Text

(Songs), Units 1, 2 and 3 - Annual Radioactive Effluent Release Report - 2020
	ML21127A150
Person / Time
Site:	San Onofre
Issue date:	04/27/2021
From:	Bates A; Southern California Edison Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	Download: ML21127A150 (333)
	v • d • e

Al Bates Manager Regulatory Affairs An EDISON INTIIRNATIONAI,* Company 10 CFR 50.36(a)

April27,2021 ATTN:Documen tControlDesk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Annual Radioactive Effluent Release Report - 2020 San Onofre Nuclear Generating Station (SONGS), Units 1, 2 and 3 Docket Nos. 50-206, 50-361 and 50-362

Dear Sir or Madam,

In accordance with 10 CFR 50.36(a), Southern California Edison (SCE) is submitting the Annual Radioactive Effluent Release Report - 2020 (ARERR) for SONGS, Units 1, 2, and 3 (Enclosure 1). The period of the report is January 1, 2020 through December 31, 2020. A separate ARERR was submitted for the SONGS Independent Spent Fuel Storage *installation (ISFSI) on February 25, 2021 which 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. * *

(\dditionally, in a~rdance with the SONGS Licensee Controlled Specifications, the SONGS Offsite Dose Calculation Manual (ODCM) Revision 16 is included with this submittal as Enclosure 3. There were three revisions to the ODCM during 2020 which are described in Enclosure 2 with the actual changes detailed for Revision 14 in Enclosure 5, Revision 15 in Enclosure 4, and Revision 16 in Enclosure 3.

There are no commitments in this letter or the enclosure.

1£t/<l

1-001

/l)H5 S_Dl tJf fc P. 0. Box 128

\ San Clemente, CA 92672 /UH~s

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

Enclosures:

1) San Onofre Nuclear Generation Station, Annual Radioactive Effluent Release Report -

2020

2) Description of Changes to the Offsite Dose Calculation Manual Sections During 2020

3) Offsite Dose Calculation Manual, San Onofre Nuclear Generating Station (SONGS),

SO123-ODCM Revision 16, November 2020

4) Offsite Dose Calculation Manual, San Onofre Nuclear Generating Station (SONGS), Page 2-22 of SO123-ODCM Revision 15, August 2020 *

5) Offsite Dose Calculation Manual, San Onofre Nuclear Generating Station (SONGS), Page 1-13 of SO123-ODCM Revision 14, February 2020

6) Offsite Dose Calculation Manual, San Onofre Nuclear Generating Station (SONGS),

SO123-ODCM Appendix A Revision 15, November 2020

7) Offsite Dose Calculation Manual, San Onofre Nuclear Generating Station (SONGS),

SO123-ODCM Appendix A Revision 14, March 2020 ~

8) Offsite Dose Calculation Manual, San Onofre Nuclear Generating Station (SONGS),

SO123-ODCM Appendix B Revisi_on 9, August 2016 cc: S. A. Morris, Regional Administrator, NRC Region IV A. M. Snyder, NRC Project Manager, SONGS Units 1, 2 and 3 R. K. Lupo, California Department of Public Health

Enclosure 1 San Onofre Nuclear Generation Station Annual(Radioactive Effluent Release Report 2020 January - December

SAN. ONOFRE NUCLEAR GENE-RATIN*G STATION Annual Radioactive Effluent *Release Report

2020 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.

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TABLE OF CONTENTS SECTION A- INTRODUCTION .................................................................................................................................... 1 SECTION 8-GASEOUS EFFLUENTS ........................................................................................................................ 2 SECTION C- LIQUID EFFLUENTS .............................................................................................................................. 8 SECTION D- PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM ....................................... 15 SECTION E- RADWASTE SHIPMENTS .................................................................................................................... 16 SECTION F -APPLICABLE LIMITS ...........................................................................................................................21 SECTION G-ESTIMATION OF ERROR. ................................................................................................................... 25 SECTION H-10 CFR 50 APPENDIX I REQUIREMENTS ......................................................................................... 26 SECTION I -CHANGES TO OFFSITE DOSE CALCULATION MANUAL .................................................................. 30 SECTION J-CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ....................................................... 32 SECTION K- MISCELLANEOUS ............................................................................................................................... 36 Abnormal Release ......................................................................................................................................... 36 Effluent Monitoring Instruments Out of Service Greater Than 30 days .......................................................... 37 Onstte Groundwater Samples ........................................................................................................................ 38 40 CFR 190 Requirements ............................................................................................................................41 Carbon-14 ......................................................................................................................................................42 SECTION L-SONGS CONCLUSIONS ......................................................................................................................43 METEOROLOGY ........................................................................................................................................................44

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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 fonnat of USNRC Regulatory Guide 1.21, Revision 1, and includes:

1. Quarterly Summaries of Gaseous Effluents for Continuous Mode 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. Raclwaste Shipments

9. 10 CFR 50 Appendix I Requirements

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

AL Applicable Limit ALARA As Low As Reasonably Achievable AR Action Request ARERR Annual Radioactive Effluent Release Report Ci Curies CR Condition Report DAS Data .Acquisition System ECL Effluent Concentration Limit GI-LLI Gastrointestinal Tract-Lower Large Intestine GPJ Groundwater Protection Initiative ISFSI Independent Spent Fuel Storage Installation LCS Licensee Controlled Specifications LLD Lower Limit of Detection m3 Meter cubed MPC Maximum Permissible Concentrations mRAD One thousandth Radiation Absorbed Dose mREM One thousandth of a Roentgen Equivalent Man NIA Not Applicable GW-NIA North Industrial Area fonnally known as Unit 1 ODCM Offsite Dose Calculation Manual pCi/1 Pico Curies per liter TLD Thennoluminescent Dosimeter

µCl/sec Micro Curies per second X/Q Chi over Q SYF South Yard Facility ANNUAL RADIOACTNE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION B. GASEOUS EFFLUENTS Table 1A, "Gaseous Effluents Summation of All Releases,* provides a detailed listing of gaseous effluents released quarterly in four categories: fission and activation gases, iodine 131, particulates with half-lives greater than eight days, and tritium. Listed for each of the four categories are:

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

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

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

Table 1C, 'Gaseous Effluents Ground Level Releases,' provides the systematic listing by radionuclide for the quantity of radioactivity released in three categories: fission gases, iodines, and particulates. The total radioactivity for each radionuclide is listed for each quarterly period for continuous mode of release. Containment purges and plant stack releases are considered to be continuous releases.

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

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1A GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Estimated First Second Third Fourth Total Unit Quarter Quarter Quarter Quarter Error,%

A. Fission and activation gases

1. Total release Ci < LLD < LLD < LLD < LLD Average release rate for

2. µCi/sec NIA N/A NIA N/A period N/A Percent of applicable

3. %MPG NIA N/A N/A N/A limit 4, Percent Effluent

% ECL NIA N/A N/A N/A

'Concentration Umit 8, Iodines

1. Total 1-131 Ci <LLD < LLD < LLD < LLD Average release rate for

2. µCi/sec NIA N/A NIA N/A period NIA

3. Percent of applicable limit %MPG N/A N/A N/A NIA Percent Effluent

4. % ECL NIA NIA NIA N/A Concentration Limit C. Particulates Particulates with half-lives

1. Ci 2.77E-06 < LLD 2.12E-05 < LLD

>8 days Average release rate for

2. µCi/sec 3.52E-07 N/A 2.67E-06 N/A period 3.00E+01 3, Percent of applicable limit %MPG 1.48E-06 NIA 1.12E-05 N/A Percent Effluent 4, % ECL 3.?0E-06 NIA 2.80E-05 N/A Concentration Limit

5. Gross alpha activity Ci < LLD < LLD < LLD < LLD NIA D. Tritium

1. Total release Ci 2.45E+00 5.04E+OO 1.30E+00 1.66E+OO Average release rate for

2. µCi/sec 3.12E-01 6.41 E-01 1.64E-01 2.09E-01 period 2.30E+01

3. Percent of applicable limit %MPG 3.27E-03 6.73E-03 1.72E-03 2.19E-03 Percent Effluent

4. % ECL 6.54E-03 1.35E-02 3.43E-03 4.39E-03 Concentration Umit ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION

\ TABLE 1C GASEOUS EFFLUENTS GROUND LEVEL RELEASES BATCH MODE Batch gaseous releases were not perfonned at SONGS in 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C (Continued)

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

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-BB 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 cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci 2.77E-06 <LLD 2.12E-05 <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 manQanese-54 Ci <LLD <LLD <LLD <LLD molylxlen um-99 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD nickel-63 Ci NIA N/A NIA <LLD strontiurn-90 Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD Total for period Ci 2.77E-06 <LLD 2.12E-05 <LLD LLD Lower Limit of Detection; see Table 1D.

N/A Ni-63 analysis was not required prior to ODCM Rev 16. Only 4Q20 composites were analyzed for Ni-63.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1D GASEOUS EFFLUENTS LOWER LIMIT OF DETECTION Continuous Mode Batch Mooe Radionuclides LLD (µCl/cc) LLD (µCl/cc)

1. Fission and activation gases krypton-85 2.20E-05 N/A krypton-85m 5.50E-08 N/A krypton-87 2.?0E-07 NIA krypton-88 1.00E-07 N/A xenon-133 1.40E-07 NIA xenon-133m 4.40E-07 NIA xenon-135 5.?0E-08 N/A xenon-135m 2.10E-06 N/A xenon-138 3.?0E-06 N/A 2.. Iodines iodine-131 2.30E-13 NIA iodine-133 2.20E-12 NIA iodine-135 1.50E-10 N/A 3, Particulates barium-140 4.80E-13 N/A cerium-141 5.80E-14 N/A cerium-144 2.30E-13 N/A cesium-134 1.30E-13 N/A cesium-137 1.10E-13 NIA cobalt-58 1.20E-13 N/A cobalt-60 1.00E-13 NIA iron-59 3.00E-13 N/A lanthanum-140 9.?0E-13 NIA manganese-54 1.20E-13 NIA molybdenum-99 7.00E-14 N/A nickel-63 1.00E-11 N/A strontium-89 1.00E-11 NIA strontium-00 1.00E-11 NIA zinc-65 3.20E-13 N/A

4. Tritium 7.20E-08 NIA

5. Alpha 1.00E-11 N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1E GASEOUS EFFLUENTS RADIATION DOSES AT THE SITE BOUNDARY First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter A. Noble Gas

1. Gamma Air Dose Mrad 0.00E+OO 0.00E+00 O.00E+O0 0.00E+OO

2. Percent of Applicable Limit % 0.00E+OO 0.00E+OO 0.OOE+OO 0.00E+O0

3. Beta Air Dose Mrad 0.00E+OO 0.OOE+00 0.OOE+OO 0.00E+O0

4. Percent Applicable Limit % 0.00E+OO 0.00E+00 0.OOE+OO 0.00E+O0 B. Tritium, Iodine, Particulates (at the nearest receptor)

I

1. Organ Dose Mrem 7.26E-05 1.43E-04 5.93E-05 8.55E-05

2. Percent of Applicable Limit % 4.84E-04 9.55E-04 3.95E-04 5.?0E-04 NOTE: Calculations performed in accordance with the ODCM utilizing x/Q and O/Q based on historical meteorological data. '

TABLE 1F GASEOUS EFFLUENTS BATCH RELEASE

SUMMARY

Batch gaseous releases were not performed at SONGS during 2020.

r ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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. Usted for each of the three categories are:

(1) the total curies released (2) the average diluted concentration (3) the percent of applicable limn (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 28, 'Uquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity rel~ 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, 'Uquid Effluents Lower Limn of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 28.

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

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE2A LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Estimated First Second Third Fourth Total Unit Quarter Quarter Quarter Quarter Error,%

A. Fission and activation products Total release (not

1. including tritium, gases, Ci 4.44E-04 5.38E-03 3.34E-03 1.?0E-02 alpha)

Average diluted

2. concentration during µCVml 5.54E-11 6.65E-10 4.20E-10 2.11 E-09 ooriod 1.20E+01

3. Percent of applicable limit %MPC 2.03E-04 1.58E-03 9.99E-04 6.35E-03 Percent Effluent

4. % ECL 2.58E-03 2.04E-02 1.25E-02 4.29E-02 Concentration Limit B. Tritium

1. Total release Ci 1.94E-01 4.46E+O0 3.63E+OO 1.61E+01 Average diluted

2. concentration during µCVml 2.42E-08 5.52E-07 4.57E-07 2.00E-06 period 1.30E+01

3. Percent of applicable limit %MPC 8.0?E-04 1.84E-02 1.52E-02 6.67E-02 Percent Effluent

4. % ECL 2.42E-03 5.52E-02 4.57E-02 2.00E-01 Concentration Limit C. Dissolved and entrained gases

1. Total release Ci <LLD <LLD <LLD <LLD Average diluted

2. concentration during µCVml N/A NIA N/A NIA period N/A

3. Percent of applicable limit

/'-

%MPC NIA N/A NIA NIA Percent Effluent

4. %ECL NIA N/A NIA N/A Concentration Limit D. Gross alpha activity

1. Total release Ci <LLD <LLD <LLD <LLD NIA Volume of waste released E. 5.42E+06 2.16E+06 2.92E+06 5.00E+00 (batch & continuous, prior to liters 6.16E+06 dilution)

F. Volume of dilution water used liters 8.01E+09 8.08E+09 7.94E+09 8.04E+09 5.00E+00 during period ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 28 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 1.10E-05 <LLD chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molylxlenum-99 Ci <LLD <LLD <LLD <LLD nickel-63 Ci N/A NIA N/A 1.29E-04 niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD 1.10E-05 1 1.29E-4

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.

N/A Ni-63 analysis was not required prior to ODCM Rev 16. Only 4Q20 composites were analyzed for Ni-63.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2B (Continued)

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

1. Fission and activation products antimony-125 Ci <LLD 1.52E-03 4.49E-04 1.04E-03 barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD* <LLD <LLD <LLD cesium-134 Ci 1.63E-07 3.68E-05 <LLD <LLD cesium-137 Ci 8.75E-05 9.45E-04 4.57E-04 2.04E-03 chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci 3.56E-04 1.S0E-03 1.51E-03 3.83E-03 iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD 1.0?E-03 9.09E-04 2.03E-03 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 nickel-63 Ci NIA N/A NIA 7.92E-3 niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci 4.44E-04 5.38E-03 3.33E-03 1.69E-02

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 Umit of Detection; see Table 2C.

NIA Ni-63 analysis was not required prior to ODCM Rev 16. Only 4Q20 composites were analyzed for Ni-63.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE2C LIQUID EFFLUENTS LOWER LIMIT OF DETECTION Continuous Mode Batch Mode Radionuclides LLD (µCl/cc) LLD (µCl/cc)

1. Fission and activation products antimony-125 1.40E-07 1.40E-07 barium-140 3.30E-07 2.?0E-07 cerium-141 4.BOE-08 4.40E-08 cerium-144 1.90E-07 1.90E-07 cesium-134 8.SOE-08 8.SOE-08 cesium-137 7.30E-08 7.30E-08 chromium-51 3.60E-07 3.30E-07 cobalt-58 7.?0E-08 7.S0E-08 cobalt-60 1.10E-07 1.10E-07 iodine-131 6.40E-08 4.B0E-08 iron-55 1.00E-06 1.00E-06 iron-59 1.B0E-07 1.?0E-07 lanthanum-140 6.40E-07 2.10E-07 manganese-54 7.60E-08 7.60E-08 molybdenum-99 6.30E-08 2.90E-08 nickel-63 1.00E-06 1.00E-06 niobium-95 7.?0E-08 7.20E-08 strontlum-89 5.00E-08 5.00E-08 strontium-90 5.00E-08 5.00E-08 technetium-99m 6.40E-08 3.00E-08 zinc-65 1.90E-07 1.90E-07 zirconium-95 1.30E-07 1.30E-07

2. Dissolved and entrained gases xenon-133 2.S0E-07 2.SOE-07 xenon-135 9.60E-08 9.60E-08

3. Tritium 1.00E-05 1.00E-05

4. Gross Alpha 1.00E-07 1.00E-07 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE2D LIQUID EFFLUENTS RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A.

1. Total body dose mrem 5.55E-04 6.63E-03 4.89E-03 1.78E-02

2. Percent of Applicable Umit % 1.85E-02 2.21E-01 1.63E-01 5.93E-01 B.

1. Umiting organ dose mrem 3.0?E-03 2.24E-02 1.00E-02 1.43E-01

2. Umiting organ for period GI-LU GI-LU GI-LU Bone

3. Percent of Applicable Umtt % 3.0?E-02 2.24E-01 1.90E-01 1.43E+OO ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE2E LIQUID EFFLUENTS BATCH RELEASE

SUMMARY

12-month period Full Releases only*

All Releases

1. Number of batch releases: 17 releases 15 releases

2. Total time period for batch releases: 4,884 minutes 4,881 minutes

3. Maximum time per:iod for a batch release: 912 minutes 912 minutes

4. Average time period for a batch release: 287 minutes 325 minutes

5. Minimum time period for a batch release: 1 minutes 180 minutes

6. Average saltwater flow during batch releases: 16,246 gpm 16,319 gpm

Note: Two liquid radWa5te batch releases 'Here unsuccessfully attempted in February 2020. These releases lasted approximately 2 minutes and 1 minute and were terminated due to process and sample flow issues associated with the liquid radwaste radiation monitor (see diSGussion of Effluent Monitoring Instruments out of Service >30 Days section on pg. 37). These two releases were very small compared to other releases for 2020 and YJSre conservatively reported along with the full batch releases. The very short time periods and small volumes for these releases creates a substantial change in some reported values and so the table is duplicated with the second data column including only the 15 full batch releases performed in 2020.

i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM

)

There were no errors in previous ARERR's identified in 2020.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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 Estimated total

1. Type of waste Unn: period error(%)

a. Spent resins, filter sludge, evaporator m3 1.70E+OO bottoms 30%

Ci 2.18E+01

b. Dry active waste (DAW), compactable and m3 1.70E+03 non-compactable 30%

Ci 1.11E+OO C. Irradiated components m3 1.55E+02 30%

Ci 5.97E+03

d. Other. Filters m3 3.00E-01 30%

Ci 1.65E+00 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 2a. Estimate of major nuclide composition [U1, U2 and U3 Resin]

Nuclide Percent Activity (Cl}

Tritium (H3) 0.27% 5.82E-02 Carbon-14 0.07% 1.61 E-02 lron-55 0.63% 1.37E-01 Cobalt-60 2.08% 4.52E-01 Nickel- 59 0.03% 5.90E-03 Nickel-63 6.91% 1.50E+OO Strontium-90 0.68% 1.47E-01 Antimony-125 1.36% 2.95E-01 Cesium-134 4.16% 9.0SE-01 Cesium-137 83.61% 1.82E+01 Cerium-144 0.14% 3.10E-02 Plutonium-238 <0.01% 3.01 E-05 Plutonium-239 <0.01% 3.81 E-05 Plutonium-241 0.06% 1.40E-02 Americium-241 <0.01% 8.37E-04 Curium-243 <0.01% 4.S0E-04 2b. Estimate of major nuclide composition [U1, U2 and 3 Dry Active Waste (DAW)]

Nuclide Percent Activity (Cl)

Carbon-14 1.40% 1.55E-02 lron-55 5.32% 5.89E-02 Cobalt-60 6.86% 7.59E-02 Nickel-63 68.07% 7.53E-01 Niobium-94 <0.01% 5.35E-09 Antimony-125 0.51% 5.59E-03 Cesium-134 0.16% 1.73E-03 Cesium-137 17.60% 1.95E-01 Cerium-144 0.03% 3.59E-04 Plutonium-238 0.02% 2.03E-04 Americium-241 0.02% 2.61 E-04 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION 2c. Estimate of major nuclide composition [U1, U2 and U3 Irradiated Components]

Nuclide Percent Activity (Cl)

Carbon-14 0.12% 7.31 E+OO Manganese-54 <0.01% 9.75E-07 lron-55 0.97% 5.80E+01 Cobalt-60 18.63% 1.11 E+03 Nickel'.. 59 0.71% 4.24E+01 Nickel-63 79.55% 4.74E+.03 Strontium-90 <0.01% 3.26E-02 Niobiurn-94 <0.01% 1.08E-01 Technetium-99 <0.01% 2.73E-02 Cesium-137 <0.01% 5.48E-02 Cerium-144 <0.01% 4.61E-09 Plutonium-238 <0.01% 4.91 E-02 Plutoniurn-239 <0.01% 2.09E-02 Plutonium-241 0.01% 6.02E-01 Americium-241 <0.01% 3.63E-02 Curium-242 <0.01% 1.97E-17 Curium-243 <0.01% 1.10E-02 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION 2d. Estimate of major nuclide composition [U1, U2 and U3 Filters]

Nucllde Percent Activity (Cl)

Carbon-14 0.67% 1.11 E-02 Manganese-54 0.03% 4.32E-04 lron-55 22.99% 3.80E-01 Cobalt-60 22.39% 3.70E-01 Nickel-59 0.32% 5.21E-03 Nickel-63 49.98% 8.26E-01 strontium-00 0.08% 1.40E-03 Niobium-94 0.03% 5.41E-04 Antimony-125 0.31% 5.11E-03 Cesium-134 0.11% 1.74E-03 Cesium-137 2.22% 3.67E-02 Cerium-144 0.08% 1.37E-03 Plutonium-238 0.02% 2.66E-04 Plutonium-239 0.01% 2.0SE-04 Plutonium-241 0.65% 1.0?E-02 Plutonium-242 <0.01% 2.77E-06 Americium-241 0.04% 6.52E-04 Curium-242 <0.01% 7.77E-07 Curium-243 0.09% 1.43E-03 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION

3. Solld Waste Disposition Number of Shipments Mode of Transportation Destination 5 Type A Cask EnergySolutions Services, Bear Creek Operations, Oak Ridge, TN 8 Rail EnergySolutions LLC, Clive Utah Disposal Site 23 Tractor Trailer EnergySolutions LLC, Clive Utah Disposal Site I EnergySolutions Services, Bear Creek Operations, Oak Ridge, TN Notes:

Note 1: SONGS maintains a contract with Energy Solutions Services (Bear Creek Operations) that provides volume reduction services. The processed volume was shipped from EnergySolutions Services facility to EnergySo/utions Clive and Waste Control Specialists using 6 shipments. Those 6 shipments may have included waste from other generators.

One shipment was made in 2020 from EnergySolutions LLC Bear Creek Operations to EnergySolutions Clive Utah Disposal Site.

Five shipments were made in 2020 from EnergySolutions LLC Bear Creek Operations to Waste Control Specialist Texas Disposal Site.

Note 2: Thirty shipments were made in 2020 from EnergySolutions-San Onofre to EnergySolutions Clive Utah Disposal Site.

B. IRRADIATED AJEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None No shipments were made in 2020 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: There were no changes made that impacted the Process Control Program in 2020.

2)

References:

a. Units 1, 2 & 3 Licensee Controlled Specification Section 5. 7.1.3

b. Procedure SDS-WM1-PCD-0018, Radwaste Process Control Program.

c. Procedure SDS-CH2-PCD-1005, Annual Radioactive Effluent Release Report

d. Regulatory Guide 1.21, Rev. 1. Junr 1974 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS Gaseous Effluents Applicable Limits The percent of Applicable Umtts, tabulated in Sections A, B, C, and Oof Table 1A, were calculated using the following equation:

% Applicable Limit (%MPG) = (Rel Rate) (X/Q) (100)

MPCe.i* (1E+6) where: Rel Rate = total microcuries 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 0.2 of Table 1A, µCVsec.

X/Q = 4.BOE-6 sec/m 3; the annual average atmospheric dispersion defined in the OOCM.

1E+6 = conversion from m3 to cc

MPCeff where: F1 = 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.

n = total number of radionuciides identified MPG = Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix B, Table 11, Column 1.

% Applicable Umtt (% ECL) = (Rel Rate) (X/Q) (100)

EC~* (1E+6) where: Rel Rate = total microcuries 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 0.2 of Table 1A, µCi/sec.

X/Q = 4.BOE-06 sec/m 3; the annual average atmospheric dispersion defined in the ODCM.

1E+6 = conversion from m3 to cc

ECLeff where: F1 = fractional concentration of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, G, by the sum of all the isotopic activity, Cr.

n = total number of radionuclides identified ECL.i = 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 - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS (Continued)

Liquid Effluents Applicable Limits The percent of Applicable Limits, tabulated in Sections A, 8, and C of Table 2A, were calculated using the following equations:

% Applicable Limit (%MPG) = (Oil Cone) (100)

MP~

where: Oil Cone = 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, 8.2, and C.2 of Table 2A, µCl/ml.

l\1PCeff where: F, = 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.

n = total number of radionuclides identified MPCi = Maximum Permissible Concentration (MPC) of the ith radionuclide from 10 CFR 20 (20.1-20.602), Appendix 8, Table 11, Column 2.

% Applicable Limit (% ECL) = (Oil Cone) (100)

EC~

where: Oil Cone = 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, 8.2, and C.2 of Table 2A, µCl/ml.

ECLeff t~

l=IECL, where: F, = 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.

n = total number of radionuclides identified ECL = Effluent Concentration Limit (ECL) of the ith radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix 8, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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 11, Column 1.

B. Table 1E lists the air doses as calculated using the historical XJQ. 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 limned to the following values:

1. During any calendar quarter: s 5 mrad for gamma radiation and s 10 mrad for beta radiation.

2. During any calendar year: 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 untt) to areas at and beyond the stte boundary shall be limited to the following values:

1. During any calendar quarter. s 7.5 mrem to any organ.

2. During any calendar year. s 15 mrem to any organ.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -.2020 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 limtt 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 g~, 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: s 1.5 mrem to the total body and s 5 mrem to any organ.

2. During any calendar year: s 3 mrem to the total body and s 10 mrem to any organ.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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 independen~ and thus, the total error is calculated according to the following formula:

Total Error Where: Error is the 1 Sigma error associated with each process.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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 Stte boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the Stte boundary1. For members of the public who traverse the Stte 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 - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1 Dose" (millirems)

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

5)

Whole Body 5.55E-04 6.63E-03 4.89E-03 1.78E-02 2.99E-02

6) 7) 8) 9) 10)

Organ 3.0?E-03 2.24E-02 1.90E-02 1.43E-01 1.73E-01 AIRBORNE EFFLUENTS 11) 12) 13) 14) 15)

Tritium, Iodines, and 1.29E-04 2.55E-04 1.20E-04 8.39E-05 5.??E-04

-Particulates NOBLE GASES "" 16) 17) 18) 19) 20)

Gamma 0.OOE+O0 0.OOE+00 0.00E+00 0.OOE+O0 0.OOE+OO

21) 22) 23) 24) 25)

Beta 0.OOE+OO 0.OOE+O0 0.OOE+OO 0.OOE+OO 0.OOE+O0

26) 27) 28) 29) 30)

DIRECT RADIATION ND ND ND ND 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; the GI-LU received the maximum dose.

7. This value was calculated using the methodology of the ODCM; the GI-LU received the maximum dose.

8. This value was calculated using the methodology of the ODCM; the GI-LU received the maximum dose.

9. This value was calculated using the methodology of the ODCM; the Bone received the maximum dose.

10. This value was calculated using the methodology of the ODCM; the Bone received the maximum dose.

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

12. The maximum organ dose was to a Teen's Whole Body and was located in the WNW sector. This was calculated using the assumptions of USNRC NUREG-0133.

13. 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 - 2020 SAN ONOFRE NUCLEAR GENERATING STATION

14. The maximum organ dose was to a Teen's Whole Body and was located in the WNW 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 WNW 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. No noble gas radioactive effluent releases occurred during this quarter.

19. No noble gas radioactive effluent releases occurred during this quarter.

20. No noble gas radioactive affluent releases occurred during this year.

21. No noble gas radioactive affluent releases occurred during this quarter.

22. No noble gas radioactive effluent releases occurred during this quarter.

23. No noble gas radioactive affluent releases occurred during this quarter.

24. No noble gas radioactive effluent releases occurred during this quarter.

25. No noble gas radioactive effluent releases occurred during this year.

26. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2020 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would be 0.13 mrem based on 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year occupancy at the seawall rNNW sector).

27. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2020 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would be 0.18 mrem based on 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year occupancy at the seawall rNNW sector).

28. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2020 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would ba 0.16 mrem based on 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year occupancy at the seawall rNNW sector).

29. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2020 SONGS AREOR. Net dose par ODCM section 3.4.1.2 would be 0.13 mrem based on 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year occupancy at the seawall rNNW sector). TLDs 55 and 56 were removed from their stations by an unknown external action during 4111 quarter 2020. The 4020 dose for TLD 55 was estimated based on the a~erage of the first three quarters.

30. TLD doses reported as Not Detected per ANSI/HPS N13.37-2014 are reported in the 2020 SONGS AREOR. Net dose per ODCM section 3.4.1.2 would be 0.60 mrem based on 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months per year occupancy at the seawall (WNW sector). TLDs 55 and 56 were removed from their stations by an.unknown external action during 4th quarter 2020. The 4020 dose for TLD 55 was estimated based on the average of the first 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 Rav. 2 for evaluating dose to the public in the unrestricted area.

For 2020, 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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION TABLE2 Percent Applicable Umit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body 1.85E-02 2.21 E-01 1.63E-01 5.93E-01 4.98E-01 Organ 3.0?E-02 2.24E-01 1.90E-01 1.43E+00 8.67E-01 AIRBORNE EFFLUENTS Tritium, Iodines, and 8.62E-04 1.?0E-03 7.99E-04 5.59E-04 1.92E-03 Particulates NOBLE GASES Gamma 0.00E+OO 0.OOE+O0 0.OOE+OO 0.OOE+OO 0.OOE+00 Beta 0.OOE+00 0.OOE+OO 0.00E+O0 0.00E+OO 0.OOE+OO NOTE: Direct Radiation is not specifically addressed in the 10 CFR 50 Appendix I Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL Three separate revisions were made to the SONGS ODCM in 2020. These changes are described below and the complete ODCM Rev 16 is included as an attachment to the ARERR submittal with revision bars and dates included for each revision in 2020.

Revision 14 (Effective: February 4, 2020)

This incofTX)rates the following:

Revises the typical Condensate Monitor Tank radioactive liquid batch release flowrate from 100 gallons per minute per pump to 120 gallons per minute per pump.

Revises the maximum radioactive liquid tank batch release flowrate administrative limit from less than 95 gallons per minute to less than 110 gallons per minute.

Revision 15 (Effective: August 10, 2020)

This revision is in response to relocating the applicable Technical Specifications to Licensee Controlled Specifications in accordance with an NRG approved License Amendment.and incorporates the following:

Re-introduces the Radioactive Waste Secondary Tanks (T057/T058) as effluent release points.

Eliminates the administrative maximum release flowrate based on actual pump flowrates that are coptrolled by station procedures and will not adversely impact site dose resutts.

Updates Controlling Location Factors in Table 2-6 based on the most recent Land Use Census.

Updates Ri Tables in Appendix A based on the most recent Land Use Census.

Revises the Technical Specification references to the new LCS references.

Revision 16 (Effective: November 30, 2020)

This revision incorporates the following: . 'l

Eliminates Noble Gas monitoring requirements.

Removes the requirements related to short half-life isotopes, including 1-131.

Removes requirements for concurrent meteorology.

Adds Nickel 63 analysis requirements as they are a major isotope in station Part 61 analysis resutts.

Modifies dose for the Unit 1 Outfall.

Removes drinking water as an ODCM required monitoring parameter.

Revises the tanner Spent Resin Waste Handling process.

Each change was evaluated and approved according to the requirements in the ODCM and Licensee Controlled Specifications.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION Changes due to the Land Use Census The Land Use Census (LUC) for 2020 identified the same critical receptor locations and occupancy factors that were identified in the 2019 LUC. The Dose Assessment for the 2020 LUC was perfonned using the NRCDose3/GASPAR II program which includes some differences from the PARTS code used to calculate Controlling Location Factors (CLFs) previously. Therefore, the uJXlated CLF table is reported per ODCM 5.2.1 and will ba incorporated in the next feasible revision to the ODCM.

TABLE 2-6 UNITS 2&3 CONTROLLING LOCATION FACTORS1 LkRikWk Radionuclide mrem/yr per µCl/sec Use:

H-3 1.59E-03 San Onofre Recreational Beach (SORB, R-P3)

Mn-54 1.45E+01 San Onofre Recreational Beach (SORB, R-Q5)

Co-58 5.50E+O0 San Onofre Recreational Beach (SORB, R-Q5)

Co-60 1.84E+02 San Onofre Recreational Beach (SORB, R-Q5)

Ni-63 1.63E+01 Cotton Point Gardens (G-3)

Zn-65 8.16E+O0 San Onofre Recreational Beach (SORB, R-Q5)

Sr-90 7.75E+02 Cotton Point Gardens (G-3)

Cs-134 5.53E+01 San Onofre Recreational Beach (SORB, R-Q5)

Cs-137 8.21E+01 San Onofre Recreational Beach (SORB, R-Q5)

Ce-144 2.96E+01 San Onofre Recreational Beach (SORB, R-P3)

These values to be used in manual calculations are the maximum LkRikWk for all locations based on the most restrictive age group.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION J. CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS Changes to the Liquid Radioactive Waste Treatment System The 2018 ARERR for SONGS desclibed changes to the Uquid Radioactive Waste Processing (LRWP) System that added a standalone skid. This skid is a single-pass, non-sluiceable design using disposable canisters that is used for processing liquid wastes throughout the Decommissioning and Disman~ement (D&D) process. The original design of this system used two receiving tanks (T075 and T076) each with 25,000 gallons capacity.

In 2020, the system was modified to improve the efficiency of liquid radwaste releases by adding two larger capacity tanks for batch releases, the Secondary Radwaste Tanks (T057 and TOSS), each capable of holding 120,000 gallons.

The pump associated with these tanks has a higher capacity for recirculation, sampling, and batch release of processed liquid radwaste. This change does not affect the total quantity of liquid waste to be processed and released, the predicted nuclide concentrations in the processed waste, or the worker doses.

The Secondary Radwaste Tanks were at one time included In the SONGS ODCM and station procedures as batch release points for liquid radwaste. They were removed as a result of the transition from operation to decommissioning at SONGS. The reintroduction of these tanks also required modification of the LRWP System by adding an additional outlet valve and piping to allow the effluent of the processing skid to be delivered directly to the Secondary Radwaste Tanks. These modifications were performed using the site's design control process which included review in accordance with 10 CFR 50.59.

The change incorporated some existing plant equipment which was previously used for the same purpose and included:

Radiation monitor 2/3RE-7813 has been maintained and remains in service.

Valve 2/3HV-7642 (AOV) which is used to automatically close to terminate a release if a high radiation signal is received.

Valve 2HV-7644 (AOV) which is used to automatically close based on low dilution pump flow.

Existing piping for the Unit 2 Outfall release path remains in place.

The evaluation of the LRWP skid in 2018 assumed that releases would occur using T075 and T076 as the source and assumed one tank release per week at 25,000 gallons per tank. The evaluated change for including T057 and T058 as the source with two tank releases per month at 120,000 gallons per tank. The evaluation, described below in more detail, adequately demonstrated that the resulting estimated dose impact remains below the regulatory limits.

Dose estimate calculations were performed using T057 and TOSS tank volumes, maximum pump ftowrate, current minimum dilution requirements, and the maximum decay corrected concentration from the last valid sample of any liquid radwaste source, including the Spent Fuel Pools. Source terms used for the evaluation are shown in Table A for the radwaste source containing the highest actMty and Table B for Spent Fuel Pool. The source term for radwaste sources includes a decontamination factor (OF) to reduce the total gamma isotope concentration to 2.00E-5

µCi/ml, consistent with requirements for batch releases of liquid radwaste at SONGS. Tritium was reduced from the highest concentration based on dilution with the next highest concentration source. No reduction was made to the Spent Fuel Pool source term, because the current concentrations resulted in gamma activities < 2.00E-5 µCi/ml.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION Table A: Maximum Radwaste Inventory Concentrations

... *Nuc11~,e .. ;Act' ., µ',ls J . . ~* .:-~cf11Wm1 :,f Cl/mfi Decayedff*'

~ ~ ,_"

. . ,... .,,, l ,-1 4 , _, * *, t'

.. , :.~-. *f :: _; .*' ,ff,,**! C

,.; *';foF.,;ihu~edt;-

H-3 1.286E-01 7.641E-02 Mn-54 5.836E-09 1.842E-09 Co-57 4.764E-10 1.504E-10 Co-60 3.003E-05 9.481E-06 Sb-125 3.913E-06 1.235E-06 Cs-134 l.320E-06 4.168E-07 Cs-137 2.808E-05 8.864E-06 Kr-85 l.536E-03 1.536E-03

- Te>_tal:".. .:; ,Y-lf302E-Oi'*

C , * ,., * ,

~ ,,7'.~7~7E-04-.: ~_; ~

V..,

Table B: Spent Fuel Pool Source Tenn

.*, Nuclide : :: :*J-Ad ~Cl/ml,'. ~

';. :t\~ T~i; \ } ) : :

,~:1- !.f-1.r.,*, *"

f' -

'"!,, (Deeijye<f) *.;

/P- :,

H-3 3.390E-02 Co-60 2.108E-06 Sb-125 2.602E-06 Cs-134 5.372E-07 Cs-137 l.411E-05

-f.Tota1_ ~- r~; f~92E'..Q2.-:\

Projected doses were calculated using methodology specified in the SONGS ODCM with the conservative assumptions summarized in Table C. '

Table C: Inputs used for Dose Estimates Max Waste Flow Min. Dilution Flow Minimum dilution flow set at minimum output for a single dilution pump thou h two m are uired for actual releases .

Release Volume (per 120,000 gal Maximum tank volume used (though actual release volumes will be tank a roximatel 100 000 allons .

Administrative Factor 0.75 Minimum Administrative Factor AF to facilitate release.

Concentrations per nuclide Adjusted to a total gamma value of 2.0E-5 to simulate radwaste processing. (This represents the minimum reduction that is allowed for release.

The highest dose per tank was used from etther the Radwaste inventory or the Spent Fuel Pool inventory, as applicable. Table D shows calculations for dose projection based on two tank releases per month, six tank releases per quarter, and a total of eight tanks released (based on 800,000 gallons in inventory) for a year.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION Table D: Projected Dose Summary

_..,.,.,,[

,:-: ,:/Dose 4~':\ * :-.~~:i --*/ ~ 'MonthD6seJ.:.imic.~. :~:- -r~': :'.%\'Montl:l:Limif :,:.*-":*

/"

_';;, ~:;,~* -., ,Mot)tfi1i'i :'; ~; _:'/' ..,_*,,.,_

Whole Body mrem 7,76E-02 1 7.76%

Oroan mrem 1.91 E-01 3.3 5.79%

,,,,i"<.~=. Qua'i:ferr-\**;~, ** *,:;r ~** .>* ' -.-"'-*i* '/} :~.~-:~ ,~-;.~.~-:: . *.r-'-~Quartett>oselirntt' *;-i~. 2L~;:.~o/J Q'ua"rter Limit. _,.. ;*,

Whole Body, mrem 2.33E-01 3 7.76%

Orqan, mrem I 5.73E-01 10 5.73%

~:/ ~,~~:~\;~ftJlhLJaJ3 /}: ~~~~r~;:7S1 :<*, -;;:.~:/]~;: 0os*e~(! :.- ~*., ~Ji.'~ ' *:Aormal .Do$el..itnit.: :'.* :*_;:

s .' :,'!:,-.r:: ,%:Ann*ualJirJiit *,:<}/

Whole Body, mrem 3.10E-01 6 5.17%

1Organ, mrem 7.64E-01 20 3.82%

1 Based on 2 tanks per month and the highest dose for either SFP or Radwaste inventory.

2 Based oo 6 tanks per qu!l'ter and the highest dose result for either SFP or Radwaste Inventory.

3 Based on Btank releases total (800,000 gallons released), Including current Radwaste Inventory and one half the volume of each spent fuel pool.

The analysis demonstrated that the changes to the LRWP System made in 2020 met the requirements of the SONGS ODCM and 10 CFR 50 Appendix I.

Comparison of Projected Doses to SONGS Licensing Basis The Defueled Safety Analysis Report (DSAR) for SONGS had previously contained estimated annual doses associated with liquid radwaste discharges. These values, however, were reflective of operational conditions such as a dilution flow of 800,000 gpm circulating water system flow and other different assumptions for exposure pathway that were no longer applicable. Since these estimated values were not reflective of the current projected doses, they were deleted from the DSAR in 2020. Comparison of the values in Table D to these obsolete values would not be meaningful, but rather the values in Table D conservatively establish accurate projected doses for the current plant conditions.

Comparison of Actual 2020 Liquid Doses to Hlstorf cal Liquid Doses.

A comparison to historical liquid release annual doses from annual effluent reports (ARERRs) since 2005 is presented in Table E and Figure t, below. This table indudes the percent of ODCM annual liquid effluent dose limit (6 mrem to the whole body and 20 mrem to any organ for two units). The projected annual dose has been included at the bottom of Table E. The data from 2005-2012 include releases during plant power operation while data from 2013 onward indude only releases following final plant shutdown. The data demonstrate that annual doses due to liquid effluent releases did not change significantly from the doses calculated during plant operation. The doses are a very small fraction of the limits in the ODCM based on 10 CFR 50, Appendix I.

Additionally, the ODCM requires the radwaste system to be functional and used to reduce radioactive materials in liquid wastes when the dose would exceed 0.06 mrem total body and 0.2 mrem to any organ over a 31-day period; annual doses do not reach that threshold, without considering the smaller 31-day doses. Therefore, current liquid releases remain ALARA.

ANNUAL RAQIOACTIVE EFFLUENT RELEASE REPORT - 2020

\

SAN ONOFRE NUCLEAR GENERATING STATION Table E: Historical Liquid Doses from SONGS ARERRs.

Total Bodv Max Organ Crltlcal Year Dose (mrem) % Limit Dose (mrem) % Limit Organ 2005 * -3.22E-02 0.54% 7.12E-02 0.36% GI-LU 2006 9.15E-04 0.02% 1.29E-03 0.006% Liver 2007 4.83E-03 0.08% 1.35E-02 0.07%- GI-LLI 2008 2.61E-03 0.04% 1.12E-02 0.06% GI-LLI 2009 2.16E-03 0.04% 5.48E-03 : 0.03% GI-LU 2010 1.96E-03 0.03% 4.56E-03 0.02% GI-LU 2011 2.02E-03 0.03% 2.85E-03 0.01% GI-LU 2012 4.75E-03 0.08% 2.83E-02 0.14% GI-LU 2013 7.90E-03 0.13% 3.61E-02 0.18% GI-LU 2014 2.27E-03 0.04% 3.65E-03 0.02% GI-LU 2015 2.85E-04 0.005% 3.72E-04 0.002% Liver 2016 1.59E-04 0.003% 2.42E-04 0.001% Liver 2017 0.00E+00 0.000% *o.OOE+00 0.000% N/A 2018 2.67E-03 0.04% 3.81E-03 *0.02%- Liver 2019 1.07E-04 0.002% 1.57E-04 0.001% Liver 2020 2.99E-02 0.50% 1.73E-01 0.87% Bone Predicted* : 3.-10E~L,: ::- * -5,2%-_ >- ,), *: .-7:6,JE.:Ot : . < ,:3.82% *., "Gt-U(, _;-,

20 -; - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - -

t 1

Eis "-

f ~

.§.

"'C QI >

t:

QI a:: 5 -r r---------------------------------------------

~

}

l-o -~--,-; * * ?t * * * )I(

W M Ml II !II! * -,\: -

2004 2006 2008 2010 2012 2014 2016 2018 2020

-rotalBody - - -Total Body Dose Limit (6 mrem) 1

-+- Max other organ - - -Organ Dose Limit (20 mrem)

Figure 1: Doses due to Liquid Effluents from SONGS 20~2020 ARERRs with ODCM Limits shown for two units.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS ABNORMAL RELEASES There were no abnonnal releases from SONGS in 2020.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K MISCELLANEOUS (Continued)

EFFLUENT MONITORING INSTRUMENTS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2020 - December 31, 2020 Instrument lnoperability Period lnoperability Cause Explanation Sample flow was found to be lower than 2/3RE-7813 Liquid required which resulted in the need to Radwaste Radiation change the flow restricting orifice. The Monitor Flow indicator switch issue time out of service was due to design, 2/27/20'20-5/5/2020 FE7643 Process Flow and sample flow issue installation, and testing of the revised 2/3FISL-D7813 Sample configuration. No liquid radwaste flow indicator discharges were made while monttor was non-Functional.

Temperature indication was not working correctly due to an issue with toggle swttches on the controller cards of 3RE-7828 Untt 3 multiple heat trace circuits. The affected Heat Trace over-Containment Purge 5/4/2020-6/15/2020 heat trace controllers continued to temperature indication Radiation Monttor provide heating to lines and only temperature indication was affected.

This issue required locating and testing/refurbishing replacement cards.

\

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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.

Groundwater sample data 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 2020 show no detectible tritium or gamma activity in groundwater 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.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K MISCELLANEOUS (Continued)

ONSITE GROUND WATER SAMPLES January 1, 2020 - December 31, 2020 Tritium Activity Gamma Activity Location Sample Date oCi/1 pCl/1 GW-NIA-1 03/20/20 <MDC NIA GW-NIA-1 05/06/20 <MDC N/A GW-NIA-1 09/03/20 <MDC NIA GW-NIA-1 10/28/20 <MDC NIA GW-NIA-2 02/27/20 <MDC NIA GW-NIA-2 04/30/20 <MDC N/A GW-NIA-2 09/03/20 <MDC N/A GW-NIA-2 10/'29/20 <MDC NIA GW-NIA-12 02/27/20 <MDC NIA GW-NIA-12 04/30/20 <MDC NIA GW-NIA-12 09/09/20 <MDC N/A GW-NIA-12 10/29/20 <MDC N/A GW-NIA-13 02/27/20 <MDC N/A GW-NIA-13 05/06/20 *<MDC NIA GW-NIA-13 09/09/20 <MDC N/A GW-NIA-13 10/28/20 <MDC N/A GW-OCA-1 02/13/20 <MDC N/A GW-OCA-1 04/29/20 <MDC N/A GW-OCA-1 09/02/20 <MDC NIA GW-OCA-1 11/04/20 <MDC NIA GW-OCA-2 02/10/20 <MDC NIA GW-OCA-2 04/27/20 <MDC N/A GW-OCA-2 08/31/20 <MDC NIA GW-OCA-2 10/26/20 <MDC NIA GW-OCA-3 02/06/20 <MDC NIA GW-OCA-3 04/23/20 <MDC NIA GW-OCA-3 08/24/20 <MDC NIA GW-OCA-3 10/22/20 <MDC N/A GW-PA-1 03/09/20 <MDC <MDC GW-PA-1 06/03/20 <MDC <MDC GW-PA-1 07/29/20 <MDC <MDC GW-PA-1 10/12/20 <MDC <MDC GW-PA-2 03/09/20 <MDC <MDC ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 SAN ONOFRE NUCLEAR GENERATING STATION Tritium Activity Gamma Activity Location Sample Date pCl/1 pCi/1 GW-PA-2 06/03/20 <MDC <MDC GW-PA-2 07/'29/20 <MDC <MDC GW-PA-2 10/12/20 <MDC <MDC GW-PA-3 03/20/20 <MDC <MDC GW-PA-3 06/10/20 <MDC <MDC GW-PA-3 08/19/20 <MDC <MDC GW-PA-3 10/14/20 <MDC <MDC GW-PA-4 03/02/20 <MDC <MDC GW-PA-4 06/11/20 <MDC <MDC GW-PA-4 08/20/20 <MDC <MDC GW-PA-4 10/15/20 <MDC <MDC NIA-3 05/07/20 <MDC NIA NIA-4 05/14/20 <MDC NIA NIA-5 05/13/20 <MDC NIA NIA-6 05/14/20 <MDC NIA NIA-7 05/13/20 <MDC NIA NIA-10 05/11/20 <MDC NIA NIA-11 05/11/20 <MDC NIA NIA-14 05/27/20 <MDC NIA NIA-15 05/27/20 <MDC NIA GW-OCA = Wells installed in the Owner Controlled Area to Implement the Ground Water Protection Initiative.

GW-PA = Wells installed In the Protected Area to implement the Ground Water Protection Initiative.

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

NIA = Temporary investigation wells installed in the North Industrial Area.

a priori LLD = 1-1-3: 3000 pCin

= Gross Beta: 4.0 pCi/1

= Gross Alpha: 3.0 pCl/I Values above MDC are reported as calculated The Beta and Alpha reported are of natural origin and not from plant operation based on the laboratory analyses.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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 all effluent pathways and direct radiation. The dtfferent categories presented are: (1) Total Body, (2) Limiting Organ, and (3) Thyroid.

Dose Category Units Year

1. Total Body

a. Total Body Dose mrem 1.11 E-01

b. Percent ODCM Specification Umit % 4.43E-01

2. Umiting Organ

a. Organ Dose (All except thyroid) (Bone) mrem 1.73E-01

b. Percent ODCM Specification Umit % 6.93E-01

3. Thyroid

a. Thyroid Dose mrem 2.22E-03

b. Percent ODCM Specification Umit % 2.96E-03 NOTE: The 40 CFR 190 dose detennination above used TLD dose of 0.0 mrem based on annual dose detennination of Not Detected shown in Table 1 on page 27. If using the net dose methodology from the ODCM, Total Body dose would be 6.0E-01 mrem.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2020 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-0117. 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 2 to RG 1.21 guidance inch:1des:

If sampling is performed, the sampling frequency may be adjl:lsted 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, 1A, 1C, 1E, 2 and 40 CFR 190 Table 1.

U2 =0 Calculated C-14 production, Ci/EFPY(1l U3 =0 U2 = 0 2020 Unit capacity factors U3 = 0 Fraction release of produced C-14 to atmosphere 0.98 Organic = 0.80 C-14 chemical form fraction assumed Inorganic = 0.20 U2 =0 C-14 curies released to atmosphere U3 =0 Critical receptor dose<2l (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 - 2020 SAN ONOFRE NUCLEAR GENERATING STATION SECTION L SONGS CONCWSIONS

1) Gaseous releases (excluding carbon-14) totaled 1.05E+01 curies of which noble gases were 0.OOE+OO curies, particulates were 2.39E-05 curies, iodines were O.00E+OO curies, and tritium was 1.05E+01 curies.

2) The radiation doses from gaseous releases were: (a) gamma air dose: 0.00E+O0 mrad at the site boundary, (b) beta air dose: 0.00E+O0 mrad at the site boundary, (c) organ dose (Teen - Skin): 5.77E-04 mrem at the highest receptor.

3) Airborne carbon-14 release was projected at 0.OOE+OO curies due to the fact that both Units 2 and 3 have been pennanently shut down since January 2012.

4) Liquid releases totaled 2.43E+01 curies of which particulates were 2.61 E-02 curies, iodines were 0.OOE+00 curies, tritium was 2.43E+01 curies, and noble gases were 0.00E+00 curies.

5) The radiation doses from liquid releases were: (a) total body: 2.99E-02 mrem, (b) limiting organ (Bone):

1.73E-01 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 36 shipments of solid radioactive waste were made from SONGS in 2020 via rail, Type A Cask, and tractor trailer transportation modes. These shipments included 1.85E+03 m3 (predominantly Dry Active Waste by vol~me) and 5.99E+3 Ci (predominantly 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. No groundwater samples in 2020 indicated detectible concentrations of tritium or 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 2020. 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 operatlon 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 - 2020 METEOROLOGY METEOROLOGY The Offsite Dose Calculation Manual (S0123-0DCM, Ref.2.2.14) 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. The Gaseous Radwaste System (GRWS) was removed from service in November 2015.

Containment ventilation operation was changed in 201 s* 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, 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 (Ref.2.2.14).

Since the weather pat!.erns have not substantially changed and the deposition and dispersion coefficients have been updated with recent data, and batch releases are no longer perrormed at SONGS, the use of historical meteorology is the preferred method for determining offsite dose. k. 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.

ENCLOSURE 2 Description of Changes to the Offstte Dose Calculation Manual Sections During 2020

During 2020, three revisions were made to the SONGS ODCM (SO123-ODCM) along with two revisions to ODCM Appendix A. There was no revision of ODCM Appendix B during 2020. The summary descriptions below are excerpted from the referenced ODCM revisions.

Revision 14 (Effective: February 4, 2020)

This revision is in response to AR 0120-34322 and incorporates the following:

Revises the typical Condensate Monitor Tank radioactive liquid batch release flowrate from 100 gallons per minute per pump to 120 gallons per minute per pump.

Revises the maximum radioactive liquid tank batch release flowrate administrative limit from less than 95 gallons per minute to less than 110 gallons per minute.

Throughout the document, change bars indicate the following types of changes:

A Addition D Deletion F EdltoriaVFormat change R Revision PAGE DESCRIPTION OF CHANGE REASON Cover Updated revision number and effective date. F 1-13 Revised Condensate Monitor Tank Release rate from 100 gpm to 120 gpm. R 1-13 Revised administrative release rate limit from 95 gpm to 110 gpm. R Page 1-13 was also changed in Revision 15 of the ODCM. The version of this page from Revision 14 of the ODCM is attached because the later change in Rev. 15 affected the same text that was changed in Rev. 14.

Revision 15 (Effective: August 10, 2020)

This revision is in response converting site Technical Specifications to Licensee Controlled Specifications and in response to AR 0120-34322. It incorporates the followlng:

Re-introduces the Radioactive Waste Secondary Tanks (T057ff058) as effluent release points.

Eliminates the administrative maximum release ftowrate which is only slightly conservative based on actual pump ftowrates, is controlled by station procedures, and will not adversely impact site dose results.

Updates Controlling Location Factors in Table 2-6 based on the most recent Land Use Census.

Updates Ri Tables In Appendix A based on the most recent Land Use Census.

Revises the Technical Specification references to the new LCS references PAGE DESCRIPTION OF CHANGE REASON Cover Updated revision number and effective date. F 1-2 Added Radioactive Waste Secondary Tanks (T057ff058) and other tanks identified in A station procedures to Table 1-1 A NOTE.

1-6 R Changed Technical Specification reference to Licensee Controlled Spectfication.

1-7 1-13 Added Radioactive Waste Secondary Tank =160 oom to factor R discussion. A Removed administrative release rate limit D Deleted "(per pump)" instances D 2-5 R Changed Technical Specification reference to Ucensee Controlled Specification.

2-6 2-15 Changed bottom bullet from "(X/Q), 7.2E-8 sec/m3" to read "(D/Q), 7.2E-8 m-2 " for NIA R 2-22 Updated Controlling Location Factors based on the most recent Land Use Census R 3-1 Chanoed Specification 2.4.1 to 2.3.1 R 3-2 Chanqed Spectfication 6.9.1 to 5.7.1 R 4-19 Added "Radioactive Waste Secondarv Tank(s)" to the flow chart A Changed Technical Specification reference to Licensee Controlled Specification R 5-1 Deleted reference to Unit 1 Pennanently Defueled Technical Specification 06.9.1 D 5-2 Changed Technical Specification reference to Licensee Controlled Soecification R Deleted reference to Unit 1 Pennanently Defueled Technical Specification 06.9.1 D 5-11 Chanqed Technical Specification reference to Licensee Controlled Specification R Deleted reference to Unit 1 Pennanently Defueled Technical Specification 06.9.1 D Changed Specification 5.1 to 5.1.1 R 5-16 R 5-17 Changed Technical Specification to Regulatory Guidance 5-19 App A Updated Ri Tables based on the most recent Land Use Census. R Page 2-22 is included as a separate attachment because this page was significantly changed in both Revisions 15 and 16.

ODCM Appendix A Revision 14 is included as a separate attachment because it was fully revised as both Revision 14 and Revision 15 during 2020.

All other changes from ODCM Rev. 15 are shown as change bars in the attached Rev. 16.

Revision 16 (Effective: November 30, 2020)

This revision incorporates the following:

Eliminates Noble Gas monitoring requirements

Removes the requirements related to short half-life isotopes, including 1-131

Removes requirements for concurrent meteorology

Adds Nickel 63 analysis requirements as they are a major isotope in station Part 61 analysis results

Modifies dose for the Unit 1 Outfall

Removes drinklng water as an ODCM required monitoring parameter

Replaces former Spent Resin Waste Handling process with new SOS process See attached ODCM Rev. 16 for Description of Changes table.

ODCM Appendix A Rev. 15 and ODCM Appendix B Rev. 9 are included as separate enclosures.

Enclosure 3 Offsite Dose Calculation Manual San Onofre Nuclear Generating Station (SONGS)

SO123-ODCM Revision 16, November 2020

November 30, 2020 Mr Doug _Ba1,Jder

SUBJECT:

. $an Onofre Nuclear Generating Station (SONGS) Offsite Dose Calculation Manual (ODCM) and Appendices: S0123-0DCM Revision 16, S0123-0DCM-A Revision 15, and S0123-0DCM.-B Revision 9 In accordance with Licensee Controlled Specification 5.5.2 1, revisions to the SONGS Offsite Dos~ Calculation Manual and Appendices.have been prepared-and reviewed for_you-r approval.

ODCM effluent screens and evaluations were performed to ensure the site's regulatory requirements of the Licensee Controlled Specifications and license basis were not cha.llenged. These ctiange~ to the ODCM and Appendrces have been documented in the SDS Electronic Documentation Management System.

This revision incorporates the foOowing:

Eliminates Noble Gas monitoring requirements .

Removes the requirements related to short half:-life iso'~opes, including 1-131

Ren:ioves requirements for concurrent meteorology

Adds Nick.el 63 analysis requirements as they are a major isotope in station Part 61 analysis results

Modifie$ do~e for the Unit 1 Outfall

Removes drinking water as an ODCM required monitoring parameter

Replaces fonner Spent Resin Waste Handling process w'ith new SOS process None of the changes in these revisions will adversely affect the accuracy or reliabflity of effluent dose calculations or set point determinations_ Your approval for these revisions ls requested. *

~ R E M P S~allst It there are all'jl questions.

obert L. Mccann ODCM/REMP Speclaffst (SOS)

~~w OOCM/REMP Specialist (SOS) o and Waste Contract Management (SCE)

Approved Qy:

D u er Vice President Decommissioning and Chief Nuclear Officer (SCE}

Attachment cc: eDMRM NRA File

Throughout the document, change bars indicate the following types of changes:

A Addition D Deletion F Editorial/Format change R Revision PAGE DESCRIPTION OF CHANGE REASON Cover Updated revision number and effective date. F i Deleted Dose- Noble Gas from Table of Contents 2.2 D i Deleted radio-iodines from Table of Contents 2.3 D ii Deleted Methods of Calculation for Gaseous Effluent Monitor D Setpoints from Table of Contents 2.6 ii Deleted For Noble Gas from Table of Contents 2.7.1 D ii Deleted radio-iodines, "all" (radioactive materials) and "with half-lives D greater than 8 days" from Table of Contents 2.7.2 ii Deleted Dose from Noble Gas in Gaseous Effluents from Table of D Contents 2.8.1 ii Deleted radio-iodines from Table of Contents 2.8.2 D ii Deleted concurrent Meteoroloav from Table of Contents 2.8.2.2 D ii Deleted Annual Total Thyroid Dose Dtot (T) from Table of Contents D 3.4.1.3 V Deleted dose factors for Noble Gases and Daughters from List of D Tables Table 2-4 vii Removed gaseous effluent monitoring instrumentation alann / trip D setpoints 1-1 Deleted references to dissolved or entrained noble gases from D Specification 1.1.1 1-2 Deleted Dissolved and Entrained Gases (gamma emitters) 1-131 and D Sr-89 from Tables 1-1A and 1-18 1-2 Added Ni-63 to Tables 1-1A and 1-1 B A 1-2 Deleted NOTE for Table 1-1 B D 1-2 Added Unit 2 Turbine Plant Sump to Table 1-1 B A 1-3 Deleted Sr-89 from Table 1-1C D 1-3 Added Ni-63 to Table 1-1 C A 1-5 Deleted short half-life isotopes from Note f D 1-11 Deleted Xe-133 and Sr-89 from Equation 1-3 D 1-11 Added Ni-63 to Equation 1-3 A 1-12 Added Ni-63 to Eauation 1-4 A 1-12 Deleted Note for D&E qases D 1-13 Deleted reference to Xe-133 from Y1C' y1 D 1-14 Deleted Xe-133 and Sr-89 from Eauation 1-3 D 1-14 Added Ni-63 to Equation 1-3 A 1-15 Added Ni-63 to Equation 1-4 A 1-16 Deleted reference to Xe-133 from }::iC'yi D 1-17 Removed reference to either outfall D 1-19 Changed "maximum" waste flow to "average" waste flow R 1-20 Deleted short half-life isotopes from Table 1-4 D 1-20 Added Ni-63 to Table 1-4 A 1-21 Deleted short half-life isotopes from Table 1-4 D 2-1 Deleted 2.1.1.a For Noble Gases from Specification 2.1.1 D 2-1 Deleted "all" (radioactive materials) and "with half-lives greater than D 8 days" from 2.1.1.b and 2.1.1.2

2-1 Deleted 2.1.1.1 Surveillance Requirement dose rate due to noble D aases 2-1 Deleted radio-iodines from Specification 2.1.1 b and 2.1.1.2 D 2-2 Deleted the following from Table 2-1: continuous sampling for Noble D gases, tritium, Principal Gamma Emitters, Continuous Sampler 1-131, 1-133, Sr-89, and Noble Gas Continuous Monitor 2-2 Added Ni-63 to Table 2-1 A 2-4 Removed reference to Specification 2.2.1 from note f D 2-4 Deleted short half-life isotopes from Note a D 2-4 Added "and those listed in Rea. Guide 1.21"to Note a A 2-4 Deleted "and iodine' from Note h D 2-4 Changed note e tritium requirement from when fuel in in the SFP to R when water is in SFP 2-5 Deleted 2.2 Dose - Noble Gas D 2-6 Deleted radio-iodines from Soecification 2.3, 2.3.1, and Action a D 2-6 Section 2.3.1 and Section 2.3.1 Action a - removed "with half-lives D greater than 8 davs" 2-7 Deleted reference to Turbine Building, Main Condenser Evacuation, D and Turbine Gland Seal from Figure 2-2 2-8 Inserted page holder for previously deleted Section 2.5 A 2-8 Deleted Methods of Calculation for Gaseous Effluent Monitor D through Setpoints 2-12 (old page numbers) 2-13 (old Removed previously deleted placeholders F page numbers) 2-9 Section 2.7.2 removed "all" (radioactive materials) and "with half-lives D areater than 8 davs" 2-9 Deleted 2.7.1 For Noble Gas D 2-9 Deleted radio-iodines from Specification 2.7.2 D 2-9 Removed reference to continuous or batch as all gaseous releases D are now continuous 2-9 Updated Maximum Dispersion Factors Wk for Equation 2-15 R 2.11 Deleted 2.8.1 Dose from Noble Gas in Gaseous Effluents D 2-12 Deleted radio-iodines and "with half-lives greater than 8 days" from D Specification 2.8.2 2-12 Updated method for data derivation from NRC code, PARTS to NRC R code GASPAR 2-12 Revised definitions for Wk R 2-13 Deleted Specification 2.8.2.2 Concurrent Meteoroloav D 2-14 Deleted Table 2-4 D 2-15 Added Ni-63 to Dose Parameters in Table 2-5 A 2-15 Deleted Dose Parameter for short half-life isotopes from Table 2-5 D 2-16 Added Ni-63 to Controllina Location Factors Table 2-6 A 2-16 Deleted controlling location factors for short half-life isotopes from D Table 2-6 2-17 Added "intentionally" A 2-18 Added "intentionally" A 3-1 Deleted aamma/beta dose from Gaseous Dose Protection D 3-4 Deleted D11 (v) from Eauation 3-3 D

3-4 Revised D(U1) R 3-4 Added Effluent/ODCM Evaluation SDS-CH2-EVA-0008 to Reference A 3-6 Deleted Annual Total Thyroid Dose Dtot m D 4-2 Removed previously deleted placeholders F 4-2 Added ISFSI CDAS A 4-5 Added ISFSI CDAS

A 4-5 Removed previously deleted placeholders F 4-6 Updated procedure number for Software Development and R Maintenance 4-7 Uodated Step 4.2.1 for alarm function of samplina instrumentation R 4-8 Deleted iodine Sampler Instrumentation from Table 4-3 D 4-8 Deleted Noble Gas Activity Monitors from Table 4-3 D 4-8 Removed previously deleted place holders1 from Table 4-3 F 4-8 Removed 2RT-7865 and 3RT-7865 under Plant Vent Stack (e) D 4-8 Added Plant Vent Stack and Ctrnt Purge System identifiers A 4-9 Deleted Note 2 a'nd 3 from Table 4-3 D 4-9 Deleted iodine from Table 4-3, Action 36 D 4-9 Deleted Action 37 D 4-10 Deleted Iodine from Table 4-3 Action 41 D 4-10. Added Plant Vent Stack and Ctmt PurQe System identifiers A 4-11 Removed previously deleted placeholders from Table 4-4 F 4-11 Deleted Noble Gas Activity Monitors D 4-11 Deleted Iodine Sampler Instrumentation from Table 4-4, 1b, and 2b D 4-12 Removed previously deleted placeholders from Table 4-4 F 4-12 Deleted Iodine Sampler Instrumentation from Table 4-3, 3a D 4-13 Deleted Notes - 1 2 3, and 7 from Table 4-4 Notation D 4-16 Removed Radiation Monitors 2RT-7865 and 3RT-7865 from Figure 4- D 6

4-16 Replaced Radiation Monitor for 7808 with sample skid R 4-17 Replaced former Spent Resin Waste handling process with new SOS R process 4-17 Deleted SRT and IX from Lec:iend of Figure 4-7 D 5-3 Deleted Iodine from Table 5-1 D 5-4 Deleted Drinking Water Pathway D 5-5 Removed 1-131 analysis for local crops D 5-6 Deleted Table 5-1 Noted and Note g D 5-7 Deleted short half-life isotooes from Table 5-2 D 5-7 Deleted notes a and b related to drinkinQ water. D 5-8 Deleted short half-life isotooes from Table 5-3 D 5-10 Deleted notes band d related to drinkinQ water. D 5-13 Replaced Section 5.4.1 with verbiage from LCS 5. 7 .1.2 R 5-15 Renamed TLD #40 to "SONGS Garden - Mesa" R 5-16 Renamed TLD #66 to "San Onofre State Beach Park" R 5-18 Revised note - to clarify SONGS Garden location R 5-18 Removed DnnkinQ Water from Table 5-4 D 5-23 Removed drinking water from Figure 5-2 D 5-24 Removed drinking water from Figure 5-3 D 5-25 Removed drinkinQ water from FiQure 5-4 D 5-26 Removed drinkinQ water from Figure 5-5 D 6-3 Deleted Iodine from Definition 6.1.13. Deleted statement about no D longer any permanent ventilation exhaust treatment systems in use at SONGS.

