ML091340258

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Annual Radioactive Effluent Release Report - 2008, Period of the Report Is January 1, 2008 Through December 31, 2008
ML091340258
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 04/29/2009
From: Scherer A
Southern California Edison Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209
Download: ML091340258 (279)
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Text

{{#Wiki_filter:1.~\jV SOUTHERN CALIFORNIA A. Edward Scherer 1$ EDISON Director Nuclear Regulatory Affairs An EDISON INTERNATlONAL Company April 29, 2009 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Docket Nos. 50-206, 50-361 and 50-362 Annual Radioactive Effluent Release Report - 2008 San Onofre Nuclear Generating Station, Units 1, 2, and 3

Dear Sir or Madam:

In accordance with 10 CFR 50.36(a), Unit 1 Permanently Defueled Technical Specification (TS) Section 06.9.1.4, and Units 2 and 3 TS Section 5.7.1.3, Southern California Edison (SCE) is providing the Annual Radioactive Effluent Release Report - 2008 (ARERR) for San Onofre Nuclear Generating Station, Units 1, 2, and 3. The period of the report is January 1, 2008 through December 31, 2008. Unit 1 Permanently Defueled TS Section 06.14.2.3 and Units 2 and 3 TS Section 5.5.2.1.1 (c) require revisions made to the Offsite Dose Calculation Manual (ODCM) for this reporting period to be submitted with the ARERR. On February 29,2008, S0123-0DCM, Revision 1 was issued and is included with this submittal. To comply with Technical Specification 5.5.2.1.1, change bars are included on all affected pages. If you require additional information, please contact Mr. Geoffrey Cook at (949) 368-9008. Sincerely, P.O. Box 128 San Clemente, CA 92674

Document Control Desk April 29, 2009 : Annual Radioactive Effluent Release Report - 2008 : ODCM, SO123-ODCM, Revision 1 cc: E. E. Collins, NRC Regional Administrator, Region IV J. E. Whitten, NRC Region IV, Nuclear Material Safety Branch Chief R. Hall, NRC Project Manager, SONGS Units 2 and 3 J. C. Shepherd, NRC Project Manager, SONGS Unit 1 G. G. Warnick, NRC Senior Resident Inspector, SONGS Units 2 and 3 S. Y. Hsu, California Department of Public Health

Enclosure 1: Annual Radioactive Effluent Release Report - 2008

SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2008 January - December

PREFACE San Onofre Nuclear Generating Station is located next to San Onofre State Beach, adjoining Camp Pendleton Marine Corps Base, in San Diego County, 64 miles south of Los Angeles, California. There are two operating pressurized water reactors with a total rated capacity of 2254 net megawatts electrical. Unit 1, rated at 410 net megawatts electrical, was supplied by Westinghouse Electric Company and began commercial operation on January 1, 1968. The unit was permanently shutdown on November 30, 1992. By August 31, 2004, all fuel was transferred to the Independent Spent Fuel Storage Installation (ISFSI). As of November 29, 2006, all remaining monitored effluent pathways were permanently removed from service. 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 (78.21%), San Diego Gas and Electric (20%), and the City of Riverside (1.79%). Effective December 29, 2006, the City of Anaheim 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 used nuclear fuel and Units 2 and 3's independent spent fuel storage installation located on the facilitys site. In addition, the City of Anaheim retains financial responsibility for its used 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. 

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TABLE OF CONTENTS SECTION A - INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 SECTION B - GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 SECTION C - LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM . . . . . . . . 19 SECTION E -RADWASTE SHIPMENTS UNITS 2 & 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 DECOMMISSIONED UNIT 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 COMMON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 SECTION F - APPLICABLE LIMITS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 SECTION G - ESTIMATION OF ERROR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL . . . . . . . . . . . . . . . . . . . . . . 38 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS . . . . . . . . . . . . . . . . 39 SECTION K - MISCELLANEOUS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 Abnormal Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 Effluent Monitors Out of Service Greater Than 30 days . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 Onsite Groundwater Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 40 CFR 190 Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 SECTION L - S.O.N.G.S. CONCLUSIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 METEOROLOGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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. It will also summarize the radwaste shipments from the decommissioning of Unit 1. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:

1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release
2. Percent of Applicable Limits
3. Estimated Total Percent Error
4. Lower Limit of Detection Concentrations
5. Batch Release Summaries
6. Previous Radioactive Effluent Release Report Addendum
7. Radwaste Shipments
8. 10 CFR 50 Appendix I Requirements
9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents-Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories: fission and activation gases, iodine-131, particulates with half-lives greater than eight days, and tritium. Listed for each of the four categories are:

(1) the total curies released (2) the average release rate (3) the percent of applicable limit (4) the estimated total error In addition, the particulate category lists the gross alpha radioactivity released for each quarter. The methodology used to calculate the percent of Applicable Limit is presented in Section F of this report. The methodology used in Table 1A to calculate the estimated total error is presented in Section G of this report. Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station does not conduct elevated releases. Table 1C, "Gaseous Effluents-Ground Level Releases," provides the systematic listing by radionuclide for the quantity of radioactivity released in three categories: fission gases, iodines, and particulates. The total radioactivity for each radionuclide is listed for each quarterly period by both "continuous" and "batch" modes of release. Waste gas decay tank releases are considered to be "batch" releases. Containment purges and plant stack releases are considered to be "continuous" releases. Table 1D, "Gaseous Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Tables 1A and 1C. Table 1E, "Gaseous Effluents-Radiation Doses at the Site Boundary," provides a quarterly summary of doses at the site boundary for this report period. Table 1F, "Gaseous Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 1.89E+1 1.21E+1
2. Average release rate for period µCi/sec 2.40E+0 1.54E+0 3.00E+1
3. Percent of applicable limit  % MPC 4.39E-3 5.14E-3
4. Percent Effluent Concentration Limit  % ECL 4.71E-3 1.36E-2 B. Iodines
1. Total iodine-131 Ci 1.35E-5 1.12E-4
2. Average release rate for period µCi/sec 1.72E-6 1.42E-5 1.90E+1
3. Percent of applicable limit  % MPC 8.24E-6 6.84E-5
4. Percent Effluent Concentration Limit  % ECL 4.12E-6 3.42E-5 C. Particulates
1. Particulates with half-lives >8 days Ci 3.79E-4 4.69E-4
2. Average release rate for period µCi/sec 4.82E-5 5.96E-5 1.60E+1
3. Percent of applicable limit  % MPC 3.96E-5 6.53E-5
4. Percent Effluent Concentration Limit  % ECL 2.01E-4 3.49E-4
5. Gross alpha activity Ci <LLD <LLD 5.00E+1 D. Tritium
1. Total release Ci 1.37E+1 1.91E+1
2. Average release rate for period µCi/sec 1.74E+0 2.43E+0 2.50E+1
3. Percent of applicable limit  % MPC 4.18E-3 5.83E-3
4. Percent Effluent Concentration Limit  % ECL 8.36E-3 1.17E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 1.63E+1 3.33E+1
2. Average release rate for period µCi/sec 2.05E+0 4.19E+0 3.00E+1
3. Percent of applicable limit  % MPC 3.56E-3 8.90E-3
4. Percent Effluent Concentration Limit  % ECL 3.23E-3 1.39E-2 B. Iodines
1. Total iodine-131 Ci 1.18E-4 1.00E-3
2. Average release rate for period µCi/sec 1.48E-5 1.26E-4 1.90E+1
3. Percent of applicable limit  % MPC 7.13E-5 6.04E-4
4. Percent Effluent Concentration Limit  % ECL 3.56E-5 3.02E-4 C. Particulates
1. Particulates with half-lives >8 days Ci 1.05E-4 2.58E-4
2. Average release rate for period µCi/sec 1.31E-5 3.25E-5 1.60E+1
3. Percent of applicable limit  % MPC 8.37E-6 2.92E-5
4. Percent Effluent Concentration Limit  % ECL 4.13E-5 1.58E-4
5. Gross alpha activity Ci <LLD <LLD 5.00E+1 D. Tritium
1. Total release Ci 1.82E+1 2.99E+1
2. Average release rate for period µCi/sec 2.29E+0 3.76E+0 2.50E+1
3. Percent of applicable limit  % MPC 5.50E-3 9.03E-3
4. Percent Effluent Concentration Limit  % ECL 1.10E-2 1.81E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C 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 4.09E-1 2.02E+0 2.13E-1 1.68E+0 krypton-85 Ci <LLD <LLD <LLD <LLD krypton-85m Ci <LLD <LLD <LLD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci 1.72E+1 1.01E+1 1.61E+1 2.98E+1 xenon-133m Ci <LLD <LLD <LLD 1.84E-1 xenon-135 Ci <LLD <LLD <LLD <LLD xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci 1.76E+1 1.21E+1 1.63E+1 3.17E+1
2. Iodines iodine-131 Ci 1.35E-5 1.12E-4 1.18E-4 1.00E-3 iodine-132 Ci 1.30E-7 <LLD <LLD 1.56E-4 iodine-133 Ci 4.28E-5 1.64E-4 3.03E-4 1.31E-4 iodine-135 Ci <LLD <LLD <LLD <LLD Total for period Ci 5.64E-5 2.76E-4 4.21E-4 1.29E-3 LLD Lower Limit of Detection; see Table 1D.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C (Continued) GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

3. Particulates barium-140 Ci <LLD <LLD <LLD <LLD bromine-82 Ci 7.83E-5 6.05E-5 4.88E-5 1.53E-4 cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 2.42E-5 <LLD <LLD 2.33E-6 cobalt-57 Ci <LLD 1.51E-6 <LLD <LLD cobalt-58 Ci 1.97E-4 1.60E-4 7.40E-5 1.32E-4 cobalt-60 Ci 1.48E-4 2.62E-4 3.05E-5 1.24E-4 iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 7.67E-6 1.53E-5 <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 2.07E-6 <LLD <LLD <LLD niobium-97 Ci 1.46E-5 1.32E-4 <LLD <LLD silver-110m Ci <LLD 3.00E-5 <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 1D.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C (Continued) GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE

  • First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter
1. Fission and activation gases krypton-85 Ci 1.30E+0 ** ** 1.64E+0 krypton-85m Ci <LLD ** ** <LLD krypton-87 Ci <LLD ** ** <LLD krypton-88 Ci <LLD ** ** <LLD xenon-133 Ci 6.87E-3 ** ** <LLD xenon-133m Ci <LLD ** ** <LLD xenon-135 Ci <LLD ** ** <LLD xenon-135m Ci <LLD ** ** <LLD xenon-138 Ci <LLD ** ** <LLD Total for period Ci 1.31E+0 ** ** 1.64E+0 LLD Lower Limit of Detection; see Table 1D.
  • Iodines and particulates are not analyzed prior to release via batch mode.
    • No batch releases were conducted in the second and third quarters of 2008.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS and BATCH MODE Continuous Mode Batch Mode Radionuclides LLD (µCi/cc) LLD (µCi/cc)

1. Fission and activation gases krypton-85 1.60E-5 N/A krypton-85m 3.70E-8 2.30E-6 krypton-87 1.90E-7 9.80E-6 krypton-88 1.30E-7 8.10E-6 xenon-133
  • 5.10E-6 xenon-133m 3.00E-7 2.00E-5 xenon-135 3.90E-8 2.50E-6 xenon-135m 1.50E-6 3.00E-5 xenon-138 2.60E-6 4.80E-5
2. Iodines iodine-132 1.30E-9 N/A iodine-135 1.50E-10 N/A
3. Particulates barium-140 5.00E-13 N/A cerium-141 5.80E-14 N/A cerium-144 2.30E-13 N/A cesium-134 1.40E-13 N/A cesium-137 1.20E-13 N/A cobalt-57 2.90E-14 N/A iron-59 3.10E-13 N/A lanthanum-140 1.00E-12 N/A manganese-54 1.30E-13 N/A molybdenum-99 7.00E-14 N/A niobium-95 1.30E-13 N/A niobium-95 1.40E-12 N/A silver-110m 1.80E-13 N/A strontium-89 1.00E-11 N/A strontium-90 1.00E-11 N/A zinc-65 3.30E-13 N/A
4. alpha 1.00E-11 N/A
  • Radionuclide was >LLD in all 4 quarters.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1E GASEOUS EFFLUENTS-RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A. Noble Gas

1. Gamma Air Dose mrad 1.51E-3 3.41E-3 1.17E-3 3.99E-3
2. Percent Applicable Limit  % 1.51E-2 3.41E-2 1.17E-2 3.99E-2
3. Beta Air Dose mrad 3.34E-3 2.62E-3 2.68E-3 6.13E-3
4. Percent Applicable Limit  % 1.67E-2 1.31E-2 1.34E-2 3.07E-2 B. Tritium, Iodine, Particulates (at the nearest receptor)
1. Organ Dose mrem 4.49E-3 5.96E-3 2.75E-3 6.57E-3
2. Percent Applicable Limit  % 2.99E-2 3.97E-2 1.83E-2 4.38E-2 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1F GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 5 releases
2. Total time period for batch releases: 1849 minutes
3. Maximum time period for a batch release: 485 minutes
4. Average time period for a batch release: 370 minutes
5. Minimum time period for a batch release: 282 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are:

(1) the total curies released (2) the average diluted concentration (3) the percent of applicable limit (4) the estimated total error In addition, Table 2A lists: (1) the gross alpha radioactivity (2) the volume of waste released (prior to dilution) (3) the volume of dilution water The methodology used to calculate the percent of applicable limit is presented in Section F of this report. The methodology used to calculate the estimated total error in Table 2A is presented in Section G of this report. Table 2B, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category. The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release. Table 2C, "Liquid Effluents-Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 2B. Table 2D, "Liquid Effluents-Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period. Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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, Ci 1.03E-2 9.15E-3
2. Average diluted concentration during µCi/ml 1.38E-11 1.21E-11 1.90E+1
3. Percent of applicable limit  % MPC 1.67E-5 1.84E-5
4. Percent Effluent Concentration Limit  % ECL 1.04E-4 1.42E-4 B. Tritium Ci 7.82E+1 2.05E+2
2. Average diluted concentration during µCi/ml 1.05E-7 2.71E-7 1.90E+1
3. Percent of applicable limit  % MPC 3.49E-3 9.02E-3
4. Percent Effluent Concentration Limit  % ECL 1.05E-2 2.71E-2 C. Dissolved and entrained gases
1. Total release Ci 2.28E-2 3.45E-2
2. Average diluted concentration during µCi/ml 3.05E-11 4.56E-11 1.90E+1
3. Percent of applicable limit  % MPC 1.53E-5 2.28E-5
4. Percent Effluent Concentration Limit  % ECL 1.53E-5 2.28E-5 D. Gross alpha radioactivity
1. Total release Ci <LLD <LLD 5.00E+1 E. Volume of waste released (batch & continuous, liters 4.12E+7 4.74E+7 5.00E+0 F. Volume of dilution water used during period liters 7.48E+11 7.58E+11 5.00E+0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2A (Continued)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Third Fourth Estimated

1. Total release (not including tritium, Ci 1.21E-2 8.42E-3
2. Average diluted concentration during µCi/ml 1.58E-11 1.42E-11 1.90E+1
3. Percent of applicable limit  % MPC 2.49E-5 2.09E-5
4. Percent Effluent Concentration Limit  % ECL 2.11E-4 1.54E-4
1. Total release Ci 4.95E+2 2.65E+2
2. Average diluted concentration during µCi/ml 6.47E-7 4.47E-7 1.90E+1
3. Percent of applicable limit  % MPC 2.16E-2 1.49E-2
4. Percent Effluent Concentration Limit  % ECL 6.47E-2 4.47E-2
1. Total release Ci 3.23E+0 6.10E-1
2. Average diluted concentration during µCi/ml 4.22E-9 1.03E-9 1.90E+1
3. Percent of applicable limit  % MPC 2.11E-3 5.14E-4
4. Percent Effluent Concentration Limit  % ECL 2.11E-3 5.14E-4
1. Total release Ci <LLD <LLD 5.00E+1 E. Volume of waste released (batch & continuous, liters 5.46E+7 4.57E+7 5.00E+0 liters 7.65E+11 5.93E+11 5.00E+0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 5.10E-6 <LLD chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD 5.10E-6 <LLD
2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 2C ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 4.87E-6 antimony-125 Ci 9.88E-4 2.63E-4 4.01E-4 8.44E-4 barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci 1.01E-5 <LLD 3.73E-5 5.51E-5 cesium-137 Ci 5.44E-5 1.26E-4 2.65E-4 1.09E-4 chromium-51 Ci 6.67E-4 <LLD 3.94E-4 1.35E-3 cobalt-57 Ci 1.23E-5 8.97E-6 1.53E-5 1.26E-5 cobalt-58 Ci 2.47E-3 2.17E-3 3.82E-3 3.49E-3 cobalt-60 Ci 1.16E-3 1.96E-3 2.86E-3 1.43E-3 iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci 3.09E-3 2.29E-3 2.78E-3 <LLD iron-59 Ci 1.61E-4 1.05E-4 <LLD 4.81E-6 lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 1.52E-4 2.48E-4 3.18E-4 1.56E-4 molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 7.58E-4 1.05E-3 4.36E-4 4.46E-4 niobium-97 Ci 9.56E-6 <LLD <LLD <LLD silver-110m Ci 4.03E-4 4.52E-4 4.52E-4 1.33E-4 strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD tin-113 Ci <LLD <LLD <LLD 6.19E-5 tin-117m Ci 2.54E-5 <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci 3.80E-4 4.69E-4 3.00E-4 3.24E-4 Total for period Ci 1.03E-2 9.15E-3 1.21E-2 8.42E-3
2. Dissolved and entrained gases krypton-85 Ci 2.25E-2 3.43E-2 3.01E-1 1.23E-1 xenon-131m Ci <LLD <LLD 7.15E-2 1.56E-2 xenon-133 Ci 3.11E-4 2.34E-4 2.84E+0 4.70E-1 xenon-133m Ci <LLD <LLD 1.61E-2 1.23E-3 xenon-135 Ci <LLD <LLD 4.01E-4 <LLD Total for period Ci 2.28E-2 3.45E-2 3.23E+0 6.10E-1 LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION LLD (µCi/ml) LLD (µCi/ml) Radionuclides Continuous Mode Batch Mode

1. Fission and activation products antimony-124 N/A 2.70E-7 barium-140 3.10E-7 2.50E-7 cerium-141 4.60E-8 4.30E-8 cerium-144 1.90E-7 1.90E-7 cesium-134 8.00E-8 8.00E-8 cesium-137 6.80E-8
  • chromium-51 3.50E-7 3.20E-7 cobalt-58 7.30E-8
  • cobalt-60 1.10E-7
  • iodine-131 6.10E-8 4.60E-8 iron-55 1.00E-6 1.00E-6 iron-59 1.70E-7 1.60E-7 lanthanum-140 6.10E-7 2.00E-7 manganese-54 7.20E-8
  • molybdenum-99 6.10E-8 2.80E-8 niobium-95 7.30E-8
  • niobium-97 1.10E-6 1.60E-7 strontium-89 5.00E-8 5.00E-8 strontium-90 5.00E-8 5.00E-8 technetium-99m 6.20E-8 2.90E-8 tin-113 N/A 5.70E-8 tin-117m N/A 2.50E-8 zinc-65 1.80E-7 1.80E-7 zirconium-95 1.20E-7 *
2. Dissolved and entrained gases xenon-131m N/A 3.20E-6 xenon-133 2.60E-7
  • xenon-133m N/A 7.30E-7 xenon-135 9.40E-8 9.40E-8
3. gross alpha 1.00E-7 1.00E-7
  • Radionuclide was >LLD in all 4 quarters.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 4.06E-4 5.74E-4 1.11E-3 5.26E-4
2. Percent Applicable Limit  % 1.35E-2 1.91E-2 3.69E-2 1.75E-2 B.
1. Limiting organ dose mrem 2.94E-3 3.11E-3 3.59E-3 1.60E-3
2. Percent Applicable Limit  % 2.94E-2 3.11E-2 3.59E-2 1.60E-2
3. Limiting organ for period GI/LLI GI/LLI GI/LLI GI/LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 164 releases
2. Total time period for batch releases: 26116 minutes
3. Maximum time period for a batch release: 522 minutes
4. Average time period for a batch release: 159 minutes
5. Minimum time period for a batch release: 50 minute
6. Average saltwater flow during batch releases: 738000 gpm ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM In the 2005 Annual Radioactive Effluent Release Report, the U2/3 Shipments in Table A3 were mistakenly reported as all being sent by truck, when two were shipped by rail. The correction is provided below and is documented in AR # 080500516.

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination TAG Transport Truck/Flatbed 6* Duratek/EnviroCare, UT Trailer Hitman Transport 1** Studsvik/Barnwell Truck/Flatbed Trailer 2 MHFLogisticalSolutions Rail EnviroCare, UT
  • SONGS maintains a contract with Duratek that provides volume reduction services. The processed volume was shipped from the Duratek facility to Envirocare using 10 shipments. Those 10 shipments included waste from other generators.

SCEs waste volume was a small fraction of the total waste volume of these shipments.

    • SONGS maintains a contract with Studsvik that provides volume reduction services. The processed volume was shipped from the Studsvik facility to Barnwell using 1 shipment. The shipment included waste from other generators.

SCEs waste volume was a small fraction of the total waste volume of these shipments. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION E. RADWASTE SHIPMENTS TABLE 3 (Units 2 & 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 3.15E+0 Ci 9.66E+2 3.00E+1
b. Dry active waste (DAW), compactable m3 3.39E+2 and non-compactable
  • Ci 2.48E+0 3.00E+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.

The spent resin containers were packaged in high integrity containers and shipped in Type A and Type B casks. N/A No shipment made. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION

2. Estimate of Major Nuclide Composition (spent resins, filter sludges)
a. americium-241  % 1.50E-4 antimony-125  % 4.66E-2 carbon-14  % 3.13E-1 cerium-144  % 7.69E-3 cesium-134  % 1.52E+0 cesium-137  % 5.51E+0 cobalt-57  % 6.44E-2 cobalt-58  % 3.93E+0 cobalt-60  % 4.14E+0 curium-243/244  % 1.00E-4 iron-55  % 1.87E+1 manganese-54  % 1.11E+0 nickel-59  % 2.37E-1 nickel-63  % 6.44E+1 niobium-95  % 3.10E-4 plutonium-238  % 5.89E-5 plutonium-239/240  % 5.66E-5 plutonium-241  % 3.46E-3 strontium-89  % 1.51E-3 strontium-90  % 3.16E-2 technetium-99  % 9.79E-3 tritium  % 1.74E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION
2. Estimate of Major Nuclide Composition (DAW)
b. americium-241  % 1.98E-3 antimony-124  % 1.07E-3 antimony-125  % 3.61E-1 carbon-14  % 7.49E-1 cerium-144  % 2.72E-1 cesium-134  % 1.65E+0 cesium-137  % 6.84E+0 chromium-51  % 7.76E-1 cobalt-57  % 8.25E-2 cobalt-58  % 6.55E+0 cobalt-60  % 5.77E+0 curium-242  % 4.39E-6 curium-243/44  % 6.66E-5 iodine-129  % 3.25E-3 iron-55  % 2.14E+1 iron-59  % 2.49E-1 manganese-54  % 1.25E+0 nickel-59  % 1.40E-1 nickel-63  % 5.32E+1 niobium-95  % 2.20E-1 plutonium-238  % 1.31E-3 plutonium-239/40  % 1.78E-3 plutonium-241  % 2.23E-3 strontium-89  % 2.57E-3 strontium-90  % 3.75E-2 technetium-99  % 3.28E-1 tritium  % 1.36E-2 zirconium-95  % 1.08E-1
c. not applicable  % N/A
d. not applicable  % N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Hittman Transport 7 EnergySolutions, UT Truck/Flatbed Trailer/Highway Hittman Transport EnergySolutions (Duratek), TN/

18

  • Truck/Flatbed Trailer/Highway EnergySolutions, UT Hittman Transport Studsvik/EnergySolutions, UT 4* Truck/Flatbed Trailer/Highway and Barnwell, SC (Type A Cask)

Hittman Transport Studsvik/EnergySolutions, UT 1* Truck/Flatbed Trailer/Highway and Barnwell, SC (Type B Cask)

  • SONGS 2/3 maintains contracts with vendors Studsvik and EnergySolutions (Duratek), that provide volume reduction services. The processed volume was shipped from the vendors facility to EnergySolutions in Clive, UT and Barnwell, South Carolina using 43 shipments. Those 43 shipments included waste from other generators. SCEs waste volume was a fraction of the total waste volume of these shipments.

B. IRRADIATED FUEL SHIPMENTS (Disposition) Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION E. RADWASTE SHIPMENTS TABLE 3 (Decommissioned Unit 1) 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 7.98E+3 compactable and non-compactable*:

Ci 1.04E+1 3.00E+1

c. Irradiated components: m3 N/A Ci N/A N/A
d. Other: m3 N/A Ci N/A N/A NOTE: Total curie content estimated.
  • Material packaged in various General Design, IP-1 and IP-2.

N/A No shipment made. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION Estimate of Major Nuclide Composition (DAW)

a. not applicable  % N/A
b. americium-241  % 5.96E-2 carbon-14  % 9.39E-1 cerium-144  % 6.16E-4 cesium-134  % 5.76E-1 cesium-137  % 4.86E+1 cobalt-60  % 7.85E+0 curium-242  % 5.29E-9 curium-243/44  % 1.16E-2 iron-55  % 2.36E+0 nickel-63  % 3.84E+1 plutonium-238  % 3.64E-2 plutonium-239/40  % 1.77E-2 plutonium-241  % 7.57E-1 silver-110m  % 5.78E-4 strontium-90  % 1.72E-1 tritium  % 2.29E-1
c. not applicable  % N/A
d. not applicable  % N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 309 BNSF Railroad/UP Railroad EnergySolutions, UT Piazza Trucking 4 EnergySolutions, UT Truck/Flatbed Trailer/Highway Hittman Transport 3 EnergySolutions, UT Truck/Flatbed Trailer/Highway Hittman Transport 2* EnergySolutions(Duratek), TN Truck/Flatbed Trailer/Highway
  • SONGS 1 maintains a contract with EnergySolutions (Duratek), that provides volume reduction services. The processed volume was shipped from the vendors facility to EnergySolutions in Clive, UT using 2 shipments. Those 2 shipments included waste from other generators. SCEs waste volume was a fraction of the total waste volume of these shipments.

B. IRRADIATED FUEL SHIPMENTS (Disposition) Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent None N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION COMMON RADWASTE SHIPMENTS TABLE 3 (COMMON) 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 sludges, m3 N/A 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
d. not applicable  % N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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/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, µCi/sec. X/Q = 4.80E-6 sec/m3; the annual average atmospheric dispersion defined in the ODCM.

  • MPCeff =

where: Fi = fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT. n = total number of radionuclides identified MPCi = 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, µCi/sec. X/Q = 4.80E-6 sec/m3; the annual average atmospheric dispersion defined in the ODCM.

  • ECLeff =

where: Fi = fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT. n = total number of radionuclides identified ECLi = 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 - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS (Continued) Liquid Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations:

  • % Applicable Limit = (Dil Conc) (100)

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

  • MPCeff =

where: Fi = fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT. n = total number of radionuclides identified MPCi = 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, µCi/ml.

  • ECLeff =

where: Fi = fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT. n = total number of radionuclides identified ECLi = 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 - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 2.00E-4 µCi/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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 = where: i = Error associated with each component. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual. Six different categories are presented: (1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; these data are also presented in Table 2D. Categories 3, 4, and 5 were calculated utilizing 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 boundary1, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. For members of the public who traverse the site boundary via highway I-5, the residency time shall be considered negligible and hence the dose "0". Table 2 in Section H presents the percent of Applicable Limits for each dose presented in Table 1. 1 ODCM Figures 1-2 & 2-2. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1 Dose * (millirems) First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS 1) 2) 3) 4) 5) Whole Body 4.06E-4 5.74E-4 1.11E-3 5.26E-4 2.61E-3

6) 7) 8) 9) 10)

Organ 2.94E-3 3.11E-3 3.59E-3 1.60E-3 1.12E-2 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15) Tritium, Iodines, and 5.39E-3 5.32E-3 5.66E-3 1.54E-2 3.18E-2 Particulates NOBLE GASES ** 16) 17) 18) 19) 20) Gamma 6.72E-3 1.25E-2 2.37E-3 1.67E-2 3.82E-2

21) 22) 23) 24) 25)

Beta 1.39E-2 8.23E-3 4.94E-3 2.60E-2 5.31E-2

26) 27) 28) 29) 30)

DIRECT RADIATION 1.38E-1 1.43E-1 1.11E-1 9.77E-2 4.26E-1

  • The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).
    • Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose.
1. This value was calculated using the methodology of the ODCM.
2. This value was calculated using the methodology of the ODCM.
3. This value was calculated using the methodology of the ODCM.
4. This value was calculated using the methodology of the ODCM.
5. This value was calculated using the methodology of the ODCM.
6. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.
7. This value was calculated using the methodology of the ODCM; the GI-LLI received the maximum dose primarily by the saltwater fish pathway.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION

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 childs liver and was located in the NNW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
12. The maximum organ dose was to a childs thyroid and was located in the NNW sector This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
13. The maximum organ dose was to a childs thyroid and was located in the NNW sector This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
14. The maximum organ dose was to a childs thyroid and was located in the NNW sector. This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
15. The maximum organ dose was to a childs thyroid and was located in the NNW sector This was calculated using the assumptions of USNRC Regulatory Guide 1.109.
16. The maximum air dose for gamma radiation was located in the 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 1.109.
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.
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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION

26. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the WSW sector.
27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the WSW sector.
28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the S sector.
29. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the S sector.
30. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours per year; highest dose was measured at the Site Boundary in the WSW sector.

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 1.35E-2 1.91E-2 3.69E-2 1.75E-2 4.36E-2 Organ 2.94E-2 3.11E-2 3.59E-2 1.60E-2 5.62E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and 3.59E-2 3.54E-2 3.77E-2 1.03E-1 1.06E-1 Particulates NOBLE GASES Gamma 6.72E-2 1.25E-1 2.37E-2 1.67E-1 1.91E-1 Beta 6.94E-2 4.11E-2 2.47E-2 1.30E-1 1.33E-1 NOTE: Direct Radiation is not specifically addressed in the Applicable Limits. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 29, 2008, revision 1 to the SONGS Offsite Dose Calculation Manual (ODCM) was issued. This revision accomplishes three objectives: 1) Incorporates the latest updates related to the 2006-2007 Land Use Census (LUC) from the J.W. Scott to D. Dick Memorandum for File, 2008 Dose Parameters for SONGS, dated February 11, 2008, 2) Creates Appendix B to incorporate historical references for the effluent control program and 3) Changes page numbers in Appendices to identify the Appendix number. Editorial corrections were made to Figure 4-5 to correct a release pathway unintentionally omitted from the figure. Added pg vi in the Table of Contents for SO123-ODCM to identify the two ODCM appendices. No 50.59 or effluent ODCM evaluation reviews were required or performed for editorial changes. None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10 CFR 20, 40 CFR 190, 10 CFR 50.35a and Appendix I to 10 CFR 50 will be maintained. Throughout the document, change bars are marked in one of four ways as follows: A Addition D Deletion F Editorial/Format change R Revision Page # Change Reason vi Added pg vi in Table of Contents to include a List of Appendices. A 2-29 Revised table 2-6 per LUC R 4-20 corrected to include a release pathway unintentionally removed in prior revision F Appendix A- ALL renumbered the page to include Appendix identification i.e. 1-1 to A1-1. F Appendix Ai- table edited to include page identifier for Table of Contents for Appendix A, Changed R of contents page numbers and reformatted A1-8 Revised Ri values per LUC R A1-10 Revised Ri values per LUC, edited page 1 of 2 to page 1 of 3 per LUC R/F A1-11 Changed from pg 2 of 2 to page 2 of 3 per LUC F A1-12 Added new pathway, page 3 of 3 per LUC A A1-13 Revised Ri values per LUC R A1-14 Revised Ri values per LUC R A1-15 Revised Ri values per LUC R A1-17 Revised Ri values per LUC R A1-19 Revised Ri values per LUC R A1-22 Changed from page 1 of 2 to page 1 of 3 per LUC F A1-23 Added new pathway, page 2 of 3 per LUC A A1-24 Changed from page 2 of 2 to page 3 of 3 per LUC F Appendix B Added Appendix B so as to include supplemental information on the effluent A control program (historical references) ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS None. SECTION K. MISCELLANEOUS Abnormal Releases

  • North Industrial Area (NIA) Main Firewater Break A pressurized in-service fire main was inadvertently broken on 08/08/2008, during excavation of an abandoned catch basin in the North Industrial Area (NIA) yard. The water flowed across the yard into the sewage treatment plant (STP) south train settling tanks, which were not in use at the time. When the tanks overflowed into the sump, the sewage treatment sump pumps turned on automatically for approximately 1 hour. The resultant unplanned, unmonitored release was estimated to be a total of 24,000 gallons, based on the pumps' discharge rate. The water that remained in the south settling tanks was subsequently sampled and the results were <LLD for gamma activity and tritium.

However, sample results for the sand that had been excavated from the catch basin indicated the presence of Cs-137 between 3.228E-7 µCi/g and 3.187E-6 µCi/g. Approximately 1.4 yds3 of sand was estimated to be entrained in the 24,000 gallons of water that was released. The maximum whole body dose of 2.38 E-7 mrem and an organ dose of 7.04 E-9 mrem that could have been received by a member of the public due to this event. This event is documented in NN 200092767. Missed Surveillances

  • Missed 2RT7817 18 Month Surveillance On 10/09/2008, it was discovered that the 18 month surveillance for 2RT-7817, which monitors the full flow condensate polisher effluent line, required by section 4.1.1b in the ODCM was not completed by its due date of 4/22/2008. Prior to the required surveillance, the work order was sent back to planning to change the work window, but the order was never revised and reissued, resulting in the missed surveillance. The compensatory action for an inoperable 2RT-7817 is a 1/24 hr grab sample during the release if the reactor coolant specific activity is <0.01

µCi/gm. The unit 2 reactor coolant specific activity was <0.01 µCi/gm from 04/22/08 to 10/10/08. The longest release through the condensate polisher deminearalizer effluent line from 04/22/2008 to 10/09/2008 occurred on 07/01/2008, was 2 hrs and 55 minutes long. As required by the effluent control program, grab samples were taken prior to each release and a release permit was generated based on the sample. The 2RT-7817 surveillance was successfully completed on its next scheduled surveillance on 10/22/2008. The dose consequences to a member of the public from releases via this pathway are included in this report; no additional dose consequences resulted from the missed surveillance. This event is documented in NN 200173009.

  • Missed 2/3RT2101 Surveillance On 10/22/2008, the North Industrial Area (NIA) sump pumps were placed in service (automatic) after it had been removed from service for maintenance activities. Operations and chemistry failed to effectively communicate the status and requirements necessary to return the NIA sump to service, thus compensatory sampling was not initiated until 10/26/2008. As soon as chemistry realized that the NIA sump pumps were in automatic but the radiation monitor was not in service, a grab sample was taken and analyzed and compensatory sampling was initiated. The plant computer system (PCS) indicated the sump pumps ran on two separate occasions during 10/22/08 and 10/26/2008.

