ML22122A040

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(Songs), Units 1, 2 and 3 - Annual Radioactive Effluent Release Report - 2021
ML22122A040
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 04/28/2022
From: Bates A
Southern California Edison Co
To:
Office of Nuclear Material Safety and Safeguards
References
Download: ML22122A040 (41)


Text

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An EDISON INTERNA110NALr,; Company ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 April 28, 2022

Subject:

Annual Radioactive Effluent Release Report - 2021 Al Bates Manager Regulatory Affairs 10 CFR 50.36(a)

San Onofre Nuclear Generating Station (SONGS), Units 1, 2 and 3 Docket Nos. 50-206, 50-361 and 50-362 In accordance with 10 CFR 50.36(a), Southern California Edison (SCE) is submitting the Annual Radioactive Effluent Release Report - 2021 (ARERR) for SONGS, Units 1, 2, and 3 (Enclosure 1 ). The period of the report is January 1, 2021 through December 31, 2021. A separate ARERR was submitted for the SONGS Independent Spent Fuel Storage Installation (ISFSI) on February 24, 2022 which stated that the ISFSI had no effluent releases.

The net result from the analysis of these effluent releases indicates that SONGS has met all the requirements of the applicable regulations that ensure adequate protection of the health of members of the public.

There are no commitments in this letter or the enclosure.

If you have any questions, please contact me at (949) 368-7024.

Enclosures:

1) San Onofre Nuclear Generation Station, Annual Radioactive Effluent Release Report - 2021 cc: S. A. Morris, Regional Administrator, NRG Region IV A. M. Snyder, NRG Project Manager, SONGS Units 1, 2 and 3 R. K. Lupo, California Department of Public Health P. 0. Box 128 San Clemente, CA 92672 San Onofre Nuclear Generation Station Annual Radioactive Effluent Release Report 2021 January - December

SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2021 January - December

PREFACE San Onofre Nuclear Generating Station is located next to San Onofre State Beach, adjoining Camp Pendleton Marine Corps Base, in San Diego County, 64 miles south of Los Angeles, California. There were three operating pressurized water reactors.

Southern California Edison notified the Nuclear Regulatory Commission (NRC) on June 12, 2013, that it had permanently ceased operation of Units 2 and 3 on June 7, 2013. The notification, called a Certification of Permanent Cessation of Power Operations, sets the stage for SCE to begin preparations for decommissioning. By August 7, 2020, all fuel was transferred to the Independent Spent Fuel Storage Installation (ISFSI).

Unit 1 was supplied by Westinghouse Electric Company and began commercial operation on January 1, 1968. The unit was permanently shut down on November 30, 1992. By August 31, 2004, all fuel was transferred to the Independent Spent Fuel Storage Installation {ISFSI). By November 29, 2006, remaining monitored effluent pathways were permanently removed from service. Currently, Unit 1 effluent pathway is routed to Unit 2. Unit 1 is owned by Southern California Edison (80%) and San Diego Gas and Electric (20%).

Unit 2 and Unit 3 were supplied by Combustion Engineering, Inc., with turbine generators supplied by G.E.C.

Turbine Generators, Ltd., of England. The units began commercial operation in August 1983, and April 1984, respectively. The twin units are owned by Southern California Edison (78.21%), San Diego Gas and Electric (20%),

and the City of Riverside (1.79%).

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

-i-

TABLE OF CONTENTS SECTION A-INTRODUCTION.................................................................................................................................... 1 SECTION B - GASEOUS EFFLUENTS........................................................................................................................ 2 SECTION C-LIQUID EFFLUENTS.............................................................................................................................. 8 SECTION D-PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM....................................... 14 SECTION E-RADWASTE SHIPMENTS.................................................................................................................... 15 SECTION F -APPLICABLE LIMITS........................................................................................................................... 18 SECTION G-ESTIMATION OF ERROR.................................................................................................................... 22 SECTION H -10 CFR 50 APPENDIX I REQUIREMENTS......................................................................................... 23 SECTION I-CHANGES TO OFFSITE DOSE CALCULATION MANUAL.................................................................. 27 SECTION J-CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS....................................................... 28 SECTION K-MISCELLANEOUS............................................................................................................................... 29 Abnormal Release......................................................................................................................................... 29 Effluent Monitoring Instruments Out of Service Greater Than 30 days.......................................................... 29 Onsite Groundwater Samples........................................................................................................................ 30 40 CFR 190 Requirements............................................................................................................................ 33 Carbon-14...................................................................................................................................................... 34 SECTION L-SONGS CONCLUSIONS...................................................................................................................... 35 METEOROLOGY......................................................................................................................................................... 36

-ii-

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION A. INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Units 1, 2 and 3. This report is prepared in the general format of USNRC Regulatory Guide 1.21, Revision 1, and includes:

1.

Quarterly Summaries of Gaseous Effluents for Continuous and Batch Modes of Release

2.

Quarterly Summaries of Liquid Effluents for Continuous and Batch Modes of Release

3.

Percent of Applicable Limits

4.

Estimated Total Error

5.

Lower Limit of Detection Concentrations

6.

Batch Summary Releases

7.

Previous Radioactive Effluent Release Report Addendum

8.

Radwaste Shipments

9.

10 CFR 50 Appendix I Requirements

10. Changes to Offsite Dose Calculation Manual These are acronyms and abbreviations used throughout the Annual Radioactive Effluent Release Report.

AL ALARA AR ARERR AREOR Ci CR DAS ECL GI-LU GPI ISFSI LCS LLD m3 MPC mrad mrem N/A NIA ODCM pCi/I SYF TLD

µCi/sec X/Q Applicable Limit As Low As Reasonably Achievable Action Request Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Curies Condition Report Data Acquisition System Effluent Concentration Limit Gastrointestinal Tract-Lower Large Intestine Groundwater Protection Initiative Independent Spent Fuel Storage Installation Licensee Controlled Specifications Lower Limit of Detection Meter cubed Maximum Permissible Concentrations One thousandth Radiation Absorbed Dose One thousandth of a Roentgen Equivalent Man Not Applicable North Industrial Area formerly known as Unit 1 Offsite Dose Calculation Manual Pico Curies per liter South Yard Facility Thermoluminescent Dosimeter Micro Curies per second Chi overQ ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents Summation of All Releases," provides a detailed listing of gaseous effluents released quarterly in four categories: fission and activation gases, iodine 131, particulates with half-lives greater than eight days, and tritium. Listed for each of the four categories are:

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

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

Table 1 B, "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 1 C, "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 for continuous mode of release. Containment purges and plant stack releases are considered to be continuous releases. Batch releases have been included because of the release of gaseous check sources and as a result of abnormal airborne radioactive releases reported in Section K.

