Text

Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report 2024
	ML25115A201
Person / Time
Site:	Palo Verde
Issue date:	04/22/2025
From:	Dilorenzo M; Arizona Public Service Co
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
	102-08938 MDD/ARS
	Download: ML25115A201 (1)
	v • d • e

Technical Specification 5.6.3 and 5.5.1 Technical Requirements Manual 3.7.102.4 A member of the STARS Alliance LLC Callaway

Diablo Canyon

Palo Verde

Wolf Creek Palo Verde Nuclear Generating Station PO Box 52034 Phoenix, AZ 85072 Mail Station 7636 Tel (623) 393-3495 102-08938 MDD/ARS April 22, 2025 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, 3, and Independent Spent Fuel Storage Installation Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74 Docket Nos. STN 50-528, STN 50-529, STN 50-530, and STN 72-44 Annual Radioactive Effluent Release Report 2024 Enclosed please find the Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Annual Radioactive Effluent Release Report (ARERR) for 2024. Arizona Public Service Company (APS) is submitting this report pursuant to the PVNGS Technical Specification Reporting Requirement, Section 5.6.3. The report also includes details regarding radioactive effluent releases from the PVNGS Independent Spent Fuel Storage Installation. There was a revision to the Offsite Dose Calculation Manual (ODCM) in 2024, see Appendix E of the ARERR pursuant to the PVNGS Technical Specification Reporting Requirement, Section 5.5.1.

PVNGS Technical Requirement Manual, Section 3.7.102.4, requires an annual report to be prepared and submitted if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination. There were no events in 2024 that met this reporting threshold.

No new commitments are being made to the Nuclear Regulatory Commission (NRC) by this letter.

Should you need further information regarding this submittal, please contact me at (623) 393-3495.

Sincerely, Michael D. DiLorenzo Department Leader Nuclear Regulatory Affairs MDD/ARS/cmr

Enclosure:

Palo Verde Nuclear Generating Station Units 1, 2, and 3 2024 Annual Radioactive Effluent Release Report cc:

J. Monninger NRC Region IV Regional Administrator W. T. Orders NRC NRR Project Manager for PVNGS A. T. Tran Acting NRC Senior Resident Inspector for PVNGS B. Goretzki Arizona Department of Health Services - Bureau of Radiation Control Dilorenzo, Michael D(Z99838)

Digitally signed by Dilorenzo, Michael D(Z99838)

Date: 2025.04.22 17:00:52 -07'00' t') aps

Enclosure Palo Verde Nuclear Generating Station Units 1, 2, and 3 2024 Annual Radioactive Effluent Release Report

2024 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT USNRC Docket No. STN 50-528/529/530 RCTSAI 1566 Prepared by:

Reviewed by:

Approved by:

PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2 AND 3 Michaelson, Thomas (Z18156)

Digitally signed by Michaelson, Thomas (Z18156)

Date: 2025.04.15 11:20:55 -07'00' Donnelly, Patrick T(Z32986)

Digitally signed by Donnelly, Patrick T(Z32986)

Date: 2025.04.17 07:15:08 -07'00' Engstrom, Herbert O(Z02964)

Digitally signed by Engstrom, Herbert O(Z02964)

Date: 2025.04.17 07:52:43

-07'00' PloVerde *"

GENERAllNG STATION

PVNGS ARERR 2024 Page 2 TABLE OF CONTENTS INTRODUCTION.................................................................................................................................................... 4 BIBLIOGRAPHY..................................................................................................................................................... 5 APPENDIX A: EFFLUENT AND WASTE DISPOSAL REPORTS................................................................................... 6 1.0 REGULATORY LIMITS............................................................................................................................. 7 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS....................................................................................... 9 3.0 AVERAGE ENERGY................................................................................................................................. 9 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY IN GASEOUS EFFLUENTS......... 9 5.0 BATCH RELEASES................................................................................................................................... 9 6.0 ABNORMAL RELEASES........................................................................................................................... 9 7.0 OFFSITE DOSE CALCULATION MANUAL AND PROCESS CONTROL PROGRAM (PCP) REVISIONS.......... 9 8.0 EFFLUENTS AND SOLID WASTES......................................................................................................... 10 9.0 MISCELLANEOUS INFORMATION........................................................................................................ 10 10.0 METEOROLOGICAL DATA.................................................................................................................... 11 11.0 DISCUSSION......................................................................................................................................... 12 APPENDIX B: DOSE CALCULATIONS.................................................................................................................... 61 APPENDIX C: NEI 07-07 GROUNDWATER PROTECTION INITIATIVE SAMPLING................................................. 70 APPENDIX D: ADJUSTED PERMITS...................................................................................................................... 75 APPENDIX E: OFF SITE DOSE CALCULATION MANUAL REVISION 32.................................................................. 77 LIST OF TABLES Table 1: Evaporation Pond Data........................................................................................................................ 15 Table 2: Batch Release Data.............................................................................................................................. 15 Table 3: Units 1, 2, and 3 Gaseous Effluents Average Lower Limit of Detection (Ci/cc)................................ 16 Table 4: Unit 1 Gaseous Effluents (Summation Of All Releases)...................................................................... 17 Table 5: Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines............ 18 Table 6: Unit 1 Gaseous Effluents-Ground Level Release-Continuous - Particulates..................................... 19 Table 7: Unit 1 Gaseous Effluents - Ground Level Releases-Batch - Fission Gases and Iodines...................... 20 Table 8: Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates........................................... 21 Table 9: Unit 1 Gaseous Effluents-Continuous and Batch-Fission Gases and Iodines.................................... 22 Table 10: Unit 1 Gaseous Effluents - Continuous and Batch - Particulates...................................................... 23 Table 11: Unit 1 Radiation Doses At And Beyond The Site Boundary............................................................... 24 Table 12: Unit 2 Gaseous Effluents - Summation of All Releases..................................................................... 25 Table 13: Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines.......... 26 Table 14: Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates................................ 27 Table 15: Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines................... 28 Table 16: Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates......................................... 29 Table 17: Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines................................ 30 Table 18: Unit 2 Gaseous Effluents - Continuous and Batch - Particulates...................................................... 31 Table 19: Unit 2 Radiation Doses at And Beyond The Site Boundary............................................................... 32 Table 20: Unit 3 Gaseous Effluents - Summation Of All Releases..................................................................... 33 Table 21: Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines.......... 34 Table 22: Unit 3 Gaseous Effluents - Ground Level Releases - Continuous Particulates.................................. 35 Table 23: Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines................... 36 Table 24: Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates......................................... 37 Table 25: Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines................................ 38 Table 26: Unit 3 Gaseous Effluents - Continuous and Batch - Particulates...................................................... 39 Table 27: Unit 3 Radiation Doses at And Beyond the Site Boundary................................................................ 40

PVNGS ARERR 2024 Page 3 Table 28: Units 1, 2, and 3 Gaseous Effluents - Continuous - Fission Gases and Iodines - Total by Quarter... 41 Table 29: Units 1, 2, and 3 Gaseous Effluents - Continuous - Particulates - Total by Quarter......................... 42 Table 30: Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines - Total by Quarter............. 43 Table 31: Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total by Quarter................................... 44 Table 32: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines - Total by Quarter............................................................................................................................................................... 45 Table 33: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total by Quarter........ 46 Table 34: Units 1, 2, and 3 Gaseous Effluents-Continuous - Fission Gases and Iodine -Total by Unit............. 47 Table 35: Units 1, 2, and 3 Gaseous Effluents-Continuous - Particulates - Total by Unit................................ 48 Table 36: Units 1, 2, and 3 Gaseous Effluents-Batch - Fission Gases and Iodine - Total by Unit..................... 49 Table 37: Units 1, 2, and 3 Gaseous Effluents-Batch - Particulates - Total by Unit.......................................... 50 Table 38: Units 1, 2, and 3 Gaseous Effluents-Continuous and Batch - Fission Gases and Iodine -

Total/Unit........................................................................................................................................... 51 Table 39: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total by Unit.............. 52 Table 40: Estimation of Total Percent Error...................................................................................................... 53 Table 41: Effluent Monitoring Instrumentation Out of Service Greater Than 30 Days.................................... 53 Table 42: Solid Waste Summary....................................................................................................................... 54 Table 43: Doses to Special Location.................................................................................................................. 64 Table 44: Integrated Population Dose............................................................................................................. 65 Table 45: Summary of Individual Doses........................................................................................................... 69 Table 46: 2024 NEI 07-07 Ground Water Protection Initiative PVNGS Well Data............................................ 73 Table 47: Adjusted Permits............................................................................................................................... 76 LIST OF FIGURES Figure 1: Onsite Well Locations & Groundwater Contours of February 2024................................................... 71 Figure 2: Onsite Well Locations & Groundwater Contours of December 2024................................................. 72

PVNGS ARERR 2024 Page 4 INTRODUCTION This report summarizes the effluent and waste disposal source term data, meteorological data, and doses from radioactive effluents for the Palo Verde Nuclear Generating Station (PVNGS) for the period of January through December 2024. The data presented meets the format provided in Regulatory Guide 1.21 (Revision 1, June 1974) of the U.S. Nuclear Regulatory Commission. The report summarizes the quantities of gaseous effluents released from each PVNGS unit and waste disposed of from PVNGS. Because PVNGS does not have a liquid effluent pathway, no liquid effluents are summarized.

PVNGS ARERR 2024 Page 5 IBLIOGRAY BIBLIOGRAPHY U.S. Nuclear Regulatory Commission, Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, 1974 & Revision 2, 2009.

U.S. Nuclear Regulatory Commission, Regulatory Guide 1.23 (Safety Guide 23), Onsite Meteorological Programs, 1972.

U.S. Nuclear Regulatory Commission, NUREG/CR-2919, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, 1982.

U.S. Nuclear Regulatory Commission, NUREG-0579, Users Guide to GASPAR Code, June 1980.

U.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, Calculations of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, Revision 1, 1977.

U.S. Nuclear Regulatory Commission, NUREG-0172, Age-specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, 1977.

U.S. Nuclear Regulatory Commission, NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, 1978.

Technical Specifications, Palo Verde Nuclear Generating Station, Units 1, 2 and 3, Docket No. 50-528/529/530.

Bechtel Power Corp., Cooling Tower Blowdown System Solar Evaporation Pond, Sept. 1980.

Generation Engineering, Geotechnical Exploration for Evaporation Pond #2, Oct. 1986.

Letter No. 212-00789-WFQ/RHM, 1989 PVNGS Evaporation Pan Data, Jan. 1989.

Offsite Dose Calculation Manual Palo Verde Nuclear Generating Station Units 1, 2 and 3, Rev. 33.

NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, Rev. 1 March 2019.

Calculation 13-NC-CH-0200, Rev 7, FSAR - Primary Coolant Activities (PCA).

PVNGS Emergency Plan, Palo Verde Nuclear Generating Station, Units 1, 2 and 3, Rev. 76, December 2024.

Environmental Report Operating License Stage, Palo Verde Nuclear Generating Station, December 1981.

Four Monitoring Wells Out of Service, 24-10891-001, PVNGS, February - 2025.

Annual Radiological Environmental Operating Report, RCTSAI 1644, PVNGS, 2024.

PVNGS ARERR 2024 Page 6 APPENDIX A: EFFLUENT AND WASTE DISPOSAL REPORTS

PVNGS ARERR 2024 Page 7 1.0 REGULATORY LIMITS 1.1 Liquid Releases 1.1.1 PVNGS ODCM Requirement 3.2 The concentration of radioactive material discharged from secondary system liquid waste to the circulating water system shall be limited to:

5.0E-07 Ci/ml for principal gamma emitters (except Ce-144) 3.0E-06 Ci/ml for Ce-144 1.0E-06 Ci/ml for I-131 1.0E-03 Ci/ml for H-3 The concentration of radioactive material discharged from secondary system liquid waste to the onsite evaporation ponds shall be limited to:

2.0E-06 Ci/ml for Cs-134 2.0E-06 Ci/ml for Cs-137 The concentrations specified in 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, for all other isotopes.

1.1.2 PVNGS ODCM Requirement 4.4 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit to areas at and beyond the SITE BOUNDARY shall be limited:

a.

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

b.

During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

1.2 Gaseous Releases 1.2.1 PVNGS ODCM Requirement 3.1 The dose rate due to radioactive materials released in gaseous effluents from the site 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 3,000 mrem/yr. to the skin, and

b.

For I-131 and I-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1,500 mrem/yr. to any organ.

PVNGS ARERR 2024 Page 8 1.2.2 PVNGS ODCM Requirement 4.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a.

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

b.

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

1.2.3 PVNGS ODCM Requirement 4.2 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit to areas at and beyond the SITE BOUNDARY 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.

1.2.4 PVNGS ODCM Requirement 4.3 The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site, when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit to areas at and beyond the SITE BOUNDARY when averaged over 31 days, would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

1.3 Total Dose 1.3.1 PVNGS ODCM Requirement 5.1 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to direct 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.

PVNGS ARERR 2024 Page 9 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS Air: Release Concentrations are limited to dose rate limits described in section 1.2.1 of this report.

3.0 AVERAGE ENERGY The average energy () of the radionuclide mixture in releases of fission and activation gases is not applicable to PVNGS.

4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY IN GASEOUS EFFLUENTS For continuous releases, sampling is in accordance with PVNGS ODCM Table 3-1.

Particulate and iodine radionuclides are sampled continuously at the Plant Vent and Fuel Building exhaust points. The particulate filters and charcoal cartridges are exchanged for analysis at least four times per month. Noble gas and tritium are sampled at least once per 31 days. The hourly average Radiation Monitoring System (RMS) effluent monitor readings are used, when available, to account for increases and decreases in noble gas concentrations between noble gas grab samples. The tritium concentration is assumed constant between sampling periods.

For batch releases, sampling is also in accordance with PVNGS ODCM Table 3-1. For containment purges, the noble gas concentration may be adjusted to account for decreases or increases in concentration during the purge using RMS readings. The volume of air released during the purge is determined using the exhaust fan rated flow rate. For Waste Gas Decay Tank releases, the volume released is corrected to standard pressure.

Effective January 1, 2004, Containment Purge release permits are updated by removing the permit pre-release particulate and iodine activity. This eliminates double accounting for the Containment Purge particulate and iodine activity at the Plant Vent but allows the particulate and iodine activity to be included in the Containment Purge pre-release dose projection.

The Lower Limit of Detection (LLD) of a measurement system is defined in Table 3 - 1 of the PVNGS ODCM. An average LLD for each radionuclide is provided in Table 3.

5.0 BATCH RELEASES 5.1 Gaseous Batch release durations are presented in Table 2.

5.2 Liquid None.

6.0 ABNORMAL RELEASES None.

7.0 ODCM AND PCP REVISIONS There was a revision to the Offsite Dose Calculation Manual (ODCM) in 2024, see Appendix E.

There were no revisions to the Radwaste Process Control Program (PCP) in 2024.

PVNGS ARERR 2024 Page 10 8.0 EFFLUENTS AND SOLID WASTES 8.1 Gaseous Effluents Gaseous effluent information is presented in Table 1 through Table 41. Included in these tables are summaries of the effluents and estimated total error.

8.2 Liquid Effluents There were no liquid effluent releases beyond the site boundary from PVNGS.

8.3 Solid Waste Solid Waste Shipments are summarized in Appendix A.

9.0 MISCELLANEOUS INFORMATION 9.1 Evaporation Ponds Releases made to the Evaporation Ponds are limited to the concentrations specified in PVNGS ODCM Requirement 3.2. The Evaporation Ponds were monitored in accordance with PVNGS ODCM Requirement 6.1.

The historical average evaporation rate is approximately 12 inches per pond for the first and fourth quarters, and 33 inches per pond for the second and third quarters.

Evaporation Pond One is approximately 261 acres which is divided into three segments: Pond 1A (131 acres), Pond 1B (77.5 acres) and Pond 1C (52.5 acres). This equates to a quarterly evaporation rate from Pond One of 3.22E+11 cc for the first and fourth quarters, and 8.85E+11 cc evaporated for the second and third quarters.

Evaporation Pond Two is approximately 232 acres which is divided into three segments: Pond 2A (117 acres), Pond 2B (87 acres) and Pond 2C (30 acres). The quarterly evaporation rate from Pond Two is 2.89E+11 cc for the first and fourth quarters, and 7.97E+11 cc for the second and third quarters.

Evaporation Pond Three is constructed of two smaller ponds of 90 acres each (3A and 3B). The quarterly evaporation rate from Pond Three is 2.20E+11 cc for the first and fourth quarters, and 6.04E+11 cc for the second and third quarters.

Using a site boundary X/Q of 5.0E-05 sec/m3 for the evaporation ponds and equation 4-3 from the ODCM, the dose from the evaporation ponds to a hypothetical individual at the site boundary, for all pathways, is summarized in Table 1.

PVNGS ARERR 2024 Page 11 9.2 Radiation Monitoring System Setpoint Verification Current effluent monitor noble gas channel alert alarm set points are based on an assumed one percent failed fuel source term. The current method used for the set point values are more reliable than basing the set points upon the constantly varying values of the actual noble gas source term presented in Table 38.

9.3 RCS Radioiodine (TRM T5.0.600)

There were no cases where primary coolant specific activity exceeded the Technical Specification 3.4.17 limits during the reporting period.

9.4 Independent Spent Fuel Storage Installation (ISFSI)

There are no radioactive effluents from the NAC-UMS System. Direct dose at the Site Boundary is reported in the Annual Radiological Environmental Operating Report (AREOR).

9.5 Major changes to the Radioactive Waste Systems (Liquid, Gaseous, And Solid).

None.

9.6 NEI 07-07 Industry Groundwater Protection Initiative Sample results from the groundwater wells that are not described in the ODCM as part of the REMP (NEI 07-07, Industry Groundwater Protection Initiative, August 2007), are included in Appendix C. This initiative provides added assurance that ground water will not be adversely affected by PVNGS operations.

There were no NEI 07-07 reportable leaks or spills. There were no positive sample results, and all samples results were below the Lower Limit of Detection.

9.7 Report Addendum None.

10.0 METEOROLOGICAL DATA The data recovery for the reporting period was 100.0 percent. The predominant wind direction was from the southwest approximately 17.2 percent of the time. The predominant stability class was stability class "E" approximately 22.1 percent of the time.

Average wind speed during the reporting period was approximately 6.5 miles per hour at the 35-foot elevation.

The annual meteorological data (Hourly Average Data or Joint Frequency Distribution) will be recorded and shall be provided to the NRC upon request.

PVNGS ARERR 2024 Page 12 11.0 DISCUSSION 11.1 Unit One Unit One operated without a refueling outage during 2024.

Maintenance outages:

x None Estimated Number of Fuel Defects1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0

0 0

0 11.2 Unit Two Unit Two operated with a refueling outage (2R25-B) from October 5, 2024, to November 9, 2024.

Maintenance outages:

x None Estimated Number of Fuel Defects1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0

0 0

0 11.3 Unit Three Unit Three operated with a refueling outage (3R24-A) from April 6, 2024, to May 11, 2024.

Maintenance outages:

x None Estimated Number of Fuel Defects1 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 0

0 0

0 1 Source: Institute of Nuclear Power (INPO), Industry Reporting Information System (IRIS)

I I I I I I I I I I I I I

PVNGS ARERR 2024 Page 13 11.4 Carbon-14 Carbon-14 is formed naturally in the upper atmosphere, and it is also formed in operating nuclear reactors.

Carbon-14 is not a new power plant effluent. The overall quantity of radioactive releases has steadily decreased due to improvements in power plant operations.

Based on the decline in other radionuclides released, Carbon-14 has the potential to achieve the status of a principal radionuclide as defined in Regulatory Guide 1.21.

The dose received by a member of the public from Carbon-14 from nuclear power plant effluents is much lower than regulatory limits, and has been a very small contributor to the total radiation dose received each year from natural and manmade sources. Studies by the United Nations Scientific Committee on the Effects of Atomic Radiation, the National Research Council report on the Biological Effects of Ionizing Radiation (BEIR VII), and the National Council on Radiation Protection and Measurements all show that the risk associated with low-dose radiation from natural and man-made sources, including nuclear power plants, is negligible.

The average member of the public in the United States is exposed to 620 mrem every year, of which approximately 311 mrem of this comes from natural sources.

The majority of the remaining dose (approximately 300 mrem) comes from medical procedures (such as, x-Rays, CAT scans, etc.). Less than one-tenth of a percent of all non-occupational radiation exposure is from nuclear facilities.2 The PVNGS calculated Carbon-14 production rate is 18.5 curies per operating cycle (500 days) or 13.5 curies per year. The production rate of 13.5 curies will be divided equally between each quarter, 3.38 curies per reactor, and the estimated Carbon-14 activity is included in the inhalation and ingestion dose calculations.

11.5 Tritium PVNGS does not have a liquid release pathway. Removal of tritium is performed by operation of the Boric Acid Concentrator (BAC) in the release mode. Comparison of PVNGS annual tritium curies released to other utilities should be made only after summing both liquid and gaseous tritium curies released.

2 Source: National Council on Radiation Protection and Measurements NCRP Report No. 160, Table 1.1.

PVNGS ARERR 2024 Page 14 11.6 Dose Summary Dose for 2024 was primarily due to the release of tritium. The calculated tritium production rate for each PVNGS reactor is estimated to be approximately 1150 curies per year; however, a large fraction of the tritium produced does not become part of the reactor coolant source term. The tritium produced in the coolant contributes immediately to the overall tritium source term, but the tritium produced by fission and neutron capture in the Core Element Assembly and borated shim rods only contributes to the reactor coolant source term if it is released through the cladding.

To control in-plant tritium concentrations, tritium releases account for tritium production that enters the reactor coolant. For 2024, the total tritium released from PVNGS was 1.75E+03 curies (see Table 39).

PVNGS ARERR 2024 Page 15 Table 1: Evaporation Pond Data Table 1: Evaporation Pond Data Evaporation Pond 1(1A, 1B, 1C)

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Historical Evaporation (ml) 3.22E+11 8.85E+11 8.85E+11 3.22E+11 Tritium Concentration (Ci/cc) 3.87E-07 7.16E-08 2.53E-07 3.22E-07 Tritium Curies 1.25E-01 6.34E-02 2.24E-01 1.04E-01 5.16E-01 Evaporation Pond 2 (2A and 2B)

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Historical Evaporation (ml) 2.52E+11 6.92E+11 6.92E+11 2.52E+11 Tritium Concentration (Ci/cc) 2.12E-07 3.73E-07 1.65E-07

<LLD Tritium Curies 5.34E-02 2.58E-01 1.14E-01

<LLD 4.25E-01 Evaporation Pond 3 (3A and 3B)

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Historical Evaporation (ml) 2.20E+11 6.04E+11 6.04E+11 2.20E+11 Tritium Concentration (Ci/cc)

<LLD 1.76E-07

<LLD

<LLD Tritium Curies

<LLD 1.06E-01

<LLD

<LLD 1.06E-01 Dose (mrem)

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Pond 1 1.73E-03 8.79E-04 3.10E-03 1.44E-03 7.15E-03 Pond 2 7.41E-04 3.58E-03 1.58E-03

<LLD 5.90E-03 Pond 3

<LLD 1.47E-03

<LLD

<LLD 1.47E-03 Total 2.47E-03 5.93E-03 4.68E-03 1.44E-03 1.45E-02 (1) Evaporation Pond 3A has no plant related influent, no detectable tritium, and is excluded from sampling.

Note - All 2024 samples are included. For some other data points, conservative or best estimates are used.

Trending is carried out continuously to verify the estimated data points as new samples are recorded.

Table 2: Batch Release Data Table 2: Batch Release Data All times are in hours Unit 1 Unit 2 Unit 3 January - June Number of batch releases 14 18 41 Total time period for batch releases 102.5 186.1 1461 Maximum time period for a batch release 82.5 93 168 Average time period for a batch release 7.32 10.34 35.63 Minimum time period for a batch release 0.48 0.52 0.1 July - December Number of batch releases 24 39 28 Total time period for batch releases 400 1550 651 Maximum time period for a batch release 168.00 168 168.00 Average time period for a batch release 16.67 39.74 23.25 Minimum time period for a batch release 0.52 0.12 0.43 January - December Number of batch releases 38 57 69 Total time period for batch releases 502.51 1736.1 2112 Maximum time period for a batch release 168.00 168.00 168.00 Average time period for a batch release 13.22 30.46 30.61 Minimum time period for a batch release 0.48 0.12 0.1

PVNGS ARERR 2024 Page 16 ble 3: Units 1, 2, and 3 Gaseous Effluents Average Lower Limit of Detection (Ci/cc)

Table 3:

Units 1, 2, and 3 Gaseous Effluents Average Lower Limit of Detection (Ci/cc)

Nuclide Continuous Batch Nuclide Continuous Batch Antimony-122 2.20E-13 1.90E-11 Argon-41 4.50E-08 4.50E-08 Antimony-124 8.40E-14 1.70E-11 Krypton-85 7.40E-06 7.40E-06 Barium-140 3.40E-13 5.70E-11 Krypton-85m 2.20E-08 2.20E-08 Bromine-82 3.30E-13 1.40E-11 Krypton-87 5.70E-08 5.70E-08 Cerium-141 8.70E-14 3.10E-11 Krypton-88 7.40E-08 7.40E-08 Cerium-144 3.60E-13 6.50E-11 Xenon-125 2.20E-08 2.20E-08 Cesium-134 1.00E-13 2.60E-11 Xenon-127 2.10E-08 2.10E-08 Cesium-137 8.10E-14 1.70E-11 Xenon-131m 9.10E-07 9.10E-07 Cesium-138 5.20E-10 7.30E-10 Xenon-133 6.30E-08 6.30E-08 Chromium-51 6.90E-13 1.40E-10 Xenon-133m 1.90E-07 1.90E-07 Cobalt-58 8.50E-14 1.70E-11 Xenon-135 2.00E-08 2.00E-08 Cobalt-60 1.00E-13 1.90E-11 Xenon-135m 8.90E-08 8.90E-08 Iron-59 1.70E-13 3.20E-11 Xenon-138 2.00E-07 2.00E-07 Lanthanum-140 2.80E-13 2.10E-11 Iodine-131 8.00E-14 7.00E-12 Manganese-54 8.30E-14 1.70E-11 Iodine-132 6.60E-12 1.90E-11 Molybdenum-99 2.40E-13 2.80E-11 Iodine-133 4.70E-13 1.10E-11 Niobium-95 8.70E-14 1.80E-11 Iodine-134 5.90E-11 8.20E-11 Rubidium-88 1.90E-08 1.90E-08 Iodine-135 7.00E-12 5.50E-11 Ruthenium-103 7.40E-14 1.50E-11 Strontium-89 2.15E-15 (1)

Strontium-90 5.60E-16 (1)

Tellurium-123m 6.60E-14 1.50E-11 Tritium 3.80E-07 3.80E-07 Zinc-65 1.90E-13 3.80E-11 Zirconium-95 1.80E-13 4.10E-11 Gross Alpha 3.60E-15 (1)

(1) Not required for batch releases.

PVNGS ARERR 2024 Page 17 T bl 4 U it 1 G Effl t (S ti Of All R l

)

Table 4:

Unit 1 Gaseous Effluents (Summation Of All Releases)

Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Est. Total Error (%) (1)

A. Fission & activation gases

1. Total release Ci 4.21E-02 3.32E-02 1.23E-01 2.19E-01 4.17E-01 3.54E+01

2. Average release rate for period Ci/sec 5.42E-03 4.22E-03 1.55E-02 2.75E-02 1.32E-02

3. Percent of ODCM Requirement limit NA (2)

NA (2)

B. Iodine 131

1. Total Iodine 131 Ci

<LLD

<LLD 3.32E+01

2. Average release rate for period Ci/sec

<LLD

3. Percent of ODCM Requirement limit NA (2)

NA (2)

C. Particulates

1. Particulates with half-lives > 8 days Ci 6.75E-07 1.14E-05 2.25E-05 3.34E-06 3.79E-05 3.43E+01

2. Average release rate for period Ci/sec 8.58E-08 1.45E-06 2.83E-06 4.21E-07 1.2E-06

3. Percent of ODCM Requirement limit NA (2)

NA (2)

4. Gross Alpha radioactivity Ci

< LLD

< LLD D. Tritium

1. Total release Ci 2.76E+01 5.34E+01 9.50E+01 1.01E+02 2.77E+02 3.85E+01

2. Average release rate for period Ci/sec 3.51E+00 6.80E+00 1.20E+01 1.27E+01 8.77E+00

3. Percent of ODCM Requirement limit NA (2)

NA (2)

(1) Estimated total error methodology is presented in Table 40.

(2) See Table 11 for percent of ODCM Requirement limits.

