ML071230130

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Annual Radioactive Effluent Release Report for 2006
ML071230130
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 12/31/2006
From:
Southern California Edison Co
To:
NRC/FSME
References
Download: ML071230130 (110)
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SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2006 January - December

SOUTHERN CALIFORNIA EDISON An EDISON INTERNATIONAL 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 pres.surized water reactors with a total rated capacity of 2254 net megawatts electrical.

Unit 1, rated at 410 net megawatts electrical, was supplied by Westinghouse Electric Company and began commercial operation on January 1, 1968. The unit was permanently shutdown on November 30, 1992. 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 net megawatts electrical each. The twin units are owned by Southern California Edison (75.05%), San Diego Gas and Electric (20%), City of Anaheim (3.16%), and the City of Riverside (1.79%).

Effective December 29, 2006, the City of Anaheim has transferred its ownership interests in San Onofre Units 2 and 3 and the entitlement to the Units 2 and 3 output, to Southern California Edison Company, except that it retains its ownership interests in its spent nuclear fuel and Units 2 and 3's independent spent fuel storage installation located on the facility's site. In addition, the City of Anaheim retains financial responsibility for its spent fuel and for a portion of the Units 2 and 3 decommissioning costs. The City of Anaheim remains a licensee for purposes of its retained interests and liabilities.

-1i-P.O. Box 128 San Clemente, CA 92674-0128

S.O.N .G.S. 1 TABLE OF CONTENTS SECTION A - INTRODUCTION . . . . . . . . . . . .

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

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

SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM .... ....... 14 SECTION E - RADWASTE SHIPMENTS ......... . . . . . . . . . . . . 15 SECTION F - APPLICABLE LIMITS. .............. . . . . . . . . . . . . 19 SECTION G - ESTIMATION OF ERROR ... .......... . . . . . . . . . . . . 21 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS . . . . . . . . . . . . . . 22 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MI\NUAL . . . .. . . . . . . . . 26 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTE MS ........ .......... 29 SECTION K - MISCELLANEOUS ..... ................ . . . . . . . . . . . . 31 SECTION L - S.O.N.G.S. 1 CONCLUSIONS . . . . . . . . . . . . . . . . . . . . . 33

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

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

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories: fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.

Listed for each of the four categories are:

(1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total error Unit 1 is undergoing decommissioning and all of the fuel is stored in the ISFSI.

Batch releases were stopped on 8/4/1993 and continuous releases were terminated on 11/27/2006. The last Offsite Dose Calculation Manual (ODCM) credited airborne release point, the Plant Vent Stack (PVS), was removed from the ODCM on 11/27/2006.

In addition, the particulate category lists the gross alpha radioactivity released for each quarter.

The methodology used to calculate the percent of Applicable Limit is presented in Section F of this report. The methodology used in Table 1A to calculate the estimated total error is presented in Section G of this report.

Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Unit 1 does not conduct elevated releases.

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

fission gases, iodines, and particulates.

Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and IC for continuous mode releases only.

Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period.

Table IF, "Gaseous Effluents-Batch Release Summary," has been deleted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. I TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error, %

A. Fission and activation gases

1. Total release Ci N/A N/A N/A
2. Average release rate for period gCi/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. lodines
1. Total iodine-131 Ci N/A N/A N/A
2. Average release rate for period MCi/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 1.15E-6 11 " 2.70E-6 1.60E+11
2. Average release rate for period gCi/sec 1.48E-7 3.43E-7
3. Percent of applicable limit  % MPC 3.85E-7 1.15E-6
4. Percent Effluent Concentration Limit  % ECL 9.61E-7 5.12E-6
5. Gross alpha activity Ci <LLD <LLD 5.OOE+1 D. Tritium
1. Total release Ci <LLD 8.08E-1 2.50E+1
2. Average release rate for period MCi/sec O.OOE+O 1.03E-1
3. Percent of applicable limit  % MPC O.OOE+O 6.68E-4
4. Percent Effluent Concentration Limit  % ECL O.OOE+O 1.34E-3 (1) On 3/7/2006, plant vent stack particulate samples were not collected for 68 minutes. During this time, there was no work being performed in the building. The prior and subsequent sample results were <LLD.

There were no dose consequences to a member of the public as a result of this event which is documented in AR #060300357.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

GASEOUS EFFLUENTS-.SUMMATION OF ALL RELEASES Estimated Third Fourth Total Quarter Quarter Error, %

A. Fission and activation gases

1. Total release Ci N/A N/A N/A
2. Average release rate for period 4Ci/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. lodines
1. Total iodine-131 Ci N/A N/A N/A
2. Average release rate for period AzCi/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 1.97E-8 4.92E-9 1.60E+1
2. Average release rate for period ktCi/sec 2.48E-9 6.19E-10
3. Percent of applicable limit  % MPC 6.44E-9 1.61E-9
4. Percent Effluent Concentration Limit  % ECL 1.61E-8 4.02E-9
5. Gross alpha activity Ci <LLD <LLD 5.OOE+1 D. Tritium
1. Total release Ci <LLD 7.73E-2 2.50E+1
2. Average release rate for period kiCi/sec O.OOE+O 9.72E-3
3. Percent of applicable limit  % MPC O.OOE+O 6.32E-5
4. Percent Effluent Concentration Limit  % ECL O.OOE+O 1.26E-4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 TABLE IC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation gases krypton-85 Ci 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.lodines 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 1.15E-6 1.54E-6 1.97E-8 4.92E-9 cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD 1.17E-6 <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 ID.

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 (2006)

S.O.N.G.S. 1 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides I LLD (uCi/cc)

1. Fission and activation gases krypton-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. lodines iodine-131 N/A iodine-133 N/A iodine-135 N/A
3. Particulates barium-140 4.30E-13 cerium-141 5.50E-14 cerium-144 2.20E-13 cesium-134 1.20E-13 cobalt-58 1.1OE-13 cobalt-60 1.70E-13 iron-59 2.70E-13 lanthanum-140 8.50E-13 manganese-54 1.10E-13 molybdenum-99 6.50E-14 strontium-89 1.OOE-11 strontium-90 1.OOE-11 zinc-65 2.90E-13
4. alpha 1.OOE-11
5. tritium 7.20E-8 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 (2006)

S.O.N.G.S. 1 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas

1. Gamma. Air Dose mrad 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 4.94E-6 6.17E-5 7.25E-8 4.48E-6
2. Percent Applicable Limit  % 6.59E-5 8.23E-4 9.67E-7 5.97E-5 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 (2006)

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 Unit 1 is undergoing decommissioning and all of the fuel is stored in the ISFSI.

As of the third quarter 2005, batch releases are no longer being conducted due to the demolition of the liquid radwaste system.

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 "continuous" mode of release. Continuous releases through the Unit 1 outfall were terminated on 10/16/2006.

The new North Industrial Area (NIA) yard drain sump discharges through either the Unit 2 or Unit 3 outfall.

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," has been deleted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci <LLD 2.04E-6 1.90E+1
2. Average diluted concentration during period gCi/ml O.OOE+O 1.31E-12
3. Percent of applicable limit  % MPC O.OOE+O 6.54E-6
4. Percent Effluent Concentration Limit  % ECL O.OOE+O 1.31E-4 B. Tritium
1. Total release Ci 7.34E-3 1.87E-4 1.90E+1
2. Average diluted concentration during period uCi/ml 7.48E-9 1.20E-1O
3. Percent of applicable limit  % MPC 2.49E-4 4.OOE-6
4. Percent Effluent Concentration Limit  % ECL 7.48E-4 1.20E-5 C. Dissolved and entrained gases
1. Total release Ci N/A N/A N/A
2. Average diluted concentration during period 4Ci/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+I E. Volume of waste released (batch &

continuous, prior to dilution) liters 3.42E+6 1.75E+4 5.OOE+O F. Volume of dilution water used during period liters 9.81E+8 1.56E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 TABLE 2A (Continued)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit Quarter Quarter Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 4.19E-5 <LLD 1.90E+1
2. Average diluted concentration during period uCCi/ml 2.24E-11 O.OOE+O
3. Percent of applicable limit  % MPC 1.12E-4 O.OOE+O
4. Percent Effluent Concentration Limit  % ECL 2.24E-3 O.OOE+O B. Tritium
1. Total release Ci 3.46E-1 4.73E-2 1.90E+1
2. Average diluted concentration during period pXCi/ml 1.85E-7 4.01E-8
3. Percent of applicable limit  % MPC 6.17E-3 1.34E-3
4. Percent Effluent Concentration Limit  % ECL 1.85E-2 4.01E-3 C. Dissolved and entrained gases
1. Total release Ci N/A N/A N/A
2. Average diluted concentration during period UCi/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 8.44E+5 3.03E+7 5.OOE+O F. Volume of dilution water used during period liters 1.87E+9 1.18E+9 5.OOE+O

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. I TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci <LLD 2.04E-6 4.19E-5 <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 2.04E-6 4.19E-5 <LLD
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.

NOTE: Due to the removal of the Liquid Radwaste System at S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. I TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides LLD (ktCi/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 I.OOE-7 NOTE: Due to the removal of the Liquid Radwaste System at S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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.

I. Total body dose mrem 4.56E-6 3.54E-5 8.67E-4 8.40E-6

2. Percent Applicable Limit 3.04E-4 2.36E-3 5.78E-2 5.60E-4 B.
1. Limiting organ dose mrem 4.56E-6 5.41E-5 1.22E-3 8.40E-6
2. Percent Applicable Limit  % 9.12E-5 1.08E-3 2.44E-2 1.68E-4
3. Limiting organ for period GI-LLI
  • Liver Liver GI-LLI *
  • All organs except bone TABLE 2E 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 (2006)

S.O.N.G.S. 1 SECTION D PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 N/A evaporator bottoms Ci N/A N/A
b. Dry active waste (DAW), m3 9.50E+3 compactable and non-compactable (incl. demolition rubble)
  • Ci 5.08E+1 3.OOE+1
c. Irradiated components m3 9.63E+O (Structural members & reactor piping)
  • Ci 3.07E+O 3.OOE+1
d. Other: (Mechanical filters)# m3 8.43E+1 Ci 1.42E-1 3.OOE+1 NOTE: Total curie content estimated.
  • Material packaged in various General Design, IP-1., USA DOT 7A Type A, and Type A packaging.
  1. Material packaged in General. Design Packaging.

N/A No Shipment made ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1

2. Estimate of major nuclide composition (by type of waste)
a. Not applicable _ N/A
b. americium-241  % 3.63E-2 carbon-14  % 2.40E+O cerium-144  % 2.25E-1 cesium-134  % 7.55E-1 cesium-137 _ 3.35E+1 cobalt-60  % 1.59E+1 curium-242  % 6.96E-5 curium-243/244  % 1.22E-2 europium-152  % 7.31E+O europium-154 _ 5.09E-1 iron-55  % 1.38E+1 nickel-59 0 2.72E-3 nickel-63  % 1.53E+1 niobium-94  % 9.98E-4 plutonium-238  % 3.52E-3 plutonium-239/240  % 1.90E-3 plutonium-241  % 8.41E-2 pl utonium-242  % 2.07E-5 silver-110m 0 7.15E-3 strontium-89 __1.50E-3 strontium-90 __1.25E-1 technetium-99 __2.49E-2 tritium  % 1.03E+I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1

2. Estimate of major nuclide composition (by type of waste)
c. carbon-14  % 8.60E-2 cobalt-60  % 6.09E+I iron-55 _ 1.16E+1 manganese-54  % 6.42E-4 nickel-59  % 3.07E-1 nickel-63  % 2.69E+I niobium-94  % 1.13E-3 technetium-99 _ 2.09E-2
d. americium-241  % 4.65E-1 carbon-14  % 3.96E-2 cerium-144  % 4.10E-2 cesium-134  % 8.36E-1 cesium-137  % 5.78E+I cobalt-60  % 6.67E+O curium-242 _ 2.68E-3 curium-243/244  % 9.04E-2

-europium-154  % 8.31E-3 iron-55 _ 1.83E+O nickel-63  % 2.13E+I niobium-94  % 1.16E-2 plutonium-238  % 3.78E-I plutonium-239/240 _ 1.54E-1 plutonium-241 _ 9.49E+O plutonium-242  % 2.98E-3 strontium-89 2.91E-1 strontium-90  % 4.57E-1 technetium-99  % 3.54E-2 tritium  % 1.44E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 3 Hittman Trucking Company EnergySolutions, UT 3* Truck I
  • TAG Transport EnergySolutions, UT Truck 2
  • TRIAD Transport Inc. EnergySolutions, UT Truck 31 TAG Transport EnergySolutions, UT Truck 303 MHF Logistical Solutions EnergySolutions, UT Rail
  • SONGS maintains contracts with vendors (Alaron and EnergySolutions, formerly known as Duratek) that provide volume reduction services. The processed volume was shipped from the vendor's facility to EnergySolutions in Clive, UT using 7 shipments. Those 7 shipments included waste from other generators. SCE's waste volume was a fraction of the total waste volume of these shipments.
    • Three of these shipments contained irradiated components.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 .(Rel Rate) (X/Q) (100)

MPCeff where: Rel Rate total curies released in each category and each .quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, /pCi/sec.

1.30E-5 sec/m3 ; the annual average atmospheric dispersion defined X/Q in the ODCM.

1 0 MPCeff 1=1 MPC i where: F1 fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, C T.

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

  • %ECL (Rel Rate) (X/Q) (100)

ECLeff where: Rel Rate total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, uCi/sec.

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

1 n F.

0. I ECLeff Fi i=i ECL where: Fi fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C1 , by the sum of all the isotopic activity, C3T n total number of radionuclides identified ECL1 Effluent Concentration Limit (ECL) of the i t h radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. I Liauid Effluents - ADDlicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, and C.3 of Table 2A, were calculated using the following equations:

% Applicable Limit (Dil Conc) (100)

MPCeff where: Dil Conc total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, ptCi/ml.

1 0 MPCef1 MPF.

i=1 MPC i where: Fi 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" n total number of radionuclides identified MPCG Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.

ECL (Dil Conc) (100)

ECLeff where: Dil Conc total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, ktCi/ml.

0 ECLeff i ECLi where: Fi fractional abundance of the i t" radionuclide obtained by dividing the activity (curies) for each radionuclide, C j, by the sum of all the isotopic activity, CT.

n total number of radionuclides identified ECL 1 Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. I SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made.