6-3 Section 6.1.13 removed "(such a system is not considered to have any D effect on Noble gas effluents)"

6-7 Deleted discussion of concurrent meteorology requirements from D Administrative Controls 6.2.2 6-7 Replaced Section 6.2.1 with verbiage from LCS 5.7.1.3 R 6-7 Replaced "unit" and "unit or station" with LCS terminology "Facility" in R Section 6.2.2 6-10 Deleted discussion about dissolved and entrained gases from D Bases 6.4.1 6-10 Replaced "reactor" with "unit in 6.4.2 R 6-11 Removed explanation for gaseous radwaste treatment system in 6.4.4 D 6-11 Removed release rate limit restrictions from noble gases to total body D and to the skin in 6.4.4 6-11 Replace "reactor with "unit" in 6.4.2 R 6-12 Deleted Dose - Noble Gases Bases 6.4.5 D 6-12 Deleted Radio-Iodines from Bases 6.4.6 D 6-14 Revised Bases 6.4.9 Radioactive Gaseous Effluent Instrumentation R

OFFSITE DOSE CALCULATION .MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION (SONGS)

SO123-0DCM Revision 16 11/2020

ODCM TABLE OF CONTENTS

. Page LIST OF FIGURES ....... :............................................. :.................................. :................ :............... iv LIST OF TABLES ......................................................................................:...... .'.................... :.......... V LIST OF APPENDICES ....................... .'.......................................................................................... vi INTRODUCTION ................ :... :............................... :............................................................... .'..... vii 1.0. LIQUID EFFLUENTS ................... :............................................................._........ 1-1 thru 1-22 1.1 Concentration .. ... .. ........ .. ....... .. .. ... .. .... .. .. .... .. ......... .. .. .. .. .... .. .. ... ..... .... .. .. .. ...... .. ... . 1-1 1.1.1 Specification .............................................................................................. 1-1 1.1.1.1, 1.1.1.2 Surveillance Requirements .... :............_.......................... :............... 1-1 1.2- Dose .................. :...................................... ,........................................................... 1-6 1.2.1 Specification ..................................... ~ ........................................................... 1-e 1.2.1.1 Surveillance Requirement ........................................................................... 1-6 1.3 Liquid Waste Treatment .................................. :................................ :..................... 1-7.

1.3.1 Specification ....................... , ..........................................: .............................. 1-7 1.3.1.1, 1.3.1.2, Surveillance Requirements .................. :....................................... 1-7 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation ........................................ 1-9

-1.4.1 Batch Release Setpoint Determination ...................... ,................................ 1-11 1.4.~. Continuous Relea.se ~etpoint Determination ................... ,...... :................... 1-14:

1.5 Dose Calculation for Liquid Effluents ............................. ,.... :.................... ,........... 1-19 1.6 Representative Sampling ................................................................... :................ 1-21 2.0 GASEOUS EFFLUENTS .................................................................................... 2-1 thru 2-25 2.1 Dose Rate .............. :..................................... :... -.............................*........................ 2-1 2.1.1 Specification* ............................... .' ...................... .'................................. :....... 2-1 2.1.1.1, 2.1.1.2 Surveillance Requfrements .......................................................... 2-1 2.2 Dose - Noble Gas - DELETED .........................................................*...................... 2-*5.

2.3 Dose - Radioactive Materials in.Particufate Form and Tritium .......... :................... 2-6 2.3.1 Specification ........................................... :.............................. ::.................... 2-6

2.3.1.1 Surveillance Requireme:nt .......................................................... :................ 2-6 SO123-0DCM Revision 16 11/2020 .

7 ODCM TABLE OF CONTENTS (Continued)

Page 2.4 Gaseous Radwaste Treatment - DELETED ............................. '. .....'...................... 2-6 2.5

DELETED, moved to Section 3 2.6 2.7 Methods_ of Calculation for Gaseous Efflue~t Monitor S~tp~ints - DELETED ....... '. 2-8.

Gaseous Effluent Dose Rate, ................................ :........ :.............................. : ....... 2-9 I~

2.7.1 For Noble Gas - DELETED ........................................... ,., ......................... : 2-9 *-

2.8 2.7.2 For Tritium and Radioactive Materials in Particulate Form ........;. .. '. .... :........ 2-9 Gaseous Effluent Dose Calculation ..................................................................... 2-10 I~

2.8.1 Dose from Noble Gas in Gaseous Effluents - DELETED ........................ 2-10 2.8.2 Dose from Tritium and Radioactive Materials in Particulate Form

in.Gaseous Effluents ...............................................................'................ 2-1.1 2.8.2.1 For Historical Meteorology ......... : ................................ ,... -..................... ,. 2-11 2.8.2.2 For Meteorology Concurrent with Releases - DELETED ................... : ..... 2-12 3.0 PROJECTED DOSES ................................................................................. .'...... 3-1 thru 3-6 3.1 Liquid Dose Projection .....................:................................. ;.......................... ;.:.-.... 3-1 3.2 Gaseous Dose Projection ... : ................................................................................ 3 3.3 Total Dose .......... : ........................-.......................................................................... 3-2 3.3.1 Specification ... :............ L .......................... '. ................................................. :3=-2

3.3.1.1 Surveillance Requirement .................................................. .-....................... 3-2

3.4 Total Dose Calculations .......... : ... -... :... : .......................-........................................... 3-3.

3.4.1 Jotal Dose to Most Likely Member of the Publ.ic ................................ : ...... J:-3 3.4.1.1 Annual.Total Organ Dose [Di-or* (0)) ..................................................... :.... 3-3 3.4.1.2 Annual Total \Mlole Body Dose Dror (\(\/8) . .-.................................. : ........... 3-4 .. I~

3.4.1.3 Armual Total Thyro,id Dose Dror (T).:. DELETED ................. :................... .'.. 3-6 ~

SO123-ODCM Revision 16

11/2020 ii

ODCM TABLE OF CONTENTS (Continued)

Page 4.0 EQUIPMENT .................................................................................................... 4-1 thru 4-21 4.1 Radioactive Liquid Effluent Monitoring Instrumentation ........................................ 4-1 4.1.1 Specification ............................................................................................. 4-1 4.1.1.1, 4.1.1.2 Surveillance Requirements ......................................................... 4-1 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation ................................... 4-7 4.2.1 Specification ............................................................................................. 4-7 4.2.1.1 Surveillance Requirement ......................................................................... 4-7 4.3 Functionality of Radioactive Waste Equipment .................................................. 4-14 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ....................................... 5-1 thru 5-26 5.1 Monitoring Program ............................................................................................. 5-t 5.1.1 Specification ................................................................................................ 5-1 5.1.1.1 Surveillance Requirement .. .. .. .. .. .. ... ..... .. ... .. ... .. ... ... .... ... ... .. .. .... .... ..... .. .. .. .. 5-2 5.2 Land Use Census .............................................................................................. 5-11 5.2.1 Specification ........................................................................................... 5-11 5.2.1.1 Surveillance Requirement ....................................................................... 5-11 5.3 lnterfaboratory Comparison Program ................................................................. 5-12 5.3.1 Specification ........................................................................................... 5-12 5.3.1.1 Surveillance Requirement ....................................................................... 5-12 5.4 Annual Radiological Environmental Operating Report ......................................... 5-13

\

5.5 Sample Locations .............................................................................................. 5-14 6.0 ADMINISTRATIVE ........................................................................................... 6-1 thru 6-15 6.1 Definitions ............................................................................................................ 6-1 6.2 Administrative Controls ........................................................................................ 6-7 6.3 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) ............................................................................................................. 6-9 6.4 Bases ................................................................................................................. 6-10 SO123-0DCM Revision 9 11/2015 iii

ODCM LIST OF FIGURES Figure Title Page 1-2 Site Boundary for Liquid Effluents ..................................................................................... 1-8 2-2 San Onofre Nuclear Generating Station Site Boundary for Gaseous Effluents ................ 2-7 4-5 SONGS Radioactive Liquid Waste Effluent Systems ..................................................... 4-15 4-6 SONGS Radioactive Gaseous Waste Effluent Systems ................................................ 4-16 4-7 Solid Waste Handling .................................................................................................... 4-17 5-1 Radiological Environmental Monitoring Sample Locations 1 Mile Radius .~*************:************************************************************************************************* 5-22 5-2 Radiological Environmental Monitoring Sample Locations 2 Mile Radius .................................................................................................................. 5-23 5-3 Radiological Environmental Monitoring Sample Locations 5 Mile Radius ................................................................................................................. 5-24 5-4 Radiological Environmental Monitoring Sample Locations Orange County ......................................... .................. ............................................. ...... 5-25 5-5 Radiological Environmental Monitoring Sample Locations San Diego County ... ... ...... ........ .. .. .. .. .. .. .. ... .. ... .. .. ..... ....... .. ...... .. .. ... .. .. .... ........ ...... .... .... .. 5-26 SO123-0DCM Revision 9 11/2015 iv

. ODCM LIST OF TABLES Table Title P~ge 1-1 Radioactive Liquid Waste Sampling and Analysis Program ................. : .... :........ : .............. 1-2 1-:3 Liquid Effluent Radiation Monitors Calibration Constants - DELETED.: ......................... 1-18' 1-4 Dose Commitment Factors, Arr ....................................................................................:. 1-20 2-1 Radioactive Gaseous Waste Sampling and Analysis Program ........................................ 2-2 2-3

Gaseous Effluent Radiation Monitor Calibration Constants - DELETED ........................ 2-13 2-4 Dose Factors for Noble Gases and Daughters - DELETED ........................................... *2-20 2-5 Dose Parameters P1k....... : ............................................................. : ................................ 2-21 2-6 Units 2 & 3*Controlling Location Factors ......................................................................... *2-22

2-7 South Yard Facility Controlling Location F~ctors (Moved to App~ndix 8) ........................ 2-23 2-8 North Industrial.Area (Unit 1) Controlling Location Factors (Moved to Appendix 8) ........ 2-24 4-1 Radioactive Liquid Effluent Monitoring Instrumentation ............... ,.................. .' ................ 4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ........ 4-6 4-3 Radioactive Gaseous Effluent Monitoring lnstrumel")tation .............................................. 4-10 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .. 4-14 5-1 . -Radiological Environmental Monitoring Program ............................................................. 5-3 5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples ................. 5-7 5-3 Detection Capabilities for Environmental Sample Analysis Maximum. Values for the *

Lower Limits of .Detection (LLD) .... ,., ..................._... ,......................................................... 5-8

5-4 Radiological Environmental Monitoring Sample Locations ..... : ...... ;................................ 5-15 5-5 Pl~Radiologie;al Environmental Monitoring Location!S,- DELETED;**********-.. _. ................... 5-20 5-6 Sector and Direction Designation for Radiological Environmental Monitoring Sample. Location Map ...... : ...................... :............................. *5-21 6-1 - Qper~ional Modes - D~LETED .................................................... ,.......................... :******* 6-5

6 Frequency Notation .................. :.................................................................. :.................... 6-6 SO123-0DCM Revisfon 16 11/2020 V

ODCM LIST OF APPENDICES Trtle Appendix Ri TABLES ........................................................................................................ SO123-ODCM-A Supplemental Information for the Effluent Controls Program .............................. SO123-ODCM-B SO123-0DCM Revision 1 02-29-08 vi

INTRODUCTION .

The-OFFSITE DOSE CALCULATION MANUAL (ODCM) is a:supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerates dose and conceAtration specifications, 'instrument requirements, as well as describes the methodology and parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents consistent with Reg: Guide 1.109 and NU REG 0133. In ~

order to meet release limits, it additionally provides calculations for liquid effluent monitoring I :-,::~

instrumentation alarm/trip setpoints. The environmental section contains the requirements for

the radiological environmental monit~ring,program.

The ODCM will be maintained at the Site for use as, a ,document of Specifications and acceptable methodologies and calculations to be used in implementing the Specifications.

Changes in the caIc*uIational methods or parameters will* be incorporated into the ODCM in order to assu_re that the ODCM represents current methodology.

SO123-0DCM Revision 16 11/2020 vii

1.0 LIQUID EFFLUENTS 1.1 CONCENTRATION SPECIFICATION 1.1.1 The concentration of radioactive material released from the site.

(see Figure t-2) shall be limited to the concentrations specifi~ in 10 CFR Part 20, Appendix B, Table 11, Column 2.

APPLICABILITY: At all times ACTION:

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

-SURVEILLANCE REQUIREMENTS

.1 Raqioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-1 .

.2 The results of the radioactMty analyses shall be used in accordance with the methodology and parameters in Section 1.4 to assure that the concentrations at the point of rel_ease are maintained within the limits of Specification 1. t.1.

SO123-0DCM Revision 16 11/2020 1-1

*TABLE 1'-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS_ PROGRAM Lower Limit

.. .. Minimum "

of Detection Liquid '1elease Sampling Analysis. Type of Activity (LLD)

Type Frequency Frequency Analysis (µCi/ml) 8 A. Batch Waste p p

Principal Gamma_ 5x10- 7 Released,h Each Batch Each Batch Emitters,

p M H-3 1x10-5 Each Bat~h Compositeb,g Gross Alpha 1x10-7 p Q Sr-90 5x1o-6 Each Batch *com positeb,g .. Ni-63 . ' 1x1o-6 Fe-55 ' 1x1o-6.

BATCH RELEASE POINTS: Primary Plant Makeup Storage Tanks '(T0SS/56), also

\ '

known as Spent Fuel Pool Makeup Water Tanks, Miscellaneous Waste Evaporator Condensate Monitor. Tanks (T075n6), Radioactive Waste Secondary Tanks (T057/T058) and other tank~ identified in station procedures.

B. Continuous D w* Pnncipal Gamma Sxt0-7 Releasee,h Grab Sample .compositec,g Emitterst Unit 2 Turbine Plant Sump 1x10-5 .

D M H-3 Grab Sample Compositec,g Gross Alpha 1x10-7 D *Q Sr-90 5x1o-8 Grab* Sample Compositec. 11 Ni-63 1xt~* ~.

Fe-55 1x1~

I~

SO123-0DCM Revision 16. :

1,1/2020 1-2

TABLE 1-1 (Continued)

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (µCi/ml) 8 C. Continuou~ 3xW w Principal Gamma sx10-7 Releasee,h Grab Sample Compositeb,g Emitterst North 1x1Q-5 3xW M H-3 Industrial

. Grab Sample Compositeb,g Area Yard Gross Alpha 1x10-7 Drain Sump Sr-90 5x10-a 3xW Q Fe-55 1x1 o-6 Grab Sample Compositeb,g Ni-63 1x1o-6 S0123-0DCM Revision 16 11/2020 1-3

TABLE 1-1 (Continued)

TABLE NOTATION

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

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

LLD= 4.66Sb E *V

2.22 i 10 6 *Y *exp (-U-r) where:

LLD = "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E = counting efficiency (as counts per transformation),

V = sample size (in units of mass or volume),

2.22 x 106 = number of transformations per minute per microcurie, Y = fractional radiochemical yield (when applicable),

A = radioactive decay constant for the particular radionuclide, and flt = elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

r The value of Sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

Typical values of E, V, Y and flt should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of the measurement system and not as a posteriori (after the fact) limit for a particular measurement.#

For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300 (revised annually).

(2) Cun:ie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K, "Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

SO123-0DCM Revision 0 02-27-07 1-4

TABLE 1-1 (Continued)

TABLE NOTATION (Continued)

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in prpportion to the rate qf flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

d. A batch release is the discharge of liquid wastes of a discrete vol_ume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g.,

from a volume. of system that has ~m input flow during the continuous release.

f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionucl1des: Mn-54, Co-58, Co-60, Zn-65, Cs-134, ~s-137, Ce-144. This list does not mean that only these riuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, and those isotopes listed in Reg. Guide 1.21, shall also be identified and reported.

g .. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

h. There shall be no liquid discharges across the beach; liquid may only be discharged through the approved outfall(s).

DELETED

- DELETED

- - DELETED SO123-ODCM Revision 16 11/2020 1-5

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

a. During any calendar quarter to less than or equal to .1.5 mr.em to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3. mrem to the total .body and to less than or equal to 1Q mrem to any organ.*

APPLICABILITY: At all times:

ACTION:

a. Wrth calculated dose from the release of radioactive materials in liquid effluents e.x.ceeding any of t,he above limits, i_n lieu of any other report required byUcensee Controlled Specification~ Section 5. 7.1, prepare and submit to the Com.mission within 30 d~ys, a Special Report which identifie_s II :~

0--~

the cause(s) for exceeding the limit(s) and*defines the corrective actions taken *to reduce the releases. and the proposed actions to be taken to

assure that subsequent releases will_be in compliance with Specification 1.2.1 ..

SURVEILLANCE REQUIREMENT

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

SO~23-0DCM

Revision 15 08/2020 1-6

1.0 LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT SPECIFICATION 1.3.1 The portable liquid ractwa*ste treatment system .shall be FUNCTIONAL.

The appropriate portions of the system shall be used to reduce the .:

radioactive materials in liquid wastes prior to their discharge when the projected doses di.Je to the liquid effluent from the site (see Figure 1-2).

when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.* *

APPLICABILITY: At all times

ACTION:

a. Wrth radioactive liquid waste being discharged with9ut treatment and *in excess of the above limits, in lieu of any other reP9rt required by Licensee lI~:

Controlled Specifications Section 5. 7.1, prepare and submit to the

Commission within 30 days, a Special Report which includes the following information: * *

. 1. Explanation of why liquid radwaste was being discharged without treatment, identification of the n'on-FUNCTIONAL equipment or subsystems and the reason for non-FUNCTIONALITY,

2. Action(s) taken to restore the non-FUNCTIONAL equipment to FUNCTIONAL status, and

3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS

.1 Doses due to liquid releases shall be projected at least once per 31 days, in accord~nce with Secti9n 3.1 .

.2 The appropriate portions of the portable liquid radwaste treatment system shall be demonstrated FUNCTIONAL by operating the liquid radwaste treatment system equipment for at least 15-minut~ prior to processing liquids. The processed liqµids shall then be ev~luated for batch r~lease.

Per unit SO123-0DCM Revision 15 08/2020 1-7

SITE BOUNDARY FOR LIQUID EFFLUENTS Fl,gure 1-2 NIA, UNIT 2 & UNIT 3 SITE BOUNDARY for L l ; ; ; ; t s (waterfrJ on Property Line) ta! I - **=

IC,ll,lllnIT J"'

/

SO123-0DCM Revision* 9 11/2015 1-8

1.0 LjQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION Liquid Effluent Line Monitor provides alann and automatic tennination of release prior to exceeding the concentration limits specified in 10 CFR 20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of Specification 1.1.1, the

alann/trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:

(1-1) where:

= setpoint, representative of a radionuclide concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release, µCi/ml R = pennissible waste effluent flow rate at the radiation monitor location, in volume per unit time in the same units as for F F = dilution water flow in volume per unit time.

= 7,000 gpm per saltwater dilution pump*

The value used in the detennination of F takes into account factors such as frictional losses, pump inefficiency, and tidal flow, and provides reasonable assurance that the radioactive release concentration is not underestimated. For radwaste discharges, the dilution water flow of 14,000 gpm shall be used and aligned to the same outfall.

NOTE: , Since the values of Rare much smaller than F, the tenn (F + R) in equation (1-1) may be replaced by F.

SO123-0DCM Revision 11 08/2017 1-9

1.0 LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION (Continued)

MPCeff = effective effluent maximum concentration permissible limit (µCi/ml) at the release point to the unrestricted area for the radionuclide mixture being released:

1

= (1-2) where:

n = number of radionuclides identified in sample analysis

= fractional concentration of the j1h radionuclide as obtained by sample analysis MPC of the j1h radionuclide (10 CFR 20, App B, Table 11, Column 2)

Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points:

Radwaste Effluent discharge.

Unit 2 Turbine Plant Sump y = NIA Yard Drain Sump The sum of the administrative values is limited to 1.0 to ensure that the total concentration from all release points to the plant discharge will not result in a release exceeding the limits of 10 CFR 20, Appendix B, Table 11, Column 2. The administrative values shall be assigned such that:

(RW,813 + T2 + Y) < 1.0.

The administrative values shall be periodically reviewed based on actual release data and revised as necessary.

SO123-0DCM Revision 10 08/2016 1-10

1.0 LIQUID EFFLUENTS (Continued) 1.4. 1' Batch Rel!385e. Setpolnt Detennlnatio'n The* waste flow (~) and *monitor setpoint (Cm) are set to meet tt,e condition of equation (1-1) for tl)e MPCeff limit. The method by which this*is apcomplished as follows*: : . * * *

STEP 1: The isotopic concentration for each batch t.ank (or sump) to be released is obtained from the sum 9f the measured concentrations in the tank (or sump) as detem,ined by

analysis. *

(1'-3) where*

C = total concentration in each batch tank, µCi/ml

= sum of the measured concentrations for each radionuclide, i, in the gamma spectrum

= gross alpha concentration determined in the previous monthly composite sample, µCi/ml *

Sr-90 concentration as detem,ined in the previous quarterly composite sample, µCi/ml Ct

H-3 con~ntration as determined in the previous monthly

composite sample, or ~s me~sured in the sample taken prior to release, µCi/ml CFe = Fe-55 concentration as detem,ined in the previous quarterly composite sample, µCi/ml

= Ni-63 concentration as detem,ined by isotopic analysis in the previous quarterly composite sample, µCi/ml SO123-0DCM Revision 16 11/2020 1-11

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 Batch Release Setpoint Detennlnatlon (Continued)

STEP 2: The effective MPG (MPCetr) for each batch tank (or sump) is 1 determined using:

(1-4) where:

MPCy1, MPCs, = the limiting concentrations of the appropriate radionuclide from MPCt, 10 CFR 20, Appendix B, Table II, Column 2 MPCFe, MPCa, MPCN1 STEP 3: The setpoint, Cm (µCi/ml) for each batch release radioactivity monitor may now be specified based on the respective values of C, r1C'v1, F, MPCefl', and R to provide compliance with the limits of 10 CFR 20, Appendix B, Table II, Column 2.

SO123-0DCM Revision 16 11/2020 1-12

1.0 LIQUID EFFLUENTS (Continued) 1.4.1.1 Radwaste Dis.charge 4ine Monitor (2/3RT-7813)

The value for Cm, the _concentration limit at the detector, is detemiined by using:

(RW 7g13XF tti C~i)

(1-6)

(R{MP~eff J where:

Radwaste Effluent discharge.administrative valu_e F dilution water flow* i_n, volume per unit time

= 7,000 gpm per saltwater dilution pump-

...,. The value used in the detennination of F takes into account factors such as

frictional losses, pu_mp inefficiency, and tidal flow, and provides reasonable assurance that the radioactive . release concentration is not underestimated.

. For radwaste discharges, th~ qih.ition water flow of 14,000 gpm shall be used and aligned fo the s~me outfall.

C = total concentration in each batch sample

= total gamma isotopic concentration, µCi/ml R = typical effluent release rate Values of R for each tank are as follows:

Primary Plant Makeup Tank = 160 gpm Condensate Monitor Tank= 120 gpm Radioactive Waste Secondary Tank= 160.gpm.

MPCeff = from equation (1-4)_

NOTE: If Cm's r1C'YT,Jhen no release is possible. To increase Cm, increase the administrative value RV1/2813, and/or increase dilution flow F (by running more dilution pumps in the

applicable discharge .structure), and/or decrease the effluent flow rate Rand recalculate Cm using the new RW,813, F, Ras applicable and equation (1-6).

1.4.1.2 Slowdown Processing System Neutralization Sump/Full Flow .

. Condensate Polisher Demineralizer (FFCPD) Sump Discharge Line Monitor (Batch) (2RT-7817, 3RT-7817) - DELETED SO123-0DCM Revision .16 11/2020 1-13

1.0 LIQUID EFFLUENTS (Continued) 1 A.2 Continuous Release Setpolnt Determination NOTE Specific grab sample may be used instead of weekly _composite to enable TPS or NIA setpoint to be set.

The waste flow (R) and monitor setpoint (Cm) are set to meet the condition of equation (1-1) for the effective MPC (MPCeff) limit The method by which this is accomplished is as follows:

STEP 1: . The isotopic concentration for the continuous rel~ases are obtained for each release stream (turbine plant sump, and NIA yard drain sump) from the sum of the respective measured concentrations as.determined by analysis:

(1-3) where:

C = total concentration (µCl/ml) *

= total gamma activity associated with each radionuclide, i, in the weekly composite analysis for the release str,eam, µCi/ml

= total measured gross alpha concentration determined from the previous monthly composite analysis for the release stream,

µCi/ml

= -total measured concentration of Sr-90 as determined from the previous quarterly composite analysis for the release stream,

µCi/ml

= total measured H-3 concentration determined from the previous weekly or monthly composite analysis for the release stream, µCi/ml

= total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream, µCi/ml

= Ni-63 concentration as determined by isotopic analysis in the previous quarterly composite sample for the release stream,

µCi/ml . .

SO123-ODCM Revision 16 1.1/2020 1-14

1.0 , LIQUID EFFLUENTS (Continued) 1.4.2 . Continuous Release Setpolnt Determination (Continued)

STEP 2: The effective M*Pc* (MPCeff) f9r each release stream (turbine plant sump or NIA yard gr~in sump) is deter.mined µsing:

(1-4) where:

MPCv1r MPCs, = the limiting concentrations of the appropriate MPCt, radionuclide from 10 CFR 20, Appendix B, Table II, MPCFa, Column*2 MPCa, MPCN1 STEP 3: The setpoint Cm (µCi/ml) for each continuous release

radioactivity monitor may now .be specified based on th*e respective values of C, I:1C'yi, F, MPCBff, and R to provide compliance with the limits of 10 CFR 20, Appendix B, Table II, Column 2.

1.4.2.1 Slowdown Processing System Neutralization Sump Discharge Line Monitors (2RT-7817, 3RT-7817) - DELETED 1.4.2.2 steam Generator Slowdown Bypass Discharge Une Monitors (2RT-6753, 2RT-6759, 3RT-6753, 3RT-6759) - DELETED SO123-0DCM Revision 16 11/2020 1-15

1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 Turbine Plant Sump Monitor (2RT-7821)

The v_alue for C2 (Unit 2), the concentration limit at the Unit 2 detector, is determined by using:

(1-13)

Equation 1-14 DELETED where:

C2 = instantaneous concentration at detector 2RT-7821 in µCi/cc T2 = Unit 2 Turbine Plant Sump administrative value F = dilution water flow in volume per unit time

= 7,000 gpm per saltwater dilution pump r;c*vi = total gamma isotopic concentration µCi/ml (STEP 1)

R = effluent flow rate; gpm, (STEP 1), typical flow rate:

= 300 gpm C = total concentration, µCi/ml MPCe11 = value of MPCeff from*equation (1-4) for the sample analysis NOTE: If Ci s r,C'yi, then no release is possible. To increase C2, increase the administrative value T2, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate C2 using the new T2, F, Ras applicable and equation (1-13). A minimum of 7,000 gpm flow shall be,used for continuous releases. If there is a loss of dilution flow, then operations start another pump or SHALL terminate all continuous liquid .effluent releases.

SO123-0DCM Revision 16 11/2020

\

1-16

1.0 LIQ.UID EFFLUENTS (Continued)

1.4.2.4 NIA Yard Drain Sump Monitor (2/3RT-2101)

~

There is one Yard Drain Sump on site, located in the North Industrial Area. It is released through the Unit 2 outfall. I t!J The value for'Cvos, the concentration limit at the detector, is detem,ined by.

using:. * * *

(1-15) where:

Cvos = instantaneous concentration at detector 2/3RT-2101 in µCi/ml y = NIA Yard Drain Sump administrative value F = dilution water flow in volume per unit time

= 7,000 gpm per saltwater dilution pump r;c:'(l* = total gamma isotopic conce~tration, µCi/ml (~TEP 1)

R = effl'uent flow rate, gpm, typical flow rates:

= 4100 gpm C = total concentration, µCi/ml MPCet1 = value of MPCeff from equation (1-4)-for the sample analysis NOTE: If Cvos s r,C'yi, then no.release Is possible. To increase Cvos, increase the administrative value, *y, and/or increase dilution flow F (by running more dilution pumps), and/or decrease the effluent flow rate, R, and recalculate Cvos using the new Y, F, Ras applicable and equj:ltion (1-15). A minimum of 7,000 gpm flow shall be used for continuous releases. If there is a loss of dilution flow, then operations start another pump or SHALL ~erminate all continuous liquid effluent releases.

SO123-ODCM Revision 16 11/2020 * .

1-17

TABLE 1-3 Liquid Effluent Radiation Monitor Calibration Constants <a>

(µCi/cc/cpm)

DELETED REMAINDER OF PAGE LEFT INTENTIONALLY BLANK SO123-0DCM Revision 9 11/2015 1-18

1.0 LIQUID EFFLUENTS (Continued) 1.5 DOSE CALCULATION FOR LIQUID EFFL.UENTS The liquid releases considered in the following dose calculations are described in Section 1.4. The dose commitment to an individual .from radioacti~e materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing. Sp.ecification 1.2.1 using the following expression.

(1_-16) where:

Arr = Site-r~lated adult ingestion dose commitment factor to the total body or an organ, r, for each identified principal ga*mma and beta emitter, i, from Table 1~ in mrem/hr per µCi/mL*

C,i = average. concentration of.radionuclide, i, in the undiluted liquid effluent during* time period, b.4,*in µCi/ml.

Dr = dose commitmenf to the total body or an organ, T, from-the liquid -

effluent for the time period; .Ati, in mrem.

Fi = near field average dilution factor (actually mixing ratio) for C,i during the time. period, b.ti. This factor is the ratio of the average undiluted liquid waste flow during time period, b.4, to the average flow from the site discharge structure to unrestricted receiving waters,

average liquid radioactive waste flo~

or: (

discharge structure exit flow

= length of the jth time period over which Cu ahd Fi are averaged for* all liquid releases, *in hours.

SO123-0DCM Revision 16 11/2020 *

1-19

TABLE 1-4 DOSE COMMITMENT FACTORS*, Arr (mrem/hr per µCi/ml)

Radionuclide Bone Liver Total Thyroid Kidney Lung GI-LLI Body

H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 . 2.82E-1 2.82E-1 Mn-54 7.06E+3* 1.35E+3 2.10Et3 2.16E+4 l_~o Fe-55 5.11E+4 3.5.3E+4 8.23E+3 1.97E+4 2.03"E+4 I §.....

3.59E+3 I ...

Co-57 1.42E+2 2.36E+2 ..

Co-58.: 6.03E+2 1.35E+3 1.22E+4 Co-60 1.73E+3 3.82E+3

3.256+4 Ni-63 4.96E+4 3.44E+3 . -1.67E+3 7.18E+2 Zn-65 Sr-90 1.61E+5 1.23E+5 5.13E+5 2.32E+5 3.01E+4 .

3.43E:+-5 3.23E+5*

3.55E+3 l~N I§.....

I ...

Ru-106 1.59E+3 . 2.01E+2 .. 3.06E+3 1.03E+5

Ag-110m 1.42E+3 *1.32E+3 7.82E+2 2.59E+3 5.37E+5 Sn-1-13* *2.26E+5 Sb-125 1.77E+2 1.97E+0 4.20E+1 1.79E-1 1.36E+2 1.94E+3 Cs-134 6.84E+3 1.63E+4 *1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-137 8.77E+3 *1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+0 1.20E+1 .5.94E+0 8.81E+0 8.70E-1 5.12E-5 ce-1*44 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 NOTE: .'Where no value is given, no data are available.

Source: Reg. Guide 1.109, Table E-11, TableA-1 USNRC NUREG-0172, Table 4 ICRP-30, Part 3, s*upplement A M_ethodology: USNRC NUREG-0133, Section 4.3.1 SO123-0DCM Revision 16 11/2020 1-20

1.0 LIQUID EFFLUENTS (Continued) 1.6 REPRESENTATIVE SAMPLING Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling in accordance with the requirements of Reg. Guide 1.21 and NUREG-0800, Section 11.5. The methodology for mixing and sampling is described in SDS-CH2-PGM-1005 and SDS-CH2-PCD-1004.

SO123-0DCM Revision 12 05/2018 1-21

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

a. DELETED

b. For Tritium and for radioactive materials in particulate form: Less than or equal to 1500 mrem/yr to any organ.-

APPLICABILITY: At a*II times ACTION:

a. -With dose rate(s) exceeding the above_limits, immediately-decrease the rel~ase rate to within the above limit(s). _*. *

SURVEILLANCE REQUIREMENTS

.1 DELETED

.2 The dose rate due to Tritium and radioactive materials- in particulate form in gaseous effluents shall be determined to be within the above limits in accordance with Section 2. 7 by obtaining representative samples and performing analyses in accordance with the sampling and analysis progra111 specified in Table 2-1 ..

SO123-0DCM Revision 16 1112020-2-1

TABLE 2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum Type of Gaseous Release Sampling of Detection Analysis Activity Type Frequency (LLD)

Frequency Analysis

(µCi/ml) 0 Continuous

Tritium 1x1o-8 Continuoust

\/111 Principal Gamma Particulate Emittersg 1x10-11

Sampler Sample M

Continuoust Composite Gross f-lpha 1x10-11 Sampler Particulate Sample Q

Continuous' Composite Sr-90 1x10-11 Sampler Particulate Ni-63 1x10-11 Sample I~

Sampling frequencies for Tritium are*

I~

Containment Main Purge - 42" : Weekly Grab 1 0 Plant Vent Stack : Weekly Grab South Yard Facility : Particulate sampling onlyh I~

SO123-0DCM Revision 16 11/2020 2-2

TABLE 2-1 (Continued)

TABLE NOTATION

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

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

LLD= 4.66 Sb E

V

2.22 x 10 6

Y

exp (-11.L~:r) where:

LLD = "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

Sb = standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E = counting efficiency (as counts per transformation),

V = sample size (in units of mass or volume),

2.22 x 106 = number of transformations per minute per microcurie, Y = fractional radiochemical yield (when applicable),

>,. = radioactive decay constant for the particular radionuclide, and

~t = elapsed time between midpoint of sample collection and time of .

counting (for plant effluents; not environmental samples).

The value of Sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.'

Typical values of E, V, Y and ~t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of the measurement system and not as a posteriori (after the fact) limit for a particular measurement.-

- For a more complete discussion of the LLD, and other detection limits, see the following:

(1) HASL Procedures Manual, HASL-300 (revised annually).

(2) Currie, LA., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K, "Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972). SO123-0DCM Revision 0 02-27-07 2-3

TABLE 2-1 (Continued)

TABLE NOTATION (Continued)

b. DELETED

c. DELETED d: Air samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler). *

e. Representative TntIum grab samples shall be taken at least once per 7 days from the spent fuel pool area, whenever water is in the spent fuel pool. In the event grab samples cannot be collected, estimate Tritium releases from the SFP area by assuming all SFP makeup water replaces trttiated water loss.

f The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate*calculation made in accordance with Specifications 2.1.1, 2.3.1.

g. The principal gamma emitters for which the LLD specrfication applies exclusively are the following radionuclides: Mn-54, Co-58, Co-60, Zn-65, Cs-134, Cs-137, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. pther peaks which are.measurable and identifiable, together with the above nuclides, and those listed In Reg. Guide 1.21, shall also be identified and reported.

h. Radioactive airborne effluents only expected to be particulate.

i. DELETED SO123-0DCM Revision 16 11/2020 2-4

2.0 GASEOUS EFFLUENTS (Continued) 2.2 DOSE - NOBLE GASES - DELETED REMAINDER OF PAGE LEFT INTENTIONALLY BLANK SO123-0DCM Revision 16 11/2020 2-5

2.0 GASEOUS EFFLUENTS (Continued) 2.3 DOSE*- RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM SPECIFICATION 2.3.1 The dose:to an individual from Tritium and radioacti_ve materials in particulate fonn in gaseous effluents released,*from each reactor unit,.

_from the Site (see Figure 2-2) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any .

organ, and *

b. During any calendar year: Less than or equal to 15 mrem to* any organ.

APPLICABILITY: At air times ACTION:

a. .With the calculated dose from the release of Tritium and radioactive

materials in particulate form, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Licensee Controlled Specifications Section 5.7'.1, prepare and submit.to the Commission -

within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases* and the proposed actions to be taken to assure that subsequent releases will be in compliance With Specification 2.3.1.,

SURVEILLANCE REQUIREMENT

.1

Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year sh~II be detennined in accordance with _$ection 2.8 at least once per 31-days.- :

2.4 GASEOUS RADWASTE TREATMENT - DELETED SO123-0DCM Revision 16

11/2020 2-6

SAN ONOFRE NUCLEAR GENERATING STATION SITE BOUNDARY FOR GASEOUS EFFLUENTS Figure 2-2 LEGEND l CONTA.1.HMEHTPUR;GE VENT STACX (El2!5 Fr9 <N) 2 CONTtNUOUSOOtAUSTVENTSTACX (EL 235 FT 91NJ

\ .\

- : * =-

SITE BOUNDARY for G a s e o ~

S0.123-ODCM Revision 16 11/2020 2-7

2.0 GASEOUS EFFLUENTS (Continued) 2.5 DELETED I~

I~

[~

2.6 METHODS OF CALCULATION FOR GASEOUS EFFLUENT MONITOR SETPOINTS-DELETED I~

REMAINDER OF PAGE LEFT INTENTIALLY BLANK SO123-ODCM Revision 16 11/2020 2-8

2.p .GASEOUS EFFLUENTS (Continued) 2.7 GASEOUS EFFLUENT DOSE RATE The methodology used for the purpose of implementation* of Specification 2.1.1 for the dose rate above background to an individual in an unrestricted area is calculated by using the following expressions:

2.7.1 r= or Noble Gas - DELETED 2.7.2 For Tritium and for Radioactive Materials in Particulate Form:

(2-15) where:

Do = organ dose rate in unrestricted areas due to radioactive Q, =

materials released in gaseous effluents, mrem/yr

'!1e*asured or calculated release rate of radionuclide, i,. µCi/sec P1k = dose parameter for. radionuclide, i, for pathway, k, from .

Table* 2-5 for the inhalation pathway in mrem/yr per µCi/m 3

The dose factors are based on the critical *indivi9ual organ and the child age group..

= highest calculated historical. annual average dispersion (X / Q) or depo~ition (D / Q) fact9r for estimating the do~ to an individual at .or beyond the unrestricted area boundary for

.pathway k. * *

= (X/Q), 2.1 E-5 sec/m 3 for Units 2/3 for the Site Boundary inhalation pathway . .The location is the unrestricted area in the

. ENE sector.

= (X/Q), 8.8E-7 sec/m 3 for Uriits 2/3 Nearest Residence for the inhalation pathway. The location is the unrestricted area in the NWsector. * *

= (X/Q), 1.9E-3 sec/m 3 for the South Yard Facility for the Site Boundary for the inhalation pathway. The location is the unrestricted area in the ENE sector.

= (X/Q), 1.5E-6 sec/m-3 for South Yard Facility for the Nearest Residence for the inhalation pathway. rhe location is the unrestricted area in the NW sector.

SO123-0DCM Revision 16 11/2020 2-9

2.0 GASEOUS EFFLUENTS '(Continued) 2.7 GASEOUS EFFLUENT DOSE RATE (Continued) 2.7.2 For Tritium and for Radioactive Materials in Partlculate Form (Continued)

= * (X/Q), 1.3E-5 sec/m 3 for the NIA (Unit 1) for the inhalation*

1m pathway. The location is the unrestricted area in the NW sector.

(P / Q), 4.2E-8 _m-2 f<;>r Units 2/3 for the Site Boundary food and ground. plane pathways. The location is the unrestricted area

m in the ENE sector.

= (D /Q), 2.4E-9 m-2 .for Units 213 Nearest Residence for the food and ground plane pathways. The location is the unrestricted 1m area in the NW sector.

(D /Q), 2.1 E-6 m-2 for the South Yard Facility for the Site ..

Boundary.for the food and ground plane pathways. The location is the unrestricted area in the ENE sector.

= (D /Q), 2.1 E-.9 m-2 for South Yard Facility Nearest Residence for the food and ground plane pathways. The location is the unrestricted area in the WNW sector.

= (D/Q), 7.2E-8111-2 for NIA (Unit 2) for.the food and ground.

.plane pathways. The location is the unrestricted area in the .

NW sector.

SO123-0DCM Revision 16 11/2020 2-10

2.0 GASEOUS EFFLUENTS (Continued) 2.8* GASEOUS EFFLUENT DOSE CALCULATION 2.8.1 Dose from Noble Gas In Gaseous Effluents - DELETED 2.8.1.1 For Historical Meteorology - DELETED 2.8.1.2 For Meteorology Concurrent with Release - DELETED REMAINDER OF PAGE INTENTIONALLY LEFT BLANK SO123-0DCM Revision 16 11/2020 2-11

2.0 GASEOUS EFFLUENTS (Continued).

2.8.2 Dose from Tritium and Radioactive Materials in Particulate Fonn* in Ga~eous Effluents The dose to an .individual from Tritium and radioactive materials in particulate fom, in gaseous effluents released to unrestricted -areas is calculated using.

the* following expressions:

2.8.2.1

For Historical Meteorology:

(2-20) where:

Do = total project~d dose from gaseo~s effluents to an individual; mrem 3.17x1 o-8 = year/second

= amount of each radionuclide, i, (Tritium, radioactive material ir:i particulate fom,), released in gaseous effluents; µCi I:kRikWk =. -sum of all pathways, k, for radionuclide, i, of the Ri W product, in mrem/yr per µCi/sec. The rkR1kWk value for each radionuclid~. i, is given in"Table 2-6 for Units 2/3., Table 2-7 (refer to Appendix B) for South Yard Facility, and Table 2-8 (refer to Appendix B)' for the North Industrial Area (Unit 1 historical value). The value given is the maximum rkR1kWk for all locations and i_s ~ased on the most restrictive age g~9ups.

= - dose factor for each identified radionuclide, i, for pathway k, (for the inhalation pathway in mrem/yr per µCi/m 3 and for the

food and ground plane pathways in m~-mrem/yr per µCi/sec),

.. at the controlling: location. The Rik's for each controlling location for each age group are given*in Appendix A. Data in these*tables are derived using the NRC code GASPAR.

= annual average dispersion (X / Q) or deposition (D / Q) factor for estimating the dose to an individual at the controlling location for pathway k.

= ( X / Q) for the inhalation pathway in sec/m 3

The (X / Q) is.

given in Appendix A.

= (QjJf) for the food and ground plane pathways in rr,-2

The (D / Q) for each controlling location is given in Appendix A.

SO123-0DCM Revision 16 11/2020 2-12

2.0

GASEOUS EFFLUENTS (Continued) 2.8.2.2 For Meteorology Concurrent with Releases: DELETED REMAIND~R OF PAGE INTENTIONALLY l.EFT BLANK.

S0123-0DCM Revision 16 11/2020

. 2-13

TABLE 2-4 DELETED DOSE FACTORS FOR NOB.LE GASES AND DAUGHTERS-DELETED REMAINDER OF PAGE INTENTIONALLY LEFT BLANK.

SO123-0DCM Revision 16 11/2020 2-14

TABLE 2-5 DOSE PARAMETER Pa/

CHILD AGE GROUP CRITICAL ORGAN Inhalation Pathway

Inhalation Pathway Radionuclide Radionuclide (mrem/yr per µCi/m 3) (mrem/yr per µCi/m 3)

H-3 1.1 E+3 1-131 1.6E+7 Mn-54 1.6E+6 1-133' 3.8E+6 Co-57 5.1E+5 1-134 5.1E+4 Co-58 1.1E+6 1-135 7.9E+5 Co-60 7.1E+6* Cs-134 1.0E+6 Ni-63 8.2E+5 Cs-137 9.1E+5 Sr-90 1.0E+B Ce-144 1.2E+7

Source: USNRC NUREG-0133, Section 5.2.1.1 SO123-ODCM Revision 16 11/2020 2-15

TABLE 2-6

- UNITS 2&3 CONTROLLING LOCATION FACTORS 1 LkR1kWk Radionuclide mrem/yr per µCi/sec Use:

H-3 2.86E-3 P: SORB Campground Mn-54 1.47E+01 Q: SORB Rec Beach Co-60 1.88E+02 Q: SORB Rec Beach Ni-63 1'.14E+02 E: Deer Consumer/Hunter Sr-90 5.77E+02 P: Cotton Point Gardens Cs-134- 5.33E+01 Q: SQRB Rec Beach Cs-137 7.82E+01 Q: SORB Rec Beach Ce-144 2.89E+01 P: SORB Campground UN-ID 8.13E+00 Q: SORB Rec Beach These values to be used in manual calculations are the maximum LkR1kWk for all locations based on the most restrictive age group.

SO123-0DCM Revision 16 11/2020 2-16

TABLE 2-7*

SOUTH YARD FACILITY CONTROLLING LOCATION FACTORSf (Moved to Appendix B)

REMAINDER OF PAGE LEFT INTENTIONALLY BLANK .

I SO123-0DCM Revision 16 11/2020 2-17

TABLE 2-8 NORTH INDUSTRIAL AREA {UNIT 1) CONTROLLING LOCATION FACTORs*1 (Moved to Appendix B)

REMAINDER OF PAGE LEFT INTENTINALLY BLANK SO123-ODCM Revision 16 11/2020 2-18

3.0 PROJECTED DOSES 3.1 LIQUID DOSE PROJECTION The methodology used for projecting a liquid dose over 31 days for Specification 1.3.1 is as follows:

.1 . Determine the monthly total body and organ doses resulting from.releases during the previous 12 months.

.2 Projected dose = Previous 12 months' dose divided by 12 for the total body and each organ.

3.2 GASEOUS DOSE PROJECTION The methodology used for projecting a gaseous dose over 31 days for Specification 2.3.1 is as follows: *

.1 Determine the monthly organ dose resulting from releases during the previous 12 months. *

.2 - Projected dose = Previous 12 months' dose divided by 1~ for the organ dose.

- \

SO123-0DCM Revision 16 11/2020 3-1

3.0 PROJECTED DOSES (Co'ntinued) 3.3 TOTAL*DOSE SPECIFICATION 3.3.1 -' The dose or dose commitment to any member of the public, due to releases. of radioactivity and radiation, from Uranium fuel cycle sources shall be limited to less than or equal to ~5. mrem to the 'total body or any organ (exq3pt the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consect.rtive months.

APPLICABILITY: At all times ACTION:

a. Wrth the calculated doses from the release of radioactive materials in iiquid or gaseous effluents exceeding twice the limits of Specifications 1.2.1 a, 1.2.1 b, 2.2.1 a, 2:2.1 b, 2:3.1 a, or 2.3.1 b in lieu of any other report ~

required by Licensee Controlled Specification Section 5.7.1, prepare and

submit a Special Report to the Director, Nuclear Reactor Regulation, U.S.

I~

NO Nuclear Regulatory Commission, Washington, D.C. 20555, within* 30 .

days, which defines the corrective action to be t.aken to reduce subsequent releases to prevent recurrence of exceeding the-limits of Specification 3.3.1.-This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from

. Uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 qonsecutive month period that includes the release(s) covered by this report. If the estimated dose(s) exceeds the limits of Specification 3.3.1, and if the release condition resulting in violation of 40 CFR 190.has not already been corrected, the Special Report shall include a request for a variance in accordance ;With the provi!?ions of 40 CFR 190 and including the specified information of paragraph 190.11 (b ). Submittal of the report is considered a timely request; and a variance is granted*

until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply In any way to the requirements for dose limitation of 10 CFR Part ~O, as addressed

elsewhere in this ODCM.

SURVEILLANCE REQUIREMENT

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

SO123-0DCM Revision 15 08/2020 3-2

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS 3.4.1 Total Dose to Most Llkely Member of the Public The total annual dose or total dose commitment to any member of the public, due to releases of radioactivity and to radiation, from Uranium fuel cycle sources within 5 miles of the Site is calculated using the following expressions. This methodology is used to meet the dose limitations of 40 CFR 190 per 12 consecutive months. The transportation of radioactive material is excluded from the dose calculations.

The Annual Total Dose is detem,ined monthly for maximum organ (gas and liquid), whole body (gas and liquid), and thyroid (gas and liquid) t6 verify the Site total is less than or equal to 25 mrem, 25 mrem, and 75 mrem respectively.

3.4.1.1 Annual Total Organ Dose [P:ror (O)]

12 213L ( ) ,.. ]

Dror ( o ) = L LI.J.Jj!(oa)+D11 OL +D,-3 (oo) (3-1)

/=IJ=l where:

NOTE: Dl-3 (OG) = Ofor bone n

D 1,(oG)=K LC,LkR,kWk 1=I i= each isotope in specific organ category j= NIA, Unit 2, and Unit 3 I= months 1 - 12 (to be summed over the most recent 12 months)

K = 3.168E-2 year-.u<:i sec -Ct SO123-0DCM Revision 9 11/2015 3-3

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total.Dose to M<<;>st Likely Member of tt:te Public (Continued) 3.4.1.1 Annual "Total Organ Dose [Rror (O)HContinued) n = number ~f isotopes in the spe'cified organ category C1 -. total particulate ga~ curies released for the month I\R1kWk = SONGS controlling location factors (Tables 2-6, 2-7*, or 2-Sj.

DiOL) = liquid organ dose for the specified org*an in mrem for the .

month. [Equation (1-16)]

Dl-3 (OG)* = gas organ dose fr~m Tritium ln mrem for the month .

. [Equation (2-15)]

Found in Appendix 8

3.4;. 1.2 Annual Total Whole Body Dose [Rror (WB)]

Dror(WB) = Lt~1 L~~~[D11(WBL) + DJ- 3 (0G)] _+ D(U1) + D(DIRECT) (3-3) where:

= NIA, Unit 2 and Unit 3

= months 1 .- 12, to be summed over the mo.st recent 12 months DJl(WB~) = liquid whole body organ dose in mrem for the whole month. .

[Equation (1-16)] .

D/~3- (OG) = gas organ dose from Tritium in mrem for the month.

[Equation (2-15)]

D(U1) = 7.96E-2 mrem/yr, Total Effective Dose Equivalent from the offshore portion .of the Unit 1* Circulating Water System.

Reference:

. Safety Evaluation related to Amendment No. 165 to Facility Operating License No. DPR-13, SCE, SONGS Unit *1 Effll'.lent/ODCM Evaluation SDS-CH2-EVA-0008, Removal of Dose

.Related to Recreational Diver in the .Unit 1

Circulating Water System SO123-0DCM Revision 1!;>

11/2020 3-4

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total Dose to Most Llkely Member of the Publlc (Continued) l 3.4.1.2 Annual Total Whole Body Dose [DroT (WB)] (Continued) 4 [

D(DIRECT)* = ~ max[D(beach),] -

i p=t D(bkgd),

n 0.0342 (3-4) p = for all TLDs per quarter q = for Quarters 1-4

Direct Radiation The direct radiation levels are evalu~ed most recently using Thulium-doped TLDs. The TLDs are placed at a minimum of 30 locations around the site.

The average dose measured by TLDs 5 to 50 miles from the site is used as background. These sites are subject to change.

The backg,round is subtracted from the highest reading TLD within 5 miles of the site (generally numbers 55 through 58). This value is the direct dose but must be prorated by the occupancy factor.

Example: Beach time (west boundary, seawall) of 300 hrs/yr, east and north boundaries of 20 hrs/yr, or 8 hrs/yr for the south boundary and west fence of parking lot 1 (top of bluff).

Reference:

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

SO123-ODCM Revision 9 11/2015 3-5

3.4.1 Total Dose to Most Likely Member of the Public (Continued) 3.4.1.3 Annual Total Thyroid Dose - DELETED REMAINDER OF PAGE LEFT INTENTIALLY BLANK SO123-0DCM Revision 16 -

11/2020 3-6

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

APPLICABILITY: At all times ACTION:

_/

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel non-FUNCTIONAL.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels FUNCTIONAL, take the ACTION shown in Table 4-1. Exert best efforts to return the instrument to FUNCTIONAL status within 30 days and, additionally, if the non-FUNCTIONAL instrument(s) remain non-FUNCTIONAL for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the non-FUNCTIONALITY was not corrected in a timely manner.

c. With less than the minimum number of radioactive liquid effluent monitoril'.lg instrumentation channels FUNCTIONAL and either the appropriate ACTION items In Table 4-1 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-2, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

SURVEILLANCE REQUIREMENTS

.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-2 .

.2 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after a change in pump operation that affects dilution flow has been completed, all pumps required to be providing dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilution to the discharge structure.

SO123-0DCM Revision 9 11/2015 4-1

TABLE 4-1 RADIOACTIVE u'QUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* FUNCTIONAL ACTION

-

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TE.RMINATION OF REL.EASE * . .

a. Liquid Radwaste Effluent Line** - 2/3RT-7813* 1 28 Ii Turbine Plant Sump Effluent Line - 2RT-7821* 1 30 c: NIA Yard Drain Sump - 2/3~T-2101* 1 44

2. PROCESS FLOW RATE MEASUREMENT DEVICES

a. Liquid RadYJaste Efflue_nt Line** - FE7643 1 31

b. Turbine Plant Sump ~ffluent Line :2FQl5887 1 31

c. NIA Yard Drain Sump Effluent Line-2/3FQl-6095 , 1 3*1

3. C_OMMAND DATA ACQUISITION_SYSTEM_ (CDAS) (Effluent Monitor Alarms) 1' 32

4. UNIT 2 PLANT COMPUTER SYSTEM (CONTROL-ROOM ALARM ANNUNCIATION)-

DELETED . .

5.. - CONTINUOUS COMPOSITF SAMPLERS

a. Turbine Pla-nt 'Sumps Effluent Line-_ZAPC-5887 1 33

6. ISFSI Command Data Acquisition System '(CDAS) (Effluent Monitor Alarms) 1 3~

~

SO123-0DCM Revision 16 11/2020 I~

4-2

TABLE 4-1 (Continued)

TABLE NOTATION

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

- Liquid effluent discharged through Rad Monitor 2/3RE-7813 will have been processed, sampled, and authorized by Liquid Release Permit prior to discharge from the site.

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

a. At least two independent samples are analyzed in accordance with Specification 1.1.1 and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculation and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 29- DELETED ACTION 30- \Mth the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab .

samples are collected and analyzed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of collection time for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 microcuries/ml.

SO123-ODCM Revision 9 11/2015 4-3

TABLE 4-1 (Continued)

TABLE NOTATION (Continued)

ACTION 31- Wrth the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases. In addition, a new flow estimate shall be made within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after a change that affects process flow has been completed. Pump curves may be used to estimate process flow.

Loss of process flow instrument(s) results in the associated gross activity monitor becoming non-FUNCTIONAL. Perfom, the compensatory action for the non-FUNCTIONAL gross activity monitor in addition to this compensatory action. [2RT-7821, 2/3RT-7813]

ACTION 32- With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the monitor is verified FUNCTIONAL by performing a channel check at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

ACTION 33- With the number of channels FUNCTIONAL less than required by the Minimum channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided grab samples are collected daily, and composited and analyzed weekly:

a. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , not to exceed 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ACTION 44- With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of collection time for gross radioactMty (beta or gamma) at a lower limit of detection of at least 10-7 microcurie/ml).

SO123-0DCM Revision 10 08/2016 4-4

TABLE 4-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTE: Frequency notations are found in Table 6-2, Frequency N,otation.

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT- CHECK CHECK CALIBRATION _TEST

1. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluents Line - 2/3RT-7813 D- p(6) R<2J Q(1)

Q(1)

b. Turbine Plant Sump Effluent Une --2RT-7821 D M<sJ R<2J I~

I ;:: .

C. NIA Yard prain Sump-Efflu'?nt'Line - 2/3RT-210.1 D Mesi R<2J Q(1)

2. PROCESS.FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line D(3) NIA R. Q D(3)

b. Turbine Plant Sump Effluent Une NIA R Q I~~ -

I ;::

C. NIA Yard Drain Surrip Effluent Line D!3l NIA R Q

3. COMMAND DATA ACQUISITION SYSTEM (CDAS) (Effluent Monitor.

Alarms) D. NIA _f\J/A(4) Q

4. UNIT 2 PLANT COMPUTER SYSTEM (CONTROL ROOM ALARM ANNUNCIATION) DELETED .

5. CONTINUOUS COMPOSITE SAMPLERS Turbine Plant Sump 2APC-5887 Q(5) NIA R Q a.

6. ISFSI CDAS (RE-2101 Effluent Monitor Alarms) D NIA NIA(-4l Q SO123-ODCM Revision 16

- 1112020 I~

4-5

TABLE 4-2 (Continued)

TABLE NOTATION Monitor Recorders are not required for the FUNCTIONALITY of the monitor, providing the non-FUNCTIONAL recorder does not cause the monitor to become non-FUNCTIONAL (i.e., feedback signal). As long as the monitor has indication, alarm capability (if

applicable), proper response (based on surveillance requirements) and isolation-function (if applicable), *the loss of the*recorder does not render the monitor non-FUNCTIONAL.

.(1)

The CHANNEL FUNCTIONAL TEST.shall also demonstrate verification of effluent path isolation actuation signal, automatic pathway isolation, and Control Room/Command

. Center alarm annunciation rf any of the following conditions exist: *

1. Instrument i_ndicates measured levels above*the:alcirm/trip setpoint.

2. Circuit failure.

Down scale failure testing is bounded by administrative limitation on' monitor setpoint which ensure monitor alarm and release termination occur prior to* reaching the level of monitor saturation.

If the instrument controls are not in the operate mode, procedures shall require that the

channel be declared non-FUNCTIONAL.

(2) The initial Ct-JANNEL CALIBRATION shall be performed using one or more.of-the reference standards certified by the Natio*nal Institute of Standards.and Technology or using standards that have been obtained from suppli_e~ that participate in measurement assurance activities with NIST. These standards shall ~rrnit calibrating the system over its intended range of _energy ~nd measurement range. For subsequent CHANNEL CALIBRATIONs, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CH~CK shall consist of verifying indi~tion of flow during periods of release.

CHANNEL CHECK shall b~ mad.e at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on whitj, continuous, periodic, or. batch releases a~e: made.

(4) The Command Data Acquisition System (CDAS) software and hardware do n_ot require CHANNEL CALIBRATION. The CDAS software is q1,.1ality affecting and controlled by the ~

site Software Modification.Request process under procedures ENG-10, Software I~ .

Development and Maintenance. The CDAS liardware Is installed. plant equipment and :

controlled by'the site design change process using procedure SDS-EN1-PCD-0001. *

(5) CHANNEL CHECK shall consist of verifying compositor* switch positions and installed counter setting and comparing integrator readings to sample volume collected at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days in which releases are made. *

(6) MGPI monitors have .automatic and continuous source check to meet this requirement.

SO123-0DCM

Revision 16 11/2020.

4-6

I, 4.0 EQUIPMENT (Continued) 4.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.2.1 The radioactive gaseous effluent sampling instrumentation channels shown in Table 4-:3 shall be FUNCTIONAL with their alarm function to ensure isokinetic sample flow is continuously monitored.

APPLICABILITY: At all*times ACTION:

a. With a radioactive gase*ous effluent sampling instrumentation channel *

I ~::::=

less conservative than required by the above specification, immediately :

suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel non-FUNCTIONAL.

b. \Mth less than the minimum number of radioactive gaseous effluent *I -~;;:

sampling instrumentation channels FUNCTIONAL, take the:ACTION ,

shown in Table 4-3. Exert best efforts to return the.instrument.to FUNCTIONAL status within 39 days and, additionally, if the non-FUNCTIONAL instrument(s) remain non-FUNCTIONAL for greater than 30 days, explain in the next Annual Radioactive Effluent Release Report why the non-FUNCTIONALITY was not corr.acted in a timely manner...

c. Wrth I ~ thari the mjnimum number of radio;:ictive gaseous effluent sampling instrumentation channels FUNCTIONAL and either the appropriate ACTION items in' Table 4-3 not taken or the necessary

~urveillances not performed at the specified frequency prescrjbed in Table 4-4, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

SURVEILLANCE REQUIREMENT

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

SO123-0DCM.

Revision 16 11/2020 4-7,

TABLE 4-3 RADIOACTNE GASEOUS EFFLUENT MONITORING iNSTRUMENTATION MINIMUM CHANNELS INSTRUMEN,....,..,. FUNCTIONAL_,, APPLICABILITY* ACTION*

1.

m PLANT VENT STACK'{2/3RT-7808)

a. Noble Gas Activity Monitor - DELETED

b. Iodine Sampler--: DELETED C. Particulate Sampler 1

40

d. Associated Sample Flo.w Measuring Device 1

36b

e. Process Flow Rate Monitoring Device-2/3RT-7808G 1 <-: 36a

2. CONTAINMENT PURGE SYSTEM (2(3)RT-7828).

a. , Noble* Gas Activity Monitor - DELETED

b. Iodine.Sampler - DELETED c.

d.

e.