An estimated total volume of 4557 gallons was released from the NIA sump. The PCS did not record any influents into the NIA sump. The samples taken before and after the event were <LLD for gamma and tritium. There was no dose consequence to a member of the public due to this event. This event is documented in NN 200192238. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2008 - December 31, 2008 S.O.N.G.S. 2 Inoperability Monitor Period Inoperability Cause Explanation 2RT-7870 04/17/00 - Inoperable process Design deficiency causes process flow instrument Condenser Air present flow measuring to be inoperable while the vacuum pump is Ejector Process device whenever running, as high flow values are not sensed. Flow Flow Monitor vacuum pump is monitor works properly during normal operations. running. The monitor is isokinetic during the vacuum pump operation due to the substitute flow value that is manually inserted whenever the vacuum pump is running. The issue was previously documented in ARs 000101252 and 000400960. It is currently being tracked in NN200001437. 2RT-6753 and 11/21/07 - Outage Activities The radiation monitors are declared inoperable by 2RT-6759 01/15/08 Operations when the monitors alarm and Steam Generator automatic functions are bypassed to support Blowdown outage activities. The radiation monitors did not Radiation malfunction, nor degrade and were placed back Monitors in service when the pathway was put back to a normal operating alignment. 2RT-7817 03/04/08 - No flow indication Monitor power supply failed. Removed defective BPS/FFCPD 04/18/08 during a HUT release power supply and installed a new power supply. Discharge to outfall. This event is documented in AR 080300101. Monitor 2RT-7865 12/17/07 - Intermittent heat Design deficiency due to heat trace being Plant Vent Stack 03/10/08 trace circuitry inadequately designed to maintain the (Containment operability temperature above the specified analysis limit for Purge) the full temperature-humidity range experienced Particulate and at SONGS. The event was summarized and Iodine Sampler documented in NN 200330946. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS (Continued) January 1, 2008 - December 31, 2008 S.O.N.G.S. 3 Inoperability Monitor Period Inoperability Cause Explanation 3RT-7870 04/17/00 - Inoperable process Design deficiency causes process flow instrument Condenser Air present flow measuring to be inoperable while the vacuum pump is Ejector Process device whenever running, as high flow values are not sensed. Flow Flow Monitor vacuum pump is monitor works properly during normal operations. running. The monitor is isokinetic during the vacuum pump operation due to the substitute flow value that is manually inserted whenever the vacuum pump is running. The issue was previously documented in ARs 000101252and 000400960. It is currently tracked in NN 200001437. 3RT-7817 03/04/08 - High Radiation Alarm The instrument was spiking when no release was BPS/FFCPD 04/10/08 and Erratic behavior in progress. No cause was determined during the Discharge investigation. The radiation monitor appeared to Monitor be working correctly after the power was cycled and the monitor was re-booted. The issue is summarized and evaluated in AR 080300142. 3RT-7817 09/24/08 - Damaged Power While completing an 18 month surveillance, the BPS/FFCPD 11/28/08 Supply battery and power supply were running very hot Discharge and damage to a connector to the power was Monitor observed. Replaced the LDU power supply and the damaged connector. Flow Switch Failure After the repairs to the power supply were completed, the monitor flow switch (FISL7817) failed to function as designed. The flow switch was replaced. The event is summarized and evaluated in NN200163311 and NN200172869. 3RT-6753 and 10/09/08 - Outage Activities The radiation monitors are declared inoperable by 3RT-6759 12/10/08 Operations when the monitors alarm and Steam Generator automatic functions are bypassed to support Blowdown outage activities. The radiation monitors did not Radiation malfunction, and were placed back in service Monitors when the pathway was put back to a normal operating alignment. 3RT-7865 11/30/07 - Intermittent heat Design deficiency due to heat trace being Plant Vent Stack 01/22/08 trace circuitry inadequately designed to maintain the (Containment operability temperature above the specified analysis limit for Purge) the full temperature-humidity range experienced Particulate and at SONGS. The event was summarized and Iodine Sampler documented in NN 200330946. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS (Continued) January 1, 2008 - December 31, 2008 S.O.N.G.S. 2/3 Inoperability Monitor Period Inoperability Cause Explanation 2/3RT-7808 05/19/08 - Low Flow Alarm The fittings to the radiation monitor flow transmitter Plant Vent Stack 06/23/08 were galled and were unable to be used to perform Monitor the instrument calibration. The fittings for the high and low flow switches were replaced so that the calibration could be performed. This issue was identified and documented in AR 080500900. 2/3RT-2101 05/05/08 - Failed Surveillance The flow totalizer failed the 18 month surveillance NIA Sump 09/10/08 but the radiation monitor remained available to Radiation Monitor alarm on high radiation signal. Replaced software and flow transducers. These issues were identified and documented in AR 080500410 and Order 800047842. 2/3RT-2101 10/01/08 - High Temperature Monitor failure due to high temperature fault. Low NIA Sump 01/23/09 Alarm work priority delayed testing to determine the Radiation Monitor cause. No degraded, nonconforming, or unanalyzed condition was identified. The monitor was reset and placed back in service. The issue was identified and documented in NN 200163285. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION Onsite Groundwater Samples This section provides results of on-site samples of groundwater in accordance with the voluntary Nuclear Energy Institute (NEI) Groundwater Protection Initiative. The sample locations and the frequency of sampling are likely to change as Unit 1 decommissioning proceeds. For those few sample data that are not below the lower limit of detection, 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 boundary. January 1, 2008 - December 31, 2008 Sample Date Location Tritium Activity, µCi/ml Gamma Activity, µCi/ml 01/02/2008 U1 DW 6 <LLD <LLD U1 DW 11 <LLD <LLD U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD 01/06/2008 U1 DW 11 <LLD <LLD U1 DW 12 <LLD <LLD 01/09/2008 U1 DW 6 <LLD <LLD U1 DW 11 <LLD <LLD U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD 01/16/2008 U1 DW 6 <LLD <LLD U1 DW 11 <LLD <LLD U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD 01/23/2008 U1 DW 6 <LLD <LLD 01/30/2008 U1 DW 6 <LLD <LLD 02/14/2008 U1 DW 6 <LLD <LLD U1 DW 11 <LLD <LLD U1 DW 13 <LLD <LLD 03/14/2008 U1 DW 6 <LLD <LLD U1 DW 11 <LLD <LLD U1 DW 13 <LLD <LLD 04/14/2008 U1 DW 6 <LLD <LLD U1 DW 11 <LLD <LLD U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD 05/15/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD 05/16/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD 05/17/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD 05/18/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION Onsite Groundwater Samples (Continued) January 1, 2008 - December 31, 2008 Sample Date Location Tritium Activity, µCi/ml Gamma Activity, µCi/ml 05/19/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD 06/04/2008 U1 DW 12 <LLD <LLD 06/05/2008 U1 DW 12 <LLD <LLD 06/07/2008 U1 DW 12 <LLD <LLD 06/08/2008 U1 DW 12 <LLD <LLD 06/09/2008 U1 DW 12 <LLD <LLD 06/10/2008 U1 DW 12 <LLD <LLD 06/12/2008 U1 DW 12 <LLD <LLD 06/13/2008 U1 DW 12 <LLD <LLD 07/09/2008 U1 DW 14 <LLD <LLD 07/10/2008 U1 DW 14 <LLD <LLD 07/11/2008 U1 DW 14 <LLD <LLD 07/13/2008 U1 DW 14 <LLD <LLD 07/14/2008 U1 DW 14 <LLD <LLD 08/15/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 08/22/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 08/23/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 08/24/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 08/25/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD U1 DW 15 <LLD <LLD 08/26/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 08/27/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION Onsite Groundwater Samples (Continued) January 1, 2008 - December 31, 2008 Sample Date Location Tritium Activity, µCi/ml Gamma Activity, µCi/ml 08/28/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 08/29/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 08/30/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 09/04/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD 09/05/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD U1 DW 15 <LLD <LLD 09/06/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD U1 DW 15 <LLD <LLD 09/07/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD U1 DW 15 <LLD <LLD 09/08/2008 U1 DW 12 <LLD <LLD U1 DW 13 <LLD <LLD U1 DW 14 <LLD <LLD U1 DW 15 <LLD <LLD 09/15/2008 U1 DW 15 <LLD <LLD U1 DW = Wells installed to support decommissioning of Unit 1. The locations of these wells will change as decommissioning proceeds. a priori LLDs = H-3: 1.0 E-5 µCi/ml, Cs-137: 6.8 E-8 µCi/ml ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION Onsite Groundwater Samples (Continued) This section provides results of on-site samples of groundwater in accordance with the voluntary Nuclear Energy Institute (NEI) Groundwater Protection Initiative. The sample locations and the frequency of sampling may change as Protection Initiative over time. For those few sample data that are not below the lower limit of detection, 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 boundary. January 1, 2008 - December 31, 2008 Sample Date Location Tritium Activity, µCi/ml Gamma Activity, µCi/ml 01/03/2008 SONGS PA 2 1.60E-6 <LLD 01/11/2008 SONGS PA 2 1.28E-6 <LLD 01/18/2008 SONGS PA 2 1.52E-6 <LLD 01/25/2008 SONGS PA 2 1.22E-6 <LLD 02/14/2008 SONGS PA 1 <LLD <LLD SONGS PA 4 <LLD <LLD 02/21/2008 SONGS PA 3 <LLD <LLD SONGS PA 2 1.81 E-6 <LLD 03/21/2008 SONGS OCA 1 <LLD <LLD 03/25/2008 SONGS OCA 2 <LLD <LLD 03/26/2008 SONGS PA 2 1.14E-6 <LLD 03/27/2008 SONGS OCA 3 <LLD <LLD 04/25/2008 SONGS PA 2 6.50E-7 <LLD 05/29/2008 SONGS PA 2 <LLD <LLD 06/11/2008 SONGS PA 1 <LLD <LLD SONGS PA 4 <LLD <LLD 06/13/2008 SONGS PA 2 5.30E-7 <LLD SONGS PA 3 <LLD <LLD 06/27/2008 SONGS OCA 1 <LLD <LLD SONGS OCA 2 <LLD <LLD SONGS OCA 3 <LLD <LLD 07/17/2008 SONGS PA 2 <LLD <LLD 09/22/2008 SONGS OCA 2 <LLD <LLD 09/24/2008 SONGS OCA 1 <LLD <LLD SONGS OCA 3 <LLD <LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION Onsite Groundwater Samples (Continued) January 1, 2008 - December 31, 2008 Sample Date Location Tritium Activity, µCi/ml Gamma Activity, µCi/ml 9/26/2008 SONGS PA 1 <LLD <LLD SONGS PA 2 2.96E-7 <LLD SONGS PA 3 <LLD <LLD SONGS PA 4 <LLD <LLD 12/29/2008 SONGS OCA 3 <LLD <LLD 12/30/2008 SONGS PA 1 <LLD <LLD SONGS PA 2 <LLD <LLD SONGS PA 3 <LLD <LLD SONGS PA 4 <LLD <LLD 12/31/2008 SONGS OCA 1 <LLD <LLD SONGS OCA 2 <LLD <LLD SONGS PA = Wells installed in the Protected Area to implement the Groundwater Protection Initiative. SONGS OCA = Wells installed in the Owner Controlled Area to implement the Groundwater Protection Initiative. a priori LLDs = H-3: 3.0E-6 µCi/ml, Cs-137: 1.8 E-8 µCi/ml ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION 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 4.72E-1
b. Percent ODCM Specification Limit  % 1.89E+0
2. Limiting Organ
a. Organ Dose (GI-LLI) mrem 6.43E-2
b. Percent ODCM Specification Limit  % 2.57E-1
3. Thyroid
a. Thyroid Dose mrem 5.49E-2
b. Percent ODCM Specification Limit  % 7.32E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 SAN ONOFRE NUCLEAR GENERATING STATION SECTION L. S.O.N.G.S. CONCLUSIONS
  • Gaseous releases totaled 1.62E+2 curies of which noble gases were 8.07E+1 curies, iodines were 2.04E-3 curies, particulates were 1.70E-3 curies, and tritium was 8.09E+1 curies.
  • The radiation doses from gaseous releases were: (a) gamma air dose: 3.82E-2 mrad at the site boundary, (b) beta air dose: 5.31E-2 mrad at the site boundary, (c) organ dose: 3.18E-2 mrem at the nearest receptor.
  • Liquid releases totaled 1.04+3 curies of which particulates and iodines were 4.00E-2 curies, tritium was 1.04E+3 curies, and noble gases were 3.90E+0 curies.
  • The radiation doses from liquid releases were: (a) total body: 2.61E-3 mrem, (b) limiting organ:

1.12E-2 mrem.

  • Radioactive releases and resulting doses generated from S.O.N.G.S. 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, Studsvik, TN, Duratek/EnergySolutions, TN, and Barnwell, SC. The total volume of the 348 shipments was 8.32E+3 cubic meters containing 9.79E+2 curies of radioactivity.
  • Meteorological conditions during the year were typical for S.O.N.G.S. Meteorological dispersion was good 33% of the time, fair 40% of the time and poor 27% of the time.
  • The total volume of releases from groundwater and dewatering wells was 2.86E+8 gallons. The largest volume was from the dewatering wells at Unit 1, but also included water from the development of the Industry Groundwater Protection Initiative-related wells in the Owner Controlled Area and the Protected Area at SONGS. The output from groundwater and dewatering wells was released through ODCM credited release points and radioactivity included in the earlier tables of this report. The results of samples taken from these on-site wells are reported in Section K.
  • The net result from the analysis of these effluent releases indicates that the operation of S.O.N.G.S. has met all the requirements of the applicable regulations that ensure adequate protection of the health of members of the public.

METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2008 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, 2008. 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 - 2008 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 08010100-08033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ -1.9 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 2 0 0 0 0 0 0 0 2 NNE 0 0 1 1 0 0 0 0 0 0 0 0 2 NE 0 0 0 0 0 1 0 0 0 0 0 0 1 ENE 0 0 0 0 1 0 0 0 0 0 0 0 1 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 1 0 0 0 0 0 0 0 1 SSE 0 0 0 0 1 2 14 2 0 0 0 0 19 S 0 0 0 3 6 15 16 1 0 0 0 0 41 SSW 0 0 0 8 6 17 13 1 0 0 0 0 45 SW 0 0 1 3 5 16 11 2 0 0 0 0 38 WSW 1 0 0 7 10 23 10 0 0 0 0 0 51 W 0 0 0 2 6 37 33 2 0 0 0 0 80 WNW 0 0 0 3 4 27 33 4 0 0 0 0 71 NW 0 0 0 0 0 4 4 0 1 0 0 0 9 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 1 0 2 27 42 143 134 12 1 0 0 0 362 NUMBER OF VALID HOURS 362 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 362 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 1 0 0 0 0 0 0 0 0 0 0 0 1 NNE 0 0 0 0 1 0 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 1 0 0 0 0 0 1 ENE 1 0 0 0 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 0 1 0 0 0 0 0 0 0 1 SE 0 0 0 2 0 1 4 0 0 0 0 0 7 SSE 0 0 0 0 2 1 6 2 1 0 0 0 12 S 0 0 0 1 1 0 2 2 1 0 0 0 7 SSW 0 0 0 1 1 4 0 1 0 0 0 0 7 SW 0 0 0 0 1 1 0 0 0 0 0 0 2 WSW 1 0 1 2 2 1 0 0 0 0 0 0 7 W 0 0 0 1 4 1 2 0 0 0 0 0 8 WNW 0 0 0 0 1 0 0 0 0 0 0 0 1 NW 0 0 0 0 0 1 1 1 0 0 0 0 3 NNW 1 0 0 0 0 0 0 0 0 0 0 0 1 TOTALS 4 0 1 7 14 10 16 6 2 0 0 0 60 NUMBER OF VALID HOURS 60 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 60 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 08010100-08033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ -1.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 1 0 0 1 0 0 0 0 0 0 0 0 2 NNE 1 0 0 0 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 1 0 0 0 1 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 2 0 1 0 0 0 3 SSE 0 0 0 0 2 2 5 4 0 0 0 0 13 S 0 0 0 3 1 0 4 1 0 0 0 0 9 SSW 0 0 0 0 4 2 0 0 0 0 0 0 6 SW 0 0 0 0 4 2 2 1 0 0 0 0 9 WSW 2 0 0 0 8 6 1 1 0 0 0 0 18 W 0 0 1 0 5 2 0 0 0 0 0 0 8 WNW 0 0 0 0 1 6 0 0 1 0 0 0 8 NW 0 0 0 0 0 1 0 0 0 0 0 0 1 NNW 0 0 0 0 0 1 0 0 0 0 0 0 1 TOTALS 4 0 1 4 25 22 14 8 3 0 0 0 81 NUMBER OF VALID HOURS 81 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 81 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 3 1 0 2 5 0 0 0 0 0 12 NNE 0 1 0 1 3 8 9 1 0 0 0 0 23 NE 0 0 0 1 0 4 4 0 2 0 0 0 11 ENE 0 0 0 1 0 1 1 0 0 1 0 0 4 E 0 0 0 0 0 1 3 1 0 0 0 0 5 ESE 0 0 0 1 1 1 14 1 0 0 0 0 18 SE 0 0 0 1 1 4 27 14 15 0 0 0 62 SSE 0 0 0 2 1 14 19 4 6 4 2 0 52 S 0 0 0 1 4 8 12 8 2 3 0 0 38 SSW 0 0 0 1 2 7 8 6 4 2 0 0 30 SW 0 0 1 3 3 2 11 9 4 1 0 0 34 WSW 0 0 1 1 3 13 10 14 1 0 0 0 43 W 0 0 0 4 8 13 8 5 4 0 0 0 42 WNW 0 0 1 6 8 12 5 2 1 0 0 0 35 NW 0 0 1 6 1 12 7 1 0 0 0 0 28 NNW 0 0 1 1 2 5 2 0 0 0 0 0 11 TOTALS 0 2 8 31 37 107 145 66 39 11 2 0 448 NUMBER OF VALID HOURS 448 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 448 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 08010100-08033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ 1.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 2 6 4 6 5 0 0 0 0 0 24 NNE 0 0 1 5 12 14 25 0 0 0 0 0 57 NE 0 0 0 3 3 1 6 0 1 0 0 0 14 ENE 0 0 0 2 0 4 1 1 0 0 0 0 8 E 0 0 1 1 3 3 2 0 0 0 0 0 10 ESE 0 0 1 2 2 8 8 5 1 0 0 0 27 SE 0 0 0 1 3 11 23 18 11 1 0 0 68 SSE 0 0 2 2 2 6 6 7 1 3 1 0 30 S 0 1 2 3 4 1 8 5 3 1 1 0 29 SSW 0 1 1 5 6 3 2 1 1 0 0 0 20 SW 0 0 0 1 1 3 1 1 0 1 0 0 8 WSW 0 1 0 4 5 0 0 4 3 0 0 0 17 W 0 1 2 3 2 5 2 3 4 0 0 0 22 WNW 0 0 0 8 3 9 2 3 4 0 0 0 29 NW 0 1 3 4 2 7 4 0 0 0 0 0 21 NNW 0 1 2 3 4 5 1 1 0 0 0 0 17 TOTALS 0 7 17 53 56 86 96 49 29 6 2 0 401 NUMBER OF VALID HOURS 401 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 401 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 3 1 4 0 0 0 0 0 0 8 NNE 0 0 3 11 20 28 10 0 1 0 0 0 73 NE 3 0 4 14 12 9 0 3 0 0 0 0 45 ENE 0 0 1 7 4 2 1 0 0 0 0 0 15 E 0 0 1 5 6 3 0 0 0 0 0 0 15 ESE 0 0 1 4 3 2 1 0 0 0 0 0 11 SE 0 0 0 1 1 1 0 0 0 0 0 0 3 SSE 0 0 0 2 4 1 1 0 0 0 0 0 8 S 0 0 0 0 3 0 0 0 0 0 0 0 3 SSW 0 0 1 0 1 0 0 0 0 0 0 0 2 SW 0 0 2 5 1 3 0 0 0 0 0 0 11 WSW 1 0 1 2 6 0 0 0 0 0 0 0 10 W 0 2 1 4 5 1 0 0 0 0 0 0 13 WNW 0 0 2 6 1 4 0 0 0 0 0 0 13 NW 0 0 1 2 5 1 0 0 0 0 0 0 9 NNW 1 0 1 3 5 3 0 0 0 0 0 0 13 TOTALS 5 2 19 69 78 62 13 3 1 0 0 0 252 NUMBER OF VALID HOURS 252 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 252 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 08010100-08033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 6 0 2 6 4 10 2 0 0 0 0 0 30 NNE 7 0 1 6 31 138 144 10 0 0 0 0 337 NE 1 0 1 12 21 36 5 1 0 0 0 0 77 ENE 0 1 4 6 6 6 3 0 0 0 0 0 26 E 0 0 1 2 3 5 1 0 0 0 0 0 12 ESE 0 1 2 4 1 2 2 0 0 0 0 0 12 SE 0 0 0 3 3 4 1 0 0 0 0 0 11 SSE 0 0 0 3 0 1 0 0 0 0 0 0 4 S 0 0 0 3 3 1 1 0 0 0 0 0 8 SSW 0 1 0 0 1 1 0 0 0 0 0 0 3 SW 0 0 0 4 2 0 0 0 0 0 0 0 6 WSW 1 0 2 2 3 2 0 0 0 0 0 0 10 W 3 0 1 2 4 1 0 0 0 0 0 0 11 WNW 0 0 0 3 3 5 0 0 0 0 0 0 11 NW 0 1 0 2 2 3 1 0 0 0 0 0 9 NNW 3 0 0 2 2 5 0 1 0 0 0 0 13 TOTALS 21 4 14 60 89 220 160 12 0 0 0 0 580 NUMBER OF VALID HOURS 580 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 580 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 8 2 7 17 11 22 12 0 0 0 0 0 79 NNE 8 1 6 24 67 188 188 12 1 0 0 0 495 NE 4 0 5 30 36 51 16 4 3 0 0 0 149 ENE 1 1 5 16 11 13 6 1 1 1 0 0 56 E 0 0 3 8 12 13 6 1 0 0 0 0 43 ESE 0 1 4 11 8 13 25 6 1 0 0 0 69 SE 0 0 0 8 9 21 57 32 27 1 0 0 155 SSE 0 0 2 9 12 27 51 19 8 7 3 0 138 S 0 1 2 14 22 25 43 17 6 4 1 0 135 SSW 0 2 2 15 21 34 23 9 5 2 0 0 113 SW 0 0 4 16 17 27 25 13 4 2 0 0 108 WSW 6 1 5 18 37 45 21 19 4 0 0 0 156 W 3 3 5 16 34 60 45 10 8 0 0 0 184 WNW 0 0 3 26 21 63 40 9 6 0 0 0 168 NW 0 2 5 14 10 29 17 2 1 0 0 0 80 NNW 5 1 4 9 13 19 3 2 0 0 0 0 56 TOTALS 35 15 62 251 341 650 578 156 75 17 4 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 - 2008 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08040100-08063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ -1.9 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 1 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 0 0 0 0 0 1 SSE 0 0 0 0 1 6 11 3 4 0 0 0 25 S 0 0 0 0 2 10 36 14 7 0 0 0 69 SSW 0 0 0 1 1 21 54 10 0 1 0 0 88 SW 0 0 0 2 14 44 57 6 0 0 0 0 123 WSW 0 0 0 2 17 54 99 2 0 0 0 0 174 W 0 0 0 1 3 57 101 0 0 0 0 0 162 WNW 0 0 0 1 2 20 93 2 0 0 0 0 118 NW 0 0 0 0 0 3 14 6 0 0 0 0 23 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 7 40 215 466 44 11 1 0 0 784 NUMBER OF VALID HOURS 784 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 784 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 1 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 0 0 0 0 0 1 SSE 0 0 0 1 0 1 3 0 0 0 0 0 5 S 0 0 0 0 0 3 3 2 0 1 0 0 9 SSW 0 0 0 0 1 5 7 0 2 0 0 0 15 SW 0 0 1 0 0 3 2 1 1 0 0 0 8 WSW 0 0 0 0 1 0 0 0 0 0 0 0 1 W 0 0 0 1 2 0 1 0 0 0 0 0 4 WNW 0 0 0 0 1 3 4 0 0 0 0 0 8 NW 0 0 0 0 0 4 7 0 0 0 0 0 11 NNW 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTALS 0 0 1 2 5 19 29 4 3 1 0 0 64 NUMBER OF VALID HOURS 64 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 64 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08040100-08063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ -1.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 1 0 1 0 0 0 0 0 0 2 NNE 0 0 0 0 1 0 0 0 0 0 0 0 1 NE 0 0 0 2 0 2 0 0 0 0 0 0 4 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 1 0 0 0 0 0 0 1 SSE 0 0 0 2 0 1 11 2 2 0 0 0 18 S 0 0 0 0 0 2 5 2 3 2 0 0 14 SSW 0 0 0 0 1 5 6 1 0 0 0 0 13 SW 0 0 0 0 1 5 3 0 0 0 0 0 9 WSW 0 0 0 0 1 1 0 0 0 0 0 0 2 W 0 0 0 1 1 3 0 0 0 0 0 0 5 WNW 0 0 0 1 3 1 1 0 0 0 0 0 6 NW 0 0 0 0 3 4 9 0 0 0 0 0 16 NNW 0 0 0 0 1 1 0 0 0 0 0 0 2 TOTALS 0 0 0 7 12 27 35 5 5 2 0 0 93 NUMBER OF VALID HOURS 93 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 93 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 C/100 METERS) 10.1-WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 13.0 13.1-18.0 >18 TOTALS N 0 0 1 5 5 6 0 0 0 0 0 0 17 NNE 0 0 0 10 6 12 0 0 0 0 0 0 28 NE 0 0 0 1 2 2 0 1 0 0 0 0 6 ENE 0 0 0 1 1 1 0 0 0 0 0 0 3 E 0 0 0 0 2 2 0 0 0 0 0 0 4 ESE 0 0 0 1 1 6 8 0 0 0 0 0 16 SE 0 0 0 1 1 24 56 14 5 0 0 0 101 SSE 0 0 0 1 8 29 56 17 10 0 0 0 121 S 0 0 0 9 10 22 46 6 2 0 0 0 95 SSW 0 0 3 2 10 14 22 5 0 0 0 0 56 SW 0 0 1 10 10 4 2 2 1 0 0 0 30 WSW 0 1 0 3 2 9 3 0 0 0 0 0 18 W 0 0 1 4 5 4 4 0 0 0 0 0 18 WNW 0 0 0 2 7 6 3 0 0 0 0 0 18 NW 0 1 0 4 5 10 11 0 0 0 0 0 31 NNW 0 0 0 2 4 6 3 0 0 0 0 0 15 TOTALS 0 2 6 56 79 157 214 45 18 0 0 0 577 NUMBER OF VALID HOURS 577 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 577 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08040100-08063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ 1.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 0 3 9 3 0 0 0 0 0 0 16 NNE 0 1 2 8 19 16 3 0 0 0 0 0 49 NE 0 1 1 3 2 6 0 0 0 0 0 0 13 ENE 0 0 0 6 2 3 0 0 0 0 0 0 11 E 0 0 1 1 2 3 0 0 0 0 0 0 7 ESE 0 1 0 2 4 7 6 0 0 0 0 0 20 SE 0 0 2 1 2 5 8 1 0 0 0 0 19 SSE 0 0 0 4 5 7 0 0 0 0 0 0 16 S 0 0 1 2 2 0 0 0 0 0 0 0 5 SSW 0 0 0 4 3 1 0 0 0 0 0 0 8 SW 0 1 0 3 1 0 0 0 0 0 0 0 5 WSW 0 0 0 3 2 0 0 0 0 0 0 0 5 W 0 0 1 1 5 3 1 0 0 0 0 0 11 WNW 0 0 0 4 4 6 2 0 0 0 0 0 16 NW 0 0 1 3 2 7 3 0 0 0 0 0 16 NNW 0 0 1 5 4 3 1 0 0 0 0 0 14 TOTALS 0 5 10 53 68 70 24 1 0 0 0 0 231 NUMBER OF VALID HOURS 231 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 231 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 2 3 3 0 0 0 0 0 0 8 NNE 0 1 2 5 15 42 11 0 0 0 0 0 76 NE 0 0 2 6 2 1 1 1 0 0 0 0 13 ENE 0 0 0 0 1 2 2 0 0 0 0 0 5 E 0 0 0 2 2 2 0 0 0 0 0 0 6 ESE 0 0 0 2 0 1 0 0 0 0 0 0 3 SE 0 0 0 1 2 1 2 0 0 0 0 0 6 SSE 0 0 0 0 2 3 1 0 0 0 0 0 6 S 0 0 0 1 0 0 0 0 0 0 0 0 1 SSW 0 0 1 2 0 1 1 0 0 0 0 0 5 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 1 0 0 1 0 0 0 0 0 0 0 2 W 0 0 2 3 2 4 0 0 0 0 0 0 11 WNW 0 0 2 2 4 9 0 0 0 0 0 0 17 NW 0 0 0 2 2 4 2 0 0 0 0 0 10 NNW 0 0 1 4 0 2 1 0 0 0 0 0 8 TOTALS 0 2 10 32 36 75 21 1 0 0 0 0 177 NUMBER OF VALID HOURS 177 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 177 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08040100-08063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 3 1 1 4 0 0 0 0 0 9 NNE 0 1 1 3 12 79 57 1 0 0 0 0 154 NE 0 0 1 5 4 20 5 0 0 0 0 0 35 ENE 0 0 0 3 0 5 1 0 0 0 0 0 9 E 0 0 0 2 1 1 0 0 0 0 0 0 4 ESE 0 0 2 2 4 2 0 0 0 0 0 0 10 SE 0 1 0 1 1 1 1 0 0 0 0 0 5 SSE 0 0 0 1 2 0 0 0 0 0 0 0 3 S 0 0 1 1 1 2 0 0 0 0 0 0 5 SSW 0 0 0 1 1 0 0 0 0 0 0 0 2 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 2 0 1 0 0 0 0 0 3 W 0 0 0 2 0 1 0 0 0 0 0 0 3 WNW 0 0 0 0 1 3 0 0 0 0 0 0 4 NW 0 0 0 0 1 4 1 0 0 0 0 0 6 NNW 0 0 1 0 0 3 2 0 0 0 0 0 6 TOTALS 0 2 6 24 31 122 72 1 0 0 0 0 258 NUMBER OF VALID HOURS 258 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 258 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 1 14 18 14 4 0 0 0 0 0 52 NNE 0 3 5 26 53 149 71 1 0 0 0 0 308 NE 0 1 4 17 10 31 6 2 0 0 0 0 71 ENE 0 0 0 10 4 11 3 2 0 0 0 0 30 E 0 0 1 5 7 8 0 0 0 0 0 0 21 ESE 0 1 2 7 9 16 14 0 0 0 0 0 49 SE 0 1 2 4 6 32 69 15 5 0 0 0 134 SSE 0 0 0 9 18 47 82 22 16 0 0 0 194 S 0 0 2 13 15 39 90 24 12 3 0 0 198 SSW 0 0 4 10 17 47 90 16 2 1 0 0 187 SW 0 1 2 15 26 56 64 9 2 0 0 0 175 WSW 0 2 0 8 26 64 103 2 0 0 0 0 205 W 0 0 4 13 18 72 107 0 0 0 0 0 214 WNW 0 0 2 10 22 48 103 2 0 0 0 0 187 NW 0 1 1 9 13 36 47 6 0 0 0 0 113 NNW 0 0 3 11 9 15 8 0 0 0 0 0 46 TOTALS 0 11 33 181 271 685 861 101 37 4 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 - 2008 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08070100-08093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ -1.9 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 3 1 0 0 0 0 0 4 S 0 0 0 0 0 3 21 0 0 0 0 0 24 SSW 0 0 0 0 5 14 29 1 0 0 0 0 49 SW 0 0 1 1 15 47 31 1 0 0 0 0 96 WSW 0 0 0 3 21 105 52 0 0 0 0 0 181 W 0 0 0 2 10 85 130 0 0 0 0 0 227 WNW 0 0 0 1 5 51 120 0 0 0 0 0 177 NW 0 0 0 0 1 5 7 1 1 0 0 0 15 NNW 0 0 0 1 0 0 0 0 0 0 0 0 1 TOTALS 0 0 1 8 57 313 391 3 1 0 0 0 774 NUMBER OF VALID HOURS 774 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 774 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 1 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 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 1 2 0 0 0 0 0 0 3 S 0 0 0 1 3 5 1 0 0 0 0 0 10 SSW 0 0 0 0 3 3 7 3 0 0 0 0 16 SW 0 0 0 2 3 4 6 0 0 0 0 0 15 WSW 0 0 0 0 3 3 0 0 0 0 0 0 6 W 0 0 0 1 3 3 1 0 0 0 0 0 8 WNW 0 0 0 1 5 7 2 0 0 0 0 0 15 NW 0 0 0 0 1 3 4 2 0 0 0 0 10 NNW 0 0 0 0 1 1 0 0 0 0 0 0 2 TOTALS 0 0 0 5 24 31 21 5 0 0 0 0 86 NUMBER OF VALID HOURS 86 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 86 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08070100-08093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ -1.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 0 0 0 0 0 0 0 0 0 1 NNE 0 0 1 3 0 0 0 0 0 0 0 0 4 NE 0 0 0 1 0 0 0 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 1 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 0 0 0 0 0 0 1 SSE 0 0 0 1 4 5 1 0 0 0 0 0 11 S 0 0 0 0 6 9 3 0 0 0 0 0 18 SSW 0 0 0 0 2 9 4 0 0 0 0 0 15 SW 0 0 1 5 2 9 2 0 0 0 0 0 19 WSW 0 0 0 1 8 5 0 0 0 0 0 0 14 W 0 0 0 1 6 4 0 0 0 0 0 0 11 WNW 0 0 0 2 16 10 1 0 0 0 0 0 29 NW 0 0 0 2 4 10 4 0 0 0 0 0 20 NNW 0 0 0 0 0 2 0 0 0 0 0 0 2 TOTALS 0 0 3 17 48 63 16 0 0 0 0 0 147 NUMBER OF VALID HOURS 147 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 147 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 2 9 13 7 0 0 0 0 0 0 31 NNE 0 0 2 14 12 12 1 0 0 0 0 0 41 NE 0 0 2 5 3 10 0 0 0 0 0 0 20 ENE 0 0 0 4 0 3 0 0 0 0 0 0 7 E 0 0 1 3 2 2 0 0 0 0 0 0 8 ESE 0 0 1 5 1 7 0 0 0 0 0 0 14 SE 0 0 1 6 12 21 11 1 0 0 0 0 52 SSE 0 0 0 4 12 58 34 1 0 0 0 0 109 S 0 0 1 12 22 49 27 0 0 0 0 0 111 SSW 0 1 2 23 28 13 7 0 0 0 0 0 74 SW 0 1 4 19 12 8 4 0 0 0 0 0 48 WSW 0 1 9 23 23 9 0 0 0 0 0 0 65 W 0 0 8 29 18 4 0 0 0 0 0 0 59 WNW 0 0 5 37 26 8 0 0 0 0 0 0 76 NW 0 0 3 19 18 17 10 2 0 0 0 0 69 NNW 0 0 7 17 15 8 0 0 0 0 0 0 47 TOTALS 0 3 48 229 217 236 94 4 0 0 0 0 831 NUMBER OF VALID HOURS 831 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 831 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08070100-08093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ 1.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 1 7 9 2 1 0 0 0 0 0 21 NNE 0 3 5 27 17 12 1 0 0 0 0 0 65 NE 0 1 2 6 3 2 0 0 0 0 0 0 14 ENE 0 0 3 3 0 1 0 0 0 0 0 0 7 E 0 1 2 2 2 0 0 0 0 0 0 0 7 ESE 0 0 0 2 3 0 0 0 0 0 0 0 5 SE 0 0 1 1 3 3 5 4 0 0 0 0 17 SSE 0 0 1 3 7 6 6 3 0 0 0 0 26 S 0 0 1 6 4 2 0 0 0 0 0 0 13 SSW 0 0 1 1 1 1 0 0 0 0 0 0 4 SW 0 0 1 2 1 0 0 0 0 0 0 0 4 WSW 0 1 1 2 0 2 0 1 0 0 0 0 7 W 0 1 1 2 1 1 0 0 0 0 0 0 6 WNW 0 0 2 2 2 1 2 0 0 0 0 0 9 NW 0 0 0 1 1 1 0 0 0 0 0 0 3 NNW 0 0 1 1 2 5 0 0 0 0 0 0 9 TOTALS 0 8 23 68 56 39 15 8 0 0 0 0 217 NUMBER OF VALID HOURS 217 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 217 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 2 5 1 0 0 0 0 0 8 NNE 0 1 0 5 15 26 1 0 0 0 0 0 48 NE 0 0 0 3 2 1 0 0 0 0 0 0 6 ENE 0 0 1 4 1 1 0 0 0 0 0 0 7 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 2 0 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 0 0 0 1 0 0 0 0 0 0 1 S 0 0 0 1 1 1 0 0 0 0 0 0 3 SSW 0 0 1 1 1 0 1 0 0 0 0 0 4 SW 0 0 0 0 1 0 0 0 0 0 0 0 1 WSW 0 0 0 0 0 0 0 0 0 0 0 0 0 W 0 0 0 1 1 0 0 0 0 0 0 0 2 WNW 0 1 0 1 0 1 3 0 0 0 0 0 6 NW 0 0 0 0 0 1 0 2 0 0 0 0 3 NNW 0 0 2 0 1 0 0 0 0 0 0 0 3 TOTALS 0 2 4 19 25 38 6 2 0 0 0 0 96 NUMBER OF VALID HOURS 96 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 96 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08070100-08093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 1 0 0 0 1 0 0 0 0 2 NNE 0 0 0 1 4 17 10 0 0 0 0 0 32 NE 0 0 0 1 1 0 0 0 0 0 0 0 2 ENE 0 0 0 0 2 0 0 0 0 0 0 0 2 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 1 1 0 0 0 0 0 0 0 2 SE 0 0 0 1 0 1 0 0 0 0 0 0 2 SSE 0 0 0 0 3 0 0 0 0 0 0 0 3 S 0 0 0 0 1 0 0 0 0 0 0 0 1 SSW 0 0 0 0 1 0 0 0 0 0 0 0 1 SW 0 0 1 1 0 0 0 0 0 0 0 0 2 WSW 0 0 1 0 0 0 0 0 0 0 0 0 1 W 0 0 0 0 0 1 0 0 0 0 0 0 1 WNW 0 0 0 0 1 0 0 0 0 0 0 0 1 NW 0 0 0 1 0 0 0 0 0 0 0 0 1 NNW 0 0 0 1 0 1 2 0 0 0 0 0 4 TOTALS 0 0 2 8 14 20 12 1 0 0 0 0 57 NUMBER OF VALID HOURS 57 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 57 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 1 4 17 24 14 2 1 0 0 0 0 63 NNE 0 4 8 50 48 67 13 0 0 0 0 0 190 NE 0 1 4 16 9 13 0 0 0 0 0 0 43 ENE 0 0 4 11 4 5 0 0 0 0 0 0 24 E 0 1 3 5 4 2 1 0 0 0 0 0 16 ESE 0 0 1 10 5 8 0 0 0 0 0 0 24 SE 0 0 2 10 15 25 16 5 0 0 0 0 73 SSE 0 0 1 8 27 75 42 4 0 0 0 0 157 S 0 0 2 20 37 69 52 0 0 0 0 0 180 SSW 0 1 4 25 41 40 48 4 0 0 0 0 163 SW 0 1 8 30 34 68 43 1 0 0 0 0 185 WSW 0 2 11 29 55 124 52 1 0 0 0 0 274 W 0 1 9 36 39 98 131 0 0 0 0 0 314 WNW 0 1 7 44 55 78 128 0 0 0 0 0 313 NW 0 0 3 23 25 37 25 7 1 0 0 0 121 NNW 0 0 10 20 19 17 2 0 0 0 0 0 68 TOTALS 0 13 81 354 441 740 555 23 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 - 2008 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08100100-08123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ -1.9 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 1 2 0 0 0 0 0 3 S 0 0 0 0 4 10 7 0 0 0 0 0 21 SSW 0 0 0 1 5 6 4 0 0 0 0 0 16 SW 0 0 0 1 6 5 2 0 0 0 0 0 14 WSW 0 0 0 2 8 18 21 1 0 0 0 0 50 W 0 0 0 0 15 43 20 3 2 0 0 0 83 WNW 0 0 0 0 4 46 68 7 6 0 0 0 131 NW 0 0 0 0 1 4 4 6 0 0 0 0 15 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 4 43 133 128 18 8 0 0 0 334 NUMBER OF VALID HOURS 334 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 334 PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ -1.7 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 1 0 0 0 0 1 NE 0 0 0 0 0 0 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 1 0 0 0 0 0 0 0 0 0 0 0 1 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 1 0 1 0 2 1 0 0 0 5 SSW 0 0 0 0 4 0 2 1 0 0 0 0 7 SW 0 0 0 2 0 0 1 1 0 0 0 0 4 WSW 1 0 1 1 0 0 2 0 0 0 0 0 5 W 0 1 0 0 2 0 0 1 0 0 0 0 4 WNW 0 0 0 1 1 4 1 0 1 0 0 0 8 NW 0 0 0 1 0 1 0 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 2 1 1 6 7 6 6 7 2 0 0 0 38 NUMBER OF VALID HOURS 38 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 38 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08100100-08123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ -1.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 0 1 0 0 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 2 0 0 0 0 2 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 3 1 0 0 0 0 4 S 0 0 0 0 1 2 1 0 0 0 0 0 4 SSW 0 0 0 0 2 0 1 0 0 0 0 0 3 SW 0 0 0 1 1 3 1 0 0 0 0 0 6 WSW 1 0 0 0 1 0 0 1 1 0 0 0 4 W 1 0 0 0 0 3 0 0 0 0 0 0 4 WNW 0 0 0 0 0 3 0 0 0 0 0 0 3 NW 0 0 0 0 1 0 4 1 0 0 0 0 6 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 2 0 0 1 7 11 10 5 1 0 0 0 37 NUMBER OF VALID HOURS 37 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 37 PASQUILL D NEUTRAL (-1.5 < DT/DZ -0.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 0 4 1 2 4 0 0 0 0 0 11 NNE 0 0 0 0 1 5 1 0 0 0 0 0 7 NE 0 0 1 1 1 3 1 3 1 0 0 0 11 ENE 0 0 0 4 1 0 1 0 0 0 0 0 6 E 1 0 0 2 1 4 1 0 0 0 0 0 9 ESE 0 0 0 1 4 3 2 6 0 0 0 0 16 SE 0 0 0 1 5 8 17 11 9 0 0 0 51 SSE 0 0 2 3 6 9 19 16 1 0 0 0 56 S 0 0 0 1 4 7 7 2 1 1 2 0 25 SSW 0 0 0 5 1 7 6 4 0 0 2 0 25 SW 0 0 1 2 2 6 6 8 2 1 0 0 28 WSW 2 0 0 0 4 4 6 2 2 0 0 0 20 W 0 0 2 3 5 7 3 4 6 0 0 0 30 WNW 0 0 1 3 6 15 6 1 1 0 0 0 33 NW 0 0 0 2 5 16 17 3 1 0 0 0 44 NNW 1 0 0 5 4 10 4 2 0 0 0 0 26 TOTALS 4 0 7 37 51 106 101 62 24 2 4 0 398 NUMBER OF VALID HOURS 398 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 398 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2008 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08100100-08123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ 1.5 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 1 5 11 10 3 0 0 0 0 0 30 NNE 0 1 1 17 15 20 5 1 0 0 0 0 60 NE 0 1 1 10 5 6 2 5 7 2 0 0 39 ENE 0 0 1 6 2 7 2 3 1 0 0 0 22 E 0 0 1 7 7 7 4 2 0 0 0 0 28 ESE 0 0 2 3 3 2 5 0 0 0 0 0 15 SE 0 0 0 7 8 10 9 0 0 0 0 0 34 SSE 0 1 0 2 5 16 8 1 1 0 0 0 34 S 0 0 0 0 1 1 0 1 0 0 0 0 3 SSW 0 0 4 0 4 0 0 1 0 0 0 0 9 SW 0 1 2 5 4 0 0 1 0 0 0 0 13 WSW 0 1 0 3 6 0 3 3 0 0 0 0 16 W 0 0 1 6 9 7 0 6 0 0 0 0 29 WNW 0 0 0 7 8 16 7 2 6 0 0 0 46 NW 0 0 2 4 6 5 5 1 0 0 0 0 23 NNW 0 0 1 4 2 7 3 0 0 0 0 0 17 TOTALS 0 5 17 86 96 114 56 27 15 2 0 0 418 NUMBER OF VALID HOURS 418 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 418 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ 4.0 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 1 0 1 7 8 5 5 0 0 0 0 0 27 NNE 0 1 1 14 32 31 16 2 0 0 0 0 97 NE 3 1 7 15 16 5 8 2 0 0 0 0 57 ENE 2 0 6 11 9 4 0 0 0 0 0 0 32 E 4 0 3 10 5 2 0 0 0 0 0 0 24 ESE 3 0 2 5 2 1 1 0 0 0 0 0 14 SE 0 0 0 4 3 1 3 0 0 0 0 0 11 SSE 0 0 0 4 4 3 4 1 0 0 0 0 16 S 0 0 1 8 2 1 0 0 0 0 0 0 12 SSW 0 0 0 3 2 0 0 0 0 0 0 0 5 SW 3 0 1 5 1 1 0 0 0 0 0 0 11 WSW 0 0 2 4 4 1 0 0 0 0 0 0 11 W 3 0 1 0 7 5 0 0 0 0 0 0 16 WNW 0 1 2 2 6 7 6 0 0 0 0 0 24 NW 2 0 3 3 5 2 3 0 0 0 0 0 18 NNW 2 0 3 5 1 3 1 0 0 0 0 0 15 TOTALS 23 3 33 100 107 72 47 5 0 0 0 0 390 NUMBER OF VALID HOURS 390 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 390 October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 08100100-08123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 C/100 METERS) WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 0 0 4 3 3 8 6 0 0 0 0 0 24 NNE 0 1 2 12 18 130 149 3 0 0 0 0 315 NE 0 1 1 10 20 29 19 4 0 0 0 0 84 ENE 0 0 1 7 10 7 6 0 0 0 0 0 31 E 0 0 0 6 5 6 0 0 0 0 0 0 17 ESE 0 0 3 2 1 2 0 0 0 0 0 0 8 SE 0 0 0 3 1 1 0 0 0 0 0 0 5 SSE 0 0 1 2 3 2 3 0 0 0 0 0 11 S 0 0 0 5 3 2 0 0 0 0 0 0 10 SSW 0 1 1 5 3 0 0 0 0 0 0 0 10 SW 0 0 0 8 0 4 1 0 0 0 0 0 13 WSW 0 0 1 4 0 1 1 0 0 0 0 0 7 W 0 0 2 2 4 1 0 0 0 0 0 0 9 WNW 0 1 1 3 6 16 0 0 0 0 0 0 27 NW 0 0 1 3 1 4 4 0 0 0 0 0 13 NNW 0 0 2 1 2 3 1 0 0 0 0 0 9 TOTALS 0 4 20 76 80 216 190 7 0 0 0 0 593 NUMBER OF VALID HOURS 593 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 593 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND DIR .22-.50 .51-75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10.0 10.1-13.0 13.1-18.0 >18 TOTALS N 1 0 6 19 24 25 18 0 0 0 0 0 93 NNE 0 3 4 43 66 186 171 7 0 0 0 0 480 NE 3 3 10 36 42 43 30 18 8 2 0 0 195 ENE 2 0 8 28 22 18 9 3 1 0 0 0 91 E 5 0 4 25 18 19 5 2 0 0 0 0 78 ESE 4 0 7 11 10 8 8 6 0 0 0 0 54 SE 0 0 0 15 17 20 29 11 9 0 0 0 101 SSE 0 1 3 11 18 31 39 19 2 0 0 0 124 S 0 0 1 15 15 24 15 5 2 1 2 0 80 SSW 0 1 5 14 21 13 13 6 0 0 0 0 75 SW 3 1 4 24 14 19 11 10 2 1 0 0 89 WSW 4 1 4 14 23 24 33 7 3 0 0 0 113 W 4 1 6 11 42 66 23 14 8 0 0 0 175 WNW 0 2 4 16 31 107 88 10 14 0 0 0 272 NW 2 0 6 13 19 32 37 11 1 0 0 0 121 NNW 3 0 6 15 9 23 9 2 0 0 0 0 67 TOTALS 31 13 78 310 391 658 538 131 50 4 4 0 2208 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 Enclosure 2: SO123-ODCM, Revision 1

