Text

2021 Annual Radioactive Effluent Release Report
	ML22108A222
Person / Time
Site:	Columbia
Issue date:	04/15/2022
From:	David Brown; Energy Northwest
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GO2-22-048
	Download: ML22108A222 (280)
	v • d • e

ENERGY David P. Brown Columbia Generating Station NORTHWEST P.O. Box 968, PE23 Richland, WA 99352-0968 Ph. 509-377-8385 l F. 509-377-4150 dpbrown@energy-northwest.com April 15, 2022 GO2-22-048 10 CFR 50.36a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 2021 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

Dear Sir or Madam:

In accordance with 10 CFR 50.36a(a)(2) and Columbia Generating Station (CGS)

Technical Specification 5.6.2, the Annual Radioactive Effluent Release Report is hereby submitted as Enclosure 1 to this letter. The report includes a summary of the quantities of radioactive liquid and gaseous effluents, and solid waste released from CGS during the reporting period.

A complete copy of the CGS Offsite Dose Calculation Manual is also enclosed with this submittal as required by Technical Specification 5.5.1 (Enclosure 2). This copy includes revisions made to the document since the last submittal.

There are no commitments being made to the U.S. Nuclear Regulatory Commission herein. If you have any questions, or require additional information, please contact Ms. D.M. Wolfgramm, Regulatory Affairs Manager, at (509) 377-4792.

Executed on the _____ day of ____________,

2022.

Respectfully, David P. Brown Site Vice President

GO2-22-048 Page 2 of 2 Enclosure 1: Columbia Generating Station Annual Radioactive Effluent Release Report, January through December 2021 Enclosure 2: Energy Northwest - Columbia Generating Station - Offsite Dose Calculation Manual cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector CD Sonoda - BPA/1399 (w/o enclosures)

J. Martell - WA DOH L. Albin - WA DOH E. Fordham - WA DOH J. Brice - WA DOH S. Snyder - PNNL (w/o Enclosure 2)

C. Stewart - ANI (w/o Enclosure 2)

EFSEC (w/o Enclosure 2)

GO2-22-048 Enclosure 1 Columbia Generating Station Annual Radioactive Effluent Release Report January through December 2021

REFERENCES:

10 CFR 50.36a(a)(2) 10 CFR 72.44(d)(3)

CGS Technical Specification 5.6.2 Columbia Generating Station Annual Radioactive Effluent Release Report January through December 2021 Energy Northwest Submitted April 2022

Table of Contents

1.0 INTRODUCTION

......................................................................................... 1 2.0 LIQUID EFFLUENTS................................................................................... 1 3.0 GASEOUS EFFLUENTS ............................................................................. 1 Routine Releases ............................................................................................. 1 Non-significant, DeMinimis Fugitive, and Diffuse Effluent Sources ........... 3 Table 3a - Non-significant Effluent Releases (Ci)........................................... 3 Abnormal Releases.......................................................................................... 3 Carbon-14 ......................................................................................................... 4 Table 3b - Carbon-14 Releases ...................................................................... 5 Out-of-Service Effluent Monitors .................................................................... 5 Missed Gaseous Effluent Samples................................................................. 5 Refueling Outage R25...................................................................................... 6 Maintenance Outage MO-02 ............................................................................ 6 Gaseous Effluent Tables ................................................................................. 7 Table 3-0 10 CFR Part 50 Appendix I Dose Compliance.............................. 7 Table 3-1 Main Plant Vent Releases - Mixed Mode ..................................... 8 Table 3-2 Turbine Building Releases - Mixed Mode .................................. 10 Table 3-3 Radwaste Building Releases - Ground Mode ............................ 12 Table 3-4 Summation of Releases ............................................................. 14 Table 3-5 Gaseous Purges and Vents ........................................................ 15 Table 3-6 Lower Limits of Detection ........................................................... 16 4.0 SOLID RADWASTE .................................................................................. 17 5.0 METEOROLOGICAL DATA ...................................................................... 26 Joint Frequency Distribution Tables for 2021 ............................................. 27 Table 5-1 1st Quarter Average, 33 Ft Above Ground Level (AGL) ............. 27 Table 5-2 2nd Quarter Average, 33 Ft AGL ................................................ 29 Table 5-3 3rd Quarter Average, 33 Ft AGL................................................. 31 Table 5-4 4th Quarter Average, 33 Ft AGL ................................................. 33 Table 5-5 Year 2021, 33 Ft AGL................................................................. 35 Columbia Generating Station i 2021 Radioactive Effluent Report

6.0 DOSE ASSESSMENT -- IMPACT ON MAN.............................................. 37 Dose to Onsite Members of the Public ........................................................ 37 Table 6.0; Dose to Members of the Public within the Site Boundary............. 38 Dose to Offsite Members of the Public ........................................................ 38 Table 6-5 Summary of Doses from Gaseous Effluents ............................... 39 Table 6-6 50-Mile Population Dose from Gaseous Effluents ...................... 40 7.0 REVISIONS TO THE ODCM ..................................................................... 41 8.0 REVISIONS TO THE PROCESS CONTROL PROGRAM (PCP) .............. 41 9.0 NEW OR DELETED LOCATIONS FOR DOSE ASSESSMENTS AND/OR ENVIRONMENTAL MONITORING LOCATIONS ............................... 41 10.0 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS .......................................................... 41 11.0 ERRATA ................................................................................................. 41 Columbia Generating Station ii 2021 Radioactive Effluent Report

1.0 Introduction This report has been prepared in compliance with Part 50 of Title 10 of the Code of Federal Regulations (CFR), specifically 10 CFR 50.36a(a)(2), and Columbia Generating Station (CGS) Technical Specification 5.6.2. It includes a summary of the quantities of radioactive liquid and gaseous effluents and solid radioactive waste released from CGS during calendar year 2021. Effluent data is summarized on a quarterly and annual basis.

Throughout this report, units of activity and dose are as defined in 10 CFR 20.1004, 20.1005, and Nuclear Regulatory Commission (NRC) Regulatory Guide 1.109-1977.

The United States National Council on Radiation Protection published in 2009 which can serve to put radiation dose into perspective for the reader of this report. It was determined that the average yearly dose to a person living in the United States is 620 mrem from all sources. Of this, ~50% is attributed to natural sources (radiation from gaseous radon, cosmic or space radiation, natural radioactive material in the ground, and natural radioactive materials in our bodies). About 48% is attributed to diagnostic and therapeutic medical exposure. Radiation dose from nuclear power was grouped into a category comprising <0.1% of the total.

2.0 Liquid Effluents No planned releases of contaminated liquids from the liquid radwaste processing system were discharged to the Columbia River from CGS during calendar year 2021.

The last discharge to the river from liquid processing took place in 1998.

According to ground water monitoring, reporting on any spills of greater than 100 gallons, and the leak detection system of the lined evaporation ponds that contain radioactive material, there is no indication of a leak or spill of radioactive liquids to ground water in 2021.

3.0 Gaseous Effluents Routine Releases Gaseous effluents from CGS are released from three (3) principal release points:

Main Plant Vent -- mixed mode release Turbine Building - mixed mode release Radwaste Building -- ground level release The gaseous source terms from each release point are listed in Tables 3-1, 3-2, and 3-

3. The activation gas argon-41 is included in these tables under fission gases to allow a match with the fission and activation gas totals of Table 3-4. Table 3-4 provides a summation of the total activity released, the average release rate, gross alpha Columbia Generating Station 1 2021 Radioactive Effluent Report

radioactivity, and the estimated total error associated with the measurements of radioactivity in the gaseous effluents.

Radioactivity measurements for gaseous effluent releases are performed for fission and activation gases by collecting the samples in a Marinelli beaker and analyzing them using gamma spectroscopy. Air is analyzed for tritium by collection of water vapor on a desiccant with subsequent distillation and liquid scintillation counting. Particulates and iodines are sampled continuously and the sample media (particulate filters and charcoal cartridges) are analyzed weekly using gamma spectroscopy. Each quarter the composite particulate filters are sent to an offsite laboratory for strontium analysis and quantification is accomplished with liquid scintillation detection. The average energy per disintegration of fission and activation gases is not included in this report as it is not required by Technical Specifications and is not used for gaseous effluent release rate limit calculations.

When a radionuclide is not positively identified at levels greater than the Minimum Detectable Activity (MDA) or Minimum Detectable Concentration (MDC), a value of zero is used for release concentrations and offsite dose assessments. The MDA is an a posteriori value that is determined during analysis of a sample. Table 3-6 contains the Lower Limit of Detection (LLD - which is an a priori value determined before a sample is analyzed) values corresponding to the sampling methods and analytical instruments used for each principal radionuclide. Carbon-14 (C-14 or C-14) releases are calculated using an Electric Power Research Institute (EPRI) methodology that is discussed in more detail later in this chapter.

Dose calculations were performed for releases using the NRC XOQDOQ and NRC Regulatory Guide 1.109 methodology, and parameter values as described in the Offsite Dose Calculation Manual (ODCM). This methodology was based on Publication 2 of the International Commission on Radiation Protection released in 1959.

Quarterly and annual doses to the potentially highest-exposed Member of the Public (MOP) at and beyond the site boundary were calculated. In addition, quarterly and annual doses were calculated at actual resident locations identified in the annual land use census. ODCM limits are based on 10 CFR 20 and Appendix I to 10 CFR 50. The threshold for air dose applies to fission and activation gases and is ten (10) mrad for beta and five (5) mrad for gamma quarterly and twenty (20) mrad for beta and ten (10) mrad for gamma annually. The threshold for organ dose applies to iodine, tritium, and particulates with half-lives greater than eight days and is seven and a half (7.5) mrem quarterly and fifteen (15) mrem annually.

The ODCM includes another set of release rate limits to provide operational flexibility and assurance that radioactive material discharged in gaseous effluents will not result in exposure to a MOP in excess of the design objectives of Appendix I to 10 CFR 50. For fission and activation gases the dose rate limits are less than or equal to 500 mrem per year to the whole body and less than or equal to 3000 mrem per year to the skin. For iodines, particulates, and for tritium, the dose rate limit is less than or equal to 1500 mrem/year to any organ.

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Dose calculations were also conducted for MOP within the site boundary. The results are discussed and tabulated in Section 6.0.

Non-significant, DeMinimis Fugitive, and Diffuse Effluent Sources There are release points around CGS that have been identified as unmonitored and evaluated for significance. These release points include;

Condensate Storage Tanks (CSTs)

Lined Evaporation Ponds

Cooling System Sediment Disposal Cell The evaluation of these sources was completed by either verifying the assumptions of previous bounding calculations, or by evaluating activity released based on sample data. Table 3a below shows the calculated radionuclide effluents releases from these sources for the year 2021. These radionuclide effluents were considered ground level releases, and were added to the annual effluent release totals for dose calculation purposes in section 6 of this report.