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

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

Table 1 F "Gaseous Effluents Batch Release Summary," provides data on the time periods for Batch Releases.

Releases designated as Batch Releases included a release of noble gas check sources and two abnormal releases.

A.

B.

C.

D.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1A GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES First Second Third Fourth Unit Quarter Quarter Quarter Quarter Fission and activation gases

1.

Total release Ci N/A N/A 1.73E-04 N/A

2.

Average release rate for

µCi/sec N/A N/A 2.18E-05 N/A period

3.

Percent of applicable

%MPG N/A N/A 1.52E-07 N/A limit

4.

Percent Effluent

%EGL N/A N/A 6.53E-08 N/A Concentration Limit Iodines

1.

Total 1-131 Ci N/A N/A N/A N/A

2.

Average release rate for

µCi/sec N/A N/A N/A N/A period

3.

Percent of applicable limit

%MPG N/A N/A N/A N/A

4.

Percent Effluent

%EGL N/A N/A N/A N/A Concentration Limit Particulates

1.

Particulates with half-lives Ci 1.20E-04 4.94E-05 2.04E-06 3.09E-04

>8 days

2.

Average release rate for

µCi/sec 1.54E-05 6.28E-06 2.57E-07 3.88E-05 period

3.

Percent of applicable limit

%MPG 2.61E-05 1.52E-05 2.69E-07 1.19E-04

4.

Percent Effluent

%ECL 6.31 E-05 5.08E-05 2.69E-07 3.31E-04 Concentration Limit

5.

Gross alpha activity Ci

< LLD

< LLD

< LLD

< LLD Tritium

1.

Total release Ci 9.13E-01

< LLD

< LLD

< LLD

2.

Average release rate for

µCi/sec 1.17E-01 N/A N/A N/A period

3.

Percent of applicable limit

%MPG 1.23E-03 N/A N/A N/A

4.

Percent Effluent

%EGL 2.47E-03 N/A N/A N/A Concentration Limit Estimated Total Error,%

9.40E+00 N/A 3.00E+01 3.70E+01 2.30E+01

1.
2.
3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C GASEOUS EFFLUENTS GROUND LEVEL RELEASES BATCH MODE First Second Third Radionuclides Released Unit Quarter Quarter Quarter Fission and activation gases krypton-85 Ci N/A N/A 1.73E-04 Total for period Ci N/A N/A 1.73E-04 Iodines Total for period Ci N/A N/A N/A Particulates cerium-144 Ci N/A

<LLD N/A cesium-134 Ci N/A

<LLD N/A cesium-137 Ci N/A 6.48E-06 N/A cobalt-58 Ci N/A

<LLD N/A cobalt-60 Ci N/A

<LLD N/A manganese-54 Ci N/A

<LLD N/A nickel-63 Ci N/A 3.20E-06 N/A strontium-90 Ci N/A

<LLD N/A zinc-65 Ci N/A

<LLD N/A Total for period Ci N/A 9.68E-06 N/A LLD Lower Limit of Detection; see Table 1 D.

Fourth Quarter N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Note 1: Fission and activation gas (krypton-85) curies are a result of release of gaseous check sources from Plant Vent Stack. Requirement for sampling and analysis of Fission and activation gases removed from ODCM.

Note 2: Requirement for sampling and analysis of Iodines removed from ODCM.

Note 3: Particulate curies are a result of abnormal releases from Unit 3 Containment Building Equipment Hatch in June 2021 as reported in Section K.

1.
2.
3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C (Continued)

GASEOUS EFFLUENTS GROUND LEVEL RELEASES CONTINUOUS MODE First Second Third Radionuclides Released Unit Quarter Quarter Quarter Fission and activation gases Total for period Ci N/A N/A N/A Iodines Total for period Ci N/A N/A N/A Particulates cerium-144 Ci

<LLD

<LLD

<LLD cesium-134 Ci

<LLD

<LLD

<LLD cesium-137 Ci 1.36E-05 3.12E-06

<LLD cobalt-58 Ci

<LLD

<LLD

<LLD cobalt-60 Ci 5.79E-06 6.28E-06

<LLD manganese-54 Ci

<LLD

<LLD

<LLD nickel-63 Ci 1.00E-04 3.03E-05 2.04E-06 strontium-90 Ci

<LLD

<LLD

<LLD zinc-65 Ci

<LLD

<LLD

<LLD Total for period Ci 1.20E-04 3.97E-05 2.04E-06 LLD Lower Limit of Detection; see Table 1 D.

Note 1: Requirement for sampling and analysis of Fission and activation gases removed from ODCM.

Note 2: Requirement for sampling and analysis of Iodines removed from ODCM. Fourth Quarter N/A N/A

<LLD

<LLD 1.59E-04

<LLD 1.97E-05

<LLD 1.30E-04

<LLD

<LLD 3.09E-04

1.
2.
3.
4.
5.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1D GASEOUS EFFLUENTS LOWER LIMIT OF DETECTION Radionuclides Continuous Mode LLD (µCi/cc)

Fission and activation gases N/A Iodines N/A Particulates cerium-144 4.40E-13 cesium-134 2.60E-13 cesium-137 2.20E-13 cobalt-58 2.40E-13 cobalt-60 3.60E-13 manganese-54 2.30E-13 strontium-90 1.00E-11 zinc-65 5.90E-13 Tritium 7.20E-08 Alpha 1.00E-11 Batch Mode LLD (µCi/cc)

N/A N/A 2.90E-12 1.?0E-12 N/A 1.50E-12 2.40E-12 1.50E-12 1.00E-11 4.00E-12 N/A N/A Note 1: Requirement for sampling and analysis of Fission and activation gases removed from ODCM.