February 29, 2008 Mr. R. T. Ridenoure SUBJECT : Revision 1 of the San Onofre Nuclear Generating Station (SONGS) Offsite Dose Calculation Manual (ODCM), SOI23-0DCM. In accordance with Technical Specification 5.5.2.1, Revision 1 to the SONGS Dose Calculation Manual has been prepared and reviewed for your approval. This revision incorporates the current changes to the Land Use Census. In addition to several administrative changes, it also creates an additional appendix to capture supplemental information pertinent to the effluent controls program; 1) a Kathleen Yhip to Daryl Dick Memorandum for File, "Recommended Effluent Concentration Limits from 10CFR20 Appendix B, Table 2, for Setpoint Calculations," dated April 23, 1993 and 2) an E.S. Medling to J. Clark Memorandum for File, "Impact of the New 10 CFR 20 Upon SONGS Effl uent Cont ro 1 Li mi t s ," dated June 14, 1993. None of the changes in this revision will adversely affect the accuracy or reliability of effluent dose calculations or set point determinations. Your approval for this revision is requested. Copies of this letter are being forwarded to the Nuclear Safety Group as required by Technical Specification 5.5.2.1. Please contact me if there are any questions. O.F. Flores Manager, Chemistry Approved by* RECEIVED COM Manager Attachment FEB 29 2008 cc: Supervis r, CDM-SON S Chern Fi e Silt: Fll.F COpy Site File Copy

2/29/2008 SUBJECT : SONGS OFFSITE DOSE CALCULATION MANUAL Revision 1 Enclosed is Revision 1 to the SONGS Offsite Dose Calculation Manual (ODCM). This revision accomplishes three objectives: 1) Incorporates the latest updates related to the 2006-2007 Land Use Census (LUC) from the J.W. Scott to D. Dick Memorandum for File, "2008 Dose Parameters for SONGS," dated February 11, 2008 2) Creates Appendix B to incorporate historical references for the effluent control program and 3) Changes page numbers in Appendices to identify the Appendix number. Editorial corrections were made to Figure 4-5 to correct a release pathway unintentionally omitted from the figure. Added pg vi in the Table of Contents for SOI23-0DCM to identify the two ODCM appendices. No 50.59 or EOE reviews were required or performed for editorial changes. None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.35a and Appendix I to 10CFR50 will be maintained. Throughout the document, change bars are marked in one of four ways as follows: A Additi on D Deletion F Editorial/Format change R Revision Page # Change Reason vi Added pg vi in Table of Contents to include a List of A Appendices. 2-29 Revised table 2-6 per LUC R 4-20 corrected to include a release pathway unintentionally F removed in prior revision Appendix renumbered the page to include Appendix identification F A- ALL i e. 1-1 to AI-I. Appendix edited to include page identifier for Table of Contents R A- table for Appendix A, Changed page numbers and reformatted of contents AI-8 Revised Ri values per LUC R

AI-IO Revised Ri values per LUC, edited page 1 of 2 to page 1 R/F of 3 per LUC AI-ll Changed from pg 2 of 2 to page 2 of 3 per LUC F AI-I2 Added new pathway, page 3 of 3 per LUC A AI-13 Revised Ri values per LUC R AI-I4 Revised Ri values per LUC R AI-I5 Revised Ri values per LUC R AI-17 Revised Ri values per LUC R AI-I9 Revised Ri values per LUC R AI-22 Changed from page 1 of 2 to page 1 of 3 per LUC F AI-23 Added new pathway, page 2 of 3 per LUC A AI-24 Changed from page 2 of 2 to page 3 of 3 per LUC F Appendix Added Appendix B so as to include supplemental A B information on the effluent control program (historical references)

OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION (SONGS) S0123-0DCM Revision 1 02-29-08

ODCM TABLE OF CONTENTS LIST OF FIGURES iv LIST OF TABLES v INTRODUCTI ON vi 1.0 LIQUID EFFLUENTS 1-1 thru 1-27 1.1 Concentration 1-1 1.1.1 Specification . . . . . 1-1 1.1.1.1, 1.1.1.2 Surveillances 1-1

1. 2 Dose 1-6 1.2.1 Specification 1-6 1.2.1.1 Surveillance 1-6 1.3 Liquid Waste Treatment 1-7 1.3.1 Specification . 1-7 1.3.1.1, 1.3.1.2, 1.3.1.3 Surveillances 1-7 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation 1-9 1.4.1 Batch Release Setpoint Determination 1-11 1.4.2 Continuous Release Setpoint Determination 1-15 1.5 Dose Calculations for Liquid Effluents 1-24 1.6 Representative Sampling 1-27 2.0 GASEOUS EFFLUENTS 2-1 thru 2-31 2.1 Dose Rate . . 2-1 2.1.1 Specification . 2-1 2.1.1.1, 2.1.1.2 Surveillances 2-1 2.2 Dose - Noble Gas 2-5 2.2.1 Specification 2-5 2.2.1.1 Surveillance 2-5 2.3 Dose - Radioiodines, Radioactive Materials in Particulate Form and Tritium . 2-6 2.3.1 Specification 2-6 2.3.1.1 Surveillance 2-6 S0123-0DCM Revision 0 02-27-07

ODCM TABLE OF CONTENTS (Continued) 2.4 Gaseous Radwaste Treatment 2-7 2.4.1 Specification 2-7 2.4.1.1 Surveillance 2-7 2.4.1.2, 2.4.1.3 Surveillances 2-8 2.5 Deleted, moved to Section 3 2.6 Gaseous Effluent Monitor Setpoints 2-10 2.6.1 Plant Stack . 2-10 2.6.2 Condenser Evacuation System 2-13 2.6.3 Containment Purge 2-15 2.6.4 Waste Gas Header 2-18 2.7 Gaseous Effluent Dose Rate 2-21 2.7.1 Noble Gases . 2-21 2.7.2 Radioiodines and Particulates 2-22 2.8 Gaseous Effluent Dose Calculation 2-23 2.8.1 Noble Gases . 2-23 2.8.1.1 Historical Meteorology 2-23 2.8.1.2 Concurrent Meteorology 2-24 2.8.2 Radioiodines and Particulates . . 2-25 2.8.2.1 Historical Meteorology 2-25 2.8.2.2 Concurrent Meteorology 2-26 3.0 PROJECTED DOSES 3-1 thru 3-5 3.1 Liquid Dose Projection 3-1 3.2 Gaseous Dose Projection 3-1 3.3 Total Dose 3-2 3.3.1 Specification. 3-2 3.3.1.1 Surveillance 3-2 3.4 Total Dose Calculations 3-3 3.4.1 Total Dose to Most Likely Member of the Public 3-3 3.4.1.1 Annual Total Organ Dose. 3-3 3.4.1.2 Annual Total Whole Body Dose 3-4 3.4.1.3 Annual Total Thyroid Dose . . 3-5 S0123-0DCM Revision 0 ii 02-27-07

ODCM TABLE OF CONTENTS (Continued) Page 4.0 EQUIPMENT 4-1 thru 4-22 4.1 Radioactive Liquid Effluent Monitoring Instrumentation 4-1 4.1.1 Specification 4-1 4.1.1.1, 4.1.1.2 Surveillances 4-1 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation 4-9 4.2.1 Specification 4-9 4.2.1.1 Surveillance 4-9 4.3 Operability of Radioactive Waste Equipment 4-19 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5-1 thru 5-27 5.1 Monitoring Program 5-1 5.1.1 Specification 5-1 5.1.1.1 Surveillance 5-2 5.2 Land Use Census 5-11 5.2.1 Specification 5-11 5.2.1.1 Surveillance 5-11 5.3 Interlaboratory Comparison Program 5-12 5.3.1 Specification 5-12 5.3.1.1 Surveillance 5-12 5.4 Annual Radiological Environmental Operating Report 5-13 5.5 Sample Locations 5-14 6.0 ADMINISTRATIVE 6-1 thru 6-17 6.1 Defi nit ions 6-1 6.2 Administrative Controls 6-8 6.3 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 6-10 6.4 Bases. 6-11 S0123-0DCM Revision 0 iii 02-27-07

ODeM LIST OF FIGURES Figure Titl e Page 1-2 Site Boundary for Liquid Effluents 1-8 2-2 Site Boundary for Gaseous Effluents . 2-9 4-5 SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems 4-20 4-6 SONGS 2 and 3 Radioactive Gaseous Waste Treatment Systems 4-21 4-7 Solid Waste Handling . . . . 4-22 5-1 Radiological Environmental Monitoring Sample Locations 1 Mile Radius . . . 5-23 5-2 Radiological Environmental Monitoring Sample Locations 2 Mile Radius . . 5-24 5-3 Radiological Environmental Monitoring Sample Locations 10 Miles Radius 5-25 5-4 Radiological Environmental Monitoring Sample Locations Orange County . 5-26 5-5 Radiological Environmental Monitoring Sample Locations San Diego County . . 5-27 S0123-0DCM iv Revision 0 02-27-07

ODeM LIST OF TABLES Table Tit 1e Page 1-1 Radioactive Liquid Waste Sampling and Analysis Program . . . 1-2 1-3 Liquid Effluent Radiation Monitors Calibration Constants 1-23 1-4 Dose Commitment Factors Ah 1-25 2-1 Radioactive Gaseous Waste Sampling and Analysis Program 2-2 2-3 Gaseous Effluent Radiation Monitor Calibration Constants 2-20 2-4 Dose Factors for Noble Gas and Daughters 2-27 2-5 Dose Parameters Pi k 2-28 2-6 Units 2 and 3 Controlling Location Factors 2-29 2-7 SYF Controlling Location Factors. 2-30 2-8 NIA (Unit 1) Controlling Location Factor 2-31 4-1 Radioactive Liquid Effluent Monitoring Instrumentation 4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements . 4-6 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation 4-10 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements . 4-14 5-1 Radiological Environmental Monitoring Program 5-3 5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples . 5-7 5-3 Maximum Values for the Lower Limits of Detection (LLD) 5-8 5-4 Radiological Environmental Monitoring Sample Locations 5-15 5-5 PIC Radiological Environmental Monitoring Locations 5-21 5-6 Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map 5-22 6-1 Operational Modes 6-6 6-2 Frequency Notation 6-7 S0123-0DCM Revision 0 v 02-27-07

ODCM LIST OF APPENDICES Tit 1e Appendix Ri TABLES S0123-0DCM-A Supplemental Information for the Effluent Controls Program S0123-0DCM-B S0123-0DCM Revision 1 vi 02-29-08

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerates dose and concentration specifications, instrument requirements, as well as describes the methodology and parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents consistent with RG 1.109 and NUREG 0133. In order to meet release limits, it additionally provides calculations for liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints. The environmental section contains the requirements for the radiological environmental monitoring program. The ODCM will be maintained at the Site for use as a document of Specifications and acceptable methodologies and calculations to be used in implementing the Specifications. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents current methodology. S0123-0DCM Revision 0 vii 02-27-07

1.0 LIQUID EFFLUENTS 1.1 CONCENTRATION SPECI FICATION 1.1.1 The concentration of radioactive material released from the site (see Figure 1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10- 4 microcuries/ml total activity. APPLICABILITY: At all times ACTION:

a. With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 

         .1   Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-1 .
         .2   The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in Section 1.4 to assure that the concentrations at the point of release are maintained within the limits of Specification 1.1.1.

S0123-0DCM 1-1 Revision 0 02-27-07

TABLE 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD) Type Frequency Frequency Analysis (Il Ci/ml) a A. Batch Waste P P Principal Gamma 5xl0-7 Rel eased Each Batch Each Batch Emi tters f 1-131 1x10- 6 P M Dissolved and lxl0- 5 One Batch/M Entrained Gases (Gamma emitters) P M H-3 ixio' Each Batch Compos i t e Gross Alpha lxl0- 7 P Q Sr-89, Sr-90 5xl0-8 Each Batch Compos i t e Fe-55 lxl0- 6 NOTE BATCH RELEASE POINTS: Primary Plant Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, Blowdown Processing System Neutralization Sump, FFCPD sumps (high conductivity, low conductivity) and holdup tank, Component Cooling Water Sump, Storage Tank Area Sump, S/G Blowdown. B. Continuous D W Principal Gamma Re l ea ses", Grab Sample Compos i t e' Emitters f 1-131 M M Dissolved and Grab Sample Entrained Gases (Gamma emi tters) D M H-3 Grab Sample Compos ite c Gross Alpha D Q Sr-89, Sr-90 Grab Sample Compos i t e' Fe-55 NOTE CONTINUOUS RELEASE POINTS: Turbine Plant Sump*, Blowdown Processing System Neutralization Sump"', S/G Blowdown Bypass Line***, S/G Blowdown, Auxiliary Building Sump: SOI23-0DCM 1-2 Revision 0 02-27-07

TABLE 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued) Lower Limit Minimum Type of of Detection Liquid Release Sampling Analysis Activity (LLD) Type Frequency Frequency Analysis (flCi/ml)a C. Continuous 3 xW W Principal Gamma 5x 10- 7 Rel ease" Grab Sample Compos i teb,g Erni t t er s' North 3 xW M H-3 lxl0- 5 Industrial Area Grab Sample Compos i teb,g Yard Drain Sump Gross Alpha lxl0- 7 3 xW Q Sr-89, Sr-90 5xl0-8 Grab Sample Compos i teb,g Fe-55 lxl0- 6 SOI23-0DCM 1-3 Revision 0 02-27-07

TABLE 1-1 (Continued) TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation): LLD E

  • V
  • 2.22 X 10 6
  • Y
  • exp (-Mt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and 6t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). The value of Sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y and 6t should be used in the calculation. It should be recognized that the LLD is defined as an £ priori (before the fact) limit representing the capability of the measurement system and not as £ posteriori (after the fact) limit for a particular measurement.# 'For a more complete discussion of the LLD, and other detection limits, see the following: (1) HASL Procedures Manual, HASL-300 (revised annually). (2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968). (3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972). S0123-0DCM 1-4 Revision 0 02-27-07

TABLE 1-1 (Continued) TABLE NOTATION

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
d. A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.
f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, and those isotopes listed in Reg. Guide 1.21, shall also be identified and reported.
g. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
  • Administrative controls shall ensure that only one continuous release point is discharging through a discharge path at any given time. The normal continuous release point via 2(3)RT-7821 is the turbine plant sump.
    • The first sump when transferring outlying sumps shall be treated as a batch release.
      • Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S21301MU619 for Steam Generator 2E088, S21301MU618 for Steam Generator 2E089, S31301MU619 for Steam Generator 3E088 and S31301MU618 for Steam Generator 3E089) is verified locked shut.

SOI23-0DCM 1-5 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.2 DOSE SPECIFICATION 1.2.1 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 1-2) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1.

SURVEILLANCE REQUIREMENTS 

         .1   Dose Calculation. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 1.5 at least once per 31 days.

S0123-0DCM 1-6 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT SPECI FICATION

1. 3.1 The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 1-2) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which includes the following information:
1. Explanation of why liquid radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability,
2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 

         .1    Doses due to liquid releases shall be projected at least once per 31 days, in accordance with Section 3.1 .
         .2    During plant operation (either unit in Mode 1-4), the appropriate portions of the liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least IS-minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days .
         .3    In plant shut-down (both units in Mode 5,6), the appropriate portions of the liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least IS-minutes prior to processing liquids unless the appropriate liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
               *Per reactor unit S0123-0DCM 1-7                             Revision 0 02-27-07

SITE BOUNDARY FOR LIQUID EFFLUENTS FIGURE 1-2 

                      'AN  ~RE      NUCLEAR 5EMEIlATIJl& 1T1TIOtI NIA UNIT 2 & UNIT 3 o        00
                                     -+--~

_. --=,. IC:ALl II 'In SOI23-0DCM 1-8 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20. Appendix B. Table II. Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of Specification 1.1.1. the alarm/trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied: (1-1) ( ~:: J ,MPC'ff where: Cm = setpoint. representative of a radionuclide concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release. ~Ci/ml R permissible waste effluent flow rate at the radiation monitor location. in volume per unit time in the same units as for F F dilution water flow in volume per unit time. 185,000 gpm per circulating water pump (4 total)* 17,000 gpm per saltwater pump (2 total)

  • The design flowrate of each circulating water pump is 205,000 gpm. The value used in the determination of F takes into account factors such as frictional losses. pump inefficiency. and tidal flow, and provides reasonable assurance that the radioactive release concentration is not underestimated.

NOTE: Since the values of R are much smaller than F. the term (F + R) in equation (1-1) may be replaced by F. S0123-0DCM 1-9 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION (Continued) MPC e ff = effective effluent maximum concentration permissible limit (pCi/ml) at the release point to the unrestricted area for the radionuclide mixture being released: (1-2) where: n = number of radionuclides identified in sample analysis Fi fractional concentration of the i t h radionuclide as obtained by sample analysis MPC i = MPC of the i t h radionuclide (10CFR20, App B, Table II, Column 2) Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points: RW 7813 Radwaste Effl uent di scharge SG 88 _Z Uni t 2 Steam Generator E-088 SG 89 _Z Uni t 2 Steam Generator E-089 SG 88 _3 Uni t 3 Steam Generator E-088 SG 89_3 Uni t 3 Steam Generator E-089 Bz Unit 2 Blowdown Processing System Neutralization Sump B3 Unit 3 Blowdown Processing System Neutralization Sump Tz Unit 2 Turbine Plant Sump T3 Unit 3 Turbine Plant Sump Y NIA Yard Drain Sump The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points to the plant discharge will not result in a release exceeding the limits of 10CFR20, Appendix B, Table II, Column 2. The administrative values shall be assigned such that: (RW 7813 + SG 88 _Z + SG 89- Z + SG 88 _3 + SG 89_3 + Bz + B3 + Tz + T3 + Y) .::: 1. O. The administrative values shall be periodically reviewed based on actual release data and revised as necessary. S0123-0DCM 1-10 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued)

1. 4.1 BATCH RELEASE SETPOINT DETERMINATION The waste flow (R) and monitor setpoint (C m) are set to meet the condition of equation (1-1) for the MPC e ff limit. The method by which this is accomplished is as follows:

STEP 1: The isotopic concentration for each batch tank (or sump) to be released is obtained from the sum of the measured concentrations in the tank (or sump) as determined by analysis. (1-3) where: C total concentration in each batch tank, pCi/ml sum of the measured concentrations for each radionuclide, i, in the gamma spectrum, excluding Xe-133, pCi/ml gross alpha concentration determined in the previous monthly composite sample, pCi/ml Sr-89 and Sr-90 concentrations as determined in the previous quarterly composite sample, pCi/ml H-3 concentration as determined in the previous monthly composite sample, or as measured in the sample taken prior to release, pCi/ml Fe-55 concentration as determined in the previous quarterly composite sample, pCi/ml Cxe = Xe-133 concentration as determined by isotopic analysis, pCi/ml S0123-0DCM 1-11 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued) STEP 2: The effective MPC (MPC e ff ) for each batch tank (or sump) is determined using: 1 (l-4) (C/C] L ( C./C i M;lC Yi 

                                     ]
                                       +   M~Cs where:

MPC,; , MPC~, the limiting concentrations of the appropriate MPC t , radionuclide from 10CFR20, Appendix B, Table II, MPC Fe , Column 2 MPC a NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 ~Ci/ml total activity. STEP 3: The setpoint, Cm (~Ci/ml) for each batch release radioactivity monitor may now be specified based on the respective values of C, 2:;C'li' F, MPC e ff , and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2. STEP 4: If the monitor reads in CPM, the setpoint may be derived using the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor limit Cm' ~Ci/ml. (1-5) (C m' ~Ci/ml) CPM max (Cal. Const., ~Ci/cclcpm) S0123-0DCM 1-12 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 BATCH RELEASE SETPOINT DETERMINATION (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2!3RT-7813) The value for Cm, the concentration limit at the detector, is determined by using: (RW 78 n) (F) (Li C' yi) (1-6) C <; m (R) (MP~ eft J where: Radwaste Effluent discharge administrative value F dilution water flow in volume per unit time 185,000 gpm per circulating water pump (4 total) 17,000 gpm per saltwater pump (2 total) C Total concentration in each batch sample 2":C 1 I .. 

                        ,,1 total gamma isotopic concentration, excluding Xe-133, pCi /ml R                   typical effluent release rate.

Values of R for each tank are as follows: Radwaste Primary Tanks 140 gpm (per pump) Radwaste Secondary Tanks 140 gpm (per pump) Primary Plant Makeup Tank 160 gpm (per pump) Condensate Monitor Tanks 100 gpm (per pump) from equation (1-4) NOTE: If C, :: 2":iC' ri ' then no release is possible. To increase Cm, increase the administrative value RW 7813 , and/or increase dilution flow F (by running more dilution pumps in the applicable discharge structure), and/or decrease the effluent flow rate R and recalculate Cm using the new RW 7813 , F, R as applicable and equation (1-6). S0123-0DCM 1-13 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 BLOWDOWN PROCESSING SYSTEM NEUTRALIZATION SUMP/FULL FLOW CONDENSATE POLISHER DEMINERALIZER (FFCPD) SUMP DISCHARGE LINE MONITOR (BATCH) (2RT-7817, 3RT-7817) The value for C2 (Unit 2) or C3 (Unit 3), the concentration limit at the Unit 2 or Unit 3 detector, is determined by using: (B 2) (F) (2: i C' Vi) (1-7) (R) (C/MPC eff ) (B 3)(F) (2: i C' Yi) (1-8) (R) (C/MPC eff ) where: C2 instantaneous concentration at detector 2RT-7817 in pCi/cc C3 instantaneous concentration at detector 3RT-7817 in pCi/cc B2 Unit 2 BPS Neutralization Sump administrative value B3 Unit 3 BPS Neutralization Sump administrative value F dilution water flow in volume per unit time 185,000 gpm per circulating water pump (4 total) 17,000 gpm per saltwater pump (2 total) 2: jC' yj = total gamma isotopic concentration, excluding Xe-133, pCi /ml, (STEP 1) R Typical release flow rates: BPS Neutralization Sump 500 gpm FFCPD High Conductivity Sump 500 gpm FFCPD Low Conductivity Sump 600 gpm FFCPD Holdup Tank 1000 gpm C total concentration in each batch sample, pCi/ml value of MPC e f f from equation (1-4) for the sample analysis NOTE: If C2 or C3 :: 2: jC' (; , then no release is possible. To increase C2 or C3 , increase the administrative value B2 or B3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent fl ow rate, R, and reca 1cul ate C2 or C3 usi ng the new B2 or B3 , F, R as applicable and equation (1-7) or (1-8). S0123-0DCM 1-14 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued)

1. 4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION The waste flow (R) and monitor setpoint (C m) are set to meet the condition of equation (1-1) for the effective MPC (MPC eff ) 1imit.

