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{{#Wiki_filter:SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2005 January -December Ii\ ISOUTHERN CALIFORNIA EDISONS An EDISON INTERNATIOINALe 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. | {{#Wiki_filter:SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2005 January - December | ||
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 cn November 30, 1992. By August 31, 2004, all fuel was transferred to the Independent Spent Fuel Storage Installation (ISFSI). Unit 1 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 ret megawatts electrical each. The twin units are owned by Southern California Edison (75.05%), San Diego Gas and Electric (20%), City of Anaheim (3.1.6%), and the City of Riverside (1.79%).P.O. Bo 128 San Clemnente, CA 92674-0128 S.O.N.G.S. | Ii\\ ISOUTHERN CALIFORNIA EDISONS An EDISON INTERNATIOINALe 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. | |||
..............-GASEOUS EFFLUENTS | The unit was permanently shutdown cn November 30, 1992. | ||
............-LIQUID EFFLUENTS | By August 31, 2004, all fuel was transferred to the Independent Spent Fuel Storage Installation (ISFSI). | ||
............-PREVIOUS RADIOACTIVE EFFLUENT RELEASE REP-RADWASTE SHIPMENTS | Unit 1 is owned by Southern California Edison (80%) and San Diego Gas and Electric (20%). | ||
...........-APPLICABLE LIMITS ............-ESTIMATION OF ERROR ........... | 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 ret megawatts electrical each. | ||
....-CHANGES TO OFFSITE DOSE CALCULATION MANUA...AD'ORT ADD........ | The twin units are owned by Southern California Edison (75.05%), San Diego Gas and Electric (20%), | ||
......... | City of Anaheim (3.1.6%), | ||
and the City of Riverside (1.79%). | |||
P.O. Bo 128 San Clemnente, CA 92674-0128 | |||
1 | S.O.N.G.S. 1 | ||
.... | |||
TABLE OF CONTENTS SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION INTRODUCTION.............. | |||
- GASEOUS EFFLUENTS............ | |||
- LIQUID EFFLUENTS............ | |||
- PREVIOUS RADIOACTIVE EFFLUENT RELEASE REP | |||
All the fuel is stored in the ISFSH and the plant is being demolished. | - RADWASTE SHIPMENTS........... | ||
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 errcor 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. | - APPLICABLE LIMITS............ | ||
in three categories: | - ESTIMATION OF ERROR........... | ||
fission gases, iodines, and particulates. | 10 CFR 50 APPENDIX I REQUIREMENTS.... | ||
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. | - CHANGES TO OFFSITE DOSE CALCULATION MANUA | ||
As of 8/4/93,"batch" mode releases are no longer conducted because of the permanent shutdown of the reactor. As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, and therefore are no longer measured. | ...AD | ||
All the fuel is stored in the ISFSI and the plant is being demolished. | 'ORT ADD 1 | ||
Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC for continuous mode releases only.Table IE, "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. | 2 8 | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | IENDUM....... 16 | ||
1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1 Estimated First Second Total Quarter Quarter Error, %A. Fission and activation gases 1. Total release Ci N/A N/A N/A 2. Average release rate for period pCi/sec N/A N/A 3. Percent of applicable limit % MPC N/A N/A 4. Percent Effluent Concentration Limit % ECL N/A N/A B. Iodines 1. Total iodine-131 Ci N/A N/A N/A 2. Average release rate for period pCi/sec N/A N/A 3. Percent of applicable limit % MPC N/A N/A 4. Percent Effluent Concentration Limit % ECL N/A N/A C. Particulates | .......... 17 | ||
: 1. Particulates with half-lives | .......... 23 | ||
>8 days Ci <LLD 4.45E-7 1.60E+1 2. Average release rate for period uCi/sec O.OOE+O 5.66E-8 3. Percent of applicable limit % MPC O.OOE+O 1.47E-7 4. Percent Effluent Concentration Limit % ECL O.OOE+O 3.68E-7 5. Gross alpha activity Ci <LLD <LLD 5.OOE+1 D. Tritium 1. Total release Ci <LLD <LLD 2.50E+1 2. Average release rate for period lCi/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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | .......... 25 | ||
1 TABLE 1A (Continued) | .......... 26 | ||
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Estimated Fourth Total Quarter Error., %A. Fission and activation gases 1. Tot~al release Ci N/A N/A N/A 2. Average release rate for period pCi/sec N/A N/A 3. Percent of applicable limit % MPC N/A N/A 4. Percent Effluent Concentration Limit % ECL N/A N/A B. Iodines 1. To-:al iodine-131 Ci N/A N/A N/A 2. Average release rate for period pCi/sec N/A N/A 3. Percent of applicable limit % MPC N/A N/A 4. Percent Effluent Concentration Limit % ECL N/A N/A | .......... 30 | ||
: 1. Pa-ticulates with half-lives | .......... 33 | ||
>8 days Ci <LLD <LLD 1.60[:÷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 5. Gross alpha activity Ci <LLD <LLD 5.OOE+1 D. Tritium 1. Total release Ci <LLD <LLD 2.501E+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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | .......... 35 | ||
1 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE 1 First j Second l Third Fourth Radionuclides Released Unit Quarter l Quarter Quarter Quarter 1. Fission and activation gases krypton-85 Ci N/A N/A N/A N/A krypton-85m Ci N/A N/A N/A N/A krypton-87 Ci N/A N/A N/A N/A krypton-88 Ci N/A N/A N/A N/A xenon-133 Ci N/A N/A N/A N/A xenon-133m Ci N/A N/A N/A N/A xenon-135 Ci N/A N/A N/A N/A xenon-135m Ci N/A N/A N/A N/A xenon-138 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A 2. Iodines iodine-131 Ci N/A N/A N/A N/A iodine-133 Ci N/A N/A N/A N/A iodine-135 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A 3. Particulates barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci <LLD 4.45E-7 <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD 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.NOTE: Due to the permanent shutdown longer conducted. | .......... 38 L | ||
of S.O.N.G.S. | J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS K - MISCELLANEOUS................. | ||
1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | L - S.O.N.G.S. 1 CONCLUSIONS........... | ||
1 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (Ci/cc)1. Fission and activation gases | -_ I- | ||
S.O.N.G.S. | |||
1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE | 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 Generatinc 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 (2005) | |||
S.O.N.G.S. 1 SECTION B. GASEOUS EFFLUENTS Table IA, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous. effluents released quarterly in four categories: | |||
fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium. | |||
Listed for each of the four categories are: | |||
(1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total error As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, anc therefore are no longer measured. All the fuel is stored in the ISFSH and the plant is being demolished. | |||
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 errcor 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. As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, and therefore are no longer measured. All the fuel is stored in the ISFSI and the plant is being demolished. | |||
Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC for continuous mode releases only. | |||
Table IE, "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 (2005) | |||
S.O.N.G.S. 1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1 | |||
Estimated First Second Total Quarter Quarter Error, % | |||
A. Fission and activation gases | |||
: 1. Total release Ci N/A N/A N/A | |||
: 2. Average release rate for period pCi/sec N/A N/A | |||
: 3. Percent of applicable limit | |||
% MPC N/A N/A | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL N/A N/A B. Iodines | |||
: 1. Total iodine-131 Ci N/A N/A N/A | |||
: 2. Average release rate for period pCi/sec N/A N/A | |||
: 3. Percent of applicable limit | |||
% MPC N/A N/A | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL N/A N/A C. Particulates | |||
: 1. Particulates with half-lives >8 days Ci | |||
<LLD 4.45E-7 1.60E+1 | |||
: 2. Average release rate for period uCi/sec O.OOE+O 5.66E-8 | |||
: 3. Percent of applicable limit | |||
% MPC O.OOE+O 1.47E-7 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL O.OOE+O 3.68E-7 | |||
: 5. Gross alpha activity Ci | |||
<LLD | |||
<LLD 5.OOE+1 D. Tritium | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 2.50E+1 | |||
: 2. Average release rate for period lCi/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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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. Tot~al release Ci N/A N/A N/A | |||
: 2. Average release rate for period pCi/sec N/A N/A | |||
: 3. Percent of applicable limit | |||
% MPC N/A N/A | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL N/A N/A B. Iodines | |||
: 1. To-:al iodine-131 Ci N/A N/A N/A | |||
: 2. | |||
Average release rate for period pCi/sec N/A N/A | |||
: 3. | |||
Percent of applicable limit | |||
% MPC N/A N/A | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL N/A N/A C. Particulates | |||
: 1. Pa-ticulates with half-lives >8 days Ci | |||
<LLD | |||
<LLD 1.60[:÷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 | |||
: 5. | |||
Gross alpha activity Ci | |||
<LLD | |||
<LLD 5.OOE+1 D. Tritium | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 2.501E+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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE 1 | |||
First j Second l Third Fourth Radionuclides Released Unit Quarter l Quarter Quarter Quarter | |||
: 1. Fission and activation gases krypton-85 Ci N/A N/A N/A N/A krypton-85m Ci N/A N/A N/A N/A krypton-87 Ci N/A N/A N/A N/A krypton-88 Ci N/A N/A N/A N/A xenon-133 Ci N/A N/A N/A N/A xenon-133m Ci N/A N/A N/A N/A xenon-135 Ci N/A N/A N/A N/A xenon-135m Ci N/A N/A N/A N/A xenon-138 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A | |||
: 2. Iodines iodine-131 Ci N/A N/A N/A N/A iodine-133 Ci N/A N/A N/A N/A iodine-135 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A | |||
: 3. Particulates barium-140 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cerium-141 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cerium-144 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cesium-134 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cesium-137 Ci | |||
<LLD 4.45E-7 | |||
<LLD | |||
<LLD cobalt-58 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD 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. | |||
NOTE: | |||
Due to the permanent shutdown longer conducted. | |||
of S.O.N.G.S. 1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (Ci/cc) | |||
: 1. Fission and activation gases kryptl)n-85 N/A krypton-85m N/A krypton-87 N/A krypton-88 N/A xenon-133 N/A xenon.-133m N/A xenon.-135 N/A xenon-135m N/A xenon -138 N/A | |||
: 2. Iodines iodine-131 N/A iodine-133 N/A jodi ne-135 N/A | |||
: 3. Particulates bariuin-140 4.30E-13 ceriuin-141 5.50E-14 ceriumn-144 2.20E-13 cesiuin-134 1.20E-13 cesiuin-137 1.OOE-13 cobalt-58 1.10E-13 cobalt-60 1.70E-13 iron-59 2.70E-13 lanthanum-140 8.50E-13 mangaliese-54 1.10E-13 molybdenum-99 6.50E-14 strontium-89 1.OOE-11 strontium-90 1.OOE-11 zinc-55 2.90E-13 | |||
: 4. alpha 1.OOE-11 | |||
: 5. tritiim 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 (2005) | |||
S.O.N.G.S. 1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY l First l Second Third l Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas | |||
: 1. Gamma Air Dose mrad N/A N/A N/A N/A | |||
: 2. Percent Applicable Limit N/A N/A N/A N/A | |||
: 3. Beta Air Dose mrad N/A N/A N/A N/A | |||
: 4. Percent Applicable Limit N/A N/A N/A N/A B. Tritium, Iodine, Particulates (at the nearest receptor) | |||
: 1. | |||
Organ Dose mrem O.OOE+O 4.80E-6 O.OOE+O O.OOE+O | |||
: 2. | |||
Percent Applicable Limit O.OOE+O 6.40E-5 O.OOE+O O.OOE+O NOTE: | |||
Calculations performed in accordance with the ODCM utilizing the historical X/Q. | |||
TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE | |||
==SUMMARY== | ==SUMMARY== | ||
NOTE: Due to the permanent shutdown of S.O.N.G.S. | 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 (2005)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
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: | 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 As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, and therefore are no longer measured. | fission and activation products, tritium, and dissolved and entrained gases. | ||
All the fuel is stored in the ISFSI and the plant is being demolished. | Listed for each of the three categories are: | ||
The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report.Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category. | (1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists: | ||
The total radioactivity of each radionuclije released is listed for each quarterly period by both "continuous" and"batch" modes of release. As of the fourth quarter of 2004, the noble gas and icdine source terms no longer exist, and therefore are no longer measured. | (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution) | ||
All the fuel is stored in the ISFSI and the plant is being demolished. | (3) the volume of dilution water As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, and therefore are no longer measured. All the fuel is stored in the ISFSI and the plant is being demolished. | ||
As of the third quarter 2005 there are no longer batch releases being conducted due to the demolition of the liquid radwaste system.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. | The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category. The total radioactivity of each radionuclije released is listed for each quarterly period by both "continuous" and "batch" modes of release. As of the fourth quarter of 2004, the noble gas and icdine source terms no longer exist, and therefore are no longer measured. All the fuel is stored in the ISFSI and the plant is being demolished. As of the third quarter 2005 there are no longer batch releases being conducted due to the demolition of the liquid radwaste system. | ||
1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter Estimated Second Total Quarter Error, % | Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. | ||
: 1. Total release Ci <LLD 5.16E-5 5.0OE+1 E. Volume of waste released (batch &continuous, prior to dilution) liters 2.16E+7 1.30E+6 5.00E+O F. Volume of dilution water used during period liters 4.01E+9 3.17E+12 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period. | ||
1 TABLE 2A (Continued) | Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Unit 1. | ||
LIQUID EFFLUENTS-SUMMATION OF ALL | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
: 1. Total release Ci <LLD <LLD 5.OOE--+1 E. Volume of waste released (batch &continuous, prior to dilution) liters 5.50E+7 2.02E+8 5.OOl+O F. Volume of dilution water used during period liters 2.51E+9 1.05E+9 5.00l+0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | S.O.N.G.S. 1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter Estimated Second Total Quarter Error, % | ||
1 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released I Unit I Quarter I 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 5.03E-6 cesium-137 Ci <LLD 6.70E-6 9.60E-7 9.44E-4 chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD 2.06E-5 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 6.70E-6 9.60E-7 9.70E-4 2. Dissolved and entrained gases xenon-133 Ci N/A N/A N/A N/A xenon-135 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A LLD Lower Limit of Detection; see Table 2C. | .5 | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | _3 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 bariumn-140 Ci <LLD <LLD N/A N/A cerium-141 Ci <LLD <LLD N/A N/A cerium-144 Ci <LLD <LLD N/A N/A cesiuin-134 Ci 4.72E-5 5.74E-5 N/A N/A cesiumn-137 Ci 4.32E-3 1.96E-3 N/A N/A chromium-51 Ci <LLD <LLD N/A N/A cobalt-58 Ci <LLD <LLD N/A N/A cobalt-60 Ci 1.68E-3 4.02E-3 N/A N/A iodine-131 Ci <LLD <LLD N/A N/A iron-55 Ci <LLD 8.28E-4 N/A N/A iron-!59 Ci <LLD <LLD N/A N/A lanthanum-140 Ci <LLD <LLD N/A N/A manganese-54 Ci <LLD <LLD N/A N/A molybdenum-99 Ci <LLD <LLD N/A N/A niobium-95 Ci <LLD <LLD N/A N/A strontium-89 Ci <LLD 1.32E-5 N/A N/A stron ium-90 Ci 4.34E-5 1.56E-5 N/A N/A technietium-99m Ci <LLD <LLD N/A N/A zinc-l;5 Ci <LLD <LLD N/A N/A zirconium-95 Ci <LLD <LLD N/A N/A Total for period Ci 6.09E-3 6.90E-3 N/A N/A 2. Dissolved and entrained gases xenon.-133 Ci N/A N/A J N/A N/A xenon.-135 Ci N/A N/A N/A N/A Total for period Ci N/A N N/A l N/A l N/A =N/A No releases conducted LLD Lower Limit of Detection; see Table 2C. | Ci 6.09E-3 6.91E-3 1.90E+1 | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 2. Average diluted concentration during period yCi/ml 1.52E-9 2.18E-12 | ||
1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides l LLD (pCi/cc)1. Fission and activation products barium-140 2.90E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 7.50E-8 cesium-137 6.40E-8 chromium-51 3.30E-7 cobalt-58 6.80E-8 cobalt-60 1.OOE-7 iodine-131 5.70E-8 iron-55 1.OOE-6 iron-59 1.60E-7 lanthanum-140 5.60E-7 manganese-54 6.70E-8 molybdenum-99 5.60E-8 niobium-95 6.80E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.70E-7 zirconium-95 1.20E-7 2. Dissolved and entrained gases xenon-133 N/A xenon-135 N/A 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 3. Percent of applicable limit | ||
1 TABLE 2C (Continued) | % MPC 1.05E-2 9.36E-6 | ||
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides LLD (Ci/cc)1. Fission and activation products bariuri-140 2.40E-7 ceri uri-141 4.OOE-8 ceriuri-144 1.70E-7 chrom um-51 3.OOE-7 cobalt -58 6.60E-8 iodine-131 4.30E-8 iron-55 1.OOE-6 iron-59 1.50E-7 lanthanum-140 1 .80E-7 manganese-54 6.70E-8 molybdenum-99 2.70E-8 niobium-95 6.40E-8 stront:ium-89 5.OOE-8 technetium-99m 2.70E-8 zinc-65 1.70E-7 zirconium-95 1.10E-7 2. Disso'ved and entrained gases xenon-*133 N/A xenon*-135 N/A 3. gross alpha 1.00E-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 4. | ||
1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A..A . | Percent Effluent Concentration Limit | ||
* ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | % ECL 1.25E-1 1.08E-4 B. Tritium | ||
1 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE | : 1. Total release Ci 1.93E+1 4.74E-1 1.90E+1 | ||
: 2. Average diluted concentration during period yCi/ml 4.81E-6 1.50E-10 | |||
: 3. Percent of applicable limit | |||
% MPG 1.60E-1 4.99E-6 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL 4.81E-1 1.50E-5 C. Dissolved and entrained gases | |||
: 1. Total release Ci N/A N/A N/A | |||
: 2. Average diluted concentration during period pCi/ml N/A N/A | |||
: 3. | |||
Percent of applicable limit | |||
% MPC N/A N/A | |||
: 4. Percent Effluent Concentration Limit | |||
% MPC N/A N/A D. Gross alpha radioactivity | |||
: 1. Total release Ci | |||
<LLD 5.16E-5 5.0OE+1 E. Volume of waste released (batch & | |||
continuous, prior to dilution) liters 2.16E+7 1.30E+6 5.00E+O F. Volume of dilution water used during period liters 4.01E+9 3.17E+12 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 TABLE 2A (Continued) | |||
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES l | |||
Estimated Third Fourth Total Unit Quarter Quarter Error, % | |||
A. Fissicn and activation products | |||
: 1. Total release (not including tritium, gases, alpha) | |||
Ci 9.60E-7 9.70E-4 1.90E+1 | |||
: 2. Average diluted concentration during period pCi/ml 3.83E-13 9.21E-10 | |||
: 3. Percent of applicable limit | |||
% MPC 1.91E-6 4.60E-3 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 3.83E-5 9.08E-2 B. Tritium | |||
: 1. Total release Ci 1.80E-3 1.35E+D 1.90E+1 | |||
: 2. Average diluted concentration during period pCi/ml 7.18E-10 1.28E-6 | |||
: 3. Percent of applicable limit | |||
% MPC 2.39E-5 1.22E-1 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 7.18E-5 1.28E-1 C. Dissolved and entrained gases | |||
: 1. Total release Ci N/A N/A N/p | |||
: 2. Average diluted concentration during period pCi/ml N/A N/A | |||
: 3. Percent of applicable limit | |||
% MPC N/A N/A | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL N/A N/A D. Gross alpha radioactivity | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 5.OOE--+1 E. Volume of waste released (batch & | |||
continuous, prior to dilution) liters 5.50E+7 2.02E+8 5.OOl+O F. Volume of dilution water used during period liters 2.51E+9 1.05E+9 5.00l+0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released I Unit I Quarter I 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 5.03E-6 cesium-137 Ci | |||
<LLD 6.70E-6 9.60E-7 9.44E-4 chromium-51 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cobalt-58 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cobalt-60 Ci | |||
<LLD | |||
<LLD | |||
<LLD 2.06E-5 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 6.70E-6 9.60E-7 9.70E-4 | |||
: 2. Dissolved and entrained gases xenon-133 Ci N/A N/A N/A N/A xenon-135 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A LLD Lower Limit of Detection; see Table 2C. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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 bariumn-140 Ci | |||
<LLD | |||
<LLD N/A N/A cerium-141 Ci | |||
<LLD | |||
<LLD N/A N/A cerium-144 Ci | |||
<LLD | |||
<LLD N/A N/A cesiuin-134 Ci 4.72E-5 5.74E-5 N/A N/A cesiumn-137 Ci 4.32E-3 1.96E-3 N/A N/A chromium-51 Ci | |||
<LLD | |||
<LLD N/A N/A cobalt-58 Ci | |||
<LLD | |||
<LLD N/A N/A cobalt-60 Ci 1.68E-3 4.02E-3 N/A N/A iodine-131 Ci | |||
<LLD | |||
<LLD N/A N/A iron-55 Ci | |||
<LLD 8.28E-4 N/A N/A iron-!59 Ci | |||
<LLD | |||
<LLD N/A N/A lanthanum-140 Ci | |||
<LLD | |||
<LLD N/A N/A manganese-54 Ci | |||
<LLD | |||
<LLD N/A N/A molybdenum-99 Ci | |||
<LLD | |||
<LLD N/A N/A niobium-95 Ci | |||
<LLD | |||
<LLD N/A N/A strontium-89 Ci | |||
<LLD 1.32E-5 N/A N/A stron ium-90 Ci 4.34E-5 1.56E-5 N/A N/A technietium-99m Ci | |||
<LLD | |||
<LLD N/A N/A zinc-l;5 Ci | |||
<LLD | |||
<LLD N/A N/A zirconium-95 Ci | |||
<LLD | |||
<LLD N/A N/A Total for period Ci 6.09E-3 6.90E-3 N/A N/A | |||
: 2. Dissolved and entrained gases xenon.-133 Ci N/A N/A J | |||
N/A N/A xenon.-135 Ci N/A N/A N/A N/A Total for period Ci N/A N | |||
N/A l | |||
N/A l | |||
N/A = | |||
N/A No releases conducted LLD Lower Limit of Detection; see Table 2C. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides l | |||
LLD (pCi/cc) | |||
: 1. Fission and activation products barium-140 2.90E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 7.50E-8 cesium-137 6.40E-8 chromium-51 3.30E-7 cobalt-58 6.80E-8 cobalt-60 1.OOE-7 iodine-131 5.70E-8 iron-55 1.OOE-6 iron-59 1.60E-7 lanthanum-140 5.60E-7 manganese-54 6.70E-8 molybdenum-99 5.60E-8 niobium-95 6.80E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.70E-7 zirconium-95 1.20E-7 | |||
: 2. Dissolved and entrained gases xenon-133 N/A xenon-135 N/A | |||
: 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 TABLE 2C (Continued) | |||
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides LLD (Ci/cc) | |||
: 1. Fission and activation products bariuri-140 2.40E-7 ceri uri-141 4.OOE-8 ceriuri-144 1.70E-7 chrom um-51 3.OOE-7 cobalt -58 6.60E-8 iodine-131 4.30E-8 iron-55 1.OOE-6 iron-59 1.50E-7 lanthanum-140 1.80E-7 manganese-54 6.70E-8 molybdenum-99 2.70E-8 niobium-95 6.40E-8 stront:ium-89 5.OOE-8 technetium-99m 2.70E-8 zinc-65 1.70E-7 zirconium-95 1.10E-7 | |||
: 2. Disso'ved and entrained gases xenon-*133 N/A xenon*-135 N/A | |||
: 3. gross alpha 1.00E-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A.. | |||
A. | |||
: 1. Total body dose mrem 1.61E-2 1.31E-2 7.08E-6 3.09E-3 | |||
: 2. Percent Applicable Limit 1.07E+O 8.71E-1 4.72E-4 2.06E-1 B. | |||
: 1. Limiting organ dose mrem 2.11E-2 4.95E-2 1.06E-5 4.52E-3 | |||
: 2. Percent Applicable Limit 4.23E-1 9.89E-1 2.12E-4 9.05E-2 | |||
: 3. Limiting organ for period GI-LLI GI-LLI Liver Liver | |||
* ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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 | ||
9 releases 2. Total time period for batch releases: | : 1. Number of batch releases: | ||
12875 minutes 3. Maximum time period for a batch release: 1722 minutes 4. Average time period for a batch release: 1431 minutes 5. Minimum time period for a batch release: 990 minutes 6. Average saltwater flow during batch releases: | 9 releases | ||
13222 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 2. Total time period for batch releases: | ||
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)12 month Estimated total 1. Type of waste Unit period error (%)a. Spent resins, filter sludges, | 12875 minutes | ||
* Ci 2.59E+2 3.0OE+1 b. Dry active waste (DAW), | : 3. | ||
m 3 | Maximum time period for a batch release: | ||
1722 minutes | |||
: 4. Average time period for a batch release: | |||
1431 minutes | |||
: 5. Minimum time period for a batch release: | |||
990 minutes | |||
: 6. Average saltwater flow during batch releases: | |||
13222 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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) 12 month Estimated total | |||
: 1. Type of waste Unit period error (%) | |||
: a. Spent resins, filter sludges, m3 1.13E+1 evaporator bottoms | |||
* Ci 2.59E+2 3.0OE+1 | |||
: b. Dry active waste (DAW), | |||
m3 3.58E+3 compactable and non-compactable (incl. demolition rubble) ** | |||
Ci 3.68E+O 3.OOE+1 | |||
: c. Irradiated components m3 2.06E+1 (Structural members & reactor piping) ** | |||
Ci 1.05E+2 3.0OE+1 | |||
: d. Other: (Mechanical filters)# | |||
m 3 | |||
1.45E+O Ci 1.90E+O 3.0OE+1 NOTE: Total curie content estimated. | |||
Material packaged in Type A or Type B casks. | |||
Material packaged in various General Design, IP-1, USA DOT 7A Type A, or Type A packagings. | |||
Material packaged in General Design Packaging. | Material packaged in General Design Packaging. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
S.O.N.G.S. 1 | |||
: 2. Estimate of major nuclide composition (by type of waste) | |||
: a. | |||
americium-241 2.97E-3 carbon-14 6.88E-3 cerium-144 8.43E-2 cesium-134 2.04E+O cesium-137 8.70E+1 cobalt-60 3.78E+O curium-242 1.33E-5 curium-243/244 1.09E-3 iron-55 1.65E-1 nickel-59 5.69E-2 nickel-63 6.28E+O niobium-94 9.16E-3 plutonium-238 | |||
__2.83E-3 plutonium-239/240 1.04E-3 p1 utonium-241 5.97E-2 plutonium-242 3.49E-5 strontium-89 1.22E-2 strontium-90 3.11E-1 technetium-99 1.76E-2 tritium 2.87E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 | |||
__2.83E-3 plutonium-239/240 | : 2. Estimate of major nuclide composition (by type of waste) | ||
: b. | |||
americium-241 3.64E-2 antimony-125 9.22E-4 carbon-14 | |||
_2.16E+O cerium-144 5.44E-1 cesium-134 2.73E+O cesium-137 | |||
__3.87E+l cobalt-57 8.71E-7 cobalt-60 2.03E+1 curium-242 2.50E-4 curium-243/244 1.16E-2 europium-155 | |||
__7.09E-5 iron-55 1.72E+1 manganese-54 3.12E-5 nickel-59 1.86E-2 nickel-63 | |||
__1.79E+1 niobium-94 4.68E-3 niobium-95 5.70E-2 plutonium-238 6.66E-3 plutonium-239/240 2.75E-3 plutonium-241 1.74E-1 ruthenium-106 1.27E-4 silver-llOm 6.92E-2 strontium-90 1.55E-1 tritium 4.78E-1 zirconium-95 6.37E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 | |||
: 2. Estimate of major nuclide composition (by type of waste) | |||
: c. | |||
americium-241 1.35E-2 carbon-14 3.85E-2 cerium-144 7.71E-2 cesium-137 3.03E-2 cobalt-58 6.86E-2 cobalt-60 3.32E+1 curi um-242 2.12E-4 curium-243/244 6.79E-3 iodine-129 2.22E-4 iron-55 5.22E+1 manganese-54 3.15E-2 nickel-59 1.76E-1 nickel-63 1.33E+1 niobium-94 2.61E-4 p1 utonium-238 2.12E-2 plutonium-239/240 7.30E-3 plutonium-241 5.39E-1 strontium-90 2.39E-2 technetium-99 6.73E-4 tritium 4.09E-4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
__3.87E+l cobalt-57 | S.O.N.G.S. 1 | ||
: 2. Estimate of major nuclide composition (by type of waste) | |||
: d. | |||
americium-241 7.32E-2 carbon-14 1.08E+O cerium-144 3.27E-2 cesium-134 5.37E+O cesium-137 2.97E+1 cobalt-57 1.70E-3 cobalt-58 5.08E-2 cobalt-60 2.14E+1 curium-242 4.83E-4 curium-243/244 2.29E-2 europium-154 3.65E-2 iron-55 1.59E+1 manganese-54 1.65E-2 ni ckel-59 1.04E-1 nickel-63 2.47E+1 niobium-94 3.31E-2 plutonium-238 4.88E-2 plutonium-239/240 2.05E-2 plutonium-241 9.89E-1 strontium-89 5.26E-3 strontium-90 7.74E-2 technetium-99 | |||
__2.56E-3 tritium 1.46E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
__7.09E-5 iron-55 | S.O.N.G.S. 1 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) | ||
: 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 4 | |||
Hittman and TAG Transport Barnwell, SC Truck 149 Piazza and TAG Transport Envirocare, UT Truck 85 MHF Logistical Solutions Envirocare, UT Rail 2 | |||
__1.79E+1 niobium-94 4.68E-3 niobium-95 5.70E-2 plutonium-238 6.66E-3 plutonium-239/240 | * TAG Transport Duratek/Envirocare, UT Truck SONCS maintains a contract with Duratek that provides volume reduction services. | ||
The processed volume was shipped from the Duratek facility to EnviroCare using 8 shipments. Those 8 shipments included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments. | |||
__2.56E-3 tritium | |||
1 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 4 Hittman and TAG Transport Barnwell, SC Truck 149 Piazza and TAG Transport Envirocare, UT Truck 85 MHF Logistical Solutions Envirocare, UT Rail 2 | |||
* TAG Transport Duratek/Envirocare, UT Truck | |||
The processed volume was shipped from the Duratek facility to EnviroCare using 8 shipments. | |||
Those 8 shipments 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) | B. IRRADIATED FUEL SHIPMENTS (Disposition) | ||
ENumDer of Shipments l Mode of Transportation Destination None No shipments Were made N/A C. DEWATERING ENumter of Containers Solidification Agent 3 N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | ENumDer of Shipments l Mode of Transportation Destination None No shipments Were made N/A C. DEWATERING ENumter of Containers Solidification Agent 3 | ||
1 SECTION F. APPLICABLE LIMITS Gaseous Effluents | N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
-Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, C.3, and D.3 of Table 1A, was calculated using the following equation:* % Applicable Limit where: Rel Rate X/Q 0 MPCeff where: F,= (Rel Rate) (X/Q) (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, yCi/sec.= 1.30E-5 sec/ | S.O.N.G.S. 1 SECTION F. APPLICABLE LIMITS Gaseous Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, C.3, and D.3 of Table 1A, was calculated using the following equation: | ||
= Maximum Permissible Concentration (MPC) of the ii" radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1. | * % Applicable Limit where: | ||
= Effluent Concentration Limit (ECL) of the ijh radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.where: F.n ECL, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Rel Rate X/Q 0 | ||
1 Liquid Effluents | MPCeff where: | ||
-Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, and C.3 of Table 2A, were calculated using the fcllowing equations: | F, | ||
= | |||
= Maximum Permissible Concentration (MPC) of the it' radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.= (Dil Conc) (100)ECLeff where: Dil Conc 0 ECLef= total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, pCi/ml.1 n Fi Ei 1=1 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, C T.= total number of radionuclides identified | (Rel Rate) (X/Q) (100) | ||
= Effluent Concentration Limit (ECL) of the it' radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.where: | MPCeff | ||
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 | 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. | ||