Note 2: Requirement for sampling and analysis of Iodines removed from ODCM.

A.

B.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1E GASEOUS EFFLUENTS RADIATION DOSES AT THE SITE BOUNDARY First Second Third Radionuclides Released Unit Quarter Quarter Quarter Noble Gas

1.

Gamma Air Dose mrad 0.00E+00 0.00E+00 1.98E-09

2.

Percent of Applicable Limit 0.00E+00 0.00E+00 1.98E-08

3.

Beta Air Dose mrad 0.00E+00 0.00E+00 2.24E-07

4.

Percent Applicable Limit 0.00E+00 0.00E+00 1.12E-06 Tritium, Iodine, Particulates (at the nearest receptor)

1.

Organ Dose mrem 5.13E-04 1.82E-04 7.38E-06

2.

Percent of Applicable Limit 3.42E-03 1.22E-03 4.92E-05 Note:

Calculations performed in accordance with the ODCM utilizing x/Q and D/Q based on historical meteorological data.

TABLE 1F GASEOUS EFFLUENTS BATCH RELEASE

SUMMARY

12-month period All Releases

1.

Number of batch releases:

3 releases

2.

Total time period for batch releases:

965 minutes

3.

Maximum time period for a batch release:

480 minutes

4.

Average time period for a batch release:

322 minutes

5.

Minimum time period for a batch release:

5 minutes Fourth Quarter 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.83E-04 6.55E-03 Note 1: Release of gaseous check sources from Plant Vent Stack and two abnormal releases from Unit 3 Containment Building Equipment Hatch. Abnormal releases reported in Section K.

Note 2: The two abnormal releases were assumed to occur over 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and the gaseous check sources were assumed to be released over a 5-minute period (for conservatism).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are:

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

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

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

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

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

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

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

A.

B.

C.

D.

E.

F.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE2A LIQUID EFFLUENTS SUMMATION OF ALL RELEASES First Second Third Fourth Unit Quarter Quarter Quarter Quarter Fission and activation products Total release (not

1.

including tritium, gases, Ci

<LLD

<LLD

<LLD

<LLD alpha)

Average diluted

2.

concentration during

µCi/ml N/A N/A N/A N/A period

3.

Percent of applicable

%MPC N/A N/A N/A N/A limit

4.

Percent Effluent

%ECL N/A N/A N/A N/A Concentration Limit Tritium

1.

Total release Ci

<LLD

<LLD

<LLD

<LLD Average diluted

2.

concentration during

µCi/ml N/A N/A N/A N/A period

3.

Percent of applicable

%MPC N/A N/A N/A N/A limit

4.

Percent Effluent

%ECL N/A N/A N/A N/A Concentration Limit Dissolved and entrained gases

1.

Total release Ci N/A N/A N/A N/A Average diluted

2.

concentration during

µCi/ml N/A N/A N/A N/A period

3.

Percent of applicable

%MPG N/A N/A N/A N/A limit

4.

Percent Effluent

%ECL N/A N/A N/A N/A Concentration Limit Gross alpha activity

1.

Total release Ci

<LLD

<LLD

<LLD

<LLD Volume of waste released.

(batch & continuous, prior to liters 3.88E+06 1.75E+06 5.48E+05 1.93E+06 dilution)

Volume of dilution water liters 7.54E+09 8.14E+09 8.00E+09 5.01E+09 used during period Estimated Total Error,%

2.20E01 2.30E01 N/A 3.20E01 5.00E+00 5.00E+00

1.
2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2B LIQUID EFFLUENTS CONTINUOUS MODE First Second Third Radionuclides Released Unit Quarter Quarter Quarter Fission and activation products cerium-144 Ci

<LLD

<LLD

<LLD cesium-134 Ci

<LLD

<LLD

<LLD cesium-137 Ci

<LLD

<LLD

<LLD cobalt-58 Ci

<LLD

<LLD

<LLD cobalt-60 Ci

<LLD

<LLD

<LLD iron-55 Ci

<LLD

<LLD

<LLD manganese-54 Ci

<LLD

<LLD

<LLD nickel-63 Ci

<LLD

<LLD

<LLD strontium-90 Ci

<LLD

<LLD

<LLD zinc-65 Ci

<LLD

<LLD

<LLD Total for period Ci

<LLD

<LLD

<LLD Dissolved and entrained gases Total for period Ci N/A N/A N/A LLD Lower Limit of Detection; see Table 2C.

Fourth Quarter

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD N/A Note:

Requirement for sampling and analysis of Dissolved and entrained gases removed from ODCM. Dissolved and entrained gases shall be reported if detected.

1.
2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2B (Continued)

LIQUID EFFLUENTS BATCH MODE First Second Third Radionuclides Released Unit Quarter Quarter Quarter Fission and activation products cerium-144 Ci N/A N/A N/A cesium-134 Ci N/A N/A N/A cesium-137 Ci N/A N/A N/A cobalt-58 Ci N/A N/A N/A cobalt-60 Ci N/A N/A N/A iron-55 Ci N/A N/A N/A manganese-54 Ci N/A N/A N/A nickel-63 Ci N/A N/A N/A strontium-90 Ci N/A N/A N/A zinc-65 Ci N/A N/A N/A Total for period Ci N/A N/A N/A Dissolved and entrained gases Total for period Ci N/A N/A N/A Note:

Batch liquid releases were not performed at SONGS during 2021. Fourth Quarter N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

1.
2.
3.
4.

A.

B.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2C LIQUID EFFLUENTS LOWER LIMIT OF DETECTION Continuous Mode Batch Mode Radionuclides LLD (µCi/cc)

LLD (µCi/cc)

Fission and activation products cerium-144 2.00E-07 N/A cesium-134 9.20E-08 N/A cesium-137 7.90E-08 N/A cobalt-58 8.40E-08 N/A cobalt-60 1.20E-07 N/A iron-55 1.00E-06 N/A manganese-54 8.20E-08 N/A nickel-63 1.00E-06 N/A strontium-90 5.00E-08 N/A zinc-65 2.00E-07 N/A Dissolved and entrained gases Tritium 1.00E-05 N/A Gross Alpha 1.00E-07 N/A TABLE 2D LIQUID EFFLUENTS RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter

1.

