ML011230506

Annual Radioactive Effluent Release Report - 2000

ML011230506
Person / Time
Site:	San Onofre
Issue date:	12/31/2000
From:	Southern California Edison Co
To:	NRC/FSME
References
+kBR1SISP20060424, -RFPFR
Download: ML011230506 (105)

Text

SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2000 January - December

I* EDISON SOUTHERN CALIFORNIA An 1EDISON' IN,7RN TIONV U,"' Co(pJnjIN PREFACE State Beach, San Onofre Nuclear Generating Station is located next to San Onofre County, 64 miles south of adjoining Camp Pendleton Marine Corps Base, in San Diego reactors with a Los Angeles, California. There are two operating pressurized water total rated capacity of 2254 net megawatts electrical.

Electric Unit 1, rated at 410 net megawatts electrical, was supplied by Westinghouse unit was permanently Company and began commercial operation on January 1, 1968. The (80%) and shutdown on November 30, 1992. It is owned by Southern California Edison San Diego Gas and Electric (20%).

with turbine Unit 2 and Unit 3 were supplied by Combustion Engineering, Inc.,

The units began generators supplied by G.E.C. Turbine Generators, Ltd., of England.

and are rated commercial operation on August 18, 1983, and April 1, 1984, respectively at 1127 net megawatts electrical each. The twin units are owned by Southern California Edison (75.05%), San Diego Gas and Electric (20%), City of Anaheim (3.16%),

and the City of Riverside (1.79%).

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

Cl) z

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

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

............... 8 SECTION C - LIQUID EFFLUENTS DENDUM S. . . .. . 16 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT AD

. . .. . 17 SECTION E - RADWASTE SHIPMENTS ..............

SECTION F - APPLICABLE LIMITS ..... ................ . . . . . . .. . 20

. . . . . . .. . 22 SECTION G - ESTIMATION OF ERROR ..... ...............

. . . . . . .. . 23 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS ..........

. . . . . . .. . 27 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL . .

. . . . . . .. . 30 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS

. . . . . . .. . 34 SECTION K - MISCELLANEOUS ...... ..................

SECTION L - S.O.N.G.S. 1 CONCLUSIONS ........... 36

-ii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release

2. Percent of Applicable Limits

3. Estimated Total Percent Error

4. Lower Limit of Detection Concentrations

5. Batch Release Summaries

6. Previous Radioactive Effluent Release Report Addendum

7. Radwaste Shipments

8. 10 CFR 50 Appendix I Requirements

9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

Listed for each of the four categories are:

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

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

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

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

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

Plant stack releases are considered to be "continuous" releases. As of 8/4/93, "batch" mode releases are no longer conducted because of the permanent shutdown of the reactor.

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

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

Table IF, "Gaseous Effluents-Batch Release Summary," has been deleted. "Batch" mode releases are no longer conducted as of 8/4/93, due to the permanent shutdown of the reactor.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Total release Ci <LLD <LLD 3.OOE+1

2. Average release rate for period uCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit  % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit  % ECL O.OOE+O O.OOE+O B. lodines

1. Total iodine-131 Ci <LLD <LLD 1.90E+1

2. Average release rate for period MCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit  % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit  % ECL O.OOE+O O.OOE+O C. Particulates

1. Particulates with half-lives >8 days Ci <LLD <LLD 1.60E+1

2. Average release rate for period MCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit  % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit  % ECL O.OOE+O 0.OOE+O

5. Gross alpha activity Ci <LLD 7.09E-8 5.OOE+1 D. Tritium

1. Total release Ci 3.42E-1 <LLD 2.50E+1

2. Average release rate for period MCi/sec 4.35E-2 O.OOE+O

3. Percent of applicable limit  % MPC 2.83E-4 O.OOE+O

4. Percent Effluent Concentration Limit  % ECL 5.65E-4 O.OOE+0O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

A. Fission and activation gases

1. Total release Ci <LLD <LLD 3.OOE+1

2. Average release rate for period /MCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit  % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit  % ECL O.OOE+O O.OOE+O B. lodines

1. Total iodine-131 Ci <LLD <LLD 1.90E+1

2. Average release rate for period gCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit  % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit  % ECL O.OOE+O O.OOE+O C. Particulates (1)

1. Particulates with half-lives >8 days Ci <LLD <LLD 1.60E+1

2. Average release rate for period MCi/sec O.OOE+O O.OOE+O

3. Percent of applicable limit  % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit  % ECL O.OOE+O O.OOE+O

5. Gross alpha activity Ci 1.80E-7 7.62E-8 5.OOE+1 D. Tritium

1. Total release Ci 4.11E-1 9.43E-1 2.50E+1

2. Average release rate for period MCi/sec 5.17E-2 1.19E-1

3. Percent of applicable limit  % MPC 3.36E-4 7.71E-4

4. Percent Effluent Concentration Limit  % ECL 6.72E-4 1.54E-3 __

(1) On 7/31/00, for approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Plant Vent Stack Particulate and Iodine sample was not collected.

There was no measurable activity in the previous or subsequent samples. An investigation was conducted and documented in Action Request 000701588.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Fission and activation gases krypton-85 Ci <LLD <LLD <LLD <LLD krypton-85m Ci <LLD <LLD <LLD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci <LLD <LLD <LLD <LLD xenon-133m Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD

2. Iodines iodine-131 Ci <LLD <LLD <LLD <LLD iodine-133 Ci <LLD <LLD <LLD <LLD iodine-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD

3. Particulates barium-140 Ci <LLD <LLD <LLD <LLD ceriurn-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD

• strontium-90 Ci <LLD <LLD <LLD

• zinc-65 Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table ID.

• Fourth quarter analyses not available at report time; values will be included in the following Annual Report.

NOTE: Due to the permanent shutdown of S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Fission and activation gases krypton-85 2.50E-5 krypton-85m 6.OOE-8 krypton-87 3.10E-7 krypton-88 2.10E-7 xenon-133 1.90E-7 xenon-133m 4.80E-7 xenon-135 6.30E-8 xenon-135m 2.40E-6 xenon-138 4.10E-6

2. Iodines iodine-131 2.90E-13 iodine-133 2.80E-12 iodine-135 1.90E-10

3. Parti cul ates barium-140 5.90E-13 cerium-141 6.60E-14 cerium-144 2.60E-13 cesium-134 1.70E-13 cesium-137 1.40E-13 cobalt-58 1.50E-13 cobalt-60 2.40E-13 iron-59 3.80E-13 lanthanum-140 1.20E-12 manganese-54 1.50E-13 molybdenum-99 7.90E-14 strontium-89 1.OOE-14 strontium-90 1.OOE-15 zinc-65 4.OOE-13

4. gross alpha 1.OOE-14

5. tritium 8.83E-8 NOTE: Due to the permanent shutdown of S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Gamma Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O

2. Percent Applicable Limit O.OOE+O O.OOE+O O.OOE+O O.OOE+O

3. Beta Air Dose mrad O.OOE+O O.OOE+O O.OOE+O O.OOE+O

4. Percent Applicable Limit  % O.OOE+O O.OOE+O O.OOE+O O.OOE+O B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem 1.28E-5 O.OOE+O 1.54E-5 3.53E-5

2. Percent Applicable Limit  % 1.70E-4 O.OOE+O 2.05E-4 4.71E-4 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.

TABLE 1F GASEOUS EFFLUENTS-BATCH RELEASE

SUMMARY

NOTE: Due to the permanent shutdown of S.O.N.G.S. 1, "BATCH MODE" releases are no longer conducted.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents-Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are:

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

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

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

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

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

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

Table 2E, "Liquid Effluents-Batch Release Summary," provides summary information regarding batch releases conducted during this report period from San Onofre Nuclear Generating Station Unit 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Total release (not including tritium, gases, alpha) Ci 1.25E-4 5.21E-6 1.90E+1

2. Average diluted concentration during period uCi/ml 7.81E-11 3.12E-12

3. Percent of applicable limit  % MPC 3.91E-4 1.56E-5

4. Percent Effluent Concentration Limit  % ECL 7.81E-3 3.12E-4 B. Tritium

1. Total release Ci 6.10E-3 1.85E-3 1.90E+1

2. Average diluted concentration during period u.Ci/ml 3.81E-9 1.11E-9

3. Percent of applicable limit  % MPC 1.27E-4 3.69E-5

4. Percent Effluent Concentration Limit  % ECL 3.81E-4 1.11E-4 C. Dissolved and entrained gases (1I

1. Total release Ci <LLD <LLD 1.90E+1

2. Average diluted concentration during period utCi/ml O.OOE+O O.OOE+O

3. Percent of applicable limit  % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit  % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 7.53E+6 1.11E+6 5.OOE+O F. Volume of dilution water used during period liters 1.60E+9 1.67E+9 5.OOE+O (1) The Unit 1 monthly April Dissolved & Entrained (D&E) gas analyses for the Yard Drain Sump and Reheater Pit Sump were not performed. These sumps are open to the atmosphere and have historically shown no measurable D&E activity. This event is documented in AR 000500230.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 4.61E-4 9.59E-6 1.90E+1

2. Average diluted concentration during period uCi/ml 2.70E-10 5.85E-12

3. Percent of applicable limit  % MPC 1.62E-3 2.92E-5

4. Percent Effluent Concentration Limit  % ECL 1.78E-2 5.85E-4 B. Tritium

1. Total release Ci 3.16E+O 2.30E-4 1.90E+1

2. Average diluted concentration during period MCi//ml 1.85E-6 1.40E-1O

3. Percent of applicable limit  % MPC 6.16E-2 4.67E-6

4. Percent Effluent Concentration Limit  % ECL 1.85E-1 1.40E-5 C. Dissolved and entrained gases

1. Total release Ci <LLD <LLD 1.90E+1

2. Average diluted concentration during period yCi/ml O.OOE+O O.OOE+O

3. Percent of applicable limit  % MPC O.OOE+O O.OOE+O

4. Percent Effluent Concentration Limit  % ECL O.OOE+O O.OOE+O D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 3.08E+5 9.50E+5 5.OOE+O F. Volume of dilution water used during period liters 1.71E+9 1.64E+9 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 1.25E-4 5.21E-6 6.72E-6 9.59E-6 chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD

• 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

• strontium-90 Ci <LLD <LLD <LLD

• technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci 1.25E-4 5.21E-6 6.72E-6 9.59E-6

2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 2C.

Fourth quarter analyses not available at report time; values will be included in the following Annual Report.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

1. Fission and activation products antimony-125 Ci <LLD <LLD 3.83E-5 <LLD 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 2.45E-5 <LLD cesium-137 Ci <LLD <LLD 2.01E-4 <LLD chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD 1.88E-4 <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 2.39E-6 <LLD technetiuum-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zi rconi um-95 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD 4.55E-4 <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 (2000)

S.O.N.G.S. 1 TABLE 2C LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides LLD (gCi/cc)

1. Fission and activation products barium-140 3.30E-7 cerium-141 5.20E-8 cerium-144 2.30E-7 cesium-134 9.90E-8 chromium-51 4.20E-7 cobalt-58 8.70E-8 cobalt-60 1.30E-7 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 lanthanum-140 2.40E-7 manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 strontium-89 5.00E-8 strontium-90 I.OOE-8 technetium-99m 3.50E-8 zinc-65 2.20E-7 zirconium-95 1.50E-7

2. Dissolved and entrained gases xenon-133 3.1OE-7 xenon-135 1.20E-7

3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

LIQUID EFFLUENTS-LOWER LIMIT OF DETECTION BATCH MODE Radionuclides JLLD (ýCi/cc)

1. Fission and activation products antimony-125 1.70E-7 barium-140 3.30E-7 cerium-141 5.20E-8 cerium-144 2.30E-7 cesium-134 9.90E-8 cesium-137 8.60E-8 chromium-51 4.20E-7 cobalt-58 8.70E-8 cobalt-60 1.30E-7 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 lanthanum-140 2.40E-7 manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 strontium-89 5.OOE-8 strontium-90 1.OOE-8 technetium-99m 3.50E-8 zinc-65 2.20E-7 zirconium-95 1.50E-7

2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7

3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 TABLE 2D LIQUID EFFLUENTS-RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit I Quarter Quarter Quarter Quarter A.

1. Total body dose mrem 1.35E-3 5.49E-5 2.70E-3 1.02E-4

2. Percent Applicable Limit  % 9.01E-2 3.66E-3 1.80E-1I 6.82E-3 B.

1. Limiting organ dose mrem 2.06E-3 8.35E-5 5.24E-3 1.56E-4

2. Percent Applicable Limit 4.13E-2 1.67E-3 1.05E-1 3.13E-3

3. Limiting organ for period Liver Liver GI-LLI Liver ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 TABLE 2E LIQUID EFFLUENTS-BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: 1 release

2. Total time period for batch releases: 3015 minutes

3. Maximum time period for a batch release: 3015 minutes

4. Average time period for a batch release: 3015 minutes

5. Minimum time period for a batch release: 3015 minutes

6. Average saltwater flow during batch releases: 6000 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. I SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

Estimated 12 month total

1. Type of waste Unit period error (%)

a. Spent resins, filter sludges, m3 N/A evaporator bottoms Ci N/A N/A

b. Dry active waste (DAW), compactable m3 5.80E+2 and non-compactable

• Ci 5.09E+O 3.OOE+1

c. Irradiated components, control rods 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 strong, tight containers of various sizes. One shipment was packaged in a DOT Type A over pack box.

