E-2 uranium-233 7.89E-8 zirconium-95 1.32E-4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1
- 2. Estimate of major nuclide composition (by type of waste)
(Cont'd)
- c. americium-241 8.58E-6 carbon-14 2.53E-2 cerium-144 2.82E-6 cesium-134 4.22E-4 cesium-137 2.79E-3 cobalt-60 6.56E+1 curium-242 4.60E-8 curium-243/244 2.92E-6 iron-55 1.61E+1 manganese-54 6.48E-3 nickel-59 1.40E-1 nickel-63 1.81E+1 niobium-94 5.34E-4 plutonium-238 1.51E-5 plutonium-239/240 5.55E-6 plutonium-241 3.48E-4 strontium-90 3.34E-5 technetium-99 1.35E-4 tritium 2.89E-5 uranium-233 3.40E-9 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1
- 2. Estimate of major nuclide composition (by type of waste)
(Cont'd)
- d. americium-241 3.20E-8 carbon-14 4.30E-4 cerium-144 3.41E-8 cesium-137 5.95E-8 cobalt-58 9.56E-8 cobalt-60 4.46E-1 curium-242 1.99E-10 curium-243/244 1.86E-8 iron-55 2.48E-1 manganese-54 5.34E-5 nickel-59 2.19E-3 nickel-63 3.04E-1 niobium-94 6.57E-6 plutonium-238 5.31E-8 plutonium-239/240 1.44E-8 plutonium-241 9.90E-7 strontium-90 1.03E-7 technetium-99 1.40E-6 tritium 4.95E-9 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 21 R&R Trucking Company EnviroCare, UT
_____Truck/Trailer 22 MHFLogistical Solutions EnviroCare, UT Rail 2
KTC/TAG Barnwell, SC Flatbed Trailer BrwlS 2*
R&R Trucking Co.
TN RAM Type B Cask Barnwell, SC These shipments were done in a NRC Type B shipping cask.
IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination None No shipments were made N/A B.
C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 qprTTnM P ADDI TrARI P I TMTTRZ I
I
I I.
I -
Gaseous Effluents - ADDlicable 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 0
MPCelf
=
(Rel Rate) (XIO) (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, pCi/sec.
=
1.30E-5 sec/m3; the annual average atmospheric dispersion defined in the Unit 1 ODCM.
1
=
n F
1=1 MPC i
=
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.
=
total number of radionuclides identified
=
Maximum Permissible Concentration (MPC) of the ijh radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.
=
(Rel Rate) (X/O) (100)
ECLeff where:
Fj n
- MPC,
% ECL where:
Rel Rate X/Q 0
ECLeff
=
total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, yCi/sec.
=
1.30E-5 sec/m3; the annual average atmospheric dispersion defined in the Unit 1 ODCM.
1 n
Fi o1l ECL 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, CT.
where:
Fi n
- ECL,
=
total number of radionuclides identified
=
Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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, ACi/ml.
1 o
MPCeff
=
E F,
1-l 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, Cr.
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 2.
8 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, itCi/ml.
1
=
n F
EL1 i=1 ECL 0
ECLef where:
F.
n ECLd
=
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
=
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 (2002)
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 a I,2
+ G2 +
G3 +...
G where:
G, =
Error associated with each component.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 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; 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 I-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.
' ODCM Figures 2-1 & 2-2.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 TABLE 1 Dose * (millirems)
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS
- 1)
- 2)
- 3)
- 4) 5)
Whole Body 1.03E-4 1.44E-2 5.38E-2 1.27E-4 6.84E-2
- 6)
- 7)
- 8)
- 9) 10)
Organ 1.52E-4 3.32E-2 2.21E-1 1.94E-4 2.33E-1 AIRBORNE EFFLUENTS
- 11)
- 12)
- 13)
- 14) 15)
Tritium, Iodines, and Particulates 2.17E-4 6.06E-4 O.OOE+O 7.42E-4 1.57E-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 1.37E-1 1.23E-1 7.60E-2 1.31E-1 4.67E-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 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.
e ODCM.
e ODCM.
e ODCM.
e ODCM.
2 ODCM.
6.
7.
8.
9.
10.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
This value was calculated using the methodology of the ODCM; the bone received the maximum dose primarily by the saltwater fish pathway.
This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
This value was calculated using the methodology of the ODCM; the bone 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.
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.
calculated using the assumptions of USNRC Regulatory Guide 1.109.
- 13.
There was no activity detected during the release period, therefore the reported organ O.OOE+O mrem.
This was 14.
15.
16.
17.
18.
19.
20.
21.
22.
23.
The maximum organ dose was to a child's calculated using the assumptions of USNRC The maximum organ dose was to a child's calculated using the assumptions of USNRC There was no activity detected during the gamma radiation was O.OOE+O mrad.
There was no activity detected during the gamma radiation was O.OOE+O mrad.
There was no activity detected during the gamma radiation was O.OOE+O mrad.
There was no activity detected during the gamma radiation was O.OOE+O mrad.
There was no activity detected during the gamma radiation was O.OOE+O mrad.
There was no activity detected during the beta radiation was O.OOE+O mrad.
There was no activity detected during the beta radiation was O.OOE+O mrad.
There was no activity detected during the beta radiation was O.OOE+O mrad.
liver and was located in the NW sector.
liver and was located in the NW sector.
release period, therefore release release
- period, period, therefore therefore therefore therefore therefore release period, the the the the the the the the reported reported reported reported reported reported reported reported air air air air air air air air This dose This This dose dose dose dose dose dose dose dose was was was was for for for for for for for for release release release release
- period, period, period, therefore period, therefore
- 24.
There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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 W 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 W 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 6.85E-3 9.62E-1 3.59E+O 8.46E-3 2.28E+O Organ 3.05E-3 6.63E-1 4.41E+O 3.88E-3 2.33E+O AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 2.89E-3 8.08E-3 O.OOE+O 9.90E-3 1.04E-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 (2002)
S.O.N.G.S. 1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 28, 2002, Revision 19 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published.
Incorporated into this revision were:
- 1.
A change to the requirement for reporting unplanned releases on a quarterly basis in the annual report,
- 2.
Updates related to the recent Land Use Census, and
- 3.
Changes to the Kelp and Shoreline Sediment environmental sample locations.
Item 1 is being changed in response to AR 011000482 to reflect the more generic language of NUREG 0472. An Effluent/ODCM Screen has been provided for item 1. Item 3 changes were made per email from Environmental Protection Group to Effluent Engineering dated 2/1/02.
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 10CFR20, 40CFR190, 10CFR50.36a, 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 2-21 Updated CLF due to Land Use Census Update.
R 2-31 Updated Dose Parameters in Table 2-11, Outage Workers due to Land Use Census R
Update.
5-22 Removed distances from titles of Shoreline Sediment locations for San Onofre State R
Beach (Southeast)
Changed dashes to the word "to" in the distance and directions for Local Crops -
F Oceanside (CONTROL).
5-23 Deleted Kelp sample Laguna Beach (CONTROL)
D Added Kelp sample Salt Creek (CONTROL) 11 to 13 miles WNW to NW A
Deleted Ocean Sediment sample Unit 1 Outfall D
Added Ocean Sediment sample SONGS Upcoast 0.9 miles WSW A
5-26 thru New maps reflecting changes to sample locations R
5-30 6-9 Changed the time frame for unplanned releases reporting in the annual report by R
replacing "on a quarterly basis" with "during the reporting period" per AR 011000482.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 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, 2002 to December 31, 2002.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 SECTION K. MISCELLANEOUS Yard Drain Sump Overflow The Unit 1 Yard Drain sump overflowed to the PMF Catch Basin due to heavy rainfall three times in 2002.
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 Estimated Start Stop Duration Activity Release Whole Body Organ Dose Date/Time Date/Time (min)
(pCi/ml)
(Curies)
Dose (mrem)
(mrem) 11/29/02 @ 2047 11/29/02 @ 2053 6
<MDA 0.OOE+o o.OOE+O o.OOE+O 12/16/02 @ 1712 12/16/02 @ 1745 33
<MDA O.OOE+O O.OOE+O O.OOE+O 12/20/02 @ 0502 12/20/02 @ 0640 98
<MDA O.OOE+0 O.OOE+0 0.00E+O Airborne Particulate Release During Large Component Removal In October 2002, penetrations were cut into the Containment sphere to allow large component removal (LCR) as a continuation of the decommissioning process.
The Unit 1 containment sphere was breached on 10/7/2002 with the removal of the opening above the reactor vessel. The final sphere opening cap was installed 12/10/2002.
Continuous air sampling was performed at each of the roof openings.
The sample analyses indicated trace amounts of Cs-137 and occasionally Co-60 and Cs-134.
The resultant curies and dose are included in the Unit 1 release data (Section B and H) of this report.
There were minimal dose consequences to members of the public as a result of this event that is documented in AR 021100412.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 - December 31, 2002 S.O.N.G.S. 1 Monitor Inoperability Period Inoperability Cause Explanation R-2100 04/24/02 - 06/22/02 Corrosion in Corrosion on the Local Processing Reheater Pit Sump electronics and Unit (LPU) caused monitor to fail.
Monitor detector
- The LPU and detector were replaced.
Upon returning to service, the monitor experienced frequent alarms. This event is documented in ARs 020401433 and 020501438.
09/25/02 - 10/29/02 Low sample flow Investigation of flow problems identified debris in canister which was blocking flow. Thorough cleaning of detector restored normal sample flow. This event is documented in AR 020901269.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 1 SECTION L.
S.O.N.G.S. 1 CONCLUSIONS Gaseous releases totaled 1.42E+O curies'of which noble gases were O.OOE+O curies, iodines were O.OOE+O curies, particulates were 1.89E-6 curies, and tritium was 1.42E+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: 1.57E-3 mrem at the nearest receptor.
Liquid releases totaled 5.79E+O curies of which particulates and iodines were 1.13E-2 curies, tritium was 5.78E+O curies, and noble gases were O.OOE+O curies.