Total body dose mrem 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2.

Percent of Applicable Limit 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1.

Limiting organ dose mrem 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2.

Limiting organ for period N/A N/A N/A N/A

3.

Percent of Applicable Limit 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I

_ _J

1.
2.
3.
4.
5.
6.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2E LIQUID EFFLUENTS BATCH RELEASE

SUMMARY

12-month period All Releases Number of batch releases:

0 releases Total time period for batch releases:

0 minutes Maximum time period for a batch release:

0 minutes Average time period for a batch release:

0 minutes Minimum time period for a batch release:

0 minutes Average saltwater flow during batch releases:

N/A Note:

Batch liquid releases were not performed at SONGS during 2021.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM 2015 ARERR-METEOROLOGY Joint Frequency Table number of hours was not reported correctly.

Period Pasquill Wind Direction or Wind Speed Reported Corrected Total Hrs Jan-March A

NNE 1.6 - 2 10 1

Jan-March B

WSW 7.1 -10 1

0 Jan-March C

s 3.1 - 5 0

1 Jan-March C

NNW 5.1 - 7 1

0 Jan-March C

Total Hrs 5.1 -7 4

1 Jul-Sept F

WSW 0.22-0.5 6

0 Jul-Sept G

WSW 0.22-0.5 4

0 Note:

The errors were found during review of data used for calculation of Historical Dispersion and Deposition Coefficients. The errors do not significantly affect the results of dose calculations as reported in the 2020 ARERR using historical meteorology.

2020 ARERR-EFFLUENT MONITORING INSTRUMENTS OUT OF SERVICE GREATER THAN 30 DAYS UNIT 2 Containment Purge monitor was not reported as out of service for greater than 30 days in the 2020 ARERR.

Instruments associated with the liquid radwaste radiation monitor were also not reported as non-functional; the liquid radwaste instruments were intentionally isolated and no releases were performed while the instruments were non-functional.

January 1, 2020 - December 31, 2020 Instrument lnoperability Period lnoperability Cause Explanation Unit 2 Containment Loss of isokinetic conditions Process flow could not be Purge Radiation 1 0/27 /2020-due to reduced process flow maintained in a range that Monitor 01/11/2021 caused by clogged exhaust maintained isokinetic flow 2RE-7828 prefilters conditions Liquid Radwaste The Liquid Radwaste Radiation No liquid radwaste discharges Monitor was intentionally Radiation Monitor 11/19/2020 -

isolated in November 2020 and were planned to occur during 2/3RT-7813 and Flow 12/31/2020 calibrations were not performed this period and the monitor was Indicator FE7643 at the scheduled frequencies intentionally secured.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION E. RADWASTE SHIPMENTS TABLE 3 (Units 1, 2 & 3)

SOLID WASTE AND IRRADIATED FUEL SHIPMENT A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 12-month

1.

Type of waste Unit period

a.

Spent resins, filter sludge, evaporator bottoms m3 N/A Ci N/A

b.

Dry active waste (DAW), compactable and non-compactable m3 1.04E+04 Ci 4.02E+00 C.

Irradiated components m3 1.07E+00 Ci 4.60E+00

d.

Other m3 N/A Ci N/A N/A: No waste of this type was shipped for burial in 2021. Estimated total error(%)

N/A 30%

30%

N/A

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) (Continued) 2a. Estimate of major nuclide composition [Resin]

There were no shipments of resin for final burial or disposal in 2021 2b. Estimate of major nuclide composition [Dry Active Waste (DAW)]

Nuclide Percent Activity (Ci)

Carbon-14 19.84%

7.98E-01 lron-55 11.54%

4.64E-01 Cobalt-60 10.24%

4.12E-01 Nickel-63 51.04%

2.0SE+00 Cesium-137 6.26%

2.52E-01 2c. Estimate of major nuclide composition [Irradiated Components]

Nuclide Percent Activity (Ci) lron-55 63.08%

2.90E+00 Cobalt-60 20.35%

9.36E-01 Nickel-63 15.48%

7.12E-01 2d. Estimate of major nuclide composition [Other]

There were no shipments of material in the category 'other' for final burial or disposal in 2021 Note: For the tables above, major nuclides are those contributing ;;::1 % of the total activity for a given waste type.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION A.

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

3. Solid Waste Disposition Number of Mode of Transportation Destination Notes Shipments 159 Rail EnergySolutions LLC, Clive Utah 1

Disposal Site 2

Tractor Trailer From Bear Creek Operations to Clive 2

Utah Disposal Site Note 1: 159 shipments were made in 2021 from SONGS directly to EnergySolutions Clive, Utah Disposal Site Note 2: SONGS maintains a contract with Energy Solutions Services (Bear Creek Operations) that provides volume reduction services. The processed volume was shipped from Energy Solutions Services facility to EnergySolutions Clive. Those shipments may include waste from other generators.

Three shipments were made in 2021 from SONGS to Energy Solutions LLC Bear Creek Operations.

o Two of the three shipments are still being processed for burial.

o One of the three shipments was processed at Bear Creek Operations during 2021 and subsequently sent to EnergySo/utions Clive, Utah Disposal Site in two separate shipments.

B.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made in 2021 N/A C.

DEWATERING Number of Containers Solidification Agent None N/A D.

CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 1, 2 & 3

1)

Changes made to the Process Control Program: Administrative and editorial changes only.

There were no changes made that impacted the Process Control Program in 2021.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS Gaseous Effluents Applicable Limits The percent of Applicable Limits, tabulated in Sections A, 8, C, and D of Table 1A, were calculated using the following equation:

% Applicable Limit (%MPG)

=

where: Rel Rate

=

1E+6

=

  • MPC err where: Fi

=

n

=

MPQ

=

% Applicable Limit(% ECL)

=

/

where: Rel Rate

=

1E+6

=

  • ECL err where: Fi

=

=

=

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

MPCe11* (1 E+6) total microcuries released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, 8.2, C.2 and D.2 of Table 1A, µCi/sec.