N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1

2. Estimate of major nuclide composition (by type of waste)

a. not applicable  % N/A

b. americium-241 0 1.64E-2 carbon- 14  % 6.03E-1 ceri um-144  % 2.57E-3 cesium-134  % 5.63E+O cesium-137  % 4.21E+1 cobalt-60  % 3.22E+1 curium-242 7.OOE-5 curium-243/244 __3.90E-3 iron-55 1.21E+1 manganese-54_ 1.96E-4 nickel-59 4.24E-2 nickel-63 5.31E+O niobium-94 __1.70E-2 niobium-95 __1.87E-1 plutonium-242 __1.14E-5 plutonium-238 __2.57E-2 plutonium-239/240 _0 9.61E-3 plutonium-241 ?_ _ 6.91E-1 ruthenium-106  % 1.OOE-3 silver-llOm __3.50E-4 strontium-90 __2.05E-1 technetium-99 Y_ _ 1.48E-3 tritium %_ 3.73E-1 uranium-233  % 2.97E-6 uranium-238  % 2.69E-6 zirconium-95  % 2.34E-1

c. not applicable  % N/A

d. not applicable  % I N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. I

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 5* Kindrick Trucking Company Truck/Trailer Envirocare, UT 1 HitmanTruck/Trailer Trucking Company Barnwell, SC 2 Kindrick Trucking Company Envirocare, UT Truck/Trailer 27 MHFLogistical Solutions Envirocare, UT Rail SONGS maintains contracts with vendors (ATG/GTS) that provide volume reduction services.

These shipments were made from their processing facility. The five shipments made from these facilities included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

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

X/Q 1.30E-5 sec/m 3; the annual average atmospheric dispersion defined in the Unit 10DCM, Rev. 13.

1 0 MPCetf 1=1 MPC i where: Fj fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, C*,

by the sum of all the isotopic activity, CT.

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

. PECL (Rel Rate) (X/O) (100)

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

X/Q 1.30E-5 sec/m3 ; the annual average atmospheric dispersion defined in the Unit 1 ODCM, Rev. 13.

n 1i 0 ECLef, 1=1 ECL i where: F, fractional abundance of the it'radionuclide obtained by dividing the activity (curies) for each radionuclide, C1 ,

by the sum of all the isotopic activity, CT.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 Liquid Effluents - Applicable Limits The percent of Applicable Limits, tabulated in Sections A.3, B.3, and C.3 of Table 2A, were calculated using the following equations:

• % Applicable Limit (Dil Conc) (100)

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

1 o MPCeff M=1 MPC i where: Fj fractional abundance of the it' radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, C,.

n total number of radionuclides identified MPC, Maximum Permissible Concentration (MPC) of the i th 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, AiCi/ml.

1 0 ECLff i= ECL1 where: Fj fractional abundance of the i t ' radionuclide obtained by dividing the activity (curies) for each radionuclide, C,,

by the sum of all the isotopic activity, CT.

n total number of radionuclides identified ECL1 Effluent Concentration Limit (ECL) of the i t' radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix B, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made.

Sources of error for gaseous effluents - batch releases are:

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

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

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

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

2 2 2 2 Total Error = oI + a2 + a3 + ... ai where: o, = Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

Six different categories are presented:

(1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, lodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; this data is also presented in Table 2D. Categories 3, 4, and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) software, Regulatory Guide 1.109 methodology, and concurrent meteorology. Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

For 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 negligible and hence the dose "0".

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. I TABLE 1 Dose * (millirems)

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

Whole Body 1.35E-3 5.49E-5 2.70E-3 1.02E-4 4.21E-3

6) 7) 8) 9) 10)

Organ 2.06E-3 8.35E-5 5.24E-3 1.56E-4 5.37E-3 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15)

Tritium, lodines, and Particulates 1.65E-4 O.OOE+O 3.47E-4 6.65E-4 1.18E-3 NOBLE GASES ** 16) 17) 18) 19) 20)

Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O

21) 22) 23) 24) 25)

Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O

26) 27) 28) 29) 30)

DIRECT RADIATION 7.32E-2 1.12E-1 1.25E-1 9.86E-2 3.43E-1

• The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).

units of mrad, reflecting the air dose.

• • Noble gas doses due to airborne effluent are in of the ODCM.

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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1

6. This value was calculated using the methodology of the ODCM.

7. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.

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

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

10. This value was calculated using the methodology of the ODCM; the liver received the maximum dose primarily by the saltwater fish pathway.

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

12. There was no activity detected during the release period, therefore the reported organ dose was O.OOE+O mrem.

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

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

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

16. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

17. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

18. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

19. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

20. There was no activity detected during the release period, therefore the reported air dose for gamma radiation was O.OOE+O mrad.

21. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

22. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

23. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

24. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1

25. There was no activity detected during the release period, therefore the reported air dose for beta radiation was O.OOE+O mrad.

26. Measurements were made using TLD dosimeters; values are presented as site wide thedose and are Boundary in W sector.

prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site dose and are

27. Measurements were made using TLD dosimeters; values are presented as site wide the W sector.

prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in dose and are

28. Measurements were made using TLD dosimeters; values are presented as site wide the W sector.

prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in dose and are

29. Measurements were made using TLD dosimeters; values are presented as site wide the W sector.

prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in dose and are

30. Measurements were made using TLD dosimeters; values are presented as site wide the W sector.

prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 9.01E-2 3.66E-3 1.80E-1 6.82E-3 1.40E-1 Organ 4.13E-2 1.67E-3 1.05E-1 3.13E-3 5.37E-2 AIRBORNE EFFLUENTS Tritium, lodines, and Particulates 2.20E-3 O.OOE+O 4.62E-3 8.87E-3 7.87E-3 NOBLE GASES Gamma O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O Beta O.OOE+O O.OOE+O O.OOE+O O.OOE+O O.OOE+O NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 SECTION I. CHANGES TO OFFSITE DOSE CALCULATION MANUAL On February 29, 2000, revision 16 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published. This revision incorporated land use census results only.

Minor format changes, correction of typographical errors, and removal of previously blank pages were also made and are described in the attached List of Affected Pages.

Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.36a, and Appendix I to IOCFR50 will be maintained. Throughout the document, change bars are marked in one of four ways as follows:

A Addition D Deletion F Editorial/Format change R Revision The following is a complete list of the changes:

OLD NEW CHANGE REASON TOC Renumbered pages as necessary based on changes in the body of the ODCM. F 2-21 Corrected a typo in the Cs-137 value of Table 2-5 F 2-24 Added an Ri for San Mateo Pt. Homes A Removed previously deleted pages: F 2-25, 2-27, 2-28, 2-30, 2-31, 2-32, 2-33, 2-35, 2-36, 2-37, 2-39, 2-41, 2 44, 2-45, 2-47, 2-50, 2-51, 2-53, 2-55.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 On July 20, 2000, revision 17 to the Unit 1 Offsite Dose Calculation Manual (ODCM) was adopted and published. Incorporated into this revision were:

1. Revised Liquid Setpoint equation to adjust for low (<100 KeV) energy gamma

emitters,

2. Added the Plant Information Monitoring System to Section 4,

3. Deleted the Investigative Report definition,

4. Revised the Source Check definition, and

5. Removed reference to the Monitor Tanks.

Safety evaluations were provided for each of the above changes with the exception of items 3 and 5. The requirement for an Investigative Report was added to the ODCM at the time that the RETS were transferred from the Technical Specifications. There existed a need to document each occurrence of failure to meet Surveillance Requirements and/or Action Statements related to the ODCM. The ODCM will now require performance of an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

The Unit 1 Monitor Tanks were removed and the associated piping was capped as part of the Unit I Decommissioning Project under PCA-175-RWL-3. The tanks were previously abandoned under SAFSTOR. The Unit 1 ODCM Table 1-1 and Figure 4-1 are being updated to reflect this new plant configuration.

Minor format changes, correction of typographical errors, and removal of previously blank pages have been made and are described in the attached List of Affected Pages.

Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR5O.36a, and Appendix I to 10CFR5O will be maintained.

Throughout the document, change bars are marked in one of four ways as fol I ows:

A Addition D Deletion F Editorial/Format change R Revi sion The following is a complete list of the changes:

OLD INEW CHANGE REASON Throughout Changed ZiCyi to ZiC',, R Section 1 Removed reference to the Monitor Tanks D 1-3 1-12 Added Factor Cxe to equation 1-3 A Changed definition of Z1 Cyi R 1-13 Divided STEP 3 into two steps (3 & 4) and reworded R A

Added equation 1-6 for CPMm, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. I 1-14 Changed definition of ZiCyi R Corrected misspelled word F 1-15 Added Factor C,,, to equation 1-3 A Changed definition of T1 CY1 R Reordered the equation factor definitions to match the order in the F equation 1-16 Divided STEP 3 into two steps (3 & 4) and reworded R Added equation 1-6 for CPMmax A 1-17 Changed definition of ZjCy* R 1-18 Changed definition of 1jCyi R 1-23 Changed procedure reference and title R Single spaced F 4-1 Changed 4.1.1.B.3 from Investigative Report to Corrective Action Program R 4-2 Added 'Effluent Line' to item 1.d. F Added PIMS to Table 4-1 A Changed '*' to '1' F Added note 2 A 4-3 Added ACTION 25 A 4-5 Added PIMS to Table 4-2 A Added 'a.' to first item in section 2 F 4-6 Added Table Notation (5), (6), and (7) A 4-7 Changed 4.2.1.B.3 from Investigative Report to Corrective Action Program R 4-8 Added PIMS to Table 4-3 A Added note 6 A 4-9 Added ACTION 26 A 4-11 Added PIMS to Table 4-4 A Added Table Notation (4), (5), and (6) A 4-13 Updated drawing per U1 Operations R 6-1 Removed previously deleted line 6.1.5 F 6-2 Deleted INVESTIGATIVE REPORT definition R Renumbered equations F 6-3 Revised SOURCE CHECK definition, R Removed previously deleted lines 6.1.10, 6.1.11, 6.1.13, 6.1.14, and 6.1.18 F Renumbered equations F 6-4 Removed previously deleted lines 6.1.21, 6.1.22 F

_Renumbered equations F ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Permanent Removal of the Liquid Radwaste System Monitor Tanks The Unit 1 Monitor Tanks, S1-RWL-D-21A&B were abandoned under SAFSTOR and all appropriate procedures changed in March 2000. Later that same year the tanks were physically demolished and removed from site. Unit 1 was permanently shutdown in 1992 with the last monitor tank" release occurring in April 1993.

During the period in which the monitor tanks were left unused, residual contamination in the tanks continued to act as a measurable radiation source despite being filled with clean water for shielding purposes. As part of the review of the relocation of the HP control point and control room to the new location in support of decommissioning, it was identified that personnel working in the new 3rd Point Entry and Operations offices would incur unnecessary exposure from these tanks due to the elevated background. The background also interfered with the new radiation monitoring instrumentation. Since the tanks would eventually need to be removed as part of decommissioning of Unit 1, it was decided to proceed with their removal relatively early in the schedule and in keeping with the ALARA principle, reduce worker dose.

The monitor tanks provided a method for segregating low activity waste that contained relatively high concentrations of chemical contaminants, thereby minimizing the potential for premature exhaustion of the ion exchange beds. Each monitor tank had a capacity of 3750 gallons compared to a HUT (3 total) that has a capacity of 55,000 gallons each. Once the plant ceased commercial operation and entered SAFSTOR, there was a concurrent reduction in the volume of liquid radwaste being generated and in the overall system capacity needed to collect and process waste. In addition, the refueling water storage tank (capacity 240,000 gallons) is currently being used as a storage tank for water from the refueling cavity. Estimates of the waste generated by decommissioning activities should not exceed the storage capacity of the HUTs and the rate at which the waste can be processed and released while meeting existing administrative dose limits.

The reduction in liquid radwaste generation experienced to date during Unit 1 decommissioning has eliminated the need for operating alignments that utilize the Monitor Tanks. The Monitor Tanks are no longer needed because the three Holdup Tanks (RLC-C-20A, B and C) are sufficient to receive and store all of the waste that is generated. Removal of the monitor tanks will not increase the amount of activity released in liquid effluents or the resultant dose to a member of the public.

Since the monitor tanks were listed in the Unit 1 ODCM (Table 1-1), they were deleted as a credited release point in Revision 17, issued July 20, 2000, subsequent to their physical removal from site. The removal of the monitor tanks will not affect the processing capacity of the radwaste treatment system and will not result in any increase in the amount of activity released in liquid radwaste during decommissioning.

Releases from Unit 1 will continue to be performed in accordance with existing Station procedures and administrative limits and will not exceed the limits of IOCFR20 or IOCFR50 appendix I.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 The following Safety Evaluation was generated for placing the monitor tanks into SAFSTOR, in support of procedure S01-4-51 change package. (March 2000)

1. May the proposed activity increase the probability of occurrence of an accident evaluated previously in the safety analysis report?

No.

Only two accidents previously analyzed for the operating license are relevant to the defueled mode: (1) Loss of Offsite Power, and (2) Fuel Handling Accident. The removal of the Monitor Tanks from service impacts only liquid radwaste processing methods, which do not affect any equipment or activities which might initiate one of these accidents.

Most of the liquid radwaste system, including these tanks, is Not Required for Operation (NRO). The components which control the release to the ocean, the radiation monitor, automatic shutoff valve and associated controls, are Required for Operation (RO). The changes to the operating instructions affect only the operation of the NRO portions of the radwaste system. There is no impact on the RO function -- the ability to control the system discharges so that only acceptable amounts and concentrations of radioactive effluent are released to the environment. The procedure changes do not increase the probability of an unacceptable release of liquid radwaste.

The changes to the liquid radwaste operations do not affect fire protection systems; consequently, there is no increase in the probability of initiating a fire.

2. May the proposed activity increase the consequences of an accident evaluated previously in the safety analysis report?

No.

The procedure changes affect only operation of the liquid radwaste system; thus, there is no impact on the consequences of a (1) Loss of Offsite Power or a (2) Fuel Handling Accident.

The tanks will be drained. The lines connected to the tanks will be isolated by closing or de-energizing interfacing valves. The integrity of the radwaste piping systems will be maintained; consequently, the consequences of natural phenomenon, such as a tornado or earthquake, will not be increased by the procedure changes.

The changes will not adversely affect the ability to fight a fire in the area.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1

3. May the proposed activity increase the probability of occurrence of a malfunction of equipment important to safety evaluated previously in the safety analysis report?