The radiation doses from liquid releases were: (a) total body: 6.84E-2 mrem, (b) limiting organ: 2.33E-1 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. 2 and 3
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 SECTION L
- 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 34 35 45 ADDENDUM.......
53 54 57 59 60
............ 64 MS.......... 65
............ 66
............ 69 lANUAL
- CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTE
- MISCELLANEOUS...............
S.O.N.G.S. 2 and 3 CONCLUSIONS......
-iii-
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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 (2002)
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 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 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 IC.
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 (2002)
S.O.N.G.S. 2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error, e A. Fission and activation gases
- 1. Total release Ci 8.23E+O 3.32E+1 3.OOE+1
- 2. Average release rate for period yCi/sec 1.06E+O 4.22E+O
- 3. Percent of applicable limit
% MPC 2.57E-3 1.11E-2
- 4. Percent Effluent Concentration Limit
% ECL 4.97E-3 2.32E-2 B. lodines
- 1. Total iodine-131 Ci 2.03E-5 1.73E-2 1.90E+1
- 2. Average release rate for period pCi/sec 2.61E-6 2.20E-3
- 3. Percent of applicable limit
% MPC 1.25E-5 1.06E-2
- 4. Percent Effluent Concentration Limit
% ECL 6.27E-6 5.28E-3 C. Particulates
- 1. Particulates with half-lives >8 days Ci 8.10E-5 1.17E-4 1.60E+1
- 2. Average release rate for period AtCi/sec 1.04E-5 1.48E-5
- 3. Percent of applicable limit
% MPC 9.75E-6 6.76E-6
- 4. Percent Effluent Concentration Limit
% ECL 2.43E-5 1.57E-5
- 5. Gross alpha activity Ci 5.58E-6
<LLD 5.OOE+1 D. Tritium
- 1. Total release Ci 1.26E+1 1.51E+1 2.50E+1
- 2. Average release rate for period uCi/sec 1.62E+O 1.92E+O
- 3. Percent of applicable limit
% MPC 3.89E-3 4.61E-3
- 4. Percent Effluent Concentration Limit
% ECL 7.78E-3 9.22E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 1A (Continued)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Estimated Total Error, %
A. Fission and activation gases
- 1. Total release Ci 1.33E+1 8.81E+O 3.00E+1
- 2. Average release rate for period ptCi/sec 1.67E+O 1.11E+O
- 3. Percent of applicable limit
% MPC 1.10E-2 4.40E-3
- 4. Percent Effluent Concentration Limit
% ECL 3.92E-2 -1.29E-2 B. Iodines
- 1. Total iodine-131 Ci 1.70E-5 1.27E-5 1.90E+1
- 2. Average release rate for period yCi/sec 2.14E-6 1.60E-6 3: Percent of applicable limit l% MPC 1.03E-5 7.67E-6
- 4. Percent Effluent Concentration Limit
% ECL 5.13E-6 3.83E-6 C. Particulates
- 1. Particulates with half-lives >8 days Ci 5.16E-5 6.42E-5 1.60E+1
- 2. Average release rate for period pCi/sec 6.49E-6 8.07E-6
- 3. Percent of applicable limit
% MPC 3.89E-6 7.31E-6
- 4. Percent Effluent Concentration Limit
% ECL 9.35E-6 1.82E-5
- 5. Gross alpha activity Ci
<LLD
<LLD 5.0OE+1 D. Tritium
- 1. Total release Ci 1.08E+1 5.78E+O 2.50E+1
- 2. Average release rate for period iCi/sec 1.36E+O 7.27E-1
- 3. Percent of applicable limit
% MPC 3.26E-3 1.75E-3
- 4. Percent Effluent Concentration Limit
% ECL 6.52E-3 3.49E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE 1 First Second F Third Fourth Radionuclides Released Unit Quarter Quarter I Quarter Quarter
- 1. Fission and activation gases argon-41 Ci 6.58E-1 3.16E+O 6.35E+O 2.01E+O krypton-85 Ci
<LLD
<LLD
<LLD
<LLD krypton-85m Ci
<LLD 2.54E-2
<LLD
<LLD krypton-87 Ci
<LLD
<1.22E-3 LLD
<LLD krypton-88 Ci
<LLD 3.46E-3
<LLD
<LLD xenon-133 Ci 6.86E+O 2.82E+1 6.19E+O 6.50E+O xenon-133m Ci
<LLD 4.95E-1
<LLD
<LLD xenon-135 Ci
<LLD 3.79E-1
<LLD
<LLD xenon-135m Ci
<LLD
<LLD
<LLD
<LLD xenon-138 Ci
<LLD
<LLD
<LLD
<LLD Total for period Ci 7.52E+O 3.23E+1 1.25E+1 8.52E+O
- 2. Iodines iodine-131 Ci 2.03E-5 1.73E-2 1.70E-5 1.27E-5 iodine-132 Ci
<LLD 1.08E-2
<LLD 1.16E-7 iodine-133 Ci 3.03E-5 6.42E-4 5.84E-6 1.87E-5 iodine-135 Ci
<LLD
<LLD
<LLD 1.36E-6 Total for period Ci 5.05E-5 2.87E-2 2.29E-5 I 3.28E-5 LLD Lower Limit of Detection; see Table 1D.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 1C (Continued)
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I
First Second Third Fourth Radionuclides Released Unit
'Quarter I Quarter Quarter Quarter
- 3. Particulates barium-140 Ci
<LLD
<LLD
<LLD
<LLD bromine-82 Ci 2.70E-5 9.70E-5 9.39E-5 4.73E-5 cerium-141 Ci
<LLD
<LLD
<LLD
<LLD cerium-144 Ci
<LLD
<LLD
<LLD
<LLD cesium-134 Ci 8.40E-8 4.61E-8
<LLD
<LLD cesium-137 Ci 7.82E-5 3.49E-5 2.58E-5
-5.93E-5 cobalt-58 Ci 2.67E-6 8.17E-5 2.58E-5 4.86E-6 cobalt-60 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 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.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 1C (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 7.10E-1 7.56E-1 6.21E-1 2.99E-1 krypton-85m Ci
<LLD
<LLD
<LLD
<LLD krypton-87 Ci
<LLD
<LLD
<LLD
<LLD krypton-88 Ci
<LLD
<LLD
<LLD
<LLD xenon-131m Ci
<LLD 3.25E-2
<LLD
<LLD xenon-133 Ci 1.69E-3 1.09E-1 1.02E-1
<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 7.11E-1 8.98E-1 7.23E-1 2.99E-1 LLD Lower Limit of Detection; see Table 1D.
Iodines and particulates are not analyzed prior to release via batch mode.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (yCi/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-133m 4.10E-7 xenon-135 5.30E-8 xenon-135m 2.OOE-6 xenon-138 3.50E-6
- 2. Iodines iodine-132 6.OOE-10 iodine-135 1.70E-10
- 3. Particulates bar um-140 2.70E-11 cerium-141 3.40E-12 cerium-144 1.40E-11 cesium-134 9.20E-12 cobalt-60 1.30E-11 iron-59 2.OOE-11 lanthanum-140 2.20E-11 manganese-54 8.20E-12 molybdenum-99 2.10E-12 strontium-89 1.OOE-13 strontium-90 1.OOE-14 zinc-65 2.20E-11
- 4. alpha 1.OOE-11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE iD (Continued)
GASEOUS EFFLUENTS-LOWER LIMIT BATCH MODE OF DETECTION Radionuclides lLLD (yCi/cc)
- 1. Fission and activation gases krypton-85m 2.50E-6 krypton-87 1.20E-5 krypton-88 8.90E-6 xenon-131m 1.70E-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 (2002)
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 1.30E-3 6.14E-3 9.35E-3 3.18E-3
- 2. Percent Applicable Limit 1.30E-2 6.14E-2 9.35E-2 3.18E-2
- 3. Beta Air Dose mrad 1.64E-3 6.60E-3 4.43E-3 2.06E-3
- 4.
