ML18117A238

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Submittal of Annual Radioactive Effluent Release Report for 2017
ML18117A238
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 04/24/2018
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: ML18117A238 (327)
v • d • e


Text

l,;P IE°Dis"O"N*

Al Bates 1 Manager Regulatory Affairs &

An EDISON INTERNATIONAL Company Nuclear Oversight 10 CFR 50.36(a)

April 24, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Subject:

Annual Radioactive Effluent Release Report - 2017 San Onofre Nuclear Generating Station (SONGS), Units 1, 2 and 3 Docket Nos. 50-206, 50-361 and 50-362

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

Additionally, in accordance with SONGS Unit 1 Permanently Defueled TS Section D6.14.2.3 and SONGS Units 2 and 3 Permanently Defueled TS Section 5.5.2.1.1 (c), the SONGS Offsite Dose Calculation Manual (ODCM) Revisio"n 11, issued August 30, 2017, is included with this submittal. There were no changes to the ODCM in 2017 after Revision 11 was issued.

Change bars, as required by TS Section D6.14.2.3 and TS Section 5.5.2.1.1 (c), are included on all affected pages.

There are no commitments in this letter or the enclosure.

If you have any questions, please contact me at (949) 368-6945.

Sincerely, Q,t_

P. 0. Box 128 San Clemente, CA 92672

Document Control Desk

Enclosures:

1) San Onofre Nuclear Generation Station, Annual Radioactive Effluent Release Report 2017
2)
3) Offsite Dose Calculation Manual Nuclear Organization San Onofre Nuclear Generation Station Appendix A, Ri Tables, S0123-0DCM-A, Revision 11, August 2017 *
4) Offsite Dose Calculation Manual Nuclear Organization San Onofre Nuclear Generation Station (SONGS) Appendix B Supplemental Information for Effluent Controls, S0123-0DCM-B, Revision 9, August 2016 cc: K. Kennedy, Regional Administrator, NRC Region IV M. G. Vaaler, NRC Project Manager R. K. Lupo, California Department of Public Health

Enclosure 1 San Onofre Nuclear Generation Station Annual Radioactive Effluent Release Report 2017 January - December

SAN ONOFRE NUCLEAR GENERATING STATION Annual Radioactive Effluent Release Report 2017 January - December

TABLE OF CONTENTS SECTION A - INTRODUCTION ........................................................................................................ 1 SECTION B - GASEOUS EFFLUENTS ............................................................................................ 2 SECTION C- LIQUID EFFLUENTS ............................................................................................... 10 SECTION D - PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM ............ 18 SECTION E - RADWASTE SHIPMENTS ....................................................................................... 21 SECTION F - APPLICABLE LIMITS ............................................................................................... 24 SECTION G- ESTIMATION OF ERROR ....................................................................................... 28 SECTION H -10 CFR 50 APPENDIX I REQUIREMENTS ............................................................. 29 SECTION I - CHANGES TO OFFSITE DOSE CALCULATION MANUAL. ...................................... 33 SECTION J - CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ........................... 35 SECTION K- MISCELLANEOUS ................................................................................................... 35 Abnormal Release .............................................................................................................. 35 Effluent Monitoring Instruments Out of Service Greater Than 30 days ................................ 36 Onsite Groundwater Samples ............................................................................................. 36 40 CFR 190 Requirements ................................................................................................. 40 Carbon-14 ........................................................................................................................... 41 SECTION L - SONGS CONCLUSIONS .......................................................................................... 42 METEOROLOGY ........................................................................................................................... 43

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION A. INTRODUCTION This Annual Radioactive Effluent Release Report summarizes the gaseous and liquid radioactive effluent releases and radwaste shipments made from the San Onofre Nuclear Generating Station, Units 1, 2 and 3. This report is prepared in the general format of USNRC Regulatory Guide 1.21, Revision 1, and includes:

1. Quarterly Summaries of Gaseous 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 Percent Error
5. Lower Limit of Detection Concentrations
6. Batch Summary Releases
7. Previous Radioactive Effluent Release Report Addendum
8. Radwaste Shipments
9. 10 CFR 50 Appendix I Requirements
10. Changes to Offsite Dose Calculation Manual These are acronyms 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 DEC Decommissioning ECL Effluent Concentration Limit GI-LLI Gastrointestinal Tract-Lower Large Intestine GPI Groundwater Protection Initiative ISFSI Independent Spent Fuel Storage Installation 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 N/A Not Applicable NIA North Industrial Area formally known as Unit 1 NN Nuclear Notification used in site's corrective action program ODCM Offsite Dose Calculation Manual PCS Plant Computer System TLD Thermoluminescent Dosimeter uCi/sec Micro Curies per second X/Q Chi over q SYF South Yard Facility ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 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 gre~ter 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-2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1A GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error,%

A. Fission and activation gases

1. Total release Ci <LLD <LLD
2. Average release rate for period µCi/sec N/A N/A N/A N/A 3.00E+01
3. Percent of applicable limit %MPG Percent Effluent Concentration
4.  % ECL N/A N/A Limit B. Iodines
1. Total 1-131 Ci <LLD <LLD
2. Average release rate for period µCi/sec N/A N/A Percent of applicable limit %MPG N/A N/A 1.90E+01 3.

Percent Effluent Concentration

4.  % ECL N/A N/A Limit C. Particulates Particulates with half-lives >8
1. Ci <LLD <LLD days
2. Average release rate for period µCi/sec N/A N/A 1.60E+01
3. Percent of applicable limit %MPG N/A N/A Percent Effluent Concentration
4.  % ECL N/A N/A Limit
5. Gross alpha activity Ci <LLD <LLD 5.00E+01 D. Tritium
1. Total release Ci 3.0?E+OO 4.57E+OO
2. Average release rate for period µCi/sec 3.95E-01 5.81 E-01 9.48E-04 1.39E-03 2.50E+01
3. Percent of applicable limit  %.MPC Percent Effluent Concentration
4.  % ECL 1.90E-03 2.79E-03 Limit NOTES:
1) SYF effluent sampler (SYF-7904) pump failed on 1/24/2017. Samples collected before and after each event showed no detectable activity. No radiological work was performed during the time that samplers were found off. (AR 0117-66420).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1A (Continued)

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

A. Fission and activation gases

1. Total release Ci <LLD <LLD Average release rate for
2. µCi/sec N/A N/A period 3.00E+01
3. Percent of applicable limit %MPC N/A N/A Percent Effluent
4.  % ECL N/A N/A Concentration Limit B. Iodines
1. Total 1-131 Ci <LLD <LLD Average release rate for
2. µCi/sec N/A N/A period 1.90E+01
3. Percent of applicable limit %MPC N/A N/A Percent Effluent
4.  % ECL N/A N/A Concentration Limit C. Particulates Particulates with half-lives >8
1. Ci <LLD 5.04E-06 days Average release rate for
2. µCi/sec N/A 6.34E-07 period 1.60E+01
3. Percent of applicable limit %MPC N/A 6.09E-07 Percent Effluent
4.  % ECL N/A 1.52E-06 Concentration Limit
5. Gross alpha activity Ci <LLD <LLD 5.00E+01 D. Tritium
1. Total release Ci 7.63E+OO 3.18E+OO Average release rate for
2. µCi/sec 9.60E-01 4.00E-01 period 2.50E+01
3. Percent of applicable limit %MPC 2.30E-03 9.60E-04 Percent Effluent
4.  % ECL 4.61E-03 1.92E-03 Concentration Limit NOTES:
1) On September 26, 2017, Common Plant Vent Stack Radiation Monitor, 2/3RE-7808 quick disconnect failed. The monitor tripped. Therefore, there was no continuous monitoring and sampling for the Plant Vent Stack from 9/26/2017 0845 to 9/26/2017 1000. This is due to 2RE-7865 (Unit 2 Plant Vent Stack radiation monitor) was non-functional on 9/25/2017. Maintenance performed corrective action on 2/3RE-7808 by fixing the quick disconnect and restoring the Common Plant Vent stack radiation Monitor. The weekly sample was collected and analyzed and showed no detectable licensed material. In addition, reviewed the sample media from the weeks before and after the event and no detectable licensed material was noted. Therefore, there is no dose or curie impact to the public.

(AR# 1017-91520)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2017 SAN ONOFRE NUCLEAR GENERATING STATION

2) SYF effluent sampler (SYF-7904) power was secured to perform maintenance work in the building on 2 different dates: 8/25/2017 1303 to 1349 and 9/1/2017 0824 to 1312. Samples were collected/analyzed before and after each event. The counted samples showed no detectable plant licensed activity. No radiological work was performed when the power was temporary secured to the air sampler. (AR #0917-32536)
3) SYF effluent sampler (SYF-7904) pump failed on 9/28/2017 and was replaced with new pump.

Samples were collected/analyzed before and after this event. The counted samples showed no detectable plant licensed activity. No radiological work was performed during the time when the sample pump failed. (AR 0917-42812).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1C GASEOUS EFFLUENTS GROUND LEVEL RELEASES BATCH MODE Batch gaseous releases were not performed at SONGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 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-88 Ci <LLD <LLD <LLD <LLD xenon-133 Ci <LLD <LLD <LLD <LLD xenon-133m Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD xenon-135m Ci <LLD <LLD <LLD <LLD xenon-138 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD
2. Iodines iodine-131 Ci <LLD <LLD <LLD <LLD iodine-133 Ci <LLD <LLD <LLD <LLD iodine-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD
3. Particulates barium-140 Ci <LLD <LLD <LLD <LLD cerium-141 Ci <LLD <LLD <LLD <LLD cerium-144 Ci <LLD <LLD <LLD <LLD cesium-134 Ci <LLD <LLD <LLD <LLD cesium-137 Ci <LLD <LLD <LLD 5.04E-06 cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 1D.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 1D GASEOUS EFFLUENTS LOWER LIMIT OF DETECTION Continuous Mode Batch Mode Radionuclides LLD (µCi/cc) LLD (µCi/cc)

1. Fission and activation gases krypton-85 2.20E-05 N/A krypton-85m 5.50E-08 N/A krypton-87 2.80E-07 N/A krypton-88 2.00E-07 N/A xenon-133 1.50E-07 N/A xenon-133m 4.40E-07 N/A 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 2.40E-13 N/A iodine-133 2.30E-12 N/A iodine-135 1.60E-10 N/A
3. Particulates barium-140 5.20E-13 N/A cerium-141 6.30E-14 N/A cerium-144 2.50E-13 N/A cesium-134 1.40E-13 N/A cesium-137 1.20E-13 N/A cobalt-58 1.30E-13 N/A cobalt-60 2.00E-13 N/A iron-59 3.20E-13 N/A lanthanum-140 1.00E-12 N/A manganese-54 1.30E-13 N/A molybdenum-99 7.60E-14 N/A strontium-89 1.00E-11 N/A strontium-90 1.00E-11 N/A zinc-65 3.40E-13 N/A 4 Tritium N/A N/A
5. Alpha 1.00E-11 N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE1E 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 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO Percent of Applicable
2.  % 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Limit
3. Beta Air Dose mrad O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Percent Applicable
4.  % O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Limit B. Tritium, Iodine, Particulates (at the nearest receptor)
1. Organ Dose mrem 1.26E-04 1.87E-04 3.12E-04 1.38E-04 Percent of Applicable
2.  % 8.37E-04 1.25E-03 2.08E-03 9.20E-04 Limit NOTE: Calculations performed in accordance with the ODCM utilizing the historical X/Q.

TABLE1F GASEOUS EFFLUENTS BATCH RELEASE

SUMMARY

Batch gaseous releases were not performed at SONGS.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION C. LIQUID EFFLUENTS Table 2A, "Liquid Effluents Summation of All Releases," provides a detailed summary of liquid effluents released quarterly in three categories: fission and activation products, tritium, and dissolved and entrained gases. Listed for each of the three categories are:

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

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

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

Table 28, "Liquid Effluents," provides the systematic listing by radionuclide for the quantity of radioactivity released in each category. The total radioactivity of each radionuclide released is listed for each quarterly period by both "continuous" and "batch" modes of release.

Table 2C, "Liquid Effluents Lower Limit of Detection," provides a listing of lower limit of detection concentrations for radionuclides not detected in Table 28.

Table 20, "Liquid Effluents Radiation Doses at the Liquid Site Boundary," presents a quarterly summary of doses at the Liquid Site Boundary for this report period.

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

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2A LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Estimated First Second Total Unit Quarter Quarter Error,%

A. Fission and activation products Total release (not including 1.

tritium, qases, alpha)

Ci <LLD <LLD Average diluted concentration

2. µCi/ml N/A N/A durinq period 1.90E+01
3. Percent of applicable limit %MPC N/A N/A Percent Effluent Concentration
4.  % ECL N/A N/A Limit B. -Tritium
1. Total release Ci <LLD <LLD Average diluted concentration
2. µCi/ml N/A N/A during period 1.90E+01
3. Percent of applicable limit %MPC N/A N/A Percent Effluent Concentration
4.  % ECL N/A N/A Limit C. Dissolved and entrained gases
1. Total release Ci <LLD <LLD Average diluted concentration
2. µCi/ml N/A N/A durinq period 1.90E+01
3. Percent of applicable limit %MPC N/A N/A Percent Effluent Concentration
4.  % ECL N/A N/A Limit D. Gross alpha activity
1. Total release Ci <LLD <LLD 5.00E+01 E. Volume of waste released (batch &

continuous, prior to dilution) liters 8.51E+06 2.05E+06 5.00E+OO F. Volume of dilution water used during period liters 6.13E+09 7.94E+09 5.00E+OO I L

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2A (Continued)

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

A. Fission and activation products Total release (not including 1.

tritium, gases, alpha)

Ci <LLD <LLD Average diluted concentration 2.

during period

µCi/ml N/A N/A 1.90E+01

3. Percent of applicable limit %MPG N/A N/A Percent Effluent Concentration
4.  % ECL N/A N/A Limit B. Tritium
1. Total release Ci <LLD <LLD Average diluted concentration 2.

durinq period

µCi/ml N/A N/A 1.90E+01

3. Percent of applicable limit %MPG N/A N/A Percent Effluent Concentration
4.  % ECL N/A N/A Limit C. Dissolved and entrained gases
1. Total release Ci <LLD <LLD Average diluted concentration
2. µCi/ml N/A N/A during period 1.90E+01
3. Percent of applicable limit %MPG N/A N/A Percent Effluent Concentration
4.  % ECL N/A N/A Limit D. Gross alpha activity
1. Total release Ci <LLD <LLD 5.00E+01 E. Volume of waste released (batch &

continuous, prior to dilution) liters 1.72E+06 1.60E+06 5.00E+OO F. Volume of dilution water used during period liters 7.48E+09 8.16E+09 5.00E+OO ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 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 <LLD <LLD chromium-51 Ci <LLD <LLD <LLD <LLD cobalt-58 Ci <LLD <LLD <LLD <LLD cobalt-60 Ci <LLD <LLD <LLD <LLD iodine-131 Ci <LLD <LLD <LLD <LLD iron-55 Ci <LLD <LLD <LLD <LLD iron-59 Ci <LLD <LLD <LLD <LLD lanthanum-140 Ci <LLD <LLD <LLD <LLD manganese-54 Ci <LLD <LLD <LLD <LLD molybdenum-99 Ci <LLD <LLD <LLD <LLD niobium-95 Ci <LLD <LLD <LLD <LLD strontium-89 Ci <LLD <LLD <LLD <LLD strontium-90 Ci <LLD <LLD <LLD <LLD technetium-99m Ci <LLD <LLD <LLD <LLD zinc-65 Ci <LLD <LLD <LLD <LLD zirconium-95 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD
2. Dissolved and entrained gases xenon-133 Ci <LLD <LLD <LLD <LLD xenon-135 Ci <LLD <LLD <LLD <LLD Total for period Ci <LLD <LLD <LLD <LLD LLD Lower Limit of Detection; see Table 2C.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 28 (Continued)

LIQUID EFFLUENTS BATCH MODE*

First Second Third Fourth Radionuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission and activation products barium-140 Ci N/A N/A N/A N/A cerium-141 Ci N/A N/A N/A N/A cerium-144 Ci N/A N/A N/A N/A cesium-134 Ci N/A N/A N/A N/A cesium-137 Ci N/A N/A N/A N/A chromium-51 Ci N/A N/A N/A N/A cobalt-58 Ci N/A N/A N/A N/A cobalt-60 Ci N/A N/A N/A N/A iodine-131 Ci N/A N/A N/A N/A iron-55 Ci N/A N/A N/A N/A iron-59 Ci N/A N/A N/A N/A lanthanum-140 Ci N/A N/A N/A N/A manganese-54 Ci N/A N/A N/A N/A molybdenum-99 Ci N/A N/A N/A N/A niobium-95 Ci N/A N/A N/A N/A strontium-89 Ci N/A N/A N/A N/A strontium-90 Ci N/A N/A N/A N/A technetium-99m Ci N/A N/A N/A N/A zinc-65 Ci N/A N/A N/A N/A zirconium-95 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A
2. Dissolved and entrained gases xenon-133 Ci N/A N/A N/A N/A xenon-135 Ci N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A
  • No liquid batch releases were conducted in 2017.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2C LIQUID EFFLUENTS LOWER LIMIT OF DETECTION Radionuclides Continuous Mode Batch Mode*

LLD (µCi/cc) LLD (µCi/cc)

1. Fission and activation products barium-140 3.30E-07 N/A cerium-141 4.80E-08 N/A cerium-144 2.00E-07 N/A cesium-134 8.60E-08 N/A cesium-137 7.30E-08 N/A chromium-51 3.?0E-07 N/A cobalt-58 7.80E-08 N/A cobalt-60 1.10E-07 N/A iodine-131 6.50E-08 N/A iron-55 1.00E-06 N/A iron-59 1.80E-07 N/A lanthanum-140 6.40E-07 N/A manganese-54 7.?0E-08 N/A molybdenum-99 6.30E-08 N/A niobium-95 7.80E-08 N/A strontium-89 5.00E-08 N/A strontium-90 5.00E-08 N/A technetium-99m 6.50E-08 N/A zinc-65 2.00E-07 N/A zirconium-95 1.30E-07 N/A
2. Dissolved and entrained gases xenon-133 2.50E-07 N/A xenon-135 9.?0E-08 N/A
3. Tritium 1.00E-05 N/A
4. Gross Alpha 1.00E-07 N/A
  • No liquid batch releases were conducted in 2017.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2D LIQUID EFFLUENTS RADIATION DOSES AT THE LIQUID SITE BOUNDARY First Second Third Fourth Unit Quarter Quarter Quarter Quarter A.

1. Total body dose mrem O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Percent of Applicable
2. Limit  % O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B.
1. Limiting organ dose mrem O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
2. Limiting organ for period N/A N/A N/A N/A Percent of Applicable
3. Limit  % O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I

L___

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2E LIQUID EFFLUENTS BATCH RELEASE

SUMMARY

12 month period

1. Number of batch releases: N/A release
2. Total time period for batch releases: N/A minutes
3. Maximum time period for a batch release: N/A minutes
4. Average time period for a batch release: N/A minutes
5. Minimum time period for a batch release: N/A minutes Average saltwater flow during batch
6. releases: N/A gpm
  • No liquid batch releases were conducted in 2017.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM

( 1) In the 2016 ARE RR an incorrect liquid tritium value was documented for the 4th quarter.

This event is documented under the site's corrective action program. (AR#0517-92745).

Corrected values are shown below. The 40 CFR 190 Site Wide Dose Determination was also recalculated and there was no change in the dose to members of the public, TABLE 2 A LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Estimated Fourth Total

' Unit Quarter Error,%

B. Tritium

1. Total release Ci 1.30 E-04 Average diluted concentration
2. µCi/ml *1.74E-11 during period 1.90E+01
3. Percent of applicable limit %MPG 5.81 E-07 Percent Effluent Concentration
4.  % ECL 1.74 E-06 Limit E. Volume of waste released (batch & liters 4.86 E+04 5.00E+OO continuous, prior to dilution)

TABLE 20 LIQUID EFFLUENTS RADIATION DOSES AT THE LIQUID SITE BOUNDARY Fourth Unit Quarter A.

1. Total body dose mrem 1.41 E-08 Percent of Applicable
2. Limit  % 4.69 E-07 B.
1. Limiting organ dose* mrem 1.41 E-08
2. Limiting organ for period (1)

Percent of Applicable

3. Limit  % 1.41 E-07
  • All organs except Bone are considered the limiting organ for the period since the only isotope detected was tritium.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM SECTION E. RADWASTE SHIPMENTS TABLE 3 (Units 2 & 3)

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 2a. Estimate of major nuclide composition (U2 and U3 Resin) There were no resin shipments in 2016.

2b. Estimate of major nuclide composition [U2 and 3 Dry Active Waste (DAW)]

Cesium-137 Cs137  % 9.39E+OO (1)

Total  % 1.00E+02 (1) Due to a transcription error, the percentage of Cs-137 reported in this table was incorrect in the 2016 Annual Radiological Effluent Release Report. The percentages in the Radioactive Waste Manifests were correct (AR 1217-80532).

In the 2016 ARERR it was reported that the destination was Energy Solutions LLC, Bear Creek Facility (SC), when it should have stated Energy Solutions LLC, Clive Utah Disposal Site. This was captured under the site's corrective action program AR# 0517-95867.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination
  • 1 Tractor/Trailer EnergySolutions LLC, Clive Utah Disposal Site
  • Note: SONGS maintains a contract with EnergySolutions LLC, Barnwell Processing Facility (Barnwell, SC) that provides volume reduction services. Processed waste was shipped from EnergySolution LLC, Barnwell Processing Facility to EnergySolutions LLC, Clive Disposal Site using one shipment. This shipment, from Barnwell to Clive, included waste from other generators, SCE's waste volume was a small fraction of the total waste included with these shipments. This shipment was sent from SONGS to EnergySolutions LLC, Barnwell Processing Facility in December 2014, processed and shipped as waste to EnergySolutions LLC, Clive Disposal Site in 2016 One shipment was made from San Onofre Nuclear Generating Station (SONGS) to EnergySolutions LLC, Bear Creek Facility (Tennessee) in 2016. This shipment has not been processed at this time.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION D. PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT ADDENDUM SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS TABLE 1 Dose* (millirems)

Fourth SOURCE Quarter LIQUID EFFLUENTS 4)

Whole Body 1.41 E-08 9)

Organ 1.41 E-08

4. This value was calculated using the methodology of the ODCM.
9. This value was calculated using the methodology of the ODCM; the Liver, Thyroid, Kidney, Lung and GI-LLI received the maximum dose primarily by the saltwater fish pathway.

TABLE 2 Percent Applicable Limit Fourth SOURCE Quarter LIQUID EFFLUENTS Whole Body 4.69 E-07 Organ 1.41 E-07 In addition to the incorrect tritium valueJor liquids, it was discovered that the quarterly limit for airborne effluents had been used to calculate the annual dose limit percentage. The correction is shown below. (CR SDS-000139)

TABLE 2 Year AIRBORNE EFFLUENTS Tritium, Iodines, and 2.94E-02 Particulates SECTION L. SONGS CONCLUSIONS In the 2016 Section L. SONGS Conclusions, the tritium values changed to 9.84E-03 curies.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION E. RADWASTE SHIPMENTS TABLE 3 (Units 2 & 3)

SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 12 month Estimated

1. Type of waste Unit period total error (%)
a. Spent resins, filter sludge, m3 evaporator bottoms N/A Ci N/A N/A
b. Dry active waste (DAW), m3 compactable and non-compactable 8.535 Ci 2.603E-02 30%

C. Irradiated components m3 N/A Ci N/A N/A

d. Other: Filters m3 N/A Ci N/A N/A NOTE:

N/A: No shipments containing these items made in 2017.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 2a. Estimate of major nuclide composition (U2 and U3 Resin) There were no resin shipments in 2017.

2b. Estimate of major nuclide composition [U2 and 3 Dry Active Waste (DAW)]

Carbon-14  % 1.23E+OO lron-55  % 1.03E+01 Cobalt-60  % 9.07E+OO Nickel-63  % 6.11 E+01 Antimonv-125  %* 9.58E-01 Cesium-134  % 3.85E-01 Cesium-137  % 1.66E+01 Cerium-144  % 3.79E-01 Plutonium-238  % 1.65E-02 Americium-241  % 2.0BE-02 Totals  % 1.00E+02 2c. Estimate of major nuclide composition (U2 and U3 Irradiated Components) There were no irradiated components shipments in 2017 2d. Estimate of major nuclide composition (U2 and U3 Filters) There were no filters shipments in 2017

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 2 Tractorffrailer EnergySolutions LLC, Clive Utah Disposal Site Notes:

1: Two disposal shipments (solid waste) were made in 2017 from EnergySolutions LLC Bear Creek to EnergySolutions Clive Utah Disposal Site.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination No shipments were made in None 2017 N/A ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION C. DEWATERING Number of Solidification Agent Containers None N/A CHANGES TO THE PROCESS CONTROL PROGRAM AT SAN ONOFRE UNITS 11 2 & 3

1) Changes made to the Process Control Program: Administrative and editorial changes only. There were no changes made that impacted the Process Control Program in 2017, however the program was transferred to SONGS Decomissioning Solutions. The SCE PCP procedure, S0123-Vll-8.5.1, was voided and replaced with SDS-WM1-PCD-0018.
2)

References:

a. Units 2 & 3 Licensee Control Specification Section 5.0.103.2.2
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-June 1974 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS Gaseous Effluents Applicable Limits The percent of Applicable Limits, tabulated in Sections A, 8, C, and D of Table 1A, were calculated using the following equation:
  • % Applicable Limit (%MPG) = (Rel Rate) (X/Q) (100)

MPCeff 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, 8.2, C.2 and D.2 of Table 1A, µCi/sec.

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

I--'-

i=l MPC i where: Fi = fractional abundance of the i1h radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified MPCi = Maximum Permissible Concentration (MPC) of the i1h radionuclide from 10 CFR 20 (20.1-20.602), Appendix 8, Table II, Column 1.

  • % ECL = (Rel Rate) (X/Q) (100)

ECLeff 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, 8.2, C.2 and D.2 of Table 1A, µCi/sec.

3 XIQ = 4.80E-06 sec/m ; the annual average atmospheric dispersion defined in the ODCM.

I--'-

i=I ECL i where: Fi = fractional abundance of the ith radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of .all the isotopic activity, CT.

n = total number of radionuclides identified 1

ECLi = Effluent Concentration Limit (ECL) of the i h radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix 8, Table 2, Column 1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 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 = (Dil Cone) (100)

MPCett where: Oil Cone = total microcuries relea$ed in each category and each quarter divided by the total volume released (sum of Sections E and F in Table 2A); the value in Sections A.2, 8.2, and C.2 of Table 2A,

µCi/ml.

I-*-'-

i=l MPC i where: F; = fractional abundance of the i1h radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified

= Maximum Permissible Concentration (MPC) of the i1h radionuclide from 10 CFR 20 (20.1-20.602), Appendix 8, Table 11, Column 2.

  • % ECL = (Dil Cone) (100)

ECLett 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,

µCi/ml.

I--'-

i=l ECL i where: F; = fractional abundance of the i1h radionuclide obtained by dividing the activity (curies) for each radionuclide, Ci, by the sum of all the isotopic activity, CT.

n = total number of radionuclides identified 1

ECL; = Effluent Concentration Limit (ECL) of the i h radionuclide from 10 CFR 20 (20.1001-20.2402), Appendix 8, Table 2, Column 2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS (Continued)

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

C B. Table 1E lists the air doses as calculated using the historical X/Q. The air dose due to noble gases released in gaseous effluents from SONGS (per unit) to areas at and beyond the site boundary shall be limited 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 unit) to areas at and beyond the site 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- 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION F. APPLICABLE LIMITS (Continued)

APPENDIX A (Continued)

LIQUID EFFLUENTS - APPLICABLE LIMITS A. Table 2A lists the total curies released, the diluted concentration, and percent of applicable limit. The percent of applicable limit compares the diluted concentration of radioactive material released to the concentrations specified in 10 CFR 20 Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration is limited to 2.00E-04 µCi/ml.

B. Table 20 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-2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION G. ESTIMATION OF ERROR Estimations of the error in reported values of gaseous and liquid effluents releases have been made.

Sources of error for gaseous effluents batch releases are:

(1) Tank volumes (2) Sampling (3) Counting (4) Calibration Sources of error for gaseous effluents - continuous releases are:

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

(1) Tank volumes (2) Sampling (3) Counting (4) Calibration Sources of error for liquid effluents - continuous releases are:

(1) Dilution flow rate (2) Sampling (3) Counting (4) Calibration These sources of error are independent, and thus, the total error is calculated according to the following formula:

Total Error =

J CT1 2 2 2

+cr2 +()3 ***CTi 2

where: = Error associated with each component.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION H. 10 CFR 50 APPENDIX I REQUIREMENTS Table 1 in Section H presents the quarterly and annual maximum dose to an individual. Six different categories are presented:

( 1) Liquid Effluents - Whole Body (2) Liquid Effluents - Organ (3) Airborne Effluents - Tritium, Iodines and Particulates (4) Noble Gases - Gamma (5) Noble Gases - Beta (6) Direct Radiation The doses for categories 1 and 2 were calculated using the methodology of the ODCM; these data are also presented in Table 2D. Categories 3, 4, and _5 were calculated utilizing RETDAS (Radioactive Effluent Tracking and Dose Assessment Software), Regulatory Guide 1.109 methodology, and concurrent meteorology. Table 1E of gaseous effluents previously presented, however, lists data similar to categories 3, 4 and 5 using methods described in the ODCM and the historical meteorology (X/Q). Category 6 presents direct dose data measured by TLD dosimeters. Each portion of each category is footnoted to briefly describe each maximum individual dose presented.

For members of the public, per the ODCM, who may at times be within the site boundary1 , the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. For members of the public who traverse the site boundary via highway 1-5, the residency time shall be considered negligible and hence the dose "O".

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

1 ODCM Figures 1-2 & 2-2.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 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 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

6) 7) 8) 9) 10)

Organ O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO AIRBORNE

11) 12) 13) 14) 15)

EFFLUENTS Tritium, Iodines, and 6.70E-04 1.16E-03 1.74E-03 1.64E-03 5.21 E-03 Particulates NOBLE GASES ** 16) 17) 18) 19) 20)

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

21) 22) 23) 24) 25)

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

26) 27) 28) 29) 30)

DIRECT RADIATION 4.14E-02 3.33E-02 5.08E-02 2.97E-02 1.55E-01

  • 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. No liquid radioactive effluent releases occurred during this quarter.
2. No liquid radioactive effluent releases occurred during this quarter.
3. No liquid radioactive effluent releases occurred during this quarter.
4. No liquid radioactive effluent releases occurred during this quarter.
5. No liquid radioactive effluent releases occurred during this year.
6. No liquid radioactive effluent releases occurred during this quarter.
7. No liquid radioactive effluent releases occurred during this quarter.
8. No liquid radioactive effluent releases occurred during this quarter.
9. No liquid radioactive effluent releases occurred during this quarter.
10. No liquid radioactive effluent releases occurred during this year.
11. The maximum organ dose was to a child's Liver, Thyroid, Kidney, Lung, and GI-LLI and was located in the NNW sector. This was calculated using the assumptions of USN RC Regulatory Guide 1.109.
12. The maximum organ dose was to a child's Liver, Thyroid, Kidney, Lung, and GI-LLI and was located in the NNW sector. This was calculated using the assumptions of USN RC Regulatory Guide 1.109.
13. The maximum organ dose was to a child's Liver, Thyroid, Kidney, Lung, and GI-LLI and was located in the NNW sector. This was calculated using the assumptions of USN RC Regulatory Guide 1.109.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2017 SAN ONOFRE NUCLEAR GENERATING STATION

14. The maximum organ dose was to a child's Liver, Thyroid, [<idney, Lung, and GI-LLI and was located in the NNW sector. This was calculated using the assumptions of USN RC Regulatory Guide 1.109.
15. The maximum organ dose was to a child's Liver, Thyroid, Kidney, Lung, and GI-LLI and was located in the NNW sector. This was calculated using the assumptions of USN RC Regulatory Guide 1.109.
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 effluent releases occurred during this year.
21. No noble gas radioactive effluent releases occurred during this quarter.
22. No noble gas radioactive effluent releases occurred during this quarter.
23. No noble gas radioactive effluent 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. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the WNW sector.
27. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year; highest dose was measured at the Site Boundary in the WNW sector.
28. Measurements were made using TLD dosimeters; values are presented as site wide dose and are prorated to

_300 hours per year; highest dose was measured at the Site Boundary in the WNW sector.

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

NOTES:

1) TLD #46, located at San Onofre State Beach Park, was found missing during the first quarter change-out, due to vandalism or environmental effects (AR 0417-71778)
2) During the fourth quarter walk-down of TLD locations it was discovered that two ISFSI TLDs were misplaced. TLDs 302 and 303 were reversed. The TLD vendor has been notified of this issue and instructed to report the results by actual location rather than TLD number for this instance (CR SDS-000044 ).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION TABLE 2 Percent Applicable Limit First Second Third Fourth SOURCE Quarter Quarter Quarter Quarter Year LIQUID EFFLUENTS Whole Body O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Organ O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO AIRBORNE EFFLUENTS Tritium, Iodines, and 4.46E-03 7.73E-03 1.16E-02 1.09E-02 1.74E-02 Particulates NOBLE GASES Gamma O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Beta O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.0.0E+OO NOTE: Direct Radiation is not specifically addressed in the Applicable Limits.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION I. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL In accordance with Permanently Defueled Technical Specification 5.5.2.1, revisions to the SONGS Offsite Dose Calculation Manual and Appendices were implemented. The revisions incorporated:

  • The ODCM statement that before any radwaste discharges can occur, an effluent evaluation plan shall be written to address processing liquid below regulatory requirements that will include: administrative controls/factors, effluent waste flow rate, and the minimum amount of dilution flow required, based on the activity released.
  • In Environment Section 5.0, Figures 5-1 through 5-3 were updated due to location change of SONGS garden.
  • Editorial comment states that the Primary Makeup Storage Tanks are also referred to as Spent Fuel Pool Makeup Water Tanks. *
  • Appendix A Sandra Sewell to Brian Metz Memorandum for file, 2016 Dose Parameters for San Onofre Units 2 and 3, dated November 30, 2016. This change was performed under NN# 203379028.

ODCM effluent screens were performed to ensure the site's regulatory requirements of the Defueled Technical Specifications and license basis were not challenged. These changes to the ODCM and Appendices have been documented in the site's corrective action program (NN#

203063159-084, NN# 203379028, and AR# 0416-89584).

None of the changes in these revisions will adversely affect the accuracy or reliability of effluent dose calculations or set point determinations. The level of radioactive effluent control required by 10CFR20, 40CFR190, 10CFR50.36a and Appendix I to 10CFR50 will be maintained.

Throughout the document, change bars indicated 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 1-2 Table 1-1 NOTE: Primary Plant Makeup Storage tanks are also known as F Spent Fuel Pool Makeup Water Tanks.

1-9 Remove wording "and/or 14,000 gpm per saltwater cooling pumps". D Saltwater Coolina pumps are no lonaer in service.

1-9 Change wording "For radwaste discharges, the dilution water flow of R 14,000 apm shall be used and aligned to the same outfall.

1-13 Remove wording "and/or 14,000 gpm per saltwater cooling pumps". D Saltwater Coolina pumos are no lonoer in service.

1-13 Change wording "For radwaste discharges, the dilution water flow of R 14,000 qpm shall be used and alioned to the same outfall.

1-16 Remove wording "and/or 14,000 gpm per saltwater cooling pumps". D Saltwater Coolino pumps are no longer in service.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING,STATION 1-17 Remove wording "and/or 14,000 gpm per saltwater cooling pumps". D Saltwater Cooling pumps are no longer in service.-

4-19 Primary Plant Makeup Storage tanks are also known as Spent Fuel Pool F Makeup Water Tanks.

5-22 Update FiQure 5-1 due to location chanQe for SONGS Qarden. R 5-23 Update FiQure 5-2 due to location chanQe for SONGS garden. R 5-24 Update Figure 5-3 due to location change for SONGS garden. R Appendix A Updated reference for 2016 Dose Parameters for San Onofre Units 2 and R 3, dated November 30, 2016.

The Land Use Census (LUC) for 2017 did not identify a new location with a higher calculated or committed dose than those calculated for the locations evaluated in the previous revision to the ODCM. Therefore, no new location is reported per ODCM 5.2.1.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION J.

  • CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS There were no changes to the radioactive waste treatment systems.

SECTION K. MISCELLANEOUS Abnormal Releases No abnormal releases were identified in 2017.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS (Continued)

EFFLUENT MONITORING INSTRUMENTS OUT OF SERVICE GREATER THAN 30 DAYS January 1, 2017 - December 31, 2017 There were no instances of effluent monitoring instrumentation out of service for greater than 30 days in 2017.

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 lnitiatve are NIA-1, NIA-2, NIA-12, NIA-13, PA-1, PA-2, PA-3, PA-4, OCA-1, OCA-2, and OCA-3 and 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 all regulatory limits. An investigation was performed to characterize the low tritium concentrations and to identify the potential source.

The investigation determined that low tritium concentrations are present in the shallow ground water situated between the former Unit 1 containment and fuel handling building, and extend 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. An extraction plan was implemented to initiate hydraulic containment of the plume, facilitate monitoring and documentation of any changes in tritium concentration .. On April 28, 2015 the NIA extraction pumps were shut off to evaluate any potential tritium rebound affect in the NIA. This was tracked in the site's corrective action program. (NN# 203138251 ).

The site continues to sample and analyze the groundwater monitoring wells in accordance to 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-15.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS (Continued)

ONSITE GROUND WATER SAMPLES January 1, 2017 - December 31, 2017 Sample Tritium Activity Gamma Activity Gross Beta, Gross Alpha, Location Date pCi/L pCi/L pCi/L pCi/L 1/23/2017 GW-OCA-1 <LLD <LLD <LLD <LLD GW-OCA-2 <LLD <LLD 4.80E+OO 1.28E+01 GW-OCA-3 <LLD <LLD <LLD 3.30E+OO 1/25/2017 GW-PA-1 <LLD <LLD 7.56E+OO 8.19E+OO GW-PA-2 <LLD <LLD 2.67E+01 5.81E+01 GW-PA-3 <LLD <LLD 3.27E+01 7.61E+OO GW-PA-4 <LLD <LLD 7.71E+OO 4.09E+OO 1/26/17 NIA-7 N/A N/A 4.58E+OO <LLD NIA-12 <LLD <LLD 6.53E+OO <LLD NIA-13 <LLD <LLD 1.19E+01 <LLD NIA-14 N/A <LLD 1.46E+01 <LLD NIA-15 <LLD <LLD 7.10E+OO <LLD 1/30/2017 GW-NIA-2 <LLD <LLD 1.39E+01 <LLD NIA-4 <LLD N/A 1.54E+01 4.38E+OO NIA-5 <LLD N/A 1.65E+01 <LLD NIA-6 <LLD <LLD 1.48E+01 1.83E+01 NIA-10 <LLD N/A 9.83E+OO <LLD NIA-11 <LLD N/A 9.14E+OO <LLD 2/8/2017 GW-NIA-1 <LLD <LLD <LLD <LLD NIA-3 <LLD N/A 9.24E+OO <LLD NIA-7 <LLD N/A N/A N/A NIA-14 <LLD N/A N/A N/A 4/24/2017 GW-OCA-1 <LLD <LLD 5.15E+OO 9.36E+OO GW-OCA-2 <LLD <LLD 5.75E+OO 1.77E+01 GW-OCA-3 <LLD <LLD <LLD 4.21E+OO 4/26/2017 GW-NIA-1 <LLD <LLD 8.17E+OO <LLD GW-NIA-2 <LLD <LLD 9.19E+OO <LLD NIA-12 <LLD <LLD 6.43E+OO <LLD NIA-13 <LLD <LLD 9.17E+OO 7.26E+OO 5/3/2017 GW-PA-1 <LLD <LLD 6.56E+OO 1.32E+01 GW-PA-2 <LLD <LLD 3.35E+01 6.30E+01 GW-PA-3 <LLD <LLD 3.55E+01 1.15E+01 GW-PA-4 <LLD <LLD 1.67E+01 7.55E+OO ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 SAN ONOFRE NUCLEAR GENERATING STATION Sample Tritium Activity Gamma Activity Gross Beta, Gross Alpha, Location Date pCi/L pCi/L pCi/L pCi/L 7/24/2017 GW-OCA-1 <LLD <LLD <LLD <LLD GW-OCA-2 <LLD <LLD <LLD 1.4E+01 GW-OCA-3 <LLD <LLD 4.14E+OO <LLD 7/26/2017 GW-PA-1 <LLD <LLD 4.60E+OO 9.78E+OO GW-PA-2 <LLD <LLD 2.81 E+01 6.85E+01 GW-PA-3 <LLD <LLD 3.48E+01 8.04E+OO GW-PA-4 <LLD <LLD 7.96E+OO <LLD 7/27/2017 GW-NIA-1 <LLD <LLD 6.46E+OO <LLD GW-NIA-2 <LLD <LLD 1.05E+01 <LLD NIA-5 <LLD <LLD 1.08E+01 <LLD NIA-6 <LLD <LLD 1.29E+01 <LLD NIA-11 <LLD N/A 4.66E+OO 6.56E+OO NIA-12 <LLD <LLD 1.05E+01 5.85E+OO NIA-13 <LLD <LLD 6.00E+OO <LLD 12/4/2017 GW-OCA-2 <LLD <LLD 4.10E+OO 7.88E+OO 12/7/2017 GW-NIA-1 <LLD <LLD 6.16E+OO 3.96E+OO GW-NIA-2 <LLD <LLD 7.52E+OO 6.96E+OO 12/11/2017 NIA-12 <LLD <LLD 5.73E+OO <LLD NIA-13 <LLD <LLD 6.90E+OO 5.94E+OO 12/13/2017 GW-PA-1 <LLD <LLD 4.51E+OO 4.25E+OO 12/14/2017 GW-PA-4 <LLD <LLD 1.42E+01 3.56E+OO 12/18/2017 GW-PA-2 <LLD <LLD 2.74E+01 4.13E+01 GW-PA-3 <LLD <LLD 1.26E+01 <LLD 12/20/17 GW-OCA-1 <LLD <LLD 7.92E+OO 4.06E+OO GW-OCA-3 <LLD <LLD <LLD <LLD 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 = H-3: 3.0E-06 µCi/ml a priori LLD = Gross Beta: 4.0 pCi/1

= Gross Alpha: 3.0 pCi/1 The Beta and Alpha reported are of natural origin and not from plant operation based on the laboratory analyses.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION ONSITE GROUND WATER SAMPLES (Continued)

Hard to detect, pCi/L Sample Date Location (Ni-63, Fe-55, Sr-89 and or Sr-90) 1/23/2017 GW-OCA-1 <LLD GW-OCA-2 <LLD GW-OCA-3 <LLD 1/25/2017 GW-PA-1 <LLD GW-PA-2 <LLD

-GW-PA-3 <LLD GW-PA-4 <LLD 1/26/2017 NIA <LLD NIA-13 <LLD 1/30/2017 GW-NIA-2 <LLD 2/8/2017 GW-NIA-1 <LLD 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.

a priori LLD = Ni-63: 50 pCi/L

= Fe-55: 200 pCi/L

= SR-89/SR-90: 2 pCi/L ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 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 different categories presented are: (1) Total Body, (2) Limiting Organ, and (3) Thyroid.

Dose Category Units Year

1. Total Body
a. Total Body Dose mrem 6.50E-01
b. Percent ODCM Specification Limit  % 2.60E+OO
2. Limiting Organ
a. Organ Dose (All except thyroid) mrem 7.62E-04
b. Percent ODCM Specification Limit  % 3.05E-03
3. Thyroid
a. Thyroid Dose mrem 7.62E-04
b. Percent ODCM Specification Limit  % 1.02E-03 MONTHLY DOSE PROJECTIONS/40CFR190 DOSE DETERMINATION Following completion of the November 2017 monthly dose calculations it was determined that the tritium minimum detectable concentration (MDC) values used for Plant Vent Stack release calculations were incorrectly calculated. As a result, the November report did not include tritium since they indicated <MDC. Additionally, the form used for 40CFR190 dose determination was found incomplete. Both of these conditions have been corrected. No ODCM or Technical Specification limits were challenged by these errors (CR SDS-000076)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION K. MISCELLANEOUS {Continued}

CARBON-14 In June, 2009, the NRC revised its guidance in Regulatory Guide (RG) 1.21, "Measuring, Evaluating and Reporting Radioactivity In Solid Wastes And Releases Of Radioactive Materials In Liquid And Gaseous Effluents From Light-Water-Cooled Nuclear Power Plants", Revision 2.

RG 1.21 explains, that in part, the quantity of carbon-14 (C-14) discharged can be estimated by sample measurements or by use of a normalized C-14 source term and scaling factors based on power generation or estimated by use of the GALE code from NUREG-0017. The dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required. Revision 2 to RG 1.21 guidance includes:

  • If sampling is performed, the sampling frequency may be adjusted to that interval that allows adequate measurement and reporting of effluents.
  • If estimating C-14 based on scaling factors and fission rates, a precise and detailed evaluation of C-14 is not necessary. It is not necessary to calculate uncertainties for C-14 or to include C-14 uncertainty in any subsequent calculation of overall uncertainty.

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

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

U2 = 0 Calculated C-14 production, Ci/EFPY(1l U3 = 0 U2 = 0 2017 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 shutdown since January 9, 2012 for Unit 2 and January 31, 2012 for Unit 3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 SAN ONOFRE NUCLEAR GENERATING STATION SECTION L. SONGS CONCLUSIONS

1) Gaseous releases (excluding carbon-14) totaled 1.84E+01 curies of which noble gases were O.OOE+OO curies, particulates were 5.04E-06 curies, iodines were O.OOE+OO curies, and tritium was 1.84E+01 curies.
2) The radiation doses from gaseous releases were: (a) gamma air dose: O.OOE+OO mrad at the site boundary, (b) beta air dose: O.OOE+OO mrad at the site boundary, (c) organ dose (child/Liver, Thyroid, Kidney, Lung, and GI-LU ): 5.21 E-03 mrem at the highest receptor.
3) Airborne carbon-14 release was projected at O.OOE+OO curies due to the fact that both units have been permanently shut down since January 2012.
4) Liquid releases totaled O.OOE+OO curies of which particulates were O.OOE+OO curies, iodines were O.OOE+OO curies, tritium ~as O.OOE+OO curies, and noble gases were O.OOE+OO curies.
5) The radiation doses from liquid releases were: (a) total body: O.OOE+OO mrem, (b) limiting organ: O.OOE+OO 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) Two (2) shipments of dry active waste were sent from Energy Solutions LLC, Bear Creek Facility to Energy Solutions LLC, Clive Utah Disposal Site. The shipment's total volume was 8.535 cubic meters, containing 2.603E-02 curies of radioactivity.
8) Meteorological conditions during the year were typical for SONGS. Meteorological dispersion was good 41 % of the time, fair 35% of the time and poor 25% of the time.
  • 9) 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. There are low but detectable concentrations of tritium identified in the shallow ground water area formerly occupied by Unit 1 that is currently identified as the North Industrial Area. 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 was no groundwater or dewatering well effluent discharges from the site during 2017. The site continues to sample, analyze and document the results of the groundwater monitoring wells in accordance to the site's Groundwater Monitoring Program.
10) The net result from the analysis of these effluent releases indicates that the operation of SONGS has met all the requirements of the applicable regulations that ensure adequate protection of the health of members of the public.

METEOROLOGY The meteorology of the San Onofre Nuclear Generating Station for each of the four quarters, 2017 is described in this section. Meteorological measurements have been made according to the guidance provided in USNRC Regulatory Guide 1.23, "Onsite Meteorological Programs." A summary report of the meteorological measurements taken during each calendar quarter are presented in Table 4A as joint frequency distribution (JFD) of wind direction and wind speed by atmospheric stability class.

The hourly data for the Annual Report is available, but have not been included in this report because of the bulk of data records.