The method by which this is accomplished is as follows: STEP 1: The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown, steam generator blowdown bypass, blowdown processing system neutralization sump, turbine plant sump, and yard drain sump) from the sum of the respective measured concentrations as determined by analysis: (1-3) where: C = total concentration (~Ci/ml) L:iC'(i total gamma activity associated with each radionuclide, i, in the weekly composite analysis for the release stream, excluding Xe-133, ~Ci/ml Co total measured gross alpha concentration determined from the previous monthly composite analysis for the release stream, ~Ci/ml C5 total measured concentration of Sr-89 and Sr-90 as determined from the previous quarterly composite analysis for the release stream, ~Ci/ml Ct = total measured H-3 concentration determined from the previous weekly or monthly composite analysis for the release stream, ~Ci/ml CFe total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream, ~Ci/ml Cxe Xe-133 concentration as determined by isotopic analysis, 

                       ~Ci/ml S0123-0DCM 1-15                           Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2 CONTINUOUS RELEASE SETPOINT DETERMINATION (Continued) STEP 2: The effective MPC (MPC ef f ) for each release stream (steam generator blowdown, blowdown processing system neutralization sump, turbine plant sump, or NIA yard drain sump) is determined using: 1 (1-4) C.IC ] (C IC] L ( M;lC i Yi 

                                       +     M~Cs where:

MPC t i , MPC s ' the limiting concentrations of the appropriate MPC t , radionuclide from 10CFR20, Appendix B, Table II, MPC Fe , Column 2 MPC y STEP 3: The setpoint, Cm (~Ci/ml) for each continuous release radioactivity monitor may now be specified based on the respect i ve val ues of C, L:;C ' i ' F, MPC ef p and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2. STEP 4: If the monitor reads in CPM, the setpoint may be derived using the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor 1imit Cm , ~Ci Iml . (1-5) (C m' ~Ci /ml ) CPM max (Cal. Const., ~Ci/cclcpm) S0123-0DCM 1-16 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 BLOWDOWN PROCESSING SYSTEM NEUTRALIZATION SUMP DISCHARGE LINE MONITORS (2RT-7817, 3RT-7817) The value for C2 (Unit 2) or C3 (Unit 3), the concentration 1 imit at the Unit 2 or Unit 3 detector, is determined by using: (B 2)(F) (l:i CI yi) (l-7) C2 :s; (R) (C/MPC e ff ) (B 3) (F) (l:i CI Yi) (1-8) C3 :s; (R) (C/MPC e ff ) where: instantaneous concentration at detector 2RT-7817 in ~Ci/cc instantaneous concentration at detector 3RT-7817 in ~Ci/cc Unit 2 Blowdown Processing System Neutralization Sump administrative value Unit 3 Blowdown Processing System Neutralization Sump administrative value F dilution water flow in volume per unit time 185,000 gpm per circulating water pump (4 total) 17,000 gpm per saltwater pump (2 total) total gamma isotopic concentration, excluding Xe-133, 

                            ~Ci /ml, (STEP 1)

R effl uent fl ow rate, gpm, (STEP 1), (maximum of 500 gpm) C total concentration, ~Ci/ml value of MPC eff from equation (1-4) for the sample analysis NOTE: If C2 or C3 :: l:iC'/i' then no release is possible. To increase C2 or C3 , increase the administrative value B2 or B3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C2 or C3 using the new B2 or B3 , F, R as applicable and equation (1-7) or (1-8). SOI23-0DCM 1-17 Revision a 02-27 -07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753, 2RT-6759, 3RT-6753, 3RT-6759) The value for C59 - 2 , C53 - 2 , C59 - 3 or C53 - 3 , the concentration limit at the Unit 2 or Unit 3 detectors, is determined by using: (SG 88 2) (F) (Zj C vi) I (1-9) C59 -2 (R) (C/MPC eff ) (SG 89 -2) (F) (Zi C vi) I (1-10) C53 - 2 <;; (R) (C /MPC eff) (SG 88 _3) (F) (Zi C Vi) I (I-H) C59 - 3 <;; (R) (C/MPC eff ) (SG 89 -3) (F) (Zi C vi) I (I-12) C53 -3 (R) (C/MPC eff ) where: C59- 2 instantaneous concentration at detector 2RT-6759 in pCi/ml C53 - 2 instantaneous concentration at detector 2RT-6753 in pCi/ml C59 - 3 instantaneous concentrat i on at detector 3RT -6759 in pCi /ml C53 - 3 instantaneous concent rat i on at detector 3RT -6753 in pCi /ml SG 88 - 2 Unit 2 E088 Steam Generator Blowdown administrative value SG 89- 2 Unit 2 E089 Steam Generator Blowdown admi ni strat i ve value SG 88 - 3 Unit 3 E088 Steam Generator Blowdown administrative value SG 89 - 3 Unit 3 E089 Steam Generator Blowdown administrative value F dilution water flow in volume per unit time 185,000 gpm per circulating water pump (4 total) 17,000 gpm per saltwater pump (2 total) S0123-0DCM 1-18 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753, 2RT-6759, 3RT-6753, 3RT-6759) (Continued) EjC' ,i = total gamma isotopic concentration, excluding Xe-133, IlCi/ml, (STEP 1) R maximum blowdown bypass effluent flowrate per steam generator, 200 gpm, (STEP 1) C total concentration, IlCi/ml MPC eff value of MPC eff from equation (l-4) for the sample analysis NOTE: If C59- 2 , C53- 2 , C59- 3 , or C53- 3 ~ EjC'(i (for the respective steam generator), then no release is possible. To increase C59- 2' C53- 2 , C59- 3 or C53- 3 , increase the administrative value SG 88 - 2 , SG 89 - 2 , SG 88 - 3 or SG 89 _3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effl uent fl ow rate Rand reca 1cul ate C59- 2 , C53- 2 , C59- 3 or C53- 3 using the new values of SG 89 _2 , SG 88 _2 , SG 89 _3 or SG 88 _3 , F, R as applicable and equation (l-9), (l-1O), (l-ll) or (1-12). SOI23-0DCM 1-19 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821, 3RT-7821) The value for C2 (Unit 2) or C3 (Unit 3), the concentration limit at the Unit 2 or Unit 3 detector, is determined by using: (T 2)(F) (l:i C' vi) (1-13) C2 :S (R) (C/MPC eff ) (T 3) (F) (l:iC Vi) I (1-14) C3 :S (R) (C/MPC eff ) where: C2 instantaneous concentration at detector 2RT-7821 in ~Ci/cc C3 instantaneous concentration at detector 3RT-7821 in ~Ci/cc T2 Unit 2 Turbine Plant Sump administrative value T3 Unit 3 Turbine Plant Sump administrative value F dilution water flow in volume per unit time 

                         =     185,000 gpm per circulating water pump (4 total) 17,000 gpm per saltwater pump (2 total) l:;C' (i       total gamma isotopic concentration, excluding Xe-133,
                              ~Ci /ml, (STEP 1)

R effluent flow rate, gpm, (STEP 1), typically flow rate: 100 gpm (per pump) C total concentration, ~Ci/ml MPC eff = value of MPC eff from equation 0-4) for the sample analysis NOTE: If C2 or C3 :: l:;C',i' then no release is possible. To increase C2 or C3 , increase the administrative value T2 or T3 , and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C2 or C3 using the new T2 or T3 , F, R as applicable and equation (1-13) or (1-14). S0123-0DCM 1-20 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821, 3RT-7821) (Continued) Use of a temporary discharge path from the Turbine Plant Sump is allowed providing the radiation monitor, 2(3)RT-7821, is in service and the normal discharge path is used concurrently. Temporary pumps facilitate faster discharge when draining the condenser to the outfall via this pathway. The following conditions shall be met:

a. The release permit shall account for the entire volume of water discharged from the Turbine Plant Sump.
b. The alarm setpoint for the monitor shall be adjusted to take into account the entire discharge flow through both the normal and temporary paths.
c. Procedures shall require the immediate termination of the discharge via the temporary path if the monitor on the normal path alarms.

S0123-0DCM 1-21 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.4 NIA YARD DRAIN SUMP MONITOR (RT-2101) There is one Yard Drain Sump on site, located in the North Industrial Area. It can be released through either the Unit 2 or Unit 3 outfall. The same radiation monitor is used for either outfall. The value for CYDS ' the concentration limit at the detector, is determined by using: (Y) (F) (6 i C' yi) (1-15) (R) (C /MPC eff) where: CYM instantaneous concentration at detector RT-2101 in ~Ci/ml Y NIA Yard Drain Sump administrative value F dilution water flow in volume per unit time 185,000 gpm per circulating water pump (4 total) 17,000 gpm per saltwater pump (2 total) 6;C'i total gamma isotopic concentration, ~Ci/ml, (STEP 1) R effluent flow rate, gpm, typical flow rates: 2300 gpm or 4100 gpm C = total concentration, ~Ci/ml MPC e ff value of MPC e ff from equation 0-4) for the sample analysis NOTE: If CYDS .::: 6;C' Ii' then no release is possible. To increase CYDS ' increase the administrative value Y, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate CYDS using the new Y, F, R as applicable and equation 0-15). S0123-0DCM 1-22 Revision 0 02-27-07

TABLE 1-3 Liquid Effluent Radiation Monitor Calibration Constants (a) (IlCi/cc/cpm) MONITOR Co-60 Ba-l33 Cs-137 2RT-6753 2.07E-8 1. 90E-8 2RT-6759 1. 90E-8 1. 90E-8 3RT-6753 1. 92E-8 1. 92E-8 3RT-6759 1.98E-8 1.97E-8 (a) This table provides typical (+/- 20%) calibration constants for the liquid effluent radiation monitors. S0123-0DCM 1-23 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.5 DOSE CALCULATION FOR LIQUID EFFLUENTS The liquid releases considered in the following dose calculations are described in Section 1.4. The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Specification 1.2.1 using the following expression. D1 (1-16) where: Ai, Site-related adult ingestion dose commitment factor to the total body or an organ. L. for each identified principal gamma and beta emitter. i. from Table 1-4 in mrem/hr per ~Ci/ml. Ci j average concentration of radionuclide. i. in the undiluted liquid effluent during time period. L'lt j

  • in ~Ci/ml.

D dose commitment to the total body or an organ. L. from the liquid effluent for the time period. L'lt j

  • in mrem.

Fj near field average dilution factor (actually mixing ratio) for C;j during the time period. L'lt j

  • This factor is the ratio of the maximum undiluted liquid waste flow during time period.

L'lt j

  • to the average flow from the site discharge structure to unrestricted receiving waters.

maximum liquid radioactive waste flow 1 or: ( discharge structure exit flow 1ength of the jth time period over whi ch Ci j and Fj are averaged for all liquid releases. in hours. S0123-0DCM 1-24 Revision 0 02-27-07

TABLE 1-4 DOSE COMMITMENT FACTORS*, Ai 1 (mrem/hr per ~Ci/ml) Radio- Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+0 3.34E+0 1.23E+0 7.40E+0 1. 40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1. 78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57 1. 42E+2 2.36E+2 3.59E+3 Co-58 6.03E+2 1. 35E+3 1.22E+4 Co-60 1. 73E+3 3.82E+3 3.25E+4 Cu-64 2.14E+2 1.01E+2 5.40E+2 1. 83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Br-84 9.39E-2 7.37E-7 Rb-88 1.79E+0 9.49E-1 2.47E-11 Sr-89 4.99E+3 1. 43E+2 8.00E+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+1 3.71E+0 4.37E+2 Sr-92 3.48E+1 1. 51 E+O 6.90E+2 Y-90 6.06E+0 1.63E-1 6.42E+4 Y-91m 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E-1 1. 56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+0 3.46E+0 8.02E+0 1. 62E+4 Zr-97 8.81E-1 1. 78E-1 8.13E-2 2.68E-1 5.51E+4 Nb-95 1. 84E+0 1. 03E+0 5.51E-1 1.01 E+O 6.22E+3 Nb-95m 1. 84E+0 1. 03E+0 5.51E-1 1.01E+0 6.22E+3 Nb-97 1.55E-2 3.91E-3 1. 43E-3 4.56E-3 1.44E+1 Mo-99 1. 28E+2 2.43E+1 2.89E+2 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 NOTE: where no value is given, no data are available.

  • Source: Reg. Guide 1.109, Table E-11, Table A-I USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S0123-0DCM 1-25 Revision 0 02-27-07

TABLE 1-4 (Continued) DOSE COMMITMENT FACTORS*, Ai, (mrem/hr per ~Ci/ml) Radio- Total nuclide Bone Liver Body Thyroid Kidney Lung GI-LLI Ru-103 1.07E+2 4.60E+1 4.07E+2 1. 25E+4 Ru-106 1. 59E+3 2.01E+2 3.06E+3 1.03E+5 Ag-110m 1.42E+3 1.32E+3 7.82E+2 2.59E+3 5.37E+5 Sn-l13 2.26E+5 Sn-l17m 2.26E+5 Sb-124 2.76E+2 5.22E+0 1. 09E+2 6.70E-1 2.15E+2 7.84E+3 Sb-125 1.77E+2 1.97E+0 4.20E+1 1.79E-1 1. 36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1. 47E+2 3.20E+2 3.89E+3 4.69E+3 Te-132 2.04E+2 1. 32E+2 1. 24E+2 1. 46E+2 1.27E+3 6.24E+3 1-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 1-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 1-133 7.45E+1 1. 30E+2 3.95E+1 1.90E+4 2.26E+2 1.16E+2 1-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 1-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 Cs-134 6.84E+3 1. 63E+4 1. 33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1. 20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1 5.94E+0 8.81E+0 8.70E-1 5.12E-5 Ba-139 7.85E+0 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140 1. 64E+3 2.06E+0 1. 08E+2 7.02E-1 1. 18E+0 3.38E+3 La-140 1.57E+0 7.94E-1 2.10E-1 5.83E+4 Ce-141 3.43E+0 2.32E+0 2.63E-1 1.08E+0 8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1. 97E-1 1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Nd-147 3.96E+0 4.58E+0 2.74E-1 2.68E+0 2.20E+4 W-187 9.16E+0 7.66E+0 2.68E+0 2.51E+3 Np-239 3.53E-2 3.47E-3 1.91E-3 1. 08E-2 7.11E+2 NOTE: where no value is given, no data are available.

  • Source: Reg. Guide 1.109, Table E-11, Table A-I USNRC NUREG-0172, Table 4 ICRP-30, Part 3, Supplement A Methodology: USNRC NUREG-0133, Section 4.3.1 S0123-0DCM 1-26 Revision 0 02-27-07

1.0 LIQUID EFFLUENTS (Continued) 1.6 Representative Sampling Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling in accordance with the requirements of Regulatory Guide 1.21 and NUREG-0800, Section 11.5. The methodology for mixing and sampling is described in SOI23-111-5.23, "Generating Effluent Release Permits Using The Vax Computer" and SOI23-111-5.2.23, "Units 2/3 Liquid Effluents". SOI23-0DCM 1-27 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS 2.1 DOSE RATE SPECIFICATION 2.1.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site (see Figure 2-2) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mremjyr to the total body and less than or equal to 3000 mremjyr to the skin, and
b. For all radioiodines, tritium and for all radioactive materials in particulate form with half lives greater than 8 days: Less than or equal to 1500 mremjyr to any organ.

APPLICABILITY: At all times ACTION:

a. With dose rate(s) exceeding the above limits, immediately decrease the release rate to within the above limit(s).

SURVEILLANCE REQUIREMENTS 

         .1   The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with Section 2.7 .
         .2   The dose rate due to radioiodines, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with Section 2.7 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2-1.

SOI23-0DCM 2-1 Revision 0 02-27-07

TABLE 2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (flCijml)a Batch P P Principal Gamma Emi t t er s" 1x10- 4 Waste Gas Each Tank Each Tank Decay Tank Grab Sample Continuous *

  • Principal Gamma Emi t t er-s? 1x10- 4
                    *
  • Trit i um 1x10- 6 Wd 1-131 1x10- 12 f

Continuous Charcoal Sampler Sample 1-133 1x10- 1O Wd Continuous f Particulate Principal Gamma Emitters 9 1x10- 11 Sampler Sample (1-131 and Others) M Continuousf Composite Gross Alpha 1x10- 11 Sampler Particulate Sample Q Continuousf Compos ite Sr-89 and Sr-90 1x10- 11 Sampler Particulate Sample Continuousf Noble Gas Noble Gases 1x10- 6 Monitor Monitor Gross Beta or Gamma 

                                               *Sampling frequencies for noble gases and tritium are:

CONTINUOUS PATHWAYS: Containment Purge - 42" Each Purgeb,C Containment Purge - 8" Month 1y Greb Condenser Air Ejector Monthly Grab" Plant Vent Stack Weekl y Grab?" South Yard Facility Particulate and Iodine sampling on ly" S0123-0DCM 2-2 Revision 0 02-27-07

TABLE 2-1 (Continued) TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation) : LLD E

  • V
  • 2.22 x 106
  • Y
  • exp (-Mt) where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22 x 10 6 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and 6t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). The value of Sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y and 6t should be used in the calculation. It should be recognized that the LLD is defined as an ~ priori (before the fact) limit representing the capability of the measurement system and not as 

      ~ posteriori (after the fact) limit for a particular measurement.*
  • For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300 (revised annually). (2) Currie, L. A., "Limits for Qual itative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968). (3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972). S0123-0DCM 2-3 Revision 0 02-27-07

TABLE 2-1 (Continued) TABLE NOTATION

b. Analyses shall also be performed on the affected unit and plant vent stack following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a I-hour period. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
c. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded.
d. (i) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler).

(ii) Sampling shall also be performed on the affected unit and plant vent stack at least once per 24 hours for at least 7 days following each shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in 1 hour and analyses shall be completed within 48 hours of changing. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement is not applicable to the South Yard Facility.

e. Tritium grab samples shall be taken at least one per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 2.1, 2.2, 2.3.
g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

h. Radioactive airborne effluents only expected to be particulate and iodine.

S0123-0DCM 2-4 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.2 DOSE - NOBLE GASES SPECIFICATION 2.2.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 2-2) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times ACTION:

a. With calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 2.2.1.

SURVEILLANCE REQUIREMENTS 

         .1   Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.

SOI23-0DCM 2-5 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.3 DOSE - RADIOIODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM SPECIFICATION 2.3.1 The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the Site (see Figure 2-2) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
b. During any calendar year: Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of tritium, radioiodines, and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 2.3.1.

SURVEILLANCE REQUIREMENTS 

         .1   Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.

SOI23-0DCM 2-6 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT SPECIFICATION 2.4.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be operable. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 2-2), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 2-2) when averaged over 31 days would exceed 0.3 mrem to any organ.* APPLICABILITY: At all times ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 5.7.2 and LCS 5.0.104.2, a Special Report which includes the following information:
1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability,
2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 

         .1   Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 3.2.
              *These doses are per reactor unit.

S0123-0DCM 2-7 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT (Continued) SURVEILLANCE REQUIREMENTS (Continued) 2.4.1.2 During plant operation (Modes 1-4), the applicable portions of the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. 

         .3  In plant shut-down (Mode 5, 6), the applicable portions of the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15-minutes prior to processing gases unless the appropriate gaseous radwaste system has been utilized to process radioactive gaseous effluents during the previous 92 days.

SOI23-0DCM 2-8 Revision 0 02-27-07

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SAN ONOFRE NUCLEAR GENERATING STATION SITE BOUNDARY FOR GASEOUS EFFLUENTS Figure 2-2 S0123-0DCM 2-9 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6 Methods of Calculation for Gaseous Effluent Monitor Setpoints Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points: PVS Plant Vent Stack CAE Condenser Air Ejector CP Containment Purge SY =: South Yard WG Waste Gas The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points on site to the environment will not result in a release exceeding the limits of Specification 2.1.1. The sum total of all these administrative values for the site shall be less than or equal to 1.0. The administrative values shall be periodically reviewed based on actual release data and revised as necessary. 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. Total Body The concentration at the detector corresponding to a 500 mrem/yr total body dose rate at the exclusion area boundary is determined by: (2-1) (PVS) (2120 cfm J (500 mrem/yr)(10-6 m3/cc) 3/sec m The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by: (2-2) cfm J (3000 mrem/yr)(10- 6m 3/cc) (PVS) (2120 3/sec m yrJ(2] (flow rate, cfm)(X/Q, sec/m 3) L .(L+1.1M., mrem/ 1 1 1 JiCi/m 3 Ct ot S0123-0DCM 2-10 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 (Continued) where: the instantaneous concentration at the detector, ~Ci/cc PVS an administrative value used to account for potential activity from other gaseous release pathways, typically 0.38. total body dose conversion factor from Table 2-4 for the i t h gamma emitting noble gas, mrem/yr per ~Ci/m3 skin Dose Conversion Factor from Table 2-4 for the i t h noble gas, mrem/yr per ~Ci/m3 air Dose Conversion Factor from Table 2-4 for the i t h noble gas, mrem/yr per ~Ci/m3 1.1 conversion factor to convert gamma air dose to skin dose concentration of the i t h noble gas as determined by sample analysis, ~Ci/cc total concentration of noble gases as determined by sample analysis, ~Ci/cc ~iCi flow rate total plant vent stack flow rate, cfm, typically 164,000 cfm 2120 conversion constant, cfm per m3/sec 500 mrem/yr total body dose rate limit, as specified by Specification 2.1.1.a 3000 mremjyr skin dose rate limit as specified by Specification 2.1.1.a X/Q = historical annual average dispersion factor for any landward sector, sec/m3 4.8E-6 sec/m3 S0123-0DCM 2-11 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.1.1 Maximum Permissible Alarm Setpoint for 2/3RT-7808, 2RT-7865-1 and 3RT-7865-1 The smaller of the values of Cdet from equations (2-1) and (2-2) shall be used to determine the maximum permissible monitor al arm setpoi nt. The maximum release rate (~Ci/sec) for Plant Vent Stack Monitors is determined by converting the concentration at the detector, Cdet (~Ci/cc) to an equivalent release rate in 

                   ~Ci/sec, as follows:

(C de t , ~Ci/cc) (flow rate, cfm) (28320) (2-3) Amax (S) (60) where: maximum permissible release rate, ~Ci/sec sma 11 er of the values of Cdet determi ned in equat ions (2-1) and (2-2). fl ow rate = plant vent stack flow rate (cfm) used in equations (2-1) and (2-2) 28320 conversion from ft 3 to cc 60 conversion from minutes to seconds S correction factor to compensate for the split flow between Unit 2 and Unit 3 Plant Vent Stacks, typically 2 for split stack monitoring and 1 for combined stack monitoring The release rate setpoint shall not be set greater than the maximum release rate determined above, when the monitor is being used to meet the requirements of Specification 2.1.1. S0123-0DCM 2-12 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 2.6.2.1 2RT-7818 and 3RT-7818 Condenser Air Ejector Monitors For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. The concentration at the detector corresponding to a total body dose rate of 500 mrem/yr at the exclusion area boundary is determined by using: Total Body (2-4) (CAE)(O.5)(2120 cfm ) (500 mrem/yr] (10- 6 m3/cc) m3/sec The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by using: Skin where: (CAE) an administrative value used to account for potential activity from other gaseous release pathways, typically 0.1. 0.5 an administrative value used to account for releases from both SONGS 2 and SONGS 3 condenser air ejectors simultaneously. Other parameters are specified in 2.6.1 and/or 2.6.2.2. (2-5) (CAE)(O.5)(2120 cfm ) ( 3000 mrem/yr) 3/sec (10- 6 m3/cc) m S0123-0DCM 2-13 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 (Continued) The smaller of the values Cdet from equations (2-4) or (2-5) is to be used in determining the maximum permissible monitor alarm setpoint (cpm), as follows: The maximum permissible alarm setting (cpm) is determined by using the calibration constant for the corresponding Condenser Evacuation System Monitor given in Table 2-3. The maximum permissible alarm setpoint is the cpm value corresponding to the concentration, Cdet> [smaller value from equation (2-4) or (2-5)] . The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (higher value in terms of ~Ci/cc/cpm). The alarm setpoint will not be set greater than the maximum permissible alarm setting determined above. 2.6.2.2 2RT-7870-1 and 3RT-7870-1 Wide Range Gas Monitors The maximum release rate (~Ci/sec) for Wide Range Gas Monitor is determined by converting the concentration at the detector, Cdet (~Ci/cc), to an equivalent release rate in ~Ci/sec. (Cdet> ~Ci/cc) (flow rate, cc /sec) (2-6) where: maximum permissible release rate, ~Ci/sec sma 11 er value of Cdet> as obtained from equations (2-4) and (2-5) flow rate flow rate of the condenser air ejector, cc/sec 4.719E5 cc/sec (conservatively assumed as design flow rate) S0123-0DCM 2-14 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. NOTE: 2(3)RT-7865 is not designed to monitor main purge. The concentration at the detector corresponding to a total body dose rate of 500 mrem/yr at the exclusion boundary is determined by using: Total Body (2-7) (CP) (P2 ) ( 2120 cfm] ( 500 mrem/yr) 3/sec (10- 6 m3/cc) m (Flow rate, cfm) (X/Q, sec/m 3) L:; (K i , mre.m/ IlC, /m y; 

                                                                              ]  (~))

Ct ot (2-8) (CP)(P)( 2120 cfm J ( 500 mrem/yr] (10- 6 m 3/cc) m3/sec The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by using: (2-9) (CP) (P 2 ) ( 2120 cfm 3/sec J ( 3000 mrem/yr-) (10 6 m3/cc) m (Flow rate, cfm) (X/Q, sec/m 3) [L:. (L + l.IM, mrem/yr J (~)) 1 1 1 Il C*, / m3 C tot SOI23-0DCM 2-15 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 (Continued) (2-10) (CP)(P)(2120 cfm J (3000mremjyr)(10 6m 3jcc) m3jsec (Flow rate, cfm) (XjQ, secjm 3) l:. 1 (L. 1 

                                                  + l.lM., mremjyr]

1 C* j 3 (~)) C 

                                                           ~ 1 m        tot where:

instantaneous concentration of the Unit 2 detector, ~Cijcc. instantaneous concentration of the Unit 3 detector, ~Cijcc. CP administrative value used to account for potential activity from other gaseous release pathways, typically 0.38. Pz and P3 are administrative values used to account for simultaneous purges of both SONGS 2 and SONGS 3. The fractions Pz and P3 wi 11 be assigned such that Pz + P3 ~ 1.0. Flow rate observed maximum flowrate in cfm from the unit specific monitor 7828. Default values will be the folloWing conservative measured flows: 50,000 cfm main purge [2(3)RT-7828 only] 3,000 cfm mini-purge (The above values replace the smaller design fl owrates.) Other parameters are as specified in 2.6.1 above. The smaller of the values of maximum permissible Cdet Z from equation (2-7) or (2-9) and Cdet3 from equations (2-8) or (2-10) is to be used in determining the maximum permissible monitor alarm setpoints. S0123-0DCM 2-16 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT-7865-1, 3RT-7865-1 (Continued) 2.6.3.1 Maximum Permissible Alarm Setting for 2(3)RT-7865-1 The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate (~Ci/sec) is determi ned by convert i ng the concent rat i on at the detector, Cdet (~Ci/cc),to an equivalent release rate in ~Ci/sec. (Cdet> ~Ci/cc) (flow rate, cc /sec) (2-6) where: maximum permissible release rate, ~Ci/sec smaller value of Cdet> as obtained from equation (2-7, 2-9) for Unit 2 or (2-8, 2-10) for Unit 3. fl ow rate flow rate, cc/sec 1.416E6 cc/sec for mini-purge . 

              . 2 Maximum Permissible Alarm Setting (RT-7828)

The maximum permissible alarm setting for RT-7828 is in ~Ci/cc and is the smaller of the values of Cdet (~Ci/cc) from equations (2-7) and (2-9) for Unit 2 or equations (2-8) and (2-10) for Un it 3. S0123-0DCM 2-17 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865-1. 2/3RT-7808 For the purpose of Specification 2.1.1. the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. Since the waste gas header discharges to the plant vent stack. either 3RT-7865-1 or 2/3RT-7808 may be used to monitor waste gas header releases. The concentration at the detector corresponding to a total body dose rate of 500 mrem/yr or a skin dose rate of 3000 mrem/yr at the exclusion area boundary is determined by using equations (2-1) or (2-2) with sample concentration (CJ and (C t ot ) being obtained from the waste gas decay tank to be released. 2.6.4.1 Maximum Permissible Alarm Setpoint for 3RT-7865-1 and 2/3RT-7808 The smaller of the values of Cdet from equations (2-1) and (2-2) shall be used to determine the maximum permissible monitor alarm setpoint. The maximum release rate (pCi/sec) for Plant Vent Stack Monitors is determined by converting the concentration at the detector. Cdet (pCi Icc) to an equi va1ent rel ease rate in pCi/sec. as follows: (C de t

  • pCi/cc) (flow rate. cfm) (28320) (2-3)

Amax (S) (60) where: maximum permissible release rate. pCi/sec sma 11 er of the values of Cdet determi ned in equat ions (2-1) and (2-2) flow rate plant vent stack flow rate (cfm) used in equations (2-1) and (2-2) 28320 conversion from ft 3 to cc 60 conversion from minutes to seconds S correction factor for 3RT-7865-1 viewing only half the total plant vent stack flow. typically 2 for 3RT-7865-1 and 1 for 2/3RT-7808. S0123-0DCM 2-18 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865-1, 2/3RT-7808 (Continued) 2.6.4.2 A release from the waste gas header is not possible if: (2-11) where: total gamma activity (~Ci/cc) of the waste gas holdup tank to be released, as determined from the pre-release sample analysis f waste gas header effluent flow rate, cfm F = plant vent stack flowrate (cfm) used in equations (2-1) and (2-2) sma 11 er of the values of Cdet determi ned in equations (2-1) and (2-2) with C being obtained j from the waste gas holdup tank to be released If a release is not possible, adjust the waste gas header fl ow by determining the maximum permissible waste gas header effluent flow rate corresponding to the Plant Vent Stack Monitor setpoint in accordance with the follOWing: (2-12) (WG) (Cd t) (F) f < e I: i Ci where: f waste gas header effluent flow rate (cfm) F plant vent stack flow rate (cfm) used in equation (2-1) or (2-2) Cdet smaller of the value of Cdet from equation (2-1) or (2-2) I:;C j = total gamma activity (~Ci/cc) of the waste gas holdup tank to be released, as determined from the pre-release sample analysis. WG an administrative value to account for the potential activity from other releases in the same release pathway, typically 0.9. S0123-0DCM 2-19 Revision 0 02-27-07

Table 2-3 Gaseous Effluent Radiation Monitor Calibration Constants(a) (pCi jccjcpm) MONITOR Kr-85 Xe-133 2RT-7818A 4.27E-8 6.86E-8 3RT-7818A 3.73E-8 5.12E-8 (a)This table provides typical (+/-20%) calibration constants for the gaseous effluent radiation monitors. S0123-0DCM 2-20 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.7 Gaseous Effluent Dose Rate The methodology used for the purpose of implementation of Specification 2.1.1 for the dose rate above background to an individual in an unrestricted area is calculated by using the following expressions: 2.7.1 FOR NOBLE GASES: (2-13) DTB 6. 1 [K i (X/Q) OJ ] (2-14) D5 6. 1 [ u, , 1. 1M.) 1 (XjQ) Q.1 where: total body dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mremjyr skin dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mremjyr the total body dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mremjyr per ~Cijm3 skin dose factor due to the beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mremjyr per ~Cijm3 air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mradjyr per ~Cijm3 (conversion constant of 1.1 mremjmrad converts air dose to skin dose.) measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, in ~Cijsec (XjQ) = Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary. 4.8E-6 secjm3 for Units 2 and 3 8.0E-5 secjm3 for South Yard Facility SOI23-0DCM 2-21 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.7.2 FOR ALL RADIOIODINES, TRITIUM AND FOR ALL RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIGHT DAYS: (2-15) where: Do organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem/yr measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, IlCi/sec dose parameter for radionuclide, i, for pathway, k, from Table 2-5 for the inhalation pathway in mrem/yr per IlCi/m3. The dose factors are based on the critical individual organ and the child age group. highest calculated annual average dispersion (X/Q) or deposition (ITlQ) factor for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k. 

                     =     (X/Q), 4.8E-6 sec/m3 for Units 2/3 for the inhalation pathway. The location is the unrestricted area in the NW sector.

(XlQ), 8.0E-5 sec/m3 for South Yard Facility for the inhalation pathway. The location is the unrestricted area in the E sector. (XlQ), 1.3E-5 sec/m3 for the NIA (Unit 1) for the inhalation pathway. The location is the unrestricted area in the NW sector. (Historical value) 

                     =     (DlQ), 4. 3E-8 m- 2 for Uni ts 2/3 for the food and ground plane pathways. The location is the unrestricted area in the E sector.

(DlQ), 8.0E-7 m- 2 for South Yard Facility for the food and ground plane pathways. The location is the unrestricted area in the E sector. (070), 7.2E-8 sec/m3 for NIA (Unit 1) for the food and ground pathways. The location is the unrestricted area in the NW sector. (Historical value) S0123-0DCM 2-22 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8 Gaseous Effluent Dose Calculation 2.8.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENTS The gaseous releases considered in the following dose calculations are described in Section 2.6. The air dose in unrestricted areas due to noble gases released in gaseous effluents is calculated using the following expressions: 2.8.1.1 For historical meteorology: (2-16) Dv = 3.17x10 -8 L;. 1 M.1 [(X/Q)Q.]1 (2-17) where: D.I total gamma air dose from gaseous effluents. mrad Dr; = total beta air dose from gaseous effluents. mrad 3.17x10-s inverse seconds per year M; air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide. i. in mrad/yr per ~Ci/m3 air dose due to beta emissions from Table 2-4 for each identified noble gas radionuclide. i. in mrad/yr per 

                           ~Ci/m3 (X/Q)         Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary.

4.8E-6 sec/m3 for Units 2 and 3 8.0E-5 sec/m3 for South Yard Facility amount of noble gas radionuclide. i. released in gaseous effluents. ~Ci. S0123-0DCM 2-23 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8.1.2 For meteorology concurrent with release: NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, quality affecting computer software is used to perform the actual calculations. (2-18) Dye (2-19) where: 

                                =   total gamma air dose from gaseous effluents in sector e, mrad
                                =   total beta air dose from gaseous effluents in sector e, mrad 1.14x10-4          inverse hours/year air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad/yr per pCi/m 3 air dose factor due to beta emissions from Table 2-4 for each identified noble gas radionuclide, i, in mraa/yr per pCi/m 3 length of the jth time period over which (X/O) j and OiJ are averaged for gaseous releases in hours (X/O) j'i         atmospheric dispersion factor for time period 6t J at exclusion boundary location in landward sector e determined by concurrent meteorology, sec/m3 average release rate of radionuclide, i, in gaseous effluents during time period, 6t j ,

pCi/sec S0123-0DCM 2-24 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2 DOSE FROM TRITIUM, RADIOIODINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS The dose to an individual from tritium, radioiodines and radioactive materials in particulate form with half lives greater than eight days in gaseous effluents released to unrestricted areas is calculated using the following expressions: 2.8.2.1 For historical meteorology: (2-20) where: total projected dose from gaseous effluents to an individual, mrem 3.17x10-8 year/second amount of each radionuclide, i, (tritium, radioiodine, radioactive material in particulate form with half lives greater than eight days), released in gaseous effluents, ~Ci sum of all pathways, k, for radionuclide, i, of the R; Wproduct, in mrem/yr per ~Ci/sec. The L:kR;kWk value for each radionuclide, i, is given in Table 2-6 for Units 2/3, Table 2-7 for South Yard Facility, and Table 2-8 for the North Industrial Area (Unit 1 historical value). The value given is the maximum L:kRikW k for all locations and is based on the most restrictive age groups. dose factor for each identified radionuclide, i, for pathway k, (for the i nha 1at i on pathway in mrem/yr per ~Ci/m3 and for the food and ground plane pathways in m2-mrem/yr per ~Ci/sec), at the controlling location. The R;k'S for each controlling location for each age group are given in Appendix A. Data in these tables are derived using the NRC code, PARTS. (See the annual update of revised R; parameters based on changes in the Land Use Census provided by Corporate Health Physics and Environmental.) S0123-0DCM 2-25 Revision 0 02-27-07

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2.1 For historical meteorology: (Continued) Wk annual average dispersion (X/Q) or deposition (D/Q) factor for estimating the dose to an individual at the controlling location for pathway k. (X/Q~or the inhalation pathway in sec/m3. The (X/Q) for each controlling location is given in Appendix A. (D/Q~or the food and ground plane pathways in m- 2

  • The (D/Q) for each cont ro11 i ng 1ocat ion is gi ven in Appendix A.