-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 | 1.30E-5 sec/M3; the annual average atmospheric dispersion defined in the Unit 1 ODCM. | ||
-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: 2+ 2 2 Total Error = G 2 + 3 + + ... a where: Gi = Error associated with each component. | 1 | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | _n Fi i.1 MPC | ||
1 SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual. | = | ||
fractional abundance of the ijt radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, C T. | |||
n | |||
= | |||
total number of radionuclides identified | |||
= | |||
Maximum Permissible Concentration (MPC) of the ii" radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1. | |||
MPC1 | |||
% ECL | |||
= | |||
(Rel Rate) (X/Q) (100) | |||
ECLeff 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, pCi/sec. | |||
= | |||
1.30E-5 sec/m3; the annual average atmospheric dispersion defined in the Unit 1 ODCM. | |||
1 | |||
=n Fi EI 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, C T. | |||
= | |||
total number of radionuclides identified | |||
= | |||
Effluent Concentration Limit (ECL) of the ijh radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1. | |||
where: | |||
F. | |||
n | |||
: ECL, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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 fcllowing 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, yCi/ml. | |||
1 o | |||
MPCet E | |||
F1 i-1 MPC where: | |||
Fj n | |||
: MPC, | |||
% ECL | |||
= | |||
fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, C T. | |||
= | |||
total number of radionuclides identified | |||
= | |||
Maximum Permissible Concentration (MPC) of the it' radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2. | |||
= | |||
(Dil Conc) (100) | |||
ECLeff where: | |||
Dil Conc 0 | |||
ECLef | |||
= | |||
total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, pCi/ml. | |||
1 n | |||
Fi Ei 1=1 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, C T. | |||
= | |||
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. | |||
where: | |||
F1 n | |||
: ECL, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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: | |||
2+ | |||
2 2 | |||
Total Error | |||
= | |||
G 2 | |||
+ | |||
3 | |||
+ | |||
+... a where: | |||
Gi | |||
= | |||
Error associated with each component. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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)(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 RETDAS (Radioactive Effluent Tracking and Dose Assessment Software), Regulatory Guide 1.109 methodology, and concurrent meteorology. | (4) | ||
Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using me:hods 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 I-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 Figure 6-1. | 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 (2005)S.O.N.G.S. | Categories 3, 4, and 5 were calculated utilizing RETDAS (Radioactive Effluent Tracking and Dose Assessment Software), | ||
1 TABLE 1 Dose * (millirems) | 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 me:hods 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 in Table 1. | |||
presents the percent of Applicable Limits for each dose presented | |||
' ODCM Figure 6-1. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 TABLE 1 Dose * (millirems) | |||
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS | First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS | ||
: 1) 2) 3) 4) 5)Whole Body 1.61E-2 1.31E-2 7.08E-6 3.09E-3 3.22E-2 6) 7) 8) 9) 10)Organ 2.11E-2 4.95E-2 1.06E-5 4.52E-3 7.12E-2 AIRBORNE EFFLUENTS | : 1) | ||
: 11) 12) 13) 14) 15)Tritium, Iodines, and Particulates O.OOE+O 2.22E-5 O.OOE+O O.OOE+O 2.22E-5 NOBLE GASES 16) 17) 18) 19) 20)Gamma N/A N/A N/A N/A N/A 21) 22) 23) 24) 25)Beta N/A N/A N/A N/A N/A 26) 27) 28) 29) 30)DIRECT RADIATION 1.65E-1 1.68E-1 1.49E-1 1.62E-1 6.12E-1 | : 2) | ||
including the 1.2.3.4.5 .This This This This This value was value was value was value was value was calculated calculated calculated calculated calculated using using using using using the methodology the methodology the methodology the methodology the methodology of the of the of the of the of the ODCM.ODCM.ODCM.ODCM.ODCM. | : 3) | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 4) 5) | ||
Whole Body 1.61E-2 1.31E-2 7.08E-6 3.09E-3 3.22E-2 | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 6) | ||
: 7) | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 8) | ||
1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 25, 2005, Revision 23 to the Unit 1 Offsite Dose Calculation Manual (OD)CM)was adopted and published. | : 9) 10) | ||
This revision incorporated | Organ 2.11E-2 4.95E-2 1.06E-5 4.52E-3 7.12E-2 AIRBORNE EFFLUENTS | ||
: 11) | |||
To support the demolition of the LRTS, notes were added in this revision to detail radwaste system specifications that are no longer applicable and instruments that are no longer required once systems were removed from service. Since the monitor was removed, requirements for surveillances and periodic maintenance were also removed. An EOE evaluation was performed for item 2.The additic'nal dilution flow pumps added in revision 22 originally were believed to have a capacity of 6,000 gpm each. In reality, the pumps are designed at approximately 5,000 gpm.Per NRC Generic Letter 89-01, no Effluent/ODCM Evaluation or 50.59 reviews wvere required or performed for editorial changes. The minor REMP sampling location change is administered by that program.None of the changes impact the accuracy or reliability of the effluent dose or setpoint calculations. | : 12) | ||
The level of radioactive effluent control required by | : 13) | ||
Throughout the document, change bars are marked in one of four ways as follows: A Addition D Deletion F Editorial/Format change R Revision Change Reason Revised to reflect removed sections D Renoved reference to dissolved or entrained gases D Renoved reference to dissolved or entrained gases and 1-131. D Renoved note (g) which dealt with dissolved or entrained gases D Added note detailing specification 1.3.1.A to no longer be applicable once the LRTS A is isolated for demolition. | : 14) 15) | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Tritium, Iodines, and Particulates O.OOE+O 2.22E-5 O.OOE+O O.OOE+O 2.22E-5 NOBLE GASES | ||
1 1-11 Corrected dilution flowrate 1-12 Added note detailing specification 1.4.1 to no longer be applicable once the LRTS is isolated for demolition. | : 16) | ||
Removed Xe-133 from setpoint equation.1-13 Removed reference to dissolved or entrained gases 1-14 Corrected dilution flowrate and removed Xe-133 from equation.2-1 Removed applicable parts of specification 2.1.1.A.1. | : 17) | ||
2-2 Removed applicable parts of specification 2.1.2.A.2-3 Removed gas grab sample and continuous noble gas monitoring for R-1254.2-4 Removed noble gases from note b.2-5 Removed note f. Modified note C to reflect no fuel in SFP.2-6 Removed specification 2.2.1.,2-7 Removed specification 2.2.2.2-10 Removed specification 2.5.1 on noble gas setpoints. | : 18) | ||
: 19) 20) | |||
Gamma N/A N/A N/A N/A N/A | |||
: 21) | |||
: 22) | |||
: 23) | |||
: 24) 25) | |||
Beta N/A N/A N/A N/A N/A | |||
: 26) | |||
: 27) | |||
: 28) | |||
: 29) 30) | |||
DIRECT RADIATION 1.65E-1 1.68E-1 1.49E-1 1.62E-1 6.12E-1 The numbered footnotes below briefly explain how each maximum dose was calculated, organ and the predominant pathway(s). | |||
including the 1. | |||
2. | |||
3. | |||
4. | |||
5. | |||
This This This This This value was value was value was value was value was calculated calculated calculated calculated calculated using using using using using the methodology the methodology the methodology the methodology the methodology of the of the of the of the of the ODCM. | |||
ODCM. | |||
ODCM. | |||
ODCM. | |||
ODCM. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 | |||
: 6. This value was calculated using the methodology of the ODCM; the GI-ILI received the maximum dose primarily by the saltwater fish pathway. | |||
: 7. This value was calculated using the methodology of the ODCM; the GI-ILI received the maximum dose primarily by the saltwater fish pathway. | |||
: 8. | |||
This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway. | |||
: 9. | |||
This value was calculated using the methodology of the ODCM; the liver 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. | |||
There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. | |||
: 12. | |||
The maximum organ dose was to the skin (all age groups) and was located in the NNE sector. | |||
This was calculated using the assumptions of USNRC Regulatory Guide 1.109. | |||
: 13. | |||
There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. | |||
: 14. | |||
There has no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem. | |||
: 15. | |||
The maximum organ dose was to the skin (all age groups) and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109. | |||
: 16. | |||
Noble Gas sampling no longer required. | |||
: 17. | |||
Noble Gas sampling no longer required. | |||
: 18. | |||
Noble Gas sampling no longer required. | |||
: 19. | |||
Noble Gas sampling no longer required. | |||
: 20. | |||
Noble Gas sampling no longer required. | |||
: 21. | |||
Noble Gas sampling no longer required. | |||
: 22. | |||
Noble Gas sampling no longer required. | |||
: 23. | |||
Noble Gas sampling no longer required. | |||
: 24. | |||
Noble Gas sampling no longer required. | |||
: 25. | |||
Noble Gas sampling no longer required. | |||
: 26. | |||
Measureinents 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 WSW sector. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 | |||
: 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 S 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 1.07E+O 8.71E-1 4.72E-4 2.06E-1 1.07E+O Organ 4.23E-1 9.89E-1 2.12E-4 9.05E-2 7.12E-1 AIRBORNE EFFLUENTS Tritium, Iodines, and O.OOE+O 2.95E-4 O.OOE+O O.OOE+O 1.48E-4 Particulates NOBLE GASES Gamma N/A N/A N/A N/A N/A Beta N/A N/A N/A N/A N/A NOTE:Direct Radiation is not specifically addressed in the Applicable Limits. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 25, 2005, Revision 23 to the Unit 1 Offsite Dose Calculation Manual (OD)CM) was adopted and published. | |||
This revision incorporated 1) Removal of all the "notes" and applicable sections from rev 22 regarding the completion of fuel transfer to the ISFSI, 2) Addition of notes supporting the planned demolition of the liquid radwaste treatment system, 3) Updates related to the 2003-2004 Land Use Census, 4) Corrected dilution flowrate values, and 5) A minor change to a REMP sampling location. | |||
A major milestone in the Unit 1 demolition plan, that of storing the last fuel cannister in the ISFSI, was accomplished in August 2004. Revision 22 was issued in advance to support that event. Several notes (dissolved/entrained gases and R-1254 setpoint) added in revision 22 were removed to reflect the completed event. | |||
The liquid radwaste treatment system (LRTS) was drained and isolated in 2005 and is currently being demolished. To support the demolition of the LRTS, notes were added in this revision to detail radwaste system specifications that are no longer applicable and instruments that are no longer required once systems were removed from service. Since the monitor was removed, requirements for surveillances and periodic maintenance were also removed. An EOE evaluation was performed for item 2. | |||
The additic'nal dilution flow pumps added in revision 22 originally were believed to have a capacity of 6,000 gpm each. In reality, the pumps are designed at approximately 5,000 gpm. | |||
Per NRC Generic Letter 89-01, no Effluent/ODCM Evaluation or 50.59 reviews wvere required or performed for editorial changes. | |||
The minor REMP sampling location change is administered by that program. | |||
None of the changes impact the accuracy or reliability of the effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR2O, | |||
: 40CFR190, JOCFR50.36a, 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 Change Reason Revised to reflect removed sections D | |||
Renoved reference to dissolved or entrained gases D | |||
Renoved reference to dissolved or entrained gases and 1-131. | |||
D Renoved note (g) which dealt with dissolved or entrained gases D | |||
Added note detailing specification 1.3.1.A to no longer be applicable once the LRTS A | |||
is isolated for demolition. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 1-11 Corrected dilution flowrate 1-12 Added note detailing specification 1.4.1 to no longer be applicable once the LRTS is isolated for demolition. Removed Xe-133 from setpoint equation. | |||
1-13 Removed reference to dissolved or entrained gases 1-14 Corrected dilution flowrate and removed Xe-133 from equation. | |||
2-1 Removed applicable parts of specification 2.1.1.A.1. | |||
2-2 Removed applicable parts of specification 2.1.2.A. | |||
2-3 Removed gas grab sample and continuous noble gas monitoring for R-1254. | |||
2-4 Removed noble gases from note b. | |||
2-5 Removed note f. Modified note C to reflect no fuel in SFP. | |||
2-6 Removed specification 2.2.1. | |||
,2-7 Removed specification 2.2.2. | |||
2-10 Removed specification 2.5.1 on noble gas setpoints. | |||
2-11 Removed specification 2.5.1 (continued). | 2-11 Removed specification 2.5.1 (continued). | ||
2-12 Removed specification 2.5.1 (continued). | 2-12 Removed specification 2.5.1 (continued). | ||
2-13 Removed specification 2.6.1 on noble gas dose rate.2-15 Removed specification 2.7.1 on noble gas dose.2-21 Per the LUC, updated 4 controlling locations and several factors.2-22 Per the LUC, updated selected Ri values.2-23 Per the LUC, updated selected Ri values.2-24 Added entire page to reflect a new location.2-25 Per the LUC, updated selected Ri values.2-26 Per the LUC, updated selected Ri values.2-27 Modified page number to account for added page in sector Q.2-28 Per the LUC, updated selected Ri values.2-29 Per the LUC, updated selected Ri values.2-30 Per the LUC, updated selected Ri values.2-31 Per the LUC, updated all Ri values.2-32 Per the LUC, updated selected Ri values.2-33 Per the LUC, updated selected Ri values. | 2-13 Removed specification 2.6.1 on noble gas dose rate. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | 2-15 Removed specification 2.7.1 on noble gas dose. | ||
1 2-34 Per the LUC, updated selected Ri values.2-35 Per the LUC, updated selected Ri values.2-36 Per the LUC, updated selected Ri values.2-37 Per the LUC, updated selected Ri values.2-38 Per the LUC, updated selected Ri values.4-2 Added note supporting demolition of LRTS instrumentation. | 2-21 Per the LUC, updated 4 controlling locations and several factors. | ||
2-22 Per the LUC, updated selected Ri values. | |||
2-23 Per the LUC, updated selected Ri values. | |||
2-24 Added entire page to reflect a new location. | |||
2-25 Per the LUC, updated selected Ri values. | |||
2-26 Per the LUC, updated selected Ri values. | |||
2-27 Modified page number to account for added page in sector Q. | |||
2-28 Per the LUC, updated selected Ri values. | |||
2-29 Per the LUC, updated selected Ri values. | |||
2-30 Per the LUC, updated selected Ri values. | |||
2-31 Per the LUC, updated all Ri values. | |||
2-32 Per the LUC, updated selected Ri values. | |||
2-33 Per the LUC, updated selected Ri values. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 1 2-34 Per the LUC, updated selected Ri values. | |||
2-35 Per the LUC, updated selected Ri values. | |||
2-36 Per the LUC, updated selected Ri values. | |||
2-37 Per the LUC, updated selected Ri values. | |||
2-38 Per the LUC, updated selected Ri values. | |||
4-2 Added note supporting demolition of LRTS instrumentation. | |||
4-3 Modified Actions 16 and 20 to support demolition of LRTS instrumentation. | 4-3 Modified Actions 16 and 20 to support demolition of LRTS instrumentation. | ||
4-5 Added note 7 to support demolition of LRTS and instruments. | 4-5 Added note 7 to support demolition of LRTS and instruments. | ||
4-6 Added note 7 to support demolition of LRTS and instruments. | 4-6 Added note 7 to support demolition of LRTS and instruments. | ||
4-7 Renoved reference to R-1254 setpoints 4-8 Renoved reference to R-1254 gaseous channel.4-9 Renoved reference to R-1254 compensatory actions 4-10 Renoved reference to R-1254 setpoints and detector source check.4-11 Renoved reference to R-1254 and removed notes 5 and 7.5-1 Corrected referenced Table number 5-23 Modified control location for non-migratory marine animals 6-3 Renoved definitions for REM RAD and Sorrento monitors, neither of which exist any loiger at Unit 1.6-8 Molified reference from specific sections in the ODCM to the ODCM in general, to be consistent with Unit 2/3. | 4-7 Renoved reference to R-1254 setpoints 4-8 Renoved reference to R-1254 gaseous channel. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | 4-9 Renoved reference to R-1254 compensatory actions 4-10 Renoved reference to R-1254 setpoints and detector source check. | ||
1 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Demolition of Liquid Radwaste Treatment System On May 13, 2005, the Liquid Radwaste Treatment System (LRTS) was permanently removed from service. The sump pumps, piping and radiation monitoring system skid (RE-1218)were removed to support the demolition of the radwaste building. | 4-11 Renoved reference to R-1254 and removed notes 5 and 7. | ||
Unit 1 has reached the point in its decommissioning where systems and buildings are being physically removed.The LRTS was designed to collect drainage from primary side equipment leaks, the spent fuel pool and the RCS itself. It consisted of tanks, ion exchangers, filters and pumps used to process waste water to achieve 10CFR20 limits upon release. A radiation monitoring system was installed to satisfy the license and control releases from the system as an ODCM-credited release point.Removal of the LRTS involved de-energizing the equipment related to the liquid radwaste processing system, placing a flange on the discharge pipe downstream of the pumps (eliminating the discharge line to the unrestricted area) and then removing a section of pipe. Later plans call for the removal of all components and piping as well as filling with concrete the outfall conduit east of the tsunami gates. The plan is to section this contaminated equipment and ship offsite to a licensed burial facility. | 5-1 Corrected referenced Table number 5-23 Modified control location for non-migratory marine animals 6-3 Renoved definitions for REM RAD and Sorrento monitors, neither of which exist any loiger at Unit 1. | ||
As part of decommissioning, primary side systems were previously removed.The containment building internals were removed and disposed of as dry active waste (DAW).All of the piped sources of wastewater to the LRTS have been permanently drained of water and all sources have been either permanently drained and isolated or demolished to prevent any further water intrusion. | 6-8 Molified reference from specific sections in the ODCM to the ODCM in general, to be consistent with Unit 2/3. | ||
Once isolation of the LRTS was completed, approximately 26000 gallons of liquid waste were generated from draindown of the spent fuel pool, flushing of the ion exchangers, demineralizers, and spent resin tank, and cleanout of the holdup tanks. AR 060102024 details the disposal method and evaluation for this water.However, after the LRTS was drained and released, there was residual water in various low points in the piping. The small quantities of liquid wastes will be dispositioned during dismantlement of the LRTS itself. This water is included in the estimate of 2000 gallons per quarter from decontamination activities and is expected to trend downwards as the demolition of the facility continues. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
This waste water will include residual water in the piping and tanks as well as water used in the washing and decontamination of system component parts.The residual water has been and continues to be disposed of per the site program.The various methods to be used to dispose of this residual water may include: 1) lease or purchase a processing skid to reduce the water contamination levels, 2) contract with an offsite vendor to use their treatment equipment to perform the same function, or 3) process it locally and then release through a credited release point to the Unit 2 or Unit 3 outfall. Release of Unit 1 water to the Unit 2 or Unit 3 outfall required a change to the operating license(s). | S.O.N.G.S. 1 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Demolition of Liquid Radwaste Treatment System On May 13, 2005, the Liquid Radwaste Treatment System (LRTS) was permanently removed from service. The sump pumps, piping and radiation monitoring system skid (RE-1218) were removed to support the demolition of the radwaste building. Unit 1 has reached the point in its decommissioning where systems and buildings are being physically removed. | ||
AR 030300754 addresses the disposition of ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | The LRTS was designed to collect drainage from primary side equipment leaks, the spent fuel pool and the RCS itself. | ||
1 radioactive liquid wastes including wastes that would have been treated using the LRTS.The only remaining credited liquid release point at Unit 1 is the Yard Drain Sump.It is still receiving drains from the outside yard including rain runoff and dewatering from the demolition process.This change was reviewed and approved acceptable pursuant to Quality Assurance Program Description (SCE-1-A), subsection 17.2.20.3.1.i per ECP 041100584. | It consisted of tanks, ion exchangers, filters and pumps used to process waste water to achieve 10CFR20 limits upon release. A radiation monitoring system was installed to satisfy the license and control releases from the system as an ODCM-credited release point. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Removal of the LRTS involved de-energizing the equipment related to the liquid radwaste processing system, placing a flange on the discharge pipe downstream of the pumps (eliminating the discharge line to the unrestricted area) and then removing a section of pipe. | ||
1 SECTION K. MISCELLANEOUS | Later plans call for the removal of all components and piping as well as filling with concrete the outfall conduit east of the tsunami gates. The plan is to section this contaminated equipment and ship offsite to a licensed burial facility. As part of decommissioning, primary side systems were previously removed. | ||
The containment building internals were removed and disposed of as dry active waste (DAW). | |||
These events are documented in ARs 050100436, 050101565, 050401494 and 050600019. | All of the piped sources of wastewater to the LRTS have been permanently drained of water and all sources have been either permanently drained and isolated or demolished to prevent any further water intrusion. | ||
Estimated Estimated Estimated Start Stop Duration Activity Release Whole Body Organ Dose Date/Time Date/Time (min) (Ci/ml) (Curies) Dose (mrem) (mrem)01/09/05 8 1620 01/09/05 @ 1720 60 <MDA | Once isolation of the LRTS was completed, approximately 26000 gallons of liquid waste were generated from draindown of the spent fuel pool, flushing of the ion exchangers, demineralizers, and spent resin tank, and cleanout of the holdup tanks. AR 060102024 details the disposal method and evaluation for this water. | ||
* O.OOE+O O.OOE+O O.OOE+O 01/26/05 @ 1843 01/26/05 @ 1908 25 <MDA | However, after the LRTS was drained and released, there was residual water in various low points in the piping. The small quantities of liquid wastes will be dispositioned during dismantlement of the LRTS itself. This water is included in the estimate of 2000 gallons per quarter from decontamination activities and is expected to trend downwards as the demolition of the facility continues. This waste water will include residual water in the piping and tanks as well as water used in the washing and decontamination of system component parts. | ||
* O.OOE+O O.OOE+O O.OOE+O 01/26/05 @ 1938 01/26/05 @ 2035 57 <MDA | The residual water has been and continues to be disposed of per the site program. | ||
* O.OOE+O O.OOE+O O.OOE+O 02/21/05 @ 0153 02/21/05 @ 0210 17 <MDA | The various methods to be used to dispose of this residual water may include: 1) lease or purchase a processing skid to reduce the water contamination levels, 2) contract with an offsite vendor to use their treatment equipment to perform the same function, or 3) process it locally and then release through a credited release point to the Unit 2 or Unit 3 outfall. Release of Unit 1 water to the Unit 2 or Unit 3 outfall required a change to the operating license(s). | ||
* O.OOE+O O.OOE+O O.OOE+O 04/28/05 @ 0617 04/28/05 @ 0710 53 <MDA | AR 030300754 addresses the disposition of ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
* O.OOE+0 0.ODE+O O.OOE+O* MDA (Minimum Detectable Activity), 95% confidence level, a posteriori | S.O.N.G.S. 1 radioactive liquid wastes including wastes that would have been treated using the LRTS. | ||
The only remaining credited liquid release point at Unit 1 is the Yard Drain Sump. | |||
Post release doses were recalculated using the lower flow rates. The net reported dose impact to a member of the public was minimal with no dose limit reached. The actual dose to the public was controlled in the release by the valid setpoint. | It is still receiving drains from the outside yard including rain runoff and dewatering from the demolition process. | ||
This event is documented in AR 050200268. | This change was reviewed and approved acceptable pursuant to Quality Assurance Program Description (SCE-1-A), subsection 17.2.20.3.1.i per ECP 041100584. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
1 Unplanned Release of the Spent Fuel Pool Heat Exchanger Drains While reviewing Yard Drain Sump (YDS) weekly composite results for the week ending 4/18/05, a slightly higher than expected concentration of tritium was noted.Investigation showed that the spent fuel pool heat exchanger (SFPHX) had been drained to the YDS earlier that week by mistake as the drains were directed to the incorrect yard drain. The plan had been to drain it to the auxiliary building sump and release it as radwaste. | 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 on four different days in 2005. Since there was no detectable activity in the grab samples taken during the overflows, there were no dose consequences to a member of the public as a result of these unplanned, unmonitored releases. These events are documented in ARs 050100436, 050101565, 050401494 and 050600019. | ||
The release was monitored and sampled per procedure. | Estimated Estimated Estimated Start Stop Duration Activity Release Whole Body Organ Dose Date/Time Date/Time (min) | ||
The monitor setpoint was appropriately conservative. | (Ci/ml) | ||
The dose impact to a member of the public was minimal as the maximum organ dose from this release (bone) was less than 10% of the total for the quarter; whole body was 6% of the quarter total. This event is documented in AR 050401027. | (Curies) | ||
Dose (mrem) | |||
However, given that the YDS was the only liquid release point in existence at that time, the entire administrative factor (1.0) for Unit 1 could have been allocated to the YDS. As such, a release could not have exceeded the limits of 10CFR20 even with the installed setpoint. | (mrem) 01/09/05 8 1620 01/09/05 @ 1720 60 | ||
Furthermore, the weekly gamma and tritium composite analyses for that time period were <LLD. There was no dose consequences to a member of the public, but if there had been any dose, it would have been included in Table 2D. This event is documentec in AR 050600267. | <MDA | ||
* O.OOE+O O.OOE+O O.OOE+O 01/26/05 @ 1843 01/26/05 @ 1908 25 | |||
The pump assembly %as replaced and the monitor returned to service on 10/14/05. | <MDA | ||
The previous successfully conducted leak check was on 7/15/05 marking that point as the earliest failure date. Leak testing revealed that the inleakage was less than 50%. Note that since all of the spent fuel has been transferred to the ISFSI (fourth quarter 2004), the requirement for a noble gas monitor is not applicable. | * O.OOE+O O.OOE+O O.OOE+O 01/26/05 @ 1938 01/26/05 @ 2035 57 | ||
Evaluation using 50% of the indicated sample flow revealed that all required LLD levels were met. All samples taken during that time period were <MDA. Therefore there were no dose consequences to a member of the public from this event which is documented in AR 051100265. | <MDA | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | * O.OOE+O O.OOE+O O.OOE+O 02/21/05 @ 0153 02/21/05 @ 0210 17 | ||
1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 -December 31, 2005 S.O.N.G.S. | <MDA | ||
1 Monitor Inoperability Period Inoperability Cause Explanation R-2101 07/09/05 -08/23/05 Detector spiking Found moisture in detector cable Yard Drain Sump during no flow connectors which caused the Monitor condition spiking. Connectors were cleaned and dried and returned to service.This event is documented in AR 050700400. | * O.OOE+O O.OOE+O O.OOE+O 04/28/05 @ 0617 04/28/05 @ 0710 53 | ||
10/16/05 -11/15/05 Detector spiking Repeat symptom. Again found which tripped pumps moisture in detector cable off whenever pumps connectors but on closer turned on due to examination found signs of arcing high sump level which caused the spiking.Connectors were cleaned and reconnected protected by vulcanized tape and desiccant to prevent moisture intrusion. | <MDA | ||
New cable on order for installation. | * O.OOE+0 0.ODE+O O.OOE+O | ||
Monitor forecast to be replaced by summer 2006 with rebuilt monitor for the new YDS as part of demolition. | * MDA (Minimum Detectable Activity), 95% confidence level, a posteriori Unknown Loss of Dilution Flow Durinq Liquid Releases Between 1/21/05 and 2/3/05, only one of two dilution pumps was providing actual dilution flow for three radwaste "C" Holdup Tank (CHUT) releases conducted during that time frame. The dilution pumps were both submerged in the intake structure with hoses attached directing dilution flow. On 2/3/05, unusual turbulence was observed on the water surface, which after investigation, revealed the disconnected hose. Operations ascertained the disconnect occurred on 1/21/05. | ||
This event is documented in AR 051000726 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | The release permit setpoints were calculated using only one of the dilution pumps so all setpoints were valid and appropriately conservative. Post release doses were recalculated using the lower flow rates. The net reported dose impact to a member of the public was minimal with no dose limit reached. The actual dose to the public was controlled in the release by the valid setpoint. This event is documented in AR 050200268. | ||
1 SECTION L. S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
1 CONCLUSIONS | S.O.N.G.S. 1 Unplanned Release of the Spent Fuel Pool Heat Exchanger Drains While reviewing Yard Drain Sump (YDS) weekly composite results for the week ending 4/18/05, a slightly higher than expected concentration of tritium was noted. | ||
Investigation showed that the spent fuel pool heat exchanger (SFPHX) had been drained to the YDS earlier that week by mistake as the drains were directed to the incorrect yard drain. The plan had been to drain it to the auxiliary building sump and release it as radwaste. The release was monitored and sampled per procedure. The monitor setpoint was appropriately conservative. The dose impact to a member of the public was minimal as the maximum organ dose from this release (bone) was less than 10% of the total for the quarter; whole body was 6% of the quarter total. This event is documented in AR 050401027. | |||