Sources of error for gaseous effluents - batch releases are:

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

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

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

(1) dilution flow rate (2) sampling (3) counting (4) calibration These sources of error are independent, and thus, the total error is calculated according to the following formula:

Total Error = 2 + + (72 + ... (32 where: 0i Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

Six different categories are presented:

(1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, lodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation The doses for categories I 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 methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

For members of the public, per the ODCM, who may at times be within the site boundary',

the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. For members of the public who traverse the site boundary via highway 1-5, the residency time shall be considered negligible and hence the dose "0".

Table 2 in Section H presents the percent of Applicable Limits for each dose presented in Table 1.

ODCM Figures 1-2 and 2-2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. I TABLE I Dose * (millirems)

First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS 1) 2) 3) 4) 5)

Whole Body 4.56E-6 3.54E-5 8.67E-4 8.40E-6 9.15E-4

6) 7) 8) 9) 10)

Organ 4.56E-6 5.41E-5 1.22E-3 8.40E-6 1.29E-3 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15)

Tritium, Iodines, and Particulates 9.33E-5 1.18E-3 1.14E-6 1.13E-4 1.38E-3 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 1.95E-1 1.78E-1 1.44E-1 8.78E-2 5.74E-1 The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1

6. This value was calculated using the methodology of the ODCM; GI-LLI, (all organs, except bone) received the maximum dose primarily by the saltwater fish pathway.
7. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
8. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
9. This value was calculated using the methodology of the ODCM; GI-LLI, (all organs, except bone) received the maximum dose primarily by the saltwater fish pathway.
10. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.
11. 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
12. The maximum organ dose was to a teen's lung and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
13. 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.
14. The maximum organ dose was to the teen's liver and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
15. The maximum organ dose was to the teen's lung and was located in the NNE sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
16. Noble Gas is no longer generated.
17. Noble Gas is no longer generated.

18, Noble Gas is no longer generated.

19. Noble Gas is no longer generated.
20. Noble Gas is no longer generated.
21. Noble Gas is no longer generated.
22. Noble Gas is no longer generated.
23. Noble Gas is no longer generated.
24. Noble Gas is no longer generated
25. Noble Gas is no longer generated.
26. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector.
27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. I

28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector.
29. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the WSW sector.
30. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector.

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 3.04E-4 2.36E-3 5.78E-2 5.60E-4 3.05E-2 Organ 9.12E-5 1.08E-3 2.44E-2 1.68E-4 1.29E-2 AIRBORNE EFFLUENTS Tritium, lodines, 1.24E-3 1.58E-2 1.52E-5 1.50E-3 9.17E-3 and 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 (2006)

S.O.N.G.S. 1 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 24, 2006, Revision 24 to the Unit 1 Offsite Dose Calculation Manual (ODCM)was adopted and published. This change incorporated updates from the 2004-2005 Land Use Census (LUC).

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.

None of the changes impacted 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 IOCFR50 will be maintained.

Throughout the document, change bars were marked in one of four ways as follows:

  • A Addition D Deletion F Editorial/Format change R Revision New Change Reason Page #

ii Modified to reflect added page R 2-21 Modified Controlling Location Factors per LUC R 2-22 Revised Ri values per LUC R 2-24 Revised Ri values and changed name of pathway per LUC R 2-27 Revised Ri values per LUC R 2-30 Revised Ri values per LUC R 2-31 Revised Ri values per LUC R 2-38 Modified Sector G page numbers due to added page F 2-39 Added page of Ri values per LUC A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 On November 27, 2006, Revision 25 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated 1) the removal of the plant vent stack (PVS) system from service and 2) the earlier removal of the yard drain sump (YDS) implementing licensing change PCN 560. Both of these changes were in support of the Unit 1 demolition process. With these changes, there will be no longer be liquid or gaseous effluent release pathways credited to Unit 1.

An approved Effluent/ODCM Evaluation (EOE) was generated for each change. No 50.59 or EOE reviews were required or performed for editorial changes made to reflect actual plant operation.

None of the changes impacted the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by IOCFR20, 40CFR190, 10CFR50.35a and Appendix I to IOCFR50 will be maintained.

Throughout the document, change bars were marked in one of four ways as follows:

A Addition D Deletion F Editorial/Format change R Revi si on New Change Reason Page #

ix Added note detailing the removal of the yard drain sump (YDS) A and the plant vent stack (PVS) from Unit 1 1-1 Added note detailing specification 1.0 as no longer A applicable.

1-3 Deleted batch release types, and sampling, and analysis D frequencies that are no longer required.

1-10 Added note detailing specification 1.4 as no longer A applicable 1-20 Added note detailing specification 1.5 as no longer A applicable 1-23 Added note detailing specification 1.6 as no longer A applicable 2-1 Added note detailing specification 2.0 as no longer A applicable 2-2 Added note detailing specification 2.1 as no longer A applicable ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 2-3 Deleted batch release types and sampling and analysis frequencies that are no longer required 2-8 Added note detailing specification 2.3 as no longer applicable 4-1 Added note detailing specification 4.0 as no longer applicable.

4-2 Deleted instrument monitoring requirements 4-5 Deleted instrument surveillance requirements 4-7 Added note detailing specification 4.2 as no longer applicable.

4-8 Deleted monitoring requirements 4-9 Deleted action table 4-10 Added note detailing specification 4.2.2 as no longer applicable.

4-11 Deleted instrument surveillance requirements 4-12 Deleted reference to Figure 4-1 and Figure 4-2 4-13 Deleted Figure 4-1; there are no longer any liquid release pathways at Unit 1.

4-14 Deleted Figure 4-2; there are no longer any gaseous release pathways at Unit I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Demolition of the Yard Drain Sump System On October 16, 2006, the Unit 1 Yard Drain Sump (YDS) was permanently removed from service per PCN 560. The sump pumps, piping, and radiation monitoring system skid (RT-2101) were removed from service for demolition, a result of the ongoing decommissioning activities at Unit 1.

The Unit 1 YDS system was designed to collect the drains from the backyard area, and surface runoff from the Unit 1 footprint (now known as the North Industrial Area) and the AWS complex/area. Due to the pending removal from service of the Unit 1 outfall and its associated pumps, a new, larger sump, now known as the North Industrial Area (NIA) YDS, has been built. The new NIA YDS performs the functions of the old YDS, in that it collects all the same drains and surface runoff. On 10/16/2006, the NIA YDS was placed in service, with its discharge being directed either to the Unit 2 or to the Unit 3 outfall. As a result, there are no longer any releases from the Unit 1 YDS which was the sole remaining ODCM-credited liquid release point.

Releases from the NIA YDS are controlled under Units 2/3 ODCM. All of the sampling and monitoring provisions that were in the Unit I ODCM were transferred to the'Units 2/3 ODCM Revision 42. Releases from the NIA YDS will be included in the Unit 2/3 totals.

Similarly, existing Unit 2/3 dose and concentration limits will apply to the NIA YDS.

All radioactive releases from SONGS will continue to meet all regulatory requirements, including dose limits and concentrations requirements for liquid releases.

This change does not adversely affect the effluent control program; the resultant doses or curies will continue to be ALARA and to meet all applicable regulatory requirements. Any radioactive waste liquid from the site will now be discharged through the Unit 2 or the Unit 3 outfall and be controlled by the Units 2&3 ODCM.

See also Section J of Units 2/3 ARERR (2006).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 Demolition of the Plant Vent Stack System Per ECP 050200988, the Plant Vent Stack (PVS) system, including the associated particulate sampler R-1254 was removed from service upon completion of the Unit 1 containment dome internal decontamination and demolition. This change is a result of the ongoing decommissioning activities at Unit 1.

The PVS was designed to provide a controlled ventilation exhaust pathway from various buildings at Unit 1 and to provide a means of sampling and monitoring prior to release to the environment. Radiation monitoring and sampling instrumentation was installed to satisfy regulations and control releases from the PVS system as an ODCM-credited release point. Following the Unit 1 permanent shut down and the decay of any airborne source term, the requirement to monitor for noble gas or to sample for iodine at Unit 1 was removed from the ODCM when all the fuel was transferred to the Independent Spent Fuel Storage Installation (ISFSI) (see AR 040501435-2). Subsequently, the only remaining required feature of R-1254 was the PVS particulate sampler.

As part of decommissioning, several buildings have already been demolished. The remaining building internals have, to the extent practical, been decontaminated to below the established administrative values requiring airborne effluent controls during decommissioning(see AR 061000193). For work on areas above the established administrative values, one or more contamination control measures are required to minimize the potential for unmonitored releases of airborne radioactive effluents. The contamination control method employed for demolishing the remaining buildings has been the use of coating/paints (see AR 061000193-2). The use of portable enclosures and local ventilation controls would be impractical for the demolition of the buildings themselves. Further, while it is unlikely that any radioactive particulate matter will actually be released from the site during these evolutions due to the use of prudent contamination control measures, continuous local air samples will be taken during building demolition.

Prior to demolishing the remaining buildings, the PVS needed to be removed since it was an obstruction to the safe and controlled demolition of the buildings. The demolition of the PVS and sampler included removing the fans, ducting, stack, and sampler skid.

Existing site procedures and programs are in place to sample the final building demolition process. Based on historical air sample data, no airborne radioactivity was expected during this last phase of work, and indeed to date, none has been found.

RG 1.21 reiterates that licensees must comply with the requirements in 10 CFR 20.106 and 10 CFR 50 Appendix A, General Design Criteria 60 and 64. All sources of airborne activity to the PVS have been removed or contained (as explained above) and the PVS was removed as part of the decommissioning effort. The PVS was removed from service and eliminated as a Unit 1 ODCM credited release point. Demolition of the remaining buildings isnot expected to result in measurable releases of airborne radioactive material. Local air samples are being taken during demolition in support of that expectation. SCE continues to meet the regulatory requirements through the Unit 1 ODCM and the effluent control program.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 SECTION K. MISCELLANEOUS Incorrect Monitor Sample Flow On 2/10/2006 at 0330, the plant vent stack fan A-22 was secured to allow for a belt adjustment. The sample flow for RT-1254 should have been adjusted when the fan configuration changed. Flow remained at 1.75 scfm instead of the procedurally required 1.20 scfm. The result was that for 348 minutes during a one week sampling period, the sample flow was outside of the procedural guidance. There was no work identified during this period of time that created a potential for an airborne release. The results of the sample analysis for the particulate filter, as well as the filter for the week before and after were <LLD. Therefore, there was no dose consequence to a member of the public as a result of this event which is documented in AR 060200615.

Incorrect Sample Preparation for the Off-Site Analysis In May 2006, it was discovered that the off-site liquid and gaseous composite samples were being prepared using an equal aliquot rather than relative proportions. Upon notification, the vendor immediately modified their procedures to use proportional sampling to prepare the composites for analysis. The affected time period was 2000 through 2005. Evaluation of all results for those years showed that the reported totals were conservative or within the error of analysis while still being an insignificant percent of any dose limit. There were no dose consequences to a member of the public as a result of this event which is documented in AR 060901296.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. I EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2006 - December 31, 2006 None.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 1 SECTION L. S.O.N.G.S. 1 CONCLUSIONS Gaseous releases totaled 8.85E-1. curies of which particulates were 3.88E-6 curies, and tritium was 8.85E-1 curies. (Noble gases and iodines are no longer released)

The radiation doses from gaseous releases were: organ dose: 1.38E-3 mrem at the nearest receptor. (No dose was attributed to gamma and beta radiation since noble gases and iodines are no longer released)

Liquid releases totaled 4.01E-1 curies of which particulates and iodines were 4.39E-5 curies, tritium was 4.01E-1 curies, and noble gases were O.OOE+O curies.

The radiation doses from liquid releases were: (a) total body: 9.15E-4 mrem, (b) limiting organ: 1.29E-3 mrem.

The radioactive releases and resulting doses generated from Unit I were below the Applicable Limits for both gaseous and liquid effluents.

S.O.N.G.S. 2 and 3 TABLE OF CONTENTS SECTION A - INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 SECTION B - GASEOUS EFFLUENTS ...... ............... . . . . . . . . . . . 35 SECTION C - LIQUID EFFLUENTS . . . . . . . . . . . . ... . . . . . . . . . . . 45 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM ... ........ .54 SECTION E - RADWASTE SHIPMENTS .............. . .... . . . . . . . 55 SECTION F - APPLICABLE LIMITS ...... ............... . . . . . . . . . . . 59 SECTION G - ESTIMATION OF ERROR ..... ............... . . . . . . . . . . . 61 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS ......... . . . . . . . . . . . 62 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL . . . . . . . . . . . 66 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS . . . . . . . . . . . 68 SECTION K - MISCELLANEOUS . . .. ..... .............. . . . . . . . . . . . 71 SECTION L - S.O.N.G.S. 2 and 3 CONCLUSIONS ........ . . . . . . . . . . . 74

-iii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 (2006)

S.O.N.G.S. 2 and 3 SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories: fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium.

Listed for each of the four categories are:

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

The methodology used to calculate the percent of Applicable Limit is presented in Section F of this report. The methodology used in Table IA to calculate the estimated total error is presented in Section G of this report.

Table IB, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Units 2 and 3 do not conduct elevated releases.

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

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

Waste gas decay tank releases are considered to be "batch" releases. Containment purges and plant stack releases are considered to be "continuous" releases.

Table ID, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and iC.