Percent Applicable Limit 8.18E-3 3.30E-2 2.21E-2 1.03E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)
- 1. Organ Dose mrem 7.85E-4 1.46E-2 6.21E-4 4.59E-4
- 2. Percent Applicable Limit I 5.24E-3 9.74E-2 4.14E-3 3.06E-3 NOTE:
Calculations performed in accordance with the ODCM utilizing the historical X/Q.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE
SUMMARY
12 month period
- 1. Number of batch releases:
10 releases
- 2. Total time period for batch releases:
4340 minutes
- 3. Maximum time period for a batch release:
582 minutes
- 4. Average time period for a batch release:
434 minutes
- 5. Minimum time period for a batch release:
145 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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 (2002)
S.O.N.G.S. 2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES First Unit Quarter Second Quarter Estimated Total Error, %
A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 1.03E-3 5.81E-3 1.90E+1
- 2. Average diluted concentration during period pCi/ml 1.37E-12 9.15E-12
- 3. Percent of applicable limit
% MPC 2.62E-6 2.10E-5
- 1. Total release Ci 4.26E+1 6.54E+2 1.90E+1
- 2. Average diluted concentration during period uCi/ml 5.70E-8 1.03E-6
- 3. Percent of applicable limit
% MPC 1.90E-3 3.44E-2
- 4. Percent Effluent Concentration Limit % ECL 5.70E-3 1.03E-1 C. Dissolved and entrained gases
- 1. Total release Ci
<LLD 2.40E-1 1.90E+1
- 2. Average diluted concentration during period yCi/ml O.OOE+O 3.78E-10
- 3. Percent of applicable limit
% MPC O.OOE+O 1.89E-4
- 4. Percent Effluent Concentration Limit % ECL O.OOE+O 1.89E-4 D. Gross alpha radioactivity
- 1. Total release Ci
<LLD
<LLD 5.0OE+1 E. Volume of waste released (batch &
continuous, prior to dilution) liters 1.12E+8 9.03E+7 5.OOE+O F. Volume of dilution water used during period liters 7.47E+11 6.34E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 2A (Continued)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Third
-Fourth Unit Quarter Quarter Estimated Total Error, %
A. Fission and activation products
- 1. Total release (not including-tritium, gases, alpha)
Ci 3.06E-3 6.69E-3 1.90E+1
- 2. Average diluted concentration during period A
Ci/ml 4.12E-12 8.71E-12
- 3. Percent of applicable limit
% MPC 7.21E-6 2.07E-5
- 1. -Total release Ci 1.16E+2 6.76E+2 1.90E+1
- 2. Average diluted concentration during period yCi/ml 1.56E-7 8.80E-7
- 3. -Percent of applicable limit
% MPC 5.20E-3 2.93E-2
- 4. Percent Effluent Concentration Limit % ECL 1.56E-2 8.80E-2 C. Dissolved and entrained gases 1.- Total release Ci 6.82E-3 4.81E-2 1.90E+1
- 2. Average diluted concentration during period MCi/ml 9.19E-12 6.25E-11
- 3. -Percent of applicable limit
% MPC 4.59E-6 3.13E-5
- 4. Percent Effluent Concentration Limit % ECL 4.59E-6 3.13E-5 D. Gross alpha radioactivity
- 1. Total release Ci 2.15E-5
<LLD 5.OOE+1 E. Volume of waste released (batch &
continuous, prior to dilution) liters 1.17E+8 1.06E+8 5.OOE+O F. Volume of dilution water used during period liters 7.43E+11 7.68E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE I
First Second Third Fourth Radionuclides Released l Unit l Quarter l Quarter l Quarter l 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
<LLD
<LLD
<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
<LLD
<LLD
<LLD
<LLD
- 2. Dissolved and entrained gases xenon-133 Ci
<LLD
<LD
<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 (2002)
S.O.N.G.S. 2 and 3 TABLE 2B (Continued)
LIQUID EFFLUENTS BATCH MODE l First l Second 1 Third Fourth Radionuclides Released Unit l Quarter Quarter l Quarter Quarter
- 1. Fission and activation products antimony-125 Ci 3.14E-4 1.94E-3 1.01E-3 3.13E-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
<LLD 1.32E-4 7.39E-5 2.98E-4 cesium-137 Ci 2.41E-5 5.66E-4 4.21E-4 1.25E-3 chromium-51 Ci
<LLD 3.35E-4 3.12E-4 2.13E-5 cobalt-58 Ci 3.22E-4 2.24E-3 5.64E-4 8.53E-4 cobalt-60 Ci 2.50E-4 3.47E-4 1.20E-4 4.29E-4 iodine-131 Ci
<LLD 8.73E-6
<LLD
<LLD iron-55 Ci
<LLD
<LLD 3.44E-4
<LLD iron-59 Ci
<LLD
<LLD 2.55E-5
<LLD lanthanum-140 Ci
<LLD
<LLD
<LLD
<LLD manganese-54 Ci 2.38E-5 3.63E-5 2.90E-5 8.43E-5 molybdenum-99 Ci
<LLD
<LLD
<LLD
<LLD niobium-95 Ci
<LLD 4.07E-5 8.27E-5 3.96E-4 niobium-97 Ci
<LLD 9.33E-6
<LLD
<LLD silver-110m Ci 9.30E-5 1.17E-4 2.68E-5
<LLD strontium-89 Ci
<LLD
<LLD
<LLD
<LLD strontium-90 Ci
<LLD
<LLD
<LLD
<LLD strontium-92 Ci
<LLD 2.10E-6 2.06E-6
<LLD technetium-99m Ci
<LLD
<LLD
<LLD
<LLD tin-113 Ci
<LLD
<LLD 4.27E-6
<LLD tungsten-187 Ci
<LLD 8.59E-6
<LLD
<LLD zinc-65 Ci
<LLD
<LLD
<LLD
<LLD zirconium-95 Ci
<LLD 1.98E-5 4.57E-5 2.26E-4 Total for period Ci 1.03E-3 5.81E-3 3.06E-3 6.69E-3
- 2. Dissolved and entrained gases krypton-85 Ci
<LLD 5.82E-2 5.89E-3 2.36E-2 (xenon-131m Ci
<LLD-7.03E-3
<LLD 1.01E-3 xenon-133 Ci
<LLD 1.74E-1 9.37E-4 2.34E-2 xenon-133m Ci
<LLD 5.02E-4
<LLD
<LLD xenon-135 Ci
<LLD
<LLD
<LLD 1.11E-5 Total for period Ci
<LLD 2.40E-1 6.82E-3 4.81E-2 LLD Lower Limit of Detection; see Table 2C.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)'
S.O.N.G.S. 2 and 3 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides lLLD (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 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-go 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 (2002)
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 cesium-134 9.90E-8 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 molybdenum-99 3.50E-8 niobium-95 8.50E-8 niobium-97 2.OOE-7 silver-110m 1.30E-7 strontium-89 5.OOE-8 strontium-90 1.OOE-8 strontium-92
-7.80E-5 technetium-99m 3.60E-8 tin-113 7.50E-8 tungsten-187 4.90E-7 zinc-65 2.20E-7 zirconium-95 1.50E-7
- 2. Dissolved and entrained gases krypton-85 4.20E-5 xenon-131m 4.OOE-6 xenon-133 3.10E-7 xenon-133m 9.20E-7 xenon-135 1.20E-7
- 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOL LIQUI1 INDARY First l Second I Third 1 Fourth Unit Quarter Quarter Quarter Quarter A.
- 1. Total body dose mrem 8.16E-5 1.16E-3 2.56E-4 1.23E-3
- 2. Percent Applicable Limit I
2.72E-3 3.87E-2 8.54E-3 4.11E-2 B.
- 1. Limiting organ dose mrem 4.47E-4 1.74E-3 5.14E-4 1.36E-3
- 2. Percent Applicable Limit 4.47E-3 1.74E-2 5.14E-3 1.36E-2
- 3. Limiting organ for period GI-LLI GI-LLI GI-LLI GI-LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE
SUMMARY
12 month period
- 1. Number of batch releases:
170 releases
- 2. Total time period for batch releases:
26435 minutes
- 3. Maximum time period for a batch release:
510 minutes
- 4. Average time period for a batch release:
156 minutes
- 5. Minimum time period for a batch release:
5 minutes
- 6. Average saltwater flow during batch releases:
735000 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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 2.09E+2 compactable and non-compactable*
Ci 3.31E+2 3.0OE+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 Type A or strong tight containers of various sizes.
N/A No shipment made.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3
- 2. Estimate of major nuclide composition (by type of waste)
- a. not applicable N/A
- b. americium-241 3.56E-5 antimony-124 5.67E-8 antimony-125 1.18E-2 carbon-14 2.13E-2 cerium-144 1.43E-7 cesium-134 8.76E-3 cesium-137 6.73E-2 chromium-51 7.87E-2 cobalt-57 2.31E-8 cobalt-58 3.33E-1 cobalt-60 1.25E-1 curium-242
_1.05E-5 curium-243/244
__3.40E-5 iodine-129 3.95E-11 iron-55 1.63E-1 iron-59 6.64E-3 manganese-54 2.51E-2 nickel-59 6.22E-6 nickel-63 1.19E-1 niobium-94 1.47E-6 niobium-95 2.05E-2 plutonium-238 2.07E-5 plutonium-239/240 1.99E-5 plutonium-241 1.65E-3 ruthenium-103 2.74E-7 silver-llOm 1.30E-5 strontium-90 2.03E-4 technetium-99 5.85E-5 tin-113 1.28E-8 tritium 3.19E-3 uranium-233/234 2.62E-9 uranium-238 8.90E-12 zirconium-95
__1.36E-2
- c.
not applicable
__O.OOE+O
- d.
not applicable
__O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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 None No shipments were made N/A B.
IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination None No shipments were made N/A C.
DEWATERING Number of Containers l Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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 1A, were calculated using the following equation:
- % Applicable Limit where:
Rel Rate X/Q o
MPCeff where:
F1
=
(Rel Rate) (X/Q) (100)
MPCe~f
=
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.
=
4.80E-6 sec/r3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM.
1
_n Fi 1=.
MPC 1
=
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 MPC1 Maximum Permissible Concentration (MPC) radionuclide from 10 CFR 20 (20.1-20.602),
Table II, Column 1.
of the i t
Appendix B,
% ECL where:
Rel Rate X/Q
° ECLeff where:
F1
=
(Rel Rate) (X/Q) (100)
ECLeff
=
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, pCi/sec.
=
4.80E-6 sec/n3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM.
1
=n F
E 1
1=1 ECL s
=
fractional abundance of the ij radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, CT.
n
- ECL, total number of radionuclides identified
=
Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 Liquid Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations:
- % Applicable Limit where:
Dil Conc o
MPCeff
=
(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, 4Ci/ml.
1
=
n F
i.1 MPC where:
F, n
MPC1
- % ECL where:
Dil Conc
=
fractional abundance of the i t
radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, CT.
=
total number of radionuclides identified
=
Maximum Permissible Concentration (MPC) of the iih 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, uCi/ml.
1
=
n F
121 ECL
° ECLeff where:
F.
n
- ECL,
=
fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Cr, 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 2.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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
=
+
G2 +
22
+
where:
Error associated with each component.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 SECTION H.
10 CFR 50 APPENDIX I REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual.
Six different categories are presented:
(1)
(2)
(3)
(4)
(5)
(6)
Liquid Effluents - Whole Body Liquid Effluents - Organ Airborne Effluents - Tritium, Iodines and Particulates Noble Gases - Gamma Noble Gases - Beta Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; these data are also presented in Table 2D.
Categories 3, 4, and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) software, Regulatory Guide 1.109 methodology, and concurrent meteorology. Table IE of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using methods described in the ODCM and the historical meteorology (X/Q).
Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.
For members of the public, per the ODCM, who may at times be within the site boundary', the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.
For members of the public who traverse the site boundary via highway 1-5, the residency time shall be considered negligible and hence the dose "0".