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 | Incorrect Setpoint on Yard Drain Sump (YDS) | ||
...........-GASEOUS EFFLUENTS | Monitor R-2101 On 6/6/2005 Operations discovered that the incorrect setpoint was installed ir the YDS monitor, R-2101. | ||
.........-LIQUID EFFLUENTS | On 6/3/2005 the north dilution pump was secured resultirg in only 2000 gpm dilution flow. The installed setpoint for R-2101 (based on 3000 gpm dilution and an administrative factor of 0.3), was non-conservative. However, given that the YDS was the only liquid release point in existence at that time, the entire administrative factor (1.0) for Unit 1 could have been allocated to the YDS. As such, a release could not have exceeded the limits of 10CFR20 even with the installed setpoint. Furthermore, the weekly gamma and tritium composite analyses for that time period were <LLD. There was no dose consequences to a member of the public, but if there had been any dose, it would have been included in Table 2D. | ||
.........-PREVIOUS RADIOACTIVE EFFLUENT RELEA!-RADWASTE SHIPMENTS | This event is documentec in AR 050600267. | ||
........-APPLICABLE LIMITS .........-ESTIMATION OF ERROR ........-10 CFR 50 APPENDIX I REQUIREMENTS | Sample Line Pump Leak on Plant Vent Stack (PVS) Monitor R-1254 On 10/11/05, a skid pump on the R-1254 sample line was found to be leaking during the channel calibration test. Since this leakage was downstream of the sample media, the result was a reduced volume from the plant vent stack being collected. | ||
The pump assembly %as replaced and the monitor returned to service on 10/14/05. The previous successfully conducted leak check was on 7/15/05 marking that point as the earliest failure date. Leak testing revealed that the inleakage was less than 50%. Note that since all of the spent fuel has been transferred to the ISFSI (fourth quarter 2004), | |||
................39................40................50 SE REPORT ADDENDUM .......58................59................63................65................66 MANUAL ............70:NT SYSTEMS ..........72................72 | the requirement for a noble gas monitor is not applicable. Evaluation using 50% of the indicated sample flow revealed that all required LLD levels were met. All samples taken during that time period were <MDA. | ||
...........-S.O.N.G.S. | Therefore there were no dose consequences to a member of the public from this event which is documented in AR 051100265. | ||
2 and 3 CONCLUSIONS | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
..-iii-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)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 | S.O.N.G.S. 1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 - December 31, 2005 S.O.N.G.S. 1 Monitor Inoperability Period Inoperability Cause Explanation R-2101 07/09/05 - 08/23/05 Detector spiking Found moisture in detector cable Yard Drain Sump during no flow connectors which caused the Monitor condition spiking. Connectors were cleaned and dried and returned to service. | ||
: 5. Batch Release Summaries 6. Previous Radioactive Effluent Release Report Addendum 7. Radwaste Shipments 8. 10 CFR 50 Appendix I Requirements | This event is documented in AR 050700400. | ||
: 9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | 10/16/05 - | ||
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: | 11/15/05 Detector spiking Repeat symptom. Again found which tripped pumps moisture in detector cable off whenever pumps connectors but on closer turned on due to examination found signs of arcing high sump level which caused the spiking. | ||
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 cuarter.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 errcr is presented in Section G of this report.Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Units 2 and 3 do not conduct elevated releases.Table 1C, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in three categories: | Connectors were cleaned and reconnected protected by vulcanized tape and desiccant to prevent moisture intrusion. New cable on order for installation. Monitor forecast to be replaced by summer 2006 with rebuilt monitor for the new YDS as part of demolition. This event is documented in AR 051000726 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
S.O.N.G.S. 1 SECTION L. S.O.N.G.S. 1 CONCLUSIONS Gaseous releases totaled 4.45E-7 curies of which particulates were 4.45E-7 curies, and tritium was O.OOE+O curies. (Noble Gas and Iodine sampling no longer required) | |||
The radiation doses from gaseous releases were: organ dose: 2.22E-5 mrem at the nearest receptor. (No dose was attributed to Gamma and Beta radiation since noble gas arid iodine sampling are no longer required) | |||
Liquid releases totaled 2.12E+1 curies of which particulates and iodines were 1.40E--2 curies, tritium was 2.12E+1 curies, and noble gases were O.OOE+O curies. | |||
The radiation doses from liquid releases were: (a) total body: 3.22E-2 mrem, (b) limiting organ: 7.12E-2 mrem. | |||
The radioactive releases and resulting doses generated from Unit 1 were below the Applicable Limits for both gaseous and liquid effluents. | |||
s.O.N.G.S. 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 RELEA! | |||
- RADWASTE SHIPMENTS........ | |||
- APPLICABLE LIMITS......... | |||
- ESTIMATION OF ERROR........ | |||
- 10 CFR 50 APPENDIX I REQUIREMENTS. | |||
CHANGES TO OFFSITE DOSE CALCULATION | |||
................ 39 | |||
................ 40 | |||
................ 50 SE REPORT ADDENDUM....... 58 | |||
................ 59 | |||
................ 63 | |||
................ 65 | |||
................ 66 MANUAL............ 70 | |||
:NT SYSTEMS.......... 72 | |||
................ 72 75 | |||
- CHANGES TO RADIOACTIVE WASTE TREATME | |||
- MISCELLANEOUS........... | |||
- S.O.N.G.S. 2 and 3 CONCLUSIONS.. | |||
-iii- | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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 (2005) | |||
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 cuarter. | |||
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 errcr is presented in Section G of this report. | |||
Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Units 2 and 3 do not conduct elevated releases. | |||
Table 1C, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in three categories: | |||
fission gases, iodines, and particulates. | 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. | The total radioactivity for each radionuclide is listed for each quarterly period by both "continuous" and "batch" modes of release. | ||
Containment purges and plant stack releases are considered to be "continuous" releases.Table 1D, "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. | Waste gas decay tank releases are considered to be "batch" releases. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Containment purges and plant stack releases are considered to be "continuous" releases. | ||
2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL | Table 1D, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC. | ||
>8 days Ci 1.08E-4 1.24E-5 1.60E+1 2. Average release rate for period uCi/sec 1.38E-5 1.58E-6 3. Percent of applicable limit % MPC 5.19E-6 5.55E-7 4. Percent Effluent Concentration Limit % ECL 1.86E-5 1.23E-6 5. Gross alpha activity Ci <LLD <LLD 5.OOE+1 D. Tritium 1. Total release Ci 1.32E+1 2.03E+1 2.50E+1 2. Average release rate for period uCi/sec 1.70E+O 2.58E+O 3. Percent of applicable limit % MPC 4.07E-3 6.20E-3 4. Percent Effluent Concentration Limit % ECL I 8.15E-3 1.24E-2 I (1)(2)on i/Z6/U0 Tor approximately u30 minutes, unit 3 conaenser air ejector particulate and ioaine samples were not collected due to inadvertent securing of the skid. Prior and subsequent samples were <MDA. There were no dose consequences to a member of the public due to this event which is documented in AR 050101560. | Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period. | ||
On 4/13/05 for less than 6 hours, no particulate samples were taken at the South Yard Facility due to an electrical fault. Prior and subsequent samples were <MDA. No work was being performed during this time.There were no dose consequences to a member of the public due to this event which is documented in AR 050401508. | 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 (2005)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
2 and 3 TABLE 1A (Continued) | S.O.N.G.S. 2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter Estimated Second Total Quarter Error, % | ||
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Esti mated Total Error, %A. Fission and activation gases 1. Total release Ci 2.97E+1 4.29E+1 3.OC'E+1 2. Average release rate for period pCi/sec 3.74E+O 5.39E+O 3. Percent of applicable limit % MPC 1.15E-2 9.77E-3 4. Percent Effluent Concentration Limit % ECL 2.86E-2 1.02E-2 B. Iodines 1. Total iodine-131 Ci 4.33E-5 2.55E-5 1.9CE+1 2. Average release rate for period pCi/sec 5.45E-6 3.21E-6 3. Percent of applicable limit % MPC 2.61E-5 1.54E-5 4. Percent Effluent Concentration Limit % ECL 1.31E-5 7.70E-6 I C. Particulates | A. Fission and activation gases | ||
: 1. Particulates with half-lives | : 1. Total release Ci 2.72E+1 2.83E+1 3.0OE+1 | ||
>8 days Ci 1.20E-5 1.06E-5 1.6C'E+1 2. Average release rate for period MCi/sec 1.51E-6 1.33E-6 3. Percent of applicable limit % MPC 1.09E-6 1.12E-6 4. Percent Effluent Concentration Limit % ECL 2.67E-6 2.78E-6 5. Gross alpha activity Ci <LLD <LLD 5.OCE+1 D. Tritium 1. Total release Ci 1.21E+1 5.02E+O 2.5CIE+1 2. Average release rate for period pCi/sec 1.52E+O 6.32E-1 3. Percent of applicable limit % MPC 3.65E-3 1.52E-3 4. Percent Effluent Concentration Limit % ECL 7.31E-3 3.03E-3 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 2. Average release rate for period pCi/sec 3.49E+O 3.61E+O | ||
2 and 3 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I First Second Third Fourth Radionuclides Released Unit Quarter Quarter l Quarter I Quarter 1. Fission and activation gases argon-41 Ci 8.41E-1 2.74E+O 4.22E+O 8.67E-1 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 2.56E+1 2.51E+1 2.55E+1 3.97E+1 xenon-133m Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD 4.48E-3 xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD LLD <LLD <LLD Total for period Ci 2.64E+1 2.78E+1 2.97E+1 4.06E+1 2. Iodines iodine-131 Ci 1.13E-5 4.33E-5 4.33E-5 2.55E-5 iodine-132 Ci <LLD <LLD 1.95E-6 <LLD iodine-133 Ci 1.24E-5 5.48E-5 7.54E-5 1.90E-5 iodine-135 Ci <LLD <LLD <LLD <LLD Total for period Ci 2.37E-5 I 9.81E-5 I 1.21E-4 4.45E-5 LLD Lower Limit of Detection; see Table 1D. | : 3. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Percent of applicable limit | ||
2 and 3-TABLE IC (Continued) | % MPC 6.71E-3 9.39E-3 | ||
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS | : 4. Percent Effluent Concentration Limit | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | % ECL 8.41E-3 1.98E-2 B. Iodines (1)(2) | ||
2 and 3 TABLE 1C (Continued) | : 1. Total iodine-131 Ci 1.13E-5 4.33E-5 1.90E+1 | ||
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE *I First Second Third Fourth Radionuclides Released Unit l Quarter l Quarter l Quarter l Quarter 1. Fission and activation gases krypton-85 Ci 7.06E-1 5.05E-1 N/A 2.27E+O krypton-85m Ci <LLD <LLD N/A <LLD krypton-87 Ci <LLD <LLD N/A <LLD krypton-88 Ci <LLD <LLD N/A <LLD xenon-133 Ci 3.57E-2 <LLD N/A 7.81E-3 xenon-133m Ci <LLD <LLD N/A <LLD xenon-135 Ci <LLD <LLD N/A <LLD xenon-135m Ci <LLD <LLD N/A <LLD xenon-138 Ci <LLD <LLD N/A <LLD Total for period Ci 7.41E-1 5.05E-1 N/A 2.28E+O LLD Lower Limit of Detection; see Table 1D. | : 2. Average release rate for period uCi/sec 1.45E-6 5.51E-6 | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 3. | ||
2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS 1ODE OF DETECTION Radionucl ides LLD (Ci/cc)1. Fission and activation gases krypton-85 1.50E-5 krypton-85m 3.80E-8 krypton-87 1.90E-7 krypton-88 1.40E-7 xenon--133m 3.10E-7 xenon--135 4.OOE-8 xenon--135m 1.50E-6 xenon--138 2.60E-6 2. Iodines__ | Percent of applicable limit | ||
% MPC 6.98E-6 2.64E-5 | |||
2 and 3 TABLE 1D (Continued) | : 4. Percent Effluent Concentration Limit | ||
GASEOUS EFFLUENTS-LOWER LIMIT OF BATCH MODE DETECTION Radionuclides LLD (IuCi/cc)1. Fission and activation gases krypton-85m 2.OOE-6 krypton-87 9.OOE-6 krypton-88 7.20E-6 xenon-133 4.60E-6 xenon-133m 1.80E-5 xenon-135 2.30E-6 xenon-135m 2.80E-5 xenon-138 4.30E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | % ECL 3.49E-6 1.32E-5 C. Particulates (1)(2) | ||
2 and 3 TABLE lE GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First l Second l Third Fourth Unit Quarter J Quarter Quarter Quarter A. Noble Gas 1. Gamma Air Dose mrad 2.57E-3 5.22E-3 7.34E-3 1.33E-3 2. Percent Applicable Limit | : 1. Particulates with half-lives >8 days Ci 1.08E-4 1.24E-5 1.60E+1 | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 2. Average release rate for period uCi/sec 1.38E-5 1.58E-6 | ||
2 and 3 TABLE iF GASEOUS EFFLUENTS-BATCH RELEASE | : 3. Percent of applicable limit | ||
% MPC 5.19E-6 5.55E-7 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 1.86E-5 1.23E-6 | |||
: 5. Gross alpha activity Ci | |||
<LLD | |||
<LLD 5.OOE+1 D. Tritium | |||
: 1. Total release Ci 1.32E+1 2.03E+1 2.50E+1 | |||
: 2. Average release rate for period uCi/sec 1.70E+O 2.58E+O | |||
: 3. Percent of applicable limit | |||
% MPC 4.07E-3 6.20E-3 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL I 8.15E-3 1.24E-2 I (1) | |||
(2) on i/Z6/U0 Tor approximately u30 minutes, unit 3 conaenser air ejector particulate and ioaine samples were not collected due to inadvertent securing of the skid. Prior and subsequent samples were <MDA. There were no dose consequences to a member of the public due to this event which is documented in AR 050101560. | |||
On 4/13/05 for less than 6 hours, no particulate samples were taken at the South Yard Facility due to an electrical fault. Prior and subsequent samples were <MDA. | |||
No work was being performed during this time. | |||
There were no dose consequences to a member of the public due to this event which is documented in AR 050401508. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 1A (Continued) | |||
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Esti mated Total Error, % | |||
A. Fission and activation gases | |||
: 1. Total release Ci 2.97E+1 4.29E+1 3.OC'E+1 | |||
: 2. Average release rate for period pCi/sec 3.74E+O 5.39E+O | |||
: 3. Percent of applicable limit | |||
% MPC 1.15E-2 9.77E-3 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL 2.86E-2 1.02E-2 B. Iodines | |||
: 1. Total iodine-131 Ci 4.33E-5 2.55E-5 1.9CE+1 | |||
: 2. Average release rate for period pCi/sec 5.45E-6 3.21E-6 | |||
: 3. Percent of applicable limit | |||
% MPC 2.61E-5 1.54E-5 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 1.31E-5 7.70E-6 I C. Particulates | |||
: 1. Particulates with half-lives >8 days Ci 1.20E-5 1.06E-5 1.6C'E+1 | |||
: 2. Average release rate for period MCi/sec 1.51E-6 1.33E-6 | |||
: 3. Percent of applicable limit | |||
% MPC 1.09E-6 1.12E-6 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 2.67E-6 2.78E-6 | |||
: 5. Gross alpha activity Ci | |||
<LLD | |||
<LLD 5.OCE+1 D. Tritium | |||
: 1. Total release Ci 1.21E+1 5.02E+O 2.5CIE+1 | |||
: 2. Average release rate for period pCi/sec 1.52E+O 6.32E-1 | |||
: 3. Percent of applicable limit | |||
% MPC 3.65E-3 1.52E-3 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 7.31E-3 3.03E-3 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I | |||
First Second Third Fourth Radionuclides Released Unit Quarter Quarter l Quarter I Quarter | |||
: 1. Fission and activation gases argon-41 Ci 8.41E-1 2.74E+O 4.22E+O 8.67E-1 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 2.56E+1 2.51E+1 2.55E+1 3.97E+1 xenon-133m Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD xenon-135 Ci | |||
<LLD | |||
<LLD | |||
<LLD 4.48E-3 xenon-135m Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD xenon-138 Ci | |||
<LLD LLD | |||
<LLD | |||
<LLD Total for period Ci 2.64E+1 2.78E+1 2.97E+1 4.06E+1 | |||
: 2. Iodines iodine-131 Ci 1.13E-5 4.33E-5 4.33E-5 2.55E-5 iodine-132 Ci | |||
<LLD | |||
<LLD 1.95E-6 | |||
<LLD iodine-133 Ci 1.24E-5 5.48E-5 7.54E-5 1.90E-5 iodine-135 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD Total for period Ci 2.37E-5 I 9.81E-5 I 1.21E-4 4.45E-5 LLD Lower Limit of Detection; see Table 1D. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 | |||
-TABLE IC (Continued) | |||
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE l First Second Third Fourth Radionuclides Released I Unit I Quarter I Quarter I Quarter Quarter | |||
: 3. Particulates bariuum-140 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLED bromine-82 Ci 3.43E-5 1.30E-4 8.17E-5 2.86E-5 ceriuum-141 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cerium-144 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD1 cesium-134 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cesium-137 Ci | |||
<LLD 1.92E-6 8.04E-6 8.88E-6 cesium-138 Ci | |||
<LLD | |||
<LLD 4.44E-5 | |||
<LLD cobal-:-58 Ci 9.48E-5 1.05E-5 3.97E-6 1.70E-6 cobal:-60 Ci 1.02E-5 | |||
<LLD | |||
<LLD | |||
<LLD iron-59 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD lanthanum-140 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD manganese-54 Ci 2.64E-6 | |||
<LLD | |||
<LLD | |||
<LLD molybdenum-99 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD stronl:ium-89 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD stronl:ium-90 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD zinc-fi5 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD zirconium-95 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD LLD Lower Limit of Detection; see Table 1D. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 1C (Continued) | |||
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE | |||
* I First Second Third Fourth Radionuclides Released Unit l Quarter l Quarter l Quarter l Quarter | |||
: 1. Fission and activation gases krypton-85 Ci 7.06E-1 5.05E-1 N/A 2.27E+O krypton-85m Ci | |||
<LLD | |||
<LLD N/A | |||
<LLD krypton-87 Ci | |||
<LLD | |||
<LLD N/A | |||
<LLD krypton-88 Ci | |||
<LLD | |||
<LLD N/A | |||
<LLD xenon-133 Ci 3.57E-2 | |||
<LLD N/A 7.81E-3 xenon-133m Ci | |||
<LLD | |||
<LLD N/A | |||
<LLD xenon-135 Ci | |||
<LLD | |||
<LLD N/A | |||
<LLD xenon-135m Ci | |||
<LLD | |||
<LLD N/A | |||
<LLD xenon-138 Ci | |||
<LLD | |||
<LLD N/A | |||
<LLD Total for period Ci 7.41E-1 5.05E-1 N/A 2.28E+O 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 (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS 1ODE OF DETECTION Radionucl ides LLD (Ci/cc) | |||
: 1. Fission and activation gases krypton-85 1.50E-5 krypton-85m 3.80E-8 krypton-87 1.90E-7 krypton-88 1.40E-7 xenon--133m 3.10E-7 xenon--135 4.OOE-8 xenon--135m 1.50E-6 xenon--138 2.60E-6 | |||
: 2. | |||
Iodines__ | |||
i odine-132 1.30E-9 i odi ne-135 1.40E-10 | |||
: 3. Particulates bari uri-140 4.30E-13 ceri uri-141 5.50E-14 ceri uri-144 2.20E-13 cesi ur-134 1.20E-13 cesi uri-137 1.OOE-13 cesi uri-138 2.60E-10 cobal 1:-60 1.70E-13 i ron-5i9 2.70E-13 l anthanum-140 8.50E-13 mangariese-54 1.10E-13 molybclenum-99 6.50E-14 stront.i um-89 1.OOE-11 stront.i um-90 1.OOE-11 zinc-65 2.90E-13 zi rcori um-95 1.90E-13 | |||
: 4. al pha 1.OOE-11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 1D (Continued) | |||
GASEOUS EFFLUENTS-LOWER LIMIT OF BATCH MODE DETECTION Radionuclides LLD (IuCi/cc) | |||
: 1. Fission and activation gases krypton-85m 2.OOE-6 krypton-87 9.OOE-6 krypton-88 7.20E-6 xenon-133 4.60E-6 xenon-133m 1.80E-5 xenon-135 2.30E-6 xenon-135m 2.80E-5 xenon-138 4.30E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE lE GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First l Second l Third Fourth Unit Quarter J Quarter Quarter Quarter A. Noble Gas | |||
: 1. | |||
Gamma Air Dose mrad 2.57E-3 5.22E-3 7.34E-3 1.33E-3 | |||
: 2. | |||
Percent Applicable Limit 2.57E-2 5.22E-2 7.34E-2 1.33E-2 | |||
: 3. | |||
Beta Air Dose mrad 4.73E-3 5.52E-3 6.18E-3 4.20E-3 | |||
: 4. | |||
Percent Applicable Limit 2.36E-2 2.76E-2 3.09E-2 2.10E-2 B. Tritium, Iodine, Particulates (at the nearest receptor) | |||
: 1. Organ Dose mrem 2.08E-3 3.24E-3 2.06E-3 8.62E-4 | |||
: 2. Percent Applicable Limit 1.38E-2 2.16E-2 1.38E-2 5.74E-3 NOTE: | |||
Calculations performed in accordance with the ODCM utilizing the historical X/Q. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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 | ||
6 releases 2. Total time period for batch releases: | : 1. Number of batch releases: | ||
2070 minutes 3. Maximum time period for a batch release: 470 minutes 4. Average time period for a batch release: 345 minutes 5. Minimum time period for a batch release: 39 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | 6 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 activat:ion 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. | 2070 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 (2005)S.O.N.G.S. | 470 minutes | ||
2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I IEstimated | : 4. Average time period for a batch release: | ||
_ First Second Total Unit Quarter Quarter Error, %A. Fission and activation products(l) | 345 minutes | ||
: 1. Total release (not including tritium, gases, alpha) Ci 5.49E-3 1.07E-2 1.90E+1 2. Average diluted concentration during period AiCi/ml 7.41E-12 1.41E-11 3. Percent of applicable limit % MPC 8.19E-6 2.19E-5 4. Percent Effluent Concentration Limit % ECL 5.90E-5 2.06E-4 B. Tritium 1. Total release Ci 1.35E+2 5.45E+2 1.90E+1 2. Average diluted concentration during period ktCi/ml 1.82E-7 7.20E-7 3. Percent of applicable limit % MPC 6.07E-3 2.40E-2 4. Percent Effluent Concentration Limit % ECL 1.82E-2 7.20E-2 C. Dissolved and entrained gases 1. Total release Ci 7.81E-5 1.40E-2 1.90E+1 2. Average diluted concentration during period uCi/ml 1.05E-13 1.85E-11 3. Percent of applicable limit % MPC 5.27E-8 9.27E-6 4. Percent Effluent Concentration Limit % ECL 5.27E-8 9.27E-6 D. Gross alpha radioactivity (1)1. Total release Ci <LLD <LLD 5.0OE+1 E. Volume of waste released (batch &continuous, prior to dilution) liters 8.58E+7 1.06E+8 5.OOE+O F. Volume of dilution water used during period liters 7.41E+11 7.57E+11 5.OOE+O (1) The sample for Unit 3 HUT released on 4/7/04 was discarded prior to use in the monthly composite for offsite analysis for alpha, Fe-55 and Sr-89/90. | : 5. Minimum time period for a batch release: | ||
The April Unit 3 FFCPD composite was comprised of 11 other tank releases. | 39 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
The missing sample was a clean sump release (#5L-102-3) having gamma and tritium both <MDA. There was no dose impact to a member of the public from this event which is documented in AR 050500801. | 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 activat:ion products, tritium, and dissolved and entrained gases. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Listed for each of the three categories are: | ||
2 and 3 TABLE 2A (Continued) | (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: | ||
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit Quarter Quarter Error-,_ I%A. FissiDn and activation products(') | (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution) | ||
: 1. Total release (not including tritium, gases, alpha) Ci 6.32E-3 7.20E-3 1.90E+1 2. Average diluted concentration during period uCi/ml 8.23E-12 9.39E-12 3. Percent of applicable limit % MPC 1.38E-5 1.68E-5 4. Percent Effluent Concentration Limit % ECL 1.14E-4 1.71E-4 B. Tritium 1. Total release Ci 7.22E+1 3.80E+2 1.90E+1 2. Average diluted concentration during period MCi/ml 9.40E-8 4.95E-7 3. Percent of applicable limit % MPC 3.13E-3 1.65E-2 4. Percent Effluent Concentration Limit % ECL 9.40E-3 4.95E-2 C. Dissolved and entrained gases 1. Total release Ci 1.90E-4 6.36E-2 1.90E+1 2. Average diluted concentration during period yCi/ml 2.47E-13 8.29E-11 3. Percent of applicable limit % MPC 1.24E-7 4.14E-5 4. Percent Effluent Concentration Limit % ECL 1.24E-7 4.14E-5 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 <LLD 5.OOE+1 E. Volume of waste released (batch &continuous, prior to dilution) liters 7.35E+7 6.40E+7 5.OOE+O F. Volume of dilution water used during period liters 7.68E+11 7.67E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)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. | ||
2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE 1 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 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 <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. | Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release. | ||
2 and 3 TABLE 2B (Continued) | Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. | ||
LIQUID EFFLUENTS BATCH | 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. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)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 LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (mCi/cc)1. Fission and activation products barium-140 2.90E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 7.50E-8 cesium-137 6.40E-8 chromium-51 3.30E-7 cobalt-58 6.80E-8 cobalt-60 1.OOE-7 iodine-131 5.70E-8 iron-55 1.OOE-6 iron-59 1.60E-7 lanthanum-140 5.60E-7 manganese-54 6.70E-8 molybdenum-99 5.60E-8 niobium-95 6.80E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.70E-7 zirconium-95 1.20E-7 2. Dissolved and entrained gases xenon-133 1.90E-7 xenon-135 8.90E-8 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
2 and 3 TABLE 2C (Continued) | S.O.N.G.S. 2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I | ||
LIQUID EFFLUENTS-LOWER LIMIT OF BATCH MODE DETECTION Radi onucli des LLD (Ci/cc)1. Fission and activation products bariurn-140 2.40E-7 ceriurn-141 4.OOE-8 ceriurn-144 1.70E-7 cesiurn-134 7.50E-8 cesiura-137 6.40E-8 chrominum-51 3.OOE-7 cobal1:-57 2.20E-8 iodine-13i 4.30E-8 iron-59 1.40E-7 lanthanum-140 1.80E-7 molybdenum-99 2.70E-8 niobitim-97 1.50E-7 stronl:ium-89 5.OOE-8 stronl:ium-90 5.OOE-8 technetium-99m 2.70E-8 tin-1:3 5.30E-8 zinc-65 1.70E-7 zircorlium-95 1.10E-7 zirconium-97 1.70E-7 2. Dissolved and entrained gases krypton-85 2.90E-5 xenon-.13lm 3.OOE-6 xenon-.133m 6.90E-7 xenon-*135 8.90E-8 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | IEstimated | ||
2 and 3 TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOI LIQUI JNDARY First Second Third I Fourth Unit Quarter Quarter Quarter Quarter A.1. Total body dose mrem 3.92E-4 1.17E-3 2.66E-4 8.43E-4 2. Percent Applicable Limit | _ First Second Total Unit Quarter Quarter Error, % | ||
2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE | A. Fission and activation products(l) | ||
: 1. Total release (not including tritium, gases, alpha) | |||
Ci 5.49E-3 1.07E-2 1.90E+1 | |||
: 2. Average diluted concentration during period AiCi/ml 7.41E-12 1.41E-11 | |||
: 3. | |||
Percent of applicable limit | |||
% MPC 8.19E-6 2.19E-5 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL 5.90E-5 2.06E-4 B. Tritium | |||
: 1. Total release Ci 1.35E+2 5.45E+2 1.90E+1 | |||
: 2. Average diluted concentration during period ktCi/ml 1.82E-7 7.20E-7 | |||
: 3. Percent of applicable limit | |||
% MPC 6.07E-3 2.40E-2 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 1.82E-2 7.20E-2 C. Dissolved and entrained gases | |||
: 1. Total release Ci 7.81E-5 1.40E-2 1.90E+1 | |||
: 2. Average diluted concentration during period uCi/ml 1.05E-13 1.85E-11 | |||
: 3. Percent of applicable limit | |||
% MPC 5.27E-8 9.27E-6 | |||
: 4. Percent Effluent Concentration Limit | |||
% ECL 5.27E-8 9.27E-6 D. Gross alpha radioactivity (1) | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 5.0OE+1 E. Volume of waste released (batch & | |||
continuous, prior to dilution) liters 8.58E+7 1.06E+8 5.OOE+O F. Volume of dilution water used during period liters 7.41E+11 7.57E+11 5.OOE+O (1) The sample for Unit 3 HUT released on 4/7/04 was discarded prior to use in the monthly composite for offsite analysis for alpha, Fe-55 and Sr-89/90. The April Unit 3 FFCPD composite was comprised of 11 other tank releases. The missing sample was a clean sump release (#5L-102-3) having gamma and tritium both <MDA. There was no dose impact to a member of the public from this event which is documented in AR 050500801. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 2A (Continued) | |||
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit Quarter Quarter Error-,_ | |||
I% | |||
A. FissiDn and activation products(') | |||
: 1. Total release (not including tritium, gases, alpha) | |||
Ci 6.32E-3 7.20E-3 1.90E+1 | |||
: 2. | |||
Average diluted concentration during period uCi/ml 8.23E-12 9.39E-12 | |||
: 3. | |||
Percent of applicable limit | |||
% MPC 1.38E-5 1.68E-5 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL 1.14E-4 1.71E-4 B. Tritium | |||
: 1. Total release Ci 7.22E+1 3.80E+2 1.90E+1 | |||
: 2. | |||
Average diluted concentration during period MCi/ml 9.40E-8 4.95E-7 | |||
: 3. | |||
Percent of applicable limit | |||
% MPC 3.13E-3 1.65E-2 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL 9.40E-3 4.95E-2 C. Dissolved and entrained gases | |||
: 1. Total release Ci 1.90E-4 6.36E-2 1.90E+1 | |||
: 2. | |||
Average diluted concentration during period yCi/ml 2.47E-13 8.29E-11 | |||
: 3. | |||
Percent of applicable limit | |||
% MPC 1.24E-7 4.14E-5 | |||
: 4. | |||
Percent Effluent Concentration Limit | |||
% ECL 1.24E-7 4.14E-5 D. Gross alpha radioactivity | |||
: 1. Total release Ci | |||
<LLD | |||
<LLD 5.OOE+1 E. Volume of waste released (batch & | |||
continuous, prior to dilution) liters 7.35E+7 6.40E+7 5.OOE+O F. Volume of dilution water used during period liters 7.68E+11 7.67E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE 1 | |||
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 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 | |||
<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 (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 2B (Continued) | |||
LIQUID EFFLUENTS BATCH MODE l First l Second Third Fourti Radionuclides Released l Unit l Quarter Quarter l Quarter l Quarter | |||
: 1. Fission and activation products antimony-125 Ci 1.32E-4 1.15E-3 1.O1E-4 6.86E-4 barium-140 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cerium-141 Ci | |||
<LLD | |||
<LLD | |||
.<LLD | |||
<LLD cerium-144 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD cesium-134 Ci 3.96E-6 6.21E-5 | |||
<LLD 2.25E-5 cesium-137 Ci 6.64E-5 6.59E-4 | |||
<LLD 3.88E-4 chromium-51 Ci 3.30E-4 | |||
<LLD | |||
<LLD | |||
<LLD cobalt-57 Ci 7.71E-7 | |||
<LLD | |||
<LLD | |||
<LLD cobalt-58 Ci 1.58E-3 2.57E-3 1.57E-3 4.83E-.4 cobalt-60 Ci 6.34E-4 1.61E-3 2.19E-3 2.26E--3 iodine-131 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD iron-55 Ci 1.67E-3 2.48E-3 1.62E-3 2.58E-3 iron-59 Ci 1.21E-4 8.83E-5 | |||
<LLD | |||
<LLD lanthanum-140 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD manganese-54 Ci 1.63E-4 3.85E-4 2.37E-4 2.94E-4 molybdenum-99 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD niobium-95 Ci 4.60E-4 9.86E-4 2.94E-4 9.65E*-5 niobium-97 Ci 8.85E-6 | |||
<LLD 1.05E-5 3.14E-5 silver-lOrm Ci 5.09E-5 1.42E-4 1.41E-4 3.53E-4 strontium-89 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD_ | |||
strontium-90 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD' technetium-99m Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLED tin-113 Ci 2.50E-5 1.94E-5 7.99E-6 | |||
<LLE' zinc-65 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LLD' zirconium-95 Ci 2.44E-4 5.18E-4 1.47E-4 | |||
<LLD zirconium-97 Ci | |||
<LLD | |||
<LLD | |||
<LLD 1.16E-5 Total for period Ci 5.49E-3 1.07E-2 6.32E-3 7.20E-3 | |||