Table 4A lists the joint frequency distribution for each quarter, 2017. Each page of Table 4A represents the data for the individual stability classes: A, B, C, D, E, F, and G. The last page of each section shows the JFD for all the stability classes. The wind speeds have been measured at_ the 10 meter level, and the stability classes are defined by the temperature differential between the 10 meter and 40 meter levels.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 17010100-17033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILLA EXTREMELY UNSTABLE (DT/DZ :;; - 1.9 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 0 0 0 1 0 0 0 0 0 1 NNE 0 0 0 1 0 0 1 0 0 0 0 0 2 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 1 0 0 0 0 0 0 1 E 0 0 0 0 1 1 0 0 0 0 0 0 2 ESE 0 0 0 1 1 1 0 0 0 0 0 0 3 SE 0 0 0 0 0 0 3 1 1 0 0 0 5 SSE 0 0 0 1 1 5 14 5 3 0 0 0 29 s 0 0 0 2 2 9 17 6 0 0 0 0 36 SSW 0 0 0 4 9 24 11 1 0 0 0 0 49 SW 0 0 0 4 10 15 9 4 0 0 0 0 42 WSW 0 0 0 4 7 18 14 3 0 0 0 0 46 w 0 0 0 1 10 52 38 10 0 0 0 0 111 WNW 0 0 0 0 1 25 57 6 0 0 0 0 89 NW 0 0 0 1 0 1 9 2 0 0 0 0 13 NNW 0 0 0 1 2 1 0 0 0 0 0 0 4 TOTALS 0 0 0 20 44 153 174 38 4 0 0 0 433 NUMBER OF VALID HOURS 433 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 433 PASQUILL B MODERATELY UNSTABLE (- 1.9 < DT/DZ :5 - 1.7 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 0 0 0 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 1 0 0 0 0 0 1 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 1 3 1 0 1 0 0 0 6 SSE 0 0 0 0 0 2 1 1 0 0 0 0 4 s 0 0 0 1 4 2 0 0 0 0 0 0 7 SSW 0 0 2 0 2 3 0 0 0 0 0 0 7 SW 0 0 0 1 6 2 1 0 0 0 0 0 10 WSW 0 0 0 0 2 1 1 0 0 0 0 0 4 w 0 0 0 0 3 4 1 0 0 0 0 0 8 WNW 0 0 0 1 2 5 2 0 0 0 0 0 10 NW 0 0 0 0 0 0 3 0 0 0 0 0 3 NNW 0 0 0 0 1 0 0 0 0 0 0 0 1 TOTALS 0 0 2 3 21 22 12 1 1 0 0 0 62 NUMBER OF VALID HOURS 62 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 62 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 17010100-17033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE ( -1.7 < DT/DZ:::; - 1.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 0 0 1 0 0 0 0 0 0 NNE 0 0 0 1 1 1 0 0 0 0 0 0 3 NE 0 0 0 0 0 0 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 3 0 0 0 0 0 3 SE 0 0 0 0 0 1 4 3 1 0 0 0 9 SSE 0 0 0 0 2 5 4 0 0 0 0 0 11 s 0 0 0 2 0 1 3 0 0 0 0 0 6 SSW 0 0 0 2 3 4 3 0 0 0 0 0 12 SW 0 0 0 3 5 3 4 0 0 0 0 0 15 WSW 0 0 1 1 1 4 2 0 0 0 0 0 9 w 0 0 0 0 4 2 3 1 1 0 0 0 11 WNW 0 0 0 0 1 10 5 1 0 0 0 0 17 NW 0 0 0 0 0 2 6 0 0 0 0 0 8 NNW 0 0 0 0 0 0 1 0 0 0 0 0 1 TOTALS 0 0 1 9 17 34 38 5 2 0 0 0 106 NUMBER OF VALID HOURS 106 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 106 PASQUILL D NEUTRAL ( - 1.5 < DT/DZ:::; - 0.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 12 6 7 3 0 0 0 0 0 28 NNE 0 1 1 5 5 12 12 8 0 0 0 0 44 NE 0 0 1 3 2 5 2 0 0 0 0 0 13 ENE 0 0 0 1 1 2 1 0 0 0 0 0 5 E 0 1 1 2 0 5 4 0 0 0 0 0 13 ESE 0 1 0 3 8 7 10 2 2 0 0 0 33 SE 0 1 0 3 11 27 46 19 8 0 2 0 117 SSE 0 0 1 3 10 21 16 5 2 4 8 3 73 s 0 0 1 6 5 9 12 5 2 1 1 0 42 SSW 0 1 2 6 3 5 3 0 4 0 0 0 24 SW 0 0 1 3 1 3 10 4 0 0 0 0 22 WSW 0 0 1 7 3 6 14 5 2 0 0 0 38 w 0 1 1 5 7 9 10 6 12 0 0 0 51 WNW 0 0 2 5 5 8 17 9 6 0 0 0 52 NW 0 0 0 6 4 10 13 6 0 0 0 0 39 NNW 0 0 1 8 8 5 8 0 0 0 0 0 30 TOTALS 0 6 13 78 79 141 181 69 38 5 11 3 624 NUMBER OF VALID HOURS 624 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 624 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 17010100-17033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE ( - 0.5 < OT/DZ :51.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 9 17 19 3 0 0 0 0 0 49 NNE 0 1 3 20 25 33 23 1 1 0 0 0 107 NE 0 0 4 9 4 5 2 0 1 0 0 0 25 ENE 0 1 1 5 12 8 1 0 0 0 0 0 28 E 0 0 2 10 8 6 1 1 0 0 0 0 28 ESE 0 0 1 2 2 4 1 1 0 0 0 0 11 SE 0 0 1 2 2 6 2 0 0 0 0 0 13 SSE 0 0 0 4 2 2 0 1 0 0 1 1 11 s 0 0 0 1 0 1 0 0 0 0 0 0 2 SSW 1 0 1 1 2 1 1 0 0 0 0 0 7 SW 0 0 2 2 0 2 0 0 0 0 0 0 6 WSW 0 0 4 0 2 0 0 0 0 0 0 7 w 0 1 0 0 4 3 0 0 0 0 0 0 8 WNW 0 0 0 5 1 7 4 0 0 0 0 0 17 NW 0 0 1 1 5 5 1 0 0 0 0 0 13 NNW 0 0 0 3 3 4 2 0 0 0 0 0 12 TOTALS 3 18 78 87 108 41 4 2 0 344 NUMBER OF VALID HOURS 344 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 344 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ :s; 4.0 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 2 7 13 4 0 0 0 0 0 26 NNE 0 1 1 4 28 66 15 2 0 0 0 0 117 NE 0 0 1 8 10 1 5 0 0 0 0 0 25 ENE 0 0 1 4 7 2 0 0 0 0 0 0 14 E 0 0 0 0 0 4 0 0 0 0 0 0 4 ESE 0 0 0 0 0 2 1 0 0 0 0 0 3 SE 0 0 0 1 2 1 0 0 0 0 0 0 4 SSE 0 0 0 2 3 1 0 0 0 0 0 0 6 s 0 0 0 2 0 1 1 0 0 0 0 0 4 SSW 0 0 0 1 0 0 0 0 0 0 0 0 1 SW 0 0 0 1 4 0 0 0 0 0 0 0 5 WSW 0 0 0 0 0 1 0 0 0 0 0 0 1 w 0 0 1 1 3 1 0 0 0 0 0 0 6 WNW 0 0 0 0 2 5 4 0 0 0 0 0 11 NW 0 0 0 1 0 5 0 0 0 0 0 0 6 NNW 0 0 0 0 2 6 2 0 0 0 0 0 10 TOTALS 0 4 27 68 109 32 2 0 0 0 0 243 NUMBER OF VALID HOURS 243 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 243 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 METEOROLOGY January - March Table 4A SITE: SAN ONOFRE PERIOD OF RECORD 17010100-17033123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (OT/DZ> 4.0 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 1 1 5 5 0 0 0 0 0 12 NNE 0 1 0 1 5 77 153 4 0 0 0 0 241 NE 0 0 0 3 6 13 4 1 0 0 0 0 27 ENE 0 0 0 3 3 4 0 0 0 0 0 0 10 E 0 0 0 4 1 2 2 0 0 0 0 0 9 ESE 0 0 0 4 2 1 0 1 0 0 0 0 8 SE 0 0 0 2 2 0 0 0 0 0 0 0 4 SSE 0 0 0 1 0 0 0 0 0 0 0 0 s 0 0 0 2 1 2 0 0 0 0 0 0 5 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 *O 0 1 0 0 0 0 0 0 1 WSW 0 0 0 0 2 1 0 0 0 0 0 0 3 w 0 0 0 0 1 2 0 0 0 0 0 0 3 WNW 0 0 4 1 2 1 3 0 0 0 0 0 11 NW 0 0 0 2 1 1 2 0 0 0 0 0 6 NNW 0 0 1 0 2 2 2 0 0 0 0 0 7 TOTALS 0 1 5 24 29 112 171 6 0 0 0 0 348 NUMBER OF VALID HOURS 348 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 348 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 1 24 31 45 17 0 0 0 0 0 118 NNE 0 4 5 32 64 189 204 15 1 0 0 0 514 NE 0 0 6 23 22 24 13 1 1 0 0 0 90 ENE 0 1 2 13 23 17 3 0 0 0 0 0 59 E 0 1 3 16 10 18 7 1 0 0 0 0 56 ESE 0 1 1 10 13 15 15 4 2 0 0 0 61 SE 0 1 1 8 18 38 56 23 11 0 2 0 158 SSE 0 0 1 11 18 36 35 12 5 4 9 4 135 s 0 0 1 16 12 25 33 11 2 1 1 0 102 SSW 1 1 5 14 19 37 18 1 4 0 0 0 100 SW 0 0 3 14 26 26 24 8 0 0 0 0 101 WSW 0 0 3 16 15 33 31 8 2 0 0 0 108 w 0 2 2 7 32 73 52 17 13 0 0 0 198 WNW 0 0 6 12 14 61 92 16 6 0 0 0 207 NW 0 0 1 11 10 24 34 8 0 0 0 0 88 NNW 0 0 2 12 18 18 15 0 0 0 0 0 65 TOTALS 1 11 43 239 345 679 649 125 47 5 12 4 2160 NUMBER OF VALID HOURS 2160 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2160 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17040100-17063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILLA EXTREMELY UNSTABLE (OT/DZ::; - 1.9 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 0 0 1 0 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 1 1 0 0 0 0 2 ENE 0 0 0 0 0 1 0 0 0 0 0 0 1 E 0 0 0 1 1 0 0 1 0 0 0 0 3 ESE 0 0 0 2 0 2 0 0 0 0 0 0 4 SE 0 0 0 0 1 1 0 2 0 0 0 0 4 SSE 0 0 0 0 2 2 14 2 5 0 0 0 25 s 0 0 0 1 8 21 46 11 2 0 0 0 89 SSW 0 0 0 2 8 22 42 9 0 0 0 0 83 SW 0 0 0 7 19 53 36 2 1 0 0 0 118 WSW 0 0 0 2 28 83 35 0 0 0 0 0 148 w 0 0 0 1 16 97 89 1 0 0 0 0 204 WNW 0 0 0 1 3 36 64 11 2 0 0 0 117 NW 0 0 0 1 0 3 10 7 0 0 0 0 21 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 0 18 86 322 337 47 10 0 0 0 820 NUMBER OF VALID HOURS 820 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 820 PASQUILL B MODERATELY UNSTABLE ( - 1.9 < OT/DZ::; - 1. 7 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 0 1 1 0 0 0 0 0 0 2 0 0 0 0 1 0 1 0 0 0 0 0 0 2 NE 0 0 0 1 1 2 1 0 0 0 0 0 5 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 2 0 0 0 0 0 2 SSE 0 0 0 2 1 4 10 2 0 0 0 0 19 s 0 0 0 2 0 3 7 2 0 0 0 0 14 SSW 0 0 0 3 3 5 3 1 0 0 0 0 15 SW 0 0 0 3 2 5 4 1 0 0 0 0 15 WSW 0 0 0 1 3 2 1 0 0 0 0 0 7 w 0 0 0 3 4 1 0 0 0 0 0 0 8 WNW 0 0 0 0 2 3 4 0 0 0 0 0 9 NW 0 0 0 0 2 8 4 0 0 0 0 0 14 NNW 0 0 0 0 1 1 1 0 0 0 0 0 3 TOTALS 0 0 0 16 20 36 37 6 0 0 0 0 115 NUMBER OF VALID HOURS 115 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 115 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17040100-17063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE ( -1.7 < DT/DZ s; - 1.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 3 6 1 0 0 0 0 0 0 10 NNE 0 0 0 5 2 3 1 0 0 0 0 0 11 NE 0 0 0 1 1 1 0 0 0 0 0 0 3 ENE 0 0 0 0 1 1 0 0 0 0 0 0 2 E 0 0 1 0 0 2 0 0 0 0 0 0 3 ESE 0 0 0 0 0 1 3 0 0 0 0 0 .4 SE 0 0 1 1 1 13 10 2 0 0 0 0 28 SSE 0 0 0 0 3 13 20 1 0 0 0 0 37 s 0 0 1 4 6 10 12 2 0 0 0 0 35 SSW 0 0 0 4 4 5 6 1 0 0 0 0 20 SW 0 1 1 1 4 14 7 4 0 0 0 0 32 WSW 0 0 0 3 3 7 1 0 0 0 0 0 14 w 0 0 0 5 3 2 0 0 0 0 0 0 10 WNW 0 0 4 5 4 2 1 0 0 0 0 0 16 NW 0 0 0 2 4 5 1 1 0 0 0 0 13 NNW 0 0 0 1 4 1 3 0 0 0 0 0 9 TOTALS 0 1 8 35 46 81 65 11 0 0 0 0 247 NUMBER OF VALID HOURS 247 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 247 PASQUILL D NEUTRAL ( - 1.5 < DT/DZ s; - 0.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 2 8 7 1 2 0 0 0 0 0 20 NNE 0 0 2 5 7 10 16 8 0 0 0 0 48 NE 0 1 0 1 2 2 1 0 1 0 0 0 8 ENE 0 0 2 4 4 1 0 0 0 0 0 0 11 E 0 0 1 1 2 6 1 0 0 0 0 0 11 ESE 0 0 0 5 8 19 11 0 0 0 0 0 43 SE 0 0 1 7 15 33 46 7 0 0 0 0 109 SSE 0 0 0 9 9 14 19 6 0 0 0 0 57 s 0 0 2 3 7 12 15 5 0 0 0 0 44 SSW 0 2 2 7 3 12 7 5 0 0 0 0 38 SW 0 1 1 8 4 3 1 2 0 0 0 0 20 WSW 1 0 0 4 1 2 2 5 0 0 0 0 15 w 3 0 0 4 0 11 15 5 0 0 0 0 38 WNW 0 1 1 2 1 10 5 1 0 0 0 0 21 NW 0 1 1 7 7 7 15 4 0 0 0 0 42 NNW 0 0 2 13 7 5 4 0 0 0 0 0 31 TOTALS 4 6 17 88 84 148 160 48 1 0 0 0 556 NUMBER OF VALID HOURS 556 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 556 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17040100-17063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE ( - 0.5 < DT/DZ s 1.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 1 1 5 2 0 0 0 0 0 0 9 NNE 0 1 0 5 15 22 11 1 1 0 0 0 56 NE 0 0 0 4 3 0 1 0 1 0 0 0 9 ENE 0 0 0 3 1 2 0 0 0 0 0 0 6 E 0 0 1 3 4 9 0 0 0 0 0 0 17 ESE 0 0 1 2 2 1 1 0 0 0 0 0 7 SE 0 0 0 1 2 3 5 0 0 0 0 0 11 SSE 0 0 1 0 5 2 0 0 0 0 0 0 8 s 0 0 0 1 0 2 0 0 0 0 0 0 3 SSW 0 0 0 3 0 1 0 0 0 0 0 0 4 SW 0 0 0 0 1 1 0 0 0 0 0 0 2 WSW 0 0 1 4 1 0 0 0 0 0 0 0 6 w 0 0 2 2 3 4 0 0 0 0 0 0 11 WNW 0 0 0 2 1 1 4 0 0 0 0 0 8 NW 0 0 0 1 5 2 2 0 0 0 0 0 10 NNW 0 0 0 2 2 3 3 0 0 0 0 0 10 TOTALS 0 1 7 34 50 55 27 1 2 0 0 0 177 NUMBER OF VALID HOURS 177 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 177 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ:;; 4.0 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 2 5 3 1 0 0 0 0 0 11 NNE 0 0 0 8 17 40 4 0 0 0 0 0 69 NE 0 0 2 5 8 2 1 0 0 0 0 0 18 ENE 0 0 0 1 2 1 1 0 0 0 0 0 5 E 0 1 0 1 2 1 0 0 0 0 0 0 5 ESE 0 0 1 0 1 0 0 0 0 0 0 0 2 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 1 1 1 0 0 0 0 0 0 0 3 s 0 0 0 0 1 0 0 0 0 0 0 0 1 SSW 0 0 0 3 1 0 0 0 0 0 0 0 4 SW 0 0 0 1 1 1 1 0 0 0 0 0 4 WSW 0 0 0 1 1 1 0 0 0 0 0 0 3 w 0 0 0 0 2 1 1 0 0 0 0 0 4 WNW 0 0 0 0 2 1 1 0 0 0 0 0 4 NW 0 0 0 1 0 0 0 0 0 0 0 0 1 NNW 0 0 2 1 3 .0 0 0 0 0 0 0 6 TOTALS 0 1 6 25 47 51 10 0 0 0 0 0 140 NUMBER OF VALID HOURS 140 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 140 l

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY April - June TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17040100-17063023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 0 1 0 1 0 0 0 0 0 2 NNE 0 0 1 0 8 56 35 0 0 0 0 0 100 NE 0 0 0 2 4 7 2 0 0 0 0 0 15 ENE 0 0 0 1 0 2 0 0 0 0 0 0 3 E 0 0 0 0 0 0 1 0 0 0 0 0 1 ESE 0 0 0 0 0 0 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 s 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 0 1 0 0 0 0 0 0 0 1 w 0 0 0 0 0 0 0 0 0 0 0 0 0 WNW 0 0 0 0 1 0 0 0 0 0 0 0 1 NW 0 0 0 0 1 2 1 0 0 0 0 0 4 NNW 0 0 0 0 1 1 0 0 0 0 0 0 2 TOTALS 0 0 1 3 17 68 40 0 0 0 0 0 129 NUMBER OF VALID HOURS 129 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 129 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 3 14 25 9 4 0 0 0 0 0 55 NNE 0 1 3 24 49 132 67 9 1 0 0 0 286 NE 0 1 2 14 19 14 7 1 2 0 0 0 60 ENE 0 0 2 9 8 8 1 0 0 0 0 0 28 E 0 1 3 6 9 18 2 1 0 0 0 0 40 ESE 0 0 2 9 11 23 15 0 0 0 0 0 60 SE 0 0 2 9 19 50 63 11 0 0 0 0 154 SSE 0 0 2 12 21 35 63 11 5 0 0 0 149 s 0 0 3 11 22 48 80 20 2 0 0 0 186 SSW 0 2 2 22 19 45 58 16 0 0 0 0 164 SW 0 2 2 20 31 77 49 9 1 0 0 0 191 WSW 1 0 1 15 38 95 39 5 0 0 0 0 194 w 3 0 2 15 28 116 105 6 0 0 0 0 275 WNW 0 1 5 10 14 53 79 12 2 0 0 0 176 NW 0 1 1 12 19 27 33 12 0 0 0 0 105 NNW 0 0 4 17 18 11 11 0 0 0 0 0 61 TOTALS 4 9 39 219 350 761 676 113 13 0 0 0 2184 NUMBER OF VALID HOURS 2184 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2184 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 METEOROLOGY July- September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17070100-17093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILLA EXTREMELY UNSTABLE (OT/DZ:,; - 1.9 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 1 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 0 0 0 0 0 0 NE 0 0 0 0 0 1 0 0 0 0 0 0 1 ENE 0 0 0 1 1 0 . 0 0 0 0 0 0 2 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 1 0 0 0 0 0 0 0 0 1 SE 0 0 1 2 1 1 2 0 0 0 0 0 7 SSE 0 0 0 1 0 9 10 3 0 0 0 0 23 s 0 0 0 5 5 12 34 5 0 0 0 0 61 SSW 0 0 0 3 10 32 40 2 0 0 0 0 87 SW 0 0 0 6 12 58 73 3 0 0 0 0 152 WSW 0 0 1 4 22 76 76 0 0 0 0 0 179 w 0 0 0 2 20 85 113 0 0 0 0 0 220 WNW 0 0 0 3 11 51 82 6 0 0 0 0 153 NW 0 0 1 0 0 7 8 0 0 0 0 0 16 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 3 29 82 332 438 19 0 0 0 0 903 NUMBER OF VALID HOURS 903 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 903 PASQUILL B MODERATELY UNSTABLE ( -1.9 < OT/DZ S-1.7 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 1 0 0 0 0 0 0 0 0 0 1 NNE 0 0 0 0 0 4 2 0 0 0 0 0 6 NE 0 0 0 0 1 3 0 0 0 0 0 0 4 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 1 0 0 0 0 0 0 0 0 1 ESE 0 0 0 0 1 0 0 0 ci 0 0 0 1 SE 0 0 0 1 1 1 1 0 0 0 0 0 4 SSE 0 0 0 0 1 4 3 1 0 0 0 0 9 s 0 0 0 2 1 4 5 0 0 0 0 0 12 SSW 0 0 0 2 6 3 0 0 0 0 0 0 11 SW 0 0 0 4 6 2 2 0 0 0 0 0 14 WSW 0 0 0 3 3 6 3 0 0 0 0 0 15 w 0 0 2 3 2 4 1 0 0 0 0 0 12 WNW 0 0 0 3 7 4 0 0 0 0 0 0 14 NW 0 0 0 4 4 4 5 0 0 0 0 0 17 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 3 23 33 39 22 1 0 0 0 0 121 NUMBER OF VALID HOURS 123 NUMBER OF CALMS 2 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 123 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17070100-17093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE (- 1.7 <OT/DZ::; - 1.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 1 0 3 2 0 0 0 0 0 0 0 6 NNE 0 0 0 4 5 6 0 0 0 0 0 0 15 NE 0 0 0 2 3 5 0 0 0 0 0 0 10 ENE 0 0 0 0 2 2 0 0 0 0 0 0 4 E 0 0 0 2 2 3 0 0 0 0 0 0 7 ESE 0 0 0 0 1 2 1 0 0 0 0 0 4 SE 0 0 0 2 2 11 5 0 0 0 0 0 20 SSE 0 0 0 2 8 11 7 4 0 0 0 0 32 s 0 0 1 2 7 12 4 1 0 0 0 0 27 SSW 0 0 0 3 6 14 2 0 0 0 0 0 25 SW 0 1 0 4 10 4 2 0 0 0 0 0 21 WSW 0 0 0 6 6 2 9 1 0 0 0 0 24 w 0 0 0 3 6 4 8 1 0 0 0 0 22 WNW 0 0 0 7 3 0 0 0 0 0 0 0 10 NW 0 0 1 7 2 2 3 0 0 0 0 0 15 NNW 0 0 2 2 2 0 1 0 0 0 0 0 7 TOTALS 0 2 4 49 67 78 42 7 0 0 0 0 249 NUMBER OF VALID HOURS 250 NUMBER OF CALMS NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 250 PASQUILL D NEUTRAL ( - 1.5 < OT/DZ ::; - 0.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 5 12 6 4 1 0 0 0 0 0 28 NNE 1 1 2 7 13 15 1 0 0 0 0 0 40 NE 0 2 0 5 3 1 0 0 0 0 0 0 11 ENE 0 2 1 7 4 1 0 0 0 0 0 0 15 E 1 1 1 7 4 1 0 0 0 0 0 0 15 ESE 0 2 0 6 11 19 0 0 0 0 0 0 38 SE 0 0 1 5 9 29 22 3 0 0 0 0 69 SSE 2 2 3 7 6 15 23 4 0 0 0 0 62 s 0 0 1 12 4 10 12 0 0 0 0 0 39 SSW 0 2 1 6 3 7 6 0 0 0 0 0 25 SW 0 2 2 7 1 5 1 0 0 0 0 0 18 WSW 0 4 1 6 2 5 2 1 0 0 0 0 21 w 1 1 5 10 4 3 14 0 0 0 0 0 38 WNW 1 0 3 6 5 8 4 0 0 0 0 0 27 NW 0 2 3 3 6 8 6 1 0 0 0 0 29 NNW 0 2 2 9 8 10 3 0 0 0 0 0 34 TOTALS 6 23 31 115 89 141 95 9 0 0 0 0 509 NUMBER OF VALID HOURS 518 NUMBER OF CALMS 9 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 518 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2017 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17070100-17093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE ( - 0.5 < DT/DZ ~ 1.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 2 2 4 4 0 0 0 0 0 0 12 NNE 0 0 0 23 17 21 1 0 0 0 0 0 62 NE 1 0 0 6 1 0 1 0 0 0 0 0 9 ENE 0 1 2 6 5 3 0 0 0 0 0 0 17 E 0 0 0 5 0 1 0 0 0 0 0 0 6 ESE 0 0 0 2 2 1 0 0 0 0 0 0 5 SE 1 1 1 0 0 2 0 1 0 0 0 0 6 SSE 0 1 1 3 2 3 4 0 0 0 0 0 14 s 0 0 2 2 2 0 1 0 0 0 0 0 7 SSW 1 0 1 2 0 1 0 0 0 0 0 0 5 SW 0 0 0 1 2 0 0 0 0 0 0 0 3 WSW 0 2 0 1 1 1 1 0 0 0 0 0 6 w 0 0 1 2 0 0 1 0 0 0 0 0 4 WNW 1 1 1 2 1 3 1 0 0 0 0 0 10 NW 0 1 0 3 2 3 1 0 0 0 0 0 10 NNW 0 0 2 2 1 2 1 0 0 0 0 0 8 TOTALS 4 7 13 62 40 45 12 1 0 0 0 0 184 NUMBER OF VALID HOURS 184 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 184 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ ~ 4.0 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 5 2 4 0 0 0 0 0 0 11 NNE 0 0 2 6 15 32 4 0 0 0 0 0 59 NE 0 0 0 3 1 3 0 0 0 0 0 0 7 ENE 0 0 0 2 1 0 0 0 0 0 0 0 3 E 0 0 0 3 1 1 0 0 0 0 0 0 5 ESE 0 0 0 1 0 0 0 0 0 0 0 0 1 SE 0 0 0 1 0 1 0 0 0 0 0 0 2 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 s 0 0 0 1 0 1 0 0 0 0 0 0 2 SSW 0 0 0 1 0 0 0 0 0 0 0 0 1 SW 0 0 1 1 0 0 0 0 0 0 0 0 2 WSW 0 0 0 0 2 3 0 0 0 0 0 0 5 w 0 0 0 1 0 0 0 0 0 0 0 0 1 WNW 0 0 0 0 0 1 0 0 0 0 0 0 1 NW 0 0 1 2 0 1 0 0 0 0 0 0 4 NNW 0 0 0 3 1 0 0 0 0 0 0 0 4 TOTALS 0 0 4 30 23 47 4 0 0 0 0 0 108 NUMBER OF VALID HOURS 125 NUMBER OF CALMS 17 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 125 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY July - September TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17070100-17093023 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (DT/DZ > 4.0 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 1 1 2 0 0 0 0 0 0 4 NNE 0 0 0 2 2 31 24 0 0 0 0 0 59 NE 0 0 0 1 2 3 1 0 0 0 0 0 7 ENE 0 0 0 0 1 1 0 0 0 0 0 0 2 E 0 0 0 0 2 2 0 0 0 0 0 0 4 ESE 0 0 0 1 2 0 1 0 0 0 0 0 4 SE 0 0 1 0 0 0 0 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 0 0 0 0 0 0 s 0 0 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 1 0 0 0 0 0 0 0 0 0 1 SW 0 0 0 0 1 0 0 0 0 0 0 0 1 WSW 0 0 0 1 0 1 0 0 0 0 0 0 2 w 0 0 0 1 2 1 0 0 0 0 0 0 4 WNW 0 0 0 3 0 0 0 0 0 0 0 0 3 NW 0 0 0 1 0 2 0 0 0 0 0 0 3 NNW 0 0 0 1 0 0 0 0 0 0 0 0 TOTALS 0 0 2 12 13 43 26 0 0 0 0 0 96 NUMBER OF VALID HOURS 105 NUMBER OF CALMS 9 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 105 ALL STABILITY CLASSES, ALL DT/DZ WIND SPEED (M/S) AT 10 METER LEVEL Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 1 8 24 15 14 1 0 0 0 0 0 63 NNE 1 1 4 42 52 109 32 0 0 0 0 0 241 NE 1 2 0 17 11 16 2 0 0 0 0 0 49 ENE 0 3 3 16 14 7 0 0 0 0 0 0 43 E 1 1 1 18 9 8 0 0 0 0 0 0 38 ESE 0 2 0 11 17 22 2 0 0 0 0 0 54 SE 1 1 4 11 13 45 30 4 0 0 0 0 109 SSE 2 3 4 13 17 42 47 12 0 0 0 0 140 s 0 0 4 24 19 39 56 6 0 0 0 0 148 SSW 1 2 3 17 25 57 48 2 0 0 0 0 155 SW 0 3 3 23 32 69 78 3 0 0 0 0 211 WSW 0 6 2 21 36 94 91 2 0 0 0 0 252 w 1 1 8 22 34 97 137 1 0 0 0 0 301 WNW 2 1 4 24 27 67 87 6 0 0 0 0 218 NW 0 3 6 20 14 27 23 1 0 0 0 0 94 NNW 0 2 6 17 12 12 5 0 0 0 0 0 54 TOTALS 10 32 60 320 347 725 639 37 0 0 0 0 2170 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS 38 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17100100-17123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILLA EXTREMELY UNSTABLE (DT/DZ s; - 1.9 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 1 1 1 0 0 0 0 0 0 0 3 NNE 0 0 0 0 0 0 0 1 0 0 0 0 1 NE 0 0 0 0 0 0 2 3 1 0 0 0 6 ENE 0 0 0 1 0 2 0 0 0 0 0 0 3 E 0 0 0 0 1 0 0 0 0 0 0 0 1 ESE 0 0 0 0 0 1 0 0 0 0 0 0 1 SE 0 0 0 0 0 1 2 0 0 0 0 0 3 SSE 0 0 0 0 2 1 7 6 2 0 0 0 18 s 0 0 0 1 1 4 12 5 1 0 0 0 24 SSW 0 0 0 2 10 9 7 1 0 0 0 0 29 SW 0 0 0 6 4 7 6 0 0 0 0 0 23 WSW 0 0 0 2 16 22 9 1 0 0 0 0 50 w 0 0 0 1 11 64 51 1 0 0 0 0 128 WNW 0 0 0 0 6 43 63 2 0 0 0 0 114 NW 0 0 0 0 2 4 2 2 0 0 0 0 10 NNW 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTALS 0 0 1 14 54 158 161 22 4 0 0 0 414 NUMBER OF VALID HOURS 414 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 414 PASQUILL B MODERATELY UNSTABLE (- 1.9 < DT/DZ s; - 1.7 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 0 0 0 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 1 1 0 0 0 0 2 NE 0 0 0 0 0 0 0 3 1 0 0 0 4 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 2 0 0 0 0 0 0 2 SE 0 0 0 0 0 0 2 0 0 0 0 0 2 SSE 0 0 0 0 1 0 1 0 0 0 0 0 2 s 0 0 0 2 1 0 1 0 0 0 0 0 4 SSW 0 0 0 1 0 0 0 0 0 0 0 0 1 SW 0 0 0 . 0 1 2 1 0 0 0 0 0 4 WSW 0 0 0 0 0 1 0 0 0 0 0 0 1 w 0 0 0 0 2 4 0 0 0 0 0 0 6 WNW 0 0 0 0 3 4 8 0 0 0 0 0 15 NW 0 0 0 0 0 1 4 0 0 0 0 0 5 NNW 0 0 0 1 1 0 0 0 0 0 0 0 2 TOTALS 0 0 0 4 9 14 18 4 1 0 0 0 50 NUMBER OF VALID HOURS 50 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 50 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17100100-17123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL C SLIGHTLY UNSTABLE ( - 1.7 < DT/DZ :s; - 1.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 1 0 0 0 0 0 0 0 0 1 NNE 0 0 0 0 1 2 0 1 0 0 0 0 4 NE 0 0 0 0 0 0 1 1 0 0 0 0 2 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 2 0 0 0 0 2 ESE 0 0 0 1 1 0 1 1 0 0 0 0 4 SE 0 0 0 0 0 0 4 1 0 0 0 0 5 SSE 0 0 0 1 0 0 2 1 2 0 0 0 6 s 0 0 0 0 0 1 1 0 0 0 0 0 2 SSW 0 0 0 0 1 1 0 0 0 0 0 0 2 SW 0 0 1 0 0 0 0 0 0 0 0 0 1 WSW 0 0 0 0 1 1 1 0 0 0 0 0 3 w 0 0 0 0 1 2 1 0 0 0 0 0 4 WNW 0 0 1 1 2 3 3 1 0 0 0 0 11 NW 0 0 0 0 0 4 1 1 0 0 0 0 6 NNW 0 0 0 0 0 2 0 0 0 0 0 0 2 TOTALS 0 0 2 4 7 16 15 9 2 0 0 0 55 NUMBER OF VALID HOURS 55 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 55 PASQUILL D NEUTRAL ( - 1.5 < DT/DZ :s; - 0.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 0 5 5 6 0 0 0 0 0 0 16 NNE 0 1 1 2 2 5 4 1 0 0 0 0 16 NE 0 0 0 2 2 0 0 1 1 0 0 0 6 ENE 0 0 0 0 0 0 0 0 0 0 0 0 0 E 0 1 0 0 2 3 0 1 0 0 0 0 7 ESE 0 0 0 1 1 15 10 0 0 0 0 0 27 SE 0 0 3 5 1 17 28 8 0 0 0 0 62 SSE 0 1 0 2 4 2 17 4 1 0 0 0 31 s 0 0 0 3 7 3 10 2 0 0 0 0 25 SSW 0 0 0 2 0 2 4 1 0 0 0 0 9 SW 0 0 2 2 1 0 1 0 0 0 0 0 6 WSW 0 0 0 2 2 2 1 0 0 0 0 0 7 w 1 0 2 3 4 11 8 0 0 0 0 0 29 WNW 0 0 1 3 5 5 0 2 0 0 0 0 16 NW 0 0 0 3 6 13 8 0 0 0 0 0 30 NNW 0 0 0 6 3 7 3 0 0 0 0 0 19 TOTALS 1 3 9 41 45 91 94 20 2 0 0 0 306 NUMBER OF VALID HOURS 306 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 306 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17100100-17123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL E SLIGHTLY STABLE ( - 0.5 < DT/DZ:,; 1.5 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1.5 2 3 5 7 10 13 18 N 0 0 4 4 16 2 0 0 0 0 0 27 NNE 0 2 6 10 20 25 1 0 0 0 0 65 NE 0 1 5 3 4 6 9 6 6 1 0 0 41 ENE 0 1 0 8 6 3 0 1 1 0 0 0 20 E 0 0 1 2 4 5 5 2 0 0 0 0 19 ESE 0 0 1 2 10 3 2 0 0 0 0 0 18 SE 1 0 2 2 0 3 3 0 0 0 0 0 11 SSE 0 0 1 0 0 1 1 0 0 0 0 0 3 s 0 0 0 2 4 2 1 0 0 0 0 0 9 SSW 0 0 0 3 1 2 0 0 0 0 0 0 6 SW 0 0 3 1 2 0 0 0 0 0 0 7 WSW 0 4 1 1 1 0 0 0 0 0 9 w 0 0 0 1 11 5 0 0 0 0 0 18 WNW 0 0 2 5 9 15 5 0 0 0 0 0 36 NW 0 1 4 3 5 2 0 0 0 0 0 16 NNW 0 0 2 5 7 0 0 0 0 0 16

  • TOTALS 2 6 17 51 73 96 58 10 7 1 0 0 321 NUMBER OF VALID HOURS 321 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 321 PASQUILL F MODERATELY STABLE (1.5 < DT/DZ:,; 4.0 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 0 0 2 5 3 7 0 0 0 0 0 18 NNE 0 0 16 34 57 22 4 0 0 0 0 134 NE 1 0 5 11 21 5 3 1 0 0 0 0 47 ENE 0 1 0 9 7 2 1 0 0 0 0 0 20 E 1 0 3 8 4 3 0 0 0 0 0 0 19 ESE 0 0 3 4 3 3 0 0 0 0 0 0 13 SE 1 0 0 2 1 6 2 0 0 0 0 0 12 SSE 0 0 0 2 1 1 0 0 0 0 0 0 4 s 0 0 2 0 2 1 0 0 0 0 0 0 5 SSW 0 0 1 6 0 0 0 0 0 0 0 0 7 SW 0 0 0 4 1 1 1 0 0 0 0 0 7 WSW 0 1 1 3 2 0 0 0 0 0 9 w 0 1 1 6 3 5 0 0 0 0 0 0 16 WNW 0 1 1 4 9 15 4 0 0 0 0 0 34 NW 0 1 0 0 3 3 1 0 0 o* 0 0 8 NNW 0 0 0 4 2 7 2 0 0 0 0 0 15 TOTALS 3 5 19 79 99 114 44 5 0 0 0 0 368 NUMBER OF VALID HOURS 368 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 368 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2017 METEOROLOGY October - December TABLE 4A SITE: SAN ONOFRE PERIOD OF RECORD 17100100-17123123 WIND SPEED (M/S) AT 10 METER LEVEL PASQUILL G EXTREMELY STABLE (OT/DZ> 4.0 °C/100 METERS)

Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 1 1 0 3 3 10 7 0 0 0 0 0 25 NNE 0 1 1 10 10 145 225 12 0 0 0 0 404 NE 0 0 3 12 19 32 17 0 0 0 0 0 83 ENE 0 0 1 5 10 9 6 0 0 0 0 0 31 E 0 2 4 8 7 3 1 0 0 0 0 0 25 ESE 1 1 1 5 1 3 0 0 0 0 0 0 12 SE 0 0 1 4 2 2 1 0 0 0 0 0 10 SSE 0 0 2 0 3 1 0 0 0 0 0 0 6 s 0 0 0 4 4 0 6 0 0 0 0 0 14 SSW 1 0 2 1 2 3 0 0 0 0 0 0 9 SW 0 0 1 7 2 0 2 0 0 0 0 0 12 WSW 0 1 0 3 1 0 0 0 0 0 0 0 5 w 0 0 1 2 4 2 2 0 0 0 0 0 11 WNW 0 1 3 3 7 11 3 1 0 0 0 0 29 NW 0 0 1 1 5 1 1 0 0 0 0 0 9 NNW 0 1 0 1 2 3 2 0 0 0 0 0 9 TOTALS 3 8 21 69 82 225 273 13 0 0 0 0 694 NUMBER OF VALID HOURS 694 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 694 ALL STABILITY CLASSES, ALL OT/DZ WIND SPEED (M/S) AT 10 METER LEVEL Wind 0.22 0.51 0.76 1.1 1.6 2.1 3.1 5.1 7.1 10.1 13.1 >18 TOTAL Dir 0.5 0.75 1 1.5 2 3 5 7 10 13 18 N 1 1 3 16 18 35 16 0 0 0 0 0 90 NNE 0 4 4 34 57 229 277 21 0 0 0 0 626 NE 1 1 13 28 46 43 32 15 9 1 0 0 189 ENE 0 2 1 23 23 16 7 1 1 0 0 0 74 E 1 3 8 18 18 14 6 5 0 0 0 0 73 ESE 1 1 5 13 16 27 13 1 0 0 0 0 77 SE 2 0 6 13 4 29 42 9 0 0 0 0 105 SSE 0 1 3 5 11 6 28 11 5 0 0 0 70 s 0 0 2 12 19 11 31 7 1 0 0 0 83 SSW 1 0 3 15 14 17 11 2 0 0 0 0 63 SW 0 1 4 22 10 12 11 0 0 0 0 0 60 WSW 1 2 2 12 24 29 13 1 0 0 0 0 84 w 1 1 4 13 36 93 63 1 0 0 0 0 212 WNW 0 2 8 16 41 96 86 6 0 0 0 0 255 NW 0 2 2 8 19 31 19 3 0 0 0 0 84 NNW 0 1 1 14 13 26 8 0 0 0 0 0 63 TOTALS 9 22 69 262 369 714 663 83 16 1 0 0 2208 NUMBER OF VALID HOURS 2208 NUMBER OF CALMS 0 NUMBER OF INVALID HOURS 0 TOTAL HOURS FOR THE PERIOD 2208 Enclosure 2 Offsite Dose Calculation Manual Nuclear Organization San Onofre Nuclear Generation Station (SONGS)

S0123-0DCM Revision 11, August 2017

August30,2017 Mr. Tom Palmisano

SUBJECT:

San Onofre Nuclear Generating Station (SONGS) Offsite Dose Calculation Manual (ODCM) and Appendices: S0123-0DCM Revision 11, S0123-0DCM-A Revision 11,

  • After the installation and testing of the saltwater dilution pumps, the saltwater dilution pumps are unable to achieve a 28,000 gpm dilution flowrate for radwaste batch releases.

The ODCM shall state that before any radwaste discharges can occur, an effluent evaluation plan shall be written to address processing liquid below regulatory requirements that will include: administrative controls/factors, effluent waste flow rate, and the minimum amount of dilution flow required, based on the activity released.*

  • In Environment Section 5.0, Figures 5-1 through 5-3 were updated due to location change of SONGS garden.

ODCM effluent screens were performed to ensure the site's regulatory requirements of the Defueled Technical Specifications and license basis were not challenged. These changes to the ODCM and Appendices have been documented in the site's corrective action program (NN# 203063159-084, NN# 203379028, and AR# 0416-89584).

These revisions incorporate the following:

1. The saltwater dilution pumps are unable to achieve the 28,000 gpm for radwaste releases.

ODCM screen was performed under AR# 0416-89584.

2. Editorial comment states that the Primary Makeup Storage Tanks are also referred to as Spent Fuel Pool Makeup Water Tanks. *
3. Environment Section 5.0, Figures 5-1 through 5-3 were changed to reflect the location change of SONGS REMP garden. The ODCM screen was performed under NN# 203063159-084.
4. Appendix A Sandra Sewell to Brian Metz Memorandum for file, 2016 Dose Parameters for San Onofre Units 2 arid 3, dated November 30, 2016. This change was performed under NN# 203379028.

None of the changes in these revisions will adversely affect the accuracy or reliability of effluent dose calculations or set point determinations. Your approval for these revisions is requested.

Please contact me if there are any questions.

Brian Metz Approved Electronically For Jason Janke Manager, Radiation Protection, Chemistry and Environmental Approved Electronically Approved by:

Thomas J. Palmisano Vice President Decommissioning and Chief Nuclear Officer Attachment cc: eDMRM NRA File

August 30, 2017

SUBJECT:

San Onofre Nuclear Generating Station (SONGS) Offsite Dose Calculation Manual (ODCM) and Appendices: S0123-0DCM Revision 11, S0123-0DCM-A Revision 11, and S0123-0DCM-B Revision 9 Enclosed are the revisions to the SONGS Offsite Dose Calculation Manual (ODCM) and Appendices. ODCM effluent reviews were required and performed for the changes.

These revisions incorporate the following:

1. The saltwater dilution pumps are unable to achieve the 28,000 gpm for radwaste releases.

ODCM screen was performed under AR# 0416-89584.

2. Editorial comment states the Primary Makeup Storage Tank are also referred to as Spent Fuel Pool Makeup Water Tanks.
3. Environment Section 5.0, Figures 5-1 through 5-3 were changed to reflect the location change of SONGS REMP garden. The ODCM screen was performed under NN# 203063159-084.
4. Appendix A Sandra Sewell to Brian Metz Memorandum for file 2016 Dose Parameters for San Onofre Units 2 and 3, dated November 30, 2016. This change was performed under NN# 203379028.

None of the changes impact the accuracy or reliability of effluent dose or set point calculations. The level of radioactive effluent control required by 10 CFR 20, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 will be maintained.

Page 1 of 2

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 Table 1-1 NOTE: Primary Plant Makeup Storage tanks are also known as F 1-2 Spent Fuel Pool Makeup Water Tanks.

Remove wording "and/or 14,000 gpm per saltwater cooling pumps". D 1-9 Saltwater Coolina pumps are no longer in service.

Change wording "For radwaste discharges, the dilution water flow of R 1-9 14,000 apm shall be used and aligned to the same outfall.

Remove wording "and/or 14,000 gpm per saltwater cooling pumps". D 1-13 Saltwater Coolina pumps are no longer in service.

Change wording "For radwaste discharges, the dilution water flow of R 1-13 14,000 qpm shall be used and alianed to the same outfall.

Remove wording "and/or 14,000 gpm per saltwater cooling pumps". D 1-16 Saltwater Coolina pumps are no lonaer in service.

Remove wording "and/or 14,000 gpm per saltwater cooling pumps". D 1-17 Saltwater Cooling pumps are no longer in service.

Primary Plant Makeup Storage tanks are also known as Spent Fuel Pool F 4-19 Makeup Water Tanks.

5-22 Update Fiaure 5-1 due to location change for SONGS garden. R 5-23 Update Fiaure 5-2 due to location chanae for SONGS aarden. R 5-24 Update Fiaure 5-3 due to location change for SONGS garden. R Appendix Updated reference for 2016 Dose Parameters for San Onofre Units 2 and 3, R A dated November 30, 2016.

Page 2 of 2

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

S0123-0DCM Revision 11 08/2017 I :...;,

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 ................................................................................................. 1-6 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 1.4.2 Continuous Release Setpoint Determination .............................................. 1-14 1.5 Dose Calculation for Liquid Effluents ................................................................... 1-19 1.6 Representative Sampling .. .... .. .. .. .. .. .. .. .. .. .. .. .. .. ... .. .. .. .. .. .. ... .. .. .. . .. .. .. .. .. .. .. .. .. .. .. .. .. 1-22 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 Requirements .......................................................... 2-1 2.2 Dose - Noble Gas ................................................................................................. 2-5 2.2.1 Specification ................................................................................................ 2-5 2.2.1.1 Surveillance Requirement ......................................................................... 2-5 2.3 Dose - Radioiodines, Radioactive Materials in Particulate Form and Tritium ........ 2-6 2.3.1 Specification ................................................................................................ 2-6 2.3.1.1 Surveillance Requirement......................................................................... 2-6 S0123-0DCM Revision 9 11/2015 L_

ODCM TABLE OF CONTENTS (Continued) 2.4 Gaseous Radwaste Treatment -- DELETED ...... ......... .. .... .. ...... ...... ........ .............. 2-6 2.5 DELETED, moved to Section 3 2.6 Methods of Calculation for Gaseous Effluent Monitor Setpoints ........................... 2-8 2.6.1 Plant Vent Stack - 2/3RT-7808G, 2RT-7865-1, 3RT-7865-1 ..................... 2-8 2.6.2 Condenser Evacuation System - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 -- DELETED ........................................................................ 2-11 2.6.3 Containment Mini Purge - 2RT-7865-1, 3RT-7865-1 ............................... 2-11 2.6.4 Waste Gas Header - 3RT-7865-1, 2/3RT-7808 - DELETED .................... 2-12

2. 7 Gaseous Effluent Dose* Rate ...... .. ............... .. .......... ........ ... ......... ...... ................. 2-14 2.7.1 For Noble Gas ......................................................................................... 2-14 2.7.2 For All Radioiodines, Tritium, and All Radioactive Materials in Particulate Form with Half Lives Greater than Eight Days ....................... 2-15 2.8 Gaseous Effluent Dose Calculation ..................................................................... 2-16 2.8.1 Dose from Noble Gas in Gaseous Effluents ........................................... 2-16 2.8.1.1 For Historical Meteorology ........ .. ......... ............ .. .......... .. .. ..... .. ............. .. 2-16 2.8.1.2 For Meteorology Concurrent with Release ............................................... 2-17 2.8.2 Dose from Tritium, Radioiodines, and Radioactive Materials in Particulate Form with Half Lives Greater than Eight Days in Gaseous Effluents ........ 2-18 2.8.2.1 For Historical Meteorology ..................................................................... 2-18 2.8.2.2 For Meteorology Concurrent with Releases ............................................. 2-19 3.0 PROJECTED DOSES ........................................................................................ 3-1 thru 3-6 3.1 Liquid Dose Projection ......................................................................................... 3-1

. 3.2 Gaseous Dose Projection ................................................................................... 3-1 3.3 Total Dose ..............................................................................:............................ 3-2 3.3.1 Specification .............................................................................................. 3-2 3.3.1.1 Surveillance Requirement ......................................................................... 3-2 3.4 Total Dose Calculations ....................................................................................... 3-3 3.4.1 Total Dose to Most Likely Member of the Public ....................................... 3-3 3.4.1.1 Annual Total Organ Dose [Drnr (0)) .......................................................... 3-3 3.4.1.2 Annual Total Whole Body Dose Drnr (WB) ................................................ 3-4 3.4.1.3 Annual Total Thyroid Dose Drnr (T) ........................................................... 3-6 S0123-0DCM Revision 9 11/2015 ii

  • ODCM TABLE OF CONTENTS (Continued) 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 ................................... 4-9 4.2.1 Specification ............................................................................................. 4-9 4.2.1.1 Surveillance Requirement ......................................................................... 4-9 4.3 Functionality of Radioactive Waste Equipment .................................................. 4-18 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ....................................... 5-1 thru 5-26 5.1 Monitoring Program ............................................................................................. 5-1 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 lnterlaboratory 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 S0123-0DCM 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 .......... ........ ...... ..... ..... ...... ........ ..... 4-19 4-6 SONGS Radioactive Gaseous Waste Effluent Systems ...... ...... ........ .... ..... .... ...... ......... 4-20 4-7 Solid Waste Handling .................................................................................................... 4-21 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 S0123-0DCM Revision 9 11/2015 iv

ODCM LIST OF TABLES Table Title Page 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, Air ...................................................................................... 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 ............................ :................................. 2-20 2-5 Dose Parameters Pik ...................................................................................................... 2-21 2-6 Units 2 & 3 Controlling Location Factors ....... ............ .. .. .. .. .. .. .. .. .. ... .. .. .. .. .. .. ... .. .. .... .. .. .. .. . 2-22 2-7 South Yard Facility Controlling Location Factors (Moved to Appendix 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 Instrumentation ............................................. 4-10 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .. 4-14 5-1 Radiological Environmental Monitoring Program ............................................................. 5-3 5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples ................. 5-7 5-3 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 PIG-Radiological Environmental Monitoring Locations - DELETED ............ ... .. .. ............. 5-20 5-6 . Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map ........................................................... 5-21 6-1 Operational Modes -- DELETED ....................................................................................... 6-5 6-2 Frequency Notation ..... .. ................. ........... .. .... ............. ..... .. ....... ............. ...... ........ .... ....... 6-6 S0123-0DCM Revision 9 11/2015 V

ODCM LIST OF APPENDICES Title Appendix Ri TABLES ........................................................................................................ S0123-0DCM-A -

Supplemental Information for the Effluent Controls Program .............................. S0123-0DCM-B S0123-0DCM Revision 1 02-29-08 vi

l INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerates dose and concentration specifications, instrument requirements, as well as describes the methodology and parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents consistent with Reg. Guide 1.109 and NU REG 0133. In order to meet release limits, it additionally provides calculations for liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints. The environmental section contains the requirements for the radiological environmental monitoring program.

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

Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents current methodology.

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

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

APPLICABILITY: At all times ACTION:

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

SURVEILLANCE REQUIREMENTS

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

.2 The results ofthe radioactivity analyses shall be used in accordance with the methodology and parameters in Section 1.4 to assure that the concentrations at the point of release are maintained within the limits of Specification 1.1.1.

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

TABLE 1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (µCi/ml)8 A. Batch Waste p p Principal Gamma 5x10-7 Released,h Each Batch Each Batch Emitterst, 1-131 1x10-6 p M Dissolved and 1x10-5 One Batch/M Entrained Gases (Gamma emitters) p M H-3 1x10-5 Each Batch Compositeb, 9 Gross Alpha 1x10-7 p Q Sr-89, Sr-90 5X10-B Each Batch Compositeb,g Fe-55 1x1 o-6 NOTE BATCH RELEASE POINTS: Primary Plant Makeup Storage Tanks, also known as Spent Fuel Pool Makeup Water Tanks, and Miscellaneous Waste Condensate Monitor Tanks.

I B. Continuous D w Principal Gamma 5x10-7 Releasee,h Grab Sample Compositec,g Emitterst 1-131 1x10-6 M M Dissolved and 1x10-5 Grab Sample Entrained Gases (Gamma emitters)

D M H-3 1x10-5 Grab Sample Compositec,g Gross Alpha 1x10-7 8

D Q Sr-89, Sr-90 5x10-Grab Sample Compositec,g Fe-55 1x10-6 CONTINUOUS RELEASE POINT: Unit 2 Turbine Plant Sump S0123-0DCM Revision 11 08/2017 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)a C. Continuous 3xW w Principal Gamma 5x10-7 Releasee,h Grab Sample Compositeb,g Emitterst North 3xW M H-3 1x10-5 Industrial Grab Sample Compositeb, 9 Area Yard Gross Alpha 1x10*7 Drain Sump 3xW Q Sr-89, Sr-90 5X10" 8 Grab Sample Compositeb,g Fe-55 1x10*5 S0123-0DCM Revision 9 11/2015 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 xl0 6

  • Y*exp (-A~t) 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 Lit = 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 ori 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 Lit 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.#

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

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

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

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

S0123-0DCM Revision O 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 proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

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

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

f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, and those isotopes listed in Reg. Guide 1.21, shall also be identified and reported.
g. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
h. There shall be no liquid discharges across the beach; liquid may only be discharged through the approved outfall(s).
  • DELETED
    • DELETED
      • DELETED S0123-0DCM Revision 9 11/2015 1-5

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

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

APPLICABILITY: At all times ACTION:

a. With calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5. 7.1, prepare and submit to the Commission within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1.

SURVEILLANCE REQUIREMENT

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

S0123-0DCM Revision 10 08/2016 1-6

1.0 LIQUID EFFLUENTS (Continued) 1.3 LIQUID WASTE TREATMENT SPECIFICATION 1.3.1 The portable liquid radwaste 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 due to the liquid effluent from the site (see Figure 1-2) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.*

APPLICABILITY: At all times ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification Section 5. 7.1, 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 non-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 accordance with Section 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-minutes prior to processing liquids. The processed liquids shall then be evaluated for batch release.

  • Per unit S0123-0DCM Revision 10 08/2016 1-7

SITE BOUNDARY FOR LIQUID EFFLUENTS Figure 1-2 NIA, UNIT 2 & UNIT 3 SITE BOUNDARY for Liquid Effluents {waterfront on Property Line)

SAN ONOm mm stNElllTIII& ITATIOII r

.r"\

I S0123-0DCM Revision 9 11/2015 1-8

1.0 LIQUID EFFLUENTS (Continued) 1.4 LIQUID EFFLUENT MONITOR METHODS OF SETPOINT CALCULATION Liquid Effluent Line Monitor provides alarm and automatic termination 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 alarm/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 = permissible waste effluent flow rate at the radiation monitor location, in volume per unit time in the same units as for F F = dilution water flow in volume per unit time.

= 7,000 gpm per saltwater dilution pump*

  • The value used in the determination of F takes into account factors such as frictional losses, pump inefficiency, and tidal flow, and provides reasonable assurance that the radioactive release concentration is not underestimated. 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 term (F + R) in equation (1-1) may be replaced by F.

S0123-0DCM Revision 11 08/2017 1-9

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

MPCett = 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 i1h radionuclide as obtained by sample analysis MPC of the i1h radionuclide (10 CFR 20, App B, Table II, Column 2)

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

RW7a13 = 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 II, Column 2. The administrative values shall be assigned such that:

(RW7a13 + T2 + Y) < 1.0.

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

S0123-0DCM Revision 10 08/2016 1-10

1.0 LIQUID EFFLUENTS (Continued) 1.4.1 Batch Release Setpoint Determination The waste flow (R) and monitor setpoint (Cm) are set to meet the condition of equation (1-1) for the MPCeff limit. The method by which this is accomplished as follows:

STEP 1: The isotopic concentration for each batch tank (or sump) to be released is obtained from the sum of the measured concentrations in the tank (or sump) as determined by analysis.

where:

C = total concentration in each batch tank, µCi/ml LjC'vi = sum of the measured concentrations for each radionuclide, i, in the gamma spectrum, excluding Xe-133, µCi/ml Ca = gross alpha concentration determined in the previous monthly composite sample, µCi/ml Cs = Sr-89 and Sr-90 concentrations as determined in the previous quarterly composite sample, µCi/ml Ci = H-3 concentration as determined in the previous monthly composite sample, or as measured in the sample taken prior to release, µCi/ml CFe = Fe-55 concentration as determined in the previous quarterly composite sample, µCi/ml Cxe = Xe-133 concentration as determined by isotopic analysis,

µCi/ml S0123-0DCM Revision O 02-27-07 1-11

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

STEP 2: The effective MPC (MPCett) for each batch tank (or sump) is determined using:

1 MPCeff =

  • Li( MP Cy)C Cyi J+( Cs/CJ+( Ct/CJ+( Ca/CJ+( Cpe/C J MPCs MP Ct MPCr,. MPCFe (1-4) where:

MPCyi, MPCs, = the limiting concentrations of the appropriate radionuclide from MPC1, 10 CFR 20, Appendix B, Table II, Column 2 MPCFe, MPCa NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 µCi/ml total activity.