No.

The procedure changes affect only operation of NRO radwaste equipment; consequently, there is no interaction with RO equipment and no increase the probability of its malfunction.

4. May the proposed activity increase the consequences of a malfunction of equipment important to safety evaluated previously in the safety analysis report?

No.

The procedure changes affect only operation of NRO radwaste equipment. This equipment does not have the potential for mitigating the consequences of a malfunction of any type of RO equipment: thus, the changes will not increase these consequences.

5. May the proposed activity create a possibility of an accident of a different type than evaluated previously in the safety analysis report?

No.

As discussed in Question 1, the procedure changes will not affect the RO function of the liquid radwaste system which controls the release of radioactive effluent to the environment. There is no impact on RO systems or equipment.

Due to the decreased demand on the radwaste systems during SAFSTOR, the reduced radwaste processing capacity without the two tanks will be adequate. The integrity of the piping systems will be maintained by complete isolation of the tanks. For these reasons, the procedure changes will not create the possibility of a different type of accident, such as a spill or rupture.

6. May the proposed activity create a possibility of a malfunction of equipment important to safety of a different type than evaluated previously in the safety analysis report?

No.

The procedure changes remove the NRO tanks from service. The changes do not affect the RO function of the radwaste system, controlled release of effluent, or any RO equipment. Removing the tanks from service will not challenge the radwaste system because the amount of radwaste generated by the defueled plant is much less than that due to normal operation. Consequently, the changes do not create the possibility of a malfunction of any equipment that is important to safety.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1

7. Does the proposed activity reduce the margin of safety as defined in the basis for any technical specification?

No.

The procedure changes will isolate and abandon the radwaste tanks that are no longer needed to process the amount of liquid radwaste generated with the plant permanently defueled. The radwaste system is not mentioned in the Permanently Defueled Technical Specification (PDTS); consequently, there is no reduction in the margin of safety defined by the PDTS.

The liquid radwaste management operations described in the Defueled Safety Analysis Report (DSAR ) do not include use of the Monitor Tanks, consequently, there is no reduction in the margin of safety defined by the DSAR.

Since the tanks had been drained, valved out of the system and abandoned under SAFSTOR, station procedures allowed the removal to be evaluated using only a one question safety evaluation so long as certain conditions are met. Safety Evaluation per PCA-175-RWL-3/NSR#309:

UNIT 1 IOCFR50.59 SAFETY EVALUATION SCREENING

1. Could this decommissioning activity impact the design, function or method of performing the function of an RO SSC as described in the DSAR, through direct, indirect or secondary effects?

NO. Monitor Tanks S1-RWL-D-21A&B create a radiation background level to the monitoring equipment in the new 3rd Point Entry (bldg. A-51). This modification will remove the tanks and cut & cap the associated lines. Per DSAR, these tanks have been drained and abandoned under SAFSTOR. Per the Q-List, the monitor tanks and its associated lines are NSR/NRO, and do not impact the safety function of any RO component. This change does not impact the liquid radwaste discharge flow path through CV-11l, a fail closed NSRAQ/RO valve which closes automatically if high radioactivity is sensed in the effluent being discharged to the ocean. The lines being capped are upstream of this valve.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 SECTION K. MISCELLANEOUS Yard Drain SumD Overflow The Unit 1 Yard Drain sump overflowed to the PMF Catch Basin due to heavy rainfall twice in 2000. Since there was no detectable activity in the grab samples taken during the overflows, there were no dose consequences as a result of these unplanned, unmonitored releases.

Estimated Estimated Start Stop Duration Activity Release Whole Body Estimated Organ Date/Time Date/Time (minutes) (uCi/ml) (Curies) Dose (mrem) Dose (mrem) 2/22/00 @ 1440 2/22/00 @ 1600 80 <LLD O.OOE+O O.OOE+O O.OOE+O 2/23/00 @ 1524 2/23/00 @ 1555 31 <LLD O.OOE+O O.OOE+O O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. I EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2000 - December 31, 2000 S.O.N.G.S. 1 Monitor Inoperability Period Inoperability Cause Explanation R-1218 06/18/00 - 09/17/00 Erratic behavior Extensive electrical problems Liquid Radwaste required complete circuit board Discharge Line rework using obsolete parts.

Monitor Waiting for design upgrade.

09/17/00 - present Radmonitor upgrade Design change upgrade modification design change installed a new instrument and connected to Plant Information Monitoring System (PIMS) in conjunction with relocation of the Control Room.

R-1254 06/26/00 - 08/15/00 Decommissioning Electrical bus work to support Plant Vent Stack work of electrical decommissioning deenergized heat Particulate and distribution trace making P/I non-functional.

Iodine Sampler realignment;heat trace inoperable Plant Vent Stack 07/05/00 - 08/15/00 Radmonitor upgrade Design change upgrade modification Monitor design change installed new instrument communications and connected to PIMS in conjunction with relocation of the Control Room.

R-2100 08/02/00 - 11/16/00 Radmonitor upgrade Design change upgrade modification Reheater Pit Sump design change installed a new instrument and Monitor connected to PIMS in conjunction with relocation of the Control Room.

R-2101 07/27/00 - 11/16/00 Radmonitor upgrade Design change upgrade modification Yard Drain Sump design change installed a new instrument and Monitor connected to PIMS in conjunction with relocation of the Control Room.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 1 SFCTTON L. S.O.N.G.S. 1 CONCLUSIONS S.O.N.G.S. 1 CONCLUSIONS D

SECTION L.

Gaseous releases totaled 1.70E+O curies of which noble gases were O.OOE+O curies, iodines were O.OOE+O curies, particulates were O.OOE+O curies, and tritium was 1.70E+O curies.

The radiation doses from gaseous releases were: (a) gamma air dose: O.OOE+O mrad at the site boundary, (b) beta air dose: O.OOE+O mrad at the site boundary, organ dose: 1.18E-3 mrem at the nearest receptor.

Liquid releases totaled 3.17E+O curies of which particulates and iodines were 6.02E-4 curies, tritium was 3.17E+O curies, and noble gases were O.OOE+O curies.

The radiation doses from liquid releases were: (a) total body: 4.21E-3 mrem, (b) limiting organ: 5.37E-3 mrem.

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

Cl) z CL

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

• 37 S. . . . . . . . . . . . . .. 38 SECTION B - GASEOUS EFFLUENTS .... ...........

S. . . . . . . . . . . . .. . 48 SECTION C - LIQUID EFFLUENTS ..........

SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM .........

.. 57

. . . . . . . . . . .. . 58 S..

SECTION E - RADWASTE SHIPMENTS .........

. . . . . . . . . . .. . 62 S..

SECTION F - APPLICABLE LIMITS .... ...........

S. . . . . . . . . . . . .. . 64 SECTION G - ESTIMATION OF ERROR .... .........

S. . . . . . . . . . . . . . 65 SECTION H - 10 CFR 50 APPENDIX I REQUIREMENTS SECTION I -*CHANGES TO OFFSITE DOSE CALCULATION MANUAL ...... ............ .. 69

.......... .. 70 SECTION - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ....

S. . . . . . . . . . . . .. . 71 SECTION K - MISCELLANEOUS ...... ............

S. . . . . . . . . . . . .. . 74 SECTION L - S.O.N.G.S. 2 and 3 CONCLUSIONS . . .

-iii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

January - December SECTION A. INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Units 2 and 3. This report is prepared in the general format of USNRC Regulatory Guide 1.21 and includes:

1. Quarterly Summaries of Gaseous and Liquid Effluents for "Continuous" and "Batch" Modes of Release

2. Percent of Applicable Limits

3. Estimated Total Percent Error

4. Lower Limit of Detection Concentrations

5. Batch Release Summaries

6. Previous Radioactive Effluent Release Report Addendum

7. Radwaste Shipments

8. 10 CFR 50 Appendix I Requirements

9. Changes to Offsite Dose Calculation Manual ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

Listed for each of the four categories are:

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

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

Table 1B, "Gaseous Effluents-Elevated Release," has not been included in this report since San Onofre Nuclear Generating Station Units 2 and 3 do not conduct elevated releases.

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

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

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

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

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

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Total release Ci 2.66E+1 2.24E+1 3.OOE+1

2. Average release rate for period uCi/sec 3.38E+O 2.85E+O

3. Percent of applicable limit  % MPC 8.45E-3 8.17E-3

4. Percent Effluent Concentration Limit  % ECL 1.70E-2 1.91E-2 B. Iodines

1. Total iodine-131 Ci 4.37E-5 5.88E-5 1.90E+1

2. Average release rate for period 4Ci/sec 5.56E-6 7.48E-6

3. Percent of applicable limit  % MPC 2.67E-5 3.59E-5

4. Percent Effluent Concentration Limit  % ECL 1.33E-5 1.79E-5 C. Particulates

1. Particulates with half-lives >8 days Ci 1.32E-5 9.01E-6 1.60E+1

2. Average release rate for period uCi/sec 1.68E-6 1.15E-6

3. Percent of applicable limit  % MPC 1.46E-6 1.1OE-6

4. Percent Effluent Concentration Limit  % ECL 3.61E-6 2.75E-6

5. Gross alpha activity Ci 4.88E-6 5.77E-6 5.OOE+1 D. Tritium

1. Total release Ci 1.81E+1 1.80E+1 2.50E+1

2. Average release rate for period 4Ci/sec 2.30E+O 2.29E+O

3. Percent of applicable limit  % MPC 5.53E-3 5.49E-3

4. Percent Effluent Concentration Limit  % ECL 1.11E-2 1.10E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

1. Total release Ci 1.37E+1 4.08E+1 3.OOE+1

2. Average release rate for period MCi/sec 1.73E+O 5.13E+O

3. Percent of applicable limit  % MPC 8.56E-3 1.26E-2

4. Percent Effluent Concentration Limit  % ECL 2.78E-2 2.40E-2 B. lodines

1. Total iodine-131 Ci 8.96E-5 1.41E-3 1.90E+1

2. Average release rate for period /.Ci/sec 1.13E-5 1.77E-4

3. Percent of applicable limit  % MPC 5.41E-5 8.51E-4

4. Percent Effluent Concentration Limit  % ECL 2.71E-5 4.26E-4 C. Particulates

1. Particulates with half-lives >8 days Ci 2.05E-4 3.19E-4 1.60E+1

2. Average release rate for period /MCi/sec 2.58E-5 4.02E-5

3. Percent of applicable limit %MPC 2.50E-5 1.85E-5

4. Percent Effluent Concentration Limit  % ECL 6.60E-5 4.99E-5

5. Gross alpha activity Ci 1.03E-5 8.52E-6 5.OOE+1 D. Tritium

1. Total release Ci 1.87E+1 1.91E+1 2.50E+1

2. Average release rate for period ktCi/sec 2.35E+O 2.40E+O

3. Percent of applicable limit  % MPC 5.65E-3 5.77E-3

4. Percent Effluent Concentration Limit  % ECL 1.13E-2 1.15E-2 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Fission and activation gases argon-41 Ci 2.30E+O 2.73E+O 4.42E+O 3.18E+O krypton-85 Ci <LLD <LLD <LLD <LLD krypton-85m Ci <LLD <LLD <LLD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci 2.41E+1 1.94E+1 8.20E+O 3.42E+1 xenon-133m Ci <LLD <LLD <LLD 6.59E-1 xenon-135 Ci <LLD <LLD 2.80E-2 4.80E-1 xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci 2.64E+1 2.21E+1 1.26E+1I 3.85E+1

2. Iodines iodine-131 Ci 4.37E-5 5.88E-5 8.96E-5 1.41E-3 iodine-132 Ci <LLD <LLD 1.67E-5 1.32E-3 iodine-133 Ci 1.21E-4 1.57E-4 2.08E-4 1.40E-4 iodine-135 Ci <LLD <LLD 4.98E-5 1.16E-5 Total for period Ci 1.65E-4 2.16E-4 3.64E-4 I 2.88E-3 LLD Lower Limit of Detection; see Table ID.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

3. Particulates antimony-122 Ci <LLD <LLD 6.34E-7 3.86E-7 barium-140 Ci <LLD <LLD <LLD <LLD bromine-82 Ci 3.50E-5 3.95E-5 7.13E-5 1.19E-4 cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD 1.84E-6 <LLD cesium-134 Ci <LLD <LLD 8.74E-6 1.82E-6 cesium-137 Ci 1.15E-5 9.01E-6 1.90E-4 7.99E-5 cesium-138 Ci <LLD <LLD 1.26E-4 <LLD chromium-51 Ci <LLD <LLD <LLD 1.56E-5 cobalt-57 Ci <LLD <LLD <LLD 1.42E-7 cobalt-58 Ci 1.67E-6 <LLD 3.71E-6 2.07E-4 cobalt-60 Ci <LLD <LLD 1.82E-7 1.03E-5 iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD 7.29E-7 2.54E-6 molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD 1.41E-6 niobium-97 Ci <LLD <LLD <LLD 6.61E-7 sodium-24 Ci <LLD <LLD 3.40E-5 1.45E-6 strontium-89 Ci <LLD <LLD <LLD

• strontium-90 Ci <LLD <LLD <LLD

• technetium-99m Ci <LLD <LLD 5.97E-6 1.30E-6 tungsten-187 Ci <LLD <LLD 1.18E-5 1.02E-6 zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD 6.54E-7 LLD Lower Limit of Detection; see Table ID.