2.8.2.2 For meteorology concurrent with releases: NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations. quality affecting computer software is used to perform the actual calculations. (2-21) where: 1.14 X 10' i'~~ [(6t j J (Rile)(WjkO)( ~J ] o total annual dose from gaseous effluents to an individual in sector e. mrem. 1ength of the r" peri od over whi ch Wjkc; and Qij are averaged for gaseous released. hours average release rate of radionuc1ide. i. in gaseous effluents during time period 6t j* ~Ci/sec dose factor for each identified radionuc1ide i. for pathway k for sector e (for the inhalation pathway in mrem/yr per ~Ci/m3 and for the food and ground plane pathways in m2 mrem/yr per ~Ci/sec) at the controlling location. A listing of Rik for the controlling locations in each landward sector for each group is given in Appendix A. The e is determined by the concurrent meteorology. dispersion (X/Q) or deposition (D/Q) factor for the time period 6t~ for each pathway k for calculating the dose to an indlvidua1 at the controlling location in sector e using concurrent meteorological conditions. (XLQ) for the inhalation pathway. sec/m3 (D/Q) for the food and ground plane pathways. m- 2 S0123-0DCM 2-26 Revision 0 02-27-07

TABLE 2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS** Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor K; Factor l., Factor Mi Factor N; Radio- (mremjyr (mrem/yr (mrad/yr (mradjyr Nuclide per j1Ci 1m 3 ) per j1Ci 1m 3 ) per j1Ci 1m 3 ) per j1Ci 1m 3 ) Kr-85m 1.17E+3 1.46E+3 1. 23E+3 1.97E+3 Kr-85 1.61E+1 1.34E+3 1. 72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1. 03E+4 Kr-88 1.47E+4 2.37E+3 1. 52E+4 2.93E+3 Xe-131m 9.15E+1 4.76E+2 1. 56E+2 1. 11E+3 Xe-133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 Xe-135m 3.12E+3 7.11E+2 3.36E+3 7.39E+2 Xe-135 1.81E+3 1.86E+3 1.92E+3 2.46E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3 4.75E+3 Ar-41 8.84E+3 2.69E+3 9.30E+3 3.28E+3

    • Source: USNRC Reg. Guide 1.109, Table B-1 S0123-0DCM 2-27 Revision 0 02-27-07

TABLE 2-5 DOSE PARAMETER Pi / CHILD AGE GROUP CRITICAL ORGAN Inhalation Pathway Inhalation Pathway Radionuclide (mrem/yr per pCi 1m 3 ) Radionuclide (mrem/yr per pCi 1m 3 ) H- 3 1.1E+3 I -131 1.6E+7 Cr-51 1.7E+4 I -132 1.9E+5 Mn-54 1.6E+6 I -133 3.8E+6 Co-57 5.1 E+5 I -134 5.1E+4 Co-58 1.1 E+6 I -135 7.9E+5 Co-60 7.1E+6 Cs-134 1. OE+6 Sr-89 2.2E+6 Cs-136 1. 7E+5 Sr-90 1. OE+8 Cs-137 9.1E+5 Zr-95 2.2E+6 Ba-140 1. 7E+6 Nb-95 6.1E+5 Ce-141 5.4E+5 Ru-l03 6.6E+5 Ce-144 1.2E+7 Te-129m 1.8E+6

  • Source: USNRC NUREG-0133, Section 5.2.1.1 SOI23-0DCM 2-28 Revision 0 02-27-07

TABLE 2-6 UNITS 2&3 CONTROLLING LOCATION FACTORS 1 6k RikWk Radionuclide mrem/yr per tlCi/sec Use: H -3 3.55E-3 R: Camp Mesa Cr-51 1.47E-1 R: Camp Mesa Mn-54 3.05E+1 R: Camp Mesa Co-57 6.59E+0 R: Camp Mesa Co-58 1.09E+1 R: Camp Mesa Co-60 4.24E+2 R: Camp Mesa Sr-89 1. 68E+ 1 Q: SC Res. with Garden Sr-90 6.60E+2 Q: SC Res. with Garden Zr-95 1. 21E+1 R: Camp Mesa Nb-95 1.07E+1 E: Deer Consumer/Hunter Ru-103 1.69E+1 E: Deer Consumer/Hunter Te-129m 7.67E+0 E: Deer Consumer/Hunter Cs-134 1. 30E+2 R: Camp Mesa Cs-136 2.80E+0 R: Camp Mesa Cs-137 1.95E+2 R: Camp Mesa Ba-140 5.95E+0 R: Camp Mesa Ce-141 1.95E+0 R: Camp Mesa Ce-144 3.83E+1 R: Camp Mesa I -131 4.47E+1 R: Camp Mesa I -132 5.79E-1 R: Camp Mesa I -133 1.08E+1 R: Camp Mesa I -134 1.49E-1 R: Camp Mesa I -135 2.27E+0 R: Camp Mesa UN-ID 1.75E+1 R: Camp Mesa These values to be used in manual calculations are the maximum 6kRikWk for all locations based on the most restrictive age group. S0123-0DCM 2-29 Revision 1 02-29-08

TABLE 2-7 SOUTH YARD FACILITY CONTROLLING LOCATION FACTORS 1 L: kRikWk Radionuclide mrem/yr per fiCi /sec Use: H -3 1.31E-3 G: San Onofre Bch Campgd Cr-51 4.15E-2 F: SO St. Pk./Guard Shack Mn-54 9.70E+0 F: SO St. Pk./Guard Shack Co-57 2.4lE+0 F: SO St. Pk./Guard Shack Co-58 3.14E+0 F: SO St. Pk./Guard Shack Co-60 1.35E+2 F: SO St. Pk./Guard Shack Sr-89 1. 71E+O F: Deer Consumer/Hunter Sr-90 1. 04E+2 G: San Onofre Bch Campgd Zr-95 7.26E+0 F: Deer Consumer/Hunter Nb-95 2.88E+1 F: Deer Consumer/Hunter Ru-103 4.56E+1 F: Deer Consumer/Hunter Te-129m 2.26E+1 F: Deer Consumer/Hunter Cs-134 4.28E+1 F: SO St. Pk./Guard Shack Cs-136 1. 04E+0 F: SO St. Pk./Guard Shack Cs-137 6.36E+1 F: SO St. Pk./Guard Shack Ba-140 1.39E+0 G: San Onofre Bch Campgd Ce-141 4.29E-1 G: San Onofre Bch Campgd Ce-144 8.39E+0 G: San Onofre Bch Campgd I -131 2.28E+1 F: Deer Consumer/Hunter I -132 1. 22E-1 G: San Onofre Bch Campgd I -133 2.22E+0 G: San Onofre Bch Campgd I -134 3.24E-2 G: San Onofre Bch Campgd I -135 4.60E-1 G: San Onofre Bch Campgd UN-ID 5.36E+0 F: SO St Pk./Guard Shack These values to be used in manual calculations are the maximum L:kRikW k for all locations based on the most restrictive age group. S0123-0DCM 2-30 Revision 0 02-27-07

TABLE 2-8 NORTH INDUSTRIAL AREA (UNIT 1) CONTROLLING LOCATION FACTORS l LkRikWk Radionuclide mrem/yr per j1Ci /sec Use: H -3 5.46E-3 A: Camp Mesa Cr-51 2.42E-1 B: Camp Mesa Mn-54 5.54E+1 B: Camp Mesa Co-57 1.17E+1 B: Camp Mesa Co-58 1. 80E+ 1 B: Camp Mesa Co-60 7.82E+2 B: Camp Mesa Sr-89 1. 82E+ 1 Q: SC Res. with Garden Sr-90 7.16E+2 Q: SC Res. with Garden Zr-95 1.93E+1 A: Camp Mesa Nb-95 7.68E+0 B. Camp Mesa Ru-103 1.09E+1 E: Deer Consumer/Hunter Te-129m 9.04E+0 A: Camp Mesa Cs-134 2.32E+2 B: Camp Mesa Cs-136 5.17E+0 B: Camp Mesa Cs-137 3.40E+2 B: Camp Mesa Ba-140 9.07E+0 A: Camp Mesa Ce-141 3.01E+0 A: Camp Mesa Ce-144 5.68E+1 A: Camp Mesa I -131 6.77E+1 A: Camp Mesa I -132 8.36E-1 A: Camp Mesa I -133 1.60E+1 A: Camp Mesa I -134 2.29E-1 A: Camp Mesa I -135 3.40E+0 A: Camp Mesa UN-ID 3.02E+1 B: Camp Mesa These values to be used in manual calculations are the maximum LkRikWk for all locations based on the most restrictive age group. S0123-0DCM 2-31 Revision 0 02-27-07

3.0 PROJECTED DOSES 3.1 Liquid Dose Projection The methodology used for projecting a liquid dose over 31 days for Specification 1.3.1 is as follows:

1. Determine the monthly total body and organ doses resulting from releases during the previous twelve months.
2. Projected dose = Previous 12 months' dose divided by 12 for the total body and each organ.

3.2 Gaseous Dose Projection The methodology used for projecting a gaseous dose over 31 days for Specification 2.4.1 is as follows:

1. Determine the monthly gamma, beta and organ dose resulting from releases during the previous twelve months.
2. Projected dose = Previous 12 months' dose divided by 12 for the gamma, beta and organ doses.

S0123-0DCM 3-1 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.3 TOTAL DOSE SPECIFICATION 3.3.1 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. APPLICABILITY: At all times ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 1.2.1.a, 1.2.1.b, 2.2.1.a, 2.2.1.b, 2.3.1.a, or 2.3.1.b in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.3.1. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release(s) covered by this report. If the estimated dose(s) exceeds the limits of Specification 3.3.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed elsewhere in this ODCM.

SURVEILLANCE REQUIREMENTS 

         .1  Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance 1.2.1.1, 2.2.1.1, and 2.3.1.1.

S0123-0DCM 3-2 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS 3.4.1 Total Dose to Most Likely Member of the Public The total annual dose or total dose commitment to any member of the public, due to releases of radioactivity and to radiation, from uranium fuel cycle sources within 5 miles of the Site is calculated using the following expressions. This methodology is used to meet the dose limitations of 40 CFR 190 per twelve consecutive months. The transportation of radioactive material is excluded from the dose calculations. The Annual Total Dose is determined monthly for maximum organ (gas & liquid), whole body (gas & liquid) and thyroid (gas & liquid) to verify that the Site total is less than or equal to 25 mrem, 25 mrem, and 75 mrem respectively . 

           .1   Annual Total Organ Dose          (DTQT (0))

(3-1) where: 

          *NOTE: D~-{OG) = 0 for bone
         **All to be summed over the most recent 12 months.

n Dj 1 (OG) = K L: c, L k Ri k Wk (3-2) i =1 each isotope in specific organ category j NIA, Unit 2 and Unit 3 months 1 - 12** K 3.1688 E-2 year-pCi sec -Ci S0123-0DCM 3-3 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total Dose to Most Likely Member of the Public (Continued) n number of isotopes in the specified organ category total particulate gas curies released for the month 2.: rikW k SONGS controlling location factors (Tables 2-6, k 2-7 or 2-8). Dj l (OL) liquid organ dose for the specified organ in mrem for the month. [equation (1-16)] gas organ dose from tritium in mrem for the month. Lequation (2-15)] 

                  .2        Annual Total Whole Body Dose DTOTJ1lIU.

12 2/3 (3-3) 

                           =   2.:       .2.: [Dj1(WBL) + Dj~-3(OG) + 0.9 Dj1 (y)] +D(DIRECT) 1=1      J=1 where:

j NIA, Unit 2 and Unit 3 months 1 - 12, to be summed over the most recent 12 months Dj l (WBL) liquid whole body organ dose in mrem for the whole month. [equation (1-16)] gas organ dose from tritium in mrem for the month. Lequation (2-15)] gamma air dose in mrad for the month. 0.9 converts mrad to mrem. [equation (2-16)] n (3-4) 4 2.: D(bkgd) i p=1 D (Direct) 2.: max[D(beach)]1 - .0342 n q =1 p for all TLDs per quarter q for Quarters 1-4 S0123-0DCM 3-4 Revision 0 02-27-07

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Annual Total Whole Body Dose 0TOTiHIll (Continued) 

                        *Oirect Radiation The direct radiation levels are evaluated most recently using thulium doped TLOs. The TLOs are placed at a minimum of 30 locations around the site. The average dose measured by TLOs 5 to 50 miles from the site is used as background. These sites are subject to change.

The background is subtracted from the highest reading TLO within 5 miles of the site (generally numbers 55 through 58). This value is the direct dose but must be prorated by the occupancy factor. Example: Beach time (west boundary, seawall) of 300 hrs/yr, east and north boundaries of 20 hrs/yr, or 8 hrs/yr for the south boundary and west fence of parking lot 1 (top of bluff).

Reference:

E. M. Goldin Memorandum for File, "Occupancy Factors at San Onofre Owner Controlled Area Boundaries," dated October 1, 1991 . 

                    .3     Annual Total Thyroid Dose 0TOT-.Ul 12  2/3 0TOT (T)      L: . L:   [OJ (OG) + OJ] (OL)]

1=1 J=l (3-5) where: j NIA, Unit 2 and Unit 3 months 1 - 12, to be summed over the most recent 12 months 0jl (OG) thyroid organ dose from gaseous iodine for the month in mrem. [equation (2-20)] liquid thyroid organ dose for the month in mrem. [equation (1-16)] S0123-00CM 3-5 Revision 0 02-27-07

4.0 EQUIPMENT 4.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Section 1.4. APPLICABILITY: At all times ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-1. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument(s) remain inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
c. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-1 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-2, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

SURVEILLANCE REQUIREMENTS 

         .1   Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-2 .
          .2  At least once per 12 hours and within 1 hour after a change in pump operation that affects dilution flow has been completed, all pumps required to be providing dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilution to the discharge structure.

SOI23-0DCM 4-1 Revision 0 02-27-07

TABLE 4-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* OPERABLE ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Effluent Line - 2/3RT-7813 1 28
b. Steam Generator Blowdown Processing System (Neutralization Sump) 1 29 Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817
c. Turbine Plant Sumps, Auxiliary Building Sump 1 30 Com)onent Cooling Water Sumps, Storage Tank Area Sumps Eff uent Line - 2(3)RT-7821
d. Steam Generator (E088) Blowdown Effluent Line - 2(3)RT-6759 1 29
e. Steam Generator (E089) Slowdown Effluent Line - 2(3)RT-6753 1 29
f. Yard Drain Sump - RT-2101 1 44
2. PROCESS FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line 1 31
b. Steam Generator Blowdown Processing System (Neutralization Sump),

Full Flow Condensate Polisher Effluent Line 1 31

c. Turbine Plant Sumps, Auxiliary BUilding Sump Com)onent Cooling Water Sumps, Storage Tank Area Sumps Eff uent Line 1 31
d. Steam Generator (E088) Slowdown Bypass Effluent Line 1 31
e. Steam Generator (E089) Blowdown Bypass Effluent Line 1 31
f. Yard Drain Sump Effluent Line 1 31 S0123-0DCM 4-2 Revision 0 02-27-07

TABLE 4-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* OPERABLE ACTION

3. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 1 32
4. UNIT 2 PLANT COMPUTER SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 1 32
5. CONTINUOUS COMPOSITE SAMPLERS
a. Turbine Plant Sump, Auxiliary Building Sumps - 2(3) APC 5887 1 33
b. Blowdown Processing System Neutralization Sump - 2(3) APC 3772 1 33
c. Steam Generator ~E088~ Blowdown to By)ass, Steam Generator E088 Blowdown - 2(3 APC 4077 1 33
d. Steam Generator ~E089~ Blowdown to By)ass, Steam Generator E089 Blowdown - 2(3 APC 4076 1 33 S0123-0DCM 4-3 Revision 0 02-27-07

TABLE 4-1 (Continued) TABLE NOTATION

  • Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i .e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 1.1.1 and
b. At least two technically qualified members of the Facility Staff independently verify the release rate calculation and discharge line va1ving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10- 7 mi crocuri es/gram:

a. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT 1-131;
b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram DOSE EQUIVALENT 1-131; or
c. Lock closed valve S2(3)1318MU577 and divert flow to T-064 for processing as liqUid radwaste.

ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue prOVided that, at least once per 12 hours, grab samples are collected and analyzed within 4 hours of collection time for gross radioactivity (beta or gamma) at a limit of detection of at least 10- 7 microcuries/m1 or lock closed valve S2(3)2419MU077 or S2(3)2419MU078 and divert flow to the radwaste sump for processing as liquid radwaste. S0123-0DCM 4-4 Revision 0 02-27-07

TABLE 4-1 (Continued) TABLE NOTATION ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the process flow rate is estimated at least once per 12 hours during actual releases. In addition, a new flow estimate shall be made within 1 hour after a change that affects process flow has been completed. Pump curves may be used to estimate process flow. Loss of process flow instrument(s) results in the associated gross activity monitor becoming INOPERABLE. Perform the compensatory action for the inoperable gross activity monitor in addition to this compensatory action. [2(3)RT-7817, 2(3)RT-7821, 2/3RT-7813] ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the monitor is verified OPERABLE by performing a channel check at least once per 4 hours during actual releases. ACTION 33 - With the number of channels OPERABLE less than required by the Minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are collected daily, and composited and analyzed weekly:

a. at least once per 24 hours, not to exceed 30 hours
b. at least once per 12 hours for steam generator when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT 1-131.

ACTION 44 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours, grab samples are collected and analyzed within 4 hours of collection time for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10- 7 microcurie/ml). S0123-0DCM 4-5 Revision 0 02-27-07

TABLE 4-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNELS FUNCTIONAL INSTRUMENT** CHECK CHECK CALI BRATI ON TEST

1. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Effluents Line - 2/3RT-7813 D P R(2) Q(1)
b. Steam Generator Blowdown Processing System (Neutralization Sump), Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 D M R(2) Q(1)
c. Turbine Plant Sump, Auxiliary Building Sum~,

Component Cooling Water Sum~s, Storage Tan Area Sumps Effluent Line - 2(3)R -7821 D M R(2) Q(1)

d. Steam Generator (E088) Blowdown Bypass Effluent Line - 2(3)RT-6759 D M R(2) Q(1)
e. Steam Generator (E089) Blowdown Bypass Effluent Line - 2(3)RT-6753 D M R(2) Q(1)
f. Yard Drain Sump Effluent Line - RT-2101 D M R(2) Q(1)
2. PROCESS FLOW RATE MEASUREMENT DEVICES
a. Liquid Radwaste Effluent Line D(3) N/A R Q
b. Steam Generator Blowdown Processing System (Neutralization Sump), Full Flow Condensate Polisher Effluent Line D(3) N/A R Q
c. Turbine Plant Sump, Auxiliary Building Sum~,

Component Cooling Water Sumps, Storage Tan Area Sumps Effluent Line D(3) N/A R Q

d. Steam Generator (E088) Blowdown Bypass Effl uent Line D(3) N/A R Q
e. Steam Generator (E089) Blowdown Bypass Effl uent Line D(3) N/A R Q
f. Yard Drain Sump Effluent Line D(3) N/A R Q S0123-0DCM 4-6 Revision 0 02-27 -07

TABLE 4-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNELS FUNCTIONAL INSTRUMENT** CHECK CHECK CALIBRATION TEST

3. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM D N/A N/A(4) Q ANNUNC IATI ON)
4. UNIT 2 PLANT COMPUTER SYSTEM (CONTROL ROOM ANNUNCIATION) D N/A N/A Q
5. CONTINUOUS COMPOSITE SAMPLERS
a. Turbine Plant Sump, Auxiliary building Sumps -

2(3) APC 5887 D(5) N/A R Q

b. Blowdown Processing System Neutralization Sump -

2(3) APC 3772 D(5) N/A R Q

c. Steam Generator (E088) Slowdown to By)ass, Steam Generator (E088) Slowdown - 2(3 APC 4077 D(5) N/A R Q
d. Steam Generator (E089) Blowdown to By)ass, Steam Generator (E089) Blowdown - 2(3 APC 4076 D(5) N/A R Q S0123-0DCM 4-7 Revision 0 02-27-07

TABLE 4-2 (Continued) TABLE NOTATION

    • Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway iso1ationt, and Control Room alarm annunciation if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.
2. Circuit failure.

t Automatic pathway isolation is tested on a once per refueling period. Down scale failure testing is bounded by administrative limitation on monitor setpoint which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation. If the instrument controls are not in the operate mode, procedures shall require that the channel be declared inoperable. (2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONs, sources that have been related to the initial calibration shall be used. (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. (4) The Data Acquisition System (DAS) software and hardware do not require Channel Calibration. The DAS software is quality affecting and controlled by the site Software Modification Request process under procedure S0123-V-4.71, Software Development and Maintenance. The DAS hardware is installed plant equipment and controlled by the site design change process utilizing procedure S0123-XXIX-2.10, Design Change Process or S0123-XXIV-IO.l, Field Change Notice (FCN) and Field Interim Design Change Notice (FIDCN). (5) CHANNEL CHECK shall consist of verifying compositor switch positions and installed counter setting, and comparing integrator readings to sample volume co11 ected. S0123-0DCM 4-8 Revision 0 02-27-07

4.0 EQUIPMENT 4.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.2.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 4-3 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with ODCM. APPLICABILITY: At all times ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-3. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument(s) remain inoperable for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
c. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-3 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-4, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

SURVEILLANCE REQUIREMENTS 

         .1   Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-4.

S0123-0DCM 4-9 Revision 0 02-27-07

TABLE 4-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** OPERABLE APPLICABILITY ACTION

1. WASTE GAS HOLDUP SYSTEM
a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2/3RT-7808, or 3RT-7865-1 1
  • 35
b. Process Flow Rate Monitoring Device 1
  • 36a
2. CONDENSER EVACUATION SYSTEM
a. Noble Gas Activity Monitor - 2(3)RT-7818, or 2(3)RT-7870-1 1 ** 37
b. Iodine Sampler 1 ** 40
c. Particulate Sampler 1 ** 40
d. Associated P&I Sample Flow Measuring Device 1 ** 36b
e. Process Flow Rate Monitoring Device 1 (l) ** 36a
3. PLANT VENT STACK
a. Noble Gas Activity Monitor - 2/3RT-7808, or 2RT-7865-1 and 3RT-7865-1 1(2)
  • 37
b. Iodine Sampler 1(2)
  • 40
c. Particulate Sampler 1(2)
  • 40
d. Associated P&I Sample Flow Measuring Device 1(2)
  • 36b
e. Process Flow Rate Monitoring Device - 2/3RT-7808, or 2RT-7865-1 and 3RT-7865-1 1
  • 36a
4. CONTAINMENT PURGE SYSTEM
a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2(3)RT-7828, or 2(3)RT-7865-1 1
  • 38
b. Iodine Sampler 1
  • 40
c. Particulate Sampler 1
  • 40
d. Associated P&I Sample Flow Measuring Device 1
  • 36b
e. Process Flow Rate Monitoring Device 1
  • 36a
5. DATA ACQUISITION SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) 1
  • 42 S0123-0DCM 4-10 Revision 0 02-27-07

TABLE 4-3 (Continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** OPERABLE APPLICABILITY ACTION

6. SOUTH YARD FACILITY (SYF) WORK AREA SYFRU-7904
a. Iodine Sampler 1
  • 40
b. Particulate Sampler 1
  • 40
c. Associated P&I Sample Flow Measuring Device 1
  • 41b
d. Process Flow Rate Monitoring Device 1
  • 41a
7. SOUTH YARD FACILITY (SYF) DECONTAMINATION UNIT SYFRU-7905
a. Iodine Sampler 1
  • 40
b. Particulate Sampler 1
  • 40
c. Associated P&I Sample Flow Measuring Device 1
  • 41b
d. Process Flow Rate Monitoring Device 1
  • 41a S0123-0DCM 4-11 Revision 0 02-27-07

TABLE 4-3 (Continued) TABLE NOTATION

  • Atall time s .
**   MODES 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.
      • Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) 2(3)RT-7818 is not equipped to monitor process flow. If another means of continuously monitoring process flow is not available, then comply with ACTION 36. (2) Due to unequal mixing in the Plant Vent Stack, both 2RT-7865-1 and 3RT-7865-1 are required to be operable when 2/3RT-7808 is inoperable. ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and
b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway.

S0123-0DCM 4-12 Revision 0 02-27-07

TABLE 4-3 (Continued) TABLE NOTATION ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

a. The process flow rate is estimated at least once per 12 hours during actual releases. In addition, a new flow estimate shall be made within 1 hour after a change that affects process flow has been completed. System design characteristics may be used to estimate process flow.
b. The particulate and iodine (P&I) sample flow rate is estimated or verified at least once per 12 hours during actual releases.

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1. ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

a. The process flow rate is estimated at least once per 12 hours during times of building occupation. System design characteristics may be used to estimate flow.
b. The particulate and iodine (P&I) sample flow rate is estimated at least once per 12 hours during times of building occupation.

ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the monitor is verified operable by performing a channel check at least once per 4 hours during actual releases. S0123-0DCM 4-13 Revision 0 02-27-07

TABLE 4-4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION TEST IS REQUIRED

1. WASTE GAS HOLDUP SYSTEM
a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release - 2/3RT-7808, 3RT-7865-1 P P R(3) 0(1) *

b. Process Flow Rate Monitoring Device P NA R 0 *
2. CONDENSER EVACUATION SYSTEM
a. Noble Gas Activity Monitor -

2(3)RT-7818, 2(3)RT-7870-1 D M R(3) 0(2) **

b. Iodine Sampler W NA NA NA **
c. Particulate Sampler W NA NA NA **
d. Associated Sample Flow Measuring Device D NA R 0 **
e. Process Flow Rate Monitoring Device (2(3)RT-7870-1) D NA R 0 **

S0123-0DCM 4-14 Revision 0 02-27-07

TABLE 4-4 (Continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALI BRATI ON TEST IS REQUIRED

3. PLANT VENT STACK
a. Noble Gas Activity Monitor - D M R(3) 0(2)
  • 2/3RT-7808, 2RT-7865-1, 3RT-7865-1
b. Iodine Sampler W NA NA NA *
c. Particulate Sampler W NA NA NA *
d. Associated Sample Flow Measuring Device D NA R 0 *
e. Process Flow Rate Monitoring Device D NA R 0 *
4. CONTAINMENT PURGE SYSTEM
a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release - 2(3)RT-7828, 2(3)RT-7865-1 D P(4) R(3) 0(1) *

b. Iodine Sampler W NA NA NA *
c. Particulate Sampler W NA NA NA *
d. Process Flow Rate Monitoring Device D NA R 0 *
e. Associated Sample Flow Measuring Device D NA R 0
  • S0123-0DCM 4-15 Revision 0 02-27-07

TABLE 4-4 (Continued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL SOURCE CHANNELS FUNCTIONAL SURVEILLANCE INSTRUMENT*** CHECK CHECK CALIBRATION TEST IS REQUIRED

5. SOUTH YARD FACILITY (SYF) WORK AREA
a. Iodine Sampler W NA NA NA *
b. Particulate Sampler W NA NA NA *
c. Process Flow Rate Monitoring Device D(5) NA R Q *
d. Associated Sample Flow Measuring Device D(5) NA R Q *
6. SOUTH YARD FACILITY (SYF) DECONTAMINATION UNIT
a. Iodine Sampler W NA NA NA *
b. Particulate Sampler W NA NA NA *
c. Process Flow Rate Monitoring Device D(6) NA R Q *
d. Associated Sample Flow Measuring Device D(6) NA R Q
  • NOTE: For 5 and 6, ECP 030100131 abandons the MGP radiation monitors and installs flow meters. This section applies to the flow meters and will take effect when ECP turnover is complete.

S0123-0DCM 4-16 Revision 0 02-27-07

TABLE 4-4 (Continued) TABLE NOTATION

  • At all time s .
 ** Modes 1-4 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.
      • Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolationt, and Control Room alarm annunciation if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.
2. Circuit failure.

t Automatic pathway isolation is tested on a once per refueling interval. t The main containment purge isolation valves are required to be tested in Mode 5 prior to performing initial core alterations. Containment purge valves are not required to be tested for automatic isolation in the event of a mid-cycle outage. Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation. If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm setpoint.
2. Circuit failure.

Down scale failure testing is bounded by administrative limitation on monitor setpoints which ensure monitor alarm and release termination occur prior to reaching the level of monitor saturation. If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable. S0123-0DCM 4-17 Revision 0 02-27-07

TABLE 4-4 (Continued) TABLE NOTATION (Continued) (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONs, sources that have been related to the initial calibration shall be used. (4) Prior to each release and at least once per month. (5) Daily checks only required during times of bUilding occupation. (6) CHANNEL CHECK required by Health Physics daily for each day that the CO 2 Decontamination Unit is used. S0123-0DCM 4-18 Revision 0 02-27-07

4.3 OPERABILITY OF RADIOACTIVE WASTE EQUIPMENT The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems are shown in Figures 4-5 thru 4-7. S0123-0DCM 4-19 Revision 0 02-27-07

FIGURE 4-5 SONGS RADIOACTIVE LIQUID WASTE TREATMENT SYSTEMS Main Condenser 

          ,----+..----

Aux. Building Sump (Continuous) t-------. Turbine Plant Sump (Continuous) 

                                                                                                                                                  ..          ~

2(3) -7821

' ************* II I * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • I I * * * * *:

Storage Tank Area Sump CCW Sump (Batch) .......... (Batch) BPS/Neutralization Sump (Batch/Continuous) i r**~ BPS Laundry Facility 

                                                                                                                                                 *          ~

2(3) -7817 HCS (Batch) FFCPD HLJT (Batch) LCS (Batch) FFCPD 

  . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .L......-
                                                                  ...    ,..s...}                                     --.<             _r__--....

S/G E-088 r- 2(3)-6759 

                                                                                                                                                                           ~ _ _..~~.~~..via                                    :
                                                                                                                                                                           ! Aux. Building Sump                                 ,
                                                                                                                                                                           ,********..***************1*******************.....**:
  ............. ~:~.~~~~~                                                                                                                                                                                                         ~

2(3)-6753 

                                                                          .I _---------------

Radwaste Primary Tanks Radwaste Secondary Tanks L~~~a~' ,j.. Primary Makeup Tanks 2/3-7813 Condensate Monitor Tanks (Batch)

  • Intake
  • NIAYDS ............ .:

2/3-2101 (Continuous) Pacific Ocean S0123-0DCM 4-20 Revision 1 02-29-08

FIGURE 4-6 SONGS RADIOACTIVE GASEOUS WASTE TREATMENT SYSTEMS 

                                                         <----- ATMOSPHERE    ------>

i Radiation Radiation l-. 

                                                                                                                   \ Radiation I     H    Radiation Sample Skid H        Monitor 2RT7870         I Monitor 2RT7828                                                                         I Mon itor I 3RT7828  I Monitor 3RT7870 SYF7904 Radiation I                                      ~ Radiationl-r---I Radiation Monitor 2RT7818 Monitor ~

2RT7865 I Monitor 3RT7865 i W Radiation Monitor ~ Sample Skid I i 3RT7818 SYF7905 PLANT VENT STACK COMMON PLENUM "it 2 Condenser II ',j" I I "it 2 Building Waste Gas Unit 3 Building II Unit 3 Unit 3 Condenser outh Yard Facil ity South Yard Facility L Containment Decay Tanks Containment Work Area Decon Area Evacuation Ventilation Ventilation Evacuation Purge (6) Purge Exhaust System Exhaust Exhaust System Exhaust 2(3)RT-7865-1 can be aligned to either containment purge or the plant vent stack S0123-0DCM 4-21 Revision 0 02-27-07

FIGURE 4-7 SOLID WASTE HANDLING l--1 

                                                 -------*--~~i            I i       i  Resin sluiced     i Loaded into Resin sluiced      Spent Resin          I   ~i       from SRT to                Transferred to              shipping cask Spent Resin from IX to SRT      accumulated         :---1            disposal     I             MPHF for    f------.-    for transport in SRT            i       I  container and     I         interim staging             to burial site
                                         ~~~~-
                                                        ~                 I      dewatered     I                                   L Filter I
                -1 I
                                                                          . evaluated for                     If not Particulate             Filter removed    Filter stored I                iincinerability-                 incenerable. I         i  Waste shi pped Process Filters             from in-line   in accumulation ~ if incinerable ~ packaged in                                  ~          to burial site position      area on site                  i   -shi pped for              drum liner for            I I         .       off-site                   disposal              1 I         ~nceneration                                             ~-----~-

Resulting Wastes Waste placed in co11 ected in cargo container I I Waste shipped disposable 

                                                               ~

Low Level Dry to processor waste packaged Active Waste recepticles for shipment to for volume f------.- and shipped located around off-site reduction from processor the plant processor Iii to burial site 1 Waste sorted for packaging on-site or vendor I, L 

                                                               ~

I, i 

                                                                    -1'  '

I Wastes packaged and transferred to MPHF Waste shipped to burial site processing Clothing packed I I Clothing I Clothing bags in boxes and i iI laundered. I Protective __ ~ collected from shipped to I--_~ returned to Clothing I poi nts around off-site ' s i t e and plant laundry restocked facility LEGEND: SRT: Spent Resin Tank MPHF: Multi Purpose Handling Facility IX:Ion Exchanger S0123-0DCM 4-22 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Monitoring Program SPECIFICATION 5.1.1 The radiological environmental monitoring program shall be conducted as specified in Table 5-1. The requirements are applicable at all times. APPLICABILITY: At all times ACTION:

a. Should the radiological environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report (see Section 5.4), a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b. Should the level of radioactivity in an environmental sampling medium exceed the reporting levels of Table 5-2 when averaged over any calendar quarter, in lieu of any other report required by Technical Specification Section 5.7.1 and LCS 5.0.104, prepare and submit to the Commission, within 30 days from the end of the affected calendar quarter a Report pursuant to 10 CFR 50.73. When more than one of the radionuclides in Table 5-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + . . '~ 1.0 limit level (1) limit level (2)

c. When radionuclides other than those in Table 5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specification(s) 1.2.1, 2.2.1 or 2.3.1, as appropriate. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report (see Section 5.4).

S0123-0DCM 5-1 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) ACTION: (Continued)

d. With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 5.7.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

SURVEILLANCE REQUIREMENTS 

         .1    The radiological environmental monitoring samples shall be collected pursuant to Table 5-1 from the locations given in Table 5-4 and Figures 5-1 through 5-5 and shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.

SOI23-0DCM 5-2 Revision 0 02-27-07

TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locations a Collection Frequencya Type and Frequency of Analyses

1. AI RBORNE Samples from at least 5 locations Continuous operation of Radioiodine cartridge. Analyze Radioiodine sampler with sample at least once per 7 days for and 3 samples from offsite locations collection as required 1-131. Particulate sampler.

Particulates (in different sectors) of the by dust loading, but at Analyze for gross beta highest calculated annual average least once per 7 days.d radioactivity ~ 24 hours ground level D/Q. following filter change. Perform gamma isotopic b analysis 1 sample from the vicinity of a on each sample when gross beta community having the highest activity is > 10 times the calculated annual average ground- yearly mean of control samples. level D/Q. Perform gamma isotopic analysis on composite (by location) 1 sample from a control location sample at least once per 15-30 km (10-20 miles) distant 92 days. and in the least prevalent wind direction C

2. DIRECT At least 30 locations including At least once per Gamma dose. At least once per RADIATIOW an inner ring of stations in the 92 days. 92 days.

general area of the site boundary and an outer ring approximately in the 4 to 5 mile range from the site with a station in each sector of each ring. The balance of the stations is in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations. SOI23-0DCM 5-3 Revision 0 02-27-07

TABLE 5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locations a Collection Frequencya Type and Frequency of Analyses

3. WATERBORNE
a. Ocean 4 locations At least once per Gamma isotopic analysis of each month and composited f monthly sample. Tritium analysis quarterly of composite sample at least once per 92 days.
b. Dr i nk i nq" 2 locations Monthly at each Gamma isotopic and tritium location. analyses of each sample.
c. Sediment 4 locations At least once per Gamma isotopic analysis of each from 184 days. sample.

Shoreline

d. Ocean 5 locations At least once per Gamma isotopic analysis of each Bottom 184 days. sample.

Sediments S0123-0DCM 5-4 Revision 0 02-27-07

TABLE 5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locations a Collection Frequencya Type and Frequency of Analyses

4. INGESTION
a. Nonmigratory 3 locations One sample in season, Gamma isotopic analysis on Marine or at least once per edible portions.