Particulate Sampler Associated Sample Flow Measuring Device Process Flow Rate Monitoring .pevjce 1

1 1

40 36b 36a

m I :;:

3. COMMAND DATA ACQUISITION SYSJ"EM (CDAS) (Effluent Monitor* 1 . 42 Alarm)

4. SOUTH YARD FACILITY (SYF) Vv'ORK AREf. (SYFRU 7904)

a. Iodine Sampler - DELETED

b. Particulate Sampler 1 -40

c. Associated Sample Flow Measuring Devi~ 1 41b

d. Process Flqw Rate M_onitoring Device 1 * . 41a SO123-0DCM Revision 16 11/2020 4-8

TABLE 4-3 (Continued)

TABLE NOTATION

At all times:

- When Containment Purge is in progress.

- - Monitor Recorders are not required for the FUNCTIONALITY of the moni~or, providing* the non-FUNCTIONAL recorder does not cause the monitor.to become non-FUNCTIONAL .

(i.e., feedback signal). As long as the* monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements)-and isolation function (if applicable), the loss of the recorder does not render the monitor non-FUNCTIONAL.

(1) DELETED (2)

(3)

DELETED*

DELETED ACTION 35 - DELETED ACTION 36-With the number of channels FUNCTIONAL less than required 'by the

~

Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may contin1;1e provided: . *

a. Th*e process flow rate. is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during actual releases. In addition, a new flow estimate shall be niade within

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months :after a change that affects process flow has been completed. .

System design. characteristics may be used

. to estimate process

. flow.

b. The particulate sample flow rate is estimated or verified at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months *during actual releases.

ACTION 37- DELETED ACTION 38- DELETED ACTION 40- Wrth the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Tabl~ 2-1.

SO123-0DCM Revision 16 11/2020

TABLE 4-3 (Co"ntinued)

TABLE NOTATION ACTION 41- Wrth the number of channels FUNCTIONAL less.than required by the M'inimum Channels FUNCTIONAL requirement, effluent releases via this pathway max continue provided:. -

a. The process flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when working with radioactive materials in the South Yard Facility Building.

System design characteristics may be used to estimate flow.

b. The particulate sample flow rate is estimated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I ,o~;:

when working with radioactive materials in the South Yard Facility ~

Building.

ACTION 42- Wrth the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the monitor is venfied FUNCTIONAL by performing a channel check at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

SO123-0DCM Revision 16 11/2020 I[J

~:::_

4-10

TABLE 4-4 RAOIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTE: Frequency notations are found in Table 6-2,* Frequency Notation.

CHANNEL.

CHANNEL SOURCE CHANNELS FUNCTIONAL INSTRUMENr- CHECK CHECK CALIBRATION TEST APPLICABILITY

1. PLANT VENT STACK (2/3RT-7808)

a. Noble Gas Activity Monitor - DELETED I~

b. Iodine Sampler - DELETED C. Particulate Sampler w NA NA NA *

d. Associated Sample Flow Measuring Device D NA R Q *

e. Process Flow Rate Monitoring Device D NA R Q *

2. *CONTAINMENT PURGE SYSTEM (2(3)RT-7828)****

a. Noble Gas Activity Monitor - DELETED I~

b. lodine:sampler - DELETED C. Particulate Sampler w* NA NA NA *

d. Process Flow Rate Monitoring Device D NA R Q *

e. Associated Sample Flow*

Measuring Devi~ D NA R Q

SO123-0DCM Revision 16 11/2020 .

4-11

TABLE 4-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE

CHANNEL FUNCTIONAL INSTRUMENT"""" CHECK CHECK CALIBRATION TEST APPLICABILITY

3. SOUTH YARD FACILITY (SYF) VVORK AREA (SYFRU 7904).

a. Iodine Sample~ - DELETED

b. particulate Sampler w NA NA- NA

I~

C. Process Flow Rate Monitoring Device. D(6) NA NA NA *

d. Associated Sample Flow Measuring Device o ~~NA R NA~~

I~
5O123-ODCM.
Revision 16 11/2020 4-12
TABLE 44 (Continued)
TABLE NOTATION
~~At all times.~~
~~DELETED~~
Monitor Recorders are not required for the FUNCTIONALITY of the monitor, providing .the non-FUNCTIONAL recorder does-not cause the monitor to become non-FUNCTIONAL (i.e., feedback* signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based on surveillance requirements) and isolation function (if applicable), the loss of the recorder does. ~ot render the monitor non-FUNCTIONAL.
~~DELETED (1) DE,LETED I~~~
(2) DELETED (3) DELETED (4) DELETED (5) Daily checks only required during times of working with radioactive materials in the South Ya("d Facility Bui[ding. - *
(6) DELETED (7) DELETED SO123-0DCM Revision 16 11/2020 4-13
4.0 EQUIPMENT (Continued) 4.3 FUNCTIONALITY OF RADIOACTIVE WASTE EQUIPMENT The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous, and solid waste management systems are shown in Figures 4-5 thru 4-7.
SO123-0DCM Revision 9 11/2015 4-14
SONGS RADIOACTIVE LIQUID WASTE EFFLUENT SYSTEMS Figure 4-5
~~ABS, CON, ~A, BPS, FFCJ>D Turbtne Buudmg Sump~~
~~2RT-7821 (Continuous}~~
~~Portable Radwaste~~
Treatment System*
Miscellaneous Waste Evaporator Condensate Monitor Tank(s)/Spent Fuel Pool Makeup 2/3RT-7813 Water Tank(s}/
Radioactive Waste SecondaryTank(s}/
(Batch}
Dewatermg/
Extraction NIAYDS 2/3RT-2101 (Continuous} I ---,
I Unrt:2 :
~~Outfall 1 L..--* ___ I KEY~~
~~PAOFIC OCEAN Radiation flllomtor ic..,re 4-5 5?NGS RoaaeCIMI ~qud Waste Systems S0123-0DCM Revision 15 08/2020 4-15~~
SONGS RADIOACTIVE GASEOUS WASTE EFFLUENT SYSTEMS Figure 4-6 .
rv,...,,...,,...,,...,~,...,,...,,...,,...,rvn.,rv,v ATM Q Sp HERE rvrvrvrvrvrvrvrvl'U":r..,rvrviv,vrv
~
~
Radia tfon Sam pie Radiation 5k Id Sample 3RT7 828 Sample Skid - >--- Skid 2RT7828 SYF7904 .
Radiation Sample Skid' 2/3RT7808 Plant Vent Stack Common Plenum Containment Containment Purge Purge South Yard Unrt: 2 Building .Unrt: 3 Building Fac1l1ty
\/ent1latJon Vent1latfon Work Area Exhaust Exhaust . Exhaust Figu~4-6SONGS R.Jd01~ Giseol.15 WiS10 Tr8oltllllfflt Syst00"5 Units 2 and Unit 3 Building Ventilation Exhaust sources include but are not limited to the Spent Fuel Buildings, Penetrations Buildings, Radwaste Building, Safety Equipment-Buildings, and Containment Buildings when personnel hatch is open.
~~SO123-ODCM Revis.ion 16 11/2020 4-16~~
SOLID WASTE HANDLING Figure 4-7 PT=~ a:caa1111Ce
~--
with Thwlstar to "4 PHF
~Jles.1 - SOS-W Ml-f'CO-OOO18
---+ ,fo,; int~ ~ ' l)f1d IOad b"io $l'llpplrl Vassel 81'1 d ti,p * .....
~I COJeffr f o r ~ .....
~bl.rl!llslte w~~~1onror Wssts ~ e d Into I WMteltlp~ to Pl!rtlctJlete Process~
--I>
Fb!rremoted from In-lint postbn Firer stored ti 1CCU ITlUAU:>n
.,-eams!te stipplrl! to burial site to lrnrrntdiate pro(Mlpr 4 fa alternate jX'OC~
corralncr ~ IICC0f061 ce with burial tlu! <:1 Intermediate i:r=r
.... oorlal site or
!me'~
P'~
methods dispoSltlon reQIWemeitS Wastesco&!aed Waste placed in Ra.J~ ~
Wastesllppe:l to Low Lllvel o,y lnrec~ ClftOcoru!Mr - mis:1 pa,:klcld and
--+ 1:nx:~f0t vollme ActlveW~e lcalted a" oond
~
fa shipment to shiwed ftom proc:=or thl!ipltm otr-su~ __., reduction robu1al',u W11$e50ftedfor -
pactl!li'lg o~e Wastespad:aeedl!nd Wmtesh pped to burl!!I
~~. ;. r,t,,~~
or vendor trar!!tmedtoMPtlf ~
fY~
Cbminibais. Cixoog pad:~
CiJth&li~,
PrcnctlYe co!ected from - in bo!(es shlppad, .
--I> tei:umed to site Md Cbtht'lj points Mound - to~-5ltelaurory 1'$ocl.ed plent l'leki(,;
11:.EGEND:
MPl-If: MultM'urpo2 Ran:Ui'l! P1!dl.l:y CM Revision 16 11/2020
~~4-17~~
~~5 ..0~~
RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 MONITORING PROGRAM' SPECIFICATION 5.1.1 The radiological environmental monitoring program shall be conducted. as specified in Table p--1. The reqLlirer:nents are applicable at all times. .
APPLICABILITY: At all times ,.
ACTION:
a: Should the radiological environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any*other report required by
. Licensee Controlled Specifications Section 5. 7 .1, prepare and submit to tt,e Commission, 1n* the Annual Radiologica~ Environmental Operating
Report (see Section 5.4), a d~scription of the reasons for not conducting the progral'!l as required and *t~e plans for preventing a recurrence. *
b. Should the level of _radioactivity in an environmental sampling medium exceed the reporting levels of Table 5-2 when averaged over any*
calendar quarter, in lieu of any other report required by Licensee Controlled Specifications Section 5.7.1, prepare and submit to the Commission, within 30 days from the end of the affected calendar quarter a Report pursuant to 10 CFR50.73. Wnen more:than one of the radionuclides in Tab!e 5-2 are deteGted in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + .. *. ~ 1.0 limit level (1) . limit level (2)
c. When radionuclides other than those in Table 5-2 are detected and are the *result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equat to or greater than the cal.endar year limits of Specification(s) 1.2.1, 2.2.1, or 2.3.1, as appropriate. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such_ an event, the condition shall be rep~rted and described in the Annual Radiological Environmental Operating Report (see _Section 5.4).
SO123-0DCM Revision 15 08/2020 5-1
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued)
\
5.1 MONITORING PROGRAM (Continued)
ACTION: (Continued)
d. With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by *
Table 5-1, identify specific locations for obtaining replacement samples and ac;fd them within.30 daySi to tt,e Radiological E,nvironmental Monitoring Program given in the ODCM. The specific locations from which sam'ples were unavailable may then be, deleted from the monitoring
~~program. Pursuant to Licensee Controlled Specifications 5. 7: 1, submit in~~
[iI ]
O N
the next Annual Radioactive Effluent Release Report documentation for a * ~
change iri the ODCM including a revised figure(s) and table for the QDCM
.reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obta.ining samples.
SURVEILLANCE REQUIREMENT
.1 The radiologi~I environmental mo,nitoring samples sh~II be collected pursuant to Table 5-1 from the locations given in Table 5--4 and Figures 5-1 through 5-5 and shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.
. '\
SO123-0DCM Revision 15 08/2020 5-2
TABLE 6-1 RADIOLOGICAL*ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sample*s Sampling and .
and/or Sample and Sample Locations& Collection Frequency8 Type and Frequency of Analyses *
1. AIRBORN~ Samples from at least 5 locations: Continuous operation of Particulate sampler. AnalyzeJor gross Particulates sampler with sample beta radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following 3 samples from offsite locations (in collection as required by *fitter change. Perform gamma isotopic" different sectors) of the highest dust loading, but at least analysis on each sample when gross calculated annual average ground level once per 7 days. beta activity. is > 10 times the yearly D/Q_, . mean* of control samples. Perform gamma isotopic analysis*on* composite 1 sample from the vicinity of a _ (by location) sample at least once per community having the highest calculated 92 days..
annual average ground-level D/Q .. *
-1 sample from a control location
,15-30 kni.(10-20 miJes) distant and in the least prevalent Wind directionc.
~~2. DIRECT At least 30 locations including an inner At least once per 92 days. Gamma dose. At least once per 92 days.~~
'RADIATION 8 ring of stations in the general area of the site boundary ahd an outer ring approximately in the 4 to 5 mile range from the site with a station in each sector of each ring. The balance of the stations i,s ii") special i_nterest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control _, stations.
SO123-ODCM .
Revision 16 11/2020 5-3
TABLE 5-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locationsa Colfection Frequency' Type and Frequency of Analyses
~~3. WATERBORNE~~
a. Ocean 4 locations At least once per month and Gamma isotopic analysis of each compositectf quarterly. monthly sample. Tritium analysis of composite sample at least once per 92 days.
~~b. Drinking - DELETED~~
~~c. Sediment 4 locations from Shoreline At least once per 184 days. Gamma isotopic analysis of each sample.~~
~~d. Ocean 5 locatic;ms Bottom Sediments At least once per 184 days. Gamma isotopic analysis of each sample.~~
_ SO123-0DCM Revision 16
- 11/2020 5-4
TABLE 5-1 (Conti~ued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM--
Exposure Pathway Number of Samples .Sampling and and/or Sample and Sample Locations8 Coliection Frequency8:
~~Type and Frequency of Analyses~~
~~4. INGESTION.~~
a. Animals 3 locations One sample in season, or Gamma isotopic analysis on edible Nonmigratory at least once per 184 days portions. ***
~~Marine if not seasonal. One sample~~
~~of each of the following species:~~
~~1. FJsh-2 adult species such as perch or~~
~~.sheephead.~~