In order to show compliance with the EFSEC Order 874 limit of 9.51E-02 mrem/year to a Maximally Exposed Individual (real or hypothetical as defined in WAC 246-247-030) due to operation of the Evaporation Ponds, the dose from these Non-significant, DeMinimis Fugitive, and Diffuse Effluent sources were calculated using ODCM methodology. A maximum organ dose of 4.47E-06 mrem was determined from these sources for a hypothetical resident at the site boundary of Columba Generating Station.

Table 3a - Non-significant Effluent Releases (Ci)

H-3 Co-60 Cs-137 CSTs 6.00E-02 N/A N/A Evaporation Ponds 2.94E-02 < MDA < MDA Sediment Disposal Cell N/A < MDA 3.40E-08 Total 8.94E-02 < MDA 3.40E-08 Abnormal Releases There was an abnormal release of turbine building air from a tear in the turbine building roof material identified on 11/17/2021. The tear was approximately 25-30 feet long, and after initial repair, it was identified that air was escaping from the turbine building roof, causing the roofing material to bubble. An estimated flow rate of 650 cubic feet per minute was assigned to this leak, based on the growth rate of the bubbling roofing material: an area of approximately 13,000 square feet of roofing material swelled to a height of approximately 3 feet over the course of one hour.

The overall pressure of the turbine building was confirmed to be negative with respect to the outside atmospheric pressure during this time period, so the driving force of this air is believed to be hot air coming from the turbine, which created a local high-pressure gradient in the ceiling above the turbine deck. The abnormal release is being considered for effluent calculations to have persisted from discovery until reactor scram Columbia Generating Station 3 2021 Radioactive Effluent Report

for the December maintenance outage on 12/6/21 01:24, whereupon the driving force of the escaping air (heat) would have been removed. During the December maintenance outage, further repairs were made to the turbine building roof and no evidence of leakage was observed following startup.

Based on the release duration and flow rate estimations above, as well as turbine building effluent air sampling data taken during this period, the following radionuclide activities are estimated to have been released through this pathway: 1.70E-03 Ci of H-3, and 5.66E-09 Ci of Co-60. This abnormal emission represents 3.98E-04% of the total particulate effluents and 8.57E-03% of the total tritium effluents for CGS in 2021, as reported in Table 3-4 of this report. The estimated activity from this abnormal release was included with the normal turbine building effluents for total release inventory and dose calculation purposes.

Carbon-14 C-14, with a half-life of 5,730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. When C-14 decays it emits a beta particle of varying energies up to 0.156 MeV with an average energy of 0.049 MeV. As a result of this low energy, the air and inhalation doses are insignificant. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.

Although 10 CFR 50.36a has always required reporting the principal nuclides released, C-14 had been exempted because of the large quantity that existed naturally in the environment. However, following release of Revision 2 of Regulatory Guide 1.21 (Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste), the NRC recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released.

A radionuclide is considered a principal radionuclide if it contributes either (1) greater than 1 percent of the 10 CFR Part 50, Appendix I, design objective dose, or (2) greater than 1 percent of the activity of all radionuclides in the type of effluent being considered.

This implementation of primary radionuclides ensures both (1) radionuclides that are present in relatively large amounts but that contribute very little to dose, and (2) radionuclides that are present in very small amounts but that have a relatively high contribution to dose, are appropriately included in the annual effluent report.

At CGS, improvements over the years have resulted in a significant decrease in radioactive gaseous emissions. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at CGS. The quantity of gaseous C-14 released to the environment is estimated using a C-14 source term scaling factor based on EPRI Technical Report 1021106 and power generation. The EPRI report estimates the production of C-14 at approximately 5 Ci/GWth - yr for a plant like CGS. This would result in a potential release of 18.1 Ci/yr based on the rated power for CGS. The EPRI Columbia Generating Station 4 2021 Radioactive Effluent Report

report also describes the chemical form of the C-14 released as being 95% Carbon Dioxide, which could be incorporated into growing plants during photosynthesis. The remainder is assumed to be methane (CH4).

Table 3b contains estimates of C-14 radioactivity released in 2021. Based on 95%

Carbon Dioxide, and assuming that all C-14 generated is released in gaseous effluent, then the total C-14 emission shown in Table 3b is 1.45E+01 Ci. Note that the reduced C-14 production in the 2nd and 4th quarters are a result of reactor shutdowns for refueling outage R25 and maintenance outage MO-02, respectively. Estimates of public dose resulting from the C-14 effluent are included in the doses reported in Section 6 of this report.

Table 3b - Carbon-14 Releases GWth-hrs Ci of 14C Ci of 14CO2 1st quarter 7,581 4.41E+00 4.19E+00 2nd Quarter 3,784 2.20E+00 2.09E+00 3rd Quarter 7,782 4.53E+00 4.30E+00 4th Quarter 7,098 4.13E+00 3.93E+00 Total Year 2021 26,245 1.53E+01 1.45E+01 Out-of-Service Effluent Monitors There were no effluent monitors out of service for greater than 30 days in 2021.

Missed Gaseous Effluent Samples The turbine building effluent air sample rack, TEA-SR-26, was discovered non-functional on the morning of 6/20/21 at approximately 09:00 due to a high vacuum trip of fan TEA-FN-93. Following this discovery, at 09:16 AM on 6/20/21, action statements and compensatory actions were entered per ODCM requirements. While troubleshooting the cause of the TEA-SR-26 failure, it was determined from the control room recorder PRM-RR-3 that TEA-SR-26 had failed on 06/19/21 at 16:15 and had therefore been non-functional for approximately 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months before discovery, before any action statement was entered, or compensatory sampling was begun.

During this 17-hour period of non-functionality, the following gaseous effluent samples were missed:

Two compensatory noble gas grab samples. Per ODCM 6.1.2.1.C.1, a compensatory noble gas grab sample is required within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and once per every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after).

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17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months of continuous particulate and iodide sampling. Per ODCM 6.1.2.1.E.1.1 auxiliary particulate and iodine sampling is required to be re-established within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and then continuously thereafter.

Due to the failure to conduct ODCM compensatory 6.1.2.1.E.1.1 within the required four hours, ODCM compensatory measure 6.1.2.1.E.1.2 was implemented, which is to collect relevant information to provide an estimate of effluent releases from the turbine building during the 17-hour period that the turbine building exhaust air was unmonitored.

This event was captured in condition reports 00422189 and 00422253.

Refueling Outage R25 Columbia Generating Station performed its 25th refueling outage, R25, between the dates of 5/8/21 and 6/17/21. Due to the prolonged shut down, offsite doses during quarter 2 of 2021 are significantly lower than in quarters 1, 3, or 4. Due to Spent fuel movements and maintenance associated with the refueling outage, additional radionuclide particulates not routinely detected in plant effluents were observed during the second quarter of 2021. Work during the refueling outage to minimize condenser air in leakage resulted in a significant decreases in Ar-41 production following the maintenance outage.

Maintenance Outage MO-02 Columbia Generating Station performed its 2nd maintenance outage, MO-02, between 12/6/21 and 12/12/21. The impact of this short duration outage on plant effluents and offsite dose was significantly less pronounced than that of the refueling outage due to the shorter time window and smaller work scope.

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Gaseous Effluent Tables Table 3-0 10 CFR Part 50 Appendix I Dose Compliance Report Period: January - December 2021 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Year*

Noble Gas Gamma Air Dose (mrad) 8.24E-03 4.57E-03 3.63E-03 2.90E-03 1.93E-02 ODCM Limit 5 5 5 5 10

% of Limit 1.65E-01 9.14E-02 7.26E-02 5.80E-02 1.93E-01 Beta Air Dose (mrad) 2.91E-03 1.61E-03 1.28E-03 1.02E-03 6.82E-03 ODCM Limit 10 10 10 10 20

% of Limit 2.91E-02 1.61E-02 1.28E-02 1.02E-02 3.41E-02 Iodine-131, Iodine-133, Tritium, and Particulates with half-lives greater than eight days.

Organ Dose (mrem) 4.37E-02 2.22E-02 4.42E-02 4.03E-02 1.50E-01 ODCM Limit 7.5 7.5 7.5 7.5 15

% of Limit 5.83E-01 2.96E-01 5.89E-01 5.37E-01 1.00E+00

Calculated quarterly doses cannot necessarily be directly compared to the annual doses. Each above listed quarterly dose is the highest calculated dose based on a number of variables. Variables that make comparison difficult include location, receptor age, target organ, and characteristics of the emitted radionuclides.

This table shows the highest air dose and organ dose for either a hypothetical resident at the site boundary or an actual resident within a 5-mile radius.

The pathways of exposure considered at the site boundary are the plume exposure, ground exposure, and inhalation pathways only. The potentially highest-exposed MOP from all gaseous effluent releases (including C-14) for 2021, was for a child resident at 4.79 miles ESE. The highest organ dose for the plume exposure, ground exposure, garden produce ingestion, and inhalation pathways at this location was 1.50E-01 mrem to the bone, which is 1.00 % of the 15 mrem 10 CFR 50 Appendix I guideline. This location and assumed exposure pathways were based on the 2021 Land Use Census.

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Table 3-1 Main Plant Vent Releases - Mixed Mode Fission Gases and Iodines Report Period: January - December 2021 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Year Nuclides Released (Ci) (Ci) (Ci) (Ci) (Ci)

A. Fission gases krypton-85 <MDA <MDA <MDA <MDA <MDA krypton-85m <MDA <MDA <MDA <MDA <MDA krypton-87 <MDA <MDA <MDA <MDA <MDA krypton-88 <MDA <MDA <MDA <MDA <MDA xenon-133 <MDA <MDA <MDA <MDA <MDA xenon-133m <MDA <MDA <MDA <MDA <MDA xenon-135 <MDA <MDA <MDA <MDA <MDA xenon-135m <MDA <MDA <MDA <MDA <MDA xenon-138 <MDA <MDA <MDA <MDA <MDA Others <MDA <MDA <MDA <MDA <MDA argon-41 3.08E+01 1.70E+01 1.36E+01 1.08E+01 7.21E+01 Total for period

3.08E+01 1.70E+01 1.36E+01 1.08E+01 7.21+01 B. Iodines iodine-131 < MDA 4.37E-06 <MDA 4.73E-06 9.10E-06 iodine-132 <MDA <MDA <MDA <MDA <MDA iodine-133 <MDA <MDA <MDA <MDA <MDA iodine-134 <MDA <MDA <MDA <MDA <MDA iodine-135 <MDA <MDA <MDA <MDA <MDA Total for period * <MDA 4.37E-06 <MDA 4.73E-06 9.10E-06

MDA values are not included in the totals. MDA = Less than the a posteriori minimal detectable activity (microcuries per unit mass or volume).