2.'1 0E-05 sec/m3; the annual average atmospheric dispersion defined in the ODCM.

conversion from m3 to cc n

p.

I--'-

i=1MPc i fractional concentration of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, Cr.

total number of radionuclides identified Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix 8, Table 11, Column 1.

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

ECLe11* (1E+6) total microcuries released in each category and each quarter, divided by the seconds in a quarter; the value in Sections A.2, 8.2, C.2 and D.2 of Table 1A, µCi/sec.

2.1 0E-05 sec/m3; the annual average atmospheric dispersion defined in the ODCM.

conversion from m3 to cc n

F*

I-'-

i=1ECL i fractional concentration of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, Cr.

total number of radionuclides identified Effluent Concentration Limit (ECL) of the ith radionuclide from 1 0 CFR 20 (20.1001-20.2402), Appendix 8, Table 2, Column 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS (Continued)

Liquid Effluents Applicable Limits The percent of Applicable Limits, tabulated in Sections A, B, and C of Table 2A, were calculated using the following equations:

% Applicable Limit (%MPG)

=

where: Oil Cone

=

  • MPC etr where: Fi

=

n

=

MPQ

=

% Applicable Limit (% ECL)

=

where: Oil Cone

=

  • ECL etr where: Fi

=

=

=

(Oil Cone) (100)

MPCe11 total microcuries released in each category and each quarter divided by the total volume released (sum of Sections E and Fin Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, µCi/ml.

n F-I--' -

i=1MPC i fractional concentration of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, Cr.

total number of radionuclides identified Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table 11, Column 2.

(Oil Cone) (100)

ECLe11 total microcuries released in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, B.2, and C.2 of Table 2A, µCi/ml.

n F-I-'-

i=l ECL i fractional concentration of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, Cr.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS (Continued}

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 release concentration limits of 10 CFR 20 Appendix B, Table II, Column 1.

B.

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

1.

During any calendar quarter:

2.

During any calendar year:

s 5 mrad for gamma radiation and s 10 mrad for beta radiation.

s 10 mrad for gamma radiation and s 20 mrad for beta radiation.

C.

The dose to a Member of the Public from iodines, tritium, and radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from SONGS (per unit) to areas at and beyond the site boundary shall be limited to the following values:

1.

During any calendar quarter:

2.

During any calendar year:

s 7.5 mrem to any organ.

s 15 mrem to any organ.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS (Continued)

APPENDIX A (Continued)

LIQUID EFFLUENTS -APPLICABLE LIMITS A.

Table 2A lists the total curies released, the diluted concentration, and percent of 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 11, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration is limited to 2.00E-04 µCi/ml.

B.

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

1.

During any calendar quarter:

2.

During any calendar year:

s 1.5 mrem to the total body and s 5 mrem to any organ.

s 3 mrem to the total body and s 10 mrem to any organ.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made.

Sources of error for gaseous effluents - continuous releases are:

(1) Fan flow rate (2) Calibration (3) Counting (4) Sampling (5) Differential pressure drop (6) Filter Digestion (7) Plateout Sources of error for liquid effluents - batch releases are:

(1) Tank volume (2) Calibration (3) Counting (4) Sampling (5) Release Flowrate (6) Dilution Flowrate (7) Sample Preparation [H3, GA]

Sources of error for liquid effluents - continuous releases are:

(1) Calibration (2) Counting (3) Sampling

( 4) Release Flowrate (5) Dilution flow rate (6) Sample Preparation [H3, GA]

These sources of error are independent, and thus, the total error is calculated according to the following formula:

Total Error

=

2 2

2 2

CT1 +a2+(J'3.. *CTi Where:

Error is the 1 Sigma error associated with each process.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual. Six different categories are presented:

(1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

The doses for each category are derived as follows:

A.

Categories 1 and 2 are calculated using the ODCM methodology. In addition, this data is presented in Table 2D.

B.

Categories 3, 4, and 5 are calculated utilizing NRCDose3, NUREG-0133 methodology, and historical meteorology. Table IE of (Gaseous Effluents, Section B) lists data similar to categories 3, 4, and 5 using methods described in the ODCM and historical meteorology (X/Q).

C. Category 6 presents direct dose data measured by TLD dosimeters.

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 boundary1. For members of the public who traverse the Site boundary (e.g., via highway 1-5), the residency time is considered negligible and hence the dose is "O."

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

1 ODCM Figures 1-2 and 2-2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS (Continued)

TABLE 1 Dose * (millirems)

First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter LIQUID EFFLUENTS

1)
2)
3)
4)

Whole Body 0.00E+00 0.00E+00 0.00E+00 0.00E+00

6)
7)
8)
9)

Organ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AIRBORNE EFFLUENTS

11)
12)
13)
14)

Tritium, Iodines, and 1.17E-04 6.78E-05 1.06E-06 5.96E-04 Particulates NOBLE GASES **

16)
17)
18)
19)

Gamma 0.00E+00 0.00E+00 1.98E-09 0.00E+00

21)
22)
23)
24)

Beta 0.00E+00 0.00E+00 2.25E-07 0.00E+00

26)
27)
28)
29)

DIRECT RADIATION ND ND ND ND Year

5) 0.00E+00
10) 0.00E+00
15) 7.80E-04
20) 1.98E-09
25) 2.25E-07
30)

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

Noble gas doses due to airborne effluent are in units of mrad, reflecting the air dose

1.

This value was calculated using the methodology of the ODCM.

2.

This value was calculated using the methodology of the ODCM.

3.

This value was calculated using the methodology of the ODCM.

4.

This value was calculated using the methodology of the ODCM.

5.

This value was calculated using the methodology of the ODCM.

6.

This value was calculated using the methodology of the ODCM.

7.

This value was calculated using the methodology of the ODCM.

8.

This value was calculated using the methodology of the ODCM.

9.

This value was calculated using the methodology of the ODCM.