Table 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," 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 (2006)

S.O.N.G.S. 2 and 3 TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error, %

.A. Fission and activation gases I. Total release Ci 5.43E+1 2.27E+1 3.OOE+1

2. Average release rate for period kiCi/sec 6.98E+O 2.89E+O
3. Percent of applicable limit  % MPC 1.38E-2 6.34E-3
4. Percent Effluent Concentration Limit  % ECL 1.85E-2 1.05E-2 B. Iodines
1. Total iodine-131 Ci 1.23E-3 1.03E-4 1.90E+1
2. Average release rate for period 4Ci/sec 1.58E-4 1.31E-5
3. Percent of applicable limit  % MPC 7.59E-4 6.29E-5
4. Percent Effluent Concentration Limit  % ECL 3.80E-4 3.14E-5 C. Particulates
1. Particulates with half-lives >8 days Ci 4.64E-4 3.28E-4 1.60E+1
2. Average release rate for period AtCj/sec 5.97E-5 4.18E-5
3. Percent of applicable limit  % MPC 2.91E-5 1.62E-5
4. Percent Effluent Concentration Limit  % ECL 1.05E-4 4.76E-5
5. Gross alpha activity Ci <LLD <LLD 5.OOE+1 D. Tritium
1. Total release Ci 1.26E+I1 5.41E+O 2.50E+1
2. Average release rate for period ptCi/sec 1.62E+O 6.88E-1
3. Percent of applicable limit  % MPC 3.89E-3 1.65E-3
4. Percent Effluent Concentration Limit  % ECL 7.78E-3 3.30E-3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 1A (Continued)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit Quarter Quarter Error, %

A. Fission and activation gases

1. Total release Ci 3.51E+1 5.49E+1 3.OOE+1
2. Average release rate for period jCi/sec 4.42E+0 6.91E+O
3. Percent of applicable limit  % MPC 9.55E-3 1.47E-2
4. Percent Effluent Concentration Limit  % ECL 1.53E-2 2.21E-2 B. lodines
1. Total iodine-131 Ci 9.72E-5(") 1.1OE-3(21 1.90E+1
2. Average release rate for period 4Ci/sec 1.22E-5 1.38E-4
3. Percent of applicable limit  % MPC 5.87E-5 6.64E-4
4. Percent Effluent Concentration Limit  % ECL 2.93E-5 3.32E-4 C. Particulates
1. Particulates with half-lives >8 days Ci 4.37E-4(l) 2.25E-3 12" 1.60E+1
2. Average release rate for period 4Ci/sec 5.50E-5 2.83E-4
3. Percent of applicable limit  % MPC 5.76E-5 1.13E-4
4. Percent Effluent Concentration Limit  % ECL 2.03E-4 4.44E-4
5. Gross alpha activity Ci <LLD <LLD 5.00E+I D. Tritium
1. Total release Ci 4.98E+O 1.76E+1 2.50E+I
2. Average release rate for period MCi/sec 6.27E-1 2.21E+O
3. Percent of applicable limit  % MPC 1.50E-3 5.31E-3
4. Percent Effluent Concentration Limit  % ECL 3.O1E-3 1.06E-2 (1) On 7/13/2006,parti culate and iodine samples were not taken from the condenser air ejector for 504 minutes. The iodine sample data *results were consistent with the sample results before, 8.19E-14 uCi/cc, and after the event, 3.15E-14 uCi/cc. Prior and subsequent particulate samples were <LLD. There were no dose consequences to a member of the public from this event and is documented in AR 060700517.

(2) From 10/10/2006 to 10/11/2006, particulate and iodine samples were not taken from the South Yard Facility,for 1452 minutes.

There was no work performed in contaminated areas that may have created an airborne source term. Prior and subsequent samples were <LLD. There were no dose consequences to a member of the public due to this event which is documented in AR 061000990.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE iC GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation gases argon-41 Ci 1.96E+O 1.30E+O 1.86E+O 2.48E+O krypton-85 Ci 1.92E+O 1.18E+O 4.80E-1 <LLD krypton-85m Ci <LLD <LLD <LLD 4.17E-2 krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD 2.43E-2 xenon-131m Ci <LLD 8.69E-2 <LLD 1.16E-1 xenon-133 Ci 5.02E+1 1.86E+1 2.65E+1 5.12E+1 xenon-133m Ci 2.08E-1 4.82E-4 3.75E-2 1.35E-1 xenon-135 Ci 1.03E-3 1.83E-2 7.22E-2 9.08E-1 xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci 5.43E+1 2.11E+1 2.90E+1 5.49E+1
2. lodines iodine-131 Ci 1.23E-3 1.03E-4 9.72E-5 1.1OE-3 iodine-132 Ci 9.99E-4 <LLD <LLD 6.94E-5 iodine-133 Ci 2.14E-5 8.81E-5 2.59E-4 1.63E-4 iodine-135 Ci <LLD 2.21E-6 5.94E-6 5.21E-6 Total for period Ci 2.26E-3 1.93E-4 3.62E-4 1.34E-3 LLD Lower Limit of Detection; see Table ID.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 1C (Continued)

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter I Quarter

3. Particulates antimony-125 Ci <LLD <LLD .<LLD 1.77E-5 barium-140 Ci <LLD <LLD <LLD <LLD bromine-82 Ci 4.20E-5 3.61E-5 1.05E-4 4.77E-5 cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 7.18E-5 3.43E-5 3.31E-4 5.37E-5 chromium-51 Ci 6.14E-6 <LLD <LLD 2.98E-4 cobalt-57 Ci <LLD <LLD <LLD 6.50E-6 cobalt-58 Ci 2.59E-4 2.70E-4 2.16E-5 1.30E-3 cobalt-60 Ci 4.69E-5 1.66E-5 8.43E-5 2.67E-4 iron-59 Ci 6.56E-5 1.12E-7 <LLD 4.85E-5 lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 1.34E-6 4.91E-6 <LLD 6.07E-5 molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 8.74E-6 2.54E-6 <LLD 1.29E-4 rubidium-88 Ci <LLD <LLD 1.56E-4 <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD tin-113 Ci 2.1OE-7 <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci 4.40E-6 <LLD <LLD 7.04E-5 LLD Lower Limit of Detection; see Table ID .

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE

  • First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter
1. Fission and activation gases krypton-85 Ci <LLD 8.89E-1 1.77E+O **

krypton-85m Ci <LLD <LLD 1.69E-3 **

krypton-87 Ci <LLD <LLD <LLD **

krypton-88 Ci <LLD <LLD <LLD **

xenon-131m Ci <LLD 1.80E-2 6.33E-2 **

xenon-133 Ci 2.35E-3 6.11E-1 4.21E+O **

xenon-133m Ci <LLD <LLD 6.08E-2 **

xenon-135 Ci <LLD <LLD 5.90E-2 **

xenon-135m Ci <LLD <LLD <LLD **

xenon-138 Ci <LLD <LLD <LLD **

Total for period Ci 2.35E-3 1.52+0 6.17E+O **

LLD Lower Limit of Detection; see Table ID.

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

No batch releases were conducted in the last quarter of 2006.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE ID GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides LLD (,uCi/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-131m 1.30E-6 xenon-135m 1.50E-6 xenon-138 2.60E-6
2. lodines iodine-132 1.30E-9 iodine-135 1.40E-1O
3. Particulates antimony-125 2.OOE-13 barium-140 4.60E-13 cerium-141 5.80E-14 cerium-144 2.30E-13 cesium-134 1.30E-13 chromium-51 5.10E-13 cobalt-57 2.90E-14 iron-59 2.90E-13 lanthanum-140 9.OOE-13 manganese-54 1.20E-13 molybdenum-99 7.OOE-14 niobium-95 1.20E-13 rubidium-88 6.30E-9 strontium-89 I.OOE-11 strontium-90 1.OOE-11 tin-113 8.70E-14 zinc-65 3.10E-13 zirconium-95 2.OOE-13
4. alpha I.OOE-11

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 1D (Continued)

GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides LLD (4Ci/cc)

1. Fission and activation gases krypton-85 9.OOE-4 krypton-85m 2.10E-6 krypton-87 9.10E-6 krypton-88 7.30E-6 xenon-131m 7.50E-5 xenon-133m 1.80E-5 xenon-135 2.30E-6 xenon-135m 2.80E-5 xenon-138 4.40E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas

1. Gamma Air Dose mrad 5.48E-3 2.88E-3 4.33E-3 6.60E-3
2. Percent Applicable Limit  % 5.48E-2 2.88E-2 4.33E-2 6.60E-2
3. Beta Air Dose mrad 9.61E-3 4.35E-3 6.59E-3 9.83E-3
4. Percent Applicable Limit  % 4.81E-2 2.17E-2 3.29E-2 4.91E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)
1. Organ Dose mrem 4.25E-3 7.59E-4 1.92E-3 5.48E-3
2. Percent Applicable Limit  % 2.84E-2 5.06E-3 1.28E-2 3.65E-2 NOTE:. Calculations performed in accordance with the ODCM utilizing the historical X/Q.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE IF GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 11 releases
2. Total time period for batch releases: 4164 minutes
3. Maximum time period for a batch release: 547 minutes
4. Average time period for a batch release: 379 minutes
5. Minimum time period for a batch release: 206 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are:

(1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists:

(1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution)

(3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report.

Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category. The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.

Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B.

Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period.

Table 2E, "Liquid Effluents-Batch Release Summary," provides summaryinformation regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Units 2 and 3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error, %

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 1.12E-2 1.50E-2 11) 1.90E+1
2. Average diluted concentration during period kiCi/ml 1.99E-11 1.99E-11
3. Percent of applicable limit  % MPC 3.69E-5 2.20E-5
4. Percent Effluent Concentration Limit  % ECL 2.75E-4 1.52E-4 B. Tritium
1. Total release Ci 2.38E+2 3.78E+2 1.90E+1
2. Average diluted concentration during period yCi/ml 4.21E-7 5.OOE-7
3. Percent of applicable limit  % MPC 1:-.40E-2 1.67E-2
4. Percent Effluent Concentration.Limit  % ECL -4.21E-2 5.OOE-2 C. Dissolved and entrained gases
1. Total release Ci 3.81E-3. 3.81E-2 1.90E+1
2. Average diluted concentration during period . iCi/ml 6.75E-12 5.04E-11
3. Percent of applicable limit  % MPC 3.37E-6 2.52E-5
4. Percent Effluent Concentration Limit  % ECL 3.37E-6 2.52E-5 D. Gross alpha radioactivity
1. Total release Ci <LLD <LLD"'1 5.OOE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 3.45E+7 5.11E+7 5.OOE+O F. Volume of dilution water used during period liters 5.65E+11 7.56E+11 5.OOE+O 1i) IWO UJ 3LIam GeneraLor lowUown samples were discarded prior to use in the Aprl I monthiy composite TOr OTTSite analysis for alpha, Fe-55 and Sr-89/90. The pre release samples were <LLD for gamma and tritium. There was no dose impact to a member of the public from this event which is documented in AR 060500859.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Estimated Third Fourth Total Unit Quarter Quarter Error, A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 4.63E-3 8.03E-3 1.90E+1
2. Average diluted concentration during period 4Ci/ml 6.06E-12 1.35E-11
3. Percent of applicable limit  % MPC 1.31E-5 2.96E-5
4. Percent Effluent Concentration Limit  % ECL 1.11E-4 1.92E-4 B. Tritium
1. Total release Ci 1.43E+2 9.04E+1 1.90E+1
2. Average diluted concentration during period pCi/ml 1.87E-7 1.52E-7
3. Percent of applicable limit  % MPC 6.24E-3 5.08E-3
4. Percent Effluent Concentration Limit  % ECL 1.87E-2 1.52E-2 C. Dissolved and entrained gases
1. Total release Ci 4.92E-2 3.01E-1 1.90E+I
2. Average diluted concentration during period 4Ci/ml 6.44E-11 5.08E-10
3. Percent of applicable limit  % MPC 3.22E-5 2.54E-4
4. Percent Effluent Concentration Limit  % ECL 3.22E-5 2.54E-4 D. Gross alpha radioactivity
1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 5.38E+7 1.02+9 5.OOE+O F. Volume of dilution water used during period liters 7.64E+11 5.93E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci <LLD <LLD <LLD 3.14E-5 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 iro.n-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 3.14E-5
2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 j 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 (2006)

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

LIQUID EFFLUENTS BATCH MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation products antimony-124 Ci <LLD <LLD <LLD 5.13E-5 antimony-125 Ci 1.55E-3 4.45E-4 6.48E-4 1.38E-3 barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci 8.83E-5 1.87E-5 <LLD 7.61E-5 cesium-137 Ci 8.06E-4 2.09E-4 2.42E-5 1.79E-4 chromium-51 Ci 6.71E-4 7.95E-4 <LLD 4.90E-4 cobalt-57 Ci .<LLD <LLD <LLD <LLD cobalt-58 CCi 4.33E-3 6.22E-3 1.26E-3 3.01E-3 cobalt-60 Ci 9.45E-4 1.34E-3 2.13E-3 1.60E-3 iodine-131 Ci 1.37E-5 <LLD <LLD 7.94E-6 iron-55 Ci 2.33E-3 3.79E-3"11 <LLD <LLD iron-59 Ci 2.83E-5 7.37E-5 <LLD 8.97E-5 lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 1.76E-4 4.81E-4 2.45E-4 2.39E-4 molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 1.51E-4 9.15E-4 1.84E-4 2.87E-4 niobium-97 Ci 7.43E-6 2.06E-5 3.15E-5 3.04E-5 sil ver-110m Ci 3.98E-5 1.70E-4 9.87E-5 3.73E-4 strontium-89 Ci <LLD <LLDM <LLD .<LLD strontium-90 Ci <LLD <LLDM <LLD <LLD technetium-99m Ci <LLD <LLD <LLD  :<LLD tin-113 Ci <LLD 1.85E-5 <LLD <LLD tin-117m Ci 2.33E-5 <LLD <LLD 1.16E-5 zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 *Ci 7..42E-5 5. 3IE-4 1.42E-5 1.55E-4 zirconium-97 Ci <LLD <LLD <LLD 1.22E-5 Total for period Ci 1.12E-2 1.50E-2 4.63E-3 8.OOE-3
2. Dissolved and entrained gases krypton-85 Ci <LLD 2.68E-2 <LLD 8.16E-3 xenon-131m Ci <LLD 1.78E-3 1.50E-3 .5.42E-3 xenon-133 Ci 3.81E-3. 9.51E-3 4.75E-2 2.86E-1 xenon-133mCi <LLD <LLD 2.42E-4 1.70E-3 xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci 3.81E-3 3.81E-2 4.92E-2 3.01E-1 LLD Lower Limit of Detection; see Table 2C, Two U3 Steam Generator Blowdown samples were discarded prior to use in the April monthly composite for offsite analysis for alpha, Fe-55 and Sr-89/90. The pre release samples were <LLD for gamma and tritium.

There was no dose impact to a member of the public from this event which is documented in AR 060500859.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides LLD (4Ci/cc)

1. Fission and activation products barium-140 2.90E-7 ceri um-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 I.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 (2006)

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

LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides ILLD (4Ci/cc)

1. Fission and activation products antimony-124 2.40E-7 barium-140 2.40E-7 cerium-141 4.OOE-8 cerium-144 1.70E-7 cesium-134 7.50E-8 chromium-51 3.OOE-7 cobalt-57 2.20E-8 iodine-131 4.30E-8 iron-55 1.OOE-6 iron-59 1.50E-7 lanthanum-140 1.80E-7 molybdenum-99 2.70E-8 strontium-89 5.OOE-8 strontium-90 5.OOE-8 technetium-99m 2.70E-8 tin-113 5.30E-8 tin-117m 2.30E-8 zinc-65 1.70E-7 zirconium-97 1.70E-7
2. Dissolved and entrained gases krypton-85 2.90E-5 xenon-131m 3.OOE-6 xenon-133m 6.90E-7 xenon-135 8.90E-8
3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A.