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Table 3-1 Main Plant Vent Releases - Mixed Mode (Continued)

Particulates and Tritium Report Period: January - December 2021 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Year Nuclides Released (Ci) (Ci) (Ci) (Ci) (Ci)

C. Particulates strontium-89 <MDA <MDA <MDA <MDA <MDA strontium-90 <MDA <MDA <MDA <MDA <MDA cesium-134 <MDA <MDA <MDA <MDA <MDA cesium-137 <MDA <MDA <MDA <MDA <MDA barium-lanthanum-140 <MDA <MDA <MDA <MDA <MDA silver-110m <MDA 3.87E-05 <MDA <MDA 3.87E-05 cerium-141 <MDA <MDA <MDA <MDA <MDA cerium-144 <MDA <MDA <MDA <MDA <MDA cobalt-58 <MDA 6.87E-05 1.87E-06 1.56E-06 7.21E-05 cobalt-60 1.19E-05 8.32E-04 7.46E-05 5.99E-05 9.78E-04 iron-59 <MDA 4.91E-06 <MDA <MDA 4.91E-06 manganese-54 <MDA 5.26E-05 4.41E-06 2.95E-06 6.00E-05 zinc-65 <MDA <MDA <MDA <MDA <MDA chromium-51 <MDA 1.27E-04 <MDA <MDA 1.27E-04 antimony-125 <MDA <MDA <MDA <MDA <MDA Bromine-82 <MDA <MDA 6.45E-06 <MDA 6.45E-06 Total for period* 1.19E-05 1.12E-03 8.73E-05 6.44E-05 1.28E-03 D. Tritium tritium 5.75E-01 6.10E-01 5.82E-01 3.85E-01 2.15E+00

MDA values are not included in the totals. MDA = Less than the a posteriori minimal detectable activity (microcuries per unit mass or volume).

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Table 3-2 Turbine Building Releases - Mixed Mode Fission Gases and Iodines Report Period: January -- December 2021 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Year Nuclides Released (Ci) (Ci) (Ci) I (Ci) I (Ci)

A. Fission gases krypton-85 <MDA <MDA <MDA <MDA <MDA krypton-85m <MDA <MDA <MDA <MDA <MDA krypton-87 <MDA <MDA <MDA <MDA <MDA krypton-88 <MDA <MDA <MDA <MDA <MDA xenon-133 <MDA <MDA <MDA <MDA <MDA xenon-133m <MDA <MDA <MDA <MDA <MDA xenon-135 <MDA <MDA <MDA <MDA <MDA xenon-135m <MDA <MDA <MDA <MDA <MDA xenon-138 <MDA <MDA <MDA <MDA <MDA Others <MDA <MDA <MDA <MDA <MDA argon-41 <MDA <MDA <MDA <MDA <MDA Total for period * <MDA <MDA <MDA <MDA <MDA B. Iodines iodine-131 1.33E-05 4.11E-05 4.18E-06 <MDA 5.86E-05 iodine-132 <MDA <MDA <MDA <MDA <MDA iodine-133 5.72E-05 4.38E-05 <MDA <MDA 1.01E-04 iodine-134 <MDA <MDA <MDA <MDA <MDA iodine-135 <MDA <MDA <MDA <MDA <MDA Total for period

7.05E-05 8.49E-05 4.18E-06 <MDA 1.60E-04

MDA values are not included in the totals. MDA = Less than the a posteriori minimal detectable activity (microcuries per unit mass or volume).

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Table 3-2 Turbine Building Releases - Mixed Mode (Continued)

Particulates and Tritium Report Period: January -- December 2021 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Year Nuclides Released (Ci) (Ci) (Ci) (Ci) (Ci)

C. Particulates strontium-89 <MDA <MDA <MDA <MDA <MDA strontium-90 <MDA <MDA <MDA <MDA <MDA cesium-134 <MDA <MDA <MDA <MDA <MDA cesium-137 <MDA <MDA <MDA <MDA <MDA barium-lanthanum-140 <MDA <MDA <MDA <MDA <MDA cerium-141 <MDA <MDA <MDA <MDA <MDA cerium-144 <MDA <MDA <MDA <MDA <MDA cobalt-58 <MDA <MDA <MDA <MDA <MDA cobalt-60 4.53E-05 2.65E-05 2.23E-05 1.14E-05 1.06E-04 iron-59 <MDA <MDA <MDA <MDA <MDA manganese-54 <MDA <MDA <MDA <MDA <MDA zinc-65 <MDA <MDA <MDA <MDA <MDA Technetium-99 2.53E-05 <MDA <MDA <MDA 2.53E-05 chromium-51 <MDA <MDA <MDA <MDA <MDA Total for period* 7.06E-05 2.65E-05 2.23E-05 1.14E-05 1.313E-04 D. Tritium tritium 4.23E+00 4.06E+00 4.26E+00 3.36E+00 1.59+01

MDA values are not included in the totals. MDA = Less than the a posteriori minimal detectable activity (microcuries per unit mass or volume).

Columbia Generating Station 11 2021 Radioactive Effluent Report

Table 3-3 Radwaste Building Releases - Ground Mode Fission Gases and Iodines Report Period: January -- December 2021 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Year Nuclides Released I (Ci) I (Ci) I (Ci) I (Ci) I (Ci) I A. Fission gases krypton-85 <MDA <MDA <MDA <MDA <MDA krypton-85m <MDA <MDA <MDA <MDA <MDA krypton-87 <MDA <MDA <MDA <MDA <MDA krypton-88 <MDA <MDA <MDA <MDA <MDA xenon-133 <MDA <MDA <MDA <MDA <MDA xenon-133m <MDA <MDA <MDA <MDA <MDA xenon-135 <MDA <MDA <MDA <MDA <MDA xenon-135m <MDA <MDA <MDA <MDA <MDA xenon-138 <MDA <MDA <MDA <MDA <MDA Others <MDA <MDA <MDA <MDA <MDA argon-41 <MDA <MDA <MDA <MDA <MDA Total for period * <MDA <MDA <MDA <MDA <MDA B. Iodines iodine-131 <MDA <MDA <MDA <MDA <MDA iodine-132 <MDA <MDA <MDA <MDA <MDA iodine-133 <MDA <MDA <MDA <MDA <MDA iodine-134 <MDA <MDA <MDA <MDA <MDA iodine-135 <MDA <MDA <MDA <MDA <MDA Total for period * <MDA <MDA <MDA <MDA <MDA

MDA values are not included in the totals. MDA = Less than the a posteriori minimal detectable activity (microcuries per unit mass or volume).

Columbia Generating Station 12 2021 Radioactive Effluent Report

Table 3-3 Radwaste Building Releases - Ground Mode (Continued)

Particulates and Tritium Report Period: January -- December 2021 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter Year Nuclides Released (Ci) (Ci) (Ci) (Ci) (Ci)

C. Particulates strontium-89 <MDA <MDA <MDA <MDA <MDA strontium-90 <MDA <MDA <MDA <MDA <MDA cesium-134 <MDA <MDA <MDA <MDA <MDA cesium-137 <MDA <MDA <MDA <MDA <MDA barium-lanthanum-140 <MDA <MDA <MDA <MDA <MDA cerium-141 <MDA <MDA <MDA <MDA <MDA cerium-144 <MDA <MDA <MDA <MDA <MDA cobalt-58 <MDA <MDA <MDA <MDA <MDA cobalt-60 2.79E-06 5.57E-07 3.31E-07 8.97E-07 4.58E-06 iron-59 <MDA <MDA <MDA <MDA <MDA manganese-54 <MDA <MDA <MDA <MDA <MDA zinc-65 <MDA <MDA <MDA <MDA <MDA Total for period* 2.79E-06 5.57E-07 3.31E-07 8.97E-07 4.58E-06 D. Tritium tritium 6.04E-01 3.01E-01 2.61E-01 5.58E-01 1.72E+00

MDA values are not included in the totals. MDA = Less than the a posteriori minimal detectable activity (microcuries per unit mass or volume).

Columbia Generating Station 13 2021 Radioactive Effluent Report

Table 3-4 Summation of Releases Gaseous Effluents Report Period: January - December 2021 Est*

1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter Year %Error A. Fission and activation gases Total release (Ci) 3.07E+01 1.70E+01 1.35E+01 1.08E+01 7.21+01 4.10E+01 Average release rate (Ci/s) 3.95E+00 2.17E+00 1.70E+00 1.36E+00 2.29E+00 Percent of ODCM limit (%) 1.57E-03 8.68E-04 6.90E-04 5.50E-04 3.68E-03 B. Iodines Total I-131 (Ci) 1.33E-05 4.55E-05 4.18E-06 4.72E-06 6.78E-05 4.30E+01 Average release rate (Ci/s) 1.71E-06 5.79E-06 5.26E-07 5.94E-07 2.15E-06 Percent of ODCM limit (%) 3.95E-07 1.34E-06 1.24E-07 1.28E-07 2.19E-06 C. Particulates Particulates with half-lives

>8 days (Ci) 8.52E-05 1.15E-03 1.10E-04 7.67E-05 1.42E-03 4.40E+01 Average release rate (Ci/s) 1.10E-05 1.46E-04 1.38E-05 9.65E-06 4.51E-05 Percent of ODCM limit (%) 2.12E-06 2.48E-05 2.97E-06 2.15E-06 3.21E-05 Gross alpha radioactivity (Ci) 9.28E-07 1.24E-06 1.29E-06 1.12E-06 4.58E-06 7.90E+01 D. Tritium Total release (Ci) 5.43E+00 4.98E+00 5.11E+00 4.32E+00 1.98E+01 2.30E+01 Average release rate (Ci/s) 6.98E-01 6.34E-01 6.43E-01 5.44E-01 6.29E-01 Percent of ODCM limit (%) 1.09E-05 9.67E-06 9.87E-06 8.80E-06 3.92E-05

Measurement errors are sample-specific. The values reported represent an approximate overall error. Some of the contributors of this error are measurements associated with estimating the sample volume, the exhaust duct flow rates, plateout factors, charcoal cartridge efficiencies, sample line vacuum, run time estimates, anisokinetic correction factors, and gravimetric, gamma spectroscopy, and liquid scintillation analysis errors.

ODCM release rate limits are based on dose rate, and the percent of ODCM limit shown in Table 3-4 is for the following limits. For fission and activation gases the dose rate limits are less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin. For I-131, particulates, and tritium the dose rate limit is less than or equal to 1500 mrem/year to any organ.

Columbia Generating Station 14 2021 Radioactive Effluent Report

Table 3-5 Gaseous Purges and Vents Report Period: January -- December 2021 Total Maximum Minimum Mean Type Number Time (hr.) Time (hr.) Time (hr.) Time (hr.)

Purge 15 85.5 9 1 5.70 Vent 44 40 2.25 0.25 0.91 Columbia Generating Station is a continuous release plant. All purges and vents are discharged through the High-Efficiency Particulate Air (HEPA) filters and charcoal beds of the Standby Gas Treatment System and released through the reactor building release duct which is, by procedure and design, sampled and continuously monitored for radioactive gaseous waste as a continuous release point.