STEP 3: The setpoint, Cm (µCi/ml) for each batch release radioactivity monitor may now be specified based on the respective values of C, LjC'vi, F, MPCett, and R to provide compliance with the limits of 10 CFR 20, Appendix B, Table II, Column 2.

S0123-0DCM Revision 9 11/2015 1-12

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:

(1-6) where:

RW7a13 = Radwaste Effluent discharge administrative value F = dilution water flow in volume per unit time

= 7,000 gpm per saltwater dilution pump**

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

C = total concentration in each batch sample LjC'vi = total gamma isotopic concentration, excluding Xe-133, µCi/ml R - typical effluent release rate Values of R for each tank are as follows:

Primary Plant Makeup Tank= 160 gpm (per pump)

Condensate Monitor Tank= 100 gpm (per pump)

The maximum liquid radwaste release discharge flow rate will be administratively limited to less than 95 gpm MPCeff = from equation ( 1-4)

NOTE: If Cm s; LjC'vi, then no release is possible. To increase Cm, increase the administrative value RW 7813 , and/or increase dilution flow F (by running more dilution pumps in the applicable discharge structure), and/or decrease the effluent flow rate Rand recalculate Cm using the new RW 7813 , 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 S0123-0DCM Revision 11 08/2017 1-13

1.0 LIQUID EFFLUENTS (Continued) 1.4.2 Continuous Release Setpoint Determination 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 releases 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 (µCi/ml)

= total gamma activity associated with each radionuclide, i, in the weekly composite analysis for the release stream, excluding Xe-133, 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-89 and 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 Cxe = Xe-133 concentration as determined by isotopic analysis,

µCi/ml S0123-0DCM Revision 10 08/2016 1-14

1.0 LIQUID EFFLUENTS (Continued) 1.4.2 Continuous Release Setpoint Determination (Continued)

STEP 2: The effective MPC (MPCett) for each release stream (turbine plant sump or NIA yard drain sump) is determined using:

1 (1-4)

MPC,ff = L;(cy/c_)+(cs/c)+( ctfc)+( ca/c )+( CFe/c)

MPCyi MPCs MP Ct MP Ca MPCFe where:

MPCvi, MPCs, = the limiting concentrations of the appropriate MPC1, radionuclide from 10 CFR 20, Appendix 8, Table II, MPCFe, Column 2 MPCa STEP 3: The setpoint Cm (µCi/ml) for each continuous release radioactivity monitor may now be specified based on the respective values of C, rpvi, F, MPCett, and R to provide compliance with the limits of 10 CFR 20, Appendix 8, 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 Line Monitors (2RT-6753, 2RT-6759, 3RT-6753, 3RT-6759) -- DELETED S0123-0DCM Revision 10 08/2016 1-15

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

The value 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 LjC'vi = total gamma isotopic concentration, excluding Xe-133, µCi/ml, (STEP 1)

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

= 300 gpm C = total concentration, µCi/ml MPCett = value of MPCett from equation (1-4) for the sample analysis NOTE: If C2 :s; LjC'vi, then no release is possible. To increase C2, increase the administrative value T 2, 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.

S0123-0DCM Revision 11 08/2017 1-16

1.0 LIQUID 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. The same radiation monitor is used for either outfall.

The value for Cvos, the concentration limit at the detector, is determined 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

= total gamma isotopic concentration, µCi/ml (STEP 1)

R = effluent flow rate, gpm, typical flow rates:

= 4100 gpm C = total concentration, µCi/ml MPCett = value of MPCett from equation (1-4) for the sample analysis NOTE: If Cvos::. rpvi, 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 equation (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 terminate all continuous liquid effluent releases.

S0123-0DCM Revision 11 08/2017 1-17

1.0 LIQUID EFFLUENTS (Continued)

TABLE 1-3 Liquid Effluent Radiation Monitor Calibration Constants (al

(µCi/cc/cpm)

DELETED REMAINDER OF PAGE LEFT INTENTIONALLY BLANK S0123-0DCM Revision 9 11/2015 1-18

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

(1-16) where:

= Site-related adult ingestion dose commitment factor to the total body or an organ, r, for each identified principal gamma and beta emitter, i, from Table 1-4 in mrem/hr per µCi/ml.

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

DT = dose commitment to the total body or an organ, r, from the liquid effluent for the time period, b.ti, in mrem.

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

discharge structure exit flow

= length of the j1h time period over which Cii and Fi are averaged for all liquid releases, in hours.

S0123-0DCM Revision 0 02-27-07 1-19

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

Radionuclide Bone Liver Total Thyroid Kidney Lung GI-LU Body H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Cr-51 5.58E+O 3.34E+O 1.23E+O 7.40E+O 1.40E+3 Mn-54 7.06E+3 1.35E+3 2.10E+3 2.16E+4 Mn-56 1.78E+2 3.15E+1 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe-59 8.06E+4 1.90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 3.59E+3 Co-58 6.03E+2 1.35E+3 1.22E+4 Co-60 1.73E+3 3.82E+3 3.25E+4 Cu-64 2.14E+2 1.01E+2 5.40E+2 1.83E+4 Zn-65 1.61 E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 Br-84 9.39E-2 7.37E-7 Rb-88 1.79E+O 9.49E-1 2.47E-11 Sr-89 4.99E+3 1.43E+2 8.00E+2 Sr-90 1.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+1 3.71E+O 4.37E+2 Sr-92 3.48E+1 1.51E+O 6.90E+2 Y-90 6.06E+O 1.63E-1 6.42E+4 Y-91m 5.73E-2 2.22E-3 1.68E-1 Y-92 5.32E-1 1.56E-2 9.32E+3 Zr-95 1.59E+1 5.11E+O 3.46E+O 8.02E+O 1.62E+4 Zr-97 8.81 E-1 1.78E-1 8.13E-2 2.68E-1 5.51E+4 Nb-95 1.84E+O 1.03E+O 5.51 E-1 1.01E+O 6.22E+3 Nb-95m 1.84E+O 1.03E+O 5.51 E-1 1.01E+O 6.22E+3 Nb-97 1.55E-2 3.91E-3 1.43E-3 4.56E-3 1.44E+1 Mo-99 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ru-106 1.59E+3 2.01E+2 3.06E+3 1.03E+5 Ao-110m 1.42E+3 1.32E+3 7.82E+2 2.59E+3 5.37E+5 NOTE: where no value is given, no data are available.

TABLE 1-4 (Continued)

DOSE COMMITMENT FACTORS*, Air (mrem/hr per µCi/ml)

Radionuclide Bone Liver Total Thyroid Kidney Lung GI-LU Body Sn-113 2.26E+5 Sn-117m 2.26E+5 Sb-124 2.76E+2 5.22E+O 1.09E+2 6.70E-1 2.15E+2 7.84E+3 Sb-125 1.77E+2 1.97E+O 4.20E+1 1.79E-1 1.36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 1-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 1-132 1.06E+1 2.85E+1 9.96E+O 9.96E+2 4.54E+1 5.35E+O 1-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 1.16E+2 1-134 5.56E+O 1.51 E+1 5.40E+O 2.62E+2 2.40E+1 1.32E-2 1-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 Cs-134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 1.75E+3 2.85E+2 Cs-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 Cs-138 6.07E+O 1.20E+1 5.94E+O 8.81E+O 8.70E-1 5.12E-5 Ba-139 7.85E+O 5.59E-3 2.30E-1 5.23E-3 3.17E-3 1.39E+1 Ba-140

  • 1.64E+3 2.06E+O 1.08E+2 7.02E-1 1.18E+O 3.38E+3 La-140 1.57E+O 7.94E-1 2.10E-1 5.83E+4 Ce-141 3.43E+O 2.32E+O 2.63E-1 1.08E+O 8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce-144 1.79E+2 7.47E+1 9.59E+O 4.43E+1 6.04E+4 Nd-147 3.96E+O 4.58E+O 2.74E-1 2.68E+O 2.20E+4 W-187 9.16E+O 7.66E+O 2.68E+O 2.51E+3 No-239 3.53E-2 3.47E-3 1.91 E-3 1.08E-2 7.11E+2 NOTE: where no value is given, no data are available.

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 S0123-lll-5.23 and S0123-lll-5.2.23.

S0123-0DCM Revision 9 11/2015.

1-22

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

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

APPLICABILITY: At all times ACTION:

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

SURVEILLANCE REQUIREMENTS

.1 The dose rate due to rioble gases in gaseous effluents shall be determined to be within the above limits in accordance with Section 2.7 .

.2 The dose rate due to radioiodines, Tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with Section 2. 7 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2-1.

S0123-0DCM Revision 0 02-27-07 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)8 Continuous Principal Gamma

  • Tritium 1x10-6 wd 1-131 1x10-12 Continuousf Charcoal Sampler Sample 1-133 1x10-10 wd Principal Gamma Continuousf Particulate Emitters 9 1x10-11 Sampler Sample (1-131 and Others)

M Continuousf Composite Gross Alpha 1x10-11 Sampler Particulate Sample Q

Continuousf Composite Sr-89 and Sr-90 1x10-11 Sampler Particulate Sample Continuousf Noble Gas Noble Gases 1x10-6 Monitor Monitor Gross Beta and Gamma

  • Sampling frequencies for Noble gases and Tritium are:

CONTINUOUS PATHWAYS:

Containment Mini Purge - 8" : Monthly Grabe. i Plant Vent Stack  : Weekly Grabe South Yard Facility  : Particulate and Iodine sampling onlyh S0123-0DCM Revision 10 08/2016 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= 4.66Sb E

  • V
  • 2.22 x 10 6
  • Y
  • exp ( -AL~: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),

'A = radioactive decay constant for the particular radionuclide, and

.Llt = 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 Lit 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, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., "Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972). S0123-0DCM Revision 0 02-27-07 2-3

TABLE 2-1 (Continued)

TABLE NOTATION (Continued)

b. DELETED
c. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
d. Air samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
e. Representative Tritium grab samples shall be taken at least once per 7 days from the spent fuel pool area, whenever spent fuel 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 tritiated 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, 2.2.1, 2.3.1.
g. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
h. Radioactive airborne effluents only expected to be particulate and iodine.
i. Units 2(3)RT-7865-1 can no longer monitor containment purge. Cold and Dark Rad Waste Building HVAC NECP 801249775 Order 801429213 disabled the ability to sample the containment purge stack by failing close the purge stack sample valves. However, this section will not be deleted in case it is determined during Decommissioning that this effluent pathway will need to be used.

S0123-0DCM Revision 10 08/2016 2-4

2.0 GASEOUS EFFLUENTS (Continued) 2.2 DOSE - NOBLE GASES SPECIFICATION 2.2.1 The air dose due to Noble gases released in gaseous effluents, from each

  • decommissioning unit via the plant vent stack, from the site (see Figure 2-2) shall be limited to the following:
a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
b. During any calendar year: Less than or equal to 1O mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times ACTION:

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

SURVEILLANCE REQUIREMENT

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

S0123-0DCM Revision 9 11/2015 2-5

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

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

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of Tritium, radioiodines, and radioactive materials in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification Section 5.7.1, 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 shall be determined in accordance with Section 2.8 at least once per 31 days.

2.4 GASEOUS RADWASTE TREATMENT-- DELETED S0123-0DCM Revision 9 11/2015 2-6

SAN ONOFRE NUCLEAR GENERATING STATION SITE BOUNDARY FOR GASEOUS EFFLUENTS Figure 2-2 LEGEND

1. CONTAINMENT PURGE VENT STACK (EL 235 FT 9 IN)
2. CONTINUOUS EXHAUST VENT STACK (EL 235 FT 9 IN)
3. TURBINE BUILDING VENTILATION EXHAUST (GENERAL AREA - NO EXHAUST DUCTING
4. MAIN CONDENSER EVACUATION CAAIP SYSTEM EXHAUST (EL 72 FT 6 IN)
5. TURBINE GLAND SEAL SYSTEM EXHAUST (El 72 FT 6 IN)

\\

I I

I PACIFIC CC EA N

/

/

SITE BOUNDARY for G a s e o ~

S0123-0DCM Revision 9 11/2015 2-7

2.0 GASEOUS EFFLUENTS (Continued) 2.6 METHODS OF CALCULATION FOR GASEOUS EFFLUENT MONITOR SETPOINTS Administrative values are used to reduce each setpoint to account for the potential activity released simultaneously from the following release points:

PVS = Plant Vent Stack CP = Containment Purge (see NOTE on page 2-11)

SY= South Yard The sum of the administrative values is limited to 1.0 to ensure the total concentration from all release points on site to the environment will not result in a release exceeding the limits of Specification 2.1.1. The sum total of all these administrative values for the site shall be less than or equal to 1.0.

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

2.6.1 Plant Vent Stack* 2/3RT-7808G, 2RT-7865-1, 3RT-7865-1 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for Noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.

Total Body The concentration at the detector corresponding to a 500 mrem/yr total body dose rate at the exclusion area boundary is determined by:

(PVS) (2120 ~~m ) (500 mrem /yr)(10- 6 m 3 /cc)

C _ m ~c det - [ ( mrem /yr) ( Ci )]

(flowrate, cfm)(X/Q, sec/m 3) Li Ki µCi /m3 Ctot (2-1)

The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by:

(PVS) (2120 ~f/m ) (3000 mrem /yr)(10- 6 m 3 /cc)

Cdet = ---------=------[-(_______/_)__C_]

m sec (flowrate, cfm)(X/Q,sec/m 3) Li Li+1.1Mi,m;(i~,;t (ct!J (2-2)

S0123-0DCM Revision 10 08/2016 2-8

2.0 GASEOUS EFFLUENTS (Continued) 2.6.1 Plant Vent Stack - 2/3RT-7808G, 2RT-7865-1, 3RT-7865-1 (Continued) where:

= the instantaneous concentration at the detector, µCi/cc PVS = an administrative value used to account for potential activity from other gaseous release pathways, typically 0.38.

= total body dose conversion factor from Table 2-4 for the i1h gamma emitting Noble gas, mrem/yr per µCi/m 3

= skin Dose Conversion Factor from Table 2-4 for the i1h Noble gas, mrem/yr per µCi/m 3

= air Dose Conversion Factor from Table 2-4 for the i1h Noble gas, mrem/yr per µCi/m 3 1.1 = conversion factor to convert gamma air dose to skin dose

= concentration of the i1h Noble gas as determined by sample analysis, µCi/cc

= total concentration of Noble gases as determined by sample analysis, µCi/cc = LjCi flow rate= total plant vent stack flow rate, cfm,

= typically 164,000 cfm 2120 = conversion constant, cfm per m3/sec 500 mrem/yr = total body dose rate limit, as specified by Specification 2.1.1 a 3000 mrem/y = skin dose rate limit as specified by Specification 2.1.1 a X/Q = historical annual average dispersion factor for any landward sector, sec/m 3 from midpoint between Unit 2 and 3

= 4.8E-6 sec/m 3 S0123-0DCM Revision 9 11/2015 2-9

2.0 GASEOUS EFFLUENTS (Continued) 2.6.1.1 Maximum Permissible Alarm Setpoint for 2/3RT-7808G, 2RT-7865-1 and 3RT-7865-1 The smaller of the values of Cdet from equations (2-1) and (2-2) shall be used to determine the maximum permissible monitor alarm setpoint.

The maximum release rate (µCi/sec) for Plant Vent Stack Monitors is determined by converting the concentration at the detector, Cdet (µCi/cc) to an equivalent release rate in µCi/sec, as follows:

(Cdet, µCi/cc )(flow rate, cfmX28320)

Amax = (S)(60) where:

Amax = maximum permissible release rate, µCi/sec

= smaller of the values of Cdet determined in equations (2-1) and (2-2).

flow rate= plant vent stack flow rate (cfm) used in equations (2-1) and (2-2) 28320 = conversion from ft 3 to cc 60 = conversion from minutes to seconds s = correction factor to compensate for the split flow between Unit 2 and Unit 3 Plant Vent Stacks, typically 2 for split stack monitoring and 1 for combined stack monitoring The release rate setpoint shall not be set greater than the maximum release rate determined above, when the monitor is being used to meet the requirements of Specification 2.1.1.

S0123-0DCM Revision 9 11/2015 2-10

2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 Condenser Evacuation System - 2RT-7818, 2RT-7870-1, 3RT-7818 or 3RT-7870-1 ** DELETED 2.6.3 Containment Mini Purge - 2RT-7865-1, 3RT-7865-1 NOTE: Units 2(3)RT-7865-1 can no longer monitor containment purge. Cold and Dark Rad Waste Building HVAC NECP 801249775 Order 801429213 disabled the ability to sample the containment purge stack by failing close the purge stack sample valves.

However, this section will not be deleted in case it is determined during Decommissioning that this effluent pathway will need to be used.

For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for Noble gas monitors is based on the gaseous effluent flow rate and the meteorological djspersion factor.

The concentration at the detector corresponding to a total body dose rate of 500 mrem/yr at the exclusion boundary is determined by using:

Total Body (CP)(P2) (2120 ~jm ) (500 mrem /yr)(10- 6 m 3 /cc) m sec (2-7)

(CP)(P3) (2120 ;fm ) (500 mrem /yr)(10- 6 m 3 /cc) m 1sec

= ----------'--------:[,--(-:--------:/,..........,)-----=c,..........-::-]

Cdet3 (flow rate, cfm)(X/Q, sec/ m 3

) :Ei Ki m;;r;1 :t (ct!) (2-8)

The concentration at the detector corresponding to a 3000 mrem/yr skin dose rate at the exclusion area boundary is determined by using:

Skin (CP)(P2) (2120 it m 1sec m ) (3000 mrem /yr)(10- 6 m 3 /cc)

Cdet2 = -----------------------,-----=

(flow rate, cfm)(X/Q ,sec/m 3 ) [ri (1i + 1.1Mi, rr;;;r;t;t) (c~!)]

(2-9)

(CP)(P3) (2120 m

it1msec ) (3000 mrem /yr)(10- m /cc) 6 3 Cdet3 = -----------'----------------

(flow rate, cfm)(X/Q ,sec /m [ri (1i + 1.1Mi, ";(i:f;;-/) (c~!)]

3

)

(2-10)

S0123-0DCM Revision 10 08/2016 2-11

2.0 GASEOUS EFFLUENTS (Continued) 2.6.3 Containment Mini Purge - 2RT-7865-1, 3RT-7865-1 (Continued) where:

Cctet2 = instantaneous concentration of the Unit 2 detector, µCi/cc.

Cctet3 = instantaneous concentration of the Unit 3 detector, µCi/cc.

CP = administrative value used to account for potential activity from other gaseous release pathways, typically 0.38.

P2 and P3 are administrative values used to account for simultaneous purges of both SONGS 2 and SONGS 3. The fractions P2 and P3 will be assigned such that P2 + P3 ::;; 1.0.

Flow rate = 3,000 cfm Other parameters are as specified in 2.6.1 above. The smaller of the values of maximum permissible Cctet2 from equation (2-7) or (2-9) and Cctet3 from equations (2-8) or (2-10) is to be used in determining the maximum permissible monitor alarm setpoints.

2.6.3.1 Maximum Permissible Alarm Setting for 2(3)RT-7865-1 The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate (µCi/sec) is determined by converting the concentration at the detector, Cctet (µCi/cc),to an equivalent release rate in

µCi/sec.

Amax = (Cdet, µCi/cc) (flow rate, cc/sec) (2-6) where:

Amax = maximum permissible release rate, µCi/sec

= smaller value of Cdet, as obtained from equation (2-7, 2-9) for Unit 2 or (2-8, 2-10) for Unit 3.

flow rate= 1.416E6 cc/sec for mini-purge.

2.6.4 Waste Gas Header - 3RT-7865-1, 2/3RT-7808 -- DELETED S0123-0DCM Revision 9 11/2015 2-12

2.0 GASEOUS EFFLUENTS (Continued)

Table 2-3 Gaseous Effluent Radiation Monitor Calibration Constants(al

(µCi/cc/cpm)

DELETED REMAINDER OF PAGE INTENTIONALLY BLANK S0123-0DCM Revision 9 11/2015 2-13

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

2.7.1 For Noble Gas:

(2-13)

(2-14) where:

DTB = total body dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem/yr Ds = skin dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem/yr Ki = the total body dose factor due to gamma emissions from Table 2-4 for each identified Noble gas radionuclide, i, in mrem/yr per µCi/m 3 Li = skin dose factor due to the beta emissions from Table 2-4 for each identified Noble gas radionuclide, i, in mrem/yr per

µCi/m 3 M = air dose factor due to gamma emissions from Table 2-4 for each identified Noble gas radionuclide, i, in mrad/yr per µCi/m 3 (conversion constant of 1.1 mrem/mrad converts air dose to Qi =

skin dose.)

measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, in µCi/sec (X/Q) = Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area bounda2'.

= 4.8E-6 sec/m for Units 2 and 3

= 8.0E-5 sec/m 3 for South Yard Facility S0123-0DCM Revision 9 11/2015 2-14

2.0 GASEOUS EFFLUENTS (Continued) 2.7.2 For All Radioiodines, Tritium, and for All Radioactive Materials in Particulate Form with Half Lives Greater than Eight Days:

(2-15) where:

Do = organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, mrem/yr

= measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, µCi/sec

= 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 individual organ and the child age group.

= highest calculated annual average dispersion (X/Q) or deposition (D / Q) factor for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k.

= (X/Q), 4.BE-6 sec/m 3 for Units 2/3 for the inhalation pathway.

The location is the unrestricted area in the NW sector.

3

= (X/Q), 8.0E-5 sec/m for South Yard Facility for the inhalation pathway. The location is the unrestricted area in the E sector.

= (X/Q), 1.3E-5 sec/m 3 for the NIA (Unit 1) for the inhalation pathway. The location is the unrestricted area in the NW sector. (Historical value)

= (D /Q), 4.3E-8 m-2 for Units 2/3 for the fooq and ground plane pathways. The location is the unrestricted area in the E sector.

= (D /Q), 8.0E-7 m-2 for South Yard Facility for the food and ground plane pathways. The location is the unrestricted area in the E sector.

3

= (X/Q), 7.2E-8 sec/m for NIA (Unit 1) for the food and ground pathways. The location is the unrestricted area in the NW sector. (Historical value)

S0123-0DCM Revision 0 02-27-07 2-15

2.0 GASEOUS EFFLUENTS (Continued) 2.8 GASEOUS EFFLUENT DOSE CALCULATION 2.8.1 Dose from Noble Gas In Gaseous Effluents The gaseous releases considered in the following dose calculations are described in Section 2.6. The air dose in unrestricted areas due to noble gases released in gaseous effluents is calculated using the following expressions:

2.8.1.1 For Historical Meteorology:

(2-16)

(2-17) where:

Dv = total gamma air dose from gaseous effluents, mrad D13 = total beta air dose from gaseous effluents, mrad 3.17x10-s = inverse seconds per year M = air dose factor due to gamma emissions from Table 2-4 for 3

each identified Noble gas radionuclide, i, in mrad/yr per µCi/m Ni = air dose due to beta emissions from Table 2-4 for each identified Noble gas radionuclide, i, in mrad/yr per µCi/m 3 (X/Q) = Maximum annual average atmospheric dispersion factor for any landward sector or distance at or beyond the unrestricted area boundary.

= 4.8E-6 sec/m 3 for Units 2 and 3

= 8.0E-5 sec/m 3 for South Yard Facility Qi = amount of Noble gas radionuclide, i, released in gaseous effluents, µCi.

S0123-0DCM Revision 9 11/2015 2-16

1 2.0 GASEOUS EFFLUENTS (Continued) 2.8.1.2 For Meteorology Concurrent with Release:

NOTE: Consistent with the methodology provided in Reg. Guide 1.109 and the following equations, quality affecting computer software is used to perform the actual calculations.

Dye = 1.14

  • 10- 4 riMi[LiMj(X/Q)jeQ.i1 )]

(2-18)

(2-19) where:

Dve = total gamma air dose from gaseous effluents in sector 8, mrad Diie = total beta air dose from gaseous effluents in sector 8, mrad 1.14x10-4 = inverse hours/year

= air dose factor due to gamma emissions from Table 2-4 for each identified Noble gas radionuclide, i, in mrad/yr per µCi/m 3

= air dose factor due to beta emissions from Table 2-4 for each identified Noble gas radionuclide, i, in mrad/yr per µCi/m 3

= length of the r time period over which (X/Q)je and Qij are averaged for gaseous releases in hours (X/Q)je = atmospheric dispersion factor for time period b.ti at exclusion boundary location in landward sector 8, which is determined by concurrent meteorology, sec/m 3

= average release rate of radionuclide, i, in gaseous effluents during time period, b.ti, µCi/sec S0123-0DCM Revision 9 11/2015 2-17

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2 Dose from Tritium, Radioiodines, and Radioactive Materials in Particulate Form with Half Lives Greater than Eight Days in Gaseous Effluents The dose to an individual from Tritium, radioiodines and radioactive materials in particulate form with half-lives greater than eight days in gaseous effluents .

released to unrestricted areas is calculated using the following expressions:

2.8.2.1 For Historical Meteorology:

(2-20) where:

D0 = total projected dose from gaseous effluents to an individual, mrem 3.17x1 o-8 = year/second Qi = amount of each radionuclide, i, (Tritium, radioiodine, radioactive material in particulate form with half-lives greater than eight days), released in gaseous effluents, µCi rkRikWk = sum of all pathways, k, for radionuclide, i, of the Ri W product, in mrem/yr per µCi/sec. The rkRikwk value for each radionuclide, 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 rkRikWk for all locations and is based on the most restrictive age groups.

Rik = 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 m2-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, PARTS. (See the annual update of revised Ri parameters based on changes in the Land Use Census provided by Radiation Protection.)

= 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) for each controlling location is given in Appendix A.

= CJ2l!l) for the food and ground plane pathways in m-2 . The (D/Q) for each controlling location is given in Appendix A.

S0123-0DCM Revision 9 11/2015 2-18

2.0 GASEOUS EFFLUENTS (Continued) 2.8.2.2 For Meteorology Concurrent with Releases:

NOTE: Consistent with the methodology provided in Reg. Guide 1.109 and the following equations, quality affecting computer software is used to perform the actual calculations.

D, ~ l.14xlo_,ttt[~t,)(R.,)(w,..l(Ct, J] 12-211 where:

Da = total annual dose from gaseous effluents to an individual in sector 8, mrem.

= length of the j1h period over which Wike and Q *..lJ are averaged for gaseous released, hours

. = average release rate of radionuclide, i, in gaseous effluents Qij during time period ~ti, µCi/sec Rike = dose factor for each identified radionuclide i, for pathway k for sector 8 (for the inhalation pathway in mrem/yr per µCi/m 3 and for the food and ground plane pathways in m 2 mrem/yr per

µCi/sec) at the controlling location. A listing of Rik for the controlling locations in each landward sector for each group is given in Appendix A. The 8 is determined by the concurrent meteorology.

= dispersion (X / Q) or deposition (D / Q) factor for the time period

~ti for each pathway k for calculating the dose to an individual at the controlling location in sector 8 using concurrent meteorological conditions.

= (XI Q) for the inhalation pathway, sec/m 3

= (D/Q) for the food and ground plane pathways, m-2 S0123-0DCM Revision 0 02-27-07 2-19

TABLE 2-4 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS**

Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor Ki Factor Li Factor Mi Factor Ni Radionuclide (mrem/yr (mrem/yr (mrad/yr (mrad/yr per µCi/m 3 ) per µCi/m 3 ) per µCi/m 3 ) per µCi/m 3 )

Kr-85m 1.17E+3 1.46E+3 1.23E+3 1.97E+3 Kr-85 1.61 E+1 . 1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.73E+3 6.17E+3 1.03E+4 Kr-88 1.47E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131m 9.15E+1 4.76E+2 1.56E+2 1.11 E+3 Xe-133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 Xe-135m 3.12E+3 7.11E+2 3.36E+3 7.39E+2 Xe-135 1.81E+3 1.86E+3 1.92E+3 2.46E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3 4.75E+3 Ar-41 8.84E+3 2.69E+3 9.30E+3 3.28E+3

TABLE 2-5 DOSE PARAMETER Pik*

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 I -131 1.6E+7 Cr-51 1.7E+4 1-132 1.9E+5 Mn-54 1.6E+6 1-133 3.8E+6 Co-57 5.1 E+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 Sr-89 2.2E+6 Cs-136 1.7E+5 Sr-90 1.0E+8 Cs-137 9.1E+5 Zr-95 2.2E+6 Ba-140 1.7E+6 Nb-95 6.1E+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-129m 1.8E+6

  • Source: USNRC NUREG-0133, Section 5.2.1.1 S0123-0DCM Revision OJ 02-27-07 2-21

TABLE 2-6 UNITS 2&3 CONTROLLING LOCATION FACTORS 1 LkRikWk Radionuclide mrem/yr per µCi/sec Use:

H-3 1.29E-3 Q:SORB Resdnt/Cmpgrnd Cr-51 3.74E-2 Q:SORB Resdnt/Cmpgrnd Mn-54 8.39E+O Q:SORB Resdnt/Cmpgrnd Co-57 1.73E+O Q:SORB Resdnt/Cmpgrnd Co-58 2.82E+O Q:SORB Resdnt/Cmpgrnd Co-60 1.16E+2 Q:SORB Resdnt/Cmpgrnd Sr-89 1.75E+1 Q: SC Res with Garden #2 Sr-90 6.88E+2 Q: SC Res with Garden #2 Zr-95 3.03E+O Q:SORB Resdnt/Cmpgrnd Nb-95 9.03E+O E: Deer Consumer/Hunter Ru-103 1.43E+1 E: Deer Consumer/Hunter Te-129m 6.49E+O E: Deer Consumer/Hunter Cs-134 3.41 E+1 Q:SORB Resdnt/Cmpgrnd Cs-136 7.62E-1 Q:SORB Resdnt/Cmpgrnd Cs-137 5.01E+1 Q:SORB Resdnt/Cmpgrnd Ba-140 1.45E+O Q: San Onofre Ill Housing Ce-141 4.67E-1 Q:San Onofre Ill Housing Ce-144 9.20E+O Q: San Onofre Ill Housing I -131 2.58E+1 Q: SC Res with Garden #2 1-132 1.35E-1 Q: San Onofre Ill Housing 1-133 2.63E+O Q: San Onofre Ill Housing 1-134 3.67E-2 Q: San Onofre 111 Housing 1-135 5.53E-1 Q: San Onofre Ill Housing UN-ID 4.60E+O Q:SORB Resdnt/Cmpqrnd These values to be used in manual calculations are the maximum LkRikWk for all locations based on the most restrictive age group.

S0123-0DCM Revision 9 11/2015 2-22

TABLE 2-7 SOUTH YARD FACILITY CONTROLLING LOCATION FACTORS 1 (Moved to Appendix B)

REMAINDER OF PAGE LEFT BLANK S0123-0DCM Revision 9 11/2015 2-23

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

REMAINDER OF PAGE LEFT BLANK S0123-0DCM Revision 9 11/2015 2-24

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 2.4.1 is as follows:

.1 Determine the monthly gamma, beta and organ dose resulting from releases during the previous 12 months .

.2 Projected dose = Previous 12 months' dose divided by 12 for the gamma, beta and organ doses.

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

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

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

SURVEILLANCE 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.

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

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

The Annual Total Dose is determined monthly for maximum organ (gas and liquid), whole body (gas and liquid), and thyroid (gas and liquid) to 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 [DrnT (O)]

(3-1) where:

  • NOTE: Dl-3 (OG) = 0 for bone (3-2) 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)

S0123-0DCM Revision 9 11/2015 3-3

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total Dose to Most Likely Member of the Public (Continued) 3.4.1.1 Annual Total Organ Dose [DrOT (O)] (Continued) n = number of isotopes in the specified organ category Ci = total particulate gas curies released for the month rkRikwk = SONGS controlling location factors (Tables 2-6, 2-7*, or 2-8*).

Dj1(0L) = liquid organ dose for the specified organ in mrem for the month. [Equation ( 1-16 )]

Dl-3 (OG)* = gas organ dose from Tritium in mrem for the month.

[Equation (2-15)]

  • Found in Appendix B 3.4.1.2 Annual Total Whole Body Dose [DrOT (WB)]

r~

,2 2/3 DroT(WB)= LLLLJ;,(WBL)+

i=I J=I o;- (0G)+0.9D/r)] +D(Ul)+D(DIRECT) 3 (3-3) where:

= NIA, Unit 2 and Unit 3

= months 1 - 12, to be summed over the most recent 12 months Di1(WBL) = liquid whole body organ dose in mrem for the whole month.

[Equation (1-16)]

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

[Equation (2-15)]

Di1(V) = gamma air dose in mrad for the month.

0.9 converts mrad to mrem.

[Equation (2-16)]

D(U1) = 0.494 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 S0123-0DCM Revision 9 11/2015 3-4

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total Dose to Most Likely Member of the Public (Continued) 3.4.1.2 Annual Total Whole Body Dose [DrnT (WB)] (Continued) n 4

LD(bkgd);

D(DIRECT)*= L max[D(beach)i]--p=_i_ _ _ 0.0342 n

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

  • Direct Radiation The direct radiation levels are evaluated 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 background 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.

S0123-0DCM Revision 9 11/2015 3-5 l

3.0 PROJECTED DOSES (Continued) 3.4 TOTAL DOSE CALCULATIONS (Continued) 3.4.1 Total Dose to Most Likely Member of the Public (Continued) 3.4.1.3 Annual Total Thyroid Dose [DrnT (T)]

12 2/3 DrnT(T) = I I l=l j=l

[Djz (OG) + Djz (OL)]

(3-5) where:

= NIA, Unit 2 and Unit 3

= months 1 - 12 (to be summed over the most recent 12 months)

Dj1(OG) = thyroid organ dose from gaseous iodine for the month in mrem. [equation (2-20)]

Dj 1 (OL) = liquid thyroid organ dose for the month in mrem.

[Equation (1-16)]

S0123-0DCM Revision 9 11/2015 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 monitoring instrumentation channels FUNCTIONAL and either the appropriate ACTION items iri 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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.

S0123-0DCM Revision 9 11/2015 4-1

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

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
a. Liquid Radwaste Effluent Line** - 2/3RT-7813*

' ** * * * .. * , -, ' ' .... * ~~ * ~ - ' * - . ** ', ** -* * * *, > -

  • 1 > '

28

b. Steam Generator Slowdown Processing System (Neutralization Sump)
.._ ________ full Flow Condensate_ Polisher Effluent Une - 2(3)RT-781} -- ___DELETED________ .. _____________ ** ___________ ......... - _______ .* .... _____ _.

_c. _____ Turbine Plant __ Sump_Effluent Line_-2RT-7~21*_______ - . . . . - 1 30. -- -- -*

1 d. Steam Generator (E088) Slowdown Effluent Line - 2(3)RT-6759 --:- DELETED ...

! e. Steam Generator (E089) Slowdown Effluent

... __Line - 4(3)RT~6753 _.: ___DELETED_____ . __ : .... f-.

f. NIA Yard Drain Sump - 2/3RT-2101* 1 44
2. PROCESS FLOW RATE MEASUREMENT DEVICES a.. _ Liquid_ Radwaste Effluent_Line**_ -_FE7643 ____ ... _______ .. _________ . _ _________________ . __ 1 31
  • b. ~>team Generator Slowdown Processing System (Neutralization Sump),*

FlJtl. Flow: 9cmc:l~q~~t~p.9li_sbE?rJ:Jfl_u_~DJ L_i_nEi_ --. _D!;~~TJ:D_ _ _ *

c. . Turbine Plant Sump. Effluent Line -2FQl5887 .. .. . .. . . .. . . . 1 ___ ---~j___________

i d. Steam Generator (E088) Slowdow~ Bypas~ :Effluent line -- DELETED * * * *

! e._. ~t~am Generajor_(E089)Blowdo_wn_ Bypass Effluent_Line_ ,.,.- DELETED . -----*-*-*--*. *.....

f. NIA Yard Drain Sump Effluent Line 2/3FQl-6095 1 31 S0123-0DCM Revision 10 08/2016 4-2

TABLE 4-1 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT* FUNCTIONAL ACTION

3. __ COMMAND DATA ACQUISITION SYSTEM (CDAS) (Effluent Monitor AlarmsL_ _____________ ----* 1-~---- **-*- __ 32 ______ _

UNIT 2 PLANT COMPUTER SYSTEM (CONTROL ROOM ALA.RM ANNUNCIATION)-

4. _*'..*DE_LETED ---- ,_*_________ -- *...... _ . ------ -~--~- _-* _. -**-* .......... __ -**. *-* -* .... _ V --* *.**.** *- ------ - - * *- -.'.. --*** ---------* ____ . , : ___ - - * * * * - * -*-** --------- . . . . . .
5. CONTINUOUS COMPOSITE SAMPLERS
a. Turbine Plant Sumps Effluent Line- 2APC-5887 1 33
b. Slowdown Processing System Neutralization Surr1p - 2(3)APC 377 -- DELETED.
c. Steam Generator (E088) Slowdown Bypass,
  • to _

~team qenerator (E08'8) Slowdown - 2(3) .APC 4077 -- DELETED

,, 0 "

. ** d. Steam Generator (E089) Slowdown to Bypass, .

l--~---------~l~atTI_ G~rier~Jor .(~O§~L!?Joyydo'{ll.!1.,:_g(~)bPC 497§ __ -- _i;>ELE"[Ep -------*---- ____  : _______ *-------* _____;______ . ___

  • _____ ._______ ..... ~

S0123-0DCM Revision 10 08/2016 4-3

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- With 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- 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of collection time for gross radioactivity* (beta or gamma) at a limit of detection of at least 10-7 microcuries/ml.

S0123-0DCM Revision 9 11/2015 4-4

TABLE 4-1 (Continued)

TABLE NOTATION (Continued)

ACTION 31 - With 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during actual releases. In addition, a new flow estimate shall be made within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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. Perform 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, not to exceed 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of collection time for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 microcurie/ml}.

S0123-0DCM Revision 10 08/2016 4-5

_______J

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

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT** CHECK CHECK CALIBRATION TEST

1. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE p(6)
a. Liquid Radwaste

~

Effluents Line

- 2/3RT-7813

. ' . . .'\ '

D Steam Generator Slowdown Processing System (Neutralization Sump), .Full Flow Condensate Polisher Effluent Line -2(3)RT-7817 DELETED

_,,,~---* -- *------------------ -- -*-------- -------** ---**- ----~~-~-* -*------ -- **-* ----~--- - -- -***- -----**--------*

c. Turbine Plant Sump Effluent Line - 2RT-7821
  • ' *** ~ .., * - --,,.-~ **- N ... - - . , * - * * * * * * * ** ----- ******.****

d.'* , Steam Generator (E088) Blowdow~:Bypass Effluentline - 2(3)RT.;6759 -- DELETED

e. Steam Generator (E089) Slowdown Bypass
  • .. _Effluent Line -_2(3)RT-6753 -'" __ DELETED ____ ... ***- ___ ***---* ... _____________ __
f. NIA Yard Drain Sump Effluent Line - 2/3RT-2101 D
2. PROCESS FLOW RATE MEASUREMENT DEVICES
a. _,,_Liquid Radwaste_.Efflu_entUne _ ----.----* _ .. ------- .. -------------- D~ NM R Q Steam Generator Slowdown Processing System (Neutralization

-" _____ Su.rnR1,.f_u!Lfl9~__Q_C?f"19~1J§.ate_ f>qlislJ.~I-~fft~eDJ.~111~ --pE:_~EJI;P.,,.. ......

,.c.:.. -- T~r.bi~~ _1:la,n_t Su_ml?_ ~!fl!J_~r:,t Li!l_e _______ . . _. _. _ ___ ----* _____ _ N/A R Q

d. Steam <;3enerator (E088}Blowdown_ Bypass Efflue~t Line DELETED

[,e. - _Stean:i J;enerator(E089) *s1owdown~B'ypass Effluerit:lioe pEL,l;:J"ED _

f. NIA Yard Drain Sump Effluent Line 0(3)

N/A R Q S0123-0DCM Revision 10 08/2016 4-6

TABLE 4-2 (Continued)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT** CHECK CHECK CALIBRATION TEST

3. COMMAND DATA ACQUISITION SYSTEM (CDAS) (Effluent Monitor D N/A N/A(4l Q Alarm~)*--*--***-**-********* _______ ......... _ ............ ***":*-* _____ .,................ ----*-**** ..................

UNIT 2 PLANT COMPUTER SYSTEM (CONTROL ROOM ALARM

_b_NN!J~G!6I1Q_t:'J)_Pg!:-l;I1;_Q__________ :_ .. __ ........... _______ .... ______ *- .. .

5. CONTINUOUS COMPOSITE SAMPLERS
a. Turbine Plant Sump 2APC-5887 .. _,,. . ~ .- ' '

NIA R '

b. Slowdown Processing System- Neutralization Sump -

2(3) AP~ 3772 DELETED .

i c. Stear-A Generator (E088) Blowdbwn to Bypass, Steam Generator (E088) Slowdown - 2(3) APC 4077 DELETED i ct.' ** Steam Generator (E089) Slowdown to Bypass, - .

!___ *--~-- -~!~~_rn __Ge_n~[§!to_r _(~Q~-~H3_19.~gg~[1 :- f_{~)_ t.F~~ -4_0?6 pE_L~1EP________ . _ ___________ .. __ ... _ _______ __ __ _ _ ___ ___ ___ _ ___ ___ __ __ _ _

S0123-0DCM Revision 10 08/2016 4-7

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 if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/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 CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONS, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

(4) The Command Data Acquisition System (CDAS) software and hardware do not require CHANNEL CALIBRATION. The CDAS software is quality affecting and controlled by the site Software Modification Request process under procedures S0123-V-4.71, Software Development and Maintenance. The CDAS hardware is installed plant

  • equipment and controlled by the site design change process using procedure S0123-XXIV-10.1, Engineering Design Changes Process - NECPs.

(5) CHANNEL CHECK shall consist of verifying compositor switch positions and installed counter setting, and comparing integrator readings to sample volume collected.

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

S0123-0DCM Revision 10 08/2016 4-8

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

APPLICABILITY: At all times ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel non-FUNCTIONAL.
b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONAL, take the ACTION shown in Table 4-3. 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 gaseous effluent monitoring instrumentation channels FUNCTIONAL and either the appropriate ACTION items in Table 4-3 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-4, perform an evaluation based on the significance of the event in accordance with the site Corrective Action Program.

SURVEILLANCE REQUIREMENT

.1 Each radioactive gaseous 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 4-4.

S0123-0DCM Revision 10 08/2016 4-9

TABLE 4-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** FUNCTIONAL***

r-:--:-':t,*' , --~-- ,.,*-'" ' ' ,* ,'*,' . '  :* ,, ,, ' ,,, ', .

11:  :

"'-'---, WASTE ,.*

GAS HOLD.UP*

SYSTEM

DELEi'ED, , . ' * , . . * , .!, *

!:a. Noble o:as Activity Monitor - Proviqir19 Alarm and Automatic f: l'~rmination ofHelease - 2/3RT-7808, .or 3RJ-786§:.J DELETED I b. Process *Flow 'F~.ate* Monitoring Device - 2/3FIT7202 DELETED

  • r-*--*-* . ... . -. . .. l

.I L_i,_:.CONQl;:NSERJ=VAGUATIONSYSJEM:D~LETED  ; . :*);, ,<' .;: I L~t Noble Gas Activity Mdnitor .:2(3)RT~7818, ci'r 2(3)RT~7870"'1 DEt.ETEfi'-> *l l

(b. Iodine Sampler- DELETED . . .

f*-~C; l:' .-

ParticuJate Sarf)pler QELETE:D.

  • -':f":

' s ; ** -~ * , '

i 1,d. Associated P~LSample Flow _Measuring Deyice DELETEO . . . . . , _ . . /

tA.~ Pg>c~ss~*Fl6wJ3ete Mo.nifori~gj@vice DEl.s_TEO:: ,: .' __i -~-- . --' -~--~u~:l~ ~,::..._: '.'_ j;'* ---* .~ *-*- "' *---* ,.**.*1

3. PLANT VENT STACK
a. Noble Gas Activity Monitor - 2/3RT-7808G, or 2RT-7865-1 and 3RT-7865-1
  • 37
b. Iodine Sampler
  • 40
c. Particulate Sampler
  • 40
d. Associated P&I Sample Flow Measuring Device
  • 36b
e. Process Flow Rate Monitoring Device - 2/3RT-7808G, or 2RT-7865-1 and 3RT-7865-1 1
  • 36a
4. CONTAINMENT PURGE SYSTEMl~J
a. Noble Gas Activity Monitor - Providing Alarm

- 2(3)RT-7865-1 1

  • 38
b. Iodine Sampler 1
  • 40
c. Particulate Sampler 1
  • 40
d. Associated P&I Sample Flow Measuring Device 1
  • 36b
e. Process Flow Rate Monitoring Device 1
  • 36a 4-10

TABLE 4-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT*** FUNCTIONAL*** APPLICABILITY ACTION

5. COMMAND DATA ACQUISITION SYSTEM (CDAS) (Effluent Monitor 1
  • 42 Alarm)
6. SOUTH YARD FACILITY (SYF) WORK AREA (SYFRU 7904)
a. Iodine Sampler 1
  • 40
b. Particulate Sampler 1
  • 40
c. Associated P&I Sample Flow Measuring Device 1
  • 41b
d. Process Flow Rate Monitoring Device 1
  • 41a r.****,. *. '.-., **.: '.~,' *", ,*',** -~ *, *:'-. ".~* C* .. ~ "*' * : ~ * ,*c,,,'"*,,,,"  :"~_**;, ~ ..* ,/:, :\,.' *y*~*: * ~.'" \','., ~:

!i?. ':;SOt[fHYARp FACILIJY (§YFfDECONTAMINATIPN.UNIT, . , .J l_~'.;;$YFRU:q905' *DELETED *} . ,, ,( '*, : * '.:::, * * .:, . .;* . * . 'Ij If a. *lodfne ~~mpler QELETEQ.:,. . . I

!' b. .*.particulate S~mpler DELl;TEQ * . . .

t;c. . AssociatE:ld )?~I Sample. Fl9w["1eas1:1ring;bevice 'DELETED£ , * -_

t,* ~t~* ~<.PS9_~~~~-flo,w~.!3~!8-.M~~nitt>JLr:)g .q,~~l9~_J?;LEI~!?_,, **- .., *-~----~ ... .~~ ....... -*-**...,"". .-.. . . .'-,

S0123-0DCM Revision 10 08/2016 4-11

TABLE 4-3 (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 not render the monitor non-FUNCTIONAL.

(1) DELETED (2) Due to unequal mixing in the Plant Vent Stack, both 2RT-7865-1 and 3RT-7865-1 are required to be FUNCTIONAL when 2/3RT-7808G is non-FUNCTIONAL.

(3) Units 2(3)RT-7865-1 can no longer monitor containment purge. Cold and Dark Rad Waste Building HVAC NECP 801249775 Order 801429213 disabled the ability to sample the containment purge stack by failing close the purge stack sample valves. However, this section will not be deleted in case it is determined during Decommissioning that this effluent pathway will need to be used.

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 continue provided:

a. The process flow rate is estimated at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during actual releases. In addition, a new flow estimate shall be made within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a change that affects process flow has been completed.

System design characteristics may be used to estimate process flow.

b. The particulate and Iodine (P&I) sample flow rate is estimated or verified at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during actual releases.

ACTION 37- 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 taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 38- With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, immediately suspend PURGING of radioactive effluents via this pathway.

ACTION 40- With 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 Table 2-1.

S0123-0DCM Revision 10 08/2016 4-12

__ _ J

TABLE 4-3 (Continued)

TABLE NOTATION ACTION 41 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided:

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

System design characteristics may be used to estimate flow.

b. The particulate and iodine (P&I) sample flow rate is estimated at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when working with radioactive materials in the South Yard Facility Building.

ACTION 42- 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

S0123-0DCM Revision 9 11/2015 4-13

i I

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

CHANNEL CHANNEL SOURCE CHANNELS FUNCTIONAL CHECK CALIBRATION TEST INSTRUMENT*** CHECK  ;* --,-, ,.. ~-,~:c**: . . . .----

..- .~- ..~*--..~--~-=-~--,'-: APPLICABILITY

. -.. . . .-,~ . --*:*. *:* j r1..*.\~ASTE GASHOLDP~ ;~~~-~,:~~~~~E~--- *

  • l . ,*, . *- ' **. *. J . .

1* . - ':a. Noble.G.as Activity Mqnitor,- ... ~- , . !

! Providing Alarm and Automatic . i 1 Terminatio~ .pf.~efea~~.,. * .. ',.' . . l'

1 b,. Process Flow Rate. Mpnitoring . -:..,,

1 _ Device. DELETED . . .

1

. i, 2. CONDENSE;R EVACUATION SYSTEM .

f * *:*DELETED i .

I_' . a. ..Noble Gas Activity Monitor -

1. 1.¢:dine .'s~niple(,.DEL~JED .

i .C ~~rticulate saii,pler 'DELETED

! .:*'d:  : *.'Ai:isoci;ied s'affiple* F16~( . .. ' ~'

l* ryleasuring Device Dl;!-ETED.

r'J e,,, 6~v~~:1~~)~~~~7~~iit~~ri~h~1t ' .*.' ' ' . **,,' -- - .**.*...... <*, ' .'. :.' ' '* '-.,. ' " ' > * ' *... J S0123-0DCM Revision 9 11/2015 4-14

TABLE 4-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT*** CHECK CHECK CALIBRATION TEST APPLICABILITY

3. PLANT VENT STACK
a. Noble Gas Activity Monitor -

2/3RT-7808G, 2RT-7865-1, 3RT-7865-1 . D M<7> R(3l a<2> *

b. Iodine Sampler w NA NA NA
  • 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 *
4. CONTAINMENT PURGE SYSTEM****
a. Noble Gas Activity Monitor -

Providing Alarm - 2(3)RT-7865-1 D p R(3l Q *

b. Iodine Sampler w NA NA NA
  • C. Particulate Sampler w NA NA NA *
d. Process Flow Rate Monitoring Device D NA R Q *
e. Associated Sample Flow Measuring Device D NA R Q
  • S0123-0DCM Revision 10 08/2016 4-15

TABLE 4-4 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT*** CHECK CHECK CALIBRATION TEST APPLICABILITY

5. SOUTH YARD FACILITY (SYF) WORK AREA (SYFRU 7904)
a. Iodine Sampler w NA NA NA *
b. Particulate Sampler w NA NA NA
  • C. Process Flow Rate Monitoring Device 0(5)

NA R Q *

d. Associated Sample Flow Measuring Device 0(5)

NA R Q *

6. SOUTH YARD FACILITY (SYF)

' DECONTAMINATION UNIT {SYF 7905)

  • .DELETED
a. lodir,e Sampier DELETED
b. Particulate Sampler DELETED

, .C. Process Flow Rate Monitoring Device DELETED d, Associated Sample .Flow Measuring Q~yjc~.. QJ;LE:Jl::p_: ___ ___ ___ _ _ ____ ..

S0123-0DCM Revision 10 08/2016 4-16

TABLE 4-4 (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 not render the monitor non-FUNCTIONAL.
        • Units 2(3)RT-7865-1 can no longer monitor containment purge. Cold and Dark Rad Waste Building HVAC NECP 801249775 Order 801429213 disabled the ability to sample the containment purge stack by failing close the purge stack sample valves. However, this section will not be deleted in case it is determined during Decommissioning that this effluent pathway will need to be used.

(1) DELETED (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room/Command Center alarm annunciation occurs if any of the following conditions exist:

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

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

If the instrument controls are not set in the operate mode, procedures shall call for declaring the channel non-FUNCTIONAL.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONs, sources that have been related to the initial calibration shall be used.

(4) DELETED (5) Daily checks only required during times of working with radioactive materials in the South Yard Facility Building.

(6) DELETED (7) MGPI monitors have automatic and continuous source check to meet this requirement.

S0123-0DCM Revision 10 08/2016 4-17

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.

S0123-0DCM Revision 9 11/2015 4-18

SONGS RADIOACTIVE LIQUID WASTE EFFLUENT SYSTEMS Figure 4-5 II ABS, ccw, STA, BPS, L - .. *-* .. ~-

FFCPD Turbine Building Sump 2RT-7821 (Continuous)

Miscellaneous Waste Condensate Monitor '

Tank(s) [also referred 2/3RT-7813 ~------i*1 to as Spent Fuel Pool Makeup Water Tank(s)] .