~~2. Crustaceae-such as crab or lobster.~~
~~3. Mollusks-such as limpets, seahares or clams.~~
~~b. Local Crops 2 locations Representative yegetables, Gamma isotopic analysis on edible nom,ally 1 leafy and portions semiannually.~~
~~1 *fleshy collected at harvest :~~
time. At least 2 vegetables collected* semiannually from each location.
SO123-ODCM Revjsion_ 16 11/2020 5-5
TABLE 6-1 (Continued)
TABLE NOTATION
~~a. Sample locations are indicated on Figures 5-1 through 5-5.~~
~~b. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.~~
c. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.
~~d. DELETED . * .~~
e. Reg. Guide 4.13 (Revision O) provi~es minimu'!l acceptable performance criteria for thermoluminescence dosimetry (TLD) system~ used for environmer,tal monitoring. One or more instruments, such*as a pressu~zed ion-chamber, for measuring and recording dose rate continuously may, be used in place of, or in addition to, integrating _dosimeters. For the* p,urpose of this tabl'e, a*
thermoluminescent dosimeter may- be considered to be one phosphor and two or: more phosphors in a packet may ,be considered as.two or more dosimeters. Film badges should not be used for.measuring direct radiation.
f. Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquo.t at time intervals which are very short (e.g., _hourly) relative to the compositing period (e,g., monthly).
g .. DELETED s*o123-ODCM Revision 16 11/202Q 5-6
TABLE 6-2* .
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Airborne Particulate
. Water* or Gases Marine Animals Local Crops Analysis (pCi/1). (pCi/m 3) (pCi/Kg, wet) (pCi/Kg, wet)
H-3 3 X 10E4 Mn-54 1 X 1Q3 3 X 104 Co-58 1 X 103 3 X 104 Co-60 3 X 102 1 X 104 Zn-65* 3 X 102 2x.104.
Cs-134 30 10 1 X 103 1 X 103 - I~
3 3 Cs-137 50 20 2 X 10 2 X 10 i~
/
(a) DELETED (b) DELETED SO123-0DCM Revision 16 11/2020 5-7
TABLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISlc>
~MUM VALUES FOR THE LOWER LIMITS OF DETE~ION (LLD)l*l Airborne Particulate Water- or Gases Marine Animals Local Crops Sediment Analysis (pCi/I) (pCi/m 3 } *(pCi/Kg, wet) (pCi/Kg, wet) (pCi/Kg, dry) gross beta 4 1 X 10-2 H-3 *3000 Mn-54 15 130 I~
I ;::
Co-58,-60 15 130 Zn-65 - 30 260 Cs-134 15 5 X 10-2 130 60 150 6x 10-2 80 I~N Cs-137 18 150 180 I~
SO123-ODCM Revision 16 11/2020 5-8
TABLE 6-3 (Continued)
TABLE NOTATION
a. The LLD Is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
/
LLD= 4.66Sb E *V *2.22 x 10 6 *Y
~~exp (-N'.ii")~~
where:
LLD = "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume)
Sb = standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E = counting efficiency (as counts per transformation)
V = sample size (in units of mass or volume) 2.22 X 106 = number of transformations per minute per microcurie Y = fractional radiochemical yield (when applicable)
>-.. = radioactive decay constant for the particular radionuclide b.t = elapsed time between midpoint of sample collection or end of the collection period and time of counting (for environmental samples, not plant effluents)
The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., Potassium-40 in milk samples). Typical values of
~~E, V, Y and b.t shall be used in the calculations'.~~
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of the measurement system and not as a posteriori (after the fact) limit for a particular measurement.*
~~For a more complete discussion of the LLD, and other detection limits, see the following:~~
(1) HASL Procedures Manual, HASL-300 (revised annually).
(2) Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968). SO123-ODCM Revision O 02-27-07 5-9
TABLE 5-3 (Continued) .
TABLE NOTAT_ION (Continued)
~~b. DELETED~~
~~c. Other peaks which are measurable and identifiable, together with the radionuclides in Tab(~ 5-3, shall be identified and reported.~~
~~d. DELETED SO123-ODCM Revision 16 11/2020 5-10~~
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) ..
5.2 LAND USE CENSUS SPECIFICATION 5.2.1. A land* use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the.nearest garden* of greater than 500 *square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five.miles.
APPLICABILITY: At all times ACTION:
a. Wrth the land use census identifying a location(s) that yields a calculated dose or dose c::ommitment greater than the values currently being calculated in Specification 2.3.1, pursuant to Licensee Controlled Specifications Section 5. 7.1, identify the new locations in the next Annual
~~\ 1~;::~~
~~Radioactive Effluent Release Report.~~
~~b. With the land use census identifying a location(s) that yields a calculated doSE! or dose commitment (vi~ the same exposure pathway) 20 percent_~~
greater than at a location from wtiich samples are currently being obtained in accordance with Specification 5.1.1, add the new location within 30 *days to the Radiological Environmental Monitoring Program I
I~
given in the ODCM. The sampling location(s), excluding the control
_station location, having the lowest calculated dose or.dose commitment(s) via the same exposure pathway, may be deleted from this monitoring.
program after October 31, of the year in which this Land Use Census was conducted. Pursuant to Licensee Controlled Specifications Section 5.7.1, submit in the next Annual Radioactive Effluent Release Rep_ort I
I ~
.documentation for a *change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.
SURVEILLANCE REQUIREMENT
.1 The land use census shall be conducted at least once per* 12* months between the dates of June 1 and .October 1 using that information which will provide the best results, such as by a door-to-<l.oor survey, aerial survey, or by consu~ng local agriculture authorities.
~~Broad leaf vegetation sampling may be performed *at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.~~
SO123-0DCM Revision 15 08/2020 5-11
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.3 INTERLABORATORY COMPARISON PROGRAM SPECIFICATION 5.3.1 Analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program that complies with Reg.
Guide 4.15.
APPLICABILITY: At all times ACTION:
~~a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.~~
SURVEILLANCE REQUIREMENT
.1 A summary of the results obtained as part of the above required lnterlaboratory Comparison Program and in accordance with Section 5.4.1 of this document shall be included in the Annual Radiological Environmental Operating Report (see Section 5.4).
SO123-ODCM Revision O 02-27-07 5-12
5.0 .RADIOLOGICAL ENVIRONMENTAL MONITORING (Co_ntinued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*
5.4.1 The Annual Radiologi~I Environmental Operating Report covering the operation of the unit during the previous *calendar year shall be submitted by May 15 of each year. The report shall include summaries, _
interpretations, and analyses of trends of the results of the Radiological Environmental Mo-nitoring Program for the reporting period. The material provided shall be consistent ~ith the objectives outli!led in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I,
.Sections-lV.B.2, IV.B.3, and IV.C. -
The Annual .Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period-pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the-Radiological Assessment Branch Technical Position, Revision 1, November 1979. The report shall identify the thermoluminescenf dosimeter (TLD) results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result, In the event that spme individual results c;1re not available for intjusion with the repprt, the report shall be s_ubmitted noting and explaining the reasons for the* missing results. The missing data shall be submitted in a_ supplementary report as soon as possible.
~~A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all ;units at the station; however, for units with separate radwaste_~~
systems, the submittal shall specify the releases of radioactive material from each unit.
SO123-0DCM Revision 16 11/2020 5
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORJNG (Continued) 5.5 SAMPLE LOCATIONS The Radiological Environmental Monitoring Sample Locations are identified in Figures 5-1 through 5-5. These sample locations are described in Table 5-4 and indicate the distance in miles and the direction, determined from degrees true north, from the center of the Units 2 and 3 building complex. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, Figures 5-1 through 5-5.
SO123-0DCM Revision 0 02-27-07 5-14
Page 1 of 5 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*
TYPE OF SAMPLE AND SAMPLING LOCATION . (miles} DIRECTION*
Direct Radiation 1 City of San Clemente (Former SDG&E Offices) 5.7 NW 2 Camp*San Mat~o (MCB, Camp Pendleton) .. 3:6 N 3 Camp San Onofre (MCB, Camp Pendleton) 2.8 NE 4 Camp Homo (MCB, _Camp Pendleton) 4.4 E 6 Old El Camino Real (AKA Old:Route 101) 3.0 ESE 8 Noncommissioned Officers' Beach Club- 1.4 NW 10 Bluff .(Adjacent to Former PIC #1) 0:1
WNW 11 Former Visitors' Center 0.4** NW 12 South Edge of Switchyard 0.2**.* E 13 Southeast Site boundary (Bluff) 0.4** ESE
~~15 . Southeast Site B(?_Undary (Office -Building) 0.1** SSE 16 East Southeast Site Boundary 0.4** ESE 17 DELETED.~~
18 DELETED*
19 San .Clemente Highlands 4.9 NNW 22 Former U.S. Coast Guard Station -*san Mateo Point* 2.7 WNW 23 SDG&E Service Center Yard 8.1 NW 31 Aurora Park-Mission Viejo 18.6 NNW 33 Camp Talaga (MCB, Camp Pendleton) 5.9 *N 34 San *onofre School (MCB, Camp Pendleton) 1.9 NW
35 Range 312.(I\n'CB, Camp Pendleton) 4.8 NNE 36 Range 208C (MCB, Camp Pendleton) 4.1 NE 38 San Onofre Sta:te Beach Park 3.4* SE
. '40 41 SONGS Gard~n - Mesa (Adjacent to Former PIC #3)
Old Route 101 - East 0.7 0.3**
NNW E
im 44 Fallbrook Fire Station 17.7 E 46 San Onofre state Beach Park 1.0 :. SE
- 8:s 47 Camp Las Flores (M_CB, Ca.mp
. . Pendleton) _ SE SO123-0DCM Revision 16 11/2020 I~
5-15
~~Page 2 of 5 TABLE 54 (Continued)~~
RADIOLOGICAL ENVIRONMENTAL MONITORING . SAMPLE LOCATIONS DISTANCE*
TYPE OF SAMPLE AND SAMPLING LOCATION. *. (miles} DIRECTION*
Direct Radiation (Continued) 49 Ca~p Chappo (MCB~ Camp Pendleton) 12.9 ESE 50 Oceanside Fire. Station (CONTROL) *
~~15.6 SE~~
, 53 San Diego County Qperations Center 44.2 * *SE 54 Escondido Fire Station 31.8 ESE*
55* San Onofre State Beach (Unit 1, West) 0.2** WNW 56 San Onofre State Beach (Unit 1, West) 0.2** w 57 San Onofre State Beach (Unit 2) 0.1~ SW 58 San Onofre State Beach (Unit 3) 0.1** s 59 SONGS Meteorological Tower 0.3** WNW 60 DELETED 61 Mesa - East Boundary (Adjacent to Former PIC #4) 0.7 N 62 MCB - Camp Pendleton (Adjacent to Former PIC #5) 0.7 NNE 63 MCB - Camp *Pendleton (Adjacent to Former PIC #16) 0.6 NE 64 MCB - Cam*p Pendleton (Adjacent to Former PIC #7) 0.6 .* ENE 65 . MCB - Gamp Pendleton (Adjacent to Former P!C #8) 0.7. E 66 San Onofre State Beach Park (Adjacent to Former PIC #9) 0.6' ESE I~
67 Former SONGS Evaporation Pond 0.6 NW (Adjacent to Former PIC #2) 68 Range 21 0C (MCB, Camp Pendleton) 4.4 ENE 73 *South Yard Facility 0.4** ESE.
1 74 Oceanside City Hall (Backup CONTROL) 15.6 SE 75 Gate 25 MCB 4.6 SE 76 Former El Camino Real Mobil $tation 4.6 NW 77 Area 62 Heavy lift pad 4.2 N 78 Homo Canyon (AKA. Sheep Valley) 4.4 . ESE
~~Distance (miles) and Dire.ction (sector) are me~ured relative to Units 2 and 3 midpoint.~~
~~Direction is determined .from degrees true north.~~
~~Distances are within the Units 2 and 3-Site Boundary (0.4 mile in all sectors) and not required by Regul~tory Guidance.~~
SO123-ODCM Revision 16 11 1-1/2020 I~
5-16
Page 3 of 5 TABLE 5-4 (Continued) .
RADIOLOGICAL ENViRONMENTAL MONITORING SAMP.LE LOCATIONS DISTANCE*
TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION*
Airborne 1 City of San Clemente (City Hall) 5.1 NW 7 AWS Roof 0.18** NW 9 State Beach Park 0.6 ESE 10 Bluff 0.7 WNW 11 Mesa EOF 0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E 14 DELETED 15 DELETED 16 San Luis Rey Substation (CONTROL) 16.7 SE Soil Samplest 1 Camp San Onofre 2.8 NE 2 Old Route 101 - (East Southeast) 3.0 ESE 3 Basilone Road/1-5 Freeway Offramp 2.0 NW 5 Former Visitor's Center 0.4** NW
.6 DELETED 7 Prince of Peace Abbey (CONTROL) 15 SE Ocean Water A Station Discharge Outfall - Unit 1 0.6 SW B Outfall - Unit '2 1.5 SW C Outfall - Unit 3 1.2 SSW D Newport Beach (CONTROL) 30.0 NW
~~Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint.~~
Direction is determined from degrees true north.
Distances are within the Units 2 and 3 Site boundary (0.4 mile in all sectors) and not required by Regulatory Guidance.
t Soil Samples are not required by Regulatory Guidance.
SO123-0QCM Revision 15 08/2020 5-17
Page 4 of 5 TABLE 5-4 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*
TYPE OF SAMPLE AND SAMPLING LOCATION {miles) DIRECTION*
Qrinking Water - D~leted
\
Shoreline. Sediment (Beach S~nd)
. I~
1 San Onofre state Beach (Southeast) 0.6 SE 2
San Onofre Surfing 'Beach 0.8 WNW 3 San Onofre state Beach (Southeast) 3.5 SE*
~~4 Newport Beach (North End) (CONTROL) * . 29:2~~
~~NW' Local Crops 1 DELETED~~
\
2 Oceanside (CONTROL)** 15 to 25 . SE to ESE 4 DELETED 6 SONGS Garden*** 0.7 NNW Distance (miles) ahd Direction (sectqr) are measured relative to Units 2 and 3 midpoint.
~~Direction is determined from degrees* true north.~~
~~Controi-location should be in Sector G or F, 15 to 25 miles from site. The control location~~
~~will be selected based on sample-avail.ability. The exact location shall be noted in the Annual Radiological Environmental Operating Report.~~
The SONGS Garden, location 6, for local crops, was relocated 0.1 miles west arid 0.3 miles north to remain on controlled property with irrigation adjacent to former PIC #3 ori September 2015 and 113niains at the site boundary. Prior to*september 2015, SONGS Garden, location 6, was just inside the east border of Sector R, 0.4 miles out from the E-50 building. . . \ .
SO123-0DCM Revision 16 11/2020 5-18
TABLE 5-4 (Continued) Page 5 of 5*
RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS
DISTANCE*
TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION*
Non-Migratory Marine Animals A Unit 1 Outfall* 0.9 WSW B Units 2 and 3 Outfall 1.5 SSW C Laguna Beach (CONTROL)** 20 to 25 WNWtoNW Kelpt A San Onofre Kelp Bed 1.5* s B San Mateo Kelp Bed 3.8 WNW C Barn Kelp Bed 6.3 SSE to SE D DELETED E Salt Creek (CONTROL) 11 to 13 WNWtoNW Ocean Bottom Sediments A DELETED B Unit 1 Outfall 0.8 SSW C Unit 2 Outfall 1.6 SW D Unit 3 Outfall 1.2 SSW E Laguna Beach (CONTROL) 20 to 25 NW F SONGS Upcoast 0.9 WSW
~~Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint.~~
~~Direction is determined from degrees true north.~~
~~A location more distant from SONGS in the WNW to NW direction may be used as the CONTROL location. .~~
t Kelp samples are not required by Regulatory Guidance.
SO123-0DCM Revision 15 08/2020 5-19
TABLE 5-5 PIC- RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS DELETED REMAINDER OF PAGE LEFT INTENTIONALLY BLANK S0123-0DCM Revision 9 11/2015 5-20
TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP DEGREES TRUE NORTH FROM SONGS 2 AND 3 MID-POINT NOMENCLATURE Sector Center Sector 22.5° Limit Line Limit Sector* Direction 348.75 0 & 360 11.25 A N 11.25 22.5 33.75 B NNE 33.75 45.0 56.25 C NE 56.25 67.5 78.75 D ENE 78.75 90.0 101.25 E E 101.25 112.0 123.75 F ESE 123.75 135.0 146.25 G SE 146.25 157.0 168.75 H SSE 168.75 180.0 191.25 J s 191.25 202.5 213.75 K SSW 213.75 225.0 236.25 L SW 236.25 247.5 258.75 M WSW 258.75 270.0 281.25 N w 281.25 292.5 303.75 p WNW 303.75 315.0 326.25 a NW 326.25 337.5 348.75 R NNW
~~Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint.~~
Direction is determined from degrees true North.
SO123-0DCM Revision O 02-27-07 5-21
RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS 1 MILE RADIUS Figure 5-1 0
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SO123-ODCM Revision 16 11/2020 5-23
RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS 5 MILE RADIUS Figure 5-3 SectorC NE T\.036@
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SO123-ODCM Revision 16 11/2020 5-24
RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS-ORANGE COUNTY Figure 5-4 Fi gure 5-4 San Onofre REMP 30-Mil e North
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SO123-ODCM Revision 16 11/2020 5-25
RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS - SAN DIEGO COUNTY Figure 5-5
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SO123-ODCM Revision 16 11/2020 5-26
6.0 ADMINISTRATIVE 6.1 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable through these Specifications.
ACTION 6.1.1 ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions.
CHANNEL CALIBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel, including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel Is calibrated.
CHANNEL CHECK 6.1.3. A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 6.1.4 A CHANNEL FUNCTIONAL TEST shall be:
~~a. Analog channels - the injection of a simulated signal into channel as close to the sensor as practicable to verify FUNCTIONALITY, including alarm and/or trip functions.~~
~~b. Bistable channels - the injection of a simulated signal into the sensor to verify FUNCTIONALITY, including alarm ahd/or trip functions.~~
~~c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify FUNCTIONALITY.~~
SO123-0DCM Revision 9 11/2015 6-1
I 6.0 ADMINISTRATIVE (Continued) 6.1 DEFINITIONS (Continued)
FREQUENCY NOTATION 6.1.5 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2.
FUNCTIONAL - FUNCTIONALITY 6.1.6 A system, subsystem, train, component or device shall be FUNCTIONAL or have FUNCTIONALITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).
MEMBERS OF THE PUBLIC 6.1.7 MEMBER(S) OF THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This./
category complies with the requirements of 10 CFR 50 and shall include non-employees of the licensee who are permitted to use pc;>rtions of the site for recreational, occupational, or purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
PURGE - PURGING 6.1.8 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
SITE BOUNDARY 6.1.9 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.
SOLIDIFICATION 6.1.10 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
SO123-0DCM Revision 9 11/2015 6-2
6.0 ADMINISTRATIVE (Continued) 6.1 DEFINITIONS (Co_ntinued)
SOURCE CHECK 6.1.11 For Sorrento Electronics oigital monitors, a SOURCE CHECK shall be the verification- of proper computer response to a check source request.
[2.(3)RT-7828, 2(3)RT-7865-1] .
For MGPI* monitors a SOURCE CHECK shall be the verification of proper computer response to the continuous_ internal detector, monitor.calibration and electrical checks. [2RT-7821, ?J3RT-7813, 2/3RT-7808G! 2/3RT-2101]
SURVEILLANCE REQUIREMENT: MEETING SPECIFIED FREQUENCY 6.1.12 The *specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified co-ndition of the Frequency is met.
For F:reql!encies specified as "once," th*e above interval extension* does not apply.
If a Completion Time.requires periodic performance on a "once.per ... "
basis,-the above Frequency extension applies to each performance.after the initial performance.
This provision is not intended to be used repeatedly as a convenient means to extend surveillance intervals beyond those specified.
Additionally, it does not apply to* any Action statements.
VENTILATION EXHAUST TREATMENT SYSTEM 6.1.13 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioactive material in particulate form in effluents by passing ventitation or vent exh~ust gases thn;:,ugh HEPA filters for the purpose-of removing particulates from the gaseous* :
~~exhaust stream prio.r to the release to the environment.~~
NOTE: Local mobile vent[lation exhaust treatment system will be used on an as needed bases when outdoor activities have the potential for
. gaseous effluent releases.
~~SO123-ODCM Revision 16 11/2020 6-3~~
6.0 ADMINISTRATIVE (Continued) 6.1 DEFINITIONS (Continued)
VENTING 6.1.14 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent used in system names does not imply a VENTING process.
SO123-0DCM Revision O 02-27-07 6-4
TABLE 6-1 OPERATIONAL MODES DELETED REMAINDER OF PAGE LEFT INTENTIONALLY BLANK SO123-0DCM Revision 9 11/2015 6-5
TABLE 6-2 FREQUENCY NOTATION NOTATION FREQUENCY s At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months w At least once per 7 days M At least once per 31 days a At least once per 92 days SA At least once per 184 days R At least once per 18 months*
p Completed prior to each release N.A. Not applicable 3xW At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 3 times per week (usually M, W, F).
~~A month is defined as a 31-day period.~~
SO123-0DCM Revision 9 11/2015 6-6
6.0 ADMINISTRATIVE (Continued) 6.2* ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*
6.2.1 The Radioactive Effluent Release Report covering the operation of the facility during the previous calendar year shall be submitted before May 1 of each year. Tt~e report shall include a summary of the quantities of radioactive ,liquid and gaseous effluents released froni the facility. The report shalJ also include a summary of the quantities of solid radioactive waste shipped .from the facility directly to the disposal site and quantities of solid radioactive waste shipped from the facility's intemiediary processor to ttie disposal site. The material provided shall be consistent with the objectives outliried in the ODCM and Process Control Program (PCP) and in confom,ance with 10 CFR 50.36a and* 10 CFR 50, -
Appendix 1, Section IV.B.1.
6.2.2 The radioactive effluent release reports shall in.elude a summary of the quantities of radioactive liquid and gaseous efflu'ents and solid waste released from the facility as outlined *in Reg. Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes *and *Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1,_ June 1974, with data
. summarized on a quarterly basis following the fomiat of Appendix B thereof.
The radioactive effluent release report shall include an as~ment of the radiation doses duefo the radioactive liquid and gaseous effluents released from the facility during the previous calendar year. This same report shall also include an assessment of the radiation doses from
. _tadioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 1-2 and 2-2) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure-time and location) shall be included in these reports. The meteorological conditions shall be used for_
cletemiining the gaseous pathway doses. The assessment of radiation doses shall be perfom,ed in accordance with the OFFSITE DOSE
~~CALCULATION MANUAL (ODCM)'. .~~
A single submrttal may be made for a multiple unit station The submrttal should combme_those sactJons that are common to all units_at the Stat:Jon, however, for unrts wrth separate radwaste system~. the submittal shall spaafy the releases of radioactJve matenal from each unit SO1.23-0DCM Revision 16 11/2020 6-7
6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS (Continued) 6.2.2 (Continued)
The radioactive effluent release report shall also include an assessment of radiation doses to 'the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby Uranium fuel cycle sources (including doses ~om primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Reg. Guide 1.109, Rev. 1.
The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:
~~a. Container volume,~~
~~b. Total curie quantity (specify whether determined by measurement or estimate),~~
~~c. Principal radionuclides (specify whether determined by measurement or estimate),~~
~~d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),~~
~~e. Type of container (e.g., LSA, Type A, Type B, Lar:ge Quantity), and~~
~~f. Solidification Agent (e.g., cement, urea formaldehyde).~~
The radioactive effluent release report shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.
The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.
SO123-0DCM Revision 9 11/2015 6-8
6.0 ADMINISTRATIVE (Continued) 6.3 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS
{Liquid and Gaseous)
Licensee initiated major changes to the radioactive waste systems (liquid and gaseous):
~~1. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was performed. The discussi~n of each change shall contain:~~
~~a. A summary of the evaluation that led to the determination that the change could be made in accordance with applicable regulations;~~
~~b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;~~
~~c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;~~
d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments thereto;
e. An evaluation of the change which shows the expected maximum exposures to indMdual in the unrestricted area and to the general population that differ from thos1p previously estimated in the license application and amendments thereto;
f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents to the actual release for the period prior to when the changes are to be made; ,
~~g. An estimate of the exposure to plant operating personnel as a result of the change; and~~
~~h. Documentation of the fact that the change was reviewed and found acceptable~~
~~2. Shall become effective upon review and acceptance.~~
SO123-0DCM Revision 9 11/2015
(
6-9
6.0 ADMINISTRATIVE (Continued) 6.4 BASES LIQUID EFFLUENTS CONCENTRATION. (1.1) 6.4.1 This specification is provided to ensure that the concentration of radioactive rriaterials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that*
the levels of radioactive materials in bodies of water outside the site will result In exposures within (1) the Section Ii.A design objectives of Appendix I, 10 CFR 50, to an individual, and (2) the limits of 10 CFR
. *?0, 106(e) 'to the population:
DOSE (1.2) 6.4.2 This specification is provided to implement the requirements of Section II.A, Ill.A ,and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix-I to assure that the releases of radioactive material in liquid effluents will be*
kept "as low as is reasonably achievable." The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix I that c.onfom,ance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure o.f an individual through appropriate pathways is unlikely to be substantially
~nderestimated. The equations specified in the ODCM for calculating the doses due to the ~ctual release rates of ~dioactive materials in liquid effluents are consistent with the methodology provided in Reg.
Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor-~ffluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Reg.
Guide 1-.113, "Estimating Aquatic Dispersion of Effh,ients from Accidental and Routine Reactor Releases for the Purpose of Implementing* -
Appendix I," April 1977.
This specification applies to the release of liquic;i effluents from each unit at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system. **
. SO123-ODCM Revision 16 11/2020 6-10
6.0 ADMlNISTRATIVE (Continued) 6.4 BASES (Continued)
LIQUID WASTE TREATMENT (1.3) 6.4.3 The FUNCTIONALITY of the liquid radwaste treatm*ent system ensures that this system will be available for use whenever liquid effluents require
. treatment prior to release to the environment The requirement that the appropriate portions of this system be* used wh~n specified provides assurance that the releases of radioactive materials *in liquid effluents. will
.be kept-"as low as is reasonably achievable." This'.specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to .1 O CFR Part 50 and the design objective given in Section I1.D of Appendix I to 10 CFR Part 50. The specified limits governing *the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
GASEOUS EFFLUENTS DOSE RATE (2.1) 6.4.4 This specification is provided to ensure that the dose at ar:iy time at the site
. boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annuar dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, .Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result In the exposure of an individual in an unrestricted area, either
.within or outside the site boundary, to annual average concentrations
~xceeding the limits'specified in Appenqix-8, Table II of 10 CFR Part 20
[10 CFR Part 20.106(b)]. For indMduals 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. These release rate limits also restrict, at_ all times, the corresponding maximum organ dose *rate above background to a member- of the public via the inhalation pathway to less than or equal to ~.
1500 mrem/year.
This specification appiies to the release.of gasepus.effluents from all units at the site. I~
SO123-0DCM Revision 16 11/2020 6-11
6.0 ADMINISTRATIVE (Continued) 6.4 B/1.SES (Continued)
DOSE - NOBLE GASES DELETED 6.4.5. DELETED
- DOS~ - ~DIOACTIVE MATERIALS IN* PARTICULATE FORM AND TRITIUM (2.3) 6.4.6 - This specification .is provided to ir:nplement the requirements of Sectior:,s I1.C, Ill.A, and IV.A of Appendix I, 10 CFR Part 50 1 The Limiting Conditions
. for Operation are the guides set forth in Section I1.C of Appendix I. The ACTION statements* provide the required operating flexibility and at the same time implem.ent the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents wil.I be kept "as low as is reasonably achievable." The ODCM calculational
. methods specified in the Surveillance Requirements implement the requirements-in Section Ill.A of Appendix I that conformance with the **
guides of Appendix I be shoWf'! by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially under:estimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject matenals are consistent with the methodology prqvided in Reg. Guide 1.109, "Calculatiol") of Annual Doses to Man from
Routine Releases of Reactor Effluents fpr the Purpose. of Evaluating Compliance with 10 CFR' Part 50, Appendix I," Revision 1, October 1977 and Reg. Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the ac:tual doses based upon the historical average atmospheric conditions. The release rate specifications for radioactive materials in particulate form and Tritium are dependent on the existing
~~radionuclide pathways to man, in the unrestricted area. The pathways.~~
which were examined in the development of these calculations were: 1) indiviaual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by I1'1an, 3) depo,sition onto grassy areas where milk animals and meat producing *animals graze with .consumption of th*e milk and meat by man, and 4) deposition on the ground with ~ubsequent exposure of man.
(
SO123-ODCM Revision 16 11/2020 6-12
6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)
GASEOUS RADWASTE TREATMENT (2.4) DELETED TOTAL DOSE (3.3) 6.4. 7 This specification is provided to meet the dose limitations of 40 CFR 190.
The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other Uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation which Is part of the nuclear fuel cycle.
SO123-0DCM Revision 9 11/2015 6-13
6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)
RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION (4.1) 6.4.8 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid
. effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments:sha!I be calculated in ~ccordar:ice with the procedures in the ODCM to ensure the alarm/trip will occur piior to exceeding-the limits of 10 CFR Part 20. The FUNCTIONALITY and *use *of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 1o* CFR Part 50.
AADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) 6.4.9 The radioactive gaseous effluent instrumentation is provided to monitor, as applicable,_ the releases c;>f radioactive materials in gaseous effluents during actual or potential releases of' gaseous effluents. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design 'Criteria 60, 63, and 64 of Appendix A to 10 CFR Part. 50.
I
,)
MONITORING PROGRAM (5.1)
The radiological monit9ring *program required by this specification provides measurements of radiation and of radioactive materials in.those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent -
_ monitoring program *l;>y_ verifying the measurable concentr¢ions of radioactive materials *and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the
environmental exposure pathways. The initially specified monitoring program will be effectiye for at least the first three years of commercial operation. Following this. period, program changes may be initiated based on operational experience. -
~~SO123-0DCM Revision 16~~
~~11/2020 6-14~~
6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)
The detection capabilities required by Table 5-1 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
LAND USE CENSUS (5.2)
I 6.4.11 This specification is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.
Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Reg. Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,
~~1) that 20% of the garden was used for growing broad leaf vegetation (i.e.,~~
~~similar to lettuce and cabbage), and~~
~~2) a vegetation yield of 2 kg/square meter.~~
INTERLABORATORY COMPARISON PROGRAM (5.3) 6.4.12 The requirement for participation in an lnterlaboratory Comparison Program is provided to ensure independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
SO123-0DCM Revision 9 11/2015 6-15
Enclosure 4 Offsite Dose Calculation Manual San Onofre Nuclear Generating Station (SONGS)
Page 2-22* of SO123-ODCM Revision 15, August 2020
~~This page was revised in Rev 16 and the changes implemented in Rev 15 were overwritten. The change bars for other changes in Rev 15 are included in the S0123-0DCM Rev. 16 attached as Enclosure 3.~~
TABLE 2-6 UNITS 2&3 CONTROWNG LOCATION FACTORS 1 LkR1kWk Radionuclide mrem/vr per uCl/sec Use:
H-3 1.29E-3 Q: SORB Rec Beach Cr-51 4.43E-2 Q: SORB Rec Beach Mn-54 8.98E+0 Q: SORB Rec Beach Co-57 1.73E+0 Q: SORB Rec Beach Co-58 3.19E+0 Q: SORB Rec Beach Co-60 1.19E+2 Q: SORB Rec Beach Sr-89 1.75E+1 Q: SC Res with Garden Sr-90 6.88E+2 Q: SC Res with Garden Zr-95 3.92E+0 Q: SORB Rec Beach Nb-95 9.03E+0 E: Peer Consumer/Hunter Ru-103 1.43E+1 E: Deer Consumer/Hunter Te-129m 6.49E+O E: Deer Consumer/Hunter Cs-134 3.41E+1 Q: SORB Rec Beach Cs-136 7.68E-1 Q: SORB Rec Beach Cs-137 5.01E+1* Q: SORB Rec Beach Ba-140 3.09E+0 Q: SORB Rec Beach Ce-141 6.74E-1 Q: SORB Rec Beach Ce-144 1.32E+1 Q: SORB Rec Beach I -131 2.58E+1 Q: SC Res with Garden 1-132 1.94E-1 Q: SORB Rec Beach 1-133 3.77E+0 Q: SORB Rec Beach 1-134 5.27E-2 Q: SORB Rec Beach 1-135 7.95E-1 Q: SORB Rec Beach UN-ID 4.94E+0 Q: SORB Rec Beach These values to be used in manual calculations are the maximum LkR,kWk for all locations based on the most restrictive age group.
SO123-ODCM Revision 15 08/2020 2-22
Enclosure 5 Offstte Dose Calculation Manual San Onofre Nuclear Generating Station (SONGS)
Page 1-13* of SO123-ODCM Revision 14, February 2020 I
~~This page was revised in Rev 15 and the changes implemented in Rev 14 were overwritten. This was the only change in Rev 14.~~
1.0 LIQUID EFFLUENTS (Continued) 1.4.1.1 Radwaste Discharge Line Monitor (2{3RT-7813}
The value for Cm, the concentration limit at the detector, Is determined by using:
(RW 7813XF tti C~i)
(1-6)
(R{MP~eff J where:
RWn13= Radwaste Effluent discharge administrative value F = dilution water flow in volume per unit time
= 7,000 gpm per saltwaterrdRutlon pump....
- rhe value used In the detem,inatlon of F takes into account factors such as frictional losses, pump inefficiency, and tidal flow, and provid~ reasonable assurance that the radioactive release concentration is not underestimated. For radwaste discharges, the dllution water flow of 14,000 gpm shall be used and allgned to the same outfaH.
C = total concentratlo~ In each batch samp~
LtC'vt = total gamma Isotopic concentration, excluding Xe-133, µCl/ml R = typical effluent release rate Values of R for each tank are as foBows:
Primary Plant Makeup Tank= 160 gpm (per pump)
Condensate Monitor Tank= 120 gpm (per pump)
The maximum llqukf radwaste release discharge flow rate wlD be administratively nmited to less than 110 gpm MPCerr = from equation (1-4)
NOTE: If Cm ~ I.iC'vi, then no release is possible. To lnaem;e Cm, increase the administrative value RW1a1:s, and/or inaease dilution flow F (by running more dDution pumps In the appncable discharge structure), and/or decrease the effluent flow rate Rand recalculate Cm using the new R\Nn13, F, R as applicable and equation (1-6).
1.4.1.2 Slowdown Processing System NeutraDzation Sump/Fun Flow Condensate Paisher Perniaeranzer CFfCPQ) SUTip Discharge Une Monitor (Batch) (2RT-7817, 3RT-7817) - DELETED SO-123-0DCM Revision 14 02/2020
Enclosure 6 Offsite Dose Calculation Manual San Onofre Nuclear Generating Station (SONGS)
SO123-ODCM Appendix A Revision 15, November 2020
OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION APPENDIX A R, TABLES SO123-ODCM-A Revision 15 11/2020
ODCM APPENDIX A TABLE OF CONTENTS Section Title 1.0 UNITS 2 AND 3 Ri TABLES*..... . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1 thru A-33
~~R1 Tables based on Parts Code results for 2019 Land Use Census (Recorded as: SDS-CH2-REC-0006).~~
Ai SO123-ODCM-A Revision 15 11/2020
TABLE 1-1 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: SURF BEACH/LIFE GUARD DISTANCE: .5 MILES X/Q 9.2E-06 SEC/(M**3) D/Q 2.lE-08 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) 'PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 3E+03 4.2E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+05 1. 3E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+03 3.1E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.5E+04 3.5E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.4E+05 2.0E+09 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.6E+04 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+05 2.0E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.8E+05 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.6E+05 2.3E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.6E+04 1.2E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.6E+04 9.9E+06 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.1E+05 1.8E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.9E+03 6.2E+08 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.1E+03 1.4E+07 cs 137 0.0E+00 0. 0E+o0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.9E+03 9.4E+08 BA 140 0.0E+00 0.0E+o0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 1.9E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+04 l.2E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.lE+0S 6.4E+06 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.1E+06 1.6E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.0E+04 1.1E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+0S 2.2E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+03 4.1E+04 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.1E+04 2.3E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.9E+04 6.8E+07 PAGEA-1 SO123-ODCM-A Revision 15 11/2020
TABLE 1-1 UNITS 2&3 PATHWAY: SORB CAMPGROUND DISTANCE: 1.0 MILES X/Q 2.2E-06 SEC/(M**3) D/Q 5.0E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 1.1E+03 0.0E+00 1.3E+03 0.0E+00 1. 3E+03 0.0E+00 CR 51 1. 3E+04 4.7E+06 1.7E+04 4.7E+06 2.1E+04 4.7E+06 1.4E+04 4.7E+06 MN 54 l.0E+06 l.4E+09 l.6E+06 1.4E+09 2.0E+06 1. 4E+09 1.4E+06 l.4E+09 co 57 4.9E+03 3.4E+08 l.3E+04 3.4E+08 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 1.1E+06 3.8E+08 l.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.2E+10 8.7E+06 2.2E+10 6.0E+06 2. 2E+10 NI 63 2.1E+05 0.0E+00 2.7E+05 0.0E+00 3.1E+05 0.0E+00 1.8E+05 0.0E+00 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 1.4E+06 2.2E+04 SR 90 1.1E+07 0.0E+00 1.5E+07 0.0E+00 1.6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 1.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 1.8E+06 2.5E+08 NB 95 4.8E+05 1.4E+08 6.1E+05 1.4E+08 7.5E+05 1.4E+08 5.0E+05 1.4E+08 RU 103 5.5E+05 1.1E+08 6.6E+05 1. 1E+08 7.8E+05 1.1E+08 5.0E+05 1.1E+08 TE 129M 1.7E+06 2.0E+07 1.8E+06 2.0E+07 2.0E+06 2.0E+07 l.2E+06 2.0E+07 cs 134 8.0E+04 6.8E+09 1. 2E+05 6.8E+09 1.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 1. 2E+04 1.5E+08 1.5E+04 1.5E+08 1.8E+04 1.5E+08 1.2E+04 l.5E+08 cs 137 7.1E+04 1.0E+l0 1. 0E+05 1.0E+l0 1.2E+05 l.0E+l0 7.5E+04 l.0E+l0 BA 140 1.6E+06 2.1E+07 l.7E+06 2.1E+07 2.0E+06 2.1E+07 1.3E+06 2.1E+07 CE 141 5.2E+05 1.4E+07 5.4E+05 1. 4E+07 6.lE+0S 1. 4E+07 3.6E+05 1. 4E+07 CE 144 9.8E+06 7.0E+07 1.2E+07 7.0E+07 1.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 1.5E+07 1.7E+07 l.6E+07 1.7E+07 1.5E+07 1.7E+07 1.2E+07 1.7E+07 I 132 1.7E+05 l.2E+06 1.9E+05 1. 2E+06 1.5E+05 1.2E+06 1.1E+05 1.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 1. 0E+06 7.5E+08 1.2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEA-2 SO123-ODCM-A Revision 15 11/2020
TABLE 1-1 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: SAN MATEO POINT HOUS DISTANCE: 2.7 MILES X/Q 2.3E-07 SEC/(M**3) D/Q 4.4E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 1.1E+03 0.0E+00 l.3E+03 0.0E+00 1. 3E+03 0.0E+00 CR 51 l.3E+04 4.7E+06 l.7E+04 4.7E+06 2.1E+04 4.7E+06 1.4E+04 4.7E+06 MN 54 1.0E+06 l.4E+09 1.6E+06 1. 4E+09 2.0E+06 l.4E+09 1. 4E+06 l.4E+09 co 57 4.9E+03 3.4E+08 1.3E+04 3.4E+08 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 1.1E+06 3.8E+08 l.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.2E+10 8.7E+06 2.2E+l0 6.0E+06 2.2E+10 NI 63 2.1E+05 0.0E+00 2.7E+05 0.0E+00 3.1E+05 0.0E+00 1.8E+05 0.0E+00 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 1. 4E+06 2.2E+04 SR 90 l.1E+07 0.0E+00 l.5E+07 0.0E+00 1. 6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 l.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 1.8E+06 2.5E+08 NB 95 4.8E+05 1.4E+08 6.1E+05 l.4E+08 7.5E+05 l.4E+08 5.0E+05 1.4E+08 RU 103 5.5E+05 1.1E+08 6.6E+05 l.1E+08 7.8E+05 1.1E+08 5.0E+05 l.1E+08 TE 129M l.7E+06 2.0E+07 1.8E+06 2.0E+07 2.0E+06 2.0E+07 1.2E+06 2.0E+07 cs 134 8.0E+04 6.8E+09 1.2E+05 6.8E+09 l.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 1. 2E+04 1.5E+08 1.5E+04 l.5E+08 1.8E+04 1.5E+08 1.2E+04 1.5E+08 cs 137 7.1E+04 1.0E+l0 1.0E+05 1.0E+l0 1.2E+05 1.0E+l0 7.5E+04 1.0E+l0 BA 140 1.6E+06 2.1E+07 1.7E+06 2 .1E+07 2.0E+06 2.1E+07 1.3E+06 2.1E+07 CE 141 5.2E+05 1.4E+07 5.4E+05 1.4E+07 6.1E+05 1.4E+07 3.6E+05 l.4E+07 CE 144 9.8E+06 7.0E+07 1.2E+07 7.0E+07 l.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 l.5E+07 1.7E+07 1.6E+07 1.7E+07 1.5E+07 1.7E+07 1. 2E+07 l.7E+07 I 132 1.7E+05 1. 2E+06 1.9E+05 1.2E+06 1.5E+05 1. 2E+06 l.1E+05 1. 2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 1.0E+06 7.5E+08 1. 2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEA-3 SO 123-ODCM-A Revision 15 11/2020
TABLE 1-1 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: COTTON POINT GARDENS DISTANCE: 2.8 MILES X/Q 2.lE-07 SEC/(M**3) D/Q 4.lE-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 O.OE+OO 1.1E+03 3.0E+03 1. 3E+03 2.0E+03 1.3E+03 1.7E+03 CR 51 l.3E+04 4.7E+06 l.7E+04 1.1E+07 2.1E+04 1.5E+07 1.4E+04 1.6E+07 MN 54 l.OE+06 1.4E+09 l.6E+06 2.0E+09 2.0E+06 2.3E+09 1.4E+06 2.3E+09 co 57 4.9E+03 3.4E+08 1.3E+04 5.8E+08 3.1E+04 6.6E+08 3.1E+04 6.3E+08 co 58 7.8E+05 3.8E+08 1.1E+06 7.5E+08 l.3E+06 9.7E+08 9.3E+05 9.9E+08 co 60 4.5E+06 2.2E+10 7.1E+06 2.4E+l0 8.7E+06 2.5E+10 6.0E+06 2.5E+l0 NI 63 2.lE+OS O.OE+OO 2.7E+05 4.6E+10 3.1E+05 l.9E+10 1. BE+05 1.2E+10 SR 89 2.0E+06 2.2E+04 2.2E+06 3.5E+10 2.4E+06 1.5E+10 1.4E+06 9.8E+09 SR 90 1.1E+07 O.OE+OO 1.5E+07 l.4E+12 1.6E+07 8. 3E+ll 9.6E+06 6. 7E+ll ZR 95 1.8E+06 2.5E+08 2.2E+06 l.1E+09 2.7E+06 1.5E+09 l.8E+06 1. 4E+09 NB 95 4.8E+05 1.4E+08 6.1E+05 4.3E+08 7.5E+05 5.9E+08 5.0E+05 6.1E+08 RU 103 5.5E+05 l.lE+OB 6.6E+05 5.0E+OB 7.8E+05 6.BE+08 5.0E+05 6.6E+08 TE 129M 1.7E+06 2.0E+07 1.8E+06 2.9E+09 2.0E+06 1.8E+09 1.2E+06 1. 2E+09 cs 134 8.0E+04 6.8E+09 1.2E+05 3.2E+10 1.5E+05 2.3E+10 9.8E+04 1. 8E+10 cs 136 l.2E+04 1. 5E+08 1.5E+04 3.7E+OB 1.8E+04 3.2E+08 l.2E+04 3.2E+08 cs 137 7.1E+04 1. OE+lO 1.0E+05 3.4E+10 1.2E+05 2.4E+10 7.5E+04 1.9E+10 BA 140 1.6E+06 2.1E+07 1.7E+06 3.0E+OB 2.0E+06 2.3E+08 1.3E+06 2.8E+08 CE 141 5.2E+05 1.4E+07 5.4E+05 4.2E+08 6.1E+05 5.5E+08 3.6E+05 5.2E+08 CE 144 9.8E+06 7.0E+07 1.2E+07 1.0E+lO l.3E+07 1. 3E+10 7.8E+06 1. lE+lO I 131 1.5E+07 1.7E+07 l.6E+07 4.8E+10 1.5E+07 3.lE+lO 1.2E+07 3.8E+10 I 132 l.7E+05 1.2E+06 1.9E+05 1.2E+06 1.5E+05 1.2E+06 l.1E+05 1.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 8.1E+08 2.9E+06 4.6E+08 2.2E+06 5.3E+08 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 1.2E+07 6.2E+05 8.2E+06 4.5E+05 9.1E+06 UN-ID* 6.5E+05 7.5E+08 1. OE+06 3.5E+09 1. 2E+06 2.6E+09 8.6E+05 2.0E+09 PAGEA-4 SO123-ODCM-A Revision 15 11/2020
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: ST PARK OFFICE TRLR DISTANCE: . 6 MILES X/Q 7.4E-06 SEC/(M**3) D/Q 3.0E-08 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2;MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+03 l.1E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 3.2E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.2E+03 7.8E+07 co 58 0. 0E+o0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 8.7E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 4.9E+09 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.1E+04 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 4.9E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+05 5.7E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 3.1E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 2.5E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+05 4.5E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+04 l.6E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+03 3.4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.7E+04 2.3E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+05 4.7E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.3E+04 3.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+06 l.6E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 3.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+04 2.8E+05 I 133 0.0E+o0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.9E+05 5.6E+05 I 134 0.0E+00 0.0E;+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.8E+03 l.0E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.0E+05 5.8E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 l.7E+08 PAGEA-5 SO123-ODCM-A Revision 15 11/2020
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SURF BEACH/GUARD SHACK DISTANCE: . 7 MILES X/Q 5.7E-06 SEC/(M**3) D/Q 2.4E-08 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 7.BE+00 0.0E+00 4.2E+0l 0.0E+00 2.2E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 1.2E+02 3.2E+04 6.9E+02 1.5E+05 2.5E+03 8.0E+05 MN 54 0.0E+00 0.0E+00 1.1E+04 9.5E+06 6.5E+04 4.5E+07 2.4E+05 2.4E+08 co 57 0.0E+00 0.0E+00 9.lE+0l 2.4E+06 1.0E+03 l.1E+07 5.4E+03 5.9E+07 co 58 0.0E+00 0.0E+00 7.6E+03 2.6E+06 4.4E+04 1.2E+07 l.6E+05 6.5E+07 co 60 0.0E+00 0.0E+00 4.9E+04 1.5E+08 2.9E+05 7.0E+0B 1.0E+06 3.7E+09 NI 63 0.0E+00 0.0E+00 l.9E+03 0.0E+00 1.0E+04 0.0E+00 3.1E+04 0.0E+00 SR 89 0.0E+00 0.0E+00 1.5E+04 1.5E+02 7.9E+04 7.1E+02 2.4E+05 3.7E+03 SR 90 0.QE+00 0.0E+00 1.0E+05 0.0E+00 5.4E+05 0.0E+00 1.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 1. 5E+04 1.7E+06 8.8E+04 8.2E+06 3.0E+05 4.3E+07 NB 95 0.0E+00 0.0E+00 4.2E+03 9.4E+05 2.5E+04 4.5E+06 8.6E+04 2.3E+07 RU 103 0.0E+00 0.0E+00 4.6E+03 7.5E+05 2.6E+04 3.6E+06 8.6E+04 1.9E+07 TE 129M 0.0E+00 0.0E+00 1.2E+04 1.4E+05 6.5E+04 6.4E+05 2.1E+05 3.4E+06 cs 134 0.0E+00 0.0E+00 8.3E+02 4.7E+07 4.8E+03 2.2E+08 1.7E+04 1.2E+09 cs 136 0.0E+00 0.0E+00 1.0E+02 1.0E+06 5.8E+02 4.9E+06 2.1E+03 2.6E+07 cs 137 0.0E+00 0.0E+00 7.2E+02 7.1E+07 4.0E+03 3.4E+08 1.3E+04 1.8E+09 BA 140 0.0E+00 0.0E+00 1.2E+04 1.4E+05 6.6E+04 6.7E+05 2.2E+05 3.5E+06 CE 141 0.0E+00 0.0E+00 3.8E+03 9.4E+04 2.0E+04 4.5E+05 6.2E+04 2.3E+06 CE 144 0.0E+00 0.0E+00 8.2E+04 4.8E+05 4.4E+05 2.3E+06 1.3E+06 1.2E+07 I 131 0.0E+00 0.0E+00 l.1E+05 1.2E+05 4.8E+05 5.6E+05 2.0E+06 2.9E+06 I 132 0.0E+00 0.0E+00 1.3E+03 8.5E+03 4.9E+03 4.1E+04 2.0E+04 2.1E+05 I 133 0.0E+00 0.0E+00 2.7E+04 l.7E+04 9.5E+04 8.0E+04 3.7E+05 4.2E+05 I 134 0.0E+00 0.0E+00 3.5E+02 3.1E+03 1.3E+03 1.5E+04 5.1E+03 7.7E+04 I 135 0.0E+00 0.0E+00 5.5E+03 1.7E+04 2.0E+04 8.2E+04 7.7E+04 4.3E+05 UN-ID* 0.0E+00 0.0E+00 6.9E+03 5.1E+06 4.1E+04 2.4E+07 1.5E+05 l.3E+08
,)
PAGEA-6 SO123-ODCM-A Revision 15 11/2020
TABLE 1-2 UNITS 2&3 PATHWAY: SORB REC BEACH DISTANCE: 1.1 MILES X/Q l.9E-06 SEC/(M**3) D/Q 7.8E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 l.1E+03 0.0E+00 l.3E+03 0.0E+00 l.3E+03 0.0E+00 CR 51 1. 3E+04 4.7E+06 l.7E+04 4.7E+06 2.1E+04 4.7E+06 l.4E+04 4.7E+06 MN 54 l.0E+06 l.4E+09 l.6E+06 1. 4E+09 2.0E+06 l.4E+09 l.4E+06 1. 4E+09 co 57 4.9E+03 3.4E+08 l.3E+04 3.4E+08 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 l.1E+06 3.8E+08 l.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.2E+l0 8.7E+06 2.2E+l0 6.0E+06 2.2E+l0 NI 63 2.1E+05 0.0E+00 2.7E+05 0.0E+00 3.1E+05 0.0E+00 l.8E+05 0.0E+00 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 l.4E+06 2.2E+04 SR 90 l.1E+07 0.0E+00 l.5E+07 0.0E+00 l.6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 l.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 l.8E+06 2.5E+08 NB 95 4.8E+05 l.4E+08 6.1E+05 1. 4E+08 7.5E+05 l.4E+08 5.0E+05 1. 4E+08 RU 103 5.5E+05 l.1E+08 6.6E+05 l.1E+08 7.8E+05 l.1E+08 5.0E+05 l.1E+08 TE 129M l.7E+06 2.0E+07 l.8E+06 2.0E+07 2.0E+06 2.0E+07 1.2E+06 2.0E+07 cs 134 8.0E+04 6.8E+09 l.2E+05 6.8E+09 l.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 l.2E+04 l.5E+08 l.5E+04 l.5E+08 l.8E+04 l.5E+08 1. 2E+04 l.5E+08 cs 137 7.1E+04 l.0E+l0 l.0E+05 l.0E+l0 l.2E+05 l.0E+l0 7.5E+04 l.0E+l0 BA 140 l.6E+06 2.1E+07 l.7E+06 2.1E+07 2.0E+06 2.1E+07 l.3E+06 2.1E+07 CE 141 5.2E+05 l.4E+07 5.4E+05 l.4E+07 6.1E+05 l.4E+07 3.6E+05 l.4E+07 CE 144 9.8E+06 7.0E+07 l.2E+07 7.0E+07 l.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 l.5E+07 1. 7E+07 l.6E+07 l.7E+07 l.5E+07 l.7E+07 l.2E+07 l.7E+07 I 132 l.7E+05 1. 2E+06 l.9E+05 1. 2E+06 l.5E+05 1. 2E+06 l.1E+05 1.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 l.0E+06 7.5E+08 1. 2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEA-7 SO123-ODCM-A Revision 15 11/2020
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SORB CAMPGROUND CK IN DISTANCE: 1.3 MILES X/Q 1.3E-06 SEC/(M**3) D/Q 5.lE-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+03 1.1E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 3.2E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.2E+03 7.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 8.7E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 4.9E+09 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.1E+04 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 4.9E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+05 5.7E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+05 3.1E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+05 2.5E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+05 4.5E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+04 1.6E+09 cs 136 0.0E+00 0.0E+o0 0.0E+o0 0.0E+00 0.0E+00 0.0E+00 2.7E+03 3.4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.7E+04 2.3E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+05 4.7E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.3E+04 3.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+06 l.6E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 3.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+04 2.8E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.9E+05 5.6E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.8E+03 1.0E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0. 0E+o0 1. 0E+05 5.8E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 1.7E+08 PAGEA-8 SO123-ODCM-A Revision 15 11/2020
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SAN ONOFRE III HOUSING DISTANCE: 1.4 MILES X/Q 9.5E-07 SEC/(M**3) D/Q 2.lE-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 1.1E+03 0.0E+00 1. 3E+03 0.0E+00 1. 3E+03 0.0E+00 CR 51 1.3E+04 4.7E+06 l.7E+04 4.7E+06 2.1E+04 4.7E+06 1. 4E+04 4.7E+06 MN 54 l.0E+06 1.4E+09 1.6E+06 l.4E+09 2.0E+06 1.4E+09 1.4E+06 1.4E+09 co 57 4.9E+03 3.4E+08 1.3E+04 3.4E+08 3.1E+04 3.4E+08 3. 1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 1.1E+06 3.8E+08 1.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+10 7.1E+06 2.2E+10 8.7E+06 2.2E+10 6.0E+06 2.2E+l0 NI 63 2.1E+05 0.0E+00 2.7E+05 0.0E+00 3.1E+05 0.0E+00 1.8E+05 0.0E+00 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 1. 4E+06 2.2E+04 SR 90 l.1E+07 0.0E+00 l.5E+07 0.0E+00 1.6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 1.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 1.8E+06 2.5E+08 NB 95 4.8E+05 l.4E+0B 6.1E+05 1. 4E+0B 7.5E+05 l.4E+0B 5.0E+05 1.4E+0B RU 103 5.5E+05 1.lE+0B 6.6E+05 l.1E+08 7.BE+05 1.lE+0B 5.0E+05 1.lE+0B TE 129M 1. 7E+06 2.0E+07 1.BE+06 2.0E+07 2.0E+06 2.0E+07 l.2E+06 2.0E+07 cs 134 B.0E+04 6.BE+09 1.2E+05 6.8E+09 1.5E+05 6.BE+09 9.8E+04 6.BE+09 cs 136 1.2E+04 1.5E+0B 1. 5E+04 1.5E+0B 1.BE+04 1.5E+0B 1.2E+04 1.5E+0B cs 137 7.1E+04 1.0E+l0 1.0E+05 1. 0E+l0 1.2E+05 1.0E+l0 7.5E+04 1.0E+l0 BA 140 1.6E+06 2.1E+07 1.7E+06 2.1E+07 2.0E+06 2.1E+07 1. 3E+06 2.1E+07 CE 141 5.2E+05 1.4E+07 5.4E+05 l.4E+07 6.1E+05 1.4E+07 3.6E+05 1.4E+07 CE 144 9.BE+06 7.0E+07 1.2E+07 7.0E+07 1.3E+07 7.0E+07 7.BE+06 7.0E+07 I 131 l.5E+07 l.7E+07 1.6E+07 1.7E+07 1.5E+07 l.7E+07 1.2E+07 1.7E+07 I 132 1.7E+05 1. 2E+06 1.9E+05 l.2E+06 1.5E+05 1. 2E+06 1. 1E+05 l.2E+06 I 133 3.6E+06 2.4E+06 3.BE+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+0B 1. 0E+06 7.5E+0B 1. 2E+06 7.5E+0B B.6E+05 7.5E+0B PAGEA-9 SO123-ODCM-A Revision 15 11/2020
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SC RES. WITH GARDEN DISTANCE: 4.0 MILES X/Q l.lE-07 SEC/(M**3) D/Q 3.6E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 1.1E+03 3.0E+03 1. 3E+03 2.0E+03 l.3E+03 l.7E+03 CR 51 l.3E+04 4.7E+06 l.7E+04 l.1E+07 2.1E+04 l.5E+07 1.4E+04 l.6E+07 MN 54 l.0E+06 1.4E+09 1.6E+06 2.0E+09 2.0E+06 2.3E+09 1. 4E+06 2.3E+09 co 57 4.9E+03 3.4E+08 1. 3E+04 5.8E+08 3.1E+04 6.6E+08 3.1E+04 6.3E+08 co 58 7.8E+05 3.8E+08 l.1E+06 7.5E+08 1.3E+06 9.7E+08 9.3E+05 9.9E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.4E+10 8.7E+06 2.5E+l0 6.0E+06 2.5E+l0 NI 63 2.1E+05 0.0E+00 2.7E+05 4.6E+l0 3.1E+05 l.9E+l0 l.8E+05 1. 2E+l0 SR 89 2.0E+06 2.2E+04 2.2E+06 3.5E+l0 2.4E+06 1.5E+l0 1.4E+06 9.8E+09 SR 90 1.1E+07 0.0E+00 l.5E+07 l.4E+l2 l.6E+07 8. 3E+ll 9.6E+06 6. 7E+ll ZR 95 l.8E+06 2.5E+08 2.2E+06 l.1E+09 2.7E+06 1.5E+09 l.8E+06 l.4E+09 NB 95 4.8E+05 l.4E+08 6.1E+05 4.3E+08 7.5E+05 5.9E+08 5.0E+05 6.1E+08 RU 103 5.5E+05 1.1E+08 6.6E+05 5.0E+08 7.8E+05 6.8E+08 5.0E+05 6.6E+08 TE 129M 1.7E+06 2.0E+07 l.8E+06 2.9E+09 2.0E+06 1. 8E+09 1.2E+06 l.2E+09 cs 134 8.0E+04 6.8E+09 1. 2E+05 3.2E+10 l.5E+05 2.3E+l0 9.8E+04 l.8E+10 cs 136 1. 2E+04 l.5E+08 l.5E+04 3.7E+08 l.8E+04 3.2E+08 1. 2E+04 3.2E+08 cs 137 7.1E+04 1. 0E+l0 l.0E+05 3.4E+l0 1.2E+05 2.4E+10 7.5E+04 l.9E+l0 BA 140 l.6E+06 2.1E+07 l.7E+06 3.0E+08 2.0E+06 2.3E+08 l.3E+06 2.8E+08 CE 141 5.2E+05 l.4E+07 5.4E+05 4.2E+08 6.1E+05 5.5E+08 3.6E+05 5.2E+08 CE 144 9.8E+06 7.0E+07 l.2E+07 l.0E+l0 l.3E+07 l.3E+l0 7.8E+06 1.lE+l0 I 131 l.5E+07 l.7E+07 l.6E+07 4.8E+10 l.5E+07 3.lE+l0 1.2E+07 3.8E+l0 I 132 l.7E+05 l.2E+06 l.9E+05 1. 2E+06 1.5E+05 1.2E+06 l.1E+05 l.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 8.1E+08 2.9E+06 4.6E+08 2.2E+06 5.3E+08 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 1. 2E+07 6.2E+05 8.2E+06 4.5E+05 9.1E+06 UN-ID* 6.5E+05 7.5E+08 l.0E+06 3.5E+09 l.2E+06 2.6E+09 8.6E+05 2.0E+09 PAGE A-10 8O123-ODCM-A Revision 15 11/2020
TABLE 1-3 UNITS 2&3 DOSE PARAMETER R (I) FOR SECTOR 'R' PATHWAY: SAN ONOFRE III HOUSING DISTANCE: 1. 3 MILES X/Q 5.2E-07 SEC/(M**3) D/Q 3.0E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2 .MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 O.OE+OO 1. 1E+03 O.OE+OO l.3E+03 0.0E+OO l.3E+03 O.OE+OO CR 51 1.3E+04 4.7E+06 l.7E+04 4.7E+06 2.1E+04 4.7E+06 l.4E+04 4.7E+06 MN 54 l.OE+06 l.4E+09 l.6E+06 1. 4E+09 2.0E+06 l.4E+09 l.4E+06 l.4E+09 co 57 4.9E+03 3.4E+08 l.3E+04 3.4E+08 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 l.1E+06 3.8E+08 l.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.2E+l0 8.7E+06 2.2E+l0 6.0E+06 2.2E+l0 NI 63 2.1E+05 O.OE+OO 2.7E+05 O.OE+OO 3.1E+05 O.OE+OO l.8E+05 O.OE+OO SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 l.4E+06 2.2E+04 SR 90 l.1E+07 O.OE+OO l.5E+07 O.OE+OO l.6E+07 O.OE+OO 9.6E+06 O.OE+OO ZR 95 l.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 l.8E+06 2.5E+08 NB 95 4.8E+05 l.4E+08 6.1E+05 1. 4E+08 7.5E+05 l.4E+08 5.0E+05 l.4E+08 RU 103 5.5E+05 l.1E+08 6.6E+05 l.1E+08 7.8E+05 l.1E+08 5.0E+05 l.1E+08 TE 129M l.7E+06 2.0E+07 l.8E+06 2.0E+07 2.0E+06 2.0E+07 l.2E+06 2.0E+07 cs 134 8.0E+04 6.8E+09 l.2E+05 6.8E+09 l.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 1. 2E+04 l.5E+08 l.5E+04 l.5E+08 l.8E+04 l.5E+08 l.2E+04 l.5E+08 cs 137 7.1E+04 l.OE+lO l.OE+05 1. OE+lO 1. 2E+05 1. OE+lO 7.5E+04 1. OE+lO BA 140 1.6E+06 2.1E+07 l.7E+06 2.1E+07 2.0E+06 2.1E+07 l.3E+06 2.1E+07 CE 141 5.2E+05 l.4E+07 5.4E+05 1. 4E+07 6.1E+05 l.4E+07 3.6E+05 l.4E+07 CE 144 9.8E+06 7.0E+07 l.2E+07 7.0E+07 l.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 l.5E+07 l.7E+07 l.6E+07 l.7E+07 l.5E+07 l.7E+07 l.2E+07 l.7E+07 I 132 l.7E+05 1. 2E+06 l.9E+05 l.2E+06 l.5E+05 1. 2E+06 l.1E+05 l.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 l.OE+06 7.5E+08 l.2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEA-11 SO 123-ODCM-A Revision 15 11/2020
TABLE 1-3 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'R' PATHWAY: SC RES. WITH GARDEN DISTANCE: 4. 9 MILES X/Q 6.6E-08 SEC/(M**3) D/Q 2.5E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 O.OE+OO l.1E+03 3.0E+03 l.3E+03 2.0E+03 1. 3E+03 1. 7E+03 CR 51 l.3E+04 4.7E+06 1.7E+04 l.1E+07 2.1E+04 1.5E+07 1.4E+04 1. 6E+07 MN 54 1.0E+06 1.4E+09 1.6E+06 2.0E+09 2.0E+06 2.3E+09 l.4E+06 2.3E+09 co 57 4.9E+03 3.4E+08 1. 3E+04 5.8E+08 3.1E+04 6.6E+08 3.1E+04 6.3E+08 co 58 7.8E+05 3.8E+08 1.1E+06 7.5E+08 1.3E+06 9.7E+08 9.3E+05 9.9E+08
. co 60 4.5E+06 2.2E+10 7.1E+06 2. 4E+10 8.7E+06 2.5E+10 6.0E+06 2.5E+10 NI 63 2.1E+05 O.OE+OO 2.7E+05 4.6E+l0 3.1E+05 1.9E+10 1.8E+05 1. 2E+10 SR 89 2.0E+06 2,2E+04 2.2E+06 3.5E+10 2.4E+06 l.5E+l0 1.4E+06 9.8E+09 SR 90 1.1E+07 O.OE+OO 1.5E+07 1. 4E+12 l.6E+07 8. 3E+ll 9.6E+06 6. 7E+ll ZR 95 1.8E+06 2.5E+08 2.2E+06 1. 1E+09 2.7E+06 1.5E+09 1.8E+06 1.4E+09 NB 95 4.8E+05 1.4E+08 6.1E+05 4.3E+08 7.5E+05 5.9E+08 5.0E+05 6.1E+08 RU 103 5.5E+05 l.1E+08 6.6E+05 5.0E+08 7.8E+05 6.8E+08 5.0E+05 6.6E+08 TE 129M 1. 7E+06 2.0E+07 1.8E+06 2.9E+09 2.0E+06 1.8E+09 1. 2E+06 1.2E+09 cs 134 8.0E+04 6.8E+09 l.2E+05 3.2E+10 1.5E+05 2.3E+10 9.8E+04 1.8E+l0 cs 136 1. 2E+04 1.5E+08 1.5E+04 3.7E+08 1.8E+04 3.2E+08 1.2E+04 3.2E+08 cs 137 7.1E+04 1. OE+lO 1.0E+05 3.4E+10 1.2E+05 2. 4E+10 7.5E+04 1.9E+l0 BA 140 1.6E+06 2.1E+07 1.7E+06 3.0E+08 2.0E+06 2.3E+08 1.3E+06 2.8E+08 CE 141 5.2E+05 1.4E+07 5.4E+05 4.2E+08 6.1E+05 5.5E+08 3.6E+05 5.2E+08 CE 144 9.8E+06 7.0E+07 l.2E+07 l.OE+lO 1. 3E+07 l.3E+10 7.8E+06 1.lE+lO I 131 1.5E+07 1.7E+07 l.6E+07 4.8E+10 1.5E+07 3.lE+lO 1.2E+07 3.8E+10 I 132 1.7E+05 1.2E+06 l.9E+05 1.2E+06 1.5E+05 l.2E+06 1.1E+05 1.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 8.1E+08 2.9E+06 4.6E+08 2.2E+06 5.3E+08 I 134 4.5E+04 4.5E+05 5. 1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 1. 2E+07 6.2E+05 8.2E+06 4.5E+05 9.1E+06 UN-ID* 6.5E+05 7.5E+08 1. OE+06 3.5E+09 1. 2E+06 2.6E+09 8.6E+05 2.0E+09 PAGEA-12 SO123-ODCM-A Revision 15 11/2020
TABLE 1-3 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'R' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 1.8 MILES X/Q 5.2E-07 SEC/(M**3) D/Q 2.5E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2. MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO 2.lE+Ol O.OE+OO 1. 8E+Ol l.5E+Ol 2.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 l.7E+02 2.4E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 O.OE+OO 1.4E+06 l.6E+04 l.9E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 3.6E+02 l.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 l.1E+04 4.1E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 6.9E+04 3.8E+08 NI 63 O.OE+OO O.OE+OO O.OE+OO 3.0E+09 O.OE+OO 1. 5E+09 2.1E+03 l.9E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 l.6E+04 3.1E+07 SR 90 O.OE+OO O.OE+OO O.OE+OO 1.0E+09 O.OE+OO 8.0E+08 l.1E+05 l.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO 1.1E+08 2.1E+04 2.0E+08 NB 95 O.OE+OO 0.0E+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 5.9E+03 8.2E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 5.9E+03 l.3E+09 TE 129M O.OE+OO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 l.4E+04 5.3E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO l.4E+08 O.OE+OO 1. 2E+08 l.1E+03 2.3E+08 cs 136 O.OE+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 l.4E+02 7.2E+06 cs 137 O.OE+OO O.OE+OO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 8.7E+02 2.3E+08 BA 140 O.OE+oO O.OE+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 l.5E+04 7.0E+06 CE 141 O.OE+oO 0.0E+OO O.OE+OO l.5E+06 O.OE+OO 2.4E+06 4.2E+03 4.0E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO l.8E+07 O.OE+OO 2.9E+07 9.0E+04 4.8E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 l.4E+05 5.9E+08 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.3E+03 1.4E+04 I 133 0.0E+OO O.OE+OO O.OE+OO 1.6E+Ol O.OE+OO 8.6E+OO 2.5E+04 2.8E+04 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.5E+02 5.2E+03 I 135 O.OE+OO O.OE+OO O.OE+OO l.lE-15 O.OE+OO 6.3E-16 5.2E+03 2.9E+04 UN-ID* O.OE+OO O.OE+OO O.OE+OO l.1E+08 O.OE+OO 9.4E+07 l.OE+04 l.3E+08 PAGEA-13 SO 123-ODCM-A Revision 15 11/2020
TABLE 1-4 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'A' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 1. 8 MILES X/Q 4.8E-07 SEC/(M**3) D/Q 2.7E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 2.lE+0l 0.0E+00 l.8E+0l 1.5E+0l 2.9E+0l CR 51 0.0E+00 0.0E+00 0.0E+00 5.0E+04 0.0E+00 l.0E+05 1.7E+02 2.4E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 7.7E+05 0.0E+00 1.4E+06 l.6E+04 1.9E+07 co 57 0.0E+00 0.0E+00 0.0E+00 4.6E+06 0.0E+00 8.0E+06 3.6E+02 1.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 l.9E+07 1.1E+04 4.1E+07 co 60 0.0E+00 0.0E+00 0.0E+00 3.6E+07 0.0E+00 7.2E+07 6.9E+04 3.8E+08 NI 63 0.0E+00 0.0E+00 0.0E+00 3.0E+09 0.0E+00 1. 5E+09 2.1E+03 1.9E+09 SR 89 0.0E+00 0.0E+00 0.0E+00 4.9E+07 0.0E+00 2.6E+07 l.6E+04 3.1E+07 SR 90 0.0E+00 0.0E+00 0.0E+00 1.0E+09 0.0E+00 8.0E+08 1.1E+05 1.2E+09 ZR 95 0.0E+00 0.0E+00 0.0E+00 6.2E+07 0.0E+00 1.1E+08 2.1E+04 2.0E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 2.3E+08 0.0E+00 4.5E+08 5.9E+03 8.2E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 4.2E+08 0.0E+00 7.5E+08 5.9E+03 1. 3E+09 TE 129M 0.0E+00 0.0E+00 0.0E+00 5.9E+08 0.0E+00 4.5E+08 1. 4E+04 5.3E+08 cs 134 0.0E+00 0.0E+00 0.0E+00 1.4E+08 0.0E+00 l.2E+08 1.1E+03 2.3E+08 cs 136 0.0E+00 0.0E+00 0.0E+00 5.1E+06 0.0E+00 4.2E+06 l.4E+02 7.2E+06 cs 137 0.0E+00 0.0E+00 0.0E+00 1. 2E+08 0.0E+00 9.3E+07 8.7E+02 2.3E+08 BA 140 0.0E+00 0.0E+00 0.0E+00 5.0E+06 0.0E+00 4.2E+06 1.5E+04 7.0E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 1.5E+06 0.0E+00 2.4E+06 4.2E+03 4.0E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 1.8E+07 0.0E+00 2.9E+07 9.0E+04 4.8E+07 I 131 0.0E+00 0.0E+00 0.0E+00 6.5E+08 0.0E+00 4.3E+08 l.4E+05 5.9E+08 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0,0E+00 1.3E+03 l.4E+04 I 133 0.0E+00 0.0E+00 0.0E+00 1.6E+0l 0.0E+00 8.6E+00 2.5E+04 2.8E+04 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.5E+02 5.2E+03 I 135 0.0E+00 0.0E+00 0.0E+00 1.lE-15 0.0E+00 6.3E-16 5.2E+03 2.9E+04 UN-ID* 0.0E+00 0.0E+00 0.0E+00 1.1E+08 0.0E+00 9.4E+07 1.0E+04 1. 3E+08 PAGEA-14 SO123-ODCM-A Revision 15 11/2020
TABLE 1-4 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'A' PATHWAY: CAMP SAN MATEO RES DISTANCE: 3.6 MILES X/Q l.lE-07 SEC/(M**3) D/Q 5.3E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+03 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+04 4.7E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 1. 4E+09 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 3.4E+08 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.3E+05 3.8E+08 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.0E+06 2.2E+l0 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+05 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 2.2E+04 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+06 2.5E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+0S l.4E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 l.1E+08 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+06 2.0E+07 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.8E+04 6.8E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+04 1. 5E+08 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.5E+04 1. 0E+l0 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+06 2.1E+07 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.6E+05 l.4E+07 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.8E+06 7.0E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+07 l.7E+07 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.lE+0S l.2E+06 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 2.4E+06 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.0E+04 4.5E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.5E+05 2.5E+06 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+05 7.5E+08 PAGEA-15 SO123-ODCM-A Revision 15 11/2020
TABLE 1-4 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'A' PATHWAY: CAMP SAN MATEO MP DISTANCE: 3.6 MILES X/Q l.lE-07 SEC/(M**3) D/Q 5.3E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+03 l.1E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 3.2E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.2E+03 7.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 8.7E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 4.9E+09 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.1E+04 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 4.9E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00- 2.2E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+05 5.7E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 3.1E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 2.5E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+05 4.5E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+04 l.6E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+03 3. 4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.7E+04 2.3E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+05 4.7E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.3E+04 3.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+06 l.6E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 3.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+04 2.8E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.9E+05 5.6E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.8E+03 l.0E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.0E+05 5.8E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 l.7E+08 PAGEA-16 SO 123-ODCM-A Revision 15 11/2020