Columbia Generating Station 15 2021 Radioactive Effluent Report

Table 3-6 Lower Limits of Detection Gaseous Effluents Report Period: January -- December 2021 Fission Gases Required LLD Achieved Analysis Nuclide (Ci/cc) LLD (Ci/cc) krypton-87 1.00E-04 1.08E-08 krypton-88 1.00E-04 1.30E-08 xenon-133 1.00E-04 1.08E-08 xenon-133m 1.00E-04 3.46E-08 xenon-135 1.00E-04 4.00E-09 xenon-138 1.00E-04 4.57E-08 Iodines iodine-131 1.00E-12 2.86E-14 iodine-133 1.00E-10 7.01E-13 Particulates strontium-89 1.00E-11 3.04E-12 strontium-90 1.00E-11 5.89E-13 cesium-134 1.00E-11 8.22E-15 cesium-137 1.00E-11 2.13E-14 molybdenum-99 1.00E-11 1.28E-13 cerium-141 1.00E-11 1.05E-14 cerium-144 1.00E-11 7.84E-14 cobalt-58 1.00E-11 1.55E-14 cobalt-60 1.00E-11 1.96E-14 iron-59 1.00E-11 4.30E-14 manganese-54 1.00E-11 2.03E-14 zinc-65 1.00E-11 3.43E-14 Gross Alpha 1.00E-11 5.50E-15 Tritium hydrogen-3 1.00E-06 5.06E-11 From ODCM Table 6.2.2.1-1 Columbia Generating Station 16 2021 Radioactive Effluent Report

4.0 Solid Radwaste This section of the annual effluent report provides information required by the Columbia Generating Station Offsite Dose Calculation Manual and recommended by Nuclear Regulatory Commission Regulatory Guide 1.21, Revision 1 (1974).

Solid Radwaste Information required by the Offsite Dose Calculation Manual January -- December 2021 Class A

1. Container Volumes (ft3)

B-25 Steel Box 96.0 PL8-120 Polyethylene HIC (SERDS) 120.3 PL14-170 Polyethylene HIC (SERDS) 170.8 14-170 Steel Liner (SERDS) 180.1 20 ft C-Van 1280 14-170 Wide Mouth Steel Liner (Open Top) 180.1

2. Total Curies 1.41E+02 Curies Columbia Generating Station 17 2021 Radioactive Effluent Report

3. Principal Radionuclides

07%.+&'5%74+'52'4%'06

Co60 7.53E+01 53.56%

Mn54 2.27E+00 1.61%

Co58 4.22E+00 3.00%

Cs137 3.18E-02 0.02%

Zn65 2.77E+00 1.97%

Ag110m 1.82E+00 1.29%

Fe55 4.97E+01 35.31%

Cs134 3.77E-03 0.00%

Fe59 2.94E-01 0.21%

Sb124 1.15E-02 0.01%

Pu241 4.37E-02 0.03%

Ni63 1.86E+00 1.32%

Sr90 4.34E-03 0.00%

Pu238 4.82E-04 0.00%

Pu239 4.15E-04 0.00%

Am241 3.36E-04 0.00%

Cm242 4.83E-04 0.00%

Cm243 3.77E-04 0.00%

C14 6.08E-01 0.43%

H3 1.03E-01 0.07%

Tc99 7.21E-02 0.05 I129 6.56E-03 0.00%

Co57 2.38E-03 0.00%

Ba140 2.67E-02 0.02%

La140 2.65E-02 0.02%

Cr51 1.47E+00 1.05%

Nb95 2.82E-03 0.00%

Ce141 1.22E-04 0.00%

Cs-136 1.61E-03 0.00%

Sb125 3.96E-03 0.00%

Nb94 1.81E-05 0.00%

Ni59 2.99E-03 0.00%

Ta182 1.36E-05 0.00%

Columbia Generating Station 18 2021 Radioactive Effluent Report

4. Source Resins 1.30E+2 Ci DAW 6.09 E+00 Ci Irradiated Components 4.77 E+00 Ci Other (Sealed Source, Mixed None Waste, & Liquid Waste) None

5. Type of Container All containers shipped as LSA, SCO or radioactive material in Excepted Packaging, Type A or Type B (including casks) as appropriate

6. Solidification Agent None Columbia Generating Station 19 2021 Radioactive Effluent Report

Class B There was one Class B waste shipment made during calendar year 2021.

1. Principal Radionuclides Nuclides Curies Percent Co60 9.45E+01 19.23%

Mn54 8.93E+00 1.82%

Co58 1.79E-01 0.04%

Cs137 3.82E-02 0.01%

Zn65 2.23E+00 0.45%

Ag110m 2.03E-01 0.04%

Fe55 3.77E+02 76.71%

Ni63 8.32E+00 1.69%

C14 1.70E-03 0.00%

H3 1.41E-02 0.00%

Tc99 3.55E-02 0.01%

I129 2.20E-03 0.00%

Co57 1.12E-02 0.00%

2. Sources - Resin

3. Type of Container PL-8-120 Polyethylene High Integrity Container

4. Solidification Agent - None Class C There were no Class C waste shipments made during calendar year 2021.

Columbia Generating Station 20 2021 Radioactive Effluent Report

Solid Radwaste Information Recommended by NRC Regulatory Guide 1.21 January -- December 2021 Solid waste shipped offsite for burial or disposal (not irradiated fuel).

1. Type of Waste Annual Est. Total Waste Stream Category Unit Cumulative Error %

A. Spent resins, filter sludge, m3 1.47E+02 evaporator bottoms, etc. Ci 6.21E+02 2.50E+01%

B. Dry Active Waste m3 3.36E+02 Ci 6.09E+00 2.50E+01%

C. Irradiated Components m3 3.41E+00 Ci 4.76E+00 2.50E+01%

D. Other Waste (Sealed Source, m3 0 mixed waste, & Liquid Waste) Ci 0 Columbia Generating Station 21 2021 Radioactive Effluent Report

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

a. Dewatered Spent Resins - Class A and B Nuclide Curies Percent Co60 1.65E+02 26.60%

Mn54 1.07E+01 1.72%

Co58 2.85E+00 0.46%

Cs137 7.00E-02 0.01%

Zn65 4.36E+00 0.70%

Ag110m 2.02E+00 0.33%

Fe55 4.24E+02 68.30%

Cs134 3.77E-03 0.00%

Fe59 2.14E-01 0.03%

Sb124 1.15E-02 0.00%

Pu241 3.44E-02 0.01%

Ni63 9.48E+00 1.53%

Sr90 3.58E-03 0.00%

Pu238 3.79E-04 0.00%

Pu239 3.26E-04 0.00%

Am241 2.64E-04 0.00%

Cm242 3.78E-04 0.00%

Cm243 2.96E-04 0.00%

C14 6.07E-01 0.10%

H3 1.17E-01 0.02%

Tc99 8.54E-02 0.01%

I129 6.81E-03 0.00%

Co57 1.36E-02 0.00%

Ba140 2.67E-02 0.00%

La140 2.65E-02 0.00%

Cr51 1.25E+00 0.20%

Nb95 2.82E-03 0.00%

Ce141 1.22E-04 0.00%

Cs-136 1.61E-03 0.00%

Sb125 3.96E-03 0.00%

Columbia Generating Station 22 2021 Radioactive Effluent Report

b. Dry Active Waste (DAW) - All Class A Nuclide Curies Percent Co60 2.04E+00 33.56%

Co58 1.55E+00 25.40%

Mn54 4.59E-01 7.53%

Tc99 2.17E-02 0.36%

Zn65 3.65E-01 5.99%

Pu241 9.32E-03 0.15%

Pu238 1.03E-04 0.00%

Pu239 8.88E-05 0.00%

Fe59 8.01E-02 1.32%

Cm243 8.06E-05 0.00%

Am241 7.17E-05 0.00%

Fe55 1.30E+00 21.34%

Cm242 1.05E-04 0.00%

Cr51 2.28E-01 3.75%

C14 1.28E-03 0.02%

Sr90 7.57E-04 0.01%

Ni63 3.22E-02 0.53%

H-3 2.78E-04 0.00%

I-129 1.89E-03 0.03%

Columbia Generating Station 23 2021 Radioactive Effluent Report

c. Irradiated Components Nuclide Curies Percent Co60 2.33E+03 48.90%

Co58 1.54E-01 0.00%

Mn54 4.61E+00 0.10%

Zn65 1.98E-01 0.00%

Fe59 4.73E-02 0.00%

Fe55 1.76E+03 36.90%

Cr51 1.63E-01 0.00%

Tc99 2.27E-02 0.00%

Ni63 6.69E+02 14.00%

C-14 1.12E+00 0.02%

H-3 6.66E-01 0.01%

I-129 5.03E-03 0.00%

Cs-137 2.18E-02 0.00%

Nb-94 1.81E-02 0.00%

Nb-95 6.41E-03 0.00%

Ni-59 2.99E+00 0.06%

Sb-124 3.79E-03 0.00%

Ta-182 1.36E-02 0.00%

d. Other Waste (sealed source, mixed waste, and liquid waste)

None Columbia Generating Station 24 2021 Radioactive Effluent Report

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 33 Tractor - Trailer US Ecology, Inc.

via Public Highway P.O. Box 638 Hanford Reservation Richland, WA. 99352 1 Tractor - Trailer Perma-Fix Northwest via Public Highway Battelle Blvd Richland, WA. 99352 5 Tractor - Trailer UniTech Services Oak Ridge via Public Highway Service Center Oak Ridge, TN Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A Columbia Generating Station 25 2021 Radioactive Effluent Report

5.0 Meteorological Data The meteorological data contained in Tables 5-1 through 5-5 was obtained from a meteorological tower located 762 meters (2500 feet) west of Columbia Generating Station. Data was recovered from two sets of redundant instruments on the tower at the 10 meter (33-foot) and 75 meter (245- foot) levels. The meteorological data is a composite file generated from the automated data recovery systems for the calendar year 2021. Data is archived on the Energy Northwest Local Area Network.

Meteorological data recovery for 2021 was 99.7% at the 10-meter (33-foot) level.

Redundant wind and temperature sensors are installed at both levels of the meteorological tower. Data from the two systems can be combined to permit maximum data recovery for defined date ranges.

The data in Tables 5-1 through 5-4 provide joint frequency distributions (JFD) at the 10-meter level by quarter for 2021. These tables show the total hours at various wind speeds for each sector and stability class. The NRC stability classes A through G and eleven wind speed categories along with the 16 wind direction sectors were used to prepare each joint frequency table. Tables 5-5 provide the annual joint frequency distributions.

Wind speed is measured in miles per hour in the tables, and any speed measured below 1.0 MPH was recorded as calm.

There are a number of atmospheric factors which affect dispersivity but which are not modeled in the CGS estimates of dispersion and deposition. Those conditions which were measured or documented at the Hanford Meteorological Station during 2021 were total precipitation (5.37 inches) and snow (17.7 inches).