L_~~~B=atch)~-~

Dewatering /

Extraction i

(

NIA VDS 2/3RT-2101 (Continuous)

KEV PACIFIC OCEAN

~~~diationMonitor ...

~ ..

Figure 4-5 SONGS Radioactive Liquid Waste Systems S0123-0DCM Revision 11 08/2017 4-19

SONGS RADIOACTIVE GASEOUS WASTE EFFLUENT SYSTEMS Figure 4-6

"'"'"'"'"'"'"'"'"'"'"'"'"'"' ATM OS PH ERE "'-~-"'"'"'"'"'"'"'"'"'"'"'"'

,, r-----l I Radiation f i Radiation f

_J I Sample f

  • Monitor [ I Monitor f
  • Skid r 2RT7865 I I 3RT7865 i , SYF7904 f L_______.______ rt* l_,_,_________ f l....-*-*-,--,*---,--.J

..................................__, .........t Radiation Monitor I 2/3RT7.808 ,

' ['~--------L--J I

I Plant Vent Stack Common Plenum 1

-r_,

I Containment [

Purge I

  • I

~ r _[,

I IC.ontainment

. Purge I

/

f l i  : South Yard

. f J Unit 2 Building f  ! Unit 3 Building fl* Facility Ventilation [  ! Venti.lation Work Area Exhaust l I

I Exhaust I Exhaust

---.-.___,_____;_J_

r L..c.____jt Figure 4-6 SONGS Radioactive Gaseous Waste Treatment Systems

  • 2(3)RT-7865 can be aligned to either containment purge or the plant vent stack. Units 2(3)RT-7865-1 can no longer monitor containment purge. Cold and Dark Rad Waste Building HVAC NECP 801249775 Order 801429213 disabled the ability to sample the containment purge stack by failing close the purge stack sample valves. However, this section will not be deleted in case it is determined during Decommissioning that this effluent pathway will need to be used.

S0123-0DCM Revision 10 08/2016 4-20

SOLID WASTE HANDLING Figure 4-7 Resin sluiced Loaded into Spent Resin fromSRTto Transferred to Resin sluiced shipping cask Spent Resin Accumulated disposal MPHFfor From IX to SRT for transport to lnSRT container and interim staging burial site dewatered Waste packaged*

Waste evaluation into a container in

.for shipping to burial Waste shipped to Filter removed Filter stored accordance with Particulate site or intermediate burial site or from in-line In accumulation burial site or Process filters processor for intermediate position area on site intermediate alternate processor processor processor methods disposition requirements Resulting Wastes Waste place in Waste shipped disposable Low Level Dry __. collected in receptacles

.cargo container

~ for shipment lo _., to processor _.. waste packaged Active Waste located around the plant off-site processor

,_.. for volume reduction and shipped

  • from processor to burial site Waste sorted ~

for packaging Wastes packaged Waste shipped

. on-site or i----. and transferred 1-iO, to burial site vendor toMPHF processing Clothing packed Clothing Clothing bags in boxes and laundered, Protective collected from shipped to returned to Clothing points around off-site site and plant laundry facility restocked LEGEND:

SRT: Spent Resin Tank MPHF: Multi Purpose Handling Facility IX: Ion Exchanger S0123-0DCM Revision 0 02-27-07 4-21

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

APPLICABILITY: At all times ACTION:

a. Should the radiological environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification Section 5. 7 .1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report (see Section 5.4), a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b. Should the level of radioactivity in an environmental sampling medium exceed the reporting levels of Table 5-2 when averaged over any calendar quarter, in lieu of any other report required by Technical Specification Section 5.7.1, prepare and submit to the Commission, within 30 days from the end of the affected calendar quarter a Report pursuant to 10 CFR 50.73. When more than one of the radionuclides in Table 5-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) + concentration (2) + ... :::: 1.0 limit level (1) limit level (2)

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

S0123-0DCM Revision 9 11/2015 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 add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from ,

which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 5.7.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

SURVEILLANCE REQUIREMENT

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

S0123-0DCM Revision 0 02-27-07 5-2

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

1. AIRBORNE Samples from at least 5 locations: Continuous operation of Radioiodine cartridge. Analyze at least Radioiodine sampler with sample once per 7 days for 1-131. Particulate and 3 samples from offsite locations (in collection as required by sampler. Analyze for gross beta Particulates different sectors) of the highest dust loading, but at least radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter calculated annual average ground level once per 7 daysd. change. Perform gamma isotopicb D/Q. analysis on each sample when gross beta activity is > 1O times the yearly 1 sample from the vicinity of a mean of control samples. Perform community having the highest calculated gamma isotopic analysis on composite annual average ground-level D/Q. (by location) sample at least once per 92 days.

1 sample from a control location 15-30 km (10-20 miles) 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.

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

S0123-0DCM Revision 0 02-27-:07 5-3

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locationsa Collection Frequencya Type and Frequency of Analyses

3. WATERBORNE
a. Ocean 4 locations At least once per month and Gamma isotopic analysis of each compositedt quarterly. monthly sample. Tritium analysis of composite sample at least once per 92 days.
b. Drinking 9 2 locations Monthly at each location. Gamma isotopic and Tritium analyses of each sample.
c. Sediment 4 locations from Shoreline At least once per 184 days. Gamma isotopic analysis of each sample.
d. Ocean 5 locations Bottom Sediments At least once per 184 days. Gamma isotopic analysis of each sample.

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

TABLE 5-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples Sampling and and/or Sample and Sample Locationsa Collection Frequenct 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. Fish-2 adult species such as perch or sheephead.
2. Crustaceae-such as crab or lobster.
3. Mollusks-such as limpets, seahares or clams.
b. Local Crops 2 locations Representative vegetables, Gamma isotopic analysis on edible normally 1 leafy and portions semiannually and 1-131 1 fleshy collected at harvest analysis for leafy crops.

time. At least 2 vegetables collected semiannually from each location.

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

TABLE 5-1 (Continued)

TABLE NOTATION

a. Sample locations are indicated on Figures 5-1 through 5-5.
b. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
c. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.
d. Canisters for the collection of radioiodine in air are subject to channeling. These devices should be carefully checked before operation in the field or several should be mounted in series to prevent loss of Iodine.
e. Reg. Guide 4.13 (Revision 0) provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.
f. Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).
g. No drinking water pathway exists at SONGS.

S0123-0DCM Revision 9 11/2015 5-6

TABLE 5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Airborne Particulate Water or Gases Marine Animals Local Crops 3

Analysis (pCi/1) (pCi/m ) (pCi/Kg, wet) (pCi/Kg, wet)

H-3 2 X 104 (a) 3 Mn-54 1 X 10 3 X 104 Fe-59 4 X 102 1 X 104 Co-58 1 X 103 3 X 104 Co-60 3 X 102 1 X 104 Zn-65 3 X 102 2 X 104 Zr-95, Nb-95 4 X 102 1-131 2(b) 0.9 1 X 102 Cs-134 30 10 1 X 103 1 X 10 3

Cs-137 50 20 2 X 103 2 X 103 2

Ba-140, La-140 2 X 10 (a) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/1 may be used.

(b) If no drinking water pathway exists, a value of 20 pCi/1 may be used.

S0123-0DCM Revision 0 02-27-07 5-7

I TABLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS!c>

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD}!a>

Airborne Particulate Water or Gases Marine Animals Local Crops Sediment Analysis (pCi/1) (pCi/m 3) (pCi/Kg, wet) (pCi/Kg, wet) (pCi/Kg, dry) gross beta 4 1 X 10-2 H-3 2ooo(b)

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95, Nb-95 15 1-131 1(d) 7 X 10-2 60 Cs-134 15 5 X 10-2 130 60 150 Cs-137 18 6 X 10-2 150 80 180 Ba-140, La-140 15 S0123-0DCM Revision 0 02-27-07 5-8

TABLE 5-3 (Continued)*

TABLE NOTATION

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

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

LLD= 4.66Sb E*V*2.22xl0 6 *Y*exp (-A~t) 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)

'A = 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). S0123-0DCM Revision 0 02-27-07 5-9

TABLE 5.3 (Continued)

TABLE NOTATION (Continued)

b. If no drinking water pathway exists, a value of 3000 pCi/1 may be used.
c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 5-3, shall be identified and reported.
d. If no drinking water pathway exists, a value of 15 pCi/1 may be used.

S0123-0DCM Revision 0 02-27-07 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. With the land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 2.3.1, pursuant to Technical Specification 5. 7 .1, identify the new locations in the next Annual Radioactive Effluent Release Report.
b. With the land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 5.1, add the new location within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s) via the same exposure pathway, may be deleted from this monitoring program after October 31, of the year in which this Land Use Census was conducted. Pursuant to Technical Specification 5. 7.1, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

SURVEILLANCE 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-door survey, aerial survey, or by consulting local agriculture authorities.

  • Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

S0123-0DCM Revision 0 02-27-07 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).

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

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

5.4.1 The annual radiological environmental operating report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 5.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the Radiological Assessment Branch Technical Position, Revision 1, November 1979, of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. J The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from the mid-point of reactor Units 2 and 3; and the results of licensee participation in the lnterlaboratory Comparison Program, required by Section 5.3.

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

S0123-0DCM Revision 9 11/2015 5-13

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

S0123-0DCM Revision O 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 Mateo (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) 0.7 . WNW 11 Former Visitors' Center 0.4** NW 12 South Edge of Switchyard 0.2** E 13 Southeast Site boundary (Bluff) 0.4** ESE 15 Southeast Site Boundary (Office Building) 0.1** SSE 16 East Southeast Site Boundary 0.4** ESE 17 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 Talega (MCB, Camp Pendleton) 5.9 N 34 San Onofre School (MCB, Camp Pendleton) 1.9 NW 35 Range 312 (MCB, Camp Pendleton) 4.8 NNE 36 Range 208C (MCB, Camp Pendleton) 4.1 NE 38 San Onofre State Beach Park 3.4 SE 40 SCE Training Center - Mesa (Adjacent to Former 0.7 NNW PIC #3) 41 Old Route 101 - East 0.3** E 44 Fallbrook Fire Station 17.7 E 46 San Onofre State Beach Park 1.0 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE S0123-0DCM Revision 9 11/2015 5-15

__J

Page 2 of 5 TABLE 5-4 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION*

Direct Radiation (Continued) 49 Camp Chappo (MCB, Camp Pendleton) 12.9 ESE 50 Oceanside Fire Station (CONTROL) 15.6 SE 53 San Diego County Operations 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 #6) 0.6 NE 64 MCB - Camp Pendleton (Adjacent to Former PIC #7) 0.6 ENE 65 MCB - Camp Pendleton (Adjacent to Former PIC #8) 0.7 E 66 San Onofre State Beach (Adjacent to Former PIC #9) 0.6 ESE 67 Former SONGS Evaporation Pond (Adjacent to Former 0.6 NW PIC #2) 68 Range 21 OC (MCB, Camp Pendleton) 4.4 ENE 73 South Yard Facility 0.4** ESE 74 Oceanside City Hall (Backup CONTROL) 15.6 SE 75 Gate 25 MCB 4.6 SE 76 Former El Camino Real Mobil Station 4.6 NW 77 Area 62 Heavy lift pad 4.2 N 78 Homo Canyon (AKA Sheep Valley) 4.4 ESE

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint.

Direction is determined from degrees true north.

    • Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.

S0123-0DCM Revision 9 11/2015 5-16

Page 3 of 5 TABLE 5-4 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE 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 Samples t 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 Technical Specification.

t Soil Samples are not required by Technical Specifications.

S0123-0DCM Revision 9 11/2015 5-17

Page 4 of 5 TABLE 5-4 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE*

TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION*

Drinking Water 4 Camp Pendleton Drinking Water Reservoir 2.0 NW 5 Oceanside City Hall (new CONTROL) 15.6 SE Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (Southeast) 0.6 SE 2 San Onofre Surfing Beach 0.8 WNW 3 San Onofre State Beach (Southeast) 3.5 SE 4 Newport Beach (North End) (CONTROL) 29.2 NW Local Crops 1 DELETED 2 Oceanside (CONTROL)** 15 to 25 SE to ESE 4 DELETED 6 SONGS Garden*** 0.7 NNW

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint.

Direction is determined from degrees true north.

      • The SONGS Garden, location 6, for local crops, was relocated 0.1 miles west and 0.3 miles north to remain on controlled property with irrigation in September 2015 and remains 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.

S0123-0DCM Revision 9 11/2015 5-18

TABLE 5-4 (Continued) Page5 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 WNW to NW 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 WNW to NW Ocean Bottom Sediments A DELETED B Unit 1 Outfall 0.8 SSW C Unit 2 Outfall 1.6 SW D Unit 3 Outfall 1.2 SSW E Laguna Beach (CONTROL) 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 Technical Specifications.

S0123-0DCM Revision 8 12/2014 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 Q NW 326.25 337.5 348.75 R NNW

  • Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint.

Direction is determined from degrees true North.

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

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S0123-0DCM Revision 11 08/2017 5-22

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S0123-0DCM Revision 11 08/2017 5-23

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S0123-0DCM Revision 11 08/2017 5-24

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S0 123-0DCM Revision 8 12/2014 5-25

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,.~,'.M e,.."t.GE<AllEOBfAC'J.UO~:O,t S0123-0DCM Revision 8 12/2014 5-26 j

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 and/or trip functions.
c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify FUNCTIONALITY.

S0123-0DCM Revision 9 11/2015 6-1

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 portions 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).

S0123-0DCM Revision 9 11/2015 6-2

6.0 ADMINISTRATIVE (Continued) 6.1 DEFINITIONS (Continued)

SOURCE CHECK 6.1.11 For Sorrento Electronics digital monitors a SOURCE CHECK shall be the verification of proper computer response to a check source request.

[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, 2/3RT-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 condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per ... "

basis, the above Frequency extension applies to each performance after the initial performance.

This provision is not intended to be used repeatedly as a convenient means to extend surveillance intervals beyond those specified.

Additionally, it does not apply to any Action Statements.

VENTILATION EXHAUST TREATMENT SYSTEM 6.1.13 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through HEPA filters for the purpose of removing Iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on Noble gas effluents).

NOTE: There are no longer any permanent ventilation exhaust treatment systems. Local mobile ventilation exhaust treatment system will be used on an as needed bases when outdoor activities have the potential for gaseous effluent releases.

S0123-0DCM Revision 10 08/2016 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.

S0123-0DCM

  • Revision O 02-27-07 6-4

TABLE 6-1 OPERATIONAL MODES DELETED REMAINDER OF PAGE LEFT INTENTIONALLY BLANK S0123-0DCM Revision 9 11/2015 6-5

TABLE 6-2 FREQUENCY NOTATION NOTATION FREQUENCY s At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> w At least once per 7 days M At least once per 31 days Q 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 3 times per week (usually M, W, F).

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

S0123-0DCM Revision 9 11/2015 6-6

6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT*

6.2.1 Routine radioactive effluent release reports covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

6.2.2 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in 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 format of Appendix B thereof.

The radioactive effluent release report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 1-2 and 2-2) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.

The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

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

S0123-0DCM Revision 9 11/2015 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 from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in 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, Large Quantity), and
f. Solidification Agent (e.g., cement, urea formaldehyde).

The radioactive effluent release report shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

S0123-0DCM 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 discussion of each change shall contain:
a. A summary of the evaluation that led to the determination that the change could be made in accordance with applicable regulations;
b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;
d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments thereto;
e. An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;
f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents to the actual release for the period prior to when the changes are to be made;
g. An estimate of the exposure to plant operating personnel as a result of the change; and
h. Documentation of the fact that the change was reviewed and found acceptable
2. Shall become effective upon review and acceptance.

S0123-0DCM 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 materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within ( 1) the Section II.A design objectives of Appendix I, 10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.106( e) to the population. The concentration limit for dissolved or entrained Noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

DOSE (1.2) 6.4.2 This specification is provided to implement the 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 conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Reg.

Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Reg.

Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

S0123-0DCM Revision 9 11/2015 6-10

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

LIQUID WASTE TREATMENT (1.3) 6.4.3 The FUNCTIONALITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section 11.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 any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 [10 CFR Part 20.106(b )]. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.

This specification applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.

S0123-0DCM Revision 9 11/2015 6-11

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued)

DOSE - NOBLE GASES (2.2) 6.4.5 This specification is provided to implement the requirements of Sections 11.B, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section 11.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially und~restimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Reg. Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Reg.

Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. For MEMBERS OF THE PUBLIC who traverse the SITE BOUNDARY via highway 1-5, the residency time shall be considered negligible and hence the dose "O". The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions.

DOSE - RADIOIODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM (2.3) 6.4.6 This specification is provided to implement the requirements of Sections 11.C, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section 11.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably 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 shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual S0123-0DCM Revision 0 02-27-07 6-12

6.0 ADMINISTRATIVE (Continued) 6.4 BASES (Continued) release rates of the subject materials are consistent with the methodology provided in Reg. Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Reg. Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revil;iion 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive materials in particulate form and Tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

GASEOUS RADWASTE TREATMENT (2.4) 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 NRG 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.

S0123-0DCM 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 shall be calculated in accordance with the procedures in the ODCM to ensure the alarm/trip will occur prior 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 10 CFR Part 50.

RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) 6.4.9 The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the waste gas holdup system. 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.

MONITORING PROGRAM (5.1) 6.4.10 The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

S0123-0DCM Revision 9 11/2015 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 g_

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) 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.

S0123-0DCM Revision 9 11/2015 6-15 L

Enclosure 3 Offsite Dose Calculation Manual Nuclear Organization San Onofre Nuclear Generation Station Appendix A Ri Tables S0123-0DCM-A, Revision 11, August 2017

OFFSITE DOSE CALCULATION MANUAL NUCLEAR ORGANIZATION SAN ONOFRE NUCLEAR GENERATING STATION APPENDIX A Ri TABLES S0123-0DCM-A Revision 11 08/2017

ODCM APPENDIX A TABLE OF CONTENTS Section 1.0 UNITS 2 AND 3 RiTABLES*................................ A1-1 thru A1-49 1-1 Dose Parameters Ri for Sector P . . . . . . . . . . . . . . . . . . . . A 1-1 1-2 Dose Parameters Ri for Sector Q . . . . . . . . . . . . . . . . . . . . A 1-6 1-3 Dose Parameters Ri for Sector R . . . . . . . . . . . . . . . . . . . . A 1-16 1-4 Dose Parameters Rifer Sector A. . . . . . . . . . . . . . . . . . . . A1-19 1-5 Dose Parameters Ri for Sector B . . . . . . . . . . . . . . . . . . . . A 1-22 1-6 Dose Parameters Ri for Sector C . . . . . . . . . . . . . . . . . . . . A 1-26 1-7 Dose Parameters Ri for Sector D . . . . . . . . . . . . . . . . . . . . A 1-32 1-8 Dose Parameters Ri for Sector E . . . . . . . . . . . . . . . . . . . . A 1-35 1-9 Dose Parameters Ri for Sector F . . . . . . . . . . . . . . . . . . . . A 1-41 1-10 Dose Parameters Ri for Sector G . . . . . . . . . . . . . . . . . . . . A 1-46 2.0 SOUTH YARD FACILITY RiTABLES**. DELETED ............. .

3.0 NORTH INDUSTRIAL AREA (UNIT 1) RTABLES** DELETED .....

References:

  • Sandra Sewell to Brian Metz Memorandum for file: "2016 Dose Parameters for San Onofre Units 2 and 3", dated November 30, 2016.

References:

    • Remove Dose Parameter (Ri) Tables from ODCM for South Yard Facility and for North Industrial Area NN # 203063159-095.

Ai S0123-0DCM-A Revision 11 08/2017

TABLE 1-1 UNITS 2&3 Page 1 of 5 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: SURF BEACH/LIFE GUARD DISTANCE: . 5 MILES X/Q l.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** O.OE+OO 0.0E+OO 7.8E+OO O.OE+OO 4.2E+Ol O.OE+OO l.2E+02 O.OE+OO CR 51 0.0E+OO O.OE+OO 1.2E+02 3.2E+04 6.9E+02 1.5E+05 1.3E+03 4.2E+05 MN 54 O.OE+OO O.OE+OO 1.1E+04 9.5E+06 6.5E+04 4.5E+07 1.3E+05 l.3E+08 co 57 0.0E+OO O.OE+OO 9.lE+Ol 2.4E+06 1.0E+03 1.1E+07 2.9E+03 3.1E+07 co 58 O.OE+OO 0.0E+OO 7.6E+03 2.6E+06 4.4E+04 1.2E+07 8.5E+04 3.5E+07 co 60 0.0E+OO O.OE+OO 4.9E+04 1.5E+08 2.9E+05 7.0E+08 5.4E+05 2.0E+09 SR 89 0.0E+OO O.OE+OO l.5E+04 l.5E+02 7.9E+04 7.1E+02 l.3E+05 2.0E+03 SR 90 O.OE+OO O.OE+OO l.OE+05 0.0E+OO 5. 4E+05 0.0E+OO 8.8E+05 0. OE+oO ZR 95 0.0E+OO O.OE+OO l.5E+04 1.7E+06 8.8E+04 8.2E+06 1.6E+05 2.3E+07 NB 95 0.0E+OO O.OE+OO 4.2E+03 9.4E+05 2.5E+04 4.5E+06 4.6E+04 1.2E+07 RU 103 0.0E+OO O.OE+OO 4.6E+03 7.5E+05 2.6E+04 3.6E+06 4.6E+04 9.9E+06 TE 129M 0.0E+OO O.OE+OO l.2E+04 1.4E+05 6.5E+04 6.4E+05 1.1E+05 1. 8E+06 cs 134 0.0E+OO 0.0E+OO 8.3E+02 4.7E+07 4.8E+03 2.2E+08 8.9E+03 6.2E+08 cs 136 0. OE+oO O.OE+OO l.OE+02 l.0E+06 5.8E+02 4.9E+06 1. 1E+03 1. 4E+07 cs 137 0. OE+oO O.OE+OO 7.2E+02 7.1E+07 4.0E+03 3.4E+08 6.9E+03 9.4E+08 BA 140 0. OE+oO O.OE+OO l.2E+04 1.4E+05 6.6E+04 6.7E+05 l.2E+05 l.9E+06 CE 141 0. OE+oO O.OE+OO 3.8E+03 9.4E+04 2.0E+04 4.5E+05 3.3E+04 l.2E+06 CE 144 0. OE+oO O.OE+OO 8.2E+04 4.8E+05 4.4E+05 2.3E+06 7.1E+05 6.4E+06 I 131 0. OE+oO O.OE+OO l.1E+05 1. 2E+05 4.8E+05 5.6E+05 1.1E+06 l.6E+06 I 132 0.0E+OO 0.0E+OO l.3E+03 8.5E+03 4.9E+03 4.1E+04 l.OE+04 l.1E+05 I 133 0.0E+OO O.OE+OO 2.7E+04 l.7E+04 9.5E+04 8.0E+04 2.0E+05 2.2E+05 I 134 0.0E+OO 0.0E+OO 3.5E+02 3.1E+03 1.3E+03 1.5E+04 2.7E+03 4.1E+04 I 135 0.0E+OO O.OE+OO 5.5E+03 1.7E+04 2.0E+04 8.2E+04 4.1E+04 2.3E+05 UN-ID* 0.0E+OO O.OE+OO 6.9E+03 5.1E+06 4.1E+04 2. 4E+07 7.9E+04 6.8E+07 PAGE Al-1 SO 123-0DCM-A Revision 5 03-17-11

TABLE 1-1 UNITS 2&3 Page 2 of 5 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: SORB RESDNT/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** l.1E+02 O.OE+OO 1.8E+02 O.OE+OO 2.1E+02 O.OE+OO 1.3E+03 0.0E+OO CR 51 2.1E+03 7.6E+05 2.8E+03 7.6E+05 3.4E+03 7.6E+05 1.4E+04 4.7E+06 MN 54 1.6E+05 2.3E+08 2.6E+05 2.3E+08 3.3E+05 2.3E+08 l.4E+06 1.4E+09 co 57 8.0E+02 5.6E+07 2.2E+03 5.6E+07 5.2E+03 5.6E+07 3.1E+04 3.4E+08 co 58 1.3E+05 6.2E+07 l.8E+05 6.2E+07 2.2E+05 6.2E+07 9.3E+05 3.8E+08 co 60 7.4E+05 3.5E+09 l.2E+06 3.5E+09 l.4E+06 3.5E+09 6.0E+06 2.2E+10 SR 89 3.3E+05 3.5E+03 3.5E+05 3.5E+03 4.0E+05 3.5E+03 1.4E+06 2.2E+04 SR 90 1.8E+06 O.OE+OO 2.4E+06 O.OE+OO 2.7E+06 0. OE+oO 9.6E+06 O.OE+OO ZR 95 2.9E+05 4.1E+07 3.7E+05 4.1E+07 4.4E+05 4.1E+07 1.8E+06 2.5E+08 NB 95 7.9E+04 2.2E+07 1.0E+05 2.2E+07 1.2E+05 2.2E+07 5.0E+05 l.4E+08 RU 103 9.1E+04 l.8E+07 l.1E+05 1.8E+07 l.3E+05 l.8E+07 5.0E+05 l.1E+08 TE 129M 2.8E+05 3.2E+06 2.9E+05 3.2E+06 3.2E+05 3.2E+06 l.2E+06 2.0E+07 cs 134 1.3E+04 1.1E+09 2.0E+04 l.1E+09 2. 4E+04 l.1E+09 9.8E+04 6.8E+09 cs 136 1.9E+03 2.5E+07 2.4E+03 2.5E+07 2.9E+03 2.5E+07 l.2E+04 1.5E+08 cs 137 1.2E+04 1.7E+09 1.7E+04 l.7E+09 2.0E+04 l.7E+09 7.5E+04 1.0E+lO BA 140 2.6E+05 3.4E+06 2.9E+05 3.4E+06 3.3E+05 3.4E+06 l.3E+06 2.1E+07 CE 141 8.5E+04 2.2E+06 8.9E+04 2.2E+06 l.OE+05 2.2E+06 3.6E+05 l.4E+07 CE 144 l.6E+06 l.1E+07 2.0E+06 1.1E+07 2.2E+06 1.1E+07 7.8E+06 7.0E+07 I 131 2.4E+06 2.8E+06 2.7E+06 2.8E+06 2.4E+06 2.8E+06 l.2E+07 1.7E+07 I 132 2.8E+04 2.0E+05 3.2E+04 2.0E+05 2.5E+04 2.0E+05 l.1E+05 l.2E+06 I 133 5.8E+05 4.0E+05 6.3E+05 4.0E+05 4.8E+05 4.0E+05 2.2E+06 2.4E+06 I 134 7.3E+03 7.4E+04 8.3E+03 7.4E+04 6.5E+03 7.4E+04 3.0E+04 4.5E+05 I 135 l.1E+05 4.1E+05 l.3E+05 4.1E+05 1.0E+05 4.1E+05 4.5E+05 2.5E+06 UN-ID* l.1E+05 l.2E+08 1.6E+05 1.2E+08 2.0E+05 l.2E+08 8.6E+05 7.5E+08 PAGEAl-2 S0123-0DCM-A Revision 5 03-17-11

TABLE 1-1 UNITS 2&3 Page 3 of 5 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: TRESTLES BEACH LOCK OUT DISTANCE: 1.8 MILES X/Q l.9E-07 SEC/(M**3) D/Q 6.6E-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 7.2E+Ol 0.0E+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.2E+02 2.7E+05 MN 54 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO 8.0E+04 7.9E+07 co 57 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.8E+03 2.0E+07 co 58 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 5.3E+04 2.2E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO 0.0E+OO 3.4E+05 1.2E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 0.0E+OO 8.0E+04 1.2E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO 0.0E+OO 5.5E+05 0.0E+OO ZR 95 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 1.0E+05 l.4E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0.0E+OO 2.9E+04 7.8E+06 RU 103 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 2.9E+04 6.2E+06 TE 129M 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 7.0E+04 1.1E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0.0E+OO 5.6E+03 3.9E+08 cs 136 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.9E+02 8.6E+06 cs 137 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 4.3E+03 5.9E+08 BA 140 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.3E+04 l.2E+06 CE 141 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.1E+04 7.8E+05 CE 144 0.0E+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 0.0E+OO 4.4E+05 4.0E+06 I 131 0.0E+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 6.8E+05 9.8E+05 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 6.5E+03 7.1E+04 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO l.2E+05 l.4E+05 I 134 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.7E+03 2.6E+04 I 135 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 2.6E+04 1.4E+05 UN-ID* 0.0E+OO 0.0E+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO 4.9E+04 4.3E+07 PAGEAl-3 S0123-0DCM-A Revision 9 09/2015

i I

TABLE 1-1 UNITS 2&3 Page 4 of 5 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: COTTON POINT ESTATES DISTANCE: 2.7 MILES X/Q 1.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 1.1E+03 O.OE+OO 1.3E+03 O.OE+OO 1.3E+03 O.OE+OO CR 51 1.3E+04 4.7E+06 1.7E+04 4.7E+06 2.1E+04 4.7E+06 1.4E+04 4.7E+06 MN 54 1.0E+06 1.4E+09 1.6E+06 l.4E+09 2.0E+06 1.4E+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 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 l.1E+07 O.OE+OO 1.5E+07 O.OE+OO 1.6E+07 O.OE+OO 9.6E+06 0.0E+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 l.4E+08 5.0E+05 l.4E+08 RU 103 5.5E+05 l.1E+08 6.6E+05 1.1E+08 7.8E+05 1.1E+08 5.0E+05 l.1E+08 TE 129M 1.7E+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 l.2E+04 l.5E+08 1.5E+04 l.5E+08 1.8E+04 1.5E+08 l.2E+04 l.5E+08 cs 137 7.1E+04 1. OE+lO l.OE+05 1. OE+lO 1.2E+05 1. OE+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 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 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 l.7E+07 1.5E+07 l.7E+07 l.2E+07 l.7E+07 I 132 l.7E+05 l.2E+06 l.9E+05 l.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 1.0E+06 7.5E+08 1. 2E+06 7.5E+08 8.6E+05 7.5E+08 PAGEAl-4 SO 123-0DCM-A Revision 5 03-17-11

TABLE 1-1 UNITS 2&3 Page 5 of 5 DOSE PARAMETER R(I) FOR SECTOR 'P' PATHWAY: COTTON POINT GARDENS DISTANCE: 2.8 MILES X/Q 1.0E-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+OO 1.1E+03 4.0E+03 1.3E+03 2.6E+03 1.3E+03 2.3E+03 CR 51 1.3E+04 4.7E+06 1.7E+04 1.1E+07 2.1E+04 1.5E+07 1.4E+04 l.6E+07 MN 54 1.0E+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 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+10 7.1E+06 2.4E+10 8.7E+06 2.5E+10 6.0E+06 2.5E+10 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+OO 1.5E+07 1.4E+12 1.6E+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 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 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 l.2E+05 3.2E+10 l.5E+05 2.3E+l0 9.8E+04 l.8E+10 cs 136 l.2E+04 1.5E+08 l.5E+04 3.7E+08 l.8E+04 3.2E+08 l.2E+04 3.2E+08 cs 137 7.1E+04 l.OE+lO 1.0E+05 3.4E+10 l.2E+05 2. 4E+10 7.5E+04 1.9E+l0 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 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 1.2E+07 l.OE+lO 1.3E+07 1. 3E+10 7.8E+06 1.lE+lO I 131 1.5E+07 1.7E+07 1.6E+07 4.8E+10 1.5E+07 3.lE+lO 1.2E+07 3.8E+10 I 132 1.7E+05 1.2E+06 1.9E+05 1.2E+06 1. 5E+05 1. 2E+O 6 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 l.2E+07 6.2E+05 8.2E+06 4.5E+05 9.1E+06 UN-ID* 6.5E+05 7.5E+08 1.0E+06 3.5E+09 1.2E+06 2.6E+09 8.6E+05 2.0E+09 PAGEAl-5 S0123-0DCM-A Revision 5 03-17-11

TABLE 1-2*

UNITS 2&3 Page 1 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: ST PARK OFFICE TRLR DISTANCE: .6 MILES X/Q 2.5E-06 SEC/(M**3) D/Q 1.4E-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** O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. 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 0. 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 0. OE+oO O.OE+OO 3.2E+05 3.2E+08 co 57 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 7.2E+03 7.8E+07 co 58 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.1E+05 8.7E+07 co 60 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO l.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 0.0E+OO ZR 95 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 4.0E+05 5.7E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 1.2E+05 3.1E+07 RU 103 0.0E+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 0.0E+OO 2.8E+05 4.5E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO 2.2E+04 1.6E+09 cs 136 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO 0. 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 0. OE+oO 1.7E+04 2.3E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 2.9E+05 4.7E+06 CE 141 0.0E+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 0.0E+OO O.OE+OO O.OE+OO 1.8E+06 1.6E+07 I 131 0. 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 O.OE+OO 0.0E+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 0.0E+OO O.OE+OO 4.9E+05 5.6E+05 I 134 0.0E+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 O.OE+OO 1.0E+05 5.8E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 2.0E+05 1.7E+08 PAGEAl-6 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-2 UNITS 2&3 Page 2 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SURF BEACH/GUARD SHACK DISTANCE: . 7 MILES X/Q 2.0E-06 SEC/(M**3) D/Q l.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 7.BE+OO O.OE+OO 4.2E+Ol O.OE+OO 2.2E+02 0.0E+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 0.0E+OO O.OE+OO 9.lE+Ol 2.4E+06 l.OE+03 l.1E+07 5.4E+03 5.9E+07 co 58 0.0E+OO O.OE+OO 7.6E+03 2.6E+06 4.4E+04 1.2E+07 l.6E+05 6.5E+07 co 60 O.OE+OO 0.0E+OO 4.9E+04 l.5E+08 2.9E+05 7.0E+OB 1.0E+06 3.7E+09 SR 89 0.0E+OO O.OE+OO l.5E+04 1.5E+02 7.9E+04 7.1E+02 2.4E+05 3.7E+03 SR 90 0.0E+OO O.OE+OO 1.0E+05 O.OE+OO 5.4E+05 0.0E+OO 1.6E+06 O.OE+OO ZR 95 0.0E+OO O.OE+OO 1.5E+04 1.7E+06 8.8E+04 8.2E+06 3. OE+05 4.3E+07 NB 95 0.0E+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 0.0E+OO O.OE+OO l.2E+04 1.4E+05 6.5E+04 6.4E+05 2.1E+05 3.4E+06 cs 134 O.OE+OO 0.0E+OO 8.3E+02 4.7E+07 4.8E+03 2.2E+08 l.7E+04 l.2E+09 cs 136 0.0E+OO O.OE+OO l.OE+02 l.OE+06 5.8E+02 4.9E+06 2.1E+03 2.6E+07 cs 137 O.OE+OO 0.0E+OO 7.2E+02 7.1E+07 4.0E+03 3.4E+08 l.3E+04 1.8E+09 BA 140 0.0E+OO O.OE+OO 1.2E+04 l.4E+05 6.6E+04 '6. 7E+05 2.2E+05 3.5E+06 CE 141 O.OE+OO O.OE+OO 3.8E+03 9.4E+04 2.0E+04 4.5E+05 6.2E+04 2.3E+06 CE 144 0.0E+OO O.OE+OO 8.2E+04 4.8E+05 4.4E+05 2.3E+06 l.3E+06 l.2E+07 I 131 0.0E+OO O.OE+OO l.1E+05 l.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 1.7E+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 1.3E+03 1.5E+04 5.1E+03 7.7E+04 I 135 0. 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* 0.0E+OO O.OE+OO 6.9E+03 5.1E+06 4.1E+04 2.4E+07 1.5E+05 1. 3E+08 PAGEAl-7 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-2 UNITS 2&3 Page 3 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SORB RESDNT/CAMPGROUND 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** l.1E+02 0. OE+oO 1.8E+02 O.OE+OO 2.1E+02 O.OE+OO 1.3E+03 0.0E+OO CR 51 2.1E+03 7.6E+05 2.8E+03 7.6E+05 3.4E+03 7.6E+05 l.4E+04 4.7E+06 MN 54 1.6E+05 2.3E+08 2.6E+05 2.3E+08 3.3E+05 2.3E+08 1.4E+06 1.4E+09 co 57 8.0E+02 5.6E+07 2.2E+03 5.6E+07 5.2E+03 5.6E+07 3.1E+04 3.4E+08 co 58 1.3E+05 6.2E+07 l.8E+05 6.2E+07 2.2E+05 6.2E+07 9.3E+05 3.8E+08 co 60 7.4E+05 3.5E+09 l.2E+06 3.5E+09 l.4E+06 3.5E+09 6.0E+06 2. 2E+10 SR 89 3.3E+05 3.5E+03 3.5E+05 3.5E+03 4.0E+05 3.5E+03 1.4E+06 2.2E+04 SR 90 l.8E+06 O.OE+OO 2.4E+06 0.0E+OO 2.7E+06 O.OE+OO 9.6E+06 O.OE+OO ZR 95 2.9E+05 4.1E+07 3.7E+05 4.1E+07 4.4E+05 4.1E+07 1.8E+06 2.5E+08 NB 95 7.9E+04 2.2E+07 l.OE+05 2.2E+07 l.2E+05 2.2E+07 5.0E+05 1.4E+08 RU 103 9.1E+04 1.8E+07 1.1E+05 1.8E+07 1.3E+05 1.8E+07 5.0E+05 l.1E+08 TE 129M 2.8E+05 3.2E+06 2.9E+05 3.2E+06 3.2E+05 3.2E+06 1. 2E+06 2.0E+07 cs 134 1.3E+04 1.1E+09 2.0E+04 l.1E+09 2.4E+04 l .1E+0*9 9.8E+04 6.8E+09 cs 136 l.9E+03 2.5E+07 2.4E+03 2.5E+07 2.9E+03 2.5E+07 1.2E+04 l.5E+08 cs 137 l.2E+04 1.7E+09 1.7E+04 l.7E+09 2.0E+04 l.7E+09 7.5E+04 l.OE+lO BA 140 2.6E+05 3.4E+06 2.9E+05 3.4E+06 3.3E+05 3.4E+06 1.3E+06 2. 1E+07 CE 141 8.5E+04 2.2E+06 8.9E+04 2.2E+06 1.0E+05 2.2E+06 3.6E+05 1.4E+07 CE 144 l.6E+06 1. 1E+07 2.0E+06 1. 1E+07 2.2E+06 1. 1E+07 7.8E+06 7.0E+07 I 131 2.4E+06 2.8E+06 2.7E+06 2.8E+06 2.4E+06 2.8E+06 l.2E+07 l.7E+07 I 132 2.8E+04 2.0E+05 3.2E+04 2.0E+05 2.5E+04 2.0E+05 1.1E+05 l.2E+06 I 133 5.8E+05 4.0E+05 6.3E+05 4.0E+05 4.8E+05 4.0E+05 2.2E+06 2.4E+06 I 134 7.3E+03 7.4E+04 8.3E+03 7.4E+04 6.5E+03 7.4E+04 3.0E+04 4.5E+05 I 135 l.1E+05 4.1E+05 l.3E+05 4.1E+05 1.0E+05 4.1E+05 4.5E+05 2.5E+06 UN-ID* l.1E+05 1.2E+08 l.6E+05 l.2E+08 2.0E+05 l.2E+08 8.6E+05 7.5E+08 PAGEAl-8 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-2 UNITS 2&3 Page 4 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SORB LIFE GUARD TOWER DISTANCE: 1.2 MILES X/Q 8.9E-07 SEC/ (M**3) D/Q 4.4E-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+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.9E+02 0. OE+oO CR 51 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.3E+03 1.1E+06 MN 54 0.0E+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.QE+OO 0.0E+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 0. 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 0. OE+oO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 2.2E+06 O.OE+OO ZR 95 0. OE+oO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+05 5.7E+07 NB 95 0. OE+oO O.OE+OO O.OE+OO O.OE+OO 0.0E+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 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.8E+05 4.5E+06 cs 134 O.OE+OO 0.0E+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 0. OE+oO 2.7E+03 3.4E+07 cs 137 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO l.7E+04 2.3E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0.0E+OO O.OE+OO 2.9E+05 4.7E+06 CE 141 O.OE+OO 0.0E+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 0.0E+OO O.OE+OO O.OE+OO O.OE+OO l.8E+06 1. 6E+07 I 131 O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 2.7E+06 3.9E+06 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.6E+04 2.8E+05 I 133 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.9E+05 5.6E+05 I 134 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 6.8E+03 1.0E+05 I 135 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 1.0E+05 5.8E+05 UN-ID* O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.0E+05 l.7E+08 PAGEAl-9 S0123-0DCM-A Revision 9 09/2015

TABLE 1-2 UNITS 2&3 Page 5 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SORE 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 0.0E+OO 2.9E+02 O.OE+OO CR 51 0. 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 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 3.2E+05 3.2E+08 co 57 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+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 l.4E+06 4.9E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 3.2E+05 4.9E+03 SR 90 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 2.2E+06 O.OE+OO ZR 95 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 4.0E+05 5.7E+07 NB 95 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO l.2E+05 3.1E+07 RU 103 O.OE+OO 0.0E+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 0.0E+OO O.OE+OO 2.8E+05 4.5E+06 cs 134 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 2.2E+04 1. 6E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0. 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 0.0E+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 0.0E+OO 0.0E+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 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.6E+04 2.8E+05 I 133 O.OE+OO 0.0E+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+OS I 135 O.OE+OO O.OE+OO 0.0E+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+OS l.7E+08 PAGEAl-10 S0123-0DCM-A Revision 9 09/2015

TABLE 1-2 UNITS 2&3 Page 6 of 10 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 1.1E+03 O.OE+OO l.3E+03 O.OE+OO 1.3E+03 O.OE+OO CR 51 1.3E+04 4.7E+06 1.7E+04 4.7E+06 2.1E+04 4.7E+06 1.4E+04 4.7E+06 MN 54 1.0E+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 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+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 l.1E+07 O.OE+OO 1.5E+07 O.OE+OO 1.6E+07 O.OE+OO 9.6E+06 0. OE+oO 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+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 l.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 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 l.2E+04 l.5E+08 l.5E+04 l.5E+08 l.8E+04 1.5E+08 l.2E+04 1. 5E+08 cs 137 7 .1E+04 1. OE+lO l.OE+05 1. OE+lO l.2E+05 1. OE+lO 7.5E+04 1. OE+lO 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 1. 2E+07 7.0E+07 1. 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 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 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 PAGE Al-11 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-2 UNITS 2&3 Page 7 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SAN MATEO PT HOMES DISTANCE: 2.7 MILES X/Q 2.6E-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** 6.5E+02 O.OE+OO l.1E+03 0.0E+OO 1.3E+03 O.OE+OO l.3E+03 O.OE+OO 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 l.OE+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 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+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 l.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 1.4E+08 7.5E+05 l.4E+08 5.0E+05 l.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 1.1E+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 1.2E+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 1.5E+08 l.8E+04 1. 5E+08 1.2E+04 1.5E+08 cs 137 7.1E+04 1. OE+lO 1.0E+05 1. OE+lO l.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 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 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 1.7E+07 l.5E+07 1.7E+07 1.2E+07 l.7E+07 I 132 1.7E+05 l.2E+06 1. 9E+05 1.2E+06 1.5E+05 l.2E+06 1.1E+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 l.2E+06 7.5E+08 8.6E+05 7.5E+08 PAGE Al-12 SO 123-0DCM-A Revision 7 09/2015

TABLE 1-2 UNITS 2&3 Page 8 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SC RES. WITH GARDEN #2 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+OO 1.1E+03 4.0E+03 1.3E+03 2.6E+03 1.3E+03 2.3E+03 CR 51 1.3E+04 4.7E+06 l.7E+04 1.1E+07 2.1E+04 1.5E+07 l.4E+04 1.6E+07 MN 54 1.0E+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+OB 1.3E+04 5.BE+OB 3.1E+04 6.6E+OB 3.1E+04 6.3E+OB 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+l0 7.1E+06 2. 4E+10 8.7E+06 2.5E+10 6.0E+06 2.5E+10 SR 89 2.0E+06 2.2E+04 2.2E+06 3.5E+10 2.4E+06 l.5E+10 l.4E+06 9.8E+09 SR 90 l.1E+07 0.0E+OO l.5E+07 l.4E+12 1.6E+07 8. 3E+ll 9.6E+06 6.7E+ll ZR 95 1. 8E+O 6 2.5E+OB 2.2E+06 1.1E+09 2.7E+06 1.5E+09 l.BE+06 l.4E+09 NB 95 4.8E+05 l.4E+08 6.1E+05 4.3E+OB 7.5E+05 5.9E+OB 5.0E+05 6.1E+08 RU 103 5.5E+05 l.lE+OB 6.6E+05 5.0E+OB 7.BE+05 6.8E+08 5.0E+05 6.6E+08 TE 129M l.7E+06 2.0E+07 1.BE+06 2.9E+09 2.0E+06 l.8E+09 1.2E+06 l.2E+09 cs 134 8.0E+04 6.BE+09 1.2E+05 3.2E+l0 1.5E+05 2.3E+10 9.8E+04 1. 8E+l0 cs 136 1. 2E+04 l.5E+OB l.5E+04 3.7E+OB 1.BE+04 3.2E+08 l.2E+04 3.2E+OB cs 137 7.1E+04 1. OE+lO l.OE+05 3.4E+10 1.2E+05 2.4E+l0 7.5E+04 l.9E+l0 BA 140 l.6E+06 2.1E+07 1.7E+06 3.0E+OB 2.0E+06 2.3E+08 l.3E+06 2.BE+08 CE 141 5.2E+05 1.4E+07 5.4E+05 4.2E+OB

  • 6.1E+05 5.5E+OB 3.6E+05 5.2E+08 CE 144 9.8E+06 7.0E+07 1.2E+07 1. OE+lO 1.3E+07 l.3E+l0 7.8E+06 1.lE+lO I 131 l.5E+07 1.7E+07 l.6E+07 4.BE+lO l.5E+07 3.lE+lO 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+O 6 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+OB 2.2E+06 5.3E+OB 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+OB 1.0E+06 3.5E+09 1.2E+06 2.6E+09 8.6E+05 2.0E+09 PAGE Al-13 S0123-0DCM-A Revision 9 09/2015

TABLE 1-2 UNITS 2&3 Page 9 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SC RES. WITH GARDEN DISTANCE: 4.1 MILES X/Q l.4E-07 SEC/(M**3) D/Q 4.7E-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+OO 0. OE+oO O.OE+OO 3.8E+03 O.OE+OO 2.4E+03 0.0E+OO 1.9E+03 CR 51 0. OE+oO 0. OE+oO O.OE+OO 4.8E+06 O.OE+OO 7.4E+06 0.0E+OO 6.7E+06 MN 54 0.0E+OO 0. OE+oO O.OE+OO 6.1E+08 O.OE+OO 8.3E+08 O.OE+OO 8.0E+08 co 57 O.OE+OO 0. OE+oO 0.0E+OO 2.2E+08 O.OE+OO 2.9E+08 O.OE+OO 2.4E+08 co 58 0.0E+OO O.OE+OO 0.0E+OO 3.3E+08 0.0E+OO 5.1E+08 O.OE+OO 4.7E+08 co 60 O.OE+OO 0. OE+oO O.OE+OO 2.0E+09 O.OE+OO 3.0E+09 O.OE+OO 2.7E+09 SR 89 O.OE+OO 0. OE+oO O.OE+OO 3.lE+lO O.OE+OO 1.2E+10 O.OE+OO 7.2E+09 SR 90 O.OE+OO 0. OE+oO O.OE+OO l.3E+12 0.0E+OO 7. 7E+ll O.OE+OO 5. 8E+ll ZR 95 0.0E+OO O.OE+OO 0.0E+OO 7.8E+08 0.0E+OO 1.1E+09 O.OE+OO 9.1E+08 NB 95 0.0E+OO O.OE+OO 0.0E+OO 2.4E+08 0.0E+OO 3.5E+08 O.OE+OO 3.1E+08 RU 103 0.0E+OO O.OE+OO O.OE+OO 3.3E+08 O.OE+OO 4.5E+08 O.OE+OO 3.8E+08 TE 129M 0.0E+OO O.OE+OO O.OE+OO 2.3E+09 0.0E+OO l.4E+09 0. OE+oO 7.9E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO 2.4E+l0 O.OE+OO 1. 5E+l0 O.OE+OO 9.2E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO 9.0E+07 0.0E+OO 5.7E+07 O.OE+OO 3.6E+07 cs 137 0.0E+OO O.OE+OO O.OE+OO 2.2E+10 O.OE+OO l.3E+10 O.OE+OO 7.8E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO l.1E+08 O.OE+OO 6.8E+07 O.OE+OO 5.3E+07 CE 141 0.0E+OO O.OE+OO O.OE+OO 3.3E+08 0.0E+OO 4.1E+08 0.0E+OO 3.2E+08 CE 144 O.OE+OO O.OE+OO O.OE+OO 9.2E+09 O.OE+OO 1.2E+10 O.OE+OO 9.0E+09 I 131 O.OE+OO O.OE+OO O.OE+OO 4.1E+09 O.OE+OO 2.1E+09 O.OE+OO l.4E+09 I 132 0.0E+OO O.OE+OO O.OE+OO 6.0E-36 0.0E+OO 2.6E-36 O.OE+OO l.7E-36 I 133 0.0E+OO O.OE+OO 0.0E+OO 4. OE-11 0.0E+OO 1. 7E-ll 0. OE+oO 1. lE-11 I 134 0. OE+oO O.OE+OO O.OE+OO 6.lE-37 O.OE+OO 2.7E-37 O.OE+OO 1.7E-37 I 135 0.0E+OO 0. OE+oO O.OE+OO 7.0E-35 0. OE+oO 3.lE-35 0. OE+oO 1. 9E-35 UN-ID* 0. OE+oO 0.0E+OO O.OE+OO 2.5E+09 0. OE+oO 1.7E+09 O.OE+OO l.1E+09 PAGE Al-14 S0123-0DCM-A Revision 9 09/2015

TABLE 1-2 UNITS 2&3 Page 10 of 10 DOSE PARAMETER R(I) FOR SECTOR 'Q' PATHWAY: SAN MATEO W/GARDEN DISTANCE: 4.1 MILES X/Q l.4E-07 SEC/(M**3) D/Q 4. 7E-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 3.8E+03 l.3E+03 2.4E+03 1.3E+03 l.9E+03 CR 51 l.3E+04 4.7E+06 1.7E+04 9.4E+06 2.1E+04 l.2E+07 l.4E+04 1.1E+07 MN 54 l.OE+06 1.4E+09 l.6E+06 2.0E+09 2.0E+06 2.2E+09 1.4E+06 2.2E+09 co 57 4.9E+03 3.4E+08 l.3E+04 5.6E+08 3.1E+04 6.3E+08 3.1E+04 5.8E+08 co 58 7.8E+05 3.8E+08 l.1E+06 7.1E+08 l.3E+06 8.9E+08 9.3E+05 8.5E+08 co 60 4.5E+06 2.2E+l0 7.1E+06 2.3E+l0 8.7E+06 2.4E+10 6.0E+06 2.4E+10 SR 89 2.0E+06 2.2E+04 2.2E+06 3.lE+lO 2.4E+06 l.2E+10 l.4E+06 7.2E+09 SR 90 l.1E+07 0. OE+oO l.5E+07 l.3E+l2 l.6E+07 7. 7E+ll 9.6E+06 5. 8E+ll ZR 95 1.8E+06 2.5E+08 2.2E+06 l.OE+09 2.7E+06 l.3E+09 1.8E+06 l.2E+09 NB 95 4.8E+05 l.4E+08 6.1E+05 3.8E+08 7.5E+05 4.9E+08 5.0E+05 4.5E+08 RU 103 5.5E+05 l.1E+08 6.6E+05 4.4E+08 7.8E+05 5.6E+08 5.0E+05 4.9E+08 TE 129M l.7E+06 2.0E+07 l.8E+06 2.4E+09 2.0E+06 l.4E+09 1. 2E+06 8.1E+08 cs 134 8.0E+04 6.8E+09 l.2E+05 3.lE+lO l.5E+05 2.2E+l0 9.8E+04 l.6E+l0 cs 136 l.2E+04 l.5E+08 l.5E+04 2.4E+08 l.8E+04 2.1E+08 l.2E+04 l.9E+08 cs 137 7.1E+04 1. OE+lO l.OE+05 3.3E+l0 l.2E+05 2.3E+10 7.5E+04 l.8E+l0 BA 140 l.6E+06 2.1E+07 l.7E+06 l.3E+08 2.0E+06 8.8E+07 1. 3E+06 7.4E+07 CE 141 5.2E+05 l.4E+07 5.4E+05 3. 4E+08 6.1E+05 4.2E+08 3.6E+05 3.3E+08 CE 144 9.8E+06 7.0E+07 l.2E+07 9.3E+09 l.3E+07 l.2E+l0 7.8E+06 9.0E+09 I 131 l.5E+07 l.7E+07 l.6E+07 4.1E+09 l.5E+07 2.1E+09 l.2E+07 l.4E+09 I 132 l.7E+05 l.2E+06 l.9E+05 1.2E+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 2.4E+06 4.5E+05 2.5E+06 UN-ID* 6.5E+05 7.5E+08 l.OE+06 3.3E+09 l.2E+06 2.4E+*o9 8.6E+05 l.8E+09 PAGE Al-15 S0123-0DCM-A Revision 9 09/2015

TABLE 1-3 UNITS 2&3 Page 1 of 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 1.3E+03 O.OE+OO 1.3E+03 O.OE+OO CR 51 1.3E+04 4.7E+06 1.7E+04 4.7E+06 2.1E+04 4.7E+06 1.4E+04 4.7E+06 MN 54 1.0E+06 1.4E+09 1.6E+06 l.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 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 l.1E+07 O.OE+OO 1.5E+07 O.OE+OO l.6E+07 O.OE+OO 9.6E+06 O.OE+OO 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+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 1.1E+08 7.8E+05 1.1E+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 1.2E+05 6.8E+09 1.5E+05 6.8E+09 9.8E+04 6.8E+o9 cs 136 l.2E+04 l.5E+08 l.5E+04 l.5E+08 1.8E+04 l.5E+08 1.2E+04 1.5E+08 cs 137 7.1E+04 l.OE+lO l.OE+05 1. OE+lO 1. 2E+05 l.OE+lO 7.5E+04 l.OE+lO BA 140 l.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 l.4E+07 5.4E+05 1.4E+07 6.1E+05 l.4E+07 3.6E+05 1.4E+07 CE 144 9.8E+06 7.0E+07 l.2E+07 7.0E+07 1.3E+07 7.0E+07 7.8E+06 7.0E+07 I 131 l.5E+07 l.7E+07 l.6E+07 1.7E+07 1.5E+07 l.7E+07 l.2E+07 1.7E+07 I 132 1.7E+05 1.2E+06 l.9E+05 1.2E+06 l.5E+05 l.2E+06 1.1E+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 PAGE Al-16 S0123-0DCM-A Revision 9 09/2015