Table 2 in Section H in Table 1.
presents the percent of Applicable Limits for each dose presented ODCM Figures 2-1 & 2-2.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 TABLE 1 Dose *
(millirems)
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS
- 1)
- 2)
- 3)
- 4) 5)
Whole Body 8.16E-5 1.16E-3 2.56E-4 1.23E-3 2.73E-3
- 6)
- 7)
- 8)
- 9) 10)
Organ 4.47E-4 1.74E-3 5.14E-4 1.36E-3 4.06E-3 AIRBORNE EFFLUENTS
- 11)
- 12)
- 13)
- 14) 15)
Tritium, Iodines, and Particulates 5.98E-3 1.18E-2 2.93E-3
-5.10E-4 1.35E-2 NOBLE GASES **
- 16)
- 17)
- 18)
- 19) 20)
Gamma 3.48E-4 1.30E-3 5.71E-3 3.82E-3 9.18E-3
- 21)
- 22)
- 23)
- 24) 25)
Beta 7.58E-4 1.30E-3 2.68E-3 2.02E-3 6.37E-3
- 26)
- 27)
- 28)
- 29) 30)
DIRECT RADIATION 1.37E-1 1.23E-1 7.60E-2 1.31E-1 4.67E-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 th(
- 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 th(
- 5. This value was calculated using the methodology of thE maximum dose was calculated, including of mrad, reflecting the air dose.
e ODCM.
? ODCM.
2 ODCM.
a ODCM.
a ODCM.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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.
- 7.
This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
- 8.
This value was calculated using the methodology of the ODCM; the GI-LLI 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 NNW 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 ENE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
- 13. The maximum organ dose was to a child's liver and was located in the NNW 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 NNW 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 ENE 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 E 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 E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3
- 25. 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.
- 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 W 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 W 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 2.72E-3 3.87E-2 8.54E-3 4.11E-2 4.56E-2 Organ 4.47E-3 1.74E-2 5.14E-3 1.36E-2 2.03E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 3.99E-2 7.84E-2 1.95E-2 3.40E-3 4.50E-2 NOBLE GASES Gamma 3.48E-3 1.30E-2 5.71E-2 3.82E-2 4.59E-2 Beta 3.79E-3 6.51E-3 1.34E-2 1.01E-2 1.59E-2 NOTE:
Direct Radiation is hot specifically addressed in the Applicable Limits.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 28, 2002, Revision 37 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated the following:
- 1.
A change to the requirement for reporting unplanned releases on a quarterly basis in the annual report,
- 2.
Updates related to the recent Land Use Census, and
- 3.
Changes to Kelp and Shoreline Sediment environmental sample locations.
Item 1 is being changed in response to AR 011000482 to reflect the more generic language of NUREG 0472. An Effluent/ODCM Screen has been provided for item 1. Item 3 changes were made per email from Environmental Protection Group to Effluent Engineering dated 2/1/02.
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 calculations.
The level 40CFR190, 10CFR50.36a, and the accuracy or reliability of effluent dose or setpoint of radioactive effluent control required by 10CFR20, Appendix I to 10CFR50 will be maintained.
Throughout the document, change bars are marked in one of four ways as follows:
A D
F R
Addition Deletion Editorial/Format change Revision The following is a complete list of the changes:
PAGE CHANGE TOC Renumbered pages as necessary based on changes in the body of the ODCM.
2-39 Format change for numbers 2-31 Updated CLF due to Land Use Census Update.
2-33 Removed previously blank page.
2-41 Updated Dose Parameters in Table 2-9, Outage Workers due to Land Use Census Update.
Sect. 2 Renumbered Section 2 pages from 2-33 on to reflect the addition of pages.
5-19 Removed distances from titles of Shoreline Sediment locations for San Onofre State Beach (Southeast)
Removed a previously deleted line 5-20 Deleted Kelp sample Laguna Beach (CONTROL)
Added Kelp sample Salt Creek (CONTROL) 11 to 13 miles WNW to NW Deleted Ocean Sediment sample Unit 1 Outfall Removed distance and direction from title of Ocean Sediment location for Unit 1 Outfall Added Ocean Sediment sample SONGS Upcoast 0.9 miles WSW REASON F
F R
F R
F R
F D
A D
R A
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 5-23 thru 5-27 6-9 New maps reflecting changes to sample locations Changed the time frame for unplanned releases reporting in the annual report by replacing "on a quarterly basis" with "during the reporting period" per AR 011000482.
R R
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, 2002 to December 31, 2002.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 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 2001 with trace amounts of tritium).
The valves were repaired during the Unit 2 refueling outage in May 2002.
This event is documented in AR 001200733.
Waste Gas System leakage in the Radwaste Building In May 2002, while venting the volume control tank through the waste gas system, equipment failure lead to a system leak into the radwaste building.
Samples were collected in the vicinity of the leak for release evaluation. The dose was included in the monthly dose data.
The dose received by the public as a result of this event was bounded by the dose received from the site for the month.
This event is documented in AR 020501046.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 - December 31, 2002 S.O.N.G.S. 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 000400960.
2RT-7817 05/20/02 --07/08/02 Monitor failure Investigation identified detector BPS/FFCPD with low flow was non-functional and was Discharge Monitor replaced. The flow switch was found to be slightly degraded but still functional. This event is documented in AR 020501134.
09/21/02 -
10/26/02 Shorted circuitry Investigation identified the with corrosion detector had been shorted and the forming connector was corroded due to water intrusion into the detector. An overhead floor plug was found to leak excessively and was repaired.
This event is documented in AR 020901084.
2RT-7865 09/23/02 -
11/21/02 Isokinetic flow Major inspection and repair-of the Plant Vent Stack probe inspection isokinetic flow probes.
This event (Containment is documented in AR 011100588.
Purge) Monitor ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2002 - December 31, 2002 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 000400960.
3RT-7865 04/29/02 -
07/02/02 Isokinetic flow Major inspection, repair and Plant Vent Stack probes calibration of the isokinetic flow (Containment probes. This event is documented Purge) Monitor in AR 020500049.
3RT-7817 06/04/02 -
current Failure due to low Monitor has had low sample flow BPS/FFCPD sample flow.
problems since installation. The Discharge Monitor piping was replaced in 2000 with marginal improvement. The long lengths of pipe and low motive force are the cause of this problem. Corrective actions currently in progress include a simplified piping design. This event is documented in ARs 010600960 and 020701020.
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 (2002)
S.O.N.G.S. 2 and 3 SECTION L.
S.O.N.G.S. 2 and 3 CONCLUSIONS Gaseous
- curies, tritium releases totaled 1.08E+2 curies of which noble gases were 6.35E+1 iodines were 1.74E-2 curies, particulates were 3.14E-4 curies, and was 4.42E+1 curies.
The radiation doses from gaseous releases were: (a) gamma air dose: 9.18E-3 mrad at the site boundary, (b) beta air dose: 6.37E-3 mrad at the site boundary, (c) organ dose: 1.35E-2 mrem at the nearest receptor.
Liquid releases totaled 1.49E+3 curies of which particulates and iodines were 1.66E-2 curies, tritium was 1.49E+3 curies, and noble gases were 2.95E-1 curies.
The radiation doses from liquid releases were: (a) total body: 2.73E-3 mrem, (b) limiting organ: 4.06E-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 (2002)
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 9.47E+1 compactable and non-compactable
- Ci 1.42E+1 3.OOE+1
- c. Irradiated components, 3
(incl. excore detectors and m
1.93E+O heated junction thermocouple)
- Ci 4.59E+1 3.0OE+1 m3 N/A
- d. Other (filters)
Ci N/A N/A Note: Total curie content estimated.
(*) Material packaged in Type A or strong tight containers of various sizes.
N/A No shipment made.
I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
COMMON
- 2.
Estimate of major nuclide composition (by type of waste)
- a. not applicable N/A
- b. americium-241 5.72E-2 antimony-124 2.85E-3 antimony-125 6.05E-1 carbon-14 1.17E+O ceri um-144 4.12E-2 cesium-134 6.36E-1 cesium-137 7.31E+O chromium-51 2.70E-1 cobalt-57 2.05E-2 cobalt-58 1.44E+O cobalt-60 3.07E+1 curium-242 8.89E-4 curium-243/244
__2.97E-2 iodine-129
__4.92E-9 iron-55 3.13E+1 iron-59 1.66E-2 manganese-54 6.18E-1 nickel-59 1.05E-1 nickel-63 2.37E+1 niobium-94 3.28E-2 niobium-95 6.83E-2 plutonium-238 8.43E-2 plutonium-239/240 2.63E-2 plutonium-241 1.66E+O ruthenium-106 4.83E-6 silver-llOm 2.82E-2 strontium-90 1.67E-1 technetium-99 5.33E-3 tritium
__1.27E-1 uranium-233 1.56E-4 uranium-235 3.19E-7 uranium-238
__1.74E-10 zirconium-95 5.05E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
COMMON
- 2.
Estimate of major nuclide composition (by type of waste)
(Cont'd)
- c. americium-241 l_%
l 6.91E-7 antimony-124 1.66E-4 antimony-125
__2.66E-2 carbon-14
__4.75E-3 cerium-144 1.35E+O cesium-137 4.60E+O chromium-51 2.38E-5 cobalt-57 2.53E-3 cobalt-58 6.56E-2 cobal t-60 1.38E+l curium-242 6.21E-7 curium-243/244 2.53E-6 iron-55 6.30E+1 iron-59
-6.95E-5 manganese-54 7.56E-1 nickel-59 3.73E-4 nickel-63 2.38E+O niobium-95 1.41E-5 plutonium-238 2.59E-7 plutonium-239/240 1.66E-7 plutonium-241 3.12E-5 promethium-147 2.51E+O silver-llOm 5.84E-4 strontium-89 3.36E-6 strontium-90 4.56E+O tin-113 7.28E-4 tritium 6.67E-4 uranium-233 5.19E-7 uranium-235 7.99E-5 zinc-65 7.04E+O zirconium-95 1.23E-4
- d. not applicable N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
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 39*
Hitman Trucking Company EnviroCare, UT
_Truck/Trailer 1
KTC/TAG Evr~rU
____________________Flatbed Trailer Evr~rU SONGS maintains a contract with vendors (ATG/Duratek) that provide volume reduction services.