PVNGS ARERR 2024 Page 18 Table 5: Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Table 5: Unit 1 Gaseous Effluents - Ground Level Releases - Continuous -

Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci

<LLD

<LLD Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD 1.05E-00 1.05E-00 Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci

<LLD

<LLD 1.05E-00 1.05E-00

2. Iodines I-131 Ci

<LLD

<LLD 9.53E-06 9.53E-06 I-132 Ci

<LLD

<LLD 4.11E-04 4.11E-04 I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD

<LLD 4.21E-04 4.21E-04

PVNGS ARERR 2024 Page 19 Table 6: Unit 1 Gaseous Effluents-Ground Level Release-Continuous - Particulates Table 6:

Unit 1 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD 1.45E-07 1.45E-07 Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD 2.03E-05 2.03E-05 Co-57 Ci

<LLD

<LLD 2.50E-06 2.50E-06 Co-58 Ci

<LLD

<LLD 1.00E-03 1.00E-03 Co-60 Ci 6.75E-07 1.02E-05 6.93E-07 1.06E-03 1.08E-03 Cr-51 Ci

<LLD

<LLD 3.13E-03 3.13E-03 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD 1.12E-06

<LLD

<LLD 1.12E-06 Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD 1.09E-04 1.09E-04 La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD 3.09E-07 1.61E-04 1.61E-04 Mo-99 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD 1.48E-05 1.16E-03 1.18E-03 Os-191 Ci

<LLD

<LLD 2.64E-06 2.64E-06 Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD 1.36E-05 1.36E-05 Sb-125 Ci

<LLD

<LLD 1.68E-05 1.68E-05 Se-75 Ci

<LLD

<LLD 3.36E-07 3.36E-07 Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD 5.38E-05 5.38E-05 Te-123m Ci

<LLD

<LLD 4.52E-06 4.52E-06 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD

<LLD 6.71E-06 7.22E-04 7.29E-04 Total Ci 6.75E-07 1.14E-05 2.25E-05 7.47E-03 7.50E-03

4. Tritium H-3 Ci 2.76E+01 2.35E+01 2.33E+01 1.82E+02 2.56E+02

PVNGS ARERR 2024 Page 20 Table 7: Unit 1 Gaseous Effluents - Ground Level Releases-Batch - Fission Gases and Iodines Table 7:

Unit 1 Gaseous Effluents - Ground Level Releases-Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci 2.90E-02 4.29E-02 5.85E-02 4.28E-02 1.73E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci 2.49E-04 8.06E-04 2.35E-03 2.11E-03 5.52E-03 Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD 1.72E-04 1.66E-04 3.39E-04 Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci 2.93E-02 4.37E-02 6.10E-02 4.50E-02 1.79E-01

2. Iodines I-131 Ci

<LLD

<LLD I-132 Ci

<LLD

<LLD I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD

PVNGS ARERR 2024 Page 21 Table 8: Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates Table 8:

Unit 1 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci

<LLD

<LLD Cr-51 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD Os-191 Ci

<LLD

<LLD Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD Sb-125 Ci

<LLD

<LLD Se-75 Ci

<LLD

<LLD Sn-113m Ci

<LLD

<LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci

<LLD

<LLD Te-123m Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD

<LLD Total Ci

<LLD

<LLD 4.Tritium H-3 Ci 5.08E-03 3.00E+01 7.17E+01 7.61E+01 1.78E+02 Note 1 - Not required for batch releases.

PVNGS ARERR 2024 Page 22 Table 9: Unit 1 Gaseous Effluents-Continuous and Batch-Fission Gases and Iodines Table 9:

Unit 1 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci 2.90E-02 4.29E-02 4.06E-02 6.06E-02 1.73E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci 2.49E-04 8.06E-04 1.52E-03 2.94E-03 5.52E-03 Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD 1.08E-04 2.31E-04 3.39E-04 Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci 2.93E-02 4.37E-02 4.23E-02 6.38E-02 1.79E-01

2. Iodines I-131 Ci

<LLD

<LLD I-132 Ci

<LLD

<LLD I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD

PVNGS ARERR 2024 Page 23 Table 10: Unit 1 Gaseous Effluents - Continuous and Batch - Particulates Table 10:

Unit 1 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD Co-60 Ci 6.75E-07 1.02E-05 6.93E-07 3.34E-06 1.50E-05 Cr-51 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD 1.12E-06

<LLD

<LLD 1.12E-06 Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD 3.09E-07

<LLD 3.09E-07 Mo-99 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD 1.48E-05

<LLD 1.48E-05 Os-191 Ci

<LLD

<LLD Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD Sb-125 Ci

<LLD

<LLD Se-75 Ci

<LLD

<LLD Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD Te-123m Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD

<LLD 6.71E-06

<LLD 6.71E-06 Total Ci 6.75E-07 1.14E-05 2.25E-05 3.34E-06 3.79E-05 Total > 8 days Ci 6.75E-07 1.14E-05 2.25E-05 3.34E-06 3.79E-05

4. Tritium H-3 Ci 2.76E+01 5.34E+01 9.50E+01 1.01E+02 2.77E+02

PVNGS ARERR 2024 Page 24 Table 11: Unit adiation Doses At And Beyond The Site Boundary Table 11:

Unit 1 Radiation Doses At And Beyond The Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Gamma Air Dose mrad 6.39E-05 9.45E-05 8.97E-05 1.34E-04 3.82E-04 ODCM Req. 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit 1.28E-03 1.89E-03 1.79E-03 2.68E-03 3.82E-03 Beta Air Dose mrad 2.26E-05 3.36E-05 3.21E-05 4.82E-05 1.37E-04 ODCM Req. 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit 2.26E-04 3.36E-04 3.21E-04 4.82E-04 6.83E-04 Maximum Organ Dose (excluding skin) mrem 2.87E-02 2.87E-02 3.26E-02 3.44E-02 1.15E-01 Age Child Child Teen Teen Child Organ Bone Bone Lung Lung Bone ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit 3.83E-01 3.83E-01 4.34E-01 4.59E-01 7.66E-01 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.

T

PVNGS ARERR 2024 Page 25 Table 12: Unit 2 Gaseous Effluents - Summation of All Releases Table 12:

Unit 2 Gaseous Effluents - Summation of All Releases Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Est. Total Error (%) (1)

A. Fission & activation gases

1. Total release Ci 4.36E-02 6.49E-02 9.65E-02 1.46E+00 1.66E+00 3.54E+01

2. Average release rate for period Ci/sec 5.55E-03 8.25E-03 1.21E-02 1.83E-01 5.25E-02

3. Percent of ODCM Requirement limit NA (2)

NA (2)

B. Iodine 131

1. Total Iodine 131 Ci

<LLD

<LLD 3.32E+01

2. Average release rate for period Ci/sec

<LLD

3. Percent of ODCM Requirement limit NA (2)

NA (2)

C. Particulates

1. Particulates with half-lives > 8 days Ci 1.91E-05 8.10E-07

<LLD 3.45E-05 5.44E-05 3.43E+01

2. Average release rate for period Ci/sec 2.42E-06 1.03E-07

<LLD 4.34E-06 1.72E-06

3. Percent of ODCM Requirement limit NA (2)

NA (2)

4. Gross Alpha radioactivity Ci

< LLD

< LLD D. Tritium

1. Total release Ci 1.85E+01 1.23E+02 4.82E+02 1.24E+02 7.48E+02 3.85E+01

2. Average release rate for period Ci/sec 2.35E+00 1.57E+01 6.07E+01 1.56E+01 2.37E+01

3. Percent of ODCM Requirement limit NA (2)

NA (2)

(1) Estimated total error methodology is presented in Table 40.

(2) See Table 19 for percent of ODCM Requirement limits.

PVNGS ARERR 2024 Page 26 Table 13: Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Table 13:

Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci

<LLD

<LLD Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD 1.05E+00 1.05E+00 Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci

<LLD

<LLD 1.05E+00 1.05E+00

2. Iodines I-131 Ci

<LLD

<LLD I-132 Ci

<LLD

<LLD I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD

PVNGS ARERR 2024 Page 27 Table 14: Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Table 14:

Unit 2 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD 1.45E-07 1.45E-07 Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD 7.37E-06 7.37E-06 Co-60 Ci 1.91E-05 8.10E-07

<LLD 6.24E-06 2.61E-05 Cr-51 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD Mo-99 Ci

<LLD

<LLD Nb-95 Ci

<LLD

<LLD 1.79E-06 1.79E-06 Os-191 Ci

<LLD

<LLD Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD Sb-125 Ci

<LLD

<LLD Se-75 Ci

<LLD

<LLD Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD Te-123m Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD

<LLD 3.31E-07 3.31E-07 Total Ci 1.91E-05 8.10E-07

<LLD 1.59E-05 3.57E-05

4. Tritium H-3 Ci 1.85E+01 1.40E+01 1.76E+01 1.39E+01 6.40E+01

PVNGS ARERR 2024 Page 28 Table 15: Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Table 15:

Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci 4.28E-02 5.37E-02 9.42E-02 5.63E-02 2.47E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci 8.28E-04 1.27E-03 2.24E-03 3.49E-01 3.53E-01 Xe-133m Ci

<LLD

<LLD 5.58E-05 5.58E-05 Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD 9.66E-03

<LLD

<LLD 9.66E-03 Xe-138 Ci

<LLD 2.24E-04

<LLD

<LLD 2.24E-04 Total Ci 4.36E-02 6.49E-02 9.65E-02 4.05E-01 6.10E-01

2. Iodines I-131 Ci

<LLD

<LLD I-132 Ci

<LLD

<LLD 7.76E-06 7.76E-06 I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD

<LLD 7.76E-06 7.76E-06

PVNGS ARERR 2024 Page 29 Table 16: Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates Table 16:

Unit 2 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD 1.10E-05 1.10E-05 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD 1.33E-06 1.33E-06 Co-60 Ci

<LLD

<LLD 1.22E-05 1.22E-05 Cr-51 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD

<LLD 3.02E-05 3.02E-05 Fe-59 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD 1.87E-07 1.87E-07 Mo-99 Ci

<LLD

<LLD 1.01E-06 1.01E-06 Nb-95 Ci

<LLD

<LLD 2.35E-06 2.35E-06 Os-191 Ci

<LLD

<LLD Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD 4.31E-08 4.31E-08 Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD 7.03E-08 7.03E-08 Sb-125 Ci

<LLD

<LLD Se-75 Ci

<LLD

<LLD Sn-113m Ci

<LLD

<LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci

<LLD

<LLD Te-123m Ci

<LLD

<LLD 1.48E-07 1.48E-07 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD

<LLD 1.37E-06 1.37E-06 Total Ci

<LLD

<LLD 5.99E-05 5.99E-05

4. Tritium H-3 Ci 1.33E-02 1.09E+02 4.65E+02 1.10E+02 6.84E+02 Note 1 - Not required for batch releases.

PVNGS ARERR 2024 Page 30 Table 17: Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Table 17:

Unit 2 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci 4.28E-02 5.37E-02 9.42E-02 5.63E-02 2.47E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci 8.28E-04 1.27E-03 2.24E-03 1.40E+00 1.40E+00 Xe-133m Ci

<LLD

<LLD 5.58E-05 5.58E-05 Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD 9.66E-03

<LLD

<LLD 9.66E-03 Xe-138 Ci

<LLD 2.24E-04

<LLD

<LLD 2.24E-04 Total Ci 4.36E-02 6.49E-02 9.65E-02 1.46E+00 1.66E+00

2. Iodines I-131 Ci

<LLD

<LLD I-132 Ci

<LLD

<LLD 7.76E-06 7.76E-06 I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD

<LLD 7.76E-06 7.76E-06

PVNGS ARERR 2024 Page 31 Table 18: Unit 2 Gaseous Effluents - Continuous and Batch - Particulates Table 18:

Unit 2 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD 1.45E-07 1.45E-07 Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD 1.10E-05 1.10E-05 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD

<LLD 8.70E-06 8.70E-06 Co-60 Ci 1.91E-05 8.10E-07

<LLD 1.84E-05 3.83E-05 Cr-51 Ci

<LLD

<LLD Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD

<LLD 3.02E-05 3.02E-05 Fe-59 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD

<LLD 1.87E-07 1.87E-07 Mo-99 Ci

<LLD

<LLD 1.01E-06 1.01E-06 Nb-95 Ci

<LLD

<LLD 4.14E-06 4.14E-06 Os-191 Ci

<LLD

<LLD Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD 4.31E-08 4.31E-08 Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD 7.03E-08 7.03E-08 Sb-125 Ci

<LLD

<LLD Se-75 Ci

<LLD

<LLD Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD Te-123m Ci

<LLD

<LLD 1.48E-07 1.48E-07 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD

<LLD 1.70E-06 1.70E-06 Total Ci 1.91E-05 8.10E-07

<LLD 7.58E-05 9.56E-05 Total > 8 days Ci 1.91E-05 8.10E-07

<LLD 3.45E-05 5.44E-05

4. Tritium H-3 Ci 1.85E+01 1.23E+02 4.82E+02 1.24E+02 7.48E+02

PVNGS ARERR 2024 Page 32 pathways present.

Table 19: Unit 2 Radiation Doses at And Beyond The Site Boundary Table 19:

Unit 2 Radiation Doses at And Beyond the Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Gamma Air Dose mrad 9.98E-05 1.29E-04 2.20E-04 2.46E-04 6.94E-04 ODCM Req. 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit 2.00E-03 2.59E-03 4.39E-03 4.91E-03 6.94E-03 Beta Air Dose mrad 3.55E-05 7.56E-05 7.82E-05 5.65E-04 7.54E-04 ODCM Req. 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit 3.55E-04 7.56E-04 7.82E-04 5.65E-03 3.77E-03 Maximum Organ Dose (excluding skin) mrem 3.04E-02 4.34E-02 1.58E-01 4.38E-02 2.55E-01 Age Child Teen Teen Teen Teen Organ Bone Lung T. Body Lung Lung ODCM Req. 4.2 Limit 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit 4.05E-01 5.79E-01 2.11E+00 5.84E-01 1.70E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual

PVNGS ARERR 2024 Page 33 Table 20: Unit 3 Gaseous Effluents - Summation Of All Releases Table 20:

Unit 3 Gaseous Effluents - Summation of All Releases Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Est. Total Error (%)(1)

A. Fission & activation gases

1. Total release Ci 1.29E-01 1.77E-01 7.48E-02 6.67E-02 4.48E-01 3.54E+01

2. Average release rate for period Ci/sec 1.64E-02 2.26E-02 9.41E-03 8.39E-03 1.42E-02

3. Percent of ODCM Requirement limit NA (2)

NA (2)

B. Iodine 131

1. Total Iodine 131 Ci

<LLD 9.53E-06

<LLD

<LLD 9.53E-06 3.32E+01

2. Average release rate for period Ci/sec

<LLD 1.21E-06

<LLD

<LLD 3.02E-07

3. Percent of ODCM Requirement limit NA (2)

NA (2)

C. Particulates

1. Particulates with half-lives > 8 days Ci

<LLD 7.40E-03 5.27E-07 2.58E-06 7.41E-03 3.43E+01

2. Average release rate for period Ci/sec

<LLD 9.41E-04 6.63E-08 3.24E-07 2.34E-04

3. Percent of ODCM Requirement limit NA (2)

NA (2)

4. Gross Alpha radioactivity Ci

< LLD

< LLD D. Tritium

1. Total release Ci 4.43E+02 1.20E+02 8.12E+01 8.20E+01 7.27E+02 3.85E+01

2. Average release rate for period Ci/sec 5.64E+01 1.53E+01 1.02E+01 1.03E+01 2.30E+01

3. Percent of ODCM Requirement limit NA (2)

NA (2)

(1) Estimated total error methodology is presented in Table 40.

(2) See Table 27 for percent of ODCM Requirement limits.

Table U

PVNGS ARERR 2024 Page 34 Table 21: Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Table 21:

Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci

<LLD

<LLD Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci

<LLD

2. Iodines I-131 Ci

<LLD 9.53E-06

<LLD

<LLD 9.53E-06 I-132 Ci

<LLD 4.11E-04

<LLD

<LLD 4.11E-04 I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD 4.21E-04

<LLD

<LLD 4.21E-04

PVNGS ARERR 2024 Page 35 Table 22: Unit 3 Gaseous Effluents - Ground Level Releases - Continuous Particulates Table 22:

Unit 3 Gaseous Effluents - Ground Level Releases - Continuous - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Total

3. Particulates Ag-110m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD 2.03E-05

<LLD

<LLD 2.03E-05 Co-57 Ci

<LLD 2.50E-06

<LLD

<LLD 2.50E-06 Co-58 Ci

<LLD 9.92E-04

<LLD 3.70E-07 9.93E-04 Co-60 Ci

<LLD 1.03E-03

<LLD 1.42E-06 1.03E-03 Cr-51 Ci

<LLD 3.13E-03

<LLD

<LLD 3.13E-03 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD 1.09E-04

<LLD

<LLD 1.09E-04 La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD 1.61E-04

<LLD 2.59E-07 1.61E-04 Mo-99 Ci

<LLD

<LLD Nb-95 Ci

<LLD 1.16E-03 1.51E-07 5.30E-07 1.16E-03 Os-191 Ci

<LLD 2.37E-06 2.69E-07

<LLD 2.64E-06 Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci 1.36E-05

<LLD

<LLD 1.36E-05 1.36E-05 Sb-125 Ci 1.68E-05

<LLD

<LLD 1.68E-05 1.68E-05 Se-75 Ci 3.36E-07

<LLD

<LLD 3.36E-07 3.36E-07 Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD 5.38E-05

<LLD

<LLD 5.38E-05 Te-123m Ci

<LLD 4.45E-06 7.28E-08

<LLD 4.52E-06 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD 7.22E-04

<LLD

<LLD 7.22E-04 Total Ci

<LLD 7.43E-03 4.93E-07 2.58E-06 7.43E-03

4. Tritium H-3 Ci 2.49E+01 1.93E+01 2.82E+01 2.01E+01 9.25E+01

PVNGS ARERR 2024 Page 36 Table 23: Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Table 23:

Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year Total

1. Fission gases Ar-41 Ci 1.29E-01 1.20E-01 7.48E-02 6.66E-02 3.90E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD 1.40E-05

<LLD

<LLD 1.40E-05 Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD 4.43E-04

<LLD

<LLD 4.43E-04 Xe-133 Ci 7.12E-05 5.66E-02

<LLD 7.22E-05 5.68E-02 Xe-133m Ci

<LLD 4.43E-04

<LLD

<LLD 4.43E-04 Xe-135 Ci 5.67E-05 2.65E-07

<LLD

<LLD 5.70E-05 Xe-135m Ci 1.83E-04

<LLD

<LLD 1.83E-04 Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci 1.29E-01 1.77E-01 7.48E-02 6.67E-02 4.48E-01

2. Iodines I-131 Ci

<LLD

<LLD I-132 Ci

<LLD 1.52E-06

<LLD

<LLD 1.52E-06 I-133 Ci

<LLD 7.63E-08

<LLD

<LLD 7.63E-08 I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD 1.60E-06

<LLD

<LLD 1.60E-06

PVNGS ARERR 2024 Page 37 Table 24: Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates l

Table 24:

Unit 3 Gaseous Effluents - Ground Level Releases - Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD Br-82 Ci 0

4.92E-06 0

0 4.92E-06 Ce-141 Ci 0

0 0

Ce-144 Ci 0

0 0

Co-57 Ci 0

0 0

Co-58 Ci 0

2.49E-06 0

0 2.49E-06 Co-60 Ci 0

7.35E-06 0

0 7.35E-06 Cr-51 Ci 0

4.02E-06 0

0 4.02E-06 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Mn-54 Ci 0

3.3E-07 0

0 3.30E-07 Mo-99 Ci 0

0 0

Nb-95 Ci 0

8.71E-06 0

0 8.71E-06 Os-191 Ci

<LLD

<LLD Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD Sb-125 Ci

<LLD

<LLD Se-75 Ci

<LLD 0

3.46E-08 0

3.46E-08 Sn-113m Ci

<LLD

<LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci

<LLD

<LLD Te-123m Ci

<LLD

<LLD Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD 6.78E-06

<LLD

<LLD 6.78E-06 Total Ci

<LLD 3.46E-05 3.46E-08

<LLD 3.46E-05

4. Tritium H-3 Ci 4.19E+02 1.01E+02 5.30E+01 6.18E+01 6.34E+02 Note 1 - Not required for batch releases.

PVNGS ARERR 2024 Page 38 Table 25: Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Table 25:

Unit 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci 1.29E-01 1.20E-01 7.48E-02 6.66E-02 3.90E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD 1.40E-05

<LLD

<LLD 1.40E-05 Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD 4.43E-04

<LLD

<LLD 4.43E-04 Xe-133 Ci 7.12E-05 5.66E-02

<LLD 7.22E-05 5.68E-02 Xe-133m Ci

<LLD 4.43E-04

<LLD

<LLD 4.43E-04 Xe-135 Ci 5.67E-05 2.65E-07

<LLD

<LLD 5.70E-05 Xe-135m Ci 1.83E-04

<LLD

<LLD 1.83E-04 Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci 1.29E-01 1.77E-01 7.48E-02 6.67E-02 4.48E-01

2. Iodines I-131 Ci

<LLD 9.53E-06

<LLD

<LLD 9.53E-06 I-132 Ci

<LLD 4.13E-04

<LLD

<LLD 4.13E-04 I-133 Ci

<LLD 7.63E-08

<LLD

<LLD 7.63E-08 I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD 4.23E-04

<LLD

<LLD 4.23E-04

PVNGS ARERR 2024 Page 39 Table 26: Unit 3 Gaseous Effluents - Continuous and Batch - Particulates Table 26:

Unit 3 Gaseous Effluents - Continuous and Batch - Particulates Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD 4.92E-06

<LLD

<LLD 4.92E-06 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD 2.03E-05

<LLD

<LLD 2.03E-05 Co-57 Ci

<LLD 2.50E-06

<LLD

<LLD 2.50E-06 Co-58 Ci

<LLD 9.95E-04

<LLD 3.70E-07 9.95E-04 Co-60 Ci

<LLD 1.04E-03

<LLD 1.42E-06 1.04E-03 Cr-51 Ci

<LLD 3.14E-03

<LLD

<LLD 3.14E-03 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD 1.09E-04

<LLD

<LLD 1.09E-04 La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD 1.61E-04

<LLD 2.59E-07 1.61E-04 Mo-99 Ci

<LLD

<LLD Nb-95 Ci

<LLD 1.17E-03 1.51E-07 5.30E-07 1.17E-03 Os-191 Ci

<LLD 2.37E-06 2.69E-07

<LLD 2.64E-06 Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD 1.36E-05

<LLD

<LLD 1.36E-05 Sb-125 Ci

<LLD 1.68E-05

<LLD

<LLD 1.68E-05 Se-75 Ci

<LLD 3.36E-07 3.46E-08

<LLD 3.71E-07 Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD 5.38E-05

<LLD

<LLD 5.38E-05 Te-123m Ci

<LLD 4.45E-06 7.28E-08

<LLD 4.52E-06 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD 7.28E-04

<LLD

<LLD 7.28E-04 Total Ci

<LLD 7.46E-03 5.27E-07 2.58E-06 7.46E-03 Total > 8 days Ci

<LLD 7.40E-03 5.27E-07 2.58E-06 7.41E-03

4. Tritium H-3 Ci 4.43E+02 1.20E+02 8.12E+01 8.20E+01 7.27E+02

PVNGS ARERR 2024 Page 40 Table 27: Unit 3 Radiation Doses at And Beyond the Site Boundary Table 27:

Unit 3 Radiation Doses at And Beyond the Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Gamma Air Dose mrad 3.39E-04 3.20E-04 1.97E-04 1.75E-04 1.03E-03 ODCM Req. 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit 6.78E-03 6.40E-03 3.93E-03 3.50E-03 1.03E-02 Beta Air Dose mrad 1.20E-04 1.35E-04 6.93E-05 6.18E-05 3.86E-04 ODCM Req. 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit 1.20E-03 1.35E-03 6.93E-04 6.18E-04 1.93E-03 Maximum Organ Dose (excluding skin) mrem 1.64E-01 5.19E-02 3.43E-02 3.43E-02 2.84E-01 Age Teen Teen Child Child Teen Organ T. Body Lung Bone Bone Lung ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limit 2.19E+00 6.92E-01 4.57E-01 4.57E-01 1.89E+00 Calculations are based on parameters and methodologies of the ODCM using historical meteorology. Dose is calculated to a hypothetical individual. In contrast, Appendix C dose calculations are based on concurrent meteorology, a real individual, and only the actual pathways present.

PVNGS ARERR 2024 Page 41 Table 28: Units 1, 2, and 3 Gaseous Effluents - Continuous - Fission Gases and Iodines - Total by Quarter Table 28:

Units 1, 2, and 3 - Ground Level Releases Gaseous Effluents - Continuous - Fission Gases and Iodines - Total by Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci

<LLD

<LLD Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci

<LLD

<LLD 1.05E+00 1.05E+00 Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci

<LLD

<LLD 1.05E+00 1.05E+00

2. Iodines I-131 Ci

<LLD 9.53E-06

<LLD

<LLD 9.53E-06 I-132 Ci

<LLD 4.11E-04

<LLD

<LLD 4.11E-04 I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD 4.21E-04

<LLD

<LLD 4.21E-04

PVNGS ARERR 2024 Page 42 Table 29: Units 1, 2, and 3 Gaseous Effluents - Continuous - Particulates - Total by Quarter Table 29:

Units 1, 2, and 3 - Ground Level Releases Gaseous Effluents - Continuous - Particulates - Total by Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD 1.45E-07 1.45E-07 Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD 2.03E-05

<LLD

<LLD 2.03E-05 Co-57 Ci

<LLD 2.50E-06

<LLD

<LLD 2.50E-06 Co-58 Ci

<LLD 9.92E-04

<LLD 7.74E-06 1.00E-03 Co-60 Ci 1.97E-05 1.04E-03 6.93E-07 1.10E-05 1.08E-03 Cr-51 Ci

<LLD 3.13E-03

<LLD

<LLD 3.13E-03 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD 1.12E-06

<LLD

<LLD 1.12E-06 Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD 1.09E-04

<LLD

<LLD 1.09E-04 La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD 1.61E-04 3.09E-07 2.59E-07 1.61E-04 Mo-99 Ci

<LLD

<LLD Nb-95 Ci

<LLD 1.16E-03 1.49E-05 2.32E-06 1.18E-03 Os-191 Ci

<LLD 2.37E-06 2.69E-07

<LLD 2.64E-06 Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD 1.36E-05

<LLD

<LLD 1.36E-05 Sb-125 Ci

<LLD 1.68E-05

<LLD

<LLD 1.68E-05 Se-75 Ci

<LLD 3.36E-07

<LLD

<LLD 3.36E-07 Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD 5.38E-05

<LLD

<LLD 5.38E-05 Te-123m Ci

<LLD 4.45E-06 7.28E-08

<LLD 4.52E-06 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD 7.22E-04 6.71E-06 3.31E-07 7.29E-04 Total Ci 1.97E-05 7.44E-03 2.30E-05 2.18E-05 7.50E-03

4. Tritium H-3 Ci 7.26E+01 5.71E+01 6.85E+01 5.77E+01 2.56E+02

PVNGS ARERR 2024 Page 43 Table 30: Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodines - Total by Quarter Table 30:

Units 1, 2, and 3 - Ground Level Releases Gaseous Effluents - Batch - Fission Gases and Iodines - Total by Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci 2.01E-01 2.16E-01 2.28E-01 1.66E-01 8.10E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD 1.40E-05

<LLD

<LLD 1.40E-05 Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD 4.43E-04

<LLD

<LLD 4.43E-04 Xe-133 Ci 1.15E-03 5.87E-02 4.60E-03 3.51E-01 4.15E-01 Xe-133m Ci

<LLD 4.43E-04

<LLD 5.58E-05 4.98E-04 Xe-135 Ci 5.67E-05 2.65E-07 1.72E-04 1.66E-04 3.96E-04 Xe-135m Ci 1.83E-04

<LLD

<LLD 1.83E-04 Xe-137 Ci

<LLD 9.66E-03

<LLD

<LLD 9.66E-03 Xe-138 Ci

<LLD 2.24E-04

<LLD

<LLD 2.24E-04 Total Ci 2.02E-01 2.86E-01 2.32E-01 5.17E-01 1.24E+00

2. Iodines I-131 Ci

<LLD

<LLD I-132 Ci

<LLD 1.52E-06

<LLD 7.76E-06 9.29E-06 I-133 Ci

<LLD 7.63E-08

<LLD

<LLD 7.63E-08 I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD 1.60E-06

<LLD 7.76E-06 9.36E-06

PVNGS ARERR 2024 Page 44 Table 31: Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total by Quarter Table 31:

Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total by Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD 4.92E-06

<LLD 1.10E-05 1.59E-05 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD 2.49E-06

<LLD 1.33E-06 3.82E-06 Co-60 Ci

<LLD 7.35E-06

<LLD 1.22E-05 1.95E-05 Cr-51 Ci

<LLD 4.02E-06

<LLD

<LLD 4.02E-06 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD

<LLD 3.02E-05 3.02E-05 Fe-59 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD 3.30E-07

<LLD 1.87E-07 5.17E-07 Mo-99 Ci

<LLD

<LLD 1.01E-06 1.01E-06 Nb-95 Ci

<LLD 8.71E-06

<LLD 2.35E-06 1.11E-05 Os-191 Ci

<LLD

<LLD Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD 4.31E-08 4.31E-08 Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD 7.03E-08 7.03E-08 Sb-125 Ci

<LLD

<LLD Se-75 Ci

<LLD

<LLD 3.46E-08

<LLD 3.46E-08 Sn-113m Ci

<LLD

<LLD Sr-89 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Sr-90 Ci Note 1 Note 1 Note 1 Note 1 Note 1 Tc-99m Ci

<LLD

<LLD Te-123m Ci

<LLD

<LLD 1.48E-07 1.48E-07 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD 6.78E-06

<LLD 1.37E-06 8.14E-06 Total Ci

<LLD 3.46E-05 3.46E-08 5.99E-05 9.45E-05

4. Tritium H-3 Ci 4.19E+02 2.40E+02 5.89E+02 2.48E+02 1.50E+03 Note 1 - Not required for batch releases.

PVNGS ARERR 2024 Page 45 Table 32: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines - Total by Quarter Table 32:

Units 1, 2, and 3 - Ground Level Releases Gaseous Effluents - Continuous and Batch - Fission Gases and Iodines - Total by Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

1. Fission gases Ar-41 Ci 2.01E-01 2.16E-01 2.28E-01 1.66E-01 8.10E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD 1.40E-05

<LLD

<LLD 1.40E-05 Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD 4.43E-04

<LLD

<LLD 4.43E-04 Xe-133 Ci 1.15E-03 5.87E-02 4.60E-03 1.40E+00 1.47E+00 Xe-133m Ci

<LLD 4.43E-04

<LLD 5.58E-05 4.98E-04 Xe-135 Ci 5.67E-05 2.65E-07 1.72E-04 1.66E-04 3.96E-04 Xe-135m Ci 1.83E-04