Animals 184 days if not seasona 1. One sample of each of the follow-ing species:

1. Fish-2 adult species such as perch or sheephead.
2. Crustaceae-such as crab or lobster.
3. Mollusks-such as limpets, seahares or clams.
b. Local Crops 2 locations Representative Gamma isotopic analysis on edible vegetables, normally portions semiannually and I-131 1 leafy and 1 fleshy analysis for leafy crops.

collected at harvest time. At least 2 vegetables collected semiannually from each location. SOI23-0DCM 5-5 Revision 0 02-27-07

TABLE 5-1 (Continued) TABLE NOTATION

a. Sample locations are indicated on Figures 5-1 through 5-5.
b. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
c. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.
d. Canisters for the collection of radioiodine in air are subject to channeling. These devices should be carefully checked before operation in the field or several should be mounted in series to prevent loss of iodine.
e. Regulatory Guide 4.13 provides mlnlmum acceptable performance criteria for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.
f. Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).
g. No drinking water pathway exists at SONGS.

S0123-0DCM 5-6 Revision 0 02-27-07

TABLE 5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Airborne Particulate Water or Gases Marine Animals Local Crops Analysis (pCi/l) (pCi/m 3 ) (pCi/Kg, wet) (pCi/Kg, wet) H-3 2 X 10 4 ( a) Mn-54 1 x 10 3 3 X 10 4 Fe-59 4 x 10 2 1 X 10 4 Co-58 1 x 10 3 3 X 10 4 Co-60 3 x 10 2 1 X 10 4 Zn-65 3 x 10 2 2 X 10 4 Zr-95, Nb-95 4 x 10 2 I-131 2(b) 0.9 1 x 10 2 Cs-134 30 10 1 X 10 3 1 X 10 3 Cs-137 50 20 2 X 10 3 2 X 10 3 Ba-140, La-140 2 x 10 2 (a) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a (b) value of 30,000 pCi/l may be used. If no drinking water pathway exists, a value of 20 pCi/l may be used. SOI23-0DCM 5-7 Revision 0 02-27-07

TABLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS c MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a Airborne Particulate Water or Gases Marine Animals Local Crops Sediment Analysis (pCi/l) (pt i /m') (pCi/Kg, wet) (pCi/Kg, wet) (pCi/Kg, dry) gross beta 4 1 x 10- 2 H-3 2000(b) Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95, Nb-95 15 I-131 1(d) 7 X 10- 2 60 Cs-134 15 5 x 10- 2 130 60 150 Cs-137 18 6 x 10-2 150 80 180 Ba-140, La-140 15 SOI23-0DCM 5-8 Revision 0 02-27-07

TABLE 5-3 (Continued) TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation): LLD E-V-2.22x10 6 - Y - e x p (-Mt) where: LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume), Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and 6t is the elapsed time between midpoint of sample collection or end of the collection period and time of counting (for environmental samples, not plant effluents ). The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E,V,Y and 6t shall be used in the calculations. It should be recognized that the LLD is defined as an £ priori (before the fact) limit representing the capability of the measurement system and not as 

  £ posteriori (after the fact) limit for a particular measurement.*
   *For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300 (revised annually). (2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968) . S0123-0DCM 5-9 Revision 0 02-27-07

TABLE 5-3 (Continued) TABLE NOTATION

b. If no drinking water pathway exists. a value of 3000 pCi/l may be used.
c. Other peaks which are measurable and identifiable. together with the radionuclides in Table 5-3. shall be identified and reported.
d. If no drinking water pathway exists. a value of 15 pCi/l may be used.

S0123-0DCM 5-10 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.2 LAND USE CENSUS SPECIFICATION 5.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal. the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. APPLICABILITY: At all times ACTION:

a. With the land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 2.3.1. pursuant to Technical Specification 5.7.1. identify the new locations in the next Annual Radioactive Effluent Release Report.
b. With the land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 5.1. add the new location within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s).

excluding the control station location. having the lowest calculated dose or dose commitment(s) via the same exposure pathway. may be deleted from this monitoring program after October 31. of the year in which this Land Use Census was conducted. Pursuant to Technical Specification 5.7.1. submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations. SURVEILLANCE REQUIREMENTS 

           .1   The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results. such as by a door-to-door survey. aerial survey. or by consulting local agriculture authorities.
  • Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

SOI23-0DCM 5-11 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.3 INTERLABORATORY COMPARISON PROGRAM SPECIFICATION 5.3.1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that complies with Regulatory Guide 4.15. APPLICABILITY: At all times ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

SURVEILLANCE REQUIREMENTS 

         .1   A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with Section 5.4.1 of this document shall be included in the Annual Radiological Environmental Operating Report (see Section 5.4).

S0123-0DCM 5-12 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT* 5.4.1 The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 5.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. The annual radiological environmental operating reports shall include summarized and tabulated results in the Radiological Assessment Branch Technical Position, Revision 1, November 1979 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from the mid-point of reactor Units 2 and 3; and the results of licensee participation in the Interlaboratory Comparison Program, required by Section 5.3.

  • A single submittal may be made for a multiple unit station, combining those sections that are common to all units at the station.

S0123-0DCM 5-13 Revision 0 02-27-07

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS The Radiological Environmental Monitoring Sample Locations are identified in Figures 5-1 through 5-5. These sample locations are described in Table 5-4 and indicate the distance in miles and the direction, determined from degrees true north, from the center of the Units 2 and 3 building complex. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, Figures 5-1 through 5-5. S0123-0DCM 5-14 Revision 0 02-27-07

Page 1 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE* TYPE OF SAMPLE AND SAMPLING LOCATION*** (miles) DIRECTION* Direct Radiation 1 City of San Clemente (Former SDG&E Offices) 5.7 NW 2 Camp San Mateo (MCB, Camp Pendleton) 3.5 N 3 Camp San Onofre (MCB, Camp Pendleton) 2.6 NE 4 Camp Horno (MCB, Camp Pendleton) 4.5 E 6 Old Route 101 (East-Southeast) 3.0 ESE 8 Noncommissioned Officers' Beach Club 1.4 NW 10 Bluff (Adjacent to PIC #1) 0.7 WNW 11 Former Visitors' Center 0.4** NW 12 South Edge of Switchyard 0.2** E 13 Southeast Site boundary (Bluff) 0.4** ESE 15 Southeast Site Boundary (Office Building) 0.1 ** SSE 16 East Southeast Site Boundary 0.4** ESE 17 Transit Dose 18 Transit Dose 19 San Clemente Highlands 5.0 NNW 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW 23 SDG&E Service Center Yard 8.1 NW

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
**  Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
      • MCB - Marine Corps Base PIC - Pressurized Ion Chamber S0123-0DCM 5-15 Revision 0 02-27-07

Page 2 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE* TYPE OF SAMPLE AND SAMPLING LOCATION*** (mi 1es ) DI RECTION* Direct Radiation (Continued) 31 Aurora Park-Mission Viejo 18.6 NNW 33 Camp Talega (MCB, Camp Pendleton) 5.7 N 34 San Onofre School (MCB, Camp Pendleton) 1.9 NW 35 Range 312 (MCB, Camp Pendleton) 4.7 NNE 36 Range 208C (MCB, Camp Pendleton) 4.2 NE 38 San Onofre State Beach Park 3.3 SE 40 SCE Training Center - Mesa (Adjacent to PIC #3) 0.7 NNW 41 Old Route 101 - East 0.3** E 44 Fallbrook Fire Station 17.7 E 46 San Onofre State Beach Park 0.9 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
**  Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
      • MCB - Marine Corps Base PIC - Pressurized Ion Chamber S0123-0DCM 5-16 Revision a 02-27-07

Page 3 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE* TYPE OF SAMPLE AND SAMPLING LOCATION*** (miles) DIRECTION* Direct Radiation (Continued) 49 Camp Chappo (MCB, Camp Pendleton) 12.8 ESE 50 Oceanside Fire Station (CONTROL) 15.6 SE 53 San Diego County Operations Center 44.3 SE 54 Escondido Fire Station 31.8 ESE 55 San Onofre State Beach (Unit 1, West) 0.2** W 56 San Onofre State Beach (Unit 1, West) 0.2** W 57 San Onofre State Beach (Unit 2) 0.1 ** WSW 58 San Onofre State Beach (Unit 3) 0.1 ** S 59 SONGS Meteorological Tower 0.3** WNW 60 Transit Control Storage Area 61 Mesa - East Boundary (Adjacent to PIC #4) 0.7 N 62 MCB - Camp Pendleton (Adjacent to PIC #5) 0.6 NNE 63 MCB - Camp Pendleton (Adjacent to PIC #6) 0.6 NE 64 MCB - Camp Pendleton (Adjacent to PIC #7) 0.6 ENE 65 MCB - Camp Pendleton (Adjacent to PIC #8) 0.7 E 66 San Onofre State Beach (Adjacent to PIC #9) 0.6 ESE 67 Former SONGS Evaporation Pond (Adjacent to PIC #2) 0.6 NW 68 Range 210C (MCB, Camp Pendleton) 4.3 ENE 73 South Yard Facility 0.4** ESE Transit Control A Tran s it con t ro 1 B Fader (Co-Located with TLD # 54)**** 31.8 ESE 74 Oceans ide Ci ty Hall (Backup CONTROL) 15.6 SE 75 Gate 25 MCB 4.6 SE 76 El Camino Real Mobil Station 4.6 NW 77 Area 62 Heavy lift pad 4.3 N 78 Sheep Valley 4.4 ESE

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
**  Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
      • MCB - Marine Corps Base PIC - Pressurized Ion Chamber
        • For fading correction due to significant increase in temperature.

SOI23-0DCM 5-17 Revision a 02-27-07

Page 4 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE* TYPE OF SAMPLE AND SAMPLING LOCATION (miles) 01 RECTION* Airborne 1 City of San Clemente (City Hall) 5.1 NW 7 AWS Roof 0.18** NW 9 State Beach Park 0.6 ESE 10 Bl uff 0.7 WNW 11 Mesa EOF 0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E 14 Mesa Medical Facil ity 0.7 NNW 15 Oceanside City Hall (CONTROL) 15.6 SE Soil Saapl es! 1 Camp San Onofre 2.6 NE 2 Old Route 101 - (East Southeast) 3.0 ESE 3 Basilone Road/I-5 Freeway Offramp 2.0 NW 5 Former Visitor's Center 0.4** NW 6 Oceanside (CONTROL) 16.0 SE Ocean Water A Station Discharge Outfall - Unit 1 0.6 SW B Outfall - Unit 2 1.5 SW C Outfall - Unit 3 1.2 SSW o Newport Beach (CONTROL) 30.0 NW

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
 ** Distances are within the Units 2 and 3 Site boundary (0.4 mile in all sectors) and not required by Technical Specification.

Soil Samples are not required by Technical Specifications. SOI23-0DCM 5-18 Revision 0 02-27-07

Page 5 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE* TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION* Drinking Water 4 Camp Pendleton Drinking Water Reservoir 2.2 NNW 5 Oceans i de City Hall (new CONTROL) 15.6 SE Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (Southeast) 0.6 SE 2 San Onofre Surfing Beach 0.8 WNW 3 San Onofre State Beach (Southeast) 3.5 SE 4 Newport Beach (North End) (CONTROL) 29.2 NW Local Crops 1 San Clemente Ranch (San Mateo Canyon) 2.6 NW 2 Oceanside (CONTROL)** 15 to 25 SE to ESE 4 San Clemente Resident w/Garden 4.4 NW 6 SONGS Garden 0.4 NNW

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
 ** Control location should be in Section G or F. 15 to 25 miles from site. The control location will be selected based on sample availability. The exact location shall be noted in the Annual Radiological Environmental Operating Report.

SOI23-0DCM 5-19 Revision 0 02-27-07

TABLE 5-4 Page 6 of 6 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE* TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTI ON* Non-Migratory Marine Animals A Unit 1 Outfall 0.9 WSW B Units 2 and 3 Outfall 1.5 SSW C Laguna Beach (CONTROL)** 15 to 150 WNW to NW Kel p' A San Onofre Kelp Bed 1.5 S B San Mateo Kelp Bed 3.8 WNW C Barn Kelp Bed 6.3 SSE D DELETED E Salt Creek (CONTROL) 11 to 13 WNW to NW Ocean Bottom Sediments A DELETED B Unit 1 Outfall 0.8 SSW C Unit 2 Outfall 1.6 SW D Unit 3 Outfall 1.2 SSW E Laguna Beach (CONTROL) 18.2 NW F SONGS Upcoast 0.9 WSW

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
** A location more distant from SONGS in the WNW to NW direction may be used as the CONTROL location.

Kelp Samples are not required by Technical Specifications. S0123-0DCM 5-20 Revision 0 02-27-07

TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Theta DISTANCE* PRESSURIZED ION CHAMBERS (Degrees)* Meters miles DIRECTION!SECTOR* Sl San Onofre Beach 298° 1070 0.7 WNW P S2 SONGS Former Evap. Pnd 313° 890 0.6 NW Q S3 Japanese Mesa 340° 1150 0.7 NNW R S4 MCB - Camp Pendleton 3° 1120 0.7 N A S5 MCB - Camp Pendleton 19° 1050 0.6 NNE B S6 MCB - Camp Pendleton 46° 940 0.6 NE C S7 MCB - Camp Pendleton 70° 870 0.6 ENE D S8 MCB - Camp Pendleton 98° 1120 0.7 E E S9 San Onofre State Beach 121° 940 0.6 ESE F

  • Distance (meters/miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north.

S0123-0DCM 5-21 Revision 0 02-27-07

TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP DEGREES TRUE NORTH FROM SONGS 2 AND 3 MID-POINT NOMENCLATURE Sector Center Sector 22.5° Limit Line Limit Sector* Direction 348.75 o & 360 11.25 A N

11. 25 22.5 33.75 B NNE 33.75 45.0 56.25 C NE 56.25 67.5 78.75 D ENE 78.75 90.0 101.25 E E 101.25 112.0 123.75 F ESE 123.75 135.0 146.25 G SE 146.25 157.0 168.75 H SSE 168.75 180.0 191.25 J S 191.25 202.5 213.75 K SSW 213.75 225.0 236.25 L SW 236.25 247.5 258.75 M WSW 258.75 270.0 281. 25 N W 281. 25 292.5 303.75 P WNW 303.75 315.0 326.25 Q NW 326.25 337.5 348.75 R NNW
  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true North.

SOI23-0DCM 5-22 Revision 0 02-27-07

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6.0 ADMINISTRATIVE 6.1 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable through these Specifications. ACTION 6.1.1 ACTION shall be that part of a specification which prescribes remedial measures required under designated cond it ions. CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. CHANNEL CHECK 6.1. 3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST 6.1. 4 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into channel as close to the sensor as practicable to verify OPERABILITY, including alarm and/or trip functions.
b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY, including alarm and/or trip functions.
c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPERABILITY.

S0123-0DCM 6-1 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) DOSE EQUIVALENT 1-131 6.1. 5 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in International Commission on Radiological Protection Publication 30, Tables titled Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activities. FREQUENCY NOTATION 6.1. 6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2. GASEOUS RADWASTE TREATMENT SYSTEM 6.1. 7 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. MEMBERS OF THE PUBLIC 6.1.8 MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category complies with the requirements of 10CFR50 and shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions. Supplemental workers and their dependents are included in this definition while they temporarily reside at Camp Mesa. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials. SOI23-0DCM 6-2 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) MODE 6.1. 9 A MODE shall correspond to anyone inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 6-1 with fuel in the reactor vessel. OPERABLE - OPERABILITY 6.1. 10 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s). PURGE - PURGING 6.1.11 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. SITE BOUNDARY 6.1.12 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. SOLIDIFICATION 6.1.13 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing). SOI23-0DCM 6-3 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) SOURCE CHECK 6.1.14 For Victoreen and NMC analog monitors, a SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. [2(3)RT-6753, 2(3)RT-6759, 2(3)RT-7818A] For Sorrento Electronics digital monitors a SOURCE CHECK shall be the verification of proper computer response to a check source request. [2(3)RT-7828, 2(3)RT-7865-1, 2(3)RT-7870-1] For MGPI monitors a SOURCE CHECK shall be the verification of proper computer response to the continuous internal detector, monitor calibration and electrical checks. [2(3)RT-7817, 2(3)RT-7821, 2/3RT-7813, 2/3RT-7808, RT-2101] SURVEILLANCE REQUIREMENT: MEETING SPECIFIED FREQUENCY 6.1.15 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance. This provision is not intended to be used repeatedly as a convenient means to extend surveillance intervals beyond those specified. Additionally, it does not apply to any Action Statements. THERMAL POWER 6.1.16 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. VENTILATION EXHAUST TREATMENT SYSTEM 6.1.17 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. S0123-0DCM 6-4 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) VENTING 6.1.18 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent used in system names does not imply a VENTING process. S0123-0DCM 6-5 Revision 0 02-27-07

TABLE 6-1 OPERATIONAL MODES REACTIVITY %OF RATED AVERAGE COOLANT OPERATION MODE CONDITION, (Keffl THERMAL POWER(a) TEMPERATURE (OF)

1. POWER OPERATION ~ 0.99 > 5% NA
2. STARTUP ~ 0.99 .::: 5% NA
3. HOT STANDBY < 0.99 NA ~ 350°F
4. HOT SHUTDOWN < 0.99 NA 350°F> Tavg >200°F
5. COLD SHUTDOWN (b) < 0.99 NA .::: 200°F
6. REFUELING (c) NA NA NA (aJ Excludlng decay heat.

(b) All reactor vessel head closure bolts fully tensioned. (c) One or more reactor vessel head closure bolts less than fully tensioned. S0123-0DCM 6-6 Revision 0 02-27-07

TABLE 6-2 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours 0 At least once per 24 hours W At least once per 7 days M At 1east once per 31 days Q At 1east once per 92 days SA At 1east once per 184 days R At 1east once per 18 months* S/U Prior to each reactor startup P Completed prior to each release N.A. Not applicable Refueling Not to exceed 24 months Interval

  • A month is defined as a 31-day period.

SOI23-0DCM 6-7 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT* 6.2.1 Routine radioactive effluent release reports covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. 6.2.2 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, "Revision I, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The radioactive effluent release report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 1-2 and 2-2) during the report period. All assumptions used in making these assessments (i .e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

  • A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the Station; however, for units with separate radwaste systems, the submittal shall spec i fy the releases of radioactive material from each unit.

S0123-0DCM 6-8 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS (Continued) 6.2.2 (Continued) The radioactive effluent release report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1. The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:

a. Container volume,
b. Total curie quantity (specify whether determined by measurement or estimate),
c. Principal radionuclides (specify whether determined by measurement or estimate),
d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
f. Solidification Agent (e.g., cement, urea formaldehyde).

The radioactive effluent release report shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period. The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period. SOI23-0DCM 6-9 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.3 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, & Gaseous) Licensee initiated major changes to the radioactive waste systems (liquid & gaseous):

1. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was performed pursuant to Quality Assurance Program Description (SCE-I-A), Subsection 17.2.20.3.1.i. The discussion of each change shall contain:
a. A summary of the evaluation that led to the determination that the change could be made in accordance with applicable regulations;
b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;
d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments thereto;
e. An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;
f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents to the actual release for the period prior to when the changes are to be made;
g. An estimate of the exposure to plant operating personnel as a result of the change; and
h. Documentation of the fact that the change was reviewed and found acceptable pursuant to Quality Assurance Program Description (SCE-I-A), Subsection 17.2.20.3.1.i.
2. Shall become effective upon review and acceptance pursuant to Quality Assurance Program Description (SCE-I-A), Subsection 17.2.20.3.1.i.

SOI23-0DCM 6-10 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES LIQUID EFFLUENTS CONCENTRATION (1.1) 6.4.1 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. DOSE (1.2) 6.4.2 This specification is provided to implement the require-ments of Section II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system. S0123-0DCM Revision 0 6-11 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) LIQUID WASTE TREATMENT (1.3) 6.4.3 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept ~as low as is reasonably achievable.~ This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. GASEOUS EFFLUENTS DOSE RATE (2.1) 6.4.4 This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b>>. For individuals 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. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. This specification applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system. SOI23-0DCM Revision a 6-12 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) DOSE - NOBLE GASES (2.2) 6.4.5 This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept lias low as is reasonably ach i evabl e ." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, IICalculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,11 Revision 1, October 1977 and Regulatory Guide 1.111, IIMethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactor s ;" Revision 1, July 1977. For individuals 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 negl igible and hence the dose 110". The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric condit ions. DOSE - RADIOIODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM (2.3) 6.4.6 This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the gUides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achi evabl e ." The ODCM calculational methods specified in the Surveillance Requirements implement the S0123-0DCM 6-13 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. GASEOUS RADWASTE TREATMENT (2.4) 6.4.7 The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. SOI23-0DCM 6-14 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) TOTAL DOSE (3.3) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle. RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION (4.1) 6.4.9 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. SOI23-0DCM 6-15 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) 6.4.10 The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumenta-tion also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. MONITORING PROGRAM (5.1) 6.4.11 The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience. The detection capabilities required by Table 5-1 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an £ priori (before the fact) limit representing the capability of a measurement system and not as £ posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report. S0123-0DCM 6-16 Revision 0 02-27-07

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) LAND USE CENSUS (5.2) 6.4.12 This specification is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,

1) that 20% of the garden was used for growing broad leaf vegetation (i .e., similar to lettuce and cabbage), and
2) a vegetation yield of 2 kg/square meter.

INTERLABORATORY COMPARISON PROGRAM (5.3) 6.4.13 The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. S0123-0DCM 6-17 Revision 0 02-27-07

OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION (SONGS) APPENDIX A Ri TABLES SO123-ODCM-A Revision 1 02-29-08

ODCM APPENDIX A TABLE OF CONTENTS Section Title Page 1.0 UNITS 2 AND 3 Ri TABLES* . . . . . . . . . . . . . . . . A1-1 thru A1-24 1-1 Dose Parameters Ri for Sector P . . . . . . . . . . A1-1 1-2 Dose Parameters Ri for Sector Q . . . . . . . . . . A1-4 1-3 Dose Parameters Ri for Sector R . . . . . . . . . . A1-8 1-4 Dose Parameters Ri for Sector A . . . . . . . . . . A1-10 1-5 Dose Parameters Ri for Sector B . . . . . . . . . . A1-13 1-6 Dose Parameters Ri for Sector C . . . . . . . . . . A1-15 1-7 Dose Parameters Ri for Sector D . . . . . . . . . . A1-17 1-8 Dose Parameters Ri for Sector E . . . . . . . . . . A1-19 1-9 Dose Parameters Ri for Sector F . . . . . . . . . . A1-21 1-10 Dose Parameters Ri for Sector G . . . . . . . . . . A1-22 2.0 SOUTH YARD FACILITY Ri TABLES** . . . . . . . . . . . . . A2-1 thru A2-10 2-1 Dose Parameters Ri for Sector D . . . . . . . . . . A2-1 2-2 Dose Parameters Ri for Sector E . . . . . . . . . . A2-2 2-3 Dose Parameters Ri for Sector F . . . . . . . . . . A2-3 2-4 Dose Parameters Ri for Sector G . . . . . . . . . . A2-7 3.0 NORTH INDUSTRIAL AREA (UNIT 1) Ri TABLES*** . . . . . . . A3-1 thru A3-21 3-1 Dose Parameters Ri for Sector P . . . . . . . . . . A3-1 3-2 Dose Parameters Ri for Sector Q . . . . . . . . . . A3-4 3-3 Dose Parameters Ri for Sector R . . . . . . . . . . A3-8 3-4 Dose Parameters Ri for Sector A . . . . . . . . . . A3-9 3-5 Dose Parameters Ri for Sector B . . . . . . . . . . A3-11 3-6 Dose Parameters Ri for Sector C . . . . . . . . . . A3-13 3-7 Dose Parameters Ri for Sector D . . . . . . . . . . A3-15 3-8 Dose Parameters Ri for Sector E . . . . . . . . . . A3-16 3-9 Dose Parameters Ri for Sector F . . . . . . . . . . A3-18 3-10 Dose Parameters Ri for Sector G . . . . . . . . . . A3-20

References:

  • J. W. Scott to D. Dick Memorandum for file: "2008 Dose Parameters for SONGS," dated February 11, 2008.
           **    M. Goeders to Po Chang Memorandum for file: Determination of meterological parameters for the SoYTH Yard facility using OCMs methodology, dated May, 30 1995.
           ***   J.W. Scott to D. Dick Memorandum for file:  2006 Dose Parameters for SONGS, dated February 7, 2007 SO123-ODCM-A Ai                             Revision 1 02-29-08

TABLE 1-1 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR P Page 1 of 3 Pathway = Surf Beach/Lifeguard Distance = 0.5 miles X/Q = 1.3E-6 sec/m3 D/Q = 5.5E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 7.8E+0 4.2E+1 1.2E+2 Cr-51 1.2E+2 3.2E+4 6.9E+2 1.5E+5 1.3E+3 4.2E+5 Mn-54 1.1E+4 9.5E+6 6.5E+4 4.5E+7 1.3E+5 1.3E+8 Co-57 9.1E+1 2.4E+6 1.0E+3 1.1E+7 2.9E+3 3.1E+7 Co-58 7.6E+3 2.6E+6 4.4E+4 1.2E+7 8.5E+4 3.5E+7 Co-60 4.9E+4 1.5E+8 2.9E+5 7.0E+8 5.4E+5 2.0E+9 Sr-89 1.5E+4 1.5E+2 7.9E+4 7.1E+2 1.3E+5 2.0E+3 Sr-90 1.0E+5 5.4E+5 8.8E+5 Zr-95 1.5E+4 1.7E+6 8.8E+4 8.2E+6 1.6E+5 2.3E+7 Nb-95 4.2E+3 9.4E+5 2.5E+4 4.5E+6 4.6E+4 1.2E+7 Ru-103 4.6E+3 7.5E+5 2.6E+4 3.6E+6 4.6E+4 9.9E+6 Te-129m 1.2E+4 1.4E+5 6.5E+4 6.4E+5 1.1E+5 1.8E+6 Cs-134 8.3E+2 4.7E+7 4.8E+3 2.2E+8 8.9E+3 6.2E+8 Cs-136 1.0E+2 1.0E+6 5.8E+2 4.9E+6 1.1E+3 1.4E+7 Cs-137 7.2E+2 7.1E+7 4.0E+3 3.4E+8 6.9E+3 9.4E+8 Ba-140 1.2E+4 1.4E+5 6.6E+4 6.7E+5 1.2E+5 1.9E+6 Ce-141 3.8E+3 9.4E+4 2.0E+4 4.5E+5 3.3E+4 1.2E+6 Ce-144 8.2E+4 4.8E+5 4.4E+5 2.3E+6 7.1E+5 6.4E+6 I -131 1.1E+5 1.2E+5 4.8E+5 5.6E+5 1.1E+6 1.6E+6 I -132 1.3E+3 8.5E+3 4.9E+3 4.1E+4 1.0E+4 1.1E+5 I -133 2.7E+4 1.7E+4 9.5E+4 8.0E+4 2.0E+5 2.2E+5 I -134 3.5E+2 3.1E+3 1.3E+3 1.5E+4 2.7E+3 4.1E+4 I -135 5.5E+3 1.7E+4 2.0E+4 8.2E+4 4.1E+4 2.3E+5 UN-ID 6.9E+3 5.1E+6 4.1E+4 2.4E+7 7.9E+4 6.8E+7 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-1 Revision 0 02-27-07

TABLE 1-1 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR P Page 2 of 3 Pathway = Cotton Point Estates Distance = 2.7 miles X/Q = 1.1E-7 sec/m3 D/Q = 3.2E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-2 Revision 0 02-27-07

TABLE 1-1 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR P Page 3 of 3 Pathway = Cotton Point Gardens Distance = 2.8 miles X/Q = 1.0E-7 sec/m3 D/Q = 3.0E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 4.0E+3 1.3E+3 2.6E+3 1.3E+3 2.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 1.1E+7 2.1E+4 1.5E+7 1.4E+4 1.6E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.3E+9 1.4E+6 2.3E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 5.8E+8 3.1E+4 6.6E+8 3.1E+4 6.3E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 7.5E+8 1.3E+6 9.7E+8 9.3E+5 9.9E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.4E+10 8.7E+6 2.5E+10 6.0E+6 2.5E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 3.5E+10 2.4E+6 1.5E+10 1.4E+6 9.8E+9 Sr-90 1.1E+7 1.5E+7 1.4E+12 1.6E+7 8.3E+11 9.6E+6 6.7E+11 Zr-95 1.8E+6 2.5E+8 2.2E+6 1.1E+9 2.7E+6 1.5E+9 1.8E+6 1.4E+9 Nb-95 4.8E+5 1.4E+8 6.1E+5 4.3E+8 7.5E+5 5.9E+8 5.0E+5 6.1E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 5.0E+8 7.8E+5 6.8E+8 5.0E+5 6.6E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.9E+9 2.0E+6 1.8E+9 1.2E+6 1.2E+9 Cs-134 8.0E+4 6.8E+9 1.2E+5 3.2E+10 1.5E+5 2.3E+10 9.8E+4 1.8E+10 Cs-136 1.2E+4 1.5E+8 1.5E+4 3.7E+8 1.8E+4 3.2E+8 1.2E+4 3.2E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 3.4E+10 1.2E+5 2.4E+10 7.5E+4 1.9E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 3.0E+8 2.0E+6 2.3E+8 1.3E+6 2.8E+8 Ce-141 5.2E+5 1.4E+7 5.4E+5 4.2E+8 6.1E+5 5.5E+8 3.6E+5 5.2E+8 Ce-144 9.8E+6 7.0E+7 1.2E+7 1.0E+10 1.3E+7 1.3E+10 7.8E+6 1.1E+10 I -131 1.5E+7 1.7E+7 1.6E+7 4.8E+10 1.5E+7 3.1E+10 1.2E+7 3.8E+10 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 8.1E+8 2.9E+6 4.6E+8 2.2E+6 5.3E+8 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 1.2E+7 6.2E+5 8.2E+6 4.5E+5 9.1E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 3.5E+9 1.2E+6 2.6E+9 8.6E+5 2.0E+9 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-3 Revision 0 02-27-07

TABLE 1-2 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR Q Page 1 of 4 Pathway = SORB Resident Employee Distance = 1.1 miles X/Q = 9.9E-7 sec/m3 D/Q = 5.0E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-4 Revision 0 02-27-07

TABLE 1-2 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR Q Page 2 of 4 Pathway = San Onofre Mobile Homes Distance = 1.4 miles X/Q = 6.9E-7 sec/m3 D/Q = 3.3E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-5 Revision 0 02-27-07

TABLE 1-2 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR Q Page 3 of 4 Pathway = San Mateo Pt Homes Distance = 2.7 miles X/Q = 2.6E-7 sec/m3 D/Q = 1.0E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-6 Revision 0 02-27-07

TABLE 1-2 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR Q Page 4 of 4 Pathway = S. C. Resident With Garden Distance = 4.1 miles X/Q = 1.4E-7 sec/m3 D/Q = 4.7E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 4.0E+3 1.3E+3 2.6E+3 1.3E+3 2.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 1.1E+7 2.1E+4 1.5E+7 1.4E+4 1.6E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.3E+9 1.4E+6 2.3E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 5.8E+8 3.1E+4 6.6E+8 3.1E+4 6.3E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 7.5E+8 1.3E+6 9.7E+8 9.3E+5 9.9E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.4E+10 8.7E+6 2.5E+10 6.0E+6 2.5E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 3.5E+10 2.4E+6 1.5E+10 1.4E+6 9.8E+9 Sr-90 1.1E+7 1.5E+7 1.4E+12 1.6E+7 8.3E+11 9.6E+6 6.7E+11 Zr-95 1.8E+6 2.5E+8 2.2E+6 1.1E+9 2.7E+6 1.5E+9 1.8E+6 1.4E+9 Nb-95 4.8E+5 1.4E+8 6.1E+5 4.3E+8 7.5E+5 5.9E+8 5.0E+5 6.1E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 5.0E+8 7.8E+5 6.8E+8 5.0E+5 6.6E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.9E+9 2.0E+6 1.8E+9 1.2E+6 1.5E+9 Cs-134 8.0E+4 6.8E+9 1.2E+5 3.2E+10 1.5E+5 2.3E+10 9.8E+4 1.8E+10 Cs-136 1.2E+4 1.5E+8 1.5E+4 3.7E+8 1.8E+4 3.2E+8 1.2E+4 3.2E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 3.4E+10 1.2E+5 2.4E+10 7.5E+4 1.9E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 3.0E+8 2.0E+6 2.3E+8 1.3E+6 2.8E+8 Ce-141 5.2E+5 1.4E+7 5.4E+5 4.2E+8 6.1E+5 5.5E+8 3.6E+5 5.2E+8 Ce-144 9.8E+6 7.0E+7 1.2E+7 1.0E+10 1.3E+7 1.3E+10 7.8E+6 1.1E+10 I -131 1.5E+7 1.7E+7 1.6E+7 4.8E+10 1.5E+7 3.1E+10 1.2E+7 3.8E+10 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 8.1E+8 2.9E+6 4.6E+8 2.2E+6 5.3E+8 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 1.2E+7 6.2E+5 8.2E+6 4.5E+5 9.1E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 3.5E+9 1.2E+6 2.6E+9 8.6E+5 2.0E+9 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-7 Revision 0 02-27-07

TABLE 1-3 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR R Page 1 of 2 Pathway = Camp Mesa Distance = 0.4 miles X/Q = 3.7E-06 sec/m3 D/Q = 2.5E-08 m-2 Infant Child Teen Adult Inhala- Inhala- Food & Food & Inhala- Food & Inhala- Food & Radio- tion tion Ground Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H 3** 4.9E+2 8.5E+2 9.6E+2 9.6E+2 l Cr-51 9.7E+3 3.5E+6 1.3E+4 3.5E+6 1.6E+4 3.5E+6 1.1E+4 3.5E+6 l Mn-54 7.6E+5 1.0E+9 1.2E+6 1.0E+9 1.5E+6 1.0E+9 1.1E+6 1.0E+9 l Co-57 3.7E+3 2.6E+8 1.0E+4 2.6E+8 2.4E+4 2.6E+8 2.4E+4 2.6E+8 l Co-58 5.9E+5 2.9E+8 8.4E+5 2.9E+8 1.0E+6 2.9E+8 7.0E+5 2.9E+8 l Co-60 3.4E+6 1.6E+10 5.3E+6 1.6E+10 6.6E+6 1.6E+10 4.5E+6 1.6E+10 l Sr-89 1.5E+6 1.6E+4 1.6E+6 1.6E+4 1.8E+6 1.6E+4 1.1E+6 1.6E+4 l Sr-90 8.5E+6 1.1E+7 1.2E+7 7.3E+6 l Zr-95 1.3E+6 1.9E+8 1.7E+6 1.9E+8 2.0E+6 1.9E+8 1.3E+6 1.9E+8 l Nb-95 3.6E+5 1.0E+8 4.6E+5 1.0E+8 5.7E+5 1.0E+8 3.8E+5 1.0E+8 l Ru-103 4.2E+5 8.2E+7 5.0E+5 8.2E+7 5.9E+5 8.2E+7 3.8E+5 8.2E+7 l Te-129M 1.3E+6 1.5E+7 1.3E+6 1.5E+7 1.5E+6 1.5E+7 9.3E+5 1.5E+7 l Cs-134 6.0E+4 5.2E+9 9.1E+4 5.2E+9 1.1E+5 5.2E+9 7.4E+4 5.2E+9 l Cs-136 8.9E+3 1.1E+8 1.1E+4 1.1E+8 1.3E+4 1.1E+8 9.1E+3 1.1E+8 l Cs-137 5.4E+4 7.8E+9 7.9E+4 7.8E+9 9.1E+4 7.8E+9 5.7E+4 7.8E+9 l Ba-140 1.2E+6 1.6E+7 1.3E+6 1.6E+7 1.5E+6 1.6E+7 9.6E+5 1.6E+7 l Ce-141 3.9E+5 1.0E+7 4.1E+5 1.0E+7 4.6E+5 1.0E+7 2.7E+5 1.0E+7 l Ce-144 7.4E+6 5.3E+7 9.0E+6 5.3E+7 1.0E+7 5.3E+7 5.9E+6 5.3E+7 l I -131 1.1E+7 1.3E+7 1.2E+7 1.3E+7 1.1E+7 1.3E+7 9.0E+6 1.3E+7 l I -132 1.3E+5 9.4E+5 1.5E+5 9.4E+5 1.1E+5 9.4E+5 8.7E+4 9.4E+5 l I -133 2.7E+6 1.9E+6 2.9E+6 1.9E+6 2.2E+6 1.9E+6 1.6E+6 1.9E+6 l I -134 3.4E+4 3.4E+5 3.8E+4 3.4E+5 3.0E+4 3.4E+5 2.3E+4 3.4E+5 l I -135 5.3E+5 1.9E+6 6.0E+5 1.9E+6 4.7E+5 1.9E+6 3.4E+5 1.9E+6 l UN-ID* 4.9E+5 5.6E+8 7.5E+5 5.6E+8 9.4E+5 5.6E+8 6.5E+5 5.6E+8 l l l l l l l l l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-8 Revision 0 02-27-07