Fourth quarter analyses not available at report time; values will be included in the following Annual Report.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE

• I First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation gases krypton-85 Ci 1.82E-1 2.68E-1 1.08E+O 1.83E+O krypton-85m Ci <LLD <LLD <LLD <LLD krypton-87 Ci <LLD <LLD <LLD <LLD krypton-88 Ci <LLD <LLD <LLD <LLD xenon-131m Ci <LLD <LLD <LLD 1.75E-2 xenon-133 Ci <LLD 1.46E-3 <LLD 4.07E-1 xenon-133m Ci <LLD <LLD <LLD 5.57E-3 xenon-135 Ci <LLD <LLD <LLD 1.67E-3 xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci 1.82E-1 2.70E-1 1.08E+O 2.26E+O LLD Lower Limit of Detection; see Table ID.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 TABLE 1D GASEOUS EFFLUENTS-LOWER LIMIT OF DETECTION CONTINUOUS MODE Radionuclides LLD (mCi/cc)

1. Fission and activation gases krypton-85 2.50E-5 krypton-85m 6.OOE-8 krypton-87 3.1OE-7 krypton-88 2.1OE-7 xenon-133m 4.80E-7 xenon-135 6.30E-8 xenon-135m 2.40E-6 xenon-138 4.10E-6

2. Iodines iodine-132 3.80E-13 iodine-135 1.50E-12

3. Particulates antimony-122 9.OOE-12 barium-140 3.OOE-11 cerium-141 3.90E-12 cerium-144 1.70E-11 cesium-134 1.OOE-11 cesium-138 7.80E-10 chromium-51 3.50E-11 cobalt-57 2.20E-12 cobalt-58 9.10E-12 cobalt-60 1.50E-11 iron-59 2.20E-11 lanthanum-140 2.OOE-11 manganese-54 9.30E-12 molybdenum-99 2.10E-12 niobium-95 8.60E-12 niobium-97 8.40E-12 sodium-24 1.80E-11 strontium-89 1.OOE-13 strontium-90 1.OOE-14 technetium-99m 2.90E-12 tungsten-187 2.80E-11 zinc-65 2.50E-11 zirconium-95 1.50E-11 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

1. Fission and activation gases krypton-85m 2.80E-6 krypton-87 1.30E-5 krypton-88 1.OOE-5 xenon-131m 1.OOE-4 xenon-133 8.30E-6 xenon-133m 2.50E-5 xenon-135 3.20E-6 xenon-135m 4.1OE-5 xenon- 138 6.10E-5 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Gamma Air Dose mrad 4.56E-3 4.90E-3 6.70E-3 6.53E-3

2. Percent Applicable Limit  % 4.56E-2 4.90E-2 6.70E-2 6.53E-2

3. Beta Air Dose mrad 5.06E-3 4.54E-3 3.84E-3 7.99E-3

4. Percent Applicable Limit 2.53E-2 2.27E-2 1.92E-2 4.OOE-2 B. Tritium, Iodine, Particulates (at the nearest receptor)

1. Organ Dose mrem 5.73E-4 5.81E-4 8.25E-4 1.80E-3

2. Percent Applicable Limit  % 3.82E-3 3.87E-3 5.50E-3 1.20E-2 NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

SUMMARY

12 month period

1. Number of batch releases: 6 releases

2. Total time period for batch releases: 2375.0 minutes

3. Maximum time period for a batch release: 583.0 minutes

4. Average time period for a batch release: 395.8 minutes

5. Minimum time period for a batch release: 174.0 minutes ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

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

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

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

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

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

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 9.51E-3 1.11E-2 1.90E+1

2. Average diluted concentration during period MCi/ml 1.26E-11 1.46E-11

3. Percent of applicable limit  % MPC 2.22E-5 3.13E-5

4. Percent Effluent Concentration Limit  % ECL 1.39E-4 3.32E-4 B. Tritium

1. Total release Ci 1.34E+2 4.04E+2 1.90E+1

2. Average diluted concentration during period kCi/ml 1.77E-7 5.32E-7

3. Percent of applicable limit  % MPC 5.91E-3 1.77E-2

4. Percent Effluent Concentration Limit  % ECL 1.77E-2 5.32E-2 C. Dissolved and entrained gases

1. Total release Ci 5.40E-2 8.14E-3 1.90E+1

2. Average diluted concentration during period uCi/ml 7.14E-11 1.07E-11

3. Percent of applicable limit  % MPC 3.57E-5 5.36E-6

4. Percent Effluent Concentration Limit  % ECL 3.57E-5 5.36E-6 D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.0OE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 3.80E+7 3.95E+7 5.OOE+O F. Volume of dilution water used during period liters 17.56E+11 7.60E+11 5.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

1. Total release (not including tritium, gases, alpha) Ci 1.44E-2 3.44E-2 1.90E+1

2. Average diluted concentration during period uCi/ml 1.88E-11 5.53E-11

3. Percent of applicable limit  % MPC 4.47E-5 7.47E-5

4. Percent Effluent Concentration Limit  % ECL 4.73E-4 5.77E-4 B. Tritium

1. Total release Ci 1.33E+3 5.33E+2 1.90E+1

2. Average diluted concentration during period MCi/ml 1.73E-6 8.56E-7

3. Percent of applicable limit  % MPC 5.77E-2 2.85E-2

4. Percent Effluent Concentration Limit  % ECL 1.73E-1 8.56E-2 C. Dissolved and entrained gases (_)

1. Total release Ci 1.02E+O 6.95E-1 1.90E+1

2. Average diluted concentration during period AzCi/ml 1.33E-9 1.11E-9

3. Percent of applicable limit  % MPC 6.67E-4 5.57E-4

4. Percent Effluent Concentration Limit  % ECL 6.67E-4 5.57E-4 D. Gross alpha radioactivity

1. Total release Ci <LLD <LLD 5.OOE+1 E. Volume of waste released (batch &

continuous, prior to dilution) liters 4.13E+7 3.68E+7 5.OOE+O F. Volume of dilution water used during period liters 7.68E+11 6.23E+11 5.OOE+O (1) The Unit 3 monthly April Dissolved & Entrained (D&E) gas analysis for the Turbine Plant System was not performed. These sumps are open to the atmosphere and have historically shown no measurable D&E activity.

This event is documented in AR 000500230.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Fission and activation products barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci <LLD <LLD <LLD <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

• 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

• strontium-90 Ci <LLD <LLD <LLD

• technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD

2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 2C.

Fourth quarter analyses not available at report time; values will be included in the following Annual Report.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

1. Fission and activation products antimony-122 Ci <LLD <LLD 2.02E-5 <LLD antimony-125 Ci 5.46E-3 4.31E-3 6.52E-3 2.09E-3 barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci 1.43E-4 8.13E-4 9.54E-4 4.99E-4 cesium-137 Ci 2.30E-4 1.14E-3 1.53E-3 1.04E-3 chromium-51 Ci <LLD <LLD <LLD 6.99E-3 cobalt-57 Ci <LLD <LLD <LLD 5.83E-5 cobalt-58 Ci 1.90E-4 1.14E-4 4.23E-5 1.78E-2 cobalt-60 Ci 5.60E-4 5.65E-4 2.16E-3 2.44E-3 iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci 1.41E-3 3.38E-3 2.66E-3

• iron-59 Ci <LLD <LLD <LLD 6.29E-4 lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci 9.10E-5 6.53E-5 2.24E-4 4.97E-4 molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci 2.86E-5 <LLD 7.22E-6 1.30E-3 niobium-97 Ci <LLD 6.77E-5 8.16E-6 <LLD ruthenium-106 Ci 2.21E-4 <LLD 8.78E-5 <LLD silver-lOrm Ci 1.11E-3 6.19E-4 2.15E-4 3.23E-4 strontium-89 Ci <LLD <LLD <LLD

• strontium-90 Ci <LLD <LLD <LLD

• strontium-92 Ci <LLD <LLD 1.69E-5 <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD 7.63E-4 zirconium-97 Ci 5.63E-5 3.52E-5 4.34E-6 <LLD Total for period Ci 9.51E-3 1.11E-2 1.45E-2 3.44E-2 LLD Lower Limit of Detection; see Table 2C.

Fourth quarter analyses not available at report time; values will be included in the following Annual Report.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

2. Dissolved and entrained gases krypton-85 Ci 5.40E-2 8.14E-3 1.32E-1 1.91E-1 xenon-131m Ci <LLD <LLD 1.97E-2 1.66E-2 xenon-133 Ci <LLD <LLD 8.70E-1 4.86E-1 xenon-133m Ci <LLD <LLD 2.28E-3 1.03E-3 xenon-135 Ci <LLD <LLD 2.14E-5 <LLD Total for period Ci 5.40E-2 8.14E-3 1.02E+O 6.95E-1 LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Fission and activation products barium-140 3.30E-7 cerium-141 5.20E-8 cerium-144 2.30E-7 cesium-134 9.90E-8 cesium-137 8.60E-8 chromium-51 4.20E-7 cobalt-58 8.70E-8 cobalt-60 1.30E-7 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 lanthanum-140 2.40E-7 manganese-54 8.80E-8 molybdenum-99 3.50E-8 niobium-95 8.50E-8 strontium-89 5.OOE-8 strontium-90 1.OOE-8 technetium-99m 3.50E-8 zinc-65 2.20E-7 zirconium-95 1.50E-7

2. Dissolved and entrained gases xenon-133 3.10E-7 xenon-135 1.20E-7

3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

1. Fission and activation products antimony-122 1.20E-7 barium-140 3.30E-7 cerium-141 5.20E-8 cerium-144 2.30E-7 chromium-51 4.20E-7 cobalt-57 2.90E-8 iodine-131 6.OOE-8 iron-55 1.OOE-6 iron-59 2.OOE-7 1anthanum-140 2.40E-7 molybdenum-99 3.50E-8 niobium-95 8.50E-8 niobium-97 2.OOE-7 rutheni urn-106 7.10E-7 strontium-89 5.OOE-8 strontium-90 1.OOE-8 strontium-92 7.80E-5 technetium-99m 3.50E-8 zinc-65 2.20E-7 zirconium-95 1.50E-7 zirconium-97 2.20E-7

2. Dissolved and entrained gases xenon-131m 3.90E-6 xenon-133 3.10E-7 xenon-133m 9.20E-7 xenon-135 1.20E-7

3. gross alpha 1.OOE-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

1. Total body dose mrem 3.37E-4 9.78E-4 2.56E-3 1.46E-3

2. Percent Applicable Limit  % 1.12E-2 3.26E-2 8.54E-2 4.86E-2 B.

1. Limiting organ dose mrem 4.31E-3 3.25E-3 3.82E-3 6.33E-3

2. Percent Applicable Limit  % 4.31E-2 3.25E-2 3.82E-2 6.33E-2

3. Limiting organ for period GI-LLI GI-LLI GI-LLI GI-LLI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

SUMMARY

12 month period

1. Number of batch releases: 177 releases

2. Total time period for batch releases: 27516 minutes

3. Maximum time period for a batch release: 540 minutes

4. Average time period for a batch release: 155 minutes

5. Minimum time period for a batch release: 2 minutes

6. Average saltwater flow during batch releases: 734000 gpm SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM None.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 SECTION E. RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

Estimated 12 month total error

1. Type of waste Unit period (%)

a. Spent resins, filter sludges, m3 2.89E+1 evaporator bottoms() Ci 1.38E+2 3.OOE+1

b. Dry active waste (DAW), m3 2.77E+1 compactable and non-compactabl e(#) Ci 3.58E+1 3.00E+1

c. Irradiated components, control m3 N/A rods Ci N/A N/A

d. Other m3 N/A Ci N/A N/A Note: Total curie content estimated.

(*) Material packaged in High Integrity Containers and shipped in Type B Cask (C of C 9208).

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

N/A No shipment made.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

2. Estimate of major nuclide composition (by type of waste)

a. americium-241  % 3.62E-4 antimony-125  % 2.96E-1 carbon-14  % 7.45E-1 cesium-134  % 6.64E+O cesium-137 _ 1.47E+1 cobalt-57  % 2.69E-1 cobalt-58 _ 2.54E+1 cobalt-60  % 5.30E+O curium-242  % 5.14E-5 curium-243/244  % 4.23E-4 iron-55  % 1.04E+1 manganese-54 _ 2.38E+O nickel-59  % 2.14E-1 nickel-63  % 3.35E+1 niobium-94  % 7.13E-3 plutonium-238  % 4.11E-4 plutonium-239/240  % 2.29E-4 plutonium-241  % 1.29E-2 strontium-89  % 3.89E-3 strontium-90  % 3.32E-2 technetium-99  % 7.87E-6 tritium _1.18E-1 %

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

2. Estimate of major nuclide composition (by type of waste) (Cont'd)

b. americium-241 8.42E-4 antimony-124 1.49E-1 antimony-125 6.51E-1 carbon-14 1.04E+O ceri um-141 1.17E-1 ceri um-144 1.21E-1 cesium-134 __________2.73E+O cesi um-137 __________2.50E+1 chromi ur-51 ___ ______9.O1E+O cobal t-57 __________1.02E-1 cobal t-58 _________ .58E+1 cobal t-60 __________5.34E+O curi um-242 ____ _____1.49E-3 curi um-243/244 %________ 1.78E-3 iodi ne-129 %_________ 5.49E-2 iron-55 %________ 2.49E+l iron-59 %________ 1.09E+O manganese-54 %_________ 7.81E-1 nickel -63 %________ 8.13E+O niobium-94 %________ 2.34E-4 ni obi um-95 %_________ 2.82E+O p1 utoni um-238 %_________ 7.80E-4 p1 utoni um-239/240 %________ 6.44E-4 p1 utoni um-241 %________ 9.64E-2 rutheni um-103 __________ 1.67E-4 sil1ver-li0m %________ 2.79E-2 stronti um-89 %________ 1.84E-2 stronti um-90 %_________ 7.21E-3 techneti um-99 __________ 3.67E-3 tin-113 __________ 4.53E-1 tritium %_________ 5.1OýE-2 urani um-233/234 %4.72E-5 urani um-238 %3.19E-5 zi rconium-95 %1.49E+O

c. not applicable %O.OOE+O

d. not applicable %________ O.OOE+O ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 33

• Kindrick Trucking Company Envirocare, UT Truck/Trailer 6 Hitman Trucking Company Barnwell, SC Truck/Trailer 2

2__Truck/Trailer Kindrick Trucking Company Envirocare, UT

• SONGS maintains contracts with vendors (ATG/GTS) that provide volume reduction services.