1. Total body dose mrem 6.28E-4 9.65E-4 3.02E-4 2.71E-4
2. Percent Applicable Limit 2.09E-2 3.22E-2 1.01E-2 9.03E-3 B.
1. Limiting organ dose mrem 1.50E-3 2.93E-3 1.11E-3 2.31E-3
2. Percent Applicable Limit 1.50E-2 2.93E-2 1.11E-2 2.31E-2
3. Limiting organ for period GI-LLI GI-LLI GI-LLI GI-LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 132 releases
2. Total time period for batch releases: 20275 minutes
3. Maximum time period for a batch release: 522 minutes
4. Average time period for a batch release: 154 minutes
5. Minimum time period for a batch release: I minute
6. Average saltwater flow during batch releases: 737197 gpm ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 (M)
a. Spent resins, filter sludges
  • m3 4.28E+O Ci 1.94E+2 3.OOE+1
b. Dry active waste (DAW), m3 4.31E+1 compactable and non-compactable
  • Ci 2.01E+2 3.OOE+1
c. Irradiated components m3 N/A Ci N/A N/A
d. Other: Filters m3 N/A Ci N/A N/A Note: Total curie content estimated.

Material packaged in containers that meet the General Design requirements and/or USA Type IP-1 of various sizes.

N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

2. Estimate of major nuclide composition (by type of waste)
a. americium-241 _ 5.OOE-04 antimony-124  % 1.05E-02 antimony-125  % I.IOE+OO carbon-14 8.OOE-O1 cerium-144 1.39E-02 cesium-134 __1.78E+00 cesium-137 _1.IIE+O1 cobalt-57 4.62E-02 cobalt-58 4.56E-02 cobalt-60 5.98E+00 curium-243/44  % 5.OOE-04 iodine-129  % 2.60E-03 iron-55  % 1.46E+01 manganese-54  % 2.96E-01 nickel-63  % 6.41E+01 niobium-94  % 2.OOE-03 niobium-95  % 2.90E-03 plutonium-238  % 4.00E-04 plutonium-239/240  % 1.OOE-04 plutonium-241  % 3.60E-03 strontium-89  % 4.40E-03 strontium-90 _ 5.77E-02 technetium-99  % 7.OOE-03 tritium  % 3.40E-02 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

2. Estimate of major nuclide composition (by type of waste)
b. americium-241 _ 3.OOE-04 antimony-124  % 6.OOE-04 antimony-125  % 3.75E-01 carbon-14  % 3.82E-01 cerium-144  % 8.70E-03 cesium-134 _ 1.96E+00 cesium-137  % 1.42E+01 chromium-51  % 1.73E-02 cobalt-57  % 2.55E-02 cobalt-58  % 6.96E-02 cobalt-60  % 7.10E+00 curium-243/44  % 3.OOE-04 lodine-129  % 4.59E-02 S.ron-55 _ 1.33E+01 iron-59  % 4.30E-03 manganese-54 _ 3.90E-01 nickel-59 _ 3.OOE-04 nickel-63  % 6.20E+01 niobium-95  % 7.60E-03 plutonium-238  % 3.OOE-04 plutonium-239/40  % 1.OOE-04 plutonium-241  % 7.70E-03 strontium-89 I.OOE-04 1

strontium-90  % 5.34E-02 technetium-99  % 9.70E-03 tritium _ 2.17E-02 zirconium-95  % 3.90E-03

c. not applicable  %, N/A
d. not applicable  % N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 5* TAG Transport EnergySolutions UT Truck/Flatbed Trailer 2
  • R&R Transport Barnwell, SC and Truck/Flatbed Trailer EnergySolutions, UT **

2 TAG Transport Truck/Flatbed Trailer EnergySolutions, UT

  • SONGS maintains contracts with vendors (EnergySolutions, formerly known as Duratek and Studsvik) that provide volume reduction services. The processed volume was shipped from EnergySolutions (Duratek) and Studsvik facilities to EnergySolutions in Clive, UT and Barnwell using 20 shipments. Those 20 shipments included waste from other generators. SCE's waste volume was a fraction of the total waste volume of these shipments.

After processing, class B/C material was buried at Barnwell, S.C. Class A material was disposed of at EnergySolutions, UT B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 SECTION F. APPLICABLE LIMITS Gaseous Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, C, and D of Table 1A, were calculated using the following equation:

?- Applicable Limit (Rel Rate) (X/0) (100)

. MPCeff where: Rel Rate total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, gCi/sec.

4.80E-6 sec/Mr3; the annual average atmospheric dispersion X/Q defined in the 0DCM.

1 0 MPCeff 1=1 MPC where: F, fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C,, by the sum of all the isotopic activity, C .

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

  • %ECL (Rel Rate) (X/0) (100)

ECLeff where: Rel Rate total curies released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, B.2, C.2 and D.2 of Table 1A, ktCi/sec.

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

1 zi o ECLeff i=1 ECL where: Fi 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.

n = total number of radionuclides identified ECL1 - Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 Liouid Effluents - ADDlicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations:

Applicable Limit (Dil Conc) (100)

MPCeff where: Dil Conc total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, yCi/ml.

1 MPCeff i MPC i where: Fj 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 MPCG Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table II, Column 2.

0 %ECL (Dil Conc) (100)

ECLeff where: Dil Conc total curies released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, 4tCi/ml.

I 0 ECLff i71 ECL i where: Fj fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Cj, by the sum of all the isotopic activity, C T" n total number of radionuclides identified ECL, Effluent Concentration Limit (ECL) of the it' radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 =

-52 21 + 2 + G3 + ... G2 where: i = Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

Six different categories are presented:

(1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, lodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; these data are also presented in Table 2D. Categories 3, 4, and 5 were calculated utilizing 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 methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

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

For members of the public who traverse the site boundary via highway 1-5, the residency time shall be considered negligible and hence the dose "0".

Table 2 in Section H presents the percent of Applicable Limits for each dose presented in Table 1.

ODCM Figures 1-2 & 2-2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 6.28E-4 9.65E-4 3.02E-4 2.71E-4 2.17E-3

6) 7) 8) 9) 10)

Organ 1.50E-3 2.93E-3 1.11E-3 2.31E-3 7.84E-3 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15)

Tritium, lodines, and Particulates 2.56E-3 8.68E-4 2.59E-3 6.61E-3 1.26E-2 NOBLE GASES ** 16) 17) 18) 19) 20)

Gamma 2.15E -2 7.12E-3 9.26E-3 3.57E-2 7.35E-2

21) 2.2) 23) 24) 25)

Beta 3.60E-2 1.38E-2 1.72E-2 5.20E-2 1.19E-1

26) 27) 28) 29) 30)

DIRECT RADIATION 1.95E- " 1.78E-1 1.44E-1 8.78E-2 5,.74E-1

  • .The numbered footnotes .below brieflwy explain hoý f each maximum dose was calculated, including the organiand the predominalnt pathway(s),-.
    • .Noble gas doses due to ..airbo~rne effluent are in units of mrad, reflecting the air dose.,
1. "This val'ue Was calculated using the methodology of the 00CM.
2. "This va-l.e was calculated using the methodology of the ODCM.
3. This value Was calculated using the methodology of the 0DCM.
4. This value was calculated using the methodology of the ODCM.
5. This value was calculated using the methodology of the ODCM.
6. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

7. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
8. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
9. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
10. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
11. The maximum organ dose was to a teen's thyroid and was located in the N sector. This was calculated 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 sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
13. The maximum organ dose was to a teen's thyroid and was located in the N sector. This was 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 sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
15. The maximum organ dose was to a teen's thyroid and was located in the N sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
16. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
17. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
18. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.i09.
19. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide .1.109.
20. The maximum air dose for gamma radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
21. The maximum air dose for beta radiation was located in the 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 located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
23. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.
24. The maximum air dose for beta radiation was located in the NNE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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

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 W sector.
28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector.
29. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the WSW sector.
30. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the W sector.

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 2.09E-2 3.22E-2 1.O1E-2 9.03E-3 3.61E-2 Organ 1.50E-2 2.93E-2 1.11E-2 2.31E-2 3.92E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 1.71E-2 5.79E-3 1.73E-2 4.40E-2 4.21E-2 NOBLE GASES Gamma 2.15E-1 7.12E-2 9.26E-2 3.57E-1 3.68E-1 Beta 1.80E-1 6.88E-2 .8.58E-2 2.60E-1 2.97E-1 NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 24, 2006, Revision 41 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated updates related to the 2004-2005 Land Use Census (LUC), and replaced environmental sampling maps; (no information was changed).

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.

None of the changes impacted 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 IOCFR50 will be maintained.

Throughout the document, change bars were marked in one of four ways as follows:

A Addition D Deletion F Editorial/Format change R Revision Page # Change Reason 2-31 Modified Controlling Location Factors per LUC R 2-33 Revised Ri values per LUC R 2-36 Revised Ri values and changed name of pathway per LUC R 2-39 Revised Ri values per LUC R 2-41 Revised Ri values and changed name of pathway per LUC R 2-42 Revised Ri values per LUC R 2-45 Revised Ri values per LUC R 2-53 Modified Sector G page numbers due to added page F 2-53a Added page of Ri values per LUC A 5-23 Replaced Figure 5-1 with a copy with better depiction of the shoreline. R 5-24 Replaced Figure 5-2 with a copy with better depiction of the shoreline. R 5-25 Replaced Figure 5-3 with a copy with better depiction of the shoreline. R 5-26 Replaced Figure 5-4 with a copy with better depiction of the shoreline. R 5-27 Replaced Figure 5-5 with a copy with better depiction of the shoreline. R ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 On October 5, 2006, Revision 42 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated the addition of the North Industrial Area Yard Drain Sump (YDS) in support of the Unit 1 demolition and in accordance with the approved licensing change PCN 560 and ECPs 050401085 and 040401753. This revision implemented the NRC licensing change.

An Effluent/ODCM Evaluation (EOE) was performed for this change. No 50.59 or EOE reviews were required or performed for editorial changes.

None of the changes impacted 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 IOCFR50 will be maintained.

Throughout the document, change bars were marked in one of four ways as follows:

A Addition D Deletion F Editorial/Format change R Revision New Change Reason Page #

i Modified page numbers to account for added pages R v Modified page numbers to account for added pages R 1-3 Added page for new section "C" in Table 1-1, listing YDS sample & analysis A requirements 1-4 thru 1-27 All pages renumbered to accommodate the two new added pages for the YDS F 1-5 Added note "g" to Table 1-1 A 1-10 Added YDS administrative factor and revised paragraph to no longer limit the A/R requirement to only Unit 2/3 1-15 Added YDS to step I A 1-16 Added YDS to step 2 A 1-22 Added YDS section to section 1.4.2.4 A 4-2 Added YDS radiation monitor and process flow device to Table 4-1 A 4-3 Added Plant Computer System to Table 4-1 A/F 4-5 Added Action 44 to Table 4-1 and added the word "the" to Action 33. A/F 4-6 Added YDS radiation monitor and process flow device to Table 4-2 A 4-7 Added Plant Computer System to Table 4-2 and moved line item 3 from page 4-6. A/F 6-4 Added RT-2101 to and removed SYFRT 7904 and SYFRT 7905 from step 6.1.15 R ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS On October 5, 2006, the North Industrial Area (formerly the Unit 1) Yard Drain Sump (YDS) was put into service. The North Industrial Area YDS is located in a slightly different location and with a larger volume capacity and discharge rate than the old Unit I YDS. The NIA YDS is released through either the Unit 2 or Unit 3 outfall. The NIA YDS will not use the Unit 1 outfall or any other portion of the Unit 1 circulating water system. A radiation monitor is installed on the new system that will alarm and automatically terminate the discharge if the setpoint is exceeded.

Corresponding with this change was the removal of the Unit I YDS from service and from the Unit 1 ODCM.

This design change incorporates the recently approved licensing amendment PCN 560.

The approved Technical Specification amendment allows San Onofre to release the yard drain sump via the Unit 2 or Unit 3 outfall. The sampling and maintenance requirements were transferred from the Unit I ODCM to the Unit 2/3 0DCM with only two modifications. The first, a minor surveillance change concerns the testing of the automatic isolation feature. As explained below, the increased sump capacity makes a single test for auto isolation of the sump pumps by the radiation monitor impractical. Rather, the different circuits are tested independently with overlap and shown to accomplish the requirement. The second item, the YDS process flow integrator, was added to the Unit 2/3 0DCM Chapter 4 Tables 4-1 and 4-2 to be consistent with NUREG-0472, Rev. 3, Draft 7 and NUREG CR-1301.

The original YDS was designed to collect drainage from the back yard area where tanks and systems containing radioactive (non-primary) liquids were located. The replacement sump and its associated radiation monitoring system and pumps will continue to collect and discharge mostly rainwater, and, occasionally, dewatering from other demolition activities.

A larger yard drain sump with a capacity of approximately 51,300 gallons was installed per ECPs 050401085 and 040401753, and is routed to Unit 2 or Unit 3 outfall. The NIA YDS design includes new pumps (typical flows approximately 4000 gpm with pump P-060 or 2300 gpm with pump P-1059), a radmonitor identical to the Unit I YDS R-2101, and new discharge piping and valves. The operation of the NIA YDS is controlled by Unit 2 Operations. The two new pumps are rated at different flow rates and are prevented from operating simultaneously by controlling circuitry. The radiation monitor instrument reading is shown on the Unit 2 Plant Computer System (PCS), a site-wide network. The auto termination function of the radiation monitor is not affected by the PCS and is controlled by the monitor alone. The control room alarm feature is through the PCS with the signal originating at the monitor. Should the PCS become inoperable, the control room alarm will be lost and appropriate compensatory actions will be performed. Additional system status shown on PCS includes: sump level, pump on/off status, flow rates, radiation monitor reading, and total volume pumped. The existing Unit 1 ODCM sampling requirements remain unchanged in the Unit 2/3 0DCM. This change involves no reduction in regulatory control as sampling requirements in effect for the Unit 1 YDS are in the Unit 2/3 0DCM and now pertain to the NIA YDS.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 In addition to the NIA YDS addition, there is also the potential for Unit 1 wastewater to be transferred to the Unit 2/3 radwaste system for processing and release. This would generally occur only if the water could not be treated to below 2E-5 uCi/ml using a temporary processing system. If the wastewater can be processed to below 2E-5 uCi/ml, the water could then be released to the Unit 2 or 3 outfall via the YDS. As another possibility, the wastewater can be shipped to an offsite vendor for treatment and disposal at an appropriately licensed facility (see AR 060102024).