TABLE 1-3 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR R Page 2 of 2 Pathway = San Onofre Mobile Homes Distance = 1.3 miles X/Q = 5.2E-7 sec/m3 D/Q = 3.0E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H 3** 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129M 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID* 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-9 Revision 0 02-27-07

TABLE 1-4 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR A Page 1 of 3 l Pathway = Camp Mesa Distance = 0.4 miles X/Q = 2.7E-6 sec/m3 D/Q = 2.1E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.9E+2 8.5E+2 9.6E+2 9.6E+2 l Cr-51 9.7E+3 3.5E+6 1.3E+4 3.5E+6 1.6E+4 3.5E+6 1.1E+4 3.5E+6 l Mn-54 7.6E+5 1.0E+9 1.2E+6 1.0E+9 1.5E+6 1.0E+9 1.1E+6 1.0E+9 l Co-57 3.7E+3 2.6E+8 1.0E+4 2.6E+8 2.4E+4 2.6E+8 2.4E+4 2.6E+8 l Co-58 5.9E+5 2.9E+8 8.4E+5 2.9E+8 1.0E+6 2.9E+8 7.0E+5 2.9E+8 l Co-60 3.4E+6 1.6E+10 5.3E+6 1.6E+10 6.6E+6 1.6E+10 4.5E+6 1.6E+10 l Sr-89 1.5E+6 1.6E+4 1.6E+6 1.6E+4 1.8E+6 1.6E+4 1.1E+6 1.6E+4 l Sr-90 8.5E+6 1.1E+7 1.2E+7 7.3E+6 l Zr-95 1.3E+6 1.9E+8 1.7E+6 1.9E+8 2.0E+6 1.9E+8 1.3E+6 1.9E+8 l Nb-95 3.6E+5 1.0E+8 4.6E+5 1.0E+8 5.7E+5 1.0E+8 3.8E+5 1.0E+8 l Ru-103 4.2E+5 8.2E+7 5.0E+5 8.2E+7 5.9E+5 8.2E+7 3.8E+5 8.2E+7 l Te-129m 1.3E+6 1.5E+7 1.3E+6 1.5E+7 1.5E+6 1.5E+7 9.3E+5 1.5E+7 l Cs-134 6.0E+4 5.2E+9 9.1E+4 5.2E+9 1.1E+5 5.2E+9 7.4E+4 5.2E+9 l Cs-136 8.9E+3 1.1E+8 1.1E+4 1.1E+8 1.3E+4 1.1E+8 9.1E+3 1.1E+8 l Cs-137 5.4E+4 7.8E+9 7.9E+4 7.8E+9 9.1E+4 7.8E+9 5.7E+4 7.8E+9 l Ba-140 1.2E+6 1.6E+7 1.3E+6 1.6E+7 1.5E+6 1.6E+7 9.6E+5 1.6E+7 l Ce-141 3.9E+5 1.0E+7 4.1E+5 1.0E+7 4.6E+5 1.0E+7 2.7E+5 1.0E+7 l Ce-144 7.4E+6 5.3E+7 9.0E+6 5.3E+7 1.0E+7 5.3E+7 5.9E+6 5.3E+7 l I -131 1.1E+7 1.3E+7 1.2E+7 1.3E+7 1.1E+7 1.3E+7 9.0E+6 1.3E+7 l I -132 1.3E+5 9.4E+5 1.5E+5 9.4E+5 1.1E+5 9.4E+5 8.7E+4 9.4E+5 l I -133 2.7E+6 1.9E+6 2.9E+6 1.9E+6 2.2E+6 1.9E+6 1.6E+6 1.9E+6 l I -134 3.4E+4 3.4E+5 3.8E+4 3.4E+5 3.0E+4 3.4E+5 2.3E+4 3.4E+5 l I -135 5.3E+5 1.9E+6 6.0E+5 1.9E+6 4.7E+5 1.9E+6 3.4E+5 1.9E+6 l UN-ID 4.9E+5 5.6E+8 7.5E+5 5.6E+8 9.4E+5 5.6E+8 6.5E+5 5.6E+8 l l l l l l l l l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-10 Revision 1 02-29-08

TABLE 1-4 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR A Page 2 of 3 l Pathway = Camp San Mateo Distance = 3.6 miles X/Q = 7.2E-8 sec/m3 D/Q = 4.1E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-11 Revision 0 02-27-07

TABLE 1-4 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR A Page 3 of 3 l Pathway = Deer Consumer/Hunter Distance = 4.2 miles l X/Q = 5.7E-8 sec/m3 D/Q = 6.6E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhalat Food & Inhala- Food & Radio- tion Ground tion Ground ion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H-3 2.8E+1 2.3E+1 1.1E+2 3.9E+1 l Cr-51 5.0E+4 1.0E+5 1.2E+3 5.8E+5 l Mn-54 7.7E+5 1.4E+6 1.2E+5 1.2E+8 l Co-57 4.6E+6 8.0E+6 2.6E+3 4.2E+7 l Co-58 9.6E+6 1.9E+7 7.7E+4 6.9E+7 l Co-60 3.6E+7 7.2E+7 5.0E+5 1.9E+9 l Sr-89 4.9E+7 2.6E+7 1.2E+5 3.1E+7 l Sr-90 1.0E+9 8.0E+8 8.0E+5 1.2E+9 l Zr-95 6.2E+7 1.1E+8 1.5E+5 2.1E+8 l Nb-95 2.3E+8 4.5E+8 4.2E+4 8.3E+8 l Ru-103 4.2E+8 7.5E+8 4.2E+4 1.3E+9 l Te-129m 5.9E+8 4.5E+8 1.0E+5 5.4E+8 l Cs-134 1.4E+8 1.2E+8 8.1E+3 7.2E+8 l Cs-136 5.1E+6 4.2E+6 1.0E+3 1.8E+7 l Cs-137 1.2E+8 9.3E+7 6.3E+3 9.7E+8 l Ba-140 5.0E+6 4.2E+6 1.1E+5 8.5E+6 l Ce-141 1.5E+6 2.4E+6 3.0E+4 5.0E+6 l Ce-144 1.8E+7 2.9E+7 6.5E+5 5.3E+7 l I -131 6.5E+8 4.3E+8 9.9E+5 5.9E+8 l I -132 9.5E+3 1.0E+5 l I -133 1.6E+1 8.6E+0 1.8E+5 2.0E+5 l I -134 2.5E+3 3.8E+4 l I -135 1.1E-15 6.3E-16 3.7E+4 2.1E+5 l UN-ID 1.1E+8 9.4E+7 7.2E+4 1.8E+8 l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-12 Revision 1 02-29-08

TABLE 1-5 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR B Page 1 of 2 Pathway = Sanitary Landfill Distance = 2.1 miles X/Q = 1.3E-7 sec/m3 D/Q = 1.1E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 8.7E+1 l Cr-51 9.9E+2 3.2E+5 l Mn-54 9.6E+4 9.5E+7 l Co-57 2.2E+3 2.3E+7 l Co-58 6.4E+4 2.6E+7 l Co-60 4.1E+5 1.5E+9 l Sr-89 9.6E+4 1.5E+3 l Sr-90 6.6E+5 l Zr-95 1.2E+5 1.7E+7 l Nb-95 3.5E+4 9.4E+6 l Ru-103 3.5E+4 7.4E+6 l Te-129m 8.4E+4 1.3E+6 l Cs-134 6.7E+3 4.7E+8 l Cs-136 8.2E+2 1.0E+7 l Cs-137 5.2E+3 7.1E+8 l Ba-140 8.7E+4 1.4E+6 l Ce-141 2.5E+4 9.4E+5 l Ce-144 5.3E+5 4.8E+6 l I -131 8.2E+5 1.2E+6 l I -132 7.8E+3 8.5E+4 l I -133 1.5E+5 1.7E+5 l I -134 2.0E+3 3.1E+4 l I -135 3.1E+4 1.7E+5 l UN-ID 5.9E+4 5.1E+7 l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-13 Revision 1 02-29-08

TABLE 1-5 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR B Page 2 of 2 Pathway = Deer Consumer/Hunter Distance = 3.8 miles X/Q = 6.8E-8 sec/m3 D/Q = 5.1E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 1.1E+2 3.9E+1 l Cr-51 5.0E+4 1.0E+5 1.2E+3 5.8E+5 l Mn-54 7.7E+5 1.4E+6 1.2E+5 1.2E+8 l Co-57 4.6E+6 8.0E+6 2.6E+3 4.2E+7 l Co-58 9.6E+6 1.9E+7 7.7E+4 6.9E+7 l Co-60 3.6E+7 7.2E+7 5.0E+5 1.9E+9 l Sr-89 4.9E+7 2.6E+7 1.2E+5 3.1E+7 l Sr-90 1.0E+9 8.0E+8 8.0E+5 1.2E+9 l Zr-95 6.2E+7 1.1E+8 1.5E+5 2.1E+8 l Nb-95 2.3E+8 4.5E+8 4.2E+4 8.3E+8 l Ru-103 4.2E+8 7.5E+8 4.2E+4 1.3E+9 l Te-129m 5.9E+8 4.5E+8 1.0E+5 5.4E+8 l Cs-134 1.4E+8 1.2E+8 8.1E+3 7.2E+8 l Cs-136 5.1E+6 4.2E+6 1.0E+3 1.8E+7 l Cs-137 1.2E+8 9.3E+7 6.3E+3 9.7E+8 l Ba-140 5.0E+6 4.2E+6 1.1E+5 8.5E+6 l Ce-141 1.5E+6 2.4E+6 3.0E+4 5.0E+6 l Ce-144 1.8E+7 2.9E+7 6.5E+5 5.3E+7 l I -131 6.5E+8 4.3E+8 9.9E+5 5.9E+8 l I -132 9.5E+3 1.0E+5 l I -133 1.6E+1 8.6E+0 1.8E+5 2.0E+5 l I -134 2.5E+3 3.8E+4 l I -135 1.1E-15 6.3E-16 3.7E+4 2.1E+5 l UN-ID 1.1E+8 9.4E+7 7.2E+4 1.8E+8 l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-14 Revision 1 02-29-08

TABLE 1-6 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR C Page 1 of 2 Pathway = Deer Consumer/Hunter Distance = 1.0 miles X/Q = 4.0E-7 sec/m3 D/Q = 4.6E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.9E+1 l Cr-51 5.0E+4 1.0E+5 1.9E+5 l Mn-54 7.7E+5 1.4E+6 2.7E+6 l Co-57 4.6E+6 8.0E+6 1.4E+7 l Co-58 9.6E+6 1.9E+7 3.7E+7 l Co-60 3.6E+7 7.2E+7 1.3E+8 l Sr-89 4.9E+7 2.6E+7 3.1E+7 l Sr-90 1.0E+9 8.0E+8 1.2E+9 l Zr-95 6.2E+7 1.1E+8 1.9E+8 l Nb-95 2.3E+8 4.5E+8 8.1E+8 l Ru-103 4.2E+8 7.5E+8 1.3E+9 l Te-129m 5.9E+8 4.5E+8 5.3E+8 l Cs-134 1.4E+8 1.2E+8 1.5E+8 l Cs-136 5.1E+6 4.2E+6 5.4E+6 l Cs-137 1.2E+8 9.3E+7 1.2E+8 l Ba-140 5.0E+6 4.2E+6 6.8E+6 l Ce-141 1.5E+6 2.4E+6 3.8E+6 l Ce-144 1.8E+7 2.9E+7 4.7E+7 l I -131 6.5E+8 4.3E+8 5.9E+8 l I -132 l I -133 1.6E+1 8.6E+0 1.1E+1 l I -134 l I -135 1.1E-15 6.3E-16 8.1E-16 l UN-ID 1.1E+8 9.4E+7 1.2E+8 l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-15 Revision 1 02-29-08

TABLE 1-6 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR C Page 2 of 2 Pathway = Camp San Onofre Distance = 2.8 miles X/Q = 8.7E-8 sec/m3 D/Q = 7.9E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-16 Revision 0 02-27-07

TABLE 1-7 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR D Page 1 of 2 Pathway = Deer Consumer/Hunter Distance = 0.8 miles X/Q = 5.3E-7 sec/m3 D/Q = 7.3E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.3E+1 3.9E+1 l Cr-51 5.0E+4 1.0E+5 3.7E+2 3.1E+5 l Mn-54 7.7E+5 1.4E+6 3.6E+4 3.9E+7 l Co-57 4.6E+6 8.0E+6 8.1E+2 2.2E+7 l Co-58 9.6E+6 1.9E+7 2.4E+4 4.7E+7 l Co-60 3.6E+7 7.2E+7 1.5E+5 6.9E+8 l Sr-89 4.9E+7 2.6E+7 3.6E+4 3.1E+7 l Sr-90 1.0E+9 8.0E+8 2.5E+5 1.2E+9 l Zr-95 6.2E+7 1.1E+8 4.6E+4 2.0E+8 l Nb-95 2.3E+8 4.5E+8 1.3E+4 8.2E+8 l Ru-103 4.2E+8 7.5E+8 1.3E+4 1.3E+9 l Te-129m 5.9E+8 4.5E+8 3.2E+4 5.3E+8 l Cs-134 1.4E+8 1.2E+8 2.5E+3 3.2E+8 l Cs-136 5.1E+6 4.2E+6 3.1E+2 9.3E+6 l Cs-137 1.2E+8 9.3E+7 1.9E+3 3.8E+8 l Ba-140 5.0E+6 4.2E+6 3.3E+4 7.3E+6 l Ce-141 1.5E+6 2.4E+6 9.4E+3 4.2E+6 l Ce-144 1.8E+7 2.9E+7 2.0E+5 4.9E+7 l I -131 6.5E+8 4.3E+8 3.1E+5 5.9E+8 l I -132 3.0E+3 3.2E+4 l I -133 1.6E+1 8.6E+0 5.6E+4 6.3E+4 l I -134 7.7E+2 1.2E+4 l I -135 1.1E-15 6.3E-16 1.2E+4 6.5E+4 l UN-ID 1.1E+8 9.4E+7 2.2E+4 1.4E+8 l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-17 Revision 1 02-29-08

TABLE 1-7 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR D Page 2 of 2 Pathway = Camp San Onofre Distance = 3.0 miles X/Q = 6.9E-8 sec/m3 D/Q = 7.2E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-18 Revision 0 02-27-07

TABLE 1-8 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR E Page 1 of 2 Pathway = Deer Consumer/Hunter Distance = 0.8 miles X/Q = 8.5E-7 sec/m3 D/Q = 1.3E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.3E+1 3.9E+1 l Cr-51 5.0E+4 1.0E+5 3.7E+2 3.1E+5 l Mn-54 7.7E+5 1.4E+6 3.6E+4 3.9E+7 l Co-57 4.6E+6 8.0E+6 8.1E+2 2.2E+7 l Co-58 9.6E+6 1.9E+7 2.4E+4 4.7E+7 l Co-60 3.6E+7 7.2E+7 1.5E+5 6.9E+8 l Sr-89 4.9E+7 2.6E+7 3.6E+4 3.1E+7 l Sr-90 1.0E+9 8.0E+8 2.5E+5 1.2E+9 l Zr-95 6.2E+7 1.1E+8 4.6E+4 2.0E+8 l Nb-95 2.3E+8 4.5E+8 1.3E+4 8.2E+8 l Ru-103 4.2E+8 7.5E+8 1.3E+4 1.3E+9 l Te-129m 5.9E+8 4.5E+8 3.2E+4 5.3E+8 l Cs-134 1.4E+8 1.2E+8 2.5E+3 3.2E+8 l Cs-136 5.1E+6 4.2E+6 3.1E+2 9.3E+6 l Cs-137 1.2E+8 9.3E+7 1.9E+3 3.8E+8 l Ba-140 5.0E+6 4.2E+6 3.3E+4 7.3E+6 l Ce-141 1.5E+6 2.4E+6 9.4E+3 4.2E+6 l Ce-144 1.8E+7 2.9E+7 2.0E+5 4.9E+7 l I -131 6.5E+8 4.3E+8 3.1E+5 5.9E+8 l I -132 3.0E+3 3.2E+4 l I -133 1.6E+1 8.6E+0 5.6E+4 6.3E+4 l I -134 7.7E+2 1.2E+4 l I -135 1.1E-15 6.3E-16 1.2E+4 6.5E+4 l UN-ID 1.1E+8 9.4E+7 2.2E+4 1.4E+8 l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-19 Revision 1 02-29-08

TABLE 1-8 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR E Page 2 of 2 Pathway = Camp Horno Distance = 4.1 miles X/Q = 7.5E-8 sec/m3 D/Q = 7.2E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-20 Revision 0 02-27-07

TABLE 1-9 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR F Page 1 of 1 Pathway = San Onofre State Park/Guard Shack Distance = 0.8 miles X/Q = 9.6E-7 sec/m3 D/Q = 8.4E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.2E+2 Cr-51 2.5E+3 8.0E+5 Mn-54 2.4E+5 2.4E+8 Co-57 5.4E+3 5.9E+7 Co-58 1.6E+5 6.5E+7 Co-60 1.0E+6 3.7E+9 Sr-89 2.4E+5 3.7E+3 Sr-90 1.6E+6 Zr-95 3.0E+5 4.3E+7 Nb-95 8.6E+4 2.3E+7 Ru-103 8.6E+4 1.9E+7 Te-129m 2.0E+5 3.4E+6 Cs-134 1.7E+4 1.2E+9 Cs-136 2.1E+3 2.6E+7 Cs-137 1.3E+4 1.8E+9 Ba-140 2.2E+5 3.5E+6 Ce-141 6.2E+4 2.3E+6 Ce-144 1.3E+6 1.2E+7 I -131 2.0E+6 2.9E+6 I -132 2.0E+4 2.1E+5 I -133 3.7E+5 4.2E+5 I -134 5.1E+3 7.7E+4 I -135 7.7E+4 4.3E+5 UN-ID 1.5E+5 1.3E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-21 Revision 0 02-27-07

TABLE 1-10 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR G Page 1 of 3 l Pathway = San Onofre State Beach Campground Distance = 1.8 miles X/Q = 2.3E-7 sec/m3 D/Q = 1.0E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.3E+1 9.2E+1 1.0E+2 1.0E+2 Cr-51 1.1E+3 3.8E+5 1.4E+3 3.8E+5 1.7E+3 3.8E+5 1.2E+3 3.8E+5 Mn-54 8.2E+4 1.1E+8 1.3E+5 1.1E+8 1.6E+5 1.1E+8 1.2E+5 1.1E+8 Co-57 4.0E+2 2.8E+7 1.1E+3 2.8E+7 2.6E+3 2.8E+7 2.6E+3 2.8E+7 Co-58 6.4E+4 3.1E+7 9.1E+4 3.1E+7 1.1E+5 3.1E+7 7.6E+4 3.1E+7 Co-60 3.7E+5 1.8E+9 5.8E+5 1.8E+9 7.2E+5 1.8E+9 4.9E+5 1.8E+9 Sr-89 1.7E+5 1.8E+3 1.8E+5 1.8E+3 2.0E+5 1.8E+3 1.2E+5 1.8E+3 Sr-90 9.2E+5 1.2E+6 1.4E+6 7.9E+5 Zr-95 1.4E+5 2.1E+7 1.8E+5 2.1E+7 2.2E+5 2.1E+7 1.5E+5 2.1E+7 Nb-95 3.9E+4 1.1E+7 5.0E+4 1.1E+7 6.2E+4 1.1E+7 4.1E+4 1.1E+7 Ru-103 4.5E+4 8.9E+6 5.4E+4 8.9E+6 6.4E+4 8.9E+6 4.1E+4 8.9E+6 Te-129m 1.4E+5 1.6E+6 1.4E+5 1.6E+6 1.6E+5 1.6E+6 1.0E+5 1.6E+6 Cs-134 6.5E+3 5.6E+8 9.9E+3 5.6E+8 1.2E+4 5.6E+8 8.0E+3 5.6E+8 Cs-136 9.7E+2 1.2E+7 1.2E+3 1.2E+7 1.5E+3 1.2E+7 9.9E+2 1.2E+7 Cs-137 5.9E+3 8.5E+8 8.5E+3 8.5E+8 9.9E+3 8.5E+8 6.2E+3 8.5E+8 Ba-140 1.3E+5 1.7E+6 1.4E+5 1.7E+6 1.7E+5 1.7E+6 1.0E+5 1.7E+6 Ce-141 4.2E+4 1.1E+6 4.5E+4 1.1E+6 5.0E+4 1.1E+6 3.0E+4 1.1E+6 Ce-144 8.1E+5 5.7E+6 9.8E+5 5.7E+6 1.1E+6 5.7E+6 6.4E+5 5.7E+6 I -131 1.2E+6 1.4E+6 1.3E+6 1.4E+6 1.2E+6 1.4E+6 9.8E+5 1.4E+6 I -132 1.4E+4 1.0E+5 1.6E+4 1.0E+5 1.2E+4 1.0E+5 9.4E+3 1.0E+5 I -133 2.9E+5 2.0E+5 3.2E+5 2.0E+5 2.4E+5 2.0E+5 1.8E+5 2.0E+5 I -134 3.7E+3 3.7E+4 4.2E+3 3.7E+4 3.2E+3 3.7E+4 2.5E+3 3.7E+4 I -135 5.7E+4 2.1E+5 6.5E+4 2.1E+5 5.1E+4 2.1E+5 3.7E+4 2.1E+5 UN-ID 5.3E+4 6.1E+7 8.2E+4 6.1E+7 1.0E+5 6.1E+7 7.1E+4 6.1E+7 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-22 Revision 0 02-27-07

TABLE 1-10 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR G Page 2 of 3 Pathway = Surfcamp.com Distance = 2.3 miles l X/Q = 1.6E-7 sec/m3 D/Q = 6.4E-10 m-2 l Infant Child Teen Adult l Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & l Radio- tion Ground tion Ground tion Ground tion Ground l Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l H -3** 2.9E+2 3.3E+2 3.3E+2 l Cr-51 4.4E+3 1.2E+6 5.5E+3 1.2E+6 3.7E+3 1.2E+6 l Mn-54 4.1E+5 3.6E+8 5.2E+5 3.6E+8 3.6E+5 3.6E+8 l Co-57 3.4E+3 8.9E+7 8.2E+3 8.9E+7 8.2E+3 8.9E+7 l Co-58 2.9E+5 9.9E+7 3.5E+5 9.9E+7 2.4E+5 9.9E+7 l Co-60 1.8E+6 5.6E+9 2.3E+6 5.6E+9 1.6E+6 5.6E+9 l Sr-89 5.6E+5 5.6E+3 6.3E+5 5.6E+3 3.6E+5 5.6E+3 l Sr-90 3.8E+6 4.3E+6 2.5E+6 l Zr-95 5.8E+5 6.5E+7 7.0E+5 6.5E+7 4.6E+5 6.5E+7 l Nb-95 1.6E+5 3.6E+7 2.0E+5 3.6E+7 1.3E+5 3.6E+7 l Ru-103 1.7E+5 2.8E+7 2.0E+5 2.8E+7 1.3E+5 2.8E+7 l Te-129m 4.6E+5 5.1E+6 5.1E+5 5.1E+6 3.2E+5 5.1E+6 l Cs-134 3.1E+4 1.8E+9 3.8E+4 1.8E+9 2.5E+4 1.8E+9 l Cs-136 3.8E+3 3.9E+7 4.6E+3 3.9E+7 3.1E+3 3.9E+7 l Cs-137 2.7E+4 2.7E+9 3.1E+4 2.7E+9 2.0E+4 2.7E+9 l Ba-140 4.5E+5 5.3E+6 5.3E+5 5.3E+6 3.3E+5 5.3E+6 l Ce-141 1.4E+5 3.6E+6 1.6E+5 3.6E+6 9.4E+4 3.6E+6 l Ce-144 3.1E+6 1.8E+7 3.5E+6 1.8E+7 2.0E+6 1.8E+7 l I -131 4.2E+6 4.5E+6 3.8E+6 4.5E+6 3.1E+6 4.5E+6 l I -132 5.0E+4 3.2E+5 3.9E+4 3.2E+5 3.0E+4 3.2E+5 l I -133 1.0E+6 6.4E+5 7.6E+5 6.4E+5 5.6E+5 6.4E+5 l I -134 1.3E+4 1.2E+5 1.0E+4 1.2E+5 7.8E+3 1.2E+5 l I -135 2.1E+5 6.6E+5 1.6E+5 6.6E+5 1.2E+5 6.6E+5 l UN-ID* 2.6E+5 1.9E+8 3.2E+5 1.9E+8 2.2E+5 1.9E+8 l l l l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-23 Revision 1 02-29-08

TABLE 1-10 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR G Page 3 of 3 Pathway = San Onofre State Beach Surfcamp Distance = 2.8 miles X/Q = 1.2E-7 sec/m3 D/Q = 4.5E-10 m-2 l Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3** 3.1E+2 3.6E+2 6.3E+2 l Cr-51 4.7E+3 1.3E+6 5.9E+3 1.3E+6 7.2E+3 2.3E+6 l Mn-54 4.4E+5 3.9E+8 5.5E+5 3.9E+8 7.0E+5 6.9E+8 l Co-57 3.7E+3 9.6E+7 8.8E+3 9.6E+7 1.6E+4 1.7E+8 l Co-58 3.1E+5 1.1E+8 3.8E+5 1.1E+8 4.6E+5 1.9E+8 l Co-60 2.0E+6 6.0E+9 2.4E+6 6.0E+9 3.0E+6 1.1E+10 l Sr-89 6.0E+5 6.0E+3 6.8E+5 6.0E+3 7.0E+5 1.1E+4 l Sr-90 4.1E+6 4.6E+6 4.8E+6 l Zr-95 6.2E+5 7.0E+7 7.5E+5 7.0E+7 8.8E+5 1.3E+8 l Nb-95 1.7E+5 3.8E+7 2.1E+5 3.8E+7 2.5E+5 6.8E+7 l Ru-103 1.9E+5 3.0E+7 2.2E+5 3.0E+7 2.5E+5 5.4E+7 l Te-129m 4.9E+5 5.5E+6 5.5E+5 5.5E+6 6.2E+5 9.8E+6 l Cs-134 3.4E+4 1.9E+9 4.1E+4 1.9E+9 4.9E+4 3.4E+9 l Cs-136 4.1E+3 4.2E+7 5.0E+3 4.2E+7 6.0E+3 7.5E+7 l Cs-137 2.9E+4 2.9E+9 3.4E+4 2.9E+9 3.8E+4 5.1E+9 l Ba-140 4.9E+5 5.7E+6 5.7E+5 5.7E+6 6.4E+5 1.0E+7 l Ce-141 1.5E+5 3.8E+6 1.7E+5 3.8E+6 1.8E+5 6.8E+6 l Ce-144 3.3E+6 1.9E+7 3.7E+6 1.9E+7 3.9E+6 3.5E+7 l I -131 4.5E+6 4.8E+6 4.1E+6 4.8E+6 6.0E+6 8.6E+6 l I -132 5.4E+4 3.5E+5 4.2E+4 3.5E+5 5.7E+4 6.2E+5 l I -133 1.1E+6 6.8E+5 8.2E+5 6.8E+5 1.1E+6 1.2E+6 l I -134 1.4E+4 1.3E+5 1.1E+4 1.3E+5 1.5E+4 2.2E+5 l I -135 2.2E+5 7.0E+5 1.7E+5 7.0E+5 2.2E+5 1.3E+6 l UN-ID* 2.8E+5 2.1E+8 3.5E+5 2.1E+8 4.3E+5 3.7E+8 l mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A1-24 Revision 1 02-29-08

TABLE 2-1 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR D Page 1 of 1 Pathway = Camp Horno Sewage Trmnt. Distance = 3.2 Miles X/Q = 1.2E-7 sec/m3 D/Q = 1.2E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.9E+2 Cr-51 3.3E+3 1.1E+6 Mn-54 3.2E+5 3.2E+8 Co-57 8.4E+4 7.8E+7 Co-58 2.1E+5 8.7E+7 Co-60 1.4E+6 4.9E+9 Sr-89 3.2E+5 4.9E+3 Sr-90 2.3E+7 Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.1E+7 Ru-103 1.2E+5 2.5E+7 Te-129m 2.6E+5 4.5E+6 Cs-134 1.9E+5 1.6E+9 Cs-136 3.3E+4 3.4E+7 Cs-137 1.4E+5 2.3E+9 Ba-140 2.9E+5 4.7E+6 Ce-141 8.3E+4 3.1E+6 Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 I -135 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-1 Revision 0 02-27-07

TABLE 2-2 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR E Page 1 of 1 Pathway = Camp Horno Distance = 3.7 Miles X/Q = 6.0E-7 sec/m3 D/Q = 5.7E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-2 Revision 0 02-27-07

TABLE 2-3 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR F Page 1 of 4 Pathway = Sheep (Meat)/Shepherd Distance = 0.3 Miles X/Q = 7.2E-6 sec/m3 D/Q = 4.5E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 I -133 1.6E+2 8.7E+3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-3 Revision 0 02-27-07

TABLE 2-3 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR F Page 2 of 4 Pathway = San Onofre State Park/Guard Shack Distance = 0.4 Miles X/Q = 5.4E-6 sec/m3 D/Q = 3.5E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.2E+2 Cr-51 2.5E+3 8.0E+5 Mn-54 2.4E+5 2.4E+8 Co-57 6.3E+4 5.9E+7 Co-58 1.6E+5 6.5E+7 Co-60 1.0E+6 3.7E+9 Sr-89 2.4E+5 3.7E+3 Sr-90 1.7E+7 Zr-95 3.0E+5 4.3E+7 Nb-95 8.6E+4 2.3E+7 Ru-103 8.6E+4 1.9E+7 Te-129m 2.0E+5 3.4E+6 Cs-134 1.5E+5 1.2E+9 Cs-136 2.5E+4 2.6E+7 Cs-137 1.1E+5 1.8E+9 Ba-140 2.2E+5 3.5E+6 Ce-141 6.2E+4 2.3E+6 Ce-144 1.3E+6 1.2E+7 I -131 2.0E+6 2.9E+6 I -132 2.0E+4 2.1E+5 I -133 3.7E+5 4.2E+5 I -134 5.1E+3 7.7E+4 I -135 7.7E+4 4.3E+5 UN-ID 1.5E+5 1.3E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-4 Revision 0 02-27-07

TABLE 2-3 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR F Page 3 of 4 Pathway = Deer Consumer/Hunter Distance = 0.4 Miles X/Q = 5.4E-6 sec/m3 D/Q = 3.5E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-5 Revision 0 02-27-07

TABLE 2-3 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR F Page 4 of 4 Pathway = Border Patrol Checkpt. Distance = 1.4 Miles X/Q = 1.2E-6 sec/m3 D/Q = 8.2E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.6E+2 Cr-51 4.1E+3 1.3E+6 Mn-54 4.0E+5 3.9E+8 Co-57 1.1E+5 9.8E+7 Co-58 2.6E+5 1.1E+8 Co-60 1.7E+6 6.1E+9 Sr-89 4.0E+5 6.2E+3 Sr-90 2.8E+7 Zr-95 5.0E+5 7.2E+7 Nb-95 1.4E+5 3.9E+7 Ru-103 1.4E+5 3.1E+7 Te-129m 3.3E+5 5.6E+6 Cs-134 2.4E+5 1.9E+9 Cs-136 4.2E+4 4.3E+7 Cs-137 1.8E+5 2.9E+9 Ba-140 3.6E+5 5.9E+6 Ce-141 1.0E+5 3.9E+6 Ce-144 2.2E+6 2.0E+7 I -131 3.4E+6 4.9E+6 I -132 3.3E+4 3.5E+5 I -133 6.1E+5 7.0E+5 I -134 8.5E+3 1.3E+5 I -135 1.3E+5 7.2E+5 UN-ID 2.5E+5 2.1E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-6 Revision 0 02-27-07

TABLE 2-4 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR G Page 1 of 4 Pathway = San Onofre Bch Campgd Distance = 0.4 Miles X/Q = 4.5E-6 sec/m3 D/Q = 1.8E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 8.0E+1 1.4E+2 1.6E+2 2.9E+2 Cr-51 1.6E+3 5.7E+5 2.1E+3 5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.1E+6 Mn-54 1.2E+5 1.7E+8 1.9E+5 1.7E+8 2.4E+5 1.7E+8 3.2E+5 3.2E+8 Co-57 4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 Co-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 2.1E+5 8.7E+7 Co-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.1E+6 2.7E+9 1.4E+6 4.9E+9 Sr-89 2.5E+5 2.7E+3 2.7E+5 2.7E+3 3.0E+5 2.7E+3 3.2E+5 4.9E+3 Sr-90 5.0E+6 1.2E+7 1.3E+7 2.3E+7 Zr-95 2.2E+5 3.1E+7 2.8E+5 3.1E+7 3.3E+5 3.1E+7 4.0E+5 5.7E+7 Nb-95 5.9E+4 1.7E+7 7.6E+4 1.7E+7 9.3E+4 1.7E+7 1.2E+5 3.1E+7 Ru-103 6.8E+4 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7 Te-129m 2.1E+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 2.4E+6 2.6E+5 4.5E+6 Cs-134 8.7E+4 8.4E+8 1.3E+5 8.4E+8 1.4E+5 8.4E+8 1.9E+5 1.6E+9 Cs-136 1.7E+4 1.9E+7 2.1E+4 1.9E+7 2.4E+4 1.9E+7 3.3E+4 3.4E+7 Cs-137 7.5E+4 1.3E+9 1.1E+5 1.3E+9 1.0E+5 1.3E+9 1.4E+5 2.3E+9 Ba-140 2.0E+5 2.5E+6 2.1E+5 2.5E+6 2.5E+5 2.5E+6 2.9E+5 4.7E+6 Ce-141 6.4E+4 1.7E+6 6.7E+4 1.7E+6 7.6E+4 1.7E+6 8.3E+4 3.1E+6 Ce-144 1.2E+6 8.6E+6 1.5E+6 8.6E+6 1.6E+6 8.6E+6 1.8E+6 1.6E+7 I -131 1.8E+6 2.1E+6 2.0E+6 2.1E+6 1.8E+6 2.1E+6 2.7E+6 3.9E+6 I -132 2.1E+4 1.5E+5 2.4E+4 1.5E+5 1.9E+4 1.5E+5 2.6E+4 2.8E+5 I -133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.6E+5 3.0E+5 4.9E+5 5.6E+5 I -134 5.5E+3 5.5E+4 6.3E+3 5.5E+4 4.9E+3 5.5E+4 6.8E+3 1.0E+5 I -135 8.6E+4 3.1E+5 9.8E+4 3.1E+5 7.7E+4 3.1E+5 1.0E+5 5.8E+5 UN-ID 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 2.0E+5 1.7E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-7 Revision 0 02-27-07