10. This value was calculated using the methodology of the ODCM.
11. The maximum organ dose was to a Teen's Skin and was located in the NW sector. This was calculated using the assumptions of USNRC NUREG-0133.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS (Continued)

12. The maximum organ dose was to the Skin for All Age Groups and was located in the NW sector. This was calculated using the assumptions of USNRC NUREG-0133.
13. The maximum organ dose was to a Child's Bone and was located in the WNW sector. This was calculated using the assumptions of USNRC NUREG-0133.
14. The maximum organ dose was to the Skin for All Age Groups and was located in the NW sector. This was calculated using the assumptions of USNRC NUREG-0133.
15. The maximum organ dose was to a Teen's Skin and was located in the NW sector. This was calculated using the assumptions of USNRC NUREG-0133.
16. No noble gas radioactive effluent releases occurred during this quarter.
17. No noble gas radioactive effluent releases occurred during this quarter.
18. The maximum air dose for gamma radiation was located in the ENE sector at the site boundary. This was calculated using the assumptions of USNRC NUREG-0133.
19. No noble gas radioactive effluent releases occurred during this quarter.
20. The maximum air dose for gamma radiation was located in the ENE sector at the site boundary. This was calculated using the assumptions of USNRC NUREG-0133.
21. No noble gas radioactive effluent releases occurred during this quarter.
22. No noble gas radioactive effluent releases occurred during this quarter.
23. The maximum air dose for beta radiation was located in the ENE sector at the site boundary. This was calculated using the assumptions of USNRC NUREG-0133.
24. No noble gas radioactive effluent releases occurred during this quarter.
25. The maximum air dose for beta radiation was located in the ENE sector at the site boundary. This was calculated using the assumptions of USNRC NUREG-0133.
26. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2021 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would be 0.13 mrem based on 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year occupancy at the seawall (WNW sector). TLDs 55 and 78 were removed from its station by an unknown external action during 1st quarter 2021. The 1 Q21 dose for TLD 55 and 78 were estimated based on the average of the other three quarters.
27. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2021 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would be 0.12 mrem based on 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year occupancy at the seawall (WNW sector).
28. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2021 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would be 0.15 mrem based on 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year occupancy at the seawall (WNW sector).
29. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2021 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would be 0.13 mrem based on 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year occupancy at the seawall (WNW sector).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS {Continued)

30. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2021 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would be 0.53 mrem based on 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year occupancy at the seawall (WNW sector). TLDs 55 and 78 were removed from its station by an unknown external action during 1st quarter 2021. The 1 Q21 dose for TLD 55 was estimated based on the average of the other three quarters.

Note:

The SONGS ODCM currently provides methodology for calculating direct radiation doses by subtracting

. background TLD results (5-50 miles from the site) from the indicator results. SONGS has adopted ANSI/HPS N13.37-2014 methodology for determining facility related dose to a Member of the Public in the AREOR; this methodology has been endorsed by RG-4.13 Rev. 2 for evaluating dose to the public in the unrestricted area. For 2021, the reported dose is Not Detected (ND) based on the AREOR procedure. The doses calculated per the ODCM net-dose methodology are provided as footnotes to Table 1.

TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Organ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 AIRBORNE EFFLUENTS Tritium, Iodines, and 7.77E-04 4.52E-04 7.0?E-06 3.97E-03 2.60E-03 Particulates NOBLE GASES Gamma 0.00E+00 0.00E+00 1.98E-08 0.00E+00 9.90E-09 Beta 0.00E+00 0.00E+00 1.13E-06 0.00E+00 5.63E-07 Note:

Direct Radiation is not specifically addressed in the 10 CFR 50 Appendix I Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There were no changes to the SONGS ODCM in 2021.

Changes due to the Land Use Census The Land Use Census (LUC) for 2021 did not identify a new location with a higher calculated or committed dose than those calculated for the locations evaluated in the previous revision to the ODCM. The Dose Assessment for the 2021 LUC was performed using the NRCDose3/GASPAR II program. Therefore, no new location is reported per ODCM 5.2.1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Changes to the Liquid Radioactive Waste Treatment System The were no changes to SONGS Radioactive Waste Treatment Systems in 2021.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS ABNORMAL RELEASES On 06/21/2021 and 06/22/2021, during decommissioning activities, licensed material (Cs-137 and Ni-63) was identified on particulate filters used for airborne sampling of the general area of the Unit 3 Containment Building Equipment Hatch. The containment ventilation was in service; however, it was determined a small amount of licensed material was released offsite from the equipment hatch. The licensed material was quantified at levels below the ODCM required LLDs and the resultant dose and curies are included in this ARERR.

EFFLUENT MONITORING INSTRUMENTS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2021 - December 31, 2021 Instrument lnoperability Period lnoperability Cause Explanation Loss of isokinetic Process flow could not be Unit 2 Containment Purge 10/27/2020-conditions due to reduced maintained in a range that Radiation Monitor 01/11/2021 process flow caused by maintained isokinetic flow 2RE-7828 conditions. Prefilters were on clogged exhaust prefilters order with a long lead time.

Unit 2 Turbine Plant Turbine building was electrically Sump Radiation Monitor 2RE-7821, Compositor 06/21/2021-Removal of electric power isolated for industrial safety 2APC-5887 and Flow 12/31/2021 to Unit 2 Turbine Building purposes in support of Totalizer 2FQl-5887 demolition work.

The Liquid Radwaste Liquid Radwaste Radiation Monitor was No liquid radwaste discharges intentionally isolated in Radiation Monitor 2/3RT-01/01/2021 -

November 2020 and were planned to occur during 7813 and Flow Indicator 12/31/2021 calibrations were not 2021 and the monitor was FE7643 performed at the scheduled intentionally secured.

frequencies ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS (Continued)

ONSITE GROUND WATER SAMPLES In 2007, the Nuclear Energy Institute (NEI) established a standard for monitoring and reporting radioactive isotopes in groundwater titled NEI Groundwater Protection Initiative, NEI 07-07. It has been established that there is no drinking water pathway for groundwater underneath SONGS. However, the site implemented the groundwater protection industry standard. This section provides results of on-site samples of ground water that were obtained as part of SCE's implementation of the voluntary industry Ground Water Protection Initiative. The sample locations and the frequency of sampling may change over time. The Groundwater Monitoring Wells that are in the Groundwater Protection Initiative are NIA-1, NIA-2, NIA-12, NIA-13, PA-1, PA-2, PA-3, PA-4, OCA-1, OCA-2, and OCA-3. These wells are sampled on a quarterly basis.