These shipments were made from the ATG/Duratek processing facilities to EnviroCare.
The 39 shipments made from these facilities 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 D.
CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 None.
REFERENCES:
- 1. Unit 1 Technical Specifications, section D6.13.2.
- 2. Units 2 and 3 License Controlled Specifications, section 5.0.103.2.2.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
COMMON COMMON 40 CFR 190 REQUIREMENTS Table 1 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 5.58E-1
- b. Percent ODCM Specification Limit 2.23E+O
- 2. Limiting Organ
- a. Organ Dose (Bone) mrem 2.50E-1
- b. Percent ODCM Specification Limit 1.OOE+O
- 3. Thyroid
- a. Thyroid Dose mrem 2.01E-2
- b.
Percent ODCM Specification Limit 2.68E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 1.09E+2 curies of which noble gases were 6.35E+1 curies, iodines were 1.74E-2 curies, particulates were 3.16E-4 curies, and tritium was 4.56E+1 curies.
Liquid releases from S.O.N.G.S. 1, 2 and 3 totaled 1.49E+3 curies of which particulates and iodines were 2.79E-2 curies, tritium was 1.49E+3 curies, and noble gases were 2.95E-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 83 radwaste shipments to Envirocare, UT and 4 shipments to Barnwell, SC.
Total volume was 1.41E+3 cubic meters containing 2.53E+3 curies of radioactivity.
Meteorological conditions during the year were typical for S.O.N.G.S.
Meteorological dispersion was good 33% of the time, fair 43% of the time and poor 24% 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 (2002)
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 dose due to noble reactor) to areas following values:
air doses as calculated using the historical X/Q.
The air gases released in gaseous effluents from S.O.N.G.S. (per at and beyond the site boundary shall be limited to the
- 1. During any calendar quarter:
- 2. During any calendar year:
5 mrad for gamma radiation and
- 10 mrad for beta radiation.
5 10 mrad for gamma radiation and
- 20 mrad for beta radiation.
C.
The dose to a Member of the Public from iodines, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values:
- 1. During any calendar quarter:
- 2. During any calendar year:
I 7.5 mrem to any organ.
- 15 mrem to any organ.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
COMMON APPENDIX A (Continued)
LIQUID EFFLUENTS - APPLICABLE LIMITS A.
Table 2A lists the total curies released, the diluted concentration, and percent of the applicable limit. The percent of applicable limit compares the diluted concentration of radioactive material released to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration is limited to 2.OOE-4 pCi/ml.
B.
Table 2D lists doses due to liquid releases. The dose commitment to a Member of the Public from radioactive materials in liquid effluents released from S.O.N.G.S. (per reactor) to unrestricted areas shall be limited to the following values:
- 1. During any calendar quarter:
- 2. During any calendar year:
< 1.5 mrem to the total body and
- 5 mrem to any organ.
< 3 mrem to the total body and
< 10 mrem to any organ.
METEOROLOGY
METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2002 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, 2002.
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 (2002)
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01123124-02033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILI EXTREMELY UNSTABLE (DT/DZ WIND DIR N
NNE NE ENE E
WNW NW NNW
.22-
.50 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
.51-
.75 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
.76-1.0 0
0 0
0 0
0 0
0 0
1 0
0 0
0 0
0 1.1-1.5 0
0 0
0 0
0 0
0 2
1 6
7 0
0 0
0 1.6-2.0 0
0 0
0 0
0 0
0 3
2 17 19 11 1
0 0
2.1-3.0 0
0 0
0 0
0 1
3 10 15 19 43 82 20 0
1 L A
< -1.9 3.1-5.0 0
0 0
0 0
0 2
0 14 5
18 21 57 51 1
0
°C/100 5.1-7.0 1
1 3
0 0
0 1
1 4
0 0
3 4
20 1
0 METERS) 7.1-10.0 1
0 2
1 0
0 0
0 0
0 0
0 0
5 0
0 10.1-13.0 0
0 0
1 0
0 0
0 0
0 0
0 0
0 0
0
- -A n
T 13.1-18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>1l8 TOAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 2
1 5
2 0
0 4
4 33 24 60 93 154 97 2
1 TOTALS 0
0 1
16 53 194 169 39 9
1 0
0 482 NUMBER OF VALID HOURS 482 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2160 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -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 1
0 1
0 0
0 0
2 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
1 1
0 0
0 2
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 2
1 0
0 0
0 4
SSE 0
0 0
1 0
3 2
2 0
0 0
0 8
S 0
0 1
0 1
1 3
1 0
0 0
0 7
SSW 0
0 0
0 1
1 1
0 0
0 0
0 3
SW 0
0 0
2 2
1 1
0 0
0 0
0 6
WSW 0
0 0
1 2
1 0
0 0
0 0
0 4
W 0
0 0
2 3
4 0
1 0
0 0
0 10 WNW 0
0 0
0 1
4 2
0 1
0 0
0 8
NW 0
0 0
0 0
0 1
0 0
0 0
0 1
NNW 0
0 0
0 0
0 0
1 0
0 0
0 1
TOTALS 0
0 1
6 10 17 12 8
2 0
0 0
56 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 56 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01123124-02033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -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 0
2 1
0 0
0 0
0 3
NE 0
0 0
0 0
0 0
0 0
0 0
0 0
ENE 0
0 0
0 0
0 0
0 1
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
0 0
0 0
0 0
0 0
SSE 0
0 0
0 0
0 4
1 0
0 0
0 5
S 0
0 0
0 1
1 3
0 0
0 0
0 5
SSW 0
0 0
0 2
1 0
0 0
0 0
0 3
SW 0
0 0
3 1
1 3
1 1
0 0
0 10 WSW 0
0 0
1 0
1 0
0 0
0 0
0 2
W 0
0 0
1 0
1 1
0 0
0 0
0 3
WNW 0
0 0
2 2
3 4
0 0
0 0
0 11 NW 0
0 0
1 0
1 2
0 0
0 0
0 4
NNW 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTALS 0
0 0
8 6
11 18 2
2 0
0 0
47 NUMBER OF VALID HOURS 47 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2160 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -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
0 2
5 7
2 0
0 0
0 0
16 NNE 0
1 2
5 4
5 4
1 0
0 0
0 22 NE 0
0 0
1 0
2 1
2 1
0 0
0 7
ENE 0
0 0
1 0
0 0
2 1
0 0
0 4
E 0
0 1
1 0
4 2
0 0
0 0
0 8
ESE 0
0 0
1 4
9 5
1 0
0 0
0 20 SE 0
0 1
3 12 26 35 9
0 0
0 0
86 SSE 0
1 1
7 8
17 23 13 1
1 0
0 72 S
0 0
1 6
5 4
8 4
6 0
0 0
34 SSW 0
1 1
6 2
6 3
2 1
2 0
0 24 SW 0
0 1
2 4
4 0
2 1
0 0
0 14 WSW 0
1 1
3 0
4 1
2 0
0 0
0 12 W
0 1
2 4
7 7
6 5
0 0
0 0
32 WNW 0
1 2
0 3
16 11 10 1
0 0
0 44 NW 0
0 1
4 6
12 23 6
1 0
0 0
53 NNW 0
0 2
1 7
6 2
0 0
0 0
0 18 TOTALS 0
6 16 47 67 129 126 59 13 3
0 0
- 466, NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 466 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01123124-02033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ s 1.5 WIND)
DIR N
NNE NE ENE E
WNW NW NNW
.22-
.50 1
0 0
0 0
1 0
0 1
0 1
0 0
0 0
0
.51-
.75 0
2 0
1 2
0 0
0 1
1 0
0 0
0 0
0
.7b-1.0 2
5 0
2 6
0 0
1 1
2 1
0 1
0 1
1 1.1-1.5 3
15 9
4 3
5 4
6 2
3 6
1 3
1 2
5 1.6b-2.0 6
14 4
4 4
2 4
1 1
1 0
0 3
3 1
6 Z.1-3.0 12 20 1
2 7
6 8
2 1
0 0
0 2
4 5
8 S.1-5.0 3
14 4
3 8
1 10 1
0 0
0 0
1 11 2
7 CC/100 METERS) 5.1-7.1-10.1-7.0 10.0 13.0 0
1 0
1 1
0 1
4 0
2 1
0 O
0 0
O 0
0 O
0 0
O 0
0 O
0 0
O 0
0 O
0 0
1 0
0 1
0 0
2 0
0 3
0 0
1 0
0 13.1-18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>18 TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 28 72 23 19 30 15 26 11 7
7 8
2 11 21 14 28 TOTALS 4
7 23 72 54 78 65 12 7
0 0
0 322 NUMBER OF VALID HOURS 322 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2160 PASQUILL F MODERATELY-STABLE (1.5 s DT/DZ s 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 1
2 4
4 6
8 0
0 0
0 0
25 NNE 0
2 2
19 39 56 9
0 0
0 0
0 127 NE 0
1 4
16 10 4
2 0
0 0
0 0
37 ENE 0
1 7
8 6
3 0
0 0
0 0
0 25 E
0 0
2 3
2 0
0 0
0 0
0 0
7 ESE 0
0 1
1 3
0 0
0 0
0 0
0 5
SE 0
0 1
3 1
0
.0 0
0 0
0 0
5 SSE 0
0 0
0 1
0 1
0 0
0 0
0 2
S 0
0 0
1 1
0 0
0 0
0 0
0 2
SSW 1
0 0
0 0
0 0
0 0
0 0
0 1
SW 0
0 0
1 1
0 0
0 0
0 0
0 2
WSW 0
0 0
0 1
0 1
0 0
0 0
0 2
W 0
0 0
1 0
2 0
0 0
0 0
0 3
WNW 0
0 0
1 0
3 1
0 0
0 0
0 5
NW 0
0 0
0 1
0 2
0 0
0 0
0 3
NNW 0
1 0
2 0
1 0
0 0
0 0
0 4
TOTALS 1
6 19 60 70 75 24 0
0 0
0 0
255 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 255 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 01123124-02033123 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
2 1
2 6
17 4
0 0
0 0
32 NNE 0
0 2
10 27 140 214 16 0
0 0
0 409 NE 0
1 1
16 12 10 3
0 0
0 0
0 43 ENE 0
0 2
5 3
2 1
0 0
0 0
0 13 E
0 0
0 1
1 0
0 0
0 0
0 0
2 ESE 0
0 0
0 0
0 0
0 0
0 0
0 0
SE 0
0 1
0 0
0 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 1
0 0
0 0
0 2
SSW 0
1 0
1 0
0 0
0 0
0 0
0 2
SW 0
0 0
0 0
0 0
0 0