: 2. Dissolved and entrained gases krypton-85 Ci | |||
<LLD 1.25E-2 | |||
<LLD 1.36E-2 xenon-131m Ci | |||
<LLD | |||
<LLD | |||
<LLD 6.58E-4 xenon-133 Ci 7.81E-5 1.54E-3 1.90E-4 4.90E-2 xenon-133m Ci | |||
<LLD | |||
<LLD | |||
<LLD 2.77E-4 xenon-135 Ci | |||
<LLD | |||
<LLD | |||
<LLD | |||
<LL11 Total for period Ci 7.81E-5 1.40E-2 1.90E-4 6.36E-2 LLD Lower Limit of Detection; see Table 2C. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (mCi/cc) | |||
: 1. Fission and activation products barium-140 2.90E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 7.50E-8 cesium-137 6.40E-8 chromium-51 3.30E-7 cobalt-58 6.80E-8 cobalt-60 1.OOE-7 iodine-131 5.70E-8 iron-55 1.OOE-6 iron-59 1.60E-7 lanthanum-140 5.60E-7 manganese-54 6.70E-8 molybdenum-99 5.60E-8 niobium-95 6.80E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.70E-7 zirconium-95 1.20E-7 | |||
: 2. | |||
Dissolved and entrained gases xenon-133 1.90E-7 xenon-135 8.90E-8 | |||
: 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 2C (Continued) | |||
LIQUID EFFLUENTS-LOWER LIMIT OF BATCH MODE DETECTION Radi onucli des LLD (Ci/cc) | |||
: 1. Fission and activation products bariurn-140 2.40E-7 ceriurn-141 4.OOE-8 ceriurn-144 1.70E-7 cesiurn-134 7.50E-8 cesiura-137 6.40E-8 chrominum-51 3.OOE-7 cobal1:-57 2.20E-8 iodine-13i 4.30E-8 iron-59 1.40E-7 lanthanum-140 1.80E-7 molybdenum-99 2.70E-8 niobitim-97 1.50E-7 stronl:ium-89 5.OOE-8 stronl:ium-90 5.OOE-8 technetium-99m 2.70E-8 tin-1:3 5.30E-8 zinc-65 1.70E-7 zircorlium-95 1.10E-7 zirconium-97 1.70E-7 | |||
: 2. Dissolved and entrained gases krypton-85 2.90E-5 xenon-.13lm 3.OOE-6 xenon-.133m 6.90E-7 xenon-*135 8.90E-8 | |||
: 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOI LIQUI JNDARY First Second Third I Fourth Unit Quarter Quarter Quarter Quarter A. | |||
: 1. Total body dose mrem 3.92E-4 1.17E-3 2.66E-4 8.43E-4 | |||
: 2. Percent Applicable Limit 1.31E-2 3.91E-2 8.85E-3 2.81E-2 B. | |||
: 1. Limiting organ dose mrem 1.38E-3 2.68E-3 1.37E-3 2.60E-3 | |||
: 2. Percent Applicable Limit 1.38E-2 2.68E-2 1.37E-2 2.60E-2 | |||
: 3. Limiting organ for period GI-LLI GI-LLI GI-LLI GI-LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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 | ||
122 releases 2. Total time period for batch releases: | : 1. Number of batch releases: | ||
18468 minutes 3. Maximul time period for a batch release: 550 minutes 4. Average time period for a batch release: 151 minutes 5. Minimum time period for a batch release: 1 minutes 6. Average saltwater flow during batch releases: | 122 releases | ||
: 2. Total time period for batch releases: | |||
18468 minutes | |||
: 3. Maximul time period for a batch release: | |||
550 minutes | |||
: 4. Average time period for a batch release: | |||
151 minutes | |||
: 5. Minimum time period for a batch release: | |||
1 minutes | |||
: 6. Average saltwater flow during batch releases: | |||
735350 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None. | 735350 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
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)12 month Estimated total 1. Type of waste Unit period error (%)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) 12 month Estimated total | ||
* Ci 3.16E-1 3.0OE+1 c. Irradiated components | : 1. Type of waste Unit period error (%) | ||
* | : a. Spent resins, filter sludges m3 N/A Ci N/A N/A | ||
: b. Dry active waste (DAW), | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | m3 4.51E+1 compactable and non-compactable | ||
2 and 3 2. Estimate of major nuclide composition (by type of waste)a. not applicable | * Ci 3.16E-1 3.0OE+1 | ||
: c. Irradiated components m3 N/A Ci N/A N/A | |||
: d. Other: Filters | |||
* m3 3.99E-2 Ci | |||
. 1.04E+O 3.OOE+1 Note: Total curie content estimated. | |||
Material packaged in strong tight containers (USA Type IP-1) of various sizes. | |||
N/A No shipment made. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 | |||
: 2. Estimate of major nuclide composition (by type of waste) | |||
: a. not applicable N/A | |||
= 3.06E+O0 c. not applicable | : b. americium-241 3.OOE-04 antimony-124 4.08E-01 antimony-125 8.60E-O1 carbon-14 5.13E-O1 cerium-144 3.04E-01 cesium-134 2.74E+00 cesium-137 1.34E+OO chromium-51 1.22E+O1 cobalt-57 2.55E-Ol cobalt-58 2.84E+01 cobalt-60 3.52E+OO curium-242 1.70E-03 curium-243/244 2.10E-03 iron-55 3.01E+01 iron-59 2.46E+OO manganese-54 1.32E+OO nickel-59 2.87E-O1 nickel-63 6.33E+OO niobium-95 5.98E+OO plutonium-238 6.OOE-04 plutonium-239/240 2.OOE-04 plutonium-241 4.74E-02 strontium-89 2.73E-02 strontium-90 1.50E-03 zirconium-95 | ||
= | |||
2 and 3 2. Estimate of major nuclide composition (by type of waste)d. americium-241 | 3.06E+O0 | ||
: c. | |||
not applicable N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 | |||
__2.16E-02 cesium-134 | : 2. Estimate of major nuclide composition (by type of waste) | ||
: d. americium-241 6.70E-03 antimony-125 1.09E+0O carbon-14 1.20E+01 cerium-144 | |||
__2.16E-02 cesium-134 1.44E-01 cesium-137 1.04E+OO cobalt-57 | |||
__2.95E-02 cobalt-58 | __2.95E-02 cobalt-58 | ||
__1.80E-01 cobalt-60 1.74E+01 curium-242 | __1.80E-01 cobalt-60 1.74E+01 curium-242 2.OOE-05 curium-243/244 1.23E-02 iodine-129 9.OOE-04 iron-55 3.26E+01 iron-59 4.OOE-04 manganese-54 3.93E-O1 nickel-63 3.48E+01 niobium-95 6.OOE-04 plutonium-238 3.30E-03 plutonium-239/240 3.50E-03 plutonium-241 1.62E-01 silver-lOm 1.61E-02 strontium-90 1.54E-02 technetium-99 7.OOE-03 tin-113 4.40E-03 tritium 1.32E-01 zirconium-95 3.80E-03 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
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 6 | |||
* TAG Transport Duratek/EnviroCare, UT Truck/Flatbed Trailer DrtkEvr~r 5 U 1** | |||
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 6 | Hitman Transport Studsvik/Barnwell 1Truck/Flatbed Trailer 2 | ||
* TAG Transport Duratek/EnviroCare, | TAG Transport EnviroCare, UT Truck/Flatbed Trailer Evr~rU SONGS maintains a contract with Duratek that provides volume reduction services. The processed volume was shipped from the Duratek facility to EnviroCare using 10 shipments. | ||
Truck/Flatbed Trailer DrtkEvr~r 5 U 1** Hitman Transport Studsvik/Barnwell | Those 10 shipments included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments. | ||
SONGS maintains a contract with Studsvik that provides volume reduction services. The processed volume was shipped from the Studsvik facility to Barnwell using 1 shipment. | |||
The shipment included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments. | |||
Truck/Flatbed Trailer Evr~rU | |||
The processed volume was shipped from the Duratek facility to EnviroCare using 10 shipments. | |||
Those 10 shipments included waste from other generators. | |||
SCE's waste volume was a small fraction of the total waste volume of these shipments. | |||
The processed volume was shipped from the Studsvik facility to Barnwell using 1 shipment. | |||
The shipment 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) | B. IRRADIATED FUEL SHIPMENTS (Disposition) | ||
Number of Shipments Mode of Transportation Destination X None No shipments were made l N/A A C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Number of Shipments Mode of Transportation Destination X | ||
2 and 3 SECTION F APPITCARLF LIMITS | None No shipments were made l N/A A | ||
-Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, C, and D of Table 1A, were calculated using the following equation: | C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
= Maximum Permissible Concentration (MPC) of the jth radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.(Rel Rate) (X/Q) (100)ECLeff% ECL where: Rel Rate X/Q total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, uCi/sec.= 4.80E-6 sec/m3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM.1= E F.1=1 ECL i o ECLetf where: F.fractional abundance of the ij radionucl ide obtained dividing the activity (curies) for each radionuclide, by the sum of all the isotopic activity, C T.by C, n ECL,= total number of radionuclides identified | S.O.N.G.S. 2 and 3 SECTION F APPITCARLF 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: | ||
= Effluent Concentration Limit (ECL) of the ijh radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1. | % Applicable Limit where: | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | Rel Rate X/Q o | ||
2 and 3 Liouid Effluents | MPCefI where: | ||
-Aoplicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations: | F. | ||
* % Applicable Limit where: Dil Conc o MPCeff where: Fj= (Dil Conc) (100)MPCeff= total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2., and C.2 of Table 2A, pCi/ml.1 F1 j.: MPC ;= fractional abundance of the i th radionuclide obtained by dividing the activity (curies) for each radionuclide, C;, by the sum of all the isotopic activity, C T.n MPC,= total number of radionuclides identified | = | ||
= Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.= (Dil Conc) (100)ECLeff | (Rel Rate) | ||
= Effluent Concentration Limit (ECL) of the ith radionu:lide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2. | (X/Q) | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | (100) | ||
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 | MPCeff | ||
-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 | total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, uCi/sec. | ||
-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 a2 + G2 + CF + ... r2 where: a = Error associated with each component. | 4.80E-6 sec/M3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | 1 | ||
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. | = | ||
Fi 1.1 MPC i | |||
= | |||
fractional abundance of the ijh radionuclide obtained by dividing the activity (curies) for each radionuclide, C,, | |||
by the sum of all the isotopic activity, C T. | |||
n MPC1 | |||
= | |||
total number of radionuclides identified | |||
= | |||
Maximum Permissible Concentration (MPC) of the jth radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1. | |||
(Rel Rate) | |||
(X/Q) | |||
(100) | |||
ECLeff | |||
% ECL where: | |||
Rel Rate X/Q total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, uCi/sec. | |||
= | |||
4.80E-6 sec/m3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM. | |||
1 | |||
= | |||
E F. | |||
1=1 ECL i o | |||
ECLetf where: | |||
F. | |||
fractional abundance of the ij radionucl ide obtained dividing the activity (curies) for each radionuclide, by the sum of all the isotopic activity, C T. | |||
by C, | |||
n | |||
: ECL, | |||
= | |||
total number of radionuclides identified | |||
= | |||
Effluent Concentration Limit (ECL) of the ijh radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 Liouid Effluents - Aoplicable 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 where: | |||
Fj | |||
= | |||
(Dil Conc) (100) | |||
MPCeff | |||
= | |||
total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2., and C.2 of Table 2A, pCi/ml. | |||
1 F1 j.: | |||
MPC ; | |||
= | |||
fractional abundance of the i th radionuclide obtained by dividing the activity (curies) for each radionuclide, C;, | |||
by the sum of all the isotopic activity, C T. | |||
n | |||
: MPC, | |||
= | |||
total number of radionuclides identified | |||
= | |||
Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2. | |||
= | |||
(Dil Conc) (100) | |||
ECLeff | |||
% ECL 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, uCi/ml. | |||
I | |||
_n FC irl ECL ; | |||
0 ECLeff where: | |||
Fj n | |||
ECL1 | |||
= | |||
fractional abundance of the i h radionuclide obtained by dividing the activity (curies) for each radionuclide,, C,, | |||
by the sum of all the isotopic activity, C T. | |||
= | |||
total number of radionuclides identified | |||
= | |||
Effluent Concentration Limit (ECL) of the ith radionu:lide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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 a2 + G2 + CF | |||
+... r2 where: | |||
a | |||
= | |||
Error associated with each component. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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)Licuid Effluents | (1) | ||
-Whole Body Licuid Effluents | (2) | ||
-Organ Airborne Effluents | (3) | ||
-Tritium, lodines 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 RETDAS (Radioactive Effluent Tracking and Dose Assessment Software), Regulatory Guide 1.109 methodology, and concurrent meteorology. | (4) | ||
Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using me:hods 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 I-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 1-2 & 2-2. | Licuid Effluents - Whole Body Licuid Effluents - Organ Airborne Effluents - Tritium, lodines 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 (2005)S.O.N.G.S. | Categories 3, 4, and 5 were calculated utilizing RETDAS (Radioactive Effluent Tracking and Dose Assessment Software), | ||
2 and 3 TABLE 1 Dose * (millirems) | 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 me:hods 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 in Table 1. | |||
presents the percent of Applicable Limits for each dose presented | |||
' ODCM Figures 1-2 & 2-2. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 TABLE 1 Dose * (millirems) | |||
First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS | First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS | ||
: 1) 2) 3) 4) 5)Whole Body 3.92E-4 1.17E-3 2.66E-4 8.43E-4 2.67E-3 6) 7) 8) 9) 10)Organ 1.38E-3 2.68E-3 1.37E-3 2.60E-3 8.03E-3 AIRBORNE EFFLUENTS | : 1) | ||
: 11) 12) 13) 14) 15)Tritium, lodines, and Particulates 1.11E-3 1.08E-3 1.24E-3 6.27E-4 3.93E-3 NOBLE GASES ** 16) 17) 18) 19) 20)Gamma 1.21E-2 1.62E-2 2.14E-2 1.99E-2 6.96E-2 21) 22) 23) 24) 25)Beta 2.24E-2 1.87E-2 1.67E-2 3.97E-2 9.75E-2 26) 27) 28) 29) 30)DIRECT RADIATION 1.65E-1 1.68E-1 1.49E-1 1.62E-1 6.12E-1 | : 2) | ||
: 3) | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 4) 5) | ||
2 and 3 6. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway.7. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway.8. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway.9. This value was calculated using the methodology of the ODCM; the GI-LLI recel primarily by the saltwater fish pathway.10. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway.11. The maxirium organ dose was to a teen's lung and was located in the NNW sector.using the assumptions of USNRC Regulatory Guide 1.109.12. The maximum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109.13. The maxirum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109.14. The maximum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109.15. The maximnum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109.ived the maximum dose ived the maximum dose ived the maximum dose ived the maximum dose ived the maximum dose I This was calculated | Whole Body 3.92E-4 1.17E-3 2.66E-4 8.43E-4 2.67E-3 | ||
[NE sector. This was[NW sector. This. was[NW sector. This. was[NW sector. This was 16. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions | : 6) | ||
: 7) | |||
: 8) | |||
: 9) 10) | |||
Organ 1.38E-3 2.68E-3 1.37E-3 2.60E-3 8.03E-3 AIRBORNE EFFLUENTS | |||
: 11) | |||
: 12) | |||
: 13) | |||
: 14) 15) | |||
Tritium, lodines, and Particulates 1.11E-3 1.08E-3 1.24E-3 6.27E-4 3.93E-3 NOBLE GASES ** | |||
: 16) | |||
: 17) | |||
: 18) | |||
: 19) 20) | |||
Gamma 1.21E-2 1.62E-2 2.14E-2 1.99E-2 6.96E-2 | |||
: 21) | |||
: 22) | |||
: 23) | |||
: 24) 25) | |||
Beta 2.24E-2 1.87E-2 1.67E-2 3.97E-2 9.75E-2 | |||
: 26) | |||
: 27) | |||
: 28) | |||
: 29) 30) | |||
DIRECT RADIATION 1.65E-1 1.68E-1 1.49E-1 1.62E-1 6.12E-1 The numbered footnotes below briefly explain how each maximum dose organ and the predominant pathway(s). | |||
Noble gas doses due to airborne effluent are in units of mrad, refl | |||
: 1. This value was calculated using the methodology of the ODCM. | |||
: 2. This value was calculated using the methodology of the ODCM. | |||
: 3. This value was calculated using the methodology of the ODCM. | |||
: 4. This value was calculated using the methodology of the ODCM. | |||
: 5. This value was calculated using the methodology of the ODCM. | |||
was calculated, including the ecting the air dose. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 | |||
: 6. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway. | |||
: 7. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway. | |||
: 8. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway. | |||
: 9. This value was calculated using the methodology of the ODCM; the GI-LLI recel primarily by the saltwater fish pathway. | |||
: 10. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway. | |||
: 11. The maxirium organ dose was to a teen's lung and was located in the NNW sector. | |||
using the assumptions of USNRC Regulatory Guide 1.109. | |||
: 12. The maximum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109. | |||
: 13. The maxirum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109. | |||
: 14. The maximum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109. | |||
: 15. The maximnum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109. | |||
ived the maximum dose ived the maximum dose ived the maximum dose ived the maximum dose ived the maximum dose I This was calculated | |||
[NE sector. This was | |||
[NW sector. This. was | |||
[NW sector. This. was | |||
[NW sector. This was | |||
: 16. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions | |||
: 17. The maximum air dose for gamma radiation was boundary, and calculated using the assumptions | : 17. The maximum air dose for gamma radiation was boundary, and calculated using the assumptions | ||
: 18. The maximum air dose for gamma radiation was boundary, and calculated using the assumptions | : 18. The maximum air dose for gamma radiation was boundary, and calculated using the assumptions | ||
| Line 421: | Line 1,646: | ||
: 20. The maximum air dose for gabma radiation was boundary, and calculated using the assumptions | : 20. The maximum air dose for gabma radiation was boundary, and calculated using the assumptions | ||
: 21. The maximum air dose for beta radiation was boundary, and calculated using the assumptions | : 21. The maximum air dose for beta radiation was boundary, and calculated using the assumptions | ||
: 22. The maximum air dose for beta radiation was of the USNRC Regulatory Guide 1.109.located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.23. The maxi:pum air dose for beta radiation was located in the NNE 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 of the USNRC Regulatory Guide 1.109. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109. | ||
2 and 3 24. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.25. The maximum air dose for beta radiation was located in the NNE 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 WSW 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 S 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 1.31E-2 3.91E-2 8.85E-3 2.81E-2 4.45E-2 Organ 1.38E-2 2.68E-2 1.37E-2 2.60E-2 4.02E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 7.39E-3 7.18E-3 8.29E-3 4.18E-3 1.31E-2 NOBLE GASES Gamma 1.21E-1 1.62E-1 2.14E-1 1.99E-1 3.48E-1 Beta 1.12E-1 9.37E-2 8.35E-2 1.98E-1 2.44E-1 NOTE: Direct Radiation is not specifically addressed in the Applicable Limits. | located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109. | ||
2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 25, 2005, Revision 40 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. | located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109. | ||
This change incorporated | located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109. | ||
located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. | |||
The minor REMP sampling location change is administered by that program.None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. | : 23. The maxi:pum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. | ||
The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.35a and Appendix I to | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
Throughout the document, change bars are marked in one of four ways as follows: A Addition D Deletion F EIditorial/Format change R F'evision Page Change Reason ii Removed South Yard Facility from section 2.6.5 D 2-10 Defined flowpath admin factors with variables. | S.O.N.G.S. 2 and 3 | ||
D,R 2-11 Revised definition PVS admin factor R 2-13 Revised definition of CAE admin factor R 2-15 Revised definition of CP admin factor R 2-16 Revised definition of CP admin factor R 2-17 Removed main purge flow rate which is N/A for RT-7865 D 2-19 Revised definition of waste gas admin factor R 2-20 Removed South Yard Facility monitor setpoint determination from section 2.6.5 D 2-21 Removed South Yard Facility monitor setpoint determination from section 2.6.5 0 2-28 Replaced equation 2-26 that was mistakenly deleted last revision F 2-31 Revised the Controlling Location Factor Table per LUC R 2-32 Per LUC, updated selected Ri values. R 2-33 Per LUC, updated selected Ri values. R 2-34 Per LUC, updated selected Ri values. R ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 24. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. | ||
2 and 3 2-35 Per LUC, updated selected Ri values. R 2-36 Per LUC, updated selected Ri values. R 2-38 Per LUC, updated selected Ri values. R 2-40 Per LUC, updated selected Ri values. R 2-41 Per LUC, updated selected Ri values. R 2-42 Per LUC, updated all Ri values. R 2-43 Per LUC, updated selected Ri values. R 2-44 Per LUC, updated selected Ri values. R 2-45 Per LUC, updated selected Ri values. R 2-46 Per LUC, updated selected Ri values. R 2-47 Per LUC, updated selected Ri values. R 2-48 Per LUC, updated selected Ri values. R 2-49 Per LUC, updated selected Ri values. R 2-50 Per LUC, updated selected Ri values. R 2-51 Per LUC, updated selected Ri values. R 2-52 Per LUC, updated selected Ri values. R 2-53 Per LUC, updated selected Ri values. R 4-10 Assigned "a" or "b" to Action 36, specifying whether the action is related to F process or sample flow.4-11 Removed SYFRT-7904, SYFRT-7905 and SYF DAS datalink from Table 4-3. D 4-13 Removed Action 43 because SYF monitors were removed. D 4-15 Removed control room annunciation DAS as the datalink has been terminated. | : 25. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109. | ||
D 4-16 Removed SYFRT-7904, SYFRT-7905 and SYF DAS from Table 4-3. D 4-18 Removed notes 7 and 8 from Table 4-4 D 4-21 Modified Figure 4-6 to show P/I sampler only in SYF R 5-20 Modified control location for non-migratory marine animals R,A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 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. | ||
2 and 3 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Units 2&3 Radioactive Waste Treatment Systems during the reporting period, January 1, 2005 to December 31, 2005.SECTION K. MISCELLANEOUS None ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | : 27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the WSW sector. | ||
2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 -December 31, 2005 S.O.N.G.S. | : 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 S sector. | ||
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. | : 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. | ||
This event is documented in ARs 000101252 and 000400960. | : 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. | ||
2RT-7865 02/11/05 -03/24/05 Intermittent Heat Discovered that during times of Plant Vent Stack trace circuitry heavy rainfall, water intrusion (Containment inoperability wets the circuitry and insulation Purge) preventing system from maintaining Particulate and temperature. | TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 1.31E-2 3.91E-2 8.85E-3 2.81E-2 4.45E-2 Organ 1.38E-2 2.68E-2 1.37E-2 2.60E-2 4.02E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 7.39E-3 7.18E-3 8.29E-3 4.18E-3 1.31E-2 NOBLE GASES Gamma 1.21E-1 1.62E-1 2.14E-1 1.99E-1 3.48E-1 Beta 1.12E-1 9.37E-2 8.35E-2 1.98E-1 2.44E-1 NOTE: | ||
Initial repairs to Iodine Sampler circuitry made system operable.Permanent repairs planned. This event is documented in AR 050200818. | Direct Radiation is not specifically addressed in the Applicable Limits. | ||
2APC-4077 08/02/05 -12/09/05 Failure of Degraded material conditions lead Steam Generator composite sampler to failure. Also found inability to E088 Blowdown calibrate. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
A new composite sampler Compositor was installed. | S.O.N.G.S. 2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 25, 2005, Revision 40 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated 1) Removal of the requirements for *a particulate activity radiation monitor from the South Yard Facility, 2) Updates related to the 2003-2004 Land Use Census (LUC), 3) A minor change to a REMP sampling location and 4) Various administrative changes. | ||
An approved Effluent/ODCM Evaluation (EOE) was generated for item 1. Per NRC Generic Letter 89-01, no 50.59 or EOE reviews were required or performed for editorial changes made to reflect actual plant operation. The minor REMP sampling location change is administered by that program. | |||
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, 10CFR50.35a 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 | |||
EIditorial/Format change R | |||
F'evision Page Change Reason ii Removed South Yard Facility from section 2.6.5 D | |||
2-10 Defined flowpath admin factors with variables. | |||
D,R 2-11 Revised definition PVS admin factor R | |||
2-13 Revised definition of CAE admin factor R | |||
2-15 Revised definition of CP admin factor R | |||
2-16 Revised definition of CP admin factor R | |||
2-17 Removed main purge flow rate which is N/A for RT-7865 D | |||
2-19 Revised definition of waste gas admin factor R | |||
2-20 Removed South Yard Facility monitor setpoint determination from section 2.6.5 D | |||
2-21 Removed South Yard Facility monitor setpoint determination from section 2.6.5 0 | |||
2-28 Replaced equation 2-26 that was mistakenly deleted last revision F | |||
2-31 Revised the Controlling Location Factor Table per LUC R | |||
2-32 Per LUC, updated selected Ri values. | |||
R 2-33 Per LUC, updated selected Ri values. | |||
R 2-34 Per LUC, updated selected Ri values. | |||
R ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 2-35 Per LUC, updated selected Ri values. | |||
R 2-36 Per LUC, updated selected Ri values. | |||
R 2-38 Per LUC, updated selected Ri values. | |||
R 2-40 Per LUC, updated selected Ri values. | |||
R 2-41 Per LUC, updated selected Ri values. | |||
R 2-42 Per LUC, updated all Ri values. | |||
R 2-43 Per LUC, updated selected Ri values. | |||
R 2-44 Per LUC, updated selected Ri values. | |||
R 2-45 Per LUC, updated selected Ri values. | |||
R 2-46 Per LUC, updated selected Ri values. | |||
R 2-47 Per LUC, updated selected Ri values. | |||
R 2-48 Per LUC, updated selected Ri values. | |||
R 2-49 Per LUC, updated selected Ri values. | |||
R 2-50 Per LUC, updated selected Ri values. | |||
R 2-51 Per LUC, updated selected Ri values. | |||
R 2-52 Per LUC, updated selected Ri values. | |||
R 2-53 Per LUC, updated selected Ri values. | |||
R 4-10 Assigned "a" or "b" to Action 36, specifying whether the action is related to F | |||
process or sample flow. | |||
4-11 Removed SYFRT-7904, SYFRT-7905 and SYF DAS datalink from Table 4-3. | |||
D 4-13 Removed Action 43 because SYF monitors were removed. | |||
D 4-15 Removed control room annunciation DAS as the datalink has been terminated. | |||
D 4-16 Removed SYFRT-7904, SYFRT-7905 and SYF DAS from Table 4-3. | |||
D 4-18 Removed notes 7 and 8 from Table 4-4 D | |||
4-21 Modified Figure 4-6 to show P/I sampler only in SYF R | |||
5-20 Modified control location for non-migratory marine animals R,A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Units 2&3 Radioactive Waste Treatment Systems during the reporting period, January 1, 2005 to December 31, 2005. | |||
SECTION K. MISCELLANEOUS None ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 - | |||
December 31, 2005 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-7865 02/11/05 - | |||
03/24/05 Intermittent Heat Discovered that during times of Plant Vent Stack trace circuitry heavy rainfall, water intrusion (Containment inoperability wets the circuitry and insulation Purge) preventing system from maintaining Particulate and temperature. Initial repairs to Iodine Sampler circuitry made system operable. | |||
Permanent repairs planned. This event is documented in AR 050200818. | |||
2APC-4077 08/02/05 - | |||
12/09/05 Failure of Degraded material conditions lead Steam Generator composite sampler to failure. Also found inability to E088 Blowdown calibrate. A new composite sampler Compositor was installed. | |||
This event is documented in ARs 050800166 and 050900588. | This event is documented in ARs 050800166 and 050900588. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 -December 31, 2005 S.O.N.G.S. | S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 - December 31, 2005 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. | ||
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. | Flow Monitor vacuum pump is Substitute flow value is running. | ||
This event is documented in ARs 000101252 and 000400960. | 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 02/18/05 -05/05/05 Intermittent heat Investigation of the heat trace Plant Vent Stack trace circuitry circuitry found water-damaged (Containment inoperability insulation at the roof penetration. | 3RT-7865 02/18/05 - 05/05/05 Intermittent heat Investigation of the heat trace Plant Vent Stack trace circuitry circuitry found water-damaged (Containment inoperability insulation at the roof penetration. | ||
Purge) Particulate Initial repairs to circuitry made and Iodine Sampler system operable. | Purge) Particulate Initial repairs to circuitry made and Iodine Sampler system operable. Permanent repairs planned. This event is documented in ARs 050401453 and 050201162. | ||
Permanent repairs planned. This event is documented in ARs 050401453 and 050201162. | 3APC-4076 12/22/04 - 05/11/05 Faulty voltage Initial investigation resulted in Steam Generetor regulator the ordering of wrong part with E089 Blowdown long lead time. Further Compositor investigation found bad capacitor on voltage regulator. Release occurred only six days during this time period. This event is documented in AR 041201355. | ||
3APC-4076 12/22/04 -05/11/05 Faulty voltage Initial investigation resulted in Steam Generetor regulator the ordering of wrong part with E089 Blowdown long lead time. Further Compositor investigation found bad capacitor on voltage regulator. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
Release occurred only six days during this time period. This event is documented in AR 041201355. | S.O.N.G.S. 2 and 3 SECTION L. S.O.N.G.S. 2 and 3 CONCLUSIONS Gaseous releases totaled 1.79E+2 curies of which noble gases were 1.28E+2 curies, iodines were 2.87E-4 curies, particulates were 4.61E-4 curies, and tritium was 5.07E+1 curies. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)S.O.N.G.S. | The radiation doses from gaseous releases were: (a) gamma air dose: 6.96E-2 mrad at the site boundary, (b) beta air dose: 9.75E-2 mrad at the site boundary, (c) organ dose: 3.93E-3 mrem at the nearest receptor. | ||
2 and 3 SECTION L. S.O.N.G.S. | Liquid releases totaled 1.13E+3 curies of which particulates and iodines were 2.97E-2 curies, tritium was 1.13E+3 curies, and noble gases were 7.78E-2 curies. | ||
2 and 3 CONCLUSIONS | The radiation doses from liquid releases were: (a) total body: 2.67E-3 mrem, (b) limiting organ: 8.03E-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 (2005)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 m1 N/A sludges, evaporator bottoms Ci N/A N/A b. Dry active waste (DAW), | COMMON | ||