Historical groundwater sample data has indicated the presence of low, but detectable levels of tritium in shallow ground water in the area formerly occupied by Unit 1 known as the North Industrial Area (NIA). The concentrations of tritium are well below regulatory limits.

Low tritium concentrations have historically been found in the shallow ground water situated between the former Unit 1 Containment and Fuel Handling Building, extending towards the seawall. Although these samples indicated the presence of tritium, the sample results were at concentrations below the Environmental Protection Agency drinking water limit of 20,000 pCi/1. Results from 2021 show one detectible tritium result from NIA-5 and no gamma activity in Groundwater Monitoring Well samples.

The site continues to sample and analyze the groundwater monitoring wells in accordance with the site's Groundwater Monitoring Program. In addition, the site samples, analyzes and documents other groundwater wells that are identified as investigatory wells. The groundwater investigatory wells analysis results are documented in this report. The groundwater investigatory wells are identified as NIA-3 through NIA-7, NIA-10, NIA-11, NIA-14, and NIA-

15. Results from 2021 identified tritium in NIA-5 groundwater sample greater than MDC but less than LLD.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS (Continued)

ONSITE GROUND WATER SAMPLES (Continued)

January 1, 2021 - December 31, 2021 Location Sample Date Tritium Activity Gamma Activity pCi/I pCi/I GW-NIA-1 01/28/21

<MDC N/A GW-NIA-1 05/17/21

<MDC N/A GW-NIA-1 08/16/21

<MDC N/A GW-NIA-1 10/28/21

<MDC N/A GW-NIA-2 01/27/21

<MDC N/A GW-NIA-2 05/20/21

<MDC N/A GW-NIA-2 08/09/21

<MDC N/A GW-NIA-2 11/01/21

<MDC N/A GW-NIA-12 01/27/21

<MDC N/A GW-NIA-12 05/20/21

<MDC N/A GW-NIA-12 08/09/21

<MDC N/A GW-NIA-12 11/01/21

<MDC N/A GW-NIA-13 01/27/21

<MDC N/A GW-NIA-13 05/17/21

<MDC N/A GW-NIA-13 08/16/21

<MDC N/A GW-NIA-13 10/28/21

<MDC N/A GW-OCA-1 01/21/21

<MDC N/A GW-OCA-1 04/28/21

<MDC N/A GW-OCA-1 08/05/21

<MDC N/A GW-OCA-1 10/27/21

<MDC N/A GW-OCA-2 01 /21 /21

<MDC N/A GW-OCA-2 04/19/21

<MDC N/A GW-OCA-2 08/04/21

<MDC N/A GW-OCA-2 10/21/21

<MDC N/A GW-OCA-3 01/18/21

<MDC N/A GW-OCA-3 04/29/21

<MDC N/A GW-OCA-3 08/02/21

<MDC N/A GW-OCA-3 10/20/21

<MDC N/A GW-PA-1 01/13/21

<MDC

<MDC GW-PA-1 05/31/21

<MDC

<MDC GW-PA-1 07/21/21

<MDC

<MDC GW-PA-1 11/03/21

<MDC

<MDC GW-PA-2 01 /13/21

<MDC

<MDC GW-OCA GW-PA GW-NIA NIA a priori LLD ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS (Continued)

Location GW-PA-2 GW-PA-2 GW-PA-2 GW-PA-3 GW-PA-3 GW-PA-3 GW-PA-3 GW-PA-4 GW-PA-4 GW-PA-4 GW-PA-4 NIA-3 NIA-4 NIA-5 NIA-6 NIA-7 NIA-10 NIA-11 NIA-14 NIA-15 ONSITE GROUND WATER SAMPLES (Continued)

January 1, 2021 - December 31, 2021 Sample Date Tritium Activity Gamma Activity pCi/1 pCi/1 05/31/21

<MDC

<MDC 07/22/21

<MDC

<MDC 11/11/21

<MDC

<MDC 01/14/21

<MDC

<MDC 05/05/21

<MDC

<MDC 07/22/21

<MDC

<MDC 11/04/21

<MDC

<MDC 01 /14/21

<MDC

<MDC 05/06/21

<MDC

<MDC 07/28/21

<MDC

<MDC 11/08/21

<MDC

<MDC 02/10/21

<MDC N/A 02/04/21

<MDC N/A 02/10/21 7.35E+02 N/A 02/04/21

<MDC N/A 02/11/21

<MDC N/A 02/01/21

<MDC N/A 02/01/21

<MDC N/A 02/11/21

<MDC N/A 02/11/21

<MDC N/A

= Wells installed in the Owner Controlled Area to implement the Ground Water Protection Initiative.

= Wells installed in the Protected Area to implement the Ground Water Protection Initiative.

= Wells installed in the North Industrial Area to implement the Ground Water Protection Initiative.

= Temporary investigation wells installed in the North Industrial Area.

= H-3: 3000 pCi/I Values above Minimum Detectable Concentration (MDC) are reported as calculated ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS (Continued) 40 CFR 190 REQUIREMENTS The Table 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 liquid, gaseous particulate and tritium, and noble gas effluent pathways, Total Effective Dose Equivalent (TEDE) resulting from the offshore portion of the U1 Circulating Water System, and direct radiation dose measured using environmental TLDs. 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 7.97E-02

b.

Percent ODCM Specification Limit 3.19E-01

2.

Limiting Organ

a.

Organ Dose (All except thyroid) (Bone) mrem 7.B0E-04

b.

Percent ODCM Specification Limit 3.12E-03 3,

Thyroid

a.

Thyroid Dose mrem 7.B0E-04

b.