Columbia Generating Station 26 2021 Radioactive Effluent Report

Joint Frequency Distribution Tables for 2021 Table 5-1 1st Quarter Average, 33 Ft Above Ground Level (AGL)

Elevation: 33 Start Date: 1/1/2021 Total number of Periods: 2159 Period: 1st Quarter Stop Date: 4/1/2021 Periods of No Data Recovery: 0 System Percent Data Recovery: 100.0%

Stability Class: A Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 27 2.2 4.5 50 4.5 6.7 42 6.7 8.9 28 8.9 11.2 14 11.2 13.4 9 13.4 17.9 15 17.9 22.4 12 22.4 29.1 9 29.1 40.3 1 40.3 90.0 0 TOTALS 24 4 1 3 3 3 10 14 22 27 15 6 7 12 22 34 207 Stability Class: B Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 2 4.5 6.7 8 6.7 8.9 1 8.9 11.2 4 11.2 13.4 2 13.4 17.9 2 17.9 22.4 4 22.4 29.1 3 29.1 40.3 0 40.3 90.0 0 TOTALS 2 1 0 0 0 0 0 2 1 2 1 1 4 6 4 2 26 Stability Class: C Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 6 2.2 4.5 8 4.5 6.7 9 6.7 8.9 8 8.9 11.2 7 11.2 13.4 8 13.4 17.9 8 17.9 22.4 7 22.4 29.1 8 29.1 40.3 3 40.3 90.0 0 TOTALS 6 0 5 0 1 0 2 5 4 3 4 3 3 13 11 12 72 Stability Class: D Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 50 2.2 4.5 129 4.5 6.7 78 6.7 8.9 67 8.9 11.2 46 11.2 13.4 25 13.4 17.9 45 17.9 22.4 26 22.4 29.1 22 29.1 40.3 3 40.3 90.0 0 TOTALS 36 14 8 0 1 1 9 29 53 41 30 30 31 54 96 58 491 Columbia Generating Station 27 2021 Radioactive Effluent Report

Table 5-1 1st Quarter Average, 33 Ft AGL (Continued)

Stability Class: E Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 54 2.2 4.5 133 4.5 6.7 122 6.7 8.9 95 8.9 11.2 66 11.2 13.4 37 13.4 17.9 59 17.9 22.4 23 22.4 29.1 20 29.1 40.3 2 40.3 90.0 0 TOTALS 23 8 4 3 1 2 26 64 75 74 42 35 50 75 89 40 611 Stability Class: F Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 58 2.2 4.5 125 4.5 6.7 94 6.7 8.9 75 8.9 11.2 55 11.2 13.4 22 13.4 17.9 18 17.9 22.4 0 22.4 29.1 1 29.1 40.3 0 40.3 90.0 0 TOTALS 15 6 6 1 2 0 9 65 46 42 25 29 34 53 72 43 448 Stability Class: G Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 39 2.2 4.5 104 4.5 6.7 56 6.7 8.9 40 8.9 11.2 14 11.2 13.4 5 13.4 17.9 2 17.9 22.4 0 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 35 20 11 0 1 1 6 37 21 17 8 6 8 21 39 29 260 Stability Class: All Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 234 2.2 4.5 551 4.5 6.7 409 6.7 8.9 314 8.9 11.2 206 11.2 13.4 108 13.4 17.9 149 17.9 22.4 72 22.4 29.1 63 29.1 40.3 9 40.3 90.0 0 TOTALS 141 53 35 7 9 7 62 216 222 206 125 110 137 234 333 218 2115 Periods of Calm while in Stability Class:

A B C D E F G Total

Columbia Generating Station 28 2021 Radioactive Effluent Report

Table 5-2 2nd Quarter Average, 33 Ft AGL Elevation: 33 Start Date: 4/1/2021 Total number of Periods: 2184 Period: 2nd Quarter Stop Date: 7/1/2021 Periods of No Data Recovery: 20 System Percent Data Recovery: 99.1%

Stability Class: A Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 0 4.5 6.7 0 6.7 8.9 0 8.9 11.2 2 11.2 13.4 3 13.4 17.9 7 17.9 22.4 9 22.4 29.1 12 29.1 40.3 0 40.3 90.0 0 TOTALS 4 4 8 0 0 0 0 1 7 1 2 4 0 1 1 0 33 Stability Class: B Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 1 4.5 6.7 6 6.7 8.9 8 8.9 11.2 17 11.2 13.4 20 13.4 17.9 20 17.9 22.4 9 22.4 29.1 7 29.1 40.3 1 40.3 90.0 0 TOTALS 10 14 14 1 0 1 0 2 13 6 5 6 0 4 2 11 89 Stability Class: C Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 18 4.5 6.7 65 6.7 8.9 64 8.9 11.2 45 11.2 13.4 32 13.4 17.9 23 17.9 22.4 15 22.4 29.1 14 29.1 40.3 1 40.3 90.0 0 TOTALS 29 23 14 5 1 3 8 14 43 21 14 18 15 16 19 34 277 Stability Class: D Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 27 2.2 4.5 145 4.5 6.7 178 6.7 8.9 130 8.9 11.2 84 11.2 13.4 46 13.4 17.9 63 17.9 22.4 33 22.4 29.1 31 29.1 40.3 4 40.3 90.0 0 TOTALS 30 40 24 17 12 22 43 82 86 55 53 64 46 79 57 31 741 Columbia Generating Station 29 2021 Radioactive Effluent Report

Table 5-2 2nd Quarter Average, 33 Ft AGL (Continued)

Stability Class: E Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 21 2.2 4.5 85 4.5 6.7 77 6.7 8.9 67 8.9 11.2 57 11.2 13.4 49 13.4 17.9 82 17.9 22.4 31 22.4 29.1 18 29.1 40.3 0 40.3 90.0 0 TOTALS 22 27 23 6 5 3 17 25 22 35 31 28 36 127 51 29 487 Stability Class: F Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 26 2.2 4.5 87 4.5 6.7 72 6.7 8.9 60 8.9 11.2 18 11.2 13.4 6 13.4 17.9 5 17.9 22.4 0 22.4 29.1 16 29.1 40.3 0 40.3 90.0 0 TOTALS 19 19 24 3 1 3 17 39 26 25 15 12 16 27 20 24 290 Stability Class: G Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 44 2.2 4.5 78 4.5 6.7 54 6.7 8.9 39 8.9 11.2 6 11.2 13.4 0 13.4 17.9 0 17.9 22.4 0 22.4 29.1 8 29.1 40.3 0 40.3 90.0 0 TOTALS 30 19 26 2 1 3 7 28 26 17 8 7 4 15 18 18 229 Stability Class: All Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 118 2.2 4.5 414 4.5 6.7 452 6.7 8.9 368 8.9 11.2 229 11.2 13.4 156 13.4 17.9 200 17.9 22.4 97 22.4 29.1 106 29.1 40.3 6 40.3 90.0 0 TOTALS 144 146 133 34 20 35 92 191 223 160 128 139 117 269 168 147 2146 Periods of Calm while in Stability Class:

A B C D E F G Total

Columbia Generating Station 30 2021 Radioactive Effluent Report

Table 5-3 3rd Quarter Average, 33 Ft AGL Elevation: 33 Start Date: 7/1/2021 Total number of Periods: 2208 Period: 3rd Quarter Stop Date: 10/1/2021 Periods of No Data Recovery: 5 System Percent Data Recovery: 99.8%

Stability Class: A Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 1 4.5 6.7 0 6.7 8.9 0 8.9 11.2 0 11.2 13.4 1 13.4 17.9 3 17.9 22.4 1 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 0 0 0 0 0 0 0 2 4 0 0 0 0 0 0 0 6 Stability Class: B Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 0 4.5 6.7 0 6.7 8.9 3 8.9 11.2 3 11.2 13.4 8 13.4 17.9 14 17.9 22.4 2 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 3 4 0 0 0 0 0 3 9 9 1 0 0 0 0 1 30 Stability Class: C Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 20 4.5 6.7 39 6.7 8.9 46 8.9 11.2 47 11.2 13.4 25 13.4 17.9 26 17.9 22.4 5 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 16 21 4 4 1 1 12 36 52 16 4 3 6 9 14 9 208 Stability Class: D Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 38 2.2 4.5 130 4.5 6.7 200 6.7 8.9 192 8.9 11.2 86 11.2 13.4 53 13.4 17.9 50 17.9 22.4 18 22.4 29.1 11 29.1 40.3 0 40.3 90.0 0 TOTALS 35 24 25 31 13 19 76 120 99 67 50 39 36 40 85 19 778 Columbia Generating Station 31 2021 Radioactive Effluent Report

Table 5-3 3rd Quarter Average, 33 Ft AGL (Continued)

Stability Class: E Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 31 2.2 4.5 67 4.5 6.7 92 6.7 8.9 83 8.9 11.2 72 11.2 13.4 36 13.4 17.9 51 17.9 22.4 15 22.4 29.1 1 29.1 40.3 0 40.3 90.0 0 TOTALS 10 5 8 9 4 5 27 48 27 40 26 25 29 80 79 26 448 Stability Class: F Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 35 2.2 4.5 119 4.5 6.7 95 6.7 8.9 81 8.9 11.2 20 11.2 13.4 6 13.4 17.9 4 17.9 22.4 0 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 20 22 11 5 1 3 24 63 56 40 14 18 12 19 29 23 360 Stability Class: G Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 85 2.2 4.5 145 4.5 6.7 77 6.7 8.9 26 8.9 11.2 4 11.2 13.4 1 13.4 17.9 0 17.9 22.4 0 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 35 34 31 3 2 1 10 37 45 31 17 12 17 15 16 32 338 Stability Class: All Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 189 2.2 4.5 482 4.5 6.7 503 6.7 8.9 431 8.9 11.2 232 11.2 13.4 130 13.4 17.9 148 17.9 22.4 41 22.4 29.1 12 29.1 40.3 0 40.3 90.0 0 TOTALS 119 110 79 52 21 29 149 309 292 203 112 97 100 163 223 110 2168 Periods of Calm while in Stability Class:

A B C D E F G Total

Columbia Generating Station 32 2021 Radioactive Effluent Report

Table 5-4 4th Quarter Average, 33 Ft AGL Elevation: 33 Start Date: 10/1/2021 Total number of Periods: 2205 Period: 4th Quarter Stop Date: 1/1/2022 Periods of No Data Recovery: 0 System Percent Data Recovery: 100.0%

Stability Class: A Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 0 4.5 6.7 0 6.7 8.9 0 8.9 11.2 0 11.2 13.4 0 13.4 17.9 0 17.9 22.4 0 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Stability Class: B Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 1 4.5 6.7 0 6.7 8.9 0 8.9 11.2 0 11.2 13.4 0 13.4 17.9 0 17.9 22.4 1 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 0 2 Stability Class: C Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 4 4.5 6.7 2 6.7 8.9 1 8.9 11.2 1 11.2 13.4 3 13.4 17.9 11 17.9 22.4 2 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 3 1 0 0 0 0 0 0 4 3 3 0 0 1 2 7 24 Stability Class: D Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 58 2.2 4.5 134 4.5 6.7 132 6.7 8.9 103 8.9 11.2 92 11.2 13.4 75 13.4 17.9 73 17.9 22.4 13 22.4 29.1 9 29.1 40.3 6 40.3 90.0 0 TOTALS 83 40 18 3 3 1 15 63 78 89 32 35 24 36 82 93 695 Columbia Generating Station 33 2021 Radioactive Effluent Report

Table 5-4 4th Quarter Average, 33 Ft AGL (Continued)