* Ci 6.16E-4 3.OOE+1 | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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 m1 N/A sludges, evaporator bottoms Ci N/A N/A | |||
: b. Dry active waste (DAW), | |||
m3 3.26E+O compactable and non-compactable | |||
* Ci 6.16E-4 3.OOE+1 m3 N/A | |||
: c. Irradiated components Ci N/A N/A m3 NIA | |||
: d. Other (filters) i N/A N/A Note: | |||
Total curie content estimated. | |||
Material packaged in various packagings. | |||
General Design, IP-1, USA DOT 7A, and Type A N/A No shipment made. | General Design, IP-1, USA DOT 7A, and Type A N/A No shipment made. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)COMMON 2. Estimate of major nuclide composition (by type of waste)a. not applicable l | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
COMMON | |||
: 2. | |||
Estimate of major nuclide composition (by type of waste) | |||
: a. not applicable l | |||
N/A | |||
: b. americium-241 4.56E-04 antimony-124 3.00E-O1 antimony-125 1.16E+OO carbon-14 2.03E+OO cerium-144 3.73E-O1 cesium-134 3.65E+oo cesium-137 1.88E+O0 chromium-51 4.22E+00 cobalt-57 3.10E-O1 cobalt-58 2.32E+01 cobalt-60 4.85E+OO curium-242 1.85E-03 curium-243/244 3.04E-03 iron-55 4.06E+01 iron-59 1.44E+OO manganese-54 1.64E+OO nickel-59 4.03E-O1 nickel-63 8.86E+OO niobium-95 2.78E+OO plutonium-238 7.73E-04 plutonium-239/240 2.89E-04 pl utoni um-241 6.61E-02 stronti um-89 1.25E-02 strontium-90 2.16E-03 zirconium-95 2.34E+OO | |||
: c. not applicable N/A | |||
: d. not applicable N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
1, 2, and 3)Number of Shipments Mode of Transportation Destination 1 TAG Transport Truck EnviroCare, UT IRRADIATED FUEL SHIPMENTS (Disposition) | COMMON A. | ||
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 D. CHANSES TO THE PROCESS None.CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 | 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 1 | |||
TAG Transport Truck EnviroCare, UT 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 D. | |||
CHANSES TO THE PROCESS None. | |||
CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 | |||
==REFERENCES:== | ==REFERENCES:== | ||
: 1. Ulit 1 Technical Specifications, section D6.13.2.2. U1its 2 and 3 License Controlled Specifications, section 5.0.103.2.2. | : 1. Ulit 1 Technical Specifications, section D6.13.2. | ||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)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. | : 2. U1its 2 and 3 License Controlled Specifications, section 5.0.103.2.2. | ||
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 6.71E-1 b. Percent ODCM Specification Limit 2.68E+O 2. Limiting Organ a. Organ Dose (GI-LLI) mrem 8.63E-2 b. Percent ODCM Specification Limit 3.45E-1 3. Thyroid a. Thyroid Dose mrem 1.22E-2 b. Percent ODCM Specification Limit __1.63E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. | ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | ||
1, 2 and 3 totaled 1.79E+2 curies of Ahich noble gases were 1.28E+2 curies, iodines were 2.87E-4 curies, particulates were 4.61E-4 curies, and tritium was 5.07E+1 curies. | 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. | ||
1, 2 and 3 totaled 1.15E+3 curies of which iodines were 4.37E-2 curies, tritium was 1.15E+3 curies, and 7.78E-2 curies. | These values were calculated utilizing doses resulting from all effluent pathways and direct radiation. The different categories presented are: (1) Total Body, (2) Limiting Organ, and (3) Thyroid. | ||
1, 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents. | Dose Category Units Year | ||
: 1. Total Body | |||
1, 2 and 3 made 245 radwaste shipments to Envirocare, UT and 5 shipments to Barnwell, SC. Total volume was 3.66E+3 cubic meters containing 3.71E+2 curies of radioactivity. | : a. Total Body Dose mrem 6.71E-1 | ||
Meteorological conditions during the year were typical Meteorological dispersion was good 36% of the time, fair 38%poor 26% of the time.for S.O.N.G.S. | : b. Percent ODCM Specification Limit 2.68E+O | ||
of the time and | : 2. Limiting Organ | ||
: a. Organ Dose (GI-LLI) mrem 8.63E-2 | |||
: b. Percent ODCM Specification Limit 3.45E-1 | |||
: 3. Thyroid | |||
: a. Thyroid Dose mrem 1.22E-2 | |||
: b. Percent ODCM Specification Limit | |||
__1.63E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 1.79E+2 curies of Ahich noble gases were 1.28E+2 curies, iodines were 2.87E-4 curies, particulates were 4.61E-4 curies, and tritium was 5.07E+1 curies. | |||
Liquid releases particulates and noble gases were from S.O.N.G.S. 1, 2 and 3 totaled 1.15E+3 curies of which iodines were 4.37E-2 curies, tritium was 1.15E+3 curies, and 7.78E-2 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 245 radwaste shipments to Envirocare, UT and 5 shipments to Barnwell, SC. | |||
Total volume was 3.66E+3 cubic meters containing 3.71E+2 curies of radioactivity. | |||
Meteorological conditions during the year were typical Meteorological dispersion was good 36% of the time, fair 38% | |||
poor 26% of the time. | |||
for S.O.N.G.S. | |||
of the time and The net result from the analysis of these effluent releases indicates thai: 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. | 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 (2005) | |||
COMMON APPENDIX A GASEOUS EFFLUENTS - APPLICABLE LIMITS A. | |||
Table 1A lists the total curies released and the release rate. The percent of applicable limit compares the released concentrations to the concentration limits of 10 CFR 20, Appendix B, Table II, Column 1. | |||
B. | |||
Table 1E lists the air doses as calculated using the historical X/Q. | |||
The air dose due to noble gases released in gaseous effluents from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values: | |||
: 1. During any calendar quarter: | |||
: 2. | |||
During any calendar year: | |||
5 mrad for gamma radiation and | |||
< 10 mrad for beta radiation. | |||
< 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: | |||
< 7.5 mrem to any organ. | |||
* 15 mrem to any organ. | |||
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
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, ;2005 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, 2005. | |||
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 (2005) | |||
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05010100-05033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A v | |||
o WIND DIR N | |||
NNE NE ENE E | |||
ESE SE SSE S | |||
SSW SW WSW W | |||
WNW NW NNW 22 51 I) | |||
I) | |||
I) | |||
I) 1) | |||
1) 1) | |||
I) | |||
I) | |||
I) | |||
I) | |||
I) | |||
I) | |||
I) | |||
I) | |||
.51 | |||
.75 | |||
-in 0 | |||
0 0 | |||
0 0 | |||
0 C | |||
EXTREMELY UNSTABLE 6 | |||
1.1 1.6 1.5 2.0 3 0 0 | |||
1 0 | |||
0 1 | |||
O 0 | |||
2 0 | |||
O 0 | |||
1 3 | |||
1 1 | |||
0 0 | |||
5 1 | |||
6 2 | |||
8 1 | |||
6 1 | |||
3 0 | |||
4 1 | |||
1 (DT/DZ 2.1 3.0 1 | |||
1 1 | |||
0 0 | |||
0 0 | |||
3 17 8 | |||
8 40 63 21 0 | |||
0 f -1.9 3.1 5.0 0 | |||
1 4 | |||
1 2 | |||
0 0 | |||
9 17 8 | |||
3 36 57 29 1 | |||
0 | |||
-C/100 METERS) 5.1 7.1 7.0 10.0 1 | |||
0 2 | |||
0 2 | |||
0 1 | |||
0 O | |||
0 O | |||
0 O | |||
0 2 | |||
1 2 | |||
0 O | |||
0 O | |||
0 0 | |||
0 3 | |||
0 11 1 | |||
O 0 | |||
O 0 | |||
10.1 13.0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 13.1 18.0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 | |||
>18 T(TAL 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
2 5 | |||
7 3 | |||
2 2 | |||
0 19 38 21 18 86 130 66 5 | |||
2 TOTALS 0 | |||
1 11 37 163 168 24 2 | |||
0 0 | |||
0 40 NUMBER OF VALID HOURS 406 NUMBER OF CALMS 0 | |||
NUMBER OF IN\\ALID HOURS 0 | |||
TOTAL HOURS FOR THE PERIOD 406 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 | |||
.53 | |||
.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 a | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
NE 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
1 0 | |||
0 0 | |||
0 1 | |||
ENE D | |||
0 0 | |||
0 0 | |||
0 0 | |||
2 0 | |||
0 0 | |||
0 2 | |||
E 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
ESE D | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
SE D | |||
0 0 | |||
0 0 | |||
0 1 | |||
0 1 | |||
0 0 | |||
0 2 | |||
SSE D | |||
0 0 | |||
1 0 | |||
1 2 | |||
0 1 | |||
0 0 | |||
0 5 | |||
S 3 | |||
0 0 | |||
0 0 | |||
1 0 | |||
4 0 | |||
0 0 | |||
0 5 | |||
SSW 0 | |||
0 0 | |||
1 2 | |||
2 3 | |||
0 0 | |||
0 0 | |||
0 8 | |||
SW 3 | |||
0 0 | |||
1 1 | |||
5 0 | |||
2 0 | |||
0 0 | |||
0 9 | |||
WSW 0 | |||
0 0 | |||
2 1 | |||
3 0 | |||
0 0 | |||
0 0 | |||
0 6 | |||
W 0 | |||
0 0 | |||
1 2 | |||
2 0 | |||
0 0 | |||
0 0 | |||
0 5 | |||
WNW 0 | |||
0 0 | |||
1 4 | |||
2 2 | |||
0 0 | |||
0 0 | |||
0 9 | |||
NW 0 | |||
0 0 | |||
0 1 | |||
1 3 | |||
0 0 | |||
0 0 | |||
0 5 | |||
NNW 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
TOTALS 0 | |||
0 0 | |||
7 11 17 12 9 | |||
2 0 | |||
0 0 | |||
58 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 58 0 | |||
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0 | |||
58 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05010100-05033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 -C/100 METERS) | |||
WIND DIR N | |||
NNE NE ENE E | |||
ESE SE SSE S | |||
SSW SW WSW W | |||
WNW NW NNW | |||
.22 | |||
.50 | |||
.51 | |||
.75 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 | |||
.76 1.0 0 | |||
0 0 | |||
0 00 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
1.1 1.5 0 | |||
0 1 | |||
0 0 | |||
0 0 | |||
0 0 | |||
1 1 | |||
1 1 | |||
1 0 | |||
0 1.6 2.0 0 | |||
0 0 | |||
1 0 | |||
0 1 | |||
1 1 | |||
2 2 | |||
1 3 | |||
0 0 | |||
2.1 3.0 0 | |||
1 0 | |||
0 0 | |||
0 1 | |||
1 0 | |||
3 2 | |||
2 3 | |||
7 2 | |||
0 3.1 5.0 0 | |||
0 1 | |||
0 0 | |||
0 0 | |||
3 1 | |||
0 0 | |||
1 0 | |||
3 2 | |||
0 5.1 7.0 0 | |||
0 0 | |||
1 0 | |||
4 2 | |||
1 1 | |||
0 0 | |||
0 1 | |||
0 0 | |||
7.1 10.0 0 | |||
0 0 | |||
0 0 | |||
0 2 | |||
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 | |||
0 | |||
>18 TOTAL 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 1 | |||
1 2 | |||
0 2 | |||
0 5 | |||
9 3 | |||
6 5 | |||
6 5 | |||
15 4 | |||
0 TOTALS 0 | |||
0 0 | |||
6 13 22 11 10 2 | |||
0 0 | |||
0 64 NUMBER OF VALID HOURS 64 NUMBER OF CALMS 0 | |||
NUMBER OF INVALID HOURS 0 | |||
TOTAL HOURS FOR THE PERIOD 64 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 4 | |||
7 5 | |||
3 0 | |||
0 0 | |||
0 0 | |||
19 NNE 0 | |||
0 0 | |||
11 11 18 1 | |||
0 0 | |||
0 0 | |||
0 41 NE 0 | |||
0 0 | |||
2 6 | |||
5 1 | |||
1 0 | |||
0 0 | |||
0 15 ENE 0 | |||
0 1 | |||
0 2 | |||
2 2 | |||
1 0 | |||
0 0 | |||
0 8 | |||
E 0 | |||
0 1 | |||
1 2 | |||
0 6 | |||
4 0 | |||
0 0 | |||
0 14 ESE 0 | |||
0 0 | |||
1 2 | |||
6 9 | |||
17 7 | |||
0 0 | |||
0 42 SE 0 | |||
0 0 | |||
3 3 | |||
7 38 37 25 2 | |||
0 0 | |||
115 SSE 0 | |||
0 0 | |||
3 5 | |||
6 17 13 22 7 | |||
8 0 | |||
81 S | |||
0 0 | |||
0 4 | |||
3 7 | |||
6 5 | |||
10 2 | |||
0 0 | |||
37 SSW 0 | |||
0 0 | |||
2 4 | |||
4 4 | |||
5 3 | |||
0 0 | |||
0 22 SW 1 | |||
0 0 | |||
5 2 | |||
4 9 | |||
2 2 | |||
0 0 | |||
0 25 WSW 0 | |||
0 2 | |||
2 1 | |||
4 8 | |||
2 1 | |||
0 0 | |||
0 20 W | |||
0 1 | |||
0 1 | |||
2 6 | |||
5 7 | |||
2 0 | |||
0 0 | |||
24 WNW 0 | |||
1 0 | |||
3 3 | |||
15 12 7 | |||
2 0 | |||
0 0 | |||
43 NW 0 | |||
0 1 | |||
1 6 | |||
14 15 1 | |||
1 0 | |||
0 0 | |||
39 NNW 0 | |||
0 1 | |||
8 6 | |||
011 5 | |||
0 0 | |||
0 0 | |||
0 31 TOTALS 1 | |||
2 6 | |||
51 65 114 141 102 75 11 8 | |||
0 576 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 576 0 | |||
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0 | |||
576 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05010100-05033123 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 | |||
ESE SE SSE S | |||
SSW SW WSW W | |||
WNW NW NNW TOTALS | |||
.*22 so 00 0 | |||
0 1 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 1 | |||
.51 | |||
.75 0 | |||
0 0 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 1 | |||
0 0 | |||
0 2 | |||
.76 1.0 0 | |||
2 1 | |||
1 1 | |||
0 0 | |||
0 0 | |||
0 1 | |||
0 0 | |||
0 0 | |||
1 1.1 1.5 7 | |||
16 0 | |||
6 2 | |||
1 2 | |||
0 1 | |||
1 0 | |||
1 1 | |||
3 0 | |||
2 43 1.6 2.0 12 14 3 | |||
1 4 | |||
5 3 | |||
1 1 | |||
1 0 | |||
1 2 | |||
0 1 | |||
4 53 2.1 3.0 11 20 5 | |||
3.1 5.0 1 | |||
7 3 | |||
5.1 7.0 0 | |||
0 0 | |||
7.1 10.0 0 | |||
0 0 | |||
10.1 13.0 0 | |||
0 0 | |||
6 5 | |||
8 2 | |||
5 4 | |||
2 2 | |||
0 3 | |||
3 5 | |||
8 1 | |||
15 5 | |||
7 2 | |||
1 1 | |||
0 3 | |||
1 5 | |||
5 3 | |||
60 3 | |||
3 6 | |||
12 9 | |||
0 0 | |||
0 0 | |||
1 2 | |||
2 0 | |||
1 2 | |||
0 8 | |||
8 3 | |||
1 1 | |||
0 2 | |||
1 1 | |||
0 28-1 1 | |||
0 0 | |||
0 3 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 13.1 18.0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 | |||
>18 TOTAL 31 59 12 21 34 25 34 25 13 6 | |||
4 5 | |||
11 14 14 18 326 NUMBER OF VALID HOURS 326 NUMBER OF CALMS 0 | |||
NUMBER OF IN'IALID HOURS 0 | |||
TOTAL HOURS FOR THE PERIOD 326 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 5 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 JOTAL DIR | |||
.EO | |||
.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N | |||
0 0 | |||
0 5 | |||
5 5 | |||
3 0 | |||
0 0 | |||
0 0 | |||
18 NNE 0 | |||
0 0 | |||
15 38 71 17 1 | |||
0 0 | |||
0 0 | |||
142 NE 0 | |||
0 1 | |||
10 6 | |||
5 4 | |||
2 0 | |||
0 0 | |||
0 28 ENE 0 | |||
1 0 | |||
1 6 | |||
5 0 | |||
0 0 | |||
0 0 | |||
0 13 E | |||
0 0 | |||
1 1 | |||
3 2 | |||
1 0 | |||
01 0 | |||
0 0 | |||
8 ESE 0 | |||
0 0 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 1 | |||
SE 0 | |||
0 0 | |||
0 1 | |||
2 0 | |||
0 0 | |||
0 0 | |||
0 3 | |||
SSE 0 | |||
0 1 | |||
0 0 | |||
1 2 | |||
0 0 | |||
0 0 | |||
0 4 | |||
S 0 | |||
0 0 | |||
2 0 | |||
2 0 | |||
0 0 | |||
0 0 | |||
0 4 | |||
SSW 0 | |||
0 1 | |||
2 0 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 3 | |||
SW 0 | |||
0 0 | |||
3 0 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 4 | |||
WSW 0 | |||
0 1 | |||
0 2 | |||
0 0 | |||
0 0 | |||
0 0 | |||
0 3 | |||
W 0 | |||
0 0 | |||
1 4 | |||
1 0 | |||
0 0 | |||
0 0 | |||
0 6 | |||
WNW 3 | |||
0 1 | |||
2 2 | |||
1 2 | |||
0 0 | |||
0 0 | |||
0 11 NW 0 | |||
0 0 | |||
1 0 | |||
1 2 | |||
0 0 | |||
0 0 | |||
0 4 | |||
NNW 0 | |||
0 0 | |||
2 2 | |||
3 2 | |||
0 0 | |||
0 0 | |||
0 9 | |||
TOTALS 3 | |||
1 6 | |||
46 69 100 33 3 | |||
0 0 | |||
0 0 | |||
261 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 261 0 | |||
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0 | |||
261 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005) | |||
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05010100-05033123 WIND SPEED (M/S) AT 10 METER LEVEL WIND | |||
.22 DIR | |||
.50 N | |||
0 NNE 0 | |||
NE 0 | |||
ENE 0 | |||
E 0 | |||
ESE 0 | |||
SE 0 | |||
SSE 0 | |||
S 0 | |||
SSW 0 | |||
SW 0 | |||
WSW 0 | |||
W 0 | |||
WNW I | |||
NW 0 | |||
NNW 0 | |||
TOTALS 1 | |||
.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 1 | |||
1 0 | |||
0 0 | |||
0 0 | |||
2 0 | |||
1 5 | |||
PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS) 1.1 1.6 2.1 3.1 5.1 7.1 1.5 2.0 3.0 5.0 7.0 10. | |||
Latest revision as of 09:24, 15 January 2025
| ML061170414 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 12/31/2005 |
| From: | Southern California Edison Co |
| To: | NRC/FSME |
| References | |
| Download: ML061170414 (107) | |
Text
SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2005 January - December
Ii\\ ISOUTHERN CALIFORNIA EDISONS An EDISON INTERNATIOINALe 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 cn November 30, 1992.
By August 31, 2004, all fuel was transferred to the Independent Spent Fuel Storage Installation (ISFSI).
Unit 1 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 ret megawatts electrical each.
The twin units are owned by Southern California Edison (75.05%), San Diego Gas and Electric (20%),
City of Anaheim (3.1.6%),
and the City of Riverside (1.79%).
P.O. Bo 128 San Clemnente, CA 92674-0128
S.O.N.G.S. 1
TABLE OF CONTENTS SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION SECTION INTRODUCTION..............
- GASEOUS EFFLUENTS............
- LIQUID EFFLUENTS............
- PREVIOUS RADIOACTIVE EFFLUENT RELEASE REP
- RADWASTE SHIPMENTS...........
- APPLICABLE LIMITS............
- ESTIMATION OF ERROR...........
10 CFR 50 APPENDIX I REQUIREMENTS....
- CHANGES TO OFFSITE DOSE CALCULATION MANUA
...AD
'ORT ADD 1
2 8
IENDUM....... 16
.......... 17
.......... 23
.......... 25
.......... 26
.......... 30
.......... 33
.......... 35
.......... 38 L
J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS K - MISCELLANEOUS.................
L - S.O.N.G.S. 1 CONCLUSIONS...........
-_ I-
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 Generatinc 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 (2005)
S.O.N.G.S. 1 SECTION B. GASEOUS EFFLUENTS Table IA, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous. effluents released quarterly in four categories:
fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.
Listed for each of the four categories are:
(1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total error As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, anc therefore are no longer measured. All the fuel is stored in the ISFSH and the plant is being demolished.
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 errcor 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. As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, and therefore are no longer measured. All the fuel is stored in the ISFSI and the plant is being demolished.
Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC for continuous mode releases only.
Table IE, "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 (2005)
S.O.N.G.S. 1 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1
Estimated First Second Total Quarter Quarter Error, %
A. Fission and activation gases
- 1. Total release Ci N/A N/A N/A
- 2. Average release rate for period pCi/sec N/A N/A
- 3. Percent of applicable limit
% MPC N/A N/A
- 4. Percent Effluent Concentration Limit
- 1. Total iodine-131 Ci N/A N/A N/A
- 2. Average release rate for period pCi/sec N/A N/A
- 3. Percent of applicable limit
% MPC N/A N/A
- 4. Percent Effluent Concentration Limit
% ECL N/A N/A C. Particulates
- 1. Particulates with half-lives >8 days Ci
<LLD 4.45E-7 1.60E+1
- 2. Average release rate for period uCi/sec O.OOE+O 5.66E-8
- 3. Percent of applicable limit
% MPC O.OOE+O 1.47E-7
- 4. Percent Effluent Concentration Limit
% ECL O.OOE+O 3.68E-7
- 5. Gross alpha activity Ci
<LLD
<LLD 5.OOE+1 D. Tritium
- 1. Total release Ci
<LLD
<LLD 2.50E+1
- 2. Average release rate for period lCi/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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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. Tot~al release Ci N/A N/A N/A
- 2. Average release rate for period pCi/sec N/A N/A
- 3. Percent of applicable limit
% MPC N/A N/A
- 4.
Percent Effluent Concentration Limit
- 1. To-:al iodine-131 Ci N/A N/A N/A
- 2.
Average release rate for period pCi/sec N/A N/A
- 3.
Percent of applicable limit
% MPC N/A N/A
- 4.
Percent Effluent Concentration Limit
% ECL N/A N/A C. Particulates
- 1. Pa-ticulates with half-lives >8 days Ci
<LLD
<LLD 1.60[:÷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
- 5.
Gross alpha activity Ci
<LLD
<LLD 5.OOE+1 D. Tritium
- 1. Total release Ci
<LLD
<LLD 2.501E+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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 TABLE 1C GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE 1
First j Second l Third Fourth Radionuclides Released Unit Quarter l Quarter Quarter Quarter
- 1. Fission and activation gases krypton-85 Ci N/A N/A N/A N/A krypton-85m Ci N/A N/A N/A N/A krypton-87 Ci N/A N/A N/A N/A krypton-88 Ci N/A N/A N/A N/A xenon-133 Ci N/A N/A N/A N/A xenon-133m Ci N/A N/A N/A N/A xenon-135 Ci N/A N/A N/A N/A xenon-135m Ci N/A N/A N/A N/A xenon-138 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A
- 2. Iodines iodine-131 Ci N/A N/A N/A N/A iodine-133 Ci N/A N/A N/A N/A iodine-135 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A
- 3. Particulates barium-140 Ci
<LLD
<LLD
<LLD
<LLD cerium-141 Ci
<LLD
<LLD
<LLD
<LLD cerium-144 Ci
<LLD
<LLD
<LLD
<LLD cesium-134 Ci
<LLD
<LLD
<LLD
<LLD cesium-137 Ci
<LLD 4.45E-7
<LLD
<LLD cobalt-58 Ci
<LLD
<LLD
<LLD
<LLD 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.
NOTE:
Due to the permanent shutdown longer conducted.
of S.O.N.G.S. 1, "BATCH MODE" releases are no ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (Ci/cc)
- 1. Fission and activation gases kryptl)n-85 N/A krypton-85m N/A krypton-87 N/A krypton-88 N/A xenon-133 N/A xenon.-133m N/A xenon.-135 N/A xenon-135m N/A xenon -138 N/A
- 2. Iodines iodine-131 N/A iodine-133 N/A jodi ne-135 N/A
- 3. Particulates bariuin-140 4.30E-13 ceriuin-141 5.50E-14 ceriumn-144 2.20E-13 cesiuin-134 1.20E-13 cesiuin-137 1.OOE-13 cobalt-58 1.10E-13 cobalt-60 1.70E-13 iron-59 2.70E-13 lanthanum-140 8.50E-13 mangaliese-54 1.10E-13 molybdenum-99 6.50E-14 strontium-89 1.OOE-11 strontium-90 1.OOE-11 zinc-55 2.90E-13
- 4. alpha 1.OOE-11
- 5. tritiim 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 (2005)
S.O.N.G.S. 1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY l First l Second Third l Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas
- 1. Gamma Air Dose mrad N/A N/A N/A N/A
- 2. Percent Applicable Limit N/A N/A N/A N/A
- 3. Beta Air Dose mrad N/A N/A N/A N/A
- 4. Percent Applicable Limit N/A N/A N/A N/A B. Tritium, Iodine, Particulates (at the nearest receptor)
- 1.
Organ Dose mrem O.OOE+O 4.80E-6 O.OOE+O O.OOE+O
- 2.
Percent Applicable Limit O.OOE+O 6.40E-5 O.OOE+O O.OOE+O NOTE:
Calculations performed in accordance with the ODCM utilizing the historical X/Q.
TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE
SUMMARY
NOTE:
Due to the permanent shutdown of S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 As of the fourth quarter of 2004, the noble gas and iodine source terms no longer exist, and therefore are no longer measured. All the fuel is stored in the ISFSI and the plant is being demolished.
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 radionuclije released is listed for each quarterly period by both "continuous" and "batch" modes of release. As of the fourth quarter of 2004, the noble gas and icdine source terms no longer exist, and therefore are no longer measured. All the fuel is stored in the ISFSI and the plant is being demolished. As of the third quarter 2005 there are no longer batch releases being conducted due to the demolition of the liquid radwaste system.
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 (2005)
S.O.N.G.S. 1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter Estimated Second Total Quarter Error, %
.5
_3 A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 6.09E-3 6.91E-3 1.90E+1
- 2. Average diluted concentration during period yCi/ml 1.52E-9 2.18E-12
- 3. Percent of applicable limit
% MPC 1.05E-2 9.36E-6
- 4.
Percent Effluent Concentration Limit
% ECL 1.25E-1 1.08E-4 B. Tritium
- 1. Total release Ci 1.93E+1 4.74E-1 1.90E+1
- 2. Average diluted concentration during period yCi/ml 4.81E-6 1.50E-10
- 3. Percent of applicable limit
% MPG 1.60E-1 4.99E-6
- 4.
Percent Effluent Concentration Limit
% ECL 4.81E-1 1.50E-5 C. Dissolved and entrained gases
- 1. Total release Ci N/A N/A N/A
- 2. Average diluted concentration during period pCi/ml N/A N/A
- 3.
Percent of applicable limit
% MPC N/A N/A
- 4. Percent Effluent Concentration Limit
% MPC N/A N/A D. Gross alpha radioactivity
- 1. Total release Ci
<LLD 5.16E-5 5.0OE+1 E. Volume of waste released (batch &
continuous, prior to dilution) liters 2.16E+7 1.30E+6 5.00E+O F. Volume of dilution water used during period liters 4.01E+9 3.17E+12 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 TABLE 2A (Continued)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES l
Estimated Third Fourth Total Unit Quarter Quarter Error, %
A. Fissicn and activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 9.60E-7 9.70E-4 1.90E+1
- 2. Average diluted concentration during period pCi/ml 3.83E-13 9.21E-10
- 3. Percent of applicable limit
% MPC 1.91E-6 4.60E-3
- 4. Percent Effluent Concentration Limit
% ECL 3.83E-5 9.08E-2 B. Tritium
- 1. Total release Ci 1.80E-3 1.35E+D 1.90E+1
- 2. Average diluted concentration during period pCi/ml 7.18E-10 1.28E-6
- 3. Percent of applicable limit
% MPC 2.39E-5 1.22E-1
- 4. Percent Effluent Concentration Limit
% ECL 7.18E-5 1.28E-1 C. Dissolved and entrained gases
- 1. Total release Ci N/A N/A N/p
- 2. Average diluted concentration during period pCi/ml N/A N/A
- 3. Percent of applicable limit
% MPC N/A N/A
- 4. Percent Effluent Concentration Limit
% ECL N/A N/A D. Gross alpha radioactivity
- 1. Total release Ci
<LLD
<LLD 5.OOE--+1 E. Volume of waste released (batch &
continuous, prior to dilution) liters 5.50E+7 2.02E+8 5.OOl+O F. Volume of dilution water used during period liters 2.51E+9 1.05E+9 5.00l+0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released I Unit I Quarter I 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 5.03E-6 cesium-137 Ci
<LLD 6.70E-6 9.60E-7 9.44E-4 chromium-51 Ci
<LLD
<LLD
<LLD
<LLD cobalt-58 Ci
<LLD
<LLD
<LLD
<LLD cobalt-60 Ci
<LLD
<LLD
<LLD 2.06E-5 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 6.70E-6 9.60E-7 9.70E-4
- 2. Dissolved and entrained gases xenon-133 Ci N/A N/A N/A N/A xenon-135 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A LLD Lower Limit of Detection; see Table 2C.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 bariumn-140 Ci
<LLD
<LLD N/A N/A cerium-141 Ci
<LLD
<LLD N/A N/A cerium-144 Ci
<LLD
<LLD N/A N/A cesiuin-134 Ci 4.72E-5 5.74E-5 N/A N/A cesiumn-137 Ci 4.32E-3 1.96E-3 N/A N/A chromium-51 Ci
<LLD
<LLD N/A N/A cobalt-58 Ci
<LLD
<LLD N/A N/A cobalt-60 Ci 1.68E-3 4.02E-3 N/A N/A iodine-131 Ci
<LLD
<LLD N/A N/A iron-55 Ci
<LLD 8.28E-4 N/A N/A iron-!59 Ci
<LLD
<LLD N/A N/A lanthanum-140 Ci
<LLD
<LLD N/A N/A manganese-54 Ci
<LLD
<LLD N/A N/A molybdenum-99 Ci
<LLD
<LLD N/A N/A niobium-95 Ci
<LLD
<LLD N/A N/A strontium-89 Ci
<LLD 1.32E-5 N/A N/A stron ium-90 Ci 4.34E-5 1.56E-5 N/A N/A technietium-99m Ci
<LLD
<LLD N/A N/A zinc-l;5 Ci
<LLD
<LLD N/A N/A zirconium-95 Ci
<LLD
<LLD N/A N/A Total for period Ci 6.09E-3 6.90E-3 N/A N/A
- 2. Dissolved and entrained gases xenon.-133 Ci N/A N/A J
N/A N/A xenon.-135 Ci N/A N/A N/A N/A Total for period Ci N/A N
N/A l
N/A l
N/A =
N/A No releases conducted LLD Lower Limit of Detection; see Table 2C.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides l
LLD (pCi/cc)
- 1. Fission and activation products barium-140 2.90E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 7.50E-8 cesium-137 6.40E-8 chromium-51 3.30E-7 cobalt-58 6.80E-8 cobalt-60 1.OOE-7 iodine-131 5.70E-8 iron-55 1.OOE-6 iron-59 1.60E-7 lanthanum-140 5.60E-7 manganese-54 6.70E-8 molybdenum-99 5.60E-8 niobium-95 6.80E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.70E-7 zirconium-95 1.20E-7
- 2. Dissolved and entrained gases xenon-133 N/A xenon-135 N/A
- 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 TABLE 2C (Continued)
LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides LLD (Ci/cc)
- 1. Fission and activation products bariuri-140 2.40E-7 ceri uri-141 4.OOE-8 ceriuri-144 1.70E-7 chrom um-51 3.OOE-7 cobalt -58 6.60E-8 iodine-131 4.30E-8 iron-55 1.OOE-6 iron-59 1.50E-7 lanthanum-140 1.80E-7 manganese-54 6.70E-8 molybdenum-99 2.70E-8 niobium-95 6.40E-8 stront:ium-89 5.OOE-8 technetium-99m 2.70E-8 zinc-65 1.70E-7 zirconium-95 1.10E-7
- 2. Disso'ved and entrained gases xenon-*133 N/A xenon*-135 N/A
- 3. gross alpha 1.00E-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A..
A.
- 1. Total body dose mrem 1.61E-2 1.31E-2 7.08E-6 3.09E-3
- 2. Percent Applicable Limit 1.07E+O 8.71E-1 4.72E-4 2.06E-1 B.
- 1. Limiting organ dose mrem 2.11E-2 4.95E-2 1.06E-5 4.52E-3
- 2. Percent Applicable Limit 4.23E-1 9.89E-1 2.12E-4 9.05E-2
- 3. Limiting organ for period GI-LLI GI-LLI Liver Liver
S.O.N.G.S. 1 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE
SUMMARY
12 month period
- 1. Number of batch releases:
9 releases
- 2. Total time period for batch releases:
12875 minutes
- 3.
Maximum time period for a batch release:
1722 minutes
- 4. Average time period for a batch release:
1431 minutes
- 5. Minimum time period for a batch release:
990 minutes
- 6. Average saltwater flow during batch releases:
13222 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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) 12 month Estimated total
- 1. Type of waste Unit period error (%)
- a. Spent resins, filter sludges, m3 1.13E+1 evaporator bottoms
- Ci 2.59E+2 3.0OE+1
- b. Dry active waste (DAW),
m3 3.58E+3 compactable and non-compactable (incl. demolition rubble) **
Ci 3.68E+O 3.OOE+1
- c. Irradiated components m3 2.06E+1 (Structural members & reactor piping) **
Ci 1.05E+2 3.0OE+1
- d. Other: (Mechanical filters)#
m 3
1.45E+O Ci 1.90E+O 3.0OE+1 NOTE: Total curie content estimated.
Material packaged in Type A or Type B casks.
Material packaged in various General Design, IP-1, USA DOT 7A Type A, or Type A packagings.
Material packaged in General Design Packaging.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1
- 2. Estimate of major nuclide composition (by type of waste)
- a.
americium-241 2.97E-3 carbon-14 6.88E-3 cerium-144 8.43E-2 cesium-134 2.04E+O cesium-137 8.70E+1 cobalt-60 3.78E+O curium-242 1.33E-5 curium-243/244 1.09E-3 iron-55 1.65E-1 nickel-59 5.69E-2 nickel-63 6.28E+O niobium-94 9.16E-3 plutonium-238
__2.83E-3 plutonium-239/240 1.04E-3 p1 utonium-241 5.97E-2 plutonium-242 3.49E-5 strontium-89 1.22E-2 strontium-90 3.11E-1 technetium-99 1.76E-2 tritium 2.87E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1
- 2. Estimate of major nuclide composition (by type of waste)
- b.
americium-241 3.64E-2 antimony-125 9.22E-4 carbon-14
_2.16E+O cerium-144 5.44E-1 cesium-134 2.73E+O cesium-137
__3.87E+l cobalt-57 8.71E-7 cobalt-60 2.03E+1 curium-242 2.50E-4 curium-243/244 1.16E-2 europium-155
__7.09E-5 iron-55 1.72E+1 manganese-54 3.12E-5 nickel-59 1.86E-2 nickel-63
__1.79E+1 niobium-94 4.68E-3 niobium-95 5.70E-2 plutonium-238 6.66E-3 plutonium-239/240 2.75E-3 plutonium-241 1.74E-1 ruthenium-106 1.27E-4 silver-llOm 6.92E-2 strontium-90 1.55E-1 tritium 4.78E-1 zirconium-95 6.37E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1
- 2. Estimate of major nuclide composition (by type of waste)
- c.
americium-241 1.35E-2 carbon-14 3.85E-2 cerium-144 7.71E-2 cesium-137 3.03E-2 cobalt-58 6.86E-2 cobalt-60 3.32E+1 curi um-242 2.12E-4 curium-243/244 6.79E-3 iodine-129 2.22E-4 iron-55 5.22E+1 manganese-54 3.15E-2 nickel-59 1.76E-1 nickel-63 1.33E+1 niobium-94 2.61E-4 p1 utonium-238 2.12E-2 plutonium-239/240 7.30E-3 plutonium-241 5.39E-1 strontium-90 2.39E-2 technetium-99 6.73E-4 tritium 4.09E-4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1
- 2. Estimate of major nuclide composition (by type of waste)
- d.
americium-241 7.32E-2 carbon-14 1.08E+O cerium-144 3.27E-2 cesium-134 5.37E+O cesium-137 2.97E+1 cobalt-57 1.70E-3 cobalt-58 5.08E-2 cobalt-60 2.14E+1 curium-242 4.83E-4 curium-243/244 2.29E-2 europium-154 3.65E-2 iron-55 1.59E+1 manganese-54 1.65E-2 ni ckel-59 1.04E-1 nickel-63 2.47E+1 niobium-94 3.31E-2 plutonium-238 4.88E-2 plutonium-239/240 2.05E-2 plutonium-241 9.89E-1 strontium-89 5.26E-3 strontium-90 7.74E-2 technetium-99
__2.56E-3 tritium 1.46E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 4
Hittman and TAG Transport Barnwell, SC Truck 149 Piazza and TAG Transport Envirocare, UT Truck 85 MHF Logistical Solutions Envirocare, UT Rail 2
- TAG Transport Duratek/Envirocare, UT Truck SONCS maintains a contract with Duratek that provides volume reduction services.