TABLE 1-3 UNITS 2&3 Page 2 of 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 IN HALAT.ION 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 l.5E+Ol 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 1.7E+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 0.0E+OO 0. OE+oO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 3.6E+02 l.8E+07 co 58 0.0E+OO 0.0E+OO O.OE+OO 9.6E+06 O.QE+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 l.6E+04 3.1E+07 SR 90 O.OE+OO 0.0E+OO O.OE+OO 1. OE+09 O.OE+OO 8.0E+08 l.1E+05 l.2E+09 ZR 95 O.OE+OO O.OE+OO 0.0E+OO 6.2E+07 O.OE+OO l.1E+08 2.1E+04 2.0E+08 NB 95 0.0E+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 l.3E+09 TE 129M 0.0E+OO 0. OE+oO O.OE+OO 5.9E+08 0. OE+oO 4.5E+08 l.4E+04 5.3E+08 cs 134 0.0E+OO O.OE+oO 0.0E+OO l.4E+08 0. 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 0.0E+OO 0.0E+OO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 8.7E+02 2.3E+08 BA 140 0.0E+OO 0.0E+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 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 0. OE+oO 0. OE+oO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO l.3E+03 l.4E+04 I 133 0.0E+OO 0. OE+oO O.OE+OO l.6E+Ol O.OE+OO 8.6E+OO 2.5E+04 2.8E+04 I 134 0.0E+OO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO 0. OE+oO 3.5E+02 5.2E+03 I 135 0.0E+OO O.OE+OO 0.0E+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 PAGEAl-17 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-3 UNITS 2&3 Page 3 of 3 DOSE PARAMETER R(I) FOR SECTOR 'R' PATHWAY: CAMP SAN MATEO STP DISTANCE: 3.7 MILES X/Q 1.0E-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** 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 2.9E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 3.3E+03 1.1E+06 MN 54 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 3.2E+05 3.2E+08 co 57 0. OE+oO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 0. OE+oO 7.2E+03 7.8E+07 co 58 0.0E+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO 0. OE+oO 2.1E+05 8.7E+07 co 60 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+06 4.9E+09 SR 89 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+05 4.9E+03 SR 90 0.0E+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 0.0E+OO 4.0E+05 5.7E+07 NB 95 0.0E+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 0.0E+OO O.OE+OO 0. 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 0. OE+oO O.OE+OO O.OE+OO 2.8E+05 4.5E+06 cs 134 0. OE+oO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.2E+04 l.6E+09 cs 136 0. OE+oO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 2.7E+03 3. 4E+07 cs 137 0. OE+oO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 0.0E+OO 1.7E+04 2.3E+09 BA 140 0.0E+OO 0.0E+OO 0.0E+OO O.OE+OO 0. 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 0. OE+oO O.OE+OO 8.3E+D4 3.1E+06 CE 144 O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 0.0E+OO 0.0E+OO l.8E+06 l.6E+07 I 131 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+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 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 0.0E+OO 4.9E+05 5.6E+05 I 134 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.8E+03 1.0E+05 I 135 0. OE+oO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 1.0E+05 5.8E+05 UN-ID* 0. OE+oO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 2.0E+05 1.7E+08 PAGEAl-18 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-4 UNITS 2&3 Page 1 of 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. 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 2.8E+Ol O.OE+OO 2.3E+01 1.5E+Ol 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 1.7E+02 2.4E+05 MN 54 O.OE+OO 0.0E+OO O.OE+OO 7.7E+05 O.OE+OO 1.4E+06 1.6E+04 1.9E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 3.6E+02 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 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 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 1.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO l.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 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 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 1.4E+02 7.2E+06 cs 137 0.0E+OO O.OE+OO O.OE+OO 1. 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 1. 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 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 3E+03 l.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 1. 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 1.1E+08 O.OE+OO 9.4E+07 l.OE+04 1.3E+08 PAGE Al-19 S0123-0DCM-A Revision 9 09/2015

TABLE 1-4 UNITS 2&3 Page 2 of 3 DOSE PARAMETER R(I) FOR SECTOR 'A' PATHWAY: CAMP SAN MATEO 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 l.3E+03 0.0E+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 0.0E+OO O.OE+OO O.OE+OO 0. 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 0. OE+oO O.OE+OO 3.1E+04 3.4E+08 co 58 O.OE+oO O.OE+OO O.OE+OO 0.0E+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 0.0E+OO 6.0E+06 2.2E+l0 SR 89 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO l.4E+06 2.2E+04 SR 90 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 9.6E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO l.8E+06 2.5E+08 NB 95 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 0.0E+OO 5.0E+05 l.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 l.2E+06 2.0E+07 cs 134 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 9.8E+04 6.8E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.2E+04 l.5E+08 cs 137 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 7.5E+04 l.OE+lO BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO l.3E+06 2.1E+07 CE 141 O.OE+OO 0.0E+OO O.OE+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 O.OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.2E+07 l.7E+07 I 132 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO l.1E+05 l.2E+06 I 133 O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+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 0.0E+OO 4.5E+05 2.5E+06 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 8.6E+05 7.5E+08 PAGEAl-20 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-4 UNITS 2&3 Page 3 of3 DOSE PARAMETER R(I) FOR SECTOR 'A' PATHWAY: DEER CONSUMER/HUNTERA2 DISTANCE: 4.2 MILES X/Q 5.7E-08 SEC/(M**3) D/Q 6.6E-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 2.8E+Ol O.OE+OO 2.3E+Ol l.8E+Ol 3.9E+Ol CR 51 0. OE+oO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO l.OE+05 2.0E+02 2.5E+05 MN 54 0. OE+oO O.OE+OO O.OE+OO 7.7E+05 O.OE+OO l.4E+06 1.9E+04 2.2E+07 co 57 0. OE+oO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 4.4E+02 1.8E+07 co 58 0. OE+oO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 l.3E+04 4.2E+07 co 60 0. OE+oO 0. OE+oO O.OE+OO 3.6E+07 0.0E+OO 7.2E+07 8.3E+04 4.3E+08 SR 89 0.0E+OO 0. OE+oO O.OE+OO 4.9E+07 0.0E+OO 2.6E+07 1.9E+04 3.1E+07 SR 90 0. OE+oO O.OE+OO O.OE+OO 1.0E+09 O.OE+OO 8.0E+08 1.3E+05 1.2E+09 ZR 95 0. OE+oO 0. OE+oO O.OE+OO 6.2E+07 O.OE+OO 1.1E+08 2.5E+04 2.0E+08 NB 95 O.OE+OO 0. OE+oO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 7.0E+03 8.2E+08 RU 103 0.0E+OO O.OE+OO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 7.0E+03 1.3E+09 TE 129M 0.0E+OO O.OE+OO O.OE+OO 5.9E+08 0.0E+OO 4.5E+08 l.7E+04 5.3E+08 cs 134 0. OE+oO 0. OE+oO O.OE+OO l.4E+08 0.0E+OO l.2E+08 l.4E+03 2.4E+08 cs 136 0.0E+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 1.7E+02 7.5E+06 cs 137 0.0E+OO O.OE+OO O.OE+OO 1.2E+08 O.OE+OO 9.3E+07 1.0E+03 2.6E+08 BA 140 O.OE+OO O.OE+OO 0.0E+OO 5.0E+06 O.OE+OO 4.2E+06 1. 8E+04 7.1E+06 CE 141 0.0E+OO O.OE+OO O.OE+OO l.5E+06 0.0E+OO 2.4E+06 5.0E+03 4.0E+06 CE 144 O.OE+OO O.OE+OO 0.0E+OO 1.8E+07 O.OE+OO 2.9E+07 1.1E+05 4.8E+07 I 131 0.0E+OO O.OE+OO 0.0E+OO 6.5E+08 0. OE+oO 4.3E+08 l.7E+05 5.9E+08 I 132 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.6E+03 1.7E+04 I 133 0.0E+OO O.OE+OO O.OE+.00 1.6E+Ol O.OE+OO 8.6E+OO 3.0E+04 3.4E+04 I 134 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 4.1E+02 6.3E+03 I 135 0.0E+OO O.OE+OO O.OE+OO 1. lE-15 O.OE+OO 6.3E-16 6.2E+03 3.5E+04 UN-ID* O.OE+OO O.OE+OO O.OE+OO 1.1E+08 O.OE+OO 9.4E+07 l.2E+04 1.3E+08 PAGE Al-21 SO 123-0DCM-A Revision 7 09-23-13

TABLE 1-5 UNITS 2&3 Page 1 of 4 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 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+OO 0.0E+OO 0.0E+OO 2.8E+Ol O.OE+OO 2.3E+Ol 1.5E+Ol 3.9E+Ol CR 51 0.0E+OO 0.0E+OO 0.0E+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 1.9E+07 co 57 0.0E+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 3.6E+02 l.8E+07 co 58 0.0E+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO 1.9E+07 1.1E+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 0.0E+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 0. OE+oO 8.0E+08 1.1E+05 l.2E+09 ZR 95 0.0E+OO O.OE+OO 0.0E+OO 6.2E+07 0. OE+oO l.1E+08 2.1E+04 2.0E+08 NB 95 O.OE+OO O.OE+OO O.OE+OO 2.3E+08 0. OE+oO 4.5E+08 5.9E+03 8.2E+08 RU 103 0.0E+OO 0. OE+oO 0.0E+OO 4.2E+08 O.OE+OO 7.5E+08 5.9E+03 l.3E+09 TE 129M 0.0E+OO 0. OE+oO O.OE+OO 5.9E+08 0.0E+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 1.1E+03 2.3E+08 cs 136 O.OE+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 1.4E+02 7.2E+06 cs 137 O.OE+OO 0.0E+OO 0.0E+OO l.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 1.5E+06 0.0E+OO 2.4E+06 4.2E+03 4.0E+06 CE 144 0.0E+OO O.OE+OO O.OE+OO 1.8E+07 O.OE+OO 2.9E+07 9.0E+04 4.8E+07 I 131 0.0E+OO O.OE+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 l.4E+05 5.9E+08 I 132 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO. 0.0E+OO O.OE+OO l.3E+03 l.4E+04 I 133 0. OE+oO 0.0E+OO 0.0E+OO 1. 6E+Ol 0. 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 O.OE+OO 3.5E+02 5.2E+03 I 135 O.OE+OO O.OE+OO O.OE+OO 1. 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 1.lE+OB O.OE+OO 9.4E+07 1.0E+04 1.3E+08 PAGEAl-22 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-5 UNITS 2&3 Page 2 of 4 DOSE PARAMETER R(I) FOR SECTOR 'B' PATHWAY: SANITARY LANDFILL DISTANCE: 2.1 MILES X/Q l.3E-07 SEC/(M**3) D/Q l.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** O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO l.2E+02 O.OE+OO CR 51 O.OE+OO 0. OE+oO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO l.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 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.9E+03 3.2E+07 co 58 0.0E+OO 0.0E+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 0. OE+oO 5.6E+05 2.0E+09 SR 89 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO l.3E+05 2.0E+03 SR 90 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 8.9E+05 O.OE+OO ZR 95 0.0E+OO O.OE+OO O.OE+OO 0. 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 O.OE+OO O.OE+OO 4.7E+04 l.3E+07 RU 103 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.7E+04 l.OE+07 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO l.1E+05 l.8E+06 cs 134 O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 9.1E+03 6.4E+08 cs 136 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO l.1E+03 l.4E+07 cs 137 O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO 0. OE+OO 7.0E+03 9.6E+08 BA 140 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO l.2E+05 l.9E+06 CE 141 0.0E+OO O.OE+OO 0.0E+OO 0. OE+oO 0.0E+OO O.OE+OO 3.4E+04 1.3E+06 CE 144 0.0E+OO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 7.2E+05 6.5E+06 I 131 0.0E+OO O.OE+OO O.OE+OO 0. 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 O.OE+OO 0.0E+OO l.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 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 2.8E+03 4.2E+04 I 135 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 4.2E+04 2.3E+05 UN-ID* 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.1E+04 6.9E+07 PAGEAl-23 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-5 UNITS 2&3 Page 3 of 4 DOSE PARAMETER R(I) FOR SECTOR 'B' PATHWAY: DEER CONSUMER/HUNTERB2 DISTANCE: 3.0 MILES X/Q 7.8E-08 SEC/ (M**3) D/Q 5.9E-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+OO O.OE+OO 0.0E+OO 2.8E+Ol O.OE+OO 2.3E+Ol 4.4E+OO 3.9E+Ol CR 51 0.0E+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 5.0E+Ol 2.1E+05*

MN 54 0.0E+OO O.OE+OO O.OE+OO 7.7E+05 0.0E+OO l.4E+06 4.9E+03 7.5E+06 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 1.1E+02 1.5E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO 1.9E+07 3.2E+03 3.8E+07 co 60 0.0E+OO O.OE+OO 0.0E+OO 3.6E+07 O.OE+OO 7.2E+07 2.1E+04 2.1E+08 SR 89 0.0E+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 4.9E+03 3.1E+07 SR 90 0.0E+OO O.OE+OO 0. OE+oO l.OE+09 O.OE+OO 8.0E+08 3. 4E+04 1.2E+09 ZR 95 0.0E+OO 0.0E+OO O.OE+OO 6.2E+07 0. OE+oO 1.1E+08 6.2E+03 l.9E+08 NB 95 0. OE+oO O.OE+OO O.OE+OO 2.3E+08 0. OE+oO 4.5E+08 1.8E+03 8.1E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 0. OE+oO 7.5E+08 l.8E+03 1.3E+09 TE 129M 0. OE+oO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 4.3E+03 5.3E+08 cs 134 0.0E+OO 0. OE+oO O.OE+OO l.4E+08 O.OE+OO 1.2E+08 3.4E+02 1.7E+08 cs 136 0.0E+OO 0. OE+oO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 4.2E+Ol 5.9E+06 cs 137 0.0E+OO 0. OE+oO 0-. OE+OO l.2E+08 0.0E+OO 9.3E+07 2.6E+02 l.5E+08 BA 140 0.0E+OO 0.0E+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 4.5E+03 6.9E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO l.5E+06 0.0E+OO 2.4E+06 1.3E+03 3.9E+06 CE 144 0.0E+OO 0.0E+OO O.OE+OO 1.8E+07 O.OE+OO 2.9E+07 2.7E+04 4.7E+07 I 131 0.0E+OO 0.0E+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 4.2E+04 5.9E+08 I 132 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 4.0E+02 4.3E+03 I 133 0.0E+OO O.OE+OO O.OE+OO l.6E+Ol O.OE+OO 8.6E+OO 7.5E+03 8.6E+03 I 134 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.0E+02 1.6E+03 I 135 0. OE+oO O.OE+OO 0.0E+OO l. lE-15 0. OE+oO 6.3E-16 l.6E+03 8.8E+03 UN-ID* 0. OE+oO O.OE+OO O.OE+OO l.1E+08 0. OE+oO 9. 4E+07 3.0E+03 1.2E+08 PAGEAl-24 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-5 UNITS 2&3 Page 4 of 4 DOSE PARAMETER R(I) FOR SECTOR 'B' PATHWAY: DEER CONSUMER/HUNTERB3 DISTANCE: 3.8 MILES X/Q 6.8E-08 SEC/(M**3) D/Q 5.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 2.8E+Ol O.OE+OO 2.3E+Ol l.8E+Ol 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 0. OE+oO 1.0E+05 2.0E+02 2.5E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 0.0E+OO 1.4E+06 l.9E+04 2.2E+07 co 57 O.OE+OO 0.0E+OO O.OE+OO 4.6E+06 0. OE+oO 8.0E+06 4.4E+02 1.8E+07 co 58 O.OE+OO 0.0E+OO 0.0E+OO 9.6E+06 O.OE+OO 1.9E+07 1.3E+04 4.2E+07 co 60 0.0E+OO O.OE+OO O.OE+OO 3.6E+07 0.0E+OO 7.2E+07 8.3E+04 4.3E+08 SR 89 O.OE+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 1.9E+04 3.1E+07 SR 90 0.0E+OO O.OE+OO O.OE+OO l.OE+09 0.0E+OO 8.0E+08 1.3E+05 1. 2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO 1.1E+08 2.5E+04 2.0E+08 NB 95 0.0E+OO O.OE+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 7.0E+03 8.2E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 0. OE+oO 7.5E+08 7.0E+03 1.3E+09 TE 129M O.OE+OO 0.0E+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 1.7E+04 5.3E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO 1.4E+08 0. OE+oO 1. 2E+08 1.4E+03 2.4E+08 cs 136 0. OE+oO 0.0E+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 l.7E+02 7.5E+06 cs 137 O.OE+OO 0.0E+OO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 l.OE+03 2.6E+08 BA 140 O.OE+OO O.OE+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 1.8E+04 7.1E+06 CE 141 0.0E+OO O.OE+OO 0. OE+oO l.5E+06 O.OE+OO 2.4E+06 5.0E+03 4.0E+06 CE 144 O.OE+OO O.OE+OO 0. OE+oO l.8E+07 O.OE+OO 2.9E+07 1.1E+05 4.8E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 1.7E+05 5.9E+08 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.6E+03 l.7E+04 I 133 0.0E+OO O.OE+OO O.OE+OO 1. 6E+Ol 0. OE+oO 8.6E+00 3.0E+04 3.4E+04 I 134 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 4.1E+02 6.3E+03 I 135 O.OE+OO O.OE+OO O.OE+OO l. lE-15 0. OE+oO 6.3E-16 6.2E+03 3.5E+04 UN-ID* O.OE+OO O.OE+OO O.OE+OO 1.1E+08 0.0E+OO 9.4E+07 l.2E+04 1.3E+08 PAGEAl-25 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-6 UNITS 2&3 Page 1 of 6 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: SEWAGE TREAT.FACILITY DISTANCE: 2.2 MILES X/Q 1.3E-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+OO 0.0E+OO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO 2.9E+02 O.OE+OO CR 51 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO 3.3E+03 l.1E+06 MN 54 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0. 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 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 2.1E+05 8.7E+07 co 60 0.0E+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 0.0E+OO 3.2E+05 4.9E+03 SR 90 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.2E+06 0.0E+OO ZR 95 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 4.0E+05 5.7E+07 NB 95 0.0E+OO 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 1.2E+05 3.1E+07 RU 103 O.OE+OO O.OE+OO 0. OE+oO 0. OE+oO 0.0E+OO O.OE+OO 1.2E+05 2.5E+07 TE 129M O.OE+OO O.OE+OO 0. 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 l.6E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 2.7E+03 3. 4E+07 cs 137 O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 0. OE+oO O.OE+OO 1.7E+04 2.3E+09 BA 140 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.9E+05 4.7E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 8.3E+04 3.1E+06 CE 144 0. OE+oO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO l.8E+06 l.6E+07 I 131 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+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 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+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 l.7E+08 PAGEAl-26 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-6 UNITS 2&3 Page 2 of 6 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: CAMP SAN ONOFRE FR.STN DISTANCE: 2.4 MILES X/Q l.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** O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 5.7E+02 0. OE+oO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 6.5E+03 2.1E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 6.4E+05 6.3E+08 co 57 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 1.4E+04 l.6E+08 co 58 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.2E+05 l.7E+08 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.7E+06 9.8E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 6.4E+05 9.8E+03 SR 90 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 4.4E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 8.0E+05 1.1E+08 NB 95 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.3E+05 6.2E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 2.3E+05 4.9E+07 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.6E+05 8.9E+06 cs 134 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0. OE+oO 4.4E+04 3.1E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.5E+03 6.8E+07 cs 137 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.4E+04 4.7E+09 BA 140 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 5.8E+05 9.3E+06 CE 141 0.0E+OO 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.6E+05 6.2E+06 CE 144 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.5E+06 3.2E+07 I 131 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.4E+06 7.8E+06 I 132 O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 5.2E+04 5.6E+05 I 133 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 9.8E+05 1.1E+06 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 1.4E+04 2.0E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.0E+05 1.1E+06 UN-ID* 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 3.9E+05 3.4E+08 PAGEAl-27 S0123-0DCM-A Revision 9 09/2015

l TABLE 1-6 UNITS 2&3 Page 3 of 6 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+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 3E+03 O.OE+OO CR 51 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 0.0E+OO 1.4E+04 4.7E+06 MN 54 O.OE+OO 0. OE+oO O.OE+OO 0. OE+oO 0.0E+OO O.OE+OO 1.4E+06 1.4E+09 co 57 0. OE+oO 0. OE+oO O.OE+OO 0. OE+oO 0.0E+OO O.OE+OO 3.1E+04 3.4E+08 co 58 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0. 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 0. OE+oO 6.0E+06 2.2E+10 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 0.0E+OO 0.0E+OO 0.0E+OO O.OE+OO 9.6E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 1.8E+06 2.5E+08 NB 95 O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO 0.0E+OO O.OE+OO 5.0E+05 l.4E+08 RU 103 0. OE+oO 0. OE+oO O.OE+OO 0. OE+oO 0. OE+oO O.OE+OO 5.0E+05 1.1E+08 TE 129M 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 1. 2E+06 2.0E+07 cs 134 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 9.8E+04 6.8E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 2E+04 l.5E+08 cs 137 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 7.5E+04 1.0E+lO BA 140 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.3E+06 2.1E+07 CE 141 O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 3.6E+05 l.4E+07 CE 144 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 0. OE+oO 7.8E+06 7.0E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 1. 2E+07 l.7E+07 I 132 0. OE+oO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO l.1E+05 1. 2E+06 I 133 0. 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 0. OE+oO 0. 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 0. OE+oO O.OE+OO 0. OE+oO 8.6E+05 7.5E+08 PAGEAl-28 S0123-0DCM-A Revision 9 09/2015

TABLE 1-6 UNITS 2&3 Page 4 of 6 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: CAMP SAN ONOFRE 524101 DISTANCE: 2.8 MILES X/Q 8.7E-08 SEC/(M**3) D/Q 7.8E-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+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 1. 4E+04 4.7E+06 MN 54 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 1. 4E+06 1.4E+09 co 57 0.0E+OO 0. OE+oO O.OE+OO O.OE+OO 0. OE+oO 0.0E+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 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 6.0E+06 2.2E+l0 SR 89 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO l.4E+06 2.2E+04 SR 90 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 9.6E+06 0. OE+oO ZR 95 O.OE+OO O.OE+OO 0. 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 0. OE+oO O.OE+OO 0.0E+OO O.OE+OO 5.0E+05 l.4E+08 RU 103 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.0E+05 1.1E+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 0. OE+oO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO 9.8E+04 6.8E+09 cs 136 0. OE+oO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO 1. 2E+04 l.5E+08 cs 137 0.0E+OO O.OE+OO 0. OE+oO 0.0E+OO O.OE+OO O.OE+OO 7.5E+04 1. OE+lO BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 1.3E+06 2.1E+07 CE 141 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO 3.6E+05 l.4E+07 CE 144 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 0. OE+oO 7.8E+06 7.0E+07 I 131 O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO 1.2E+07 l.7E+07 I 132 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO l.1E+05 l.2E+06 I 133 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 0.0E+OO 2.2E+06 2.4E+06 I 134 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.0E+04 4.5E+05 I 135 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 0. 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 PAGEAl-29 S0123-0DCM-A Revision 9 09/2015

TABLE 1-6 UNITS 2&3 Page 5 of 6 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: 3.0 MILES X/Q 7.BE-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+OO O.OE+OO O.OE+OO 2.8E+Ol 0.0E+OO 2.3E+Ol 2.8E+Ol 3.9E+Ol CR 51 0.0E+OO O.OE+OO 0.0E+OO 5.0E+04 O.OE+OO 1.0E+05 3.2E+02 2.9E+05 MN 54 0.0E+OO O.OE+OO 0.0E+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 1.9E+07 2.1E+04 4.5E+07 co 60 0.0E+OO O.OE+OO 0.0E+OO 3.6E+07 O.OE+OO 7.2E+07 l.3E+05 6.2E+08 SR 89 0.0E+OO O.OE+OO O.OE+OO 4.9E+07 0. OE+oO 2.6E+07 3.1E+04 3.1E+07 SR 90 0.0E+OO O.OE+OO 0.0E+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 0.0E+OO 1.1E+08 4.0E+04 2.0E+08 NB 95 0.0E+OO O.OE+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 l.1E+04 8.2E+08 RU 103 0.0E+OO O.OE+OO O.OE+OO 4.2E+08 0.0E+OO 7.5E+08 l.1E+04 l.3E+09 TE 129M O.OE+OO 0.0E+OO 0.0E+OO 5.9E+08 O.OE+OO 4.5E+08 2.8E+04 5.3E+08 cs 134 0. OE+oO O.OE+OO O.OE+OO 1. 4E+08

  • O.OE+OO 1. 2E+08 2.2E+03 3.0E+08 cs 136 0. OE+oO 0.0E+OO 0.0E+OO 5.1E+06 O.OE+OO 4.2E+06 2.7E+02 8.8E+06 cs 137 0. OE+oO O.OE+OO O.OE+OO 1. 2E+08 0.0E+OO 9.3E+07 1.7E+03 3.5E+08 BA 140 0. OE+oO O.OE+OO O.OE+OO 5.0E+06 0.0E+OO 4.2E+06 2.8E+04 7.2E+06 CE 141 0. OE+oO O.OE+OO O.OE+OO l.5E+06 O.OE+OO 2.4E+06 8.1E+03 4.1E+06 CE 144 0. OE+oO O.OE+OO O.OE+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 0. OE+oO 4.3E+08 2.7E+05 5.9E+08 I 132 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.6E+03 2.8E+04 I 133 0.0E+OO O.OE+OO O.OE+OO l.6E+Ol O.OE+OO 8.6E+OO 4.8E+04 5.5E+04 I 134 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.7E+02 l.OE+04 I 135 0.0E+OO O.OE+OO O.OE+OO l. lE-15 0.0E+OO 6.3E-16 1.0E+04 5.6E+04 UN-ID* 0.0E+OO 0. OE+oO O.OE+OO 1.1E+08 0.0E+OO 9.4E+07 l.9E+04 1.4E+08 PAGE Al-30 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-6 UNITS 2&3 Page 6 of 6 DOSE PARAMETER R(I) FOR SECTOR 'C' PATHWAY: DEER CONSUMER/HUNTERC2 DISTANCE: 3.2 MILES X/Q 7.2E-08 SEC/(M**3) D/Q 6.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 2.8E+Ol O.OE+OO 2.3E+Ol 4.4E+00 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 5.0E+Ol 2.1E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 O.OE+OO 1.4E+06 4.9E+03 7.5E+06 co 57 O.OE+OO 0. OE+oO O.OE+OO 4.6E+06 0.0E+OO 8.0E+06 l.1E+02 1.5E+07 co 58 0.0E+OO 0. OE+oO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 3.2E+03 3.8E+07 co 60 O.OE+OO 0.0E+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 2.1E+04 2.1E+08 SR 89 O.OE+OO 0. OE+oO O.OE+OO 4.9E+07 0.0E+OO 2.6E+07 4.9E+03 3.1E+07 SR 90 O.OE+OO 0. OE+oO O.OE+OO l.OE+09 O.OE+OO 8.0E+08 3.4E+04 1.2E+09 ZR 95 O.OE+OO O.OE+OO 0.0E+OO 6.2E+07 O.OE+OO l.1E+08 6.2E+03 1.9E+08 NB 95 O.OE+OO 0. OE+oO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 1. 8E+03 8.lE+OB RU 103 0.0E+OO 0. OE+oO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 1. 8E+03 l.3E+09 TE 129M O.OE+OO 0. OE+oO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 4.3E+03 5.3E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO 1.4E+08 O.OE+OO l.2E+08 3. 4E+02 1.7E+08 cs 136 O.OE+OO 0. OE+oO 0.0E+OO 5.1E+06 O.OE+OO 4.2E+06 4.2E+Ol 5.9E+06 cs 137 O.OE+OO 0. OE+oO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 2.6E+02 l.5E+08 BA 140 O.OE+OO 0. OE+oO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 4.5E+03 6.9E+06 CE 141 O.OE+OO 0. OE+oO O.OE+OO 1.5E+06 O.OE+OO 2.4E+06 1. 3E+03 3.9E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO 1.8E+07 O.OE+OO 2.9E+07 2.7E+04 4.7E+07 I 131 O.OE+OO O.OE+OO 0.0E+OO 6.5E+08 0.0E+OO 4.3E+08 4.2E+04 5.9E+08 I 132 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.0E+02 4.3E+03 I 133 O.OE+OO 0.0E+OO O.OE+OO l.6E+Ol O.OE+OO 8.6E+OO 7.5E+03 .8. 6E+03 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.0E+02 l.6E+03 I 135 O.OE+OO 0. OE+oO O.OE+OO l.lE-15 0.0E+OO 6.3E-16 l.6E+03 8.8E+03 UN-ID* O.OE+OO O.OE+OO O.OE+OO 1.1E+08 O.OE+OO 9.4E+07 3.0E+03 l.2E+08 PAGE Al-31 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-7 UNITS 2&3 Page 1 of 3 DOSE PARAMETER R(I) FOR SECTOR 'D' PATHWAY: DEER CONSUMER/HUNTER DISTANCE: .8 MILES X/Q 4.SE-07 SEC/(M**3) D/Q 6.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** O.OE+OO O.OE+OO O.OE+OO 2.8E+Ol O.OE+OO 2.3E+Ol 2.8E+Ol 3.9E+Ol CR 51 0.0E+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 1. 4E+06 3.1E+04 3.4E+07 co 57 0.0E+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 7.0E+02 2.1E+07 co 58 0.0E+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO 1.9E+07 2.1E+04 4.5E+07 co 60 0.0E+OO O.OE+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 1.3E+05 6.2E+08 SR 89 0.0E+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 3.1E+04 3.1E+07 SR 90 0.0E+OO 0.0E+OO O.OE+OO 1.0E+09 O.OE+OO 8.0E+08 2.2E+05 1.2E+09 ZR 95 0.0E+OO O.OE+OO O.OE+OO 6.2E+.07 O.OE+OO 1. 1E+08 4.0E+04 2.0E+08 NB 95 0.0E+OO O.OE+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 1.1E+04 8.2E+08 RU 103 0.0E+OO O.OE+OO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 1.1E+04 1.3E+09 TE 129M 0.0E+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 1.2E+08 2.2E+03 3.0E+08 cs 136 0.0E+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 2.7E+02 8.8E+06 cs 137 0.0E+OO O.OE+OO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 l.7E+03 3.5E+08 BA 140 0.0E+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 O.OE+OO 2.4E+06 8.1E+03 4.1E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO l.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 O.OE+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 O.OE+OO 2.6E+03 2.8E+04 I 133 0.0E+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 l.OE+04 I 135 O.OE+OO O.OE+OO O.OE+OO 1. lE-15 O.OE+OO 6.3E-16 l.OE+04 5.6E+04 UN-ID* 0.0E+OO O.OE+OO O.OE+OO l .1E+08 O.OE+OO 9.4E+07 1.9E+04 l.4E+08 PAGEAl-32 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-7 UNITS 2&3 Page 2 of 3 DOSE PARAMETER R(I) FOR SECTOR 'D' PATHWAY: DEER CONSUMER/HUNTERD2 DISTANCE: 2.2 MILES X/Q 1.lE-07 SEC/(M**3) D/Q 1. 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** O.OE+OO 0.0E+OO O.OE+OO 2.8E+Ol O.OE+OO 2.3E+Ol 4.lE+Ol 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 4.7E+02 3.4E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 0.0E+OO l.4E+06 4.5E+04 4.8E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 1.0E+03 2.5E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO 1.9E+07 3.0E+04 4.9E+07 co 60 O.OE+OO 0.0E+OO O.OE+OO 3.6E+07 0.0E+OO 7.2E+07 1.9E+05 8.3E+08 SR 89 O.OE+OO 0.0E+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 4.5E+04 3.1E+07 SR 90 O.OE+OO O.OE+OO O.OE+OO 1.0E+09 O.OE+OO 8.0E+08 3.1E+05 1.2E+09 ZR 95 0.0E+OO O.OE+OO O.OE+OO 6.2E+07 0.0E+OO 1.1E+08 5.7E+04 2.0E+08 NB 95 O.OE+OO O.OE+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 1.6E+04 8.2E+08 RU 103 O.OE+OO O.OE+OO 0.0E+OO 4.2E+08 0. OE+oO 7.5E+08 l.6E+04 l.3E+09 TE 129M 0. OE+oO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 4.0E+04 5.3E+08 cs 134 O.OE+OO O.OE+OO O.OE+OO l.4E+08 O.OE+OO 1.2E+08 3.2E+03 3.7E+08 cs 136 O.OE+OO O.OE+OO O.OE+OO 5.1E+06 0.0E+OO 4.2E+06 3.9E+02 l.OE+07 cs 137 O.OE+OO 0.0E+OO O.OE+OO 1.2E+08 O.OE+OO 9.3E+07 2.4E+03 4.5E+08 BA 140 O.OE+OO 0.0E+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 4.1E+04 7.5E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO l.5E+06 O.OE+OO 2.4E+06 l.2E+04 4.3E+06 CE 144 O.OE+OO O.OE+OO 0.0E+OO 1.8E+07 O.OE+OO 2.9E+07 2.5E+05 4.9E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 6.5E+08 0.0E+OO 4.3E+08 3.9E+05 5.9E+08 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 3.7E+03 4.0E+04 I 133 0. OE+oO 0.0E+OO O.OE+OO 1. 6E+Ol O.OE+OO 8.6E+OO 7.0E+04 8.0E+04 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 9.7E+02 1.5E+04 I 135 0. OE+oO 0.0E+OO O.OE+OO 1. lE-15 O.OE+OO 6.3E-16 1. 5E+04 8.2E+04 UN-ID* 0. OE+oO O.OE+OO O.OE+OO 1.1E+08 O.OE+OO 9.4E+07 2.8E+04 1.5E+08 PAGE Al-33 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-7 UNITS 2&3 Page 3 of 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+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO l.3E+03 0. OE+oO CR 51 0.0E+OO O.OE+OO O.OE+.00 0.0E+OO 0.0E+OO O.OE+OO l.4E+04 4.7E+06 MN 54 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO l.4E+06 l.4E+09 co 57 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.1E+04 3.4E+08 co 58 0.0E+OO O.OE+OO 0.0E+OO 0.0E+OO 0.0E+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 0.0E+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 0.0E+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 0.0E+OO 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 5.0E+05 1. 1E+08 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.2E+06 2.0E+07 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 9.8E+04 6.8E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.2E+04 1.5E+08 cs 137 0.0E+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 0. OE+oO 7.5E+04 1. OE+lO BA 140 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO l.3E+06 2. 1E+07 CE 141 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.6E+05 l.4E+07 CE 144 O.OE+OO O.OE+OO 0.0E+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 l.2E+07 l.7E+07 I 132 0.0E+OO O.OE+OO O.OE+OO 0. OE+OO

  • O.OE+OO . 0. OE+oO l .1E+05 l.2E+06 I 133 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 2.4E+06 I 134 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 3.0E+04 4.5E+05 I 135 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 4.5E+05 2.5E+06 UN-ID* 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 8.6E+05 7.5E+08 PAGEAl-34 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-8 UNITS 2&3 Page 1 of 6 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 2.8E+Ol O.OE+OO 2.3E+Ol 2.8E+Ol 3.9E+Ol CR 51 0. OE+oO O.OE+OO O.OE+OO 5.0E+04 O.OE+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 0.0E+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 0.0E+OO O.OE+OO O.OE+OO 3.6E+07 O.OE+OO 7.2E+07 1.3E+05 6.2E+08 SR 89 0.0E+OO O.OE+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 3.1E+04 3.1E+07 SR 90 0.0E+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 0.0E+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. OE+oO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 l.1E+04 8.2E+08 RU 103 0.0E+OO 0. OE+oO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 l.1E+04 1.3E+09 TE 129M 0.0E+OO O.OE+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 2.8E+04 5.3E+08 cs 134 0.0E+OO O.OE+OO O.OE+OO l.4E+08 O.OE+OO 1.2E+08 2.2E+03 3.0E+08 cs 136 0. 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 0. OE+oO O.OE+OO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 l.7E+03 3.5E+08 BA 140 O.OE+OO 0.0E+OO O.OE+OO 5.0E+06 0.0E+OO 4.2E+06 2.8E+04 7.2E+06 CE 141 0.0E+OO O.OE+OO 0.0E+OO 1.5E+06 O.OE+OO 2.4E+06 8.1E+03 4. 1E+06 CE 144 0.0E+OO O.OE+OO O.OE+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 O.OE+OO 4.3E+08 2.7E+05 5.9E+08 I 132 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.6E+03 2.8E+04 I 133 0.0E+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 0. OE+oO O.OE+OO 0. OE+oO O.OE+OO 0. OE+oO 6.7E+02 1.0E+04 I 135 O.OE+OO 0. 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 0. OE+oO O.OE+OO 1.1E+08 0.0E+OO 9.4E+07 1.9E+04 1.4E+08 PAGEAl-35 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-8 UNITS 2&3 Page 2 of 6 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: DEER CONSUMER/HUNTERE2 DISTANCE: 1.0 MILES X/Q 5.8E-07 SEC/(M**3) D/Q 8.4E-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 0.0E+OO 2.8E+Ol 0. OE+oO 2.3E+Ol 4.3E+Ol 3.9E+Ol CR 51 O.OE+OO 0.0E+OO 0.0E+OO 5.0E+04 0.0E+OO l.OE+05 4.9E+02 3.5E+05 MN 54 O.OE+OO O.OE+OO 0.0E+OO 7.7E+05 0.0E+OO l.4E+06 4.8E+04 5.0E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4.6E+06 0. OE+oO 8.0E+06 l.1E+03 2.5E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 0. OE+oO l.9E+07 3.2E+04 5.0E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 3.6E+07 0.0E+OO 7.2E+07 2.0E+05 8.7E+08 SR 89 O.OE+OO 0.0E+OO 0.0E+OO 4.9E+07 0.0E+OO 2.6E+07 4.8E+04 3.1E+07 SR 90 O.OE+OO 0.0E+OO O.OE+OO l.OE+09 0. OE+oO 8.0E+08 3.3E+05 l.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 0.0E+OO l.1E+08 6.0E+04 2.0E+08 NB 95 O.OE+OO 0.0E+OO O.OE+OO 2.3E+08 0. OE+oO 4.5E+08 l.7E+04 8.2E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 0. OE+oO 7.5E+08 l.7E+04 1. 3E+09 TE 129M O.OE+OO 0.0E+OO 0.0E+OO 5.9E+08 O.OE+OO 4.5E+08 4.2E+04 5.3E+08 cs 134 O.OE+OO 0. OE+oO O.OE+OO l.4E+08 0. OE+oO l.2E+08 3.3E+03 3.8E+08 cs 136 O.OE+OO 0. OE+oO O.OE+OO 5.1E+06 0. OE+oO 4.2E+06 4.1E+02 l.1E+07 cs 137 0.0E+OO 0. OE+oO O.OE+OO 1. 2E+08 0. OE+oO 9.3E+07 2.6E+03 4.7E+08 BA 140 0.0E+OO 0. OE+oO 0.0E+OO 5.0E+06 0. OE+oO 4.2E+06 4.3E+04 7.5E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO l.5E+06 0. OE+oO 2.4E+06 l.2E+04 4.3E+06 CE 144 0.0E+OO 0.0E+OO O.OE+OO l.8E+07 O.OE+OO 2.9E+07 2.6E+05 4.9E+07 I 131 0.0E+OO 0.0E+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 4.1E+05 5.9E+08 I 132 O.OE+OO 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.9E+03 4.2E+04 I 133 O.OE+OO O.OE+OO O.OE+OO l.6E+Ol O.OE+OO 8.6E+OO 7.3E+04 8.3E+04 I 134 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO l.OE+03 l.5E+04 I 135 0.0E+OO O.OE+OO O.OE+OO 1. lE-15 O.OE+OO 6.3E-16 l.5E+04 8.6E+04 UN-ID* O.OE+OO 0.0E+OO O.OE+OO l.1E+08 O.OE+OO 9.4E+07 2.9E+04 l.5E+08 PAGE Al-36 SO 123-0DCM-A Revision 7 09-23-13

TABLE 1-8 UNITS 2&3 Page 3 of 6 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: DEER CONSUMER/HUNTERE3 DISTANCE: 1. 4 MILES X/Q 3.7E-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** 0.0E+OO O.OE+OO O.OE+OO 2.8E+Ol 0. OE+oO 2.3E+Ol 2.4E+Ol 3.9E+Ol CR 51 0.0E+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 2.8E+02 2.8E+05 MN 54 0.0E+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 0.0E+OO O.OE+OO 4.6E+06 0.0E+OO 8.0E+06 6.0E+02 2.0E+07 co 58 O.OE+OO 0.0E+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 1.8E+04 4.4E+07 co 60 0.0E+OO O.OE+OO 0.0E+OO 3.6E+07 O.OE+OO 7.2E+07 l.1E+05 5.5E+08 SR 89 O.OE+OO O.OE+OO 0.0E+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 1.0E+09 O.OE+OO 8.0E+08 1.8E+05 l.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO 1.1E+08 3.4E+04 2.0E+08 NB 95 0.0E+OO O.OE+OO 0.0E+OO 2.3E+08 O.OE+OO 4.5E+08 9.6E+03 8.2E+08 RU 103 0.0E+OO O.OE+OO O.OE+OO 4.2E+08 0. OE+oO 7.5E+08 9.6E+03 l.3E+09 TE 129M O.OE+OO O.OE+OO O.OE+OO 5.9E+08 0. OE+oO 4.5E+08 2.4E+04 5.3E+08 cs 134 0.0E+OO O.OE+OO O.OE+OO l.4E+08 0. OE+oO 1.2E+08 1. 9E+03 2.8E+08 cs 136 0.0E+OO O.OE+OO O.OE+OO 5.1E+06 O.OE+OO 4.2E+06 2.3E+02 8.3E+06 cs 137 0.0E+OO O.OE+OO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 l.4E+03 3.1E+08 BA 140 0.0E+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 0.0E+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. 8E+07 O.OE+OO 2.9E+07 1.5E+05 4.8E+07 I 131 0.0E+OO O.OE+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 2.3E+05 5.9E+08 I 132 0.0E+QO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+03 2.4E+04 I 133 0.0E+OO 0.0E+OO O.OE+OO 1.6E+Ol O.OE+OO 8.6E+OO 4.1E+04 4.7E+04 I 134 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 5.7E+02 8.6E+03 I 135 0.0E+OO O.OE+OO O.OE+OO 1. lE-15 O.OE+OO 6.3E-16 8.6E+03 4.8E+04 UN-ID* 0. OE+oO O.OE+OO O.OE+OO 1.1E+08 O.OE+OO 9.4E+07 l.7E+04 1.4E+08 PAGEAl-37 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-8 UNITS 2&3 Page 4 of 6 DOSE PARAMETER R(I) FOR SECTOR 'E' PATHWAY: DEER CONSUMER/HUNTERE4 DISTANCE: 2.6 MILES X/Q l.4E-07 SEC/ (M**3) D/Q 1.6E-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 0.0E+OO 2.3E+Ol 5.lE+Ol 3.9E+Ol CR 51 O.OE+OO 0.0E+OO O.OE+OO 5.0E+04 0.0E+OO l.OE+05 5.8E+02 3.8E+05 MN 54 O.OE+OO 0.0E+OO O.OE+OO 7.7E+05 0.0E+OO l.4E+06 5.6E+04 5.8E+07 co 57 0.0E+OO O.OE+OO O.OE+OO 4.6E+06 O.OE+OO 8.0E+06 l.3E+03 2.7E+07 co 58 O.OE+OO 0.0E+OO O.OE+OO 9.6E+06 O.OE+OO 1.9E+07 3.7E+04 5.2E+07 co 60 O.OE+OO O.OE+OO 0.0E+OO 3.6E+07 O.OE+OO 7.2E+07 2.4E+05 1.0E+09 SR 89 O.OE+OO O.OE+OO 0.0E+OO 4.9E+07 O.OE+OO 2.6E+07 5.6E+04 3.1E+07 SR 90 O.OE+OO O.OE+OO 0.0E+OO 1.0E+09 O.OE+OO 8.0E+08 3.9E+05 1.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO 1.1E+08 7.1E+04 2.0E+08 NB 95 O.OE+OO 0.0E+OO O.OE+OO 2.3E+08 0.0E+OO 4.5E+08 2.0E+04 8.2E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 2.0E+04 l.3E+09 TE 129M O.OE+OO O.OE+OO O.OE+OO 5.9E+08 0. OE+oO 4.5E+08 5.0E+04 5.3E+08 cs 134 O.OE+OO 0.0E+OO O.OE+OO l.4E+08 O.OE+OO 1. 2E+08 3.9E+03 4.2E+08 cs 136 O.OE+OO O.OE+OO O.OE+OO 5.1E+06 0.0E+OO *4.2E+06 4.8E+02 1.1E+07 cs 137 O.OE+OO 0.0E+OO O.OE+OO l.2E+08 O.OE+OO 9.3E+07 3.0E+03 5.3E+08 BA 140 O.OE+OO 0.0E+OO O.OE+OO 5.0E+06 O.OE+OO 4.2E+06 5.1E+04 7.6E+06 CE 141 0.0E+OO O.OE+OO O.OE+OO 1.5E+06 O.OE+OO 2.4E+06 l.5E+04 4.4E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO l.8E+07 O.OE+OO 2.9E+07 3.1E+05 5.0E+07 I 131 O.OE+OO 0.0E+OO O.OE+OO 6.5E+08 O.OE+OO 4.3E+08 4.8E+05 5.9E+08 I 132 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 4.6E+03 5.0E+04 I 133 O.OE+OO O.OE+OO 0.0E+OO 1.6E+Ol 0.0E+OO 8.6E+OO 8.7E+04 9.9E+04 I 134 0. OE+oO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 1. 2E+03 l.8E+04 I 135 O.OE+OO O.OE+OO O.OE+OO 1.lE-15 0.0E+OO 6.3E-16 l.8E+04 1.0E+05 UN-ID* O.OE+OO 0. OE+oO O.OE+OO l.1E+08 0.0E+OO 9.4E+07 3.5E+04 1.5E+08 PAGE Al-38 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-8 UNITS 2&3 Page 5 of 6 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 0.0E+OO O.OE+OO 3.6E+02 0.0E+OO CR 51 0. 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 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 4.0E+05 3.9E+08 co 57 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 9.0E+03 9.8E+07 co 58 O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO 0.0E+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 0. 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 0. OE+oO O.OE+OO O.OE+OO 2.7E+06 O.OE+OO ZR 95 0.0E+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 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 3.5E+05 5.6E+06 cs 134 O.OE+OO O.OE+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 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.4E+03 4.3E+07 cs 137 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+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 0.0E+OO 0.0E+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 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 0.0E+OO 3.3E+04 3.5E+05 I 133 O.OE+OO O.OE+OO O.OE+OO 0.0E+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 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* 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.5E+05 2.1E+08 PAGE Al-39 S0123-0DCM-A Revision 9 09/2015 L

TABLE 1-8 UNITS 2&3 Page 6 of 6 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** O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 1.3E+03 O.OE+OO CR 51 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.4E+04 4.7E+06 MN 54 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 1.4E+06 1.4E+09 co 57 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 0. 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 SR 89 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0. OE+oO 0.0E+OO 1.4E+06 2.2E+04 SR 90 O.OE+OO O*. OE+OO 0.0E+OO O.OE+OO 0. OE+oO 0.0E+OO 9.6E+06 0.0E+OO ZR 95 0.0E+OO 0.0E+OO O.OE+OO 0. OE+oO 0. OE+oO O.OE+OO l.8E+06 2.5E+08 NB 95 0. OE+oO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO 5.0E+05 1.4E+08 RU 103 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 5.0E+05 1.1E+08 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 1.2E+06 2.0E+07 cs 134 O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO 0. OE+oO 0.0E+OO 9.8E+04 6.8E+09 cs 136 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO 1.2E+04 l.5E+08 cs 137 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO 7.5E+04 1.0E+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 O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+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 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1. 2E+07 l.7E+07 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO l.1E+05 1. 2E+06 I 133 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+06 2.4E+06 I 134 0.0E+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 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 4.5E+05 2.5E+06 UN-ID* O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 8.6E+05 7.5E+08 PAGEAl-40 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-9 UNITS 2&3 Page 1 of 5 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: SO ST. PK./GUARD SHACK DISTANCE: .8 MILES X/Q 9.6E-07 SEC/(M**3) D/Q 8.4E~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 0.0E+OO O.OE+OO 2.2E+02 O.OE+OO CR 51 0. OE+oO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.5E+03 8.0E+05 MN 54 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.4E+05 2.4E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 5.4E+03 5.9E+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.6E+05 6.5E+07 co 60 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.OE+06 3.7E+09 SR 89 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.4E+05 3.7E+03 SR 90 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.6E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 3.0E+05 4.3E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.6E+04 2.3E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.6E+04 l.9E+07 TE 129M O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.1E+05 3.4E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.7E+04 1.2E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.1E+03 2.6E+07 cs 137 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO l.3E+04 l.8E+09 BA 140 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+05 3.5E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.2E+04 2.3E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.3E+06 l.2E+07 I 131 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.0E+06 2.9E+06 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.0E+04 2.1E+05 I 133 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 3.7E+05 4.2E+05 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 5.1E+03 7.7E+04 I 135 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 7.7E+04 4.3E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 1.5E+05 l.3E+08 PAGE Al-41 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-9 UNITS 2&3 Page 2 of 5 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.BE-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+OO 0.0E+OO O.OE+OO 2.8E+Ol O.OE+OO 2.3E+Ol 2.4E+Ol 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 O.OE+OO 1.0E+05 2.8E+02 2.8E+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 0.0E+OO O.OE+OO 4.6E+06 0. OE+oO 8.0E+06 6.0E+02 2.0E+07 co 58 0.0E+OO 0.0E+OO O.OE+OO 9.6E+06 0. OE+oO 1.9E+07 1.8E+04 4.4E+07 co 60 O.OE+OO O.OE+OO O.OE+OO 3.6E+07 0.0E+OO 7.2E+07 1.1E+05 5.5E+08 SR 89 O.OE+OO O.OE+OO 0.0E+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 1.0E+09 O.OE+OO 8.0E+08 1.8E+05 1.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO l.1E+08 3.4E+04 2.0E+08 NB 95 O.OE+OO 0. OE+oO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 9.6E+03 8.2E+08 RU 103 O.OE+OO O.OE+OO O.OE+OO 4.2E+08 0. OE+oO 7.5E+08 9.6E+03 l.3E+09 TE 129M 0. OE+oO O.OE+OO O.OE+OO 5.9E+08 0. OE+oO 4.5E+08 2.4E+04 5.3E+08 cs 134 0. OE+oO O.OE+OO O.OE+OO 1. 4E+08 0. OE+oO 1.2E+08 l.9E+03 2.8E+08 cs 136 O.OE+OO O.OE+OO O.OE+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 l.2E+08 0.0E+OO 9.3E+07 1.4E+03 3.1E+08 BA 140 O.OE+OO O.OE+OO O.OE+OO 5.0E+06 0.0E+OO 4.2E+06 2.4E+04 7.2E+06 CE 141 0.0E+OO 0. OE+oO O.OE+OO 1.5E+06 0. OE+oO 2.4E+06 6.9E+03 4.1E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO l.8E+07 0. OE+oO 2.9E+07 1.5E+05 4.8E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 6.5E+08 0. OE+oO 4.3E+08 2.3E+05 5.9E+08 I 132 0.0E+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 0. OE+oO 5.7E+02 8.6E+03 I 135 O.OE+OO O.OE+OO 0.0E+OO 1.lE-15 0. OE+oO 6.3E-16 8.6E+03 4.8E+04 UN-ID* O.OE+OO O.OE+OO 0.0E+OO 1.1E+08 O.OE+OO 9.4E+07 1.7E+04 1.4E+08 PAGEAl-42 SO 123-0DCM-A Revision 7 09-23-13

TABLE 1-9 UNITS 2&3 Page 3 of 5 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 l.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. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.5E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.9E+03 l.3E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 3.8E+05 3.8E+08 co 57 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 8.6E+03 9.4E+07 co 58 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.5E+05 l.OE+08 co 60 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.6E+06 5.9E+09 SR 89 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.8E+05 5.9E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.6E+06 0. OE+oO ZR 95 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.8E+05 6.9E+07 NB 95 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.4E+05 3.7E+07 RU 103 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO l.4E+05 3.0E+07 TE 129M O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 0. OE+oO 3.4E+05 5.4E+06 cs 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.7E+04 1. 9E+09 cs 136 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 3.3E+03 4.1E+07 cs 137 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.1E+04 2.8E+09 BA 140 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 3.5E+05 5.6E+06 CE 141 O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 9.9E+04 3.7E+06 CE 144 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 2.1E+06 l.9E+07 I 131 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 3.3E+06 4.7E+06 I 132 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.1E+04 3.4E+05 I 133 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 5.9E+05 6.7E+05 I 134 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 8.2E+03 l.2E+05 I 135 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.2E+05 6.9E+05 UN-ID* 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 2.4E+05 2.0E+08 PAGEAl-43 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-9 UNITS 2&3 Page 4 of 5 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: HWY PATROL WEIGH STN DISTANCE: 2.1 MILES X/Q 2.2E-07 SEC/(M**3) D/Q l.6E-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. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.8E+02 O.OE+OO CR 51 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+03 1.0E+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.1E+05 3.1E+08 co 57 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 7.0E+03 7.7E+07 co 58 O.OE+OO O.OE+OO 0. OE+OO O.OE+OO 0.0E+OO O.OE+OO 2.1E+05 8.5E+07 co 60 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+oO O.OE+OO l.3E+06 4.8E+09 SR 89 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 3.1E+05 4.8E+03 SR 90 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 2.1E+06 0.0E+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO 4.0E+05 5.6E+07 NB 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 1.1E+05 3.1E+07 RU 103 0. OE+oO O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO 0. OE+oO l.1E+05 2.4E+07 TE 129M 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 2.8E+05 4.4E+06 cs 134 0. OE+oO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 2.2E+04 1.5E+09 cs 136 0. OE+oO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0. OE+oO 2.7E+03 3. 4E+07 cs 137 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 1.7E+04 2.3E+09 BA 140 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO 2.8E+05 4.6E+06 CE 141 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0.0E+OO O.OE+OO 8.1E+04 3.1E+06 CE 144 O.OE+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO O.OE+OO l.7E+06 l.6E+07 I 131 0.0E+OO O.OE+OO 0.0E+OO 0. OE+oO O.OE+OO 0.0E+OO 2.7E+06 3.8E+06 I 132 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0.0E+OO O.OE+OO 2.6E+04 2.8E+05 I 133 O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 0.0E+OO O.OE+OO 4.8E+05 5.5E+05 I 134 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.7E+03 1.0E+05 I 135 O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 1.0E+05 5.6E+05 UN-ID* O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 1.9E+05 l.7E+08 PAGEAl-44 S0123-0DCM-A Revision 9 09/2015