This new design does not introduce a new source of radioactivity for the site. The ongoing demolition of Unit I systems, structures and components continues to reduce and remove possible source terms. The new YDS will be controlled under the Effluent Program and be discharged into the Unit 2 or 3 outfall each of which has a significantly higher dilution flow rate. Given the higher release flow rates from this new system, any trace amounts of activity released via the new NIA YDS will be more diluted than the previous Unit 1 releases resulting in a lower dose to the public.

NUREG-0133, NUREG-0472, Rev.3 Draft 7, and NUREG-1301 provide licensees with acceptable means to implement the regulatory requirements in 10 CFR 20 and 10 CFR 50 for control of radioactive effluents. All Part 50 licensees regardless of operating status are subject to those requirements unless the NRC has granted them an explicit waiver.

As discussed in the description above, the North Industrial Area YDS system will be released through either the Unit 2 or 3 outfall. The primary purpose of the YDS is now to collect rainwater from the North Industrial Area (formerly Unit 1) and release it through the Unit 2 or Unit 3 outfall.

This change reflects the physical re-routing of the YDS system.. Regulatory approval for this change has been received in PCN 560 in the letter from N. Kalyanam to R.

Rosenblum "San Onofre Nuclear Generating Station, Units 2 and 3 - Issuance of Amendments Re: Revision of Facility Operating License Condition 2.B(6) Special Nuclear Materials (TAC Nos. MC7777 and MC7778), dated February 28, 2006. SCE continues to meet the regulatory requirements, including those described in NUREG-0133, NUREG-0472, Rev.3 Draft 7, and NUREG-1301, through the Unit 2/3 0DCM and the effluent control program. All curies and dose released from the YDS are now included in the Unit 2/3 totals since the release is via Unit 2 or 3 outfall. The IOCFR50 App I dose limits for Unit 2/3 have not been changed. The admin factor for the YDS has been taken from other Unit 2/3 systems so the same control of potential simultaneous releases is in effect.

This change does not adversely impact the interface between any contaminated and non-contaminated systems. The North Industrial Area sewage treatment plant overflow line is routed to the new YDS just as it was in the old design. The overflow line is a gravity drain from the sewage plant to the oily waste section of the YDS and has two check valves to prevent back flow from the YDS into the sewage plant. A new check valve was installed at the YDS; this valve will be checked periodically per AR 061201195 to ensure functionality. Further, the sewage plant is at a higher elevation than is the YDS connection to this overflow that will reduce the challenge to the check valves.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 RG 1.21 reiterates that licensees must comply with the requirements in 10 CFR 20.106 and 10 CFR 50 Appendix A, General Design Criteria 60 and 64. The YDS system is being routed to Unit 2 or 3 as part of the decommissioning effort. The Unit 1 outfall is to be abandoned and therefore all sources of water into the outfall must be isolated.

SCE continues to meet the regulatory requirements through the Unit 1 and Unit 2/3 ODCMs and the effluent control program. The new NIA YDS has the same mode of release termination as did the Unit 1 YDS. Upon alarming, the radiation monitor terminates the release by securing the pumps. This methodology is considered equivalent to closure of the discharge valve. The discharge piping is an up-hill non-siphon arrangement and the securing of the pumps provides automatic termination of the release should the radiation monitor alarm.

PCN 560 was approved by the NRC, on February 28, 2006, to allow for the transfer of the North Industrial Area YDS to either Unit 2 or Unit 3 for release. The NRC also approved the transfer of Unit I generated wastewater to the Unit 2/3 radwaste system for processing and release as necessary. The requirements for continuous monitoring and periodic and compensatory sampling and analysis of the yard drain sump are maintained as was previously described in the Unit 1 ODCM. Effectively, with these changes to the ODCMs, there is now a site-wide administrative factor for all liquid radioactive release points to ensure that the limits of IOCFR20 App B are not exceeded, and the existing Unit 2/3 10CFR5O App I dose limits will accommodate Ul releases. There will be no reduction in the margin of safety.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 SECTION K. MISCELLANEOUS Broken Pressure GauQe at Unit 2 FFCPD On 8/29/06, during the recirculation of the Unit 2 FFCPD HUT for release, an instrument line to a pressure gauge separated and an estimated volume of 78 gallons spilled in the area which was then released via the Unit 2/3 outfall as an unplanned, unmonitored release. The water flowed into a nearby yard area drain. Analysis of the water indicated 3.6E-6 uCi/ml of tritium. No other isotopes were identified. Any dose received by a member of the public due to this event was minimal and bounded by the subsequent release of the HUT. This event is documented in AR 060801279.

Incorrect Sample Preparation for the Off-Site Analysis In May 2006, it was discovered that the off-site liquid and gaseous composite samples were being prepared using an equal aliquot rather than relative proportions. Upon notification, the vendor immediately modified their procedures to use proportional sampling to prepare the composites for analysis. The affected time period was 2000 through 2005. Evaluation of all results for those years showed that the reported totals were conservative or within the error of analysis while still being an insignificant percent of any dose limit. There were no dose consequences to a member of the public as a result of this event which is documented in AR 060901296.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2006 - December 31, 2006 S.O.N.G.S. 2 Monitor Inoperability Period Inoperability Cause Explanation 2RT-7870 04/17/00 - present Inoperable process Design deficiency causes process flow Condenser Air flow measuring instrument to be inoperable while the Ejector Process device whenever vacuum pump is running, as high flow Flow Monitor vacuum pump is values are not sensed. Flow monitor running. works properly during normal operations. The monitor is isokinetic during the vacuum pump operation due to the substitute flow value that is automatically inserted whenever the vacuum pump is running. The issue is summarized and evaluated for corrective work in AR 060900207-4.

2RT-7817 01/20/06 - 05/04/06 Electrical outage Following an electrical outage on the BPS/FFCPD and inoperable flow common power supply, the root valves Discharge Monitor transmitter to the flow meter were blocked due to the accumulation of debris. During the investigation, the age and condition of the system components warranted replacing the sensing lines prior to returning the flow meter to service. This event is documented in AR 060300157 and 060201216.

2RT-7821 01/13/06 - 04/02/06 Monitor was removed System required investigation and Turbine Plant Sump from service to piping replacement to resolve pipe Monitor support engineering leakage. During this time period Unit investigation of a 2 TPS was routed to Unit 3 TPS. This system pipe leak event is documented in WAR 2-R4ML338.

06/11/06 - 08/30/06 Monitor was re- Work on unrelated downstream system moved from service forced TPS outage. During this time to support period Unit 2 TPS was routed to Unit replacing Oily 3 TPS. This event is documented in Waste Sump pumps, WAR 2-0600959.

2MP097 and 2MP098.

2RT-7828 01/24/06 - 03/02/06 Monitor unavailable An extensive electrical system outage Containment Purge due to electrical during Unit 2 refueling outage caused Monitor outage unavailability of radmonitor.

2RT-7865 used for containment purges.

This event is documented EDMR E2-06-0052.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 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 as high flow values are not sensed.

running. Flow monitor works properly during normal operations. The monitor is isokinetic during the vacuum pump operation due to the substitute flow value that is automatically inserted whenever the vacuum pump is running. The issue is summarized and evaluated for corrective work in AR 060900207-4.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

S.O.N.G.S. 2 and 3 SECTION L. S.O.N.G.S. 2 and 3 CONCLUSIONS Gaseous releases totaled 2.08E+2 curies of which noble gases were 1.67E+2 curies, iodines were 4.15E-3 curies, particulates were 3.48E-3 curies, and tritium was 4.06E+1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: 7.35E-2 mrad at the site boundary, (b) beta air dose: 1.19E-1 mrad at the site boundary, (c) organ dose: 1.26E-2 mrem at the nearest receptor.

Liquid releases totaled 8.49E+2 curies of which particulates and iodines were 3.89E-2 curies, tritium was 8.49E+2 curies, and noble gases were 3.92E-1 curies.

The radiation doses from liquid releases were: (a) total body: 2.17E-3 mrem, (b) limiting organ: 7.84E-3 mrem.

The radioactive releases and resulting doses generated from Unijts 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.

COMMON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 Hi N/A sludges, evaporator bottoms Ci N/A N/A
b. Dry active waste (DAW), m3 N/A compactable and non-compactable Ci N/A N/A m3 N/A
c. Irradiated components Ci N/A N/A m3 N/A
d. Other (filters)

Ci N/A N/A N/A No shipment made.

2. Estimate of major nuclide composition (by type of waste)
a. not applicable  % N/A
b. not applicable  % N/A
c. not applicable  % N/A

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 None No shipments were made N/A B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A D. CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 None.

REFERENCES:

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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 6.01E-1
b. Percent ODCM Specification Limit  % 2.40E+O
2. Limiting Organ
a. Organ Dose (GI-LLI) mrem 2.05E-2
b. Percent ODCM Specification Limit 0 8.22E-2
3. Thyroid
a. Thyroid Dose mrem 1.41E-2
b. Percent ODCM Specification Limit  % 1.88E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

COMMON Onsite Groundwater Samples January 1,'2006 - December 31, 2006 This section provides results of on-site samples of groundwater in accordance with Action 2.1 of the voluntary Nuclear Energy Institute (NEI) Groundwater Protection Initiative. The sample locations and the frequency of sampling are likely to change as the Groundwater Protection Initiative is implemented. For those few sample data that are not <LLD, the levels are near the analytical sensitivity for the laboratory techniques. They do not indicate that there has been an inadvertent release of radioactive material beyond the site boundaries.

Sample Date Location Tritium Activity, uCi/ml Gamma Activity, (uCi/ml) 08/07/2006 CTMT DOME 3.30E-4 7.96E-8 08/09/2006 CTMT DOME 4.98E-5 <LLD 08/14/2006 CTMT DOME 7.51E-5 <LLD 08/18/2006 CTMT DOME 6.01E-5 <LLD 08/23/2006 CTMT DOME 2.92E-5 <LLD 10/11/2006 U1 DW 5 2.58E-5 <LLD UI DW4 <LLD <LLD U1 DW 8 3.77E-6 <LLD U1 DW I <LLD <LLD U1 DW 2 <LLD <LLD U1 DW3 <LLD <LLD 10/13/2006 Composite 2.96E-6 <LLD 10/14/2006 Composite 3.60E-6 <LLD U1 DW 5 4.57E-6 <LLD UlDW 6 5.70E-6 <LLD U1 DW4 3.50E-6 <LLD Composite 6.77E-6 <LLD 10/15/2006 Composite <LLD <LLD U1 DW 4 3.54E-6 <LLD U1 DW 5 5.90E-6 <LLD U1 DW 6 7.86E-6 <LLD U1 DW 8 5.82E-6 <LLD Composite 7.49E-6 <LLD Composite 3.98E-6 <LLD 10/16/2006 Composite 7.01E-6 <LLD Composite 4.79E-6 <LLD U1 DW 4 <LLD <LLD U1 DW 8 <LLD <LLD U1 DW 6 4.24E-6 <LLD U1 DW 5 <LLD <LLD UI DW 8 6.02E-6 <LLD Composite <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

COMMON Onsite Groundwater Samples

.lin"iAr\i 1 9nnk - naromhar 11 9NN()1 Sample Date Location Tritium Activity, uCi/ml Gamma Activity, (uCi/ml) 10/17/2006 Composite <LLD <LLD Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD Composite 2.98E-6 <LLD Composite <LLD <LLD 10/18/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 3.42E-6 <LLD NIA South DW <LLD <LLD Composite <LLD <LLD Composite <LLD <LLD 10/19/2006 Composite <LLD <LLD U1DW 4 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 3.63E-6 <LLD U1DW 5 3.23E-6 <LLD Composite <LLD 1.05E-7 Composite <LLD 7.38E-8 10/20/2006 Composite <LLD 5.88E-8 U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD Composite <LLD 9.97E-8 Composite <LLD 7.38E-8 10/21/2006 Composite <LLD <LLD U1DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD Composite <LLD 5.07E-8 Composite <LLD <LLD 10/22/2006 Composite <LLD <LLD Composite <LLD <LLD Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

COMMON Onsite Groundwater Samples January 1, 2006 - December 31, 2006 Sample Date Location Tritium Activity, uCi/ml Gamma Activity, (uCi/ml) 10/23/2006 Composite <LLD <LLD U1 DW 5 <LLD <LLD UI DW 6 <LLD <LLD U1 DW 8 5.40E-6 <LLD U1 DW 4 <LLD <LLD Composite <LLD <LLD Composite <LLD <LLD 10/24/2006 U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD Composite <LLD <LLD 10/25/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD Composite <LLD <LLD 10/26/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW5 <LLD <LLD U1 DW 6 <LLD <LLD 10/27/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW5 <LLD <LLD U1 DW 6 <LLD <LLD 10/28/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW8 <LLD <LLD 10/29/2006 U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD Composite <LLD <LLD 10/30/2006 Composite <LLD <LLD U1 DW 1 <LLD <LLD U1 DW 2 <LLD <LLD U1 DW 3 <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 7 <LLD <LLD U1 DW 8 <LLD <LLD U1 DW 8 <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

COMMON Onsite Groundwater Samples January 1, 2006 - December 31, 2006 Sample Date Location Tritium Activity, uCi/ml Gamma Activity, (uCi/ml) 10/31/2006 Composite <LLD <LLD UI DW 4 <LLD <LLD UI DW 5 <LLD <LLD UI DW 6 <LLD <LLD U1 DW 8 <LLD <LLD 11/01/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD 11/02/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD 11/04/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD 11/05/06 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD 11/06/2006 Composite <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 8 <LLD <LLD 11/13/2006 U1 DW 1 <LLD <LLD U1 DW 2 <LLD <LLD U1 DW 3 <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD UI DW 7 <LLD <LLD U1 DW 8 <LLD <LLD 11/20/2006 U1 DW 1 <LLD <LLD U1 DW 2 <LLD <LLD U1 DW 3 <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 7 <LLD <LLD U1 DW 8 <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

COMMON Sample Date Location Tritium Activity, uCi/ml Gamma Activity, (uCi/ml) 11/27/2006 U1 DW 1 <LLD <LLD U1 DW 2 <LLD <LLD UI DW 3 <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 7 <LLD <LLD U1 DW 8 <LLD <LLD 12/04/2006 U1 DW 1 <LLD <LLD U1 DW 2 <LLD <LLD U1 DW 3 <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD UI DW 7 <LLD <LLD U1 DW 8 <LLD <LLD 12/11/2006 U1 DW 1 <LLD <LLD U1 DW 2 <LLD <LLD U1 DW 3 <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD UI DW 7 <LLD <LLD UI DW8 <LLD <LLD 12/18/2006 U1 DW 1 <LLD <LLD U1 DW 2 <LLD <LLD U1 DW 3 <LLD <LLD U1 DW 4 <LLD <LLD U1 DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1DW 7 <LLD <LLD U1 DW 8 <LLD <LLD 12/19/2006 UI DW 5 <LLD <LLD U1 DW 6 <LLD <LLD 12/26/2006 U1 DW I <LLD <LLD U1 DW 2 <LLD <LLD U1 DW 3 <LLD <LLD UI DW 4 <LLD <LLD UI DW 5 <LLD <LLD U1 DW 6 <LLD <LLD U1 DW 7 <LLD <LLD U1 DW 8 <LLD <LLD DW Dewatering Wells to support U1 decommissioning.