Stability Class: E Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 39 2.2 4.5 131 4.5 6.7 136 6.7 8.9 148 8.9 11.2 102 11.2 13.4 75 13.4 17.9 104 17.9 22.4 46 22.4 29.1 27 29.1 40.3 2 40.3 90.0 0 TOTALS 27 12 18 2 0 5 28 102 122 128 93 30 31 48 94 70 810 Stability Class: F Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 47 2.2 4.5 111 4.5 6.7 99 6.7 8.9 103 8.9 11.2 56 11.2 13.4 25 13.4 17.9 10 17.9 22.4 2 22.4 29.1 3 29.1 40.3 0 40.3 90.0 0 TOTALS 19 10 15 4 0 1 6 84 77 39 30 18 20 39 64 30 456 Stability Class: G Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 33 2.2 4.5 82 4.5 6.7 38 6.7 8.9 23 8.9 11.2 7 11.2 13.4 2 13.4 17.9 0 17.9 22.4 1 22.4 29.1 0 29.1 40.3 0 40.3 90.0 0 TOTALS 15 12 2 1 0 0 1 14 22 16 13 9 13 13 31 24 186 Stability Class: All Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 177 2.2 4.5 463 4.5 6.7 407 6.7 8.9 378 8.9 11.2 258 11.2 13.4 180 13.4 17.9 198 17.9 22.4 65 22.4 29.1 39 29.1 40.3 8 40.3 90.0 0 TOTALS 147 75 53 10 3 7 50 263 303 275 171 92 89 137 274 224 2173 Periods of Calm while in Stability Class:

A B C D E F G Total

Columbia Generating Station 34 2021 Radioactive Effluent Report

Table 5-5 Year 2021, 33 Ft AGL Elevation: 33 Start Date: 1/1/2021 Total number of Periods: 8756 Period: 2021 Annual Stop Date: 1/1/2022 Periods of No Data Recovery: 25 System Percent Data Recovery: 99.7%

Stability Class: A Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 27 2.2 4.5 51 4.5 6.7 42 6.7 8.9 28 8.9 11.2 16 11.2 13.4 13 13.4 17.9 25 17.9 22.4 22 22.4 29.1 21 29.1 40.3 1 40.3 90.0 0 TOTALS 28 8 9 3 3 3 10 17 33 28 17 10 7 13 23 34 246 Stability Class: B Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 0 2.2 4.5 4 4.5 6.7 14 6.7 8.9 12 8.9 11.2 24 11.2 13.4 30 13.4 17.9 36 17.9 22.4 16 22.4 29.1 10 29.1 40.3 1 40.3 90.0 0 TOTALS 15 19 14 1 0 1 0 7 23 17 7 7 5 10 7 14 147 Stability Class: C Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 6 2.2 4.5 50 4.5 6.7 115 6.7 8.9 119 8.9 11.2 100 11.2 13.4 68 13.4 17.9 68 17.9 22.4 29 22.4 29.1 22 29.1 40.3 4 40.3 90.0 0 TOTALS 54 45 23 9 3 4 22 55 103 43 25 24 24 39 46 62 581 Stability Class: D Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 173 2.2 4.5 538 4.5 6.7 588 6.7 8.9 492 8.9 11.2 308 11.2 13.4 199 13.4 17.9 231 17.9 22.4 90 22.4 29.1 73 29.1 40.3 13 40.3 90.0 0 TOTALS 184 118 75 51 29 43 143 294 316 252 165 168 137 209 320 201 2705 Columbia Generating Station 35 2021 Radioactive Effluent Report

Table 5-5 Year 2021, 33 Ft AGL (Continued)

Stability Class: E Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 145 2.2 4.5 416 4.5 6.7 427 6.7 8.9 393 8.9 11.2 297 11.2 13.4 197 13.4 17.9 296 17.9 22.4 115 22.4 29.1 66 29.1 40.3 4 40.3 90.0 0 TOTALS 82 52 53 20 10 15 98 239 246 277 192 118 146 330 313 165 2356 Stability Class: F Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 166 2.2 4.5 442 4.5 6.7 360 6.7 8.9 319 8.9 11.2 149 11.2 13.4 59 13.4 17.9 37 17.9 22.4 2 22.4 29.1 20 29.1 40.3 0 40.3 90.0 0 TOTALS 73 57 56 13 4 7 56 251 205 146 84 77 82 138 185 120 1554 Stability Class: G Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 201 2.2 4.5 409 4.5 6.7 225 6.7 8.9 128 8.9 11.2 31 11.2 13.4 8 13.4 17.9 2 17.9 22.4 1 22.4 29.1 8 29.1 40.3 0 40.3 90.0 0 TOTALS 115 85 70 6 4 5 24 116 114 81 46 34 42 64 104 103 1013 Stability Class: All Wind Speed Min Max N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 1.0 2.2 718 2.2 4.5 1910 4.5 6.7 1771 6.7 8.9 1491 8.9 11.2 925 11.2 13.4 574 13.4 17.9 695 17.9 22.4 275 22.4 29.1 220 29.1 40.3 23 40.3 90.0 0 TOTALS 551 384 300 103 53 78 353 979 1040 844 536 438 443 803 998 699 8602 Periods of Calm while in Stability Class:

A B C D E F G Total

Columbia Generating Station 36 2021 Radioactive Effluent Report

6.0 Dose Assessment -- IMPACT ON MAN Liquid Effluents - There were no liquid discharges from the radwaste processing system to the Columbia River during calendar year 2021. As such, the liquid dose reporting tables (Tables 6-1 through 6-4) described in the implementing procedure, PPM 16.12.5, have been excluded from this report.

Gaseous Effluents - The software program RADEAS, based on Regulatory Guide 1.109, was used to calculate doses at and beyond the site boundary in Tables 6-0 and Table 6-5 using the 2021 annual meteorological data and site-specific variables as required and defined in the ODCM. Table 6-5 shows the highest calculated doses at and beyond the site boundary for Beta and Gamma air dose, skin dose, total body dose, and maximum organ dose. Table 6-6 provides the population collective dose within a 50-mile radius. Table 6-6 also provides the annual average individual doses associated with each pathway based on the population within 50 miles. These values were obtained by dividing 50-mile collective dose (person-rem) by the 2010 US Census 50-mile population (448,383) and converting to mrem.

During the growing season, CGS conducts a five-mile land use census to determine the locations of nearest residents, gardens, and milk animals or other livestock out to five miles in each sector. The 2021 Land Use Census identified one resident vegetable garden (broad leaf) greater than 500 ft2 within 5 miles of CGS. A second resident garden greater than 500 ft2 was identified just outside of the 5-mile radius in the eastern sector. This garden was considered in dose determinations, as a previous XOQDOQ calculation (2015) resulted in deposition factors higher for the garden outside of the 5-mile radius than for the resident garden within the 5-mile radius. Cattle and horses were observed within 5-miles, but there were no observed milking animals within the 5-mile radius. A substantial commercial fruit orchard and corn crops were observed in all eastern sectors with residents, it was assumed for dose calculational purposes that these crops were being consumed by the residents.

Dose to Onsite Members of the Public The term Member of the Public includes all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

Dose was evaluated to MOP that were not identified per the criteria of the 2021 Land Use Census. This includes non-Energy Northwest employees that work east of the site, in buildings associated with sites WNP-1 and WNP-4. The maximum dose from gaseous effluents to these individuals was estimated assuming exposure to the plume, inhalation, and ground deposition pathways and an occupancy factor consistent with ODCM section 3 as a bounding condition.

Columbia Generating Station 37 2021 Radioactive Effluent Report

The following table (6.0) shows estimated dose to Members of the Public from gaseous effluents within the site boundary of Columbia Generating Station for a fraction of a year spent at each location.

Table 6.0; Dose to Members of the Public within the Site Boundary Total Highest Body Thyroid Organ Hours Dose Dose Dose Location Spent (mrem) (mrem) (mrem)

WNP-4 Whse.2-4 2.08E+03 1.17E-03 1.17E-03 1.50E-03 WNP-1 Bldg 121 2.08E+03 2.54E-03 2.54E-03 3.33E-03 DOE Site 618-11 2.08E+03 2.22E-04 2.23E-04 3.08E-04 Ashe Substation 2.08E+03 4.83E-03 4.83E-03 6.88E-03 Dose to Offsite Members of the Public For all routine releases (including liquid doses since no liquid discharges were made),

the highest calculated annual organ dose was 1.50E-01 mrem to bone for a member of the public living at 4.79 miles ESE of Columbia Generating Station. The highest beyond site boundary dose to the thyroid was 3.31E-02 mrem, to the total body was 3.31E-02 mrem, and to the skin was 4.30E-03 mrem.

For environmental dosimetry stations at or beyond the site boundary, no significant increases in the average ambient exposure were observed when compared to control dosimeter locations for year 2021.

For a Boiling Water Reactor, demonstrating conformance with Appendix I of 10 CFR 50 is generally adequate for demonstrating compliance with 40 CFR 190 when the sources of direct radiation from various sources, including the ISFSI, are indistinguishable from background.

The information contained in Table 6-5 is consistent with previous effluent release reports from Columbia Generating Station. There are no ingestion pathways for a hypothetical MOP at the site boundary.

The five sub-tables in Table 6-5 show maximum estimated exposure and dose at and beyond the site boundary. No residents were observed at the site boundary. The maximum exposure and dose beyond the site boundary is estimated for locations with actual residents.

Columbia Generating Station 38 2021 Radioactive Effluent Report

Table 6-5 Summary of Doses from Gaseous Effluents

1. Maximum Air Dose at or beyond the Site Boundary (1.2 miles) 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Dose*

Beta air dose (mrad) 2.91E-03 1.61E-03 1.28E-03 1.02E-03 6.82E-03 Gamma air dose (mrad) 8.24E-03 4.57E-03 3.63E-03 2.90E-03 1.93E-02

2. Maximum Annual Dose at the Site Boundary 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Dose*

Total body dose (mrem) 8.25E-03 9.76E-03 4.11E-03 3.31E-03 2.54E-02 Skin dose (mrem) 1.17E-02 1.26E-02 5.68E-03 4.52E-03 3.45E-02

3. Maximum Annual Dose Beyond the Site Boundary 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Dose*

Total body dose (mrem) 9.82E-03 5.33E-03 9.41E-03 8.52E-03 3.31E-02 Skin dose (mrem) 1.66E-03 1.27E-03 7.63E-04 6.06E-04 4.30E-03

4. Maximum Organ Dose at the Site Boundary (1.2 miles) 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Cumulative*

Maximum Organ dose (mrem) 1.17E-02 1.26E-02 5.68E-03 4.52E-03 3.45E-02

5. Maximum Organ Dose Beyond the Site Boundary 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Cumulative*

Maximum Organ dose (mrem) 4.37E-02 2.22E-02 4.42E-02 4.03E-02 1.50E-01 Columbia Generating Station 39 2021 Radioactive Effluent Report

Table 6-6 50-Mile Population Dose from Gaseous Effluents A. 50-mile population collective dose Exposure Total Body Max. Organ Pathway (person-rem) (person-rem)

Plume 8.95E-03 1.59E-02 Ground 5.66E-03 6.66E-03 Inhalation 2.31E-03 3.13E-03 Vegetables 2.37E-01 1.17E+00 Milk 1.05E-01 5.22E-01 Meat 7.45E-02 3.70E-01 Total 4.33E-01 2.08E+00 B. Average Individual*

Exposure Total Body Max. Organ Pathway (mrem) (mrem)

Plume 2.00E-05 3.55E-05 Ground 1.26E-05 1.49E-05 Inhalation 5.15E-06 6.98E-06 Vegetables 5.29E-04 2.61E-03 Milk 2.34E-04 1.16E-03 Meat 1.66E-04 8.25E-04 Total 9.67E-04 4.66E-03

These values are derived by dividing the 50-mile population collective doses by the population within 50 miles of Columbia Generating Station (448,383). The population estimate is based on the 2010 census conducted by the United States Census Bureau tabulated/compiled by the Washington State Office of Financial Management, Small Area Estimate Program. The Maximum Organ was bone.