TABLE 1-5 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'B' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 1.6 MILES X/Q 8.lE-07 SEC/(M**3) D/Q 3.4E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO 2.lE+Ol O.OE+OO l.BE+Ol l.5E+Ol 2.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO l.OE+05 l.7E+02 2.4E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 O.OE+OO l.4E+06 l.6E+04 l.9E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 3.6E+02 l.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 l.1E+04 4.1E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 6.9E+04 3.8E+08 NI 63 O.OE+OO O.OE+OO O.OE+OO 3.0E+09 O.OE+OO l.5E+09 2.1E+03 l.9E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 l.6E+04 3.1E+07 SR 90 O.OE+OO O.OE+OO O.OE+OO l.OE+09 O.OE+OO 8.0E+OB l.1E+05 1. 2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO l.lE+OB 2.1E+04 2.0E+OB NB 95 O.OE+OO O.OE+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 5.9E+03 8.2E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 5.9E+03 1. 3E+09 TE 129M O.OE+OO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 l.4E+04 5.3E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO l.4E+08 O.OE+OO l.2E+08 l.1E+03 2.3E+08 cs 136 0.0E+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 1. 4E+02 7.2E+06 cs 137 O.OE+OO O.OE+OO 0.0E+OO l.2E+08 O.OE+OO 9.3E+07 8.7E+02 2.3E+08 BA 140 O.OE+OO O.OE+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 l.5E+04 7.0E+06 CE 141 0.0E+OO O.OE+OO O.OE+OO l.5E+06 O.OE+OO 2.4E+06 4.2E+03 4.0E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO l.8E+07 0.0E+OO 2.9E+07 9.0E+04 4.8E+07 I 131 O.OE+OO 0.0E+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 1. 4E+05 5.9E+08 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+03 l.4E+04 I 133 O.OE+OO O.OE+OO O.OE+OO l.6E+Ol O.OE+OO 8.6E+OO 2.5E+04 2.8E+04 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.5E+02 5.2E+03 I 135 O.OE+OO O.OE+OO O.OE+OO l.lE-15 O.OE+OO 6.3E-16 5.2E+03 2.9E+04 UN-ID* O.OE+OO O.OE+OO O.OE+OO l.1E+08 O.OE+OO 9.4E+07 l.OE+04 l.3E+08 PAGEA-17 SO123-ODCM-A Revision 15 11/2020
TABLE 1-5 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'B' PATHWAY: SANITARY LANDFILL DISTANCE: 2.1 MILES X/Q 4.4E-07 SEC/(M**3) D/Q l.8E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2 .MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+03 4.3E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+05 l.3E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+03 3.2E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+04 3.5E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.6E+05 2.0E+09 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.7E+04 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+05 2.0E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.9E+05 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.6E+05 2.3E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.7E+04 l.3E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.7E+04 l.0E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.1E+05 l.8E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.1E+03 6.4E+08 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.1E+03 1. 4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.0E+03 9.6E+08 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 l.9E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.4E+04 l.3E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.2E+05 6.5E+06 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.1E+06 l.6E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.1E+04 l.2E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 2.3E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+03 4.2E+04 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.2E+04 2.3E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 O.0E+00 8.1E+04 6.9E+07 PAGEA-18 SO123-ODCM-A Revision 15 11/2020
TABLE 1-6 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: SEWAGE TREAT.FACILITY DISTANCE: 2.2 MILES X/Q 2.7E-07 SEC/(M**3) D/Q l.8E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+02 0.0E+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.3E+03 l.1E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 3.2E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 7.2E+03 7.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.1E+05 8.7E+07 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+06 4.9E+09 NI 63 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.1E+04 O.OE+OO SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 4.9E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 0.0E+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 5.7E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 1. 2E+05 3.1E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.2E+05 2.5E+07 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.8E+05 4.5E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.2E+04 l.6E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.7E+03 3.4E+07 cs 137 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.7E+04 2.3E+09 BA 140 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.9E+05 4.7E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.3E+04 3.1E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.8E+06 l.6E+07 I 131 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.7E+06 3.9E+06 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.6E+04 2.8E+05 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.9E+05 5.6E+05 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+OO 6.8E+03 l.OE+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO l.OE+05 5.8E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.0E+05 l.7E+08 PAGEA-19 SO123-ODCM-A Revision 15 11/2020
TABLE 1-6 UNITS2&3 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: CAMP SAN ONOFRE FR.STN DISTANCE: 2.4 MILES X/Q 2.2E-07 SEC/(M**3) D/Q 1.4E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+03 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+04 4.7E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+06 1. 4E+09 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.1E+04 3.4E+08 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.3E+05 3.8E+08 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.0E+06 2.2E+10 NI 63 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.8E+05 O.OE+OO SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.4E+06 2.2E+04 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.8E+06 2.5E+08 NB 95 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.0E+05 1. 4E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.0E+05 l.1E+08 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.2E+06 2.0E+07 cs 134 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 9.8E+04 6. 8E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 1.2E+04 1. 5E+08 cs 137 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.5E+04 1. OE+lO BA 140 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 0.0E+OO 1.3E+06 2.1E+07 CE 141 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 3.6E+05 1. 4E+07 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 7.8E+06 7.0E+07 I 131 O.OE+OO O.OE+OO 0.0E+OO O.OE+oO O.OE+OO O.OE+OO 1.2E+07 1.7E+07 I 132 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.1E+05 l.2E+06 I 133 O.OE+OO O.OE+OO O.OE+OO 0 ._QE+oO O.OE+OO O.OE+OO 2.2E+06 2.4E+06 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.0E+04 4.5E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.5E+05 2.5E+06 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.6E+05 7.5E+08 PAGEA-20 SO123-ODCM-A Revision 15 11/2020
TABLE 1-6 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: CAMP SAN ONOFRE barr DISTANCE: 2.6 MILES X/Q 1.9E-07~SEC/(M**3) D/Q 1.2E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+03 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+04 4.7E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+06 1. 4E+09 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 3.4E+08 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.3E+05 3.8E+08 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.0E+06 2.2E+10
NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+05 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+06 2.2E+04 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+06 2.5E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 1.4E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 1.1E+08 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+06 2.0E+07 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.8E+04 6.8E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+04 1.5E+08 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.5E+04 1.0E+l0 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+06 2.1E+07 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.6E+05 l.4E+07 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.8E+06 7.0E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+07 l.7E,1--07 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.1E+05 1.2E+06 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 2.4E+06 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.0E+04 4.5E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.5E+05 2.5E+06 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+05 7.5E+08 PAGE A-21 SO123-ODCM-A Revision 15 11/2020
TABLE 1-7 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 3.0 MILES X/Q l.4E-07 SEC/(M**3) D/Q 8.5E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2 .MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO 2.lE+Ol O.OE+OO l.8E+Ol 2.8E+Ol 2.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 0.0E+OO l.OE+05 3.2E+02 2.9E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 O.OE+OO l.4E+06 3.1E+04 3.4E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 7.0E+02 2.1E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 2.1E+04 4.5E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 1. 3E+05 6.2E+08 NI 63 O.OE+OO O.OE+OO O.OE+OO 3.0E+09 O.OE+OO l.5E+09 4.0E+03 l.9E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 3.1E+04 3.1E+07 SR 90 O.OE+OO O.OE+OO O.OE+OO l.OE+09 O.OE+OO 8.0E+08 2.2E+05 l.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO l .1E+08 4.0E+04 2.0E+08 NB 95 O.OE+OO 0.0E+OO O.OE+OO 2.3E+08 0.0E+OO 4.5E+08 l.1E+04 8.2E+08 RU 103 O.OE+OO O.OE+OO 0.0E+OO 4.2E+08 O.OE+OO 7.5E+08 l.1E+04 l.3E+09 TE 129M O.OE+OO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 2.8E+04 5.3E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO 1. 4E+08 O.OE+OO l.2E+08 2.2E+03 3.0E+08 cs 136 O.OE+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 2.7E+02 8.8E+06 cs 137 O.OE+OO O.OE+OO O.OE+OO 1. 2E+08 O.OE+OO 9.3E+07 l.7E+03 3.5E+08 BA 140 O.OE+OO O.OE+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 2.8E+04 7.2E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO l.5E+06 0.0E+OO 2.4E+06 8.1E+03 4.1E+06 CE 144 O.OE+OO O.OE+OO 0.0E+OO l.8E+07 O.OE+OO 2.9E+07 l.7E+05 4.8E+07 I 131 0.0E+OO O.OE+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 2.7E+05 5.9E+08 I 132 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.6E+03 2.8E+04 I 133 O.OE+OO O.OE+OO 0.0E+OO l.6E+Ol O.OE+OO 8.6E+OO 4.8E+04 5.5E+04 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.7E+02 l.OE+04 I 135 O.OE+OO O.OE+OO O.OE+OO l.lE-15 O.OE+OO 6.3E-16 l.OE+04 5.6E+04 UN-ID* O.OE+OO O.OE+OO O.OE+OO l.1E+08 O.OE+OO 9.4E+07 l.9E+04 1. 4E+08 PAGEA-22 SO123-ODCM-A Revision 15 11/2020
TABLE 1-7 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'D' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: . 8 MILES X/Q 1.2E-05 SEC/(M**3) D/Q 2.9E-08 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 2.lE+0l 0.0E+00 1.BE+0l 2.BE+0l 2.9E+0l CR 51 0.0E+00 0.0E+00 0.0E+00 5.0E+04 0.0E+00 1.0E+05 3.2E+02 2.9E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 7.7E+05 0.0E+00 1.4E+06 3.1E+04 3.4E+07 co 57 0.0E+00 0.0E+00 0.0E+00 4.6E+06 0.0E+00 8.0E+06 7.0E+02 2.1E+07 co 58 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 1.9E+07 2.1E+04 4.5E+07 co 60 0.0E+00 0.0E+00 0.0E+00 3.6E+07 0.0E+00 7.2E+07 1.3E+05 6.2E+08 NI 63 0.0E+00 0.0E+00 0.0E+00 3.0E+09 0.0E+00 1.5E+09 4.0E+03 1.9E+09 SR 89 0.0E+00 0.0E+00 0.0E+00 4.9E+07 0.0E+00 2.6E+07 3.1E+04 3.1E+07 SR 90 0.0E+00 0.0E+00 0.0E+00 1.0E+09 0.0E+00 8.0E+08 2.2E+05 1. 2E+09 ZR 95 0.0E+00 0.0E+00 0.0E+00 6.2E+07 0.0E+00 1. 1E+08 4.0E+04 2.0E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 2.3E+08 0.0E+00 4.5E+08 1.1E+04 8.2E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 4.2E+08 0.0E+00 7.5E+08 1.1E+04 l.3E+09 TE 129M 0.0E+00 0.0E+00 0.0E+00 5.9E+08 0.0E+00 4.5E+08 2.8E+04 5.3E+08 cs 134 0.0E+00 0.0E+00 0.0E+00 l.4E+08 0.0E+00 l.2E+08 2.2E+03 3.0E+0B cs 136 0.0E+00 0.0E+00 0.0E+00 5.1E+06 0.0E+00 4.2E+06 2 .. 7E+02 8.8E+06 cs 137 0.0E+00 0.0E+00 0.0E+00 1.2E+08 0.0E+00 9.3E+07 1.7E+03 3.5E+08 BA 140 0.0E+00 0.0E+00 0.0E+00 5.0E+06 0.0E+00 4.2E+06 2.8E+04 7.2E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 1.5E+06 0.0E+00 2.4E+06 8.1E+03 4.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 1.8E+07 0.0E+00 2.9E+07 1.7E+05 4.8E+07 I 131 0.0E+00 0.0E+00 0.0E+00 6.5E+08 0.0E+00 4.3E+08 2.7E+05 5.9E+08 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+o0 0.0E+00 0.0E+00 2.6E+03 2.8E+04 I 133 0.0E+00 0.0E+00 0.0E+00 l.6E+0l 0.0E+00 8.6E+00 4.8E+04 5.5E+04 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.7E+02 1.0E+04 I 135 0.0E+00 0.0E+00 0.0E+00 l.lE-15 0.0E+00 6.3E-16 1.0E+04 5.6E+04 UN-ID* 0.0E+00 0.0E+00 0.0E+00 1.lE+0B 0.0E+00 9.4E+07 l.9E+04 1. 4E+08 PAGEA-23 SO123-ODCM-A Revision 15 11/2020
TABLE 1-7 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'D' PATHWAY: CAMP SAN ONOFRE barr DISTANCE: 3.0 MILES X/Q 6.0E-07 SEC/(M**3) D/Q 1.lE-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MR.EM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 3E+03 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 4E+04 4.7E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+06 1.4E+09 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 3.4E+08 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.3E+05 3.BE+0B co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.0E+06 2.2E+10 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+05 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 2.2E+04 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+06 2.5E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 1. 4E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 1. lE+0B TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+06 2.0E+07 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.8E+04 6.8E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+04 1.5E+08 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.5E+04 1.0E+l0 BA 140 0.0E+00 0. 0E+o0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+06 2.1E+07 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.6E+05 1.4E+07 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.8E+06 7.0E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+07 1.7E+07 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.1E+05 1.2E+06 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 2.4E+06 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.0E+04 4.5E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.5E+05 2.5E+06 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+05 7.5E+08 PAGEA-24 SO123-ODCM-A Revision 15 11/2020
.}
TABLE 1-8 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: . 8 MILES X/Q 4.lE-06 SEC/(M**3) D/Q 3.8E-08 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 2.lE+0l 0.0E+00 l.8E+0l 2.8E+0l 2.9E+0l CR 51 0.0E+00 0.0E+00 0.0E+00 5.0E+04 0.0E+00 1. 0E+05 3.2E+02 2.9E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 7.7E+05 0.0E+00 l.4E+06 3.1E+04 3.4E+07 co 57 0.0E+00 0.0E+00 0.0E+00 4.6E+06 0.0E+00 8.0E+06 7.0E+02 2.1E+07 co 58 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 l.9E+07 2.1E+04 4.5E+07 co 60 0.0E+00 0.0E+00 0.0E+00 3.6E+07 0.0E+00 7.2E+07 1. 3E+05 6.2E+08 NI 63 0.0E+00 0.0E+00 0.0E+00 3.0E+09 0.0E+00 1.5E+09 4.0E+03 1.9E+09 SR 89 0.0E+00 0.0E+00 0.0E+00 4.9E+07 0.0E+00 2.6E+07 3.1E+04 3 .1E+07 SR 90 0.0E+00 0.0E+00 0.0E+00 l.0E+09 0.0E+00 8.0E+08 2.2E+05 1.2E+09 ZR 95 0.0E+00 0.0E+00 0.0E+00 6.2E+07 0.0E+00 1.1E+08 4.0E+04 2.0E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 2.3E+08 0.0E+00 4.5E+08 l.1E+04 8.2E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 4.2E+08 0.0E+00 7.5E+08 1.1E+04 1. 3E+09 TE 129M 0.0E+00 0.0E+00 0.0E+00 5.9E+08 0.0E+00 4.5E+08 2.8E+04 5.3E+08 cs 134 0.0E+00 0.0E+00 0.0E+00 1.4E+08 0.0E+00 1. 2E+08 2.2E+03 3.0E+08 cs 136 0.0E+00 0.0E+00 0.0E+00 5.1E+06 0.0E+00 4.2E+06 2.7E+02 8.8E+06 cs 137 0.0E+00 0.0E+00 0.0E+00 1. 2E+08 0.0E+00 9.3E+07 1.7E+03 3.5E+08 BA 140 0.0E+00 0.0E+00 0.OE+00 5.0E+06 0.0E+00 4.2E+06 2.8E+04 7.2E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 l.5E+06 0.0E+00 2.4E+06 8.1E+03 4.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 1.8E+07 0.0E+00 2.9E+07 l.7E+05 4.8E+07 I 131 0.0E+00 0.0E+00 0.0E+00 6.5E+08 0.0E+00 4.3E+08 2.7E+05 5.9E+08 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+03 2.8E+04 I 133 0.0E+00 0.0E+00 0.0E+00 1.6E+0l 0.0E+00 8.6E+00 4.8E+04 5.5E+04 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.7E+02 1.0E+04 I 135 0.0E+00 0.0E+00 0.0E+00 1.lE-15 0.0E+00 6.3E-16 1.0E+04 5.6E+04 UN-ID* 0.0E+00 0.0E+00 0.0E+00 1.1E+08 0.0E+00 9.4E+07 1.9E+04 1.4E+08 PAGEA-25 SO 123-ODCM-A Revision 15 11/2020
TABLE 1-8 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: CAMP HORNO MOTOR POOL DISTANCE: 4. 0 MILES X/Q l.lE-07 SEC/(M**3) D/Q 7.6E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.6E+02 O.OE+OO CR 51 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.1E+03 l.3E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 3.9E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.0E+03 9.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.6E+05 l.1E+08 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.7E+06 6.1E+09 NI 63 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.1E+04 O.OE+OO SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 6.2E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.7E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.0E+05 7.2E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+05 3.9E+07 RU 103 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+05 3.1E+07 TE 129M O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 3.5E+05 5.6E+06 cs 134 O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.8E+04 l.9E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.4E+03 4.3E+07 cs 137 0.0E+OO 0. OE+oO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.1E+04 2.9E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.6E+05 5.9E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.OE+05 3.9E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.2E+06 2.0E+07 I 131 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.4E+06 4.9E+06 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.3E+04 3.5E+05 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 6.1E+05 7.0E+05 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.5E+03 1. 3E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+05 7.2E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.5E+05 2.1E+08 PAGEA-26 SO123-ODCM-A Revision 15 11/2020
TABLE 1-8 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: CAMP HORNO DISTANCE: 4.1 MILES X/Q 1.lE-07 SEC/(M**3) D/Q 7.2E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2 .MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+03 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 1.4E+04 4.7E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.4E+06 1. 4E+09 co 57 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 3.1E+04 3.4E+08 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.3E+05 3.8E+08 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.0E+06 2.2E+10 NI 63 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.8E+05 O.OE+OO SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.4E+06 2.2E+04 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.8E+06 2.5E+08 NB 95 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.0E+05 1. 4E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.0E+05 l.1E+08 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 2E+06 2.0E+07 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.8E+04 6.8E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO l.2E+04 1.5E+08 cs 137 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.5E+04 1.0E+lO BA 140 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 1.3E+06 2.1E+07 CE 141 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 3.6E+05 l.4E+07 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.8E+06 7.0E+07 I 131 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.2E+07 1.7E+07 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+oO O.OE+OO O.OE+OO 1.1E+05 1. 2E+06 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 2.4E+06 I 134 O.OE+OO O.OE+OO 0. OE+00 1 O.OE+OO O.OE+OO O.OE+OO 3.0E+04 4.5E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.5E+05 2.5E+06 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.6E+05 7.5E+08 PAGEA-27 SO123-ODCM-A Revision 15 11/2020
TABLE 1-9 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: SO ST. PK./GUARD SHACK DISTANCE: . 8 MILES X/Q 5.3E-06 SEC/(M**3) D/Q 3.2E-08 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2. MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.5E+03 8.0E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.4E+05 2.4E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.4E+03 5.9E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.6E+05 6.5E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.0E+06 3.7E+09 NI 63 0.0E+00 0.0E+00 0.0_E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.4E+05 3.7E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.0E+05 4.3E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+04 2.3E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+04 1.9E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 3.4E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.7E+04 1. 2E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00. 2.1E+03 2.6E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+04 1.8E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+05 3.5E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.2E+04 2.3E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+06 1. 2E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 2.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+04 2.1E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.7E+05 4.2E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.1E+03 7.7E+04 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.7E+04 4.3E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.5E+05 1. 3E+08 PAGEA-28 SO123-ODCM-A Revision 15 11/2020
TABLE 1-9 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 1.5 MILES X/Q 1.lE-06 SEC/(M**3) D/Q 6.5E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO 2.lE+Ol O.OE+OO 1.BE+Ol 2.4E+Ol 2.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 2.BE+02 2.BE+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 O.OE+OO 1.4E+06 2.7E+04 2.9E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 6.0E+02 2.0E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 1.BE+04 4.4E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 l.1E+05 5.5E+OB NI 63 O.OE+OO O.OE+OO O.OE+OO 3.0E+09 O.OE+OO 1.5E+09 3.4E+03 1.9E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 2.7E+04 3 .1E+07 SR 90 O.OE+OO O.OE+OO O.OE+OO 1. OE+09 O.OE+OO 8.0E+OB 1.BE+05 1. 2E+09 ZR 95 O.OE+oO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO l.lE+OB 3.4E+04 2.0E+OB NB 95 O.OE+OO O.OE+OO O.OE+OO 2.3E+OB O.OE+OO 4.5E+08 9.6E+03 8.2E+08 RU 103 O.OE+oO 0. OE+oO 0.0E+OO 4.2E+OB O.OE+OO 7.5E+OB 9.6E+03 1. 3E+09 TE 129M O.OE+OO O.OE+OO O.OE+OO 5.9E+OB O.OE+OO 4.5E+OB 2.4E+04 5.3E+08 cs 134 0.0E+OO O.OE+OO O.OE+OO 1. 4E+OB O.OE+OO l.2E+OB 1.9E+03 2.BE+OB cs 136 O.OE+OO O.OE+OO 0.0E+oO 5.1E+06 O.OE+OO 4.2E+06 2.3E+02 8.3E+06 cs 137 O.OE+OO O.OE+OO O.OE+OO 1. 2E+OB O.OE+OO 9.3E+07 1.4E+03 3.lE+OB BA 140 O.OE+OO O.OE+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 2.4E+04 7.2E+06 CE 141 0.0E+OO O.OE+OO O.OE+OO 1.5E+06 O.OE+OO 2.4E+06 6.9E+03 4.1E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO 1.BE+07 O.OE+OO 2.9E+07 1.5E+05 4.BE+07 I 131 O.OE+OO O.OE+OO O.OE+OO 6.5E+OB O.OE+OO 4.3E+OB 2.3E+05 5.9E+OB I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+03 2. 4E+04 I 133 O.OE+oO O.OE+OO O.OE+OO 1.6E+Ol O.OE+OO 8.6E+OO 4.1E+04 4.7E+04 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.7E+02 8.6E+03 I 135 O.OE+OO O.OE+OO O.OE+OO 1.lE-15 O.OE+OO 6.3E-16 8.6E+03 4.BE+04 UN-ID* O.OE+OO O.OE+OO O.OE+OO 1.lE+OB O.OE+OO 9.4E+07 1.7E+04 1. 4E+OB PAGEA-29 SO123-ODCM-A Revision 15 11/2020
TABLE 1-9 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: BORDER PATROL CHECKPT. DISTANCE: 1. 9 MILES X/Q 6.6E-07 SEC/(M**3) D/Q 3.7E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI /M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.3E+03 l.1E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 3.2E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.2E+03 7.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.1E+05 8.7E+07 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+06 4.9E+09 NI 63 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 4.1E+04 O.OE+OO SR 89 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 3.2E+05 4.9E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 5.7E+07 NB 95 0. OE+QO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 2E+05 3.1E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 1. 2E+05 2.5E+07 TE 129M 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.8E+05 4.5E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+04 l.6E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+O.D O.OE+OO 2.7E+03 3.4E+07 cs 137 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.7E+04 2.3E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+05 4.7E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 8.3E+04 3.1E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO l.8E+06 l.6E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.7E+06 3.9E+06 I 132 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.6E+04 2.8E+05 I 133 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 4.9E+05 5.6E+05 I 134 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 6.8E+03 1. OE+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.OE+05 5.8E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.0E+05 l.7E+08 PAGEA-30 SO123-ODCM-A Revision 15 11/2020
TABLE 1-10 UNITS 2&3 DOSE PARAMETER R{I) FOR SECTOR 'G' PATHWAY: SAN ONOFRE BCH CAMPGD DISTANCE: 1.8 MILES X/Q 6.2E-07 SEC/(M**3) D/Q 2.0E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 5.3E+0l 0.0E+00 9.2E+0l 0.0E+00 1.0E+02 0.0E+00 1.0E+02 0.0E+00 CR 51 1.1E+03 3.8E+05 1.4E+03 3.8E+05 1.7E+03 3.8E+05 1.2E+03 3.8E+05 MN 54 8.2E+04 l.1E+08 l.3E+05 1.1E+08 1.6E+05 l.1E+08 l.2E+05 1.1E+08 co 57 4.0E+02 2.8E+07 1.1E+03 2.8E+07 2.6E+03 2.8E+07 2.6E+03 2.8E+07 co 58 6.4E+04 3.1E+07 9.1E+04 3.1E+07 l.1E+05 3.1E+07 7.6E+04 3.1E+07 co 60 3.7E+05 1.8E+09 5. 8E+05 1.8E+09 7.2E+05 1.8E+09 4.9E+05 1.8E+09 NI 63 1.7E+04 0.0E+00 2.3E+04 0.0E+00 2.5E+04 0.0E+00 1.5E+04 0.0E+00 SR 89 1.7E+05 1.8E+03 1.8E+05 1.8E+03 2.0E+05 l.8E+03 l.2E+05 1. 8E+03 SR 90 9.2E+05 0.0E+00 1. 2E+06 0.0E+00 1.4E+06 0.0E+00 7.9E+05 0.0E+00 ZR 95 l.4E+05 2.1E+07 1.8E+05 2.1E+07 2.2E+05 2.1E+07 1.5E+05 2.1E+07 NB 95 3.9E+04 l.1E+07 5.0E+04 1.1E+07 6.2E+04 1.1E+07 4.1E+04 l.1E+07 RU 103 4.5E+04 8.9E+06 5.4E+04 8.9E+06 6.4E+04 8.9E+06 4.1E+04 8.9E+06 TE J_29M l.4E+05 l.6E+06 l.4E+05 1.6E+06 l.6E+05 1.6E+06 1.0E+05 l.6E+06 cs 134 6.5E+03 5.6E+08 9.9E+03 5.6E+08 l.2E+04 5.6E+08 8.0E+03 5.6E+08 cs 136 9.7E+02 l.2E+07 l.2E+03 1.2E+07 1.5E+03 1.2E+07 9.9E+02 l.2E+07 cs 137 5.9E+03 8.5E+08 8.5E+03 8.5E+08 9.9E+03 8.5E+08 6.2E+03 8.5E+08 BA 140 l.3E+05 1.7E+06 1.4E+05 1.7E+06 1.7E+05 1.7E+06 l.0E+05 l.7E+06 CE 141 4.2E+04 1.1E+06 4.5E+04 1.1E+06 5.0E+04 l.1E+06 3.0E+04 l.1E+06 CE 144 8.1E+05 5.7E+06 9.8E+05 5.7E+06 1. 1E+06 5.7E+06 6.4E+05 5.7E+06 I 131 l.2E+06 l.4E+06 l.3E+06 1.4E+06 1. 2E+06 1.4E+06 9.8E+05 1.4E+06 I 132 1.4E+04 1.0E+05 1.6E+04 1.0E+05 1.2E+04 1.0E+05 9.4E+03 1.0E+05 I 133 2.9E+05 2.0E+05 3.2E+05 2.0E+05 2.4E+05 2.0E+05 1.8E+05 2.0E+05 I 134 3.7E+03 3.7E+04 4.2E+03 3.7E+04 3.2E+03 3.7E+04 2.5E+03 3.7E+04 I 135 5.7E+04 2.1E+05 6.5E+04 2.1E+05 5.1E+04 2.1E+05 3.7E+04 2.1E+05 UN-ID* 5.3E+04 6.1E+07 8.2E+04 6.1E+07 l.0E+05 6.1E+07 7.1E+04 6.1E+07 PAGE A-31 SO123-ODCM-A Revision 15 11/2020
TABLE 1-10 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: HWY PATROL WEIGH STN DISTANCE: 2.1 MILES X/Q 4.4E-07 SEC/(M**3) D/Q l.4E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2:MREM/YR (MREM/YR (M2 .MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+03 l.1E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 3.2E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.2E+03 7.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 8.7E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 4.9E+09 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.1E+04 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 4.9E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+05 ' 5.7E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 3.1E+07' RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 2.5E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+05 4.5E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+04 l.6E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+03 3.4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.7E+04 2.3E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+05 4.7E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.3E+04 3.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+06 l.6E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 3.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+04 2.8E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.9E+05 5.6E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.8E+03 l.0E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.0E+05 5.8E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 l.7E+08 PAGEA-32 SO123-ODCM-A Revision 15 11/2020
TABLE 1-10 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: ENDLS SUM SURFCAMP/RES DISTANCE: 2.8 MILES X/Q 2.4E-07 SEC/(M**3) D/Q 7.0E-10 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO 4.6E+Ol O.OE+OO 5.2E+Ol O.OE+OO 4.2E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO 7.0E+02 1.9E+05 8.6E+02 l.9E+05 4.7E+03 1. 5E+06 MN 54 O.OE+OO O.OE+OO 6.5E+04 5.7E+07 8.2E+04 5.7E+07 4.6E+05 4.5E+08 co 57 O.OE+OO O.OE+OO 5.4E+02 1.4E+07 l.3E+03 1.4E+07 1.0E+04 1.1E+08 co 58 O.OE+OO O.OE+OO 4.5E+04 l.6E+07 5.5E+04 1.6E+07 3.1E+05 l.2E+08 co 60 O.OE+OO O.OE+OO 2.9E+05 8.8E+08 3.6E+05 8.8E+08 2.0E+06 7 .1E+09 NI 63 O.OE+OO O.OE+OO 1.1E+04 O.OE+OO 1.3E+04 O.OE+OO 5.9E+04 O.OE+OO SR 89 O.OE+OO O.OE+OO 8.9E+04 8.9E+02 9.9E+04 8.9E+02 4.6E+05 7.1E+03 SR 90 O.OE+OO O.OE+OO 6.1E+05 O.OE+OO 6.8E+05 O.OE+OO 3.2E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO 9.2E+04 1.0E+07 1 .'1E+05 1.0E+07 5.8E+05 8.3E+07 NB 95 O.OE+OO O.OE+OO 2.5E+04 5.6E+06 3.1E+04 5.6E+06 1.7E+05 4.5E+07 RU 103 O.OE+OO 0 ._OE+OO 2.7E+04 4.5E+06 3. 2E+04 4.5E+06 1.7E+05 3.6E+07 TE 129M O.OE+OO O.OE+OO 7.2E+04 8.1E+05 8.1E+04 8.1E+05 4.1E+05 6.5E+06 cs 134 O.OE+OO O.OE+OO 5.0E+03 2.8E+08 6.0E+03 2.8E+08 3.2E+04 2.2E+09 cs 136 O.OE+OO O.OE+OO 6.0E+02 6.2E+06 7.3E+02 6.2E+06 3.9E+03 4.9E+07 cs 137 O.OE+OO O.OE+OO 4.3E+03 4.2E+08 5.0E+03 4.2E+08 2.5E+04 3.4E+09 BA 140 O.OE+OO O.OE+OO 7.2E+04 8.4E+05 8.4E+04 8.4E+05 4.2E+05 6.8E+06 CE 141 O.OE+OO O.OE+OO 2.2E+04 5.6E+05 2.5E+04 5.6E+05 l.2E+05 4.5E+06 CE 144 O.OE+OO O.OE+OO 4.9E+05 2.9E+06 5.5E+05 2.9E+06 2.6E+06 2.3E+07 I 131 O.OE+OO O.OE+OO 6.7E+05 7.1E+05 6.0E+05 7.1E+05 3.9E+06 5.7E+06 I 132 O.OE+OO 0.0E+OO 8.0E+03 5.1E+04 6.2E+03 5.1E+04 3.8E+04 4. 1E+05 I 133 O.OE+OO O.OE+OO 1.6E+05 1.0E+05 l.2E+05 1.0E+05 7.1E+05 8.1E+05 I 134 O.OE+OO O.OE+OO 2.1E+03 l.8E+04 1.6E+03 1.8E+04 9.8E+03 1. 5E+05 I 135 O.OE+OO O.OE+OO 3.3E+04 1.0E+05 2.6E+04 1.0E+05 1.5E+05 8.3E+05 UN-ID* O.OE+OO O.OE+OO 4.1E+04 3.1E+07 5.1E+04 3.1E+07 2.8E+05 2.5E+08 PAGEA-33 SO123-ODCM-A Revision 15 11/2020
TABLE 1-10 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: STATE PARK HOST DISTANCE: 2.9 MILES X/Q 2.iE-07 SEC/(M**3) D/Q 6.0E-10 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+03 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+04 4.7E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 l.4E+09 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 3.4E+08 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.3E+05 3.8E+08 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.0E+06 2.2E+10 NI 63 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+05 0.0E+00 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+06 2.2E+04 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+06 2.5E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 1. 4E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 1.1E+08 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+06 2.0E+07 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.8E+04 6.8E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+04 l.5E+08 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.5E+04 1.0E+l0 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+06 2.1E+07 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.6E+05 1.4E+07 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.8E+06 7.0E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+07 1.7E+07 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.1E+05 1.2E+06 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 2.4E+06 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.0E+04 4.5E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.5E+05 2.5E+06 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+05 7.5E+08 PAGEA-34 SO123-ODCM-A Revision 15 11/2020
r Enclosure 7 Offsite Dose Calculation Manual San Onofre Nuclear Generating Station (SONGS)
SO123-ODCM Appendix A Revision 14, March 2020
OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION APPENDIX A R1 TABLES SO123-ODCM-A Revision 14 03/2020
ODCM APPENDIX A TABLE OF CONTENTS Section Title 1.0 UNITS 2 AND 3 R1 TABLES*......... . . . . . . . . . . . . . . . . . . . . . . . A-1 thru A-33
~~R1 Tables based on Parts Code results for 2018 Land Use Census (SDS-CH2-REC-0002).~~
Ai SO123-ODCM-A Revision 13 11/2018
TABLE 1-1 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: SURF BEACH/LIFE GUARD DISTANCE: . 5 MILES X/Q 1. 3E-06 SEC/ (M**3) D/Q 5.5E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 7.8E+00 0.0E+00 4.2E+0l 0.0E+00 l.2E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 1.2E+02 3.2E+04 6.9E+02 1. 5E+05 l.3E+03 4.2E+05 MN 54 0.0E+00 0.0E+00 l.1E+04 9.5E+06 6.5E+04 4.5E+07 1. 3E+05 1.3E+08 co 57 0.0E+00 0.0E+00 9.lE+0l 2.4E+06 l.0E+03 1.1E+07 2.9E+03 3.1E+07 co 58 0.0E+00 0.0E+00 7.6E+03 2.6E+06 4.4E+04 1.2E+07 8.5E+04 3.5E+07 co 60 0.0E+00 0.0E+00 4.9E+04 l.5E+08 2.9E+05 7.0E+08 5.4E+05 2.0E+09 SR 89 0.0E+00 0.0E+00 l.5E+04 l.5E+02 7.9E+04 7.1E+02 1. 3E+05 2.0E+03 SR 90 0.0E+00 0.0E+00 l.0E+05 0.0E+00 5.4E+05 0.0E+00 8.8E+05 0.0E+00 ZR 95 0.0E+00 0.0E+00 l.5E+04 l.7E+06 8.8E+04 8.2E+06 1. 6E+05 2.3E+07 NB 95 0.0E+00 0.0E+00 4.2E+03 9.4E+05 2.5E+04 4.5E+06 4.6E+04 l.2E+07 RU 103 0.0E+00 0.0E+00 4.6E+03 7.5E+05 2.6E+04 3.6E+06 4.6E+04 9.9E+06 TE 129M 0.0E+00 0.0E+00 1.2E+04 l.4E+05 6.5E+04 6.4E+05 l.1E+05 1.8E+06 cs 134 0.0E+00 0.0E+00 8.3E+02 4.7E+07 4.8E+03 2.2E+08 8.9E+03 6.2E+08 cs 136 0.0E+00 0.0E+00 1.0E+02 l.0E+06 5.8E+02 4.9E+06 1.1E+03 l.4E+07 cs 137 0.0E+00 0.0E+00 7.2E+02 7.1E+07 4.0E+03 3.4E+08 6.9E+03 9.4E+08 BA 140 0.0E+00 0.0E+00 1.2E+04 l.4E+05 6.6E+04 6.7E+05 1.2E+05 l.9E+06 CE 141 0.0E+00 0.0E+00 3.8E+03 9.4E+04 2.0E+04 4.5E+05 3.3E+04 1. 2E+06 CE 144 0.0E+00 0.0E+00 8.2E+04 4.8E+05 4.4E+05 2.3E+06 7.1E+05 6.4E+06 I 131 0.0E+00 0.0E+00 l.1E+05 l.2E+05 4.8E+05 5.6E+05 1.1E+06 1.6E+06 I 132 0.0E+00 0.0E+00 1.3E+03 8.5E+03 4.9E+03 4.1E+04 1.0E+04 l.1E+05 I 133 0.0E+00 0.0E+00 2.7E+04 l.7E+04 9.5E+04 8.0E+04 2.0E+05 2.2E+05 I 134 0.0E+00 0.0E+00 3.5E+02 3.1E+03 1. 3E+03 1.5E+04 2.7E+03 4.1E+04 I 135 0.0E+o0 0.0E+00 5.5E+03 l.7E+04 2.0E+04 8.2E+04 4.1E+04 2.3E+05 UN-ID* 0.0E+00 0.0E+00 6.9E+03 5.1E+06 4.1E+04 2.4E+07 7.9E+04 6.8E+07 PAGEA-1 SO123-ODCM-A Revision 5 03-17-11
TABLE 1-1 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'P' page 2-39 6 PATHWAY: SORB CAMPGROUND DISTANCE: 1.0 MILES X/Q 4.4E-07 SEC/(M**3) D/Q 1. 7E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 1.1E+03 0.0E+00 l.3E+03 0.0E+00 l.3E+03 0.0E+00 CR 51 1.3E+04 4.7E+06 l.7E+04 4.7E+06 2.1E+04 4.7E+06 1.4E+04 4.7E+06 MN 54 l.0E+06 1.4E+09 l.6E+06 l.4E+09 2.0E+06 l.4E+09 1.4E+06 l.4E+09 co 57 4.9E+03 3.4E+08 1.3E+04 3.4E+08 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 l.1E+06 3.8E+08 1.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+10 7.1E+06 2.2E+l0 8.7E+06 2.2E+10 6.0E+06 2.2E+l0 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 l.4E+06 2.2E+04 SR 90 1.1E+07 0.0E+00 1.5E+07 0.0E+00 1. 6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 1.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 1.8E+06 2.5E+08 NB 95 4.8E+05 1.4E+08 6.lE+0S l.4E+08 7.5E+05 1.4E+0B 5.0E+05 1.4E+08 RU 103 5.SE+0S 1.1E+08 6.6E+05 1.1E+08 7.BE+0S 1.lE+0B 5.0E+0S 1.1E+08 TE 129M -1.7E+06 2.0E+07 1.8E+06 2.0E+07 2.0E+06 2.0E+07 1. 2E+06 2.0E+07 cs 134 8.0E+04 6.BE+09 1.2E+05 6.8E+09 1.5E+05 6.BE+09 9.BE+04 6.8E+09 cs 136 1. 2E+04 1.SE+0B 1. 5E+04 1.5E+08 1.BE+04 l.SE+0B 1. 2E+04 1.SE+0B cs 137 7.1E+04 1.0E+l0 1. 0E+0S 1. 0E+l0 1.2E+05 1. 0E+l0 7.5E+04 1. 0E+l0 BA 140 1.6E+06 2.1E+07 1.7E+06 2.1E+07 2.0E+06 2.1E+07 1.3E+06 2.1E+07 CE 141 5.2E+05 1. 4E+07 5.4E+05 1. 4E+07 6. lE+0S 1.4E+07 3.6E+05 l.4E+07 CE 144 9.BE+06 7.0E+07 1.2E+07 7.0E+07 1. 3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 1.5E+07 1.7E+07 1.6E+07 l.7E+07 1.5E+07 1.7E+07 1.2E+07 1.7E+07 I 132 1.7E+05 1.2E+06 1.9E+05 l.2E+06 1.SE+0S 1.2E+06 1.lE+0S 1.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 *2.4E+06 I 134 4.5E+04 4.SE+0S 5.1E+04 4.SE+0S 4.0E+04 4.SE+0S 3.0E+04 4.SE+0S I 135 7.0E+0S 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.SE+0S 7.SE+0B l.0E+06 7.SE+0B 1.2E+06 7.5E+08 8.6E+05 7.SE+0B PAGEA-2 SO 123-ODCM-A Revision 14 03/2020
TABLE 1-1 UNITS2&3 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: SAN MATEO POINT HOUS DISTANCE: 2.7 MILES X/Q l.lE-07 SEC/(M**3) D/Q 3. 2E-10 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 O.OE+OO l.1E+03 O.OE+OO l.3E+03 O.OE+OO l.3E+03 O.OE+OO CR 51 1.3E+04 4.7E+06 1.7E+04 4.7E+06 2.1E+04 4.7E+06 l.4E+04 4.7E+06 MN 54 l.OE+06 l.4E+09 1.6E+06 1.4E+09 2.0E+06 1. 4E+09 1.4E+06 1. 4E+09 co 57 4.9E+03 3.4E+08 1.3E+04 3.4E+08 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 1.1E+06 3.8E+08 1. 3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+10 7.1E+06 2.2E+10 8.7E+06 2.2E+10 6.0E+06 2.2E+10 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 1.4E+06 2.2E+04 SR 90 1.1E+07 O.OE+OO 1.5E+07 O.OE+OO 1.6E+07 O.OE+OO 9.6E+06 O.OE+OO ZR 95 l.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 1.8E+06 2.5E+08 NB 95 4.8E+05 1.4E+08 6.1E+05 l.4E+08 7.5E+05 1.4E+08 5.0E+05 1. 4E+08 RU 103 5.5E+05 1.1E+08 6.6E+05 l.1E+08 7.8E+05 1.1E+08 5.0E+05 l.1E+08 TE 129M 1.7E+06 2.0E+07 1.8E+06 2.0E+07 2.0E+06 2.0E+07 1.2E+06 2.0E+07 cs 134 8.0E+04 6.8E+09 l.2E+05 6.8E+09 1.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 1.2E+04 1.5E+08 l.5E+04 1.5E+08 1. 8E+04 1. 5E+08 1.2E+04 1. 5E+08 cs 137 7.1E+04 l.OE+lO 1.0E+05 1.0E+lO 1.2E+05 1.0E+lO 7.5E+04 1.0E+lO BA 140 1.6E+06 2.1E+07 1.7E+06 2.1E+07 2.0E+06 2.1E+07 1. 3E+06 2.1E+07 CE 141 5.2E+05 l.4E+07 5.4E+05 l.4E+07 6.1E+05 l.4E+07 3.6E+05 1. 4E+07 CE 144 9.8E+06 7.0E+07 1.2E+07 7.0E+07 1.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 1.5E+07 1.7E+07 l.6E+07 1.7E+07 1.5E+07 l.7E+07 1.2E+07 l.7E+07 I 132 1.7E+05 l.2E+06 1.9E+05 1.2E+06 1.5E+05 1.2E+06 1.1E+05 1.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 1.0E+06 7.5E+08 1. 2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEA-3 SO123-ODCM-A Revision 13 11/2018
TABLE 1-1 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: COTTON POINT GARDENS DISTANCE: 2.8 MILES X/Q l.0E-07 SEC/(M**3) D/Q 3. 0E-10 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 1. 1E+03 4.0E+03 l.3E+03 2.6E+03 l.3E+03 2.3E+03 CR 51 l.3E+04 4.7E+06 l.7E+04 l.1E+07 2.1E+04 1. 5E+07 l.4E+04 l.6E+07 MN 54 l.0E+06 l.4E+09 l.6E+06 2.0E+09 2.0E+06 2.3E+09 l.4E+06 2.3E+09 co 57 4.9E+03 3.4E+08 l.3E+04 5.8E+08 3.1E+04 6.6E+08 3.1E+04 6.3E+08 co 58 7.8E+05 3.8E+08 l.1E+06 7.5E+08 l.3E+06 9.7E+08 9.3E+05 9.9E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.4E+l0 8.7E+06 2.5E+l0 6.0E+06 2.5E+l0 SR 89 2.0E+06 2.2E+04 2.2E+06 3.5E+l0 2.4E+06 1. 5E+l0 l.4E+06 9.8E+09 SR 90 l.1E+07 0.0E+00 l.5E+07 l.4E+l2 l.6E+07 8.3E+ll 9.6E+06 6. 7E+ll ZR 95 l.8E+06 2.5E+08 2.2E+06 l.1E+09 2.7E+06 l.5E+09 l.8E+06 l.4E+09 NB 95 4.8E+05 l.4E+08 6.1E+05 4.3E+08 7.5E+05 5.9E+08 5.0E+05 6.1E+08 RU 103 5.5E+05 l.1E+08 6.6E+05 5.0E+08 7.8E+05 6.8E+08 5.0E+05 6.6E+08 TE 129M l.7E+06 2.0E+07 l.8E+06 2.9E+09 2.0E+06 l.8E+09 l.2E+06 l.2E+09 cs 134 8.0E+04 6.8E+09 l.2E+05 3.2E+l0 l.5E+05 2.3E+l0 9.8E+04 l.8E+l0 cs 136 l.2E+04 l.5E+08 1. 5E+04 3.7E+08 l.8E+04 3.2E+08 l.2E+04 3.2E+08 cs 137 7.1E+04 l.0E+l0 l.0E+05 3.4E+l0 l.2E+05 2.4E+l0 7.5E+04 l.9E+l0 BA 140 l.6E+06 2.1E+07 l.7E+06 3.0E+08 2.0E+06 2.3E+08 l.3E+06 2.8E+08 CE 141 5.2E+05 1. 4E+07 5.4E+05 4.2E+08 6.1E+05 5.5E+08 3.6E+05 5.2E+08 CE 144 9.8E+06 7.0E+07 l.2E+07 1. 0E+l0 l.3E+07 l.3E+l0 7.8E+06 l.lE+l0 I 131 l.5E+07 l.7E+07 l.6E+07 4.8E+l0 l.5E+07 3.lE+l0 l.2E+07 3.8E+l0 I 132 l.7E+05 l.2E+06 l.9E+05 l.2E+06 l.5E+05 1. 2E+06 l.1E+05 l.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 8 .1E+08 2.9E+06 4.6E+08 2.2E+06 5.3E+08 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 l.2E+07 6.2E+05 8.2E+06 4.5E+05 9.1E+06 UN-ID* 6.5E+05 7.5E+08 l.0E+06 3.5E+09 1. 2E+06 2.6E+09 8.6E+05 2.0E+09 PAGEA-4 SO123-ODCM-A Revision 5 03-17-11
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: ST PARK OFFICE TRLR DISTANCE: .6 MILES X/Q 2.lE-06 SEC/(M**3) D/Q 1.2 E-08 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+03 1.1E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 3.2E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.2E+03 7.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 8.7E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0._0E+00 0.0E+00 l.4E+06 4.9E+09 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 4.9E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+05 5.7E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 3.1E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 2.5E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+05 4.5E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+04 1.6E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+03 3.4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.7E+04 2.3E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+05 4.7E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.3E+04 3.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+06 1.6E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 3.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+04 2.8E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.9E+05 5.6E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.8E+03 1.0E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.0E+05 5.8E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 1.7E+08 PAGEA-5 SO123-ODCM-A Revision 13 11/2018
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SURF BEACH/GUARD SHACK DISTANCE: .7 MILES X/Q l.8E-06 SEC/(M**3) D/Q 9.8E-09/M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2 .MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO 7.8E+OO O.OE+OO 4.2E+Ol 0.0E+OO 2.2E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO l.2E+02 3.2E+04 6.9E+02 l.5E+05 2.5E+03 8.0E+05 MN 54 O.OE+OO O.OE+OO l.1E+04 9.5E+06 6.5E+04 4.5E+07 2.4E+05 2.4E+08 co 57 O.OE+OO O.OE+OO 9.lE+Ol 2.4E+06 1. OE+03 l.1E+07 5.4E+03 5.9E+07 co 58 O.OE+OO O.OE+OO 7.6E+03 2.6E+06 4.4E+04 l.2E+07 l.6E+05 6.5E+07 co 60 O.OE+OO o:oE+OO 4.9E+04 1. 5E+08 2.9E+05 7.0E+08 l.OE+06 3.7E+09 SR 89 O.OE+OO O.OE+OO l.5E+04 l.5E+02 7.9E+04 7.1E+02 2.4E+05 3.7E+03 SR 90 O.OE+OO O.OE+OO l.OE+05 O.OE+OO 5.4E+05 O.OE+OO l.6E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO l.5E+04 l.7E+06 8.8E+04 8.2E+06 3.0E+05 4.3E+07 NB 95 O.OE+OO O.OE+OO 4.2E+03 9.4E+05 2.5E+04 4.5E+06 8.6E+04 2.3E+07 RU 103 0.0E+OO O.OE+OO 4.6E+03 7.5E+05 2.6E+04 3.6E+06 8.6E+04 l.9E+07 TE 129M O.OE+OO O.OE+OO 1. 2E+04 1. 4E+05 6.5E+04 6.4E+05 2.1E+05 3.4E+06 cs 134 O.OE+OO O.OE+OO 8.3E+02 4.7E+07 4.8E+03 2.2E+08 l.7E+04 1. 2E+09 cs 136 O.OE+OO O.OE+OO 1.0E+02 l.OE+06 5.8E+02 4.9E+06 2.1E+03 2.6E+07 cs 137 O.OE+OO O.OE+OO 7.2E+02 7.1E+07 4.0E+03 3.4E+08 l.3E+04 l.8E+09 BA 140 O.OE+OO O.OE+OO 1. 2E+04 1. 4E+05 6.6E+04 6.7E+05 2.2E+05 3.5E+06 CE 141 0.0E+OO O.OE+OO 3.8E+03 9.4E+04 2.0E+04 4.5E+05 6.2E+04 2.3E+06 CE 144 O.OE+OO O.OE+OO 8.2E+04 4.8E+05 4.4E+05 2.3E+06 1. 3E+06 l.2E+07 I 131 O.OE+OO O.OE+OO l.1E+05 1. 2E+05 4.8E+05 5.6E+05 2.0E+06 2.9E+06 I 132 O.OE+OO O.OE+OO 1.3E+03 8.5E+03 4.9E+03 4.1E+04 2.0E+04 2.1E+05 I 133 O.OE+OO O.OE+OO 2.7E+04 l.7E+04 9.5E+04 8.0E+04 3.7E+05 4.2E+05 I 134 0.0E+OO O.OE+OO 3.5E+02 3.1E+03 l.3E+03 l.5E+04 5.1E+03 7.7E+04 I 135 O.OE+OO O.OE+OO 5.5E+03 l.7E+04 2.0E+04 8.2E+04 7.7E+04 4.3E+05 UN-ID* O.OE+OO O.OE+OO 6.9E+03 5.1E+06 4.1E+04 2.4E+07 1. 5E+05 l.3E+08 PAGEA-6 SO123-ODCM-A Revision 13 11/2018
TABLE 1-2 UNITS 2&3 PATHWAY: SORB REC BEACH DISTANCE: 1.1 MILES X/Q 9.9E-07 SEC/(M**3) D/Q 5.0E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 l.1E+03 0.0E+00 1.3E+03 0.0E+00 1. 3E+03 0. 0E+o0 CR 51 1.3E+04 4.7E+06 1.7E+04 4.7E+06 2 .1E+04 4.7E+06 1. 4E+04 4.7E+06 MN 54 1.0E+06 1.4E+09 l.6E+06 1. 4E+09 2.0E+06 1.4E+09 1. 4E+06 1. 4E+09 co 57 4.9E+03 3.4E+08 1.3E+04 3.4E+08 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 1.1E+06 3.8E+08 1. 3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.2E+10 8.7E+06 2.2E+10 6.0E+06 2.2E+10 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 1. 4E+06 2.2E+04 SR 90 1.1E+07 0.0E+00 1.5E+07 0.0E+00 1.6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 1.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 1. 8E+06 2.5E+08 NB 95 4.8E+05 1. 4E+08 6.1E+05 l.4E+08 7.5E+05 1.4E+08 5.0E+05 1. 4E+08 RU 103 5.5E+05 1.1E+08 6.6E+05 1.1E+08 7.8E+05 1.1E+08 5.0E+05 1.1E+08 TE 129M 1. 7E+06 2.0E+07 1. 8E+06 2.0E+07 2.0E+06 2.0E+07 1.2E+06 2.0E+07 cs 134 8.0E+04 6.8E+09 1. 2E+05 6.8E+09 1.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 1.2E+04 1.5E+08 1.5E+04 1.5E+08 1.8E+04 1.5E+08 1.2E+04 1.5E+08 cs 137 7.1E+04 1.0E+l0 1.0E+05 1.0E+l0 1. 2E+05 1.0E+l0 7.5E+04 1.0E+l0 BA 140 1.6E+06 2.1E+07 1.7E+06 2.1E+07 2.0E+06 2.1E+07 1.3E+06 2.1E+07 CE 141 5.2E+05 1.4E+07 5.4E+05 1.4E+07 6.1E+05 1.4E+07 3.6E+05 1.4E+07 CE 144 9.8E+06 7.0E+07 1. 2E+07 7.0E+07 1.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 1.5E+07 1.7E+07 1.6E+07 1.7E+07 1.5E+07 l.7E+07 1.2E+07 1.7E+07 I 132 1.7E+05 1.2E+06 1.9E+05 1.2E+06 1.5E+05 1.2E+06 1.1E+05 1. 2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 1.0E+06 7.5E+08 1.2E+06 7.5E+08 8.6E+05 7.5E+08 DOSE PARAMETER R(I) FOR SECTOR 'Q' page 2-45 12 PAGEA-7 SO 123-ODCM-A Revision 14 03/2020
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SORB CAMPGROUND CK IN DISTANCE: 1.3 MILES X/Q 7.9E-07 SEC/(M**3) D/Q 3.9E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.3E+03 1.1E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 3.2E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.2E+03 7. 8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.1E+05 8. 7E+07 co 60 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 1.4E+06 4.9E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 4.9E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 5.7E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 2E+05 3.1E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 1. 2E+05 2.5E+07 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.8E+05 4.5E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+04 1.6E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.7E+03 3.4E+07 cs 137 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 1.7E+04 2.3E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+05 4.7E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 8.3E+04 3.1E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.8E+06 1.6E+07 I 131 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.7E+06 3.9E+06 I 132 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.6E+04 2.8E+05 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.9E+05 5.6E+05 I 134 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 6.8E+03 1.0E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.0E+05 5.8E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.0E+05 1.7E+08 PAGEA-8 SO123-ODCM-A Revision 9 09/2015
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SAN ONOFRE III HOUSING DISTANCE: 1.4 MILES X/Q 6.9E-07 SEC/(M**3) D/Q 3.3E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 O.OE+OO l.1E+03 0.0E+OO 1.3E+03 O.OE+OO 1. 3E+03 O.OE+OO CR 51 1.3E+04 4.7E+06 l.7E+04 4.7E+06 2.1E+04 4.7E+06 1. 4E+04 4.7E+06 MN 54 1.0E+06 l.4E+09 l.6E+06 l.4E+09 2.0E+06 1.4E+09 1.4E+06 1.4E+09 co 57 4.9E+03 3.4E+OB 1.3E+04 3.4E+OB 3.1E+04 3.4E+OB 3.1E+04 3.4E+OB co 58 7.BE+05 3.BE+OB 1.1E+06 3.BE+OB 1. 3E+06 3.BE+OB 9.3E+05 3.BE+OB co 60 4.5E+06 2.2E+10 7.1E+06 2.2E+10 8.7E+06 2.2E+10 6.0E+06 2.2E+10 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2. 4E+06 2.2E+04 1.4E+06 2.2E+04 SR 90 1.1E+07 O.OE+OO 1.5E+07 O.OE+OO 1.6E+07 O.OE+OO 9.6E+06 O.OE+OO ZR 95 l.8E+06 2.5E+OB 2. 2E+,06 2.5E+OB 2.7E+06 2.5E+08 1.BE+06 2.5E+OB NB 95 4.BE+05 1.4E+OB 6.1E+05 1.4E+OB 7.5E+05 1. 4E+OB 5.0E+05 1.4E+OB RU 103 5.5E+05 l.lE+OB 6.6E+05 l.lE+OB 7.BE+05 1.lE+OB 5.0E+05 1.lE+OB TE 129M 1.7E+06 2.0E+07 1.BE+06 2.0E+07 2.0E+06 2.0E+07 1.2E+06 2.0E+07 cs 134 8.0E+04 6.BE+09 1. 2E+05 6.BE+09 1.5E+05 6.BE+09 9.BE+04 6.BE+09 cs 136 1. 2E+04 l.5E+OB 1.5E+04 1.5E+OB 1.BE+04 1.5E+OB 1. 2E+04 l.5E+OB cs 137 7.1E+04 1.0E+lO 1.0E+05 1.0E+lO 1.2E+05 1.0E+lO 7.5E+04 1.0E+lO BA 140 1. 6E+06 2.1E+07 1.7E+06 2.1E+07 2.0E+06 2.1E+07 1.3E+06 2.1E+07 CE 141 5.2E+05 l.4E+07 5.4E+05 1.4E+07 6.1E+05 l.4E+07 3.6E+05 l.4E+07 CE 144 9.BE+06 7.0E+07 1.2E+07 7.0E+07 1.3E+07 7.0E+07 7.BE+06 7.0E+07 I 131 l.5E+07 l.7E+07 l.6E+07 l.7E+07 1.5E+07 l.7E+07 1.2E+07 l.7E+07 I 132 1. 7E+05 1.2E+06 1.9E+05 1.2E+06 l.5E+05 1.2E+06 l.1E+05 1.2E+06 I 133 3.6E+06 2.4E+06 3.BE+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 1.0E+06 7.5E+OB 1. 2E-F06 7.5E+08 8.6E+05 7.5E+OB PAGEA-9 SO123-ODCM-A Revision 7 09-23-13
TABLE 1-2 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SC RES. WITH GARDEN DISTANCE: 4.0 MILES X/Q 1.4E-07 SEC/(M**3) D/Q 4.9E-10 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 1.1E+03 4.0E+03 1.3E+03 2.6E+03 1.3E+03 2.3E+03 CR 51 l.3E+04 4.7E+06 1.7E+04 l.1E+07 2.1E+04 l.5E+07 l.4E+04 l.6E+07 MN 54 l.0E+06 l.4E+09 l.6E+06 2.0E+09 2.0E+06 2.3E+09 1.4E+06 2.3E+09 co 57 4.9E+03 3.4E+08 l.3E+04 5.8E+08 3.1E+04 6.6E+08 3.1E+04 6.3E+08 co 58 7.8E+05 3.8E+08 l.1E+06 7.5E+08 l.3E+06 9.7E+08 9.3E+05 9.9E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.4E+10 B.7E+06 2.5E+10 6.0E+06 2.5E+l0 SR 89 2.0E+06 2.2E+04 2.2E+06 3.5E+l0 2.4E+06 l.5E+l0 l.4E+06 9.8E+09 SR 90 l.1E+07 0.0E+00 l.5E+07 l.4E+12 l.6E+07 8. :3E+ll 9.6E+06 6. 7E+ll ZR 95 l.8E+06 2.5E+08 2.2E+06 l.1E+09 2.7E+06 l.5E+09 l.8E+06 l.4E+09 NB 95 4.8E+05 l.4E+08 6.1E+05 4.3E+08 7.5E+05 5.9E+08 5.0E+05 6.1E+08 RU 103 5.5E+05 1.lE+0B 6.6E+05 5.0E+0B 7.8E+05 6.8E+08 5.0E+05 6.6E+08 TE 129M 1.7E+06 2.0E+07 l.8E+06 2.9E+09 2.0E+06 l.BE+09 1. 2E+06 1. 2E+09 cs 134 8.0E+04 6.8E+09 l.2E+05 3.2E+l0 l.5E+05 2.3E+l0 9.8E+04 l.8E+10 cs 136 1.2E+04 l.5E+08 l.5E+04 3.7E+08 1.8E+04 3.2E+08 1. 2E+04 3.2E+08 cs 137 7.1E+04 l.0E+l0 l.0E+05 3.4E+l0 l.2E+05 2.4E+l0 7.5E+04 l.9E+10 BA 140 1.6E+06 2.1E+07 l.7E+06 3.0E+08 2.0E+06 2.3E+08 l.3E+06 2.8E+08 CE 141 5.2E+05 1.4E+07 5.4E+05 4.2E+08 6.1E+05 5.5E+08 3.6E+05 5.2E+08 CE 144 9.8E+06 7.0E+07 l.2E+07 1. 0E+l0 l.3E+07 l.3E+l0 7.8E+06 l.lE+l0 I 131 l.5E+07 l.7E+07 l.6E+07 4.8E+l0 l.5E+07 3.lE+l0 l.2E+07 3.8E+l0 I 132 l.7E+05 1. 2E+06 l.9E+05 l.2E+06 l.5E+05 1. 2E+06 l.1E+05 l.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 8.1E+08 2.9E+06 4.6E+08 2.2E+O~ 5.3E+08 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 l.2E+07 6.2E+05 8.2E+06 4.5E+05 9.1E+06 UN-ID* 6.5E+05 7.5E+08 l.0E+06 3.5E+09 1. 2E+06 2.6E+09 8.6E+05 2.0E+09 PAGEA-10 SO123-ODCM-A Revision 13 11/2018
TABLE 1-3 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SC RES. WITH GARDEN DISTANCE: 4. 0 MILES X/Q l.4E-07 SEC/(M**3) D/Q 4.9E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 l.1E+03 4.0E+03 l.3E+03 2.6E+03 l.3E+03 2.3E+03 CR 51 l.3E+04 4.7E+06 l.7E+04 l.1E+07 2.1E+04 l.5E+07 l.4E+04 l.6E+07 MN 54 l.0E+06 l.4E+09 l.6E+06 2.0E+09 2.0E+06 2.3E+09 l.4E+06 2.3E+09 co 57 4.9E+03 3.4E+08 l.3E+04 5.8E+08 3.1E+04 6.6E+08 3.1E+04 6.3E+08 co 58 7.8E+05 3.8E+08 l.1E+06 7.5E+08 l.3E+06 9.7E+08 9.3E+05 9.9E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.4E+l0 8.7E+06 2.5E+l0 6.0E+06 2.5E+l0 SR 89 2.0E+06 2.2E+04 2.2E+06 3.5E+10 2.4E+06 1. 5E+10 l.4E+06 9.8E+09 SR 90 l.1E+07 0.0E+00 l.5E+07 l.4E+l2 l.6E+07 8. 3E+ll 9.6E+06 6. 7E+ll ZR 95 l.8E+06 2.5E+08 2.2E+06 l.1E+09 2.7E+06 1. 5E+09 1.8E+06 1. 4E+09 NB 95 4.8E+05 1. 4E+08 6.1E+05 4.3E+08 7.5E+05 5.9E+08 5.0E+05 6.1E+08 RU 103 5.5E+05 l.1E+08 6.6E+05 5.0E+08 7.8E+05 6.8E+08 5.0E+05 6.6E+08 TE 129M 1.7E+06 2.0E+07 l.8E+06 2.9E+09 2.0E+06 l.8E+09 l.2E+06 l.2E+09 cs 134 8.0E+04 6.8E+09 1. 2E+05 3.2E+l0 l.5E+05 2.3E+l0 9.8E+04 1. 8E+l0 cs 136 1. 2E+04 l.5E+08 l.5E+04 3.7E+08 l.8E+04 3.2E+08 1. 2E+04 3.2E+08 cs 137 7.1E+04 l.0E+l0 l.0E+05 3.4E+l0 1. 2E+05 2.4E+l0 7.5E+04 1. 9E+l0 BA 140 l.6E+06 2.1E+07 l.7E+06 3.0E+08 2.0E+06 2.3E+08 1. 3E+06 2.8E+08 CE 141 5.2E+05 l.4E+07 5.4E+05 4.2E+08 6.1E+05 5.5E+08 3.6E+05 5.2E+08 CE 144 9.8E+06 7.0E+07 l.2E+07 1. 0E+l0 l.3E+07 1. 3E+l0 7.8E+06 l.lE+l0 I 131 1. 5E+07 1.7E+07 l.6E+07 4.8E+l0 l.5E+07 3.lE+l0 1. 2E+07 3. 8E+l0 I 132 l.7E+05 l.2E+06 l.9E+05 l.2E+06 1.5E+05 l.2E+06 l.1E+05 l.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 8.1E+08 2.9E+06 4.6E+08 2.2E+06 5.3E+08 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 l.2E+07 6.2E+05 8.2E+06 4.5E+05 9 .1E+06 UN-ID* 6.5E+05 7.5E+08 l.0E+06 3.5E+09 l.2E+06 2.6E+09 8.6E+05 2.0E+09 PAGEA-11 SO123-ODCM-A Revision 13 11/2018
TABLE 1-3 UNITS2&3 DOSE PARAMETER R(I) FOR SECTOR 'R' PATHWAY: SAN ONOFRE III HOUSING DISTANCE: 1.3 MILES X/Q 5.2E-07 SEC/(M**3) D/Q 3.0E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 6.5E+02 0.0E+00 1.1E+03 0.0E+00 1.3E+03 0.0E+00 1. 3E+03 0.0E+00 CR 51 l.3E+04 4.7E+06 1.7E+04 4.7E+06 2.1E+04 4.7E+06 1.4E+04 4.7E+06 MN 54 1.0E+06 l.4E+09 l.6E+06 l.4E+09 2.0E+06 1.4E+09 l.4E+06 1.4E+09 co 57 4.9E+03 3.4E+08 1.3E+04 3.4E+08 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 7.8E+05 3.8E+08 1.1E+06 3.8E+08 1.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.2E+l0 8.7E+06 2.2E+10 6.0E+06 2. 2E+10 SR 89 2.0E+06 2.2E+04 2.2E+06 2.2E+04 2.4E+06 2.2E+04 1. 4E+06 2.2E+04 SR 90 1.1E+07 0.0E+00 l.5E+07 0.0E+00 1.6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 1.8E+06 2.5E+08 2.2E+06 2.5E+08 2.7E+06 2.5E+08 l.8E+06 2.5E+o8-NB 95 4.8E+05 l.4E+08 6.1E+05 l.4E+08 7.5E+05 1.4E+08 5.0E+05 l.4E+08 RU 103 5.5E+05 1.1E+08 6.6E+05 1.1E+08 7.8E+05 1.1E+08 5.0E+05 1.1E+08 TE 129M 1. 7E+06 2.0E+07 1.8E+06 2.0E+07 2.0E+06 2.0E+07 1.2E+06 2.0E+07 cs 134 8.0E+04 6.8E+09 1.2E+05 6.8E+09 1.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 1. 2E+04 1.5E+08 1. 5E+04 1.5E+08 1.8E+04 1. 5E+08 1. 2E+04 1.5E+08 cs 137 7.1E+04 1.0E+l0 1.0E+05 1.0E+l0 1.2E+05 1.0E+l0 7.5E+04 1.0E+l0 BA 140 l.6E+06 2.1E+07 1.7E+06 2.1E+07 2.0E+06 2.1E+07 1.3E+06 2.1E+07 CE 141 5.2E+05 1.4E+07 5.4E+05 l.4E+07 6.1E+05 1.4E+07 3.6E+05 1.4E+07 CE 144 9.8E+06 7.0E+07 1. 2E+07 7.0E+07 1.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 1.5E+07 1.7E+07 1.6E+07 l.7E+07 1.5E+07 1.7E+07 1.2E+07 1.7E+07 I 132 l.7E+05 1.2E+06 l.9E+05 1.2E+06 1.5E+05 1.2E+06 l.1E+05 l.2E+06 I 133 3.6E+06 2.4E+06 3.8E+06 2.4E+06 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 4.5E+04 4.5E+05 5.1E+04 4.5E+05 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 7.0E+05 2.5E+06 7.9E+05 2.5E+06 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 1.0E+06 7.5E+08 1. 2E+06 7.5E+08 8.6E+05 7.5E+08 PAGE A-12 SO 123-ODCM-A Revision 9 09/2015
TABLE 1-3 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'R' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 1.8 MILES X/Q 3.lE-07 SEC/(M**3) D/Q 2.0E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION- FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO 0.0E+OO O.OE+OO 2.8E+Ol O.OE+OO 2.3E+Ol l.5E+Ol 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO l.OE+05 l.7E+02 2.4E+05 MN 54 O.OE+OO 0.0E+OO O.OE+OO 7.7E+05 O.OE+OO l.4E+06 l.6E+04 l.9E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 3.6E+02 l.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 l.1E+04 4.1E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 6.9E+04 3.8E+08 SR 89 O.OE+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 1. 6E+04 3.1E+07 SR 90 O.OE+OO O.OE+OO O.OE+OO l.OE+09 O.OE+OO 8.0E+OB l.1E+05 l.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO 1. lE+OB 2.1E+04 2.0E+OB NB 95 O.OE+OO O.OE+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 5.9E+03 8.2E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 5.9E+03 1. 3E+09 TE 129M O.OE+OO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 1. 4E+04 5.3E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO 1. 4E+08 O.OE+OO l.2E+08 l.1E+03 2.3E+08 cs 136 O.OE+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 l.4E+02 7.2E+06 cs 137 O.OE+OO O.OE+OO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 8.7E+02 2.3E+08 BA 140 O.OE+OO O.OE+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 l.5E+04 7.0E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO 1.5E+06 O.OE+OO 2.4E+06 4.2E+03 4.0E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO 1.8E+07 O.OE+OO 2.9E+07 9.0E+04 4.8E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 l.4E+05 5.9E+08 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 3E+03 l.4E+04 I 133 O.OE+OO O.OE+OO O.OE+OO l.6E+Ol O.OE+OO 8.6E+OO 2.5E+04 2.8E+04 I 134 O.OE+OO O.OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.5E+02 5.2E+03 I 135 O.OE+OO O.OE+OO O.OE+OO l.lE-15 O.OE+OO 6.3E-16 5.2E+03 2.9E+04 UN-ID* O.OE+OO O.OE+OO O.OE+OO l.1E+08 O.OE+OO 9.4E+07 l.OE+04 l.3E+08 PAGEA-13 SO123-ODCM-A Revision 7 09-23-13
TABLE 1-4 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'A' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 1.8 MILES X/Q 2.lE-07 SEC/(M**3) D/Q 1. SE-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO 2.8E+Ol O.OE+OO 2.3E+Ol 1.5E+Ol 3.9E+Ol CR 51 O.OE+OO 0. OE+oO O.OE+OO 5.0E+04 O.OE+OO l.OE+05 l.7E+02 2.4E+05 MN 54 O.OE+OO 0. OE+oO O.OE+OO 7.7E+05 O.OE+OO 1.4E+06 1.6E+04 1.9E+07 co 57 O.OE+oO 0. OE+oO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 3.6E+02 1.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO 1.9E+07 1.1E+04 4.1E+07 co 60 0.0E+OO 0. OE+oO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 6.9E+04 3.8E+08 SR 89 O.OE+OO 0. OE+oO O.OE+OO 4.9E+07 0. OE+oO 2.6E+07 1.6E+04 3.1E+07 SR 90 O.OE+OO 0.0E+OO O.OE+OO 1.0E+09 O.OE+OO 8.0E+08 1.1E+05 1. 2E+09 ZR 95 O.OE+OO 0.0E+OO O.OE+OO 6.2E+07 O.OE+OO 1.1E+08 2.1E+04 2.0E+08 NB 95 O.OE+OO O.OE+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 5.9E+03 8.2E+08 RU 103 O.OE+OO 0. OE+oO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 5.9E+03 1. 3E+09 TE 129M 0.0E+OO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 1.4E+04 5.3E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO 1.4E+08 O.OE+OO 1. 2E+08 1.1E+03 2.3E+08 cs 136 0.0E+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 1.4E+02 7.2E+06 cs 137 0.0E+OO 0. OE+oO 0.0E+OO 1. 2E+08 O.OE+OO 9.3E+07 8.7E+02 2.3E+08 BA 140 0.0E+oO O.OE+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 1.5E+04 7.0E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO l.5E+06 0. OE+oO 2.4E+06 4.2E+03 4.0E+06 CE 144 O.OE+oO O.OE+OO O.OE+OO 1.8E+07 O.OE+OO 2.9E+07 9.0E+04 4.8E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 l.4E+05 5.9E+08 I 132 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 1. 3E+03 1.4E+04 I 133 O.OE+oO O.OE+OO O.OE+OO 1.6E+Ol O.OE+OO 8.6E+OO 2.5E+04 2.8E+04 I 134 0.0E+OO 0. OE+oO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 3.5E+02 5.2E+03 I 135 O.OE+OO O.OE+OO O.OE+OO l.lE-15 O.OE+OO 6.3E-16 5.2E+03 2.9E+04 UN-ID* 0.0E+OO O.OE+OO O.OE+oO l.1E+08 0.0E+OO 9.4E+07 1.0E+04 1. 3E+08 PAGE A-14 SO123-ODCM-A Revision 9 09/2015
TABLE 1-4 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'A' PATHWAY: CAMP SAN MATEO RES DISTANCE: 3.6 MILES X/Q 7.2E-08 SEC/(M**3) D/Q 4. lE-10 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.3E+03 1.1E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 3.2E+OB co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.2E+03 7.BE+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.1E+05 8.7E+07 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.4E+06 4.9E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 4.9E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 5.7E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.2E+05 3.1E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.2E+05 2.5E+07 TE 129M O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.BE+05 4.5E+06 cs 134 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+04 1.6E+09 cs 136 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 2.7E+03 3.4E+07 cs 137 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.7E+04 2.3E+09 BA 140 O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+05 4.7E+06 CE 141 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 8.3E+04 3.1E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.8E+06 l.6E+07 I 131 O.OE+oO 0.0E+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 2.7E+06 3.9E+06 I 132 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.6E+04 2.8E+05 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 4.9E+05 5.6E+05 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.8E+03 1.0E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO l.OE+05 5.BE+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.0E+05 1.7E+OB PAGEA-15 SO123-ODCM-A Revision 13 11/2018
TABLE 1-4 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'A' PATHWAY: CAMP SAN MATEO MP DISTANCE: 3. 6 MILES X/Q 7.2E-08 SEC/(M**3) D/Q 4.lE-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+03 1.1E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 3.2E+08 co 57 0.0E+00 0.0E+00 0. 0E+o0 0.OE+00 0.0E+00 0.0E+00 7.2E+03 7.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 8.7E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+06 4.9E+09 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 4.9E+03 SR 90 0.0E+00 0.0E+00 0. 0E+o0 0.0E+00 0.0E+00 0.0E+00 2.2E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+05 5.7E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 3.1E+07 RU 103 0.0E+00 0.0E+00 0.0E+o0 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 2.5E+07 TE 129M 0.0E+00 0.0E+b0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+05 4.5E+06 cs 134 0.0E+00 0.0E+00 0.0E+o0 0.0E+00 0.0E+00 0.0E+00 2.2E+04 1.6E+09 cs 136 0.0E+00 0.0E+00 0.0E+o0 0.0E+00 0.0E+00 0. 0E+Q0 2.7E+03 3.4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.7E+04 2.3E+09 BA 140 0.0E+00 0.0E+00 0.0E+o0 0.0E+00 0.0E+00 0.0E+00 2.9E+05 4.7E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.3E+04 3.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+06 l.6E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 3.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+04 2.8E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.9E+05 5.6E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.8E+03 1.0E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 0E+05 5.8E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 1.7E+08 PAGEA-16 SO123-ODCM-A Revision 13 11/2018
TABLE 1-5 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'B' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 1.6 MILES X/Q 2.0E-07 SEC/(M**3) D/Q 1. 8E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 2.8E+0l 0.0E+00 2.3E+0l 1.5E+0l 3.9E+0l CR 51 0.0E+00 0.0E+00 0.0E+00 5.0E+04 0.0E+00 l.0E+05 l.7E+02 2.4E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 7.7E+05 0 ."'0E+00 1.4E+06 l.6E+04 l.9E+07 co 57 0.0E+00 0.0E+00 0.0E+00 4.6E+06 0.0E+00 8.0E+06 3.6E+02 l.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 l.9E+07 l.1E+04 4.1E+07 co 60 0.0E+00 0.0E+00 0.0E+00 3.6E+07 0.0E+00 7.2E+07 6.9E+04 3.8E+08 SR 89 0.0E+00 0.0E+00 0.0E+00 4.9E+07 0.0E+00 2.6E+07 l.6E+04 3.1E+07 SR 90 0.0E+00 0.0E+00 0.0E+00 l.0E+09 ---- 0.0E+00 8.0E+08 1.1E+05 1.2E+09 ZR 95 0.0E+00 0.0E+00 0.0E+00 6.2E+07 0.0E+00 l .1E+08 2.1E+04 2.0E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 2.3E+08 0.0E+00 4.5E+08 5.9E+03 8.2E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 4.2E+08 0.0E+00 7.5E+08 5.9E+03 1. 3E+09 TE 129M 0.0E+00 0.0E+00 0.0E+00 5.9E+08 0.0E+00 4.5E+08 1.4E+04 5.3E+08 cs 134 0.0E+00 0.0E+00 0.0E+00 l.4E+08 0.0E+00 1. 2E+08 1.1E+03 2.3E+08 )
cs 136 0.0E+00 0.0E+00 0.0E+00 5.1E+06 0.0E+00 4.2E+06 l.4E+02 7.2E+06 cs 137 0.0E+00 0.0E+00 0.0E+00 1. 2E+08 0.0E+00 9.3E+07 8.7E+02 2.3E+08 BA 140 0.0E+00 0.0E+00 0.0E+00 5.0E+06 0.0E+00 4.2E+06 l.5E+04 7.0E+06 CE 141 0.0E+00 0.0E+00 ) 0.0E+00 l.5E+06 0.0E+00 2.4E+06 4.2E+03 4.0E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 l.8E+07 0.0E+00 2.9E+07 9.0E+04 4.8E+07 I 131 0.0E+00 0.0E+00 0.0E+00 6.5E+08 0.0E+00 4.3E+08 1.4E+05 5.9E+08 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 3E+03 l.4E+04 I 133 0.0E+00 0.0E+00 0.0E+00 l.6E+0l 0.0E+00 8.6E+00 2.5E+04 2.8E+04 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.5E+02 5.2E+03 I 135 0.0E+00 0.0E+00 0.0E+00 l.lE-15 0.0E+00 6.3E-16 5.2E+03 2.9E+04 UN-ID* 0.0E+00 0.0E+00 0.0E+00 l.1E+08 0.0E+00 9.4E+07 1.0E+04 1.3E+08 PAGEA-17 SO 123-ODCM-A Revision 7 09-23-13