TABLE 1-9 UNITS 2&3 Page 5 of 5 DOSE PARAMETER R(I) FOR SECTOR 'F' PATHWAY: DEER CONSUMER/HUNTERF2 DISTANCE: 5.0 MILES X/Q 6.2E-08 SEC/(M**3) D/Q 3.3E-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** O.OE+OO O.OE+OO O.OE+OO 2.8E+Ol 0. OE+oO 2.3E+Ol 6.7E+Ol 3.9E+Ol CR 51 O.OE+OO O.OE+OO O.OE+OO 5.0E+04 0. OE+oO l.OE+05 7.6E+02 4.3E+05 MN 54 O.OE+OO O.OE+OO O.OE+OO 7.7E+05 O.OE+OO l.4E+06 7.4E+04 7.6E+07 co 57 O.OE+OO O.OE+OO O.OE+OO 4. 6E+O 6

  • O.OE+OO 8.0E+06 l.7E+03 3.2E+07 co 58 O.OE+OO O.OE+OO O.OE+OO 9.6E+06 O.OE+OO l.9E+07 4.9E+04 5.7E+07 co 60 O.OE+OO 0.0E+OO O.OE+OO
  • 3.6E+07 O.OE+OO 7.2E+07 3.1E+05 l.3E+09 SR 89 O.OE+OO 0.0E+OO O.OE+OO 4.9E+07 O.OE+OO 2.6E+07 7.4E+04 3.1E+07 SR 90 O.OE+OO 0.0E+OO O.OE+OO l.OE+09 O.OE+OO 8.0E+08 5.1E+05 l.2E+09 ZR 95 O.OE+OO O.OE+OO O.OE+OO 6.2E+07 O.OE+OO l.1E+08 9.3E+04 2.1E+08 NB 95 O.OE+(JO 0.0E+OO O.OE+OO 2.3E+08 O.OE+OO 4.5E+08 2.7E+04 8.2E+08 RU 103 0. OE+oO O.OE+OO O.OE+OO 4.2E+08 O.OE+OO 7.5E+08 2.7E+04 l.3E+09 TE 129M O.OE+OO 0.0E+OO O.OE+OO 5.9E+08 O.OE+OO 4.5E+08 6.5E+04 5.3E+08 cs 134 0. OE+oO O.OE+OO O.OE+OO l.4E+08 O.OE+OO 1. 2E+08 5.1E+03 5.1E+08 cs 136 0.0E+OO O.OE+OO O.OE+OO 5.1E+06 0. OE+oO 4.2E+06 6.3E+02 l.3E+07 cs 137 0. OE+oO O.OE+OO 0.0E+OO l.2E+08 O.OE+OO 9.3E+07 4.0E+03 6.6E+08 BA 140 0.0E+OO O.OE+OO 0.0E+OO 5.0E+06 0.0E+OO 4.2E+06 6.7E+04 7.9E+06 CE 141 O.OE+OO 0.0E+OO 0. OE+oO 1. 5E+06 O.OE+OO 2.4E+06 l.9E+04 4.6E+06 CE 144 O.OE+OO O.OE+OO 0. OE+oO 1. 8E+07 0.0E+OO 2.9E+07 4.1E+05 5.0E+07 I 131 O.OE+OO O.OE+OO 0. OE+oO 6.5E+08 O.OE+OO 4.3E+08 6.3E+05 5.9E+08 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 6.0E+03 6.5E+04 I 133 0. OE+oO 0.0E+OO O.OE+OO l.6E+Ol O.OE+oO 8.6E+OO 1. 1E+05 l.3E+05 I 134 0. OE+oO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO 0.0E+OO l.6E+03 2.4E+04 I 135 0. OE+oO O.OE+OO 0.0E+OO 1. lE-15 0. OE+oO 6.3E-16 2.4E+04 l.3E+05 UN-ID* O.OE+OO O.OE+OO 0.0E+OO l.1E+08 0. OE+oO 9.4E+07 4.6E+04 l.6E+08 PAGEAl-45 S0123-0DCM-A Revision 9 09/2015

TABLE 1-10 UNITS 2&3 Page 1 of 4 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. OE-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+Ol O.OE+OO 9.2E+Ol O.OE+OO 1.0E+02 0. OE+oO l.OE+02 O.OE+OO CR 51 l.1E+03 3.8E+05 l.4E+03 3.8E+05 1.7E+03 3.8E+05 1.2E+03 3.8E+05 MN 54 8.2E+04 1.1E+08 1.3E+05 1.1E+08 1.6E+05 l.1E+08 1. 2E+05 l.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 1.1E+05 3.1E+07 7.6E+04 3.1E+07 co 60 3.7E+05 l.8E+09 5.BE+05 1.BE+09 7.2E+05 l.8E+09 4.9E+05 1.8E+09 SR 89 l.7E+05 1. 8E+03 1.BE+05 1.BE+03 2.0E+05 1. 8E+03 l.2E+05 1.8E+03 SR 90 9.2E+05 0.0E+OO 1.2E+06 O.OE+OO 1.4E+06 O.OE+OO 7.9E+05 O.OE+OO ZR 95 1.4E+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 129M 1.4E+05 1. 6E+06 1.4E+05 1.6E+06 l.6E+05 l.6E+06 1.0E+05 l.6E+06 cs 134 6.5E+03 5.6E+08 9.9E+03 5.6E+OB l.2E+04 5.6E+08 8.0E+03 5.6E+08 cs\ 136 9.7E+02 l.2E+07 1.2E+03 l.2E+07 1.5E+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 1.4E+05 1.7E+06 1.7E+05 1.7E+06 1.0E+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 1.4E+06 l.2E+06 1.4E+06 9.8E+05 l.4E+06 I 132 1.4E+04 l.OE+05 l.6E+04 l.OE+05 l.2E+04 1. OE+05 9.4E+03 l.OE+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 1.0E+05 6.1E+07 7.1E+04 6.1E+07 PAGEAl-46 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-10 UNITS 2&3 Page 2 of 4 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: YMCA SURFCAMP/RES DISTANCE: 2.0 MILES X/Q 1.9E-07 SEC/(M**3) D/Q 8.0E-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 0.0E+OO 4.9E+Ol O.OE+OO 5.6E+Ol O.OE+OO 5.5E+Ol O.OE+OO CR 51 O.OE+OO O.OE+OO 7.4E+02 2.0E+05 9.2E+02 2.0E+05 6.3E+02 2.0E+05 MN 54 O.OE+OO O.OE+OO 6.9E+04 6.1E+07 8.7E+04 6.1E+07 6.1E+04 6 .1E+07 co 57 O.OE+OO O.OE+OO 5.8E+02 1.5E+07 l.4E+03 1. 5E+07 l.4E+03 1.5E+07 co 58 O.OE+OO O.OE+OO 4.8E+04 1.7E+07 5.9E+04 1.7E+07 4.1E+04 l.7E+07 co 60 O.OE+OO O.OE+OO 3.1E+05 9.4E+08 3.8E+05 9.4E+08 2.6E+05 9.4E+08 SR 89 O.OE+OO O.OE+OO 9.4E+04 9.5E+02 1.1E+05 9.5E+02 6.1E+04 9.5E+02 SR 90 O.OE+OO O.OE+OO 6.5E+05 O.OE+OO 7.2E+05 O.OE+OO 4.2E+05 O.OE+OO ZR 95 O.OE+OO O.OE+OO 9.8E+04 1.1E+07 1. 2E+05 1.1E+07 7.7E+04 1.1E+07 NB 95 O.OE+OO O.OE+OO 2.7E+04 6.0E+06 3.3E+04 6.0E+06 2.2E+04 6.0E+06 RU 103 O.OE+OO O.OE+OO 2.9E+04 4.8E+06 3.4E+04 4.8E+06 2.2E+04 4.8E+06 TE 129M O.OE+OO O.OE+OO 7.7E+04 8.6E+05 8.7E+04 8.6E+05 5.4E+04 8.6E+05 cs 134 O.OE+OO. O.OE+OO 5.3E+03 3.0E+08 6.4E+03 3.0E+08 4.3E+03 3.0E+08 cs 136 O.OE+OO O.OE+OO 6.4E+02 6.6E+06 7.8E+02 6.6E+06 5.3E+02 6.6E+06 cs 137 O.OE+OO O.OE+OO 4.6E+03 4.5E+08 5.3E+03 4.5E+08 3.3E+03 4.5E+08 BA 140 O.OE+OO O.OE+OO 7.6E+04 9.0E+05 8.9E+04 9.0E+05 5.6E+04 9.0E+05 CE 141 O.OE+OO O.OE+OO 2.4E+04 6.0E+05 2.7E+04 6.0E+05 1.6E+04 6.0E+05 CE 144 O.OE+OO O.OE+OO 5.2E+05 3.0E+06 5.9E+05 3.0E+06 3.4E+05 3.0E+06 I 131 O.OE+OO O.OE+OO 7.1E+05 7.5E+05 6.4E+05 7.5E+05 5.2E+05 7.5E+05 I 132 O.OE+OO O.OE+OO 8.5E+03 5.4E+04 6.6E+03 5.4E+04 5.0E+03 5.4E+04 I 133 O.OE+OO O.OE+OO 1.7E+05 1. 1E+05 1.3E+05 1.1E+05 9.4E+04 1.1E+05 I 134 O.OE+OO O.OE+OO 2.2E+03 2.0E+04 1.7E+03 2.0E+04 l.3E+03 2.0E+04 I 135 O.OE+OO O.OE+OO 3.5E+04 l.1E+05 2.7E+04 1.1E+05 2.0E+04 1.1E+05 UN-ID* O.OE+OO O.OE+OO 4.4E+04 3.3E+07 5.4E+04 3.3E+07 3.8E+04 3.3E+07 PAGEAl-47 SO 123-0DCM-A Revision 9 09/2015

TABLE 1-10 UNITS 2&3 Page 3 of 4 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: HWY PATROL WEIGH STN DISTANCE: 2.1 MILES X/Q 1.8E-07 SEC/(M**3) D/Q 7.SE-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 2.8E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 3.2E+03 l.OE+06 MN 54 O.OE+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 3.1E+05 3.1E+08 co 57 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO 7.0E+03 7.7E+07 co 58 0.0E+OO 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0. OE+oO 2.1E+05 8.5E+07 co 60 O.OE+OO O.OE+OO 0-. OE+OO O.OE+OO O.OE+OO O.OE+OO 1.3E+06 4.8E+09 SR 89 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 3*. 1E+05 4.8E+03 SR 90 O.OE+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 2.1E+06 O.OE+OO ZR 95 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 4.0E+OS 5.6E+07 NB 95 O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 1.1E+05 3.1E+07 RU 103 O.OE+OO 0. OE+oO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 1.1E+05 2.4E+07 TE 129M O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO 0.0E+OO 2.8E+05 4.4E+06 cs 134 0.0E+OO 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.2E+04 l.5E+09 cs 136 O.OE+OO 0. OE+oO O.OE+OO 0.0E+OO O.OE+OO 0. OE+oO 2.7E+03 3.4E+07 cs 137 O.OE+OO 0. OE+oO 0.0E+OO O.OE+OO 0. OE+oO O.OE+OO l.7E+04 2.3E+09 BA 140 O.OE+OO 0. OE+oO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 2.8E+05 4.6E+06 CE 141 0.0E+OO 0. OE+oO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 8.1E+04 3.1E+06 CE 144 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO O.OE+OO l.7E+06 1. 6E+07 I 131 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO 2.7E+06 3.8E+06 I 132 O.OE+OO O.OE+OO O.OE+OO O.OE+OO 0. OE+oO O.OE+OO 2.6E+04 2.8E+05 I 133 O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO 4.8E+05 5.5E+05 I 134 0.0E+OO O.OE+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO 6.7E+03 l.OE+05 I 135 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO O.OE+OO O.OE+OO l.OE+05 5.6E+05 UN-ID* 0.0E+OO 0.0E+OO O.OE+OO O.OE+OO 0.0E+OO 0.0E+OO l.9E+05 1.7E+08 PAGEAl-48 S0123-0DCM-A Revision 7 09-23-13

TABLE 1-10 UNITS 2&3 Page 4 of 4 DOSE PARAMETER R(I) FOR SECTOR 'G' PATHWAY: ENDLS SUM SURFCAMP/RES DISTANCE: 2.8 MILES X/Q 1.2E-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 0. OE+oO 6.3E+02 O.OE+OO CR 51 O.OE+OO O.OE+OO 7.0E+02 l.9E+05 8.6E+02 l.9E+05 7.2E+03 2.3E+06 MN 54 O.OE+OO O.OE+OO 6.5E+04 5.7E+07 8.2E+04 5.7E+07 7.0E+05 6.9E+08 co 57 O.OE+OO O.OE+OO 5.4E+02 l.4E+07 l.3E+03 l.4E+07 l.6E+04 l.7E+08 co 58 O.OE+OO O.OE+OO 4.5E+04 l.6E+07 5.5E+04 1. 6E+07 4.6E+05 l.9E+08 co 60 O.OE+OO O.OE+OO 2.9E+05 8.8E+08 3.6E+05 8.8E+08 3.0E+06 l.lE+lO SR 89 0.0E+OO O.OE+OO 8.9E+04 8.9E+02 9.9E+04 8.9E+02 7.0E+05 l.1E+04 SR 90 0.0E+OO 0.0E+OO 6.1E+05 O.OE+OO 6.8E+05 O.OE+OO 4.8E+06 0.0E+OO ZR 95 O.OE+OO O.OE+OO 9.2E+04 l.OE+07 l.1E+05 l.OE+07 8.8E+05 l.3E+08 NB 95 0.0E+OO O.OE+OO 2.5E+04 5.6E+06 3.1E+04 5.6E+06 2.5E+05 6.8E+07 RU 103 O.OE+OO 0. OE+oO 2.7E+04 4.5E+06 3.2E+04 4.5E+06 2.5E+05 5.4E+07 TE 129M 0.0E+OO 0. OE+oO 7.2E+04 8.1E+05 8.1E+04 8.1E+05 6.2E+05 9.8E+06 cs 134 O.OE+OO 0. OE+oO 5.0E+03 2.8E+08 6.0E+03 2.8E+08 4.9E+04 3.4E+09 cs 136 0.0E+OO 0.0E+OO 6.0E+02 6.2E+06 7.3E+02 6.2E+06 6.0E+03 7.5E+07 cs 137 0.0E+OO O.OE+OO 4.3E+03 4.2E+08 5.0E+03 4.2E+08 3.8E+04 5.1E+09 BA 140 O.OE+OO O.OE+OO 7.2E+04 8.4E+05 8.4E+04 8.4E+05 6.4E+05 l.OE+07 CE 141 O.OE+OO 0. OE+oO 2.2E+04 5.6E+05 2.5E+04 5.6E+05 l.8E+05 6.8E+06 CE 144 0.0E+OO O.OE+OO 4.9E+05 2.9E+06 5.5E+05 2.9E+06 3.9E+06 3.5E+07 I 131 0.0E+OO O.OE+OO 6.7E+05 7.1E+05 6.0E+05 7.1E+05 6.0E+06 8.6E+06 I 132 0.0E+OO 0. OE+oO 8.0E+03 5.1E+04 6.2E+03 5.1E+04 5.7E+04 6.2E+05 I 133 O.OE+OO O.OE+OO l.6E+05 l.OE+05 1.2E+05 l.OE+05 1. lE+O 6 l.2E+06 I 134 0.0E+OO 0. OE+oO 2.1E+03 l.8E+04 l.6E+03 l.8E+04 l.5E+04 2.2E+05 I 135 0. OE+oO 0. OE+oO 3.3E+04 l.OE+05 2.6E+04 l.OE+05 2.2E+05 l.3E+06 UN-ID* O.OE+OO 0. OE+oO 4.1E+04 3 .1E+07 . 5.1E+04 3.1E+07 4.3E+05 3.7E+08 PAGEAl-49 SO 123-0DCM-A Revision 9 09/2015

Enclosure 4 Offsite Dose Calculation Manual Nuclear Organization San Onofre Nuclear Generation Station (SONGS)

Appendix B, Supplemental Information for Effluent Controls S0123-0DCM-B, Revision 9, August 2016

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

APPENDIX B SUPPLEMENTAL INFORMATION FOR EFFLUENT CONTROLS S0123-0DCM-B Revision 9 08/2016

ODCM APPENDIX B .

TABLE OF CONTENTS Section Title Page 1.0 Gas and Liquid Effluent Concentration Limits for Radiation Monitor B1-1 thru Setpoint Calculations B1-5 1-1 K. Yhip to D. Dick, Memorandum for file "Recommended Effluent Concentration Limits from 10CFR20 Appendix B, Table 2, for setpoint calculations," dated April 23, 1993 81-1 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 . 82-1 thru 82-2 2-1 E.S. Medling to J. Clark and P. Knapp, Memorandum for file "Impact of new 10 CFR 20 upon SONGS Effluent Control Limits,

" dated June 14, 1993 B2-1 3.0 SONGS Radiological Environmental Monitoring Program Bases 83-1 thru 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 Calculation Manual Changes 84-1 4-1 Ross T. Ridenoure to L. L. Mccann, Memorandum for File "Offsite Dose Calculation Manual (ODCM) Approval Designee",

dated April 27, 2010. B4-1 5.0 Miscellaneous Gaseous Releases 85-1 thru 85-18 5-1 Memorandum for file , "Units 2/3 BuildingNentilation Envelopes/Turbine/MS IV Areas", Revision 1, January 13, 2012 85-1 6.0 Carbon-14 86-1 thru 86-8 6-1 SONGS Carbon-14 Production, Release and Offsite Dose Calculation Methodology 86-1 7.0 Offsite Dose Calculation Manual Changes 87-1 thru Safety Evaluation for Modifying References to 10 CFR 50.59 87-4 Bi S0123-0DCM-B Revision 9 08/2016

ODCM APPENDIX B TABLE OF CONTENTS Section Title 8.0 Site Boundary Sample Garden Relocation, Activity/Document B8-1 Number/NN 203063159-084 9.0 Eric Golden, "Correlation - Effluents and Environmental Data", B9-1 thru Letter addressed to B. D. Metz, November 4, 2014 B9-3 10.0 Remove Controlling Location Factors Tables 2-7 and 2-8 (South Yard Facility and North Industrial Area ) and Associated Ri Tables in B10-1 thru Appendix A from the ODCM B10-4 11.0 Radwaste Processing Techniques Airborne Effluent Evaluation Memo, B11-1 thru dated December 20, 1999 B11-6 12.0 Airborne Effluent Controls During Decommissioning Memo, dated B12-1 thru September 27, 2000 B12-12 13.0 Airborne Contamination from Decommissioning Activities Memo, dated B13-1 thru December 13, 2013 B13-3 Bii S0123-0DCM-B Revision 9 08/2016

TABLE 1-1 UNITS 2 & 3 DOSE PARAMETER R; FOR SECTOR P Apri1 23, 1993 TO: DARYL DICK, SONGS Effluent Engineering

SUBJECT:

RECOMMENDED EFFLUENT CONCENTRATION FROM 10CFR20 APPENDIX B, TABLE 2, FOR SETPOINT CALCULATIONS

Daryl, I have indicated on the attached table which effluent concentration limits (ECLs) are recommended for use when calculating radiation monitor setpoint values for liquid and airborne radioactive effluent releases from SONGS.

For simplicity's sake, when the station implements the new 10CFR20, ECLs should be used exclusively. In cases where more than one value is listed (based on retention) in Appendix B, Table 2, the most conservative value is recommended for routine calculations. Under conditions which require more flexibility, actual chemical and physical characteristics of the release stream may be considered to allow use of a more representative value. It is recommended that each of these instances be documented. Since no ECLs are provided in Column 2 for dissolved and entrained gases in liquids, per NU REG 1301,

  • Offsite Dose Calculation manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors*, Specification 3.11.1.1, a value of 2E-4 uCi/ml should be used.

If there are any questions, please call me at 50512.

Kathleen Yhip HPE Engineer cc: HPE Files 81-1 S0123-0DCM-B Revision 1 02-29-08

TABLE 1-1 UNITS 2 & 3 DOSE PARAMETER R; FOR SECTOR P GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECI) 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 ?E-9 5E-9 Na-24 5E-5 3E-5 3 Ar-41 1E-8 4E-8 Ar-41 2E-4 4 Sc-46 3E-10 8E-10 Sc-46 1E-5 4E-5 6E-8 d 5 Cr-51 8E-8 Cr-51 5E-4 2E-3 3E-8 w, a 6 Mn-54 1E-9 1E-9 Mn-54 3E-5 1E-4 2E-8 d 7 Mn-56 2E-8 Mn-56 ?E-5 1E-4 3E-8w 3E-9 d 8 Fe-55 3E-8 Fe-55 1E-4 8E-4 6E-9w 5E-10 d 9 Fe-59 2E-9 Fe-59 1E-5 5E-5

?E-10 w 4E-9w 10 Co-57 61::-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-10 w 12 Co-60 3E-10 Co-60 3E-6 3E-5 5E-11 a 4E-8 d 13 Cu-64 4E-8 Cu-64 2E-4 2E-4 3E-8 w, a 14 Zn-65 4E-10 2E-9 Zn-65 5E-6 1E-4 6E-9 d 15 Br-82 6E-9 Br-82 4E-5 4E-5 5E-9w 8E-8 d 16 Br-84 3E-8 Br-84 4E-4 2E-4

' 9E-8w 17 Kr-85 ?E-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-88 9E-8 2E-8 Kr-88 2E-4 21 Rb-88 9E-8 2E-4 Rb-88 4E-4 2E-4 81-2 SO 123~0DCM-B Revision 1 02-29-08

GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECI) VALUES ISOTOPE GAS ECL GAS MPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) (ECL) (MPC) 22 Rb-89 2E-7 2E-4 Rb-89 9E-4 2E-4 1E-9 d 23 Sr-89 3E-10 Sr-89 8E-6 3E-6 2E-10 a 3E-11 d 24 Sr-90 3E-11 Sr-90 5E-7 3E-7 6E-12a 8E-9 d 25 Sr-91 9E-9 Sr-91 2E-5 5E-5 5E-9 a 1E-8 d 26 Sr-92 1E-8 Sr-92 4E-5 6E-5 9E-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 30 Zr-95 1E-9 Zr-95 2E-5 6E-5 5E-10 w 3E-9 d 31 Zr-97 3E-9 Zr-.97 9E-6 2E-5 2E-9 w, a 32 Nb-95 2E-9 3E-9 Nb-95 3E-5 1E-4 4E-9 w 33 Nb-95m 1E-10 Nb-95m 3E-5 3E-6 3E-9 a 34 Nb-97 1E-7 2E-7 Nb-97 3E-4 9E-4 4E-9 d 35 Mo-99 7E-9 Mo-99 2E-5 4E-5 2E-9 a 2E-7 d 36 Tc-99m 5E-7 Tc-99m 1E-3 3E-3 3E-7w 2E-9 d 37 Ru-103 1E-9 w 3E-9 Ru-103 3E-5 8E-5 9E-10 a 1E-10 d 38 Ru-106 8e-11 w 2E-10 Ru-106 3E-6 1E-5 2E-11 a 2E-10 d 39 Ag-110m 3E-10 w 3E-10 Ag-11 Om 6E-6 3E-5 1E-10 a 2E-9 d 40 Sn-113 2E-9 Sn-113 3E-5 9E-5 8E-10 w B1-3 S0123-0DCM-B Revision 1 02-29-08

GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECI) VALUES ISOTOPE GAS ECL GAS MPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) (ECL) (MPC) 3E-9 d 41 Sn-117m 1E-10 Sn-117m 3E-5 3E-6 2E-9w 3E-9 d 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-10 w 3E-9 d 44 Sb-125 9E-10 Sb-125 3E-5 1E-4 7E-10 w 45 Xe-131m 2E-6 4E-7 Xe-131m 2E-4 46 Xe-133 5E-7 3E-7 Xe-133 2E-4 47 Xe-133m 6E-7 3E-7 Xe-133m 2E-4 48 Xe-135 7E-8 1E-7 Xe135 2E-4 49 Xe-135m 4E-8 3E-8 Xe-135m 2E-4 50 Xe-138 2E-8 3E-8 Xe138 2E-4 9E-10 d 51 Te-129m 1E-9 Te-129m 7E-6 2E-5 3E-10 w 1E-9 d 52 Te-132 4E-9 Te-132 9E-6 2E-5 9E-10 53 1-131 2E-10 1E-10 1-131 1E-6 3E-7 54 1-132 2E-8 3E-9 1-132 1E-4 8E-6 55 1-133 1E-9 4E-10 1-133 7E-6 1E-6 56 1-134 6E-8 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 8E-6 2E-5 64 La-140 2E-9 4E-9 La-140 9E-6 2E-5 1E-9 w 65 Ce-141 5E-9 Ce-141 3E-5 9E-5 8E-10 a B1-4 S0123-0DCM-B Revision 1 02-29-08

GAS AND LIQUID EFFLUENT CONCENTRATION LIMIT (ECI) VALUES ISOTOPE GAS ECL GAS MPC ISOTOPE LIQUID ECL LIQUID MPC (ECL) (MPC) (ECL) (MPC) 3E-9w 66 Ce-143 7E-9 Ce-143 2E-5 4E-5 2E-9 a 4E-11 w 67 Ce-144 2E-10 Ce-144 3E-6 1E-5 2E-11 a 68 Nd-147 1E-9 8E-9 Nd-147 2E-5 6E-5 69 W-187 1E-8 1E-8 W-187 3E-5 6E-5 70 Np-239 3E-9 2E-8 Np-239 2E-5 1E-4 71 ALPHA 1E-15 2E-14 ALPHA 2E-9 3E-8 B1-5 S0123-0DCM-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 implemented by all licensees by January 1, 1994. Unit 1 Technical Specification (T5) 6.8.4.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 regarding 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 concluded that 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 any time SCE deems appropriate.

The above conclusion is in agreement with the position presented to NRC Staff by NUMARC during a meeting earlier this month. Preliminary comments from the NRC staff indicate their concurrence. The NRC is expected to issue meeting minutes by mid-June, showing their concurrence.

LICENSING ISSUE Revised Part 20 [20.1008) (b )] generally requires that the license condition and TS references to the old Part 20, Sections 20.1-20.601 should be considered to have been replaced by comparable references to the new Part 20, Sections 20.1001-20.2401. The revised Part 20

[20.1008(c)] requires that any TS that is more restrictive than a requirement in the revised Part 20 remains in force until there is a TS change through a license amendment.

The limit on annually averaged radioactivity concentrations in effluents to unrestricted areas, which is a requirement in the old Part 20 (20.106), has been changed to an optional method

[20.1302(b )(2)(i)] of demonstrating compliance with the annual dose limit specified in 20.1301 and is no longer ITSELF a requirement in the revised Part 20.

SONGS 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 permitted. The revised Part 20 contains NO comparable "at all times" concentration limit.

82-1 S0123-0DCM-B.

Revision 1 02-29-08

The SONGS TS, by not permitting any arbitrary averaging period, are therefore MORE RESTRICTIVE than the revised part 20 limits.

Accordingly, since the SONGS TS are more restrictive than the revised Part 20, the provision of 20.1008( c) applies, with the result that the TS remains in effect, as is, until it is revised, or the license is renewed. With this conclusion, SONGS may exercise any of the following options:

1. NOT request any TS changes, with the result that SONGS must still establish setpoints in accordance with 10 CFR 20, Appendix B, Table II.
2. Request an amendment to section 6.8.4 changing the reference to the "revised" Part 20, Appendix B, Table 2.
3. Request an amendment to the Tech Specs of units 2/3, and NOT of 1, or vice versa.
4. Upon 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 COM 82-2 S0123-0DCM-B Revision 1 02-29-08

MEMORANDUM FOR FILE September 10, 1997

SUBJECT:

Radiological Environmental Monitoring Program Bases

REFERENCES:

1. Letter from Jack B. Moore, SCE to US Atomic Energy Commission, Proposed Environmental Technical Specifications, February 21, 1974.
2. Memorandum from E. S. Medling to D. F. Pilmer, 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 Locations, October 28, 1992.
5. Memorandum from M. Goeders to E. M. Goldin, Bases for Selection of REMP Sample Locations, February 28, 1994.
6. Updated Final Safety Analysis Report, San Onofre Nuclear Generating Station Units 2/3.

Page 2.3H-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, SCE to US Nuclear Regulatory Commission, February 26, 1982.
9. Final Environmental Statement, San Onofre Nuclear Generating Station Units 2 and 3, NUREG-0490, US Nuclear Regulatory Commission, 1981.
10. Final Environmental Statement, San Onofre Nuclear Generating Station Unit 1, US Atomic Energy Commission, 1973.
11. Environmental Report - Operating License Stage, San Onofre Nuclear Generating Station, Sections 6.1 and 6.2.

83-1 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 1997

12. Letter from H. L Ottoson, SCE to Joseph 0. Ward, California 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. Memorandum from M. Goeders to E. M. Goldin, Modification of SONGS Radiological Environmental Monitoring (REM) Sample Analysis Program, November 25, 1992.
15. Memorandum from E. M. Goldin to M. J. Johnson, Deletion of Unnecessary REMP Sample Analyses, January 8, 1996.

INTRODUCTION The Offsite 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, NUREG-0800, NUREG-0133, NUREG-0472, and NUREG-1301. Between the time of publication of the first RETS (Reg Guide 4.8 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 those 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.

While the portion of the Unit 1 and Units 2/3 ODCMs dealing with REMP are not precisely identical in verbiage, the REMP sample requirements are the same. Sample locations, collection frequency and analyses are identified in a table in each ODCM. The table is divided into four sections for the pathways that could permit human exposure to radionuclides. Each section below describes the basis for the sample locations and/or provides appropriate references. A brief note follows 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 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 1997 AIRBORNE: Five 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 early 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 revised 1979-1983 meteorological database.

References 4 and 5 contains a more detailed 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 Q. Note that these sectors are the #2, #3, and

  1. 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 is 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 are Q, 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 Kin the SSW direction.

Because the Unit 1 release point is offset from the center of the Exclusion Area Boundary (EAB), the Unit 1 sectors do 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 border between Q 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. With regard to Unit 1, air sampler #12 is located very close to the boundary of two sectors that each require sampling. However, to ensure complete ODCM compliance, a new air sa_mpler was installed in sector R in 1997, air sampler #14.

Local Community:

ODCM Requirement: One sample from the vicinity of a community having the highest calculated annual average ground level D/Q.

Air sampler #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 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 1997 Q as having the highest landward D/Q for Unit 1 (Sector K, offshore has the highest D/Q). For Units 2/3, Sector Q 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 Requirement: 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 provide 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, 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 complied with the logic described in the footnote and because it provided continuity in data (the existing Unit 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), B (north northeast), C (northeast), A (north), and finally Sector Q (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 elimination of the offshore Sectors and the landward Sectors B, C, and A, the 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 Q. However, again noting the footnote guidance, the continuity of data, and the sufficiently distant location, Sector Q adequately meets the, ODCM requirement. Finally, due to the imminent sale of the Huntington Beach Generating Station, the control air sample will being relocated to Sector G (denoted as Air Sampler #14).

Since Unit 1 and Units 2/3 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: 1/25/73-1/24/76 Sectors Wind From Percent Frequency 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 Q 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 WNW 10.8 p F NNE 10.9 B K*

NE 14 C L*

Total 99.9 B3-5 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 1997 RANKED BY PERCENT FREQUENCY Data from Reference 7 Dates: 1/1/79-12/31/83 Sectors Wind 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 WNW 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 sampling 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 thermoluminescent 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 B3-6 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 1997 identified in given sectors for Units 2/3 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 precise 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 TLD Number Location Site (sector) (miles)

WNW (P) 0.39 10 PIC#1 NW (Q) 1.22 8 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#5 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 TLD Number Location Site (sector) (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 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 1997 Outer Ring:

ODCM Requirement: An outer ring in the four to five mile range from the Site with a station in each sector of each ring.

References 4 and 5 documented the location of thermoluminescent dosimeters (TLD) in an outer ring around both Unit 1 and Units 2/3. 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 2/3 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) (miles)

WNW(P) 2.42 22 San Mateo Point NW(Q) 5.33 1 San Clemente NNW (R) 4.76 19 San Clemente Hiohlands N (A) 3.38 2 Camp San Mateo NNE (B) 4.66 35 Ranae 312 NE (C) 4.32 36 Ranqe 208C ENE (D) 4.48 68 Range 210C E (E) 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 Direction Distance TLD Number Location (sector) (miles)

WNW (P) 2.7 22 San Mateo Point NW(Q) 5.6 1 San Clemente NNW (R) 5.0 19 San Clemente Hiahlands N (A) 5.7 33 Camp Taleqa NNE (B) 4.7 35 Range 312 NE (C) 4.2 36 Ranoe 208C ENE (D) 4.3 68 Ranoe 210C E (E) 4.5 4 Camp Homo ESE (F) 3.0 6 Old Route 101 SE(G) 3.3 38 State Beach 83-8 S0123-0DCM-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 locations close to the plant, and several locations sufficiently distant to provide adequate controls. References 4 and 5 identified the logic for selecting those stations.

The direct radiation program is close to that in NUREG-0472 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.

B3-9 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 1997 WATERBORNE: Four categories.

Ocean REMP Requirement: Four Locations There are four ocean water sample locations, one at each Unit outfall and one control in the Newport Beach area. Note that these locations were based on the program originally proposed in Reference 1. The "indicator" locations should be near the respective outfalls but outside of the turbulent discharge area. The pathway for exposure, as discussed in Reference 1, is from swimming and a small amount of ingestion of seawater.*

Drinking Water REMP Requirement: Two Locations Reference 8 noted that there is no reliable surface water in the vicinity of San Onofre.

Moreover, there is no drinking water pathway for the area near San Onofre (Reference 9, pages 2-3, 2-4). Nevertheless, in accordance with Reference 8, samples are taken from nearby wells to monitor ground water. There are two locations sampled for drinking water. Until recently, two "indicator" locations were sampled for drinking water and a third sample was taken from the Huntington Beach area as a control. In 1997, the best "drinking water" location was identified as local wells about 2.4 miles from San Onofre on Camp 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 ever 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 taken at an appropriate control location (Newport Beach). The indicator locations are slightly upcoast

(-0.2 miles 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 19, page 2-3), indicator samples are preferentially taken downcoast. The control is therefore appropriately taken upcoast at a sufficient distance (Newport Beach at 83-10 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 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 Ocean bottom sediments are collected at four indicator locations and one control location. Two indicator locations are near the Unit 1 outfall and one each at Unit 2 and Unit 3 outfalls. The control location is at Laguna Beach which is about 18 miles upcoast and sufficiently distant to be unaffected by plant operation. Reference 1 noted that ocean bottom sediment could contribute to human exposure through marine plants and animals.

In addition to the ODCM required samples, ocean water and ocean 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 presence of a defect in the discharge conduit. This defect allows some very limited discharge closer to shore than the designed discharge locations. After accumulation of sufficient negative data, this optional sampling program may be discontinued.

As discussed above, due to the location of San Onofre on the coast, the waterborne pathways differ from a typical land bound plant. Consequently the REMP samples required by the ODCMs for these media differ from the standard programs described in NUREG-0472 and NUREG-1301.

INGESTION: Two categories Nonmigratory Marine Animals REMP Requirement: Three locations Nonmigratory marine animals are collected at two indicator locations and one control location. The indicator locations are at the Unit 1 outfall and the vicinity of the Units 2 and 3 outfalls. The control location is at Laguna Beach, which is about 18 miles upcoast and sufficiently distant to be unaffected by plant operation. Nonmigratory marine animals provide a potential pathway for human exposure through ingestion.

The types of animals collected are specified in the ODCMs (Fish, Crustacea, and Mollusks) and depend on the species available,::Reference 1 noted that the samples may be taken within 2 miles of the discharge outfall. This flexibility is 83-11 SO 123-0DCM-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 harvest 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 miles distant in the downcoast direction. The indicator location has usually been the San Clemente Ranch at 2.6 miles in the northwest direction. These indicator and control locations were specified 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 t~e west northwest direction, 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-1301.

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 important to monitor and assess potential exposure to the public.

Soil samples have also been historically taken in the vicinity of SONGS. The purpose is to evaluate whether there might be any accumulation of radioactivity in the soil 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 Strontium-89 and Strontium-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 or ER-OLS (Reference 11 ). The ER-OLS described the early B3-13 SO 123-0DCM-B Revision 2 02-27-09

REMP Samples 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 early programs for the sake of continuity. Moreover, the older program at Unit 1 was used as the preoperational program for Units 2/3. The State of California 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 this confirmatory program.

For all the above reasons, the REMP has been built on existing programs and requirements rather than simply starting fresh when new regulatory guidance was issued.

SAMPLE ANALYSES Samples are analyzed 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 describe 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 closely.

E. M. GOLDIN Attachment cc: E. S. Medling M. J. Johnson D. Dick K. C. Yhip N. A. Hansen HPE/CDM Files 83-13 S0123-0DCM-B Revision 2 02-27-09

REMP Samples September 10, 1997 DEVELOPMENTAL RESOURCES The following documents were not specifically 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 Specifications, December 12, 1983.
2. Letter from NRC to K. P. Baskin, Offsite Dose Calculation Manual, October 2, 1984.
3. Letter from NRC to K. P. Baskin, Offsite Dose Calculation Manual, August 30, 1985.
4. Memorandum from E. S. Medling to D. L. Cox, Request for Amendment to SONGS Units 2/3 Technical Specifications, September 16, 1988.
5. Memorandum from J. Brown to K. Yhip, Critical Organ for 40CFR190 Evaluation of Gaseous Effluent Dose, April 2, 1991.
6. Memorandum from W. Edwards to K. Yhip, Calcium Sulfate vs Lithium Fluoride TLD Comparison, September 17, 1991.
7. Memorandum for File, M. Goeders, Channeling in Radioiodine Charcoal Cartridges, December 30, 1993
8. Memorandum from M. Goeders 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. Memorandum from M. J. Johnson to E. Goldin, Revision of the Radiological Environmental Monitoring Program (REMP) Sample Locations, January 21, 1997.

83-14 SO 123-0DCM-B Revision 2 02-27-09

Subject:

Approval of Offsite Dose Calculation Manual Changes, April 27, 2010 Ross T. Ridcnourc Senior Vkc 1'1\.':-ikk*nt and C!\:O San Onofn.* Nt11.:kar G~ncrating Stution April 27, 2010 MESSR: L. L. MCCANN

SUBJECT:

Offsite Dose Calculation Manual (ODCM) Approval Designee Technical Specification 5.5.2.1.1 "Licensee-initiated changes to the ODCM,"

Section 5.5.2.1.1.b requires licensee-initiated changes to the ODCM to become effective upon review and approval by the corporate officer with direct responsibility for the plant or designee.

Consistent with the above, effective May 5th, 2010, Doug Bauder is assigned as my designee for approval of ODCM revisions.

cc:

D.R. Bauder R. J. StOnge L. T. Conklin E. S. Medling A. J. Brough COM Mail Stop 1),1, l'.0. ll(>X 1213 San Ckmenlc. CA lJ1672 tcJ~*ll 168-6255 P/\X 86255 Fux: 1q..Jq) 36t{-6183 Ro:,s.l~idc110ur._*l!f'.~n.*.t:om 84-1 S0123-0DCM-B Revision 6 08-09-12

Memorandum for File

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 BACKGROUND Units 2/3 consists of the following building/ventilation envelopes/areas: Control Room Complex Ventilation; Control Building Ventilation; Radwaste Building Ventilation; Safety Equipment Building Ventilation System; Penetration Building Ventilation System; MSIV/Turbine Building 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 leak. In addition, there are also planned but unmonitored releases of airborne radioactive material that result from system operation as designed but occur infrequently and are impractical to monitor.

For each one of the ventilation envelope/areas, the following documents form the regulatory 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 operation, anticipated operational occurrences, 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 containment leakage, and that "continuous gaseous effluent monitors are not required for open structures, such as PWR turbine buildings or atmospheric vents for liquid waste tanks containing treated or processed liquid waste and located outside of buildings." As a practical consideration, is the regulatory guidance recognizes that there may be release points th.at cannot be monitored because (a) instrumentation may not exist that could reliably 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, particularly in-line. These releases are not anticipated to result in a significant amount (curies) of activity being released or in a significant dose to the public.
4. Section 9.4 and Section 11.3 of the UFSAR recognize that there are building leakages and steam leaks, which are not monitored, to the outside atmosphere.
5. 10 CFR 20 provides airborne Derived Air Concentration (DAC) limits for station workers within the radiologically controlled area, which is controlled by the health physics radiation protection program, as well as Maximum Permissible Concentration (MPC) limits for a member of the public in the unrestricted area, which is assessed by the effluent program.

For example, Xe-133 is an isotope most likely to cause an airborne problem for building/ventilation envelopes/areas. One DAC Xe-133 = 1E-4 uCi/cc for the radiologically 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. The actual or estimated flowrate and isotopes are determined when Effluent B5-1 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Engineering implements S0123-lll-5.25, "Evaluation 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 uCi/cc for the radiologically controlled area and one MPC = 2E-7 uCi/cc for the unrestricted area. The effluent impact for steam releases are evaluated in Attachments A and C

  • For 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of Auxiliary Feedwater Pumps operation per year, the effluent impact is 6.58E-7 mrem during the year at the controlling location (Camp Mesa)
  • For 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of Atmospheric Dump Valves operation at full capacity per year, the effluent impact is 6.58E-5 mrem during the year at the controlling location (Camp Mesa)

While these examples are provided for Xe-133 and H-3, it holds true 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, generally 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. Examples of nuisance pathways include:

  • Diffusion across the surface of water contained in *an open sump
  • Normal leakage from a PWR 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 Complex Ventilation (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 normal supply fan and exhausted to the atmosphere at 2700 cfm. Of all the areas in this envelope, 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 directed to the Plant Vent Stack. The Plant Vent Stack is an ODCM-credited release point that is periodically sampled per the ODCM and is monitored prior to discharge to the environment.

Although the Turbine Laboratory is considered a potentially airborne radioactive area, due to administrative practices that limit operation with primary to secondary leakage, it does 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 pressure control valve, and when the sample reaches the Turbine Lab, it is at ambient pressure. As a result, the likelihood of an airborne issue for radioactive materials is remote.

85-2 SO 123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MS IV 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 S0123-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 Control Room Complex Ventilation envelope is contaminated to the 25% DAC HP threshold for an airborne radiation area, at an exhaust rate of 2700 cfm, the effluent impact at the site boundary is no greater than 5.13E-6 mrem/hr 1E-4 uCi/cc

  • 0.25
  • 2700 cfm
  • 2.832E4 cc/ft 3
  • 1 min/60 sec
  • 4.8E-6 sec/m 3
  • 294 mrem/yr per uCi/m3
  • 1 yr/8766 hrs = 5.13E-6 mrem/hr Control Building Ventilation (Units 2(3)

The Control Building Ventilation System serves the Control Building except for the Control Room Complex Ventilation Envelope. It includes the following subsystem:

Consistent with standard ALARA practices, ESF Switchgear Room Normal and Emergency Cooling subsystem, ESF Battery Rooms Normal and Emergency Ventilation subsystem, Switchgear Room Ventilation subsystem, Communication Battery Room Ventilation subsystem, HP Computer Air Conditioning subsystem, Communication Room Air Conditioning subsystem, Cable Spreading and Electrical Room Ventilation subsystem, Chiller Rooms Normal and Emergency Ventilation subsystems, Public Address and Communication Rooms Air Conditioning subsystem, and Health Physics and Locker Room 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 Stack is an ODCM-credited release point that is periodically sampled per the ODCM and is monitored prior to discharge to the environment.

Areas 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 materials. All other areas are not potentially airborne radioactive and are exhausted by normal exhaust fans at about 110,000 cfm to the atmosphere.

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 this ventilation envelope, Effluent Engineering will implement S0123-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 extremely unlikely event that the entire Control Building Ventilation envelope is contaminated to the 25% DAC HP threshold for an airborne 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 uCi/cc

  • 0.25
  • 110000 cfm
  • 2.832E4 cc/ft 3
  • 1 min/60 sec
  • 4.8E-6 sec/m 3
  • 294 mrem/yr per uCi/m3
  • 1 yr/8766 hrs = 2.09E-4 mrem/hr 85-3 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Radwaste Building Ventilation (Units 2/3)

The Radwaste Ventilation System serves the Radwaste Building and is comprised of several subsystems: Radwaste Area Ventilation subsystem, Post Accident Sampling Laboratory Air Conditioning subsystem, Control Element Drive Mechanism Control System Room Air Conditioning subsystem, Radwaste Building Addition Ventilation subsystem, and Charging and Boric Acid Pump Rooms Emergency Ventilation.

Relative to other building/ventilation envelopes, the Radwaste envelope has a higher potential for unmonitored releases since it contains most, if not all, 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 negative pressure relative to other adjacent building/ventilation envelopes. This envelope is normally exhausted (about 78,100 cfm) to the Plant Vent Stack. The Plant Vent Stack is an ODCM-credited release point that is periodically sampled per the ODCM and is monitored prior to discharge to the environment.

Due to this envelope's higher potential to become airborne, additional design, procedural, and administrative controls are implemented to ensure a negative pressure is maintained to minimize ex-filtration to the outside atmosphere. For example: The ventilation supply and exhaust units are 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 Truck Bay dampers are interlocked with the truck bay door, a boundary door to the outside 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 S023-1-5, "Auxiliary Building Normal HVAC System Operation," provides explicit directions on the Radwaste/Truck Bay ventilation envelope to ensure a negative 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 and to outside areas. Operations Instructions S023-15-60.B, "Annunciator Panel," directs that Effluent Engineering be notified for a potential unplanned or uncontrolled release if Radwaste HVAC is lost.

As an additional note, signs are posted on appropriate radwaste envelope doors to remind station personnel to keep doors closed when egress or ingress is not required.

Based on the relative potential for radioactive material to become airborne, the design and procedural controls that are being implemented are proper and adequate.

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 material at 25% DAC or higher is detected by HP or Area Radiation Monitors in this ventilation envelope and concurrent with a loss of Radwaste HVAC, Effluent Engineering will implement S0123-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 Radwaste Ventilation envelope is determined to contain or exceed the 25% DAC HP threshold for an airborne radiation area and concurrent with a loss of Radwaste HVAC, at an exhaust rate of 78100 cfm from the Radwaste Building Ventilation Envelope, the effluent impact at the site boundary is no greater than

  • 1.48E-4 mrem/hr. Note: Upon loss of Radwaste HVAC, there is essentially no differential pressure between the Radwaste Envelope and outside atmosphere.

1E-4 uCi/cc

  • 0.25
  • 78100 cfm
  • 2.832E4 cc/ft 3
  • 1 min/60 sec
  • 4.8E-6 sec/m 3
  • 294 mrem/yr per uCi/m3
  • 1 yr/8766 hrs = 1.48E-4 mrem/hr 85-4 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Safety Equipment Building Ventilation System (Per Unit)

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 air conditioning subsystem, and the elevator room (Unit 2 only).

Under normal operation, this ventilation envelope is not considered potentially airborne radioactive.

In the unlikely event of an accident condition, particularly with fuel failure, safety injection system actuation followed by a breach of pressure boundary equipment or components in the safety 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 periodically sampled per the ODCM and is monitored prior to discharge to the environment. The only excepted area is the elevator equipment room (Unit 2 only), that draws outside air directly and exhausts (1160 cfm) directly to the outside atmosphere.

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 material at 25% DAC or higher is detected by HP or Area Radiation Monitors in this ventilation envelope, Effluent Engineering will implement S0123-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 Safety Equipment 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 Safety Equipment Building HVAC, there is essentially no differential pressure between the Safety Equipment Building envelope and outside*atmosphere.

1E-4 uCi/cc

  • 0.25
  • 9000 cfm
  • 2.832E4 cc/ft 3
  • 1 min/60 sec
  • 4.8E-6 sec/m 3
  • 294 mrem/yr per uCi/m3
  • 1 yr/8766 hrs = 1. 71 E-5 mrem/hr Penetration Building 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 potential exists for an airborne concern. For this reason, this envelope is exhausted (about 9000 cfm per Unit) to the Plant Vent Stack. The Plant Vent Stack is an ODCM-credited release point that is periodically sampled per the ODCM and is monitored prior to discharge to the 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 material at 25% DAC or higher is detected by HP or Area Radiation Monitors in this ventilation envelope, Effluent Engineering will implement S0123-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.

  • 85-5 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Unmonitored Effluent Impact: In the unlikely 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 is essentially no differential pressure between the Penetration Envelope and outside atmosphere.

1E-4 uCi/cc

  • 0.25
  • 9000 cfm
  • 2.832E4 cc/ft 3
  • 1 min/60 sec
  • 4.8E-6 sec/m 3
  • 294 mrem/yr per uCi/m3
  • 1 yr/8766 hrs = 1. 71 E-5 mrem/hr Electrical Tunnel Ventilation (Units 2/3)

The Electrical Tunnel Ventilation System includes these subsystems: Safety Equipment Building (SEB) Electrical Tunnel, and the 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, including tritium. They are exhausted directly to the environment with the SEB tunnel at a normal rate of about 11,000 cfm and the Access Building and Underground Cable tunnel at a normal rate of about 17,000 cfm.

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 the Safety Equipment Building (SEB) Electrical Tunnel, or the Access Building and Underground Cable Tunnel becomes flooded with water containing licensed material, including tritium, Effluent Engineering will implement S0123-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 Electrical Tunnel Ventilation envelope is contaminated to the 25% DAC HP threshold for an airborne radiation area, at an exhaust rate of 28000 cfm, the effluent impact at the site boundary is no greater than 5.32E-5 mrem/hr.

1E-4 uCi/cc

  • 0.25
  • 28000 cfm
  • 2.832E4 cc/ft3
  • 1 min/60 sec
  • 4.8E-6 sec/m 3
  • 294 mrem/yr per uCi/m3
  • 1 yr/8766 hrs = 5.32E-5 mrem/hr Fuel Handling Building Ventilation System (Per Unit)

Barring the 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) to the Plant Vent Stack with the option to route the air through a HEPA filter system The Plant Vent Stack is an ODCM-credited release point that is periodically sampled per the ODCM and is monitored prior to discharge to the 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 material at 25% DAC or higher is detected by HP or Area Radiation Monitors in this ventilation envelope, Effluent Engineering will implement S0123-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.

B5-6 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1

  • Unmonitored Effluent Impact: In the unlikely event that the entire Fuel Handling Building Ventilation 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 no greater than 4.94E-5 mrem/hr. Note: Upon loss of Fuel Handling Building HVAC, there is essentially no differential pressure between the Fuel Handling Building Envelope and outside atmosphere.

1E-4 uCi/cc

  • 0.25
  • 26000 cfm
  • 2.832E4 cc/ft 3
  • 1 min/60 sec
  • 4.8E-6 sec/m 3
  • 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 habitability in the Tendon Gallery. A potential airborne radioactive concern would be if the Tendon Gallery became flooded with water containing licensed material, including tritium. The exhaust (about 5000 cfm) goes directly to outside atmosphere.

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 the Tendon gallery becomes flooded with water containing licensed material, Effluent Engineering will implement S0123-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 threshold for an airborne radiation area, at an exhaust rate of 5000 cfm, the effluent impact at the site boundary is no greater than 9.50E-6 mrem/hr.

1E-4 uCi/cc

  • 0.25
  • 5000 cfm
  • 2.832E4 cc/ft3
  • 1 min/60 sec
  • 4.8E-6 sec/m 3
  • 294 mrem/yr per .uCi/m3
  • 1 yr/8766 hrs = 9.50E-6 mrem/hr MSIV/Turbine Building General Area (Per Unit)

Since these areas are open structures that contain equipment 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 concentration(s) of licensed 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 material 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 discharge 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 Gland Seal Steam System: 1% (708 lbm/hr)

B5-7 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 As is the case for the steam and 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 to secondary leak where tritium activity is released from the Unit 2 and 3 turbine building steam leakage and Turbine Gland Seal Steam system occur for 8760 hrs/yr the effluent impact at the controlling location (Camp Mesa) would be 9.14E-6 mrem/yr (Attachment 8)