Composite Weekly composite of the dewatering wells.

CTMT DOME In the containment sphere, holes were drilled and tapped in order to remove the groundwater beneath the UI containment sphere.

LLD H-3: 1.0 E-5 uCi/ml, Cs-137: 5.0 E-7 uCi/ml ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 2.09E+2 curies of which noble gases were 1.67E+2 curies, iodines were 4.15E-3 curies, particulates were 3.48E-3 curies, and tritium was 4.15E+1 curies.

Liquid releases from S.O.N.G.S. 1, 2 and 3 totaled 8.49E+2 curies of which particulates and iodines were 3.89E-2 curies, tritium was 8.49E+2 curies, and noble gases were 3.92E-1 curies.

Radioactive releases and resulting doses generated from S.O.N.G.S. 1, 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.

S.O.N.G.S. 1, 2 and 3 made 348 radwaste shipments to EnergySolutions, UT and I shipment to Barnwell, SC. Total volume was 9.64E+3 cubic meters containing 4.51E+2 curies of radioactivity.

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

Meteorological dispersion was good 39% of the time, fair 33% of the time and poor 28% of the time.

Groundwater initiative releases contained 1.22E-1 curies of tritium and 1.51E-6 curies of particulates. Total volume was 2.62E+8 gallons which consisted of dewatering at Unit 1. All these releases were through an ODCM credited release point and the dose impact was insignificant. All these groundwater initiative totals are reported elsewhere in this document.

The net result from the analysis of these effluent releases indicates that the operation of S.O.N.G.S. 1, 2 and 3 has met all the requirements of the applicable regulations and therefore has not resulted in any detrimental effects to a member of the public.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

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:
  • 5 mrad for gamma radiation and 10 mrad for beta radiation.
2. During any calendar year: 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: 7.5 mrem to any organ.
2. During any calendar year: 15 mrem to any organ.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

COMMON APPENDIX A (Continued)

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

B. Table 2D lists doses due to liquid releases. The dose commitment to a Member of the Public from radioactive materials in liquid effluents released from S.O.N.G.S. (per reactor) to unrestricted areas shall be limited to the following values:

1. During any calendar quarter:
  • 1.5 mrem to the total body and 5 mrem to any organ.
2. During any calendar year:
  • 3 mrem to the total body and 10 mrem to any organ.

METEOROLOGY METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2006 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, 2006. 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 (2006)

METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 06010100-06033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ * -1.9 'C/100 METERS)

WIND .22 .51 .76 1.1 1. 6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 1 0 0 0 0 0 1 NNE 0 0 0 1 0 0 0 1 0 0 0 0 2 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 1 0 0 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 1 0 0 2 2 0 0 0 0 5 SSE 0 0 0 0 1 9 9 4 2 0 0 0 25 S 0 0 0 3 7 16 13 6 1 0 0 0 46 SSW 0 0 0 1 9 18 11 0 0 0 0 0 39 SW 0 1 0 3 i4 28 19 2 0 0 0 0 67 WSW 0 0 0 5 16 29 24 2 4 0 0 0 80 W 0 1 1 0 3 47 72 2 0 0 0 0 126 WNW 0 0 0 1 5 20 68 12 0 0 0 0 106 NW 0 0 0 1 2 4 6 1 0 0 0 14 0

NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 2 1 16 58 171 225 32 7 0 0 0 512 NUMBER OF VALID HOURS 512 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 512 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ * -1.7 'C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 1 2 0 0 0 0 3 NE 0 0 0 0 0 0 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 1 0 0 0 0 0 1 E 0 1 0 0 0 1 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 1 0 0 0 0 1 SSE 0 0 0 0 0 5 6 4 0 0 0 0 15 S 0 0 0 2 0 2 2 1 2 0 0 0 9 SSW 0 0 0 0 1 3 2 1 0 0 0 0 7 SW 0 0 0 0 1 4 2 1 0 0 0 0 8 WSW 0 0 0 0 1 2 0 1 1 0 0 0 5 W 0 0 0 0 3 3 1 2 0 0 0 0 9 WNW 0 0 0 1 0 3 1 0 0 0 0 0 5 NW 0 0 0 0 1 2 4 2 0 0 0 0 9 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 1 0 4 7 25 21 15 3 0 0 0 76 NUMBER OF VALID HOURS 76 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 76 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 06010100-06033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1. 7 < DT/DZ -< -1..5 -C/lO0 METERS)

WIND .22 .51 .76 1.1 1.6 22.1 3.1 5..1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3 .0 5.0 7..0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 2 0 0 0 0 0 0 2 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 1 0 0 0 0 0 0 0 E 0 0 0 0 0 1 0 0 0 0 0 0 ESE 0 0 0 0 0 0 1 1 0 0 0 0 2 SE 0 0 0 0 0 1 2 0 0 0 0 0 3 SSE 0 1 3 2 0 0 11 0 0 0 3 2 0 S 0 0 0 2 0 3 1 1 0 0 0 0 7 SSW 0 0 0 2 2 3 0 0 0 0 0 7 0

SW 0 0 0 1 2 1 5 0 0 0 0 0 9 WSW 0 0 0 1 6 3 0 0 0 0 0 0 10 W 0 0 0 1 2 2 0 0 1 0 0 0 6 W.NW 0 0 0 0 0 3 1 1 0 0 0 0 5 NW 0 0 0 0 0 3 5 1 0 0 0 0 9 NNW 0 0 1 0 2 0 0 0 0 0 0 0 3 TOTALS 0 0 1 5 18 23 19 7 3 0 0 0 76 NUMBER OF VALID HOURS 76 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 76 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 'C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 1 3 4 6 3 0 0 0 0 0 17 NNE 0 0 1 2 6 15 6 1 0 0 0 0 31 NE 0 0 0 2 1 3 5 2 0 0 0 0 13 ENE 0 0 0 1 0 0 0 0 0 0 0 0 1 E 0 0 0 2 0 2 1 0 0 0 0 0 5 ESE 0 0 0 1 3 3 2 0 0 0 0 0 9 SE 0 0 0 0 1 12 24 12 13 0 0 0 62 SSE 0 0 0 2 0 13 18 5 4 1 2 0 45 S 0 0 0 0 6 3 7 10 3 0 1 0 30 SSW 0 0 0 4 2 2 5 2 0 0 1 0 16 SW 0 0 0 5 4 3 4 4 2 1 0 0 23 WSW 0 0 1 2 5 2 5 3 4 0 0 0 22 W 0 0 1 7 2 5 5 14 11 0 0 0 45 WNW 0 0 0 2 5 8 14 3 2 0 0 0 34 NW 0 0 1 1 4 9 8 5 1 0 0 0 29 NNW 0 0 0 4 4 12 1 0 0 0 0 0 21 TOTALS 0 0 5 38 47 98 108 61 40 2 4 0 403 NUMBER OF VALID HOURS 403 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 403 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 06010100-06033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DTr/DZ 1.5 °C/l00 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 3.0 2.0 5.0 7.0 10. 0 13.0 18.0 N 10 10.

7° 0 0 0 13 5 0 0 0 0 0 29 NNE 0 1 0 10 9 28 27 0 0 0 0 76 NE 0 0 0 2 5 2 3 2 1 0 0 0 15 2 0 ENE 0 0 0 2 4 2 0 0 0 0 0 10 E 0 0 1 5 2 4 2 0 0 0 0 0 14 ESE 0 0 0 0 2 2 3 0 0 0 0 0 7 SE 0 0 1 0 1 3 2 0 1 0 0 0

.9 SSE 0 0 0 1 3 3 5 0 1 0 0 0 13 S 0 0 0 1 1 0 1 2 0 0 0 0 5 SSW 0 0 0 0 2 0 1 0 0 0 0 0 3 SW 0 0 0 2 1 2 0 0 0 0 0 0 5 WSW 0 1 1 2 1 1 0 1 1 0 0 0 8 W 0 1 0 1 1 2 0 0 0 0 3 0 8 WNW 0 1 0 3 6 3 4 0 2 0 0 0 19 NW 0 0 1 2 2 3 4 0 0 0 0 0 12 NNW 0 0 0 3 2 6 5 0 0 0 0 0 16 TOTALS 0 4 4 35 55 72 66 7 6 0 0 0 249 NUMBER OF VALID HOURS 249 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 249 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ

  • 4.0 'C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 4 11 2 0 0 0 0 0 17 NNE 0 1 1 7 43 56 25 3 0 0 0 0 136 NE 0 0 0 6 7 11 7 1 1 0 0 0 33 ENE 0 0 2 3 4 2 0 0 0 0 0 0 11 E 0 0 1 5 3 1 0 0 0 0 0 0 10 ESE 0 0 0 0 2 0 0 0 0 0 0 0 2 SE 0 1 1 2 0 1 0 0 0 0 0 0 5 SSE 0 0 0 3 2 1 0 0 0 0 0 0 6 S 0 0 1 2 1 1 0 0 0 0 0 0 5 SSW 0 0 1 2 1 0 0 0 0 0 0 0 4 SW 0 0 1 2 2 0 1 0 0 0 0 0 6 WSW 0 0 0 2 0 0 1 0 0 0 0 0 3 W 0 0 0 2 4 0 0 0 0 0 0 0 6 WNW 0 0 1 0 8 7 0 0 0 0 0 0 16 NW 0 0 1 1 4 2 0 0 0 0 0 0 8 NNW 0 0 1 2 2 4 0 0 0 0 0 0 9 TOTALS 0 2 11 39 87 97 36 4 1 0 0 0 277 NUMBER OF VALID HOURS 277 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 277 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 06010100-06033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 -C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 2 4 6 3 0 0 0 0 0 16 NNE 0 0 1 8 16 196 187 9 0 0 0 0 417 NE 0 0 7 15 13 7 1 0 0 0 0 43 ENE 0 0 1 7 6 3 1 0 0 0 0 0 18 E 0 0 1 3 4 3 1 0 0 0 0 0 13 1