These shipments were made from their processing facility. The 33 shipments made from these facilities included waste from other generators. SCE's waste volume was a small fraction of the total waste volume of these shipments.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING Number of Containers Solidification Agent 6 N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

% Applicable Limit = (Rel Rate) (XWO) (100)

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

X/Q 4.80E-6 sec/m 3 ; the annual average atmospheric dispersion defined in the Units 2&3 0DCM, Rev. 31.

1 0 MPCeff n Fi i=1 MPC i where: F- fractional abundance of the i th radionuclide obtained by dividing the activity (curies) for each radionuclide, C1 , by the sum of all the isotopic activity, CT.

n - total number of radionuclides identified 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, *uCi/sec.

X/Q 4.80E-6 sec/m 3 ; the annual average atmospheric dispersion defined in the Units 2&30DCM, Rev. 31.

1 o ECLeff n Fi M ECL i where: Fi fractional abundance of the it" radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified ECLj = Effluent Concentration Limit (ECL) of the i th radionuclide from 10 CFR 20 (20.1001-20.2402),

Appendix B, Table 2, Column 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

% Applicable Limit = (Dil Conc) (100)

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

1 0 MPCeff n F.

i=i MPC i where: F, fractional abundance of the i" radionuclide obtained by dividing the activity (curies) for each radionuclide, C1 , by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified MPC1 Maximum Permissible Concentration (MPC) of the it' 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, 4zCi/ml.

1 ECLeff n F.

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

n total number of radionuclides identified ECL, Effluent Concentration Limit (ECL) of the it' radionuclide from 10 CFR 20 (20.1001-20.2402),

Appendix B, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made.

Sources of error for gaseous effluents - batch releases are:

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

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

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

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

Total Error C1a2+ a2 + 2y+ 2 where: o- Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

Six different categories are presented:

(1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; these data are also presented in Table 2D. Categories 3, 4, and 5 were calculated utilizing RRRGS (Radioactive Release Report Generating System) software, Regulatory Guide 1.109 methodology, and concurrent meteorology. Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

For 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 negligible and hence the dose "0".

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 TABLE I Dose * (millirems)

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

Whole Body 3.37E-4 9.78E-4 2.56E-3 1.46E-3 5.34E-3

6) 7) 8) 9) 10)

Organ 4.31E-3 3.25E-3 3.82E-3 6.33E-3 1.77E-2 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15)

Tritium, lodines, and Particulates 6.65E-3 3.28E-3 3.68E-3 4.75E-3 1.78E-2 NOBLE GASES ** 16) 17) 18) 19) 20)

Gamma 1.51E-3 3.45E-3 1.82E-3 1.94E-3 7.18E-3

21) 22) 23) 24) 25)

Beta 1.39E-3 3.26E-3 1.56E-3 2.12E-3 8.08E-3

26) 27) 28) 29) 30)

DIRECT RADIATION 7.32E-2 1.12E-1 1.25E-1 9.86E-2 3.43E-1

• The numbered footnotes below briefly explain how each maximum dose was calculated, including the organ and the predominant pathway(s).

reflecting the air dose.

• • Noble gas doses due to airborne effluent are in units of mrad, ODCM.

1. This value was calculated using the methodology of the ODCM.

2. This value was calculated using the methodology of the of the ODCM.

3. This value was calculated using the methodology ODCM.

4. This value was calculated using the methodology of the of the ODCM.

5. This value was calculated using the methodology ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

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

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

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

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

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

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

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

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

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

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

16. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

17. The maximum air dose for gamma radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

18. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

19. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

20. The maximum air dose for gamma radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

21. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

22. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

23. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

24. The maximum air dose for beta radiation was located in the E sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

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

25. The maximum air dose for beta radiation was located in the ENE sector, at the exclusion area boundary, and calculated using the assumptions of the USNRC Regulatory Guide 1.109.

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

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

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

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

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

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 1.12E-2 3.26E-2 8.54E-3 4.86E-2 8.89E-2 Organ 4.31E-2 3.25E-2 3.82E-2 6.33E-2 8.86E-2 AIRBORNE EFFLUENTS Tritium, Iodines, and Particulates 4.43E-2 2.19E-2 2.46E-2 3.16E-2 5.94E-2 NOBLE GASES Gamma 1.15E-2 3.45E-2 1.82E-2 1.94E-2 3.59E-2 Beta 6.95E-3 1.63E-2 7.79E-3 1.06E-2 2.02E-2 NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL On February 29, 2000, Revision 35 to the Units 2/3 Offsite Dose Calculation Manual (ODCM) was adopted and published. This change incorporated final turnover items related to DCP 7022 (South Yard Facility radiation monitors), along with some other minor administrative improvements. Incorporated into this revision are:

1. Added setpoint methodology for SYF particulate radiation monitors,

2. Added SYF Data Aquistion System (DAS) and associated ACTION 43 to Section 4, and

3. Changes related to the Land Use Census update.

Safety Evaluations were provided for items 1 and 2.

Per NRC Generic Letter 89-01, no safety reviews were required or performed for editorial changes or changes made to reflect actual plant operation.

Minor format changes, correction of typographical errors, and removal of previously blank pages were made and are described in the attached List of Affected Pages.

None of the changes impact the accuracy or reliability of effluent dose or setpoint calculations. The level of radioactive effluent control required by IOCFR20, 40CFRI90, 10CFR50.36a, and Appendix I to 10CFR50 will be maintained.

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

A Addition D Deletion F Editorial/Format change R Revision The following is a complete list of the changes:

OLD NEW CHANGE REASON TOC Renumbered pages as necessary based on changes in the body of the ODCM. F 2-12 Removed the previously blank page. D 2-14 2-13 Changed format of equation definitions to be consistent with the rest of F the ODCM.

2-20 & Added Section 2.6.5 for the South Yard Facility A 2-21 2-31 Corrected a typo in the Cs-137 value of Table 2-6 F 2-33 Added R1 Table for San Mateo Pt. Homes A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 OLD NEW CHANGE REASON 4-9 Added "SOUTH YARD FACILITY" to item 7. F Added item 8, South Yard Facility Data Acquisition System or Datalink to A Main DAS.

4-11 Added ACTION 43, associated with the SYF DAS A 4-14 Added item 8, South Yard Facility Data Acquisition System or Datalink to A Main DAS.

6-4 Corrected the revision date from 11-03-99 to 11-09-99. F SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the Units 2&3 Radioactive Waste Treatment Systems during the reporting period, January 1, 2000 to December 31, 2000.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 SECTION K. MISCELLANEOUS Missed Independent Verification Prior to Radwaste Tank Release On 10/03/00, radwaste tank T-057 (permit #OL-371-0) was released without performing the required independent verification of the discharge line valving. After the release was completed but prior to the monitor flush, the missed verification was identified and performed satisfactorily. There were no additional dose consequences to the public due to this event which is documented in Action Request (AR) 001000162.

Missed 4 Hour Channel Check During Purge with DAS Communication Inoperable On 10/07/00, a Unit 2 Containment purge was in progress using monitor 2RT-7828 with the Data Acquisition System (DAS) communication inoperable. The monitor once per 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> channel check for the inoperable DAS at 1205 was missed due to increased Control Room activity during reactor shutdown for refueling outage. The channel check was successfully completed at 1430 with the purge still in progress. There were no dose consequences as a result of this event which is documented in AR 001000377.

Incorrect Vendor Information on Steam Generator Blowdown Flow Devices On 11/06/00, it was determined that the vendor supplied calibration data for the Steam Generator blowdown flow devices were incorrect. New calculations showed flow has been underestimated by as much as 25% since plant startup.

An evaluation has shown no dose limits were challenged because of this vendor error. An investigation and assessment is documented in AR 001100455.

Incorrectly Recorded Meteorological Data On 10/27/00, it was determined the meteorological data collected since 07/27/98 was in error. Subsequent to a hard drive failure, the meteorological data was incorrectly converted (by a factor of 2) for all wind speeds. The meteorological data were corrected for calculations of the year 2000 data.

The data collection process will be modified to be checked with more detail after any physical computer failure. An evaluation of previous year's data is ongoing under AR 001002318.

Unplanned. Unmonitored Release From Unit 2 FFCPD During Resin Backwash On 12/26/00, the Unit 2 FFCPD experienced a five minute leak due to a broken plexiglass flow sight glass. The break occurred during the initial backwash step of the regeneration process. Approximately 1500 gallons of clean sluice water flowed into the storm drains and directly to the outfall conduits.

Analysis of the spilled resin indicated no detectable activity. The sight glasses will be replaced with an improved design. There was no dose to the public as a result of this event which is documented in AR 001201226.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 Leaking Unit 2 Steam Generator Blowdown Valves On 12/13/00, Unit 2 Steam Generators were determined to be leaking past their blowdown isolation valves to the outfall. The maximum leak rate was determined to be 2 gpm. Repairs are planned for the next outage. Compensatory sampling is being performed (samples indicate no detectable activity to date) and release data are being evaluated and documented. This event is documented in AR 001200733.

Improperly Installed Monitor Setpoints on 3RT-7817 On 12/11/00, it was determined the installed alarm setpoint for the Unit 3 Full Flow Condensate Polishing Demineralizer (FFCPD) discharge line monitor, 3RT-7817, was incorrect. The installed value was erroneously set at 5.00E6 uCi/ml rather than the correct 5.OOE-6 uCi/ml. An investigation showed that the error was made during a surveillance performed on 11/08/00. The releases conducted during this time period had no detectible gamma activity (two releases had trace amounts of tritium). There was no additional dose consequence to the public due to this event. The surveillance procedure was modified to add an extra setpoint verification step. An investigation and assessment is documented in AR 001200587.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2000 - December 31, 2000 S.0.N.G.S. 2 Monitor Inoperability Period Inoperability Cause Explanation 2RT-7817 08/09/00 - 10/02/00 Failed flow Replaced portions of sample piping BPS/FFCPD measuring devices which had plugged. Accumulated Discharge Monitor corrosion buildup had stopped flow.

2RT-7870 04/17/00 - present Inoperable process Design deficiency causes process Condenser Air flow measuring flow instrument to be inoperable Ejector Process device whenever while the vacuum pump is running.

Flow Monitor vacuum pump is Substitute flow value is running. automatically inserted whenever the vacuum pump is running as high flow values are not sensed. Flow monitor works properly during normal

_operations.

EFFLUENT RADIATION MONITORS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2000 - December 31, 2000 S.O.N.G.S. 3 Monitor Inoperability Period Inoperability Cause Explanation 3RT-7817 05/04/00 - 06/23/00 Improper sample Replaced portions of sample piping BPS/FFCPD flow which had plugged. Accumulated Discharge Monitor corrosion buildup had stopped flow.

3RT-7870 04/17/00 - present Inoperable process Design deficiency causes process Condenser Air flow measuring flow instrument to be inoperable Ejector Process device whenever while the vacuum pump is running.

Flow Monitor vacuum pump is Substitute flow value is running. automatically inserted whenever the vacuum pump is running as high flow values are not sensed. Flow monitor works properly during normal

_operations.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

S.O.N.G.S. 2 and 3 SECTION L. S.O.N.G.S. 2 and 3 CONCLUSIONS Gaseous releases totaled 1.78E+2 curies of which noble gases were 1.04E+2 curies, iodines were 3.63E-3 curies, particulates were 9.95E-4 curies, and tritiumwas 7.39E+1 curies.

The radiation doses from gaseous releases were: (a) gamma air dose: 7.18E-3 mrad at the site boundary, (b) beta air dose: 8.08E-3 mrad at the site boundary, (c) organ dose: 1.78E-2 mrem at the nearest receptor.

Liquid releases totaled 2.40E+3 curies of which particulates and iodines were 6.95E-2 curies, tritium was 2.40E+3 curies, and noble gases were 1.78E+O curies.

The radiation doses from liquid releases were: (a) total body: 5.34E-3 mrem, (b) limiting organ: 1.77E-2 mrem.

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

COMMON ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

COMMON COMMON RADWASTE SHIPMENTS TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

Estimated

1. Type of waste Unit 12 month period total error (%)

m3 N/A

a. Spent resins, filter sludges, evaporator bottoms Ci N/A N/A

b. Dry active waste (DAW), m3 N/A compatible and non compatible Ci N/A N/A m3 N/A

c. Irradiated components, control rods Ci N/A N/A m3 N/A Ci 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 (2000)

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

3. Solid Waste Disposition (S.O.N.G.S. 1, 2, and 3)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made N/A C. DEWATERING See Units 2/3 section of this report.

D. CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3 None.

REFERENCES:

1. Unit I Technical Specifications, section D6.13.2.

2. Units 2 and 3 Licensee Controlled Specifications, Section 5.0.103.2.2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

COMMON COMMON 40 CFR 190 REQUIREMENTS Table 1 below presents the annual site-wide doses and percent of ODCM Specification limits to members of the public. These values were calculated utilizing doses resulting from all effluent pathways and direct radiation. The different categories presented are: (1) Total Body, (2) Limiting Organ, and (3) Thyroid.

Dose Category Units Year

1. Total Body

a. Total Body Dose mrem 3.74E-1

b. Percent ODCM Specification Limit 1.50E+O

2. Limiting Organ

a. Organ Dose (GI-LLI) mrem 2.69E-2

b. Percent ODCM Specification Limit  % 1.07E-1

3. Thyroid

a. Thyroid Dose mrem 8.52E-3

b. Percent ODCM Specification Limit  % 1.14E-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

COMMON COMMON CONCLUSIONS Gaseous releases from S.O.N.G.S. 1, 2 and 3 totaled 1.80E+2 curies of which noble gases were 1.02E+2 curies, iodines were 3.63E-3 curies, particulates were 9.95E-4 curies, and tritium was 7.56E+1 curies.