<LLD

<LLD 1.83E-04 Xe-137 Ci

<LLD 9.66E-03

<LLD

<LLD 9.66E-03 Xe-138 Ci

<LLD 2.24E-04

<LLD

<LLD 2.24E-04 Total Ci 2.02E-01 2.86E-01 2.32E-01 1.57E+00 2.29E+00

2. Iodines I-131 Ci

<LLD 9.53E-06

<LLD

<LLD 9.53E-06 I-132 Ci

<LLD 4.13E-04

<LLD 7.76E-06 4.21E-04 I-133 Ci

<LLD 7.63E-08

<LLD

<LLD 7.63E-08 I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD 4.23E-04

<LLD 7.76E-06 4.30E-04

PVNGS ARERR 2024 Page 46 Table 33: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total by Quarter Table 33:

Units 1, 2, and 3 - Ground Level Releases Gaseous Effluents - Continuous and Batch - Particulates - Total by Quarter Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

3. Particulates Ag-110m Ci

<LLD

<LLD 1.45E-07 1.45E-07 Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD 4.92E-06

<LLD 1.10E-05 1.59E-05 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD 2.03E-05

<LLD

<LLD 2.03E-05 Co-57 Ci

<LLD 2.50E-06

<LLD

<LLD 2.50E-06 Co-58 Ci

<LLD 9.95E-04

<LLD 9.07E-06 1.00E-03 Co-60 Ci 1.97E-05 1.05E-03 6.93E-07 2.32E-05 1.10E-03 Cr-51 Ci

<LLD 3.14E-03

<LLD

<LLD 3.14E-03 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD 1.12E-06

<LLD

<LLD 1.12E-06 Cs-138 Ci

<LLD

<LLD 3.02E-05 3.02E-05 Fe-59 Ci

<LLD 1.09E-04

<LLD

<LLD 1.09E-04 La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD 1.61E-04 3.09E-07 4.45E-07 1.62E-04 Mo-99 Ci

<LLD

<LLD 1.01E-06 1.01E-06 Nb-95 Ci

<LLD 1.17E-03 1.49E-05 4.67E-06 1.19E-03 Os-191 Ci

<LLD 2.37E-06 2.69E-07

<LLD 2.64E-06 Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD 4.31E-08 4.31E-08 Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD 1.36E-05

<LLD 7.03E-08 1.37E-05 Sb-125 Ci

<LLD 1.68E-05

<LLD

<LLD 1.68E-05 Se-75 Ci

<LLD 3.36E-07 3.46E-08

<LLD 3.71E-07 Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD 5.38E-05

<LLD

<LLD 5.38E-05 Te-123m Ci

<LLD 4.45E-06 7.28E-08 1.48E-07 4.67E-06 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD 7.28E-04 6.71E-06 1.70E-06 7.37E-04 Total Ci 1.97E-05 7.47E-03 2.30E-05 8.17E-05 7.60E-03 Total > 8 days Ci

<LLD

<LLD 1.45E-07 1.45E-07

4. Tritium H-3 Ci 8.50E+02 7.27E+02 5.71E+02 6.59E+02 2.81E+03

PVNGS ARERR 2024 Page 47 Table 34: Units 1, 2, and 3 Gaseous Effluents-Continuous - Fission Gases and Iodine -Total by Unit Table 34:

Units 1, 2, and 3 - Ground Level Releases Gaseous Effluents - Continuous - Fission Gases and Iodine -Total by Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total

1. Fission gases Ar-41 Ci

<LLD

<LLD Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD Xe-133 Ci

<LLD 1.05E+00

<LLD 1.05E+00 Xe-133m Ci

<LLD

<LLD Xe-135 Ci

<LLD

<LLD Xe-135m Ci

<LLD

<LLD Xe-137 Ci

<LLD

<LLD Xe-138 Ci

<LLD

<LLD Total Ci

<LLD 1.05E+00

2. Iodines I-131 Ci

<LLD

<LLD 9.53E-06 9.53E-06 I-132 Ci

<LLD

<LLD 4.11E-04 4.11E-04 I-133 Ci

<LLD

<LLD I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD

<LLD 4.21E-04 4.21E-04

PVNGS ARERR 2024 Page 48 Table 35: Units 1, 2, and 3 Gaseous Effluents-Continuous - Particulates - Total by Unit Table 35:

Units 1, 2, and 3 - Ground Level Releases Gaseous Effluents - Continuous - Particulates - Total by Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total

3. Particulates Ag-110m Ci

<LLD 1.45E-07

<LLD 1.45E-07 Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD

<LLD Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD 2.03E-05 2.03E-05 Co-57 Ci

<LLD

<LLD 2.50E-06 2.50E-06 Co-58 Ci

<LLD 7.37E-06 9.93E-04 1.00E-03 Co-60 Ci 1.50E-05 2.61E-05 1.03E-03 1.08E-03 Cr-51 Ci

<LLD

<LLD 3.13E-03 3.13E-03 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci 1.12E-06

<LLD

<LLD 1.12E-06 Cs-138 Ci

<LLD

<LLD Fe-59 Ci

<LLD

<LLD 1.09E-04 1.09E-04 La-140 Ci

<LLD

<LLD Mn-54 Ci 3.09E-07

<LLD 1.61E-04 1.61E-04 Mo-99 Ci

<LLD

<LLD Nb-95 Ci 1.48E-05 1.79E-06 1.16E-03 1.18E-03 Os-191 Ci

<LLD

<LLD 2.64E-06 2.64E-06 Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD

<LLD Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD

<LLD 1.36E-05 1.36E-05 Sb-125 Ci

<LLD

<LLD 1.68E-05 1.68E-05 Se-75 Ci

<LLD

<LLD 3.36E-07 3.36E-07 Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD 5.38E-05 5.38E-05 Te-123m Ci

<LLD

<LLD 4.52E-06 4.52E-06 Zn-65 Ci

<LLD

<LLD Zr-95 Ci 6.71E-06 3.31E-07 7.22E-04 7.29E-04 Total Ci 3.79E-05 3.57E-05 7.43E-03 7.50E-03

4. Tritium H-3 Ci 9.95E+01 6.40E+01 9.25E+01 2.56E+02

PVNGS ARERR 2024 Page 49 Table 36: Units 1, 2, and 3 Gaseous Effluents-Batch - Fission Gases and Iodine - Total by Unit Table 36:

Units 1, 2, and 3 Gaseous Effluents - Batch - Fission Gases and Iodine - Total by Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total

1. Fission gases Ar-41 Ci 1.73E-01 2.47E-01 3.90E-01 8.10E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD 1.40E-05 1.40E-05 Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD 4.43E-04 4.43E-04 Xe-133 Ci 5.52E-03 3.53E-01 5.68E-02 4.15E-01 Xe-133m Ci

<LLD 5.58E-05 4.43E-04 4.98E-04 Xe-135 Ci 3.39E-04

<LLD 5.70E-05 3.96E-04 Xe-135m Ci

<LLD

<LLD 1.83E-04 1.83E-04 Xe-137 Ci

<LLD 9.66E-03

<LLD 9.66E-03 Xe-138 Ci

<LLD 2.24E-04

<LLD 2.24E-04 Total Ci 1.79E-01 6.10E-01 4.48E-01 1.24E+00

2. Iodines I-131 Ci

<LLD

<LLD I-132 Ci

<LLD 7.76E-06 1.52E-06 9.29E-06 I-133 Ci

<LLD

<LLD 7.63E-08 7.63E-08 I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD 7.76E-06 1.60E-06 9.36E-06

PVNGS ARERR 2024 Page 50 Table 37: Units 1, 2, and 3 Gaseous Effluents-Batch - Particulates - Total by Unit Table 37:

Units 1, 2, and 3 Gaseous Effluents - Batch - Particulates - Total by Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total

3. Particulates Ag-110m Ci

<LLD

<LLD Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD 1.10E-05 4.92E-06 1.59E-05 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD Co-57 Ci

<LLD

<LLD Co-58 Ci

<LLD 1.33E-06 2.49E-06 3.82E-06 Co-60 Ci

<LLD 1.22E-05 7.35E-06 1.95E-05 Cr-51 Ci

<LLD

<LLD 4.02E-06 4.02E-06 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci

<LLD

<LLD Cs-138 Ci

<LLD 3.02E-05

<LLD 3.02E-05 Fe-59 Ci

<LLD

<LLD La-140 Ci

<LLD

<LLD Mn-54 Ci

<LLD 1.87E-07 3.30E-07 5.17E-07 Mo-99 Ci

<LLD 1.01E-06

<LLD 1.01E-06 Nb-95 Ci

<LLD 2.35E-06 8.71E-06 1.11E-05 Os-191 Ci

<LLD

<LLD Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD 4.31E-08

<LLD 4.31E-08 Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD 7.03E-08

<LLD 7.03E-08 Sb-125 Ci

<LLD

<LLD Se-75 Ci

<LLD

<LLD 3.46E-08 3.46E-08 Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD Te-123m Ci

<LLD 1.48E-07

<LLD 1.48E-07 Zn-65 Ci

<LLD

<LLD Zr-95 Ci

<LLD 1.37E-06 6.78E-06 8.14E-06 Total Ci

<LLD 5.99E-05 3.46E-05 9.45E-05

4. Tritium H-3 Ci 1.78E+02 6.84E+02 6.34E+02 1.50E+03 Note 1 - Not required for batch releases.

PVNGS ARERR 2024 Page 51 Table 38: Units 1, 2, and 3 Gaseous Effluents-Continuous and Batch - Fission Gases and Iodine - Total by Unit Table 38:

Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Fission Gases and Iodine - Total by Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total

1. Fission gases Ar-41 Ci 1.73E-01 2.47E-01 3.90E-01 8.10E-01 Kr-83m Ci

<LLD

<LLD Kr-85 Ci

<LLD

<LLD Kr-85m Ci

<LLD

<LLD Kr-87 Ci

<LLD

<LLD Kr-88 Ci

<LLD

<LLD 1.40E-05 1.40E-05 Kr-89 Ci

<LLD

<LLD Kr-90 Ci

<LLD

<LLD Xe-131m Ci

<LLD

<LLD 4.43E-04 4.43E-04 Xe-133 Ci 5.52E-03 1.40E+00 5.68E-02 1.47E+00 Xe-133m Ci

<LLD 5.58E-05 4.43E-04 4.98E-04 Xe-135 Ci 3.39E-04

<LLD 5.70E-05 3.96E-04 Xe-135m Ci

<LLD

<LLD 1.83E-04 1.83E-04 Xe-137 Ci

<LLD 9.66E-03

<LLD 9.66E-03 Xe-138 Ci

<LLD 2.24E-04

<LLD 2.24E-04 Total Ci 1.79E-01 1.66E+00 4.48E-01 2.29E+00

2. Iodines I-131 Ci

<LLD

<LLD 9.53E-06 9.53E-06 I-132 Ci

<LLD 7.76E-06 4.13E-04 4.21E-04 I-133 Ci

<LLD

<LLD 7.63E-08 7.63E-08 I-134 Ci

<LLD

<LLD I-135 Ci

<LLD

<LLD Total Ci

<LLD 7.76E-06 4.23E-04 4.30E-04

PVNGS ARERR 2024 Page 52 Table 39: Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total by Unit Table 39:

Units 1, 2, and 3 Gaseous Effluents - Continuous and Batch - Particulates - Total by Unit Nuclides Released Unit Unit 1 Unit 2 Unit 3 Total

3. Particulates Ag-110m Ci

<LLD 1.45E-07

<LLD 1.45E-07 Ba-140 Ci

<LLD

<LLD Br-82 Ci

<LLD 1.10E-05 4.92E-06 1.59E-05 Ce-141 Ci

<LLD

<LLD Ce-144 Ci

<LLD

<LLD 2.03E-05 2.03E-05 Co-57 Ci

<LLD

<LLD 2.50E-06 2.50E-06 Co-58 Ci

<LLD 8.70E-06 9.95E-04 1.00E-03 Co-60 Ci 1.50E-05 3.83E-05 1.04E-03 1.10E-03 Cr-51 Ci

<LLD

<LLD 3.14E-03 3.14E-03 Cs-134 Ci

<LLD

<LLD Cs-136 Ci

<LLD

<LLD Cs-137 Ci 1.12E-06

<LLD

<LLD 1.12E-06 Cs-138 Ci

<LLD 3.02E-05

<LLD 3.02E-05 Fe-59 Ci

<LLD

<LLD 1.09E-04 1.09E-04 La-140 Ci

<LLD

<LLD Mn-54 Ci 3.09E-07 1.87E-07 1.61E-04 1.62E-04 Mo-99 Ci

<LLD 1.01E-06

<LLD 1.01E-06 Nb-95 Ci 1.48E-05 4.14E-06 1.17E-03 1.19E-03 Os-191 Ci

<LLD

<LLD 2.64E-06 2.64E-06 Rb-88 Ci

<LLD

<LLD Ru-103 Ci

<LLD 4.31E-08

<LLD 4.31E-08 Ru-106 Ci

<LLD

<LLD Sb-122 Ci

<LLD

<LLD Sb-124 Ci

<LLD 7.03E-08 1.36E-05 1.37E-05 Sb-125 Ci

<LLD

<LLD 1.68E-05 1.68E-05 Se-75 Ci

<LLD

<LLD 3.71E-07 3.71E-07 Sn-113m Ci

<LLD

<LLD Sr-89 Ci

<LLD

<LLD Sr-90 Ci

<LLD

<LLD Tc-99m Ci

<LLD

<LLD 5.38E-05 5.38E-05 Te-123m Ci

<LLD 1.48E-07 4.52E-06 4.67E-06 Zn-65 Ci

<LLD

<LLD Zr-95 Ci 6.71E-06 1.70E-06 7.28E-04 7.37E-04 Total Ci 3.79E-05 9.56E-05 7.46E-03 7.60E-03 Total > 8 days Ci

<LLD 1.45E-07

4. Tritium H-3 Ci 2.77E+02 7.48E+02 7.27E+02 1.75E+03

PVNGS ARERR 2024 Page 53 Table 40: Estimation of Total Percent Error Table 40: Estimation of Total Percent Error Noble Gases Iodines Particulates Tritium Error 25 25 25 25 Sample counting error 10 10 10 10 Counting system calibration error 5

5 5

5 Counting system source error 20 N/A N/A N/A Temperature/volume correction error 10 10 10 10 Process flow measuring device (1)

N/A 15 15 15 Sample flow measuring device N/A 5

N/A N/A Iodine collection efficiency error N/A N/A 10 N/A Plate-out error N/A N/A N/A 20 Bubbler collection efficiency error N/A N/A N/A 2

Sample volume transfer error (pipette)

N/A N/A N/A 2

Sample volume error (graduate)

Note 1 - % of full scale.

The estimated total error is calculated as follows:

Total Percent Error = (

+

+ +

)

Where En = Percent error associated with each contributing parameter.

Parameters contributing to errors in the measurement of gaseous effluents include: process flow rates, sample collection, analytical counting and tank volumes. The values in Table 40 (%) were used for error calculations.

Table 41: Effluent Monitoring Instrumentation: Out of Service Greater Than 30 Daystrumentation Out of Service Greater Than 30 Days Unit Instrument Dates of Inoperability Cause of Inoperability Explanation None

PVNGS ARERR 2024 Page 54 Table 42: Solid Waste Summary Table 42: Solid Waste Summary 1.0 Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel)

Table 1.c: Irradiated Components Waste Class Volume (ft3)

Volume (m3)

Curies Shipped Percent Error None Table 1.a: Spent Resin, Filters, Sludge, Evaporator Bottoms, etc.

Waste Class Volume (ft3)

Volume (m3)

Curies Shipped Percent Error A

2.24E+03 6.34E+01 2.22E+01 2.50E+01 B

2.41E+02 6.81E+00 7.05E+01 2.50E+01 C

<LLD

<LLD N/A All 2.48E+03 7.03E+01 9.27E+01 2.50E+01 Table 1.b: Dry Compressible Waste, Contaminated Equipment, etc.

Waste Class Volume (ft3)

Volume (m3)

Curies Shipped Percent Error A

2.71E+04 7.68E+02 3.34E-01 2.50E+01 B

<LLD

<LLD N/A C

<LLD

<LLD N/A All 2.71E+04 7.68E+02 3.34E-01 2.50E+01 Table 1.d: Other Waste: Oil, S/G Cleaning Solution Waste Class Volume (ft3)

Volume (m3)

Curies Shipped Percent Error A

4.06E+03 1.15E+02 5.51E-03 2.50E+01 B

<LLD

<LLD N/A C

<LLD

<LLD N/A All 4.06E+03 1.15E+02 5.51E-03 2.50E+01 Table 1.e: Summary of All Waste Shipped Waste Class Volume (ft3)

Volume (m3)

Curies Shipped Percent Error A

3.34E+04 9.46E+02 2.26E+01 2.50E+01 B

2.41E+02 6.81E+00 7.05E+01 2.50E+01 C

<LLD

<LLD N/A All 3.37E+04 9.53E+02 9.31E+01 2.50E+01 I

I I

I

PVNGS ARERR 2024 Page 55 2.0 Estimate of major nuclide composition Table 2.a: Spent Resin, Filters, Sludge, Evaporator Bottoms, etc.

Nuclide Percent Abundance Curies Percent Error H-3 3.94E-01 3.65E-01 2.50E+01 C-14 1.86E-01 1.72E-01 2.50E+01 Mn-54 7.01E+00 6.50E+00 2.50E+01 Fe-55 8.67E+00 8.04E+00 2.50E+01 Co-57 2.41E-01 2.23E-01 2.50E+01 Co-58 3.23E+00 2.99E+00 2.50E+01 Co-60 1.66E+01 1.54E+01 2.50E+01 Ni-59 2.86E-01 2.65E-01 2.50E+01 Ni-63 5.35E+01 4.96E+01 2.50E+01 Zn-65 3.86E-02 3.58E-02 2.50E+01 Sr-90 4.65E-02 4.31E-02 2.50E+01 Zr-95 1.75E-04 1.62E-04 2.50E+01 Nb-95 2.64E-02 2.45E-02 2.50E+01 Tc-99 9.40E-02 8.71E-02 2.50E+01 Ag-110m 1.62E+00 1.50E+00 2.50E+01 Sn-113 1.11E-01 1.03E-01 2.50E+01 Sb-124 1.62E-02 1.50E-02 2.50E+01 Sb-125 6.86E+00 6.36E+00 2.50E+01 Cs-137 1.02E+00 9.46E-01 2.50E+01 Ce-144 3.19E-02 2.96E-02 2.50E+01 Pu-238 7.41E-05 6.87E-05 2.50E+01 Pu-239 4.11E-05 3.81E-05 2.50E+01 Pu-241 3.50E-03 3.24E-03 2.50E+01 Am-241 1.59E-04 1.47E-04 2.50E+01 Am-243 1.94E-05 1.80E-05 2.50E+01 Cm-242 4.83E-05 4.48E-05 2.50E+01 Cm-243 1.93E-04 1.79E-04 2.50E+01 Total 9.27E+01 2.50E+01

PVNGS ARERR 2024 Page 56 Table 2.b: Dry Active Waste (DAW)

Nuclide Percent Abundance Curies Percent Error H-3 8.55E-03 2.86E-05 2.50E+01 C-14 5.17E-01 1.73E-03 2.50E+01 Sc-46 6.52E-02 2.18E-04 2.50E+01 Cr-51 1.65E+01 5.51E-02 2.50E+01 Mn-54 1.93E+00 6.47E-03 2.50E+01 Fe-55 4.49E+00 1.50E-02 2.50E+01 Fe-59 5.11E-01 1.71E-03 2.50E+01 Co-57 5.20E-02 1.74E-04 2.50E+01 Co-58 1.30E+01 4.35E-02 2.50E+01 Co-60 1.83E+01 6.13E-02 2.50E+01 Ni-63 1.38E+00 4.60E-03 2.50E+01 Zn-65 1.92E-01 6.42E-04 2.50E+01 Sr-89 1.08E-02 3.62E-05 2.50E+01 Sr-90 6.34E-03 2.12E-05 2.50E+01 Zr-95 1.61E+01 5.38E-02 2.50E+01 Nb-95 2.53E+01 8.46E-02 2.50E+01 Tc-99 2.84E-05 9.50E-08 2.50E+01 Ag-110m 7.56E-02 2.53E-04 2.50E+01 Sn-113 3.59E-01 1.20E-03 2.50E+01 Sb-124 1.74E-01 5.83E-04 2.50E+01 Sb-125 5.80E-01 1.94E-03 2.50E+01 Te-123m 1.56E-01 5.21E-04 2.50E+01 Cs-137 3.59E-02 1.20E-04 2.50E+01 Ce-144 9.09E-02 3.04E-04 2.50E+01 Hf-181 1.76E-01 5.89E-04 2.50E+01 Pu-238 6.49E-05 2.17E-07 2.50E+01 Pu-239 4.25E-05 1.42E-07 2.50E+01 Am-241 9.48E-05 3.17E-07 2.50E+01 Cm-242 8.88E-05 2.97E-07 2.50E+01 Cm-243 6.37E-05 2.13E-07 2.50E+01 Total 3.34E-01 2.50E+01

PVNGS ARERR 2024 Page 57 Table 2.e: Summary of All Waste Shipped Nuclide Percent Abundance Curies Percent Error H-3 3.92E-01 3.65E-01 2.50E+01 C-14 1.92E-01 1.79E-01 2.50E+01 Sc-46 2.34E-04 2.18E-04 2.50E+01 Cr-51 5.92E-02 5.51E-02 2.50E+01 Mn-54 6.98E+00 6.50E+00 2.50E+01 Fe-55 8.65E+00 8.05E+00 2.50E+01 Fe-59 1.84E-03 1.71E-03 2.50E+01 Co-57 2.40E-01 2.23E-01 2.50E+01 Co-58 3.26E+00 3.03E+00 2.50E+01 Co-60 1.67E+01 1.55E+01 2.50E+01 Ni-59 2.85E-01 2.65E-01 2.50E+01 Ni-63 5.33E+01 4.96E+01 2.50E+01 Zn-65 3.91E-02 3.64E-02 2.50E+01 Sr-89 3.89E-05 3.62E-05 2.50E+01 Sr-90 4.63E-02 4.31E-02 2.50E+01 Zr-95 5.80E-02 5.40E-02 2.50E+01 Nb-95 1.17E-01 1.09E-01 2.50E+01 Tc-99 9.36E-02 8.71E-02 2.50E+01 Ag-110m 1.62E+00 1.51E+00 2.50E+01 Sn-113 1.12E-01 1.04E-01 2.50E+01 Sb-124 1.68E-02 1.56E-02 2.50E+01 Sb-125 6.84E+00 6.37E+00 2.50E+01 Te-123m 5.60E-04 5.21E-04 2.50E+01 Cs-137 1.02E+00 9.46E-01 2.50E+01 Ce-144 3.21E-02 2.99E-02 2.50E+01 Table 2.c: Irradiated Components Nuclide Percent Abundance Curies Percent Error None Table 2.d: Other Waste: Oil Nuclide Percent Abundance Curies Percent Error C-14 9.95E+01 5.48E-03 2.50E+01 Co-60 2.92E-01 1.61E-05 2.50E+01 Cs-137 1.67E-01 9.18E-06 2.50E+01 Total 5.51E-03 2.50E+01

PVNGS ARERR 2024 Page 58 Hf-181 6.33E-04 5.89E-04 2.50E+01 Pu-238 7.40E-05 6.89E-05 2.50E+01 Pu-239 4.10E-05 3.82E-05 2.50E+01 Pu-241 3.48E-03 3.24E-03 2.50E+01 Am-241 1.58E-04 1.47E-04 2.50E+01 Am-243 1.93E-05 1.80E-05 2.50E+01 Cm-242 4.85E-05 4.51E-05 2.50E+01 Cm-243 1.92E-04 1.79E-04 2.50E+01 Total 9.31E+01 2.50E+01 3.0 Irradiated Fuel Shipments None.

4.0 Supplemental Information Table 4.a: Shipment Mode and Location Number of Shipments Mode of Transport Destination 3

Highway EnergySolutions, UT 48 Highway Waste Control Specialists, TX 6

Highway Perma-Fix of Florida Table 4.b: Shipping Container Characteristics Number of Containers Type of Waste Container Type Solidification Agent 17 Dry Active Waste 20' Sealand None 2

Dry Active Waste Metal Liner None 1

Dry Active Waste Metal Box None 1

Dry Active Waste Polyethylene Bag None 26 Dry Active Waste Intermodal None 12 Resin Polyethylene Liner None 3

Concentrates Metal Liner None 1

Other: Oil Metal Liner None 6

Other: S/G Cleaning Solution ISO Tank None

PVNGS ARERR 2024 Page 59 Table 4.e: Principal Radionuclides Refer to Tables 2.a - 2.e.

Table 4.c: Container Volume in m3 by Waste Class Type of Waste Class A Class B Class C Spent Resin, Filters, Sludge, Evaporator bottoms, etc.

6.34E+01 6.81E+00

<LLD DAW 7.68E+02

<LLD

<LLD Irradiated Components

<LLD

<LLD Other Waste: Oil 1.15E+02

<LLD

<LLD Table 4.d: Container Activity in Ci by Waste Class Type of Waste Class A Class B Class C Spent Resin, Filters, Sludge, Evaporator bottoms, etc.

2.22E+01 7.05E+01

<LLD DAW 3.34E-01

<LLD

<LLD Irradiated Components

<LLD

<LLD Other Waste: Oil 5.51E-03

<LLD

<LLD Table 4.f Source of Waste and Processing Employed Type of Waste Source Spent Resin, Filters, Sludge, Evaporator bottoms, etc.

Mechanical filters: no processing; Concentrates as a liquid: no processing; Resin: dewatered prior to shipment.

DAW Non-compacted DAW: no processing employed Irradiated Components N/A Other Waste: Oil, S/G Cleaning Solution Oil: no processing employed; S/G Cleaning Solution: no processing employed.

PVNGS ARERR 2024 Page 60 Table 4.g Type of Container Type of Waste Type of Container Spent Resin, Filters, Sludge, Evaporator bottoms, etc.

(15) General Design Containers Dry Active Waste (47) General Design Containers Irradiated Components N/A Other Waste: Oil, S/G Cleaning Solution (7) General Design Containers Table 4.h Solidification Agent or Absorbent Type of Waste Solidification Agent/Absorbent Spent Resin, Filters, Sludge, Evaporator bottoms, ect.

No solidification agents or absorbents used to process material Dry Active Waste No solidification agents or absorbents used to process material Irradiated Components N/A Other Waste: Oil, Metal, S/G Cleaning Solution No solidification agents or absorbents used to process material

PVNGS ARERR 2024 Page 61 APPENDIX B: DOSE CALCULATIONS

PVNGS ARERR 2024 Page 62 12.1 Gaseous Effluent Dose Calculations Doses to the maximum individual and the surrounding population resulting from the release of radioactive material in gaseous effluents from the Palo Verde Nuclear Generating Station were calculated using the GASPAR computer program. The radionuclides considered in the dose calculations were Tritium, Iodine-131, Iodine-132, Iodine-133, Iodine-135, all noble gases, and particulates having a half-life greater than eight days and for which dose factors are contained in NUREG-0172. Locations selected for individual dose calculations included for each sector, the site boundary, and within five miles, if present, the nearest residence, the nearest garden, and the nearest milk animal. GASPAR implements the radiological dose models of Regulatory Guide 1.109 to determine the radiation exposure to man from four principal atmospheric exposure pathways: plume, ground deposition, inhalation, and ingestion. Doses to the maximum individual and the population were calculated as a function of age group and pathway for significant body organs.

The Energy Information Center was relocated to an offsite location in 2011; however, Table 43 provides doses to the historical location of the Energy Information Center for comparison purposes.

Table 44 presents the Integrated Population Dose.

Table 45 summarizes the individual doses and compares the result to PVNGS ODCM Requirement limits. The site boundary and residence locations for which data are presented represent the highest annual doses.

Based on results obtained by placing TLDs on the site boundary in each sector, the net dose for this reporting period, from direct-radiation, (plume and ground deposition) from all three units was indistinguishable from preoperational values of 8 - 14 R/hr (17 - 30 mR/Std Qtr).

12.2 Liquid Effluent Dose Calculations There were no liquid effluents associated with the operation of this facility.

12.3 Dose Calculation Models The GASPAR computer code was used to evaluate the radiological consequences of the routine release of gaseous effluents. GASPAR implements the dose calculation methodologies of Regulatory Guide 1.109, Revision 1.

Source terms for each quarter are combined with station-specific demographic data and each quarters atmospheric diffusion estimates for gaseous dose calculations.

Atmospheric diffusion estimates are generated by the XOQDOQ computer code using onsite meteorological data as input. Additional input to GASPAR includes the following site-specific data:

x 0 to 5 mile nearest residence, milk animal and garden in each of the 16 compass sectors, based on the 2024 Land Use Census.

x 0 to 10 mile population from the PVNGS Emergency Plan, Rev 76.

PVNGS ARERR 2024 Page 63 x The 10 to 50 mile population distribution from the PVNGS UFSAR, Figure 2.1-12.

x The population distribution of metropolitan Phoenix, greater than 50 miles from PVNGS, is conservatively included in the 40 to 50 mile sectors x Absolute humidity of 6 g/m3 from the PVNGS UFSAR, Table 2.3-16.

x The fraction of the year that vegetables are grown (0.667) from the PVNGS ER-OL, Section 2.1.3.4, Table 2.1-8.

x The fraction of daily feed derived from pasture while on pasture (0.35) and length of grazing season for milk animals beyond 5 miles (0.75) from the PVNGS ER-OL, Section 2.1.3.4.3.

x The fraction of daily feed derived from pasture while on pasture (0.05) and length of grazing season for meat animals (0.25) from the PVNGS ER-OL, Section 2.1.3.4.4.

x There were ten (10) sectors reported as containing milk animal (goat or cow) locations within five (5) miles. For calculation purposes these milk animals are assumed to be fed 100% on pasture grass during the year.

x Other values used for input to GASPAR are default values from Regulatory Guide 1.109, Rev. 1.