ESE 0 0 0 4 0 1 0 0 0 0 0 0 5 SE 0 0 1 0 1 0 0 0 0 0 0 2 SSE 0 0 4 0 4 0 0 0 0 0 0 9 0

S 0 0 3 1 1 0 1 0 0 0 0 6 SSW 0 0 01 1 0 1 0 0 0 0 0 0 2 SW 0 0 0 2 0 1 I 0 0 0 0 0 4 WSW 0 0 0i7 0 1 0 0 0 0 0 0 0 2 W 0 0 0 1 3 1 1 0 0 0 0 0 7 WNW 0 0 0 1 2 3 2 0 0 0 0 0 9 NW 0 0 1 1 2 2 0 0 0 0 0 6 NNW 0 0 0 5 6 1 0 0 0 0 0 8 TOTALS 1 0 54 242 206 0 0 567 45 11 0 0 NUMBER OF VALID HOURS 567 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 567 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 6 25 33 14 0 0 0 0 0 80 NNE 0 2 3 28 74 297 246 17 0 0 0 0 667 NE 0 0 0 17 28 29 23 6 2 0 0 0 105 ENE 0 0 3 13 15 7 4 0 0 0 0 0 42 E 1 1 3 15 10 12 4 0 0 0 0 0 46 ESE 0 0 0 6 7 6 6 1 0 0 0 0 26 SE 0 1 2 4 2 18 30 16 14 0 0 0 87 SSE 0 0 1 10 9 37 39 16 9 1 2 0 124 S 0 0 1 13 16 26 24 21 6 0 1 0 108 SSW 0 0 1 8 17 26 22 3 0 0 1 0 78 SW 0 1 1 15 24 39 32 7 2 1 0 0 122 WSW 0 1 3 12 30 37 30 7 10 0 0 0 130 W 0 2 3 12 18 61 81 18 12 0 0 0 207 WNW 0 1 2 8 26 47 90 16 4 0 0 0 194 NW 0 0 3 6 14 25 29 9 1 0 0 0 87 NNW 0 0 2 9 11 28 7 0 0 0 0 0 57 TOTALS 1 9 30 182 326 728 681 137 60 2 4 0 2160 NUMBER OF VALID HOURS 2160 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06040100-06063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ * -1.9 'C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 I 0 0 1 0 0 0 0 0 0 2 NNE 0 0 0 1 1 2 0 0 0 0 0 0 4 NE 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 1 0 1 0 0 0 0 0 2 SSE 0 0 0 2 0 7 1 1 0 0 0 12 S 0 0 0 3 7 15 28 6 0 0 0 0 59 SSW 0 0 0 2 6 17 33 0 0 0 0 0 58 SW 0 0 0 6 9 43 43 0 0 0 0 0 101 WSW 0 0 0 4 20 53 66 1 4 0 0 0 148 W 0 0 0 2 10 62 101 2 1 0 0 0 178 WNW 0 0 0 2 6 36 83 7 2 0 0 0 136 NW 0 0 0 0 0 5 5 4 3 0 0 0 17 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 1 21 62 234 367 21 11 0 0 0 717 NUMBER OF VALID HOURS 717 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 717 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ * -1.7 'C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 1 1 0 0 0 0 0 0 0 2 NNE 0 0 0 1 0 0 0 0 0 0 0 0 1 NE 0 0 0 1 0 0 0 0 0 0 0 0 1 ENE 0 0 0 1 0 0 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 1 1 0 0 0 0 0 0 0 2 SE 0 0 0 0 0 0 1 1 0 0 0 0 2 SSE 0 0 1 2 0 7 6 8 2 0 0 0 26 S 0 0 0 0 3 6 3 4 0 0 0 0 16 SSW 0 0 0 4 1 4 11 0 1 0 0 0 21 SW 0 0 0 2 4 12 8 0 0 0 0 0 26 WSW 0 0 0 2 3 4 4 0 1 0 0 0 14 W 0 0 0 1 3 4 1 0 2 0 0 0 11 WNW 0 0 1 2 2 3 1 0 0 0 0 0 9 NW 0 0 0 0 1 4 2 1 0 0 0 0 8 NNW 0 0 0 0 1 0 0 0 0 0 0 0 1 TOTALS 0 0 2 18 20 44 37 14 6 0 0 0 141 NUMBER OF VALID HOURS 141 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 141 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06040100-06063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ _* -1.5 -C/100 METERS) 2.1 3.1 5.1 °C/i00 METERS) 10.1 13.1 >18 TOTAL WIND .22 .51 .76 1.1 1,6 7.1 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 0 0 0 0 0 0 0 3 NNE 0 0 0 1 1 5 0 0 .0 0 0 0 7 NE 0 0 0 0 2 1 0 0 0 0 0 0 3 ENE 0 0 0 1 0 0 0 0 0 0 0 0 E 0 0 0 0 0 1 0 0 0 0 0 0 ESE 0 0 0 0 1 0 0 0 0 0 0 0 SE 0 0 1 10 1 0 0 0 0 0 13 01 2 6 14 11 7 1 0 0 0 42 SSE 0 0 S 0 0 5 4 8 11 3 0 0 0 0 32 SSW 0 1 3 7 8 10 2 0 0 0 0 33 SW 0 0 3 4 9 8 1 0 0 0 0 25 0 13 WSW 0 0 0 2 7 2 2 0 0 0 0 0 W 0 0 0 4 1 2 0 0 0 0 0 0 7 WNW 0 1 0 3 4 4 1 0 0 0 0 0 13 NW 0 0 00 2 6 9 4 1 0 0 0 0 22 NNW 0 0 0 2 2 0 0 0 0 0 0 4 TOTALS 0 3 2 28 48 75 48 14 2 0 0 0 220 NUMBER OF VALID HOURS 220 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 220 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 'C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 1 10 4 11 0 0 0 0 0 0 26 NNE 0 0 3 8 5 6 0 0 0 0 0 0 22 NE 0 0 1 2 10 3 0 0 0 0 0 0 16 ENE 0 1 2 0 4 5 0 0 0 0 0 0 12 E 0 0 0 2 3 1 0 0 0 0 0 0 6 ESE 0 2 0 2 5 5 2 0 0 0 0 0 16 SE 0 0 1 6 10 24 26 5 0 0 0 0 72 SSE 0 0 0 4 13 27 20 14 2 0 0 0 80 S 0 1 0 5 15 14 11 3 6 0 0 0 55 SSW 0 0 0 11 8 16 11 1 1 0 0 0 48 SW 0 0 2 8 4 12 9 1 2 0 0 0 38 WSW 0 1 2 8 8 10 12 2 2 0 0 0 45 W 0 0 2 6 3 8 5 3 0 0 0 0 27 WNW 0 1 2 7 6 4 4 6 0 0 0 0 30 NW 0 0 0 8 6 9 7 0 0 0 0 0 30 NNW 0 0 4 7 7 5 1 2 0 0 0 0 26 TOTALS 0 6 20 94 111 160 108 37 13 0 0 0 549 NUMBER OF VALID HOURS 549 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 549 ANNUAL RADIOACTIVE'EFFLUENT RELEASE REPORT (2006)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06040100-06063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ

  • 1.5 'C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 1 13 4 9 3 0 1 0 0 0 31 NNE 0 0 2 9 23 16 4 0 0 0 0 0 54 NE 0 0 3 3 4 1 0 0 0 0 0 0 11 ENE 0 0 0 5 3 1 0 0 0 0 0 0 9 E 0 1 0 1 4 2 0 0 0 0 0 0 8 ESE 0 0 0 0 1 0 0 0 0 0 0 0 1 SE 0 0 1 0 1 1 4 1 0 0 0 0 8 SSE 0 0 1 4 2 5 8 3 0 0 0 0 23 S 0 0 0 1 0 3 2 0 0 0 0 0 6 SSW 0 1 1 3 1 1 0 0 0 0 0 0 7 SW 0 3 1 4 2 0 1 0 0 0 0 0 11 WSW 0 0 0 1 1 0 0 0 0 0 0 0 2 W 0 0 3 3 4 5 1 0 0 0 0 0 16 WNW 0 0 1 0 1 1 3 0 0 0 0 0 6 NW 0 0 0 3 1 3 2 0 0 0 0 0 9 NNW 0 0 0 3 3 2 0 .0 0 0 0 0 8 TOTALS 0 5 14 53 55 50 28 4 1 0 0 0 210 NUMBER OF VALID HOURS 210 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 210 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ

  • 4.0 'C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 1 3 2 1 0 0 0 0 0 7 NNE 0 0 1 12 49 34 5 0 0 0 0 0 101 NE 0 0 1 6 1 2 0 0 0 0 0 0 10 ENE 0 0 0 1 2 2 0 0 0 0 0 0 5 E 0 0 0 3 0 0 0 0 0 0 0 0 3 ESE 0 0 0 1 1 1 0 0 0 0 0 0 3 SE 0 0 0 1 0 0 0 0 0 0 0 0 1 SSE 0 0 1 3 0 1 2 0 0 0 0 0 7 S 0 1 0 2 1 0 0 0 0 0 0 0 4 SSW 0 0 0 1 0 0 0 0 0 0 0 0 1 SW 0 0 0 1 0 0 0 0 0 0 0 0 1 WSW 0 0 0 0 1 0 0 0 0 0 0 0 1 W 0 0 0 1 3 2 1 0 0 0 0 0 7 WNW 0 0 0 0 1 2 4 0 0 0 0 0 7 NW 0 0 0 1 1 0 1 0 0 0 0 0 3 NNW 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTALS 0 1 3 34 63 46 15 0 0 0 0 0 162 NUMBER OF VALID HOURS 162 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 162 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06040100-06063023 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 STABLE 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 EXTREMELY 0 1 1 0 0 0 0 0 2 NNE 0 0 0 2 10 86 67 3 0 0 0 0 168 NE 0 0 0 1 I 2 0 0 0 0 0 0 4 ENE 0 0 0 0 0 0 1 0 0 0 .0 0 1 E 0 0 0 1 0 1 0 0 0 0 0 0 2 ESE 0 0 0 0 0 1 0 0 0 0 0 0 1 SE 0 0 0 0 0 1 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 1 0 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 1 0 0 0 0 0 0 0 0 1 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 0 0 0 0 0 0 W 0 0 0 0 0 0 i 0 0 0 0 0 1 WNW 0 0 0 0 0 1 0 0 0 0 0 0 NW 0 0 0 0 0 0 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 1 0 0 0 0 TOTALS 0 0 0 5 12 93 71 4 0 0 0 0 185 NUMBER OF VALID HOURS 185 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 185 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 26 14 24 5 0 1 0 0 0 73 NNE 0 0 6 34 89 149 76 3 0 0 0 0 357 NE 0 0 5 13 18 9 0 0 0 0 0 0 45 ENE 0 1 2 8 9 8 1 0 0 0 0 0 29 E 0 1 0 7 7 5 0 0 0 0 0 0 20 ESE 0 2 0 4 9 7 2 0 0 0 0 0 24 SE 0 0 2 8 13 36 33 7 0 0 0 0 99 SSE 0 1 3 16 23 54 54 34 6 0 0 0 191 S 0 2 1 16 30 46 55 16 6 0 0 0 172 SSW 0 2 2 25 23 46 65 3 3 0 0 0 169 SW 0 3 3 24 23 76 69 2 2 0 0 0 202 WSW 0 1 2 17 40 69 84 3 7 0 0 0 223 W 0 0 5 17 24 83 110 5 3 0 0 0 247 WNW 0 2 4 14 20 51 96 13 2 0 0 0 202 NW 0 0 0 14 15 30 22 6 3 0 0 0 90 NNW 0 0 4 10 14 9 2 2 0 0 0 0 41 TOTALS 0 15 42 253 371 702 674 94 33 0 0 0 2184 NUMBER OF VALID HOURS 2184 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06070100-06093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ * -1.9 'C/100 METERS)

WIND .22 .51 .76 - 1.1 - 1.6 - 2.1 3.1 - 5.1 7.1 -10.1 -13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 1 0 0 0 0 0 0 1 NNE 0 0 0 1 0 0 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 1 1 0 0 0 0 0 0 0 2 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 1 0 0 0 0 0 0 0 0 1 SSE 0 0 0 1 0 4 10 4 0 0 0 0 19 S 0 0 0 1 2 19 41 6 0 0 0 0 69 SSW 0 0 0 5 8 27 19 0 0 0 0 0 59 SW 0 0 1 1 16 38 33 0 0 0 0 0 89 WSW 1 0 0 2 19 62 44 0 0 0 0 0 128 W 0 0 0 1 21 78 111 0 0 0 0 0 211 WNW 0 0 0 1 6 47 156 11 0 0 0 0 221 NW 1 0 0 1 3 1 13 8 1 0 0 0 28 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 2 0 1 16 76 277 427 29 1 0 0 0 829 NUMBER OF VALID HOURS 829 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 829 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ * -1.7 'C/100 METERS)

WIND .22 - .51 .76 1.1 1.6 2.1 - 3.1 - 5.1 - 7.1 - 10.1 - 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 1 1 0 0 0 0 0 0 2 NNE 2 0 0 0 0 2 0 0 0 0 0 0 4 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 1 0 2 5 5 1 0 0 0 0 14 S 0 0 0 1 0 2 3 2 0 0 0 0 8 SSW 0 0 0 1 4 4 0 0 0 0 0 0 9 SW 0 0 0 1 0 2 3 0 0 0 0 0 6 WSW 0 0 0 2 1 2 0 0 0 0 0 0 5 W 0 0 0 3 1 1 3 0 0 0 0 0 8 WNW 0 0 2 1 7 10 3 0 0 0 0 0 23 NW 0 0 0 1 1 3 6 0 0 0 0 0 11 NNW 0 0 1 0 0 0 0 0 0 0 0 0 1 TOTALS 2 0 4 10 17 32 23 3 0 0 0 0 91 NUMBER OF VALID HOURS 91 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 91 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06070100-06093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ * -1.5 'C/100 METERS)

WIND .22 .51 .76 - 1.1 - 1.6 - 2.1 - 3.1 5.1 - 7.1 - 10.1 - 13.1 - >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 1 1 0 0 0 0 0 0 0 2 NNE 0 0 0 2 1 3 0 0 0 0 0 0 6 NE 0 0 0 0 1 2 0 0 ,0 0 0 0 3 ENE 0 0 0 0 1 0 0 0 0 0 0 0 1 E 0 0 0 1 0 0 0 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 1 0 0 0 0 0 0 1 SSE 0 1 0 0 3 0 4 2 0 0 0 0 10 S 0 0 0 0 4 7 4 1 0 0 0 0 16 SSW 0 0 0 5 4 8 2 0 0 0 0 0 19 SW 0 0 0 2 4 10 9 0 0 0 0 0 25 WSW 0 0 0 0 3 4 3 0 0 0 0 0 10 W 0 0 1 0 1 3 5 1 0 0 0 0 11 WNW 0 0 0 0 3 3 2 0 0 0 0 0 8 NW 0 0 0 1 2 12 13 2 0 0 0 0 30 NNW 0 0 0 2 1 0 0 0 0 0 0 0 3 TOTALS 0 1 1 14 29 53 42 6 0 0 0 0 146 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 * -0.5 'C/100 METERS)

WIND .22 .51 .76 1.1 - 1.6 - 2.1 3.1 - 5.1 7.1 -10.1 -13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 2 10 12 5 0 0 0 0 0 0 30 NNE 4 0 1 11 11 11 1 0 0 0 0 0 39 NE 0 1 0 2 4 3 0 0 0 0 0 0 10 ENE 0 0 1 7 3 0 0 0 0 0 0 0 11 E 0 0 3 7 7 2 0 0 0 0 .0 0 19 ESE 0 0 3 2 3 1 8 0 0 0 0 0 17 SE 0 0 1 4 13 22 23 1 0 0 0 0 64 SSE 0 2 3 10 18 27 42 6 0 0 0 0 108 S 0 0 1 7 10 11 16 0 0 0 0 0 45 SSW 0 0 5 6 13 8 6 0 0 0 0 0 38 SW 0 6 4 6 5 9 3 0 0 0 0 0 33 WSW 1 1 2 7 2 6 6 0 0 0 0 0 25 W 0 1 5 13 8 6 12 1 0 0 0 0 46 WNW 2 0 1 9 7 3 4 3 0 0 0 0 29 NW 0 1 1 12 4 18 5 2 0 0 0 0 43 NNW 0 1 2 10 10 3 2 0 0 0 0 0 28 TOTALS 7 14 35 123 130 135 128 13 0 0 0 0 585 NUMBER OF VALID HOURS 585 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 585 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06070100-06093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ

  • 1.5 'C/100 METERS)

WIND .22 - .51 .76 1.1 1.6 - 2.1 - 3.1 - 5.1 7.1 - 10.1 - 13.1 - >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 1 2 10 4 1 0 0 0 0 0 18 NNE 5 0 5 18 30 16 1 0 0 0 0 0 75 NE 0 1 3 9 1 1 0 0 0 0 0 0 15 ENE 0 1 1 11 2 1 1 0 0 0 0 0 17 E 1 1 1 5 3 0 0 0 0 0 0 0 11 ESE 0 1 1 3 4 2 0 0 0 0 0 0 11 SE 0 0 1 3 3 3 2 1 0 0 0 0 13 SSE 0 1 2 2 4 4 13 2 0 0 0 0 28 S 0 2 1 2 2 1 0 0 0 0 0 0 8 SSW 0 1 1 1 1 0 0 0 0 0 0 0 4 SW 0 1 1 0 1 0 0 0 0 0 0 0 3 WSW 2 0 3 0 1 1 0 0 0 0 0 0 7 W 1 1 1 3 4 3 0 0 0 0 0 0 13 WNW 1 1 2 6 2 3 1 0 0 0 0 0 16 NW 0 1 2 3 0 3 2 0 0 0 0 0 11 NNW 0 2 2 5 2 2 0 0 0 0 0 0 13 TOTALS 10 14 28 73 70 44 21 3 0 0 0 0 263 NUMBER OF VALID HOURS 263 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 263 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ

  • 4.0 'C/1O0 METERS)

WIND .22 - .51 - .76 - 1.1 - 1.6 - 2.1 3.1 - 5.1 - 7.1 -10.1 -13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 1 0 3 2 0 0 0 0 0 0 7 NNE 0 1 2 7 30 42 4 0 0 0 0 0 86 NE 0 0 3 5 11 1 0 0 0 0 0 0 20 ENE 0 0 0 2 1 3 1 0 0 0 0 0 7 E 0 0 0 3 1 2 0 0 0 0 0 0 6 ESE 0 0 0 0 1 0 0 0 0 0 0 0 1 SE 0 0 0 2 2 0 0 0 0 0 0 0 4 SSE 0 0 0 0 0 0 2 0 0 0 0 0 2 S 0 0 0 1 0 0 0 0 0 0 0 0 1 SSW 0 0 1 0 0 1 0 0 0 0 0 0 2 SW 0 0 1 2 0 1 0 0 0 0 0 0 4 WSW 0 0 0 0 1 0 0 0 0 0 0 0 1 W 0 0 0 1 1 0 0 0 0 0 0 0 2 WNW 0 0 0 4 0 1 1 0 0 0 0 0 6 NW 0 0 1 1 2 0 0 0 0 0 0 0 4 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 2 9 28 53 53 8 0 0 0 0 0 153 NUMBER OF VALID HOURS 153 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 153 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06070100-06093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 'C/100 METERS)

WIND .22 - .51 - .76 1.1 - 1.6 - 2.1 - 3.1 - 5.1 - 7.1 - 10.1 - 13.1 - >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 1 0 0 0 0 0 1 NNE 1 0 1 0 13 60 37 0 0 0 0 0 112 NE 0 0 0 2 2 5 0 0 0 0 0 0 9 ENE 0 0 0 1 1 1 0 0 0 0 0 0 3 E 1 0 0 2 0 0 0 0 0 0 0 0 3 ESE 1 0 0 0 0 0 0 0 0 0 0 0 1 SE 0 0 0 0 0 1 0 0 0 0 0 0 1 SSE 1 0 0 0 1 0 1 0 0 0 0 0 3 S 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 4 0 0 0 0 0 0 0 0 0 0 0 4 W 0 0 0 0 0 0 0 0 0 0 0 0 0 WNW 2 0 1 0 0 0 0 0 0 0 0 0 3 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 0 1 0 0 0 0 0 0 0 1 TOTALS 10 0 2 5 18 67 39 0 0 0 0 0 141 NUMBER OF VALID HOURS 141 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 141 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 2 4 13 27 13 2 0 0 .0 0 0 61 NNE 12 1 9 39 85 134 43 0 0 0 0 0 323 NE 0 2 6 18 19 12 0 0 0 0 0 0 57 ENE 0 1 2 21 8 5 2 0 0 0 0 0 39 E 2 1 4 19 12 4 0 0 0 0 0 0 42 ESE 1 1 4 5 8 3 8 0 0 0 0 0 30 SE 0 0 2 10 18 27 25 2 0 0 0 0 84 SSE 1 4 6 13 28 40 77 15 0 0 0 0 184 S 0 2 2 12 18 40 64 9 0 0 0 0 147 SSW 0 1 7 18 30 48 27 0 0 0 0 0 131 SW 0 7 7 12 26 60 48 0 .0 0 0 0 160 WSW 8 1 5 11 27 75 53 0 0 0 0 0 180 W 1 2 7 21 36 91 131 2 0 0 0 0 291 WNW 5 1 6 21 25 67 167 14 0 0 0 0 306 NW 1 2 4 19 12 37 39 12 1 0 0 0 127 NNW 0 3 5 17 14 5 2 0 0 0 0 0 46 TOTALS 31 31 80 269 393 661 688 54 1 0 0 0 2208 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06100100-06123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ * -1.9 'C/100 METERS)

WIND .22 .51 .76 1.1 - 1.6 - 2.1 - 3.1 - 5.1 7.1 -10.1 -13.1 - >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 4 1 0 0 0 5 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 1 0 0 0 0 0 0 1 SE 0 0 0 0 2 1 3 1 0 0 0 0 7 SSE 0 0 0 0 1 4 10 0 0 0 0 0 15 S 0 0 0 1 1 19 13 0 0 0 0 0 34 SSW 0 0 0 5 8 16 14 0 0 0 0 0 43 SW 0 0 1 3 13 24 19 0 0 0 0 0 60 WSW 0 0 0 4 18 35 11 1 0 0 0 0 69 W 0 0 0 3 22 78 31 1 0 0 0 0 135 WNW 0 0 0 0 8 23 67 10 0 3 0 0 i11 NW 0 0 0 0 0 2 4 0 0 0 0 0 6 NNW 0 0 0 0 2 0 0 0 0 0 0 0 2 TOTALS 0 0 1 16 75 203 172 17 1 3 0 0 488 NUMBER OF VALID HOURS 488 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 488 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ * -1.7 'C/100 METERS)

WIND .22 - .51 - .76 1.1 1.6 2.1 - 3.1 - 5.1 7.1 -10.1 -13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 1 0 0 0 1 0 0 0 2 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 1 0 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 1 1 0 0 0 0 2 SSE 0 0 0 0 2 1 3 1 0 0 0 0 7 S 0 0 0 0 0 1 2 1 0 0 0 0 4 SSW 0 0 0 0 2 1 0 0 0 0 0 0 3 SW 0 0 0 1 0 3 3 0 1 0 0 0 8 WSW 0 0 0 1 2 1 0 0 0 0 0 0 4 W 0 0 1 1 2 3 1 0 0 0 0 0 8 WNW 0 0 0 1 1 2 3 0 0 0 1 0 8 NW 0 0 0 0 0 0 5 0 0 0 0 0 5 NNW 0 0 0 0 0 1 0 0 0 0 0 0 1 TOTALS 0 0 1 4 10 14 18 3 2 0 1 0 53 NUMBER OF VALID HOURS 53 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 53 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06100100-06123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ * -1.5 'C/100 METERS)

WIND .22 - .51 .76 1.1 - 1.6 - 2.1 3.1 5.1 7.1 -10.1 -13.1 - >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 1 0 0 1 0 0 0 0 0 0 2 NE 0 0 0 0 1 0 0 0 0 0 0 0 1 ENE 0 0 0 0 0 1 0 0 0 0 0 0 1 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 1 1 0 0 0 0 2 SSE 0 0 0 1 1 1 5 2 0 0 0 0 10 S 0 0 1 1 0 0 1 2 0 0 0 0 5 SSW 0 0 1 0 1 4 1 0 0 0 0 0 7 SW 0 0 1 0 0 1 0 0 1 0 0 0 3 WSW 0 0 1 0 0 0 0 1 0 0 0 0 2 W 0 0 0 1 3 1 0 0 0 0 0 0 5 WNW 0 0 0 0 3 3 1 0 0 1 0 0 8 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 5 3 10 13 12 6 1 1 0 0 51 NUMBER OF VALID HOURS 51 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 51 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 'C/100 METERS)

WIND .22 - .51 - .76 1.1 - 1.6 - 2.1 3.1 - 5.1 7.1 - 10.1 - 13.1 - >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 1 3 5 3 0 0 0 0 0 0 13 NNE 0 0 3 3 4 2 2 1 0 0 0 0 15 NE 0 0 0 0 1 1 1 1 0 0 0 0 4 ENE 0 0 0 0 1 0 0 0 0 0 0 0 1 E 0 0 0 0 2 2 5 0 0 0 0 0 9 ESE 0 0 1 2 1 6 6 0 0 0 0 0 16 SE 0 0 1 3 2 13 23 6 0 0 0 0 48 SSE 0 0 1 0 6 14 18 6 0 0 0 0 45 S 0 0 1 7 1 6 5 0 0 0 0 0 20 SSW 0 1 1 2 3 3 6 2 2 0 0 0 20 SW 0 1 0 4 1 5 6 1 3 0 0 0 21 WSW 0 0 1 5 3 2 2 2 0 0 0 0 15 W 0 0 2 1 8 3 8 9 1 0 0 0 32 WNW 0 0 0 2 4 7 4 4 2 1 0 0 24 NW 0 0 1 3 14 9 15 2 1 0 0 0 45 NNW 0 0 1 6 1 12 2 0 0 0 0 0 22 TOTALS 0 3 14 41 57 88 103 34 9 1 0 0 350 NUMBER OF VALID HOURS 350 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 350

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06100100-06123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ

  • 1.5 'C/I00 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 5 7 6 4 0 0 0 0 0 23 NNE 0 0 2 25 25 21 8 1 1 0 0 0 83 NE 0 0 1 3 3 3 4 8 1 2 0 0 25 ENE 0 0 0 4 6 2 1 0 0 0 0 0 13 E 0 2 3 6 2 3 0 0 0 0 0 0 16 ESE 0 0 1 3 3 9 1 0 0 0 0 0 17 SE 0 0 1 2 3 2 2 0 0 0 0 0 10 SSE 0 0 1 3 2 5 2 0 0 0 0 0 13 S 0 0 1 3 1 3 1 1 0 0 0 0 10 SSW 0 0 1 2 0 0 1 0 0 0 0 0 4 SW 0 0 2 4 0 0 0 1 0 0 0 0 7 WSW 0 1 1 3 0 0 0 0 0 0 0 0 5 W 0 0 1 3 4 9 1 0 0 0 0 0 18 WNW 1 0 2 3 4 12 2 1 1 0 0 0 26 NW 0 0 1 5 5 2 3 0 0 0 0 0 16 NNW 0 3 2 3 3 3 3 0 0 0 0 0 17 TOTALS 1 6 21 77 68 80 33 12 3 2 0 0 303 NUMBER OF VALID HOURS 303 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 303 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ

  • 4.0 °C/100 METERS)

WIND .22 - .51 .76 1.1 1.6 - 2.1 - 3.1 5.1 7.1 -10.1 -13.1 - >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 2 2 4 5 5 2 0 0 0 0 0 20 NNE 0 0 4 12 44 72 11 1 0 0 0 0 144 NE 0 1 4 28 17 8 5 0 0 0 0 0 63 ENE 0 0 3 10 3 3 0 0 0 0 0 0 19 E 0 1 0 1 4 2 1 0 0 0 0 0 9 ESE 0 0 0 2 2 0 1 0 0 0 0 0 5 SE 0 0 0 0 0 0 1 0 0 0 0 0 1 SSE 0 0 1 1 2 1 1 0 0 0 0 0 6 S 0 0 0 2 2 0 0 0 0 0 0 0 4 SSW 0 1 2 2 1 1 0 0 0 0 0 0 7 SW 0 0 0 2 0 0 0 0 0 0 0 0 2 WSW 0 0 1 1 2 1 0 0 0 0 0 0 5 W 0 0 0 3 2 3 0 0 0 0 0 0 8 WNW 0 0 0 1 2 7 4 0 0 0 0 0 14 NW 2 2 3 1 5 2 1 0 0 0 0 0 16 NNW 0 1 3 2 5 5 1 0 0 0 0 0 17 TOTALS 2 8 23 72 96 110 28 1 0 0 0 0 340 NUMBER OF VALID HOURS 340 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 340

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2006)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 06100100-06123123 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 5 0 0 1 2 7 4 0 0 0 0 0 19 NNE 0 0 0 2 48 199 176 0 0 0 0 0 425 NE 0 0 0 12 16 32 12 0 0 0 0 0 72 ENE 0 0 1 10 6 2 0 0 0 0 0 0 19 E 0 0 1 3 1 3 0 0 0 0 0 0 8 ESE 0 0 0 1 0 4 0 0 0 0 0 0 5 SE 0 0 2 0 3 0 0 0 0 0 0 0 5 SSE 0 0 0 2 2 0 0 0 0 0 0 0 4 S 0 0 1 3 3 0 0 0 0 0 0 0 7 SSW 0 0 1 4 4 1 0 0 0 0 0 0 10 SW 0 0 0 4 1 1 4 0 0 0 0 0 10 WSW 0 0 0 2 0 0 1 0 0 0 0 0 3 W 10 0 0 1 5 0 0 0 0 0 0 0 16 WNW 0 0 0 1 1 4 0 0 0 0 0 0 6 NW 0 0 0 1 1 3 3 0 0 0 0 0 8 NNW 0 0 1 0 0 4 1 0 0 0 0 0 6 TOTALS 15 0 7 47 93 260 201 0 0 0 0 0 623 NUMBER OF VALID HOURS 623 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 623 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 5 3 4 13 19 21 10 0 0 0 0 0 75 NNE 0 0 10 42 122 295 197 3 2 0 0 0 671 NE 0 1 5 43 38 44 22 13 2 2 0 0 170 ENE 0 0 4 24 16 8 1 0 0 0 0 0 53 E 0 3 4 10 9 11 6 0 0 0 0 0 43 ESE 0 0 2 8 6 20 8 0 0 0 0 0 44 SE 0 0 4 5 10 16 31 9 0 0 0 0 75 SSE 0 0 3 7 16 26 39 9 0 0 0 0 100 S. 0 0 4 17 8 29 22 4 0 0 0 0 84 SSW 0 2 6 15 19 26 22 2 2 0 0 0 94 SW 0 1 4 18 15 34 32 2 5 0 0 0 111 WSW 0 1 4 16 25 39 14 4 0 0 0 0 103 W 10 0 4 13 46 97 4i 10 1 0 0 0 222 WNW 1 0 2 8 23 58 81 15 3 5 1 0 197 NW 2 2 5 10 26 19 34 2 1 0 0 0 101 NNW 0 4 7 11 11 25 7 0 0 0 0 0 65 TOTALS 18 17 72 260 409 768 567 73 16 7 1 0 2208 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208

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