TABLE 2-4 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR G Page 2 of 4 Pathway = Highway Patrol Weigh Station Distance = 1.6 Miles X/Q = 4.2E-7 sec/m3 D/Q = 1.7E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.0E+2 Cr-51 3.4E+3 1.1E+6 Mn-54 3.3E+5 3.3E+8 Co-57 8.8E+4 8.1E+7 Co-58 2.2E+5 9.0E+7 Co-60 1.4E+6 5.1E+9 Sr-89 3.3E+5 5.1E+3 Sr-90 2.4E+7 Zr-95 4.2E+5 6.0E+7 Nb-95 1.2E+5 3.2E+7 Ru-103 1.2E+5 2.6E+7 Te-129m 2.8E+5 4.7E+6 Cs-134 2.0E+5 1.6E+9 Cs-136 3.5E+4 3.6E+7 Cs-137 1.5E+5 2.4E+9 Ba-140 3.0E+5 4.9E+6 Ce-141 8.6E+4 3.2E+6 Ce-144 1.8E+6 1.7E+7 I -131 2.8E+6 4.1E+6 I -132 2.7E+4 2.9E+5 I -133 5.1E+5 5.8E+5 I -134 7.1E+3 1.1E+5 I -135 1.1E+5 6.0E+5 UN-ID 2.1E+5 1.8E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-8 Revision 0 02-27-07

TABLE 2-4 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR G Page 3 of 4 Pathway = Sheep (Meat)/Shepherd Distance = 2.3 Miles X/Q = 2.4E-7 sec/m3 D/Q = 9.2E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.1E+0 Cr-51 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 I -133 1.6E+2 8.7E+3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-9 Revision 0 02-27-07

TABLE 2-4 SOUTH YARD FACILITY DOSE PARAMETER Ri FOR SECTOR G Page 4 of 4 Pathway = Deer Consumer/Hunter Distance = 2.9 Miles X/Q = 1.8E-7 sec/m3 D/Q = 6.4E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A2-10 Revision 0 02-27-07

TABLE 3-1 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR P Page 1 of 3 Pathway = Surf Beach/Life Guard Distance = 0.3 miles X/Q = 3.8E-6 sec/m3 D/Q = 1.7E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 7.8E+0 4.2E+1 1.2E+2 Cr-51 1.2E+2 3.2E+4 6.9E+2 1.5E+5 1.3E+3 4.2E+5 Mn-54 1.1E+4 9.5E+6 6.5E+4 4.5E+7 1.3E+5 1.3E+8 Co-57 9.1E+1 2.4E+6 1.0E+3 1.1E+7 2.9E+3 3.1E+7 Co-58 7.6E+3 2.6E+6 4.4E+4 1.2E+7 8.5E+4 3.5E+7 Co-60 4.9E+4 1.5E+8 2.9E+5 7.0E+8 5.4E+5 2.0E+9 Sr-89 1.5E+4 1.5E+2 7.9E+4 7.1E+2 1.3E+5 2.0E+3 Sr-90 1.0E+5 5.4E+5 8.8E+5 Zr-95 1.5E+4 1.7E+6 8.8E+4 8.2E+6 1.6E+5 2.3E+7 Nb-95 4.2E+3 9.4E+5 2.5E+4 4.5E+6 4.6E+4 1.2E+7 Ru-103 4.6E+3 7.5E+5 2.6E+4 3.6E+6 4.6E+4 9.9E+6 Te-129m 1.2E+4 1.4E+5 6.5E+4 6.4E+5 1.1E+5 1.8E+6 Cs-134 8.3E+2 4.7E+7 4.8E+3 2.2E+8 8.9E+3 6.2E+8 Cs-136 1.0E+2 1.0E+6 5.8E+2 4.9E+6 1.1E+3 1.4E+7 Cs-137 7.2E+2 7.1E+7 4.0E+3 3.4E+8 6.9E+3 9.4E+8 Ba-140 1.2E+4 1.4E+5 6.6E+4 6.7E+5 1.2E+5 1.9E+6 Ce-141 3.8E+3 9.4E+4 2.0E+4 4.5E+5 3.3E+4 1.2E+6 Ce-144 8.2E+4 4.8E+5 4.4E+5 2.3E+6 7.1E+5 6.4E+6 I -131 1.1E+5 1.2E+5 4.8E+5 5.6E+5 1.1E+6 1.6E+6 I -132 1.3E+3 8.5E+3 4.9E+3 4.1E+4 1.0E+4 1.1E+5 I -133 2.7E+4 1.7E+4 9.5E+4 8.0E+4 2.0E+5 2.2E+5 I -134 3.5E+2 3.1E+3 1.3E+3 1.5E+4 2.7E+3 4.1E+4 I -135 5.5E+3 1.7E+4 2.0E+4 8.2E+4 4.1E+4 2.3E+5 UN-ID 6.9E+3 5.1E+6 4.1E+4 2.4E+7 7.9E+4 6.8E+7 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-1 Revision 0 02-27-07

TABLE 3-1 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR P Page 2 of 3 Pathway = Cotton Point Estates (w/o Garden) Distance = 2.5 miles X/Q = 1.4E-7 sec/m3 D/Q = 4.2E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-2 Revision 0 02-27-07

TABLE 3-1 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR P Page 3 of 3 Pathway = Cotton Point Estates with Garden Distance = 2.6 miles X/Q = 1.3E-7 sec/m3 D/Q = 3.9E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 4.0E+3 1.3E+3 2.6E+3 1.3E+3 2.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 1.1E+7 2.1E+4 1.5E+7 1.4E+4 1.6E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.3E+9 1.4E+6 2.3E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 5.8E+8 3.1E+4 6.6E+8 3.1E+4 6.3E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 7.5E+8 1.3E+6 9.7E+8 9.3E+5 9.9E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.4E+10 8.7E+6 2.5E+10 6.0E+6 2.5E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 3.5E+10 2.4E+6 1.5E+10 1.4E+6 9.8E+9 Sr-90 1.1E+7 1.5E+7 1.4E+12 1.6E+7 8.3E+11 9.6E+6 6.7E+11 Zr-95 1.8E+6 2.5E+8 2.2E+6 1.1E+9 2.7E+6 1.5E+9 1.8E+6 1.4E+9 Nb-95 4.8E+5 1.4E+8 6.1E+5 4.3E+8 7.5E+5 5.9E+8 5.0E+5 6.1E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 5.0E+8 7.8E+5 6.8E+8 5.0E+5 6.6E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.9E+9 2.0E+6 1.8E+9 1.2E+6 1.2E+9 Cs-134 8.0E+4 6.8E+9 1.2E+5 3.2E+10 1.5E+5 2.3E+10 9.8E+4 1.8E+10 Cs-136 1.2E+4 1.5E+8 1.5E+4 3.7E+8 1.8E+4 3.2E+8 1.2E+4 3.2E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 3.4E+10 1.2E+5 2.4E+10 7.5E+4 1.9E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 3.0E+8 2.0E+6 2.3E+8 1.3E+6 2.8E+8 Ce-141 5.2E+5 1.4E+7 5.4E+5 4.2E+8 6.1E+5 5.5E+8 3.6E+5 5.2E+8 Ce-144 9.8E+6 7.0E+7 1.2E+7 1.0E+10 1.3E+7 1.3E+10 7.8E+6 1.1E+10 I -131 1.5E+7 1.7E+7 1.6E+7 4.8E+10 1.5E+7 3.1E+10 1.2E+7 3.8E+10 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 8.1E+8 2.9E+6 4.6E+8 2.2E+6 5.3E+8 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 1.2E+7 6.2E+5 8.2E+6 4.5E+5 9.1E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 3.5E+9 1.2E+6 2.6E+9 8.6E+5 2.0E+9 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-3 Revision 0 02-27-07

TABLE 3-2 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR Q Page 1 of 4 Pathway = San Onofre Recreation Beach Distance = 0.8 miles X/Q = 1.2E-6 sec/m3 D/Q = 6.1E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-4 Revision 0 02-27-07

TABLE 3-2 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR Q Page 2 of 4 Pathway = San Onofre Mobile Homes Distance = 1.2 miles X/Q = 9.1E-7 sec/m3 D/Q = 4.3E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-5 Revision 0 02-27-07

TABLE 3-2 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR Q Page 3 of 4 Pathway = San Mateo Pt Homes Distance = 2.5 miles X/Q = 2.8E-7 sec/m3 D/Q = 1.1E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-6 Revision 0 02-27-07

TABLE 3-2 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR Q Page 4 of 4 Pathway = San Clemente Resident With Garden Distance = 3.9 miles X/Q = 1.5E-7 sec/m3 D/Q = 5.1E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 4.0E+3 1.3E+3 2.6E+3 1.3E+3 2.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 1.1E+7 2.1E+4 1.5E+7 1.4E+4 1.6E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.3E+9 1.4E+6 2.3E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 5.8E+8 3.1E+4 6.6E+8 3.1E+4 6.3E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 7.5E+8 1.3E+6 9.7E+8 9.3E+5 9.9E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.4E+10 8.7E+6 2.5E+10 6.0E+6 2.5E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 3.5E+10 2.4E+6 1.5E+10 1.4E+6 9.8E+9 Sr-90 1.1E+7 1.5E+7 1.4E+12 1.6E+7 8.3E+11 9.6E+6 6.7E+11 Zr-95 1.8E+6 2.5E+8 2.2E+6 1.1E+9 2.7E+6 1.5E+9 1.8E+6 1.4E+9 Nb-95 4.8E+5 1.4E+8 6.1E+5 4.3E+8 7.5E+5 5.9E+8 5.0E+5 6.1E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 5.0E+8 7.8E+5 6.8E+8 5.0E+5 6.6E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.9E+9 2.0E+6 1.8E+9 1.2E+6 1.2E+9 Cs-134 8.0E+4 6.8E+9 1.2E+5 3.2E+10 1.5E+5 2.3E+10 9.8E+4 1.8E+10 Cs-136 1.2E+4 1.5E+8 1.5E+4 3.7E+8 1.8E+4 3.2E+8 1.2E+4 3.2E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 3.4E+10 1.2E+5 2.4E+10 7.5E+4 1.9E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 3.0E+8 2.0E+6 2.3E+8 1.3E+6 2.8E+8 Ce-141 5.2E+5 1.4E+7 5.4E+5 4.2E+8 6.1E+5 5.5E+8 3.6E+5 5.2E+8 Ce-144 9.8E+6 7.0E+7 1.2E+7 1.0E+10 1.3E+7 1.3E+10 7.8E+6 1.1E+10 I -131 1.5E+7 1.7E+7 1.6E+7 4.8E+10 1.5E+7 3.1E+10 1.2E+7 3.8E+10 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 8.1E+8 2.9E+6 4.6E+8 2.2E+6 5.3E+8 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 1.2E+7 6.2E+5 8.2E+6 4.5E+5 9.1E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 3.5E+9 1.2E+6 2.6E+9 8.6E+5 2.0E+9 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-7 Revision 0 02-27-07

TABLE 3-3 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR R Page 1 of 1 Pathway = San Onofre Mobile Homes Distance = 1.2 miles X/Q = 6.0E-7 sec/m3 D/Q = 3.5E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-8 Revision 0 02-27-07

TABLE 3-4 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR A Page 1 of 2 Pathway = Camp Mesa Distance = 0.3 miles X/Q = 4.2E-6 sec/m3 D/Q = 3.2E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-9 Revision 0 02-27-07

TABLE 3-4 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR A Page 2 of 2 Pathway = Camp San Mateo Distance = 3.5 miles X/Q = 7.8E-8 sec/m3 D/Q = 4.4E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-10 Revision 0 02-27-07

TABLE 3-5 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR B Page 1 of 2 Pathway = Camp Mesa Distance = 0.3 miles X/Q = 3.9E-6 sec/m3 D/Q = 3.4E-8 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.1E+3 1.3E+3 1.3E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co-57 4.9E+3 3.4E+8 1.3E+4 3.4E+8 3.1E+4 3.4E+8 3.1E+4 3.4E+8 Co-58 7.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 1.1E+7 1.5E+7 1.6E+7 9.6E+6 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 8.0E+4 6.8E+9 1.2E+5 6.8E+9 1.5E+5 6.8E+9 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 1.5E+4 1.5E+8 1.8E+4 1.5E+8 1.2E+4 1.5E+8 Cs-137 7.1E+4 1.0E+10 1.0E+5 1.0E+10 1.2E+5 1.0E+10 7.5E+4 1.0E+10 Ba-140 1.6E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-11 Revision 0 02-27-07

TABLE 3-5 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR B Page 2 of 2 Pathway = Sanitary Landfill Distance = 2.1 miles X/Q = 1.4E-7 sec/m3 D/Q = 1.2E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.8E+1 Cr-51 6.6E+2 2.1E+5 Mn-54 6.4E+4 6.3E+7 Co-57 1.4E+3 1.6E+7 Co-58 4.2E+4 1.7E+7 Co-60 2.7E+5 9.8E+8 Sr-89 6.4E+4 9.9E+2 Sr-90 4.4E+5 Zr-95 8.1E+4 1.1E+7 Nb-95 2.3E+4 6.2E+6 Ru-103 2.3E+4 5.0E+6 Te-129m 5.6E+4 9.0E+5 Cs-134 4.5E+3 3.1E+8 Cs-136 5.5E+2 6.9E+6 Cs-137 3.4E+3 4.7E+8 Ba-140 5.8E+4 9.4E+5 Ce-141 1.7E+4 6.2E+5 Ce-144 3.6E+5 3.2E+6 I -131 5.4E+5 7.9E+5 I -132 5.2E+3 5.7E+4 I -133 9.8E+4 1.1E+5 I -134 1.4E+3 2.1E+4 I -135 2.0E+4 1.2E+5 UN-ID 3.9E+4 3.4E+7 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-12 Revision 0 02-27-07

TABLE 3-6 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR C Page 1 of 2 Pathway = Deer Consumer/Hunter Distance = 1.1 miles X/Q = 3.7E-7 sec/m3 D/Q = 4.6E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 5.4E+0 3.9E+1 Cr-51 5.0E+4 1.0E+5 6.2E+1 2.1E+5 Mn-54 7.7E+5 1.4E+6 6.0E+3 8.6E+6 Co-57 4.6E+6 8.0E+6 1.4E+2 1.5E+7 Co-58 9.6E+6 1.9E+7 4.0E+3 3.9E+7 Co-60 3.6E+7 7.2E+7 2.6E+4 2.3E+8 Sr-89 4.9E+7 2.6E+7 6.0E+3 3.1E+7 Sr-90 1.0E+9 8.0E+8 4.1E+4 1.2E+9 Zr-95 6.2E+7 1.1E+8 7.6E+3 1.9E+8 Nb-95 2.3E+8 4.5E+8 2.2E+3 8.1E+8 Ru-103 4.2E+8 7.5E+8 2.2E+3 1.3E+9 Te-129m 5.9E+8 4.5E+8 5.3E+3 5.3E+8 Cs-134 1.4E+8 1.2E+8 4.2E+2 1.8E+8 Cs-136 5.1E+6 4.2E+6 5.2E+1 6.1E+6 Cs-137 1.2E+8 9.3E+7 3.2E+2 1.6E+8 Ba-140 5.0E+6 4.2E+6 5.5E+3 6.9E+6 Ce-141 1.5E+6 2.4E+6 1.6E+3 3.9E+6 Ce-144 1.8E+7 2.9E+7 3.3E+4 4.7E+7 I -131 6.5E+8 4.3E+8 5.1E+4 5.9E+8 I -132 4.9E+2 5.3E+3 I -133 1.6E+1 8.6E+0 9.3E+3 1.1E+4 I -134 1.3E+2 1.9E+3 I -135 1.1E-15 6.3E-16 1.9E+3 1.1E+4 UN-ID 1.1E+8 9.4E+7 3.7E+3 1.3E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-13 Revision 0 02-27-07

TABLE 3-6 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR C Page 2 of 2 Pathway = Camp San Onofre Distance = 2.9 miles X/Q = 8.4E-8 sec/m3 D/Q = 7.4E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-14 Revision 0 02-27-07

TABLE 3-7 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR D Page 1 of 1 Pathway = Camp San Onofre Distance = 3.0 miles X/Q = 7.0E-8 sec/m3 D/Q = 7.2E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-15 Revision 0 02-27-07

TABLE 3-8 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR E Page 1 of 2 Pathway = Deer Consumer/Hunter Distance = 1.0 miles X/Q = 6.0E-7 sec/m3 D/Q = 8.4E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E+1 2.3E+1 8.9E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 1.0E+3 5.2E+5 Mn-54 7.7E+5 1.4E+6 9.8E+4 1.0E+8 Co-57 4.6E+6 8.0E+6 2.2E+3 3.8E+7 Co-58 9.6E+6 1.9E+7 6.5E+4 6.4E+7 Co-60 3.6E+7 7.2E+7 4.2E+5 1.6E+9 Sr-89 4.9E+7 2.6E+7 9.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 6.7E+5 1.2E+9 Zr-95 6.2E+7 1.1E+8 1.2E+5 2.1E+8 Nb-95 2.3E+8 4.5E+8 3.5E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 3.5E+4 1.3E+9 Te-129m 5.9E+8 4.5E+8 8.6E+4 5.3E+8 Cs-134 1.4E+8 1.2E+8 6.8E+3 6.3E+8 Cs-136 5.1E+6 4.2E+6 8.4E+2 1.6E+7 Cs-137 1.2E+8 9.3E+7 5.3E+3 8.4E+8 Ba-140 5.0E+6 4.2E+6 8.9E+4 8.2E+6 Ce-141 1.5E+6 2.4E+6 2.5E+4 4.8E+6 Ce-144 1.8E+7 2.9E+7 5.5E+5 5.2E+7 I -131 6.5E+8 4.3E+8 8.4E+5 5.9E+8 I -132 8.0E+3 8.7E+4 I -133 1.6E+1 8.6E+0 1.5E+5 1.7E+5 I -134 2.1E+3 3.2E+4 I -135 1.1E-15 6.3E-16 3.1E+4 1.8E+5 UN-ID 1.1E+8 9.4E+7 6.1E+4 1.7E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-16 Revision 0 02-27-07

TABLE 3-8 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR E Page 2 of 2 Pathway = Camp Horno Distance = 4.2 miles X/Q = 7.3E-8 sec/m3 D/Q = 6.9E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E+3 Cr-51 1.4E+4 4.7E+6 Mn-54 1.4E+6 1.4E+9 Co-57 3.1E+4 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 Sr-90 9.6E+6 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru-103 5.0E+5 1.1E+8 Te-129m 1.2E+6 2.0E+7 Cs-134 9.8E+4 6.8E+9 Cs-136 1.2E+4 1.5E+8 Cs-137 7.5E+4 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I -135 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-17 Revision 0 02-27-07

TABLE 3-9 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR F Page 1 of 2 Pathway = San Onofre State Park/Guard Shack Distance = 1.0 miles X/Q = 5.8E-7 sec/m3 D/Q = 4.8E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.2E+2 Cr-51 2.5E+3 8.0E+5 Mn-54 2.4E+5 2.4E+8 Co-57 5.4E+3 5.9E+7 Co-58 1.6E+5 6.5E+7 Co-60 1.0E+6 3.7E+9 Sr-89 2.4E+5 3.7E+3 Sr-90 1.6E+6 Zr-95 3.0E+5 4.3E+7 Nb-95 8.6E+4 2.3E+7 Ru-103 8.6E+4 1.9E+7 Te-129m 2.1E+5 3.4E+6 Cs-134 1.7E+4 1.2E+9 Cs-136 2.1E+3 2.6E+7 Cs-137 1.3E+4 1.8E+9 Ba-140 2.2E+5 3.5E+6 Ce-141 6.2E+4 2.3E+6 Ce-144 1.3E+6 1.2E+7 I -131 2.0E+6 2.9E+6 I -132 2.0E+4 2.1E+5 I -133 3.7E+5 4.2E+5 I -134 5.1E+3 7.7E+4 I -135 7.7E+4 4.3E+5 UN-ID 1.5E+5 1.3E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-18 Revision 0 02-27-07

TABLE 3-9 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR F Page 2 of 2 Pathway = Border Patrol Checkpoint Distance = 2.2 miles X/Q = 1.8E-7 sec/m3 D/Q = 1.3E-9 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 3.3E+2 Cr-51 3.7E+3 1.2E+6 Mn-54 3.6E+5 3.6E+8 Co-57 8.1E+3 8.8E+7 Co-58 2.4E+5 9.8E+7 Co-60 1.5E+6 5.5E+9 Sr-89 3.6E+5 5.6E+3 Sr-90 2.5E+6 Zr-95 4.6E+5 6.5E+7 Nb-95 1.3E+5 3.5E+7 Ru-103 1.3E+5 2.8E+7 Te-129m 3.2E+5 5.1E+6 Cs-134 2.5E+4 1.8E+9 Cs-136 3.1E+3 3.9E+7 Cs-137 1.9E+4 2.7E+9 Ba-140 3.3E+5 5.3E+6 Ce-141 9.3E+4 3.5E+6 Ce-144 2.0E+6 1.8E+7 I -131 3.1E+6 4.4E+6 I -132 2.9E+4 3.2E+5 I -133 5.5E+5 6.3E+5 I -134 7.7E+3 1.2E+5 I -135 1.2E+5 6.5E+5 UN-ID 2.2E+5 1.9E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-19 Revision 0 02-27-07

TABLE 3-10 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR G Page 1 of 2 Pathway = San Onofre State Park Beach Distance = 2.0 miles Campground X/Q = 2.0E-7 sec/m3 D/Q = 8.2E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 5.3E+1 9.2E+1 1.0E+2 1.0E+2 Cr-51 1.1E+3 3.8E+5 1.4E+3 3.8E+5 1.7E+3 3.8E+5 1.2E+3 3.8E+5 Mn-54 8.2E+4 1.1E+8 1.3E+5 1.1E+8 1.6E+5 1.1E+8 1.2E+5 1.1E+8 Co-57 4.0E+2 2.8E+7 1.1E+3 2.8E+7 2.6E+3 2.8E+7 2.6E+3 2.8E+7 Co-58 6.4E+4 3.1E+7 9.1E+4 3.1E+7 1.1E+5 3.1E+7 7.6E+4 3.1E+7 Co-60 3.7E+5 1.8E+9 5.8E+5 1.8E+9 7.2E+5 1.8E+9 4.9E+5 1.8E+9 Sr-89 1.7E+5 1.8E+3 1.8E+5 1.8E+3 2.0E+5 1.8E+3 1.2E+5 1.8E+3 Sr-90 9.2E+5 1.2E+6 1.4E+6 7.9E+5 Zr-95 1.4E+5 2.1E+7 1.8E+5 2.1E+7 2.2E+5 2.1E+7 1.5E+5 2.1E+7 Nb-95 3.9E+4 1.1E+7 5.0E+4 1.1E+7 6.2E+4 1.1E+7 4.1E+4 1.1E+7 Ru-103 4.5E+4 8.9E+6 5.4E+4 8.9E+6 6.4E+4 8.9E+6 4.1E+4 8.9E+6 Te-129m 1.4E+5 1.6E+6 1.4E+5 1.6E+6 1.6E+5 1.6E+6 1.0E+5 1.6E+6 Cs-134 6.5E+3 5.6E+8 9.9E+3 5.6E+8 1.2E+4 5.6E+8 8.0E+3 5.6E+8 Cs-136 9.7E+2 1.2E+7 1.2E+3 1.2E+7 1.5E+3 1.2E+7 9.9E+2 1.2E+7 Cs-137 5.9E+3 8.5E+8 8.5E+3 8.5E+8 9.9E+3 8.5E+8 6.2E+3 8.5E+8 Ba-140 1.3E+5 1.7E+6 1.4E+5 1.7E+6 1.7E+5 1.7E+6 1.0E+5 1.7E+6 Ce-141 4.2E+4 1.1E+6 4.5E+4 1.1E+6 5.0E+4 1.1E+6 3.0E+4 1.1E+6 Ce-144 8.1E+5 5.7E+6 9.8E+5 5.7E+6 1.1E+6 5.7E+6 6.4E+5 5.7E+6 I -131 1.2E+6 1.4E+6 1.3E+6 1.4E+6 1.2E+6 1.4E+6 9.8E+5 1.4E+6 I -132 1.4E+4 1.0E+5 1.6E+4 1.0E+5 1.2E+4 1.0E+5 9.4E+3 1.0E+5 I -133 2.9E+5 2.0E+5 3.2E+5 2.0E+5 2.4E+5 2.0E+5 1.8E+5 2.0E+5 I -134 3.7E+3 3.7E+4 4.2E+3 3.7E+4 3.2E+3 3.7E+4 2.5E+3 3.7E+4 I -135 5.7E+4 2.1E+5 6.5E+4 2.1E+5 5.1E+4 2.1E+5 3.7E+4 2.1E+5 UN-ID 5.3E+4 6.1E+7 8.2E+4 6.1E+7 1.0E+5 6.1E+7 7.1E+4 6.1E+7 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-20 Revision 0 02-27-07

TABLE 3-10 NORTH INDUSTRIAL AREA (UNIT 1) DOSE PARAMETER Ri FOR SECTOR G Page 2 of 2 Pathway = San Onofre State Beach Distance = 3.0 miles Campground Resident X/Q = 1.1E-7 sec/m3 D/Q = 4.0E-10 m-2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 9.2E+1 1.0E+2 2.4E+2 Cr-51 1.4E+3 3.8E+5 1.7E+3 3.8E+5 2.8E+3 8.9E+5 Mn-54 1.3E+5 1.1E+8 1.6E+5 1.1E+8 2.7E+5 2.7E+8 Co-57 1.1E+3 2.8E+7 2.6E+3 2.8E+7 6.0E+3 6.6E+7 Co-58 9.1E+4 3.1E+7 1.1E+5 3.1E+7 1.8E+5 7.3E+7 Co-60 5.8E+5 1.8E+9 7.2E+5 1.8E+9 1.1E+6 4.1E+9 Sr-89 1.8E+5 1.8E+3 2.0E+5 1.8E+3 2.7E+5 4.1E+3 Sr-90 1.2E+6 1.4E+6 1.8E+6 Zr-95 1.8E+5 2.1E+7 2.2E+5 2.1E+7 3.4E+5 4.8E+7 Nb-95 5.0E+4 1.1E+7 6.2E+4 1.1E+7 9.7E+4 2.6E+7 Ru-103 5.4E+4 8.9E+6 6.4E+4 8.9E+6 9.7E+4 2.1E+7 Te-129m 1.4E+5 1.6E+6 1.6E+5 1.6E+6 2.4E+5 3.8E+6 Cs-134 9.9E+3 5.6E+8 1.2E+4 5.6E+8 1.9E+4 1.3E+9 Cs-136 1.2E+3 1.2E+7 1.5E+3 1.2E+7 2.3E+3 2.9E+7 Cs-137 8.5E+3 8.5E+8 9.9E+3 8.5E+8 1.4E+4 2.0E+9 Ba-140 1.4E+5 1.7E+6 1.7E+5 1.7E+6 2.4E+5 3.9E+6 Ce-141 4.5E+4 1.1E+6 5.0E+4 1.1E+6 6.9E+4 2.6E+6 Ce-144 9.8E+5 5.7E+6 1.1E+6 5.7E+6 1.5E+6 1.3E+7 I -131 1.3E+6 1.4E+6 1.2E+6 1.4E+6 2.3E+6 3.3E+6 I -132 1.6E+4 1.0E+5 1.2E+4 1.0E+5 2.2E+4 2.4E+5 I -133 3.2E+5 2.0E+5 2.4E+5 2.0E+5 4.1E+5 4.7E+5 I -134 4.2E+3 3.7E+4 3.2E+3 3.7E+4 5.7E+3 8.6E+4 I -135 6.5E+4 2.1E+5 5.1E+4 2.1E+5 8.6E+4 4.8E+5 UN-ID 8.2E+4 6.1E+7 1.0E+5 6.1E+7 1.7E+5 1.4E+8 mrem/yr Inhalation Pathway, units = Ci/m3 (m2)(mrem/yr) Food & Ground Pathway, units = Ci/sec SO123-ODCM-A A3-21 Revision 0 02-27-07

OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION (SONGS) APPENDIX B SUPPLEMENTAL INFORMATION FOR EFFLUENT CONTROLS SO123-ODCM-B Revision 0 02-29-08

ODCM APPENDIX B TABLE OF CONTENTS Section Title Page 1.0 Gas and Liquid Effluent Concentration Limits for Radiation Monitor Setpoint Calculations . . . . . . . . . . . B1-1 thru 

       . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B1-5 1-1   K. Yhip to D. Dick, Memorandum for file Recommended Effluent Concentration Limits from 10CFR20 Appendix B,Table 2,for setpoint calculations, dated April 23, 1993    . . . . . . . . . B1-1 1-2   Table of the Gas and Liquid Concentrations Limits for Specific Isotopes . . . . . . . . . . . . . B1-2 2.0   SONGS Effluent Control Limits: 10 CFR 20 impact    . . . . . . B2-1 thru
       . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B2-2 2-1   E.S. Medling to J. Clark and P. Knapp, Memorandum for file Impact of new 10 CFR 20 upon SONGS Effluent Control Limits, dated June 14, 1993. . . . . . . . . . . . . . . . . . . . . B2-1 SO123-ODCM-B Bi                             Revision 0 02-29-08

SO123-ODCM-B B1-1 Revision 0 02-29-08

TABLE 1-1 UNITS 2 & 3 DOSE PARAMETER Ri FOR SECTOR P Page 1 of 4 GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECL) VALUES ISOTOPE GAS ECL GAS MPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) (ECL) (MPC) 1 H-3 1E-7 2E-7 H-3 1E-3 3E-3 2 Na-24 7E-9 5E-9 Na-24 5E-5 3E-5 3 Ar-41 1E-8 4E-8 Ar-41 2E-4 4 Sc-46 3E-10 8E-10 Sc-46 1E-5 4E-5 6E-8 d 5 Cr-51 8E-8 Cr-51 5E-4 2E-3 3E-8 w,a 6 Mn-54 1E-9 1E-9 Mn-54 3E-5 1E-4 2E-8 d 7 Mn-56 2E-8 Mn-56 7E-5 1E-4 3E-8 w 3E-9 d 8 Fe-55 3E-8 Fe-55 1E-4 8E-4 6E-9 w 5E-10 d 9 Fe-59 2E-9 Fe-59 1E-5 5E-5 7E-10 w 4E-9 w 10 Co-57 6E-9 Co-57 6E-5 4E-4 9E-10 a 2E-9 w 11 Co-58 2E-9 Co-58 2E-5 9E-5 1E-9 a 2E-10 w 12 Co-60 3E-10 Co-60 3E-6 3E-5 5E-11 a 4E-8 d 13 Cu-64 4E-8 Cu-64 2E-4 2E-4 3E-8 w, a 14 Zn-65 4E-10 2E-9 Zn-65 5E-6 1E-4 6E-9 d 15 Br-82 6E-9 Br-82 4E-5 4E-5 5E-9 w 8E-8 d 16 Br-84 3E-8 Br-84 4E-4 2E-4 9E-8 w 17 Kr-85 7E-7 3E-7 Kr-85 2E-4 18 Kr-85m 1E-7 1E-7 Kr-85m 2E-4 19 Kr-87 2E-8 2E-8 Kr-87 2E-4 20 Kr-88 9E-8 2E-8 Kr-88 2E-4 21 Rb-88 9E-8 2E-4 Rb-88 4E-4 2E-4 SO123-ODCM-B B1-2 Revision 0 02-29-08

GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECL) VALUES ISOTOPE GAS ECL GAS MPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) (ECL) (MPC) 22 Rb-89 2E-7 2E-4 Rb-89 9E-4 2E-4 1E-9 d 23 Sr-89 3E-10 Sr-89 8E-6 3E-6 2E-10 a 3E-11 d 24 Sr-90 3E-11 Sr-90 5E-7 3E-7 6E-12 a 8E-9 d 25 Sr-91 9E-9 Sr-91 2E-5 5E-5 5E-9 a 1E-8 d 26 Sr-92 1E-8 Sr-92 4E-5 6E-5 9E-9 a 27 Y-90 9E-10 3E-9 Y-90 7E-6 2E-5 3E-7 w 28 Y-91m 6E-7 Y-91m 2E-3 3E-3 2E-7 a 29 Y-92 1E-8 1E-8 Y-92 4E-5 6E-5 4E-10 d, a 30 Zr-95 1E-9 Zr-95 2E-5 6E-5 5E-10 w 3E-9 d 31 Zr-97 3E-9 Zr-97 9E-6 2E-5 2E-9 w, a 32 Nb-95 2E-9 3E-9 Nb-95 3E-5 1E-4 4E-9 w 33 Nb-95m 1E-10 Nb-95m 3E-5 3E-6 3E-9a 34 Nb-97 1E-7 2E-7 Nb-97 3E-4 9E-4 4E-9 d 35 Mo-99 7E-9 Mo-99 2E-5 4E-5 2E-9 a 2E-7 d 36 Tc-99m 5E-7 Tc-99m 1E-3 3E-3 3E-7 w 2E-9 d 37 Ru-103 1E-9 w 3E-9 Ru-103 3E-5 8E-5 9E-10 a 1E-10 d 38 Ru-106 8E-11 w 2E-10 Ru-106 3E-6 1E-5 2E-11 a 2E-10 d 39 Ag-110m 3E-10 w 3E-10 Ag-110m 6E-6 3E-5 1E-10 a Sn-113 2E-9 d Sn-113 40 2E-9 3E-5 9E-5 8E-10 w SO123-ODCM-B B1-3 Revision 0 02-29-08

GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECL) VALUES ISOTOPE GAS ECL GAS MPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) (ECL) (MPC) 3E-9 d 41 Sn-117m 1E-10 Sn-117m 3E-5 3E-6 2E-9 w 3E-9 d 42 Sb-122 5E-9 Sb-122 1E-5 3E-5 2E-9 w 1E-9 d 43 Sb-124 7E-10 Sb-124 7E-6 2E-5 3E-10 w 3E-9 d 44 Sb-125 9E-10 Sb-125 3E-5 1E-4 7E-10 w 45 Xe-131m 2E-6 4E-7 Xe-131m 2E-4 46 Xe-133 5E-7 3E-7 Xe-133 2E-4 47 Xe-133m 6E-7 3E-7 Xe-133m 2E-4 48 Xe-135 7E-8 1E-7 Xe-135 2E-4 49 Xe-135m 4E-8 3E-8 Xe-135m 2E-4 50 Xe-138 2E-8 3E-8 Xe-138 2E-4 9E-10 d 51 Te-129m 1E-9 Te-129m 7E-6 2E-5 3E-10 w 1E-9 d 52 Te-132 4E-9 Te-132 9E-6 2E-5 9E-10 w 53 I-131 2E-10 1E-10 I-131 1E-6 3E-7 54 I-132 2E-8 3E-9 I-132 1E-4 8E-6 55 I-133 1E-9 4E-10 I-133 7E-6 1E-6 56 I-134 6E-8 6E-9 I-134 4E-4 2E-5 57 I-135 6E-9 1E-9 I-135 3E-5 4E-6 58 Cs-134 2E-10 4E-10 Cs-134 9E-7 9E-6 59 Cs-136 9E-10 6E-9 Cs-136 6E-6 6E-5 60 Cs-137 2E-10 5E-10 Cs-137 1E-6 2E-5 61 Cs-138 8E-8 3E-8 Cs-138 4E-4 2E-4 62 Ba-139 4E-8 3E-8 Ba-139 2E-4 2E-4 63 Ba-140 2E-9 1E-9 Ba-140 8E-6 2E-5 64 La-140 2E-9 4E-9 La-140 9E-6 2E-5 1E-9 w 65 Ce-141 5E-9 Ce-141 3E-5 9E-5 8E-10 a SO123-ODCM-B B1-4 Revision 0 02-29-08

GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECL) VALUES ISOTOPE GAS ECL GAS MPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) (ECL) (MPC) 3E-9 w 66 Ce-143 7E-9 Ce-143 2E-5 4E-5 2E-9 a 4E-11 w 67 Ce-144 2E-10 Ce-144 3E-6 1E-5 2E-11 a 68 Nd-147 1E-9 8E-9 Nd-147 2E-5 6E-5 69 W-187 1E-8 1E-8 W-187 3E-5 6E-5 70 Np-239 3E-9 2E-8 Np-239 2E-5 1E-4 71 ALPHA 1E-15 2E-14 ALPHA 2E-9 3E-8 SO123-ODCM-B B1-5 Revision 0 02-29-08

SO123-ODCM-B B2-1 Revision 0 02-29-08

SO123-ODCM-B B2-2 Revision 0 02-29-08}}

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