The processed volume was shipped from the Duratek facility to EnviroCare using 8 shipments. Those 8 shipments 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)
ENumDer of Shipments l Mode of Transportation Destination None No shipments Were made N/A C. DEWATERING ENumter of Containers Solidification Agent 3
N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 SECTION F. APPLICABLE LIMITS Gaseous Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, C.3, and D.3 of Table 1A, was calculated using the following equation:
- % Applicable Limit where:
Rel Rate X/Q 0
MPCeff where:
F,
=
(Rel Rate) (X/Q) (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, yCi/sec.
=
1.30E-5 sec/M3; the annual average atmospheric dispersion defined in the Unit 1 ODCM.
1
_n Fi i.1 MPC
=
fractional abundance of the ijt radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, C T.
n
=
total number of radionuclides identified
=
Maximum Permissible Concentration (MPC) of the ii" radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.
MPC1
% ECL
=
(Rel Rate) (X/Q) (100)
ECLeff 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, pCi/sec.
=
1.30E-5 sec/m3; the annual average atmospheric dispersion defined in the Unit 1 ODCM.
1
=n Fi EI 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, C T.
=
total number of radionuclides identified
=
Effluent Concentration Limit (ECL) of the ijh radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.
where:
F.
n
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 fcllowing 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, yCi/ml.
1 o
MPCet E
F1 i-1 MPC where:
Fj n
- MPC,
% ECL
=
fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C1, by the sum of all the isotopic activity, C T.
=
total number of radionuclides identified
=
Maximum Permissible Concentration (MPC) of the it' radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.
=
(Dil Conc) (100)
ECLeff where:
Dil Conc 0
ECLef
=
total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, pCi/ml.
1 n
Fi Ei 1=1 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, C T.
=
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.
where:
F1 n
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:
2+
2 2
Total Error
=
G 2
+
3
+
+... a where:
Gi
=
Error associated with each component.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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)
(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 RETDAS (Radioactive Effluent Tracking and Dose Assessment 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 me:hods 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 in Table 1.
presents the percent of Applicable Limits for each dose presented
' ODCM Figure 6-1.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 1.61E-2 1.31E-2 7.08E-6 3.09E-3 3.22E-2
- 6)
- 7)
- 8)
- 9) 10)
Organ 2.11E-2 4.95E-2 1.06E-5 4.52E-3 7.12E-2 AIRBORNE EFFLUENTS
- 11)
- 12)
- 13)
- 14) 15)
Tritium, Iodines, and Particulates O.OOE+O 2.22E-5 O.OOE+O O.OOE+O 2.22E-5 NOBLE GASES
- 16)
- 17)
- 18)
- 19) 20)
Gamma N/A N/A N/A N/A N/A
- 21)
- 22)
- 23)
- 24) 25)
Beta N/A N/A N/A N/A N/A
- 26)
- 27)
- 28)
- 29) 30)
DIRECT RADIATION 1.65E-1 1.68E-1 1.49E-1 1.62E-1 6.12E-1 The numbered footnotes below briefly explain how each maximum dose was calculated, organ and the predominant pathway(s).
including the 1.
2.
3.
4.
5.
This This This This This value was value was value was value was value was calculated calculated calculated calculated calculated using using using using using the methodology the methodology the methodology the methodology the methodology of the of the of the of the of the ODCM.
ODCM.
ODCM.
ODCM.
ODCM.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1
- 6. This value was calculated using the methodology of the ODCM; the GI-ILI received the maximum dose primarily by the saltwater fish pathway.
- 7. This value was calculated using the methodology of the ODCM; the GI-ILI received the maximum dose primarily by the saltwater fish pathway.
- 8.
This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
- 9.
This value was calculated using the methodology of the ODCM; the liver 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.
There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem.
- 12.
The maximum organ dose was to the skin (all age groups) and was located in the NNE sector.
This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
- 13.
There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem.
- 14.
There has no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem.
- 15.
The maximum organ dose was to the skin (all age groups) and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
- 16.
Noble Gas sampling no longer required.
- 17.
Noble Gas sampling no longer required.
- 18.
Noble Gas sampling no longer required.
- 19.
Noble Gas sampling no longer required.
- 20.
Noble Gas sampling no longer required.
- 21.
Noble Gas sampling no longer required.
- 22.
Noble Gas sampling no longer required.
- 23.
Noble Gas sampling no longer required.
- 24.
Noble Gas sampling no longer required.
- 25.
Noble Gas sampling no longer required.
- 26.
Measureinents 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 WSW sector.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1
- 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 S 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 1.07E+O 8.71E-1 4.72E-4 2.06E-1 1.07E+O Organ 4.23E-1 9.89E-1 2.12E-4 9.05E-2 7.12E-1 AIRBORNE EFFLUENTS Tritium, Iodines, and O.OOE+O 2.95E-4 O.OOE+O O.OOE+O 1.48E-4 Particulates NOBLE GASES Gamma N/A N/A N/A N/A N/A Beta N/A N/A N/A N/A N/A NOTE:Direct Radiation is not specifically addressed in the Applicable Limits.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 25, 2005, Revision 23 to the Unit 1 Offsite Dose Calculation Manual (OD)CM) was adopted and published.
This revision incorporated 1) Removal of all the "notes" and applicable sections from rev 22 regarding the completion of fuel transfer to the ISFSI, 2) Addition of notes supporting the planned demolition of the liquid radwaste treatment system, 3) Updates related to the 2003-2004 Land Use Census, 4) Corrected dilution flowrate values, and 5) A minor change to a REMP sampling location.
A major milestone in the Unit 1 demolition plan, that of storing the last fuel cannister in the ISFSI, was accomplished in August 2004. Revision 22 was issued in advance to support that event. Several notes (dissolved/entrained gases and R-1254 setpoint) added in revision 22 were removed to reflect the completed event.
The liquid radwaste treatment system (LRTS) was drained and isolated in 2005 and is currently being demolished. To support the demolition of the LRTS, notes were added in this revision to detail radwaste system specifications that are no longer applicable and instruments that are no longer required once systems were removed from service. Since the monitor was removed, requirements for surveillances and periodic maintenance were also removed. An EOE evaluation was performed for item 2.
The additic'nal dilution flow pumps added in revision 22 originally were believed to have a capacity of 6,000 gpm each. In reality, the pumps are designed at approximately 5,000 gpm.
Per NRC Generic Letter 89-01, no Effluent/ODCM Evaluation or 50.59 reviews wvere required or performed for editorial changes.
The minor REMP sampling location change is administered by that program.
None of the changes impact the accuracy or reliability of the effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR2O,
- 40CFR190, JOCFR50.36a, 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 Change Reason Revised to reflect removed sections D
Renoved reference to dissolved or entrained gases D
Renoved reference to dissolved or entrained gases and 1-131.
D Renoved note (g) which dealt with dissolved or entrained gases D
Added note detailing specification 1.3.1.A to no longer be applicable once the LRTS A
is isolated for demolition.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 1-11 Corrected dilution flowrate 1-12 Added note detailing specification 1.4.1 to no longer be applicable once the LRTS is isolated for demolition. Removed Xe-133 from setpoint equation.
1-13 Removed reference to dissolved or entrained gases 1-14 Corrected dilution flowrate and removed Xe-133 from equation.
2-1 Removed applicable parts of specification 2.1.1.A.1.
2-2 Removed applicable parts of specification 2.1.2.A.
2-3 Removed gas grab sample and continuous noble gas monitoring for R-1254.
2-4 Removed noble gases from note b.
2-5 Removed note f. Modified note C to reflect no fuel in SFP.
2-6 Removed specification 2.2.1.
,2-7 Removed specification 2.2.2.
2-10 Removed specification 2.5.1 on noble gas setpoints.
2-11 Removed specification 2.5.1 (continued).
2-12 Removed specification 2.5.1 (continued).
2-13 Removed specification 2.6.1 on noble gas dose rate.
2-15 Removed specification 2.7.1 on noble gas dose.
2-21 Per the LUC, updated 4 controlling locations and several factors.
2-22 Per the LUC, updated selected Ri values.
2-23 Per the LUC, updated selected Ri values.
2-24 Added entire page to reflect a new location.
2-25 Per the LUC, updated selected Ri values.
2-26 Per the LUC, updated selected Ri values.
2-27 Modified page number to account for added page in sector Q.
2-28 Per the LUC, updated selected Ri values.
2-29 Per the LUC, updated selected Ri values.
2-30 Per the LUC, updated selected Ri values.
2-31 Per the LUC, updated all Ri values.
2-32 Per the LUC, updated selected Ri values.
2-33 Per the LUC, updated selected Ri values.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 2-34 Per the LUC, updated selected Ri values.
2-35 Per the LUC, updated selected Ri values.
2-36 Per the LUC, updated selected Ri values.
2-37 Per the LUC, updated selected Ri values.
2-38 Per the LUC, updated selected Ri values.
4-2 Added note supporting demolition of LRTS instrumentation.
4-3 Modified Actions 16 and 20 to support demolition of LRTS instrumentation.
4-5 Added note 7 to support demolition of LRTS and instruments.
4-6 Added note 7 to support demolition of LRTS and instruments.
4-7 Renoved reference to R-1254 setpoints 4-8 Renoved reference to R-1254 gaseous channel.
4-9 Renoved reference to R-1254 compensatory actions 4-10 Renoved reference to R-1254 setpoints and detector source check.
4-11 Renoved reference to R-1254 and removed notes 5 and 7.
5-1 Corrected referenced Table number 5-23 Modified control location for non-migratory marine animals 6-3 Renoved definitions for REM RAD and Sorrento monitors, neither of which exist any loiger at Unit 1.
6-8 Molified reference from specific sections in the ODCM to the ODCM in general, to be consistent with Unit 2/3.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Demolition of Liquid Radwaste Treatment System On May 13, 2005, the Liquid Radwaste Treatment System (LRTS) was permanently removed from service. The sump pumps, piping and radiation monitoring system skid (RE-1218) were removed to support the demolition of the radwaste building. Unit 1 has reached the point in its decommissioning where systems and buildings are being physically removed.
The LRTS was designed to collect drainage from primary side equipment leaks, the spent fuel pool and the RCS itself.
It consisted of tanks, ion exchangers, filters and pumps used to process waste water to achieve 10CFR20 limits upon release. A radiation monitoring system was installed to satisfy the license and control releases from the system as an ODCM-credited release point.
Removal of the LRTS involved de-energizing the equipment related to the liquid radwaste processing system, placing a flange on the discharge pipe downstream of the pumps (eliminating the discharge line to the unrestricted area) and then removing a section of pipe.
Later plans call for the removal of all components and piping as well as filling with concrete the outfall conduit east of the tsunami gates. The plan is to section this contaminated equipment and ship offsite to a licensed burial facility. As part of decommissioning, primary side systems were previously removed.
The containment building internals were removed and disposed of as dry active waste (DAW).
All of the piped sources of wastewater to the LRTS have been permanently drained of water and all sources have been either permanently drained and isolated or demolished to prevent any further water intrusion.
Once isolation of the LRTS was completed, approximately 26000 gallons of liquid waste were generated from draindown of the spent fuel pool, flushing of the ion exchangers, demineralizers, and spent resin tank, and cleanout of the holdup tanks. AR 060102024 details the disposal method and evaluation for this water.
However, after the LRTS was drained and released, there was residual water in various low points in the piping. The small quantities of liquid wastes will be dispositioned during dismantlement of the LRTS itself. This water is included in the estimate of 2000 gallons per quarter from decontamination activities and is expected to trend downwards as the demolition of the facility continues. This waste water will include residual water in the piping and tanks as well as water used in the washing and decontamination of system component parts.
The residual water has been and continues to be disposed of per the site program.
The various methods to be used to dispose of this residual water may include: 1) lease or purchase a processing skid to reduce the water contamination levels, 2) contract with an offsite vendor to use their treatment equipment to perform the same function, or 3) process it locally and then release through a credited release point to the Unit 2 or Unit 3 outfall. Release of Unit 1 water to the Unit 2 or Unit 3 outfall required a change to the operating license(s).
AR 030300754 addresses the disposition of ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 radioactive liquid wastes including wastes that would have been treated using the LRTS.
The only remaining credited liquid release point at Unit 1 is the Yard Drain Sump.
It is still receiving drains from the outside yard including rain runoff and dewatering from the demolition process.
This change was reviewed and approved acceptable pursuant to Quality Assurance Program Description (SCE-1-A), subsection 17.2.20.3.1.i per ECP 041100584.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 on four different days in 2005. Since there was no detectable activity in the grab samples taken during the overflows, there were no dose consequences to a member of the public as a result of these unplanned, unmonitored releases. These events are documented in ARs 050100436, 050101565, 050401494 and 050600019.
Estimated Estimated Estimated Start Stop Duration Activity Release Whole Body Organ Dose Date/Time Date/Time (min)
(Ci/ml)
(Curies)
Dose (mrem)
(mrem) 01/09/05 8 1620 01/09/05 @ 1720 60
<MDA
- O.OOE+O O.OOE+O O.OOE+O 01/26/05 @ 1843 01/26/05 @ 1908 25
<MDA
- O.OOE+O O.OOE+O O.OOE+O 01/26/05 @ 1938 01/26/05 @ 2035 57
<MDA
- O.OOE+O O.OOE+O O.OOE+O 02/21/05 @ 0153 02/21/05 @ 0210 17
<MDA
- O.OOE+O O.OOE+O O.OOE+O 04/28/05 @ 0617 04/28/05 @ 0710 53
<MDA
- O.OOE+0 0.ODE+O O.OOE+O
- MDA (Minimum Detectable Activity), 95% confidence level, a posteriori Unknown Loss of Dilution Flow Durinq Liquid Releases Between 1/21/05 and 2/3/05, only one of two dilution pumps was providing actual dilution flow for three radwaste "C" Holdup Tank (CHUT) releases conducted during that time frame. The dilution pumps were both submerged in the intake structure with hoses attached directing dilution flow. On 2/3/05, unusual turbulence was observed on the water surface, which after investigation, revealed the disconnected hose. Operations ascertained the disconnect occurred on 1/21/05.
The release permit setpoints were calculated using only one of the dilution pumps so all setpoints were valid and appropriately conservative. Post release doses were recalculated using the lower flow rates. The net reported dose impact to a member of the public was minimal with no dose limit reached. The actual dose to the public was controlled in the release by the valid setpoint. This event is documented in AR 050200268.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 Unplanned Release of the Spent Fuel Pool Heat Exchanger Drains While reviewing Yard Drain Sump (YDS) weekly composite results for the week ending 4/18/05, a slightly higher than expected concentration of tritium was noted.
Investigation showed that the spent fuel pool heat exchanger (SFPHX) had been drained to the YDS earlier that week by mistake as the drains were directed to the incorrect yard drain. The plan had been to drain it to the auxiliary building sump and release it as radwaste. The release was monitored and sampled per procedure. The monitor setpoint was appropriately conservative. The dose impact to a member of the public was minimal as the maximum organ dose from this release (bone) was less than 10% of the total for the quarter; whole body was 6% of the quarter total. This event is documented in AR 050401027.
Incorrect Setpoint on Yard Drain Sump (YDS)
Monitor R-2101 On 6/6/2005 Operations discovered that the incorrect setpoint was installed ir the YDS monitor, R-2101.
On 6/3/2005 the north dilution pump was secured resultirg in only 2000 gpm dilution flow. The installed setpoint for R-2101 (based on 3000 gpm dilution and an administrative factor of 0.3), was non-conservative. However, given that the YDS was the only liquid release point in existence at that time, the entire administrative factor (1.0) for Unit 1 could have been allocated to the YDS. As such, a release could not have exceeded the limits of 10CFR20 even with the installed setpoint. Furthermore, the weekly gamma and tritium composite analyses for that time period were <LLD. There was no dose consequences to a member of the public, but if there had been any dose, it would have been included in Table 2D.
This event is documentec in AR 050600267.
Sample Line Pump Leak on Plant Vent Stack (PVS) Monitor R-1254 On 10/11/05, a skid pump on the R-1254 sample line was found to be leaking during the channel calibration test. Since this leakage was downstream of the sample media, the result was a reduced volume from the plant vent stack being collected.
The pump assembly %as replaced and the monitor returned to service on 10/14/05. The previous successfully conducted leak check was on 7/15/05 marking that point as the earliest failure date. Leak testing revealed that the inleakage was less than 50%. Note that since all of the spent fuel has been transferred to the ISFSI (fourth quarter 2004),
the requirement for a noble gas monitor is not applicable. Evaluation using 50% of the indicated sample flow revealed that all required LLD levels were met. All samples taken during that time period were <MDA.
Therefore there were no dose consequences to a member of the public from this event which is documented in AR 051100265.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 - December 31, 2005 S.O.N.G.S. 1 Monitor Inoperability Period Inoperability Cause Explanation R-2101 07/09/05 - 08/23/05 Detector spiking Found moisture in detector cable Yard Drain Sump during no flow connectors which caused the Monitor condition spiking. Connectors were cleaned and dried and returned to service.
This event is documented in AR 050700400.
10/16/05 -
11/15/05 Detector spiking Repeat symptom. Again found which tripped pumps moisture in detector cable off whenever pumps connectors but on closer turned on due to examination found signs of arcing high sump level which caused the spiking.
Connectors were cleaned and reconnected protected by vulcanized tape and desiccant to prevent moisture intrusion. New cable on order for installation. Monitor forecast to be replaced by summer 2006 with rebuilt monitor for the new YDS as part of demolition. This event is documented in AR 051000726 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 1 SECTION L. S.O.N.G.S. 1 CONCLUSIONS Gaseous releases totaled 4.45E-7 curies of which particulates were 4.45E-7 curies, and tritium was O.OOE+O curies. (Noble Gas and Iodine sampling no longer required)
The radiation doses from gaseous releases were: organ dose: 2.22E-5 mrem at the nearest receptor. (No dose was attributed to Gamma and Beta radiation since noble gas arid iodine sampling are no longer required)
Liquid releases totaled 2.12E+1 curies of which particulates and iodines were 1.40E--2 curies, tritium was 2.12E+1 curies, and noble gases were O.OOE+O curies.
The radiation doses from liquid releases were: (a) total body: 3.22E-2 mrem, (b) limiting organ: 7.12E-2 mrem.
The radioactive releases and resulting doses generated from Unit 1 were below the Applicable Limits for both gaseous and liquid effluents.
s.O.N.G.S. 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 RELEA!
- RADWASTE SHIPMENTS........
- APPLICABLE LIMITS.........
- ESTIMATION OF ERROR........
- 10 CFR 50 APPENDIX I REQUIREMENTS.
CHANGES TO OFFSITE DOSE CALCULATION
................ 39
................ 40
................ 50 SE REPORT ADDENDUM....... 58
................ 59
................ 63
................ 65
................ 66 MANUAL............ 70
- NT SYSTEMS.......... 72
................ 72 75
- CHANGES TO RADIOACTIVE WASTE TREATME
- MISCELLANEOUS...........
- S.O.N.G.S. 2 and 3 CONCLUSIONS..
-iii-
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 (2005)
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 cuarter.
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 errcr is presented in Section G of this report.
Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Units 2 and 3 do not conduct elevated releases.
Table 1C, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in three categories:
fission gases, iodines, and particulates.
The total radioactivity for each radionuclide is listed for each quarterly period by both "continuous" and "batch" modes of release.
Waste gas decay tank releases are considered to be "batch" releases.
Containment purges and plant stack releases are considered to be "continuous" releases.
Table 1D, "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 (2005)
S.O.N.G.S. 2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit First Quarter Estimated Second Total Quarter Error, %
A. Fission and activation gases
- 1. Total release Ci 2.72E+1 2.83E+1 3.0OE+1
- 2. Average release rate for period pCi/sec 3.49E+O 3.61E+O
- 3.
Percent of applicable limit
% MPC 6.71E-3 9.39E-3
- 4. Percent Effluent Concentration Limit
% ECL 8.41E-3 1.98E-2 B. Iodines (1)(2)
- 1. Total iodine-131 Ci 1.13E-5 4.33E-5 1.90E+1
- 2. Average release rate for period uCi/sec 1.45E-6 5.51E-6
- 3.
Percent of applicable limit
% MPC 6.98E-6 2.64E-5
- 4. Percent Effluent Concentration Limit
% ECL 3.49E-6 1.32E-5 C. Particulates (1)(2)
- 1. Particulates with half-lives >8 days Ci 1.08E-4 1.24E-5 1.60E+1
- 2. Average release rate for period uCi/sec 1.38E-5 1.58E-6
- 3. Percent of applicable limit
% MPC 5.19E-6 5.55E-7
- 4. Percent Effluent Concentration Limit
% ECL 1.86E-5 1.23E-6
- 5. Gross alpha activity Ci
<LLD
<LLD 5.OOE+1 D. Tritium
- 1. Total release Ci 1.32E+1 2.03E+1 2.50E+1
- 2. Average release rate for period uCi/sec 1.70E+O 2.58E+O
- 3. Percent of applicable limit
% MPC 4.07E-3 6.20E-3
- 4. Percent Effluent Concentration Limit
% ECL I 8.15E-3 1.24E-2 I (1)
(2) on i/Z6/U0 Tor approximately u30 minutes, unit 3 conaenser air ejector particulate and ioaine samples were not collected due to inadvertent securing of the skid. Prior and subsequent samples were <MDA. There were no dose consequences to a member of the public due to this event which is documented in AR 050101560.
On 4/13/05 for less than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, no particulate samples were taken at the South Yard Facility due to an electrical fault. Prior and subsequent samples were <MDA.
No work was being performed during this time.
There were no dose consequences to a member of the public due to this event which is documented in AR 050401508.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 1A (Continued)
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Quarter Fourth Quarter Esti mated Total Error, %
A. Fission and activation gases
- 1. Total release Ci 2.97E+1 4.29E+1 3.OC'E+1
- 2. Average release rate for period pCi/sec 3.74E+O 5.39E+O
- 3. Percent of applicable limit
% MPC 1.15E-2 9.77E-3
- 4.
Percent Effluent Concentration Limit
% ECL 2.86E-2 1.02E-2 B. Iodines
- 1. Total iodine-131 Ci 4.33E-5 2.55E-5 1.9CE+1
- 2. Average release rate for period pCi/sec 5.45E-6 3.21E-6
- 3. Percent of applicable limit
% MPC 2.61E-5 1.54E-5
- 4. Percent Effluent Concentration Limit
% ECL 1.31E-5 7.70E-6 I C. Particulates
- 1. Particulates with half-lives >8 days Ci 1.20E-5 1.06E-5 1.6C'E+1
- 2. Average release rate for period MCi/sec 1.51E-6 1.33E-6
- 3. Percent of applicable limit
% MPC 1.09E-6 1.12E-6
- 4. Percent Effluent Concentration Limit
% ECL 2.67E-6 2.78E-6
- 5. Gross alpha activity Ci
<LLD
<LLD 5.OCE+1 D. Tritium
- 1. Total release Ci 1.21E+1 5.02E+O 2.5CIE+1
- 2. Average release rate for period pCi/sec 1.52E+O 6.32E-1
- 3. Percent of applicable limit
% MPC 3.65E-3 1.52E-3
- 4. Percent Effluent Concentration Limit
% ECL 7.31E-3 3.03E-3 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE I
First Second Third Fourth Radionuclides Released Unit Quarter Quarter l Quarter I Quarter
- 1. Fission and activation gases argon-41 Ci 8.41E-1 2.74E+O 4.22E+O 8.67E-1 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 2.56E+1 2.51E+1 2.55E+1 3.97E+1 xenon-133m Ci
<LLD
<LLD
<LLD
<LLD xenon-135 Ci
<LLD
<LLD
<LLD 4.48E-3 xenon-135m Ci
<LLD
<LLD
<LLD
<LLD xenon-138 Ci
<LLD LLD
<LLD
<LLD Total for period Ci 2.64E+1 2.78E+1 2.97E+1 4.06E+1
- 2. Iodines iodine-131 Ci 1.13E-5 4.33E-5 4.33E-5 2.55E-5 iodine-132 Ci
<LLD
<LLD 1.95E-6
<LLD iodine-133 Ci 1.24E-5 5.48E-5 7.54E-5 1.90E-5 iodine-135 Ci
<LLD
<LLD
<LLD
<LLD Total for period Ci 2.37E-5 I 9.81E-5 I 1.21E-4 4.45E-5 LLD Lower Limit of Detection; see Table 1D.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3
-TABLE IC (Continued)
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE l First Second Third Fourth Radionuclides Released I Unit I Quarter I Quarter I Quarter Quarter
- 3. Particulates bariuum-140 Ci
<LLD
<LLD
<LLD
<LLED bromine-82 Ci 3.43E-5 1.30E-4 8.17E-5 2.86E-5 ceriuum-141 Ci
<LLD
<LLD
<LLD
<LLD cerium-144 Ci
<LLD
<LLD
<LLD
<LLD1 cesium-134 Ci
<LLD
<LLD
<LLD
<LLD cesium-137 Ci
<LLD 1.92E-6 8.04E-6 8.88E-6 cesium-138 Ci
<LLD
<LLD 4.44E-5
<LLD cobal-:-58 Ci 9.48E-5 1.05E-5 3.97E-6 1.70E-6 cobal:-60 Ci 1.02E-5
<LLD
<LLD
<LLD iron-59 Ci
<LLD
<LLD
<LLD
<LLD lanthanum-140 Ci
<LLD
<LLD
<LLD
<LLD manganese-54 Ci 2.64E-6
<LLD
<LLD
<LLD molybdenum-99 Ci
<LLD
<LLD
<LLD
<LLD stronl:ium-89 Ci
<LLD
<LLD
<LLD
<LLD stronl:ium-90 Ci
<LLD
<LLD
<LLD
<LLD zinc-fi5 Ci
<LLD
<LLD
<LLD
<LLD zirconium-95 Ci
<LLD
<LLD
<LLD
<LLD LLD Lower Limit of Detection; see Table 1D.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 1C (Continued)
GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE
- I First Second Third Fourth Radionuclides Released Unit l Quarter l Quarter l Quarter l Quarter
- 1. Fission and activation gases krypton-85 Ci 7.06E-1 5.05E-1 N/A 2.27E+O krypton-85m Ci
<LLD
<LLD N/A
<LLD krypton-87 Ci
<LLD
<LLD N/A
<LLD krypton-88 Ci
<LLD
<LLD N/A
<LLD xenon-133 Ci 3.57E-2
<LLD N/A 7.81E-3 xenon-133m Ci
<LLD
<LLD N/A
<LLD xenon-135 Ci
<LLD
<LLD N/A
<LLD xenon-135m Ci
<LLD
<LLD N/A
<LLD xenon-138 Ci
<LLD
<LLD N/A
<LLD Total for period Ci 7.41E-1 5.05E-1 N/A 2.28E+O 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 (2005)
S.O.N.G.S. 2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT CONTINUOUS 1ODE OF DETECTION Radionucl ides LLD (Ci/cc)
- 1. Fission and activation gases krypton-85 1.50E-5 krypton-85m 3.80E-8 krypton-87 1.90E-7 krypton-88 1.40E-7 xenon--133m 3.10E-7 xenon--135 4.OOE-8 xenon--135m 1.50E-6 xenon--138 2.60E-6
- 2.
Iodines__
i odine-132 1.30E-9 i odi ne-135 1.40E-10
- 3. Particulates bari uri-140 4.30E-13 ceri uri-141 5.50E-14 ceri uri-144 2.20E-13 cesi ur-134 1.20E-13 cesi uri-137 1.OOE-13 cesi uri-138 2.60E-10 cobal 1:-60 1.70E-13 i ron-5i9 2.70E-13 l anthanum-140 8.50E-13 mangariese-54 1.10E-13 molybclenum-99 6.50E-14 stront.i um-89 1.OOE-11 stront.i um-90 1.OOE-11 zinc-65 2.90E-13 zi rcori um-95 1.90E-13
- 4. al pha 1.OOE-11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 1D (Continued)
GASEOUS EFFLUENTS-LOWER LIMIT OF BATCH MODE DETECTION Radionuclides LLD (IuCi/cc)
- 1. Fission and activation gases krypton-85m 2.OOE-6 krypton-87 9.OOE-6 krypton-88 7.20E-6 xenon-133 4.60E-6 xenon-133m 1.80E-5 xenon-135 2.30E-6 xenon-135m 2.80E-5 xenon-138 4.30E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE lE GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First l Second l Third Fourth Unit Quarter J Quarter Quarter Quarter A. Noble Gas
- 1.
Gamma Air Dose mrad 2.57E-3 5.22E-3 7.34E-3 1.33E-3
- 2.
Percent Applicable Limit 2.57E-2 5.22E-2 7.34E-2 1.33E-2
- 3.
Beta Air Dose mrad 4.73E-3 5.52E-3 6.18E-3 4.20E-3
- 4.
Percent Applicable Limit 2.36E-2 2.76E-2 3.09E-2 2.10E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)
- 1. Organ Dose mrem 2.08E-3 3.24E-3 2.06E-3 8.62E-4
- 2. Percent Applicable Limit 1.38E-2 2.16E-2 1.38E-2 5.74E-3 NOTE:
Calculations performed in accordance with the ODCM utilizing the historical X/Q.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE iF GASEOUS EFFLUENTS-BATCH RELEASE
SUMMARY
12 month period
- 1. Number of batch releases:
6 releases
- 2. Total time period for batch releases:
2070 minutes
- 3. Maximum time period for a batch release:
470 minutes
- 4. Average time period for a batch release:
345 minutes
- 5. Minimum time period for a batch release:
39 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 activat:ion 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 (2005)
S.O.N.G.S. 2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I
_ First Second Total Unit Quarter Quarter Error, %
A. Fission and activation products(l)
- 1. Total release (not including tritium, gases, alpha)
Ci 5.49E-3 1.07E-2 1.90E+1
- 2. Average diluted concentration during period AiCi/ml 7.41E-12 1.41E-11
- 3.
Percent of applicable limit
% MPC 8.19E-6 2.19E-5
- 4.
Percent Effluent Concentration Limit
% ECL 5.90E-5 2.06E-4 B. Tritium
- 1. Total release Ci 1.35E+2 5.45E+2 1.90E+1
- 2. Average diluted concentration during period ktCi/ml 1.82E-7 7.20E-7
- 3. Percent of applicable limit
% MPC 6.07E-3 2.40E-2
- 4. Percent Effluent Concentration Limit
% ECL 1.82E-2 7.20E-2 C. Dissolved and entrained gases
- 1. Total release Ci 7.81E-5 1.40E-2 1.90E+1
- 2. Average diluted concentration during period uCi/ml 1.05E-13 1.85E-11
- 3. Percent of applicable limit
% MPC 5.27E-8 9.27E-6
- 4. Percent Effluent Concentration Limit
% ECL 5.27E-8 9.27E-6 D. Gross alpha radioactivity (1)
- 1. Total release Ci
<LLD
<LLD 5.0OE+1 E. Volume of waste released (batch &
continuous, prior to dilution) liters 8.58E+7 1.06E+8 5.OOE+O F. Volume of dilution water used during period liters 7.41E+11 7.57E+11 5.OOE+O (1) The sample for Unit 3 HUT released on 4/7/04 was discarded prior to use in the monthly composite for offsite analysis for alpha, Fe-55 and Sr-89/90. The April Unit 3 FFCPD composite was comprised of 11 other tank releases. The missing sample was a clean sump release (#5L-102-3) having gamma and tritium both <MDA. There was no dose impact to a member of the public from this event which is documented in AR 050500801.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 2A (Continued)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit Quarter Quarter Error-,_
I%
A. FissiDn and activation products(')
- 1. Total release (not including tritium, gases, alpha)
Ci 6.32E-3 7.20E-3 1.90E+1
- 2.
Average diluted concentration during period uCi/ml 8.23E-12 9.39E-12
- 3.
Percent of applicable limit
% MPC 1.38E-5 1.68E-5
- 4.
Percent Effluent Concentration Limit
% ECL 1.14E-4 1.71E-4 B. Tritium
- 1. Total release Ci 7.22E+1 3.80E+2 1.90E+1
- 2.
Average diluted concentration during period MCi/ml 9.40E-8 4.95E-7
- 3.