PVNGS ARERR 2024 Page 64 Table 43: Doses to Special Location Table 43: Doses to Special Location (mrem)

T.Body GI-Tract Bone Liver Kidney Thyroid Lung Skin 1st Quarter Adult 5.00E-01 5.00E-01 1.92E-03 5.00E-01 5.00E-01 5.00E-01 5.00E-01 5.01E-01 Teen 5.03E-01 5.03E-01 1.92E-03 5.03E-01 5.03E-01 5.03E-01 5.03E-01 5.04E-01 Child 4.46E-01 4.46E-01 1.92E-03 4.46E-01 4.46E-01 4.46E-01 4.46E-01 4.47E-01 Infant 2.57E-01 2.57E-01 1.92E-03 2.57E-01 2.57E-01 2.57E-01 2.57E-01 2.58E-01 2nd Quarter Adult 2.10E-01 2.10E-01 2.40E-02 2.10E-01 2.10E-01 2.10E-01 2.12E-01 2.14E-01 Teen 2.11E-01 2.11E-01 2.40E-02 2.11E-01 2.11E-01 2.11E-01 2.15E-01 2.15E-01 Child 1.89E-01 1.89E-01 2.40E-02 1.89E-01 1.89E-01 1.89E-01 1.92E-01 1.94E-01 Infant 1.19E-01 1.19E-01 2.40E-02 1.19E-01 1.19E-01 1.19E-01 1.21E-01 1.23E-01 1st Semi-Annual Adult 7.10E-01 7.10E-01 2.59E-02 7.10E-01 7.10E-01 7.10E-01 7.12E-01 7.15E-01 Teen 7.14E-01 7.14E-01 2.59E-02 7.14E-01 7.14E-01 7.14E-01 7.18E-01 7.19E-01 Child 6.35E-01 6.35E-01 2.59E-02 6.35E-01 6.35E-01 6.35E-01 6.38E-01 6.40E-01 Infant 3.76E-01 3.76E-01 2.59E-02 3.76E-01 3.76E-01 3.76E-01 3.78E-01 3.81E-01 3rd Quarter Adult 3.12E-01 3.12E-01 6.46E-04 3.12E-01 3.12E-01 3.12E-01 3.12E-01 3.12E-01 Teen 3.13E-01 3.13E-01 6.46E-04 3.13E-01 3.13E-01 3.13E-01 3.13E-01 3.14E-01 Child 2.77E-01 2.77E-01 6.46E-04 2.77E-01 2.77E-01 2.77E-01 2.77E-01 2.77E-01 Infant 1.59E-01 1.59E-01 6.46E-04 1.59E-01 1.59E-01 1.59E-01 1.59E-01 1.60E-01 4th Quarter Adult 4.88E-01 4.88E-01 1.76E-03 4.88E-01 4.88E-01 4.88E-01 4.89E-01 4.89E-01 Teen 4.91E-01 4.91E-01 1.76E-03 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.92E-01 Child 4.34E-01 4.34E-01 1.76E-03 4.34E-01 4.34E-01 4.34E-01 4.35E-01 4.35E-01 Infant 2.51E-01 2.51E-01 1.76E-03 2.51E-01 2.51E-01 2.51E-01 2.51E-01 2.25E-01 2nd Semi-Annual Adult 8.00E-01 8.00E-01 2.41E-03 8.00E-01 8.00E-01 8.00E-01 8.01E-01 8.01E-01 Teen 8.05E-01 8.05E-01 2.41E-03 8.05E-01 8.05E-01 8.05E-01 8.05E-01 8.06E-01 Child 7.11E-01 7.11E-01 2.41E-03 7.11E-01 7.11E-01 7.11E-01 7.12E-01 7.12E-01 Infant 4.10E-01 4.10E-01 2.41E-03 4.10E-01 4.10E-01 4.10E-01 4.10E-01 3.84E-01 Annual Adult 1.51E+00 1.51E+00 2.83E-02 1.51E+00 1.51E+00 1.51E+00 1.51E+00 1.52E+00 Teen 1.52E+00 1.52E+00 2.83E-02 1.52E+00 1.52E+00 1.52E+00 1.52E+00 1.53E+00 Child 1.35E+00 1.35E+00 2.83E-02 1.35E+00 1.35E+00 1.35E+00 1.35E+00 1.35E+00 Infant 7.86E-01 7.86E-01 2.83E-02 7.86E-01 7.86E-01 7.86E-01 7.88E-01 7.66E-01

PVNGS ARERR 2024 Page 65 Table 44: Integrated Population Dose Table 44: Integrated Population Dose ()

January to March April through June Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Plume 1.14E-04 1.14E-04 1.14E-04 1.14E-04 1.14E-04 1.14E-04 1.14E-04 2.04E-04 0.00%

0.00%

22.82%

0.00%

Ground 3.87E-04 3.87E-04 3.87E-04 3.87E-04 3.87E-04 3.87E-04 3.87E-04 4.55E-04 0.01%

0.01%

77.18%

0.01%

Inhalation 2.92E+00 2.92E+00 0.00E-00 2.92E+00 2.92E+00 2.92E+00 2.92E+00 2.92E+00 39.24%

39.24%

0.00%

39.24%

Vegetation 3.90E+00 3.90E+00

<LLD 3.90E+00 3.90E+00 3.90E+00 3.90E+00 3.90E+00 52.39%

52.39%

00.00%

52.39%

Cow Milk 4.09E-01 4.09E-01

<LLD 4.09E-01 4.09E-01 4.09E-01 4.09E-01 4.09E-01 5.49%

5.49%

00.00%

5.49%

Meat 2.13E-01 2.13E-01

<LLD 2.13E-01 2.13E-01 2.13E-01 2.13E-01 2.13E-01 2.86%

2.86%

00.00%

2.86%

Total 7.45E+00 7.45E+00 5.01E-04 7.45E+00 7.45E+00 7.45E+00 7.45E+00 7.45E+00 Per Capita Dose (rem)

(1) 3.80E-06 3.80E-06 2.56E-10 3.80E-06 3.80E-06 3.80E-06 3.80E-06 3.80E-06 Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Plume 5.98E-05 5.98E-05 5.98E-05 5.98E-05 5.98E-05 5.98E-05 5.98E-05 1.08E-04 0.0%

0.0%

0.19%

0.0%

Ground 3.02E-02 3.02E-02 3.02E-02 3.02E-02 3.02E-02 3.02E-02 3.02E-02 3.55E-02 0.98%

0.98%

98.47%

0.98%

0.97%

1.15%

Inhalation 1.42E+00 1.42E+00 3.84E-04 1.42E+00 1.42E+00 1.42E+00 1.44E+00 1.42E+00 45.96%

45.94%

1.25%

45.96%

45.97%

46.31%

45.88%

Vegetation 1.37E+00 1.37E+00 2.37E-05 1.37E+00 1.37E+00 1.37E+00 1.37E+00 1.37E+00 44.36%

44.38%

0.08%

44.35%

44.06%

44.28%

Cow Milk 2.05E-01 2.05E-01 2.01E-06 2.05E-01 2.05E-01 2.05E-01 2.05E-01 2.05E-01 6.63%

6.63%

0.01%

6.33%

6.59%

6.62%

Meat 6.39E-02 6.41E-02 5.06E-07 6.39E-02 6.39E-02 6.39E-02 6.39E-02 6.39E-02 2.07%

2.07%

0.00%

2.07%

2.06%

2.07%

Total 3.09E+00 3.09E+00 3.07E-02 3.09E+00 3.09E+00 3.09E+00 3.11E+00 3.09E+00 Per Capita Dose (rem)

(1) 1.58E-06 1.58E-06 1.57E-08 1.58E-06 1.58E-06 1.58E-06 1.59E-06 1.58E-06

PVNGS ARERR 2024 Page 66 Table 44: Integrated Population Dose January through June July through September Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Plume 1.74E-04 1.74E-04 1.74E-04 1.74E-04 1.74E-04 1.74E-04 1.74E-04 3.12E-04 0.00%

0.00%

0.56%

0.00%

Ground 3.06E-02 3.06E-02 3.06E-02 3.06E-02 3.06E-02 3.06E-02 3.06E-02 3.60E-02 0.29%

0.29%

98.13%

0.29%

0.34%

Inhalation 4.34E+00 4.34E+00 3.84E-04 4.34E+00 4.34E+00 4.34E+00 4.36E+00 4.34E+00 41.21%

41.21%

1.23%

41.21%

41.33%

41.19%

Vegetation 5.27E+00 5.27E+00 2.37E-05 5.27E+00 5.27E+00 5.27E+00 5.27E+00 5.27E+00 50.04%

50.04%

0.08%

50.04%

49.94%

50.01%

Cow Milk 6.14E-01 6.14E-01 2.01E-06 6.14E-01 6.14E-01 6.14E-01 6.14E-01 6.14E-01 5.83%

5.82%

0.01%

5.83%

5.82%

Meat 2.77E-01 2.77E-01 5.06E-07 2.77E-01 2.77E-01 2.77E-01 2.77E-01 2.77E-01 2.63%

2.63%

0.00%

2.63%

Total 1.05E+01 1.05E+01 3.12E-02 1.05E+01 1.05E+01 1.05E+01 1.05E+01 1.05E+01 Per Capita Dose (rem)

(1) 5.36E-06 5.36E-06 1.59E-08 5.36E-06 5.36E-06 5.36E-06 5.36E-06 5.36E-06 Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Plume 7.89E-05 7.89E-05 7.89E-05 7.89E-05 7.89E-05 7.89E-05 7.89E-05 1.43E-04 0.00%

0.00%

78.33%

0.00%

Ground 2.02E-05 2.02E-05 2.02E-05 2.02E-05 2.02E-05 2.02E-05 2.02E-05 2.38E-05 0.00%

0.00%

20.06%

0.00%

Inhalation 2.35E+00 2.35E+00 1.61E-06 2.35E+00 2.35E+00 2.35E+00 2.35E+00 2.35E+00 46.49%

46.49%

1.60%

46.49%

Vegetation 2.26E+00 2.26E+00 8.23E-09 2.26E+00 2.26E+00 2.26E+00 2.26E+00 2.26E+00 44.70%

44.70%

0.01%

44.70%

Cow Milk 3.43E-01 3.43E-01 7.42E-11 3.43E-01 3.43E-01 3.43E-01 3.43E-01 3.43E-01 6.81%

6.81%

0.00%

6.81%

Meat 1.01E-01 1.01E-01 4.59E-10 1.01E-01 1.01E-01 1.01E-01 1.01E-01 1.01E-01 2.00%

2.00%

0.00%

2.00%

Total 5.05E+00 5.05E+00 1.01E-04 5.05E+00 5.05E+00 5.05E+00 5.05E+00 5.05E+00 Per Capita Dose (rem)

(1) 2.58E-06 2.58E-06 5.16E-11 2.58E-06 2.58E-06 2.58E-06 2.58E-06 2.58E-06

PVNGS ARERR 2024 Page 67 Table 44: Integrated Population Dose October through December July through December Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Plume 4.23E-05 4.23E-05 4.23E-05 4.23E-05 4.23E-05 4.23E-05 4.23E-05 7.85E-05 0.00%

0.00%

10.34%

0.00%

Ground 3.67E-04 3.67E-04 3.67E-04 3.67E-04 3.67E-04 3.67E-04 3.67E-04 4.31E-04 0.01%

0.01%

89.50%

0.01%

Inhalation 1.72E+00 1.72E+00 6.51E-07 1.72E+00 1.72E+00 1.72E+00 1.72E+00 1.72E+00 32.31%

32.31%

0.16%

32.31%

Vegetation 3.23E+00 3.23E+00 4.12E-09 3.23E+00 3.23E+00 3.23E+00 3.23E+00 3.23E+00 60.54%

60.54%

00.00%

60.54%

60.53%

Cow Milk 2.16E-01 2.16E-01 8.69E-10 2.16E-01 2.16E-01 2.16E-01 2.16E-01 2.16E-01 4.06%

4.06%

00.00%

4.06%

Meat 1.65E-01 1.65E-01 3.06E-10 1.65E-01 1.65E-01 1.65E-01 1.65E-01 1.65E-01 3.09%

3.09%

00.00%

3.09%

Total 5.33E+00 5.33E+00 4.10E-04 5.33E+00 5.33E+00 5.33E+00 5.33E+00 5.33E+00 Per Capita Dose (rem)

(1) 2.72E-06 2.72E-06 2.09E-10 2.72E-06 2.72E-06 2.72E-06 2.72E-06 2.72E-06 Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Plume 1.21E-04 1.21E-04 1.21E-04 1.21E-04 1.21E-04 1.21E-04 1.21E-04 2.21E-04 0.00%

0.00%

23.76%

0.00%

Ground 3.87E-04 3.87E-04 3.87E-04 3.87E-04 3.87E-04 3.87E-04 3.87E-04 4.55E-04 0.00%

0.00%

75.79%

0.00%

Inhalation 4.07E+00 4.07E+00 2.26E-06 4.07E+00 4.07E+00 4.07E+00 4.07E+00 4.07E+00 39.20%

39.20%

0.44%

39.20%

39.21%

39.20%

Vegetation 5.48E+00 5.48E+00 1.23E-08 5.48E+00 5.48E+00 5.48E+00 5.48E+00 5.48E+00 52.84%

52.84%

0.00%

52.84%

52.83%

52.84%

Cow Milk 5.60E-01 5.60E-01 9.43E-10 5.60E-01 5.60E-01 5.60E-01 5.60E-01 5.60E-01 5.40%

5.40%

0.00%

5.40%

Meat 2.65E-01 2.65E-01 7.65E-10 2.65E-01 2.65E-01 2.65E-01 2.65E-01 2.65E-01 2.56%

2.56%

0.00%

2.56%

Total 1.04E+01 1.04E+01 5.10E-04 1.04E+01 1.04E+01 1.04E+01 1.04E+01 1.04E+01 Per Capita Dose (rem)

(1) 5.31E-06 5.31E-06 2.60E-10 5.31E-06 5.31E-06 5.31E-06 5.31E-06 5.31E-06

PVNGS ARERR 2024 Page 68 Table 44: Integrated Population Dose January through December Pathway Total Body GI-Tract Bone Liver Kidney Thyroid Lung Skin Plume 2.95E-04 2.95E-04 2.95E-04 2.95E-04 2.95E-04 2.95E-04 2.95E-04 5.33E-04 0.00%

0.00%

0.93%

0.00%

Ground 3.10E-02 3.10E-02 3.10E-02 3.10E-02 3.10E-02 3.10E-02 3.10E-02 3.64E-02 0.15%

0.15%

97.77%

0.15%

0.17%

Inhalation 8.41E+00 8.41E+00 3.86E-04 8.41E+00 8.41E+00 8.41E+00 8.43E+00 8.41E+00 40.22%

40.21%

1.22%

40.22%

40.28%

40.21%

Vegetation 1.08E+01 1.08E+01 2.37E-05 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 51.43%

51.43%

0.07%

51.43%

51.37%

51.41%

Cow Milk 1.17E+00 1.17E+00 2.01E-06 1.17E+00 1.17E+00 1.17E+00 1.17E+00 1.17E+00 5.61%

5.61%

0.01%

5.61%

Meat 5.43E-01 5.43E-01 5.07E-07 5.43E-01 5.43E-01 5.43E-01 5.43E-01 5.43E-01 2.60%

2.60%

0.00%

2.60%

2.59%

Total 2.09E+01 2.09E+01 3.17E-02 2.09E+01 2.09E+01 2.09E+01 2.09E+01 2.09E+01 Per Capita Dose (rem)

(1) 1.07E-05 1.07E-05 1.62E-8 1.07E-05 1.00E-05 1.07E-05 1.07E-05 1.07E-05

PVNGS ARERR 2024 Page 69 Table 45: Summary of individual doses Radiation Doses At And Beyond The Site Boundary Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Year total Gamma Air Dose mrad 4.67E-04 9.22E-05 1.44E-04 3.30E~04 1.01E-03 ODCM Req 4.1 Limit mrad 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

% ODCM Limit 9.34E-03 1.84E-03 2.88E-03 6.60E~03 1.01E-02 Beta Air Dose mrad 1.65E-04 3.28E-05 5.13E-05 1.17E-04 3.59E-04 ODCM Req 4.1 Limit mrad 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

% ODCM Limit 1.65E-03 3.28E-04 5.13E-04 1.17E-03 1.79E-03 Maximum Individual Total Body mrem 3.11E-04 6.13E-05 9.61E-05 2.19E-04 6.72E-04 Skin mrem 4.97E-04 9.84E-05 1.54E-04 3.52E-04 1.08E-03 Location Unit 1 miles 1.70 SSE 1.70 SSE 1.27 SE 1.70 SSE 1.70 SSE Unit 2 miles 1.88 SSE 1.88 SSE 1.31 SE 1.88 SSE 1.88 SSE Unit3 miles 1.73 SSE 1.73 SSE 1.40 SE 1.73 SSE 1.73 SSE Maximum Organ Dose11 ' From All Radionuclides Age Infant Child Infant Infant Infant Organ Bone Bone Bone Bone Bone mrem 2.10E+00 1.07E+00 1.15E+00 2.21E+00 5.93E+00 ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limir' 2.80E+01 1.43E+01 1.53E+01 2.95E+01 3.95E+01 Location Unit 1 miles 3.65 SE 1.44 N 3.32 ESE 3.65 SE 3.65 SE Unit2 miles 3.66 SE 1.63 N 3.37 ESE 3.66 SE 3.66 SE Unit3 miles 3.61 ESE 1.86 NNE 3.36 ESE 3.61 ESE 3.61 ESE Maximum Organ Dose<1> From All Radionuclides Excluding C-14 Age Infant Child Infant Infant Infant Organ Thyroid GI-Tract Thyroid Thyroid Thyroid mrem 1.75E-01 7.35E-02 1.57E-01 1.54E-01 4.85E-01 ODCM Req. 4.2 Limit mrem 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

% ODCM Limif 21 2.33E+00 9.80E-01 2.09E+00 2.05E+00 3.23E+00 Organ Dose from tritium only for mrem 1.75E-01 6.89E-02 1.57E-01 1.54E-01 4.84E-01 Unit 2 location above Fraction of organ dose from 100.00 93.74 100.00 100.00 99.79 tritum only for Unit 2 location X/Q for Unit 2 location above sedm' 1.56E-06 4.09E-07 1.09E-06 2.52E-06 1.60E-06 D/Q for Unit 2 location above m-2 6.51E-10 3.64E-09 3.04E-10 6.08E-10 4.46E-10 (1) Excluding skin (2) ODCM Requirement 5.1 has higher limits than ODCM Requirement 4.2; therefore the percent of limits are more conservative based on ODCM Requirement 4.2 than on ODCM Requirement 5.1

PVNGS ARERR 2024 Page 70 45: Su APPENDIX C: NEI 07-07 GROUNDWATER PROTECTION INITIATIVE SAMPLING

PVNGS ARERR 2024 Page 71 Figure 1. Onsite Well Locations and Groundwater Contours of February 2024 Legend

~ Shallow Aquifer Monitoring Well Groundwater Elevation Contour Line (Dashed Denotes Inferred) 1:....J Site Boundary I

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PVNGS ARERR 2024 Page 72 Figure 2. Onsite Well Locations and Groundwater Contours of December 2024 7

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PVNGS ARERR 2024 Page 73 Table 46: 2024 NEI 07-07 Ground Water Protection Initiative PVNGS Well Data Monitoring Well ID Sample ID Sample Date Radionuclide Concentration (pCi/L)

APP-9 PV-APP-9-0224 02/13/2024 Tritium

<417 APP-9 PV-APP-9-0424 04/28/2024 Tritium

<532 APP-9 (1)

Tritium APP-9 PV-APP-9-122024 12/12/2024 Tritium

<407 APP-9 (1)

Cesium-134 APP-9 PV-APP-9-122024 12/12/2024 Cesium-134

<9.92 APP-9 (1)

Cesium-137 APP-9 PV-APP-9-122024 12/12/2024 Cesium-137

<10.7 APP-9 (1)

Cobalt-60 APP-9 PV-APP-9-122024 12/12/2024 Cobalt-60

<12.1 APP-10 PV-APP-10-0224 02/13/2024 Tritium

<416 APP-10 PV-APP-10-0424 04/28/2024 Tritium

<536 APP-10 PV-APP-10-0924 09/10/2024 Tritium

<419 APP-10 PV-APP-10-122024 12/11/2024 Tritium

<415 APP-10 PV-APP-10-0924 09/10/2024 Cesium-134

<11.2 APP-10 PV-APP-10-122024 12/11/2024 Cesium-134

<6.38 APP-10 PV-APP-10-0924 09/10/2024 Cesium-137

<12.7 APP-10 PV-APP-10-122024 12/11/2024 Cesium-137

<8.22 APP-10 PV-APP-10-0924 09/10/2024 Cobalt-60

<10.5 APP-10 PV-APP-10-122024 12/11/2024 Cobalt-60

<8.26 APP-12 PV-APP-12-0224 02/13/2024 Tritium

<417 APP-12 PV-APP-12-0424 04/28/2024 Tritium

<533 APP-12 (1)

Tritium APP-12 (1)

Cesium-134 APP-12 (1)

Cesium-137 APP-12 (1)

Cobalt-60 APP-15 (1)

Tritium APP-15 (1)

Cesium-134 APP-15 (1)

Cesium-137 APP-15 (1)

Cobalt-60 APP-22 PV-APP-22-0924 09/11/2024 Tritium

<420 APP-22 PV-APP-22-122024 12/11/2024 Tritium

<416 APP-22 PV-APP-22-0924 09/11/2024 Cesium-134

<7.72 APP-22 PV-APP-22-122024 12/11/2024 Cesium-134

<5.25 APP-22 PV-APP-22-0924 09/11/2024 Cesium-137

<8.76 APP-22 PV-APP-22-122024 12/11/2024 Cesium-137

<5.22 APP-22 PV-APP-22-0924 09/11/2024 Cobalt-60

<8.02 APP-22 PV-APP-22-122024 12/11/2024 Cobalt-60

<5.23 APP-4R PV-APP-4R-0924 09/11/2024 Tritium

<418 APP-4R PV-APP-4R-122024 12/12/2024 Tritium

<413

PVNGS ARERR 2024 Page 74 APP-4R PV-APP-4R-0924 09/11/2024 Cesium-134

<7.10 APP-4R PV-APP-4R-122024 12/12/2024 Cesium-134

<9.35 APP-4R PV-APP-4R-0924 09/11/2024 Cesium-137

<7.79 APP-4R PV-APP-4R-122024 12/12/2024 Cesium-137

<13.7 APP-4R PV-APP-4R-0924 09/11/2024 Cobalt-60

<6.33 APP-4R PV-APP-4R-122024 12/12/2024 Cobalt-60

<12.4 PV-14H PV-PV-14H-0924 09/11/2024 Tritium

<416 PV-14H PV-PV-14H-122024 12/11/2024 Tritium

<417 PV-14H PV-PV-14H-0924 09/11/2024 Cesium-134

<7.94 PV-14H PV-PV-14H-122024 12/11/2024 Cesium-134

<8.87 PV-14H PV-PV-14H-0924 09/11/2024 Cesium-137

<8.76 PV-14H PV-PV-14H-122024 12/11/2024 Cesium-137

<13 PV-14H PV-PV-14H-0924 09/11/2024 Cobalt-60

<7.37 PV-14H PV-PV-14H-122024 12/11/2024 Cobalt-60

<12.2 PV-34H (1)

Tritium PV-34H (1)

Cesium-134 PV-34H (1)

Cesium-137 PV-34H (1)

Cobalt-60 PV-R2AR PV-PV-R2AR-0424 04/28/2024 Tritium

<536 PV-R2AR PV-PV-R2AR-122024 12/12/2024 Tritium

<411 PV-R2AR PV-PV-R2AR-0424 04/28/2024 Cesium-134

<6.52 PV-R2AR PV-PV-R2AR-122024 12/12/2024 Cesium-134

<10.3 PV-R2AR PV-PV-R2AR-0424 04/28/2024 Cesium-137

<6.77 PV-R2AR PV-PV-R2AR-122024 12/12/2024 Cesium-137

<11.8 PV-R2AR PV-PV-R2AR-0424 04/28/2024 Cobalt-60

<6.64 PV-R2AR PV-PV-R2AR-122024 12/12/2024 Cobalt-60

<9.97 (1) - Pump failure or temporary power disruption causing one or more samples not to be obtained.

Regarding pump failures, see evaluation and actions taken, 24-10891-001, PVNGS, February - 2025.

PVNGS ARERR 2024 Page 75 APPENDIX D: ADJUSTED 2024 PERMITS

PVNGS ARERR 2024 Page 76 Table 47:

Table 47: Adjusted Permits Permit Reason for Adjustment 20242117 The Ar-41 activity listed on batch permit 20242117 was adjusted from 3.79 Ci to 2.89E-1 Ci to account for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of decay (reactor shutdown to release start and one volume of containment, 2.6E6 ft3).

20242120 Permit 20242120 was adjusted for double counting due to overlapping Refueling

- and Plant Vent purges during the Unit 2 fall outage.

20243062, 20243063 20243062 Plant Vent permit was revised to account for tritium interference on Refueling Purge permit 20243063. Permits 20243062, 20243063 and 20243066 have overlapping timestamps. Additional nuclides were adjusted by removing the lowest results, 20243063, thereby achieving a reduction of some double counting, while retaining over-conservatism.

20243081 Activity on Plant Vent permit 20243081 was excluded because it was accounted for on permits 20243080 and 20243081.

20243168 Plant Vent permit 20243168 was adjusted to account for concurrent Fuel Building purge permits at all three units.

PVNGS ARERR 2024 Page 77 APPENDIX E: OFF Site Dose Calculation Manual ODCM Revision 32.

Jun I 2024 Originator OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 Michaelson, REVISION32 Digitally signed by Michaelson, Thomas (Zl 8156)

Thomas (Zl 8156) ~~~~~~024.06.05 no?:51 McCann, Sean Technical Reviewer P(Zl Ol 95)

Digitally signed by McCa nn, Sean P(Z10195)

Date: 2024.06.25 13:19:24 -07'00' Manager, Radiation Protection PRB 5 i mo n, Erik (Z17539)

Presented 7/9/2024 Digitally signed by Simon, Erik {Z17539)

Date: 2024.06.26 15:08:53

-07'00'

TABLE OF CONTENTS TITLE

1.0 INTRODUCTION

1.1 Liquid Effluent Pathways 1.2 Gaseous Effluent Pathways 1.3 Nuisance Pathways 1.4 Meteorology 2.0 GASEOUS EFFLUENT MONITOR SETPOINTS

2.1 Requirements

Gaseous Monitors 2.1.1 Surveillance Requirements 2.1.2 Implementation of the Requirements 2.1.2.1 Equivalent Dose Factor Determination 2.1.2.2 Site Release Rate Limit (Qs1rn) 2.1.2.3 Unit Release Rate Limits (~T) 2.1.2.4 Setpoint Determination 2.1.2.5 Monitor Calibration 3.0 GASEOUS AND LIQUID EFFLUENT DOSE RATES PAGE 1

1 2

2 4

5 5

5 12 13 14 15 15 16 17

3.1 Requirements

Gaseous Effluents 17 3.1.1 Surveillance Requirements 1 7 3.1.2 Implementation of the Requirements 18

3.2 Requirements

Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System-Concentration 26 3.2.1 Surveillance Requirements 26 3.2.2 Implementation of the Requirements 26 4.0 GASEOUS & LIQUID EFFLUENTS - DOSE 31

4.1 Requirements

Noble Gases 31 4.1.1 Surveillance Requirements 31 4.1.2 Implementation of the Requirement: Noble Gas 32

4.2 Requirement

Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 33 4.2.1 Surveillance Requirements 33 4.2.2 Implementation of the Requirement 34

4.3 Requirements

Gaseous Radwaste Treatment 36 4.3.1 Surveillance Requirements 36 4.3.2 Implementation of the Requirement 37

4.4 Requirements

Liquid Effluents 57 4.4.1 Surveillance Requirements 57 4.4.2 Implementation of the Requirements 57

TABLE OF CONTENTS TITLE 5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE

5.1 Requirement

Total Dose 5.1.1 Surveillance Requirements 5.1.2 Implementation of the Requirement 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

6.1 Requirement

REMP 6.1.1 Surveillance Requirements 6.1.2 Implementation of the Requirements

6.2 Requirement

Land Use Census 6.2.1 Surveillance Requirements 6.2.2 Implementation of the Requirements

6.3 Requirement

Interlaboratory Comparison Program 6.3.1 Surveillance Requirements 6.3.2 Implementation of the Requirements 7.0 RADIOLOGICAL REPORTS 7.1 Requirement: Annual Radioactive Eflluent Release Report 7.2 Requirement: Annual Radiological Environmental Operating Report APPENDIX A DETERMINATION OF CONTROLLING LOCATION PAGE 58 58 58 58 62 62 63 63 71 71 71 72 72 72 83 83 85 86 APPENDIX B BASES FOR REQUIREMENTS 87 2.1 RADIOACTNE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 87 3.1 GASEOUS EFFLUENT-DOSE RATE 87 3.2 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - CONCENTRATION 88 4.1 GASEOUS EFFLUENT-DOSE, Noble Gases 88 4.2 GASEOUS EFFLUENT-DOSE - Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days91 4.3 GASEOUS RADWASTE TREATMENT 89 4.4 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS - DOSE 90 5.1 TOTAL DOSE AND DOSE TO PUBLIC ONSITE 90 6.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 91 6.2 LAND USE CENSUS 91 6.3 INTERLABORATORY COMPARISON PROGRAM 91 APPENDIX C DEFINITIONS APPENDIX D REFERENCES 11 92 96

LIST OF TABLES TABLE TITLE PAGE 1-1 NUISANCE PATIIWAYS 3

2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 6

2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 10 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 20 3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY 23 3-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 24 3-4 Pi VALUES FOR THE INHALATION PATHWAY 25 3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 27 3-6 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 30 3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 30 4-1 Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PA1HWAY 39 4-2 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PA1HWAY -ADULT RECEPTOR 40 4-3 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PA1HWAY - TEEN RECEPTOR 41 4-4 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PA1HWAY - CHILD RECEPTOR 42 4-5 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PA1HWAY -

ADULT RECEPTOR 43 4-6 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATIIWAY -

TEEN RECEPTOR 44 4-7 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATIIWAY -

CHILD RECEPTOR 45 4-8 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PA1HWAY -

ADULT RECEPTOR 46 4-9 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PA1HWAY -

TEEN RECEPTOR 47 4-10 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PA1HWAY -

CHILD RECEPTOR 48 111

LIST OF TABLES TABLE TITLE PAGE 4-11 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTOR 49 4-12 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -

ADULT RECEPTOR 50 4-13 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -

TEEN RECEPTOR 51 4-14 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -

CHILD RECEPTOR 52 4-15 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - INFANT RECEPTOR 53 4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT l 54 4-17 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 2 55 4-18 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 3 56 6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 64 6-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 68 6-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS 69 6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS 73 C-1 FREQUENCY NOTATION 95 lV

LIST OF FIGURES FIGURE TITLE 6-1 Radiological Environmental Monitoring Program Sample Sites 0 - 10 miles 6-2 Radiological Environmental Monitoring Program Sample Sites 10 - 35 Miles 6-3 Radiological Environmental Monitoring Program Sample Sites 35 - 75 Miles DELETED 6-4 Site Exclusion Area Boundary DELETED 6-5 Gaseous Effiuent Release Points 6-6 Low Population Zone DELETED V

PAGE 77 78 79 80 81 82

1.0 INTRODUCTION

The Offsite Dose Calculation Manual (ODCM) implements the program elements which are required by the Administrative Controls section of the Technical Specifications. The ODCM contains the operational requirements, the surveillance requirements, and actions required if the operational requirements are not met for the Radioactive Effluent Controls Program and the Radiological Environmental Monitoring Program to assure compliance with 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50. The Technical Specifications, Section 3.0, also apply to the ODCM. Substitute the word "Requirements" for "Limiting Condition for Operation." It should be noted that the hot and cold shutdown and operability requirements in Technical Specification 3.0.3 and 3.0.4 do not apply to any of the requirements contained in this ODCM. The ODCM also contains descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by the Technical Specifications.