Liquid releases form S.O.N.G.S. 1, 2 and 3 totaled 2.40E+3 curies of which particulates and iodines were 7.55E-2 curies, tritium was 2.40E+3 curies, and noble gases were 1.78E+O curies.

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

S.O.N.G.S. 1, 2 and 3 made 7 radwaste shipments to Barnwell, SC and 69 shipments to Envirocare, UT. Total volume was 6.37E+2 cubic meters containing 1.79E+2 curies of radioactivity.

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

Meteorological dispersion was good 31% of the time, fair 46% of the time and poor 23% of the time.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

COMMON APPENDIX A GASEOUS EFFLUENTS - APPLICABLE LIMITS A. Table 1A lists the total curies released and the release rate. The percent of applicable limit compares the released concentrations to the concentration limits of 10 CFR 20, Appendix B, Table II, Column 1.

B. Table 1E lists the air doses as calculated using the historical X/Q. The air dose due to noble gases released in gaseous effluents from S.O.N.G.S. (per reactor) to areas at and beyond the site boundary shall be limited to the following values:

1. During any calendar quarter: mrad for gamma radiation and S5 S10 mrad for beta radiation.

2. During any calendar year: mrad for gamma radiation and S10

• 20 mrad for beta radiation.

The dose to a Member of the Public from iodines, tritium, and all C.

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: g 15 mrem to any organ.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

COMMON APPENDIX A (Continued)

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

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

1. During any calendar quarter: <1.5 mrem to the total body and S5 mrem to any organ.

2. During any calendar year: <3 mrem to the total body and

<10 mrem to any organ.

METEOROLOGY METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2000 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, 2000. 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 (2000)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99123124-00033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ < -1.9 °C/100 METERS)

.51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND .22-DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 0 0 0 0 0 0 0 0 0 0 0 0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 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 E 0 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 4 1 0 0 0 0 5 SSE 0 0 2 2 10 10 10 0 0 0 0 0 34 S 0 0 0 1 2 3 10 5 0 0 0 0 0 21 SSW 0 1 0 3 8 15 8 0 0 0 0 0 35 SW 0 0 0 6 12 31 17 0 0 0 0 0 66 WSW 0 0 1 6 55 60 4 1 0 0 0 128 W 1 0 0 0 1 3 16 36 8 1 0 0 0 65 WNW 0 0 0 0 0 0 0 2 0 0 0 0 2 NW 0 0 0 0 0 0 0 0 1 0 0 0 1 NNW TOTALS 1 1 3 15 42 137 140 15 3 0 0 0 357 357 NUMBER OF CALMS 0 NUMBER OF VALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 NUMBER OF INVALID HOURS PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ * -1.7 'C/100 METERS)

.51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND .22-DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 0 0 0 0 0 0 0 0 0 0 0 0 0 N

0 0 0 0 0 0 0 0 0 0 0 1 NNE 1 0 0 0 0 0 1 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E

0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 1 0 0 0 0 1 SE 1 0 0 0 1 1 4 2 0 0 0 0 9 SSE 0 0 0 2 4 1 0 1 0 0 8 S 0 0 0 0 1 2 4 4 0 0 0 0 0 11 SSW 0 0 0 1 0 1 4 1 0 0 0 0 0 7 SW 0 0 0 1 0 2 0 0 0 0 0 0 3 WSW 0 0 0 1 0 0 0 0 0 1 0 0 2 W

0 0 1 0 2 2 0 0 0 0 0 5 WNW 0 0 0 0 1 0 0 2 0 0 0 0 3 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 2 0 1 4 5 16 15 6 0 2 0 0 51 TOTALS 51 NUMBER OF CALMS 21840 NUMBER OF VALID HOURS TOTAL HOURS FOR THE PERIOD NUMBER OF INVALID HOURS 0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99123124-00033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ * -1.5 -C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 3.1 7.I- 1U.1- 13.1-5).1J-- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 N 0 0 0 10A 0nr 13 0 180A 0 1 0 0 0 0 0 0 0 1 NNE 3 0 0 0 0 0 1 0 0 0 1 0 5 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 1 0 0 0 0 0 1 1 SSE 0 0 0 1 0 3 0 0 0 0 0 5 S 0 0 0 0 0 3 4 0 0 0 0 0 7 SSW 0 0 0 0 2 4 3 1 0 0 0 0 10 SW 0 0 1 2 1 2 4 0 0 0 0 0 10 WSW 0 0 0 0 1 0 1 0 0 0 0 0 2 W 0 0 2 1 2 1 2 2 0 0 0 0 10 WNW 2 0 0 2 2 1 2 0 0 0 0 0 9 NW 0 0 0 0 0 1 4 3 0 0 0 0 8 NNW 0 0 0 0 1 0

TOTALS 5 0 2 8 8 16 1 230 07 0 0 0 0 00 0 0 69 NUMBER OF VALID HOURS 69 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 'C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 I

5 1 5 7 II 1 2 0 1 0 34 NNE 0 2 1 7 3 5 4 7 0 1 0 0 30 NE 0 0 2 0 2 2 3 10 0 0 0 0 19 ENE 0 0 0 1 1 1 0 0 0 0 0 0 3 E 0 0 0 1 1 6 2 1 0 0 0 0 11 ESE 0 0 0 2 4 2 12 2 1 0 0 0 23 SE 0 0 1 1 4 20 54 26 8 0 0 0 114 SSE 1 0 1 6 8 24 31 8 13 9 0 0 101 S 0 0 0 5 4 15 10 3 7 6 0 0 50 SSW 0 1 2 5 2 12 10 8 3 1 0 0 44 SW 0 1 3 5 5 5 9 3 1 1 0 0 33 WSW 0 2 1 4 3 6 11 2 1 0 0 0 30 W 0 0 2 7 4 6 13 3 3 0 0 0 38 WNW 0 2 1 4 7 13 16 2 4 0 0 0 49 NW 0 0 1 7 2 20 17 11 0 0 0 0 58 NNW 0 0 0 2 4 8 7 1 0 0 0 22 TOTALS 1 9 18 0 1 0 659 20 58 59 152 2:10 88 43 18 I T

NUMBER OF VALID HOURS 659 NUMBER OF CALMS NUMBER OF INVALID HOURS 0 0 TOTAL HOURS FOR THE PERIOD 2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99123124-00033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0.5 < DT/DZ * -1.5 -C/100 METERS) 1.1 1.6 5.1- 7.1- 110.1 13.1-13.1

>1Q TATAI WIND .22 .51 .76 2.1 3.1 2.0 3.0 5.0 7.0 10.0 113.0 18.0 DIR .50 .75 1.0 1.5 30 8 9 2 0 0 0 N 0 0 1 6 4 0 0 30 72 16 21 17 1 0 0 NNE 0 1 1 15 0 0 40 5 6 12 0 0 0 NE 0 1 5 11 0 0 18 1 3 2 1 1 0 0 0 ENE 0 1 3 6 14 0 2 2 1 3 2 0 0 E 0 0 2 2 17 3 5 3 0 0 1 0 0 ESE 0 1 1 3 23 4 4 8 4 0 0 0 0 SE 1 0 0 2 23 6 8 7 0 0 0 0 0 SSE 0 0 0 2 7 2 0 1 0 0 0 0 0 S 0 0 2 2 6 2 0 0 0 0 0 0 SSW 0 0 1 3 0 2 1 0 0 0 0 0 0 0 SW 0 0 1 0 6 1 0 0 1 0 0 0 WSW 0 0 1 3 0 20 4 10 2 0 0 0 W 0 0 2 1 1 0 27 6 3 7 4 0 0 0 WNW 1 1 1 3 1 23 4 6 4 0 0 0 NW 0 0 1 3 5 0 18

• 1 3 1 6 7 0 0 0 0 0 NINItr n 2 5 23 65 52 79 85 24 8 3 0 0 346 TOTALS 346 NUMBER OF CALMS 0 NUMBER OF VALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 NUMBER OF INVALID HOURS PASQUILL F MODERATELY STABLE (1.5 5 DT/DZ * -0.5 'C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 0 1 3 1 4 6 8 0 0 0 0 0 23 N

3 0 2 14 42 43 31 1 0 0 0 0 136 NNE 0 2 2 18 25 11 2 0 0 0 0 0 60 NE 2 5 1 2 1 0 0 0 0 0 12 ENE 0 1 0 0 2 3 1 0 1 0 0 0 0 0 7 E

0 0 1 2 0 1 0 0 0 0 0 0 4 ESE 0 0 1 0 0 3 1 0 0 0 0 0 5 SE 0 0 0 0 1 2 1 1 0 0 0 0 5 SSE 0 1 1 4 1 1 1 0 0 0 0 0 9 S

0 0 1 1 1 0 1 0 0 0 0 0 4 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 1 2 1 0 0 0 0 0 0 0 4 WSW 0 1 0 2 0 5 1 0 0 0 0 0 9 W

1 0 0 0 1 2 0 0 0 0 0 0 4 WNW 1 0 0 2 1 4 1 0 0 0 0 0 9 NW 2 0 0 1 1 1 2 0 0 0 0 0 7 NNW 7 6 16 55 80 81 51 2 0 0 0 0 298 TOTALS 298 NUMBER OF CALMS 0 NUMBER OF VALID HOURS TOTAL HOURS FOR THE PERIOD 2184 NUMBER OF INVALID HOURS 0

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY January - March TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 99123124-00033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4 .0 'C/100 METERS)

WIND .22 .51 - .76 1.1 1.6 2.1 .1 7.1 10.1 13.1 >18 5.0 5.1 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 10.0 13.0 18.0 0 8 7.0 N 0 0 1 1 9 0 0 0 0 21 2

NNE 1 1 0 3 17 108 1.33 0 0 0 0 270 7

NE 0 0 1 5 13 21 6 0 0 0 0 46 0

ENE 0 0 1 2 5 0 0 0 0 0 0 8 0

E 0 1 2 2 0 1 0 0 0 0 0 6 0

ESE 0 0 0 1 1 1 0 0 0 0 0 3 0

SE 0 0 0 2 0 0 0 0 0 0 0 2 0

SSE 0 0 1 1 2 1 1 0 0 0 0 8 2

S 0 0 0 0 0 0 0 0 0 0 0 0 0

SSW 0 0 0 0 0 0 0 0 0 0 0 0 0

SW 0 1 o 1 0 0 0 0 0 0 0 2 0

WSW 0 0 0 1 0 0 0 0 0 0 0 1 0

W 1 1 0 1 2 1 0 0 0 0 0 6 0

WNW 4 0 0 0 0 1 3 0 0 0 0 8 0

NW 3 0 0 1 3 2 3 0 0 0 0 13 0 1 NNW 4 0 1 1 2 2 TOTALS 13 4 6 22 46 147 154 0 120 0 0 0 0 00 0 0 1 404 NUMBER OF VALID HOURS 404 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 N0 i ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 U

1-u 14 30 36 5 0 U 1 0 109 NNE 8 4 4 39 78 177 186 17 0 1 0 0 514 NE 0 3 10 34 45 41 23 10 0 0 0 0 166 ENE 0 2 6 14 8 6 3 1 1 0 0 0 41 E 0 1 6 8 2 9 5 2 3 2 0 0 38 ESE 0 1 2 8 8 9 15 2 1 1 0 0 47 SE 1 0 2 5 8 27 64 31 8 0 0 0 146 SSE 2 0 2 10 18 39 49 14 13 9 0 0 156 S 0 1 5 13 17 31 30 4 7 7 0 0 115 SSW 0 1 5 12 12 30 23 9 3 1 0 0 96 SW 0 3 6 11 16 26 22 3 1 1 0 0 89 WSW 0 2 3 17 18 39 29 3 1 0 0 0 112 W 2 2 5 15 15 72 86 11 4 1 0 0 213 WNW 8 3 2 11 14 41 62 17 9 0 0 0 167 NW 4 0 2 13 11 33 29 24 0 0 0 0 116 NNW 6 0 2 7 8 18 16 1 1 0 0 0 31 25 71 59 TOTALS 227 292 628 678 154 54 23 1 0 2184 1

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 (2000)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00033124-00063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ < -1.9 -C/100 METERS) 1.1 EXTREMELY 1.6 2.1 3.1 5.1" 7.1 10.1 13.1 >10 TOTAL WIND .22 .51 .7b UNSTABLE 5.0 7.0 10.0 13.0 18.0

.50 .75 1.0 1.5 2.0 3.0 DIR 0 0 0 0 0 0 0 0 0 0 0 0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 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 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 2 0 0 0 8 1 0 2 3 0 SSE 0 0 0 7 0 0 0 52 1 7 10 27 0 S 0 0 0 0 0 54 0 5 16 26 4 0 0 SSW 0 0 3 0 0 0 91 1 11 35 41 0 0 SW 0 0 3 0 0 0 167 2 24 71 67 0 0 WSW 0 0 3 0 0 229 0 16 87 125 1 0 0 W 0 0 0 1 0 0 96 0 2 21 65 7 0 WNW 0 0 0 0 0 7 0 0 0 4 3 0 0 NW 0 0 0 0 0 0 0 1 0 0 0 0 0 NNW 0 0 0 0 0 705 242 358 24 1 IUIML3 v u 705 NUMBER OF CALMS 0 NUMBER OF VALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2184 NUMBER OF INVALID HOURS PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ * -1.7 °C/10O

.51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND .22-DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 0 0 0 0 0 0 0 0 0 0 0 0 N 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 1 0 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E 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 0 2 2 1 0 0 0 0 5 0 0 0 0 2 2 8 2 0 0 0 0 14 S