TABLE 1-5 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'B' PATHWAY: SANITARY LANDFILL DISTANCE: 2.1 MILES X/Q 1.3E-07 SEC/(M**3) D/Q 1. lE-0 9 /M* * ( 2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO l.2E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.3E+03 4.3E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+05 l.3E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+03 3.2E+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.6E+04 3.5E+07 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.6E+05 2.0E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+05 2.0E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.9E+05 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.6E+05 2.3E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 4.7E+04 l.3E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.7E+04 1.0E+07 TE 129M O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 1.1E+05 1.8E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 9.1E+03 6.4E+08 cs 136 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.1E+03 1.4E+07 cs 137 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.0E+03 9.6E+08 BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.2E+05 1.9E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.4E+04 l.3E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.2E+05 6.5E+06 I 131 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.1E+06 1. 6E+06 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 1.1E+04 1. 2E+05 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.0E+05 2.3E+05 I 134 O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 2.8E+03 4.2E+04 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.2E+04 2.3E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.1E+04 6.9E+07 PAGEA-18 SO 123-ODCM-A Revision 7 09-23-13
TABLE 1-6 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: SEWAGE TREAT.FACILITY DISTANCE: 2.2 MILES X/Q l.3E-07 SEC/(M**3) D/Q l.2E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+oO 0.0E+OO O.OE+OO O.OE+OO 2.9E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.3E+03 l.1E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 3.2E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.2E+03 7.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.1E+05 8.7E+07 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 4E+06 4.9E+09 SR 89 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 4.9E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 5.7E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.2E+05 3.1E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.2E+05 2.5E+07 TE 129M O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 2.8E+05 4.5E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+04 l.6E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.7E+03 3.4E+07 cs 137 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.7E+04 2.3E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+05 4.7E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.3E+04 3.1E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.8E+06 l.6E+07 I 131 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.7E+06 3.9E+06 I 132 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.6E+04 2.8E+05 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.9E+05 5.6E+05 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.8E+03 l.OE+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. OE+05 5.8E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.0E+05 l.7E+08 PAGEA-19 SO123-ODCM-A Revision 7 09-23-13
TABLE 1-6 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: CAMP SAN ONOFRE FR.STN DISTANCE: 2.4 MILES X/Q 1.lE-07 SEC/(M**3) D/Q 1. 0E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+03 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+04 4.7E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+06 1.4E+09 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 3.4E+08 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.3E+05 3.8E+08 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.0E+06 2.2E+l0 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+06 2.2E+04 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+06 2.5E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 1.4E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.0E+05 1.1E+08 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+06 2.0E+07 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 9.8E+04 6.8E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+04 1.5E+08 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.5E+04 1.0E+l0 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+06 2.1E+07 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.6E+05 l.4E+07 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.8E+06 7.0E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.2E+07 1.7E+07 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 1E+05 1. 2E+06 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 2.4E+06 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.0E+04 4.5E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.5E+05 2.5E+06 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+05 7.5E+08 PAGEA-20 SO123-ODCM-A Revision 13 11/2018
TABLE 1-6 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: CAMP SAN ONOFRE barr DISTANCE: 2.6 MILES X/Q 9.7E-08 SEC/(M**3) D/Q 8.9E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+03 0.0E+00 l.3E+03 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+04 4.7E+06 l.4E+04 4.7E+06 MN 54 0.0E+00 0.0E+00 0. 0E+o0 0.0E+00 2.0E+06 1.4E+09 l.4E+06 l.4E+09 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 0.0E+o0 0.0E+00 0.0E+00 0.0E+00 8.7E+06 2.2E+l0 6.0E+06 2.2E+l0 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.4E+06 2.2E+04 l.4E+06 2.2E+04 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 2.5E+08 l.8E+06 2.5E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.5E+05 l.4E+08 5.0E+05 l.4E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.8E+05 l.1E+08 5.0E+05 l.1E+08 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 2.0E+07 l.2E+06 2.0E+07 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+04 l.5E+08 l.2E+04 l.5E+08 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 l.0E+l0 7.5E+04 l.0E+l0 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 2.1E+07 l.3E+06 2.1E+07 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.1E+05 l.4E+07 3.6E+05 l.4E+07 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.5E+07 l.7E+07 l.2E+07 l.7E+07 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.5E+05 l.2E+06 l.1E+05 1. 2E+06 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEA-21 SO 123-ODCM-A
/
Revision 13
--- 11/2018
TABLE 1-7 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 3.0 MILES X/Q 7.8E-08 SEC/(M**3) D/Q 6.8E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 2.8E+0l 0.0E+00 2.3E+0l 2.8E+0l 3.9E+0l CR 51 0.0E+00 0.0E+00 0.0E+00 5.0E+04 0.0E+00 l.0E+05 3.2E+02 2.9E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 7.7E+05 0.0E+00 l.4E+06 3.1E+04 3.4E+07 co 57 0.0E+00 0.0E+00 0.0E+00 4.6E+06 0.0E+00 8.0E+06 7.0E+02 2.1E+07 co 58 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 l.9E+07 2.1E+04 4.5E+07 co 60 0.0E+00 0.0E+00 0.0E+00 3.6E+07 0.0E+00 7.2E+07 l.3E+05 6.2E+08 SR 89 0.0E+00 0.0E+00 0.0E+00 4.9E+07 0.0E+00 2.6E+07 3.1E+04 3.1E+07 SR 90 0.0E+00 0.0E+00 0.0E+00 1. 0E+09 0.0E+00 8.0E+08 2.2E+05 1. 2E+09 ZR 95 0.0E+00 0.0E+00 0.0E+00 6.2E+07 0.0E+00 l.1E+08 4.0E+04 2.0E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 2.3E+08 0.0E+00 4.5E+08 l.1E+04 8.2E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 4.2E+08 0.0E+00 7.5E+08 l.1E+04 l.3E+09 TE 129M 0.0E+00 0.0E+00 0.0E+00 5.9E+08 0.0E+00 4.5E+08 2.8E+04 5.3E+08 cs 134 0.0E+00 0.0E+00 0.0E+00 l.4E+08 0.0E+00 l.2E+08 2.2E+03 3.0E+08 cs 136 0.0E+00 0.0E+00 0.0E+00 5.1E+06 0.0E+00 4.2E+06 2.7E+02 8.8E+06 cs 137 0.0E+00 0.0E+00 0.0E+00 1. 2E+08 0.0E+00 9.3E+07 l.7E+03 3.5E+08 BA 140 0.0E+00 0.0E+00 0.0E+00 5.0E+06 0.0E+00 4.2E+06 2.8E+04 7.2E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 1. 5E+06 0.0E+00 2.4E+06 8.1E+03 4.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 l.8E+07 0.0E+00 2.9E+07 l.7E+05 4.8E+07 I 131 0.0E+00 0.0E+00 0.0E+00 6.5E+08 0.0E+00 4.3E+08 2.7E+05 5.9E+08 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+03 2.8E+04 I 133 0.0E+00 0.0E+00 0.0E+00 l.6E+0l 0.0E+00 8.6E+00 4.8E+04 5.5E+04 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.7E+02 l.0E+04 I 135 0.0E+00 0.0E+00 0.0E+00 l.lE-15 0.0E+00 6.3E-16 l.0E+04 5.6E+04 UN-ID* 0.0E+00 0.0E+00 0.0E+00 l.1E+08 0.0E+00 9.4E+07 1. 9E+04 1. 4E+08 PAGEA-22 SO123-ODCM-A Revision 7 09-23-13
TABLE 1-7 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'D' PATHWAY: CAMP SAN ONOFRE barr DISTANCE: 3. 0 MILES X/Q 6.9E-08 SEC/(M**3) D/Q 7.2E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+03 0.0E+00 1.3E+03 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+04 4.7E+06 1.4E+04 4.7E+06
-,MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 1.4E+09 l.4E+06 1.4E+09 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.7E+06 2.2E+10 6.0E+06 2.2E+10 SR 89 0.0E+00 0.0E+00 0.0E+00 0. 0E+o0 2.4E+06 2.2E+04 1.4E+06 2.2E+04 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 2.5E+08 l.8E+06 2.5E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.5E+05 1.4E+08 5.0E+05 1.4E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.8E+05 1.1E+08 5.0E+05 1.1E+08 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 2.0E+07 1.2E+06 2.0E+07 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+04 1.5E+08 1.2E+04 1. 5E+08 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 1. 0E+l0 7.5E+04 1.0E+l0 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 2.1E+07 1.3E+06 2 .1E+07 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.1E+05 1. 4E+07 3.6E+05 1.4E+07 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.5E+07 l.7E+07 l.2E+07 l.7E+07 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 5E+05 1.2E+06 l.1E+05 1. 2E+06 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEA-23 SO123-ODCM-A Revision 13 11/2018
TABLE 1-8 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: .8 MILES X/Q 7.lE-07 SEC/(M**3) D/Q 1.lE-08 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO 2.BE+Ol O.OE+OO 2.3E+Ol 2.8E+Ol 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 3.2E+02 2.9E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 O.OE+OO l.4E+06 3.1E+04 3.4E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 7.0E+02 2.1E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 2.1E+04 4.5E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 1.3E+05 6.2E+08 SR 89 O.OE+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 3.1E+04 3.1E+07 SR 90 O.OE+OO O.OE+OO O.OE+OO 1.0E+09 O.OE+OO 8.0E+08 2.2E+05 1.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO l.1E+08 4.0E+04 2.0E+OB NB 95 O.OE+OO O.OE+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 l.1E+04 8.2E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 l.1E+04 1.3E+09 TE 129M O.OE+OO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 2.8E+04 5.3E+08 cs 134 O.OE+OO 0.0E+OO O.OE+OO 1.4E+08 O.OE+OO 1.2E+08 2.2E+03 3.0E+08 cs 136 0.0E+OO 0.0E+OO 0.0E+OO 5.1E+06 O.OE+OO 4.2E+06 2.7E+02 8.8E+06 cs 137 O.OE+OO O.OE+OO O.OE+OO 1. 2E+08 O.OE+OO 9.3E+07 1.7E+03 3.5E+08 BA 140 O.OE+OO O.OE+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 2.8E+04 7.2E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO 1.5E+06 O.OE+OO 2.4E+06 8.1E+03 4.1E+06 CE 144 0.0E+OO O.OE+OO 0.0E+OO 1.8E+07 O.OE+OO 2.9E+07 1.7E+05 4.8E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 6.5E+08 0.0E+OO 4.3E+08 2.7E+05 5.9E+08 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.6E+03 2.8E+04 I 133 O.OE+OO O.OE+OO O.OE+OO l.6E+Ol O.OE+OO 8.6E+OO 4.8E+04 5.5E+04 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.7E+02 1.0E+04 I 135 O.OE+OO O.OE+OO O.OE+OO l.lE-15 O.OE+OO 6.3E-16 1.0E+04 5.6E+04 UN-ID* O.OE+OO O.OE+OO O.OE+OO l.1E+08 O.OE+OO 9.4E+07 1.9E+04 1.4E+08 PAGEA-24 SO 123-ODCM-A Revision 7 09-23-13
TABLE 1-8 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: CAMP HORNO MOTOR POOL DISTANCE: 4.0 MILES X/Q 7.7E-08 SEC/(M**3) D/Q 7.5E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.6E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.1E+03 l.3E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 3.9E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.0E+03 9.8E+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.6E+05 l.1E+08 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.7E+06 6.1E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 6.2E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.7E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.0E+05 7.2E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+05 3.9E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+05 3.1E+07 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.5E+05 5.6E+06 cs 134 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.8E+04 l.9E+09 cs 136 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 3.4E+03 4.3E+07 cs 137 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 0 .. OE+OO 2.1E+04 2.9E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.6E+05 5.9E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO _ O.OE+OO O.OE+OO O.OE+OO l.OE+05 3.9E+06 CE 144 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 2.0E+07 I 131 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 3.4E+06 4.9E+06 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.3E+04 3.5E+05 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.1E+05 7.0E+05 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.5E+03 l.3E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+05 7.2E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.5E+05 2.1E+08 PAGEA-25 SO123-ODCM-A Revision 9 09/2015
TABLE 1-8 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: CAMP HORNO DISTANCE: 4.1 MILES X/Q 7.5E-08 SEC/(M**3) D/Q 7.2E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+03 0.0E+00 l.3E+03 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+04 4.7E+06 l.4E+04 4.7E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 1.4E+09 l.4E+06 1.4E+09 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.1E+04 3.4E+08 3.1E+04 3.4E+08 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.3E+06 3.8E+08 9.3E+05 3.8E+08 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.7E+06 2.2E+10 6.0E+06 2. 2E+10 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.4E+06 2.2E+04 l.4E+06 2.2E+04 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.6E+07 0.0E+00 9.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 2.5E+08 1.8E+06 2.5E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.5E+05 1.4E+08 5.0E+05 l.4E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.8E+05 l.1E+08 5.0E+05 1.1E+08 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 2.0E+07 l.2E+06 2.0E+07 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.5E+05 6.8E+09 9.8E+04 6.8E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+04 l.5E+08 1. 2E+04 l.5E+08 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 1.0E+l0 7.5E+04 1. 0E+l0 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 2.1E+07 l.3E+06 2.1E+07 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.1E+05 l.4E+07 3.6E+05 1.4E+07 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.5E+07 1.7E+07 l.2E+07 1.7E+07 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.5E+05 1. 2E+06 1.1E+05 1. 2E+06 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+06 2.4E+06 2.2E+06 2.4E+06 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+04 4.5E+05 3.0E+04 4.5E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.2E+05 2.5E+06 4.5E+05 2.5E+06 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEA-26 SO 123-ODCM-A Revision 13 11/2018
TABLE 1-9 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: SO ST. PK./GUARD SHACK DISTANCE: . 8 MILES X/Q 8.lE-07 SEC/(M**3) D/Q 7.0E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.5E+03 8.0E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.4E+05 2.4E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.4E+03 5.9E+07 co 58 0.0E+00 0.0E+00 - 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.6E+05 6.5E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.0E+06 3.7E+09 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.4E+05 3.7E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.6E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.0E+05 4.3E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+04 2.3E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.6E+04 1.9E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 3.4E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.7E+04 1.2E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+03 2.6E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+04 l.8E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+05 3.5E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.2E+04 2.3E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.3E+06 1. 2E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+06 2.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+04 2.1E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.7E+05 4.2E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.1E+03 7.7E+04 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.7E+04 4.3E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.5E+05 1.3E+08 PAGEA-27 SO 123-ODCM-A Revision 13 11/2018
TABLE 1-9 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 1.5 MILES X/Q 3.6E-07 SEC/(M**3) D/Q 2.8E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 2.8E+0l 0.0E+00 2.3E+0l 2.4E+0l 3.9E+0l CR 51 0.0E+00 0.0E+00 0.0E+00 5.0E+04 0.0E+00 l.0E+05 2.8E+02 2.8E+05 MN 54 0.0E+00 0.0E+00 0.0E+00 7.7E+05 0.0E+00 1.4E+06 2.7E+04 2.9E+07 co 57 0.0E+00 0.0E+00 0.0E+00 4.6E+06 0.0E+00 8.0E+06 6.0E+02 2.0E+07 co 58 0.0E+00 0.0E+00 0.0E+00 9.6E+06 0.0E+00 1.9E+07 1.8E+04 4.4E+07 co 60 0.0E+00 0.0E+00 0.0E+00 3.6E+07 0.0E+00 7.2E+07 l.1E+05 5.5E+08 SR 89 0.0E+00 0.0E+00 0.0E+00 4.9E+07 0.0E+00 2.6E+07 2.7E+04 3.1E+07 SR 90 0.0E+00 0.0E+00 0.0E+00 1.0E+09 0.0E+00 8.0E+08 1.8E+05 1. 2E+09 ZR 95 0.0E+00 0.0E+00 0.0E+00 6.2E+07 0.0E+00 1.1E+08 3.4E+04 2.0E+08 NB 95 0.0E+00 0.0E+00 0.0E+00 2.3E+08 0.0E+00 4.5E+08 9.6E+03 8.2E+08 RU 103 0.0E+00 0.0E+00 0.0E+00 4.2E+08 0.0E+00 7.5E+08 9.6E+03 1. 3E+09 TE 129M 0.0E+00 0.0E+00 0.0E+00 5.9E+08 0.0E+00 4.5E+08 2.4E+04 5.3E+08 cs 134 0.0E+00 0.0E+00 0.0E+00 1.4E+08 0.0E+00 1. 2E+08 1.9E+03 2.8E+08 cs 136 0.0E+00 0.0E+00 0.0E+00 5.1E+06 0.0E+00 4.2E+06 2.3E+02 8.3E+06 cs 137 0.0E+00 0.0E+00 0.0E+00 1.2E+08 0 ._0E+00 9.3E+07 1.4E+03 3.1E+08 BA 140 0.0E+00 0.0E+00 0.0E+00 5.0E+06 0.0E+00 4.2E+06 2.4E+04 7.2E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 1.5E+06 0.0E+00 2.4E+06 6.9E+03 4.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 1.8E+07 0.0E+00 2.9E+07 1.5E+05 4.8E+07 I 131 0.0E+00 0.0E+00 0.0E+00 6.5E+08 0.0E+00 4.3E+08 2.3E+05 5.9E+08 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+03 2.4E+04 I 133 0.0E+00 0.0E+00 0.0E+00 1.6E+0l 0.0E+00 8.6E+00 4.1E+04 4.7E+04 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 5.7E+02 8.6E+03 I 135 0.0E+00 0.0E+00 0.0E+00 1.lE-15 0.0E+00 6.3E-16 8.6E+03 4.8E+04 UN-ID* 0.0E+00 0.0E+00 0.0E+00 l.1E+08 0.0E+00 9.4E+07 l.7E+04 1.4E+08 PAGEA-28 SO123-ODCM-A Revision 7 09-23-13
TABLE 1-9 UNITS2&3 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: BORDER PATROL CHECKPT. DISTANCE: 1.9 MILES X/Q 2.6E-07 SEC/(M**3) D/Q 1.9E-09 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+03 1.1E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 3.2E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 -7. 2E+03 7.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 8.7E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.4E+06 4.9E+09 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 4.9E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+05 5.7E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 3.1E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 2.5E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+05 4.5E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+04 l.6E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+03 3.4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.7E+04 2.3E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+05 4.7E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.3E+04 3.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.8E+06 l.6E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 3.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+04 2.8E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.9E+05 5.6E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.8E+03 1.0E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.0E+05 5.BE+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 1. 7E+08 PAGEA-29 S0123-0DCM-A Revision 13 11/2018
TABLE 1-10 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: SAN ONOFRE BCH CAMPGD DISTANCE: 1.8 MILES X/Q 2.3E-07 SEC/(M**3) D/Q 1. 0E-09 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 5.3E+0l 0.0E+00 9.2E+0l 0.0E+00 l.0E+02 0.0E+00 l.0E+02 0. 0E+o0 CR 51 l.1E+03 3.8E+05 l.4E+03 3.8E+05 l.7E+03 3.8E+05 1. 2E+03 3.8E+05 MN 54 8.2E+04 l.1E+08 l.3E+05 l.1E+08 l.6E+05 l.1E+08 1. 2E+05 l.1E+08 co 57 4.0E+02 2.8E+07 l .1E+03 2.8E+07 2.6E+03 2.8E+07 2.6E+03 2.8E+07 co 58 6.4E+04 3.1E+07 9.1E+04 3.1E+07 l.1E+05 3.1E+07 7.6E+04 3.1E+07 co 60 3.7E+05 l.8E+09 5.8E+05 l.8E+09 7.2E+05 l.8E+09 4.9E+05 l.8E+09 SR 89 l.7E+05 l.8E+03 l.8E+05 l.8E+03 2.0E+05 l.8E+03 l.2E+05 l.8E+03 SR 90 9.2E+05 0.0E+00 l.2E+06 0.0E+00 l.4E+06 0.0E+00 7.9E+05 0.0E+00 ZR 95 l.4E+05 2.1E+07 l.8E+05 2.1E+07 2.2E+05 2.1E+07 l.5E+05 2.1E+07 NB 95 3.9E+04 l.1E+07 5.0E+04 l.1E+07 6.2E+04 l.1E+07 4.1E+04 l.1E+07 RU 103 4.5E+04 8.9E+06 5.4E+04 8.9E+06 6.4E+04 8.9E+06 4.1E+04 8.9E+06 TE 129M 1. 4E+05 l.6E+06 l.4E+05 l.6E+06 l.6E+05 l.6E+06 l.0E+05 l.6E+06 cs 134 6.5E+03 5.6E+08 9.9E+03 5.6E+08 l.2E+04 5.6E+08 8.0E+03 5.6E+08 cs 136 9.7E+02 1. 2E+07 l.2E+03 l.2E+07 l.5E+03 l.2E+07 9.9E+02 l.2E+07 cs 137 5.9E+03 8.5E+08 8.5E+03 8.5E+08 9.9E+03 8.5E+08 6.2E+03 8.5E+08 BA 140 l.3E+05 l.7E+06 l.4E+05 l.7E+06 l.7E+05 l.7E+06 l.0E+05 l.7E+06 CE 141 4.2E+04 l.1E+06 4.5E+04 l.1E+06 5.0E+04 l.1E+06 3.0E+04 l.1E+06 CE 144 8.1E+05 5.7E+06 9.8E+05 5.7E+06 l.1E+06 5.7E+06 6.4E+05 5.7E+06 I 131 l.2E+06 1. 4E+06 l.3E+06 l.4E+06 1. 2E+06 l.4E+06 9.8E+05 1. 4E+06 I 132 l.4E+04 1. 0E+05 l.6E+04 l.0E+05 l.2E+04 l.0E+05 9.4E+03 l.0E+05 I 133 2.9E+05 2.0E+05 3.2E+05 2.0E+05 2.4E+05 2.0E+05 l.8E+05 2.0E+05 I 134 3.7E+03 3.7E+04 4.2E+03 3.7E+04 3.2E+03 3.7E+04 2.5E+03 3.7E+04 I 135 5.7E+04 2.1E+05 6.5E+04 2.1E+05 5.1E+04 2.1E+05 3.7E+04 2.1E+05 UN-ID* 5.3E+04 6.1E+07 8.2E+04 6.1E+07 l.0E+05 6.1E+07 7.1E+04 6.1E+07 PAGEA-30 SO123-ODCM-A Revision 7 09-23-13
TABLE 1-10 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: HWY PATROL WEIGH STN DISTANCE: 2.1 MILES X/Q l.BE-07 SEC/(M**3) D/Q 7.5E-10 /M** (2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+02 0.0E+00 CR 51 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.3E+03 l.1E+06 MN 54 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 3.2E+08 co 57 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 7.2E+03 7.8E+07 co 58 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.1E+05 8.7E+07 co 60 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.4E+06 4.9E+09 SR 89 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 3.2E+05 4.9E+03 SR 90 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.2E+06 0.0E+00 ZR 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.0E+05 5.7E+07 NB 95 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1. 2E+05 3.1E+07 RU 103 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.2E+05 2.5E+07 TE 129M 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.8E+05 4.5E+06 cs 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 ~ 2.2E+04 1.6E+09 cs 136 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+03 3.4E+07 cs 137 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.7E+04 2.3E+09 BA 140 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.9E+05 4.7E+06 CE 141 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 8.3E+04 3.1E+06 CE 144 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 1.8E+06 1.6E+07 I 131 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.7E+06 3.9E+06 I 132 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.6E+04 2.8E+05 I 133 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4.9E+05 5.6E+05 I 134 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.8E+03 l.0E+05 I 135 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l.0E+05 5.8E+05 UN-ID* 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 2.0E+05 l.7E+08 PAGE A-31 SO123-ODCM-A Revision 13 11/2018
TABLE 1-10 UNITS 2&3 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: ENDLS SUM SURFCAMP/RES DISTANCE: 2.8 MILES X/Q l.2E-07 SEC/(M**3) D/Q 4.5E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO 4.6E+Ol O.OE+OO 5.2E+Ol O.OE+OO 4.2E+02 *O.OE+OO CR 51 O.OE+OO O.OE+OO 7.0E+02 l.9E+05 8.6E+02 l.9E+05 4.7E+03 l.5E+06 MN 54 O.OE+OO O.OE+OO 6.5E+04 5.7E+07 8.2E+04 5.7E+07 4.6E+05 4.5E+08 co 57 O.OE+OO O.OE+OO 5.4E+02 l.4E+07 1. 3E+03 1. 4E+07 l.OE+04 l.1E+08 co 58 O.OE+OO O.OE+OO 4.5E+04 l.6E+07 5.5E+04 l.6E+07 3.1E+05 l.2E+08 co 60 O.OE+OO O.OE+OO 2.9E+05 8.8E+08 3.6E+05 8.8E+08 2.0E+06 7.1E+09 SR 89 O.OE+OO O.OE+OO 8.9E+04 8.9E+02 9.9E+04 8.9E+02 4.6E+05 7.1E+03 SR 90 O.OE+OO O.OE+OO 6.1E+05 O.OE+OO 6.8E+05 O.OE+OO 3.2E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO 9.2E+04 l.OE+07 l.1E+05 l.OE+07 5.8E+05 8.3E+07 NB 95 O.OE+OO O.OE+OO 2.5E+04 5.6E+06 3.1E+04 5.6E+06 l.7E+05 4.5E+07 RU 103 O.OE+OO O.OE+OO 2.7E+04 4.5E+06 3.2E+04 4.5E+06 l.7E+05 3.6E+07 TE 129M O.OE+OO O.OE+OO 7.2E+04 8.1E+05 8.1E+04 8 .1E+05 4.1E+05 6.5E+06 cs 134 O.OE+OO O.OE+OO 5.0E+03 2.8E+08 6.0E+03 2.8E+08 3.2E+04 2.2E+09 cs 136 O.OE+OO O.OE+OO 6.0E+02 6.2E+06 7.3E+02 6.2E+06 3.9E+03 4.9E+07 cs 137 O.OE+OO 0.0E+OO 4.3E+03 4.2E+08 5.0E+03 4.2E+08 2.5E+04 3.4E+09 BA 140 O.OE+OO 0.0E+OO 7.2E+04 8.4E+05 8.4E+04 8.4E+05 4.2E+05 6.8E+06 CE 141 O.OE+OO 0.0E+OO 2.2E+04 5.6E+05 2.5E+04 5.6E+05 l.2E+05 4.5E+06 CE 144 0.0E+OO O.OE+OO 4.9E+05 2.9E+06 5.5E+05 2.9E+06 2.6E+06 2.3E+07 I 131 O.OE+OO O.OE+OO 6 .*7E+05 7.1E+05 6.0E+05 7.1E+05 3.9E+06 5.7E+06 I 132 O.OE+OO O.OE+OO 8.0E+03 5.1E+04 6.2E+03 5.1E+04 3.8E+04 4 .1E+05 I 133 O.OE+OO O.OE+OO l.6E+05 l.OE+05 l.2E+05 l.OE+05 7.1E+05 8.1E+05 I 134 O.OE+OO O.OE+OO 2.1E+03 l.8E+04 l.6E+03 l.8E+04 9.8E+03 l.5E+05 I 135 O.OE+OO O.OE+OO 3.3E+04 l.OE+05 2.6E+04 l.OE+05 l.5E+05 8.3E+05 UN-ID* O.OE+OO 0.0E+OO 4.1E+04 3.1E+07 5.1E+04 3.1E+07 2.8E+05 2.5E+08 PAGEA-32 SO123-ODCM-A Revision 13 11/2018
TABLE 1-10 UNITS2&3 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: STATE PARK HOST DISTANCE: 2.9 MILES X/Q l.lE-07 SEC/(M**3) D/Q 4.2E-10 /M**(2)
INFANT CHILD TEEN ADULT RADIO- INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND INHALATION FOOD & GROUND NUCLIDE (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR (MREM/YR (M2.MREM/YR PER UCI/M3) PER UCI/SEC) PER UCI/M3) PER UCI/SEC) PER UCI/M~) PER UCI/SEC) PER UCI/M3) PER UCI/SEC)
H 3** O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+03 O.OE+OO CR 51 O.OE+OO 0. OE+O.O O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+04 4.7E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+06 -l. 4E+09 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.1E+04 3.4E+08 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.3E+05 3.8E+08 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.0E+06 2.2E+l0 SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+06 2.2E+04 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.8E+06 2.5E+08 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.0E+05 l.4E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 5.0E+05 l.1E+08 TE 129M O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 0.0E+OO O.OE+OO l.2E+06 2.0E+07 cs 134 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 9.8E+04 6.8E+09 cs 136 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO l.2E+04 l.5E+08 cs 137 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 7.5E+04 l.OE+lO BA 140 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO l.3E+06 2 .1E+07 CE 141 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 3.6E+05 l.4E+07 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.8E+06 7.0E+07 I 131 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO l.2E+07 l.7E+07 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.1E+05 1. 2E+06 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 2.4E+06 I 134 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 3.0E+04 4.5E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.5E+05 2.5E+06 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.6E+05 7.5E+08 PAGEA-33 SO 123-ODCM-A Revision 13 11/2018
Enclosure 8 Offsite Dose Calculation Manual San Onofre Nuclear Generating Station (SONGS)
SO123-ODCM Appendix B Revision 9, August 2016
OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION.(SONGS)
APPENDIXB SUPPLEMENTAL INFORMATION FOR EFFLUENT CONTROLS S0123-0DCM-B Revision 9 08/2016
ODCM APPENDIX B TABLE OF CONTENTS Section
~~Title 1.0 *Gas and Liquid Effluent Concentration Limits for Radiation Monitor . B1-1 thru Setpoin( Calculations B1-5~~
~~1-1 K Yhlp to D. Dick, Memorandum for file "Recommended Effluent~~
. Concentration Limits from 10CFR20 Appendix B, Table 2, for setpoint calculations," dated April 23, 1993 B1-1 1-2 Table of the Gas and liquid.Concentrations Limits for Specific Isotopes B1 -2 2.0 SONGS Effluent Control Limits: -10 CFR 20 Impact - B2-1 thru B2-2 2-1 E.S. Medling to J. Clark and P. Knapp, Memorandum for file "Impact of new 10 CFR 20 upon SONGS Effluent Control Limits, a.datedJune14,1993 . B2-1 3.0 SONGS Radiological Environmental Monitoring Program Bases 83-1 thru r
. . . 83-14 3-1 E;.M. Goldin, Memorandum for File *Radiological Environmental Monitoring Program Bases", dated September 10, 1997.
June 14, 1993 83-1 4.0 Approval of Offsite Dose Galculatlon Manual Changes B4-1 4-1
~~Ross T. Ridenoure to L. L. McCann, Memorandum for File~~
~~0tts1te Dose Gafculation Manual (QDCM) Approval Designee",~~
dated April 27, 2010. B4-1 5.0 Miscellaneous Gaseous Releases B5-1 thru.
B5-18
~1 Memorandum for file , *units 2/3 BuildingNentilatlon l;:nve~pes/Turblne/MSIV Areas", Revision 1, January 13, 2012. B5-1 6.0 Garbon-14 86-1 thru 86-8 6-1 SONGS Garbon-14.Produ'ction, Release and Offsite Dose Calculation Methodolqgy 86:-1 7.0 Offsite Dose Galculatlon Manual Changes B7-1 thru Safety Evaluation for Modifying References to 10 CFR 50.59 B7-4 Bi SO123-ODCM-B Revlsl,o,h ~
08/2016
\
ODCM APPENDIX B TABLE OF CONTENTS Section ~
8.0 Site Boundary Sample Garden Relocation, Activity/Document 88-1 Number/NN 203063159-084 9.0 Eric Golden, "Correlation - Effluents and Environmental Data", 89-1 thru Letter addressed to B. D. Metz, November 4, 2014 89-3 10.0 Remove Controlling Location Factors Tables 2-7 and 2-8 (South Yard Facility and North Industrial Area) and Associated Ri Tables In 810-1 thru Appendix A from the ODCM 810-4 11.0 Radwaste Processing Techniques Airborne Effluent Evaluation Memo, 811-1 thru dated December 20, 1999 811-6 12.0 Airborne Effluent Controls During Decommissioning Memo, dated* 812-1 thru September 27, 2000 812-12 13.0 Airborne Contamination from Decommissioning Activities Memo, dated 813-1 thru December 13, 2013 813-3 BIi S0123-0DCM-B Revision 9 08/2016
TABLE'1*1 UNITS 2 & 3-DOSE PARAMETER R; FOR SECTOR P Aprl1 23, 1993 TO: DARYL DICK, SONGS Effluent Engineering
~~SUBJECT:~~
RECOMMENDED EFFLUENT CONCENTRATION FROM 10CFR20 APPENDIX B; TABLE 2, FOR SETPOINT CALCULATIONS
,Daryl, 1have Indicated on the attached.table which effluent concentration limits (ECLs) are recommended for use. when calculating radiation monitor setpoint values for llqulcl and 'airborne radioactive effluent releases from SONGS. .
-For simplicity's sake, when the .~Ion implements the new 10CFR20, ECLs should be used exclusively: In cases where more than one valu~ Is listed (based on retention) in Appendix B, Table 2, the most conservative value is reco'mmen.c;ted for routine calculations. Under conditions which require more flexlbillty, actµal chemical and phyS:lcal characteristics of the release stream may be considered to allowµ~ of El more representative value. It is recommended that~ of these instances be
documente:d. Since no ECLs are provided In* Colur:nn 2 for dissolved and entrained gases In llqulds, per NUREG 1301, *Offsite Dose Calcu~ manual Guidance:_ Standard Radiological Effluent Controls for Pressurized Water Reactors*, Specification 3.11.1.1, a value of 2E-4 uCi/ml should be llsed.
If there are any qu~ns, please call me at 50512.
Kathleen Yhip HPE Engineer cc: HPE Flies 81-1 SO123-0DCM-B Revision 1-02-29-08
TABLE 1-1 UNITS 2 & 3 DOSE PARAMETER R; FOR SECTOR P GAS AND LIQUID EFFLUENT CONCE!'fTRATION LIMIT (ECQ VALUES ISOTOPE GAS ECL GAS MPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) (ECL) (MPC)
~~1 H-3 . 1E-7 2E-7 H-3 1E-3 3E-3 2 .Na-24 7E-9 5E-9 Na-24 SE-5 3t-5.~~
~~-.3 Ar-41 .1E-8 4E-8 Ar-41~~
~~2E-4 4 Sc-46 3E-10 BE-10 So-46 1E-5 4E-5 6E-8d 5 Cr-51 BE-8 Cr-51 SE-4 2E-3 3E-8 w, a~~
6. Mn--54 1E-9 1E-9 Mn-54 3E-5 1E-4 2E-8 d 7 Mn-56 2E-8 Mn-56 . 7E-5 1E-4 3E-8w 3E-9 d 8 F:e--55 3E-8 Fe-55 1E-4
~~BE-4 6E-9w 5E-10 d 9 Fe-59 .. 2E-9 Fe-59. 1E-5 SE-5~~
~~. 7E-10 w 4E-9w 10 Co-57 6E-9 Co-57 6E-5 4E-4 9E-10 a~~
~~2E-9w 11 Co-58 2E-9~~
~~Co-58 2E-5 9E-5~~
- 1E-9 a 2E-1o*w 12 Co-60 3E-10 -Co-60 3E-6 3E-5 SE-11 a
'4E-8 d 13 Cu-64. . 4E-8 Cu-64 2E-4 2E-4 3E-8w a 14 . .zn-:65 4E-10 2E-9 Zn-65 SE-6 1E-4 6E-9 d 15 Br-82 6E-9 Br-82 4E-5 4E-5 5E-9w 8E-8 d 16 Br-84 3E-8 Br-84 4E-4 2E-4 9E-8w 17 Kr-85. 7E-7 3E-7 Kr-85 .. 2E-4 18 Kr-85m 1E-7 1E-7 Kr-85m 2E-4 19 Kr-87 2E-8 2E-8 Nr-87 2E-4 20 Kr-as 9E-8 2E-8 Kr-88 2E-4
~~21 Rb-88~~
~~9E-8 2E-4 Rl:r88 4E-4 *. 2E-4~~
. ~ ..
81-2 SO123-0DCM-B Revision 1 02-29-08
, V
GAS AN~ LIQUID EFFLUENT CONCENTRATION LIMIT (EC~ VALUES ISOTOPE GAS ECL GASMPC ISOTOPE LIQUID ECL LIQUID MPG (EGL) (MPC) (EOL) (MPG_) *
~~22 RIHl9 2E-7 2E-4 Rb-89 9E-4 2E-4 1E-9 d 23 Sr-89 3E-10 Sr-89 BE-6 3E:..S~~
~~2E-10 a~~
24 3E-11 d Sr-90 3E-11 Sr-90 SE-7 . 3E-7 6E-12 a 8E-9d 25 Sr-91 9E-9 Sr-91 2E-5 5E-5 5E-9a 1.E-8 d 26 Sr-92 1E-8 Sr-92 4E-5 6E-5 9E-8 a 27 Y-90 9E10 3E-9 Y-90 7E-6 2E-5 3E-7w
~~.28 Y-91m 6E-7 Y-91m 2E-3 3E-3~~
2E-7 a 29 Y-92 1E-8. 1E-8 Y-92 . 4E-5 6E-5 4E-10 d, a .J 30 Zr-95 1E-9 Zr-95 2E-:-5 6E-5 5E-10w 3E-9_d 31 zr.:.e1 3E-9 Zr-97 9E-6 , 2E-5 2E-9w, a 32 .. Nb--95 2E-9 3E-9 Nb--95 *3E.:.5 1E-4 4E-9w 33 Nb--95m 1E-10 Nb--95m* 3E-5 3E-6 3E-9 a 34 Nb--97 1E-7 2E-7 Nb--97 3E-4 9E-4
. 35 4E-9 d Mo-99 7E-9 Mo-99 2E-5 4E-5 2E-9 a 35*
~~Tc-99m 2E-7d 5E-7 Tc-99m *1,E-3* 3E-3 3E-7w~~
~~. 2E-9 d 37 Ru-103 1E-9w 3E-9* Ru-103 3E-5 BE-5 9E-10 a 1E-10 d~~
~~aa Ru-106 . Be-11 w 2E-10 Ru-106 3E-6 1E-5~~
~~2E-11 a 2E-10 d 39 Ag-110m 3E-10w 3E-10 Ag-110m 6E.:S 3E-5~~
.1E-10 a 2E-9 d.
40 Sn-113 BE-10 w 2E-9 Sn-113 3E-5. 9E-5 B1-3 SO123-0DCM-B Revision 1 02-29-08
GA~ AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECI) VALUES
.ISOTOPE. GAS ECL GASMPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) *(ECL) (MPC) 3E-9d
-41 Sn-117m -1E-10 Sn-117m 3E-5 3E-6
-2E-9 w 3E-9d 42 Sb-122
~~5E-9~~
~~Sb-122 1E-5 3E-5~~
- . 2E-9w 1E-9 d 43 Sb-124 7E-10 Sb-124 7E-6 2E-5 3E-10w 3E-9d 44 Sb-125 9E-10 Sb-125 3E-5 1E-4 7E-10 w 45 Xe-131m 2E-6 4E-7. Xe-131m 2E-4 46 Xe-133 '5E-7 3E-7 Xe-133 . 2E-4. --
47 Xe-133m 6E-7 3E-7 Xe-133m 2E-4 48 Xe-135 7E-8 1E-7 Xe135* 2E-4 49 ~135m 4E-8 3E-8 Xe-135m 2E-4 50 Xe-138 2E-8 3E-8 Xe138 . 2E-4 9E-10 d 51 T~129m 1E-9 Te-129m 7E 2E-5 3E-10w
-- - . 1E-9-d 52 Te-132 4E-9 Te-132 9E-6
~~2E-5~~
.9E-10 53 1-131 2E:*10 1E-10 1-131 1E-6 3E-7 54 1-132 2E-8 3E-9 1-132 1E4 8E-6 55 1-133 1E-9 4E-10 1-133 7E-6, 1E-6 56 1-134 6E 6E-9 1-134 . 4E-4
~~2E-5 57 1-135 6E-9 1E-9 1-135 3E-5 4E-6 --~~
58 *Cs-134 2E-10 4E-10 Cs-134 9E-7 9E-6 59 Cs-136 9E-10 6E.:.9 Cs-136 6E-6 6E-5 60 Cs-137 2E-10 5E-10 Cs-137 1E-6 2E-5 61 Cs-138 8E-8 3E-8 Cs-138 4E-4 2E-4 62 Ba-139 4E-8 3E-8 Ba-139 2E-4 2E-4 63 -Ba-140 2E-9 1E-9 Ba-140- BE-6 2E-5 64 La-140 2E-9 4E-9
~~La-140 . 9E-6 2E-5 1E-9w 65 Ce-141 5E-9 Ce-141 3E-5 9E-5 BE-10 a B1-4 SO123-0DCM-B Revision 1 02-29-08~~
GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECI) VALUES ISOTOPE GAS ECL GAS MPG ISOTOPE LIQUID EGL LIQUID MPC (EGL) (MPG) (EGL) (MPG) 3E-9w 66 Ce-143 7E-9 Ce-143 2E-5 4E-5 2E-9a 4E-11 w 67 Ge-144 2E-10 Ce-144 3E-6 1E-5 2E-11 a 68 Nd-147 1E-9 8E-9 Nd-147 2E-5 6E-5 69 W-187 -1E-8 1E W-187 3E-5 6E-5 70 Np-239 3E-9 2E-8 Np-239 2E-5 1E--4 71 ALPHA 1E-15 2E-14 ALPHA 2E-9 3E-8 B1-5 SO123-0DGM-B Revision 1 02-29-08
June 14, 1993'
- .J. CLARK P. KNAPP-*
~~SUBJECT:~~
Impact of new 10 CFR *20 upon SONGS Effluent Control Limits INTRODUCTION The New 10 CFR 20 is mandated to be lmpleniented by all licensees by January 1, 1994. Unit 1 *
~~Technical Specification (TS) 6.B.4.f. (2) AND (7) and Units 2 and 3 TS 6.8.4.e. (2) and (7)~~
require programs which set limits on concentrations of liquid and gaseous releases from the site according to 10 CFR 20 Appendix B, Table II. Questions have been asked of licensing **
- ~rdlng the-effect of the new regulation upon SONGS-Effluent Control 'Limits, and if it is
. necessary to revise the TS prior to implementation of the new rule.
EXECUTIVE
~~SUMMARY~~
Licensing has reviewed the applicable TS and the new 10 CFR 20. As a result of the above, Licensing has concludecHhat SCE Is not required to obtain amendments to the TS as a result of Implementation of the revised Part 20. The new Part 20 permits the existing TS cited above to be amended at Bl1Y, time SCE *deems appropriate. * -
The aboye concfuslon Is In .agre,ernent with the ~ presented to NRC .Staff by NU.MARC during a _meeting earlier this month. Preliminary cominents from the NRC staff Indicate their concurrence. The NRC Is expected to issue me~ng minutes by mid-June, showing their concurrence.
~~LICENSING ISSUE Revised Part 20 [20.'1008) (b)] generally ~ulres that the license condition and TS references to the old*Part 20,* sect1ons-29.1-20.601 should~ considered to have been replaced by~~
~~compara_ble references to the new Part 20, Sections 20.1001-20.2401-. The revised Part 20~~
[20.1008(c)] requires-that any TS that is mpre restrictive than a requirement in t~ revised Part 20 remains in force until there Is a TS charnJe through a fii;:er!se amendment The limit:on annually averaged radioactivity concentrations In effluents t6 unrestricted areas, wtlich is a requirement in the old Part 20 (20.106), has been changed tci an optional method (20.1302(b)(2)(Q] of .demonstrating *compl~nce with the annual dose limit specified in 20.1301 and is no longer ITSELF a requirement in the revised Part 20.
&ONGS TS require that effluent concentrations be maintained below the indicated level at all times. "At all times" is reasonably accepted as meaning that averaging beyond Instrument
~~response*times is not pem1itt~. The revised Part 20 contains NO comparable *at all times" concentration limit.~~
B2-1 SO123-0DCM-B .
Revision 1.
02-29-08
The SONGS TS, by not permtttlng any arbitrary ~eraging period, are therefore MORE
~ESTRICTNE than the revrsed part 20 limits.
Accordingly, since the SONGS TS are*more restrictive than the revised Part'20, the provision of 20: 1O()B(c) applies, with the res1,1lt that the TS re~!ris in effect, as Is, until It Is revised, or the license is renewed. ~h this conclusion, SONGS may exercise _any of the following options:
1. NOT request any TS changes, with the result that SONGS must still establish setpolnts in accordance with 1o* CFR 20, Appendix B, Table II. *
2. Request an amendment to section 6.8.4 changing the reference to the "revised" Pert 20, Appendix B, Table 2. * * * *
~~3. Request ~n amendment to the Tech Specs of units 213, and NOT of 1, *or vice versa.~~
~~4. Upqn approval by the NRC, Implement any of the above.Tech Spec changes~~
_ Irrespective of the Implementation date of the revised 10 CFR 20.
_This memo does not intend to say that any requirements of 10 CFR 20 and 40 CFR 190 are
~~invalid, Including those limits pertaining to dose to members of the public, and applicable survey methods to confirm conformance with those limits.~~
~~E. S. MEDLING~~
~~. cc: W. Marsh D.Dick S. Hetterick~~
~~P. Chang~~
- L. Bray NLFS CDM 82-2 $0123-0DCM-B Revision 1 02-29-08
MEMORANDUM FOR FILE .
September 10, 1997
~~SUBJECT:~~
~~Radiological Environmental Monttorlng Program Bases~~
~~REFERENCES:~~
~~1. Letter fro1_11 Jack-8. Moore, SCE to US Atomic Energy Commission, Proposed Environmental Technical Specifications, February 21, 1974. -~~
2. Memorandum from E. s: Medling to D. F. Pit~, Environmental Air Sampler Placement, October 28, 1983. - * ** * *
~~3. Memorandum from M. Goeders to E. S. Medling, Air Sampler Location Determination, August*22, 1988. -~~
~~4. Memorandum from R. M. Rosenblum to H. W. Newton, Reassessment of the REMP L~ons, October 28, 1992. - --~~
~~5. Memorandum from M. Goeders to E. M. Goldin, Bases for Selection of REMP Sample Locations, Febru~ry 28, 1994.~~
~~6. Upd~ed Flnal Safety Analysis Report, San Onofre Nuclear Generating Station Units 213.-~~
~~Page 2.3t-f-1 (Appendix 2.3H). . .- - .~~
~~7. UFSAR/UFHA Change Request No. SAR23-581. Add 1979-1983 meteorological data to the UFSAR. .~~
~~8. Letter from K. P. Baskin, see to_ us* Nuclear Regulatory Commission, February 26, 1982.~~
~~9. Flnal Environmental Statement, San Onofre Nuclear Generating Station Units 2 and 3,~~
~~. NUREG-0490, US ,Nuclear Regu~ry Commission, 1981. .~~
10. Flnal Environmental Statement, San Onofre Nuclear Generating Station Unit 1, US Atomic Energy Commission, 1973. **
11. Environmental Report - Operating u*cense Stage, San Onofre Nuclear Generati~g Station, Sections 6.1 and 6.2. *
~~83-1 SO123-0DCM-B Revision 2 02-27-09~~
\
REMP Samples September 1o, 1997
~~12. Letter from H. L Ottoson, SCE to Joseph 0. Ward, Califomla Department of Health, Proposed Radiological 'Environmental Monitoring Program, May 19, 1976.~~
~~13. Letter from Edgar D. Bailey, California Department of Health Services to Eric M: Goldin, SCE, Environmental Radiation Monitoring, February 10, 1993.~~
~~14.*Memo*randum from M. Goeders to E. M. Goldin, Modification of SONGS Radiological~~
'Environmental Monitoring (REM) Sample Analysis Program, November 25, 1992. *
~~' ' T 'I~~
15. Memorandum from E. M. Goldin to M. J. Johnson, Deletion of Unnecessary REMP Sample Analyses, January 8, 1996. *
. INTRODUCTION ...
The Offslte_ Dose Calculation Manuals (ODCM) *contain Radiological Effluent Technical Specifications (RETS)*that require monitoring the environs of the power plant. The RETS are based on standards published by the US Nuclear Regulatory Commission (NRC) In Regulatory Guide 4.8; Regulatory Guide 1.109, NURE~800; NUREG-0133, NUREG-0472, and NUREG-1301. Between the time of publication of the first RETS (Reg Gulde *t°B In 1975) and the latest version (NUREG-1301 in 1991) a number of changes took place in the precise wording for the Radiological Environmental Monitoring Program (REMP). Concurrent with thOS& changes, San Onofre Nuclear*Generating Station incorporated RETS first In the Technical Specifications and later, upon implementation. of. Generic Letter 89-01, In the ODCMs. This memorandum reviews the--REMP as It exits and either cites references or provides the logic behind the construction of
- .the program. The majority of the original RETS for Unit 1 was proposed In a letter to the Atomic
'Energy Commission (Reference 1) in which the REMP sampling and analysis *program was detailed.. . .
. 'vVhile the portion of the Unit 1 and Units *213 ODCMs dealing with REMP are not precisely Identical In verbiage, the REMP sa*mple requirements are the same. Sample locations, collection frequency and analyses are Identified In a table In each ODCM. The table is divided Into fo*ur sections for the pathways that could permJt human exposure to radlonuclides. Each section below describes the basis for the sample locations and/or provides appropriate references. A brief note foUows each sample type with a description In general terms of differences between the San Onofre program and the standard program in regulatory guidance documents.
83-2 SO123-ODCM-B Revision 2 02-27--09
REMP Samples .. September 10, 1997 .
AIRBORNE: Fi~e samples.
Indicator Locations:
ODCM Requirement: Three samples from offsite locations (in different sectors) of the highest calculated annual average ground* level D/Q.
~~See Reference 2 for an earfy documented basis for air sampler placement for Units 2/3.~~
Reference 3 contains an evaluation of Units 2/3 air sampler locations based on the
_revi~ 1979-1983 ry,eteorological database. * * *
~~References 4 and 5 contains a more *detalled evaluation of air sampler location using the.~~
~~five year average meteorological database (1979 through 1983 inclusive). Units 2/3~~
~~requires air.samplers in Sectors E, F, and a. Note that these sectors are the #2, #3, and~~
4 ranked deposition coefficients (D/Q) calculated for the Exclusion Area Boundary (EAB). The corresponding air samplers are numbers* 13, 9, and 12. The highest ranked D/Q 1s*offshore In the SSW direction (sector K), a location that cannot be sampled and does not represent a pathway for human exposure. *
The three landward sectors with the highest D/Q values for Unit 1 ere a, R and A using the five year average meteorological database (1979 through 1983 inclusive). Note again 'that the highest D/Q Is found in the offshore sector K In the SSW direction.
~~Because the Unit 1*release point Is offset.from the center of the Exclusion Area Boundary (EAB), the Uri It 1 sectors *oo not completely match the sectors for Units 2/3.~~
Therefore, the air sampler for sector Q is air sampler #12, for sector R also #12 (on the a
border between and R), and A is air sampler #11.
Air sampler #12 appears to have been 'intended to satisfy both Units 2/3 and* Unit 1 requirements. Wth regard 'to Unit 1, air sampler #t2 Is located very close to the boundary of two sectors that each 'require sampling. However, to ensure complete ODCM compliance, a new air sampler was instaRed In sector R *1n 1997, air sampler #14.
-Local Convnunlty:_
ODCM Requirement: o*ne sample from the vicinity of a community having the highest calculated annual average ground level D/Q.
, I
~~Air sampier #1 *in the City of San Clemente satisfies this requirement. It Is located in sector Q for both Unit 1. and Units 2/3. Reference 4 Identified Sector~~
~~B3-3 SO123-0DCM-B Revision 2 02-27-09~~
REMP Samples September 10, 1997 a as having the highest landward D/Q for Unit 1 (Sector K, offshore has the highest D/Q). For Units 2/3, Sector a has the third highest D/Q. The highest is Sector K (offshore), the second highest D/Q Is Sector E. Since Sector E has no community within ten miles, the air sampler location In Sector Q In the Northwest direction Is appropriate.
Since deposition, D/Q, decreases with Increasing distance, a Distant community In Sector E will have a D/Q value considerably lower than the closer community In Sector Q. Reference 3 provided early documentation that air sampler #1 met this particular ODCM requirement. . .
Control Locations:
ODCM Requir:ement: One sample from a control location 15-30 km (10-20 miles) distant and In the least prevalent wind direction*. The footnote (*) reads: The purpose of this sample Is to obtain background Information. If It is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provk:te valid background data may be substituted.
At the time the Unit 1 REMP was being developed, regulatory guidance did not specify air sampler locations according to the ODCM.wording above. In Reference 1, proposed RETS included a control air sampler location In Huntington Beach. The Huntington Beach Generating Station Is an SCE facility I providing an easy and secure location and access. Therefore, during the subsequent licensing of Units 2/3, the* draft RETS that were part of the Units 2/3 license application Included Identification of Huntington Beach as the location for the control air sampler. The meteorological database used was a 1973-1976 three year average in which Sector P had the lowest wind prevalence for landward sectors. Therefore, although Huntington Beach was somewhat farther than the precise ODCM wording, it was an appropriate location for a control because it compiled with the logic described in the footnote and because It provided continuity in data (the existing Unft 1 program).
Upon adoption of the 1979 through 1983 five year average meteorological database, Huntington Beach remained the control location for the same reasons just stated:
continuity In data and sufficient distance to provide appropriate control data*. The newer meteorological. database, however, indicated _that Sector Q was now the fifth least prevalent wind direction. Higher Sectors Included (In order of.decreasing wind prevalence) M (offshore), N (offshore), H (offshore), P (mostly offshore), L (offshore), G (southeast), J (offshore), 8-(north northeast), C (northeast), A (north), and finally Sector a (northwest). Note that Sectors A, B and C are landward sectors on Marine Corps Base camp Pendleton. These Sectors, at a considerably higher elevation when sufficiently distant, would not be representative of the coastal location. Therefore, upon 83-4 S0123-0DCM-B Revision 2 02-27-09
REMP Samples September 10, 1997 B,
' elimination of the offshore Sectors and the .landward Sectors C, and A, ttie two primary Sectors remaining are G and Q; To meet the ODCM requirement without regard for the footnote guidance, Sector G would appear to be preferable over a. However, again noting the footnote ,
guidance, the continuity of data, and the sufficiently distant location, Sector Q adequately meets the, ODCM requirement Flnally, due to the Imminent sale of the Huntington Beach Generating Station, the control air sample wnt being, relocated to Sector G (denoted as Air Sampler #14). ,
Since Unit 1 and Units 213 have the same meteorological database (even though the EAB D/Q
'and X/Q values differ), the logic above-applies to Unit 1 as well. References 3, 4 and 5 have all documented the REMP air sampler locations. * .
The following table presents the frequency of wind direction for both *the 1973-1976 and 1979-1983 databases, *sectors with an asterisk(*) are offshore. :
RANKED. BY PERCENT FREQUENCY Data from Reference 6 Dates: 1/25/"13-1124176 Sectors VVind From Percent Freciuency From To E 1.6 E N* ...
ESE 2.2 F p ..
ENE 2.9 D M*
NNW 3.2 R* H*
N. 3.4 A J*
SE 4.9 G a SW 5.3 L* C SSW 6.1 * 'K* B NW 6.1 Q G WSW 6.4 M* ) D s 6.5
~~J* A SSE .' 7 .. H* R w .'~~
8.6 N* E
'Nt(IN 10.8 p F* .,
NNE 10.9 B K*
NE 14 C . L*.
Total *99.9 83-5 SO123-ODCM-B Revision 2 02-27-09 r
REMP Samples _September 1O, 1997 RANKED BY PERCENT FREQUENCY Data from Reference 7 Dates: 1/1fl9-12131/83 Sectors
\Nlnd From Percent Frequency From To ENE 1.5 D M*
E 1.7
E N*
NNW 2 R H*
ESE 2.4 F p NE 3.1 C L*
NW 3.7 Q G N 4.6 A J*
SSW 5.6 K* B SW 5.8 L* C s 6.1 J* A SE 6.9 G Q SSE 7 H*. R
\MJW 7.3 p -F WSW 7.5 M* D w 11.1 N* E NNE 23.7 B K*
Total 100 The ODCM requirements for airborne samples are consistent with the standard requirements in .
NUREG-0472 and NUREG-1301. Some variations in the wording exists, but the overall airborne sar:npfing and analysis program is very close to that in the guidance documents.
DIRECT RADIATION: Thirty locations, Inner Ring:
ODCM Requirement: An Inner ring of stations In the general area of the site boundary.
References 4 and 5 documented the location of thermolumln8898nt dosimeters (TLD) in an Inner ring around both Unit 1 and Units 2/3. Note that In order to accommodate one TLD In each sector for both Unit 1 and Units 2/3, some TLDs 83-6 SO123-ODCM-B Revision 2 02-27-09
REMP Samples September 1o, 1997 identified in given sectors for Units 2tJ are in different sectors for Unit 1. Due to presence of the Interstate Freeway and other obstacles, some TLDs are only located in the general vicinity of' the EAB, as permitted by the ODCM. The tables below reproduce the data from Reference 4, as updated by a Global Positioning System for more prectse distances. Note also that Reference 4 identified the fact that some sectors are over the ocean and cannot be monitored by TLD. Therefore, the sectors that are monitored are only those on land. **
UNIT 1 INNER RING Direction from Distance Site (sector) (miles)
TLD Number Location WNW(P) 0.39 *
~~10 PIC#1 NW(Q) .. . 1.22 a Beach Club NNW(R)~~
0.30 67 PIC#2 N (A) 0.54 40 PIC#3 NNE (B) 0.63' 61 PIC#4 NE (C) ... 0.66 62 PIC#S ENE (D). 0.72 63 PIC#6 E (E) 0.76 64 PIC#7 ESE (F) 0.86 66 PIC#9 SE(G) 1.28 46 State Beach UNITS 2/3 INNER RING Direction from Distance*
~~Site (sector) TLD Number Location~~
~~(miles)~~
~~WNW(P) 0.675 10 PIC#1 NW(Q) 0.55 67 PIC#2 NNW(R)~~
0.72 40* PIC#3 N (A) 0.70 61 PIC'#4 NNE (B) . 0.65 62 PIC#5 NE (C) 0.58 ' 63 PIC #6 ENE (D)
~~0.54 64 PIC#7 E (E) . 0.70 65 PIC#8~~
ESE(F) 0.58 66 .PIC#9 SE (G) 1.0 .. '46 State Beach 83-7 SO123-0DCM-B Revision 2 02-27-09
REMP Samples September 10, 1997 Outer Ring:
ODCM Requirement: An outer rlng*in the four to five mile range from the Site with *a station in each sector of ~-ring.
References 4 and 5 documented the location of thennolumlnescent doslmeters*(TLD) in an outer ring around both Unit 1 and Units 213. As with the inner ring, In order to accommodate one TLD in each sector for both Unit -1 and Units 2/3, some TLDs identified in given sectors for *units 213 are Indifferent sectors for Unit 1. Due to presence
. of the Interstate Freeway and other obstacles, some TLDs are located in a general *
~~range of four to five miles, as permitted by the ODCM. The tables below reproduce the data from Reference 4.~~
UNIT 1 OUTER RING Direction from Distance TLD Number Location Site (sector) (mlles)
\/1/NW{P) . 2.42 22 San Mateo Point NW(Q) 5.33 1 San Clemente NNW(R) 4.76 19 San Clemente Highlands N (A) 3.38 2 Camp .San Mateo NNE (B) 4.66 35 Ranae 312 NE (C) 4.32 36 Ranae208C ENE (D) 4.48 68 Range210C
~~e CE) 4.73 4 Camp Homo ESE (F)~~
~~3.28 6 Old Route 101 SE(G)~~
~~3.58 38 state Beach UNITS 2/3 OUTER RING Dir.action Distance TLD Number Location (sector) (miles)~~
~(P) 2.7 22 San Mateo Point NW(Q) 5.6 1 San Clemente NNWCR) 5.0 19 San Clemente Hiahlands N (A) 5.7 33 CampTaleaa NNE (B) 4.7 35 , Range 312 NE(C) 4.2 36 Ranae208C ENE (D) . *4_3 68 Ranae 21oc*
E (El 4.5 4 Camp Homo ESE(F) 3.0 6 Old Route 101 SE (G) 3.3 38 State Beach 83-8 , SO123-0DCM-B Revision 2 .
02-27-09
REMP Samples September 10,.1997 Balance:
ODCM Requirement: The balance of the stations are In areas of specific Interest such* as population centers,* nearby residences, schools, and two or three areas to serve as controls.
The remaining TLDs are located in other regions of interest (Marine Corps Camps),
schools (San Onofre School), a hospital In San Clemente, *several Jocattons close to the plant, and several locations sufficiently distant to provide adequate controls. References .
4 and 5 identified the logic for selecting those station~:
The direct* radiation program ls close to that in NURE&o472 and NUREG-1301. The major difference Is that the San Onofre program has fewer TLDs placed around the plant due to the seaward sectors. The ocean, and consequent lack of pathway for direct radiation measurement, limits the number of TLD locations. * *
/l B3-9 S0123-0DCM-B Revision 2 02-27-09
'. \
REMP Samples .: September 1o, 1997 WATERBORNE: Four categories.
Ocean REMP Requirement: Four Locations There are four ocean water sample locations, one at each Uhit outfall and one control in the Newport Beach area. Note that these locat~s were based on the prpgram originally proposed* 111 Reference 1. The "indicator" location~ should be near the respective outfalls but outside of the turbul~t discharge area. The pathway for exposure, as discussed In Reference 1, Is from.swimming and a small amount of ing~on of seawater.
. Drinking ~ r 'r
~~REMP Req~irement Two Locations Reference 8 'noted that there Is r19 reliable surface water in the vicinity of San Onofre.~~
Moreover, there Is no drinking water pathway for the area near ~n Onofre (Reference 9, pages 2-3, 2-4). Nevertheless, in accordance \Ylth Reference 8, samples are taken from.nearby wells to rhonitor ground water.. There are two locations sampled for drinking .\Y!)ter. Until recently, two "indicator" locations were sampled to*r drinking
_. water and a third sample was taken from the Huntington Beaqh ~ as a control. In
1997, the best "drinking water" location was Identified as local wells about 2.4 miles from San Onofre on Gamp Pendleton. As discussed In Reference 9, the flow'of groundwater is toward the ocean such that.It Is not likely that any discharges. from San Onofre, should
that ~ r occur, could contaminate groundwater. *
Sediment from Shoreline REMP Requirement: Four Locations Three samples* are taken In the vicinity of San Onofre with a fourth sample 'ta.ken at an appropriate control location (Newport Beach). The Indicator locations are sllghtfy upcoast
~~(~.2 mnes from Units 2/3 midpoint at the_ San Onofre Surf Beach), downcoast~~
~~(-0.8 miles from the midpoint at the San Onofre State Beach) and farther downcoast .~~
(-3.5 miles from the midpoint also on the State Beach). Because the predominant ocean current is downcoast (Reference 1~. page 2-3), indicator samples are preferentlany taken downcoast. The control ls therefore appropriately taken* upcoast at a sufficient distance (Newport Beach at 83'.-10 SO123-0DCM-B
)
Revision 2 02-27-09
REMP Samples *. September 1O, 1997
~29 miles). Reference 1 pointed out that this sample is Intended to detect any human exposure by direct radiation (from sunbathing).
Ocean Bottom Sediments
.REMP Requirement: Five Locations Ocea{l bottom sediments are .collected at four Indicator locations and one COfltrol location. Two indicator locations are near the Unit 1 outfall and one each at Unit 2 and Unit 3 outfaDs. The control location Is at Laguna Beach wfJlch Is about 18 mi~ upcoast a.nd sufficiently distant to be unaffected by plant operation: Reference 1 noted that ocean bottom sediment could contrlbute*to human exposure through marlne'plants and animals..
In addition to the ODCM required samples, ocean water and oce~n bottom sediment samples have been taken *near the shore at the Units 2/3 discharge structure. The purpose was to monitor any potential accumulation of radioactivity due to the ~nee of a ~ in the discharge conduit. This defect allows some very Jlmited discharge clqser .to shore than the designed discharge locations. After accumulation of sufficient negative 'data, this optional.
sampling program may be discontinued.
As.cfrscusseci'abo\/8, due to the location of San Onofre on the coast, th~ waterborne pathways differ.from .a typical land bound plant. Consequently the REMP samples required by the ODCMs for these ~ia differ from the standard programs described*in NUREG-0472 and NUREG-1301. . .
INGE~TION: Two categories*
Nonmigratory Marine Animals REMP R~uirement Three locations Nonmig~ry marine animals are collected at two indicator locations and one control l o ~ . The Indicator locations are at the Unit 1 outfall and the vicinity of the Units 2 ahd 3 outfalls. n,e control location Is at Laguna Beach, which Is about 18 mlles upcoast and sufflcfentfy distant to be unaffected by plant operation. Nonmigratory marine animals provide a potential pathway for human exposure thr9ugh Ingestion.
The types of animals collected are specified.In the ODCMs (Fish, Crustacea, and Mollusks) and depend on the species available. Reference 1 noted thaf the samples may be taken within 2 mllet;1 of the discharge outfall:Thls flexibility is 83-11 SO123-ODCM-B Revision 2 02-27--09
REMP Samples September .10, 1997 important to ensure the ability to find the appropriate samples during the defined sampling period. * * * * **
Local Crops
REMP Requirement-Two-locations Representative vegetables, normally one*leafy and one fleshy are collected at tia'rvest time at two locations. The locations are one Indicator and one control. The control has typically been a truck farm in the Oceanside area, over 20 mites distant In the downcoast dJrectlon. The indicator location has usually been the San aeinente Ranch at 2.6 miles in the northwest direction. These Indicator and control locations were spedfled in the original program in Reference 1: Because of the required ODCM analysis for the highest radiation exposure contribution, samples may also* be taken from the* Cotton Point Estates gardens, residential gardens at 2.8 miles in the west no~est dlrectl~n,
~~The lack of milk cows In the area around San Onofre and the limitations in vegetable crops cause the ODCM requirements to differ from the standard programs in NUREG-0472 and NUREG-~301.~~
ADDITIONAL SAMPLES The program has historically collected two types *of samples that are not required by the ODCMs. These are kelp samples and soil samples.' Kelp samples were originally specified In Reference 1 and have been collected for many years because of the commercially harvested kelp bed near San Onofre. Kelp is used In many consumer products. Should any accumulation of radioactivity in kelp occur, it would be lmportanf to monitor and assess potential exposure to the public. . . . - . .
Soil samples *have also .been hlstorlcally taken In the vicinity of SONGS. The purpose Is to evaluate whether there *might be any accumulation of radioactivity In the soft around the plant.
There are four indicator locations and one control.
The original program as described In Reference 1 also Included jackrabbit samples. The animals' thyroids were evaluated for the presence *of lodine-131 and femurs were evaluated tor Strontlum-89 and Strontfum-90. This sampling medium and associated analysis was eliminated.
The original.REMP was described in the Unit 1 Final Environmental Statement (Reference 10) ..
The Units 2/3 program was described In the Environmental Report, Operating License Stage o~
ER-OLS (Reference 11 ). The ER-OLS described the early
~~83-13 SO123-0DCM-B Revision-2 02-27-09~~
REMP 8amples . September 10, 1997 sampling for soil and kelp that are no longer required by the ODCMs or by regulatory guidance, and other sample types no longer collected (such as jackrabbits). Much of the present program was built upon the earty *programs for the sake of continuity. Moreover, the older program at Unit 1 was used as the preoperatfonal program for Units ~. The State of Callfomla Department of Health has also required environmental monitoring around commercial nuclear power plants.
~~see*Reference 12 for the proposal to the State for the REMP. The California agency also collects and analyzes some samples of certain media. Reference 13 *is representative of the~~
,level of detail for ~Is confirmatory program. . .
For aH the above reasons, the REMP has been builfon exlstin*g programs and requlreme*nts rather than simply starting fresh when new reg1:1~ry guidance was Issued.
SAMPLE ANALYSES Samples are analyzect according to ODCM requirements. In the past, many analytical practices were employed that were not required. Several memoranda were written to justify elimination of these unnecessary sample analyses. References 14 and 15 desaibe elimination of unnecessary analytical procedures. After the deletion of unnecessary analyses, the
~~requirements of the ODCMs match the guidance in NUREG-0472 and NUREG-1301 relatively dosely. .~~
E. M. GOLDIN Attachment cc: E. S. Medling M. J. Johnson D. Dick K. C. Yhip N. A. Hansen HPE/CDM Files 83-13 5O123-0DCM-B Revision *2 .
02-27-09
REMP. Samples September 10,. 1997 DEVELOPMENTAL RESOURCES The following documents were not speclflcally referred to in the text. They are, however, helpful In a complete description of the development of the REMP and in some cases provide a basis for specified aspects of the REMP. .
1.
~~Letter from M. 0. Medford, SCE to NRC, Radiological Effluent Technical Specificatlo11;8, December 12; '1983.~~
2.
~~L,etter from NRC to K. P.: Baskin, Offslte Dose Calculation Manual, October 2, 1984,.~~
~~3. Letter from NRC to KP. Baskf!'}, Offsite 0ose*eaIculation Manual, August 30, 1985.~~
4. Memorandum from E. S. M.edling to D. L. Cox, Request for Amendment to SONGS Units 2/3 Technical Specifications, September 16, 1988. * *
~~5. Memorandum from J. Brown. to K. Yhlp, Critical Organ for 40CFR190 Eval1:1ation of Gaseous Effluent Dose, AprD 2, 1991.~~
~~6. Memorandum from W. Edwards to K Yhip, Calcium Sulfate vs Lithium Fluoride TLIJ Comparison, September 17, 1991.~~
~~7. Memorandum for FIie, M. Goeders, Channeling in Radlolodlne Charcoal Cartridges, December 30, 1993~~
~~. 8. Memorandum from M. Goeclers to*E. M. Goldin, Justification for Not Collecting Leafy Vegetables at SONGS, March 15, 1994.~~
~~9. Memorandum from E. M. Goldin to P. K Chang and M. J. Johnson, Revision of Tables~~
~~. for Environmental Sample Analyses, June 7, 1996.~~
~~10. Meni<?randum from M. J. Johnson to E. Goldin, Revisiqn of the Radiologies!~~
Environmental Monitoring Program (REMP) Sample Locations, January 21; 1997.
83-14 S0123-0DCM-B Revision 2 02-27--09
~~Subject:~~
Approval of Offsite qose Calculation Manual Changes, April 27, 201 O Cl f5Tsu<5N*
,,,tn/'1,tJ\l"l.Jfl:\1ll1~lf 1~11)-l-&H Ro,,;'f, Rolcnoun:
Semo, \'.:e f'h'lUknl ur><l t','\IJ
~n Ot11.f1ct"\t.9'k-.u (i~'Ttc.r-'"-1&,i: !,'1-t11klt\
April27,2D10 MESSR: LL.MCCANN SUBJECT; Offuite Dose Calculation Manual (ODCM) Approval Dsslgnae Technical Spectficalion 5.52.1.1 "Lieensee--inltiated changes to the ODCM, ft Section 6.5.2 .1.1.b requires licel l9ee Initiated, changes to the'OOCM to become effective ~ review and epprowl by the corporate officer with direct responsibilly for the plant ordes!gnee.
Consistent with the above, effectlve May 5th, 2010, Doug Bauder ls assigned as my designee for approval of ODCM revlaions. -
cc:
D.R. Bauder R. J. St Onge L T, Conklln E. s Meding A, J. Brough COM
\la,I !>l*~
l'O.l\11,t~
l~, t kuw111c ~ \ \Jlri7 !
~~'119* ;t,llt>2iil'\\~hll>~~
I~'- lq~q, '\t,il.ti~1
. II,,,.... tii,,~*h-i>0-n....,~cl"11!\l 84-1 SO123-0DCM-B Revision 6 08-09-12
Memorandum for File
~~SUBJECT:~~
~~Units 213 BuildingNentllatlon Envelopes/Turbine/MSIV ** January 1~. 2012~~
.
Areas, Revision 1 BA~KGROUND Units 213 consists of the following building/ventilation envelopes/areas: Control Room Complex Ventilation; Control Building Ventilation; Radwaste Building Ventilation; Safety.Equipment Building Ventilation ,System;*Penetratlon Building Ventilation System; MSIV/Turblne Bulldlng General Areas; Electrical. Tunnels; Fuel Handling Building Ventilation System; Containment Purge System; and Tendon Gallery Ventilation System.
~~Occasionally, a potential pathway Is created for an unplanned and/or unmonitored release of airborne radioactive material directly to atmosphere through open doors, building air leakage,* steam~~
.~ak. In addition, t~re are also plan11~ but unmonitored ~leases of airborne radioactive material that result from system operation as designed but occur Infrequently and are Impractical to monitor.
For each one of the ventilatt?n envelope/areas, th*e following documents form the reg~tatory guidance or licensing basis:: . * **
1. 10 CFR 20 and 10 CFR 50 (subpart 50.34, 50.34a; 50.36a, appendix A GDC 60 and 64, and Appendix I) require that licensees establish programs and instruments to control and monitor radioactive effluents under normal c;iperation, anticipated operational occur:rences,
~~and accident conditions.~~
~~2. The UFSAR commits to providing an effluent monitoring system which is designed to perform to meet the requirements of '.10 CFR 20, 10 CFR 50, and follow the~~