0 0
0 0
WSW 0
1 1
1 0
0 1
0 0
0 0
0 4
W 0
0 1
1 1
3 0
0 0
0 0
0 6
WNW 0
0 1
1 1
4 0
0 0
0 0
0 7
NW 0
0 0
2 1
0 0
0 0
0 0
0 3
NNW 0
0 0
3 0
0 4
0 0
0 0
0 7
TOTALS 0
3 11 43 49 165 241 20 0
0 0
0 532 NUMBER OF VALID HOURS 532 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
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
1 1
6 10 17 32 30 6
2 0
0 0
105 NNE 0
5 11 49 84 223 242 19 1
0 0
0 634 NE 0
2 5
42 26 17 10 6
7 0
0 0
115 ENE 0
2 11 18 13 7
4 5
5 1
0 0
66 E
0 2
9 8
7 11 10 0
0 0
0 0
47 ESE 1
0 1
7 9
15 6
1 0
0 0
0 40 SE 0
0 3
10 17 36 49 11 0
0 0
0 126 SSE 0
1 2
14 11 25 31 17 1
1 0
0 103 S
1 1
3 12 12 17 29 9
6 0
0 0
90 SSW 1
3 4
11 8
23 9
2 1
2 0
0 64 SW 1
0 2
20 25 25 22 3
2 0
0 0
100 WSW 0
2 2
14 22 49 24 6
0 0
0 0
119 W
0 1
4 12 25 101 65 11 0
0 0
0 219 WNW 0
1 3
5 11 54 80 32 7
0 0
0 193 NW 0
0 2
9 9
18 31 10 1
0 0
0 80 NNW 0
1 3
11 13 16 13 2
0 0
0 0
59 TOTALS 5
22 71 252 309 669 655 140 33 4
0 0
2160 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2160 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02033124-02063023 WIND SPEED (M/S) AT 10 METER LEVEL EXTREMELY UNSTABLE WIND DIR N
NNE NE ENE E
WNW NW NNW
.22-
.50 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
.51-
.75 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
.76-1.0 0
0 0
0 0
0 0
0 0
0 0
1 0
0 0
0 1.1-1.5 0
0 0
0 0
0 0
0 0
2 1
1 1
1 1
1.6-2.0 0
0 0
0 0
0 0
2 2
4 7
8 7
1 0
0 PASQUILL A (DT/DZ < -
2.1-3 3.0 5
0 0
0 0
0 0
1 1
8 17 46 1
90 1:
49 1(
12 i
0 1
-1.9
.1-
.0 0
0 0
0 0
0 4
58 51 58 13 39 0
0
°C/100 5.1-7.0 0
0 0
0 0
0 1
0 18 4
0 9
0 8
1 0
METERS) 7.1-10.0 0
0 0
0 0
0 0
0 4
0 0
1 0
0 0
0 e
A s
4 4
e A
e
^
10.1-13.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>18 TOiAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 2
7 90 76 123 223 166 64 2
2 TOTALS 0
0 1
7 31 225 445 41 5
0 0
0 755 NUMBER OF VALID HOURS 755 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2184 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -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
1 0
0 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 2
1 0
0 0
0 3
SSE 0
0 0
0 0
0 1
3 0
0 0
0 4
S 0
0 0
1 2
7 9
3 0
0 0
0 22 SSW 0
0 0
1 3
3 9
1 0
0 0
0 17 SW 0
0 0
0 1
3 3
0 0
0 0
0 7
WSW 0
0 0
1 0
2 1
0 0
0 0
0 4
W 0
0 0
1 1
3 0
0 0
0 0
0 5
WNW 0
0 0
0 2
4 1
1 0
0 0
0 8
NW 0
0 0
0 0
2 1
1 0
0 0
0 4
NNW 0
0 0
O 0
0 0
0 0
0 0
0 TOTALS 0
0 0
5 9
24 27 10 0
0 0
0 75 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 75 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2184
11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02033124-02063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -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
1 0
0 0
0 0
1 NNE 0
0 0
0 0
1 0
0 0
0 0
0 1
NE 0
0 0
1 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
2 0
1 0
0 0
0 3
SSE 0
0 0
0 0
1 7
3 2
0 0
0 13 S
0 0
0 0
2 5
8 6
0 0
0 0
21 SSW 0
0 0
1 1
4 7
1 0
0 0
0 14 SW 0
0 0
3 4
7 1
0 0
0 0
0 15 WSW 0
0 1
0 4
6 1
0 0
0 0
0 12 W
0 0
0 0
1 5
0 0
0 0
0 0
6 WNW 0
0 0
1 0
2 2
0 0
0 0
0 5
NW 0
0 0
1 0
2 6
1 0
0 0
0 10 NNW 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTALS 0
0 1
7 12 35 33 12 2
0 0
0 102 NUMBER OF VALID HOURS 102 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2184 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -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 5
19 3
2 0
0 0
0 0
31 NNE 1
0 2
16 13 32 3
0 0
0 0
0 67 NE 0
0 1
8 11 5
0 0
0 0
0 0
25 ENE 0
0 1
3 5
4 0
0 0
0 0
0 13 E
0 0
1 2
4 13 5
0 0
0 0
0 25 ESE 1
2 1
4 6
27 14 0
0 0
0 0
55 SE 1
3 2
4 15 49 57 5
2 0
0 0
138 SSE 0
0 2
19 27 35 67 29 6
0 0
0 185 S
0 2
2 26 14 32 35 17 3
0 0
0 131 SSW 1
0 1
10 15 31 11 1
0 0
0 0
70 SW 1
0 3
7 6
18 11 0
0 0
0 0
46 WSW 0
0 1
4 4
9 3
2 0
0 0
0 23 W
0 1
1 8
6 3
5 0
0 0
0 0
24 WNW 0
1 2
5 6
9 7
2 0
0 0
0 32 NW 0
2 1
3 7
13 19 2
0 0
0 0
47 NNW 0
0 1
6 3
13 4
0 0
0 0
0 27 TOTALS 5
11 24 130 161 296 243 58 11 0
0 0
939 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 939 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY April -
June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02033124-02063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ
- 1.5 'C/100 METERS)
WIND DIR N
NNE NE ENE E
WNW NW NNW
.22-
.50 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
.75 0
0 0
0 0
0 0
0 0
0 1
0 0
0 0
0
./b-1.0 1
2 1
0 2
0 1
0 0
0 0
1 0
0 0
0 1.1-1.5 2
13 8
0 0
0 0
0 1
0 1
0 0
1 0
0 1.b-2.0 6
14 3
1 0
0 0
1 0
0 0
0 0
0 1
0 Z.1-3.0 4
25 0
4 2
0 4
0 1
1 0
0 0
0 1
2 3.1-5.0 3
5 0
0 2
1 3
2 0
0 0
0 0
0 0
1 5.1-7.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
7.1-10.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1U. 1-13.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
- 3.
1-18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>1J TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 16 60 12 5
6 1
8 3
2 1
2 1
0 1
2 3
TOTALS 1
1 8
26 26 44 17 0
0 0
0 0
123 NUMBER OF VALID HOURS 123 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2184 PASQUILL F MODERATELY STABLE (1.5 s DT/DZ s 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
2 0
0 0
0 0
0 0
2 NNE 0
0 2
5 20 31 11 0
0 0
0 0
69 NE 0
0 3
3 1
0 0
0 0
0 0
0 7
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 1
0 0
0 0
0 0
0 1
SE 0
0 0
0 0
0 0
0 0
0 0o 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
0 0
1 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 1
0 0
0 0
0 0
0 1
W 0
0 0
0 0
0 0
0 0
0 0
0 0
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
0 0
0 0
0 0
0 0
0
- 0 TOTALS 0
0 5
9 25 32 11 0
0 0
0 0
82 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 82 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02033124-02063023 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
3 0
0 0
0 0
4 NNE 0
0 1
2 4
57 34 0
0 0
0 0
98 NE 0
0 0
0 0
1 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
1 0
0 0
0 0
0 1
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 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 0
0 0
0 0
0 0
0 0
0 0
WNW 0
0 0
0 0
0 1
0 0
0 0
0 1
NW 0
0 0
0 0
0 2
0 0
0 0
0 2
NNW 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTALS 0
0 1
2 4
60 40 1
0 0
0 0
108 NUMBER OF VALID HOURS 108 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 N
0 0
3 7
27 8
9 0
0 0
0 0
54 NNE 2
0 7
37 51 146 53 0
0 0
0 0
296 NE 0
0 5
20 15 6
0 0
0 0
0 0
46 ENE 0
0 1
3 6
8 0
0 0
0 0
0 18 E
0 0
3 2
4 16 7
0 0
0 0
0 32 ESE 1
2 1
4 7
27 15 0
0 0
0 0
57 SE 1
3 3
4 15 56 62 9
2 0
0 0
155 SSE 0
0 2
19 30 37 81 35 8
0 0
0 212 S
0 2
2 28 20 53 110 44 7
0 0
0 266 SSW 1
0 1
12 23 57 78 7
0 0
0 0
179 SW 1
1 3
13 18 74 83 0
0 0
0 0
193 WSW 0
0 4
6 17 107 118 11 1
0 0
0 264 W
0 1
1 10 15 60 114 0
0 0
0 0
201 WNW 0
1 2
9 9
27 53 11 0
0 0
0 112 NW 0
2 1
5 8
18 28 5
0 0
0 0
67 NNW 0
0 1
7 3
16 5
0 0
0 0
0 32 TOTALS 6
12 40 186 268 716 816 122 18 0
0 0
2184 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2184 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY July -
September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02063024-02093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A (DT/DZ < -1.9 EXTREMELY UNSTABLE WIND DIR N
NNE NE ENE E
WNW NW NNW TOTALS
.22-
.50 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
.51-
.75 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
.76-1.0 0
0 0
0 0
0 0
0 0
0 1
2 0
0 0
3 1.1-1.5 0
0 1
0 0
0 0
0 1
4 3
2 2
2 0
0 15 1.6-2.0 0
0 0
0 0
0 1
1 5
5 18 14 5
1 1
1 52 2.1-3.0 0
1 0
0 0
0 0
2 12 10 51 82 73 12 1
0 24 3.1-5.0 0
0 0
0 0
0 0
1 33 33 38 62 123 34 2
0' 326
°C/100 5.1-7.0 0
0 0
0 0
0 0
1 8
3 0
0 0
0 2
0 14 METERS) 7.1-10.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
10.1-13.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
13.1-18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
>18 TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 1
0 0
0 1
5 59 55 110 161 205 49 6
1 NUMBER OF VALID HOURS 654 NUMBER OF CALMS 1
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2208 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -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
1 0
0 0
0 0
1' NNE 0
0 0
0 1
1 0
0 0
0 0
0 2
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
1 0
0 0
1 0
1 0
0 0
0 3
S 0
0 0
0 0
1 9
0 0
0 0
0 10 SSW 0
0 0
3 1
7 2
1 0
0 0
0 14 SW 0
0 0
0 1-6 4
0 0
0 0
0 11 WSW 0
0 0
0 6
5 0
0 0
0 0
0 11 W
0 0
0 3
3 5
3 0
0 0
0 0
14 WNW 0
0 0
0 2
7 5
0 0
0 0
0 14 NW 0
0 0
- 0.