Percent of applicable limit
% MPC 3.13E-3 1.65E-2
- 4.
Percent Effluent Concentration Limit
% ECL 9.40E-3 4.95E-2 C. Dissolved and entrained gases
- 1. Total release Ci 1.90E-4 6.36E-2 1.90E+1
- 2.
Average diluted concentration during period yCi/ml 2.47E-13 8.29E-11
- 3.
Percent of applicable limit
% MPC 1.24E-7 4.14E-5
- 4.
Percent Effluent Concentration Limit
% ECL 1.24E-7 4.14E-5 D. Gross alpha radioactivity
- 1. Total release Ci
<LLD
<LLD 5.OOE+1 E. Volume of waste released (batch &
continuous, prior to dilution) liters 7.35E+7 6.40E+7 5.OOE+O F. Volume of dilution water used during period liters 7.68E+11 7.67E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE 1
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 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
<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 (2005)
S.O.N.G.S. 2 and 3 TABLE 2B (Continued)
LIQUID EFFLUENTS BATCH MODE l First l Second Third Fourti Radionuclides Released l Unit l Quarter Quarter l Quarter l Quarter
- 1. Fission and activation products antimony-125 Ci 1.32E-4 1.15E-3 1.O1E-4 6.86E-4 barium-140 Ci
<LLD
<LLD
<LLD
<LLD cerium-141 Ci
<LLD
<LLD
.<LLD
<LLD cerium-144 Ci
<LLD
<LLD
<LLD
<LLD cesium-134 Ci 3.96E-6 6.21E-5
<LLD 2.25E-5 cesium-137 Ci 6.64E-5 6.59E-4
<LLD 3.88E-4 chromium-51 Ci 3.30E-4
<LLD
<LLD
<LLD cobalt-57 Ci 7.71E-7
<LLD
<LLD
<LLD cobalt-58 Ci 1.58E-3 2.57E-3 1.57E-3 4.83E-.4 cobalt-60 Ci 6.34E-4 1.61E-3 2.19E-3 2.26E--3 iodine-131 Ci
<LLD
<LLD
<LLD
<LLD iron-55 Ci 1.67E-3 2.48E-3 1.62E-3 2.58E-3 iron-59 Ci 1.21E-4 8.83E-5
<LLD
<LLD lanthanum-140 Ci
<LLD
<LLD
<LLD
<LLD manganese-54 Ci 1.63E-4 3.85E-4 2.37E-4 2.94E-4 molybdenum-99 Ci
<LLD
<LLD
<LLD
<LLD niobium-95 Ci 4.60E-4 9.86E-4 2.94E-4 9.65E*-5 niobium-97 Ci 8.85E-6
<LLD 1.05E-5 3.14E-5 silver-lOrm Ci 5.09E-5 1.42E-4 1.41E-4 3.53E-4 strontium-89 Ci
<LLD
<LLD
<LLD
<LLD_
strontium-90 Ci
<LLD
<LLD
<LLD
<LLD' technetium-99m Ci
<LLD
<LLD
<LLD
<LLED tin-113 Ci 2.50E-5 1.94E-5 7.99E-6
<LLE' zinc-65 Ci
<LLD
<LLD
<LLD
<LLD' zirconium-95 Ci 2.44E-4 5.18E-4 1.47E-4
<LLD zirconium-97 Ci
<LLD
<LLD
<LLD 1.16E-5 Total for period Ci 5.49E-3 1.07E-2 6.32E-3 7.20E-3
- 2. Dissolved and entrained gases krypton-85 Ci
<LLD 1.25E-2
<LLD 1.36E-2 xenon-131m Ci
<LLD
<LLD
<LLD 6.58E-4 xenon-133 Ci 7.81E-5 1.54E-3 1.90E-4 4.90E-2 xenon-133m Ci
<LLD
<LLD
<LLD 2.77E-4 xenon-135 Ci
<LLD
<LLD
<LLD
<LL11 Total for period Ci 7.81E-5 1.40E-2 1.90E-4 6.36E-2 LLD Lower Limit of Detection; see Table 2C.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT CONTINUOUS MODE OF DETECTION Radionuclides LLD (mCi/cc)
- 1. Fission and activation products barium-140 2.90E-7 cerium-141 4.30E-8 cerium-144 1.70E-7 cesium-134 7.50E-8 cesium-137 6.40E-8 chromium-51 3.30E-7 cobalt-58 6.80E-8 cobalt-60 1.OOE-7 iodine-131 5.70E-8 iron-55 1.OOE-6 iron-59 1.60E-7 lanthanum-140 5.60E-7 manganese-54 6.70E-8 molybdenum-99 5.60E-8 niobium-95 6.80E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 5.70E-8 zinc-65 1.70E-7 zirconium-95 1.20E-7
- 2.
Dissolved and entrained gases xenon-133 1.90E-7 xenon-135 8.90E-8
- 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 2C (Continued)
LIQUID EFFLUENTS-LOWER LIMIT OF BATCH MODE DETECTION Radi onucli des LLD (Ci/cc)
- 1. Fission and activation products bariurn-140 2.40E-7 ceriurn-141 4.OOE-8 ceriurn-144 1.70E-7 cesiurn-134 7.50E-8 cesiura-137 6.40E-8 chrominum-51 3.OOE-7 cobal1:-57 2.20E-8 iodine-13i 4.30E-8 iron-59 1.40E-7 lanthanum-140 1.80E-7 molybdenum-99 2.70E-8 niobitim-97 1.50E-7 stronl:ium-89 5.OOE-8 stronl:ium-90 5.OOE-8 technetium-99m 2.70E-8 tin-1:3 5.30E-8 zinc-65 1.70E-7 zircorlium-95 1.10E-7 zirconium-97 1.70E-7
- 2. Dissolved and entrained gases krypton-85 2.90E-5 xenon-.13lm 3.OOE-6 xenon-.133m 6.90E-7 xenon-*135 8.90E-8
- 3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 2D D EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOI LIQUI JNDARY First Second Third I Fourth Unit Quarter Quarter Quarter Quarter A.
- 1. Total body dose mrem 3.92E-4 1.17E-3 2.66E-4 8.43E-4
- 2. Percent Applicable Limit 1.31E-2 3.91E-2 8.85E-3 2.81E-2 B.
- 1. Limiting organ dose mrem 1.38E-3 2.68E-3 1.37E-3 2.60E-3
- 2. Percent Applicable Limit 1.38E-2 2.68E-2 1.37E-2 2.60E-2
- 3. Limiting organ for period GI-LLI GI-LLI GI-LLI GI-LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE
SUMMARY
12 month period
- 1. Number of batch releases:
122 releases
- 2. Total time period for batch releases:
18468 minutes
- 3. Maximul time period for a batch release:
550 minutes
- 4. Average time period for a batch release:
151 minutes
- 5. Minimum time period for a batch release:
1 minutes
- 6. Average saltwater flow during batch releases:
735350 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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) 12 month Estimated total
- 1. Type of waste Unit period error (%)
- a. Spent resins, filter sludges m3 N/A Ci N/A N/A
- b. Dry active waste (DAW),
m3 4.51E+1 compactable and non-compactable
- Ci 3.16E-1 3.0OE+1
- c. Irradiated components m3 N/A Ci N/A N/A
- d. Other: Filters
- m3 3.99E-2 Ci
. 1.04E+O 3.OOE+1 Note: Total curie content estimated.
Material packaged in strong tight containers (USA Type IP-1) of various sizes.
N/A No shipment made.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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.OOE-04 antimony-124 4.08E-01 antimony-125 8.60E-O1 carbon-14 5.13E-O1 cerium-144 3.04E-01 cesium-134 2.74E+00 cesium-137 1.34E+OO chromium-51 1.22E+O1 cobalt-57 2.55E-Ol cobalt-58 2.84E+01 cobalt-60 3.52E+OO curium-242 1.70E-03 curium-243/244 2.10E-03 iron-55 3.01E+01 iron-59 2.46E+OO manganese-54 1.32E+OO nickel-59 2.87E-O1 nickel-63 6.33E+OO niobium-95 5.98E+OO plutonium-238 6.OOE-04 plutonium-239/240 2.OOE-04 plutonium-241 4.74E-02 strontium-89 2.73E-02 strontium-90 1.50E-03 zirconium-95
=
3.06E+O0
- c.
not applicable N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3
- 2. Estimate of major nuclide composition (by type of waste)
- d. americium-241 6.70E-03 antimony-125 1.09E+0O carbon-14 1.20E+01 cerium-144
__2.16E-02 cesium-134 1.44E-01 cesium-137 1.04E+OO cobalt-57
__2.95E-02 cobalt-58
__1.80E-01 cobalt-60 1.74E+01 curium-242 2.OOE-05 curium-243/244 1.23E-02 iodine-129 9.OOE-04 iron-55 3.26E+01 iron-59 4.OOE-04 manganese-54 3.93E-O1 nickel-63 3.48E+01 niobium-95 6.OOE-04 plutonium-238 3.30E-03 plutonium-239/240 3.50E-03 plutonium-241 1.62E-01 silver-lOm 1.61E-02 strontium-90 1.54E-02 technetium-99 7.OOE-03 tin-113 4.40E-03 tritium 1.32E-01 zirconium-95 3.80E-03 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 6
- TAG Transport Duratek/EnviroCare, UT Truck/Flatbed Trailer DrtkEvr~r 5 U 1**
Hitman Transport Studsvik/Barnwell 1Truck/Flatbed Trailer 2
TAG Transport EnviroCare, UT Truck/Flatbed Trailer Evr~rU SONGS maintains a contract with Duratek that provides volume reduction services. The processed volume was shipped from the Duratek facility to EnviroCare using 10 shipments.
Those 10 shipments included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments.
SONGS maintains a contract with Studsvik that provides volume reduction services. The processed volume was shipped from the Studsvik facility to Barnwell using 1 shipment.
The shipment 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 X
None No shipments were made l N/A A
C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 SECTION F APPITCARLF 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
MPCefI where:
F.
=
(Rel Rate)
(X/Q)
(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, uCi/sec.
=
4.80E-6 sec/M3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM.
1
=
Fi 1.1 MPC i
=
fractional abundance of the ijh radionuclide obtained by dividing the activity (curies) for each radionuclide, C,,
by the sum of all the isotopic activity, C T.
n MPC1
=
total number of radionuclides identified
=
Maximum Permissible Concentration (MPC) of the jth radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 1.
(Rel Rate)
(X/Q)
(100)
ECLeff
% ECL where:
Rel Rate X/Q total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, uCi/sec.
=
4.80E-6 sec/m3; the annual average atmospheric dispersion defined in the Units 2&3 ODCM.
1
=
E F.
1=1 ECL i o
ECLetf where:
F.
fractional abundance of the ij radionucl ide obtained dividing the activity (curies) for each radionuclide, by the sum of all the isotopic activity, C T.
by C,
n
- ECL,
=
total number of radionuclides identified
=
Effluent Concentration Limit (ECL) of the ijh radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 Liouid Effluents - Aoplicable 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 where:
Fj
=
(Dil Conc) (100)
MPCeff
=
total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2., and C.2 of Table 2A, pCi/ml.
1 F1 j.:
MPC ;
=
fractional abundance of the i th radionuclide obtained by dividing the activity (curies) for each radionuclide, C;,
by the sum of all the isotopic activity, C T.
n
- MPC,
=
total number of radionuclides identified
=
Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.
=
(Dil Conc) (100)
ECLeff
% ECL 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, uCi/ml.
I
_n FC irl ECL ;
0 ECLeff where:
Fj n
ECL1
=
fractional abundance of the i h radionuclide obtained by dividing the activity (curies) for each radionuclide,, C,,
by the sum of all the isotopic activity, C T.
=
total number of radionuclides identified
=
Effluent Concentration Limit (ECL) of the ith radionu:lide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 a2 + G2 + CF
+... r2 where:
a
=
Error associated with each component.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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)
Licuid Effluents - Whole Body Licuid Effluents - Organ Airborne Effluents - Tritium, lodines 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 RETDAS (Radioactive Effluent Tracking and Dose Assessment 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 me:hods 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 in Table 1.
presents the percent of Applicable Limits for each dose presented
' ODCM Figures 1-2 & 2-2.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 3.92E-4 1.17E-3 2.66E-4 8.43E-4 2.67E-3
- 6)
- 7)
- 8)
- 9) 10)
Organ 1.38E-3 2.68E-3 1.37E-3 2.60E-3 8.03E-3 AIRBORNE EFFLUENTS
- 11)
- 12)
- 13)
- 14) 15)
Tritium, lodines, and Particulates 1.11E-3 1.08E-3 1.24E-3 6.27E-4 3.93E-3 NOBLE GASES **
- 16)
- 17)
- 18)
- 19) 20)
Gamma 1.21E-2 1.62E-2 2.14E-2 1.99E-2 6.96E-2
- 21)
- 22)
- 23)
- 24) 25)
Beta 2.24E-2 1.87E-2 1.67E-2 3.97E-2 9.75E-2
- 26)
- 27)
- 28)
- 29) 30)
DIRECT RADIATION 1.65E-1 1.68E-1 1.49E-1 1.62E-1 6.12E-1 The numbered footnotes below briefly explain how each maximum dose organ and the predominant pathway(s).
Noble gas doses due to airborne effluent are in units of mrad, refl
- 1. This value was calculated using the methodology of the ODCM.
- 2. This value was calculated using the methodology of the ODCM.
- 3. This value was calculated using the methodology of the ODCM.
- 4. This value was calculated using the methodology of the ODCM.
- 5. This value was calculated using the methodology of the ODCM.
was calculated, including the ecting the air dose.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3
- 6. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway.
- 7. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway.
- 8. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway.
- 9. This value was calculated using the methodology of the ODCM; the GI-LLI recel primarily by the saltwater fish pathway.
- 10. This value was calculated using the methodology of the ODCM; the GI-LLI recei primarily by the saltwater fish pathway.
- 11. The maxirium organ dose was to a teen's lung and was located in the NNW sector.
using the assumptions of USNRC Regulatory Guide 1.109.
- 12. The maximum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109.
- 13. The maxirum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109.
- 14. The maximum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109.
- 15. The maximnum organ dose was to a teen's thyroid and was located in the N calculated using the assumptions of USNRC Regulatory Guide 1.109.
ived the maximum dose ived the maximum dose ived the maximum dose ived the maximum dose ived the maximum dose I This was calculated
[NE sector. This was
[NW sector. This. was
[NW sector. This. was
[NW sector. This was
- 16. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions
- 17. The maximum air dose for gamma radiation was boundary, and calculated using the assumptions
- 18. The maximum air dose for gamma radiation was boundary, and calculated using the assumptions
- 19. The maximum air dose for gamma radiation was boundary, and calculated using the assumptions
- 20. The maximum air dose for gabma radiation was boundary, and calculated using the assumptions
- 21. The maximum air dose for beta radiation was boundary, and calculated using the assumptions
- 22. The maximum air dose for beta radiation was of the USNRC Regulatory Guide 1.109.
located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.
located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.
located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.
located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.
located in the NNE sector, at the exclusion area of the USNRC Regulatory Guide 1.109.
located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
- 23. The maxi:pum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3
- 24. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
- 25. The maximum air dose for beta radiation was located in the NNE 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 WSW 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 S 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 1.31E-2 3.91E-2 8.85E-3 2.81E-2 4.45E-2 Organ 1.38E-2 2.68E-2 1.37E-2 2.60E-2 4.02E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 7.39E-3 7.18E-3 8.29E-3 4.18E-3 1.31E-2 NOBLE GASES Gamma 1.21E-1 1.62E-1 2.14E-1 1.99E-1 3.48E-1 Beta 1.12E-1 9.37E-2 8.35E-2 1.98E-1 2.44E-1 NOTE:
Direct Radiation is not specifically addressed in the Applicable Limits.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 25, 2005, Revision 40 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated 1) Removal of the requirements for *a particulate activity radiation monitor from the South Yard Facility, 2) Updates related to the 2003-2004 Land Use Census (LUC), 3) A minor change to a REMP sampling location and 4) Various administrative changes.
An approved Effluent/ODCM Evaluation (EOE) was generated for item 1. Per NRC Generic Letter 89-01, no 50.59 or EOE reviews were required or performed for editorial changes made to reflect actual plant operation. The minor REMP sampling location change is administered by that program.
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, 10CFR50.35a 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
EIditorial/Format change R
F'evision Page Change Reason ii Removed South Yard Facility from section 2.6.5 D
2-10 Defined flowpath admin factors with variables.
D,R 2-11 Revised definition PVS admin factor R
2-13 Revised definition of CAE admin factor R
2-15 Revised definition of CP admin factor R
2-16 Revised definition of CP admin factor R
2-17 Removed main purge flow rate which is N/A for RT-7865 D
2-19 Revised definition of waste gas admin factor R
2-20 Removed South Yard Facility monitor setpoint determination from section 2.6.5 D
2-21 Removed South Yard Facility monitor setpoint determination from section 2.6.5 0
2-28 Replaced equation 2-26 that was mistakenly deleted last revision F
2-31 Revised the Controlling Location Factor Table per LUC R
2-32 Per LUC, updated selected Ri values.
R 2-33 Per LUC, updated selected Ri values.
R 2-34 Per LUC, updated selected Ri values.
R ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 2-35 Per LUC, updated selected Ri values.
R 2-36 Per LUC, updated selected Ri values.
R 2-38 Per LUC, updated selected Ri values.
R 2-40 Per LUC, updated selected Ri values.
R 2-41 Per LUC, updated selected Ri values.
R 2-42 Per LUC, updated all Ri values.
R 2-43 Per LUC, updated selected Ri values.
R 2-44 Per LUC, updated selected Ri values.
R 2-45 Per LUC, updated selected Ri values.
R 2-46 Per LUC, updated selected Ri values.
R 2-47 Per LUC, updated selected Ri values.
R 2-48 Per LUC, updated selected Ri values.
R 2-49 Per LUC, updated selected Ri values.
R 2-50 Per LUC, updated selected Ri values.
R 2-51 Per LUC, updated selected Ri values.
R 2-52 Per LUC, updated selected Ri values.
R 2-53 Per LUC, updated selected Ri values.
R 4-10 Assigned "a" or "b" to Action 36, specifying whether the action is related to F
process or sample flow.
4-11 Removed SYFRT-7904, SYFRT-7905 and SYF DAS datalink from Table 4-3.
D 4-13 Removed Action 43 because SYF monitors were removed.
D 4-15 Removed control room annunciation DAS as the datalink has been terminated.
D 4-16 Removed SYFRT-7904, SYFRT-7905 and SYF DAS from Table 4-3.
D 4-18 Removed notes 7 and 8 from Table 4-4 D
4-21 Modified Figure 4-6 to show P/I sampler only in SYF R
5-20 Modified control location for non-migratory marine animals R,A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Units 2&3 Radioactive Waste Treatment Systems during the reporting period, January 1, 2005 to December 31, 2005.
SECTION K. MISCELLANEOUS None ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 -
December 31, 2005 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-7865 02/11/05 -
03/24/05 Intermittent Heat Discovered that during times of Plant Vent Stack trace circuitry heavy rainfall, water intrusion (Containment inoperability wets the circuitry and insulation Purge) preventing system from maintaining Particulate and temperature. Initial repairs to Iodine Sampler circuitry made system operable.
Permanent repairs planned. This event is documented in AR 050200818.
2APC-4077 08/02/05 -
12/09/05 Failure of Degraded material conditions lead Steam Generator composite sampler to failure. Also found inability to E088 Blowdown calibrate. A new composite sampler Compositor was installed.
This event is documented in ARs 050800166 and 050900588.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2005 - December 31, 2005 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 02/18/05 - 05/05/05 Intermittent heat Investigation of the heat trace Plant Vent Stack trace circuitry circuitry found water-damaged (Containment inoperability insulation at the roof penetration.
Purge) Particulate Initial repairs to circuitry made and Iodine Sampler system operable. Permanent repairs planned. This event is documented in ARs 050401453 and 050201162.
3APC-4076 12/22/04 - 05/11/05 Faulty voltage Initial investigation resulted in Steam Generetor regulator the ordering of wrong part with E089 Blowdown long lead time. Further Compositor investigation found bad capacitor on voltage regulator. Release occurred only six days during this time period. This event is documented in AR 041201355.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
S.O.N.G.S. 2 and 3 SECTION L. S.O.N.G.S. 2 and 3 CONCLUSIONS Gaseous releases totaled 1.79E+2 curies of which noble gases were 1.28E+2 curies, iodines were 2.87E-4 curies, particulates were 4.61E-4 curies, and tritium was 5.07E+1 curies.
The radiation doses from gaseous releases were: (a) gamma air dose: 6.96E-2 mrad at the site boundary, (b) beta air dose: 9.75E-2 mrad at the site boundary, (c) organ dose: 3.93E-3 mrem at the nearest receptor.
Liquid releases totaled 1.13E+3 curies of which particulates and iodines were 2.97E-2 curies, tritium was 1.13E+3 curies, and noble gases were 7.78E-2 curies.
The radiation doses from liquid releases were: (a) total body: 2.67E-3 mrem, (b) limiting organ: 8.03E-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 (2005)
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 m1 N/A sludges, evaporator bottoms Ci N/A N/A
- b. Dry active waste (DAW),
m3 3.26E+O compactable and non-compactable
- Ci 6.16E-4 3.OOE+1 m3 N/A
- c. Irradiated components Ci N/A N/A m3 NIA
- d. Other (filters) i N/A N/A Note:
Total curie content estimated.
Material packaged in various packagings.
General Design, IP-1, USA DOT 7A, and Type A N/A No shipment made.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
COMMON
- 2.
Estimate of major nuclide composition (by type of waste)
- a. not applicable l
N/A
- b. americium-241 4.56E-04 antimony-124 3.00E-O1 antimony-125 1.16E+OO carbon-14 2.03E+OO cerium-144 3.73E-O1 cesium-134 3.65E+oo cesium-137 1.88E+O0 chromium-51 4.22E+00 cobalt-57 3.10E-O1 cobalt-58 2.32E+01 cobalt-60 4.85E+OO curium-242 1.85E-03 curium-243/244 3.04E-03 iron-55 4.06E+01 iron-59 1.44E+OO manganese-54 1.64E+OO nickel-59 4.03E-O1 nickel-63 8.86E+OO niobium-95 2.78E+OO plutonium-238 7.73E-04 plutonium-239/240 2.89E-04 pl utoni um-241 6.61E-02 stronti um-89 1.25E-02 strontium-90 2.16E-03 zirconium-95 2.34E+OO
- c. not applicable N/A
- d. not applicable N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 1
TAG Transport Truck EnviroCare, UT 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 D.
CHANSES TO THE PROCESS None.
CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3
REFERENCES:
- 1. Ulit 1 Technical Specifications, section D6.13.2.
- 2. U1its 2 and 3 License Controlled Specifications, section 5.0.103.2.2.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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 6.71E-1
- b. Percent ODCM Specification Limit 2.68E+O
- 2. Limiting Organ
- a. Organ Dose (GI-LLI) mrem 8.63E-2
- b. Percent ODCM Specification Limit 3.45E-1
- 3. Thyroid
- a. Thyroid Dose mrem 1.22E-2
- b. Percent ODCM Specification Limit
__1.63E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 1.79E+2 curies of Ahich noble gases were 1.28E+2 curies, iodines were 2.87E-4 curies, particulates were 4.61E-4 curies, and tritium was 5.07E+1 curies.
Liquid releases particulates and noble gases were from S.O.N.G.S. 1, 2 and 3 totaled 1.15E+3 curies of which iodines were 4.37E-2 curies, tritium was 1.15E+3 curies, and 7.78E-2 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 245 radwaste shipments to Envirocare, UT and 5 shipments to Barnwell, SC.
Total volume was 3.66E+3 cubic meters containing 3.71E+2 curies of radioactivity.
Meteorological conditions during the year were typical Meteorological dispersion was good 36% of the time, fair 38%
poor 26% of the time.
for S.O.N.G.S.
of the time and The net result from the analysis of these effluent releases indicates thai: 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 (2005)
COMMON APPENDIX A GASEOUS EFFLUENTS - APPLICABLE LIMITS A.
Table 1A lists the total curies released and the release rate. The percent of applicable limit compares the released concentrations to the concentration limits of 10 CFR 20, Appendix B, Table II, Column 1.
B.
Table 1E lists the air doses as calculated using the historical X/Q.
The air dose due to noble gases released in gaseous effluents from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values:
- 1. During any calendar quarter:
- 2.
During any calendar year:
5 mrad for gamma radiation and
< 10 mrad for beta radiation.
< 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:
< 7.5 mrem to any organ.
- 15 mrem to any organ.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
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, ;2005 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, 2005.
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 (2005)
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05010100-05033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A v
o WIND DIR N
NNE NE ENE E
WNW NW NNW 22 51 I)
I)
I)
I) 1)
1) 1)
I)
I)
I)
I)
I)
I)
I)
I)
.51
.75
-in 0
0 0
0 0
0 C
EXTREMELY UNSTABLE 6
1.1 1.6 1.5 2.0 3 0 0
1 0
0 1
O 0
2 0
O 0
1 3
1 1
0 0
5 1
6 2
8 1
6 1
3 0
4 1
1 (DT/DZ 2.1 3.0 1
1 1
0 0
0 0
3 17 8
8 40 63 21 0
0 f -1.9 3.1 5.0 0
1 4
1 2
0 0
9 17 8
3 36 57 29 1
0
-C/100 METERS) 5.1 7.1 7.0 10.0 1
0 2
0 2
0 1
0 O
0 O
0 O
0 2
1 2
0 O
0 O
0 0
0 3
0 11 1
O 0
O 0
10.1 13.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 13.1 18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>18 T(TAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
2 5
7 3
2 2
0 19 38 21 18 86 130 66 5
2 TOTALS 0
1 11 37 163 168 24 2
0 0
0 40 NUMBER OF VALID HOURS 406 NUMBER OF CALMS 0
NUMBER OF IN\\ALID HOURS 0
TOTAL HOURS FOR THE PERIOD 406 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
.53
.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 a
0 0
0 0
0 0
0 0
0 0
0 0
NE 0
0 0
0 0
0 0
1 0
0 0
0 1
ENE D
0 0
0 0
0 0
2 0
0 0
0 2
E 0
0 0
0 0
0 0
0 0
0 0
0 0
ESE D
0 0
0 0
0 0
0 0
0 0
0 0
SE D
0 0
0 0
0 1
0 1
0 0
0 2
SSE D
0 0
1 0
1 2
0 1
0 0
0 5
S 3
0 0
0 0
1 0
4 0
0 0
0 5
SSW 0
0 0
1 2
2 3
0 0
0 0
0 8
SW 3
0 0
1 1
5 0
2 0
0 0
0 9
WSW 0
0 0
2 1
3 0
0 0
0 0
0 6
W 0
0 0
1 2
2 0
0 0
0 0
0 5
WNW 0
0 0
1 4
2 2
0 0
0 0
0 9
NW 0
0 0
0 1
1 3
0 0
0 0
0 5
NNW 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTALS 0
0 0
7 11 17 12 9
2 0
0 0
58 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 58 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
58 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05010100-05033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 -C/100 METERS)
WIND DIR N
NNE NE ENE E
WNW NW NNW
.22
.50
.51
.75 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
.76 1.0 0
0 0
0 00 0
0 0
0 0
0 0
0 0
1.1 1.5 0
0 1
0 0
0 0
0 0
1 1
1 1
1 0
0 1.6 2.0 0
0 0
1 0
0 1
1 1
2 2
1 3
0 0
2.1 3.0 0
1 0
0 0
0 1
1 0
3 2
2 3
7 2
0 3.1 5.0 0
0 1
0 0
0 0
3 1
0 0
1 0
3 2
0 5.1 7.0 0
0 0
1 0
4 2
1 1
0 0
0 1
0 0
7.1 10.0 0
0 0
0 0
0 2
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
0
>18 TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 1
1 2
0 2
0 5
9 3
6 5
6 5
15 4
0 TOTALS 0
0 0
6 13 22 11 10 2
0 0
0 64 NUMBER OF VALID HOURS 64 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 64 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 4
7 5
3 0
0 0
0 0
19 NNE 0
0 0
11 11 18 1
0 0
0 0
0 41 NE 0
0 0
2 6
5 1
1 0
0 0
0 15 ENE 0
0 1
0 2
2 2
1 0
0 0
0 8
E 0
0 1
1 2
0 6
4 0
0 0
0 14 ESE 0
0 0
1 2
6 9
17 7
0 0
0 42 SE 0
0 0
3 3
7 38 37 25 2
0 0
115 SSE 0
0 0
3 5
6 17 13 22 7
8 0
81 S
0 0
0 4
3 7
6 5
10 2
0 0
37 SSW 0
0 0
2 4
4 4
5 3
0 0
0 22 SW 1
0 0
5 2
4 9
2 2
0 0
0 25 WSW 0
0 2
2 1
4 8
2 1
0 0
0 20 W
0 1
0 1
2 6
5 7
2 0
0 0
24 WNW 0
1 0
3 3
15 12 7
2 0
0 0
43 NW 0
0 1
1 6
14 15 1
1 0
0 0
39 NNW 0
0 1
8 6
011 5
0 0
0 0
0 31 TOTALS 1
2 6
51 65 114 141 102 75 11 8
0 576 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 576 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
576 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05010100-05033123 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 TOTALS
.*22 so 00 0
0 1
0 0
0 0
0 0
0 0
0 0
0 1
.51
.75 0
0 0
1 0
0 0
0 0
0 0
0 1
0 0
0 2
.76 1.0 0
2 1
1 1
0 0
0 0
0 1
0 0
0 0
1 1.1 1.5 7
16 0
6 2
1 2
0 1
1 0
1 1
3 0
2 43 1.6 2.0 12 14 3
1 4
5 3
1 1
1 0
1 2
0 1
4 53 2.1 3.0 11 20 5
3.1 5.0 1
7 3
5.1 7.0 0
0 0
7.1 10.0 0
0 0
10.1 13.0 0
0 0
6 5
8 2
5 4
2 2
0 3
3 5
8 1
15 5
7 2
1 1
0 3
1 5
5 3
60 3
3 6
12 9
0 0
0 0
1 2
2 0
1 2
0 8
8 3
1 1
0 2
1 1
0 28-1 1
0 0
0 3
0 0
0 0
0 0
0 13.1 18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>18 TOTAL 31 59 12 21 34 25 34 25 13 6
4 5
11 14 14 18 326 NUMBER OF VALID HOURS 326 NUMBER OF CALMS 0
NUMBER OF IN'IALID HOURS 0
TOTAL HOURS FOR THE PERIOD 326 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 5 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 JOTAL DIR
.EO
.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N
0 0
0 5
5 5
3 0
0 0
0 0
18 NNE 0
0 0
15 38 71 17 1
0 0
0 0
142 NE 0
0 1
10 6
5 4
2 0
0 0
0 28 ENE 0
1 0
1 6
5 0
0 0
0 0
0 13 E
0 0
1 1
3 2
1 0
01 0
0 0
8 ESE 0
0 0
1 0
0 0
0 0
0 0
0 1
SE 0
0 0
0 1
2 0
0 0
0 0
0 3
SSE 0
0 1
0 0
1 2
0 0
0 0
0 4
S 0
0 0
2 0
2 0
0 0
0 0
0 4
SSW 0
0 1
2 0
0 0
0 0
0 0
0 3
SW 0
0 0
3 0
1 0
0 0
0 0
0 4
WSW 0
0 1
0 2
0 0
0 0
0 0
0 3
W 0
0 0
1 4
1 0
0 0
0 0
0 6
WNW 3
0 1
2 2
1 2
0 0
0 0
0 11 NW 0
0 0
1 0
1 2
0 0
0 0
0 4
NNW 0
0 0
2 2
3 2
0 0
0 0
0 9
TOTALS 3
1 6
46 69 100 33 3
0 0
0 0
261 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 261 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
261 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05010100-05033123 WIND SPEED (M/S) AT 10 METER LEVEL WIND
.22 DIR
.50 N
0 NNE 0
NE 0
ENE 0
E 0
ESE 0
SE 0
SSE 0
S 0
SSW 0
SW 0
WSW 0
W 0
WNW I
NW 0
NNW 0
TOTALS 1
.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 1
1 0
0 0
0 0
2 0
1 5
PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS) 1.1 1.6 2.1 3.1 5.1 7.1 1.5 2.0 3.0 5.0 7.0 10.0 0
1 8
8 0
0 2
12 148 167 8
0 1
10 17 15 4
0 0
5 6
2 0
0 1
3 2
1 0
0 3
1 0
0 0
0 0
2 3
0 0
0 3
1 2
1 0
0 0
1 2
1 0
0 0
0 0
3 0
0 2
0 2
0 0
0 3
2 0
0 0
0 1
1 0
0 0
0 1
0 2
0 0
0 1
1 1
0 0
0 0
1 1
0 0
0 18 41 194 198 12 0
10.1 13.0 0
0 00 0
0 0
0 0
0 0
0 0
0 0
0o 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
17 337 47 13 7
4 6
8 4
3 4
5 2
6 3
3 469 NUMBER OF VALID HOURS 469 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 469 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
NNE NE ENE E
WNW NW NNW TOTALS 0
0 0
0 1
0 0
0 0
0 1
0 0
4 0
0 6
0 0
0 2
0 0
0 0
0 0
0 0
2 1
0 0
0 2
2 2
3 0
1 2
1 1
1 3
0 3
1 3
25 16 26 30 16 1
45 75 259 193 11 14 25 33 28 10 7
15 19 6
7 5
13 9
25 8
8 8
14 14 23 5
9 15 46 53 8
11 19 36 26 8
6 33 26 12 7
13 19 19 6
13 11 24 12 4
11 17 49 48 2
7 18 78 63 11 12 15 51 53 21 3
13 24 28 3
13 14 23 10 0
182 289 699 623 198 0
0 0
1 2
7 34 34 13 4
3 1
4 4
2 0
109 0
0 0
1 1
0 2
7 5
0 0
0 0
0 0
0 16 0
0 0
0 0
0 0
8 0
0 0
0 0
0 0
0 0
89 0
585 0
112 0
60 0
67 0
74 0
165 0
151 0
104 0
69 0
69 0
131 0
183 0
164 0
74 0
63 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 (2005)
METEOROLOGY April -
June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05040100-05063023 WIND SPEED (M/S) AT 10 METER LEVEL
,1 WIND DIR N
NNE NE ENE E
WNW NW NNW
.22
. 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
.7f
.c C
c C
C C
C
[
C C
C C
C EXTREMELY UNSTABLE 6
1.1 1.6 1.5 2.0 0
0 0
0 O
0 O
0 O
0 1
0 O
0 I
0 1
I 2
6 4
12 I
3 18 I
1 19 I
0 11 I
1 7
I 0
0 I
0 0
PASQUILL A (DT/DZ 2.1 3.