recommendations of Regulatory Guide (RG) 1.21 Revision 1. Additionally, guidance from NUREG-0800, NUREG-0472,* NUREG-0133, and RG 1.109 were used in the development of the* radiological effluents specifications and the ODCM.
3. NUREG-0800, Standard Review Plan, recognizes that there are some unmonitored release points, such as contaJnment leakage, and that "contiluous gaseous effluent monitors are not required for open structures, such as PWR turbine buDdings or atmospheric vents for liquid waste tanks containing treated o.r pr0C8$58d liquid waste and located outside of buUdlngs.n As a practical consideration, is the regulatory guidance recognizes that there may be release points that cannot be monitored because (a) instrumentation may not exist that could reliably function under the operatinij conditions of the system that Is being monitored or (b) because the concentrations are typically below concentrations that can be reliably
~~~ermined, particularly in-lirie. These releases are not anticipated to result In a significant amount (curies) of actlvfty being released or In a significant dose to the public.~~
4. Section 9.4 an.d Section 11.3 of the UFSAR recognize that there are bulldlng* leakages and steam leaks, which are not monitored, to the outside atmosphere. *
5. 10 CFR 20 provides airborne Derived Air Concentration (DAC) mnits for s~on workers within the radlologlcally controlled area, which Is controlled by the* health physics radiation protection PrOQram, as well as M~mum Permissible Cpncentratlon (MPC) limits for a member of the publ~ In the unrestricted area, which is assessed by the effluent program.
For example, Xe-133 fs an isotope most likely to cause an airborne problem for building/ventilation envelopes/areas. One DAC Xe-133 = 1E-4 uCi/cc for the radlologlcally
. controlled area and one MPC = 3E-7 uCi/cc for the unrestricted area. Station* Health Physics (HP) procedure considers 25% DAC an airborne radioactivity.area, The unmonitored
effluent Impact Is based ,on this criterion and* the affected envelope exhaust ventilation flowrate. Th~ actual or estimated flowrate and Isotopes are determin~d when Effluent 85-1 SO123-0DCM-B Revision 6 08-09-12
~~SUBJECT:~~
Units 2/3 BuildingNentllation Envelopes/Turbine/MSIV January' 13, 2012 Areas, Revision 1
- Engineering Implements SO123-111-5.25, *1:;valuation and Reporting of Abnormal Releases
~~of Radioactive Material,* for* a potentially unplanned or uncontrolled release ..~~
For steam leaks or steam releases from equipment (e.g. ADVs or Auxiliary Feedwater pump*
turbines, tritium <3H) Is the most likely Isotope present and potentially .released In the absence of a primary to secondary leak. One DAC H-3 = 2E-5 uCVcc for the radiologically controlled area and one MPC :::= 2E-7 uCVcc for the unrestricted area. The effluent Impact for steam releases are evaluated In Attachments A and C -
For 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months of Auxiliary Feedwater Pumps operation per year, the effluent impact Is 6.58E-7 mrem during they~ at the controlling location (Camp Mesa) *
~~For 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months of Atmospheric Dump Valves operation at full capacity per year, the~~
~~effluent Impact is 6.58E-5 mrem during the year at the controlUng location (Camp~~
.Mesa) .
Whil_e these examp~ a~ provided for Xe-1~ and H-3, It holds tf1Je for other isotopes as well NUISANCE PATHWAYS Nuisance pathways are releases that occur passiVely and are expected to result In Insignificant doses to the public, genera Ry less than .1 % of the ALARA standards in 10 CFR 50 Appendix I.
Because the concentration of licensed* material In these sources is typically below RETS LLDs or .
the total quantity of licensed material-that could be released Is very small, it is impractical to monitor or control these Incremental releases. Examp~ of nuisance pathways Include:
~~Diffusion across the surface of water contained in an open sump -~~
~~Normal leakage from a PVVR turbine building . . _~~
Atmospheric vent valves on tanks containing treated or processed liquid waste In several of the ventilation envelopes discussed below, the ventilation *exhaust is routed to the plant vent stack for discharge. ;The plant vent_ stack Is an ODCM-credited release point_ that Is routinely sampled and Is equipped With in-line Instrumentation that monitors the discharge to ensure that the release meets all regulatory requirements. -
Control* Room ComPle>c YeoUiation {Units 213)
The Control Room Complex Ventilation System envelopes the areas, equipment and materials to which the control room operator could require access during an emergency. The control room is maintained at a slightly positive pressure by a nonnal supply fan and exhausted to the atmosphere at ?700 cfm. Of all the*.areas In thls*envel6pe, the Turbine Laboratory Is kept at a slightly negative *
.
pressure relative to .the other areas, because it is a potentially airborne radioactive *area. This negative pressure is maintained by an exhaust fan dedicated to the lab; the exhaust of this fan (about 1050 cfm) Is dlred:ecfto the Plant Vent Stack..The Plant Vent.Stack is an ODCM-CfBQ.ited
-release point that Is periodically sampled per the ODCM and Is monitored prior to discharge to the *
- environment. *
Although the Turbine LabQ~ is considered _a potentially airborne radioactive area; due to administrative practices that limit operation with primary to .secondary leakage, it d.oes not typically present an airborne Issue. A primary to secondary leak Is the only credible source term to the lab.
However, the steam generator sample passes through a flow orifice and a ~ure control valve, and when the sample reaches the Turbine Lab, it is at ambient pressure. As a result, the likeUhood of an airborne Issue for radioactive materials is remote.
85-2 SO123-0DCM-B Revision 6 08-09-12
~~SUBJECT:~~
~~Units 213 BuildingNentilation Envelopes/Turblne/MSIV January 13, 2012 Areas, Revision 1~~
Effluent Controls: For this envelope, doors may be opened for personnel and equipment*
Ingress/egress, operatiOnal and* maintenance activities In the absence of airborne radioactivity. If airborne at 25%-DAC or higher is detected by HP or Area Radiation Monitors In this ventilation envelope, Effluent Engineering will Implement SO123-lll-5.25,*"Evaluatlon and Reporting of Abnormal Releases of Radioactive Material,* for a potentially unplanned-or uncontroRed release. All unrlarined or unmonitored releases of radioactive material that meet the criteria In RG 1.21 rev 1 wU be induded in the appllcable Annual Radioactive Effluent Release Report. . .
Unmo_r'l,itored Effluent Impact: In the unlikely e*vent that the entire Co,:rtrol Room Complex Ventilation envelope Is contaminated to the 25% DAC HP th~hold for an airborne* radiation area, at an exhaust rate of 2700 cfm, the effluent lmpj:lci at the site boundary is no greater than *
~~5.13E-6 mrem/hr~~
~~1E-4 uCVcc~~
~~0.25~~
~~2700 cfm~~
~~2.832E4 cc/ft3~~
~~1 mln/60 sec~~
~~4.8!=-6 sec/m3~~
~~294 .1111'.'em/yr per uCVm3~~
~~1 yr/8766 hrs= 5.13E-6 mrem/hr Control Building Ventilation (Units 2(3)~~
The Control Building Ventilation System serves the Control Bull9lng except for the Control Room Complex Ventilation ~nvelope. It includes the following subsystem:
Consistent with standard ALARA practices, ESF Switchgear Room Nonna! and Emergency Cooling subsystem, ESF Battery. Rooms Normal and Emergency Ventilation subsystem, Switchgear Room Ventilation subsystem, Communication ~ery Room Ventilation subsystem, HP Computer Air ,
Condltionln~ subsystem, Communication.Room Air Conditioning subsystem, Cable Spreading and Bectrie:al Room Ventllatl0f'1 subsystem, Chiller Rooms Nonnal and Emergency Ventllatlori subsystems, Public Address and Communication Rooms Air Conditioning subsystem, and Health Physics and 1-ocker ~oom Air Conditioning.subsystem. Several potentially airborne radioactive
zones in the Health Physics and Locker Room areas are maintained at a slightly negative pressure relative to other areas and are exhausted (about 14,000 cfm) to the Plant Vent Stack. The Plant Vent ~ck is an ODCM-cred~ release point that is periodically sampled per the ODCM and Is monitored prior to discharge to* the environment. * *
Are~s include: central liquid sampling room, radioactive chemical laboratory, restrooms, corridor, personnel decontamination areas and decontamination monitor area. Plant experience has shown these* areas rarely, if ever, pose an airborne issue for radioactive mater_ials. All other areas are not potentially airborne radioactive and are exhausted by normal exhaust fans at about 110,000 cfm to the abnosphere*.
Effluent Controls: For this envelope, doors may be opened for personnel and equipment ingress/egress, operational and'maintenance activities in the absence of airborne radioactivity. If airborne radioactive material at 25% DAC or higher Is detected by HP or Area Radiation Monitors in.
th!$ ventilation envelope, Effluent Engineering will implement SO123-11I-5.25, "Evaluation and Reporting of Abnormal Releases of Radioactive Material," for a potentially unplanned or uncontrolled release. All unplanned or unmonitored releases of radioactive material that meet the criteria in RG 1.21 rev 1 will be Included in the applicable Annual Radioactive Effluent Release
. Report.
Unmonlt9red Effluent Impact: In the extremely unlikely event that the entire Control Building Ventilation envelope Is contaminated to the 25% DAG HP threshold for an alrbom_e radiation *area, at an exhaust rate of 110,000 cfm, the effluent Impact at the site boundary Is no greater than 2:09E-4 mrem/hr.
1E-4 uCVcc
~~0.25~~
~~110000 cfm~~
~~2.832E4' cc/ft3~~
~~1 mln/60 sec~~
~~4.8E-6 sec/m3~~
~~294 .~~
~~mrem/yr per uCl/m3~~
1 yr/8766 hrs = 2.09E-4 mrem/hr*
85-3 SO123-0DCM-B Revision 6.
08-09-12
~~SUBJECT:~~
Units 213 BuildingNentilatlon Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Ractwaste Building V~ntnatlon <Units 2/3}.
The Ra~ste Ventilation System serves the Radwaste Building and is comprised of several subsy~ms: Radwaste Area Ventilation subsystem, Post Accident Sampling Laboratory Air Conditioning subsystem, Control Element Drive Mechanism Control System Room Air Conditioning subsystem, Raci:waste Building Addition Ventilation subsystem,. and Charging and Boric Acid Pump Rooms Emergency Ventilation. . *
Relative t9_other building/ventilation envelopes, the Radwaste envelope has a higher potential.for unmonitored releases since It contains most, if not an, of the.systems and components associated with liquid (such as hold up tanks) and gas processing (such as waste gas compressor and decay tanks) involving licensed material. As a result, consistent with standard ALARA practices, the entire*
envelope Is considered potentially airborne radioactive and is maintained under a ~tive pressure relative to other adjacent bulldlng/ve~ envelopes. This envelope Is normally exhausted (about 78,100 cfm) to the Plant Vent Stack. The P1ant Vent Stacie 1s* an OD CM-credited release point that .
_is perlodicatty* sampled per the ODCM and is monitored prior to di~a_rge to th~ environment.
L Due to -this envelope's higher potential to become airborne, additional design, procedural, and.
administrative controls are implemented tq ensure a negativ~ pressure is maintained to minimize ex-filtration to the outside atmosphere. For example: The*ventilation supply.and exhaust units ere ***
interlocked to operate in pairs. A supply' unit cannot operate without an exhaust unit, which Is at a higher capacity to maintain a _slightly negative pressure, also operating: .The Radwaste Truclc Bay dampers are Interlocked wttt,:the truck bay door, a boundary door to the*outslde atmosphere. The dampers cannot be opened when the roll up door Is open and the roll up door cannot be opened
when the dampers are open. Operations Instruction SO23-1-5, "AuxlRary Building Nonnal HVAC System Operation," provides expllcit directions on the Radwaste/Truck Bay ventilation envelope to ensure_a_negatlve pressure envelope Is maintained. If Radwaste HVAC. Is lost, an Immediate action Is directed by this procedure to close all Radwaste doors leading to adjacent buildings end to outside areas. Operations Instructions SO23-15-60.B, "Annuntjator Panel," directs that Effluent Engineering be notified for a potential unplanned or uncontrolled release If Radwaste HVAC is lost As en additional note, signs ere'postecf on appropriate redwaste envelope doors to remind station personnel to keep doors closed when egress or Ingress Is not required.
~~Based Of! the reletive*potential fQr radioactive material to become eirbQme, the design and procedural controls that are being Implemented are. proper and adequate.~~
Effluent Controls: For this envelope, doors may be o~ned for personnel and equiprflent ingress/egress, operational and maintenance activities In the absence of airborne radioactive materials. If airborne radioectiv~ material at 25% DAC or higher is 'detected by HP 'or Area Radiation Monitors In this ~ o n envelope and concurrent with a I ~ of Redwaste HVAG, Effluent Engineering will Implement S0123-111-5.25, "Evaluation end Reporting of Abnormal Releases of Radioactive Material," for a potentially unplanned or uncontrolled re.lease. All unplanned or unmonitored releases of radioactive material that meet the criteria in RG 1.21 rev 1 will be Included In the applicable Annual Radioactive Effluent Release Report.
Unmonitored Effluent Impact: In the unllkely event that the entire Radwaste Ventilation envelope Is detennlned to contain or exceed the 25% DAC HP threshold for an airborne radiation area end concurrent with *a loss of Radwaste HVAC, at *an exhaust rate of 78100 cfm from the Redwaste Bulleting Ventilation Envelope, *the effluent impact at the site boundary is-no greater than **
1=48E-4 mtem/hr: Note: Upon loss of Radwaste HVAC, there is ~ntially no di~rentlal pressure between the Radwaste Envelope and outside atmosphere. .
1E-4 uCVcc
~~0.25~~
~~78100 cfm~~
~~2.832E4 cc/ft3~~
~~1 min/60 sec~~
~~4.8E-6 sec/m3~~
~~294 mrem/yr per uCi/m3~~
~~1- yr/8766 hrs~~
~~1.48E-4 mrem/hr B5-4 . SO123-0DCM-B Revision 6~~
~~.08-09-12~~
~~SUBJECT:~~
Units 2/3 BuildingNentilatioh Envelopes/Turpine/MSN January 13, 2012 Areas, Revision 1 Safety Equipment Bujkfing Ventilation System <Per unm The Safety Equipment Building Ventilation System Include these subsystems: the *safety Injection pump rooms, the component cooling water-pump rooms, the*safety equipment building heat exchanger rooms and piping rooms, the safety equipment building air conditioning equipment room, the safety equipment building lobby area al_r conditioning subsy~em, and the elevator room (Unit 2 only).
Under normal operation, this ventilation *envelope is* not considered potentially airborne radioactive.
In the u11likely event of an accident condition, particular1y with fuel tanure, safety injection system actuation followed by a breach of pressure bolfndary equipment or components in t!ie *satety
. equipment building can potentially result In airborne radioactive material. For this reason, the exhaust of this envelope is directed to the-Plant Vent Stack by the Penetration and *Safety .
Equipment Exhaust Fan (about 9000 cfm per Unit). The Plant Vent Stack is an ODCM-credited release point that Is ~riodically sampled per.the ODCM_an(J is monitored prior to discharge fo the z
environment. The only excepted area is the elevator equi~ room (Unit only), that draws outside air directly and exhausts (1160 cfm) d i ~ to the outside atrno~here.
Effluent Controls: For this envelope, doors may be opened for personnel and equipment =
ingress/egress, operational and maintenance activities in the a_bsence of airborne radioactive materials. If al~e radioactive material at 25% DAC or ~lgher Is detected by HP or Area Radiation Monitors In this ventilation envelope, Effluent Engineering will impfement SO123-lll-5:25, "Evaluation and Reporting of Abnormal Releases ofRadioactlve Material/' for a potentially
unplanned or uncontrolled release. All unplanned orunmonltorecl releases of radioacttve*rnaterial that meet the criteria In RG 1.21 rev 1 will be included In the applicable Annual Radioactive Effluent Release Report.
~~Unmonitored Effluent Impact In the unlikety ev~nt t~at the entire Safety Equipment Building .~~
~~Ventilation envelope Is contaminated to .the 25% DAC HP threshold for an airbOme radiation area, at an exhaust rate of 9000 cfm, the effluent Impact at the site boundary is no greater than~~
~~1.11 E-5 rnrem/hr Note: Upon I~ of Safety Equlp,:nent Building ijVAC, there Is essentially no differential pressure betw~n :tJ:le Safety Equipment Building, envelope and outside atmosphere.~~
~~1E-4 uCVcc~~
~~0.25~~
~~9000 cfm.* 2.832E~ cc/ft3* 1 min/60 sec* 4.BE-6 sec-Jm3~~
~~294 mremlyr.~~
~~per uCilm3~~
~~1' yr/8766 hrs~~
~~1. 71 E-5 mremlhr~~
. I Penetration Bulldlng Ventilation System <Per Unit}
The Penetration Building Ventilation System Includes these subsystems: Penetration Building Air Conditioning Subsystem, and Penetration Area Cooling Subsystem. This envelope Is normally not considered *potentially airborne radioactive. However, In the unlikely event of a breach of Integrity In a mechanical or electrical penetration, the*potentlal exists for an airborne conce~. For this reason,
this envel~-is exhausted (about 9000 cfm per Unit) to the Plant Vent Stack. The Plant Vent Stack is an <:;>DCM-credited release point that is perlodlcally sampled per the ODCM and Is monitored prior to discharge to tf:le environment..
Effluent Controls: For this envelope, doors may be opened for personnel and equipment ingress/egress, operational and maintenance activities In the absence of airborne radioactive materials. If airborne radioactive'mater1al at 25% DAC or higher Is detected by HP or Area Radiation Monitors In this ventilation envelope, Effluent Engineering will implement S0123-111~5.25,
~~"Evaluation and R~ppitlng of Abnormal Releases of Radioactive Material," for a*potentially~~
unplanned or uncontrolled release. All unplanned or unmonitored releases of radioactive material that meet the criteria in RG 1.21 rev 1 will be included in the applicab!e Annual Radioactive Effluent 1
Release Report. . ,
B5-5 SO123-0DCM-B Revision 6 *
. '0S:09-12
~~SUBJECT:~~
Units 2/3 BulldingNentllation Envelopes/Turblne/MSN January 13, 2012 Areas,* Revision 1 Unmonitored Effluent Impact In the unllkely event:that the entire Penetration Building Ventilation envelope Is contaminated to the 25% DAC HP threshold for an airborne radiation area, at an exhaust rate of 9000 cfm, the effluent impact at the site boundary Is no greater.than
~~1.71 E-5 mrem/hr. Note: Upon loss of Penetration Building HVAC, there ls essentially no dlfferentlal pressl:Jre between the P~etratlon Envelope and outside atmosphere.~~
~~,1E-4 uCVcc~~
~~0.25~~
~~9000 cfm~~
~~2.832E4 cc/ft3* 1 mln/60 sec* 4.BE-6 sec/m3 '* 294 mrem/yr per uCl/m3 **1 yr/8766 hrs =.1.71E-5 mrem/hr~~
~~Electrical Tunnel Ventilatjon (Units 2/3}~~
The Electrical Tunnel Ventilation System Includes these subsystem$: Safety Equipment Bulleting : *
(SEB) Electrical Tunnel, and me Access Building and Underground Cable tunnel. The potential airborne radioactive concern would be if either of these structures were to become flooded with
.water containing licensed material, 'rr1cludlng tritium. They are* exhausted directly to the environment
~~with the SEB tunnel at a normal rate of about 11,000 cfm and the Access Bulldlng and Underground Cable tunnel at a normal rate of about 17,000 cfm.~~
~~Effluent Controls: For this envelope-, doo~ may be opened for personnel and equipment~~
. Ingress/egress, operational and maintenance activities In the absence of airborne radioactive materials.-lfthe safety Equipment Building (SEB) Electrical Tunnel, or the Access Bulldlng and Underground Cable Tunnel becomes flooded with water containing licensed material, Including tritium, Effluent Englneering'will Implement SO123-I11-5.25, "Evaluation and Reporting of Abnormal Releases of Radioactive Material," for a:potentlally unplanned or uncontrolled release. All unplanned or unmonitored releases of radioactive material that meet the criteria in* RG 1.21 rev 1 will be Included In the appli~le Annual Radioactive Effluent Release Report.
Unmonitored Effluent Impact: in the unlikely event that the entire Electrical Tunnel Ventilation envelope is contaminated to the 25%. DAG. HP threshold for ari airborne radiation area, at an exhaust rate of 28000 cfm, the effluent impact at tJ:le site boundary Is no g_reater than .
~~5.32E-5 mrem/hr. .~~
1E-4 uCVcc*
~~025~~
~~28000 cfm *. 2.832E4 ccJtt3~~
~~1 rnln/60 sec~~
~~4.BE-6 soclm3~~
~~294 mrerrt/yr per uCi/m3~~
1 yrl8766 hrs = 5.32E-5 mremlhr Fuel Handling Building VentHation.System* <Per Unitl Barri~ th~ loss of the Fuel Handling Building Ventilation System or an accident and emergency condition such as a fuel handling accident, the Fuel Handling Building Ventilation envelope does not present an airborne radioactive material concern. This ventilation is exhausted (about 26,000 cfm) a to the Plant Vent Stacie with the option to route the air tt)rough HEPA filter'system The Plant Vent Stack is an ODCM-creclited release point that is periodically sampled per the ODCM and is monitpreg prior to dlsch$rge to the environment :.
Effluent Controls: For .this envelope, doors may be opened for personnel and equipment ingress/eg~. operational and maintenance actfvltles In the absence of airborne. radioactive mat~. If airborne radioactive material at 25% DAC or higher Is detected by HP or Area Radiation Monitors in this ventilation envelope, Effluent Engineering will Implement SO123-111-5.25,
*Evaluation and Reporting of Abnormal Releases of Radioactive Material,"'for a potentially
unplanned or uncontrolled release. All unplanned or unmonitored releases of radioactive materiel that meet the*criteria in RG 1.21 rev 1 wlll be Included In the applicable Annual Radioactive Effluent Relea5t\' Report 85-6"* SO123-ODCM-B Revision 6 08-09-12
~~SUBJECT:~~
Units 2/3 BulldlrigNentllatlon Envelopes/Turb.lne/MSIV January 13, 2012.
Areas, Revision 1 Unmonitored Effluent Impact: In the unlikely event that the entire Fuei Handling Building yentilatlon
.. envelope is contaminated to the 25% DAC HP threshold for an airborne radiation area, at an exhaust rate of 26000 cfm, the effluent impact at the site boundary is i:io greater than 4.94E-5 mrem/hr. Note: Upon loss of Fuel Handling BuUdlng HVAC, there Is essentially no differential pressure between the Fuel Handllng.BuUdlng Envelope and outside atmosphere.
1E-4 uCi/cc
~~0.25~~
~~26000 cm,~~
~~2.832E4 cctft3~~
~~1 min/60 sec~~
~~4.8E-6 sec/m3~~
~~294 mrem/yr per uCi/m3~~
1 yr/8766 hrs = 4.94E-5 mrem'hr Tendon Gallery Ventilation- System This system is operated continuously to maintain personnel habitabUity in .the Tendon Gallery. A potential airborne radioactive concern would be if the Tendon Gallery became flooded with water containing licensed material, Including bitlum. The exhat,JSt (about 5000 cfm) goes directly to : .
outside atmosp~ere.
Effluent Controls: For* this envelope, doo",-s may be opened ~r: personnel and eq'uiprnent .
ingress/egress, operational and maintenance activities In the absence of airborne radioactive materials. If the Tendon gallery becomes flooded with water containing'licensed mat~rial, Effluent
,-Engineering win Implement SO123-lll-5.25, "Evaluation and Reporting of Abnormal Releases of Radioactive. Material," for a potentially unplanned or uncontrolled release. All unplanned or unmonitored releases of radioactive material that meet the criteria in RG 1.21 rev 1 will be included in the applicable Annual Radioactive Effluent Release Report. **
Unmonitored Effluent Impact: In the unlikely event that the entire Tendon Galley Ventilation envelope Is *contaminated to the 25% DAC HP thresijold for en airborne radiation area, *at an exhaust rate of 5000 cfm, the* effluent impact at the site boundary is no greater than 9.50E-6 mremlhr. * * * * *
~~1E-4 uCi/cc~~
~~0.25~~
~~5000 cfm~~
~~2.832E4 cclft3 ** 1 min/60 sec~~
~~4~8E-6 sec/m3~~
~~294 mrem/yr per uCl/m3~~
~~1 yr/8766 hrs = 9.50E-6 mremlhr MSNITyrbjne Building General Area <Per Unit)~~
~~Since th8Sl3 areas are open structures that contain ~ulpment and components to support the steam and power conversion cycle, there is the potential for an unmonitored airborne release.~~
Under typical operating conditions,* there is detectable tritium present In the steam and power conversion system due to migration across the steam generator tubes. The concentratlon(s) of Hcensed material In the main condenser evacuation.system, main steam line monitors, steam
~~. generator blowdown monitor and sampling system are determined by sampling the condensate and~~
~~feedwater systems. * .~~
It is also possible for this _system to contain licensed matertaI*as a result of primary to secondary leak. Section 11.3 of the UFSAR Indicates that the preponderance of the primary to secondary gaseous radioactivity will be released through the Main Condenser Evacuation System. The Main .
. _Condenser Evacuation System Is an ODCM-credited release point that is periodically sampled per the ODCM and Is monitored prior to .disctl~rge to the environment The other turbine area flow paths listed in UFSAR Section 11.3 represent the following percentages In*terms of curies released to the atmosphere relative to the Main Condenser Evacuation System on an annual basis: :
~~a. Turbine Building Steam Leakage, 2.4% (1,700 lbm/hr)~~
~~b. Turbine Glan'd Seal Steam System: 1% (708 lbm/hr)~~
~~B5-7* 8O123-ODCM-B Revision 6 08-09-12~~
~~SUBJECT:~~
Units 2/3 BulldlngNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 As Is the case for the steam end power conversion systems mentioned earlier in this section, samples of feedwater and condensate systems are routinely collected and analyzed to determine levels of radioactivity In these systems. _ .
Unmonitored Effluent Impact In the absence of a primary ~o secondary ieak where tritiun:i activity is released from the Unit land 3.turbine bulldlng steam.leakage and Turbine Gland Seal Steam system occur for 87~ hrs/yr the effluent impact at the contronirig location (Camp Mesa) would be
- 9.14E-6 mrernfyr (Attachment B)
PLANNED BUT UNMONITORED RELEASES Section 1Oof the UFSAR also discusses three -other main steam flowpaths: steam driven auxiliary
~ r pump, main steam ~feties, and abnosph~c dump va!ves (AQV). Samples of_feedwater and condensate systems are routinely collected and analyzed to determine levels of radioactivity In these systems. .
There are systems or components that, Integral to their operation as designed, are more Hkely to have a radioactive release during the use of the equipment but, due to operating conditions, monitoring for licensed material cannot practicably be accomptished. As previously discussed, reg4latory guidance recognlz~ that there may be re~se points that cannot be' monitored because (a). lnstnlmentation may not exist that could rellably function under the operating conditions of the system that is being monitored-or (b) because the concentrations are typically below concentrations that can be reliably determined, pa~la~ by In-line ll')struments. These releases' ere not *.
anticipated to result In a significant amount (curies) of actMty*being released or In a significant dose
~~to the pu_bllc. - - -~~
.. Steam Driven Auxiljary Feedwater Pump In en accident scenario or for quarterly 1ST surveillance, operation of.the steam driven auxm~-
feedweter pump 11'!8Y be required. The ~alist of the ste~ driven pump turbine g~.to outside atmosphere. Typically, In an accident scenario, the other two electric driven. auxiliary feedwater pumps will be used unless the accident Involves a loss of power, Although the main steam supply
-rate to the turbine pump Is not explicitly provided in the UFSAR or other readily available
documents, based on the ~mum pump flOYI COOQltlons in Section, 10.4 d the UFSAR for**
~~accident mitigation, the maximum steam f19W rate to the pump can be calculated to b:e about 25,000~~
~~_lbm/hr (Attachment A). - ..~~
Assuming these planned releases occur 6 times per year for 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months , 4 times for 1ST and 2 times
.for abnorrnaVaccident conditions, a total of 1.5 E6 lbm of steam would have been exhausted:to the
~~atmosphere. -~~
Since the main steam flpwrete is approximately 1.. 5E7 lbn'l/hr, for a primary to secondary leak, this wouk:I represent about 0.2% of the noble gas activity released through the Main Condenser : .
Evacuation System,. The Main Condenser Evacuation System Is an ODCM-0-edlted release point
_ that is periodically sampled per the ODCM end is monitored pfior to discharge to the environment In the absence of a primary to secondary leak, where tritium activity is released in the steam but not from the Main Condenser Evacuation System, this*would represent abourD.01% of the alrborile
_ tritium activity released from the Plant Vent Stack. (Attachment A) The Plant Vent Steck Is an ODCM-credlted release point that is periodically sampled per the ODCM end is monitored prior to discharge .to the environment.
. 85-8 SO123-0DCM-B Revision 6 -
08-09-12
~~SUBJECT:~~
Units 213 BuildihgNentllatlon Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 The conclusion Is that similar to turbine bulldlng steam leakage and th~ turbine gland seal steam system, *operation of the steam driven auxiliary feedwater pump does riot constitute a significant or major release flpwpath. However, since these are planned but unmonitored releases and the secondary systems normally contain tritium, 8c!Cf1 reJease shall be evaluated per the CQrrecti\1.8 Action Program to determine If the dose and curies released should be included In the Annual Radioacti~ Effluent R~se Report.
In the unlikely event Qf an abnormal/accident condition when the steam drive auxiliary feedwater pump Is needed: * * * *
subsequent to an emergency event declaration, Effluent- Engineering will Implement SO123-I11-5.22:23, "Determining a Source Term for Offsite Dose Calculations in an Accident Situation," *
~~subsequent t9 the emergency event, Effluent Engineering will Implement SO123-111-5.25, .~~
"Evaluation and Reporting of Abnormal Releases of Radioactive Material". All unplanned or*
unmonitored releases of radioactive* material that meet the criteria in RG 1.21 rev 1 will be included In the applicable.Annual Radioactive Effluent Release R~rt.
Main Steam Safety va1yes There !3ie a total of 18 rosin steam safety valves per unit with a maximum total of 1.5 E7 lbm/hr of relieving* capacity during an accident or abnormal scenario d~ding on plant condition such as decay heat history, .etc,. Actuation of the valves Is an unllkely event (unplanned release) supported by P.tant experience. During the dual unit 'trip from full power in September, 2011, the Steam Bypass Control System relieved excess steam to the Main Condensers. No Main steam Safety Valves opened during this event.
If the main steam safety valves are used, Effluent Engineerlr19 wHI implement S0123-111-5.25, REvaluatlon and Reporting of AbflormaJ Releases*of Radioactive Material," for a potentially unplanned or uncontrolled re~se. * *
. In the unlikely event of an abnormal/accident condition when the main steam safety valves are needed for.decay heat removal: . *
*subsequent to an emergency eyent declaration, Effluent Engineering will implement
~~SO123-lll-5.22.-23, "Determining a Source Term for Offsite Dose Calculations. In en Accident Situation," .~~
subsequent to the emergency event, Effluent E_ngineerln~ will implement SO123-111-5.25, "Evaluation and Reporting of Abnormal Releases of RadK>active Material*. All unplanned or unmonitored releases of radioactive material that meet the criteria in RG 1.21 rev 1 will be included In the applicable Annual Radioactive Effluent Release Report.
Atmospheric Pump Vatyes There are two atmospheric dump valves per unit wfttl a maximum total of 1.5 E6 lbm/hr of relieving capacity during en accident or abnormal scenario depending on plant condition such as decay heat history, etc. Under normal operations, these valves typically are not used since the main condenser
.is available. Even if they are used during normal plant operat1o*ns, they are throttled to a fraction pf the maximum relieving capacity. . . **
For a primary to secondary leak .and assuming that the dump valves. are operated 1O hours per year at full capacity, a total of 1.5 E7 lbm of steam would be exhausted to the atmosphere. Since the.
'B5-9 SO123-0DCM-B Revision 6
.08--09-12
~~SUBJECT:~~
Uni~ 2/3 BuildingNentllat!on Envelopes/Turbine/MSIV January 13, 2012 Are~~ 1 Revision 1 main steam flowrate is approXlmately 1.5E7 lbmhlr, this represents about 1O % of the noble _gas activity released through the Main Condenser Evacuation System. *
In the absence of a* primary to secondary leak, where tritium activity is not released through the r Main Co~denser Evacuation System, operation of the dump valves for .100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months per year at full capacity would represent about 1 % of the airborne-tritium actMty released through the Plant Vent Stack. (Attactiment Cf The Plant Venf Stack Is an ODCM-credlted release point that Is periodically sampled per the ODCM and is monitored prior to discharge to the environment .
Thereto~, for normal operation, the conclusion Is similar to turbine building steam leakage, the turbine gland seal steam system, and the steam driven aux feedwater pump, operation of the atmospheric dump "'8lves does not constitute a significant. or major release flowpath. However,
since use of the ADVs are planned releases and the secondary systems nonnally contain tritium, each release shall be evaluated per the Corrective Action Program to determine if the dose and curies released should be included l,:t the Annual Radi~ctlve Effluent Release Report. Refer to Attachment D to calculate the steam flowrate from the ADVs. *
In the unlikely event of ~n -~br:JormaVaccldent condition when the atmosph:erlc dump valves *are need~ to _assist the main steam safeties for decay heat removal: * *
~~subsequent to an emergency event ~ration, Effluent Engineering wUI Implement SO123-111-5.22.23, "Determining a Source Term for Offsite Dose Calculations in an Accident~~
Situation," * * * *
subsequent to the emergency event, Effluent Engineerlnp wlll implement SO123-111-5.25, "Evalul!ltion and Reporting of Abnormal Releases of Radioactive Material*. All unplanned or unmonitored releases of radioactive material that meet the atterla in RG 1.21 rev 1 will be
~~included in the applicable Annual Radi~actlve Effluent R~se Report.~~
~~Containment with Equipment Hatch Open and No Purge In Progress <Per Unit} * .~~
With its inherent source* term, the containment envelope is an ODCM-credited release poinl Mini and normal purges ofthe*contalnment are conducted through a monitored and sampled flowpath prior to release. The mini purge is exhausted at a rate of abpl,rt 2000 CFM, and the normal purge at about 40,000 cfrn. Wten shutdown to Mode 5, primarily for a refu~~ outage, the purge system supplies Jhe containment with outside air through the equipment h . When the hatch Is open, auiclliary air samplers at the hatch are continuously sampling for particulate arid iodi,:te activity.
Effluent Controls: If <:9ncentrations of Ucensed material are detected around the equipment hatch opening*, Effluent Engineering will implement SO123-,111-5.25, "Evaluation and Reporting of Abno~ Releases of Rad~ Material," for a potentially unplannecfor uncontrolled release. All unplanned or unmonitored releases of radioactive material that meet the criteria In RG 1.21 rev 1 *
. wlll be included in the applicable Annual Radioactive Effluent Release Report.
Unmonitored Effluent Impact In the unl!kely event that the containment envelope is contaminated to the 25% DAC HP threshold for an airbQme radiation area, at an exhaust rate of 40000 CFM, the effluent impact at the site boundary is no greater than 7.60E-5 mrem/hr. Note: Upon loss of containment purge,: there is essentially: no differential pressure between the Containment Envelope and outside atmosphere 1E-4 uCi/cc
~~0.25~~
~~40000 cfm~~
~~2.B32E4 cc/ft3~~
~~1 min/80 sec~~
~~4.BE-6 ~ 3~~
~~294 mrem/yr per uCi/m3~~
~~1' yr/8766. hrs* 7.60E-5 mrem/hr B5-10 SO123-0DCM-B Revision 6~~
~~08-09-12~~
~~SUBJECT:~~
Units 2/3 BulldlngNentllation Envelopes/Turbine/MSIV January.13, 2012 Areas;-Revislon 1 North lndu.strial Area <formerly Unij 1}
Unit 1 was permanently shutdown In November 1992 and systems containing or pot~tially containing licensed material have been drained and removed or abandoned In place .. Used fuel from Unit 1 Is stored In Qle ISFSI. Barring a fuel.handling accident In the ISFSI, there Is simply no credible airborne source term. *
~~Occasionally; work is performed In the North Industrial~ (\.)nit 1) on large components for Units * .~~
~~2 or 3. Each major work activity that has the potential to result in airborne radioactivity shall have an Effluent ~~luation (EOE) perfonned.~~
~~85-11 S01 ~3-0DCM-B Revision 6 08-09-12~~
~~SUBJECT:~~
~~Units 2/3 Building/Ventilation Envelopesffurbine/MSIV January 13, 2012 Areas,* Revision 1~~
CONCLU$10N The evaluation of the Units 213 building .ventilation envelopes/areas with a potential tor an unrT)Onitored airborne ~ has determined that - . _ 1 1.- The design of the building ventilation envelopes, turbine buiidlng/MSIV areas does not assume that tney ere air-leak tight or steam-leak tight Building air leakage/steam leaks are *-
~~unavoidable facts of plant operations. However, they are not significant or major radioactive effluent flowpaths and cannot practicably be monitored and samplf:KI.~~
~~2. In the absence of airborne radioactive materials, doors may be opened for personnei and equipment ingress/egress, operational and maintenance activities. -~~
3. The adoption of 25% PAC Health Physics criterion for an airborne. area within the -*
radlologlcally ~trolled area as a_ ~reshold for an evaluation of a potential_ly unplanned or uncontrolled effluent release from an unmonitored flowpath is proper and appropriate.
Performing an evaluation and taking actions at this point will further mitigate the Impact of any potentially unplanned or uncontrolled release to a member of the public. *
4. Additional design and procedural controls are implemented for the radwaste and containment open to atmosphere with purge In progress 911velopes. This attention reflects tt:ie Inherently higher potential for an unplanned or uncontrolled release from* an unmonitored flowpath directly to the atmosphere.
5. Planned but unmonitored releases .such as the use of main steam safety valves or atmospheric dump valves or auxiliary feedwater pump or opening of containment with no purge In progress will be evaluated case-by-case using approved station procedures. All unplanned or unmonitored releases of radioactive material that meet the criteria In RG 1.21 tev 1 will be Included in' the applicable Ann'ual' Radioactive Effluent Release Report.
~~If you have any questions or concerns regarding this matter, please contact James Demlow at 86780.~~
~
1/1312012 Date _ _ __
J. Demlow Attachment A .-Units 2 and 3 Steam Driven Aux Feedwater Pump Release Cslculation Attachment B Units 2 and 3 Turbine Gland Seal Steam System Release Calculation Attachment C . Units 2 and 3 Atmospheric Dump Valve Release Calculation Attachment D Units 2 arid 3 Atmospheric Dump Valve Steam Flowrate Calculation cc: L. McCann
~~K. Yhlp J. Scott COM 85-12 - S0123-0DCM-8 Revision 6 08-09-12~~
~~SUBJECT:~~
Un~ 2/3 BuildingNentllatlon Envelopes/Turbln_e/MSIV January 13, 2012 A{eas, Revision 1 Attachment A Units 2 ~nd 3 Steam Driven Aux F~ter Pump Calculation Steam Flow Rate Although the main steam flowrate to the Units 2 and 3 Steam Driven Aux Feedwater Pump turbine is not prc;,vided In the UFSAR or other avaDable references, the expected maximum flowrate can be calculat~ based on accident ~eslgn conditions proyided In Section 10.4 of the UFSAR.
For accident conditions, using main steam from the steam generator to the turbine and exhausting
~~the steam to atmosphere, the pump is designed ,to draw from the condensate storage tank (ambient condition~ of 80 F water a~ atmospheric pressure) at a rate of 500 gpm for a steam generatrn:"~~
pressure of 1172 psia or 700 gpm for a steam generator pressure of.1000 psla. Applylng the* _
conservation of energy principle, the work done by the main steam on the turbine can be equated to the work done by th*e pump In transporting the condensate storage tank fluid to the steam generator.
- - The work done by the steam cin *the turbine Is:
M.x delta h
. where M Is ~n steam mass flowrate, delta h Is _the change.in enthalpy of the steam between steam generator pressure and atmospheric pressure. .
The work done by the pump on the fluid is:
. . F * 'v
delta P of where F is the pump flowrate, v is the specific volume the condensate tank water at 80° F, delta P is the change ir:t pressure from atmospheric to steam Generator pressure. U~ng a steam table, for the two flow conditions described in the UFSAR, :the maximum steam
~~flowrate to the aux feedwater pump turbine may be calculated. It turns out to be about 25,000 lbm/hr.~~
~~85-13 . SO123-0DCM-B Revl~on 6 08-09-12~~
~~SUBJECT:~~
~~Units 2/3 Building/Ventilation Envelopes/Turbine/MSIV *January 13, 2012 Areas, Revision 1 Attachment A Assumptions~~
~~. Each unit pumps are operated 6 times per*year for 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months ~~
~~2.5E4 lbm/hr is discharge:d ,~~
~~No detectable Primary to Secondary Leak~~
Steam Generator tritium activity Is 1E-5 uCi/cc due to diffusion *
~~82 CVyr of gaseous 3H released from Plant Vent Stack (2010 ARERR)~~
~~870 Ci/yr of liquid 3 H released (2010 ARE RR)~~
CQndensed steam Is cc;,ntain!:KI In air as water vapor* at 100% humidity Since tritium is not released from the Condenser Evacuation System, only non-condensable gases, the Plant Vent Stacie Is used for this calculation .
~~. Qgm~~
~~. 1lbm of saturated steam = 334 ft3 (Steam Tables)~~
~~1 m3 of air contains 30 g water vapor at 30 C° (100% hunvdlty)~~
~~1 ft3 = 0.02813 m3~~
~~. Calculations Tritfum Release Rate Into atmosphere 2.5E4 lbnilhr.~~
~~334 ft3/lbm~~
~~0.02813 m3/ft3~~
~~30. g/m3~~
~~1E-5 uCi/cc~~
~~1hr/36-00 sec~~
~~2.0E-2 uCi/sec Tritium Curles released into abnosphere 2:0E-2 uCi/sec *_ 60 hrs~~
~~3600 sec/hr* 1E-6 CVuCI~~
~~2 units = 8.6E-3 Cl Percent of Tritium Curies Released from Plant Vent Stack~~
** 8.6E:-3 Ci / 82 Ci (PVS) *. 100 111 1E-2%
Effluent Impact
~ (Camp Mesa) 2.0E-2 uCi/sec
~~4.81E-3 mrem/yr per uCVsec~~
~~1 yr/8766 hrs* 60 hrs= 6.58E-7 inrem per year~~
~~4.81 E-3* mrem/yr per uCVsec from ODCM Tabl~ 2-6 85-14' SO123-ODCM-B Revision 6~~
~~.. 08--09-12~~
~~SUBJECT:~~
Uni~ 2f3 Bulldlng/Ventilatlon Envelopes/Turbine/MSIV J~nuary 13, 2012 Areas; Revision 1 Attachment B Units 2 and 3 Turbine Building Leakage and Gland Seal Steam System Release Calculatlon Assumptions
~~Each unit *seal steam operated for 8766 hrs/yr~~
~~2408 lbni/hr Is dlscharg~~~
~~No detectable Primary to Secondary Le~k~~

~~Steam Generator tritium activity Is 1E-5 uCl/cc due to diffusion~~
~~82 Cl/yr of gaseous 3H released from Plant Vent Stacie (2010 ARE RR)~~
~~870 Ci/yr of liquid 3H released (201 oARERR) * '~~
Condensed steam I~ contained In air ~ water vapor at 100% humidify Since tritium Is not released from the Condenser Evacuation System, only non-condensable gases, the Plant Vent Stack Is used for this calculation.
~~1lbm of saturated steam = *334 ft3 (Steam Tables) .~~
~~1 m3 of air contains 30 g water vapor at 30 C° (100% humidity )~~
~~1 ft3 = 0.02813 m3~~
. *calculatlons
'Tritium Release Rate Into atmosphere 2408 lbm/hr
~~334 tt3/fbm~~
~~0.02813 m3/tt3~~
~~30 g/m3~~
~~1E-5 uCi/cc~~
~~1hr/3600 sec~~
~~= 1J~E-3 uCi/sec Effluent Impact Dose (Camp ~ese) 3 H: 1.9E-3 uCVsec~~
~~4:81 E-3 mrern/yr per uCi/sec = 9.14E-6 mrem/yr 4.81 E-3 mrem/yr per uCi/sec from ODCM Table 2-6 85-15 S0123-0DCM-B Revls1on6 08-09-12~~
~UBJECT: Units _213 BulldlngNenijlatlon Envelopes/Turbine/MSIV January 13, 2012 Areas*, Revision 1 Attachment C Units 2 and 3 Atmospheric Dump Valve Release 9tlculatlon There are two atmospheric dump valves per unit wtth'a maximum total of 1.5 E6 lbnv'hr of relieving capacity depending on plant co_ndition such as decay heat history, etc. If the valves are used during normal plant operations, they are throttled to a fraction of the maximum relieving capacity.
$eC<)ndary systemstritium activity is due to diffusion across the Steam Generator.tubes.
Assumptions ,

~~Each unit dump valves are operated continuously at 100% for 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months per year~~
~~1.5E6 lbmlhr Is discharged . .~~
~~. No detectable Primary to Secondary Leak~~
~~Steam Generator tritium activity is 1E-5 uCi/cc due to diffusion~~
~~82 CVyr of gaseous 3 H released. from Plant Vent Stack (2010 ARE RR)~~
~~870 Cl/yr of liquid 3 H released (2010 ARERR) .~~
Condensed steam Is contained In air as water vapor at 100% humidity Since tritium Is not released from the Condenser Evacuation System, only non-condensable gases, the: Plant Vent Stack Is used for this calculation.
~~Qgm . . . .~~
* . 1lbm of saturated steam ., 334 ft' (S1earn Tables)
~~1lbm .:. 2200 g . * . . .~~
~~1 m3* of air contains 30 g water vapor at 30 C° (100% humidity )~~
~~1 ft'= 0.02813 m3.~~
~~CaJculatlons Tritium Release Rate Into atmosphere 1.5E6 lbm/hr~~
~~334 ft3/lbm~~
~~0.02813 m31ft'_~~
~~30 g/m3~~
~~1E:s uCVcc~~
~~1hr/3600 sec~~
~~= 1.2 uCVsec Tritium Curles released Into atmosphere 1.2 uCVsec~~
~~100 hrs~~
~~3600 sec/hr* 1E-6 CVuCI~~
~~2 units = 0.8 Ci Percent' of Tritium Curles Reieased from Plant Vent Stack 0.8 Ci / 82 Ci (PVS)~~
~~100 = 1.0%.~~
~~Effluent Impact Dose (Camp Mesa) 1.2 uCVsec~~
~~4.81 E-3 mrem/yr per uCi/Sec~~
~~1 yr/8766 'hrs* 100 hrs :ii 6.58E-5 mrem for the year 4.81 E-3 mrem/yr per uCVsec from ODCM Table 2-6 B&-16 SO123-0DCM-B Revision 6~~
~~,08-09-12~~
~~SUBJECT:~~
Units 2/3 BuildingNentilation Envelopes/Turblne/MSIV January 13, 2012 Areas, Revision 1 Attachment D UnJts 2 and 3 Atmospheric Dump Valve Steam Flowrate Calculation NN 201286374 SPT 5 Results:
'The Tab "Summary Table" to Microsoft Excel spreadsheet "stmflow.xls" attached to this notification**
~~SPT assignment contains the table/methodology to estimate steam flow out of an Atmospheric Dump Valve (ADV) for various valve positions and steam generator -pressure ranges.~~
~~Background:~~
Steam Flow Instruments are not very accurate at the low flows of an ADVs, therefore it was decided the best/most accurate way to determine ADV flows at various ADV positions and steam pressures was to utilize the SONGS Simulator to attain flow values. The rational Is that the simulator is model
~~for SONGS so It should provide good predicted values.~~
~~Twelve simulator runs were completed. One run for each of the following ADV open positions: 5%,~~
~~10%, 15%, 25%, 30%, 35%, 45%, 55%, 65%, 80%, 90%, and 100%. The runs were started with simulator set for normal operating temperature (NOD and pressure (NOP) with plant In Mode 3.~~
~~The ADVS were run up to position slightly above the runs ADV position. For example .for the 5%~~
run, then ADV W8$ at 5:1 % open. The steam generator pressure was then allowed to drift down.
The flies* from these runs data fifes were puUed. The* data flies contain five data columns. Data columns were for time into the run, AQV #1 position open, ADV #2 position qpen, Flow from ADV
1 in million lbm/hr, *Flow from ADV #2 in million lbm/hr, steam generator #1 pressure in psla, and steam generator #2 pressure _In psla. Simulator _George Marengo provided these data files to Main Steam System Engineer Danny Lowenberg.
(Those files are being stored In the "reference" section of the Main Steam System Notebook. To get to these_ flies go to ~ata3 911 .sos2/ME&SE Library/Engineering Notebooks/ MSTM/References.
The spreadsheet "stmflow.?(ls~ ~m also be stored h~re.) *_ * *
Each file was used as Input for the appflcable valve position tab on Microsoft Excel spreadsheet nstmflow.xls". It was observed aj very hlgti p~ures that the ADV flow.increased*wfth decreasing pressure. until a certain pressure was reached based* on ADV valve position, then ADV flow would start to decrease with decreasing pressure. For the generation of the applicable valve position tab on Microsoft Excel spreadsheet "stmflow.xls" the steam generator pressure of highest steam flow was identified. Data fields from the data files for various pressures were copied onto the applicable valve position tab on spreadsheet nstrnflow.xls". TI:ie (jata fields were always at slightly higher pressure then pressure desired ensuring conse~ve flows were attairJ8(t. On the valve ~ltion tab the data was then summarized In table by using ADV #1 flow and ADV #1 pressure with the pressure rounded to *down to whole value. The maximum .pressure In the table was pressure that
~~had the highest flow. This summary table from the Individual valve position tab was-then used as Input to the Summary Table In the "Summary Table" tab of the spreadsheet.~~
~~85-17 . SO123-QDCM-B Revision .6 08-09-12~~
~~SUBJECT:~~
Units 2/3 Building/Ventilation Envelopes/Turbine/MSIV Janu~ry 13, 2012 Areas, Revision 1 Units-2 and 3 Atmospheric Dump Valve Steam-Flowrate Calculation*
NN 2Q1286374 SPT 5 The Summary Table results were compared to results attained tram* actual ADV flow test on the units durlnQ the 1986/1987 time frame. Memorandum for File dated March 26, 1987,
~~Subject:~~
Atmosphenc Dump Valve Capacity San Onofre Nuclear Generating station, Units 2 & 3 contains summary flow results of the testing corrected to 900 psia. The 100% open nominal flows in lbm/hr were 816,478 (3HV8419); 804,240 (3HV8421); 885,660 (2HV8419); and 800,320 (2HV8421). The Summary Table value for 100% open at 900 psia of 837,690 compares favorably with the as found test values. * ** * -
The Memorandum for FIie provides additional flows* corrected to 900 *psia *of other valve positions for 2HV8419 and 3HV8419. A comparison of the test nominal flow values at various positions to
. Summary Table flow values is provided below. Again the Summary Table values compare favorably with the test values.
Summary Table Valve Position Flow- Position
~~Flow 3HV8419 . 68% .546,809 65%' 543,370~~
3HV8419 50% 354,861 45% 375,350 3HV8419' 40% *231,596 35% 289,730 2HV8419 64% 583,040 65% 543,370
~~, 2HV8419~~
~~23% 119,860 25%~~
208,420 The methodology for use ,Is CQnservatlve In that It will in generally give greater values for flow than expected. The only non-conservative direction is that for brief open spikes tn* valve 'position (<15 seconds), the maxrmum valve pasition does not have to be used. The methodology for use is
~~contain at top of the Table on the Summary Table and is repeated *below.. ..~~
Usage Instructions Enter Column for percent valve open :and row associated for associated SIG pressure (Pl 1013/1023) read the corresponding ml lion Lbmslhr in flow. If- actual pressure >max reading for associated vaJve position, then use the highest flow value for that valve position. 'Mien actual steam generator pressure Is not listed, then use the pressure In table that is just a~ve actual.
When actual percent open is not listed, then use the percenfopen in the table that Is Just above actual. For large changes In ADV position or steam pressure, then use smaller duration to giy~
better estimate of flow. Duration should npt be greater than 15 minutes unless steam pressure*is stable. Typically should use the highest open position during an duration. If the highest open position was held for less than 15 seconds, can use the highest position that valve was at or above for at least 15 seconds assuming duration period for flow calculation ts at least 5 minutes.
. Written by: Danny Lowenberg Peer reviewed by: Wayne Hampton 3/16/11 B5-18 SO123-ODCM-B Revision 6 ,
08-09-12
~~SUBJECT:~~
~~San Onofre Nuclear Gen~rating Station Carbon~14 June 18, 2012~~
Production, Release and Offsite o.se Calculation Methodology San OnofTe Nuclear Generating Station Carbon-14-Productionl Release an_d Offsite Dose Calculation Methodofogy p ~ br-, - . ~. ¢/4!fi
\
lilrt-.cl.b,:
~llr*~*
,-,Y-&IZ -
bifu I 1'111 paper ~thll!r.tlldclbl )IIOadrn,a,llll" Xll-14 (C-1~) prG:lldc11,llnd C.1,4ga110W
..-.dvon!:Di~tl tn'lt I! 8tn0nC>~ Nu>irOaiinlt,g Slalon !!ONQ81. Tllo C-1-4~
~tv'Tnlil in ~ to Mtlmn ~ 111'11¥"11'IT'fl'I e '1,4 ti . . IIINGW MN 'lllJellal. . .
'11'11Hal!rnill' 91DW-~ "1 0l'd!I Ill ITIMi ,M lf'f:J°'dli:i111!111:1 lno7JIOl'8!I C-1, In ltillH' f;IIQW'II' plant 2'110 Ar.fllaf rulCIJCIIQ;,'ye Efm't RemN ~ ~l:Rllt). 1ba ~14 ~or.
-~~16!rr~W 1-ba-.ilQOl r'l'l~1PJidii cllnE.f'RIFo ,pg,t 10211ce. ~ I.A :Ctlll.iotl-1<1 In Nue..ur ~ P!M! (3agou, ~ p ~ 2 0 1 0 .
Thi! lffllllrlltl'II le tP,llllllli.fr.r ~ C-'H QIIYoll.l mllfflse aott.~ ~net dole C O I i ~ fer' "ncw'an n uure * ,._~~-
86-1 S0123-0DCM-B Revision 6 08-09-12
~~SUBJECT:~~
San Onofre Nuclear Generating Station Carbon-14 *. June 18, 2012 Production, Release and Offsite Dose Calculation Methodology
1.0Scope ..
This paper documents the methodology for estimating carbon-14 (~14) production and C-14 gaseous waste
effluent source terms at SONGS Unit 2 and Unit 3. C-14effluent'source terms are used to estimate*
radiolog!c:al doses from C-14 In site gaseous waste efflyenta. These estimates. are generated In order to meet NRC requirements to Incorporate C-14 in nuclear-power plant 201 OAnnual Radioactive Effl~ent Release Reports (ARERRs). The C-14 production and effluent s~rce term eatlmates are based.on EPRI
methodology provided in EPRI Report 1021106, Estimation of Csrbon:-14 In Nudear Power: Pjant Gaseous Effluents, December 201 o. This paper Is applicable for estimating C-14 gaseous release activity and close components for Inclusion In future SONGS ARERRs. . *
2.0 Background - NRC Updated Guidance on Rep~rtlng Routine Rele~*
NRC regulations establish limits for rad1onuclideslhat potentially (µ.Jld be released from a nuclear power plant. There are a lbnlted number of radlom~ldes that* are ~ -in sufficient quantit;ies, ~
concentrations at any site to warrant reporting to the agency. Under guidance Issued by the NRC in 1974, nuclear power plants treated all radionuc:lides ea "principal radionuclldes" end performed sensitivity analysis *.
to determine the radionuclides that !)ad to be lncl.uded In their annual reports:
In June 2009, the NRC provided revised guidance In Regulatory Gµlde 1.21, Measuring, Evaluating and Reporting Radioactive Material In Liquid and Gaseous Effluents and Solid Waste, (RG 121) Revision 2, establlshJng a rlsk-lnforri:ied approach for identifying principal radionuclldes. SGE; is not commltteq to ..
Implementation of Revision 2 of RG 1.21; SCE Is committed to RG 1.21 Revision 1. However, there la new g u ~ ln_Revlslon 2 on the reporting of C-14 re1e:ases that is Informative and useful In the preparation of the Annual Radioacttve Effluent Release Report.
In Section 1.8 of Revision 2 of this doCtment, the NRC revised guidance states, "If adopt-,g a risk-Informed perspective, a radionuc:llde Is considered a principal radionuclide If It contributes either (1) greater than *1 % of quarterly or yearty dose limits or (2) greater t,han 1% of the activity of all radlonudldes In the type of effluent being considered.* ,
In Section 1.9 of Revision 2t, the NRC states, "Radioactive effluents from commercial nuclear power plants ... have decreaeed to.the point that carbon-14 ls likely to be a principal radlonucllde... ln gaseous
affluents.* In other words, while *re1eases of car'bon-14 have not increased, licensees' actions to reduce the quantity of radioactive effluents have been sufficiently successful that the dec:Bne In releases of other radlonucll~ now makes carbon-14 a more significant contributor In relative terms.
The~ section goes on to state, "Csrbon-14 releases In PWRs occur primarily as a mix of o~nic carbon and carbon dioxide released from the waste gas system ... Because*tt,e dose contribution of carbon-14 In *
'liquid radioactive waste Is much leas than that contributed by gaseous radioactive waste, ~uation of carbon-14 in Uquld radioactive waste is not required." {emphasis added}
Section 1.9 of this report also specifies that, "The quantify of carbon-14 dlSCharged can be estimated by
. sample measurements or by use of a normalized carbon-14 sou-ce term and scaling factors based on power
.~neration ... , or esti~ed by use of the GALE code from Nl,JREG-0017: {emphasis added}
The NRC has clarified to EPRI and NEI that C-14 production estimates may be made using EPRI
. methodology (provl~ In EPRI Report 1021106). The EPRI methodology was developed because the GALE code*from NUREG-0017 has no provlalon for C-14 production or release as a function of reactor power. The EPRI rn:ethodology estimates full power C-14 production rates for BWRs and l?\IIJRs using (1) either two or three unit specific core neutron flux energy groups, (2) "effective" neutron cross sections for the neutron energy groups, and (3) unit speclflc coolant mass*~ to the core ne~ flux. The EPRI report also summarizes dlstrtbutlon of C-14 source terms for gaseous, liquid and solid releases in* BWRs and P'Mu

~~based on C-14 measurements cited In literature.~~
~~86-2 SO123-0DCM-B Revision 6 .~~
~~08-09-12~~
suB.JECT: San Onofre Nuclear Generating Station Carbon-14 June 18, 2012 Proctuction, Release and Offsite Dose Calculation Methodology 3.0 EPRI Methodology ~r Estimating C-1~ Production Rate In p~
Equation 1 Is used to calculate the maxlmt.m annual production rate of C-14, PRMAX, In curies for each oolt
{operating et full power (FP) for one year) vie the 17O(n,a) 14C end 14N(n,p)14C reactions: , .
PRMAX *.. N * [ ~ + !24!§1/4 + <J'.t!<2i
~~1,QE-24~~
J
M
~~3, 1536E+ 7, Cl.yr - * [Eq 1]~~
.3.7E+10 :
where: *
= 1.27E+22 atoms 17O/kg H2') or 4.284E+19 atoms 14N/kg-ppm N
= "effective" thermal rlel!iron'cross-sectlon (Table' 2),
= "core average" thermal neutron flux at FP (Table 3), n/cm 2-s .
0'1 "effective~ lntennedlate neutron cross-section (Table 2), *
(jJ, = *core average* Intermediate neutron flux et FP (Table 3), n/an -sec 2 O'f "" "effective" fast net.rtrQn _cross-section (J~e ?),
-'Pr = ."core average* fast neutron flux at FP (Table 3), n/cm2-sec 1.0E-24 = .conversion factor, 1.0E-24 crr.2/bam :.
,i . . - C-14 d ~ constant, 3.833E-12/sec M . = total "ectlve coolant mess" exposed to neutron flux, kg 3.153BE+7 = conversion factor, 3.1536E+7 sec/yr (365 days/yr).
3.7E+10 = ,conversion fador,:3-?E+10 dlslntegrati~i Table 1. SONGS Active Coolant Mass'., and 100% Full Power Values Active Coolant Volume"" Active Coolant Mau 1'-I ThennaJ Power Unit 2 784 tr 1" 1 15881.5 ka 3438 MWt Unit 3 . '784ft' 1" 1 ,, 15881.5 ka 3438 MWt (a) Active.coolant volume Is the portion of reactor COOiant exposed to the core neutron flux.
(b) Actjve 009lant volume from N-0220-030 ECN-~~3 . _
(c) Active coolant mass= Active coolant volume (ftj x density correction at 100% power (20-:257 kg/ft3)
. Table 2. "Effective* Neutron Cn:>ss-8ectlona for C-14'Productlon In PWRs1.,
Unit Crosa-Sectlon'"' "O(n,a)'"C Reaction "N(n,p)-c Reaction
' . Thermal 0.121 barns 0.951 barns 2and 3 lntennedlete 0.0291 barns _0.0379 barns Fast 0.1124 barns 0.0436* barns (a) Values from EPRI Report 1021106 based on EP~I methodology.
(b) Thermal S0.625 eV, lr;rtermediate >0.625 eV end < 1 Mev, Fast> 1 _Mey Table 3. "Cora A.vo-" Neutron Flux Values Neutron F1ux'*1 BOC. MOC EOC Av~e Unit Cycle n/cm2s
nJcm2s nlan2s n/, s*
FP thermal flux 3.482E+13 3.684E+13 4.355E+13 3.840E+13 U2 FP Intermediate flux'DJ C17 2.040E+14 2.094E+14 2.129E+14 2.088E+14 FP fast flux'g' '7.356E+13 7.550E+13 7.677E+13 7.528E+13 FP thermal flux 3.428E+13 3.645.E+13 , . 4.369E+13 3.814E+13 U3. FP intermediate flux'"1 1.985E+14 2.064E+14 2.099E+14 2.049E+14 en FP fast flux 1" 1 7.155E+13 7.441E+.13 7.568E+13 7.388E+13 (a) Full Power (FP) flux values from Plant Data Tables (M-38097, Unit 2 and M-38097, Unit 3) - TWo flux energy groups are listed: thermal (S0.625 eV) end !ritermediate + fest {>0.625 eV).
neutron:
(b) lntennedlete =Intermediate+ fast (l+F) x 0.75 (c) Fast .. (l+F) x 0.25 86-3' 50123-0DCM-B Revision 6 08--09-12
~~SUBJECT:~~
San Onofre Nuclear Generating Station Carbon-14 June 18, 2012 Proc;tuctlon, Release and ~!ta Dose.Calculation Methodology.
3.1 R~ Nitrogen Calc;ulatlon During power operation, coolant ammonia concentrations average between 0.6 end 1* ppm.
Equation 2 estimates the C-14 production vie the 14N(n,p) "c reaction using the yearly average ammonia concentration. * **
~~RCS ~. ppm= (ppm ammonia) ~ (14 g N / 17 g NH3) .[Eq2]~~
3.2 RCSNCT Nitrogen Calculation During power.~. coolant nitrogen concentrations ere estimated from Volume Control Tank even*
overpressure: Equation 3 estimates the*e-14 production vie the 1~N(n,p) 14C reaction using the yeerty average VCT pressure, temperature end percent N2 * .
RCS. N, ppm = (VCT ~.mol,e fraction) * (28.01 g N2'mole} * (1 E6 mg/kg) [Eq 3]
/ (18.02 g H20/mole) where:
VCT N2, mole fraction = (VCT Nz, etm,) / [Henry's Constant (Nz), atm- mole N2 / mole H2O]
Henry's Constant, _N2 '!" (-3.6024 ~ (VCT Temp, deg F) 2 + 1284.6
~~VCT Temp, deg F + .9290.5].~~
etm - mole N2 / mole H2O (VCT N2, etm) = [(VCT N2, %)/100) * (VCT pressure, pslg +14.7) / 14.7 3.3 Calculation Results for Estimating ~-14.Produc6on Rates.
Using the EPRI methodology described above In equation 1, the annual C-14 production rates fn each of the* unit are calculated. The-results are reported in-the ARERR.
For each unit, the cyde-averages of the maximum annual C-14 production rate are used for estimating gaseous pathway C-14 activity~ aryd dose contributions _In the ARERR .*
The maximum annual C-14 production rate values are calculated using a PWR spreadsheet developed for EPRI by NWr Corporation for utlllty Information purposes. *
\
86-4 S0123-0DCM-B Revision 6 08-09-12
~~SUBJECT:~~
San Onofre Nuclear Generating Station Carbon-14 June 18, 2012 Production, Release and Offs~ Dose Calculation Me~odology 4.0 Esti_matlng C-14 Gas~us Rala~ses For PVVRa, EPRI Report 1021106 summarized the dlstr1but!on of C-14 In release pathways as follows:
gaseous 90% to 98%;-nquid <1% and solid 2% to 10%. The report alao states that 5% to 30% of C-14 In PWR ~ waste effluen~ exists In the carbon cf10xlde form, which contributes to population dose .via photosynthesis uptake In the food consumption cycle. EPRI Report.105715, Characterization of Garbon-14 Generated by the Nuclear Power Industry, N:ovember 19a5, Gited that the carbon dioxide form ofC-14
~~averaged 20% in.effluents fro_m ~ight US and German PWRs.~~
For SONGS, C-14 gaseous dose calculations in the ARERRs are made using the following assumptions for each unit ( 1) continuous release of the estl~ated C-14 generated during power operation based the number o f ~ full power days (EFPDa) for the period, (2) maximum C-14 activity literature values for gaseous releases cited In EPRI Report 11021106 (98% ), and (3) average fraction of C-14 as carbon dioxide for gaseous releases referenced In FPRI Report 105715 (20%).
. 4.1 Equation 4 estimates the C-14 activity released, Ac-,.., Into the gueoua pathway during the time:
~for'eachunlt. * * - * .-
Ae-14 = PRi.w<
~~0.98~~
~~EFPD I time period, days [Eq 4].~~
where:
PRMAX = -maximum annual production rate of C-14, Cl/yr
~~0. 98 = fraction C-14 In PWR gaseous* pathway releases (maximum literature valµe.ln EPRI Report 1~1106, .~~
~~EFPD = nwnber of effective full power days for the unit during the time period, e.g. quarterly or y~. days *. * ** .~~
~~r,rne period = number of days during the time period, e.g. quarterly or yearly, days~~
4.2 Equation *5 estimates the C-14 activity released In carbon dioxide fonn, Ac.,.,, c:02, Into the *
~~~ u~~
~~pathway during ~ time period for ea.ch 1:1n1t Ae-14. CO2 = Ac-1.,~~
~~0.20, Cl (fort/me perkxi) [Eq5]~~
where:
Ac-u = C-14 activity released into the gaseoµs pathway during the time period for each unit, CVyr .
0.20 = fraction of C-14 as carbo,:i dloxlde*in PWR gaseous pathway rel~s (average vafue In EPRI Report 105715) 86-5 S0123-0DCM-B Revision 6 08-09-12
~~SUBJECT:~~
~~San Onofre Nuclear Generating Station Carbon-14 June 18, 2012 Production, Release and Offslte Dose C~lculation M_ethodology 6.0 C-14 Gaseous Releases Dose Calculations~~
~~5.1 C-14 lnhalatlon Dose Calculation (Reg. Guide 1.109 Eq. C-3) c'14 (r,8) = 3.17 x 104~~
~~Qi c-<< * [X/Q](r,8) where:~~
~~C114 (r,8) = annual* average gr01,_1nd-level concentration of C-14 In* air at location (r,8), pCl/m 3 .~~
QI e-1 = ** release rate of C-1-4, Ci/yr, (Ac.t.<< from Eq. 4) *
[X/Q](r,8} average atmosphere dlspe~on ta,ctor at location (r,8), sec/rri3 (using concurrent meteorology from RETDAS program), this value Is not decayed or depleted since C-14 is released as organic (CH3, etc) or Inorganic (CCh) and Isotope C-14 half-life is greeter than 5~0 years *
~~6.2 C-14 Food ~f:IJway Dose C~ulatlons~~
~~Per the 2011 Land Use Census, the MIik pathway does not CIST8rltly exist at SONGS s.2.1 C-14 concentration In Vegetation (Reg. Gulde 1.109 Eq. C-8)~~
The_concentratlon of C-14 In vegetation ls calculated by 8SSL111lng that Its ratio to the natural carbon In .vegetation Is the same as the ratio of C-14 to natural carbon In the atmosphere surrounding the vegetation. (Reg Gulde 1.109 Eq. C-8) *
~~Cv14 (r,8) = 3.17 X 107~~
p
~~014 * [X/Q](r,8)~~
~~0.11 I 0.16 where:~~
Cv14(r,8) m the concentration of C-14 In vegetation grown at location 1
(r,8), pCl/kg p = 1, fradional equilibrium. ratio, (continuous release) 014 :I amual release rate of C-14 as CO2, Cl/yr (Ae-14. CO2 from Eq. ~
[X/Q](r,8) : = average atmosphere cfisperslon factor at location (r,8), sec/m3 (using concurrent meteorology from RETDAS program) 0.11 * = fraction of the total plant mass that Is natural carbon' 0.16 3.17 X 107
= concentration of nab.Ira! cart>on In the atmosphere, g/m 3
= 1E+12 pCI/Cl
~~1E+3 g/kg / 3.1 SE+7 sec/yr ,~~
5.2.2 C-14 Concentration In MUk (Reg. Gulde 1.109 Eq. C-10)
Cm1 (r,8) = Fm
~~Cv14 (r,8)~~
Q,
~~axp-)J, where:~~
C'"14.(r,8) cv1<4 (r,8) .
= the concentration of C-14 In milk at locatlon (r,8), pCVliter the concentration of C-14 In animal feed, for C-14 tl¥s is the .
concentration of C-14 In vegetation grown at location
_(r,8), pCi/kg*
~~F~ -* average fraction of daily intake of C-14 which appears In mHk,~~
Reg. Gulde 1.109 Table E-1, (~rbon = 12E-2) o, . C amount of feed consumed by animal per day, Reg. Gulde 1.109 Table E-3, (cow= 50 kg/day) exp--Ajt, = 1, due to C-14 half-life greeter then 5000 years B6-6 S0123-0DCM-B Revision 6 08-09-12
~~SUBJECT:~~
~~$arfOnofre Nucl~ar Generating Station Garbon-14~~