0 2
0 0
0 0
0 0
2 NNW 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTALS 0
1 0
6 14 35 24 2
0 0
0 0
82 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 82 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 1
2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02063024-02093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -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 1
0 1
0 0
0 0
0 0
2 NNE 0
0 0
0 0
1 0
0 0
0 0
0 1
NE 0
0 0
0 1
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
1 1
0 0
0 0
0 2
SSE 0
0 0
0 0
0 2
1 0
0 0
0 3
S 0
0 0
0 3
3 7
2 0
0 0
0 15 SSW 0
0 0
0 4
8 7
0 0
0 0
0 19 SW 0
0 0
0 3
12 6
0 0
0 0
0 21 WSW 0
0 0
3 5
7 1
0 0
0 0
0 16 W
0 0
0 2
3 5
2 0
0 0
0 0
12 WNW 0
0 0
0 0
8 3
1 0
0 0
0 12 NW 0
0 0
0 0
0 2
0 0
0 0
0 2
NNW 0
0 0
0 0
1 1
0 0
0 0
0 2
TOTALS 0
0 0
6 19 47 32 4
0 0
0 0
108 NUMBER OF VALID HOURS 108 NUMBER OF CALMS 1
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2208 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -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 12 10 10 0
0 0
0 0
0 35 NNE 0
0 1
17 13 18 0
0 0
0 0
0 49 NE 0
0 2
8 5
0 0
0 0
0 0
0 15 ENE 0
1 0
2 3
1 0
0 0
0 0
0 7
E 0
1 3
1 2
3 1
0 0
0 0
0 11 ESE 1
0 4
3 2
6 4
0 0
0 0
0 20 SE 1
1 1
12 14 30 26 4
0 0
0 0
89 SSE 0
3 3
13 19 36 49 12 1
0 0
0 136 S
0 2
2 11 15 36 56 5
0 0
0 0
127 SSW 0
1 7
14 17 27 12 2
0 0
0 0
80 SW 0
7 9
11 4
14 2
0 0
0 0
0 47 WSW 1
3 6
7 8
4 0
0 0
0 0
0 29 W
2 4
5 15 11 8
8 0
0 0
0 0
53 WNW 0
2 3
10 18 15 7
1 0
0 0
0 56 NW 1
2 1
9 9
6 6
0 0
0 0
0 34 NNW 0
1 3
11 11 5
0 0
0 0
0 0
31 TOTALS 6
29 52 156 161 219 171 24 1
0 0
0 819 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 819 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 1
2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY July -
September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02063024-02093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY 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 1
2 17 7
8 2
0 0
0 0
0 37 NNE 2
0 7
11 14 11 2
0 0
0 0
0 47 NE 0
3 0
3 2
1 0
0 0
0 0
0 9
ENE 0
0 3
4 1
0 0
0 0
0 0
0 8
E 0
1 1
0 1
1 0
0 0
0 0
0 4
ESE 0
0 0
2 3
2 0
0 0
0 0
0 7
SE 0
0 1
6 10 14 8
0 0
0 0
0 39 SSE 0
1 1
7 5
10 10 1
0 0
0 0
35 S
0 0
3 9
5 4
5 1
0 0
0 0
27 SSW 0
0 3
4 3
3 1
0 0
0 0
0 14 SW 0
2 1
6 3
5 0
0 0
0 0
0 17 WSW 0
0 1
6 1
0 0
0 0
0 0
0 8
W 1
2 1
2 3
1 1
0 0
0 0
0 11 WNW 0
0 3
2 4
7 3
1 0
0 0
0 20 NW 0
0 0
1 7
4 1
0 0
0 0
0 13 NNW 0
0 2
3 2
2 0
0 0
0 0
0 9
TOTALS 3
10 29 83 71 73 33 3
0 0
0 0
305 NUMBER OF VALID HOURS 306 NUMBER OF CALMS 1
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2208 PASQUILL F MODERATELY STABLE (1.5 5 DT/DZ s 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 0
2 5
10 6
2 0
0 0
0 0
26 NNE 0
1 7
13 12 25 1
0 0
0 0
0 59 NE 0
2 0
2 1
1 0
0 0
0 0
0 6
ENE 1
0 0
0 1
0 0
0 0
0 0
0 2
E 0
1 2
1 0
0 0
0 0
0 0
0 4
ESE 0
0 0
2 0
1 1
0 0
0 0
0 4
SE 0
0 0
1 0
2 4
1 0
0 0
0 8
SSE 0
0 0
2 5
2 0
0 0
0 0
0 9
S 0
2 1
3 0
0 0
0 0
0 0
0 6
SSW 0
0 2
2 0
0 0
0 0
0 0
0 4
SW 1
0 0
0 0
1 0
0 0
0 0
0 2
WSW 0
0 0
0 0
1 0
0 0
0 0
0 1
W 0
0 0
0 0
2 1
0 0
0 0
0 3
WNW 0
0 0
0 0
1 3
1 0
0 0
0 5
NW 0
2 0
0 0
0 1
0 0
0 0
0 3
NNW 0
2 1
0 1
0 0
0 0
0 0
0 4
TOTALS 3
10 15 31 30 42 13 2
0 0
0 0
146 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 146 0
NUMBER OF CALMS TOTAL HOURS FOR 1
2208 THE PERIOD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02063024-02093023 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
1 2
3 4
9 0
0 0
0 0
19 NNE 0
0 0
4 6
25 14 0
0 0
0 0
49 NE 0
0 0
0 3
1 0
0 0
0 0
0 4
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 1
1 0
1 0
3 0
0 0
0 6
SSE 0
0 0
0 0
2 1
0 0
0 0
0 3
S 0
0 1
0 0
0 0
0 0
0 0
0 1
SSW 0
0 0
0 0
0 0
0 0
0 0
0 0
SW 1
0 0
0 0
0 0
0 0
0 0
0 1
WSW 0
0 0
0 0
0 0
0 0
0 0
0 0
W 0
0 0
0 0
0 1
0 0
0 0
0 1
WNW 0
0 0
0 0
0 1
1 0
0 0
0 2
NW 0
0 1
0 0
2 1
0 0
0 0
0 4
NNW 0
0 0
0 1
0 2
0 0
0 0
0 3
TOTALS 1
0 4
7 13 35 29 4
0 0
0 0
93 NUMBER OF VALID HOURS 93 NUMBER OF CALMS 1
NUMBER OF INVALID HOURS 0
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 N
1 2
7 37 30 29 14 0
0 0
0 0
120 NNE 2
1 15 45 46 82 17 0
0 0
0 0
208 NE 0
5 2
14 12 3
0 0
0 0
0 0
36 ENE 1
1 3
6 5
1 0
0 0
0 0
0 17 E
0 3
6 2
3 4
1 0
0 0
0 0
19 ESE 1
0 4
7 5
9 5
0 0
0 0
0 31 SE 1
1 3
20 25 48 39 8
0 0
0 0
145 SSE 0
5 4
22 30 53 63 16 1
0 0
0 194 S
0 4
7 24 28 56 110 16 0
0 0
0 245 SSW 0
1 12 27 30 55 55 6
0 0
0 0
186 SW 2
9 10 20 29 89 50 0
0 0
0 0
209 WSW 1
3 8
18 34 99 63 0
0 0
0 0
226 W
3 6
8 24 25 94 139 0
0 0
0 0
299 WNW 0
2 6
14 25 50 56 5
0 0
0 0
158 NW 1
4 2
10 17 15 13 2
0 0
0 0
64 NNW 0
3 6
14 16 8
3 0
0 0
0 0
50 TOTALS 13 50 103 304 360 695 628 53 1
0 0
0 2208 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2208 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 1
2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02093024-02123123 WIND SPEED (M/S) AT 10 METER LEVEL EXTREMELY UNSTABLE WIND DIR NN-NNE NE ENE E
WNW NW NNW TOTALS
.22-
.50 0
0 0
0 0
0 0
0 0
0 2
0 0
0 0
0 2
.51-
.75 0
0 0
0 0
0 0
0 0
0 1
2 3
0 0
0 6
.76-1.0 0
0 0
0 0
0 0
1 0
2 4
0 0
0 07 1.1-1.5 0
0 0
0 0
0 1
4 4
3 6
5 0
0 0
23 1.6-2.0 0
0 0
0 0
0 1
1 10 7
16 11 12 0
0 0
58 PASQUILL A (DT/DZ < -
2.1-3.