Columbia Generating Station 40 2021 Radioactive Effluent Report

7.0 REVISIONS TO THE ODCM There were no changes made to the ODCM in 2021. The ODCM is included as an enclosure to the letter transmitting this "Radioactive Effluent Release Report in compliance with Columbia Technical Specification 5.5.1.

8.0 REVISIONS TO THE PROCESS CONTROL PROGRAM (PCP)

The PCP is maintained as a Plant Operations Committee approved procedure, SWP-RMP-02. There was one revision to the PCP in 2021, SWP-RMP-02 (Rev 008), issued on 01/28/2021. This revision updates step 2.2.1 b to revise the language to be consistent with the FSAR, Section 11.4.3.7 for describing that resin processing equipment will be subject to the Preventive Maintenance (PM) and Corrective maintenance programs established at Columbia, as applicable.

9.0 NEW OR DELETED LOCATIONS FOR DOSE ASSESSMENTS AND/OR ENVIRONMENTAL MONITORING LOCATIONS The 2021 5-Mile Land Use Census (LUC) DID NOT identify any necessary changes to locations for dose assessments or environmental monitoring locations.

10.0 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS No major changes (as defined by ODCM Section 6.4.3) were made to the radioactive waste treatment systems (liquid, gaseous, or solid) during 2021.

11.0 Errata There are no errata to include in this report.

Columbia Generating Station 41 2021 Radioactive Effluent Report

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Radioactive Liquid Effluent Monitoring Instrumentation 6.1.1 6.1 INSTRUMENTATION 6.1.1 Radioactive Liquid Effluent Monitoring Instrumentation RFO 6.1.1.1 The radioactive liquid effluent monitoring instrumentation channels in Table 6.1.1-1 shall be Functional.

APPLICABILITY: In accordance with Table 6.1.1-1.

COMPENSATORY MEASURES

NOTE-----------------------------------------------------------

Separate condition entry is allowed for each channel.

REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. One or more required A.1 Enter the condition Immediately radioactive liquid effluent referenced in Table 6.1.1-1 monitoring for the channel.

instrumentation channels nonfunctional.

B. As required by B.1 Perform SR 6.2.1.1.1 on Prior to radioactive Compensatory two independent samples liquid release through Measure A.1 and of the batch to be released. the radwaste effluent referenced in line Table 6.1.1-1.

AND B.2 Verify the associated Prior to radioactive release rate calculations liquid release through and the discharge valve the radwaste effluent lineup using two qualified line members of the technical staff.

AND B.3 Restore the channel to 30 days Functional status.

Columbia Generating Station 6.1.1-1 Amendment 50, May 2013

Radioactive Liquid Effluent Monitoring Instrumentation 6.1.1 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME C. As required by C.1 Analyze a grab sample for Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory radioactivity (beta or Measure A.1 and gamma) of the associated referenced in pathway. The LLD shall be Table 6.1.1-1. 1E-7 Ci/ml.

AND C.2 Restore the channel to 30 days Functional status.

D. As required by D.1 Estimate the flow rate At the beginning of Compensatory through the associated the release and once Measure A.1 and pathway. per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during referenced in releases through the Table 6.1.1-1. associated line AND D.2 Restore the channel to 30 days Functional status.

E. Required Compensatory E.1 Prepare and submit, in the Upon submittal of Measure B.3, C.2, or D.2 Radioactive Effluent current calendar year and associated Release Report, the reason Radioactive Effluent Completion Time not the channel was not Release Report met. restored to Functional status within 30 days.

Columbia Generating Station 6.1.1-2 Amendment 50, May 2013

Radioactive Liquid Effluent Monitoring Instrumentation 6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.1.1.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 6.1.1.2 Perform Source Check. Prior to each radioactive release SR 6.1.1.3 Perform Source Check. 31 days SR 6.1.1.4 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 6.1.1.5 Perform CHANNEL CALIBRATION. 18 months Columbia Generating Station 6.1.1-3 Amendment 50, May 2013

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Radioactive Gaseous Effluent Monitoring Instrumentation 6.1.2 6.1 INSTRUMENTATION 6.1.2 Radioactive Gaseous Effluent Monitoring Instrumentation RFO 6.1.2.1 The radioactive gaseous effluent monitoring instrumentation channels in Table 6.1.2-1 shall be Functional.

APPLICABILITY: In accordance with Table 6.1.2-1.

COMPENSATORY MEASURES

NOTE-----------------------------------------------------------

Separate condition entry is allowed for each channel.

REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. One or more required A.1 Enter the condition Immediately channels nonfunctional. referenced in Table 6.1.2-1 for the channel.

B. As required by B.1 Verify the Reactor Building Immediately Compensatory Elevated Discharge Measure A.1 and Radiation Monitor is referenced in Functional.

Table 6.1.2-1.

OR B.2 Verify the Condition C Immediately Compensatory Actions are being met.

Columbia Generating Station 6.1.2-1 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation 6.1.2 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME C. As required by C.1 Take a noble gas grab 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Compensatory sample at the associated Measure A.1 and sample location. AND referenced in Table 6.1.2-1. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND C.2 Analyze the grab sample 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after for gamma emitters as completion of required by Required Required Compensatory Compensatory Measure C.1. Measure C.1 AND C.3 Restore the channel to 30 days Functional status.

D. As required by D.1 Estimate the flow rate 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Compensatory through the associated Measure A.1 and pathway. AND referenced in Table 6.1.2-1. Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter AND D.2 Restore the channel to 30 days Functional status.

E. As required by E.1.1 Establish auxiliary sampling 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Compensatory equipment to continuously Measure A.1 and collect samples from the AND referenced in associated effluent release Table 6.1.2-1. pathway as required in Continuously Table 6.2.2.1-1. thereafter OR Columbia Generating Station 6.1.2-2 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation 6.1.2 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME E. (continued) E.1.2 Collect relevant information Immediately to provide an estimate of effluent releases.

AND E.2 Restore the channel to 30 days Functional status.

F. As required by F.1.1 Verify that at least one Immediately Compensatory Measure Functional channel is A.1 and referenced in providing indication of the Table 6.1.2-1. offgas post treatment activity concentration.

OR F.1.2.1 Verify that the offgas 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months charcoal beds are not bypassed AND F.1.2.2 Take a noble gas grab 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sample at the associated sample location. AND Every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND thereafter F.1.2.3 Analyze the grab sample 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after for gamma emmiters as completion of required by Compensatory Required Measure F.1.2.2. Compensatory Measure F.1.2.2 AND Columbia Generating Station 6.1.2-3 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation 6.1.2 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME F. (continued) F.2.1 Verify the nonfunctional 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channel is placed in a trip condition.

OR F.2.2 Implement administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months controls to prevent exceeding effluent limits.

AND 30 days F.3 Restore the channel to Functional status.

G. Required Compensatory G.1 Prepare and submit, in the Upon submittal of Measure C.3, D.2, E.2, Radioactive Effluent current calendar year or F.3 and associated Release Report, the reason Radioactive Effluent Completion Time not the channel was not Release Report met or Compensatory restored to Functional Measure E.1.2 status within the required performed. Completion Time or the use of Compensatory Measure E.1.2.

H. As required by H.1 Verify the Offgas Treatment Immediately Compensatory System (RECHAR) is not Measure A.1 and bypassed.

referenced in Table 6.1.2-1. AND H.2 Verify that at least one Main Immediately Condenser Offgass Post-Treatment Radiation Monitor is Functional.

AND Columbia Generating Station 6.1.2-4 Amendment 55, August 2016

Radioactive Gaseous Effluent Monitoring Instrumentation 6.1.2 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME H. (continued) H.3 Install a temporary portable 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Area Radiation Monitor and record radiation levels. AND Every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter AND H.4 Take a grab sample and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months analyze to verify that the noble gas gross gamma AND activity d 332mCi/sec.

Every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter AND H.5.1 Restore the channel to 30 days Functional status.

OR H.5.2 Prepare and submit, in the Upon submittal of Radioactive Effluent current calendar year Release Report, the reason Radioactive Effluent the channel was not Release Report restored to Functional status within the required Completion Time.

I. Required Compensatory I.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Measure and associated Completion Time of Condition H not met.

Columbia Generating Station 6.1.2-5 Amendment 55, August 2016

Radioactive Gaseous Effluent Monitoring Instrumentation 6.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.1.2.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 6.1.2.2 Perform Source Check. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 6.1.2.3 Perform CHANNEL CHECK. 7 days SR 6.1.2.4 Perform Source Check. 31 days SR 6.1.2.5 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 6.1.2.5a Perform CHANNEL CHECK. Prior to mechanical vacuum pump use SR 6.1.2.6 Perform CHANNEL CALIBRATION. 18 months SR 6.1.2.7 Perform CHANNEL CALIBRATION. Each refueling outage Columbia Generating Station 6.1.2-6 Amendment 55, August 2016

Radioactive Gaseous Effluent Monitoring Instrumentation 6.1.2 Table 6.1.2-1 (page 1 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM ALARM/

SPECIFIED PER COMPENSATORY SURVEILLANCE TRIP FUNCTION CONDITIONS FUNCTION MEASURE A.1 REQUIREMENTS SETPOINT

1. Main Condenser (a) 2 F SR 6.1.2.1 (c)

Offgas Post- SR 6.1.2.2 Treatment Radiation SR 6.1.2.5 Monitor SR 6.1.2.7

2. Main Condenser (a) 1 H SR 6.1.2.1 1.5 times Offgas Pre- SR 6.1.2.4 steady Treatment Radiation SR 6.1.2.5 state full Monitor SR 6.1.2.6 power 2a. Mechanical Vacuum (f) 1 B SR 6.1.2.5a (c)

Pump Discharge SR 6.1.2.7 Radiation Monitor

3. Reactor Building Elevated Discharge Radiation Monitor (b) a) Low Range (e) 1 C SR 6.1.2.1 (c)

Activity Monitor SR 6.1.2.4 SR 6.1.2.5 SR 6.1.2.6 b) Iodine Sampler (e) 1 E SR 6.1.2.3 N/A c) Particulate (e) 1 E SR 6.1.2.3 N/A Sampler d) Effluent System (e) 1 D SR 6.1.2.1 (d)

Flow Rate SR 6.1.2.5 Monitor SR 6.1.2.6

e. Sampler Flow (e) 1 D SR 6.1.2.1 (d)

Rate Monitor SR 6.1.2.5 SR 6.1.2.6 (a) When an Offgas Steam Jet Air Ejector is operating.