3.0 5.
0 0
0 0
0 0
0 4
18 3
24 4
57 5
66 E
68 12 31 6
1 0
.1.9 1
0 0
0 0
0 0
0 0
3 6
9 i1
- 4
.8 7
0
°C/100 METERS) 5.1 7.0 0
0 0
0 0
0 0
2 11 2
1 3
0 12 5
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
0
>18 TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 0
10 73 91 130 170 203 119 13 0
TOTALS 0
0 0
12 74 269 419 36 0
0 0
0 810 NUMBER OF VALID HOURS 810 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 810 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ s -1.7 -C/100 METERS)
WIND
..2
.51
.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1
>18 TOTAL DIR
.!iO
.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 1
1 0
0 0
0 0
0 0
0 2
ENE 0
0 0
0 0
0 0
0 0
0 0
0 0
E 0
0 0
0 0
0 0
0 0
0 0
0 0
ESE 0
0 0
0 0
0 0
0 0
0 0
0 0
SE 0
0 0
0 0
1 0
0 0
0 0
0 1
SSE 0
0 0
0 1
6 2
1 2
0 0
0 12 S
0 0
0 1
1 1
5 0
0 0
0 0
8 SSW 0
1 0
2 0
2 6
3 0
0 0
0 14 SW 0
0 0
0 2
6 1
0 0
0 0
0 9
WSW 0
0 0
1 4
4 4
0 0
0 0
0 13 W
0 0
0 0
2 2
1 0
0 0
0 0
5 WNW 0
0 0
0 1
6 1
1 0
0 0
0 9
NW 0
0 0
1 0
2 6
0 0
0 0
0 9
NNW 0
0 0
0 0
2 0
0 0
0 0
0 2
TOTALS 0
1 1
6 11 33 26 5
2 0
0 0
85 NUMBER OF VALID HOURS NUMBER OF INV'ALID HOURS 85 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
85 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05040100-05063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ s -1.5 °C/100 METERS)
WIND DIR N
NNE NE ENE E
WNW NW NNW TOTALS
.22
.50 0
0 0
O 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
0 0
0 0
0 0
1.1 1.5 0
1 0
0 1
0 1
1 2
0 5
2 3
1 0
1 18 1.6 2.0 2
0 2
0 0
0 1
2 2
2 4
0 3
2 0
0 2.1 3.0 1
1 1
0 0
0 0
4 5
6 10 5
3 3
.5 2
46 3.1 5.0 0
0 0
0 0
3 8
6 16 3
7 2
0 4
0 49 5.1 7.0 0
0 0
0 0
0 0
3 3
2 1
1 0
1 1
0 7.1 10.0 0
0 0
0 0
0 0
0 0
0 1
0 0
0 0
0 1
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
3 2
3 0
1 0
5 18 18 26 24 15 11 7
10 3
146 NUMBER OF VALID HOURS 146 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 146 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
1 10 3
5 0
0 0
0 0
0 19 NNE 0
0 1
8 9
9 4
0 0
0 0
0 31 NE 0
0 1
4 2
4 0
0 0
0 0
0 11 ENE 0
1 0
0 3
1 0
0 0
0 0
0 5
E 0
0 1
7 5
4 2
0 0
0 0
0 19 ESE 0
0 0
3 2
15 13 0
0 0
0 0
33 SE 1
0 4
4 7
27 29 9
1 0
0 0
82 SSE 0
0 0
4 15 24 26 7
0 0
0 0
76 S
0 0
0 6
5 19 23 5
0 0
0 0
5B SSW 0
0 1
10 9
12 14 6
0 0
0 0
52 SW 0
2 4
8 8
7 12 2
0 0
0 0
43 WSW 0
2 2
9 2
7 7
5 0
0 0
0 34 W
0 1
2 7
5 7
7 5
0 0
0 0
34 WNW 0
0 0
2 2
1 5
3 1
0 0
0 14 NW 0
0 2
5 2
14 5
1 1
2 0
0 32 NNW 0
0 4
4 5
4 2
0 0
0 0
0 19 TOTALS 1
6 23 91 84 160 149 43 3
2 0
0 562 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 562 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
562 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY April -
June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05040100-05063023 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
.EO 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
.7b 1.0t 2
0 0
0 3
0 0
1 1
2 0
0 0
2 1
1.1 1.5 8
8 8
4 2
3 0
1 1
1 2
1 0
3 0
2 1.b 2.0 7
11 2
2 3
2 1
1 1
1 1
1 0
3 1
3 Z.1 3.0 3
13 1
5 5
3 2
1 1
1 0
0 0
0 0
6 S.1 5.0 0
2 0
0 1
1 0
2 0
0 0
0 0
4 0
4 5.1 7.0 0
0 0
0 0
00 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 10.1 13.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 13.1 18.0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
>18 TOTAL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 15 36 11 11 11 12 3
5 4
4 5
2 0
10 3
16 TOTALS 0
0 12 41 40 41 14 0
0 0
0 0
148 NUMBER OF VAI.ID HOURS 148 NUMBER OF CALMS 0
NUMBER OF INV/ALID HOURS 0
TOTAL HOURS FOR THE PERIOD 148 PASQUILL F MODERATELY STABLE (1.5 < 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 7OTAL 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 7
1 2
2 0
0 0
0 0
12 NNE 0
1 2
18 41 38 1
0 0
0 0
0 101 NE 0
0 3
16 5
2 1
2 0
0 0
0 29 ENE 0
0 1
1 4
2 0
1 0
0 0
0 9
E 0
0 1
3 0
0 0
0 0
0 0
0 4
ESE 0
0 0
1 0
0 0
0 0
0 0
0 1
SE 0
0 1
1 1
0 0
0 0
0 0
0 3
SSE 0
0 0
2 3
0 0
0 0
0 0
0 5
S 0
0 1
1 1
0 1
0 0
0 0
0 4
SSW 0
0 0
2 2
0 0
0 0
0 0
0 4
SW 0
0 0
1 0
2 0
0 0
0 0
0 3
WSW 0
0 0
2 0
0 0
0 0
0 0
0 2
W 0
0 1
2 1
1 0
0 0
0 0
0 5
WNW 0
0 0
0 2
2 0
0 0
0 0
0 4
NW 0
0 1
1 2
0 0
0 0
0 0
0 4
NNW 0
1 1
1 2
2 0
0 0
0 0
0 7
TOTALS 0
2 12 59 65 51 5
3 0
0 0
0 197 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 197 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
197
-go-
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05040100-05063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G 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
.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
0 0
0 0
0 0
EXTREMELY 1.1 1.5 0
2 2
1 0
0 0
0 1
0 0
0 0
0 0
0 6
STABLE 1.6 2.0 1
14 6
0 0
0 1
0 0
0 0
0 0
0 0
1 23 (DT/DZ 2.1 3.0 3
120 6
1 0
1 0
0 0
0 0
0 0
0 0
1 132 3.1 5.0 2
63 0
2 0
0 0
0 0
0 0
0 1
2 0
1 71 5.1 7.0 0
3 0
0 0
0 0
0 0
0 0
0 0
1 0
0
> 4.0 °C/100 METERS) 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 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
-i 6
202 14 4
0 1
1 0
1 0
0 0
1 3
0 3
236 NUMBER OF VALID HOURS 236 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 236 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
1 22 14 15 4
0 0
0 0
0 56 NNE 0
1 5
37 75 181 70 3
0 0
0 0
372 NE 0
0 5
31 17 14 1
2 0
0 0
0 70 ENE 0
1 1
6 9
9 2
1 0
0 0
0 29 E
0 0
2 13 8
9 3
0 0
0 0
0 35 ESE 0
0 3
8 4
19 14 0
0 0
0 0
48 SE 1
0 5
6 11 30 32 9
1 0
0 0
95 SSE 0
0 0
8 23 39 41 13 2
0 0
0 126 S
0 0
2 14 16 44 71 19 0
0 0
0 166 SSW 0
1 2
19 26 45 85 13 0
0 0
0 191 SW 0
2 6
19 33 82 67 4
1 0
0 0
214 WSW 0
2 2
16 26 82 99 9
0 0
0 0
236 W
0 1
3 12 22 81 135 5
0 0
0 0
259 WNW 0
0 0
7 17 43 80 18 1
0 0
0 166 NW 0
0 5
7 5
22 22 7
1 2
0 0
71 NNW 0
1 6
8 11 17 7
0 0
0 0
0 50 TOTALS 1
9 48 233 317 732 733 103 6
2 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 (2005)
METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05070100-05093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ s -1.9 °C/100 METERS)
WIND
.22
.51
.76 1.1 1.6 -
2.1 3.1 -
5.1 -
7.1 - 10.1
- 13.1 -
>18 TOTAL DIR
.50
.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N
0 0
0 0
0 0
0 0
0 0
0 0
0 NNE 0
0 0
0 0
0 0
0 0
0 0
0 0
NE 0
0 0
0 0
0 0
0 0
0 0
0 0
ENE 0
0 0
0 0
0 0
0 0
0 0
0 0
E 0
1 0
0 0
0 0
0 0
0 0
0 1
ESE 0
0 0
0 1
0 0
0 0
0 0
0 1
SE 0
0 0
1 2
0 0
0 0
0 0
0 3
SSE 0
0 0
0 0
7 1
3 0
0 0
0 11 S
0 0
0 2
3 10 23 4
0 0
0 0
42 SSW 0
0 0
3 8
24 38 3
0 0
0 0
76 SW 0
0 0
3 15 57 28 0
0 0
0 0
103 WSW 0
0 1
4 27 111 38 1
0 0
0 0
182 W
0 0
0 1
12 108 113 0
0 0
0 0
234 WNW 0
0 0
0 4
63 101 0
0 0
0 0
168 NW 0
0 0
1 0
5 3
1 0
0 0
0 10 NNW 0
0 0
2 1
0 0
0 0
0 0
0 3
TOTALS 0
1 1
17 73 385 345 12 0
0 0
0 834 NUMBER OF VAI.ID HOURS 834 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 834 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 1
1 1
0 0
0 0
0 0
3 NNE 0
0 0
0 0
1 0
0 0
0 0
0 1
NE 0
0 0
0 0
1 0
0 0
0 0
0 1
ENE 0
0 0
0 1
0 0
0 0
- 0.
0 0
1 E
0 0
1 1
0 0
0 0
0 0
0 0
2 ESE 0
0 0
1 0
0 0
0 0
0 0
0 1
SE 0
0 0
0 0
0 0
0 0
0 0
0 0
SSE 0
0 0
0 1
3 3
2 0
0 0
0 9
S 0
0 0
4 1
6 3
0 0
0 0
0 14 SSW 0
0 0
4 3
6 5
0 0
0 0
0 18 SW 0
0 1
2 6
4 0
0 0
0 0
0 13 WSW 0
0 0
0 3
3 0
0 0
0 0
0 6
W 0
0 0
2 3
2 0
0 0
0 0
0 7
WNW 0
0 0
3 3
10 0
1 0
0 0
0 17 NW 0
0 0
0 0
13 1
0 0
0 0
0 14 NNW 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTALS 0
0 2
18 22 50 12 3
0 0
0 0
107 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 107 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
107 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05070100-05093023 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
2 1
0 0
0 0
0 0
4 NNE 0
0 0
5 2
4 2
0 0
0 0
0 13 NE 0
0 0
2 3
0 0
0 0
0 0
0 5
ENE 0
0 0
1 1
0 0
0 0
0 0
0 2
E 0
0 0
0 0
0 0
0 0
0 0
0 0
ESE 0
0 1
0 0
0 0
0 0
0 0
0 1
SE 0
0 1
3 0
2 0
0 0
0 0
0 6
SSE 0
0 0
0 2
13 11 3
1 0
0 0
30 S
0 0
0 2
6 14 3
1 0
0 0
0 26 SSW 0
0 0
2 6
9 4
0 0
0 0
0 21 SW 0
0 0
2 2
9 1
0 0
0 0
0 14 WSW 0
0 1
3 3
4 0
0 0
0 0
0 11 W
0 0
0 2
5 8
0 0
0 0
0 0
15 WNW 0
0 0
3 8
4 3
0 0
0 0
0 18 NW 0
0 1
2 3
8 4
0 0
0 0
0 18 NNW 0
0 0
1 2
1 0
0 0
0 0
0 4
TOTALS 0
0 4
29 45 77 28 4
1 0
0 0
188 NUMBER OF VALID HOURS 188 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 188 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 25 9
2 0
0 0
0 0
0 38 NNE 0
1 2
15 10 16 6
0 0
0 0
0 50 NE 0
0 2
13 8
6 1
0 0
0 0
0 30 ENE 0
0 1
3 2
3 0
0 0
0 0
0 9
E 0
0 1
1 2
5 0
0 0
0 0
0 9
ESE 0
0 1
9 5
15 4
0 0
0 0
0 34 SE 0
0 0
10 14 29 20 0
0 0
0 0
73 SSE 0
0 0
17 22 26 26 3
0 0
0 0
94 S
1 1
1 17 16 18 7
0 0
0 0
0 61 SSW 0
1 1
15 13 11 0
1 0
0 0
0 42 SW 0
1 6
12 2
4 1
0 0
0 0
0 26 WSW 0
1 1
4 4
1 0
0 0
0 0
0 11 W
0 0
6 6
6 5
7 0
0 0
0 0
30 WNW 0
0 6
19 11 6
1 0
0 0
0 0
43 NW 0
2 3
14 12 17 6
0 0
0 0
0 54 NNW 1
1 4
14 16 4
1 0
0 0
0 0
41 TOTALS 2
8 37 194 152 168 80 4
0 0
0 0
645 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 645 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
645 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05070100-05093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ
- 1.5 °C/100 METERS)
WIND
.22 -
.51
.76 -
1.1 1.6 -
2.1 -
3.1 -
5.1 -
7.1 - 10.1 -
13.1 -
>18 TOTAL DIR
.50
.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N
O 0
1 11 7
2 0
0 0
0 0
0 21 NNE 0
0 6
19 19 11 8
0 0
0 0
0 63 NE 0
1 1
6 2
0 1
0 0
0 0
0 11 ENE 0
1 0
3 4
2 0
0 0
0 0
0 10 E
0 0
2 2
0 3
0 0
0 0
0 0
7 ESE 0
1 0
3 3
4 0
0 0
0 0
0 11 SE 0
0 0
2 2
6 3
0 0
0 0
0 13 SSE 0
0 0
0 3
5 1
0 0
0 0
0 9
S 0
0 0
0 0
1 0
0 0
0 0
0 1
SSW 0
0 0
1 1
1 0
0 0
0 0
0 3
SW 0
1 1
1 1
0 0
0 0
0 0
0 4
WSW 0
0 1
2 1
1 0
0 0
0 0
0 5
W 0
0 2
2 2
2 0
0 0
0 0
0 8
WNW 0
0 1
2 4
0 1
0 0
0 0
0 8
NW 0
0 1
2 3
2 1
0 0
0 0
0 9
NNW 0
1 3
3 1
3 0
0 0
0 0
0 11 TOTALS 0
5 19 59 53 43 15 0
0 0
0 0
194 NUMBER OF VALID HOURS 194 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 194 PASQUILL F MODERATELY STABLE (1.5 < 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 10TAL 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 3
2 5
0 0
0 0
0 0
10 NNE 0
0 2
11 18 23 0
0 0
0 0
0 54 NE 0
1 1
4 2
1 0
0 0
0 0
0 9
ENE 0
0 1
3 1
0 0
0 0
0 0
0 5
E 0
1 1
2 1
0 0
0 0
0 0
0 5
ESE 0
0 2
2 0
1 0
0 0
0 0
0 5
SE 0
0 0
0 0
1 0
2 0
0 0
0 3
SSE 0
0 0
0 2
3 0
0 0
0 0
0 5
S 0
0 0
0 0
1 0
0 0
0 0
0 1
SSW 0
1 1
1 0
0 0
0 0
0 0
0 3
SW 0
0 0
2 0
0 0
0 0
0 0
0 2
WSW 0
1 0
0 0
0 0
0 0
0 0
0 1
W 0
0 2
2 3
0 0
0 0
0 0
0 7
WNW 0
0 1
1 0
2 0
0 0
0 0
0 4
NW 0
0 0
0 2
0 0
0 0
0 0
0 2
NNW 0
0 0
1 0
1 1
0 0
0 0
0 3
TOTALS 0
4 11 32 31 38 1
2 0
0 0
0 119 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 119 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
119 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05070100-05093023 WIND SPEED (M/S) AT 10 METER LEVEL EXTREMELY STABLE PASQUILL G (DT/DZ > 4.0 'C/100 METERS)
WIND
.22 -
.51 -
.76 -
1.1 -
1.6 -
2.1 -
3.1 -
5.1 -
7.1 - 10.1 - 13.1 -
>18 TOTAL DIR
.50
.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N
0 0
0 0
0 3
3 0
0 0
0 0
6 NNE 0
0 0
3 4
70 17 0
0 0
0 0
94 NE 0
0 1
2 0
2 1
0 0
0 0
0 6
ENE 0
0 0
0 0
1 0
0 0
0 0
0 1
E 0
0 0
0 1
2 0
0 0
0 0
0 3
ESE 0
0 0
0 2
0 0
0 0
0 0
0 2
SE 0
0 0
0 0
0 0
0 0
0 0
0 0
SSE 0
0 0
1 1
3 0
0 0
0 0
0 5
5 0
0 0
0 0
1 0
0 0
0 0
0 1
SSW 0
0 0
1 0
0 0
0 0
0 0
0 1
SW 0
0 0
0 0
0 0
0 0
0 0
0 0
WSW 0
0 0
0 0
0 0
0 0
0 0
0 0
W 0
0 0
0 1
0 0
0 0
0 0
0 1
WNW 0
0 0
0 0
0 0
0 0
0 0
0 0
NW 0
1 0
0 0
0 0
0 0
0 0
0 1
NNW 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTALS 0
1 1
7 9
82 21 0
0 0
0 0
121 NUMBER OF VALID HOURS 121 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 121 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 41 21 14 3
0 0
0 0
0 82 NNE 0
1 10 53 53 125 33 0
0 0
0 0
275 NE 0
2 5
27 15 10 3
0 0
0 0
0 62 ENE 0
1 2
10 9
6 0
0 0
0 0
0 28 E
0 2
5 6
4 10 0
0 0
0 0
0 27 ESE 0
1 4
15 11 20 4
0 0
0 0
0 55 SE 0
0 1
16 18 38 23 2
0 0
0 0
98 SSE 0
0 0
18 31 60 42 11 1
0 0
0 163 5
1 1
1 25 26 51 36 5
0 0
0 0
146 SSW 0
2 2
27 31 51 47 4
0 0
0 0
164 SW 0
2 8
22 26 74 30 0
0 0
0 0
162 WSW 0
2 4
13 38 120 38 1
0 0
0 0
216 W
0 0
10 15 32 125 120 0
0 0
0 0
302 WNW 0
0 8
28 30 85 106 1
0 0
0 0
258 NW 0
3 5
19 20 45 15 1
0 0
0 0
108 NNW 1
2 7
21 20 9
2 0
0 0
0 0
62 TOTALS 2
19 75 356 385 843 502 25 1
0 0
0 2208 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2208 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY October -
December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05100100-05123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ s -1.9 °C/100 METERS)
WIND
.;2 -
.51 -
.76 -
1.1 1.6 -
2.1 -
3.1 -
5.1 -
7.1 10.1 -13.1
>18 TOTAL DIR
.50
.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N
0 0
0 0
0 0
0 0
0 0
0 0
0 NNE 0
0 0
0 0
0 0
0 0
0 0
0 0
NE 0
0 0
0 0
0 0
1 0
0 0
0 1
ENE 0
0 0
0 0
1 0
0 0
0 0
0 1
E 0
0 0
0 0
0 0
0 0
0 0
0 0
ESE 0
0 0
0 0
0 0
0 0
0 0
0 0
SE 0
0 0
1 0
0 0
0 0
0 0
0 1
SSE 0
0 0
3 0
3 5
0 0
0 0
0 11 S
0 0
0 0
8 23 21 6
0 0
0 0
58 SSW 0
0 0
1 10 18 11 0
0 0
0 0
40 SW 0
0 0
4 13 21 7
0 0
0 0
0 45 WSW 0
0 0
6 18 34 13 1
0 0
0 0
72 W
0 0
0 1
13 88 54 2
0 0
0 0
158 WNW 0
0 0
1 5
22 44 7
0 0
0 0
79 NW 0
0 0
2 0
1 4
0 0
0 0
0 7
NNW 0
0 0
0 1
0 1
0 0
0 0
0 2
TOTALS 0
0 0
19 68 211 160 17 0
0 0
0 475 NUMBER OF VA'ID HOURS 475 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 475 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
.';0
.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
2 0
0 0
0 0
0 0
0 2
NE 0
0 0
0 2
0 0
1 0
0 0
0 3
ENE 0
0 0
0 0
0 1
0 0
0 0
0 1
E 0
1 0
0 0
0 0
0 0
0 0
0 1
ESE 0
0 0
0 0
1 0
0 0
0 0
0 1
SE 0
0 0
1 1
0 1
0 0
0 0
0 3
SSE 0
0 0
1 1
2 0
3 0
0 0
0 7
S 0
0 0
1 1
1 3
0 0
0 0
0 6
SSW 0
0 0
0 0
3 1
0 0
0 0
0 4
SW 0
0 0
1 4
2 1
0 0
0 0
0 8
WSW 0
0 0
2 3
2 1
0 0
0 0
0 8
W 0
0 0
3 0
6 2
0 0
0 0
0 11 WNW 0
0 0
1 1
2 1
0 0
0 0
0 5
NW 0
0 1
1 1
3 5
0 0
0 0
0 11 NNW 0
0 0
2 0
0 0
0 0
0 0
0 2
TOTALS 0
1 1
15 14 22 16 4
0 0
0 0
73 NUMBER OF VALID HOURS NUMBER OF INV'ALID HOURS 73 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
73 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05100100-05123123 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 2
4 0
0 0
0 0
0 0
6 NNE 0
0 0
7 1
0 0
0 0
0 0
0 8
NE 0
0 0
2 0
0 0
0 0
0 0
0 2
ENE 0
0 0
0 0
2 0
0 0
0 0
0 2
E 0
1 0
0 0
0 0
0 0
0 0
0 1
ESE 0
0 0
0 0
0 1
0 0
0 0
0 1
SE 0
0 0
1 2
1 2
0 0
0 0
0 6
SSE 0
0 0
0 0
1 2
4 0
0 0
0 7
S 0
0 0
1 0
3 0
0 0
0 0
0 4
SSW 0
0 0
1 1
1 0
0 1
0 0
0 4
SW 0
0 0
2 1
3 0
0 0
0 0
0 6
WSW 0
0 0
5 0
3 0
0 0
0 0
0 8
W 0
0 0
6 3
2 0
0 0
0 0
0 11 WNW 0
0 1
1 3
4 0
0 0
0 0
0 9
NW 0
0 1
1 2
3 2
0 0
0 0
0 9
NNW 0
0 0
1 0
0 0
0 0
0 0
0 1
TOTALS 0
1 2
30 17 23 7
4 1
0 0
0 85 NUMBER OF VALID HOURS 85 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 85 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
1 4
4 4
1 0
0 0
0 0
14 NNE 0
0 0
4 7
5 5
0 0
0 0
0 21 NE 0
1 0
3 0
2 0
2 0
0 0
0 8
ENE 0
0 0
1 0
4 0
0 0
0 0
0 5
E 0
0 0
4 2
6 0
1 0
0 0
0 13 ESE 0
0 0
1 0
9 11 5
1 0
0 0
27 SE 0
0 3
2 4
18 30 6
0 0
0 0
63 SSE 0
0 1
4 9
17 19 10 1
0 0
0 61 S
0 0
1 0
6 7
5 6
1 0
0 0
26 SSW 0
0 0
3 1
5 7
3 4
0 0
0 23 SW 0
0 5
1 6
2 1
0 0
0 0
0 15 WSW 0
0 0
8 6
0 1
0 0
0 0
0 15 W
0 0
3 4
5 5
2 0
0 0
0 0
19 WNW 0
0 1
5 6
7 3
0 0
0 0
0 22 NW 0
0 0
5 4
14 12 0
0 0
0 0
35 NNW 0
0 2
5 10 11 3
0 0
0 0
0 31 TOTALS 0
1 17 54 70 116 100 33 7
0 0
0 398 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 398 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
398 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05100100-05123123 WIND SPEED (M/S)
AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < 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 lOTAL DIR
.O
.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N
0 0
0 6
12 11 1
0 0
0 0
0 30 NNE 0
1 0
8 8
17 10 2
0 0
0 0
46 NE 0
0 1
5 1
2 1
1 0
0 0
0 11 ENE 0
1 1
2 0
5 1
0 0
0 0
0 10 E
0 1
1 3
7 4
1 1
0 0
0 0
18 ESE 0
0 0
2 1
3 0
0 0
0 0
0 6
SE 0
0 2
1 1
5 5
0 0
0 0
0 14 SSE 0
0 0
2 2
6 1
0 0
0 0
0 11 S
0 0
0 4
2 3
0 0
0 0
0 0
9 SSW 0
0 0
3 2
2 0
0 0
0 0
0 7
SW 0
0 2
1 5
1 0
0 0
0 0
0 9
WSW 0
0 0
3 4
2 0
0 0
0 0
0 9
W 0
0 0
0 5
3 1
0 0
0 0
0 9
WNW 0
0 2
3 7
18 2
0 0
0 0
0 32 NW 0
0 1
5 3
11 1
0 0
0 0
0 21 NNW 0
1 1
1 5
6 1
0 0
0 0
0 15 TOTALS 0
4 11 49 65 99 25 4
0 0
0 0
257 NUMBER OF VALID HOURS 257 NUMBER OF CALMS 0
NUMBER OF INV'ALID HOURS 0
TOTAL HOURS FOR THE PERIOD 257 PASQUILL F MODERATELY STABLE (1.5 < 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 lOTAL 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 7
5 6
2 0
0 0
0 0
21 NNE 0
O 0
18 24 64 13 1
0 0
0 0
120 NE
)
1 3
15 7
8 1
2 1
0 0
0 38 ENE O
0 2
8 5
5 0
0 0
0 0
0 20 E
O 0
0 0
1 5
0 0
0 0
0 0
6 ESE
'O 0
0 2
3 1
0 0
0 0
0 0
6 SE O2 0
0 0
0 1
0 0
0 0
0 0
1 SSE O
1 1
1 1
1 0
0 0
0 0
0 5
S
')
0 0
2 5
1 0
0 0
0 0
0 8
SSW I) 0 1
1 1
2 1
0 0
0 0
0 6
SW I) 0 1
5 1
2 0
0 0
0 0
0 9
WSW I) 0 3
2 1
1 0
0 0
0 0
0 7
W (3
0 1
2 4
5 0
0 0
0 0
0 12 WNW
(
0 1
3 5
13 2
0 0
0 0
0 24 NW
()
0 0
2 3
4 1
0 0
0 0
0 10 NNW
()
1 1
5 2
2 3
0 0
0 0
0 14 TOTALS
(
3 15 73 68 121 23 3
1 0
0 0
307 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 307 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
307 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2005)
METEOROLOGY October -
December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 05100100-05123123 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 2
10 9
7 0
0 0
0 0
28 NNE 0
0 1
7 35 175 182 1
0 0
0 0
401 NE 0
1 0
8 21 17 5
0 0
0 0
0 52 ENE 0
0 0
3 6
9 2
0 0
0 0
0 20 E
0 0
1 2
3 7
0 0
0 0
0 0
13 ESE 0
0 1
2 5
2 2
0 0
0 0
0 12 SE 0
0 1
4 1
1 3
0 0
0 0
0 10 SSE 0
0 3
3 5
4 1
0 0
0 0
0 16 S
0 1
3 0
2 1
0 0
0 0
0 0
7 SSW 0
0 0
4 0
2 1
0 0
0 0
0 7
SW 0
1 0
1 0
0 0
0 0
0 0
0 2
WSW 0
1 0
1 3
2 2
0 0
0 0
0 9
W 0
0 0
2 4
2 0
0 0
0 0
0 8
WNW 0
0 1
4 1
4 1
0 0
0 0
0 11 NW 0
0 0
1 2
5 1
0 0
0 0
0 9
NNW 0
0 0
0 3
2 3
0 0
0 0
0 8
TOTALS 0
4 11 44 101 242 210 1
0 0
0 0
613 NUMBER OF VALID HOURS 613 NUMBER OF CALMS 0
NUMBER OF INVALID HOURS 0
TOTAL HOURS FOR THE PERIOD 613 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
2 21 35 30 11 0
0 0
0 0
99 NNE 0
1 1
46 75 261 210 4
0 0
0 0
598 NE 0
3 4
33 31 29 7
7 1
0 0
0 115 ENE 0
1 3
14 11 26 4
0 0
0 0
0 59 E
0 3
2 9
13 22 1
2 0
0 0
0 52 ESE 0
0 1
7 9
16 14 5
1 0
0 0
53 SE 0
0 6
10 9
26 41 6
0 0
0 0
98 SSE 0
1 5
14 18 34 28 17 1
0 0
0 118 S
0 1
4 8
24 39 29 12 1
0 0
0 118 SSW 0
0 1
13 15 33 21 3
5 0
0 0
91 SW 0
1 8
15 30 31 9
0 0
0 0
0 94 WSW 0
1 3
27 35 44 17 1
0 0
0 0
128 W
0 0
4 18 34 111 59 2
0 0
0 0
228 WNW 0
0 6
18 28 70 53 7
0 0
0 0
182 NW 0
0 3
17 15 41 26 0
0 0
0 0
102 NNW 0
2 4
14 21 21 11 0
0 0
0 0
73 TOTALS 0
14 57 284 403 834 541 66 9
0 0
0 2208 NUMBER OF VALID HOURS NUMBER OF INVALID HOURS 2208 0
NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 0
2208