The ODCM provides the parameters and methodology to be used in calculating offsite doses resulting from radioactive effluents, the calculation of gaseous effluent monitor Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. Included are methods for determining air, whole body, and organ dose at the controlling location due to plant effluents to assure compliance with the regulatory requirements detailed in the ODCM. Methods are included for performing dose projections to assure compliance with the gaseous treatment system operability sections of the ODCM.

The ODCM utilizes information from NRC Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," October 1977, and NRC NUREG 0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978. NUREG 0133 utilizes some of the key information in Regulatory Guide 1.109 to provide methods which were used in the preparation of the radiological effluent Technical Specifications and which have now been transferred to the ODCM in accordance with NRC Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program," January 31, 1989, and NUREG 1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," Generic Letter 89-01, Supplement No. 1, April 1991. Further guidance for the implementation of the new 10 CFR Part 20, effective January 1, 1994, was obtained from the Federal Register, Vol. 58, December 23, 1993. It is recognized that this is only draft guidance, however, it is the only guidance for referencing the new 10 CFR 20 in the ODCM.

1.1 Liquid Effluent Pathways Dose calculation methodology for radioactive liquid effluents is not included in this manual due to the desert location of the plant, the hydrology of the area, and the fact that there are no liquid releases to areas at or beyond the SITE BOUNDARY during normal operation. All liquid discharges to the onsite evaporation ponds are controlled by Section 3.2. The impact of postulated accidental seepages on the groundwater system, and in particular on the existing wells located in the 5-mile zone around the site area has been calculated and analyzed in Section 2.4.13.3 of the PVNGS UFSAR.

If plant operating conditions become such that the likelihood of a liquid effluent pathway is created, then dose calculation methodology for this pathway will be added to this manual.

1 ODCMRev.32

1.2 Gaseous Effluent Pathways All gaseous effluents are treated as ground level releases and are considered to be "long-term" as discussed in NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." This includes the containment purge and Waste Gas Decay Tank releases as well as the normal ventilation system and condenser vacuum exhaust releases. All releases are either greater than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months in duration or are made at random, not depending upon atmospheric conditions or time of day. The releases are lumped together and calculated as an entity. Historical annual average X/Q values are used throughout this manual for all gaseous effluent setpoint and dose calculations. Airborne releases are further subdivided into two subclasses:

1.2.1 Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form with Half-lives Greater than Eight Days In this model, a controlling location is identified for assessing the maximum exposure to a MEMBER OF THE PUBLIC for the various pathways and to critical organs. Infant exposure occurs through inhalation and any actual milk pathway. Child, teenager and adult exposure derives from inhalation, consumed vegetation pathways, and any actual milk and meat pathways. Dose to each of the seven organs listed in Regulatory Guide 1.109 (bone, liver, total body, thyroid, kidney, lung and GI-LLI) are computed from individual nuclide contributions in each sector. The largest of the organ doses in any sector is compared to 10 CFR 50, Appendix I design objectives. The release rates of these nuclides will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.

1.2.2 Noble Gases The air dose from both the beta and gamma radiation component of the noble gases will be assessed and compared to the 10 CFR 50, Appendix I design objectives. The noble gas release rate will be converted to instantaneous dose rates for comparison to the limits of 10 CFR 20.

Section 2.0 of this manual discusses the methodology to be used in determining effluent monitor alarm/trip setpoints to assure compliance with the 10 CFR Part 20 limits as implemented in Section 3.0. Section 4.0 discusses the methods to assure releases are As Low As Reasonably Achievable (ALARA) in accordance with Appendix I to 10 CFR Part 50.

Methods are described in Section 5.0 for determining the annual cumulative dose to a MEMBER OF THE PUBLIC from gaseous effluents and direct radiation to assure compliance with 40 CFR Part 190.

The requirements for the Annual Radiological Effluent Release Report and the Radiological Environmental Monitoring Program, including the Annual Land Use Census and the Interlaboratory Comparison Program, and the Annual Environmental Report are described in Sections 6.0 and 7.0 of this manual.

1.3 Nuisance Pathways This section addresses the potential release pathways which should not contribute more than 10% of the doses evaluated in this manual. Table 1-1 lists examples of potential release pathways. The ODCM methodology for calculation of doses will be applied to an applicable release pathway if a likely potential arises for contributing more than 10% of the doses evaluated in this manual.

2 ODCMRev.32

Evaporation Pond Cooling Towers Laundry/Decon Building Exhaust TABLE 1-1 NUISANCE PATHWAYS (EXAMPLES)

Unmonitored Secondary System Steam Vents/Reliefs Turbine Building Ventilation Exhaust Unmonitored Tank Atmospheric Vents Dry Active Waste Processing and Storage (DA WPS) Facility Secondary Side Decontamination Equipment Low Level Radioactive Material Storage Facility Outage Support Facility 3

ODCMRev.32

1.4 Meteorology Historical annual average atmospheric dispersion (X/Q) and deposition (D/Q) data, based on nine years of meteorological data, and given in Table 3-2 for each of the three nuclear generating units are used to demonstrate compliance with the ODCM Requirements. These Requirements include:

Section 2.0 Section 3.0 Section 4.0 Section 5.0 Gaseous Effluent Monitor Setpoints; Gaseous and Liquid Effluent - Dose Rate Gaseous and Liquid Effluent - Dose Total Dose and Dose to Public Onsite Sections 2.0 and 3.0 specify utilizing the highest X/Q or D/Q meteorological dispersion parameter at the Site Boundary for any of the three units as applicable. Using the highest dispersion parameter for any of the units provides a conservative assumption to assure compliance with the higher 10 CFR Part 20 limits.

Section 4.0 specifies utilizing the highest X/Q at the Site Boundary for the particular unit, from Table 3-2 for noble gases. The highest X/Q and D/Q are utilized for the particular unit's releases as applicable for gases other than noble gases (iodines, particulates, and tritium) for the controlling pathway's location (site boundary using Table 3-2 or other controlling locations using Table 4-16, 4-17, or 4-18).

Section 5.0 specifies utilizing the highest X/Q for the particular unit's releases at the controlling location from Table 4-16, 4-1 7, or 4-18, for noble gases. The highest X/Q and D/Q are utilized for the particular unit's releases as applicable for gases other than noble gases at the controlling pathway's location using Table 4-16, 4-17, or 4-18.

Section 7.0 requires that 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.

4 ODCMRev.32

2.0 GASEOUS EFFLUENT MONITOR SETPOINTS

2.1 Requirements

Gaseous Monitors The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2-1 shall be FUNCTIONAL with their alarm/trip setpoints set to ensure that the dose requirements in Section 3.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section 2.1.2.

Applicability:

As shown in Table 2-1.

Action:

a. With the low range radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Requirement, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel nonfunctional, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels FUNCTIONAL, take the ACTION shown in Table 2-1. Restore the nonfunctional instrumentation to FUNCTIONAL status within 30 days or, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this nonfunctionality was not corrected within the time specified.

2.1.1 Surveillance Requirements

a. 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 2-2.

b. The specified Frequency for each Surveillance Requirement is met if the Surveillance Requirement 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 "Prior to each release," the above interval extension does not apply.

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.

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TABLE2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT FUNCTIONAL APPLICABILITY ACTION

1.

GASEOUS RADWASTE SYSTEM

a.

Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release #RU-12 l

35

b.

Flow Rate Monitor 36

2.

NOT USED

3.

DELETED

4.

PLANT VENT SYSTEM A.

Low Range Monitors

a.

Noble Gas Activity Monitor #RU-143 l

37

b.

Iodine Sampler l

40 C.

Particulate Sampler 1

40

d.

Flow Rate Monitor 1

36

e.

Sampler Flow Rate Measuring Device 1

36 B.

High Range Monitors

a.

Noble Gas Activity Monitor #RU-144 1

42

b.

Iodine Sampler 1

42 C.

Particulate Sampler 1

42

d.

Sampler Flow Rate Measuring Device 1

42 6

ODCMRev.32

TABLE 2-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT FUNCTIONAL APPLICABILITY ACTION

5.

FUEL BUILDING VENTILATION SYSTEM A.

Low Range Monitors

a.

Noble Gas Activity Monitor #RU-145 1

37,41

b.

Iodine Sampler 1

40

c.

Particulate Sample 1

40

d.

Flow Rate Monitor 1

36

e.

Sampler Flow Rate Measuring Device 1

36 B.

ffigh Range Monitors

a.

Noble Gas Activity Monitor #RU-146 1

42

b.

Iodine Sampler 1

42 C.

Particulate Sample 1

42

d.

Sampler Flow Rate Measuring Device 1

42 7

ODCMRev.32

Table 2-1 (Continued)

TABLE NOTATION At all times.

During GASEOUS RADWASTE SYSTEM operation Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).

During waste gas release.

In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.

ACTION 35 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a.

At least two independent samples of the tanks contents are analyzed, and

b.

At least two technica11y qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

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 the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 the actions of (a) or (b) or ( c) are performed:

a.

Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s).

b.

Place moveable air monitors in-line.

c.

Either take grab samples at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , OR obtain gas channel monitor readings locally at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the channel is functional locally but nonfunctional due to loss of communication with the minicomputer. The surveillance requirements of Section 2.1.1 must be performed at the required frequencies for the channel to be functional locally.

ACTION 38 -

NOT USED ACTION 39 -

NOT USED 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 3-1 within one hour after the channel has been declared nonfunctional.

ACTION 41 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirements, comply with Technical Requirements Manual TLCO 3.3.108.

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Table 2-1 (Continued)

TABLE NOTATION ACTION 42 - With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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TABLE2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED

1.

GASEOUS RADWASTE SYSTEM

a.

Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release RU-12 p

P(7)

R(3)

Q(l ),(2),P###

b.

Flow Rate Monitor p

N.A.

R Q,P###

2.

DELETED

3.

DELETED

4.

PLANT VENT SYSTEM (RU-143 and RU-144)

a.

Noble Gas Activity Monitor D(5)

M(7)

R(3)

Q(2)

b.

Iodine Sampler N.A.

N.A.

C.

Particulate Sampler N.A.

N.A.

d.

Flow Rate Monitor D(6)

N.A.

R Q

e.

Sampler Flow Rate Measuring Device D(6)

N.A.

R Q

5.

FUEL BUILDING VENTILATION SYSTEM (RU-145 and RU-146)

a.

Noble Gas Activity Monitor D(5)

M(7)

R(3)

Q(2)

b.

Iodine Sampler N.A.

N.A.

C.

Particulate Sample N.A.

N.A.

d.

Flow Rate Monitor D(6)

N.A.

R Q

e.

Sampler Flow Rate Measuring Device D(6)

N.A.

R Q

ODCMRev.32

(1)

(2)

Table 2-2 (Continued)

TABLE NOTATION At all times.

During GASEOUS RADWASTE SYSTEM operation Whenever the condenser air removal system is in operation, or whenever turbine glands are being supplied with steam from sources other than the auxiliary boiler(s).

During waste gas release.

In MODES 1, 2, 3, and 4 or when irradiated fuel is in the fuel storage pool.

Functional test should consist of, but not be limited to, a verification of system isolation capability by the insertion of a simulated alarm condition.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(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 (NIST) 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 CALIBRATION, sources that have been related to the initial calibration may be used in lieu of the reference standards associated with the initial calibration.

(4)

NOTUSED (5)

The channel check for channels in standby status shall consist of verification that the channel is on-line and reachable.

(6)

Daily channel check not required for flow monitors in standby status.

(7)

LED may be utilized as the check source in lieu of a source of increased activity.

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2.1.2 Implementation of the Requirements The general methodology for establishing low range gaseous effluent monitor setpoints is based upon a site release rate limit in µCi/sec derived from site specific meteorological dispersion conditions, radioisotopic distribution, and whole body and skin dose factors. The high alarm of the low range monitors will alann/trip when the release rate from an individual vent will result in exceeding the limits in Section 3.1. 80% of Section 3.1 limits is considered to be the site release rate limit. The site release rate limit will be allocated among the licensed units' release points. The unit release rate limit will then be utilized for the determination of gaseous effluent monitor setpoints. A fraction of the unit release rate limit is then allotted to each release point and its monitor alert setpoint (µCi/cc) is derived using actual or fan design flow rates.

Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be reviewed based on actual release data.

For the purpose of implementation of Section 2.1, the alarm setpoint levels for low range effluent noble gas monitors are established to ensure that personnel are alerted when the noble gas releases are at a rate such that if the releases would continue for the year they would approach the total body dose rate of 500 mrem/yr and 3000 mrem/yr skin dose in Section 3.1.

The equations in Section 3.1 of this manual provide the methodology for calculating the gaseous effluent dose rate.

The evaluation of doses due to releases of radioactive material can be simplified by the use of equivalent dose factors as defined in Section 2.1.2.1.

The equivalent dose factors will be evaluated periodically to assure that the best information on isotopic distribution is being used for the dose equivalent value.

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2.1.2.1 Equivalent Dose Factor Determination The equivalent whole body dose factor is calculated as follows:

Where:

£ I (2-1) the equivalent whole body dose factor weighted by historical radionuclide distribution in releases in mrem/yr per µCi/m3.

the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per µCi/m3 from Table 3-3.

the fraction of noble gas radionuclide in the total noble gas radionuclide mix.

The equivalent skin dose factor is calculated as follows:

(2-2)

Where:

(L+ 1.lM)eq = the equivalent skin dose factor due to beta and gamma emissions from all noble gases released, weighted by the historical radionuclide distribution in releases in mrem/yr per µCi/m3.

Li

= the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per µCi/m3 from Table 3-3.

Mi

= the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per µCi/m3 from Table 3-3.

fj the fraction of noble gas radionuclide i in the total noble gas radionuclide mix.

1.1

= unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.

13 ODCMRev.32

2.1.2.2 Site Release Rate Limit (Qs1TE)

The release rates corresponding to 80% of the whole body (QWB) and skin (Qsi<l dose rate limits are calculated using the equivalent dose factors defined in Section 2.1.2.1.

The site release rate limit (Qs1rn) is the lower of QWB or QsK, thus assuring that the more restrictive dose rate limit will not be exceeded.

The Qs1TE is established as follows:

Where:

QSITE,WB (X/Q)srrE 0.8 (2-3) the site release rate, in µCi/sec, that would deliver a dose rate 80% of the whole body dose rate limit, DWB.

whole body dose rate limit of 500 mrem/yr.

equivalent whole body dose factor, in mrem/yr per µCi/m3 weighted by the historical radionuclide distribution.

8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, at the Site Boundary for any of the 3 units, from Table 3-2.

administrative factor to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.

(DsK)(0.8)

QSITE,SK = (L+l lM) (X/ )

eq Q SITE (2-4)

Where:

QsrrE,SK = the site release rate limit, in µCi/sec, that would deliver a dose rate 80%

of the skin dose rate limit, DsK*

DsK skin dose rate limit of 3000 mrem/yr.

(L+l.lM)eq = equivalent skin dose factor, in mrem/yr per µCi/m3, weighted by the radionuclide distribution.

(X/Q)srrE 8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, at the Site Boundary for any of the three units, from Table 3-2.

0.8

= administrative factor to compensate for any unexpected variability in the radionuclide mix and to ensure that Site Boundary dose rate limits will not be exceeded.

After determination of the Qs1rn whole body and skin dose rates (equations 2-3 and 2-4, respectively), the most conservative result will be used as Qs1rn, the site release rate limit.

14 ODCMRev.32

2.1.2.3 Unit Release Rate Limits (QUNIT)

Typically Qs1rn will be divided equally among operating units. If operational history dictates a larger fraction of the Qs1TE be assigned to a specific unit then a weighted average of each unit's contribution to the Qs1rn will be utilized to determine the Qumr.

QUNIT Where:

fUNIT QsITE

= (fUNIT) (Qs1rn)

(2-5)

= unit release rate limit, in µCi/sec.

the fraction ~1) of noble gas historically released from a specific operating unit to the total of a11 noble gas released from the site.

the site release rate limit, in µCi/sec determined in Section 2.1.2.2.

2.1.2.4 Setpoint Determination To comply with the requirements in Section 2.1, the alarm/trip setpoints can now be established using the unit release rate limit (QUNIT) to ensure that the noble gas releases do not exceed the dose rate limits.

To allow for multiple sources of releases from different or common release points, the eflluent monitor setpoint includes an administrative factor which allocates a percentage of the unit release rate limit to each of the release sources. Monitor setpoints will also be adjusted in accordance with Nuclear Administrative and Technical Manual procedures to account for monitor-specific characteristics.

Monitors RU-143 and RU-145 The alarm/trip setpoint for Monitors RU-143 and RU-145 is calculated as follows:

(QuN1r)(a)

Monitor Setpoint < _...;..;..;:..;.;.:.;;.;;...;....;.__

(472)(Flow Rate)

(2-6)

Where:

Monitor Setpoint Flow Rate 472 a

the setpoint for the eftluent monitor, in µCi/cc, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.

unit release rate limit, in µCi/sec, as determined in Section 2.1.2.3.

the flow rate, in cfin, from flow rate monitors or the fan design flow rate for the release source under consideration.

conversion factor, cubic centimeter/second per cubic feet/minute.

fraction of QUNIT allocated for a specific release point. The sum of these administrative values shall be less than or equal to one.

15 ODCMRev.32

Monitor RU-12 The alarm/trip setpoint for Monitor RU-12, the Waste Gas Decay Tank Monitor, is calculated as follows:

Monitor

[(QuNIT)(a)(0.9)-(H)(PF)(472)]

~-------------

(2-7) setpoint (Flow Rate)(472)

Where:

Monitor Setpoint Flow Rate PF H

a 0.9 472 the setpoint for the monitor, in µCi/cc at STP, which provides a safe margin of assurance that the allowable dose rate limits will not be exceeded.

unit release rate limit, in µCi/sec, as determined in Section 2.1.2.3.

flow rate, in cfm at STP at which the tank will be released.

the current process flow of the plant vent in CFM.

the current plant vent monitor concentration in µCi/cc.

fraction of QUNIT allocated for a specific release point. This administrative value should be equal to or less than the administrative value used for the Plant Vent.

an administrative value to account for potential increases in activity from other contributors to the same release point.

conversion factor, cubic centimeter/second per cubic feet/minute.

If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms, and yet assure an alarm should an inadvertent release occur.

2.1.2.5 Monitor Calibration The Radiation Level Conversion Factor (RLF) for each monitor is entered into the Radiation Monitoring System Database and may change whenever the monitor is calibrated. Calibration is performed in accordance with Nuclear Administrative and Technical Manual procedures.

16 ODCMRev.32

3.0 GASEOUS AND LIQUID EFFLUENT DOSE RATES

3.1 Requirements

Gaseous Effluents The dose rate due to radioactive materials released in gaseous effluents from the site (see Figure 6-4 and Figure 6-5) shall be limited to the following:

a.

For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and

b.

For 1-131 and 1-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

Applicability:

At all times.

Action:

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

3.1.1 Surveillance Requirements

a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods contained in Section 3.1.2.

b. The dose rate due to 1-131, 1-133, tritium and all radionuclides 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 the methods contained in Section 3.1.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-1.

17 ODCMRev.32

3.1.2 Implementation of the Requirements Noble Gases Noble gas activity monitor setpoints are established at release rates which permit corrective action to be taken before exceeding the 10 CFR 20 annual dose limits as described in Section 2.0. The requirements for sampling and analysis of continuous and batch eflluent releases are given in Table 3-1. The methods for sampling and analysis of continuous and batch eflluent releases are given in the Nuclear Administrative and Technical Manual procedures.

The dose rate in unrestricted areas shall be determined using the following equations.

For whole body dose rate:

(3-1)

For skin dose rate:

Where:

K I (X/Q)sITE L* I M-l 1.1 (3-2) the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in rnrem/yr per µCi/m3 from Table 3-3.

the release rate of radionuclide i, in µCi/sec.

8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, for any of the three units, from Table 3-2.

the annual whole body dose rate (mrem/yr.).

the skin dose factor due to the beta emissions for each identified noble gas radionuclide i, in mrem/yr per µCi/m3 from Table 3-3.

the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per µCi/m3 from Table 3-3.

the annual skin dose rate (mrem/yr).

unit conversion constant of 1.1 mrem/mrad converts air dose to skin dose.

18 ODCMRev.32

1-131, 1-133, tritium and radionuclides in particulate form with half-lives greater than 8 days The methods for sampling and analysis of continuous and batch releases for 1-131, 1-133, tritium and radionuclides in particulate form with half-lives greater than 8 days, are given in the applicable Nuclear Administrative and Technical Manual procedures. Additional monthly and quarterly analyses shall be performed in accordance with Table 3-1. The total organ dose rate in unrestricted areas shall be determined by the following equation:

Where:

P* I (X/Q)sITE (3-3) the dose factor, in mrem/yr per µCi/m3, for radionuclide i, for the inhalation pathway, from Table 3-4.

8.91E-06, the highest calculated annual average dispersion parameter, in sec/m3, at the Site Boundary, for any of the three units, the release rate of radionuclide i, in µCi/sec the total organ dose rate (mrem/yr).

19 ODCMRev.32

TABLE3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWERLIMIT SAMPLING ANALYSIS TYPE OF OF DETECTION GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (LLD) (µCi/mlt A. Waste Gas Storage p

p Principal Gamma l.0E-04 Each Tank Grab Each Tank Emittersg Sample B. Containment Purge p

p Principal Gamma l.0E-04 Each Purgeb,c Each Purgeb,c Emittersg Grab Sample H-3 l.0E-06 C. 1. DELETED Mb,e Mb Principal Gamma l.0E-04

2. Plant Vent Grab Sample Emittersg

3. Fuel Bldg. Exhaust H-3 l.0E-06 Continuoui 4/Md I-131 l.0E-12 Charcoal Sample I-133 l.0E-10 Continuoui 4/Md Principal Gamma l.0E-11 Particulate Emittersg Sample (I-131, Others)

Continuousf M

Gross Alpha l.0E-11 Composite Particulate Sample Continuoui Q

Sr-89, Sr-90 l.0E-11 Composite Particulate Sample D. All Radwaste Types as Continuousf Noble Gas Noble Gases Gross Beta l.0E-06 listed in A., B., and C.,

Monitor or Gamma above.

20 ODCMRev. 32

Table 3-1 (Continued)

TABLE NOTATION a

The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a real signal.

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

LLD =-----4_._66_S_b ____ _

E

V

2.22£6

Y

exp ( -.:lLlt)

Where:

LLD is the a priori lower limit of detection as defined above (as µCi per unit mass or volume). Current literature defines the LLD as the detection capability for the instrumentation only and the MDC minimum detectable concentration, as the detection capability for a given instrument, procedure and type of sample.

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

Eis the counting efficiency (as counts per transformation),

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

2.22E6 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and Llt is the elapsed time between the 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 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 should include the typical contributions of other radionuclides normally present in the samples. Typical values ofE, V, Y, and Llt 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 a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

21 ODCMRev.32

Table 3-1 (Continued)

TABLE NOTATION b

Analyses shall also be performed following SHUTDOWN, STARTUP, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a I-hour period if I) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has increased more than a factor of3; and 2) the noble gas activity monitor on the plant vent shows that effluent activity has increased by more than a factor of 3. If the associated noble gas vent monitor is nonfunctional, samples must be obtained as soon as possible. Analyses shall be performed within a four-hour period. This requirement does not apply to the Fuel Building Exhaust.

c Sampling and analyses shall also be performed at least once per 31 days when purging time exceeds 30 days continuous.

d Samples shall be changed at least 4 times a month and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing ( or after removal from sampler). When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10.

e Tritium grab samples shall be taken at least monthly from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

f The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Requirements 3.1, 4.1 and 4.2 of theODCM.

g The principal gamma emitters for which the LLD specification applies include 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 in the Annual Radioactive Effluent Release Report.

22 ODCMRev. 32

TABLE3-2 DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE SITE BOUNDARY UNITl UNIT2 UNIT3 DISTANCE X/Q D/Q DISTANCE X/Q D/Q DISTANCE X/Q D/Q DIRECTION (METERS)

(SEC/m3)

(m-2)

(METERS)

(SEC/m3)

(m-2)

(METERS)

(SEC/m3)

(m-2)

N 1037 4.93E-06 9.24E-09 1318 3.85E-06 6.17E-09 1661 3.54E-06 4.86E-09 NNE 1057 4.14E-06 1.19E-08 1342 3.18E-06 7.93E-09 1693 2.86E-06 6.23E-09 NE 2206 2.84E-06 6.84E-09 2545 2.42E-06 5.34E-09 2756 2.21E-06 4.65E-09 ENE 1967 2.51E-06 4.43E-09 2206 2.22E-06 3.64E-09 2337 2.08E-06 3.30E-09 E

1927 2.56E-06 3.24E-09 2163 2.27E-06 2.66E-09 2290 2.14E-06 2.41E-09 ESE 1967 2.61E-06 2.46E-09 2067 2.32E-06 2.1 IE-09 2023 2.37E-06 2.l0E-09 SE 2049 3.56E-06 2.36E-09 2101 3.47E-06 2.26E-09 2256 3.24E-06 2.00E-09 SSE 2730 3.80E-06 1.58E-09 3026 3.43E-06 1.32E-09 2786 3.72E-06 1.52E-09 s

3006 5.07E-06 1.78E-09 2699 5.16E-06 1.97E-09 2346 5.90E-06 2.51E-09 SSW 2258 6.52E-06 3.20E-09 1836 7.90E-06 4.56E-09 1607 8.91E-06 5.73E-09 SW 1487 7.47E-06 5.65E-09 1208 7.72E-06 6.88E-09 1057 8.68E-06 8.61E-09 WSW 1251 4.52E-06 5.93E-09 1014 5.55E-06 8.44E-09 889 5.34E-06 8.83E-09 w

1225 4.73E-06 9.49E-09 993 5.86E-06 1.34E-08 871 6.72E-06 1.67E-08 WNW 1244 3.76£-06 6.76E-09 1010 4.67E-06 9.60E-09 885 5.37E-06 1.19E-08 NW 1254 3.43E-06 5.87E-09 1191 3.62E-06 6.40E-09 1045 4.17E-06 7.98E-09 NNW 1069 3.70E-06 7.26E-09 1342 2.85E-06 4.87E-09 1561 2.93E-06 4.58E-09

Reference:

Distances are from the PVNGS ER-OL, Table 2.3-33. Dispersion and Deposition parameters are from a September, 1985, calculation by NUS Corporation based on 9 years of meteorological data; NUS Corporation letter NUS-ANPP-1386, dated October 4, 1985.