0 0 2 0 5 6 3 0 0 0 0 16 SSW 0 SW 0 0 1 0 1 5 4 0 0 0 0 0 11 0 0 4 1 4 1 0 0 0 0 0 10 WSW 0 0 0 0 4 2 3 0 0 0 0 0 9 W 0 WNW 0 0 0 0 0 6 3 0 0 0 0 0 9 NW 0 0 0 0 1 0 2 2 0 0 0 0 5 NNW 0 0 0 1 0 0 0 0 0 0 0 0 1 0 1 7 9 27 30 8 0 0 0 0 82 TOTALS 0 NUMBER OF VALID HOURS 82 NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 21840 NUMBER OF INVALID HOURS 1

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00033124-00063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ g -1.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 1 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 2 0 0 0 0 0 0 2 SSE 0 0 0 0 1 2 3 0 0 0 0 0 6 S 0 0 0 1 1 5 8 1 2 0 0 0 18 SSW 0 0 0 1 3 7 7 0 0 0 0 0 18 SW 0 0 1 2 2 2 4 0 0 0 0 0 11 WSW 0 0 1 0 2 2 1 0 0 0 0 0 6 W 0 0 0 4 1 2 1 2 0 0 0 0 10 WNW 1 0 0 0 2 3 2 4 0 0 0 0 12 NW 0 0 0 0 0 3 4 1 0 0 0 0 8 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 1 0 2 8 12 29 30 8 2 0 0 0 92 NUMBER OF VALID HOURS 92 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2184 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 4 11 7 6 1 0 0 0 0 0 29 NNE 0 0 2 7 10 9 2 0 0 0 0 0 30 NE 0 1 1 12 7 5 1 0 0 0 0 0 27 ENE 0 2 1 3 4 3 0 0 0 0 0 0 13 E 0 3 0 4 5 9 4 0 0 0 0 0 25 ESE 0 0 1 6 6 24 15 0 0 0 0 0 52 SE 0 0 1 5 17 33 37 6 1 0 0 0 100 SSE 0 2 3 11 24 53 39 9 8 0 0 0 149 S 0 1 4 9 14 30 33 7 1 1 0 0 100 SSW 0 2 7 15 12 15 13 3 2 0 0 0 69 SW 1 1 4 10 6 10 3 3 2 0 0 0 40 WSW 0 2 4 7 7 4 3 1 0 0 0 0 28 W 1 2 4 10 5 8 8 1 1 0 0 0 40 WNW 1 1 1 10 7 11 5 0 0 0 0 0 36 NW 0 1 0 7 14 15 21 2 1 0 0 0 61 NNW 0 2 5 6 4 3 8 0 1 0 0 0 29 TOTALS 3 20 42 133 149 238 193 32 17 1 0 0 828 NUMBER OF VALID HOURS 828 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00033124-00063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0. 5 < DT/DZ 5 -1.5 °C/100 METERS) 1.1 1.6 2.1 3.1 5.1- 7.1- 1i0.1 . 13.1-13.1 >1R TOTAL WIND .22 .51 .76 18.0 TOTAL 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 >18 DIR .50 A^ .75 0 1 8 7 3 0 0 0 0 22 N 0 2 1 0 76 15 26 23 5 0 0 0 0 NNE 0 02 5 0 20 0 7 4 1 0 0 0 0 0 NE 0 8 0 12 5 2 0 0 0 0 0 0 ENE 0 2 3 0 13 4 4 4 1 0 0 0 0 E 0 0 0 0 8 3 1 3 0 0 0 0 0 ESE 0 1 0 0 14 2 2 3 4 0 0 0 0 SE 0 0 3 0 15 2 2 7 1 2 0 0 SSE 0 1 0 0 6 0 0 4 0 0 0 0 0 2 0 0 0 4 S

0 1 0 0 0 0 0 0 0 2 1 0 3 SSW 0 1 0 0 0 1 0 0 1 0 0 SW 0 0 0 0 0 0 1 0 0 0 0 1 0 WSW 0 1 0 0 0 0 3 1 0 0 1 0 0 W 0 0 0 0 0 4 0 0 1 0 2 1 0 WNW 0 4 0 0 0 0 5 0 0 0 0 1 0 NW 0 1 0 0 0 0 0 9 2 0 2 2 NNW 54 25 3 0 0 0 0 215 1 22 43 53 IV ItLJ 215 NUMBER OF CALMS 0 NUMBER OF VALID HOURS 1 TOTAL HOURS FOR THE PERIOD 2184 NUMBER OF INVALID HOURS PASQUILL F MODERATELY STABLE (1.5

• DT/DZ g -0.5 'C/100 METERS)

.22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 0 2 4 2 1 0 0 0 0 0 9 N 0 0 2 13 28 30 7 0 0 0 0 0 82 NNE 0 2 6 7 1 7 0 0 0 0 0 0 22 NE 1 0 2 5 0 0 0 0 0 0 0 0 7 ENE 0 0 0 1 1 0 0 0 0 0 0 0 3 E 0 1 0 0 0 1 0 0 0 0 0 0 1 ESE 0 0 0 1 0 0 0 0 0 0 0 2 SE 0 0 1 0 0 1 0 0 0 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 0 1 0 0 0 0 1 SSW 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 1 1 0 0 0 0 0 0 2 W 0 0 0 0 2 2 2 0 0 0 0 0 6 WNW 0 0 0 0 0 1 0 0 0 0 0 0 1 NW 0 0 0 1 1 0 0 0 0 0 0 2 NNW 0 0 0 3 11 29 39 45 10 1 0 0 0 0 139 TOTALS 1 139 NUMBER OF CALMS 0 NUMBER OF VALID HOURS TOTAL HOURS FOR THE PERIOD 2184 1

NUMBER OF INVALID HOURS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00033124-00063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STAEBLE (DT/DZ > 4.0 -C/100 METERS) 1 WIND .22 .51 .76- 1.1 STAB2 .6- 2.1- 3.1- 5.1- 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 1 2 0 1 0 0 0 0 0 4 NNE 0 0 0 0 8 52 37 1 0 0 0 0 98 NE 0 0 1 2 2 4 0 0 0 0 0 0 9 ENE 0 0 0 1 2 0 0 0 0 0 0 0 3 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 1 0 1 0 0 0 0 0 0 0 2 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 1 0 0 0 0 0 0 1 S 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 1 0 1 0 0 0 0 0 2 W 0 0 0 0 1 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 1 0 0 0 0 0 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTALS 0 0 2 4 17 57 41 1 0 0 0 0 122 NUMBER OF VALID HOURS 122 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS I TOTAL HOURS FOR THE PERIOD 2184 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 2 5 15 21 15 6 0 0 0 0 0 64 NNE 0 4 9 35 72 115 51 1 0 0 0 0 287 NE 1 1 16 28 14 18 1 0 0 0 0 0 79 ENE 0 4 6 14 8 3 0 0 0 0 0 0 35 E 0 4 0 9 10 13 5 0 0 0 0 0 41 ESE 0 1 2 9 8 28 15 0 0 0 0 0 63 SE 0 0 5 7 20 38 42 6 1 0 0 0 119 SSE 0 3 4 14 27 67 48 14 8 0 0 0 185 S 0 3 5 10 24 47 80 17 3 1 0 0 190 SSW 0 2 9 22 20 44 52 11 2 0 0 0 162 SW 1 2 7 15 21 52 52 4 2 0 0 0 156 WSW 0 2 7 14 35 82 73 1 0 0 0 0 214 W 1 3 4 14 29 100 138 4 1 0 0 0 294 WNW 2 1 1 11 13 45 79 11 1 0 0 0 164 NW 0 1 0 7 15 20 35 8 1 0 0 0 87 NNW 1 4 5 10 7 5 10 0 1 0 0 0 43 TOTALS 6 37 85 234 344 692 687 77 20 1 0 0 2183 NUMBER OF VALID HOURS 2183 NUMBER OF CALMS NUMBER OF INVALID HOURS 0

1 TOTAL HOURS FOR THE PERIOD 2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00063024-00093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ < -1.9 °C/100 METERS)

.76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND .22- .51-

.50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 DIR 0 1 1 0 0 0 0 0 0 0 2 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 1 0 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 1 0 0 0 0 0 0 1 E 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 1 0 0 0 0 0 0 0 0 1 SE 0 0 0 0 1 4 7 1 1 0 0 0 14 SSE 0 0 0 1 5 16 40 6 0 0 0 0 68 S 0 0 0 3 3 21 36 0 0 0 0 0 63 SSW 0 0 0 5 10 35 34 0 0 0 0 0 84 SW 0 0 0 5 26 82 59 0 0 0 0 0 172 WSW 0 0 0 4 9 105 117 0 0 0 0 0 235 W 0 0 0 0 4 27 82 3 0 0 0 0 116 WNW 0 0 0 1 0 0 12 0 0 0 0 0 13 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 21 60 291 387 10 1 0 0 0 770 TOTALS 0 0 770 NUMBER OF CALMS 0 NUMBER OF VALID HOURS 2208 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ : -1.7 -C/100 METERS)

.76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND .22- .51-DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 0 0 0 0 0 0 0 0 0 0 0 N 0 0 0 0 1 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 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 1 1 5 2 0 0 0 0 9 SSE 0 0 0 0 1 5 2 0 0 0 0 0 8 S 0 0 0 0 1 0 2 5 2 0 0 0 0 10 SSW 0 0 0 0 5 2 0 0 0 0 0 7 SW 0 0 0 1 0 5 1 0 0 0 0 0 7 WSW 0 0 0 3 5 5 0 0 0 0 0 0 13 W 0 0 0 0 1 2 0 0 0 0 0 3 WNW 0 0 0 0 0 0 0 0 4 1 0 0 0 0 5 NW 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 5 9 25 21 5 0 0 0 0 65 TOTALS 0 0 NUMBER OF VALID HOURS 65 NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 22080 0

NUMBER OF INVALID HOURS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00063024-00093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ .-1.5 °C/100 METERS)

WIND .22 .51 .76 1.1 1.6 2.1 5.1- 7.1 10.1-3.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 *.V 0 18.0 13 N 0 0 0 0 0 1 0 0 0 0 0 1 0

NNE 0 0 0 0 0 2 0 0 0 0 0 2 NE 0 0 0 0 0 0 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 1 0 0 0 0 0 0 0 0 1 SE 0 0 0 0 0 0 0 1 0 0 0 0 1 SSE 0 0 0 1 1 2 2 1 0 0 0 7 0 0 0 S 0 2 1 3 5 0 1 0 0 12 0

SSW 0 1 1 0 2 4 8 1 0 0 0 17 SW 0 0 0 0 1 2 6 3 0 0 0 0 12 WSW 0 2 0 0 1 2 4 5 0 0 0 0 14 W 0 0 0 0 2 9 5 1 0 0 0 0 17 WNW 0 0 0 0 0 2 9 0 0 0 0 0 11 NW 0 0 1 0 1 0 0 6 1 1 0 0 10 NNW 0 0 0 0 0 0 TOTALS 0 2 2 10 19 370 311 4 2 0 0 0 0 0 107 NUMBER OF VALID HOURS 107 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 U 7 / 2 0 0 0 0 0 40 NNE 0 3 4 16 20 24 5 0 0 0 0 0 72 NE 0 0 1 2 8 3 0 0 0 0 0 0 14 ENE 1 0 0 3 4 2 0 0 0 0 0 0 10 E 0 1 1 2 3 4 0 0 0 0 0 0 11 ESE 0 0 2 4 1 10 2 0 0 0 0 0 19 SE 0 2 2 5 9 22 18 2 0 0 0 0 60 SSE 0 0 2 14 15 40 31 6 1 0 0 0 109 S 0 3 9 13 13 27 29 6 0 0 0 0 100 SSW 0 1 2 15 12 17 11 3 0 0 0 0 61 SW 0 1 6 11 14 9 7 4 0 0 0 0 52 WSW 0 1 5 9 7 5 2 0 0 0 0 0 29 W 0 3 4 22 12 9 5 0 0 0 0 0 55 WNW 0 0 4 12 16 17 10 0 0 0 0 0 59 NW 0 0 3 9 7 20 15 1 0 0 0 0 55 NNW 0 1 5 7 10 6 3 0 0 0 1 55 163 158 0 0 32 TOTALS 16 222 1 40 22 1 0 0 0 T778 1 0 0 T -77 NUMBER OF VALID HOURS 778 NUMBER OF CALMS NUMBER OF INVALID HOURS 0 0 TOTAL HOURS FOR THE PERIOD 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00063024-00093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE (-0. 5 < DT/DZ -1.5 -C/100 METERS)

>ig TflTAI 1.1 1.6 2.1 3.1 5.1- 7.1- 10.1 13.1-13.1 WIND .22 .51 .76 18.0 13.0 7.0 10.0

>18

.75 1.0 1.5 2.0 3.0 5.0 DIR .50 0 1 4 5 7 6 0 0 0 0 0 23 23 N 0 0 0 105 7 32 35 26 3 0 0 0 NNE 0 2 0 0 26 4 4 12 3 3 0 0 0 0 NE 0 0 0 6 1 2 3 0 0 0 0 0 0 ENE 0 0 0 10 4 2 2 1 0 0 0 0 0 E 1 0 0 7 2 3 1 1 0 0 0 0 ESE 0 0 0 0 17 0 1 2 0 4 4 6 0 0 0 SE 4 1 1 0 0 0 15 0 0 2 2 5 0 SSE 0 0 0 0 0 6 0 0 0 2 2 2 0 S 1 1 0 0 0 0 6 1 1 1 0 1 0 SSW 1 0 0 0 0 0 0 1 0 0 0 0 0 SW 1 0 0 0 2 0 0 1 0 0 0 0 0 WSW 0 0 0 0 0 0 3 0 0 0 0 2 W 0 0 0 0 0 0 6 0 0 0 3 0 3 WNW 4 0 0 0 0 0 7 NW 0 1 0 0 0 2 1 0 2 1 0 2 0 0 0 0 0 0 6 NNW 3 15 29 65 60 58 15 1 0 0 0 0 246 TOTALS 246 NUMBER OF CALMS 0 NUMBER OF VALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 NUMBER OF INVALID HOURS PASQUILL F MODERATELY STABLE (1.5