Percent ODCM Specification Limit 1.04E-03 Note:

The 40 CFR 190 dose determination above used TLD dose of 0.00E+00 mrem based on annual dose determination of Not Detected shown in Table 1 on page 24. If using the net dose methodology from the ODCM, Total Body dose would be 6.11 E-01 mrem.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS (Continued)

CARBON-14 In June 2009, the NRC revised its guidance in Regulatory Guide (RG) 1.21, Measuring, Evaluating And Reporting Radioactivity In Solid Wastes And Releases Of Radioactive Materials In Liquid And Gaseous Effluents From Light-Water-Cooled Nuclear Power Plants, Revision 2. RG 1.21 explains, that in part, the quantity of carbon-14 (C-14) discharged can be estimated by sample measurements or by use of a normalized C-14 source term and scaling factors based on power generation or estimated by use of the GALE Code from NUREG-0017. The dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required. Revision 3 to RG 1.21 guidance includes:

If sampling is performed, the sampling frequency may be adjusted to that interval that allows adequate measurement and reporting of effluents.

If estimating C-14 based on scaling factors and fission rates, a precise and detailed evaluation of C-14 is not necessary. It is not necessary to calculate uncertainties for C-14 or to include C-14 uncertainty in any subsequent calculation of overall uncertainty.

Electric Power Research Institute (EPRI) Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents," was used to estimate the production and release quantities of C-14.

C-14 calculated production, discharge parameters and resulting dose are reported here, separately from Tables 1, 1 A, 1 C, 1 E, 2 and 40 CFR 190 Table 1.

Calculated C-14 production, Ci/EFPY(1l U2 = 0 U3 = O 2021 Unit capacity factors U2= 0 U3 = O Fraction release of produced C-14 to atmosphere 0.98 C-14 chemical form fraction assumed Organic

= 0.80 Inorganic

= 0.20 C-14 curies released to atmosphere U2 = 0 U3 = 0 Critical receptor dose [Child (bone)], mrem 0

(1) Effective Full Power Year Note:

Units have been shut down since January 9, 2012 for Unit 2 and January 31, 2012 for Unit 3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION SECTION L. SONGS CONCLUSIONS

1) Gaseous releases (excluding carbon-14) totaled 9.32E-01 curies of which noble gases were 1.73E-04 curies, particulates were 4.80E-04 curies, iodines were 0.00E+00 curies, and tritium was 9.31 E-01 curies.
2) The radiation doses from gaseous releases were: (a) gamma air dose: 1.98E-09 mrad at the site boundary, (b) beta air dose: 2.25-E-07 mrad at the site boundary, (c) organ dose (Teen - Skin): 7.80E-04 mrem at the highest receptor.
3) Airborne carbon-14 release was projected at 0.00E+00 curies due to the fact that both Units 2 and 3 have been permanently shut down since January 2012.
4) Liquid releases totaled 0.00E+00 curies of which particulates were 0.00E+00 curies, iodines were 0.00E+00 curies, tritium was 0.00E+00 curies, and noble gases were 0.00E+00 curies.
5) The radiation doses from liquid releases were: (a) total body: 0.00E+00 mrem, (b) limiting organ (N/A):

0.00E+00 mrem.

6) The radioactive releases and resulting doses generated from Units 2 and 3 were below the Applicable Limits for both gaseous and liquid effluents.
7) A total of 159 shipments of solid radioactive waste were made from SONGS in 2021 via rail to Energy Solutions Clive, Utah disposal site. Two shipments of processed waste were made from Bear Creek Operations on behalf of SONGS in 2021 via tractor trailer to Energy Solutions Clive, Utah disposal site. These shipments included 1.04E+04 m3 (predominantly Dry Active Waste by volume) and 8.62E+00 Ci (predominantly Dry Active Waste and Irradiated Components by activity).
8) The results of samples taken from on-site ground water wells in support of the Industry Ground Water Protection Initiative are reported in Section K. One groundwater sample in 2021 indicated detectible concentrations of tritium and is reported in Section K. No groundwater samples indicated detectable concentrations of gamma emitting nuclides. The ground water beneath SONGS is not a source of drinking water. On April 28, 2015, the extraction pumps were secured to evaluate the impact of groundwater extraction. There were no groundwater or dewatering well effluent discharges from the site during 2021. The site continues to sample, analyze, and document the results of the groundwater monitoring wells in accordance with the site's Groundwater Monitoring Program.
9) The net result from the analysis of these effluent releases indicates that the operation of SONGS has met all the requirements of the applicable regulations that ensure adequate protection of the health of members of the public.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2021 SAN ONOFRE NUCLEAR GENERATING STATION METEOROLOGY The Offsite Dose Calculation Manual (ODCM) has required the use of concurrent meteorology since its inception.

This is appropriate and reasonable for an operating reactor site that performs intermittent and varied releases, specifically batch waste gas releases and containment ventilation.

Units 2 and 3 ceased commercial operation in January 2012. Fuel was removed from both reactors and placed in the Spent Fuel Pools and, as of 2020, all fuel has been transferred to the ISFSI. The Gaseous Radwaste System (GRWS) was removed from service in November 2015. Containment ventilation operation was changed in 2018 to establish the containment ventilation as a continuous release pathway. Therefore, gaseous batch releases are no longer performed. All gaseous releases are now continuous.

Based on the guidance provided in Regulatory Guide 1.111 and NUREG-0133 and considering current station conditions, it is reasonable and acceptable to utilize historical meteorology rather than concurrent meteorology. To support this change, an evaluation of SONGS historical meteorology was performed in 2020, along with an independent evaluation of the need for concurrent meteorology. The results of those evaluations support the removal of concurrent meteorology requirements from the ODCM.

Since the weather patterns have not substantially changed and the deposition and dispersion coefficients have been updated with recent data, and batch releases are no longer performed at SONGS, the use of historical meteorology is the preferred method for determining offsite dose. As such, the meteorological tower is no longer needed for the purpose of routine release calculations.

Alternate Meteorology Data In the case of an event having the potential of a radiological release during decommissioning, it is prudent to have some method for determining actual meteorological conditions to ensure accurate calculations. Additionally, the historical weather will be evaluated over time to ensure conditions do not significantly change. In order to meet these two conditions, alternate local sources of weather data were evaluated. The weather station with the most favorable data as compared to SONGS was found to be KNXF, Mcolf Camp Pendleton (Red Beach) Airport; this station has similar elevation and distance to the shoreline. The data from the two stations tracked reasonably well and it has been concluded that this other station can be used for alternate weather data in the future.