23 ODCMRev.32

TABLE3-3 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Whole Body Skin Gamma Air Dose Factor Dose Factor Dose Factor Beta Air Dose Ki L* I M, I Factor Ni mrem/yr mrem/yr mrad-m3 mrad-m3 Radionuclide

µCi/m3

µCi/m3 yr-µCi yr-µCi Kr-83m 7.56E-02 l.93E+0l 2.88E+02 Kr-85m 1.17E+03 l.46E+03 1.23E+03 1.97E+03 Kr-85 l.61E+0l 1.34E+03 l.72E+0l 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 l.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 l.66E+04 l.01E+04 l.73E+04 1.06E+04 Kr-90 l.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-13lm 9.15E+0l 4.76E+02 l.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 l.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 l.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 l.42E+03 l.22E+04 l.51E+03 l.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Reference:

Regulatory Guide 1.109, Table B-1.

24 ODCMRev.32

TABLE3-4 Pi VALUES FOR THE INHALATION PATHWAY mrem/yr

µCi/m3 NUCLIDE Age Group Organ pi H-3 TEEN LIVER l.27E+03 CR-51 TEEN LUNG 2.10E+04 MN-54 TEEN LUNG 1.98E+06 FE-59 TEEN LUNG l.53E+06 CO-58 TEEN LUNG l.34E+06 CO-60 TEEN LUNG 8.72E+06 ZN-65 TEEN LUNG l.24E+06 SR-89 TEEN LUNG 2.42E+06 SR-90 TEEN BONE 1.08E+08 ZR-95 TEEN LUNG 2.69E+06 SB-124 TEEN LUNG 3.85E+06 I-131 CHILD THYROID l.62E+07 I-133 CHILD THYROID 3.85E+06 CS-134 TEEN LIVER l.13E+06 CS-137 CHILD BONE 9.07E+05 BA-140 TEEN LUNG 2.03E+06 CE-141 TEEN LUNG 6.14E+05 CE-144 TEEN LUNG l.34E+07 25 ODCMRev.32

3.2 Requirements

Secondary System Liquid Waste Discharges To Onsite Evaporation Ponds or Circulating Water System - Concentration The concentration of radioactive material discharged from secondary system liquid waste to the circulating water system shall be limited to:

5.0E-07 µCi/ml for the principal gamma emitters (except Ce-144) 3.0E-06 µCi/ml for Ce-144 l.0E-06 µCi/ml for 1-131 1.0E-03 µCi/ml for H-3 The concentration of radioactive material discharged from secondary system liquid waste to the onsite evaporation ponds shall be limited to:

2.0E-06 µCi/ml for Cs-134 2.0E-06 µCi/ml for Cs-137 The concentrations specified in 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, for all other isotopes Applicability:

At all times.

Action:

When any secondary system liquid waste discharge pathway concentration determined in accordance with the surveillance requirements given below exceeds the above Requirements, divert that discharge pathway to the liquid radwaste system without delay or terminate the discharge.

3.2.1 Surveillance Requirements

a. Secondary system liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 3-5.

3.2.2 Implementation of the Requirements This requirement is implemented by Nuclear Administrative and Technical Manual procedures.

26 ODCMRev.32

TABLE3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release Sampling&

Type Of (LLDt Pathway Destination Analysis Frequency Notes Activity Analysis

(µCi/ml)

1.

Chemical Waste Neutralizer Retention Tank p

Each Batch Principal Gamma Emittersc 5.0E-07 Tank (CWNT)b liquid radwaste N. A.

I-131 1.0E-06 H-3 1.0E-05

2.

Steam Generator Blowdown circ. water p

Each Batch 1

Principal Gamma Emittersc 5.0E-07 Low TDS Sumpb CWNT N. A.

1-131 1.0E-06 H-3 1.0E-05

3.

Condensate

a. Condensate Polishing Low circ. water p

Each Batch 3

Principal Gamma Emittersc 5.0E-07 TDS Sumpb CWNT N. A.

I-131 1.0E-06 H-3 1.0E-05

b. Initial Backwash (low TDS sump) to p

Each Discharge Principal Gamma Emittersc 5.0E-07 circ. water I-131 1.0E-06 (low TDS sump) to N. A.

H-3 l.0E-05 CWNT

c. Pre-service rinse effluent Condensate p

Each Batch Principal Gamma Emittersc 5.0E-07 Polishing Low TDS I-131 1.0E-06 Sumpb through H-3 1.0E-05 SCN-UV-233 condenser through N. A.

SC-N-UV232

d. Overboard condensate circ water through p

Each Discharge Principal Gamma Emittersc 5.0E-07 CD-N-Vl94 I-131 1.0E-06 Retention Tank p

Each Discharge 2

H-3 1.0E-05 through SC-N-V079

4.

Turbine Building Sumpu Retention Tank D Grab Sample 3

Principal Gamma Emittersc 5.0E-07 CWNT N. A.

I-131 1.0E-06 H-3 1.0E-05 27 ODCMRev.32

TABLE3-5 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Of Detection Secondary System Liquid Release Sampling&

Type Of (LLDt Pathway Destination Analysis Frequency Notes Activity Analysis

(µCi/ml)

5.

North & South Condenser Area Retention Tank D Grab Sample 3

Principal Gamma Emittersc 5.0E-07 Sumpsd CWNT N. A.

I-131 l.0E-06 H-3 l.0E-05

6.

Steam Generator Blowdown to Retention Tank p

Each Discharge 2

Principal Gamma Emittersc 5.0E-07 Retention Tank through SC-N-V064 I-131 1.0E-06 H-3 1.0E-05

7.

Retention Tank to Evaporation evaporation pond p

Each Batch Principal Gamma Emittersc 5.0E-07 Pond I-131 1.0E-06 H-3 l.0E-05 1

Sampling and analysis are required only when concentration for chemical waste neutralizer tank or steam generator activity exceeds the requirement 2

RU-200 shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3-6. The Alarm/Trip setpoints for RU-200 are set to ensure that the concentrations in the Retention Tanks do not exceed the Requirement 3

Sampling and analysis are required only when concentration for chemical waste neutralizer tank or condensate activity exceeds the requirement 28 ODCMRev. 32

Table 3-5 (Continued)

TABLE NOTATION a

The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system which may include radiochemical separation:

LLD =-----4_._66_S_b ____ _

E

V

2.22£6

Y

exp ( -.:lLlt)

Where:

LLD is the "a priori" lower limit of detection as defined above as microcuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate as counts per minute, E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield when applicable, A is the radioactive decay constant for the particular radionuclide, and Lltistheelapsedtimebetweenmidpointofsamplecollectionandtimeof counting.

Typical values ofE, V, Y,andLltshould 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 a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

b 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 to assure representative sampling.

c The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 3.0E-06. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.

d A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

29 ODCMRev. 32

TABLE3-6 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Channel Mode in which Channel Source Channel Functional Surveillance is Instrument Check Check Calibration Test Required RU-200 p

N.A.

R Q

See Table 3-7 TABLE3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Mode in which Surveillance Secondary System Liquid Release Pathway is Required Action ifRU-200 is nonfunctional Obtain grab sample at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyze in accordance Pre-service rinse to Retention Tanks At All Times with section 3.2 Obtain grab sample at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyses in accordance Condensate overboard to Retention Tanks 1-4 with section 3.2 Modes 1-4: Suspend the release Steam Generator Blowdown/Drain to Retention At All Times Modes 5,6 & defueled: Obtain grab Tanks sample at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyze in accordance with sec-tion 3.2 30 ODCMRev. 32

4.1 GASEOUS & LIQUID EFFLUENTS - DOSE

4.2 Requirements

Noble Gases The air dose due to noble gases released in gaseous effluents, from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 6-4 and Figure 6-5) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,

b.

During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

Applicability:

At all times.

Action:

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

4.1.1 Surveillance Requirements

a. Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology contained in Section 4.1.2 at least once per 31 days.

31 ODCMRev.32

4.1.2 Implementation of the Requirement: Noble Gas The air dose in unrestricted areas beyond the site boundary due to noble gases released in gaseous effluents from each unit during any specified time period shall be determined by the following equations:

For gamma radiation:

(4-1)

For beta radiation:

(4-2)

Where:

Mi

= the air dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrad/yr per µCi/m3 from Table 3-3.

Ni the air dose factor due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per µCi/m3 from Table 3-3.

(X/Q)UNIT the highest calculated annual average dispersion parameter, in sec/m3, at the D~u 3.17E-08 site boundary for the particular Unit, from Table 3-2. Optionally, the highest value may be used for any Unit calculation.

=7.47E-06 from Unit 1

=7.90E-06 from Unit 2

=8.91E-06 from Unit 3

= the total gamma air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.

= the total beta air dose, for the particular unit, in mrad, due to noble gases released in gaseous effluents for a specified time period at the SITE BOUNDARY.

= the integrated release, from the particular unit, in µCi, of each identified noble gas radionuclide i, in gaseous effluents for a specified time period.

the inverse of seconds in a year (yr/sec).

The cumulative gamma air dose and beta air dose for a quarterly or annual evaluation shall be based on the calculated dose contribution from each specified time period occurring during the reporting time period.

32 ODCMRev.32

4.2 Requirement

Iodine-131, Iodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tntmm, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see UFSAR Figure 2.1-4 and ODCM Figure 6-5) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b.

During any calendar year: Less than or equal to 15 mrems to any organ.

Applicability:

At all times.

Action:

With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

4.2.1 Surveillance Requirements

a. Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters contained in Section 4.2.2 at least once per 31 days.

33 ODCMRev.32

4.2.2 Implementation of the Requirement The organ dose to an individual from 1-131, 1-133, tritium, and all radionuclides in particulate form, with half-lives greater than eight days, in gaseous effluents released to unrestricted areas from each reactor unit is calculated using the following expressions:

Where:

3.17E-08 (4-3)

= the total accumulated organ dose from gaseous effluents for a particular unit, to a MEMBER OF THE PUBLIC, in mrem, at the SITE BOUNDARY or at the controlling location.

the quantity of radionuclide i, in µCi, released in gaseous effluents from a particular unit.

the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mrem/yr per µCi/m5 and for the food and ground plane pathways in m2 - mrem/yr per µCi/sec, except H-3, which has units of mrem/yr per µCi/m3) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15.

the inverse of seconds per year (yr/sec).

the highest annual average dispersion or deposition parameter for the particular Unit, used for estimating the dose at the site boundary or to a MEMBER OF THE PUBLIC at the controlling location for the particular Unit. Optionally, the highest value may be used for any Unit calculation.

(X/Q)UNIT, in sec/m3 for the inhalation pathway and for all tritium calculations, for organ dose at the site boundary, from Table 3-2.

=7.47E-06 from Unit 1

=7.90E-06 from Unit 2

=8.91E-06 from Unit 3 (X/Q)UNIT, in sec/m3 for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16, 4-17 or 4-18.

=2.92E-06 from Unit 1

=2.19E-06 from Unit 2

=2.3 lE-06 from Unit 3 (D/Q)UNIT, in m-2, for the food and ground plane pathways, for organ dose at the site boundary, from Table 3-2.

=l.19E-08 from Unit 1

=l.34E-08 from Unit 2

=l.67E-08 from Unit 3 34 ODCMRev.32

(D/Q)UNIT, in m-2, for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18.

=3.25E-09 from Unit 1

=3.88E-10 from Unit 2

=4.21E-10 from Unit 3 Residences, vegetable gardens and milk animals located within 5 miles of the site will be identified during the annual land use census. The controlling pathway and location will be identified and will be used for all MEMBER OF THE PUBLIC dose evaluations.

The Ri values were calculated in accordance with the methodologies in NUREG-0133. The following site specific information was used to calculate Ri:

The length of the grazing season for milk animals (f8).

Ref. ER-OL, Section 2.1.3.4.3 The length of the grazing season for meat animals (f8).

Ref. ER-OL, Section 2.1.3.4.4 The fraction of daily feed derived from pasture while on pasture for milk animals (fp)-

Ref. ER-OL, Section 2.1.3.4.3 The fraction of daily feed derived from pasture while on pasture for meat animals (fp)-

Ref. ER-OL, Section 2.1.3.4.3 The fraction of year vegetables are grown, (f1) approximation.

Ref. ER-OL, Section 2.1.3.4, Table 2.1-8.

The annual absolute humidity (g/m3), H, Ref. UFSAR, Table 2.3-16 35 0.75 0.25 0.35 0.05 0.667 6

ODCMRev.32

4.3 Requirements

Gaseous Radwaste Treatment The GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous eftluent air doses due to gaseous effluent releases, from each reactor unit, from the site (see UFSAR Figure 2.1-4 and ODCM Figure 6-5) when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous eftluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see UFSAR Figure 2.1-4 and ODCM Figure 6-

5) when averaged over 31 days would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

Applicability:

At all times:

Action:

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, a Special Report which includes the following information:

a.

Identification of the nonfunctional equipment or subsystems and the reason for nonfunctionality,

b.

Action(s) taken to restore the nonfunctional equipment to FUNCTIONAL status, and

c.

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

4.3.1 Surveillance Requirements

a. Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the methodology and parameters in Section 4.3.2.

36 ODCMRev.32

4.3.2 Implementation of the Requirement Where possible, consideration for expected operational evolutions (i.e., outages, etc.) should be taken in the dose projections.

Dose Projection - Noble Gases The air dose, in mrads is determined using the methodology described in Section 4.1.2 of this manual. This information is used to determine an air dose projection for the next 31 days using the following equations:

For gamma radiation:

31 dayy

= Dy+/-._CDy (4-4)

For beta radiation:

31 day B Where:

Dy CDy CDB (4-5) the total gamma air dose in mrads at the site boundary due to noble gases released in gaseous effluents for the previous 31 days.

the total beta air dose in mrads at the site boundary due to noble gases released in gaseous effluents for the previous 31 days.

any current or projected change in gamma air dose, in mrads, due to noble gases released in gaseous effluents, which could have a significant impact on 31 dayy.

any current or projected change in beta air dose, in mrads, due to noble gases released in gaseous effluents, which could have a significant impact on 31 dayB.

When performing the 31 day dose projection using the Gaseous Radioactive Effluent Tracking System (GRETS), Dy and DB will include the dose from any release permits that fall within the selected 31 day time period. As a result, the actual dose projection will often be based on the accumulated dose for a time period greater than 31 days.

37 ODCMRev.32

Dose Projection 131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days The organ dose, in mrem, is determined using the methodology described in Section 4.2.2 of this manual. This information is used to determine an organ dose projection for the next 31 days using the following equation:

Where:

(4-6) the total organ dose due to 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in mrem, released in gaseous effluents for the previous 31 days.

any current or projected change in organ dose, in mrem, which could have a significant impact on 31 daYo.

When performing the 31 day dose projection using the Gaseous Radioactive Effluent Tracking System (GRETS), D0 will include the dose from any release permits that fall within the selected 31 day time period. As a result, the actual dose projection will often be based on the accumulated dose for a time period greater than 31 days.

38 ODCMRev.32

TABLE4-1 Ri DOSE CONVERSION FACTORS FOR THE GROUND PLANE PATHWAY NUCLIDE T.BODY SKIN H-3 0.00E+00 0.00E+00 CR-51 4.66E+06 5.51E+06 MN-54 1.39E+09 1.63E+09 FE-59 2.73E+08 3.21E+08 CO-58 3.79E+08 4.44E+08 CO-60 2.15E+I0 2.53E+I0 ZN-65 7.47E+08 8.59E+08 SR-89 2.16E+04 2.51E+04 SR-90 0.00E+00 0.00E+00 ZR-95 2.45E+08 2.84E+08 SB-124 5.98E+08 6.90E+08 I-131 l.72E+07 2.09E+07 I-133 2.45E+06 2.98E+06 CS-134 6.86E+09 8.00E+09 CS-137 l.03E+10 l.20E+10 BA-140 2.05E+07 2.35E+07 CE-141 1.37E+07 1.54E+07 CE-144 6.95E+07 8.04E+07 39 ODCMRev.32

TABLE4-2 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY-ADULT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.87E+03 2.87E+03 2.87E+03 2.87E+03 2.87E+03 2.87E+03 CR-51 0.00E+00 0.00E+00 4.00E+04 2.39E+04 8.82E+03 5.31E+04 l.01E+07 MN-54 0.00E+00 2.97E+08 5.66E+07 0.00E+00 8.83E+07 0.00E+00 9.09E+08 FE-59 1.14E+08 2.68E+08 1.03E+08 0.00E+00 0.00E+00 7.49E+07 8.93E+08 CO-58 0.00E+00 2.84E+07 6.38E+07 0.00E+00 0.00E+00 0.00E+00 5.76E+08 CO-60 0.00E+00 1.59E+08 3.51E+08 0.00E+00 0.00E+00 0.00E+00 2.99E+09 ZN-65 3.00E+08 9.56E+08 4.32E+08 0.00E+00 6.39E+08 0.00E+00 6.02E+08 SR-89 9.08E+09 0.00E+00 2.61E+08 0.00E+00 0.00E+00 0.00E+00 1.46E+09 SR-90 5.76E+l 1 0.00E+00 l.41E+ll 0.00E+00 0.00E+00 0.00E+00 l.67E+10 ZR-95 l.08E+06 3.47E+05 2.35E+05 0.00E+00 5.45E+05 0.00E+00 1.10E+09 SB-124 9.53E+07 1.80E+06 3.78E+07 2.31E+05 0.00E+00 7.42E+07 2.71E+09 I-131 5.49E+07 7.85E+07 4.50E+07 2.57E+10 1.35E+08 0.00E+00 2.07E+07 I-133 l.39E+06 2.42E+06 7.38E+05 3.56E+08 4.22E+06 0.00E+00 2.17E+06 CS-134 4.44E+09 l.06E+10 8.64E+09 0.00E+00 3.42E+09 l.13E+09 1.85E+08 CS-137 6.06E+09 8.29E+09 5.43E+09 0.00E+00 2.81E+09 9.36E+08 1.60E+08 BA-140 9.43E+07 l.19E+05 6.18E+06 0.00E+00 4.03E+04 6.78E+04 l.94E+08 CE-141 l.73E+05 l.17E+05 l.33E+04 0.00E+00 5.44E+04 0.00E+00 4.48E+08 CE-144 3.12E+07 l.30E+07 l.67E+06 0.00E+00 7.73E+06 0.00E+00 l.05E+10 40 ODCMRev.32

TABLE4-3 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY -TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 3.36E+03 3.36E+03 3.36E+03 3.36E+03 3.36E+03 3.36E+03 CR-51 0.00E+00 0.00E+00 5.60E+04 3.11E+04 l.23E+04 7.99E+04 9.41E+06 MN-54 0.00E+00 4.41E+08 8.74E+07 0.00E+00 1.31E+08 0.00E+00 9.04E+08 FE-59 1.69E+08 3.94E+08 1.52E+08 0.00E+00 0.00E+00 1.24E+08 9.31E+08 CO-58 0.00E+00 4.16E+07 9.59E+07 0.00E+00 0.00E+00 0.00E+00 5.74E+08 CO-60 0.00E+00 2.42E+08 5.45E+08 0.00E+00 0.00E+00 0.00E+00 3.15E+09 ZN-65 4.11E+08 1.43E+09 6.65E+08 0.00E+00 9.12E+08 0.00E+00 6.04E+08 SR-89 1.43E+10 0.00E+00 4.10E+08 0.00E+00 0.00E+00 0.00E+00 1.70E+09 SR-90 7.30E+l 1 0.00E+00 1.80E+ll 0.00E+00 0.00E+00 0.00E+00 2.05E+10 ZR-95 1.64E+06 5.17E+05 3.56E+05 0.00E+00 7.60E+05 0.00E+00 1.19E+09 SB-124 1.47E+08 2.70E+06 5.73E+07 3.33E+05 0.00E+00 1.28E+08 2.96E+09 I-131 5.29E+07 7.41E+07 3.98E+07 2.16E+10 1.28E+08 0.00E+00 1.47E+07 I-133 l.29E+06 2.19E+06 6.68E+05 3.06E+08 3.84E+06 0.00E+00 1.66E+06 CS-134 6.90E+09 1.62E+10 7.53E+09 0.00E+00 5.16E+09 l.97E+09 2.02E+08 CS-137 9.86E+09 1.31E+10 4.57E+09 0.00E+00 4.46E+09 1.73E+09 1.87E+08 BA-140 1.07E+08 1.31E+05 6.88E+06 0.00E+00 4.44E+04 8.80E+04 1.65E+08 CE-141 2.61E+05 1.74E+05 2.00E+04 0.00E+00 8.19E+04 0.00E+00 4.98E+08 CE-144 5.11E+07 2.12E+07 2.75E+06 0.00E+00 1.26E+07 0.00E+00 1.29E+10 41 ODCMRev.32

TABLE4-4 Ri DOSE CONVERSION FACTORS FOR THE VEGETATION PATHWAY - CHILD RECEPTOR NUCLIDES BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 5.23E+03 5.23E+03 5.23E+03 5.23E+03 5.23E+03 5.23E+03 CR-51 0.00E+00 0.00E+00 1.08E+05 6.02E+04 l.64E+04 l.10E+05 5.75E+06 MN-54 0.00E+00 6.49E+08 l.73E+08 0.00E+00 l.82E+08 0.00E+00 5.45E+08 FE-59 3.79E+08 6.13E+08 3.05E+08 0.00E+00 0.00E+00 l.78E+08 6.38E+08 CO-58 0.00E+00 6.21E+07 1.90E+08 0.00E+00 0.00E+00 0.00E+00 3.62E+08 CO-60 0.00E+00 3.70E+08 1.09E+09 0.00E+00 0.00E+00 0.00E+00 2.05E+09 ZN-65 7.93E+08 2.11E+09 l.31E+09 0.00E+00 1.33E+09 0.00E+00 3.71E+08 SR-89 3.44E+IO 0.00E+00 9.83E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+09 SR-90 l.22E+12 0.00E+00 3.09E+l 1 0.00E+00 0.00E+00 0.00E+00 l.64E+10 ZR-95 3.72E+06 8.17E+05 7.27E+05 0.00E+00 l.17E+06 0.00E+00 8.52E+08 SB-124 3.38E+08 4.39E+06 l.19E+08 7.47E+05 0.00E+00 1.88E+08 2.12E+09 I-131 9.95E+07 1.00E+08 5.68E+07 3.31E+I0 1.64E+08 0.00E+00 8.90E+06 I-133 2.36E+06 2.91E+06 l.10E+06 5.41E+08 4.85E+06 0.00E+00 l.17E+06 CS-134 l.57E+10 2.57E+10 5.43E+09 0.00E+00 7.98E+09 2.86E+09 1.39E+08 CS-137 2.34E+IO 2.24E+IO 3.31E+09 0.00E+00 7.31E+09 2.63E+09 1.40E+08 BA-140 2.20E+08 1.93E+05 1.28E+07 0.00E+00 6.27E+04 l.15E+05 l.11E+08 CE-141 6.15E+05 3.07E+05 4.55E+04 0.00E+00 1.34E+05 0.00E+00 3.83E+08 CE-144 l.24E+08 3.89E+07 6.62E+06 0.00E+00 2.15E+07 0.00E+00 l.0IE+I0 42 ODCMRev.32

TABLE4-5 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY-ADULT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 4.33E+02 4.33E+02 4.33E+02 4.33E+02 4.33E+02 4.33E+02 CR-51 0.O0E+00 0.00E+00 3.44E+02 2.06E+02 7.58E+0l 4.57E+02 8.65E+04 MN-54 0.00E+00 2.71E+06 5.18E+05 0.00E+00 8.08E+05 0.00E+00 8.31E+06 FE-59 2.60E+07 6.11E+07 2.34E+07 0.00E+00 0.00E+00 1.71E+07 2.04E+08 CO-58 0.00E+00 2.84E+06 6.36E+06 0.00E+00 0.00E+00 0.00E+00 5.75E+07 CO-60 0.00E+00 2.61E+07 5.76E+07 0.00E+00 0.00E+00 0.00E+00 4.90E+08 ZN-65 9.97E+07 3.17E+08 1.43E+08 0.00E+00 2.12E+08 0.00E+00 2.00E+08 SR-89 3.41E+07 0.00E+00 9.79E+05 0.00E+00 0.00E+00 0.00E+00 5.47E+06 SR-90 4.43E+09 0.00E+00 1.09E+09 0.00E+00 0.00E+00 0.00E+00 1.28E+08 ZR-95 2.68E+05 8.58E+04 5.81E+04 0.00E+00 1.35E+05 0.00E+00 2.72E+08 SB-124 2.67E+06 5.05E+04 1.06E+06 6.48E+03 0.00E+00 2.08E+06 7.59E+07 I-131 1.36E+05 1.94E+05 1.11E+05 6.37E+07 3.33E+05 0.00E+00 5.13E+04 I-133 4.56E-03 7.94E-03 2.42E-03 1.17E+00 1.39E-02 0.00E+00 7.14E-03 CS-134 2.17E+08 5.17E+08 4.23E+08 0.00E+00 l.67E+08 5.56E+07 9.05E+06 CS-137 3.11E+08 4.25E+08 2.78E+08 0.00E+00 1.44E+08 4.79E+07 8.22E+06 BA-140 4.35E+05 5.46E+02 2.85E+04 0.00E+00 1.86E+02 3.13E+02 8.95E+05 CE-141 8.87E+02 6.00E+02 6.80E+0l 0.00E+00 2.79E+02 0.00E+00 2.29E+06 CE-144 4.23E+05 1.77E+05 2.27E+04 0.00E+00 l.05E+05 0.00E+00 1.43E+08 43 ODCMRev.32

TABLE4-6 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY -TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.58E+02 2.58E+02 2.58E+02 2.58E+02 2.58E+02 2.58E+02 CR-51 0.00E+00 0.00E+00 2.75E+02 l.53E+02 6.03E+0l 3.93E+02 4.62E+04 MN-54 0.00E+00 2.07E+06 4.11E+05 0.00E+00 6.18E+05 0.00E+00 4.25E+06 FE-59 2.08E+07 4.85E+07 1.87E+07 0.00E+00 0.00E+00 1.53E+07 1.15E+08 CO-58 0.00E+00 2.19E+06 5.04E+06 0.00E+00 0.00E+00 0.00E+00 3.02E+07 CO-60 0.00E+00 2.03E+07 4.56E+07 0.00E+00 0.00E+00 0.00E+00 2.64E+08 ZN-65 7.01E+07 2.43E+08 1.14E+08 0.00E+00 1.56E+08 0.00E+00 1.03E+08 SR-89 2.88E+07 0.00E+00 8.24E+05 0.00E+00 0.00E+00 0.00E+00 3.43E+06 SR-90 2.87E+09 0.00E+00 7.08E+08 0.00E+00 0.00E+00 0.00E+00 8.05E+07 ZR-95 2.14E+05 6.76E+04 4.65E+04 0.00E+00 9.93E+04 0.00E+00 1.56E+08 SB-124 2.18E+06 4.02E+04 8.52E+05 4.95E+03 0.00E+00 1.91E+06 4.40E+07 I-131 1.13E+05 1.58E+05 8.49E+04 4.61E+07 2.72E+05 0.00E+00 3.13E+04 I-133 3.82E-03 6.48E-03 l.98E-03 9.04E-01 l.14E-02 0.00E+00 4.90E-03 CS-134 1.73E+08 4.07E+08 1.89E+08 0.00E+00 l.29E+08 4.94E+07 5.06E+06 CS-137 2.58E+08 3.43E+08 1.20E+08 0.00E+00 l.17E+08 4.54E+07 4.88E+06 BA-140 3.59E+05 4.40E+02 2.31E+04 0.00E+00 1.49E+02 2.96E+02 5.54E+05 CE-141 7.45E+02 4.97E+02 5.71E+0l 0.00E+00 2.34E+02 0.00E+00 1.42E+06 CE-144 3.56E+05 1.47E+05 1.91E+04 0.00E+00 8.80E+04 0.00E+00 8.96E+07 44 ODCMRev.32

TABLE 4-7 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MEAT PATHWAY - CHILD RECEPTOR NUCLIDES BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 3.12E+02 3.12E+02 3.12E+02 3.12E+02 3.12E+02 3.12E+02 CR-51 0.O0E+00 0.00E+00 4.29E+02 2.38E+02 6.51E+0l 4.35E+02 2.28E+04 MN-54 0.00E+00 2.37E+06 6.31E+05 0.00E+00 6.64E+05 0.00E+00 l.99E+06 FE-59 3.68E+07 5.96E+07 2.97E+07 0.00E+00 0.00E+00 1.73E+07 6.20E+07 CO-58 0.00E+00 2.55E+06 7.82E+06 0.00E+00 0.00E+00 0.00E+00 1.49E+07 CO-60 0.00E+00 2.40E+07 7.09E+07 0.00E+00 0.00E+00 0.00E+00 1.33E+08 ZN-65 1.05E+08 2.80E+08 1.74E+08 0.00E+00 1.77E+08 0.00E+00 4.92E+07 SR-89 5.45E+07 0.00E+00 l.56E+06 0.00E+00 0.00E+00 0.00E+00 2.11E+06 SR-90 3.70E+09 0.00E+00 9.39E+08 0.00E+00 0.00E+00 0.00E+00 4.99E+07 ZR-95 3.81E+05 8.36E+04 7.45E+04 0.00E+00 1.20E+05 0.00E+00 8.73E+07 SB-124 3.95E+06 5.12E+04 1.38E+06 8.72E+03 0.00E+00 2.19E+06 2.47E+07 I-131 2.09E+05 2.11E+05 1.20E+05 6.96E+07 3.46E+05 0.00E+00 1.87E+04 I-133 7.09E-03 8.77E-03 3.32E-03 l.63E+00 1.46E-02 0.00E+00 3.53E-03 CS-134 3.05E+08 5.00E+08 1.06E+08 0.00E+00 l.55E+08 5.56E+07 2.70E+06 CS-137 4.75E+08 4.55E+08 6.71E+07 0.00E+00 1.48E+08 5.33E+07 2.85E+06 BA-140 6.63E+05 5.81E+02 3.87E+04 0.00E+00 1.89E+02 3.46E+02 3.36E+05 CE-141 1.40E+03 6.99E+02 1.04E+02 0.00E+00 3.07E+02 0.00E+00 8.72E+05 CE-144 6.72E+05 2.11E+05 3.58E+04 0.00E+00 l.17E+05 0.00E+00 5.49E+07 45 ODCMRev.32