~~June 18, 2012 Production, Release ar:id Offsite Dose Calculation Me~odology 6.2.3 c~14 coocen1':!tlon lo Meat (Reg. Gulde 1.1oe Eq. e-12) cF 14 (r,8) = F,~~
~~Cv14 (r,8)~~
~~Ot. e>qJ-).,1, where:~~
C"114 (r,8) = the concentration of C-14 in animal flesh at locatlon (r,8). pCl/kg cv14 (r,8) = the concentration of C-14 In animal feed, tor C-14 this Is the concentration of C-14 i_n_ vegetation grown et location (r,8), pCIAcg .
Fm = average fraction of daily* intake of C-14 which appears In each, kilogram of flesh, Reg. Gulde 1.109 Table E-1 (carbon= 3.1 E-2)
O, = amount of feed consumed by animal per day, -
'Reg. Guide 1.109 Table E-3 (cow= 50 *kg/dey) exp-,1/4 = 1, ~ to C-1_4 half-life greater than 5000 years 5.2A Annual C-14 Dose by f:ood Exposure Pathway (Reg. Gulde 1.109 Eq. C-13)
Leafy Vegetables DF/e-1:'4f-
~~uv.~~
fg
~~C\4 (r,9)~~
~~MIik. = DFle-~* um.* C°114(r,8)~~
~~M~ = ' DFle-1-4Ja~~
~~Lf.~~
~~cF14 (r,8)~~
~~Non-Leafy Vegetables = DF~1-4ja~~
~~lfa~~
f1
~~Cv14 (~.8) where:~~
DFle-t.Qa = C-14 dose converslon*factor for organ (D end age group (a)
Reg. Guide 1,109 Tables E-11 through E-14 .
. where the following ~ fro,m Reg. Guide 1.109 Table E-15:
uv.
fg O"',.
UF
-=
=
Ingestion rate.of non-leafy vegetables by age group (a), kg/yr 0.76, fraction of non-leafy vegetables ingested grown in.garden ingestion rate of milk by age group (a), literBlyr Ingestion rate of meat by age group (a), kg/yr LIi u 11 = Ingestion rate of leafy vegetables by age group (a), kg/yr
~~f1 C 1.0, fraction of leafy .vegetables ingested grown In garden 5.2.5 C-14 Total Dose~~
-~-~1-4 total dose in mren:i at.receptor (r,8) is the sum of the exposure pathways which exlst at that location per the Land Use Census. The hlghest receptor annual dose, age group, crtticel organ, sector and exposure pathway are reported in the ARERR.
86-7 S0123-0DCM-B Revision 6 08:.09-12
SUBJ.ECT: San Onofre Nuclear Generating Station Carbon-14 June 18, 2012 Production, Release and Offsite Dose Calculation Methodology 6.0 References 6.1 Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactive Material In Liquid and Gaseous Effluents and Solid Waste, Revision 2 6.2 Regulatory Gulde 1.109, Calculatiofl ,of Annual Doses to Man from Routine Rel~ses of Reactor Effluents for the Purpose of Evaluation Compliance wfth 10 CFR Part 50, Appendix I, Revision 1 6.3 *EPRI Report 1024827, CartxJn'.-14 Dose Calculation Methods at Nuclear Power Plants, April 2Q12 6.4 EPRI Report 1021106, Estimation of Carbon-14 In Nudear Power Plant Gaseous Effluents, December 2010 6.5 EPRJ Report 105715, Characterization of Carbon-14 Generated by the Nuclear Power Industry, November 1995 8.6 N-0220-030 Rev. 0 ECN A54033, SONGS Units 2 and 3 Transient Analysis Model (TAM): Reactor
.Coolant System Volumes
6.7 M-38097 Rev. 39, Plant Physics Data Book Unij 2 Cycle 17 6.8 M-38098 Rev. 29, Plant Physics Data Book Unit 3 Cycle 16 6.9 Radlologlcal end Dose Assessment Software (RETDAS), Version 3.6, Canberra Industries, Inc.
86-8 S0123-0DCM-B Revision 6 08-09-12
February 2001
~~SUBJECT:~~
Offsite Oose Calculation Manual Changes .
Safety Evaluation fc?r M~ifying References to 10 CFR 50.59 INTRODUCTION .
In IO CFR Part SO, "Domestic Licensing of Production and Utilization Facilities," Section 50.59, "Chang~
Tests and Expenments,' contains requirements for the process by which licensees may make changes to their facilities and procedures as described in the safety analysis report, without prior NRC approval, tmcler certain conditions. The rule was promulgated in 1962 and revised in 1968.
A proposed ne~ rule was published fqr comment in October 1998. Following consideratiqn of public
. comments, on October 4, 1999 the NRC issued.a final revjsion to 10 CFR 50.59 that will become effective*
March 12, 2001. The new program is scheduled for implementation at San Onofre on July 31, 2001.
DISCUSSION Following publication of the~~ rule, the Nuclear~ Imtitute (NEI) submitted a guidance document for the implementation of 10 CFR 50.59 and requested NRC endorsement through a regulatory guide.
Subsequently, NEI submitted dociunent NEI 96-07 for endorsement.
A ~ to Regulatory Guide 1.1~7, Revision 1 ofNEl 96-07,-,'Guidelin~ for IO CFR 50.59 Evaluations,"
dated Nov~mber 2000, provides methods that arc acceptable to the NRC staff for complying with.the
_provisions of IO CFR 50.59. ..
The new IO CFR 50.59 (c) (4) states: The provisions in tiµ~ section do not.apply to changes to the facility or.
procedures when the applicable ~lations establish more specific criteria for accomplishing such changes.
NEI 96-07 clarifies that statement to include 'Offsite Dose Calculation Manual changes controlled by teclmical specifications_.' San Onofre Licensee Controlled Specification 5.5 .2.1.1 provides. the specific criteria for accomplishing QDCM changes.
~~5.52.1.1 Licensee-initiated changes to the ODCM:~~
~~a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain: . .~~
~~1. Sufficient inform8;tion to support the change(s) together with the appropriate analyses or evaluations justifying the cbange(s);~~
2. A determination that the change(s) maintain the levels of radioactive effluent control required by IO CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability, of effluent, dose, or setpohrt calculations. '
~~3. Documentation of the fact that the change has been reviewed and found acceptable.~~
~~b. S~ become effective upon review and approval by the Vice President-Nuclear Oeneratioµ or his designee.~~
c: a Shall be submitted to*the NRC in the form ofa complete, legible copy of tho entire ODCM as part ofor concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by marldngs in-the margin of the affected pages, clearly indicating tile area of the page that was changed, and shall indicate the date (i.e... month and year) the change was implemented.
~~87-1 SO123-QDCM-B Revlslqn 9 08/2016~~
. ( .
February 2001
~~SUBJECT:~~
Offsite Dose Calculation Manual Changes Safety Evaluation for Modifying References to 10 CFR 50.59.
To reflect the changes in the regulatory guidance, ODCM section 63 .1.1.a will be changed as follows:
from:
~~"A smnrnary of the evaluation that led to the detennination that the change could be made in accordance with 10 CFR 50.59";~~
to:
"A swnmary of the evaluation that led to the detennination that the change could be made in'accordance with applicable regulations".
As part of the implementation of the revised 10 CFR 50.59, a separate procedure is being implemented for effluem evaluations. Included in the procedure will be a checklist of related regulations, regulatory guidance, and licensing basis documents to ensure a comprehensive review. The effluent evaluations will be performed by qualified personnel for changes to the ODCM as well as design changes. Other regulatory guidance documents (e.g. NRC Infonnation Bulletin 80-10, NRC Information Circular 80-18, NRC Generic Letter 81-
~~38) also refer to performing a 10 CFR 50.59 evaluation for situations that could affect the control of ,~~
radioactive effluents. Wherever the regulatory guidance refers to a IO CFR 50.59 evaluation that addresses the potential for creating or modifying the control of radioactive effluents, an effluent evaluation using the new procedure will be performed instead.
CONCLUSION The purpose of the ODCM is to ensure compliance with regulations regarding dose and curies released, .
setpoint calculations, sampling and monitoring of effluent pathways, and control and maintenance of radiation monitors. This new method of change evaluation more directly addresses these issues through a set of review questions developed as a method for evaluating changes to the ODCM. These questions will replace the 50.59 evaluation and will be used to assess the effects related to ODCM changes.
Effluent evaluations will be performed by qualified personnel in accordance with a site-procedure to ensure compliance with all applicable regulations and regul~ry guidance. As such, there will be no increase in radioactive effluents released to the environment and no increase in dose to a member of the public.
87-2 SO123-0DCM-B Revision 9 08/2016
. February 2001
~~SUBJECT:~~
Offsite Dose Calculation Manual Ch~ges S ~ Evaluation for Modifying References to 10 CFR 50.59 I. ¥ay° the proposed activity increase the probability of occurrence of an, accident evaluated previously in the S;llfety analysis report?
No.
The Licemee Controlled Specifications provide the guidance necessary to ensure that OOCM changes reflect the requirements of the specific controlling regulations. The ODCM has no effect on tl!e probability of
~~accidents and therefore this change will not increase the probability of occurrence of any previously eval,uated accident~~
~~2. May the proposed activity increase the consequences of an accident evaluaied previously in the safety analysis reJ)C?!t?~~
No.
The proposed change is an administrative change that does not affect operation of equipment or ilif: facility. It does not influence any credible ~cident at Units.2/3 - a release due to leakage or failure of a radioacti_ve waste system (section 15.73.2); and the postulated failure ofa liquid. tank (section 15.7.~3). As sucb;this .
activity cannot increase the consequ~ of an accident previously evaluated in the UFSAR.
~~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.
Toe ODCM bas_ no effect on the opera~ility of ~y .equipment,. It pro'1des guidance for detennining whether
. some equipment important to safety is operable and in some cases provides compensatory action to mitigate for inoperab,e equipment used to ~Jlect., transfer, treat, .or discharge radioa.ctive_eflluents. Therefore this change has will not ~ e the probability of occurrence of a malfuncti~n of equipment important to ~ety.
~~4. May the proposed activity increase th!' consequences of a malfunction of equipment important to safety~~
. evaluated previously in the safety analysis report?
No.
The pDCM does not alter operation of important to s.afety equipment nor does it change the frequency of operation of the equipment, it cannot increase the consequence of a malfunction of equipment important to safety evaluated previously in the safety analysis report. *
~~5. May the proposed activity create the possibility of an accident ofa differenJ type than any* evaluated previously in the safety analysis report?~~
~~No.~~
Operation _of plant equipment is not modified by this activity and therefore cannot create the possibility of an accident of a di:fferen~ type' than any eval~ed previously in the safety analysis report B7-3 S012WDCM-B Revision 9.
08/2016
February 2001 .
~~SUBJECT:~~
~~Offsite ~ Calculation Manual Changes Safety Evaluation for Modifying References to 10 CFR 50.59~~
~~6. May the proposed activity create the possibility of a malftmction of equipment.important to safety of a different type than any eyaluated previously in the safety analysis report?~~
No.
Toe ODCM does not alter operation of important to safety equipment nor does it change the frequency of operation of the equipment. The proposed change creates a set ofsqeening questions that ensure that ODCM.
~~end design changes* are reviev,:ed for their effect rel~ to applicable regulatiom and controlling dqc~ep.ts ..~~
These questions require review of specific regulations, licenses, and safety analysis reports. Changes to the new method will not create the possibility of a malfunction of equipment important to safety of a different type than any evaluated previously.
~~7. Does*the proposed activity reduce the margin of safety *as defined in the ha.sis f~rtechnical specification?~~
No.
The Licensee Controlled Speciflcation currently requires and will ~tinue to require (1) justification for ODCM changes, (~). no adverse impac~ to effluent controls, and (3) documentation of adequate review for acceptability. Currently, changes to the ODCM are evalUBted using the 10 CFR 50.59 process.
The current process ensures that the ODCM provides adequate instruction to.ensure that the requirements of applicable regulations are fulfilled.*Tbe proposed process will specifically callout each regulation against which changes to the ODCM are to be evaluated. Evaluating ODCM changes against these priteria bas been, and will ~ntinue to be, the standard. The new methqd simply will emure that aJl applicable requirements are.
considered. Chemistry procedures changes and review question development are in progress that will emure the Technical Specifi~on requirements are met and that there ~ no reduction in the margin of safety. There will be no resultant dose*to a member of the* public and no reduction in the margin of safety for any licensing specification .or in the control of radioactive eflluen~ as required by 10 CFR 2Q and IO CFR 50.
B7-4 S0123-0DCM-B Revision 9 08/2016
~~Title:~~
Site Boundary Sample Garden Relocation .
Activity/Document Number/NN: 203063159-084 Brief description of activity: The garden relocation is needed to accommodate changes in the owner controlled area, and the need to provide irrigation for sample viability in drought conditions. The new location remains in the same downwind sector (highest D/Q sector) as the current garden location (Sample collection performed in lieu of milk sampling due to the absence of dairy farms within 30 miles of the station). This new location is in the same sector as the current garden (location #6) , but in the middle of sector R (NNW) vs. near the border with sector A (N). However, dispersion modelling assumes a sector average value across the width of the sector at a given distance thereby averaging out small differences in the compass direction within a primary wind sector. The new location is also further out (0.7 miles from the center point between the Unit 2 and Unit 3 vent release points vs 0.4 miles from the current site boundary garden which is necessary to accommodate changes in the owner controlled area).
The additional distance does not change this garden as the controlling location for most radionuclides. This new location is adjacent to air sampling station #11 and will be designated location 6'; a location with functional irrigation . This will ensure adequate samples during harvest; a challenge during the 6 year drought with the current garden location 6. This location is also located on SONGS controlled property enclosed with a chain link fence. With the decommissioning and deconstruction of SONGS structures on the MESA, the current garden is no longer on property controlled by SONGS; it is on property returned to the Department of the Navy. The ODCM will note the date of the location switch, and it will be mentioned in the annual AREOR so that any trend shifts/changes in analytical results not otherwise accounted for may be attributed to the increased distance from the plant.
New SONGS Garden Location, 6', at AP sample location 11.
Performed by Qualified Screener: David A Montt Date: 01/15/2015 Independent Reviewer: Mark Strum Date: 01/19/2015 Approved by Supervisor, Effluent Engineering (or designee)
Carla Cook Date: 07/15/2015 88-1 SO123-ODCM-B Revision 9 08/2016
~~SUBJECT:~~
~~Correlation - Effluents and Environmental Data Nowmber 4, 2014 B. D. l1ETZ~~
~~SUBJECT:~~
~~COIT9latlon - !flluents and Erwlronlnental Data R!f'ERl!NCE8:~~
~~1. Memofllndum M Goedera to~ Goldin, Feb!Uary 28, 1994, Oo<<nenlatlon of the Correlation Study for 1992~~
~~2. Memorandum for Fie, EM Goldin, February 13. 2004, Con1)lance with 10 a:R eo, Append:< f, SecGori NB. AR 0401O14S-1~~
~~3. S0123-IX-1.10;Revlew, Analyels Md Reporting cl Radlologlcal Envtolu11911taf .~~
~~Montollng Program (RfMP) Date. Rev. 10~~
4. 2013 Arlnual Radla!oglcal Enm>nmental Opera~ Report. San Onorre Nuclem-OemlnClg SCalon Unltll 1, 2, & 3, May 2014 OBJECT1VE: RagulalcM In 10 CFR 50, A ~ I, ~ N B . Subparagraph 2 raqulres "data on ll1t!IIISla'8bl levef11 of radudoo and f8<lloaotlve ltl818rien In the erNlronment to avab..lalQ the reilatlonshlp between (llJ8l'1IIIIM of radmolYI mal8rlal relea88d II effluant& and resutant radletlon do8ea ID lndlviiual& .*. " Thill memorandum nr.48wB the ewluatloo rA 1he relallonshlp betwaen effluent releateS and doae& a! 888a)'Dd by 1he Raclaloglcal Emlroomental ~ n g
~(RB,F).
Dl9CUSSION In the 1990'1-, 88dl year an analyst& Wa& l)G(fa,,a:l lodelm'mlr111 lhe rele1lonsh,'p be4weefl .
8lluant RIIN8ae and en\llronm8ntal &ample reeolla. hi 8X8ml]te of a \181Yrlgorous calculallon may be found n RiMnl4 ioe 1. That level of eva1ua11on was d8lem'i'led lo 1>e unnecessary .
(Referenoe 2) as long aa ectlons were In place 10 trigger an 8'MJ8tion r BrMl'Olimertal samples exceeded som6 ~ wluea.. This po8ltloo W8II de>.leloped beealiae* *
~~Based on an aoeakllal Industry SUMI)', many nuclear plants kl lh8 US do not conduct any spedflo evaluation on an annual basis (existing REMP lW1d El'fluarlt program c:ontrolll eatlafy the requnment)~~
~~REMP samples rarely indlcete a n y ~ plant-related ,acioactlvlty In the plant effYirom (l.o. there .oan be no pubftc dou I llere Is oo detedeble radlol!otMty In the lrnmedlale envtrorunnnt)~~
Many plaita t,lggec' an ""lu&tlon when REW eemplea exr.eed lnw<<Hgahl 1&"818 In ordat to ensure that a proper'evaultlon \'IOIJld ba completed If 1"1808ssary, Relerellce 2 recommended J)l'008du'e changes ti h::orpo~ scion levels. ThaC wa cor,'llllet8d and the followk,g requlrementa ere in plaoe; ProcedlX6 S0123-IX-1.10 (Refe,ence 3) inoludee the folbmg reqLirementa:
~~89-1 SO123-ODCM-B Revision 9 08/2016~~
~~SUBJECT:~~
Correlation - Effluents and Environmental Data. -
B. D. Metz Cormlallon - Effluents and Environmental Data Nowmber 4, 201.t 6.2.2.2.4 IF any REMP sample 1'8$Ub excaad admn!Slnltive llmis and lllll varlfied lo be aboYe the detection Omit, THEN the Redologtca l EfflUGnt arn:2 Enw'onmerrlal Speciallal Of deaignea SHALL either resolve lhe ls8u& by labOC'ato!)' l'800llnta or addlllonel eamplng, or generate a Nolflcetlon with a task asslgried to D1e Radlologlcal Effluent and En-Aronmenlal Specialist or deslgnee lo ewtoote the data 6.2.2.2.5 If any REMP aarnple reruts wccaed tha adm!nls!ratlve liml~s) and the resub rire aJao greater than the detscllon li'nlts 1hsn gonerate an !Xiditlonal task aaslgned lo Radla1lon Pro(eotlon requestng a peer check of the Redlologlcal Effluent and Engineering Speclall&ta' evalutrlloo.
6.2.2.2.8 A &I.IITIINlry of the dam e'llalliaaOll 8llall be k1duded tn the Annua I Radiological EIMroomental Operating Report {AREOR}.
e.2.2.2.1 The lnvestlgetion SHALL 001nperB lhe expected conc:entrallon of radlonucldes Ill REM? samples lo that aetuelly obsenl8d. 01 pto,Ada a ~a for explalnlng why the cleteclon d radlonuc#des r1 lhe REMP sampte(s) should be expected Ill the obseMd leYe(a..
Theee prooedural requk-ements adeque&ely 11 ~
~~the regulatory requtemem s for 1!11'1 evaluation of the relatlon&hlp, Bhould one ever ne!MJ to be completed.~~
SONGS COMPLIANCE FOR 2013 The 2013 Annual Radlolol}lcal Enwonmemat Operating Report (Reference 4) Included the folowng \18fbiage (page 29):
L Correlation of Effluent Com:entra tlone to Conc:eutra tlons In the 6m'lrolmlent In aceotdanoe with 10 CFR 50 Appendix I, 1\1'.b.2 d8la oo measurable levels of raciallon and redloeoelve meieria. ~ \he environment haw been t!Wluated lo detemme !he relatlonehlp betwei,n quanDIIM of raclloacltY8 materlal released In effluents end resultsra radiaHon ~ lo lrn:lvldualri' from prlndpal pslllwaya rl eicpost.n.
The REMP aol C&-137 kwels In the cootrol and lndcator samples are 11lmlstlcatly equfvalent, leading to the conolu8lon lhat Cl:-137 In 808 ls allrlbotable to residue!Jal oul from ex1emal anthropogenic factonl such Iii ~ t 'MeaJ)onS teatlng, Chemob)I. 811d F~aDa Hchl.
Data from 2013 contlnuo lo GUpport lhe ~ oancluslon that the mel!l8lX8d concentrallon of t-13 ~ rn kelp Is not lllCf888lng near SONGS. and 16 not atan&fioally hlgh81" sround SONGS lhan It 16 at the oontrol locallona. 1-131 k'l kelp Is due k> the relsase of medical edmlriatra1ion& to too ooeen from sewage weatmsnt racllllles. The effluent based comilalion calcu1aDon lndlcet&s" that 1-131 acllvlty In kelp altrlbwlble to the oparallon of SONGS would~ l.lldelecl2bla and the resul\anl. doae8 to lnd!Vlduais WOIJtd be neg/lglbl&. I 89-2 S0123-0 DCM-B Revision 9 08/2016
~~SUBJECT:~~
Correlation - Effluents and Environmental Data B.O.~ Corre!etion- Eflllenta and Envtronmenlal Data NoWllllber 4, 2014 The data from sir &emplars olose to SONGS. tlVI data tom air aamplers furt\er &:wefi, and the data from Ille Ocaanskl& contl'ol eampter are statlstically equal This wording addresses tie queallon l'8Q'l'dlng tie evaluatlOl'I bu: not 'Y8l'f c:leariy Therefore, the follo,Jng soot1on, appllcable t> the calender yw 2013, Is reoommended forfUturs AREOR&:
Ra.IP 88l'IIJ)kls. bo1tl tetren1al end marine. lndka1ad no aoeumulatlon of ptam.related radl08Ctivlty In th9 environs. No fiSmples. as shown In Table 8-2, exceeded ln'i8Sllgallon lewla and, In facl, all asmp1es with deteotat;e aotMty were nae stallsllcaJly lilfefent from eonll'ols 8l'ld were thereforo atlributed t, ~ e d souroM ..; peirt nuclesr weapona fallout. Chernobyl, Ftlwahlma, and medlcal Iodine releasee In 6&W81'8ge. Al.
such, the operaloM of SONGS did not haw any measurable e8ect on the enwonment.
Tha regwrtocy requlrament to evall!1e the relatlonahlp ~ QUMtlliaa d rat1oaa1ve matertals ~ 11'1 ~ 1111d the lll8Wla'rt radla6on d068$ to lndlvid1DS may be eu1Ml-1zed by 1hG followi,g oonolusion:
Efluent program rel9asn 111'8 9V81ualed annualy lo delermlne the reoeplor(a) with fhe hlQhes( hypolletlcal d01&. REMP alll;lleB colleoW lhrQJgh the >'8Sf lndlcaled no llgnlfloant aocunuldon of plant-re1aled ~ l y above CX>MOI l0odons. therefore pl'0'11dlng aaurance that the eft.l8l'lt program projections .-e conalsteritMlh radloklglcal envlronmenlsl fTlllUUf1lffl9n The 001 IGei dlmit.118 of plllnt-relaled radioactivity lo
'GOVln:lnmental aamplea were leea than expeoted baeed on eCuenf ~ fla1her demonatratlng program eonaervahm.
Prepered*by November ... 2014 Ede Goldln, CHP cc: C. A. Cook J.B:Jmlke J.B. Moore (BHI) 89-3 S0123-0DCM-B Revision 9 08/2016
Remove Controlling Location Factors Tables 2-7 and 2-8 (South Yard Facility and North Industrial Area) and Associated Ri Tables in Appendix A from the ODCM Remove Cootroffng LocaUa1 FactDrs Tablas 2-7 and 2-8 (South Ymd Facilb' and North ln<iJstr1al Area) and Assoclated RI Tables In Appendix A ft"om the 00CM
~~References:~~
~~1. 12/11/94 EM Goldl'I to PK ChanO. Souttryarcl Facility Disperslon and Deposlbon Faclors for Poertial Normal Gaseous Blh.lent Releases; Detetninatlon of Corr1)llanc8 with 10 CFR 50, Appendix I~~
~~2. 'lllffil .JW Scott mD llck. 2001 Dose Parameters for SONGS Unit 1 and Units 213~~
~~3. :zJ:1 W8 .1N Scott to D Dick, 2008 Dose Parameters for sat Onofre N u c l e a r ~~~
~~SlaHm~~
~~4. 219111 JW Scott to L McCann, 2011 Ckse Pal3meters for San Onofre Nuclear Generalktg Stmial Soulh Yard Facllty and North lnwslrtal Area~~
~~5. ~ RegulatoryGUde 1.21, REw. 1, Measoong, ~ and Reporllrig Radloadlve Mat8l1al In LJqusd and GaseaJs Effluents and Solid wastf3 -~~
BackglOUnd:
The Ollglnal Offsl1e Dose Calcutatlon Manual (OOCM) applied to SONGS lJrlt 1 Oliy. Once Units 2/3 wete ~ a separate 00CM \ICIS aeated for lhos8 two newer unilS. In rater Y83JS. dose paametertableS {Ri) and effluent calcuatlm provJsionS were added to the 00CM fortha South Yam Faclll.y (SYF}, see Refaeim 1 for the earlesl analysJs. Eventucdly after lln!t 1 was permanently rettred from 581Vice, the lJrit 1 ODCM was comblned wilh lhe IJntls 2/3 ODCM and a slevmle document was a-sated (References 2 and 3). The area lhal housed lJnlt 1, desl!;lnaled as lhe North lndUsb1al Ama or NIA. aJter lJnA demolition, was ~ for pdedla!fy conlandl ialed equ4Jnent staging, such that everiualfy dose J)allalt l8lefs tables for the NIA were Included In the sinole 00CM In place of the untt. 1 tables Clscusson:
In late 2014, radloadJviel,J cootamlnated equipment was removed from_the NIA and that area was lllleased from Restr1cted Area (RA) ~ some of.the SYF was atso l8l110V8d from RA status to SUW()rtequlpment stalJll:l9 fa- SONGS decornmlsskll1Y There IS no longer an aiJbom8 racloattlve effluent sotR0 al eitherlhe NIA or the SYF. Toeretore, there is no rl88d for Controllng l.ocatlon Fadors or R. tables In the ODC~ for these tm areas.
The Glossary In Ille most recert Reference 5 (ReViSion 2. 2009) defines the points that reqwe IIICldtoiiJig.
=
oignibu release poim-ADy hx:aicm, from v;iJich i:adioatti'R! material isidmsed.. that
~
(1) W1Ud (2) noble gases di,chmgied to the !libIJOll!bmi in~==
aimibu!n greater1hm 1 pt'ftm otfiie adMty disclmgfld fum all tJie: Jdease paints fiir a of efllueDt CtllSidimd. Regulmory Guide L109 lim the lmee ofefBqem as waS1e..
111d (3) all ofii!5r radimm:Jides rfiscbuged to t h e ~ in gaseous radioactive Wll51e.
B10-1 S0123-0DCM-B Revision 9 08/2016
Remove Controlllng_Locatlon Factors Tables 2-7 and 2-8 (South Yard Facllitt and.North Industrial Area) and Associated. Ri Tables in Appendix A from the ODCM Evan t h e ~ 1 (19!4) of that RQJlatozy ~ ~ t h a t
~ ll**l*BHl&..hr,mdbl!~akm;~ g;ISIICMS"efflm!Dtdi.dmppaths..
Since the NIA no lollger 1)35 MY radioad!lle material other 1hal the Unit 1 Reactor Pressure V8SSEII, a sealed soid radioactive waste container and lf1e ISFSl, housing only sealed airtight canister.:l, ald the SYF Is no lonOer used for any signlfi:ant radioactive 8QUIJ)ment refurbishment, neither of these locallons Is caisidered a ~ release ~ nor a "pmcipaJ discharge path" and theref<<e do not leQldre aiboma effluert monlt011ng. As such.
them is no need r a - ~ locatlon factors Of doSe parame1e!s spedllc to either area 'in the ODCM. Note that Reference 4 pointed out that there were no airborne effluent releases from the SYF ewn In 2011 duJtng suppot1ilg q,era1lons of Unts 213.
CONCLUSION"
. 'Ramove the NIA and SYF ControU!ng L.ocalion Facus and RI tables from the SONGS 00CM.
other SYF and NA dose caladatlm paraneters may mmain In the ODCM In case some radialogk:al welt Is conducted il either k>catlon In the future during decomnnssioning support 0
adlvttles. Whm the fadlly IS no longer OQlng to 1:l!:1 used to support radlological WOO{, the SYF and NIA Clffsft& dose calwaffon provisions may be removed as weG.
810-2 S0123-0DCM-B Revision 9 08/2016
Remove Controlling Location Factors Tables 2-7 and 2-8 (South Yard f!'aclllty and North Industrial Area) and Associated RI Tables in Appendix A from the ODCM TABLE 2-7 SOUTH YARD FACILITY CONTROLLING LOCATION FACTORS 1 I:kRikWk Radionuclide mremtvr per uCl/sec Use:
H-3 1.43E-3 R: Camp Mesa Cr-51 5.65E-2 R: Camp Mesa Mn-54 1.21E+1 R: Camp Mesa Co-57 2.45E+O R: Camp Mesa Co-58 4.13E+O R: Camp Mesa Co-60 1.66E+2 R: Camp Mesa Sr-89 8.59E+O P: Cotton Point Gardens Sr-90 3.37E+2 P: Cotton Point Gardens Zr-95 *4.74E+O R: Camp Mesa Nb-95 1.82E+O R: Camp Mesa Ru-103 1.64E+O R: Camp Mesa Te-129m 2.34E+O R: Camp Mesa Cs-134 4.84E+1 R: Camp Mesa Cs-136 1.08£:+0 R: Camp Mesa Cs-137 7.11E+1 R: Camp Mesa Ba-140 2.35E+O R: Camp Mesa Ce-141 7.70E-1 R: Camp Mesa Ce-144 1.48E+1 R: Camp Mesa 1-131 1.77E+1 R: Camp Mesa 1-132 2.18E-1 R: Camp Mesa 1-133 4.20E+O R: Camp Mesa 1-134 5.93E-2 R: Camp Mesa 1-135 8.87E-1 R: Camp Mesa
-UN-ID 6.65E+O R: Camo Mesa These values to be used In manual calculations are the maximum r.HlkWk for all locations based on the most restrictive age group.
B10-3 S0123-0DCM-B Revision 9 08/2016
Remove Controlllngtocatlon Factors Tables 2-7 and 2-8 (South Yard Faclllty and North.Industrial Area) and Associated Ri Tables In Appendix A from the. OOCM TABLE 2-8 NO~H INDUSTRIAL A ~ (tJNIT 1) CONTROLLING LOCATION FACTORS1
~~
Radlonucllde mrem/yr per uCl/sec Use:
H-3 5.46E-3 A: Camp.Mesa Cr-51 2.42E-1
B: Camp Mesa Mn-54 5.54E+1. : B: Camp Mesa*
~~Co-57~~
~~1.17E+1 B: Camp Mesa Co-58 1.B0E+1 B: Camp Mesa~~
. Co-60 7.82E+2 . 8: Camp Mesa Sr-89 1.82E+1 Q: SC Res. With Garden Sr-90 7.16E+2 Q: SC Res. With Garden Zr-95
~~1.93E+1 A: Camp Mesa~~
~~,Nb-95 7.68E+0~~
B: Camp Mesa Ru-103 - 6.B0E+0 A: Camp Mesa Te-129m 9.04E+0 A: Camp Mesa Cs-134. 2.32E+2 B: Carpp.Mesa Cs-136 ' 5.17E+O B: Camp Mesa Cs-137 3.40E+2 - .* B: Camp Mesa B&-140 9.07E+O A: Camp Mesa Ce-141: 3.01E+0 A: C~mpMesa Ce-144 . 5.68E+1. . A: Camp Mesa 1-131 EtTTE+1 A: Camp Mesa :
1-132 8.36E-1 A: Camp Mesa 1-133 1.60E+1 A: .Camp Mesa 1-134 2.29E-1 A: Camp Mesa 1-135 3.40E+0 A: Camp Mesa*
UN-ID 3.02E+1 *e: Camp Mesa These values to be used In manual calculations are the maximum IkRikWk for all locations based on the most restrictive age group. * **
I ,
~~B10-4 8O123-ODCM-B Revision 9 08/2016~~
RAOWASTE PROCESSING TECHNIQUES AIRBORNE EFFLUENT EVALUATION I:
RADWASTI PROCESSrNG TECHNIQUES AIRBORNE EWLUENT EVALUATION
' December 20, 1999 INTRODUCTION Decommissioning of Unit l will involw the removal.of equipment, sy5tcms, and auuctures that are contaminated or have provioualy bcca contamillated or oxpo,ed to radioactive materials.
Diamantlement ll%ld dlspoaitloo of the resultant matcriab and wute1 may include pbysic:ally
_cutting the components, decontamination of'the items, and packaging for ibipment and dlspoaal Thia Memo to Pile evaluates the potOlltial for creating radioactive offlumu (eirbome and liquids)
&om severa1 preparation anc1 pacJcqina mathoda. This memo does not addren proceaina oi handlins of mixed wastes (both radioactive and hazard0111). This memo docs not address wort actmt1es other than those performed at preYioutly analyzed and Clltabmhed locations; it does not, for example, consider wort performed outside the OWIW controled ania located OD the Grant of Easement. 'lbia memo provides recommendations to ensure compllance with regulatory requimnerits for the COl\ll'OI ofradioective eftlucmu and a generic evaluation of those methods with regards to the reqwremencs* ofl O CFR 50. 59
~~DISCUSSION .~~
Title l O to tu Code of Federal ~u\ationa Part SO Appendix A .flJecifies the design criteria Cor COG8trUCtioo and operation of a nuclear power plant. In particular, General De,igll Criteria 63 and 64 respectively require monitoring ofradloactiYe waste system.I and associated handling areas and effluent ciscbarge patba. There are also ,everaJ reauJmory guidance documents ( NUREG-0472, NURE0-0800 aeetion I 1.4, and Reg Oukle 1.143) t h a t ~ the Reed tbr monitprillgeither the waste treatment systems' discharse or the exhaust ofbulldma(a) that house those systems.
Treatment techn1ques used to reduce or rmiove radioactivity from cootanxnated materlals and equipmenl are coaaidered radwuto P'(ICCSleS. At, lllCb, either the exhaust ftolll thoso systemS used to perform the procellb,s or treatment or the exhaust from the buildings in which tbe -
sylleml are housed must be monitored. Previous documeatr 3 gmcrated at the site have also evaluated radwute trcatmeat tcchnlquea and provided recommendadoas fur cfflueut controls.
The reader should review those documents in add'rtfon to this memo for guidanoe; lhe constraints atabtbhed in reference 1 are considered ~
Wbcncver pOSlllble, radwaste processes (e.a. beatmeat, decontamination. and pa.caging) shall be conducted inside buildings that exhaust through an ODCM~eclit¢ release point and are ITIOCll19i:e(! I.lid sampled lsokinetically. Al the same time, the existing buildlnga cannot ,
accommodate all of the components being removed or t h e ~ equipment. It is likely that temporary work enclosures will be established outside of the existing buikfmsa with mosutored _
HVAC aystem (rad waste auxiliary building.~). Unfortunately, it is not always practicaJ to duet tile exhaust from the worlc enclosute 'to a moniton:d building for discharge through the Plant Vent Stacie. . ., .
811-1 S0123-0DCM-B Revision 9 08/2016
RADWASTE PROCESSING TEOINIQUESAIRBORNE EFFLUENT EVALUATION Because of the .time aince Jbmdown (Ncweimer 1992). ooble gases are no lonpr produced and the radioiodinc, have decayed away. Work activitiea, panicularly~ dw Ulf! mecbaiical or alin.sive methods, can scneme and mu,paid ~ partic;ulate matter. To remove the paniculate matter prior to diacharp IO lbnolphere. HEPA usaits 'sball be placed oa tho exhautt
&om each work enclosure or oo the discharge from the aquipmeat itself. The HEPA. units arc commorcially rated at a *minimum of 99% officiency and mull be poriodically verified to ensure inte;rity and loadq withla dealp apoclflcatlons. For work performed la temporary enclosures or unmonitcired buildings, mrface contamiRatlon levels ahall be maintained within tho llmili ..
established in the referenc:ed design calculatioll for a closest wlyzed locadotr. For destructive
~ methods., the coruminlltion timlts ror the COi blast room at the South Yard Faclity (sheet 9v) should be applied. Acconfmg to the Unit I- Decomnliasionlllg Project radwaste team'. total contamination levelJ are not. expected to exceed IE6 dpm/100 cm1.
AJ, discussed pmiioudy, the oaly anticipated aitborne effluents auributable to thelo work ICtivlties are i n ~ form. llegulatoly Gulde 1.21 and Regulatoty Guido-1.97 note that ln;atantaaeous moaltormt fbr paniculate matter or radiobines is not typicaily com\dered pnctical ~ to tecbnological limitation,. Accontina}y, sampling.win be Uled lmtead of :
moaitorillg to determine whether or not there Im-been a release of airborao effluenCI due to l'lldwuta proc:eaiiia and bandlin& and to quantify*tbe lfflOUllt of activky rdeued. Cont,muous ampJes for particulate matter will be taken downstream oltbe HEPA umta for eadl wodt enclosure and analyzed weelcly as an effluent sample. Any activity demlted will be saportoc! to the NRC In the Annual Radioactive Bffluent_ llelase Report la accordance witb .1 OCFR. S0.36&.
Wotk activities that generate or involve liquids: abaU lndude measures to control spills and prew:m 1111 ~tored release to local area drains and ~ Uao uaratricted area. As _ :
iq1propuate, meuures may Include temporary berms or secondary COlltai.nment. Wute water gcncratcd by ~ activities ahall be dlsposed of properly in accordance with .
established Sta!ioo procedures to prevem ~ of either NRC requiremeali.or conditions of
~~the NPDES perrit. In addition, ~ must be llkan to prevem lb! inadvertent~ of radioectively "clean" syaems lllce ~ water aupply and tho san!t8ly sewer syatem..~~
~~Radioactive liquid, or wastewater generated from a rad~ treatment process wll not be releaaed to Ille 8tOt'm Or yard drains.~~
Written procedwtS rmnt be developed for the perfomwlce of the activities discussed in this document.. Additionally, ifa worldocarion ~ established or a trealmcnt technique Is used for_a*
period that extends (or is anticipated to extend) beyond the Defueied Safety Analysi1 Report'*
(DSAR) update cycle (l years), the DSAR should.be updated to reOect the new techniques or work arcu not already desoribcd. Chanacs to _t,reatment techaiques or systems (equipment.
piping) chat arc uaed to transfer, treat, dispose ot; or store radloactiva wutes require a review of a
this evaluation or pertbnnanco of separate evaluation per NRC mBulletin 80-18 and 10 CPR SO.S9. Failure to review and modify this evaluation, establish procedures, or update the DSAR may result in violalion of regulatory or adminlstratjve'requirements.
B11-2 50123-0DCM-B Revision 9 08/2016
RADWASTE PR~NG TECHNIQUES AIRBORNE EFFLUENT EVALUATION TECHNIQUE DBSCRlPTION AIRBORNE LIQUID COMMENTS MONITORING MONITORINO" Splilll!r * -~to0pCII Y" tN
~>:rm~
ShcmiaS,uwma. *
~~process ..; adjas lmi<<ma!lled.piping.~ d,lo~~
= of ye N WortClldowi'C
~calllna fcnyl. abccl mmoJ. . i CCIIICl'C!le
~~Abrasiwb&astins. ~ remonJ a( llllfacc coa1iag Y" IN Verify booth 'illcgrity.~~
~';;OCJlllimiioll1104 &om c:non i'mbmlEPAchcob.
l,ti,el,IJPlmlly:rtl.S'"'IO'soclloo. Mr/bo bmn!ous w.slC.
iBeadblailaa Pliyl,cal*procca lo ll!IIIIJYC smface Y" IN V~boalb~.
~ ~ '
~~tioa !tom Perform IE'A cboab.~~
,_ ._ *- - - . Sllld pmtlCIC Msybo~Waslls l\l{ulllatswfm:o o-latlnli~llqialdatimiscab N *y itn:almcnl 10,,.....c.-kaCA1111111erim.llllllpmt,,
pn.CID '
!Sriocwlpms' Mamial r--iof'c i, 1~1wioa IN y May~*mixed-J!'OIIIAil~
fcn-liing-i ~of<IO"CS& IY" IN Wodi: cncbuR.
~~SS plpc. 200 mi Pwrrorm HBPA cbeclcs.~~
~rubblu.a ord!as o{CIOIIQ1Clo Y" N DIISlODOlrDlmcaun:s blocbCOIIIMllqr.bar,
- - _(DAW) ~otllll Y" ~ Pcmln!I HEPA diecb
~
Vohaoorab:tlonofDAW GIC ill SS Y" ( ~ PabmHBPAcbem.
~ 100 pl dz-, a putrlpar:bpig Um~locutico
~ ffoppm.CiDIMIJ'DDobWbb' H N µ,c mlllbmtd IXIIIIIOls movinJequipmod,Wllllle,coallliaCffl dc !ran- locGlioa ID m:io1JMir ConlaiJier ROlllm" rmmltnncc "'~ ya IN ~fie Cl&llbl!,bed r:murol IIICI coolliner~ locallana
,
~~Moallcnd HVAC or 1.-1 llir 1Aq1laa~~
~~MorlltorcdHVAC~~~
~~Momloml n:lcmcpxDt cr-raulii!gtoliqllldndwasto ~ o r spill prcvmlcn-The above table sunvnarizes the processes considered in this memo to I.,In. A_~~
11
~~&E cc. 0. Dick. 8ffiuant Engineering L BrayfS. Enright, Decomnaissionlng Ml Johnson, Environmental Protection .
E. M GQ!dln, HP&B ~
HP&E Illes
~~CM-\~~
B11-3 S0123-0DCM-B Revision 9 08/2016
RADWASTE PROCESSING TECHNIQUES AIRBORNE EFRUENT EVALUATION EFFLUENT SAFETY EVALUATION I. Moy the proposed activity lucreme the probabllity of occurrence of on acddenc evaluated previoualy la dte SAR? -
NO.
The only remainin8 Unit I accident that ls evalua!ed in the DSAR is the Fuel Handli1lg accident The proposed decolluimlnation and packagins'activities will DOt affect the Fuel Handling accidem nor can they incruse lite probability of the accident occurring. *
~~2. May tbe proposed activity illcreue die eeuequencet of DD aecideAt evaluated previously In tlu:SAR!~~
NO The proposed activities to dismantle equipment at Unit I and, as necessary, reduce or remove radioactivity from the materiab prior to final diaposaJ are similar to existing decontamination technlquea used at SONGS. Those radwaRe proceaes Involve ecclvfcy lnveatoriel well below that considered In the Fuel Handling scenario at Unit 1. Furthermore, the dose comequencea of the Fuel Handling accident an, Ul DO way aflected by the proposed activitiea.
~~3. May the proposed actk1tY incnale the probabUlty o( occurrences of a malluncdon or equipment Important lo safety evaluated pnvlously lo the SAR?~~
NO The Unit l DSAR describes existing techniques for decootamitiatio used at SONGS. None of"the l)'SlemS or equipment used to perfbnn tbese procase, is comidered important _to safety. N such, or there Is no chBDge In the probebllhy important to safety equipment ma1flmctiooing nor Is there any change in t'ailure modea of IUch e q ~ *
4. May the proposed DdMty lacreue the c:omequeoces ofmall'uncdon of C4pipmeat imp,ortant lo safety e.aluated prerioOllf Ill tu SAltf NO The Unit 1 DSAR describes existlna techniques lor decontamination used at SONGS. None of the l)'9lGml or equipment used to perform these pn,c:,ems is c:onadered important to safety. M such, the proposed activities cannot Increase the coosequeoce& of a malfunction of important to safety equipment.
~~5. May the proposed activity create the possibility or an acddeat or a dlffere*t type lhan any evaluated previoasly la the SAR1~~
~~NO _~~
Neither the Unit I DSAR nor the Units 213 UFSAR consider removal of activity from equipment and/or materials as cn:dtie Initiators ofao accident. In particular, design calodatlon N-03:zo.ocnl comidered these actMtia, within the Unit I Protected Area, in addition ~o the Units 2/3 Protected Area and the South Yard Pacility. The design bats fire involved the HEPA unitgn-the exhaust from Ille work enclosure. As such, thl5 accident type ba.s been previously considered and evaluated intheDSAR.
811-4 S0123-0DCM-B Revision 9 08/2016
RAOWASTE PROCESSING TECHNIQUES AIRBORNE EFFLUENT EVALUATION
~~6. May the proposed actiYity create the posslblllty el a nuJfuncdon or equipme11t Important to aCety er a different '1-pe than mtlaatod prmoas1y In the SAR?~~
NO Equipment used to reduce or ren,ve IIC!ivity lrOl'II materlab i, not conaidered important to sa&=ty.
The propo,ed radwute procaset CIIIIIOI therefore*crea&e the pos11'biity of a l'Allfllnctlon or equipment ciff.-ent from sc:enarios previowty conlidered ill the DSAR.
7,
~~Dea die pr.ope,ed actirity redace Utt 111argin ,ol nfety as ddlaed lo tltc *ut. lor any trdaoh:al spcdftcatlon?~~
~~NO Radwute procaaes peifonned in~~
~~building with drains co die IJquid radwwe treatlllellt system and an HVAt; that la discbarp:I through the Plam Veot Stack are already~ in accordance with the 1tad011'1 effluent c:ootrol prosram.~~
Worlt activ!tiea that ar6 perfunaed in terupormy enclosures, or ouaide o f ~ with a monitored HYAC sy&tem require lmplanoot or other meamrm and oontroll. 1n Ill c:ua where liqwdl are uled or waste ls ganerated. spill control measures will be Implemented and exi9tlng Station procedure,, fbllowed for dbpoaL For techniques that m,;y pnente particulate llldvlty, local air ampflns will be perfbrmed lit tlte immediate area or at the exbault II-om the temporary wor1t eoclosuR. Ant use of HBPA liltffl wil allo require periodic checb lo wrify the 61tera' iJUesrlty and pedbnnance wtdlln dalgn speclJlcatm. Closed loop ayatems or coattiorneot booths wtll llcewlae be verified poriodlcally IO be lnlact and without ~ lcabp. Duat control measures and worker protectioo p(tlCCdures wlD abo be imptement'cd. a appropriate, to miDimizie the spreed or contaminatioD and the rmeesc or llltivlty.
The Soutk Yard Facility cak:ulatioff N-0320-007 ~ the conseqa,eocc, ofworkias on radio6ctively corarninalecl material inside mid outside moa1tored bulldqp. Contamination leveli OD equipment and materiaJI handled -.nd proceued using thu propo,ed techniques wW be maintained below the limit, establltbed ill the calculalion.
Given the constraintl discussed above, the limits of 10 CFR 20 and the Unit 1 Offsite Do,o Calc!dition Manual will 110t N exceeded Therefore, there Is ao l'U1Ctioa In the margin or safety fbr any licemiaa spec:lfication.
8 Dou tbe prope,ed dwtp Coredore ll dttH1mltilanlng -i,tiuo7 NO.
The proposed aotivity does not &tl'ect the COllflguradon of the plant or tho safe maintenance ofche spent W. The radwaste treatment teclnques comidered in tbe Memo to File may be used durins the decommlsalonblg process. -
~~9. DoeJ the proposed dlaoge inYolYc ** major stnactural cbaJ11e to radioactive componeats ot GeCadlityf .~~
NO No physical equipment add'itions or removals are irnplcmerud with this chanp, Temporary \YOtk 811-5 S0123-0DCM-B Revision 9 08/2016
RADWASTE PROCESSING TEOiNIQUES AIRBORNE ~FFLUENT EV~UATION ondosuros may be crectod to house the proc:esaina equipmeat and work acdvlties but these will not a
involve major ltnlCtUrll chailge to Bdioectr,,e compooeni.*1a the facility. .
~~10. Dees Ch~ proposed cbanp subatandally lacreue the cost al.decoatmlldonbsl?~~
.NO.
The bandling and diapoiltion of equipment, ~ and structures removed from Unit I is an Integral part of deconmaslonlng. Aa IUCh, tbe 'processina ol radwuto should have been included in decommlaioning cost estimates. .
11. Deel dte proposed dtaage came 11DY 11piacu, eQffl'Oll-00 Impact DOt prevlomly rmewed?*
NO ............- .
The propoaed worlc IICtiYities 'Mil be performed in acconmce widi existh,a Station progrum for the control of hazardous and radioactive efflueats. TIMre will be no meuurablo illlpact to the.
environment or tbe health ud aafety of the pubtlc.
~~12, Doee Ltte pl'Ope,ed wnp vlelate die tenu of tbe WltlDs Hcenn or 10 CJl'R 50.59 1111 applied to the emdaa Hcemo't .~~
NO Tho ndioloaical effluent controls prosnin i- MICained predoalmandy in tbe 00CM. The proposed pioooaing of radwaste will be porfonnod to enswe tile coatJ'!)!of radioadivo efBuents and .
hazardous materials. .Tho cbaap ii allo ~ per 10 CPR _50.S9 in Ibis docwnn.
RBFERBNCRS ,*
!."Evaluation of Solid Radwato Pr<<oaoa and Decontmninatloa.Tecblliquel", Memo to PDo by
. E.M. Goldin, dated 1214/1995 .
2.Altbomc, Source Tonn for South Yard Shops P'm:ility ~ Outdoor ~ e a , NEDO calculation N-0320-007, l"DYi.lion A:, dated 4116195 J.*Re: Ef8uollt Comrol ISIUel" email from Linda Bray to Kathy Y1up and Daryl Dick, dated 6115/1999 B11-6 S0123-0DCM:.S .
Revision 9 08/2016
AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING HP&B POliftion Paper Seplenlber21;2000 INTRODUCTION San Onofre Unit 1 ceased commercial operation in November 1992 and was placed in SAFSTOR until June 1999 when deconunissionmg beam- In the time lince shutdown, noble gases are no lo11pr produced and radioiocfinea have decayed away. lleleases fiom the waste gu*system are no looger performod end tho current !IOIH'Ce! to the plant vent atack lncfude the spent fuel stotagc building, contaJnment, and the radwaste auxilfuy building. Since 1994, Ibero bas been no detectable beta-gamma activity In the particulate sample; taken from the plant vent stack1*
Activo dec:ommissionin of the Unit iDYolvea cfmnantlement of aystems and equipmect fbr ditposal in addition to demolition of various ltnlctunls. Al warranted, COl1l{X>DOOtl and structures are decontaminated by a variety of methods prior to diaposal off'..._ Currently, hudllng and ,
proceaing of contaminated tDllerial andt'or Nprlpment does not require efflueot contro!s2- >unless removable particulate activity levels exceed I.SES dpm/100 mil and/or removable Iodines exceed 2 sB4 dpm/too cm1.
Thia memorandum evaluates the potential for lirbome radioac:ti~ eft1uenq from the variou1 decornmiMk,ning and decontamlnatioo led!mquea ad recomnaeoda measures to control aod minimize 1111mo,titored reloasos. It does not coalidcrthewe of explosives orwrecting bails fbr demolitioo nor does it ~ the potential for a-eating bazmdoua wasldeffluents from processing of mixed waste DISCUSSION Regulatory ReguiRo)ents Title 10 to !he Code ofFederal Regulations Pct SO Appendix A specifies !he design criteria fo(
construction and operation ofa nuclear power plant. In particular, General Design Criteria 63 and 64 reapectively require monitoring of radioactiw waste ayatema and usociatcd handling areaa and efBoont dlscbarge paths. There are also several rcgu}atoJy guidallce documents ( NUREG-o472, Nl.JRBG.0800 section 11.4, and.Reg Guide J.143) that reiterate tho aeed for monitoring either or the waste tteatnten& l)'Steml' discharge tllo exhaust of building(s) that house those systems.
Using die data collected from monitoring alld routiDo sampling ot'tbe effluent relca8e polnta, tolal activity released and the resultant potential dose to a IMll1ber of tho public is then reported to the NRC in the Annual Rad-,oactive Efflacnt Release Report u required by 10 CPR S0.36a and IO CFR SO Appendix I.
812-1 S0123-0DCM-B Revision 9 08/2016
AIRBORNE EFFLUENT CONTR.Ot.S DURING DECOMMISSIONING Dooontan:iDation techniquol UICd to ~ or ~ radioaclivity from coutamlnatod materiaJt and equipment are conadered radwaste proceaea. Radioactive waste lreltloent systema or methods are also descrl>ed In the DSAJl u required by l OCPR. 50.341(1>): Cbanpa to syatems ot teohniquea used to collect. tranlfer, procea, or dbpose ofradioactivo wutos RlUJl be evaluated in
. acoordance with 10 CFR. SO.S9 ad reported in cbe Annual Radioactive Effluent ReloiR Report u required by apecification 6.3.3 of the Unit I 9fliilc Doao Calculation Manuel*(ODCM).
Airbqme.Controls '
WbeneYe{ rwonably adaevable. nidwute p m sbeJI be conducted bmde monitored bwldloga.' '
Liquids should be removed or drained pior to dlamantq ~ *.eat ..... IIU\lcttnl. IfBquid cannot ba removed prior to ~ or If lquida are u.ed In the treatrftOlll. decool111 de-atlo11, or demolitJon teahnlque. spil control wnes (bcnu. drip colloc:tion hap. etc) mmt be implemenled to preYeat unplanned. UIUIIOIDtOlad lquid releucl. Surface wetting.during building demolition sbou1d be ped'onned ao that tbe llllface is dampened but no nm-off'or pudcles are generated.
Werk prefflNI perf'onaed la monitored baildlqfllncnan Tbere are DO effluent control restrictiou whelaewr tho wor1c la perfonned in a lll0illtoted building.
. Colltainntellt, the spent fuel building. mid the radwate auxilary bulJdins are designed to eoan the bul~'.s atmoipbere b vented throup Iha Uall I Plant vem: Stack. the Ofliko Dose Calculat1on Manual (OOCM):-cRditcd airborne releue point. lf.aptive prcauro in
monitored buBdiJ1g ia lost, work on contam1nllted oquipmcat above 25,000 dpavl 00 ctrl- IQ91e IUrfice oomamination (fixed plus remoYllble OMfM!ioalioo ~250,000 dpm/100 car.) sbould be delayed until *negative presiun, can be Ratored .,.t mmteined, or ~ until CODlamiDatloa CODtrol .
~~measures ,required tbr wodc OUlaide of raonitoRlll buUdlngs are lmplomenced Work p1"0Cellti perf'onaed oatside of a moailond h a ~~~
~~from time to time, IODlC of the COllipODWb beias removed 01' the procemug equipment caM0t be phyalcaly accommodated within tho cxitdns facilties. In addition. the bulkfinp themtelvea .~~
will ovcntuaDy require dlnantlemcnt. For those rare instances wbcre the controls recommended below cannot be practically implmnented. a cese by cue ~ may be med.
One or m;ore contarinatlon control meuurea are required for worfdng cm componenu or buJJcllnga with removable C011ta111iomon leYob SNJlkll' than or equal to 25,000 dpnv'IOO rd (or fixed pluJ lelDOYlblo ~ 2:2SO,OOO dpm/100 an2) to mininaizo the potential for urunooJtored ~ of airborne rad"loactlve ~ In princlple, these lile8IUrCS attempt to reduce tho amount of matllriaJ that can be auspcaded Gr to reduce tbo ll1l0Ulll of "IISllllpOOded
A momlDn:d baMng 11-111111: it undei-ner,lli'IO~ and~ e:dllllll DrOUIICdlo III OOCM-credNed rolcasc~(Plllll VcSll!cltlll Uail I). Thcl'latVcalStlCII iscqaippodw)iaCGlltmllolJlndletioomoailor ad llllllpilld \rihtclWy b',pmilcalalm mxl rmliobbea . '
2 812-2 S0123-0DCM-B Revision 9 08/2016
AIRBORNE EFFLUENT CONTROLS . DURING . DECOMMISSIONING 1
material avallable for releue. Con11aiination coatn:11 meuures iDcludo the use of'lhatlves, local ventilation coatro1s, aoo temporary work eocJmurea.
Examples of contaminat1on control measures include:
L F"ixativea:
~~paint,~~
~~coatinp~~
~~lellllllll~~
~~lfOUl ' ' '~~
~~b. Local veatilatioll controla:~~
~~elephant tnDlb'portabfe HVAC aaita with fllteR(IU exhausl~~
~~vacwma wilh filtered exhaust C. Encloama:~~
~~tentl witJl &ltcred exhaust~~
~~plude bap"enclOling pipe, vrilh ftltered exhaust.~~
~~pfaticJ&bric COYer &>r ~ openiap in bulldinp~~
air curtain for doonl1arp opcmRP ia buildinp While it ii UDlikdy that any radioacdYe particulale matter will ldually be nlea&ed frora the site wllen prudent contamhlldioa C0lltrof measuroa ue ~ l e d . continuous local air aampJCII
*lhol:dd be taken dwiiis w o r k ~ perft,rmed OUlllde ofa mcaitored buldlng.
The co11tamin<<don ooatrol meuura lflll are uled ahould emure that airborne radioactivity ~
do not exceed 0.05 beta,;pmma DAC at" detectable leveh ol alpha DAC. If either oftbme tlireahold, Is exceeded, additional coatrol mcuureuball be iaplemcated to meet these tlnsho1ds within
~~ralllODlble period oftiaic. Addltionaly; lttbc a i r ~ lbclW lewll grater' than 0.05 beta-pmma DAC or deteotabtc leveb of alpha DAC, they abcdd. be oouated as effluent IIIIDplca.~~
The ample results lllouJd be provided to Bfflue:nt ~ f o r ~ .
M dccornmissiomng prosreae1, openinp will be aoated in moaitond ~Mitiptioa cffbrts should be taken to miaimize the potelltial for umnonitored rdcucs ud ensure coatimied
~ with the requiremcnta of 10 CFR 20 and 10 CPR SO to mordtor IDd mcuure re&cascs from Unit 1. For example, bqc openlap (equipmcat hatch, 1ClllpOnly boles) illouJd be covered witb platio or fiibrio or 1111 air aurtlin atablhhd near tlic openmg to maintain aD9tive prcuure.
Smaller opeamp like conuhwcnt pcnctrat1oas &bould bo sealed and pipes containlng illtemal ao.
contaminadon ~lS,000 dpm.1100 on!- (250,000 dpnv'IOO 1 fixed plilS removablc)should be covcrod 0< equiv.lent meuura tilbn to preveat the apn,ad of~ COl!CMPOwwn ..
T h e ~ threahold ot25,ooo dpm/100 arr 1oose mrfic:c contamtaat1on (lSO.ooo dpm/100 ad ftxcd plus remoYlble) cmwes tllat the.lknlu of 10 CPR 20 and IO CPR SO
""Fllllndecbraall" l'lllln .,umof cid='a HHPA.&llarorTorilcbt0Dllcoloc'oreoequiftxmtdc,\cecapebl,s ofreao'liaa~ ollbepenlaulslolllllllcrl:ma_ciacliap.
812-3 S0123-0DCM-B Revision 9 08/2016
.. r
AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING Appendix 1 will be raet. Addltlonally, it also lltbfiea ALAR.A cost considerations since the HP division currently implelnoata control mcuura ror worker protectioo purpose, at aimllar lcvda",.
Contamination coutrol lllelllllrel ani recommended, but not ~ for work below l'eolOVlblc leveb of2S,OOO dpmflOO cm2. .
In addition to tlio <:ORtrOla recommended above, other measures may be implemeated during lhe deatoition ofbuildiaga fw non-radiok>gica purposea. Dl1lt abatement ii fraquemly required by the local a i r ~ rcgulatora (San Diqc) Air Pollution Coatrol District for SONGS) to millimhe adverse Impacts. Typical dUJt c:ontrol um>lvoa the uao of water to dampen the bulkHng PJrfisce or the ~ which would also reduce the partlc:IHaociated activity available for a:elease liom the site aad the potOlllial for publie exposure.
C9JIB'IZllff)CC AMtyps . ,
In the unlikely evenc that tho C011taminatioa coatrol lllOUUT'el fail, the potenlial radioactivity relewd ftom wortdngoa eqwproat/structures contarnimffd up to l.5E6 dplw100 cd- total aaMty WU also evaluated. A couervatiYe calculation (see Appendix A) WU perfonncd UIWRlns that level of conternk!ldnn over a 200 sq ft IWface, dlatributed in ooe (I) cubic meter of air, aad rclea9cd imtantaneoualy (I second) to the enwoomeot. llcsupension values found in the literature ranp from 0.5 tc lE-6; a value or lE-3 for beta-pmma surface C('<<ltllminldoo' was uaed. N seen on ahcot 6 of Appendix A, the resultant organ dose for that single event (1. 7E-3 mn:m) WU below the limha in *10 CPR. .SO Appeadlx I.
CONCLUSION Doconunissionliw Unit 1 lnYOlvos the dbmantJoment or equipment and s,stmm and die dcmotition of stnx:tura, aome of'Mlick will be DODtanllnalecl Decot!*unlnqtioo and resizing of the compoAeDta may also be perfbnacd prior to dlsposi1. On OCCUKX\ the components and poruolll oftha aystems may not be physically IICCOl1U1IOda1e in tbe existing buildings. Farthennorc. die aboveground ltrU0tunll tbermdYel will ultimately be removed. These ldivitioa IJIUll, by default, occu,- oullide of the buildblp with a monitored HVAC l)'llem and tha), create the poteDtia) for
_unmoniton:d releases of.radioectivo airborne cffluen15 from Unit I. For work that must occ:ur outside of a. moaitorcd balldin& prudcat control mcuum are nx:ommended to minimize the apread of coataminatioo and minimize the potential fur the releue of airborne partiailates whlle
~ dole to the public u low u ta rcuonably achievable (Al.ARA).
Contamlnatlon control mouures are roqulred for WOC'k on equipment and/or sttuc:ture1 with :t ,1 25,000 dpm/100 oar nmovable contamination (2250,000 dpni]OO cm1 fixed plus removable contamlnatlon). One or more contamination c:ontrol 'measum alCh u fixatives, local veatftauon lllCIIIW'ei, and encloitns shall be uaed 1o OIIIW'e that lir llmplel talen du:ing the work activity do not cxc:ocd O.OS beta-gamma DAC or detectable leYeb ofalpba DACs. If either of these detection thresholds ls exceeded, additional coc:im,1 measures shall be implemented, to minlmi7.C 4
B12-4 S0123-0DCM-B Revision 9 08/2016
AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING airborne radioecdvtty within
~~roasouablo ~ ~~~
~~Corrtamlnlltioa ooatrol moasuros an,.; recominended boJow 15,000 dpm/100 cnr removable conr.nlaation to nualmize personnel eicposure-fjn~ *4ft f:~L REFERENCES~~
~~1. Annual Radioactive Bftluent Rcleuo Reports 1994-1999 .~~
~~2. "Handling 111d Worlcing Oil Radioactive Material Outlldo Momtorod Buildings* Memo to file, J. R.. Clark, April 26. 1!>93.~~
~~3. S012l-VID-20.IO"R~.WorkP!an niegandCoatrok"Reviaion4~~
~~4. S0123-VD-20.9 "RadloJoslc:al Svrveya" ReYbioo S S. "Air Samplina In the W<>tkplacc'" NURBG-1400 draft report fbr commeat. October !991 -~~
cc: John C11sier, Operations Daryl Dtck, Effluent Engineering Judd S1 lls, Oecomahsfonfng HP Drew Spiker, Deco11Dfss1onfng Rich St. Onge, Decomfss1oafng Garry Moore, NORAD - Oversight HP&£ Files COM s
B12-5 S0123-0DCM-B Revision 9 08/2016
AIRBORNE EFRUENT CONTROLS DURING DECOMMISSIONING Appendix A.
CONSEQUENCE ANALYSIS for AIRBORNE EFFLUENT CONTROLS.DURING DECOMMISSIONING 812-6 S0123-0DCM-B Revision 9 08/2016
AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING
.-rHOOOLOGY:
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AIRBORNE EFFLUENT CONTROl.S DURING DECOMMISSIONING I:
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!TOTAi I 812-8 SO123-0DCM-8 Revision 9 08/2016
AIRBORNE EFRUENT CONTROLS DURING DECOMMISSIONING .I IUSING IJ >IN CAI A ~
fl,/l'OAVI MPC""" I, N/MPC-- .. ,,. ,_ AftrZI"~~
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._, 11'111:M-w* u.-....,,_...-IDO IMollllb
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~~SUBJECT:~~
~~AIRBORNE CONTAMINATION FROM DECOMMISSIONING ACTIVITIES December 13, 2013 J. A.CAREY~~
~~SUBJECT:~~
~~Airborne Contamination from Decommlsalonlng Activities~~
~~REFERENCES:~~
~~1. Airborne Effluent Controls During Decommissioning, K Yhip, September 27, 2000~~
~~2. Airborne Source Term for* South Yard Shops Facility and Outdoor ActMties, Calculation N-0320-007, Rev. 1, April 28, 1995 .~~
~~3. SONGS Health Physics Procedure $O123-Vll-20.10, Radlological Work Planning and Controls~~
4. Ractwaste Processing Techniques-Airborne Effluent Evaluation, K Yhip, December 20,. ***
1999 PROBLEM STATEMENT Reference 1 provided a conservative limit of 250,000 dpm/100 cm2 total contamination (fixed plus removable) for surfaces that may be worked upon during decommissioning without having to consider additional engineered controls to mitigate airborne releases. The paper further specified the engineered controls that may be employed for contamination levels above that criterion and was
written when the majority of radioactive work at the San Onofre Nuclear Generating Station (SONGS) Unit 1 decommissioning took place Inside monitored buildings. Now, access to effluent, monitored buildings may not be achievable for large Items and for demolition of some non-power block buildings themselves. This memorandum reviews the guldeHnes In Reference 1 considering
~~the current state of facilities at the SONGS site and applies limits from a more rigorous formal calculation (Ref. 2) for assessing off-site impacts from airborne releases. The provided guidance~~
~~. supports continued safe work, ensures compliance with effluent controls, while minimizing production restrictions.~~
EVALUATION Revision O of Calculation N-0320-007, Airborne Source Tenn for.South Yard Shops-and'Outdoor Activities (January 4, 1993) was c:irlglnally Initiated to evaluate the Impact of work in the South Yard because that facility Is located in dose proximity to site boundaries. The calculation also Included an evaluation of performing some radiological work in the Protected Areas but outslde.ofmon~red buildings. The calculation was slgniflcantly revised In 1995 (Reference 2) to account for a source term with reactor ~ant contaminated equipment and to also address mixed waste prOC88Sing ..
The center of the Unit 1 Protected Area (now the North Industrial Area or'NIA) was closer to the Site Boundary-than the Units 2/3 Protected Area (PA) center. Therefore; the limits for Unit 1 were
- more restrictive than those for Units 2/3. Tlle calculation included two major cases each for Unit 1 and for Units 2/3, the first for *normal" activities (machining, dtllllng, sawing, grinding) and the
~ d for _a "design basis!' ~ent (a fire) in which the resuspended. radioactivity was muq, greater.
With the permanent shutdown of SONGS Units 2 and 3, some demolition work will be conducted in*
the NIA. In order to ship certain items for disposal, some size 'reduction may be required. For .
example, the Unit 2 reactor head vent ducting and the reactor head lift rig are too big to fit on transport vehicles. The means to cut th~ items futo small enough pieces may incl1,1de sawing and crushing but ~lso could include torch cutting.
B13-1 SO123-0DCM~B Revision 9 08/2016 I.
~~SUBJECT:~~
AIRBORNE CONTAMINATION FROM DECOMMl~IONl~G ACTIVITIES The llrnlts for the nonnaf case apply (10 CFR Part.20 airborne effluent concentration limlts or ECLs) *
for sawing and crushing but the larger release factor for the design basis accident*ls more appropriate for aggressive work such as torch cutting. Since the rest of the parameters (wind speed, *stability class, XJQ, etc.} that enter Into the evaluation are not significantly different, the
. impact from these activities In the NIA can be estimated by ratloing the "normar case to the "design *
. basis" accident release factor. The normal case was based on a release factor of-1 x 10-a. The design basis accident (fire) was evaluated using a release factor of 1 x 10-3. (Note that the calculation also used a release fraction of 5 x 10-a*for carbon dioxide pellet blasting for :
decontamination that could be applicable for aggressive decontamination measures In the a*rea.) If
all other parameters are left intact, for the aggressive activities, dividing the limiting surface contamination by a factor of 1000 will result in an estimate of the contamination (total contamination, not just removable) that results In an offslte airborne concentration of 1 ECL Note also that the isotopic distribution used in the calculation was based on the Units 2/3 dry active
~~.waste (DAW) composite profile. This profiJe is dominated by 137Cs, 134Cs, and 60Co. This~~
~~radionuclide profile Is appropriate for the Units 213 components under consideration *and to the~~
~~remote potential for contamination on building surfaces in the Units 2/3 PA. It Is worth noting that~~
. . the temporary structures In the NIA are not subject to radioactive contamination but when they are removed, the Units 2/3 radionuclide profile is applicable because these structures, In some cases, housed Units 213 components and not Unit 1 components (that would have a different radionuclide distribution}:
The surface contamination Umlt for work under normal conditions (machining, drilling, sawing,
*grinding) was 1.3 x 1011 dpm/100 cm2 (from results table on page 7, Reference 2): Therefore, dividing by 1000 to account for potentially significantly higher releases during aggressive operations on contaminated surfaces*yietds ~ 1 x 108 dpm/100 an2. Note this value 1s not es high as the design basis evenflri the calculation due to the continued use of normal atmospheric dispersion parameters. Even If a safety margin of 10 Is applied to account for larger su*rface areas (the calculation assumed a 2 square*yard surface resuspended every second), the limiting total surface
~~contamination level Is still~ 1 x 107 dpm/100 cm2 for work In the NIA. This is comparable to the ,~~
limitation In SONGS Health Physics Procedure SO123-Vll-20.1 O (Ref. 3) that includes a cr1ter1on of*
1.5 x 108 dprn/100 cm2 for loose surface contamination on work outside an effluent-monitored
buUdlng (equivalent to 1.5 x 107 dpm/100 cm2 total contamination) and applies site-wide, not just for the NIA The admJnistrative value of 250,000 dpm/100 cm2 total contamination from Reference 1 Is therefore conservatiyely low by a factor of 40.
Working in the Units 2/3 PA, for example the demolition of non-power block buildings, is bounded by the above evaluation becau~ of the greater distance to the Site Boundary (raises the atmospheric dispersion XJQ by greater than a factor of 3). Reference 2, page 7 includes results for
~~the Units 2/3 PA that are higher then the NIA results by this fa$r of 3. Moreover, *aggressive decontamination will not be required in the Units 2/3 PA since the materiel is not contaminated o.e.~~
demolition of _support buildings).
Lastly; these results and limits apply to offsite airborne concentrations and not to local wor1c~r protection: Limits for local worker airborne contamination controls may be considerably more restrictive. Local contamination controls may also be required to prevent releases to yard areas or storm draJns. *
.813-2 SO123-0DCM-B Revision 9 08/2016
~~SUBJECT:~~
~~AIRBORNE' CONTAMINATION FROM DECOMMISSIONING ACTivlTIES RECOMMENDATIO NS Work on contaminated components or work to demolish buHdlngs may be performed on surfaces~~
with total contamination levels up to 1 x 107 dpm/100 cm2, raised from the currently conservative 250,000 dpm/100 an2 (total contamination, fixed plus removable). In addition, an initial limit for torch cutting steel (for example, the head Dft rig) may be ~bl_ished also at 1 x 107 dpm/100 crn2.
\J\hllle torch cutting may cause a ~latively high resuspension _rate, this activity will affect only small ,.
areas at any given time. As before, local air samples should be.taken to evaluate the conditions * '
early In the demolition and c~ng processes to ensure the controls are adequate. Adjustment may be necessary In the unllkefl/ event that radioactive contamination is discovered on air samples *
~~taken during decontamination or demontion. If airborne contamination levels are not significant~~
(defined to be greater than 0.1 DAC in the general work area), then the contamination levels couJd be raised higher subject to approval by the Radiological Effluent and Environmental Specialist, but should n-ot exceed 1 x 1011 dprn/100 cm2, ~r loose surface contamination, 1% of th~ limit suggested
.in Reference 2. As always, AlARA principles such as *ctecontemlnatlon should be used on the local surfaces that are subject to cutting or other activities that might resuspend radioactivity. I f ~ .
engineered controls should be employed such es containment enclosures, HEPA ventilation units, fixatlVes, or spray/mist to prevent resuspension. Reference 4 tabulates many decontamination operations along with recommendations on work enclosures and air sampling.
CONCLUSION
~~Employ local air samplers~~
~~Decontaminate surfaces to the extent practical~~
~~Utilize containment enclosures if available~~
~~Draw air through' HEPA units If practical~~
~~Employ !'Tlist/spray or flxawes if necessary~~
Limits for contamination:*
7 o 1 x 10 dpm/100 c:,~total activity, fixed plus removable) a 1.5 x 1011 dpm/100 (removable activity llmit in Ref. 3) a Higher levels may be used if, air samples support and Effluent Engineering approves, particularly in the Units 2/3 Protected Area a The previously identified adminis~e limit of 250,000 dpm/100 cm2 (total contamination, fixed plus removable) may be adequate for the majority of the work In :the yard areas
~~This evaluation applies to surface contamination. Be aware of any possibility for activated material that would not apply to this evaluation.~~
Prepared by:
E. M. GOLDIN
~~Reviewed and Approved by:~~
S. SEWELL cc: A. S. Martinez S.Veughen C.Cook
-C.Ahola CDM Flies 813-3 SO123-0DCM-B Revision 9 08/2016

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Sr-90 concentration as detem,ined in the previous quarterly composite sample, µCi/ml Ct

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