• DT/DZ g -0.5 'C/100 METERS)

.22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 0 0 1 0 1 0 0 0 0 0 0 0 2 N

0 0 7 9 27 42 8 0 0 0 0 0 93 NNE 0 0 0 8 0 0 0 0 0 0 0 0 8 NE 0 3 1 1 0 0 0 0 0 0 0 0 5 ENE 0 0 1 0 1 0 0 0 0 0 0 0 2 E

0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 1 0 1 0 0 0 0 0 0 0 2 SE 0 1 0 0 0 0 2 1 0 0 0 0 0 4 SSE 0 1 0 0 0 0 0 0 0 0 0 1 S 0 0 0 0 1 1 0 1 0 0 0 0 0 3 SSW 0 0 0 1 1 0 0 0 0 0 0 0 2 SW 0 0 0 2 0 0 0 0 0 0 0 2 WSW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 W

0 0 0 0 1 0 0 0 0 0 0 0 1 WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 NW 0 0 1 0 1 0 1 0 0 0 0 0 3 NNW 1 3 13 20 36 44 11 0 0 0 0 0 128 TOTALS 128 NUMBER OF CALMS 0 NUMBER OF VALID HOURS TOTAL HOURS FOR THE PERIOD 2208 NUMBER OF INVALID HOURS 0 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00063024-00093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS)

° WIND .22 .51 .76 1.1 1.6 2.1 3.1 5.1 7.1 I0.I 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 1 2 1 1 0 0 0 0 0 5 NNE 0 0 0 2 2 52 35 1 0 0 0 0 92 NE 0 0 1 2 2 3 0 0 0 0 0 0 8 ENE 0 0 0 0 1 0 0 0 0 0 0 0 1 E 0 0 0 1 0 0 0 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 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 1 1 0 1 0 0 0 0 0 0 3 SSW 0 0 0 0 0 0 2 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 0 0 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 1 0 0 0 0 0 1 NNW 0 0 0 0 1 0 0 0 0 0 TOTALS 0 0 2 7 7 57 40 1 0 0 0 00 0 0 114*1 NUMBER OF VALID HOURS 114 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 1 10 26 18 15 3 0 0 0 0 0 73 NNE 0 5 18 59 85 147 51 1 0 0 0 0 366 NE 0 4 6 24 15 10 0 0 0 0 0 0 59 ENE 1 4 3 7 5 2 0 0 0 0 0 0 22 E 1 5 4 5 5 5 0 0 0 0 0 0 25 ESE 0 0 4 8 2 11 2 0 0 0 0 0 27 SE 0 3 5 6 14 26 24 03 0 0 0 0 81 SSE 1 0 4 17 22 54 47 11 2 0 0 0 158 S 0 3 11 19 22 54 76 12 1 0 0 0 198 SSW 1 3 4 20 19 45 64 6 0 0 0 0 162 SW 0 1 6 18 27 56 46 4 0 0 0 0 158 WSW 0 1 7 17 38 96 67 0 0 0 0 0 226 W 0 3 4 31 36 126 123 0 0 0 0 0 323 WNW 0 0 4 15 23 57 94 3 0 0 0 0 196 NW 0 2 3 11 7 22 42 3 1 0 0 0 91 NNW 1 1 8 8 11 8 6 0 0 0 0 0 43 TOTALS 5 36 101 291 349 734 645 43 4 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 (2000)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00093024-00123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL A EXTREMELY UNSTABLE (DT/DZ < 1.9 °C/100 METERS)

.51 .76 1.6 1.1 EXTREMELY 2.1- 3 .1 5.1 7.1 10.1 13.1 >18 TOTAL WIND .22 UNSTABLE 7.0 10.0 13.0 18.0

.50 .75 1.0 1.5 2.0 3.0 5 .0 DIR 0 0 0 0 00 0 0 0 0 0 N 0 0 1 01 0 0 0 2 0 0 0 0 0 NNE 0 0 1 0 0 0 1 0 0 0 0 0 0 NE 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 1 0 0 3 0 0 2 0 0 SE 0 0 0 0 1 0 0 10 2 5 0 SSE 0 0 0 0 1 0 0 0 18 0 4 12 0 S 0 0 0 0 0 0 11 0 2 7 2 0 0 SSW 0 0 0 0 0 0 22 3 7 8 4 0 0 SW 0 0 0 0 0 0 59 0 5 8 33 13 0 0 WSW 0 0 0 0 0 139 1 0 9 64 61 4 0 W 0 0 0 0 0 74 0 1 3 20 45 5 0 WNW 0 0 0 0 0 2 0 0 0 0 1 1 0 NW 0 0 0 0 0 0 0 n n n n 0 0 0 0 1 9 31 138 147 13 2 0 0 0 341 TOTALS 0 341 NUMBER OF CALMS 0 NUMBER OF VALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 NUMBER OF INVALID HOURS PASQUILL B MODERATELY UNSTABLE (-1.9 < DT/DZ - -1.7 °C/100 METERS)

.51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND .22-

.50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 DIR 0 0 0 0 0 0 0 0 0 0 0 0 N 0 0 0 0 0 0 0 0 1 0 0 0 2 NNE 1 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 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 1 0 1 0 0 0 2 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 1 0 3 2 0 0 0 0 0 6 S 0 0 0 1 0 1 0 0 0 0 0 2 SSW 0 0 0 0 0 0 1 1 0 0 0 0 0 2 SW 0 0 0 0 0 4 1 0 0 0 0 0 5 WSW 0 0 0 0 6 4 1 0 0 0 0 0 11 W 0 0 0 0 0 4 5 1 0 0 0 0 10 WNW 0 0 0 0 1 1 3 0 0 0 0 0 5 NW 0 0 0 0 0 0 0 0 0 0 0 0 0 NNW 0 0 0 1 8 17 15 1 2 0 0 0 45 TOTALS 1 45 NUMBER OF CALMS 22080 NUMBER OF VALID HOURS TOTAL HOURS FOR THE PERIOD 0

NUMBER OF INVALID HOURS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00093024-00123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (-1.7 < DT/DZ * -1.5 'C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 0 0 0 0 0 0 1 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 1 1 0 0 0 0 0 2 SSE 0 0 0 0 0 1 2 2 3 0 0 0 8 S 0 0 0 1 0 1 2 0 0 0 0 0 4 SSW 0 0 0 1 2 2 2 0 0 0 0 0 7 SW 0 0 0 1 1 3 1 0 0 0 0 0 6 WSW 0 0 0 3 5 1 1 0 0 0 0 0 10 W 0 0 0 0 2 9 5 1 0 0 0 0 17 WNW 0 0 0 0 3 2 3 1 1 0 0 0 10 NW 0 0 0 0 0 3 2 1 0 0 0 0 6 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 1 0 0 6 13 23 19 5 4 0 0 0 71 NUMBER OF VALID HOURS 71 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 PASQUILL D NEUTRAL (-1.5 < DT/DZ * -0.5 °C/100 METERS)

WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N A-v) U 7 0 0 0 0 0 29 NNE 0 0 0 7 7 11 3 0 1 0 0 0 29 NE 1 0 2 2 2 3 2 0 0 0 0 0 12 ENE 0 0 0 1 1 0 3 1 0 0 0 0 6 E 0 0 0 1 2 2 0 0 0 0 0 0 5 ESE 0 0 1 2 0 5 12 1 0 0 0 0 21 SE 0 0 1 0 3 14 36 5 0 0 0 0 59 SSE 0 1 1 5 4 13 17 5 0 0 0 47 S 0 0 0 6 3 10 14 5 0 0 0 39 SSW 0 0 2 5 8 7 13 2 0 0 0 38 1 1 SW 0 3 8 7 7 9 2 0 0 0 38 1

WSW 0 0 7 8 2 4 2 0 0 0 24 W 0 1 2 3 6 6 15 4 4 0 0 0 41 WNW 0 0 0 2 3 7 16 14 4 0 0 0 46 NW 0 1 0 5 2 3 18 15 3 0 0 0 0 47 NNW 0 0 2 2 6 7 9 1 0 0 0 27 TOTALS 3 8 24 76 0 0 0 70 139 149 34 508 5 0 0 T

NUMBER OF VALID HOURS 508 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00093024-00123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE 1.6 (-0. 5 < DT/DZ -1.5 'C/100 METERS) 1.1 2.1 3.1 5.1- 1.1- 10.1 13.1 >18 TO3AL WIND .2Z .51 .76 5.1 7.1 13.0 18.0 1.5 2.0 3.0 5.0 7.0 10.0 DIR .50 .75 1.0 0 13 13 3 0 0 0 0 38 0 0 2 7 133 N 49 19 2 0 0 0 1 3 5 15 39 0 52 NNE 4 4 3 1 0 0 0 4 7 22 7 0 18 NE 0 2 1 1 0 0 0 3 5 6 0 ENE 0 0 0 0 0 25 1 7 2 4 10 1 0 E 0 0 0 0 0 23 1 3 5 1 9 3 0 ESE 1 0 0 0 0 27 1 1 2 5 9 9 0 SE 0 0 0 0 0 12 0 2 2 4 3 1 0 SSE 0 0 0 0 0 9 1 0 4 2 2 0 0 S 0 0 0 0 4 1 1 1 1 0 0 0 SSW 0 0 0 0 0 8 0 2 2 2 0 2 0 0 SW 0 0 0 0 0 4 1 0 0 1 0 2 0 WSW 0 5 0 0 0 23 0 0 1 9 6 1 0 W 1 4 0 0 0 41 1 1 5 6 13 11 0 WNW 0 0 0 0 0 29 0 4 3 4 8 9 0 NW 1 0 0 0 0 0 25 1 1 7 4 5 7 NNW 0 2 0 0 0 471 a., 1 --z 7A 15 TOTALS 4 1,+ .3 0 o? v

• 471 NUMBER OF CALMS 0 NUMBER OF VALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 NUMBER OF INVALID HOURS PASQUILL F MODERATELY STABLE (1.5

• DT/DZ * -0.5 °C/100 METERS)

.76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL WIND .22- .51-

.50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 DIR 2 5 7 6 0 0 0 0 0 22 N 0 0 2 15 41 111 42 2 0 0 0 0 215 NNE 1 2 1 19 25 20 7 0 0 0 0 0 74 NE 0 1 2 4 3 2 0 0 0 0 0 0 13 ENE 0 1 3 4 1 0 1 0 0 0 0 0 8 E 0 0 2 1 3 0 0 0 0 0 0 0 5 ESE 0 0 1 2 5 0 1 0 0 0 0 0 10 SE 0 0 2 1 0 1 0 0 0 0 0 0 3 SSE 0 0 1 0 0 0 0 0 0 0 0 1 S 0 0 0 1 1 0 0 0 0 0 0 0 0 1 SSW 0 0 0 0 0 0 0 0 0 0 0 2 SW 0 0 0 2 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 1 1 1 0 0 0 0 0 4 W 0 1 0 0 2 3 1 0 0 0 0 0 8 WNW 1 0 1 0 1 2 1 0 0 0 0 0 6 NW 0 1 1 0 1 2 0 0 0 0 0 4 NNW 0 0 0 1 53 87 148 62 2 0 0 0 0 376 TOTALS 2 6 16 NUMBER OF VALID HOURS 376 NUMBER OF CALMS TOTAL HOURS FOR THE PERIOD 22080 0

NUMBER OF INVALID HOURS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2000)

METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 00093024-00123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS)

WIND .22 .51 .76- 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 0 0 1 7 6 0 0 0 0 0 14 NNE 4 0 0 3 7 115 179 12 0 0 0 0 320 NE 0 0 0 5 8 10 6 0 0 0 0 0 29 ENE 1 0 0 1 3 2 0 0 0 0 0 8 E 0 0 0 0 0 0 11 0 0 0 0 0 1 ESE 0 0 1 0 0 1 0 0 0 0 0 0 2 SE 0 0 0 0 2 1 0 0 0 0 0 0 3 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 S 0 0 0 1 0 0 0 0 0 0 0 0 1 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 1 0 0 0 0 0 1 0 0 WSW 0 0 0 1 0 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 0 0 0 0 0 0 WNW 0 0 0 1 2 4 1 0 0 0 0 0 8 NW 0 0 0 0 1 1 2 0 0 0 0 0 0 4 NNW 0 0 0 1 1 2 n A 0 0 TOTALS 5 0 1 12 26 142 198 12 0 20 0 00 0 396 NUMBER OF VALID HOURS 396 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL WIND .22- .51- .76- 1.1- 1.6- 2.1- 3.1- 5.1- 7.1- 10.1- 13.1- >18 TOTAL DIR .50 .75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N 0 0 7 18 27 34 17 0 0 0 0 0 103 NNE 8 5 6 40 94 286 244 17 2 0 0 0 702 NE 1 5 11 48 42 37 20 3 1 0 0 0 168 ENE 1 1 6 11 13 4 6 2 1 0 0 0 45 E 0 1 9 7 7 12 3 0 0 0 0 0 39 ESE 1 1 6 8 4 15 15 1 0 0 0 0 51 SE 0 1 4 4 15 25 50 5 2 0 0 0 106 SSE 0 1 4 8 9 20 25 8 5 0 0 0 80 S 0 1 0 14 6 20 30 6 1 0 0 0 78 SSW 0 0 3 8 14 17 18 2 1 0 0 0 63 SW 0 3 3 16 18 19 17 2 1 0 0 0 79 WSW 0 1 1 16 22 40 21 2 0 0 0 0 103 W 2 3 4 7 33 99 73 14 0 0 0 0 235 WNW 1 1 4 10 23 62 80 15 1 0 0 0 197 NW 2 1 10 5 10 33 33 5 0 0 0 0 99 NNW 0 3 3 14 12 16 12 0 0 0 0 0 60 TOTALS 16 28 81 234 349 739 664 82 15 0 0 0 2208 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS NUMBER OF INVALID HOURS 0

0 TOTAL HOURS FOR THE PERIOD 2208