TABLE4-8 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY-ADULT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 l.02E+03 l.02E+03 l.02E+03 l.02E+03 l.02E+03 l.02E+03 CR-51 0.00E+00 0.00E+00 8.28E+03 4.95E+03 l.82E+03 l.10E+04 2.08E+06 MN-54 0.00E+00 3.99E+06 7.61E+05 0.00E+00 l.19E+06 0.00E+00 l.22E+07 FE-59 9.69E+06 2.28E+07 8.73E+06 0.00E+00 0.00E+00 6.36E+06 7.59E+07 CO-58 0.00E+00 l.74E+06 3.90E+06 0.00E+00 0.00E+00 0.00E+00 3.53E+07 CO-60 0.00E+00 8.41E+06 l.85E+07 0.00E+00 0.00E+00 0.00E+00 1.58E+08 ZN-65 6.34E+08 2.02E+09 9.12E+08 0.00E+00 1.35E+09 0.00E+00 l.27E+09 SR-89 4.90E+08 0.00E+00 l.41E+07 0.00E+00 0.00E+00 0.00E+00 7.86E+07 SR-90 2.43E+10 0.00E+00 5.96E+09 0.00E+00 0.00E+00 0.00E+00 7.02E+08 ZR-95 3.39E+02 1.09E+02 7.37E+0l 0.00E+00 l.71E+02 0.00E+00 3.45E+05 SB-124 9.11E+06 1.72E+05 3.61E+06 2.21E+04 0.00E+00 7.09E+06 2.59E+08 I-131 7.77E+07 l.11E+08 6.37E+07 3.64E+10 1.91E+08 0.00E+00 2.93E+07 I-133 l.02E+06 1.77E+06 5.39E+05 2.60E+08 3.08E+06 0.00E+00 1.59E+06 CS-134 2.83E+09 6.73E+09 5.50E+09 0.00E+00 2.18E+09 7.23E+08 l.18E+08 CS-137 3.83E+09 5.24E+09 3.43E+09 0.00E+00 1.78E+09 5.91E+08 1.01E+08 BA-140 7.11E+06 8.93E+03 4.66E+05 0.00E+00 3.04E+03 5.11E+03 1.46E+07 CE-141 8.73E+03 5.90E+03 6.70E+02 0.00E+00 2.74E+03 0.00E+00 2.26E+07 CE-144 1.01E+06 4.21E+05 5.41E+04 0.00E+00 2.50E+05 0.00E+00 3.41E+08 46 ODCMRev.32

TABLE4-9 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 l.33E+03 l.33E+03 1.33E+03 1.33E+03 l.33E+03 l.33E+03 CR-51 0.00E+00 0.00E+00 1.45E+04 8.03E+03 3.17E+03 2.06E+04 2.43E+06 MN-54 0.00E+00 6.64E+06 l.32E+06 0.00E+00 1.98E+06 0.00E+00 1.36E+07 FE-59 1.69E+07 3.95E+07 1.52E+07 0.00E+00 0.00E+00 1.24E+07 9.33E+07 CO-58 0.00E+00 2.93E+06 6.76E+06 0.00E+00 0.00E+00 0.00E+00 4.04E+07 CO-60 0.00E+00 1.42E+07 3.21E+07 0.00E+00 0.00E+00 0.00E+00 l.86E+08 ZN-65 9.74E+08 3.38E+09 l.58E+09 0.00E+00 2.17E+09 0.00E+00 1.43E+09 SR-89 9.03E+08 0.00E+00 2.59E+07 0.00E+00 0.00E+00 0.00E+00 1.08E+08 SR-90 3.43E+10 0.00E+00 8.48E+09 0.00E+00 0.00E+00 0.00E+00 9.64E+08 ZR-95 5.94E+02 1.87E+02 l.29E+02 0.00E+00 2.75E+02 0.00E+00 4.32E+05 SB-124 1.62E+07 2.99E+05 6.34E+06 3.69E+04 0.00E+00 1.42E+07 3.27E+08 I-131 l.41E+08 l.98E+08 l.06E+08 5.76E+10 3.40E+08 0.00E+00 3.91E+07 I-133 l.86E+06 3.15E+06 9.60E+05 4.39E+08 5.52E+06 0.00E+00 2.38E+06 CS-134 4.91E+09 1.16E+10 5.36E+09 0.00E+00 3.67E+09 1.40E+09 1.44E+08 CS-137 6.95E+09 9.24E+09 3.22E+09 0.00E+00 3.15E+09 l.22E+09 1.32E+08 BA-140 1.28E+07 l.57E+04 8.27E+05 0.00E+00 5.33E+03 1.06E+04 1.98E+07 CE-141 1.60E+04 l.07E+04 l.23E+03 0.00E+00 5.03E+03 0.00E+00 3.06E+07 CE-144 1.86E+06 7.68E+05 9.97E+04 0.00E+00 4.59E+05 0.00E+00 4.67E+08 47 ODCMRev.32

TABLE4-10 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - CHILD RECEPTOR NUCLIDES BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 2.09E+03 CR-51 0.00E+00 0.00E+00 2.95E+04 l.64E+04 4.47E+03 2.99E+04 l.56E+06 MN-54 0.00E+00 9.94E+06 2.65E+06 0.00E+00 2.79E+06 0.00E+00 8.34E+06 FE-59 3.92E+07 6.35E+07 3.16E+07 0.00E+00 0.00E+00 l.84E+07 6.61E+07 CO-58 0.00E+00 4.48E+06 l.37E+07 0.00E+00 0.00E+00 0.00E+00 2.61E+07 CO-60 0.00E+00 2.21E+07 6.52E+07 0.00E+00 0.00E+00 0.00E+00 l.23E+08 ZN-65 l.91E+09 5.09E+09 3.17E+09 0.00E+00 3.21E+09 0.00E+00 8.95E+08 SR-89 2.23E+09 0.00E+00 6.38E+07 0.00E+00 0.00E+00 0.00E+00 8.65E+07 SR-90 5.80E+10 0.00E+00 l.47E+10 0.00E+00 0.00E+00 0.00E+00 7.81E+08 ZR-95 l.38E+03 3.03E+02 2.70E+02 0.00E+00 4.34E+02 0.00E+00 3.16E+05 SB-124 3.84E+07 4.99E+05 l.35E+07 8.49E+04 0.00E+00 2.13E+07 2.41E+08 I-131 3.42E+08 3.44E+08 l.96E+08 1.14E+ll 5.65E+08 0.00E+00 3.06E+07 I-133 4.51E+06 5.57E+06 2.11E+06 l.04E+09 9.29E+06 0.00E+00 2.25E+06 CS-134 1.13E+10 l.86E+10 3.92E+09 0.00E+00 5.76E+09 2.07E+09 1.00E+08 CS-137 l.67E+10 l.60E+10 2.36E+09 0.00E+00 5.22E+09 1.88E+09 1.00E+08 BA-140 3.10E+07 2.71E+04 l.81E+06 0.00E+00 8.83E+03 1.62E+04 1.57E+07 CE-141 3.94E+04 l.97E+04 2.92E+03 0.00E+00 8.62E+03 0.00E+00 2.45E+07 CE-144 4.57E+06 1.43E+06 2.44E+05 0.00E+00 7.94E+05 0.00E+00 3.74E+08 48 ODCMRev.32

TABLE4-11 Ri DOSE CONVERSION FACTORS FOR THE GRASS-COW-MILK PATHWAY - INFANT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 3.18E+03 3.18E+03 3.18E+03 3.18E+03 3.18E+03 3.18E+03 CR-51 0.00E+00 0.00E+00 4.67E+04 3.05E+04 6.66E+03 5.93E+04 l.36E+06 MN-54 0.00E+00 1.85E+07 4.19E+06 0.00E+00 4.10E+06 0.00E+00 6.79E+06 FE-59 7.32E+07 1.28E+08 5.04E+07 0.00E+00 0.00E+00 3.78E+07 6.11E+07 CO-58 0.00E+00 8.96E+06 2.23E+07 0.00E+00 0.00E+00 0.00E+00 2.23E+07 CO-60 0.00E+00 4.52E+07 1.07E+08 0.00E+00 0.00E+00 0.00E+00 l.07E+08 ZN-65 2.57E+09 8.81E+09 4.06E+09 0.00E+00 4.27E+09 0.00E+00 7.44E+09 SR-89 4.25E+09 0.00E+00 1.22E+08 0.00E+00 0.00E+00 0.00E+00 8.74E+07 SR-90 6.31E+10 0.00E+00 1.61E+10 0.00E+00 0.00E+00 0.00E+00 7.88E+08 ZR-95 2.45E+03 5.97E+02 4.23E+02 0.00E+00 6.43E+02 0.00E+00 2.97E+05 SB-124 7.41E+07 1.09E+06 2.30E+07 1.97E+05 0.00E+00 4.64E+07 2.29E+08 1-131 7.14E+08 8.42E+08 3.70E+08 2.77E+ll 9.83E+08 0.00E+00 3.00E+07 1-133 9.52E+06 1.39E+07 4.06E+06 2.52E+09 l.63E+07 0.00E+00 2.35E+06 CS-134 1.82E+10 3.40E+10 3.44E+09 0.00E+00 8.76E+09 3.59E+09 9.24E+07 CS-137 2.67E+10 3.13E+10 2.22E+09 0.00E+00 8.39E+09 3.40E+09 9.78E+07 BA-140 6.37E+07 6.37E+04 3.28E+06 0.00E+00 1.51E+04 3.91E+04 1.57E+07 CE-141 7.81E+04 4.77E+04 5.61E+03 0.00E+00 1.47E+04 0.00E+00 2.46E+07 CE-144 6.55E+06 2.68E+06 3.67E+05 0.00E+00 l.08E+06 0.00E+00 3.76E+08 49 ODCMRev.32

TABLE4-12 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY-ADULT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 l.26E+03 l.26E+03 l.26E+03 l.26E+03 l.26E+03 l.26E+03 CR-51 0.00E+00 0.00E+00 l.00E+02 5.95E+0l 2.28E+0l l.44E+04 3.32E+03 MN-54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 l.40E+06 7.74E+04 FE-59 l.18E+04 2.78E+04 l.06E+04 0.00E+00 0.00E+00 l.02E+06 l.88E+05 CO-58 0.00E+00 l.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 l.06E+05 CO-60 0.00E+00 1.15E+04 l.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 ZN-65 3.24E+04 l.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 SR-89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 l.40E+06 3.50E+05 SR-90 9.92E+07 0.00E+00 6.I0E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 ZR-95 l.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 l.77E+06 l.50E+05 SB-124 3.12E+04 5.89E+02 l.24E+04 7.55E+0l 0.00E+00 2.48E+06 4.06E+05 I-131 2.52E+04 3.58E+04 2.05E+04 l.19E+07 6.13E+04 0.00E+00 6.28E+03 I-133 8.64E+03 l.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 CS-134 3.73E+05 8.48E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+0l 2.57E+03 0.00E+00 l.67E+0l 1.27E+06 2.18E+05 CE-141 1.99E+04 l.35E+04 l.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 l.43E+06 l.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 50 ODCMRev.32

TABLE4-13 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY -TEEN RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 l.27E+03 l.27E+03 l.27E+03 l.27E+03 l.27E+03 l.27E+03 CR-51 0.00E+00 0.00E+00 1.35E+02 7.50E+0l 3.07E+0l 2.IOE+04 3.00E+03 MN-54 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 l.98E+06 6.68E+04 FE-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 l.53E+06 l.78E+05 CO-58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 l.34E+06 9.52E+04 CO-60 0.00E+00 l.51E+04 l.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 l.24E+06 4.66E+04 SR-89 4.34E+05 0.00E+00 l.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 SR-90 l.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 ZR-95 l.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 SB-124 4.30E+04 7.94E+02 1.68E+04 9.76E+0l 0.00E+00 3.85E+06 3.98E+05 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 I-133 l.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 CS-137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA-140 5.47E+04 6.70E+0l 3.52E+03 0.00E+00 2.28E+0l 2.03E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 51 ODCMRev.32

TABLE4-14 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - CHILD RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 l.12E+03 l.12E+03 l.12E+03 l.12E+03 l.12E+03 l.12E+03 CR-51 0.00E+00 0.00E+00 1.54E+02 8.55E+0l 2.43E+0l l.70E+04 l.08E+03 MN-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 l.27E+06 7.07E+04 CO-58 0.00E+00 l.77E+03 3.16E+03 0.00E+00 0.00E+00 l.11E+06 3.44E+04 CO-60 0.00E+00 l.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 ZN-65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 SR-89 5.99E+05 0.00E+00 l.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR-90 l.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 ZR-95 l.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 SB-124 5.74E+04 7.40E+02 2.00E+04 l.26E+02 0.00E+00 3.24E+06 l.64E+05 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I-133 l.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS-134 6.51E+05 l.01E+06 2.25E+05 0.00E+00 3.30E+05 l.21E+05 3.85E+03 CS-137 9.07E+05 8.25E+05 l.28E+05 0.00E+00 2.82E+05 l.04E+05 3.62E+03 BA-140 7.40E+04 6.48E+0l 4.33E+03 0.00E+00 2.llE+0l l.74E+06 1.02E+05 CE-141 3.92E+04 l.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 0.00E+00 l.17E+06 l.20E+07 3.89E+05 52 ODCMRev.32

TABLE4-15 Ri DOSE CONVERSION FACTORS FOR THE INHALATION PATHWAY - INFANT RECEPTOR NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 CR-51 0.00E+00 0.00E+00 8.95E+0l 5.75E+0l l.32E+0l l.28E+04 3.57E+02 MN-54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 CO-58 0.00E+00 l.22E+03 l.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 CO-60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 ZN-65 l.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 SR-89 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 l.31E+05 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 l.75E+06 2.17E+04 SB-124 3.79E+04 5.56E+02 l.20E+04 l.01E+02 0.00E+00 2.65E+06 5.91E+04 I-131 3.79E+04 4.44E+04 l.96E+04 1.48E+07 5.18E+04 0.00E+00 l.06E+03 I-133 1.32E+04 l.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 l.90E+05 7.97E+04 1.33E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 l.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+0l 2.90E+03 0.00E+00 l.34E+0l 1.60E+06 3.84E+04 CE-141 2.77E+04 l.67E+04 l.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 CE-144 3.19E+06 l.21E+06 l.76E+05 0.00E+00 5.38E+05 9.84E+06 1.48E+05 53 ODCMRev.32

TABLE4-16 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PATHWAY LOCATIONS CENTERED ON UNIT 1 X/Q RESIDENCE(b)

D/Q X/Q GARDEN(b)

D/Q X/Q MILK(b)

D/Q DIRECTION (Sec/m3)

Dist. Miles (m-2)

(Sec/m3)

Dist. Miles (m-2)

(Sec/m3)

Dist. Miles (m-2)

N 2.92E-06 1.4 3.25E-09 2.92E-06 1.4 3.25E-09 7.03E-07 (a) 3.48E-10 NNE l.81E-06 1.8 2.88E-09 4.70E-07 (a) 4.04E-10 4.70E-07 (a) 4.04E-10 NE l.95E-06 1.9 3.85E-09 l.76E-06 2.1 3.29E-09 5.77E-07 (a) 6.51£-10 ENE l.03E-06 2.7 l.08E-09 l.03E-06 2.7 l.08E-09 3.86E-07 (a) 2.86E-10 E

9.39E-07 2.8 6.68E-10 3.71E-07 (a) l.87E-10 3.71E-07 (a) l.87E-10 ESE 6.37E-07 3.7 2.84E-10 4.12E-07 4.6 l.60E-10 4.12E-07 4.6 l.60E-10 goat SE 8.83E-07 4.1 2.61E-10 8.83E-07 4.1 2.61E-10 5.84E-07 (a) 1.52E-10 SSE l.27E-06 4.7 2.61E-10 l.09E-06 (a) 2.15E-10 l.09E-06 (a) 2.15E-10 s

2.58E-06 4.6 4.85E-10 2.09E-06 5.2 3.59E-10 2.13E-06 5.1 3.71E-10 cow SSW 3.26E-06 3.5 8.26E-10 2.28E-06 (a) 4.53E-10 2.28E-06 (a) 4.53E-10 SW 2.80E-06 2.9 9.lOE-10 1.58E-06 (a) 3.56E-10 1.58E-06 (a) 3.56E-10 WSW l.95E-06 2.6 1.09E-09 8.55E-07 (a) 3.18E-10 8.55E-07 (a) 3.18E-10 w

7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 WNW 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 NW 8.24E-07 3.8 5.25E-10 7.55E-07 4.1 4.61E-10 6.02E-07 (a) 3.27E-10 NNW l.46E-06 2.0 l.47E-09 5.20E-07 (a) 3.04E-10 5.20E-07 (a) 3.04E-10 (a) 5-mile value used since there is no pathway located within the sector up to five miles.

(b) Controlling locations are discussed in Appendix A.

References:

1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.

54 ODCMRev. 32

TABLE4-17 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PA1HWAYLOCATIONS CENTERED ON UNIT 2 X/Q RESIDENCE(b)

D/Q X/Q GARDEN(b)

D/Q X/Q MILK(b)

D/Q DIRECTION (Sec/m3)

Dist. Miles (m-2)

(Sec/m3)

Dist. Miles (m-2)

(Sec/m3)

Dist. Miles (m-2)

N 2.73E-06 1.5 2.92E-09 2.39E-06 1.7 2.35E-09 7.03E-07 (a) 3.48E-10 NNE 2.20E-06 1.5 3.87E-09 2.20E-06 1.5 3.87E-09 4.70E-07 (a) 4.04E-10 NE l.85E-06 2.0 3.55E-09 1.57E-06 2.3 2.78E-09 5.77E-07 (a) 6.51£-10 ENE 1.03E-06 2.7 l.08E-09 l.03E-06 2.7 l.08E-09 3.86E-07 (a) 2.86E-10 E

8.80E-07 3.0 6.06E-10 3.71E-07 (a) l.87E-10 3.71E-07 (a) l.87E-10 ESE 6.25E-07 3.7 2.76E-10 3.96E-07 4.7 l.51E-10 3.96E-07 4.7 l.5 lE-10 goat SE 9.06E-07 4.0 2.72E-10 9.06E-07 4.0 2.72E-10 5.84E-07 (a) 1.52E-10 SSE l.34E-06 4.5 2.81E-10 l.09E-06 (a) 2.15E-10 l.09E-06 (a) 2.15E-10 s

2.63E-06 4.5 5.0lE-10 2.19E-06 5.0 3.88E-10 2.19E-06 5.0 3.88E-10 cow SSW 3.48E-06 3.2 9.19E-10 2.28E-06 (a) 4.53E-10 2.28E-06 (a) 4.53E-10 SW 2.93E-06 2.7 9.75E-10 l.58E-06 (a) 3.56E-10 l.58E-06 (a) 3.56E-10 WSW 2.0lE-06 2.5 1.16E-09 8.55E-07 (a) 3.18E-10 8.55E-07 (a) 3.18E-10 w

7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 WNW 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 NW 7.84E-07 4.0 4.88E-10 7.84E-07 4.0 4.88E-10 6.02E-07 (a) 3.27E-10 NNW 1.46E-06 2.0 l.47E-09 5.20E-07 5.0 3.04E-10 5.20E-07 (a) 3.04E-10 (a) 5-mile value used since there is no pathway located within the sector up to five miles.

(b) Controlling locations are discussed in Appendix A.

References:

1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.

55 ODCMRev. 32

TABLE4-18 PALO VERDE NUCLEAR GENERATING STATION DISPERSION AND DEPOSITION PARAMETERS FOR LONG TERM RELEASES AT THE NEAREST PA1HWAYLOCATIONS CENTERED ON UNIT 3 X/Q RESIDENCE(b)

D/Q X/Q GARDEN(b)

D/Q X/Q MILK(b)

D/Q DIRECTION (Sec/m3)

Dist. Miles (m-2)

(Sec/m3)

Dist. Miles (m-2)

(Sec/m3)

Dist. Miles (m-2)

N 2.58E-06 1.8 2.47E-09 2.42E-06 1.9 2.22E-09 7.03E-07 (a) 3.48E-10 NNE l.85E-06 1.7 2.97E-09 1.85E-06 1.7 2.97E-09 4.70E-07 (a) 4.04E-10 NE l.66E-06 2.2 3.00E-09 l.48E-06 2.4 2.54E-09 5.77E-07 (a) 6.51£-10 ENE 8.75E-07 2.9 8.86E-10 8.75E-07 2.9 8.86E-10 3.86E-07 (a) 2.86E-10 E

8.90E-07 3.0 6.17E-10 4.06E-07 4.6 2.15E-10 4.25E-07 4.5 2.3 lE-10 goat ESE 6.37E-07 3.7 2.84E-10 5.80E-07 4.0 2.46E-10 3.73E-07 (a) l.37E-10 SE 5.84E-07 (a) 1.52E-10 5.84E-07 (a) 1.52E-10 5.84E-07 (a) 1.52E-10 SSE 1.36E-06 4.4 2.88E-10 l.09E-06 (a) 2.15E-10 l.09E-06 (a) 2.15E-10 s

2.65E-06 4.2 5.25E-10 2.25E-06 4.9 4.06E-10 2.31E-06 4.8 4.21E-10 cow SSW 3.64E-06 3.1 9.82E-10 2.28E-06 (a) 4.53E-10 2.28E-06 (a) 4.53E-10 SW 3.19E-06 2.5 1.llE-09 1.58E-06 (a) 3.56E-10 1.58E-06 (a) 3.56E-10 WSW 2.12E-06 2.4 1.26E-09 8.55E-07 (a) 3.18E-10 8.55E-07 (a) 3.18E-10 w

7.54E-07 (a) 4.44E-10 7.54E-07 (a) 4.44E-10 7.54E-10 (a) 4.44E-10 WNW 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 6.03E-07 (a) 3.25E-10 NW 6.83E-07 4.3 4.05E-10 6.82E-07 4.3 4.05E-10 6.02E-07 (a) 3.27E-10 NNW l.34E-06 2.2 1.26E-09 5.16E-07 5.0 3.0lE-10 5.20E-07 (a) 3.04E-10 (a) 5-mile value used since there is no pathway located within the sector up to five miles.

(b) Controlling locations are discussed in Appendix A.

References:

1984 Land Use Census (letter ANPM-21221-JRM/LEB). NUS Corporation letters NUS-ANPP-1385 and NUS-ANPP-1386.

56 ODCMRev. 32

4.4 Requirements

Liquid Effluents The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (See Figure 6-4 and Figure 6-5) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b.

During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

Applicability:

At all times.

Action:

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

4.4.1 Surveillance Requirements Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

4.4.2 Implementation of the Requirements This Requirement does not require implementation guidance. There are no offsite liquid effluent releases.

57 ODCMRev. 32

5.0 TOTAL DOSE AND DOSE TO PUBLIC ONSITE

5.1 Requirement

Total Dose The annual ( calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to direct radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

Applicability:

At all times.

Action:

With the calculated doses from the release of radioactive materials in liquid and gaseous effluents exceeding twice the limits of Section 4.4a, 4.4b, 4. la, 4.1 b, 4.2a or 4.2b calculations shall be made including direct radiation contributions from the reactor units (including outside storage tanks, etc.) to determine whether the above limits of Section 5.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203(a)(4), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose( s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report within 30 days is considered a timely request, and a variance is granted until staff action on the request is complete.

5.1.1 Surveillance Requirements

a. Cumulative dose contributions from the gaseous effluents shall be determined in accordance with the surveillance requirements of Section 4.4.1, 4.1.1 and 4.2.1 and in accordance with the methodology and parameters contained in Section 5.1.2.

b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in Section 5.1.2. This requirement is applicable only under conditions set forth in Section 5.1, Action.

5.1.2 Implementation of the Requirement Since all other uranium fuel cycle sources are greater than 20 miles away, only the PVNGS site need be considered.

The total dose to any MEMBER OF THE PUBLIC will be determined based on a sum of the doses from all three units' releases and doses from direct radiation from PVNGS.

58 ODCMRev. 32

This dose evaluation is performed annually and submitted with the Annual Radioactive Effluent Release Report to assure compliance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

NUREG-0543, Methods for Demonstrating L WR Compliance With the EPA Uranium Fuel Cycle Standard ( 40 CFR Part 190), February 1980, provides a discussion on compliance with 40 CFR Part 190 in relation to the Radiological Environmental Technical Specifications for sites of up to four nuclear power reactors. The NUREG concludes that as long as a nuclear plant site operates at a level below the 10 CFR Part 50, Appendix I reporting requirements, and there is no significant source of direct radiation from the site, no extra analysis is required to demonstrate compliance with 40 CFR Part 190. As a result, this dose evaluation will also be performed whenever calculated doses associated with effluent releases exceed twice the limits of Section 4.4a, 4.4b, 4.la, 4.lb, 4.2a or 4.2b.

Dose Contribution from Liquid and Gaseous Effluents The annual whole body dose accumulated by a MEMBER OF THE PUBLIC for the noble gases released in gaseous effluents is determined by using the following equation:

Where:

K I Qi (X/Q)UNIT 3.17E-08

= (3.17E-08) ~i [(Ki) (X/Q)UNIT (Qi)]

(5-1) the whole body dose factor due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per µCi/m3 from Table 3-3.

the integrated release of radionuclide i, in µCi for the previous calendar year.

the highest calculated annual average dispersion parameter, in sec/m3, for a particular unit, at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.

=2.92E-06 from Unit 1

=2.19E-06 from Unit 2

=2.3 lE-06 from Unit 3 the annual whole body dose in mrem to a MEMBER OF THE PUBLIC at the controlling location due to noble gases released in gaseous effluents.

the inverse of seconds in a year (yr/sec).

59 ODCMRev.32

The annual dose to any organ accumulated by a MEMBER OF THE PUBLIC for iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous eftluents is determined by using the following equation:

(5-2)

Where:

D0

= the total annual organ dose from gaseous effluents to a MEMBER OF THE PUBLIC, in mrem, at the controlling location.

Qi

= the integrated release of radionuclide i, in µCi, for the previous calendar year.

Rik

= the dose factor for each identified radionuclide i, for pathway k (for the inhalation pathway in mrem/yr per µCi/m3 and for the food and ground plane pathways in m2-mrem/yr per µCi/sec) at the controlling location. The Rik's for each age group are given in Tables 4-1 through 4-15.

WK the highest annual average dispersion or deposition parameter for the particular unit, used for estimating the total annual organ dose to a MEMBER OF THE PUBLIC at the controlling location for the particular unit.

3.17E-08 (X/Q)UNIT, in sec/m3 for the inhalation pathway and for all tritium calculations, for organ dose at the controlling location, from Table 4-16, 4-1 7, or 4-18, or concurrent meteorological data if available.

=2.92E-06 from Unit 1

=2.19E-06 from Unit 2

=2.3 lE-06 from Unit 3

= (D/Q)UNIT, in m-2, for the food and ground plane pathways, for organ dose at the controlling location, from Table 4-16, 4-17, or 4-18, or concurrent meteorological data if available.

=3.25E-09 from Unit 1

=3.88E-10 from Unit 2

=4.21E-10 from Unit 3 the inverse of seconds in a year (yr/sec).

60 ODCMRev. 32

Dose Due to Direct Radiation The component of dose to a MEMBER OF THE PUBLIC due to direct radiation will be evaluated by first determining the direct radiation dose at the site boundary in each sector, and then extrapolating the site boundary dose to the controlling location by the inverse square law of distance.

Dose from Radiactive Liquid and Gaseous Effluents to MEMBERS OF THE PUBLIC due to their activities within the SITE BOUNDARY.

These activities have been determined to be limited to the vicinity of the controlling location of Administrative Building "C", formerly the Energy Information Center (EiC), located inside the SITE Boundary. An assumption was made that no MEMBER OF THE PUBLIC would spend more than eight hours per year at this location. However this calculation has been historically performed assuming an occupancy factor of one (implying continuous occupancy over the entire year).

A X/Q, determined for Administrative Building "C", will be used for this assessment.

Equations 5-1 and 5-2 in Section 5.1.2 should be used for this assessment.

61 ODCMRev. 32

6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

6.1 Requirement

REMP The radiological environmental monitoring program shall be conducted as specified in Table 6-1, based on locations determined using data from the pre-operational monitoring period; and/or the operational monitoring period indicating a need to make changes in the program.

Applicability:

At all times.

Action:

a. With the radiological environmental monitoring program not being conducted as specified in Table 6-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, as required by Section 7.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 6-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to A MEMBER OF THE PUBLIC is less than the calendar year limits of Section 4.4, 4.1 and 4.2. When more than one of the radionuclides in Table 6-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

+ -------+... > 1 0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 6-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Section 4.4, 4.1 and 4.2. 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.

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 6-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

62 ODCMRev. 32

6.1.1 Surveillance Requirements The radiological environmental monitoring samples shall be collected pursuant to Table 6-1 from the specific locations given in Table 6-4 and Figure 6-1 and Figure 6-2 and shall be analyzed pursuant to the requirements of Table 6-1, and the detection capabilities required by Table 6-3.

6.1.2 Implementation of the Requirements The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected based on the effluent measurements and modeling of the environmental exposure pathways.

Thus the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals resulting from station operation.

This requirement is implemented by Nuclear Administrative and Technical Manual procedures.