3.0 5.
0 0
0 0 -
0 0
2 5
19 12 25 47 82 i
11 9
1 0
204 1.
.1.9
.1-
.0 0
0 0
0,
0 4
3 9
4 Li
[4 65 26 0
0
.36
°C/100 5.1-7.0 0
0 0
0 0
0 0
0 1
0 0
3 0
5 0
0 9
METERS) 7.1-10.0 0
0 0
0 0
0 1
0 0
0 0
0 0
1 0
0 2
10.1-13.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
13.1-18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
>18 TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
-5 0
0 0
0 0
0 8
10 44 27 60 87 167 43 1
0 447 NUMBER OF VALID HOURS 447 NUMBER OF CALMS 27 NUMBER OF INVALID HOURS 0
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 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 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 0
0 0
0 0
0 0
ESE 0
0 0
0 0
1 0
0 0
0 0
0 1
SE 0
0 0
0 0
0 0
1, 0
0 0
0 1
SSE 0
0 0
0 1
1 2
0 0
0 0
0 4
5 0
0 0
0 0
2 2
0 0
0 0
0 4
SSW 0
0 0
0 0
2 4
0 0
0 0
0 6
SW 0
0 0
0 0
0 1
0 0
0 0
0 1
WSW 0
0 0
1
- 3.
3 1
2 0
0 0
0 10 W
0 0
0 0
1 2
0 0
0 0
0 0
3 WNW 0
0 0
0 1
1 2
1 0
0 0
0 5
NW 0
0 0
0 0
0 0
0 0
0 0
0 0
NNW 0
0 0
0 0
1 0
0 0
0 0
0 1
TOTALS 0
0 0
1 6
14 13 4
0 0
0 0
38 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 38 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 27 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02093024-02123123 WIND SPEED (M/S) AT 10 METER LEVEL WIND DIR N
NNE NE ENE E
WNW NW NNW n n
.22-
.50 0
0 0
0 0
0 0
0 0
1 0
0 1
0 0
.bl-
.75 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 SLIGHTLY
.76-1.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 PASQUILL C UNSTABLE (-1.7 < DT/DZ * -1.5 °C/100 METERS) 1.1-1.5 0
0 0
0 0
0 0
0 1
3 0
1 2
1 0
0 1.6-2.0 0
0 0
0 0
0 0
0 0
0 2
1 0
0 0
0 2.1-3.0 0
0 0
0 0
0 0
3 3
3 0
1 1
1 0
0 3.1-5.0 0
0 0
0 0
0 2
2 2
4 1
0 1
2 0
0 5.1-7.0 0
0 0
0 0
0 0
0 00 0
0 0
1 0
7.1-10.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 10.1-13.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 13.1-18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0o
>18 TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 2
5 6
10 4
3 4
5 1
TOTALS 2
0 0
8 3
12 14 1
0 0
0 0
40 NUMBER OF VALID HOURS 40 NUMBER OF CALMS 27 NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2208 PASQUILL D NEUTRAL (-1.5 < DT/DZ s -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
1 2
4 7
9 11 0
0 0
0 0
0 35 NNE 0
3 2
8 7
4 2
0 0
0 0
0 28 NE 0
1 0
3 3
4 0
1 1
0 0
0 13 ENE 0
0 1
6 1
0 0
4 1
0 0
0 14 E
0 0
3 1
1 3
6 1
1 0
0 0
17 ESE 0
0 1
0 3
3 1
2 1
0 0
0 11 SE 0
1 1
7 6
29 20 4
10 0
0 0
78 SSE 0
0 4
4 8
27 19 1
2 1
1 0
68 S
1 1
3 10 4
11 4
0 1
0 2
0 37 SSW 2
2 1
2 5
2 2
1 0
0 0
0 17 SW 1
0 3
1 4
7 12 3
0 1
0 0
32 WSW 1
1 0
6 6
1 8
2 0
0 0
0 26 W
0 0
0 4
9 2
3 0
1 0
0 0
20 WNW 0
0 3
8 8
18 10 0
1 0
0 0
48 NW 0
2 2
8 6
20 8
1 0
0 0
0 49 NNW 2
2 6
8 3
7 1
1 0
0 0
- 0.
34 TOTALS 8
15 34 83 83 149 96 21 19 2
3 0
527 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 527 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 27 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY October -
December TABLE 4A SITE: SAN ONOFRE PERIOD-OF RECORD 02093024-02123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ s 1.5 C/100 METERS)
WIND DIR N
NNE NE ENE E
WNW NW NNW
.22-
.50 3
1 0
0 0
0 2
0 1
0 1
0 0
1 0
1
.51-
.75 1
0 1
1 1
0 1
0 1
1 1
0 0
0 0
1
.7b-1.0 2
5 2
2 3
0 1
0 1
0 1
0 0
0 1
3
- 1. 1-1.5 14 13 5
3 4
1 2
2 0
1 2
0 1
0 2
0 1.b-2.0 9
20 3
1 1
1 3
0 3
0 0
1 2
3 3
4 2.1-3.0 25 16 3
4 4
1 6
1 1
0 0
2 1
7 7
4
-3.1-5.0 7
9 2
1 2
2 6
1 2
4 2
1 2
3 4
3 5.1-7.0 1
1 0
0 0
0 0
0 2
3 4
2 2
1 0
7.1-10.0 2
0 0
0 0
0 0
2 0
1 0
0 1
3 1
0
- 0. 1-13.0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 IS.1-18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>lb TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 64 66 17 12 15 5
22 6
9 10 10 8
9 19 19 16 TOTALS 10 9
21 50 54 82 51 16 10 1
0 0
307 NUMBER OF VALID HOURS 307 NUMBER OF CALMS 27 NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 2208 PASQUILL F MODERATELY STABLE (1.5 s 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
2 9
7 15 16 0
0 0
0 0
51 NNE 0
1 7
20 35 43 17 0
0 0
0 0
124 NE 4
0 2
6 3
3 3
0 0
0 0
0 21 ENE 1
1 5
4 1
1 0
0 0
0 0
0 14 E
0 0
2 1
1 0
0 0
0 0
0 0
5 ESE 0
0 2
0 1
2 0
0 0
0 0
0 5
SE 2
0 0
0 0
0 0
0 0
0 0
0 2
SSE 0
0 1
1 0
0 0
0 0
0 0
0 2
S 0
1 0
0 0
0 0
0 0
0 0
0 1
SSW 0
0 1
1 0
0 0
0 0
0 0
0 2
SW 0
0 1
0-0 0
0 0
0 0
0 0
1 WSW 0
0 0
1 1
0 0
0-0 0
0 0
2 W
0 0
2 1
0 0
0 0
0 0
0 0
3 WNW 0
0 1
1 3
8 2
0 0
0 0
0 15 NW 1
1 0
0 0
3 0
0 0
0 0
0 5
NNW 0
0 1
2 1
4 0
0 0
0 0
0 8
TOTALS 9
5 27 47 53 79 38 0
0 0
0 0
261 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 261 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 27 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2002)
METEOROLOGY October -
December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 02093024-02123123 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
2 0
2 4
6 27 46 4
0 0
0 0
91 NNE 1
2 3
12 20 162 218 7
0 0
0 0
425 NE 1
0 2
1 4
4 1
0 0
0 0
0 14 ENE 0
4 1
4 0
1 0
0 0
0 0
0 10 E
0 0
0 0
1 0
0 0
0 0
0 0
2 ESE 0
0 0
1 0
2 0
0 0
0 0
0 3
SE 0
0 2
3 0
2 3
0 0
0 0
0 10 SSE 1
1 0
1 2
1 0
0 0
0 0
0 6
S 0
0 3
0 1
0 0
0 0
0 0
0 4
SSW 0
0 0
1 0
0 0
0 0
0 0
0 1
SW 1
0 0
0 0
0 0
0 0
0 0
0 2
WSW 1
0 1
0 0
0 0
0 0
0 0
0 2
W 0
0 0
0 1
1 2
1 0
0 0
0 5
WNW 0
0 0
0 1
1 4
0 0
0 0
0 6
NW O
0 1
0 0
0 0
0 0
0 0
0 1
NNW 0
0 0
2 0
3 1
0 0
0 0
0 6
TOTALS 7
7 15 29 36 204 275 12 0
0 0
0 588 NUMBER OF VALID HOURS 588 NUMBER OF CALMS 27 NUMBER OF INVALID HOURS 0
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 N
7 4
10 34 31 79 69 4
2 1
0 0
242 NNE 2
6 17 53 82 225 246 8
0 0
0 0
643 NE 5
2 6
15 13 14 7
2 1
0 0
0 66 ENE 1
6 9
17 3
6 1
4 1
0 0
0 50 E
0 1
8 6
4 7
8 1
1 0
0 0
39 ESE 0
0 3
2 5
9 3
2 1
0 0
0 25 SE 4
2 4
12 10 39 35 5
11 0
0 0
123 SSE 1
1 5
9 12 38 27 1
4 1
1 0
101 S
2 3
8 15 18 36 19 1
1 0
2 0
105 SSW 2
3 2
12 12 19 18 3
1 0
0 0
73 SW 6
2 7
6 22 32 27 6
0 1
0 0
110 WSW 2
3 5
15 23 54 24 11 0
0 0
0 138 W
0 3
2 13 25 89 73 3
2 0
0 0
211 WNW 2
0 4
10 16 47 49 8
5 0
0 0
141 NW 1
3 4
10 9
31 12 3
1 0
0 0
76 NNW 3
3 10 12 8
19 5
1 0
0 0
0 65 TOTALS 38 42 104 241 293 744 623 63 31 3
3 0
2208 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2208 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 27 2208