PLANNED BUT UNMONITORED RELEASES Section 10 of the UFSAR also discusses three other main steam flowpaths: steam driven auxiliary feedwater pump, main steam safeties, and atmospheric dump valves (ADV). 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 likely to have a radioactive release during the use of the equipment but, due to operating conditions, monitoring for licensed material cannot practicably be accomplished. As previously discussed, 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 operating conditions of the system that is being monitored or (b) because the concentrations are typically below concentrations that can be reliably determined, particularly by in-line instruments. These releases are not anticipated to result in a significant amount (curies) of activity being released or in a significant dose to the public.

Steam Driven Auxiliary Feedwater Pump In an accident scenario or for quarterly 1ST surveillance, operation of the steam driven auxiliary feedwater pump may be required. The exhaust of the steam driven pump turbine goes 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 maximum pump flow conditions in Section 10.4 of the UFSAR for accident mitigation, the maximum steam flow rate to the pump can be calculated to be about 25,000 lbm/hr (Attachment A).

Assuming these planned releases occur 6 times per year for 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />, 4 times for 1ST and 2 times for abnormal/accident conditions, a total of 1.5 E6 lbm of steam would have been exhausted to the atmosphere.

Since the main steam flowrate is approximately 1.5E7 lbm/hr, for a primary to secondary leak, this would represent about 0.2% of the noble gas activity 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 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 about 0.01 % of the airborne tritium activity released from the Plant Vent Stack. (Attachment A) The Plant Vent Stack is an ODCM-credited release point that is periodically sampled per the ODCM and is monitored prior to discharge to the environment.

85-8 SO 123-0DCM-8 Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 The conclusion is that similar to turbine building steam leakage and the turbine gland seal steam system, operation of the steam driven auxiliary feedwater pump does not constitute a significant or major release flowpath. However, since these are planned but unmonitored releases and the secondary systems normally contain tritium, each release shall be evaluated per the Corrective Action Program to determine if the dose and curies released should be included in the Annual Radioactive Effluent Release Report.

In the unlikely event of an abnormal/accident condition when the steam drive auxiliary feedwater pump is needed:

  • subsequent to an emergency event declaration, Effluent Engineering will implement S0123-lll-5.22.23, "Determining a Source Term for Offsite Dose Calculations in an Accident Situation,"
  • subsequent to the emergency event, Effluent Engineering will implement S0123-lll-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 Report.

Main Steam Safety Valves There are a total of 18 main steam safety valves per unit with a maximum total of 1.5 E7 lbm/hr of relieving capacity during an accident or abnormal scenario depending on plant condition such as decay heat history, etc,. Actuation of the valves is an unlikely event (unplanned release) supported by plant 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 Engineering will implement S0123-lll-5.25, "Evaluation and Reporting of Abnormal Releases of Radioactive Material," for a potentially unplanned or uncontrolled release.

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 event declaration, Effluent Engineering will implement S0123-lll-5.22.23, "Determining a Source Term for Offsite Dose Calculations in an Accident Situation," ,
  • subsequent to the emergency event, Effluent Engineering will implement S0123-lll-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 Report.

Atmospheric Dump Valves There are two atmospheric dump valves per unit with a maximum total of 1.5 E6 lbm/hr of relieving capacity during an 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 operations, they are throttled to a fraction of the maximum relieving capacity.

For a primary to secondary leak and assuming that the dump valves are operated 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per year at full capacity, a total of 1.5 E7 lbm of steam would be exhausted to the atmosphere. Since the 85-9 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 main steam flowrate is approximately 1.5E7 lbm/hr, this represents about 10 % 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 Main Condenser Evacuation System, operation of the dump valves for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year at full capacity would represent about 1 % of the airborne tritium activity released through the Plant Vent Stack. (Attachment C) The Plant Vent Stack is an ODCM-credited release point that is periodically sampled per the ODCM and is monitored prior to discharge to the environment.

Therefore, 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 valves does not constitute a significant or major release flowpath. However, since use of the ADVs are planned releases and the secondary systems normally contain tritium, each release shall be evaluated per the Corrective Action Program to determine if the dose and curies released should be included in the Annual Radioactive Effluent Release Report. Refer to Attachment D to calculate the steam flowrate from the ADVs.

In the unlikely event of an abnormal/accident condition when the atmospheric dump valves are needed to assist the main steam safeties for decay heat removal:

  • subsequent to an emergency event declaration, Effluent Engineering will implement S0123-lll-5.22.23, "Determining a Source Term for Offsite Dose Calculations in an Accident Situation,"
  • subsequent to the emergency event, Effluent Engineering will implement S0123-lll-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 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 point. Mini and normal purges of the containment are conducted through a monitored and sampled flowpath prior to release. The mini purge is exhausted at a rate of about 2000 CFM, and the normal purge at about 40,000 cfm. When shutdown to Mode 5, primarily for a refueling outage, the purge system supplies the containment with outside air through the equipment hatch. When the hatch is open, auxiliary air samplers at the hatch are continuously sampling for particulate and iodine activity.

Effluent Controls: If concentrations of licensed material are detected around the equipment hatch opening, Effluent Engineering will implement S0123-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 containment envelope is contaminated to the 25% DAC HP threshold for an airborne 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
  • 2.832E4 cc/ft 3
  • 1 min/60 sec
  • 4.BE-6 sec/m 3
  • 294 mrem/yr per uCi/m3
  • 1 yr/8766 hrs= 7.60E-5 mrem/hr 85-10 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 North Industrial Area (formerly Unit 1)

Unit 1 was permanently shutdown in November 1992 and systems containing or potentially containing licensed material have been drained and removed or abandoned in place. Used fuel from Unit 1 is stored in the 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 Area (Unit 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 Evaluation (EOE) performed.

85-11 SO 123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 CONCLUSION The evaluation of the Units 2/3 building ventilation envelopes/areas with a potential for an unmonitored airborne release has determined that:

1. The design of the building ventilation envelopes, turbine building/MS IV areas does not assume that they are 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 sampled.
2. In the absence of airborne radioactive materials, doors may be opened for personnel and equipment ingress/egress, operational and maintenance activities.
3. The adoption of 25% DAG Health Physics criterion for an airborne area within the radiologically controlled area as a threshold for an evaluation of a potentially 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 envelopes. This attention reflects the 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 iri RG 1.21 rev 1 will be included in the applicable Annual Radioactive Effluent Release Report.

If you have any questions or concerns regarding this matter, please contact James Dem low at 86780.

_ _ 1/13/2ff12_ __

J. Demlow Date

Attachment:

A Units 2 and 3 Steam Driven Aux Feedwater Pump Release Calculation 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 and 3 Atmospheric Dump Valve Steam Flowrate Calculation cc: L. Mccann K. Yhip J. Scott COM B5-12 SO 123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Attachment A Units 2 and 3 Steam Driven Aux Feedwater Pump Calculation Steam Flow Rate Although the main steam flowrate to the Units 2 and 3 Steam Driven Aux Feedwater Pump turbine is not provided in the UFSAR or other available references, the expected maximum flowrate can be calculated based on accident design conditions provided 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 conditions of 80 F water at atmospheric pressure) at a rate of 500 gpm for a steam generator pressure of 1172 psia or 700 gpm for a steam generator pressure of 1000 psia. Applying the conservation of energy principle, the work done by the main steam on the turbine can be equated to the work done by the pump in transporting the condensate storage tank fluid to the steam generator.

The work done by the steam on the turbine is:

M x delta h where M is main 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 where F is the pump flowrate, v is the specific volume of the condensate tank water at 80° F, delta P is the change in pressure from atmospheric to steam Generator pressure. Using 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.

B5-13 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation 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 <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />
  • 2.5E4 lbm/hr is discharged
  • No detectable Primary to Secondary Leak
  • 82 Ci/yr of gaseous 3 H released from Plant Vent Stack (201 O ARERR)
  • 870 Ci/yr of liquid 3H 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.
  • 1lbm of saturated steam= 334 ft 3 (Steam Tables)
  • 1 m3 of air contains 30 g water vapor at 30 C0 (100% humidity )
  • 1 ft 3 = 0.02813 m3 Calculations Tritium Release Rate into atmosphere 2.5E4 lbm/hr
  • 334 ft 3/lbm
  • 0.02813 m3/ft3
  • 30 g/m 3
  • 1hr/3600 sec

= 2.0E-2 uCi/sec Tritium Curies released into atmosphere 2.0E-2 uCi/sec

  • 60 hrs
  • 3600 sec/hr
  • 2 units = 8.6E-3 Ci Percent of Tritium Curies Released from Plant Vent Stack 8.6E-3 Ci / 82 Ci (PVS)

Effluent Impact Dose (Camp Mesa) 2.0E-2 uCi/sec

  • 4.81 E-3 mrem/yr per uCi/sec
  • 1 yr/8766 hrs* 60 hrs= 6.58E-7 mrem per year 4.81 E-3 mrem/yr per uCi/sec from ODCM Table 2-6 B5-14 SO 123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Attachment B Units 2 and 3 Turbine Building Leakage and Gland Seal Steam System Release Calculation Assumptions

  • Each unit seal steam operated for 8766 hrs/yr
  • 2408 lbm/hr is discharged
  • No detectable Primary to Secondary Leak
  • 82 Ci/yr of gaseous 3 H released from Plant Vent Stack (201 O ARERR)
  • 870 Ci/yr of liquid 3H released (201 O 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.
  • 1lbm of saturated steam = 334 ft 3 (Steam Tables)
  • 1 m3 of air contains 30 g water vapor at 30 C0 (100% humidity)
  • 1 ft3 = 0.02813 m3 Calculations Tritium Release Rate into atmosphere 2408 lbm/hr
  • 334 ft3/lbm
  • 0.02813 m3/ft3
  • 30 g/m 3
  • 1hr/3600 sec

= 1.9E-3 uCi/sec Effluent Impact Dose (Camp Mesa) 3 H: 1.9E-3 uCi/sec

  • 4.81 E-3 mrem/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 SO 123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Attachment C Units 2 and 3 Atmospheric Dump Valve Release Calculation There are two atmospheric dump valves per unit with a maximum total of 1.5 E6 lbm/hr of relieving capacity depending on plant condition 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.

Secondary systems tritium 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 <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per year
  • 1.5E6 lbm/hr is discharged
  • No detectable Primary to Secondary Leak
  • 82 Ci/yr of gaseous 3H released from Plant Vent Stack (2010 ARERR)
  • 870 Ci/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.
  • 1lbm of saturated steam = 334 ft3 (Steam Tables)
  • 11bm = 2200 g
  • 1 m3 of air contains 30 g water vapor at 30 C 0 (100% humidity )
  • 1 ft 3 = 0.02813 m 3 Calculations Tritium Release Rate into atmosphere 1.5E6 lbm/hr
  • 334 ft 3/lbm
  • 0.02813 m3/ft3
  • 30 g/m 3
  • 1hr/3600 sec

= 1.2 uCi/sec Tritium Curies released into atmosphere 1.2 uCi/sec

  • 100 hrs
  • 3600 sec/hr
  • 2 units = 0.8 Ci Percent of Tritium Curies Released from Plant Vent Stack 0.8 Ci/ 82 Ci (PVS)
  • 100 = 1.0%

Effluent Impact Dose (Camp Mesa) 1.2 uCi/sec

  • 4.81 E-3 mrem/yr per uCi/sec
  • 1 yr/8766 hrs
  • 100 hrs = 6.58E-5 mrem for the year 4.81 E-3 mrem/yr per uCi/sec from ODCM !able 2-6 85-16 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Attachment D Units 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 (NOT) 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 was at 5.1 % open. The steam generator pressure was then allowed to drift down.

The files from these runs data files were pulled. The data files contain five data columns. Data columns were for time into the run, ADV #1 position open, ADV #2 position open, Flow from ADV

  1. 1 in million lbm/hr, Flow from ADV #2 in million lbm/hr, steam generator #1 pressure in psia, and steam generator #2 pressure in psia. 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 files go to data3 on sos2/ME&SE Library/Engineering Notebooks/ MSTM/References.

The spreadsheet "stmflow.xls" will also be stored here.)

Each file was used as input for the applicable valve position tab on Microsoft Excel spreadsheet "stmflow.xls.. It was observed at very high pressures that the ADV flow increased with 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 "stmflow.xls". The data fields were always at slightly higher pressure then pressure desired ensuring conservative flows were attained. On the valve position 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 S0123-0DCM-B Revision 6 08-09-12

SUBJECT:

Units 2/3 BuildingNentilation Envelopes/Turbine/MSIV January 13, 2012 Areas, Revision 1 Units 2 and 3 Atmospheric Dump Valve Steam Flowrate Calculation NN 201286374 SPT 5 The Summary Table results were compared to results attained from actual ADV flow test on the units during the 1986/1987 time frame. Memorandum for File dated March 26, 1987,

Subject:

Atmospheric 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 File 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 conservative in that it will in generally give greater values for flow than expected. The only non-conservative direction is that for brief open spikes in valve position (<15 seconds), the maximum valve position 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 million Lbms/hr in flow. If actual pressure >max reading for associated valve position, then use the highest flow value for that valve position. When actual steam generator pressure is not listed, then use the pressure in table that is just above actual.

When actual percent open is not listed, then use the percent open in the table that is just above actual. For large changes in ADV position or steam pressure, then use smaller duration to give better estimate of flow. Duration should not 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 is at least 5 minutes.

Written by: Danny Lowenberg Peer reviewed by: Wayne Hampton 3/16/11 85-18 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 S OIJTF 1£a:R!'I CAI.' FORr>IIA L:U eor,..,

San Onofre Nuclear Generating Station Carbon-14 ProducUonl Release and

_O_ff~ite Dos~_~alculation Methodofog_y___ _

I hi!! ~apet do~umenti,; thP.: mi,;11odc lcgy lo ai.lim~e, G.lr:icn-14 (C-14) F)ro:luallc 11 9nd r.::.14 g:is:sous

'MIi!£~ eftluerr: !!OU rce. ttrm! at Sen C!n ~:re NllL.:hM Gr,:n U!l;liil'.!il SIBtl()n (SON GB). Tho C-141,,ffl,Jan!

sQurce-te-mij are U&E:d t~ estlm8!~ radlolcglr..,f rln."l'l~ fmrp c.. *14 Jn ~e, gaaeaue V/'191:e effluents.

Thl!lse gl!ltlmatei; wmr!lo gena~ecl .,, c,IT.f~ ta ma Al \ RO rA:p11r~rn91ltS ui lno:irporatm c-1, In nuciear JJCW'ir phmt2.010 Ar-nuar ~Qeiic;ic:r,:\<e Effluent ~elei!s~ Rl!l!'.JO~ ,:A~l=RR~). Tha C-14 prc:auittar.

and elfluent ~U"Wrrr e1.tln1a'."!; 'I','!~ bi1sea on !;?FU mi:111.,dol~~ ~r:i*Jj,;ll!:q in EPRI Ri-=port 10211CEl, "E~tlrn.;;itl(on ,..f c.irlicm-H in N!!c,ear ~,o,,.~r Plol!II\! G613E!Oll9 EfflL12r.1B, ~~ember 2010, This d11curnEK'li hi appliCAhl!'tfr:r esflr-H!1!ng G-14 (11!1!1.!!Cll! r!!IF."3e aatl*:lt:., antt-dose eompnnf!,rt!i ft:£

  • nclu:s'cn Ir. futur& SiNl ;;._..: l:~"S.

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 (C-14) production and C-14 gaseous waste effluent source terms at SONGS Unit 2 and Unit 3. C-14 effluent source terms are used to estimate radiological doses from C-14 in site gaseous waste effluents. These estimates are generated in order to meet NRC requirements to incorporate C-14 in nuclear power plant 2010 Annual Radioactive Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates are based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010. This paper is applicable for estimating C-14 gaseous release activity and dose components for inclusion in future SONGS ARERRs.

2.0 Background - NRC Updated Guidance on Reporting Routine Releases NRC regulations establish limits for radionuclides that potentially could be released from a nuclear power plant. There are a limited number of radionuclides that are released in sufficient quantities and concentrations at any site to warrant reporting to the agency. Under guidance issued by the NRC in 1974, nuclear power plants treated all radionuclides as "principal radionuclides" and performed sensitivity analysis to determine the radionuclides that had to be included in their annual reports.

In June 2009, the NRC provided revised guidance in Regulatory Guide 1.21, Measuring, Evaluating and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, (RG 1 .21) Revision 2, establishing a risk-informed approach for identifying principal radionuclides. SCE is not committed to implementation of Revision 2 of RG 1.21; SCE is committed to RG 1.21 Revision 1. However, there is new guidance in Revision 2 on the reporting of C-14 releases that is informative and useful in the preparation of the Annual Radioactive Effluent Release Report.

In Section 1.8 of Revision 2 of this document, the NRC revised guidance states, "if adopting a risk-informed perspective, a radionuclide is considered a principal radionuclide if it contributes either (1) greater than 1% of quarterly or yearly dose limits or (2) greater than 1% of the activity of all radionuclides 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 decreased to the point that carbon-14 is likely to be a principal radionuclide ... in gaseous effluents." In other words, while releases of carbon-14 have not increased, licensees' actions to reduce the quantity of radioactive effluents have been sufficiently successful that the decline in releases of other radionuclides now makes carbon-14 a more significant contributor in relative terms.

The same section goes on to state, "Carbon-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system ... Because the dose contribution of carbon-14 in liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of carbon-14 in liquid radioactive waste is not required." {emphasis added}

Section 1.9 of this report also specifies that, "The quantity of carbon-14 discharged can be estimated by sample measurements or by use of a normalized carbon-14 source term and scaling factors based on power generation ... , or estimated by use of the GALE code from NUREG-0017." {emphasis added}

The NRG has clarified to EPRI and NEI that C-14 production estimates may be made using EPRI methodology (provided in EPRI Report 1021106). The EPRI methodology was developed because the GALE code from NUREG-0017 has no provision for C-14 production or release as a function of reactor power. The EPRI methodology estimates full power C-14 production rates for BWRs and PWRs 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 specific coolant mass exposed to the core neutron flux. The EPRI report also summarizes distribution of C-14 source terms for gaseous, liquid and solid releases in BWRs and PWRs based on C-14 measurements cited in literature.

B6-2 SO 123-0DCM-B Revision 6 08-09-12

SUBJECT:

San Onofre Nuclear Generating Station Carbon-14 June 18, 2012 Production, Release and Offsite Dose Calculation Methodology 3.0 EPRI Methodology for Estimating C-14 Production Rate in PWRs Equation 1 is used to calculate the maximum annual production rate of C-14, PRMAX, in curies for each unit 17 14 14 14 (operating at full power (FP) for one year) via the 0(n,a) C and N(n,p) C reactions.

PRMAX = N

  • f0;1J!!/!th +CJ";~+ O",.!!f!t]
  • 1.0E-24 *A* M
  • 3.1536E+7, Ci/yr [Eq 1]

- - - - - 3.7E+10 where:

N = 1.27E+22 atoms 17 0/kg H20 or 4.284E+19 atoms 14N/kg-ppm N O"th = "effective" thermal neutron cross-section (Table 2),

(/Jth = "core average" thermal neutron flux at FP (Table 3), n/cm 2-s a; = "effective" intermediate neutron cross-section (Table 2), **

(f}j = "core average" intermediate neutron flux at FP (Table 3), n/cm 2-sec O"f = "effective" fast neutron cross-section (Table 2),

(f)r = "core average" fast neutron flux at FP (Table 3), n/cm 2-sec 1.0E-24 = conversion factor, 1.0E-24 cm 2/barn A = C-14 decay constant, 3.833E-12/sec M = total "active coolant mass" exposed to neutron flux, kg 3_1536E+7 = conversion factor, 3.1536E+ 7 sec/yr (365 days/yr).

3.7E+10 = conversion factor, 3. 7E+10 disintegrations/sec-Ci Table 1. SONGS Active Coolant Mass'"' and 100% Full Power Values Active Coolant Volume'"' Active Coolant Mass 1"1 Thermal Power Unit 2 784 ft"\UJ 15881.5 kq 3438 MWt Unit 3 784 ft" \UJ 15881.5 kq 3438 MWt (a) Active coolant volume is the portion of reactor coolant exposed to the core neutron flux.

(b) Active coolant volume from N-0220-030 ECN A54033 3

(c) Active coolant mass= Active coolant volume (ft ) x density correction at 100% power (20.257 kg/ft 3 )

Table 2. "Effective" Neutron Cross-Sections for C-14 Production in PWRs'a' Unit Cross-Section'u' 11 O(n,a) ,..C Reaction 1

.. N(n,p) ,..C Reaction Thermal 0.121 barns 0.951 barns 2 and 3 Intermediate 0.0291 barns 0.0379 barns Fast 0.1124 barns 0.0436 barns (a) Values from EPRI Report 1021106 based on EPRI methodology ..

(b) Thermal s0.625 eV, Intermediate >0.625 eV and < 1 Mev, Fast> 1 Mev Table 3. "Core Average" Neutron Flux Values Neutron Fluxla) BOC MOC EOC Avera~e Unit Cycle 2 2 2 n/cm s n/cm s n/cm s n/cm s FP thermal flux 3.482E+13 3.684E+13 4.355E+13 3.840E+13 U2 FP intermediate flux 1D' 2.040E+14 2.094E+14 2.129E+14 2.088E+14 C17 FP fast flux'"' 7.356E+13 7.550E+13 7.677E+13 7.528E+13 FP thermal flux 3.428E+13 3.645E+13 4.369E+13 3.814E+13 U3 FP intermediate flux 101 1.985E+14 2.064E+14 2.099E+14 2.049E+14 C17 FP fast flux 1" 1 7.155E+13 7.441 E+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 neutron flux energy groups are listed: thermal (S0.625 eV) and intermediate + fast (>0.625 eV).

(b) Intermediate= intermediate+ fast (l+F) x 0.75 (c) Fast= (l+F) x 0.25 B6-3 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 3.1 RCS Nitrogen Calculation During power operation, coolant ammonia concentrations average between 0.6 and 1 ppm.

14 14 Equation 2 estimates the C-14 production via the N(n,p) C reaction using the yearly average ammonia concentration.

RCS N, ppm= (ppm ammonia)* (14 g N / 17 g NH 3) [Eq 2]

3.2 RCSNCT Nitrogen Calculation During power operation, coolant nitrogen concentrations are estimated from Volume Control Tank (VCT) overpressure. Equation 3 estimates the C-14 production via the 14N(n,p)14C reaction using the yearly average VCT pressure, temperature and percent N 2

  • RCS N, ppm= (VCT N2 ,mole fraction)* (28.01g N2/mole) * (1 E6 mg/kg) [Eq3]

/ (18.02 g H20/mole) where:

VCT N2 , mole fraction = (VCT N2 , atm) / [Henry's Constant (N 2 ), atm- mole N2 / mole H2 0]

2 Henry's Constant, N2 = [-3.6024 * (VCT Temp, deg F) + 1284.6

  • VCT Temp, deg F + 9290.5]

atm - mole N2 / mole H2 0 (VCT N2 , atm) = [(VCT N2 , %)/100) * (VCT pressure, psig +14.7) / 14.7 3.3 Calculation Results for Estimating C-14 Production Rates Using the EPRI methodology described above in equation 1, the annual C-14 production rates in each of the unit are calculated. The results are reported in the ARERR.

For each unit, the cycle-averages of the maximum annual C-14 production rate are used for estimating gaseous pathway C-14 activity releases and dose contributions in the ARERR The maximum annual C-14 production rate values are calculated using a PWR spreadsheet developed for EPRI by NWT Corporation for utility information purposes.

86-4 SO 123-0DCM-B Revision 6 08-09-12

SUBJECT:

San Onofre Nuclear Generating Station Carbon-14 June 18, 2012 Production, Release and Offsite Dose Calculation Methodology 4.0 Estimating C-14 Gaseous Releases For PWRs, EPRI Report 1021106 summarized the distribution of C-14 in release pathways as follows:

gaseous 90% to 98%, liquid <1 % and solid 2% to 10%. The report also states that 5% to 30% of C-14 in PWR gaseous waste effluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in the food consumption cycle. EPRI Report 105715, Characterization of Carbon~14 Generated by the Nuclear Power Industry, November 1995, cited that the carbon dioxide form of C-14 averaged 20% in effluents from eight 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 estimated C-14 generated during power operation based the number of effective full power days (EFPDs) 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 EPRI Report 105715 (20%).

4.1 Equation 4 estimates the c~14 activity released, Ac.14, into the gaseous pathway during the time period for each unit.

Ac.14 = PRMAX

  • 0.98
  • EFPD I time period, days [Eq4]

where:

PRMAX = maximum annual production rate of C-14, Ci/yr 0.98 = fraction C-14 in PWR gaseous pathway releases (maximum literature value in EPRI Report 1021106, EFPD = number of effective full power days for the unit during the time period, e.g. quarterly or yearly, days Time 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 form, Ac. 14, co 2, into the gaseous pathway during the time period for each unit.

Ac.14, co2 = Ac.14

  • 0.20, Ci (for time period) [Eq5]

where:

Ac.14 = C-14 activity released into the gaseous pathway during the. time period for each unit, Ci/yr 0.20 = fraction of C-14 as carbon dioxide in PWR gaseous pathway releases (average value in EPRI Report 105715) 86-5 SO 123-0DCM-B Revision 6 08-09-12

SUBJECT:

San Onofre Nuclear Generating Station Carbon-14 June 18, 2012 Production, Release and Offsite Dose Calculation Methodology 5.0 C-14 Gaseous Releases Dose Calculations 5.1 C-14 Inhalation Dose Calculation (Reg. Guide 1.109 Eq. C-3) 4 Ci14(r,8) = 3.17 X 10 *Qi C-14 *[X/Q](r,8) where:

Ci14 (r,8) = annual average ground-level concentration of C-14 in air at location (r,8), pCi/m 3 Qi C-14 = release rate of C-14, Ci/yr, (Ac_ 14, from Eq. 4)

[X/Q](r,8) = average atmosphere dispersion factor at location (r,8), sec/m 3 (using concurrent meteorology from RETDAS program), this value is not decayed or depleted since C-14 is released as organic (CH 3 , etc) or inorganic (CO 2 ) and isotope C-14 half-life is greater than 5000 years 5.2 C-14 Food Pathway Dose Calculations

  • Per the 2011 Land Use Census, the Milk pathway does not currently exist at SONGS 5.2.1 C-14 Concentration in Vegetation (Reg. Guide 1.109 Eq. C-8)

The concentration of C-14 in vegetation is calculated by assuming 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 Guide 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) = the concentration of C-14 in vegetation grown at location (r,8), pCi/kg p = 1, fractional equilibrium ratio, (continuous release) 014 = annual release rate of C-14 as CO 2, Ci/yr (Ac-14, co2 from Eq. 5) 3

[X/Q](r,8) = average atmosphere dispersion factor at location (r,8), sec/m (using concurrent meteorology from RETDAS program) 0.11 = fraction of the total plant mass that is natural carbon 0.16 = concentration of natural carbon in the atmosphere, g/m 3 7

3.17 X 10 = 1E+12 pCi/Ci

  • 1E+3 g/kg / 3.15E+ 7 sec/yr 5.2.2 C-14 Concentration in Milk (Reg. Guide 1.109 Eq. C-10) cm 14 (r,8) = Fm
  • Cv14 (r,8)
  • O,
  • exp-J..;f, where:

cm14(r,8) = the concentration of C-14 in milk at location (r,8), pCi/liter

  • cv14 (r,8) = the concentration of C-14 in animal feed, for C-14 this is the concentration of C-14 in vegetation grown at location (r,8), pCi/kg Fm = average fraction of daily intake of C-14 which appears in milk, Reg. Guide 1.109 Table E-1, (carbon = 1.2E-2)

O, = amount of feed consumed by animal per day, Reg. Guide 1.109 Table E-3, (cow= 50 kg/day) exp-,\tt = 1, due to C-14 half-life greater than 5000 years 86-6 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 5.2.3 C-14 Concentration in Meat (Reg. Guide 1.109 Eq. C-12)

CF14 (r,8) = Ft

  • cv14 (r,8)
  • O,. exp-Jo.;t, where:

cm14(r,8) = the concentration of C-14 in animal flesh at location (r,8), pCi/kg Cv14 (r,8) = the,concentration of C-14 in animal feed, for C-14 this is the concentration of C-14 in vegetation grown at location (r,8), pCi/kg Fm = average fraction of daily intake of C-14 which appears in each, kilogram of flesh, Reg. Guide 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/day) exp-Aitf = 1, due to C-14 half-life greater than 5000 years 5.2.4 Annual C-14 Dose by Food Exposure Pathway (Reg. Guide 1.109 Eq. C-13)

Leafy Vegetables = DF1c-14ja

  • U\
  • f 9
  • Cv14 (r,8)

Milk = DF1c-14ja

  • uma. cm14(r,8)

Meat = DF1c-14ja

  • u\
  • cF14 (r,8)

Non-Leafy Vegetables = DF1c-14ja

  • U\
  • f,
  • Cv14 (r,8) where:

DF1c-14ja = C-14 dose conversion factor for organ U) and age group (a)

Reg. Guide 1.109Tables E-11 through E-14 where the following are from Reg. Guide 1.109 Table E-15:

U\ = ingestion rate of non-leafy vegetables by age group (a), kg/yr fg = 0. 76, fraction of non-leafy vegetables ingested grown in garden um = ingestion rate of milk by age group (a), liters/yr Fa U a = ingestion rate of meat by age group (a), kg/yr Ula = ingestion rate of leafy vegetables by age group (a), kg/yr f, = 1.0, fraction of leafy vegetables ingested grown in garden 5.2.5 C-14 Total Dose The C-14 total dose in mrem at receptor (r,8) is the sum of the exposure pathways which exist at that location per the Land Use Census. The highest receptor annual dose, age group, critical organ, sector and exposure pathway are reported in the ARERR.

86-7 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 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 Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluation Compliance with 10 CFR Part 50, Appendix I, Revision 1 6.3 EPRI Report 1024827, Carbon-14 Dose Calculation Methods at Nuclear Power Plants, April 2012 6.4 EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010 6.5 EPRI Report 105715, Characterization of Carbon-14 Generated by the Nuclear Power Industry, November 1995 6.6 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 Unit 2 Cycle 17 6.8 M-38098 Rev. 29, Plant Physics Data Book Unit 3 Cycle 16 6.9 Radiological and Dose Assessment Software (RETDAS), Version 3.6, Canberra Industries, Inc.

B6-8 S0123-0DCM-B Revision 6 08-09-12

February 2001

SUBJECT:

Offsite Dose Calculation Manual Changes Safety Evaluation for Modifying References to 10 CFR 50.59 INTRODUCTION Ih 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," Section 50.59, "Changes, Tests and Experiments,11 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, under certain conditions. The rule was promulgated in 1962 and revised in 1968.

A proposed new rule was published for comment in October 1998. Following consideration of public comments, on October 4, 1999 the NRC issued a final revision 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 revised rule, the Nuclear Energy Institute (NEI) submitted a guidance document for the implementation of 10 CFR 50.59 and requested NRC endorsement through a regulatory guide.

Subsequently, NEI submitted document NEI 96-07 for endorsement.

According to Regulatory Guide 1.187, Revision 1 ofNEI 96-07, "Guidelines for 10 CFR 50.59 Evaluations,"

dated November 2000, provides methods that are acceptable to the NRC staff for complying with the provisions of 10 CFR 50.59.

The new 10 CFR 50.59 (c) (4) states: The provisions in this section do not apply to changes to the facility or procedures when the applicable regulations establish more specific criteria for accomplishing such changes.

NEI 96-07 clarifies that statement to include 'Offsite Dose Calculation Manual changes controlled by technical specifications_.' San Onofre Licensee Controlled Specification 5.5.2.1.1 provides the specific criteria for accomplishing ODCM changes.

5.5.2.1.1 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
1. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s);
2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 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 setpoint calculations.
3. Documentation of the fact that the change has been reviewed and found acceptable.
b. Shall become effective upon review and approval by the Vice President-Nuclear Generation or his designee.
c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or 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 markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e. ** month and year) the change was implemented.

B7-1 S0123-0DCM-B Revision 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 6.3 .1.1.a will be changed as follows:

from:

"A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59";

to:

"A summary of the evaluation that led to the determination 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 effluent 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 Information 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 10 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 regulatory 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.

B7-2 S0123-0DCM-B Revision 9 08/2016

February 2001

SUBJECT:

Offsite Dose Calculation Manual Changes Safety Evaluation for Modifying References to 10 CFR 50.59

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

No.

The Licensee Controlled Specifications provide the guidance necessary to ensure that ODCM changes reflect the requirements of the specific controlling regulations. The ODCM has no effect on the probability of accidents and therefore this change will not increase the probability of occurrence of any previously evaluated accident.

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

No.

The proposed change is an administrative change that does not affect operation of equipment or the facility. It does not influence any credible accident at Units 2/3 - a release due to leakage or failure of a radioactive waste system (section 15.7.3.2); and the postulated failure of a liquid tank (section 15.7.3.3). As such, this activity cannot increase the consequences 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.

The ODCM has no effect on the operability of any equipment. It provides guidance for determining whether some equipment important to safety is operable and in some cases provides compensatory action to mitigate for inoperable equipment used to collect, transfer, treat, or discharge radioactive effluents. Therefore this change has will not increase the probability of occurrence of a malfunction of equipment important to safety.

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

No.

The ODCM does not alter operation of important to safety 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 of a different 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 different type than any evaluated previously in the safety analysis report.

B7-3 S0123-0DCM-B Revision 9 08/2016

February 2001

SUBJECT:

Offsite Dose Calculation Manual Changes Safety Evaluation for Modifying References to 10 CFR 50.59

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

No.

The 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 of screening questions that ensure that ODCM and design changes are reviewed for their effect related to applicable regulations and controlling documents.

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 basis for technical specification?

No.

The Licensee Controlled Specification currently requires and will continue to require (1) justification for ODCM changes, (2) no adverse impact to effluent controls, and (3) documentation of adequate review for acceptability. Currently, changes to the ODCM are evaluated 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. The proposed process will specifically callout each regulation against which changes to the ODCM are to be evaluated. Evaluating ODCM changes against these criteria has been, and will continue to be, the standard. The new method simply will ensure that all applicable requirements are considered. Chemistry procedures changes and review question development are in progress that will ensure the Technical Specification requirements are met and that there is 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 effluents as required by 10 CFR 20 and 10 CFR 50.

87-4 SO 123-0DCM-B Revision 9 08/2016 L_

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 B8-1 S0123-0DCM-B Revision 9 08/2016

SUBJECT:

Correlation - Effluents and Environmental Data Nov.ember 4, 2014

6. Cl. METZ

SUBJECT:

Co1119lation - Effluents and Environmental Data

REFERENCES:

1. Memorandum M Goeders to EM Goldin, February 28, *1994, Documentation of the Correlation Study for 1992
2. Memorandum for Fite, EM Goldin, February 13, 2004, Compllanoow1th 10 CFR 50, Appendix I, Seclion IV B, AR 040101459-1
3. $0123-JX-1.10, Review, Analysis and Reporting of Radiological Environmental Monitoring Program (REMP) Data, Rav. 10
4. 2013 Annual Radiological Environmental 0!X)ratlng Rep,ort, San Onofre Nuclear Generating Station Units 1, 2, & 3, May 2014 OBJECTIVE: Rsgu!aoons ln 10 CFR 50, Appe11dlx I, Sedon IV B, Subparagraph 2 requires

data on mea5urab!e levels of radiation and radioactive materlals in lhe environment to evaluale the relationship between quantities of radioactive material release-0 In emuents and resultant radiation doses to individuals ..*" This memorandum reviews the evaluation of the relallonship bsl1N8en emuenl releases and doooa as assayed by the Radiological Environmental Monltorlng Program (REMP).

DISCUSSION In the 1990's, each year an analysis was performed to delemiine U,e relationship between effluent releases and environmental sample results. An example of a very rigorous calculallon may be found in Referenoe 1. That level of evaluation was determined to be unnecessary (Reference 2) as long as actioM were in place to trigger an e\"aluetion if environmental samples exceeded some predetermined values_ lhis position was developed becaus.e:

  • Based on en anecdotal industry survey, many nuclear plants in !tie US do not conduct any speclflc eva.luatlon on an annual oosis (existing REMP and Effluent program con1rols satisfy the r,a,q ulre rnent)
  • REMP samples rarely indicate any detectable plant-related radioactivity in the plant environs (i.e. there can be no public dose if 11,ere is no detectable radioactivity in Ille lmmecBtate environment)

" Many plants b'lgger .an evaluatloo when REMP samples exceed invesligalion levels In order to ensure that a proper evaluation would be completed If necessary, Reference 2 recommended procedure changes to incorporate aclfon levels. That was oompleted and the following requirements are in place:

Prooodure S0123-iX-1.10 {Reference 3) lnclLJdea the following requirements:

B9-1 S0123-0DCM-B Revision 9 08/2016

SUBJECT:

Correlation - Effluents and Environmental Data B. D. Metz Correlation - Effluents and EJwironmenta1 Data Novomber 4, 2014 6.2.2.2.4 IF any REMP sample results exceed admlnialratlve limits and are verified lo be above the dBtecti<>n limit, lHEN the Radiological EffllJent and Environmental Spe-clallst or designee SHALL either rosolve the issue by lab-Oratory recounts or additional sampling, or generate a Notification \*llH1 a task assigne,d to the Radiolog1cal Effluent and Environmental Speeoialiat or desi-gnee fo e'llaluate tl:le data.

6.2.2.2.5 If any REMP sample results exceed tt1e administrative limlt{s) and the results are aloo greater then the detectlon limits tllon generate an additional task assigned to Radiation Protection requesting a peer check of the Radiological Effiusnt and Englneering Specialisls' evaluation.

6.2.2.2.6 A summary of tlie data evaluaUon shall be included rn the Annual Radiological En\Jironmental Operating Report (AREOR}.

6.2.2.2.7 The lnvestigalion SHALL compare 1he expected concentration of radlonuclides in REMP samples to that actually observed, or provide a basis for explaining why lh-e deteciion of radlonuclfdes ln !he REMP sample(s) should be expected at the observed levels.

These procedural requirements adequately implement the regulatory requirements for an evaluation of the relationship, should one ever need to be completoo.

SONGS COMPLIANCE FOR 2D13 The 2013 Ar;nual Radiological Environmental Operating Report (Reference 4) lnclude-d the following verbiage (page 29):

L. Correlatio11 of EUluent Co11cl!lntrat1011s. to Concantratlons in tho Environmerit In ac(;()rdanoe with 10 CFR 50 Appendix r, lV.b.2 data on measurable levels or radiation and rad[oa.G!ive materials In ihe environment have been ovaluated to determine the relationship between quanti1ies of radioactive material releasad In e!fl.uents and resultant radiation doses to individuals from principal pathways of exposur~.

The REMP soil Cs-137 levals In the control and indicator samples are statistically equivalent, leading lo the conclusion !hat Cs-137 tl'I so11 is attributable to residual fal!oul from extgmal anthropogenic factom such as nuclear weapons testing, Chernob'.)li, and Fukusl1ln1a Dai-lchi.

Dala from 2013 contimm to support the historical conclusion thal the measured concentration of 1-131 in kelp ls notiricroasing near SONGS, and Is not sfalfstically higher around SONGS than It Is at the control locations. 1*131 in kelp is due to the release of medical administraiions to the ocean from sewage ltea1ment iacilltles. The emuent based correlation calculaUon indicafas that 1-131 activity In kelp attributt'lbte to the operaUon of SONGS would be undeteclabla an{! the resultant doses to ir..oividua!s woulci be negligible.

89-2 S0123-0DCM-B Revision 9 08/2016

SUBJECT:

Correlation - Effluents and Environmental Data

13. D. Me~ Correlation - Effluents and Etwlronmenlal Data November 4, 2014 The data from air samplers close lo SONGS, the data from air samplers funher away, and the data fmm lhe Ocaansfoe control sampler are slatistlcal[y equaL This wording addresses lhe questiori regardlrig !he evaloa.tlon but not very clearly, Therefore, the following sectkm, applicable to the calenoar year 2013, Is recommended for Mure AREORs:

REMP samples, boll1 terrestrial and marine, indicated no accumulatloo of plant-related radioactivity in the environs. No samples, as shown in Table &2, excilladoo Investigation levels and, in fact, all samples with detectable actMty were no! stati:slically different from controls and were therefore attr1buted to non-plo1nt-related souroes - past nuclear

\veapom, fallout, Chernobyl, Fukushima, and medical lodfne releases in a.ewerage. As such, the operations of SONGS did not have any measurable effoot on the environment.

The regulatory requirement to evaluate the ralatlonshlp belween quantifies of r.a.dioactlve materials released in effluents and the resultant radlaUon doses. to individuals may be summarized by th.a following conclusion:

Effluent program releases are evaluated annually lo determine tha receptorr(s) with 1.he highest hypolhetical dose. REMP samp!l)s collected lhrough the year indicated no slgnmcant aooumulaUon of plant,related raoioactlv.lly above oonlrol localions, therefore prmiiding assuranoo that lhe emuent program projections are consistent wiltl radiological environmental measl!rements. The oonoonlratioos of plant-related radioactivity In environmental samples were less than expected ba,sed on effluent releases, further demonstrating program conservatism.

Prepared by November 4, 2014 Eric Goldin, CHP Reviewed by cc: C. A. Cook J.B. Jaol<e J.B. Moore (BHI)

.... 3 ..

B9-3 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 Controlling Location Factors Tables 2-7 and 2-8 (Sollih Varel Facility and North

[ndustrial Area} and Associated Ri Tables in Appendix A lrom the ODCM

References:

1. 12/11/94 EM Goldin to PK Chang, Soutnyarc! Facility Dispersion and Deposition Factors for Potential Normal Gaseous Effluent Releases; Detemiination of Compliance with 10 CFR 50, Appendix: I
2. 2f7/07 JVV Scott to D Dick, 2007 Dose Parameters for SONGS Unit 1 and Units 213
3. 2/11/08 .Nv Scott to D Dick, 2008 Dose Parameters for San Onofre Nuclear Generating Station
4. 2/9/11 .JW Scott to L Mccann, 2011 Dose Parameters for San Onofffi Nuclear Generating station South Yard FacDity and North Industrial Area
5. NRG Regulatory Guide 1.21, Rev. 1, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste

Background:

The original Offsite Dose calculation Manual (ODCM) applled to SONGS Unit 1 only. Once Units 2/3 were operating, a separate ODCM was created for those two newer units. In later years, dose parameterta!Jles (Ri) and effluent calcufalion provisions were added to the ODCM for the South Yard Facility (SYF}, see Reference 1 for the earliest analysis. Eventually after Unit 1 was permanently retired from service, the Unit i ODCM was combined with the Units 213 ODCM and a sitewide document was created (References 2 and 3). Tile area that housed Unit 1, designated as the North Industrial Area or N[A after Unit demolition, was used for potentially contaminated equipment staging, sucl1 that eventually dose parameters tables for the NIA were included in the single ODCM in place of the Unit 1 tables.

Discussion:

In late 2014, radioactively contaminated equipment was removed from the NIA and that area was released from Restricted Area {RA) designation_ Some of the SYF was also removed from RA status to support equipment staging for SONGS decommissioning. There is no longer an airborne radioactive effluent source at either the NLA or the SYF. Therefore, there is no need for Controlling Location Factors or ~ tables in tile ODCM for these two areas.

The Glossary in the most recent Reference 5 (Revisioo 2, 2009) defines tile points that require monitoring:

significant release point-Any location, from which rndioac,tive material is released, that contributes greater than 1 percent of the activity discharged from all the release points fur a particulru: type of effluent considered. Regulatory Gtude L 109 lists the three types of effluent as (1) liquid effiuenls, (2) noble gases discharged to the atmosphere in gaseous radioactive waste, and (3) all other rndionudides disd.w:ged to the atmosphere in gaseous radioactive waste..

810-1 SO 123-0DCM-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 Even tile Revision 1 (1974) of that Regulatoly Guide noted that:

Cool:imimis: monitoring iliould be ccmd1.11.."1ed aloog principal gaseous effi=t disclm-ge ~

Since tile NIA no longer has any radioaclive material othertt'lan ti1e Unit 1 Reactor Pressure Vessel, a sealed soUd radioactive waste container and tile ISFSI, housing only sealed airtight canisters, and the SYF is no longer used for any significant radioactive equipment refurbishment, neither of t11ese localions is considered a "significant release poinr nor a "principal discharge path" and therefore do not require airborne effluent monitoring. As such, there is no need for controlling location factors or dose parameters specific to either area in the ODCM. Note that Reference 4 pointed out that there vo1ere no airborne effluent releases from t11e SYF even in 2011 during supporting operations of Units 213.

CONCLUSION:

Remove the NIA and SYF Controlling Locaoon Factors and Hi tables from tile SONGS ODCM.

other SYF and NIA dose calculation parameters may remain in tile ODCM in case some radio[ogical work is conducted in eitl,er location in the ruture during decommissioning support activities. When tlle facility ls no longer going to be used to support radiological work, the SYF and NIA offsite dose calculation provisions may IJe removed as well.

810-2 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 TABLE 2-7 SOUTH YARD FACILITY CONTROLLING LOCATION FACTORS 1 I:kRikWk Radionuclide mrem/yr per µCi/sec Use:

H -3 1.43E-3 R: Camp Mesa Cr-51 5.65E-2 R: Camp Mesa Mn-54 1.21 E+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 1.08E+O R: Camp Mesa Cs-137 7.11 E+1 R: Camp Mesa Ba-140 2.35E+O R: Camp Mesa Ce-141 7.?0E-1 R: Camp Mesa Ce-144 1.48E+1 R: Camp Mesa I -131 1.77E+1 R: Camp Mesa I -132 2.18E-1 R: Camp Mesa I -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: Camp Mesa These values to be used in manual calculations are the maximum I:kRikWk for all locations based on the most restrictive age group.

810-3 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 TABLE 2-8 NORTH INDUSTRIAL AREA (UNIT 1) CONTROLLING LOCATION FACTORS 1 LkRikwk Radionuclide mrem/yr per µCi/sec Use:

H-3 5.46E-3 A: Camp Mesa Cr-51 2.42E-1 B: Camp Mesa Mn-54 5.54E+1 B: Camp Mesa Co-57 1.17E+1 B: Camp Mesa Co-58 1.80E+1 B: Camp Mesa Co-60 7.82E+2 B: Camp Mesa Sr.,89 1.82E+1 Q: SC Res. With Garden Sr-90 7.16E+2 Q: SC Res. With Garden Zr-95 1.93E+1 A: Camp Mesa Nb-95 7.68E+O B: Camp Mesa Ru-103 6.80E+O A: Camp Mesa Te-129m 9.04E+O A: Camp Mesa Cs-134 2.32E+2 B: Camp Mesa Cs-136 5.17E+O B: Camp Mesa Cs-137 3.40E+2 B: Camp Mesa Ba-140 9.07E+O A: Camp Mesa Ce-141 3.01E+O A: Camp Mesa Ce-144 5.68E+1 A: Camp Mesa I -131 6.77E+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+O A: Camp Mesa UN-ID 3.02E+1 B: Camp Mesa These values to be used in manual calculations are the maximum LkRikWk for all locations based on the most restrictive age group.

B10-4 S0123-0DCM-B Revision 9 08/2016

RADWASTE PROCESSING TECHNIQUES AIRBORNE EFFLUENT EVALUATION RADWAS1'E PROCESSING TECHNIQUES Am.BORNE EFFLUENT EVALUATION December 20, 1999 INTRODUCTION Decommissioning of Unit 1 will involve the removal of equipment, systems, and structures that are contaminated or have previously been contaminated or exposed to radioactive materials.

Dismantlement and disposition of the resultant materials and wastes may include physically cutting the components, decontaminntion of the items, and packaging for shipment and disposal.

This Memo to File evaluates the potential for creating radioactive effluents (airborne and liquids) from several preparation and packaging methods. This memo does not address processing or handling of mixed wastes (both radioactive and hazardous). This memo does not address work activities other than those performed at previously analyzed and established locations; it does not,

. for e:<ample, consider work performed outside the owner controlled area located on the Grant of Easement. This memo provides recommendations to ensure compliance with regulatory requirements for the control of radioactive effluents and a generic ~aluation of those methods with regards to U1e requirements of IO CFR 50.59.

  • DISCUSSION Title 10 ~o the Code of Federal Regulations Part 50 Appendix A.~pecifies the design criteria for construction and operation of a nuclear power plant. In particular, General Design Criteria 63 and 64 respectively require monitoring of radioactive waste systems and associated handling areas and effluent discharge paths. There are also several regulatory guidance documents ( NUREG*0472, NUREG-0800 section J 1.4, and Reg Guide 1.143) that reiterate the need for monitoring either the waste treatment systems' discharge or the exhaust ofbuilding(s) that house those systems.

Treatment techniques used to reduce or remove radioactivity from contaminated materials and equipment are considered rad\vaste processes. As such, either the exhaust from those systems used to perfonn the processing or treatment or the exhaust from the buildings in which the systems are housed must be monitored. Previous documents1* 2 generated at the site have also evaluated radwaste treatment techniques and provided recommendations for effluent controls.

The reader shoi1ld review those documents in addition to this memo for guidance; the constraints established in reference l are considered appli~ble.

Whenever possible, radwaste processes (e.g. treatment, decontamination, ;µ1d packaging) shall be conducted inside buildings that exhaust through an ODCM*credited release point and are monitored and sampled isokinetically. At the same time, the existing buildings cannot accommodate all of the components being removed or the processing equipment. It is likely that temporary work enclosures will be established outside of the existing buildings with monitored HVAC system (radwaste auxiliary building, containment). Unfortunately, it is not always practical to duct the exhaust from the work enclosure to a monitored building for discharge through the Plant Vent Stack. "'

  • B11-1 S0123-0DCM-B Revision 9 08/2016

RADWASTE PROCESSING TECHNIQUES AIRBORNE EFFLUENT EVALUATION Because of the time since shutdown (November 1992), noble gases are no longer produced and the radioiodines have decayed away. Work activities, particularly those that use mechanical or abrasive methods, can generate and resuspend radioactive particulate matter. To remove the particulate matter prior to discharge to atmosphere, HEPA units shall be placed on the exhaust from each work enclosure or on the discharge from the equipment itself. The HEPA units are commercially rated at a minimum of 99% efficiency and must be periodically verified to ensure integrity and loading within design specifications. For work performed in temporary enclosures or unmonitored buildings, surface contamination levels shall be maintained withln the limits established in the referenced design calculation for a closest analyzed location2* For destructive decontamination methods, the contamination limits for the CO2 blast room at the South Yard Facility (sheet 9v) should be applied. According to the Unit l Decommissioning Project radwaste team3, total contamination levels are not expected to ex~ed 1E6 dpm/100 cm2*

As discussed previously, the only anticipated airborne effluents attributable to these work activities are in particulate form. Regulatory Guide 1.21 and Regulatory Guide 1.97 note that instantaneous monitoring for particulate matter or radioiodines is not typically considered practical due to technological limitations. Accordingly, sampling will be used instead of monitoring to determine whether or not there has*been a release of airborne effluents due to rad waste processing and handling, and to quantify the amount of activity released. Contjnuous samples for particulate matter will be taken downstream of the HEPA units for each work enclosure and analyzed weekly as an effluent sample. Any activity detected will be report_ed to the NRC in the Annual Radioactive Effluent. Release Report in accordance with 10 CFR 50.36a.

Work activities that generate or involve liquids shall include measures to control spills and prevent an unmonitored release to local area drains and subsequently the unrestricted area. As appropriate, measures may include temporary benns or s~ondary containment. Waste water generated by decommissioning activities shall be disposed of properly in accordance with established Station procedures to prevent violation of either NRC requirements or conditions of the NPDES permit. In addition, care must be taken to prevent the inadvertent contamination of radioactively "clean" systems like domestic water supply and the sanitary sewer system.

Radioactive liquids or wastewater generated from a radwaste treatment process shall not be to released the storm or yard drains.

Written procedures must be developed for the perfonnance of the activities discussed in this document. Additionally, if a work location i~ established or a treatment technique is used for a period tliat extends (or is anticipated to ex:tend) beyond the Defueled Safety Analysis Report (DSAR) update cycle (2 years), the DSAR should be updated to reflect the new techniques or work areas not already.described. Changes to treatment techniques or systems (equipment,

.piping) that are used to transfer, treat, dispose of. or store radioactive wastes require a review of this evaluation or performance ofa separate eyaluation per NRC lE Bulletin 80-18 and 10 CFR 50.59. Failure to review and modify this evaluation, establish procedures, or update the DSAR may result in violation ofregul~tory or administrative requirements.

B11-2 S0123-0DCM-B Revision 9 08/2016

RADWASTE PROCESSING TECHNIQUES AIRBORNE EFFLUENT EVALUATION TECHNIQUE DESCRIPTION Am.BORNE LIQUID COMMENTS MONITORING MONITORING" Splitter Mechanical snwing/cutting to open y* N pipes >3" in diameter Shenring, sawing, McchaniClll process to adjusl size of y* N Work enclosure torch culling structural steel, piping, conduit. cable trays, sheet metnl, w1d concl'l!te Abrnsive blnsting Physical renKIVW of s1ufnce cooling y* N Verify booth integrity.

nnd/or contn.'llination from carbon Perform HEPA checks.

steel. typically 2** I.s** 1O' sections. May be huznrdou..~ waste.

Bead blnsting Physiool process to remove surfnec Y' N Verify booth integrity.

coaling aml/or contamination from Perfonn HEPA checks.

non-ferrous motcrinls, small po."ts etc Mny be hazardous waste Wil:lhing surface Cleaning using mild liquid chemicals N y treatment on non-ferrous materials. StnDII parts, instrument pnru, etc Surface wiping Mllllunl removol of contnminotion N y Mny create mixed waste from flat surfac1.-s Crushing metal Mechanicnl crushing of <Io* CS & y* N Work enclosure.

SS pipe, 200 tons Perform HEPA check:;.

Concrete rubbliz1.-r Mechnnienl crushing of concrete y* N Dust control mtasures blocks containing rcbnr ..

Shredding (DAW) Mecbanicol shn.'l!lling of soft y* N Pcrfonn HEPA checks mntcrfals Ccmpac:tion Volume reduction of DAW etc in 55 y* r N Petfonn HEPA cbecks.

or I00 gol drums BS part of pnckaging Use estnblished locations Hnndling Hoppers, conveyors, forldifts for N N Use established controls moving equipment, waste, containers e!c from one location to another Container Routine maintenance to ensure y* N Use estnblishc:d controls nnd refurbishment container integrity locations

  • Monitored HVAC or local air snmplcs
  • Monitored HVAC required
  • Monitored release point or routing to liquid rodwastc l!'Clltrnelll. or spill prcvcnlion measures The ,bove t,ble o,mm,rl,es the prooesses '°"'""d mthis memo to t.}Ji.ll, r,~,~~~~ Jw&E4 cc: D. Dick, Effluent Engineering L. Bray/S. Enright, Decommissioning M. J. Johnson, Environmental Protection E. M. Goldin, HP&E BJh)Y HP&E files Cl>M 811-3 S0123-0DCM-B Revision 9 08/2016

RADWASTE PROCESSING TECHNIQUES AIRBORNE EFFLUENT EVALUATION EFFLUENT SAFETY EVALUATION I. Mny the proposed nctivity incre.'lse the probability of occurrence of nn accident evnlunted previously in the SAR?

NO.

The only remaining Unit l accident that is evaluated in the DSAR is the Fuel Handling accident.

The proposed decontamination and packaging activities will not affect the Fuel Handling accident nor can they increase the probability of the accident occurring.

2. May the proposed activity increase the consequences of :m accident evaluated previously in the SAR?

NO The proposed activities to dismantle equipment at Unit 1 and, as necessary, reduce or remove radioactivity from the materials prior to final disposal are similar to existing decontamination techniques used at SONGS. These radwaste processes involve activity inventories well below that considered in the Fuel Handling scenario at Unit I. Furthennore, the dose consequences of the Fuel Handling accident are in no way affected by the proposed activities.

3. May the proposed activity increase the probability of occurrences of n mnJfunction of equipment important to safety evaluated previously in the SAR?

NO The Unit 1 DSAR describes existing techniques for decontamiiiation used at SONGS. None of the systems or equipment used to perform these processes is considered important to safety. As such, there is no change in the probability of important to safety equipment malfunctioning nor is there any change in failure modes of such equipment. .1 *

4. May the proposed activity increase the consequences of malfunction of equipment imp_ortant to safety evruunted previously in the SAR?

NO The Unit 1 DSAR describes existing techniques for decontamination used at SONGS. None of the systems or equipment used to perfonn these processes is considered important to safety. As such, the proposed activities cannot increase the consequences of a malfunction of important to safety equipment *

5. Mny the proposed activity crente the possibility of an accident or a different type than nny evaluated previously in the SAR?

NO Neither the Unit 1 DSAR nor the Units 2/3 lJFSAR consider removal of activity from equipment and/or materials as credible initiators of an accident. In particular, design calculation N-0320-0073 considered these activities within the Unit l Protected Area, in addition to the Units 2/3 Protected Area and the South Yard Facility. The design basis fire involved the HEPA unit.9n*the exhaust from the work enclosure. As such, this accident type has been previously considered and evaluated in theDSAR.

811-4 S0123-0DCM-B Revision 9 08/2016

RADWASTE PROCESSING TECHNIQUES AIRBORNE EFFLUENT EVALUATION

6. Mny the proposed activity crentc the possibility of n malfunction of equipment important to safety of n dilTerent type than evalunted previously in the SAR?

NO Equipment used to reduce or remove activity from materials is not considered important to safety.

The proposed radwaste processes cannot therefore create the possibility of a malfunction of equipment different from scenarios previously considered in the DSAR.

7. Does tile proposed activity reduce the margin of safety as defin~d in the bnsis for any technical specilicntion?

NO Radwaste processes performed in a building with drains to the liquid radwaste treatment system and nn HVAC that is discharged through the Plant Vent Stack are already monitored in accordance with the station's effluent control program.

Work activities that arc perfonned in temporary enclosures, or outside of buildings with a monitored HYAC system require implement of other measures and controls. In all cases where liquids are used or waste is generated, spill control measures will be implemented and e.xisting Station procedures foUowed for disposal. For teclmiques that may generate particulate activity, local air sampling will be performed in the immediate area or at the exhaust from the temporary work enclosure. Any use of HEP A filters will also require periodic checks to verify the filters' integrity and performance within design specifications. Closed loop systems or containment booths will likewise be verified periodically lo be intact and without significant leakage. Dust control measures and worker protection procedures will also be impl~inented, as appropriate, to minimize the spread of contamination and the release of activity.

The South Yard Facility calculation N-0320-007 considered the consequences of working on radioactively contaminated material inside and outside monitored buildings. Contamination levels on equipment and materials handled and processed using the proposed techniques will be maintained below the limits established in the calculation.

Given the constraints discussed above, the limits of IO CPR 20 and the Unit 1 Offsite Dose Calculation Manual will not be exceeded. Therefore, there is no reduction in the margin of safety for any licensing specification.

8. Docs the proposed change foreclose a decommissioning option?

NO.

The proposed activity does not affect the configuration of the plant or the safe maintenance of the spent fuel. The radwaste treatment techniques considered in the Memo to File may be used during the decommissioning process.

9. Does the proposed change involve a mnjor structural change to radioactive components of the facility?

NO No physical equipment additions or removals are implemented with this change. Temporary work B11-5 S0123-0DCM-B Revision 9 08/2016

RADWASTE PROCESSING TECHNIQUES AIRBORNE EFFLUENT EVALUATION enclosures may be erected to house the processing equipment and work activities but these will not involve a major structural change to radioactive components in the facility.

10. Does the proposed change substantially increase the cost of decommissioning?

NO.

The handling and disposition of equipment, systems, and structures removed from Unit 1 is an integral part of decommissioning. As such, the processing ofradwaste should have been included in decommissioning cost estimates.

11. Does the proposed change cause any significant environmental impact not previously reviewed?

NO The proposed work activities will be performed in accordance with existing Station programs for the control of hazardous and radioactive effluents. There will be no measurable impact to the environment or the health and safety of the public.

12. Does the proposed change violate the tenus of the existing license or IO CFR 50.59 as applied to the existing license?

NO The radiological effluent controls program is contained predominantly in the ODCM. The proposed processing of radwaste will be perfonned to ensure the contr9l of radioactive effluents and hazardous materials. The change is also justified per IO CFR :so. 59 in this document.

REFERENCES .1'

!."Evaluation of Solid Radwaste Processes and Decont~ation Techniques", Memo to File by E.M. Goldin, dated 12/4/1995 2.Airbome Source Term for South Yard Shops Facility and Outdoor Activities, NEDO calculation N-0320-007, revision A, dated 4/16/95 3."Re: Effluent Control Issues" email from Linda Bray to Kathy Yhip and Daryl Dick, dated 6/15/1999 811-6 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING HP&E Position Paper September 27, 2000 1NTR0DUC110N San Onofre Unit 1 ceased commercial operation in November 1992 and was placed in SAFSTOR until June 1999 when decommissioning began. In the time since shutdown, noble gases are no longer produced and radioiodines have decayed away. Releases from the waste gas system are no longer performed and the current sources to the plant vent stack include the spent fuel storage building, containment, and the radwaste auxiliary building. Since 1994, there has been no detectable beta-gamma activity in the particulate samples taken from the plant vent stack'.

Active decommissioning of the Unit involves dismantlement of systems and equipment for disposal in addition to demolition of various structures. As warranted, components and structures are decontaminated by a variety of methods prior to disposal off-site. Currently, handling and processing of contaminated material and/or equipment does not require effiuent controlsi. 3 unless removable particulate activity levels exceed I.SES dpm/100 cm2 and/or removable iodines exceed 2.8E4 dpm/100 cm2*

This memorandum evaluates the potential for airborne radioactive effluents from the various decommissioning and decontamination techniques and recommends measures to control and minimize unmonitored releases. It does not consider the use of explosives or wrecking balls for demolition nor does it address the potential for creating hazardous waste/effiuents from processing of mixed waste.

DISCUSSION Regulatory Requirements Title 10 to the Code of Federal Regulations Part 50 Appendix A specifies the design criteria for construction and operation ofa nuclear power plant. In panici.Jlar, General Design Cri.teria 63 and 64 respectively require monitoring of radioactive waste systems and associated handling areas and efiluent discharge paths. There are also several regulatory guidance documents ( NUREG-0472, NUREG-0800 section 11.4, and Reg Guide 1.143) that reiterate the need for monitoring either the waste treatment systems' discharge or the exhaust ofbuilding(s) that house those systems.

Using the data collected from monitoring and routine sampling of the effiuent release points, total activity released and the resultant potential dose to a member of the public is then reported to the NRC in the Annual Radioactive Effiuent Release Report as required by IO CFR 50.36a and I 0 CFR 50 Appendix 1.

B12-1 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING Decontamination techniques used to reduce or remove radioactivity from contaminated materials and equipment *are considered radwaste processes. Radioactive waste treatment systems or methods are also described in the DSAR as required by IO CFR 50.34(b). Changes to systems or techniques used to collect, transfer, process, or dispose of radioactive wastes must be evaluated in accordance with 10 CFR 50.59 and reported in the Annual Radioactive Effluent Release Report as required by specification 6.3.3 of the Unit I Offsite Dose Calculation Manual (ODCM).

Airborne Control$

Whenever reasonably achievable, radwaste processes shall be conducted inside monitored buildings. t Liquids should be removed or drained prior to dismantling equipment or structures. If liquid cannot be removed prior to dismantling or if liquids are used in the treatment, decontamination, or demolition technique, spill control measures (berms, drip collection bags, etc) must be implemented to prevent unplanned, unmonitored liquid releases. Surface wetting during building demolition should be perfonned so that the surface is dampened but no run-off or puddles are generated.

  • Work processes pe1fo1med in monitored building/structure There are no effluent control restrictions whenever the work is performed in a monitored building.

Containment, the spent fuel building; and the radwaste auxiliary building are designed to ensure the building's atmosphere is vented through the Unit I Plant Vent Stack, the Offsite Dose Calculation Manual (ODCM)-credited airborne release point. If negative pressure in a monitored building is lost, work on contaminated equipment above 25,000 dpm/100 cm2 loose surface contamination (fixed plus removable contamination ;,:250,000 dpm/100 cm2) should be delayed until negative pressure can be restored and maintained, or stopped until contamination control measures required for work outside of monitored buildings are implemented.

Work processes performed outside of n monitored building/structure From time to time, some of the components being removed or the processing equipment cannot be physically accommodated within the existing facilities. In addition, the buildings themselves wilJ eventually require dismantlement. For those rare instances where the controls recommended below cannot be practically implemented, a case by case evaluation may be used.

One or more contamination control measures are required for working on components or buildings with removable contamination levels greater than or equal to 25,000 dpm/100 cm2 (or fixed plus removable contamination ~250,000 dpm/100 cm2) to minimize the potential for unmonitored releases of airborne radioactive effluents. In principle, these measures attempt to reduce the amount of material that can be suspended or to reduce the amount of resuspended

! A monitored building is one that is under ncgntiv~ pre,.."'llll'C 1111d whose cxhau~1 is routed to an ODCM-cn:ditcd release point (Pinnt Vent Slllck nl Unit l ), The Pinnt Vent Stack is equipped with o continuous rrulinlion monitor und s111np!ed isokinctically for particulates and radioiodincs.

2 812-2 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING material available for release. Contamination control measures include the use of fixatives, local ventilation controls, and temporary work enclosures.

Examples of contamination control measures include:

a. Fixatives_:
  • paints
  • sealants
b. Local ventilation controls:
  • elephant trunks/portable HV AC units with filtercdlt exhaust
  • vacuums with filtered exhaust
c.

Enclosures:

  • tents with filtered exhaust
  • plastic bags enclosing pipes with filtered exhaust
  • plastic/fabric cover for doors/large openings in buildings
  • air curtain for doon;/large openings in buildings While it is unlikely that any radioactive particulate matter will actually be released from the site when prudent contamination control measures are implemented, continuous local air samples should be taken during work activities perfonned outside ofa monitored building.

The contamination control measures that are used should ensure that airborne radioactivity levels do not exceed 0.05 beta-gamma DAC or detectable levels of alpha DAC. If either of these thresholds is exceeded, additional control measures shall be implemented to meet these thresholds within a reasonable period of time. Additionally, if the air samples show levels greater than 0.05 beta-gamma DAC or detectable levels of alpha DAC, they should be counted as effluent samples.

The sample results should be provided to Effluent Engin~ring for evaluation.

As decommissioning progresses, openings will be created in monitored buildings. Mitigation efforts should be taken to minimize the potential for unmonitored releases and ensure continued compliance with the requirements of IO CFR 20 and l OCFR 50 to monitor and measure releases from Unit 1. For example, large openings (equipment hatch, temporary holes) should be covered with plastic or fabric or an air curtain established near the opening to maintain a negative pressure.

Smaller openings like containment penetrations should be sealed and pipes containing internal contamination :i:25,000 dpmllOO cm2 (250,000 dptri/100 cm2 fixed plus removable)should be covered or equivalent measures taken to prevent the spread ofloose contamination.

The recommended threshold of2S,000 dpm/100 cm2 loose surface contamination (250,000 dpm/100 cm2 fixed plus removable) ensures that the limits of10 CFR20 and 10 CFR 50 U"Filtered exhaust" refers to use of either a HEPA filter or Toril dust coUcctor or ll!1 equivalent device capable of removing >99% of the particulate mntter from the dischorge 3

B12-3 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING Appendix l will be mel Additionally, it also satisfies ALARA cost considerations since the HP division currently implements control measures for.worker protection purposes at similar levels4*

Contamination control measures are recommended, but not required, for work below removable levels of25,000 dpm/100 cm2*

In addition to the controls r~ommended above, other measures may be implemented during the demolition of buildings for non-radiological purposes. Dust abatement is frequently required by the local air quality regulators (San Diego Air Pollution Control District for SONGS) to minimize adverse impacts. Typical dust control involves the use of water to dampen the building surface or the rubble which would also reduce the particle-associated activity available for release from the site and the potential for public exposure.

Consequence Analysis 1n the unlikely event that the contamination control measures fail, the potential radioactivity released from working on equipment/structures contaminated up to 1.5E6 dpm/100 cm2 total activity was also evaluated. A conservative calculation (see Appendix A) was performed assuming that level of contamination over a 200 sq ft surface, distributed in one (1) cubic meter of air, and released instantaneously (l second) to the environment. Resuspension values found in the literature range from 0.5 to lE-6; a value of lE-3 for beta-gamma surface contamination5 was used. As seen on sheet 6 of Appendix A, the resultant organ dose for that single event ( l. 7E-3 mrem) was below the limits in 10 CFR 50 Appendix 1.

CONCLUSION Decommissioning Unit 1 involves the dismantlement of equipment and systems and the demolition of structures, some of which will be contaminated. Decontaminl!.tion and resizing of the components may also be performed prior to disposal. On occasion: the components and portions of the systems may not be physically accommodated in the existing buildings. Furthermore, the aboveground structures t~emselves will ultimately be removed. These activities must, by default, occur outside of the buildings with a monitored HV AC system and they create the potential for unmonitored releases of radioactive airborne effluents from Unit I. For work that must occur outside ofa monitored building, prudent control measures are recommended to minimize the spread of contamination and minimize the potential for the release of airborne particulates while maintaining dose to the public as low as is reasonably achievable (ALAR.A).

Contamination control measures arc required for work on equipment and/or structures with ~

25,000 dpm/100 cm2 removable contamination (~250,000 dpm/100 cm2 fixed plus removable contamination). One or more contamination control measures such as fixatives, local ventilation measures, and enclosures shall be used to ensure that air samples taken during the work activity do not exceed 0.05 beta-gamma DAC or dete<:table levels of alpha DACs. If either of these detection thre.,;holds is exceeded, additional control measures shall be implemented to minimize 4

812-4 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING airborne radioactivity within a reasonable time frame.

Contamination control measures are also'recommended below 25,000 dpm/100 cm2 removable contamination to minimize personnel exposure:

REFERENCES

1. Annual Radioactive Effluent Release Reports 1994-1999
2. "Handling and Working on Radioactive Material Outside Monitored Buildings" Memo to file, J. R. Clark, April 26, 1993.
3. SO 123-VIU-20. l O "Radiological Work Planning and Controls" Revision 4
4. S0123-VII-20.9 "Radiological Surveys" Revision 5 S. "Air Sampling in the Workplace" NUREG-1400 draft report for comment, October 1991 cc: John Custer, Operations Daryl Dick, Effluent Engineering Judd Sills, Decorrrnissioning HP Dre1*1 Spiker, Decorrrnissioning Rich St. Onge, Decorrrnissioning Gerry Moore,*NORAD - Oversight HP&E Files COM 5

812-5 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING Appendix A CONSEQUENCE ANALYSIS for AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING ip,HP&E Verified by: Tye 812-6 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING METHODOLOGY:

STEP 1 Cnlcula!e current isotopl<: d'i$1nbullo(i fOf U1 DAW D Knowing tho lsolop!o dlslributlon of U1 DAW, corre,ct fO( dOC11y alnc* llmo of 6'amplo analysis wile<<, A ls thucllvity nt llmo t Ao la tho acl!vlty al time t=O lambda'= 0.693/half-tife of i!Oloj:o t is the time elllpr;ed alnco lnhlal ruialysb b N = A:l&um(AI) c Calculate tho avorage isolopo 1$tnoo1ion from tho thro" srunplos (1193, 9/94, 4112199)

STEP 2 Calc\Jlato maximum C011tamlnatlon l&vob not to excoed 10 CFR 20 a Uso methodology In Calculation N--0320-007 *Airborne Source Tonns for Soulh Yard Facmty and Outdoor Ac!ivitie3*

CL "(1 MPC

  • Re!enoo Duration
  • 1EB cm3/m3)11At/MPC
  • Roloaso Fraction
  • X/Q) whoro CL Is tho aciM1y imll llOt to oxceed 1 MPC (ct ECL)

Releoso Duration lo assumed to be 1 second N b the norma!lzod, d<Qy c:omicted nb1.,'lllfanco (from step 1 :ibave)

MPC 19 lhe MPC value from 10 CFR 20 (or ECL)

Rolea~ Fr11ciion is amount resuspundod due to work activity

)(JQ la tho d!l.~r&lon factor b To convert sctMty timit into a contarnlnatlon love!

CL'= [(Cl* 2.22E6 c!pm/uCl)/(surface area)r100cm2 whMI ~ aroo. ls ansurood to be no greater lhM 200 sq ft affeclad by work aciM1y c To ensure that s i t e ~ remain below tha lirnibl of 10 CFR 20 multlply CL (or CL') by U1 adrnlnlstr.llivo factor, 0.03 STEP 3 Calculalb publlc dose impec1 if canlamlnadod matorlal worn relMis_ed off-cito a Q = {(A1" CL)N)

  • I where a le !ho release rate of ili:otope, I V Is tho volume released. asaumod to be 1 cubic meter f ls 1h11 flow rata, as&llllad to be 1 cubic meter per &e<:a1d b Using tha molhodology In &ecllon 2 of tho U1 OOCM Oo =i.wn t'or e:ich Isotope, I [(sum for oaeh pathway (P
  • W)}
  • Cl
  • tj whllf& O is tho organ do.e rato for 1hls WOik activity P is tho do$-O puraroo!'Br (or Isotope l t'or pathway k (table 2-1 of tho U1 OOCM)

Wis tho highest calctllatnd dlspersicn parameter for pathway k ut or beyond tho slm boundary {U1 ODCMJ

"'°mblo2.So!UI OOC!.llor [RJml"'03cllp;,1hway(P"W))

Q la lh9 release rato for ooch lsatopo I B12-7 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING U1 DAW ISOTOPIC DISTRIBUTION lHALFLIFE Jnn-93 to 4/1/2000

. L -

Sop-94 to 4/1/2000 ! 4112/99 to 4/112000

\ (1981 Koohor) Alld N.- I Abd i N.~n oclMl'I N.Abdn HJ l4.4S5E+03 3.096E-03 2.057E-03 4.48SE.Q313.601E-04 2.62BE-04 4.487E-04 2.690E-04 2:li4BE-C4 2.362E-03

.C14 i2.093E+06 6.738E-03 6.732E-03 1.46BE-02 1.743E-03 1.742E-031 2.974E-03 Mn54 l3.127E+02 2.581E-03 7.313E-06 1.595E-05 1.119E-03 1.220E.05 2.083E-05 Fe55 9.862E+02 1.908E-02 2.970E-03 6.476E-03 1.166E-01 2.782E-02 4.751E-02 3.4CCE-04 2.649E-C4 :usee-o:i Cose 7.080E+01 3.404E-02 1.904E-13 4.153E-13 Co60 1.925E+03 1.359E-05 5.241E.06 1.143E-05 4.363E-02i 2.094E.-02 3.576E-02 1.260E-03 1:109E-03 1.029E-02 Nl63 3.656E ..04 7.326E-03 6.968E-03 1.519E.02 6.834E-02l 5.575E-021 1.123E-01 1.6-COE-031 1.589E-031 1.474E-02 Sr89 - "S:055801 4.970E-04 8.641E-20 1.884E-19 I Sr90 1.045E...04 2.535E-04 2.127E-04 4.637E-04 1.730E-041 1.511_!:-04 2.580E-04 9.600E.05! 9.JnE-05 8.699E-04 Cs134 7.531E.,02 4.300E.01 3.764E-02 8.208E-02 2.750E-01i 4.212E-02 7.192E-02!9,670E*031 6.975E-0316.471E-02 Cs137 1.102E*04 4. 746E-Q~4.018E-01 8.762E-01 4.817E-01i 4.237E-01! 7.:.235E-01l9.970E-02i 9.750E-02! 9,045E-0_!

Pu238 3.2058-04 7.729E-06 7.299E-06 '1.592E-05 1.049E-04! 1.004E-041 1.714E-0411.800E.06' 1.786E-06i 1.657E-05 Pu239/240 2.399E.,06 2.261E-08 2.259E-06 4.926E-0613.491E-05 3.489E-05! S.957E-0512.100E-06I 2.1ooe:oo 1.9486-05 i>u:ii,- 5]80E.+03 2.531E-04 1.1aeE§.-04 3.894E*04 3.672e:03! 2.807E-03 4.793E-03 i Pu242 1.373E.,08 2.693E-07\ 2.693E-071 4.598E-07 l Am241 1.579E+05 4.515E-06 4.463E.()6 9.731E-06 8.681E-05 8.604E-OSI 1.469E-041 I Cm242 1.630E+02 2.1235-06 2.751E-11 5.998E-11 1.578E-04 2.712E-081 4.630E-08I i

Cm243/244 1.041E+04 2.843E-06 2.384E-05 5.198E.0611.205E-04 1.052E-04 1.796E-C4 I U233!234 8.930E+07 i 1.921E-07 1.921E-07 3.280E-07 U238 1.632E+12 !9.741E-08 9.741E-08l I

1.663E-07! I I-TOTAL 9.785E-01 4.5S6E-01 1.000E""00i9.92SE-01 5.857E-01!1.COOE+OO 1.129E-01I 1.07SE-01 1.000E+OO i

I I

  • -7aij.93 Sep.94 4/12199 Al' I

- I I iN. Abdn N.Abdn N.Abdn Averano I i I H3 I 4.485E-03 4.487E-04 2.362E-03 2.432:-03 I I I C14 Mn54 l 1.46SE-02 2.974E-03

__J_1.595E-05 2.0S3E-05 5.884:-031 1.226E-05

--l l

____[..I __ I I **--- I

Fe55 I 6.476E-03 4.751E-02 2.4S8E.Q3 1.881E-02 I I i I '.

Co58 l 4.15:lE-13 1.384E-13  ! I coeo l 1.143E-05 3.576E.-02 1.029E-02 . 1.5355-02 *1 I 'I I I

~163  ! 1.519E-02 1.123E-01 1.474E.02 4.740E*02 *--,--*--1 Sr89  ! 1.884E-19

- 6.281E-20

- I I I

I Sr90  ! 4.637E-04 2.580E-04 8.699E-04 5.305E-04 I T- I Cs134 I a.2oae-02 7.192E-02 6.471E-02 7.291E-02 *- *------L I ( i lw*-*-*-

'I Cs137 Pu238 I 8.762E-01 7.235E-01 9.045E-01 8.347E-01 1.592E-05 1.714E-04 1.657E-05 6.796E-05 -1 ______L l I I - i Pu239/240 4.926E-06 5.B57E-05 1.948E-05! 2.799E-05 ..

~~!

Pu242 3.894E-04 4.793E.03 4.598E-07 I 1.727E-03 I 1.533E-07 II I I

i I

l I

I I

I I

i Am21l1 9.731E-06 1A69E-04

- 1* 5.221 E-05 I I i I Cm242 5.998E-11 4.63CE-08 I 1.545E*08 I I I I Cm243/2<!4 5.198E-06 1.795E-04 6.1tffE.-05 I- I  ! i U233/234 . 3.280E-07 -t.093E-07 I I i I U238 TOTAL 1.663E-07 11.000E+OO 1,000E+OOI 1.0COE+OO 1.000E+OO 5.5445-08 I

I I

l I

I i

1------

I B12-8 S0123-0DCM-B Revision 9 08/2016

AIRBORNE EFFLUENT CONTROLS DURING DECOMMISSIONING USING METHODOLOGY DESCRIBED IN CALCULATION N-0320-007 At (DAW) MPC* (UClhnl) Al'/MPC (mVuCI) !ECL* (uCl/ml) Al'IECL (ml/uCI)

H3 cfi___ 2.43E-03 2.00E-07 1.22E+04, 1.00E-07 2.43E+04 5.88E-03 1.00E-07 5.88E+04, 3.00E-09 1.9SE+06 Mn54 1.23E-05 1.00E-09 1.23E+041 1.00E-09 1.23E+04 Fe55 1.88E*02 3.00E-08 6,27E+05 3.00E-09 6.27E+0S Co60 1.54E-02 3.00E-10 S.12E+07 5.00E-11 3.07E+08 Nl63 4.74E-02 - 2.00E-09 2.37E+07 1.00E-09 4.74E+07 Sr90 5.31E*04 3.00E-11 1.nE+07 6.00E-12 8.84E+07 Cs134 7.29E-02 4.00E-10 1.82E+08 2.00E-10 3.65E+08 Cs137 8.35E-01° 5.00E*10 1.67E+09 2.00E-10 4.17E+09 Pu238 6.SOE-05 1.00E-12 6,80E+07 2.00E-14 3.40E+09 Pu239/240 2.SOE-05 1.00E-12 2.80E+07 2.00E-14 1.40E+09 Pu241 1.73E-03 1.00E-09 1.73E+06 8.00E-13. 2.1SE+09 Pu242 1.53E-07 1.00E-12 1.53E+05 8.00E-13 1.92E+OS Am241 5.22E*05 4.00E-12 1.31E+07 2.00E-14. 2.61E+09 Cm242 1.55E-08 8.00E-12 2.58E+03 4.00E-13

  • 3.S6E+04 Cm243/244 6.16E.Q5 3.00E-12 2.05E+07 2.00E-14 3.08E+09 TOTAL 1.00E+OO 2.0BE+09 1.76E+10
  • most conse,v.tbvo va/110 oxcoJ/1 for afphn ollittets /hat 11111 11ssumod to 111 /Molllble Surface area 200 sq ft (assumed mmmum lll'l!ll effectod by Ille edMly)

Release fraction 1.00E-03 surface contaminated beta-aamma {dmft NUREG-1400, 1991)

XIQ 1.30E-05 sedm3 (UI OOCM)

MPC - CL = (1 MPC

  • Release Duration
  • 1ES cm3/m3)1{Al'IMPC " IRelease Fraction
  • X/Q)

CL= 1<1 MPC

  • 1 sec* 1E6 cm3/m3}/(2.08E9
  • 1E*3
  • 1.3E-5l

= 3.70E+04 uCI CL1 = 0.03

  • CL

= 1.11E+03 uCI

= (CL1 uCI

  • 2.22ES dpm/uCi)/(surface area)
1.33E+04 dpm or 1,33E+06 dem/100cm2 total due to particulate ECL CL = (1 ECL
  • Release ouraUon
  • 1ES cm3/m3llCAf/ECL
  • Release Fraction
  • XIQ)

I I CL= 1{1 ECL 0 1 sec* 1E6 cm3/m3)/{1.76E10

  • 1.3E-5}

= 4.36E+03 uCI CL1::: 0.03

  • CL
1.31E+02

= (CL uCI

  • 2.22E6 dpm/uCl)/(surface area)

= 1.56E-t03 dom or 1.66E+05 dem11oocm2 total due to ~ articulate 812-9 S0123-0DCM-B Revision 9 08/2016

RELEASE SHEET* MPC LIMIT L___ -*--*-*-* . I

! I Ul DAW corrected to 4/2000 I UNIT 1 I A:,' MPCconc ECL cone I SOURCE DEMOLmON H3 2.43E-03 2.70E-06 CI4 5.SSE-03 6.54E-06 3.18E-07Ll

7. 70E.07 I - I HlST X/Q I l.30E-05 sedm3

-- ;e:

Mn54 l.23E-05 l.S6E-08 l.60E-09 DURATION 1.0 sec  ;:a Cl Fe55 1.&SE--02 2.09E-0S 2.46E-06 RELEASE RATE l m3/scc 0 Co60 1.54E-02 l.71E-05 2.0IE-06  ;:a Ni63 I 4.74E-02 5.27E-05 6.20E-06 I

--~----~- --**-**********T-*- z m

Sr90 5.31E-04 5.90E-071 6.94E-08

  • I  ! m Csl34 7.2!1E-02 8.lOE-OSi 9.54E-06 AITERDISP CURIES RELRATE  % REL RATE 'Tl

'Tl Csl37 8.35E:0f 9.286-04 l.09E-04 ISOTOPE I MPC I CONC uCilcc ELEASE Ci/sec uCilsec r-Pu238 6.SOE-05. 1.SSE--08 8.S9E-09 H-3 2.00E-07 2.703E-06 3.514E*ll 2.703E-06 2.703E--06 2.4:iE-03 2.70E+o0 e m

Pu239/240 I 2.SOE-051 3.llE-08 3.66E-091 ALPHA i 1.00E-12 2.1S3E-06 2.799E-ll l.153E-06 2.153E-06 l.95E-03 2.ISE+OO z

-I Pu241 l.73E-03! 1.92E--06 2.26E-07 MN-54 l.OOE-09 l.362E-08 1.771E-13 l.362E-08 1.362E-08 I 1.23E-OS l.36E--02 Pu242 l.S3E-07 1.70E~l0 2.0IE-11 FE-55 :J.OOE-08 2.09lE-05 2.718E-IO t----

2.09IE-05 2.09lE-05 l.89E-02' 2.09E-t-OI n

*- 0 OJ Am24I S.22E-05 5.SOE-08 6.8'.lE-09 C0-60 3.00E-10 1.706E-05 2.218E-I0 l.706B-05 l.706E-05 l.S4E-02 l.7IE+ol z-I Cru.242 I I.SSE-OS l.72E*ll 2.02E-12 NI-63 2.006-09 5.27E-OS 6.8486-10 5.268E-05 5.268E-05 4.77E-02 5.27E+ol

a N Cm2*13/244 6.16E-OSI 6.SSE-08 S.06E-09 SR-90 3.00E-11 S.896E-07 7.66SE-12 5.896E-07 S.896E-07 S.34E-04
5.90E-01 I 0 I CS-134 4.00E-10 8.l03E-05 l.OS3E-09 I8.103E-05 8.l03E-05 7.33E-02 8.lOE+ol r-0 S.40E-Ol 9.28E+o2 V'l TOTAL l.OOE+oO l.llE-03 l.31E-04 CS-137 5.00E-10 9.277E-04 1.206F....OS 9.277E-04 9.217E-04 C

I TOTAL l.105E-03 l.436E-08 UOSE-03 l.lOSE-03 l.10E+o3 C MPC limit (uCi) 1.llE+-03

    • ---*----~~ -. '  :!:!

ECL limit (uCi) l.3IE+o2 ERikWk ACTIVITY Release Rllte O=Do~ z I rrwm/yr/UCl/s UCI uCVS'!C mrem Cil Diso. Vol (cm3) J.OOE+06

  • H-3 I l.18E-o3 2.70E+o0 2.70E+o0

-- MN-54 'iME+oo 1.36E-02 l.36E-02 H-3 MN-54 -

l.OlE-10 3.396-09

~ ___

C m

n I C0-60 l.036+o2 l.71E-t-Ol l.71E+ol I C0-60 ---* 5.57E-0S 0 I

SR-90 2.0SE+o3 l 5.90E-OI S.90E-Ol SR-90 3.89E-0S s:

I

/ CS-134 3.84E+ol 8.lOE+ol 8.IOE+ol

- CS-13*1 9.86E-OS s:

CS-137 4.38E+ol 9.28E+o2 9.2SE+o2 CS-137 l.29E-03 vi i i TOTAL l.48E-03  !!?

I 0 i z z

Cil 0 ~ C/)

~ CD Q N <....,.

0 en* N O')

-*w Q I

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RELEASE SHEET - ECL LIMIT I I

ut DAW co1TCcted to 4nooo1 UNIT 1 Ai' 1MPCconc ECLconc SOURCE DEMOLmON H3 2.43E-03 2.70B-06 3.lSE-071 I CI4

-- S.SSE-03! 6.54E.o6 7.70E-071 IDSTX/Q UOE-05 sec/m3  ! ;e:

--i  :::c Mn54 Fc55 I l.23E-05 l.36E--08 l.6DE-09,

+l-~E-02 2.09E-05 2.46E-06 DURATION RELEASE RATE 1.0 1 m3/=

sec I

I

~-

c:i 0

Co6D 1.54E-02 l.71E-05 2.0JE-06  :::c Ni63 4.74E--02 5.27E-05 6.20E-06 z

m SrJO S.31E-04 5.90E471 6.94E-08 I m

-n Csl34 7.29E-02 8.lOE-05 9.54E-06 AFTERDISP CURIES REL RATE  % RELRATE -n

&iI*r---*- -8.35E-Ol -9:fiE-Oi L09E-04 ,---- ISOTOPE I ECL I CONC r-uCi/cc ELEASE Ci/se.c uCi/sec e Pu238 6.SOE-05 7.55E-08 S.89E-09 H-3 l.OOE-0'7 3.182E-07 4.I37E-12 3.182E-07 3.IS2E-07 2.45E--03 3-ISE--01 m Pu239/240 . 2.SOE-05 3.llE-08 3.66E-09 ALPHA 2.00E-14 2.535E-07 3.295E*l2 2.535E-07 2.535E-07 1.95E-03 2.53F.-Ol z

-t Pu24I l.73E-03 1.92E-06 2.26E-07 MN-54 l.OOE-09 1.604£-09 2.0SSE-14 I.604E-09 J.604F,..09 l.:23E-05 l.60E-03 n Pu2.J2 1.:53E-07 l.70E-10, 2.0IE-11 FE-55 3.00E--09 2.462E-06 3.200E-ll 2.462E-06 2.462E-06 l.89E-021 2.46E+OO 0 Am241 5.22E--05l 5.SOE-08 6.SJE-091 C0-60 5.00E-11 2.009E-06 2.611E*ll 2.009E.o6 2.009E-06 l.54E-02 2.0lE+oo z

-t Cm242 l.55FAl8. l.72E~ll 2.02E*l2 NI-63 1.00F.-09 6.20E-06 8.062F..-ll 6.202E-06 6.202E-06 4.77E-02I 6.20E-tOO  :::c I 'SR-90 0

Cm2*l3/244 6.16E-05 6.SSE-08 S.06E-09 6.00E-12 6.942E-08 9.024E-13 6.942£-08 6.942E-08 5.34E-041 6.94E-02 r-I - 7.33E-02 U'l I CS-134 2.00E-10 9.539E--06 1.240£.10 9.539E--06 9.539E-06 9.54E-t00 C

TOTAL I 1.00E+OO 1.llE-031 l.3IE-04 CS-137 2.00E-10 l.092E-04 l.420E-09 1.092E-04 l.092E-04 8.40E-Ol I l.09E~-02 C

---**--- I l.30IE--04 [_ l.691E-09 il.301E--04 J.3~l?~'.!- __l.30E+o2 ~

..,,_~--*------... --~---------- ------ TOTAL MPC limit (uCi)*f 1.11 E+03 z I l ERlkWk ACTIVITY Release Rate Gl ECL limit (uCi) l.31E*102 Diso. Vol (cm3) . l.OOE+-06!

I I  !

I H-3

-t mremlyrtuCVs l.lSE-03 uCI 3.lSE-01 uCl/seo 3.ISE-01 - H-3 OrnanDosc mrem l.19:E-11 C

m n

! i t,..{N.54 7.84E+OO 1.60E-03i 1.60E-03 jMN-54 3.99E-l0 0 I 'I C0-60 l.03E-t02 2.0lE-tOO 2.0IE+oo: C0-60 6.56E--06 s 4.58E-06 s::

SR-90 CS-134 2.08E+o3 3.84E+ol 6.94E-02 6.94E-02 9.54E+o0 --9.S4E+OO

~--- SR-90 CS-~ ~ 5 vi

'I  !!?

CS-137 4.JSE+Ol ! l.09E*102i 1.09E+o2 CS-137 1.52.E-04 0 z

1 i I i .

TOTAL l.74E-04

--**--*--i*-*--**----**-** ------. ~--**----- -----*---------- z Gl t I 0 ~ CJ)

~ (1) 0 I\.) < .....

0 ui' I\.)

..... -*w O') Q I

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RELEASE*SHEET-1.SE6 dpm/100crm I I

Ul DAW contcicd to *l/2000 I UNlT 1 At MPCconc ECLconc ! SOURCE DEMOLmON H3 2.43E-03 3.0SH-06 3.0SE,06i I '

Cl4 S.SSE-031 7.JSE-06 7.38E-06f ~ST'X/0 l.30E-0S s<</m'J ;e Mn54 l.23E-OS l.54E,()8 1.S4E-08 URATION 1.0 see :a Fess IJJ 1.88E-02 2.36E-OS 2.36E-0Sf RELEASE RATE l m3/sec_ I 0 Co60 l.S4E-02 l.93E-05 J.93E-05 :a Ni63 4.74E-02 S.9SE-OS S.95E-05 z m

Sr90 S.31E-M 6.66E-07 6.66E-07 I m Cs134 7.29E-02 9:ISE-05 9.lSE-OS AFTER.DISP CURIES RELRATE  % RELRATE 'Tl

'Tl Cs137 8.3SE-Ol J.OSE-03 l.OSE-03 ISOTOPE MPC I CONC .I uCi/cc El.SASE Ci/sec uCi/scc r-Pu238 6.80E-0S S.53E-08 U3E-08 H-3 2.00E-07 J.OS2E-06 J.968E-U 3.0SlE-06 3.0S2H-06 2.45E-03 3.0SE+oo e:

m Pu239/240 Pu241 2.80E-OS 1 3.SlE-08 J.SlE-08 ALPHA 1.00E-12 2.431E-06 3.161E-11 2.431E-06 2.431E--06 I.9SE-03 2.43E+oo z

-I l.TIE-03 2.17E-o6 2.17E-06 MN-54 1.00&-09 1.S38E-08 2.000E-13 l.S38E-08 l.S38E-08 1.23E-OS 1.S4E-02 Pu242 l.SJB-07 L92E~IO l.92E-I0 FE-SS 3.00E-08 2.36IE-OS. 3.070E-10 2.361B-OS t.361E-OS L89E-02 2.36Et0l n Am241 5.22E-OS 6;5SE-08 6:SSE-08 I C0-60 3.00E-10 l.927E-OS 2.SOSE-10 1.927E-OS l.927E-OS l:54E-02 l.93E+ol 0 ClJ Cm242 l.SSE-08 L94B-11 1.9.\B-11 NI-63 2.00E-09 S.9SE-OS 7.733B-10 S.949E-OS S.949E-OS 4.77E-02 S.95E-+Ol z

-I N Cm243/244 6.16E-05 7:73E-08 7.73E-08 SR-90 3.00E-11 6.6S8E-07 8.6S6E-l2 6.6SSE-07 I6.65SE-07 S.3-tE-04 6.66E-01 :a I

CS-134 4.00E-10 9.ISOE-05 I.189E-09 9.ISOE-05 9.ISOE-OS 7.33E-02 -9.lSE+ol 0

....>. r-N 1.lSE-03. l.2SE-03. 111 TOTAL l.OOE-+00 CS-137 S.OOB-10 l.048E-03 1.3628-08 1.048E-03 1.04SE-03 .UOE-01 1.0SEt03 TOTAL 1.248E-03 l.622E-08 1;2488-03 l.248E-03 l.2SE+o3 C C:

MPC limit (uCi) l.26E+03 =!

ECL limit (uCi) l.26E+o3 ERikWk ACTIVITY RdeasoRate OnmnDOSI! z C) mteml'yr/UCl/s UCI uCU&ec mrem DiSD; Vol (c:m3) I.OOE+-06 H-3 l.lSE-03 3;osE+oO 3.0SE+oo H-3 l.14E-10 C MN-54 7.84E+OO I.S4E.02 1.54E-02 MN-54 3.82E-09 m n

C0-60 L03Et02 l.93E+ol 1.93Et01 C0-60 6.29E-05 0 I SR-90

  • 2.08E*Hl3 6.66E-OI 6.66E-Ol SR-90 4.39E-OS s:

CS-134 3.84E+Ol 9.1SE+ol 9.lSE+oJ CS-134 I.I IE-04 s:

CS-137 4.38E+ol 1.0SE+o3 1.0SE+o3 CS-137 l.4SE.03 iii TOTAL 1.67E,-03 ~

  • 0 z

z C) o :::a en

~ CD Q N~.--"

O en N

....>. - * (.,)

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SUBJECT:

AIRBORNE CONTAMINATION FROM DECOMMISSIONING ACTIVITIES December 13, 2013 J. A. CAREY

SUBJECT:

Airborne Contamination from Decommissioning Activities

REFERENCES:

1. Airborne Effluent Controls During Decommissioning, K. Yhip, September 27, 2000
2. Airborne Source Term for South Yard Shops Facility and Outdoor Activities, Calculation N-0320-007, Rev. 1, April 28, 1995
3. SONGS Health Physics Procedure S0123-Vll-20.10, Radiological Work Planning and Controls
4. Radwaste Processing Techniques -Airborne Effluent Evaluation, K. Yhip, December 20, 1999 .

PROBLEM STATEMENT Reference 1 provided a conservative limit of 250,000 dpm/100 cm 2 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 guidelines 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 Term for South Yard Shops and Outdoor Activities (January 4, 1993) was originally initiated to evaluate the impact of work in the South Yard because that facility is located in close proximity to site boundaries, The calculation also included an evaluation of performing some radiological work in the Protected Areas but outside of monitored buildings. The calculation was significantly revised in 1995 (Reference 2) to account for a source term with reactor coolant contaminated equipment and to also address mixed waste processing.

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. The calculation included two major cases each for Unit 1 and for Units 2/3, the first for "normal" activities (machining, drilling, sawing, grinding) and the second for a "design basis" event (a fire) in which the resuspended radioactivity was much 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 these items into small enough pieces may include sawing and crushing but also could include torch cutting.

813-1 SO 123-0DCM-B Revision 9 08/2016

SUBJECT:

AIRBORNE CONTAMINATION FROM DECOMMISSIONING ACTIVITIES The limits for the normal case apply (10 CFR Part 20 airborne effluent concentration limits or ECLs) for sawing and crushing but the larger release factor for the design basis accident is more appropriate for aggressive work such as torch cutting. Since the rest of the parameters (wind speed, stability class, X/Q, etc.) that enter into the evaluation are not significantly different, the impact from these activities in the NIA can be estimated by ratioing the "normal" case to the "design basis" accident release factor. The normal case was based on a release factor of 1 x 1o-6

  • 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 10-5 for carbon dioxide pellet blasting for decontamination that could be applicable for aggressive decontamination measures in the area.) 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 offsite airborne concentration of 1 EGL. Note

'also that the isotopic distribution used in the calculation was based on the Units 2/3 dry active waste (DAW) composite profile. This profile is dominated by 137Cs, 134Cs, and 60Co. This radionuclide profile is appropriate for the Units 2/3 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 2/3 components and not Unit 1 components (that would have a different radionuclide distribution).

The surface contamination limit for work under normal conditions (machining, drilling, sawing, grinding) was 1.3 x 1011 dpm/100 cm 2 (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 yields - 1 x 108 dpm/100 cm 2 . Note this value is not as high as the design basis event in 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 surface 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 cm 2 for work in the NIA. This is comparable to the limitation in SONGS Health Physics Procedure S0123-Vll-20.10 (Ref. 3) that includes a criterion of 1.5 x 106 dpm/100 cm 2 for loose surface contamination on work outside an effluent-monitored building (equivalent to 1.5 x 107 dpm/100 cm 2 total contamination) and applies site-wide, not just for the NIA. The administrative value of 250,000 dpm/100 cm 2 total contamination from Reference 1 is therefore conservatively 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 because of the greater distance to the Site Boundary (raises the atmospheric dispersion X/Q by greater than a factor of 3). Reference 2, page 7 includes results for the Units 2/3 PA that are higher than the NIA results by this factor of 3. Moreover, aggressive decontamination will not be required in the Units 2/3 PA since the material is not contaminated (i.e.

demolition of support buildings).

Lastly, these results and limits apply to offsite airborne concentrations and not to local worker 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 drains.

813-2 SO 123-0DCM-B Revision 9 08/2016

' -'"--*----~ . - - - - - - * - - - - - - * - - - - -.. - - - ~ - - ~ - * - * * - - - - - ~ - - - . - ~ - , ' ' 7 _ _ _ _ ........,

SUBJECT:

AIRBORNE CONTAMINATION FROM DECOMMISSIONING ACTIVITIES RECOMMENDATIONS Work on contaminated components or work to demolish buildings may be performed on surfaces with total contamination levels up to 1 x 107 dpm/100 cm 2 , raised from the currently conservative 250,000 dpm/100 cm 2 (total contamination, fixed plus removable). In addition, an initial limit for 7 2 torch cutting steel (for example, the head lift rig) may be established also at 1 x 10 dpm/100 cm

  • While torch cutting may cause a relatively 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 cutting processes to ensure the controls are adequate. Adjustment may be necessary in the unlikely event that radioactive contamination is discovered on air samples taken during decontamination or demolition. If airborne contamination levels are not significant (defined to be greater than 0.1 DAC in the general work area), then the contamination levels could be raised higher subject to approval by the Radiological Effluent and Environmental Specialist, but should not exceed 1 x 108 dpm/100 cm 2 , for loose surface contamination, 1% of the limit suggested in Reference 2. As always, ALARA principles such as decontamination should be used oh the local surfaces that are subject to cutting or other activities that might resuspend radioactivity. If practical, engineered controls should be employed such as containment enclosures, HEPA ventilation units, fixatives, 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 mist/spray or fixatives if necessary
  • Limits for contamination:

o 1 x 107 dpm/100 cm 2 (total activity, fixed plus removable) o 1.5 x 106 dpm/100 cm 2 (removable activity limit in Ref. 3) o Higher levels may be used if air samples support and Effluent Engineering approves, particularly in the Units 2/3 Protected Area o The previously identified administrative limit of 250,000 dpm/100 cm 2 (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. Vaughan C. Cook C. Ahola COM Files 813-3 S0123-0DCM-B Revision 9 08/2016

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