63 ODCMRev. 32

TABLE6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Samples Sampling and Type and Frequency and/or Sample and Sample Locations8 Collection Frequency8 of Analysisd Airborne Samples from 5 locations: 4 samples Continuous sampling Gross beta weeklyc, at or near the SITE BOUNDARIES collected weekly, or 1-131 weekly; gamma Radioiodine and

(#14A, 15, 29, 40) including 3 more frequently if isotopic analysis of particulates different sectors of the highest required by dust composite (by calculated annual average ground loading.

location) quarterly.

level D/Q.*

1 sample (#40) from areas of special interest, which is from the vicinity of a community having the highest calculated annual average D/Q.

1 sample (#6A) from a control location 15-30 km (9-18 mi) distant and in the least prevalent wind direction.e Direct radiationb Forty ( 40) routine monitoring Quarterly Gamma dose stations (#5-40, #42, #44, #46, #50) quarterly.

either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the site boundary (16 locations);

An outer ring of stations, one in each meteorological sector in the 6-8 km (4-5 mi) range from the site (16 locations); and The balance of the stations (8 locations) to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

D/Q refers to average annual relative ground deposition rate.

64 ODCMRev. 32

Jun 2024 Jun 2024 TABLE6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Samples Sampling and Type and Frequency and/or Sample and Sample Locations8 Collection Frequency8 of Analysisd Waterborne Surface 85 acre Water storage reservoir (#60)

Quarterlyh grab sample Tritium and gamma 45 acre Water storage reservoir (#61) isotopic analysis Evaporation pond #1 (#59A, #59B, quarterly.

59C)

Evaporation pond #2 (#63A, #63B)

Evaporation pond #3 (#64A, #64B)

Ground 3 onsite we11sf (#57, #SSA, #65)

Quarterly grab sample Tritium and gamma isotopic analysis quarterly.

Drinking (well) 3 wells from surrounding residences Composite sample of I-131 analysis on each

(#46, #48, #49) that would be weekly grab samples composite when the affected by its discharge.

over 2-week period dose calculated for when I-131 analysis is the consumption of performed, monthly the water is greater composite of weekly than 1 rnrem per grab samples otherwise year.g Composite for gross beta and gamma isotopic analyses monthly. Composite for tritium analysis quarterly.

Ingestion Samples from milking animals in Semimonthly for Gamma isotopic and 3 locations, when available, within 8 animals on pasture; I-131 analysis Milk km (5 mi) distant in sectors of otherwise, monthly.

semimonthly when highest dose potential animals are on pasture

(#49, #54, #66) where doses are or monthly at other calculated to be greater than 1 rnrem times.

per year_g, i One sample from milking animals at a control location 15 to 30 km (9-18 mi) distant (#53) and in the least prevalent wind direction. e 65 ODCMRev.32

TABLE6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Samples Sampling and Type and Frequency and/or Sample and Sample Locations8 Collection Frequency8 of Analysisd Food Products

I sample (#47, #49) of3 types of Monthly during Gamma isotopic broad leaf vegetation (as available) growing season.

analysis.

from locations identified per the criteria of Section 6.2b. of this manual.

I control sample (#62) of3 types of Monthly during Gamma isotopic broad leaf vegetation (as available) growing season.

analysis.

grown 15 to 30 km (9-18 mi) distant in the least prevalent wind direction. e

When broad leaf vegetation samples are not available, reports from 4 existing supplemental airborne radioiodine sample locations will be substituted.

66 ODCMRev. 32

TABLE 6-1 (Continued)

TABLE NOTATION a

The number, media, frequency, and location of sampling may vary from site to site. It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question. Actual locations (distance and direction) from the site shall be provided in Table 6-4 and Figure 6-lor Figure 6-2 in the ODCM. Refer to Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants."

June I b 2024 Regulatory Guide 4.13 provides guidance for thermoluminescence dosimetry (TLD), and optically stimulated luminescence dosimeter (OSLO) 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.

c Particulate sample filters shall be analyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air or water is greater than 10 times the yearly mean of control samples for any medium, gamma isotopic analysis should be performed on the individual samples.

d Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

e The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the wind direction and distance criteria, other sites that provide valid background data may be substituted.

f Groundwater samples should be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

g The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

h Quarterly grab samples are not required from the onsite evaporation pond if the evaporation pond has not received any influent since the last sample was taken.

When milk sample is required, but none are present or unavailable, broad leaf vegetation samples shall be collected from a sector of the highest D/Q within the 8 km (5 mi) radius.

67 ODCMRev. 32

Analysis H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 1-131 Cs-134 Cs-137 TABLE6-2 REPORTING LEVELS FOR RADIOACTMTY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Particulate Fresh Milk Food Products Water (pCi/1) or Gas (pCi/m3)

(pCi/1)

(pCi/kg, wet) 20,000

1,000 400 1,000 300 300 400 2 **

0.9 3

100 30 10 60 1,000 50 20 70 2,000 Ba-La-140 200 300 For drinking water samples. This is a 40 CFR 141 value. Ifno drinking water pathway exists, a value of 30,000 pCi/1 may be used.

If no drinking water pathway exists, a reporting level of 20 pCi/1 may be used.

68 ODCMRev. 32

TABLE6-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL ANALYSIS a Lower Limit of Detection (LLD)b Airborne Particulate Fresh Milk Food Products Analysis Water (pCi/1) or Gas (pCi/m3)

(pCi/1)

(pCi/kg, wet)

Gross Beta 4

0.01 H-3 2000*

Mn-54 15 Fe-59 30 Co-58, -60 15 Zn-65 30 Zr-95 30 Nb-95 15 1-131 1**

0.07 1

60 Cs-134 15 0.05 15 60 Cs-137 18 0.06 18 80 Ba-140 60 60 La-140 15 15 NOTE: This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

If no drinking water pathway exists, a value of 3000 pCi/1 may be used.

If no drinking water pathway exists, a value of 15 pCi/1 may be used.

69 ODCMRev.32

June 2024 Table 6-3 (Continued)

TABLE NOTATION Guidance for detection capabilities for thermoluminescent dosimeters, and optically stimulated, dosimeters used for environmental measurements is given in Regulatory Guide 4.13.

b Table 6-3 indicates acceptable detection capabilities for radioactive materials in environmental samples.

These detection capabilities are tabulated in terms of the lower limits of detection (LLDs ). The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) 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_.6_6_S_b ___ _

E

V

2.22

Y

exp ( -ALlt)

Where:

LLD is the a priori lower limit of detection as defined above ( as pCi per unit mass or volume),

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

Eis the counting efficiency (as counts per disintegration),

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

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and Lit for environmental samples is the elapsed time between sample collection ( or end of the s a m p 1 e collection period) and time of counting.

In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should include the typical contributions of other radionuclides normally present in the samples ( e.g.,

potassium-40 in milk samples). Typical values ofE, 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 a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

70 ODCMRev.32

6.2 Requirement

Land Use Census A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation.

Applicability:

At all times.

Action:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Section 4.2.1, identify the new location(s) in the next Annual Radioactive Effluent Release Report, pursuant to Section 7.1.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Section 6.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may then be deleted from the monitoring program.

6.2.1 Surveillance Requirements

a. The land use census shall be conducted during the growing season annually using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.

6.2.2 Implementation of the Requirements The above Requirement is implemented by Nuclear Administrative and Technical Manual procedures.

Broad Leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 6-1 shall be followed, including analysis of control samples.

71 ODCMRev.32

6.3 Requirement

Interlaboratory Comparison Program Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that correspond to samples required by Table 6-1, as applicable.

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 pursuant to Section 7.2.

6.3.1 Surveillance Requirements

a. A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the methodology and parameters in this manual shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.2.

6.3.2 Implementation of the Requirements PVNGS laboratories or contract laboratories which perform analyses for the Radiological Environmental Monitoring Program (REMP) participate in an Interlaboratory Comparison Program. The participation includes all of the determinations (sample medium-radionuclide combinations) that are included in the monitoring program.

If deviation from specified limits is identified an investigation is made to determine the reason for the deviation and corrective actions are taken as necessary. The results of all analyses made under this program are included in the Annual Radiological Environmental Operating Report.

72 ODCMRev. 32

June 2024 June 2024 June 2024 TABLE6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE NOTE DESIGNATION SITE SAMPLE TYPE (d)

(a)

LOCATION DESCRIPTION (c)

I TLDOROSLD SUP E30 Goodyear 2

TLDOROSLD SUP ENE24 Scott-Libby School 3

TLDOROSLD SUP E21 Liberty School 4

TLDOROSLD SUP E16 Buckeye 4

Air SUP E16 Same as TLD 5

TLD OR OSLO (b)

SP ESEll Palo Verde School 6

TLD OR OSLO (b)

Control SSE31 APS Gila Bend substation 6

Air (b)

Control SSE13 Old US 80 7

TLD OR OSLO (b)

SP SE7 Old US 80 and Arlington School Rd.

7 Air SUP ESE3 Arlington School 8

TLD OR OSLO (b)

OR SSE4 Southern Pacific Pipeline Rd.

9 TLD OR OSLO (b)

OR S5 Southern Pacific Pipeline Rd.

10 TLD OR OSLO (b)

OR SES 355th Ave. and Elliot Rd.

11 TLD OR OSLO (b)

OR ESE5 339th Ave. and Dobbins Rd.

12 TLD OR OSLO (b)

OR E5 339th Ave. and Buckeye-Salome Rd.

13 TLD OR OSLO (b)

IR Nl N site boundary 14 TLD OR OSLO (b)

IR NNE2 NNE site boundary 14 Air (b)

NNE2 3 71 st Ave. and Buckeye-Salome Rd.

15 TLD OR OSLO (b)

IR NE2 NE site boundary, WRF access road 15 Air (b)

NE2 Same as TLD 16 TLD OR OSLO (b)

IR ENE2 ENE site boundary 17 TLD OR OSLO (b)

IR E2 E site boundary 17 Air SUP E3 351st Ave.

18 TLD OR OSLO (b)

IR ESE2 ESE site boundary 19 TLD OR OSLO (b)

IR SE2 SE site boundary 20 TLD OR OSLO (b)

IR SSE2 SSE site boundary 73 ODCMRev. 32

June 2024 June 2024 June 2024 June 2024 June 2024 TABLE6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE NOTE DESIGNATION SITE SAMPLE TYPE (d)

(a)

LOCATION DESCRIPTION (c) 21 TLD OR OSLD (b)

IR S3 S site boundary 21 Air SUP S3 Same as TLD 22 TLD OR OSLD (b)

IR SSW3 SSW site boundary 23 TLD OR OSLD (b)

OR W5 N of Elliot Rd 24 TLD OR OSLD (b)

OR SW4 N of Elliot Rd.

25 TLD OR OSLD (b)

OR WSW5 N of Elliot Rd.

26 TLD OR OSLD (b)

OR SSW4 Duke Property 27 TLD OR OSLD (b)

IR SWI SW site boundary 28 TLD OR OSLD (b)

IR WSWI WSW site boundary 29 TLD OR OSLD (b)

IR WI W site boundary 29 Air (b)

WI Same as TLD 30 TLD OR OSLD (b)

IR WNWl WNW site boundary 31 TLD OR OSLD (b)

IR NWl NW site boundary 32 TLD OR OSLD (b)

IR NNWl NNW site boundary 33 TLD OR OSLD (b)

OR NW4 S of Buckeye Rd.

34 TLD OR OSLD (b)

OR NNWS 395th Ave. and Van Buren St.

35 TLD OR OSLD (b)

SP NNW8 Tonopah 35 Air SUP NNW8 Same as TLD 36 TLD OR OSLD (b)

OR NS Wintersburg Rd. and Van Buren St.

37 TLD OR OSLD (b)

OR NNE5 363rd Ave. and Van Buren St.

38 TLD OR OSLD (b)

OR NE5 355th Ave. and Buckeye Rd.

39 TLD OROSLD (b)

OR ENE5 343rd Ave. N of Broadway Rd.

40 TLD OROSLD (b)

SP N2 Wintersburg 40 Air (b)

N2 Same as TLD 41 TLDOROSLD SUP ESE3 Arlington School 42 TLD OR OSLD (b)

SP N8 Ruth Fisher School 43 TLDOROSLD SUP NE5 Winters Well School 74 ODCMRev. 32

June 2024 June 2024 June 2024 June 2024 June 2024 June 2024 June 2024 I

I TABLE6-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE COLLECTION LOCATIONS LOCATION SAMPLE NOTE DESIGNATION SITE SAMPLE TYPE (d)

(a)

LOCATION DESCRIPTION (c) 44 TLD OR OSLD (b)

Control ENE35 El Mirage TLDOROSLD SUP Transit 45 Control ONSITE Central lab, lead pig 46 TLD OR OSLD (b)

SP ENE30 Litchfield Park School 46 Water(b)

WD NNW8 Local residence 47 TLDOROSLD SUP E35 Littleton School 47 Vegetation (b)

N3 Local residence 48 TLDOROSLD SUP E24 Jackrabbit Trail 48 Water(b)

WD SWl Local residence 49 TLDOROSLD SUP ENEll Palo Verde Rd.

49 Water(b)

WD N2 Local residence 49 Milk(b)

N2 Local residence 49 Vegetation (b)

N2 Local residence 50 TLD OR OSLD (b)

OR WNW5 S of Buckeye-Salome Rd.

53 Milk (b)

Control NE30 Local residence (goats) 54 Milk (b)

NNE4 Local residence (goats) 55 Water WDSUP SW3 Local residence 57 Groundwater (b)

WG onsite Well 27ddc 58 Groundwater (b)

WG onsite Well 27dcb 59 Surface Water (b) ws onsite Evaporation Pond #lA 59 Surface Water (b) ws onsite Evaporation Pond #lB 59 Surface Water (b) ws onsite Evaporation Pond #lC 60 Surface Water (b) ws onsite 85 acre Water storage reservoir 61 Surface Water (b) ws onsite 45 acre Water storage reservoir 62 Vegetation (b)

Control ENE26 Commercial produce company 63 Surface Water (b) ws onsite Evaporation Pond #2A 63 Surface Water (b) ws onsite Evaporation Pond #2B 64 Surface Water (b) ws onsite Evaporation Pond #3A 64 Surface Water (b) ws onsite Evaporation Pond #3B 65 Groundwater (b)

WG onsite Well 24aab 75 ODCMRev. 32

June 2024 SAMPLE SITE 66 NOTES:

LOCATION NOTE DESIGNATION SAMPLE TYPE (d)

(a)

LOCATION DESCRIPTION (c)

Milk (b)

Control SE4 Local Residence (goats)

(a) Distance and direction are relative to the Unit 2 containment, rounded to the nearest mile.

(b) These samples fulfill the requirements of the ODCM, Table 6-1.

(c) Refer to Figure 6-1 and Figure 6-2 for relative locations of sample sites.

( d) IR - inner ring OR - outer ring SP - school or population center WS - waterborne surface WG - waterborne ground WD - waterborne drinking SUP -designated supplemental sampling location 76 ODCMRev. 32

June I 2024 V 1 2'61.U 9

8 7

-lf-'l.l,_C'(!!I KEY TO MAP Sample Site CD A Air V Ve~el:ation W Water T TLID M Milk School

Airs1riP f N

U,:,lill E

"~-.

"t)* ~

i OL.-lWW.li Figure 6-1 Radiological Envi ronrner:ita:I Mondori:ng Program Sample Si,tes 0 - 10 Mil.es r.

ODCMRev. 32

l___j:'. J_ ~

CACTUS RO NE SCOTT-LIBBY r'ii) \\

SCH~

~

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.... t.<:SRO ENiE

\\

1T

\\..441)\\ : L MIRAGE GOODY~R II

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-=;=-v w

~

"O ltl,.V\\

(47-f)I LITTLETON SCHOOL

\\

ffi:

~

ffi LIBERTY ~/

~ :

~

SCHOOL-'ji-

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=

,,J,,.,--::J.~ -!--

~E+-+-___:_~f-------~ ----=t:-=-::~~7t---'.a:ai.r BASELINE RO 1

a'.

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BASELINE RO BU KEYE ~

Q) r-DOSBINS RO LOWER ~VER RD I PAlO *

/VERDE O>

Q.

Olo HWY80 / SC~5 T

HASSAYAMPA>--__.2!a!~~;._-G~--t---------i

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,,,,,,SE 10 miles

I, 78

~ -

25 miles miles KEY TO MAP Sample Site CD A Air V Vegetation W Water T TLD M Milk School

Airstrip a::J

,' 35 miles Figure' 6-2 Radiological Environmental Monitoring Program Sample Sites 10 - 35 Miles miles ODCMRev. 32

Figure 6-3 Radiological Environmental Monitoring Program Sample Sites 35 - 75 Miles DELETED 79 ODCM Rev. 32

79 ODCM Rev. 32

Figure 6-4 Site Exclusion Area Boundary DELETED Refer to UFSAR Figure 2.1-4 80 ODCM Rev. 32

80 ODCM Rev. 32

Offsite Dose Calculation Manual I

Fuel Building Exhaust r 100**3" -,--1 24'-0" _ ~

CONT

~ ----::

EXHAUST POINTS KEY PLAN

~ - - - - *I Plant Vent/

Condenser Vacuum Combined Exhaust Auxiliary Building Elevation of Exhaust Point Above Grade Plant Vent/Condenser Vacuum 145' Fuel Building 109'-9" 81 Palo Verde Nuclear Generating Station Radwaste Building Figure 6-5 Gaseous Effluent Release Points ODCMRev. 32

Figure 6-6 Low Population Zone DELETED Refer to UFSAR Figure 2.1-15 82 ODCM Rev. 32

RADIOLOGICAL REPORTS

7.1 Requirement

Annual Radioactive Effluent Release Report Routine Annual Radioactive Eflluent Release Reports covering the operation of the units during the previous calendar year shall be submitted in accordance with Technical Specification 5.6.3.

The Annual Radioactive Eflluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous eftluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Eflluents 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 Annual 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 on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), 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 6-4) 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 methodology and parameters in the ODCM.

The Annual 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 calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contributions are given Section 5.0 and Regulatory Guide 1.109 Rev. 1, October 1977.

The Annual Radioactive Effluent Release Report shall also include information required by the Technical Requirements Manual, Section 5.0.600.1.

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.

- In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

83 ODCM Rev. 32

The Annual Radioactive Effluent Release Reports shall include the following information for each class of solid waste ( as defined by 10 CFR Part 61) 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.

Source of waste and processing employed ( e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e.

Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f.

Solidification agent or absorbent (e.g., cement, urea formaldehyde).

The Annual Radioactive Effluent Release Reports sha11 include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

Changes to the ODCM shall be submitted in the form of a complete, legible copy as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Changes made to the Process Control Program shall be submitted with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the Process Control Program was made.

84 ODCM Rev. 32

7.2 Requirement: Annual Radiological Environmental Operating Report Routine Annual Radiological Environmental Operating Reports covering the operation of the units during the previous calendar year shall be submitted by May 15 of each year in accordance with Technical Specification 5.6.2.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with 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 6.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 6-4 and Figure 6-1 and Figure 6-2 as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps** covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Section 6.3; discussion of all deviations from the sampling schedule of Table 6-1; and discussion of all analyses in which the LLD required by Table 6-3 was not achievable.

A single submittal may be made for a multiple unit station.

One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

85 ODCM Rev. 32

APPENDIX A DETERMINATION OF CONTROLLING LOCATION The controlling location is the location of the MEMBER OF THE PUBLIC who receives the highest doses.

The determination of a controlling location for implementation of 10CFR50 for radioiodines and particulates is known to be a function of:

(1) Isotopic release rates (2) Meteorology (3) Exposure pathway (4) Receptor's age The incorporation of these parameters into Equation 5-2 results in the respective equations at the controlling location. The isotopic release rates are based upon the source terms calculated using the PVNGS Environmental Report, Operating License Stage, Table 3.5-12, without carbon.

All of the locations and exposure pathways, identified in the 1984 Land Use Census, have been evaluated. These include cow milk ingestion, goat milk ingestion, vegetable ingestion, inhalation, and ground plane exposure. An infant is assumed to be present at all milk pathway locations. A child is assumed to be present at all vegetable garden locations. The ground plane exposure pathway is only considered to be present where an infant is not present. Naturally, inhalation is present everywhere an individual is present.

For the determination of the controlling locations, the highest X/Q and D/Q values, based on the 9 year meteorological data base, for the vegetable garden, cow milk, and goat milk pathways, are selected for each unit. The receptor organ doses have been calculated at each of these locations. Based upon these calculations, it is determined that the controlling receptor pathway is a function of unit location. For Unit 1, the controlling receptor is a garden-child pathway; for releases from Unit 2 and Unit 3 the controlling receptor is a cow milk-infant pathway. These determinations are based upon Table 4-16, 4-17, or 4-18, which, in turn, is based upon the 1984 Land Use Census. Locations of the nearest residences, gardens and milk animals, as determined in the 1984 Land Use Census, are given in Table 4-16, 4-17, and 4-18.

86 ODCM Rev. 32

APPENDIXB BASES FOR REQUIREMENTS B-2.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 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 and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, 64 of Appendix A to 10 CFR PART50.

There are two separate radioactive gaseous effluent monitoring systems: the low range effluent monitors for normal plant radioactive gaseous effluents and the high range effluent monitors for post-accident plant radioactive gaseous effluents. The low range monitors operate at all times until the concentration of radioactivity in the effluent becomes too high during post-accident conditions. The high range monitors only operate when the concentration of radioactivity in the effluent is above the setpoint in the low range monitors.

B-3.1 GASEOUS EFFLUENT - DOSE RATE This requirement provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY, in excess of the design objectives of Appendix I to 10 CFR part 50. This requirement is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II.C design objectives of Appendix I to 10 CFR part 50. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the total body or to less than or equal to 3000 mrems/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 mrems/year. This requirement does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).

This requirement applies to the release of radioactive materials in gaseous effluents from all reactor units at the site.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLD). Detailed discussion of the LLD and other detection limits can be found in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually).

87 ODCM Rev. 32

B-3.2 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS-CONCENTRATION This requirement is provided to ensure that the annual total effective dose equivalent to individual members of the public from the licensed operation does not exceed the requirements of 10 CFR Part 20, due to the accumulated activity in the evaporation ponds from the secondary system discharges.

Restricting the concentrations of the secondary liquid wastes discharged to the onsite evaporation ponds will restrict the quantity of radioactive material that can accumulate in the ponds. This, in turn, provides assurance that in the event of an uncontrolled release of the pond's contents to an UNRESTRICTED AREA, the resulting total effective dose equivalent to individual members of the public at the nearest exclusion area boundary will not exceed the requirements of 10 CFR Part 20.

This requirement applies to the secondary system liquid waste discharges of radioactive materials from all reactor units to the onsite evaporation ponds.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLD). Detailed discussion of the LLD and other detection limits can be found in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually).

B-4.1 GASEOUS EFFLUENT - DOSE, Noble Gases This requirement is provided to implement Sections 11.B, III.A and IV.A of Appendix I, 10 CFR Part 50. This requirement 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 that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.

88 ODCM Rev. 32

B-4.2 GASEOUS EFFLUENT - DOSE - lodine-131, lodine-133, Tritium, and All Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days This requirement is provided to implement the requirements of Sections 11.C, III.A, IV.A of Appendix I, 10 CFR Part 50. This requirement is the guide set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases for Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that 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.

This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.

B-4.3 GASEOUS RADWASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.Band II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

This requirement applies to the release of radioactive materials in gaseous effluents from each reactor unit at the site.

The minimum analysis frequency of 4/M (i.e., at least 4 times per month at intervals no greater than 9 days and a minimum of 48 times a year) is used for certain radioactive gaseous waste sampling in Table 3-1. This will eliminate taking double samples when quarterly and weekly samples are required at the same time.

89 ODCM Rev. 32

B-4.4 SECONDARY SYSTEM LIQUID WASTE DISCHARGE TO ONSITE EVAPORATION PONDS-DOSE This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. This requirement 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 to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

This requirement 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.

B-5.1 TOTAL DOSE AND DOSE TO PUBLIC ONSITE This requirement is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR 20.130l(d). The requirement specifies the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. Even if a site was to contain up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units (including outside storage tanks, etc.) are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 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 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, submittal of the Special Report within 30 days with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.

The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to other requirements for dose limitation of 10 CFR Part 20, as addressed in Section 3.2 and 3.1 of the ODCM.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. Demonstration of compliance with the limits of 40 CFR Part 190 or with the design objectives of Appendix I to 10 CFR Part 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.

90 ODCM Rev. 32

B-6.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

The Radiological Environmental Monitoring Program required by this requirement provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLDs required by Table 6-3 are considered optimum 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 an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD and other detection limits can be found in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984), and in the HASL Procedures Manual, HASL-300 (revised annually).

B-6.2 LAND USE CENSUS This requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from 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 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of2 kg/m2.

B-6.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

91 ODCM Rev. 32

Note:

APPENDIXC DEFINITIONS The following defmitions were derived from the Palo Verde Nuclear Generating Station Technical Specifications. These selected definitions support those portions of the Technical Specifications which were transferred to the ODCM and have been incorporated into the Requirements sections of the ODCM.

Defmitions:

The defmed terms of this section appear in capitalized type and are applicable throughout the Requirements sections of this ODCM.

ACTION ACTION shall be that part of a requirement which prescribes remedial measures required under designated conditions.

CHANNEL CALIBRATION See the Technical Specification defmition.

CHANNEL CHECK See the Technical Specification defmition.

CHANNEL FUNCTIONAL TEST See the Technical Specification defmition.

DOSE EQUIVALENT 1-131 See the Technical Specification defmition.

FUNCTIONAL-FUNCTIONALITY Functionality is an attribute of a structure, system, or component SSC(s) that is not controlled by the Technical Specifications (TSs ). An SSC not controlled by TSs is functional or has functionality when it is capable of performing its function(s) as set forth in the current licensing basis (CLB). These CLB function(s) may include the capability to perform a necessary and related support function for an SSC(s) controlled by TSs.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defmed in Table C-1.

GASEOUS RADWASTE SYSTEM A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

92 ODCM Rev. 32

APPENDIXC DEFINITIONS (Continued)

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC means any individual except when that individual is receiving occupational dose. This shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OCCUPATIONAL DOSE OCCUPATIONAL dose means the dose received by an individual in the course of employment in which the individuals assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 10CFR35.75, from voluntary participation in medical research programs, or as a member of the public.

OPERABLE-OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or 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).

MODE See the Technical Specification definition.

PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

PURGE-PURGING PURGE or PURGING shall be 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.

RATED THERMAL POWER See the Technical Specification definition.

SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

93 ODCM Rev. 32

SOLIDIFICATION 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).

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNRESTRICTED AREA An UNRESTRICTED AREA sha11 be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING VENTING shall be 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.

94 ODCM Rev. 32

NOTATION s

D w

4/M M

Q SA ANNUALLY R

p SIU N.A.

TABLEC-1 FREQUENCY NOTATION FREQUENCY*

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

At least once per 7 days.

At least 4 times per month at intervals no greater than 9 days and a minimum of 48 times per year.

At least once per 31 days.

At least once per 92 days.

At least once per 184 days.

At least once per 365 days At least once per 18 months.

Completed prior to each release.

Prior to reactor startup.

Not Applicable.

The specified Frequency for each Surveillance Requirement and Sampling Requirement is met if the Surveillance Requirement or Sampling Requirement 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.

95 ODCM Rev. 32

APPENDIXD REFERENCES 1

Title 10, Code of Federal Regulations, Part 20, "Standards for Protection Against Radiation."

2 Title 10, Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities."

3 Title 40, Code of Federal Regulations, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations."

4 Federal Register, Vol. 58, No. 245, Thursday, December 23, 1993, Notices, pages 68170-68179.

5 Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974.

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

7 Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.

8 Regulatory Guide 4.1, "Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.

9 NUREG-0133, Preparation of Radiological Effluent Technical Specifications For Nuclear Power Plants, Oct. 1978.

10 NUREG 0841, "Final Environmental Statement Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3", Section 5.9.1.4, February, 1982.

11 NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactor", April 1991.

12 Environmental Report Operating License Stage, Palo Verde Nuclear Generating Station, December 1981.

13 PVNGS Updated Final Safety Analysis Report 14 Calculation 13-NC-ZY-252, "Annual Average Dose from Normal Operation Liquid Discharge from the Evaporation Pond", Rev 0.

15 Calculation 13-NC-ZY-253, "Annual Average Dose from Normal Operation Airborne Direct and Sky Shine from the Evaporation Pond", Rev 0.

16 Calculation 13-NC-ZY-254, "Radiation Dose Due to an Evaporation Pond Dike Failure During a Seismic Event", Rev. 0.

96 ODCM Rev. 32

ML25115A201

Contents

Text

Subject:

Enclosure:

1.0 INTRODUCTION

2.1 Requirements

3.1 Requirements

3.2 Requirements

4.1 Requirements

4.2 Requirement

4.3 Requirements

4.4 Requirements

5.1 Requirement

6.1 Requirement

6.2 Requirement

6.3 Requirement

1.0 INTRODUCTION

2.1 Requirements

3.1 Requirements

Reference:

Reference:

3.2 Requirements

4.2 Requirements

4.2 Requirement

4.3 Requirements

References:

References:

References:

4.4 Requirements

5.1 Requirement

6.1 Requirement

6.2 Requirement

6.3 Requirement

7.1 Requirement

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ML25115A201

Text

Subject:

Enclosure:

1.0 INTRODUCTION

2.1 Requirements

3.1 Requirements

3.2 Requirements

4.1 Requirements

4.2 Requirement

4.3 Requirements

4.4 Requirements

5.1 Requirement

6.1 Requirement

6.2 Requirement

6.3 Requirement

1.0 INTRODUCTION

2.1 Requirements

3.1 Requirements

Reference:

Reference:

3.2 Requirements

4.2 Requirements

4.2 Requirement

4.3 Requirements

References:

References:

References:

4.4 Requirements

5.1 Requirement

6.1 Requirement

6.2 Requirement

6.3 Requirement

7.1 Requirement

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