(b) When building exhaust is secured collect building ambient air samples and other data to characterize building out-leakage.

(c) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of RFO 6.2.2.1, Dose Rate-Gaseous Effluents are not exceeded.

(d) Alarm/trip setpoints shall be determined in accordance with the associated instrumentation specifications and set to ensure a representative sample is obtained.

(e) During building exhaust system operation.

(f) During startup and shutdown when vacuum is being maintained with a Mechanical Vacuum Pump and the Steam Seal System is operational.

Columbia Generating Station 6.1.2-7 Amendment 51, December 2013

Radioactive Gaseous Effluent Monitoring Instrumentation 6.1.2 Table 6.1.2-1 (page 2 of 2)

Radioactive Gaseous Effluent Monitoring Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM ALARM/

SPECIFIED PER COMPENSATORY SURVEILLANCE TRIP FUNCTION CONDITIONS FUNCTION MEASURE A.1 REQUIREMENTS SETPOINT

4. Turbine Building Ventilation Exhaust Radiation Monitor (b) a) Noble Gas (e) 1 C SR 6.1.2.1 (c)

Activity Monitor SR 6.1.2.4 Low Range SR 6.1.2.5 SR 6.1.2.6 b) Iodine Sampler (e) 1 E SR 6.1.2.3 N/A c) Particulate (e) 1 E SR 6.1.2.3 N/A Sampler d) Effluent System (e) 1 D SR 6.1.2.1 (d)

Flow Rate SR 6.1.2.5 Monitor SR 6.1.2.6

e. Sampler Flow (e) 1 D SR 6.1.2.1 (d)

Rate Monitor SR 6.1.2.5 SR 6.1.2.6

5. Radwaste Building Ventilation Exhaust Radiation Monitor (b) a) Noble Gas (e) 1 C SR 6.1.2.1 (c)

Activity Monitor SR 6.1.2.4 Low Range SR 6.1.2.5 SR 6.1.2.6 b) Iodine Sampler (e) 1 E SR 6.1.2.3 N/A c) Particulate (e) 1 E SR 6.1.2.3 N/A Sampler d) Effluent System (e) 1 D SR 6.1.2.1 (d)

Flow Rate SR 6.1.2.5 Monitor SR 6.1.2.6

e. Sampler Flow (e) 1 D SR 6.1.2.1 (d)

Rate Monitor SR 6.1.2.5 SR 6.1.2.6 (b) When building exhaust is secured collect building ambient air samples and other data to characterize building out-leakage.

(c) Alarm/trip setpoints shall be determined in accordance with ODCM methodology and set to ensure the limits of RFO 6.2.2.1, Dose Rate-Gaseous Effluents are not exceeded.

(d) Alarm/trip setpoints shall be determined in accordance with the associated instrumentation specifications and set to ensure a representative sample is obtained.

(e) During building exhaust system operation.

Columbia Generating Station 6.1.2-8 Amendment 50, May 2013

Liquid Concentration 6.2.1.1 6.2 RADIOACTIVE EFFLUENTS 6.2.1 Liquid Effluents 6.2.1.1 Liquid Concentration RFO 6.2.1.1 The concentration of radioactive material released in liquid effluents to Unrestricted Areas (see Figure 3-1) shall be limited to:

a. Ten times the concentration specified in Table 2, Column 2 of Appendix B to 10 CFR 20 for radionuclides other than dissolved or entrained noble gases; and

b. 2 E-4 Ci/ml total activity concentration for all dissolved or entrained noble gases.

APPLICABILITY: At all times.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Concentration of A.1 Initiate action to restore Immediately radioactive material concentration to within released to Unrestricted limits.

Areas not within limits.

Columbia Generating Station 6.2.1.1-1 Amendment 50, May 2013

Liquid Concentration 6.2.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.1.1.1 The radioactivity content of each batch of Prior to each radioactive liquid waste shall be determined prior to batch release release by sampling and analysis in accordance with Table 6.2.1.1-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of RFO 6.2.1.1.

SR 6.2.1.1.2 Post-release analysis of samples composited from In accordance batch releases shall be performed in accordance with with Table 6.2.1.1-1. The results of the post-release Table 6.2.1.1-1 analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of RFO 6.2.1.1.

Columbia Generating Station 6.2.1.1-2 Amendment 50, May 2013

Liquid Concentration 6.2.1.1 Table 6.2.1.1-1 (page 1 of 1)

Radioactive Liquid Waste Sampling and Analysis Program SAMPLE LOWER MINIMUM LIMIT OF SAMPLE TYPE OF DETECTION LIQUID RELEASE SAMPLE ANALYSIS ACTIVITY (LLD)

TYPE FREQUENCY FREQUENCY ANALYSIS Batch waste tank Prior to Prior to release Principal 5E-7 Ci/ml release release of of each batch Gamma each batch Emitters I-131 1E-6 Ci/ml Dissolved and 1E-5 Ci/ml entrained gases (gamma emitters)

Batch waste tank Prior to 31 days Tritium 1E-5 Ci/ml release release of composite each batch Gross Alpha 1E-7 Ci/ml Batch waste tank Prior to 92 days Fe-55 1E-6 Ci/ml release release of composite each batch Sr-89 5E-8 Ci/ml Sr-90 5E-8 Ci/ml Columbia Generating Station 6.2.1.1-3 Amendment 50, May 2013

Liquid Dose 6.2.1.2 6.2 RADIOACTIVE EFFLUENTS 6.2.1 Liquid Effluents 6.2.1.2 Liquid Dose RFO 6.2.1.2 The dose or dose commitment to a Member of the Public from radioactive materials in liquid effluents released to Unrestricted Areas (see ODCM Figure 3-1) shall be limited to:

a. 1.5 mrem to the whole body and 5 mrem to any organ during any calendar quarter; and

b. 3 mrem to the whole body and 10 mrem to any organ during any calendar year.

APPLICABILITY: When radioactive liquid effluents are released.

COMPENSATORY MEASURES

NOTE-----------------------------------------------------------

Enter applicable Conditions and Required Compensatory Measures of ODCM 6.2.3, "Total Dose," when the calculated dose from liquid effluents exceeds twice the limits of RFO 6.2.1.2.

REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Calculated dose from A.1 Submit a Special Report to 30 days the release of the NRC that identifies radioactive materials in causes for exceeding limits, liquid effluents to corrective actions taken to Unrestricted Areas not reduce releases, corrective within limits. actions to assure that subsequent releases will be in compliance with the required limits, results of radiological analyses of drinking water source, and the radiological impact on potentially affected drinking water supplies with regard to 40 CFR 141.

Columbia Generating Station 6.2.1.2-1 Amendment 50, May 2013

Liquid Dose 6.2.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.1.2.1 Verify the cumulative dose contributions from 31 days radioactive liquid effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Columbia Generating Station 6.2.1.2-2 Amendment 50, May 2013

Liquid Waste Management System 6.2.1.3 6.2 RADIOACTIVE EFFLUENTS 6.2.1 Liquid Effluents 6.2.1.3 Liquid Waste Management System RFO 6.2.1.3 The Liquid Waste Management System shall be Functional. Appropriate portions of the system shall be used to reduce the radioactive materials in liquid waste prior to discharge when the projected doses due to the liquid effluent, from the reactor unit to Unrestricted Areas, would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.

APPLICABILITY: At all times.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Liquid waste being A.1 Submit a Special Report to 30 days discharged without the NRC that includes treatment when explanation of why the RFO 6.2.1.3 limits are Liquid Waste Management exceeded. System was not Functional or why liquid radwaste was being discharged without treatment. The Special Report shall identify any required nonfunctional equipment and the reasons for the non-functionality, the corrective actions taken to restore the required nonfunctional equipment to Functional status, and the corrective actions to prevent recurrence.

Columbia Generating Station 6.2.1.3-1 Amendment 50, May 2013

Liquid Waste Management System 6.2.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.1.3.1 Dose due to liquid releases to Unrestricted Areas Prior to each shall be projected in accordance with the batch release methodology and parameters in the ODCM.

SR 6.2.1.3.2 The installed Liquid Waste Management System See RFOs 6.2.1.1 shall be demonstrated Functional by meeting and 6.2.1.2 RFOs 6.2.1.1 and 6.2.1.2.

Columbia Generating Station 6.2.1.3-2 Amendment 50, May 2013

Dose Rate 6.2.2.1 6.2 RADIOACTIVE EFFLUENTS 6.2.2 Gaseous Effluents 6.2.2.1 Dose Rate RFO 6.2.2.1 The dose rate at and beyond the Site Boundary (See Figure 3-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following:

a. For nobles gases, less than or equal to 500 mrem per year to the whole body and less than or equal to 3000 mrem per year to the skin; and

b. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days, less than or equal to 1500 mrem per year to any organ.

APPLICABILITY: At all times.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Dose rate from the A.1 Initiate action to restore Immediately release of radioactive dose rate to within limits.

materials in gaseous effluents at and beyond the Site Boundary not within limits.

Columbia Generating Station 6.2.2.1-1 Amendment 51, December 2013

Dose Rate 6.2.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.2.1.1 Verify the dose rate due to noble gases in gaseous In accordance effluents is within limits in accordance with with methodology and parameters in the ODCM. Table 6.2.2.1-1 SR 6.2.2.1.2 Verify dose rate due to iodine-131, iodine-133, In accordance tritium, and all radionuclides in particulate form with with half lives > 8 days in gaseous effluents is within Table 6.2.2.1-1 limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses.

Columbia Generating Station 6.2.2.1-2 Amendment 50, May 2013

Dose Rate 6.2.2.1 Table 6.2.2.1-1 Part 1 (Page 1 of 5)

Radioactive Gaseous Waste Sampling and Analysis Program Requirements Applicable At All Times SAMPLE TYPE SAMPLE MINIMUM TYPE OF SAMPLE LOWER FREQUENCY ANALYSIS ACTIVITY LIMIT OF FREQUENCY ANALYSIS DETECTION (LLD)

Primary Containment 31 days 31 days Tritium 1 E-6 Ci/ml (a)

Tritium Grab Sample Reactor Building Elevated 7 days 7 days Tritium 1 E-6 Ci/ml Discharge Vent Tritium Grab Sample Reactor Building Elevated 31 days 31 days Principal 1 E-4 Ci/ml Discharge Noble Gas Grab Gamma Sample Emitters Turbine and Radwaste 31 days 31 days Principal 1 E-4 Ci/ml Building Vent Noble Gas Gamma and Tritium Grab Samples Emitters Tritium 1 E-6 Ci/ml Charcoal Filter Sample (All Continuous 7 days I-131 1 E-12 Ci/ml Building Vents) (b)(c)

I-133 1 E-10 Ci/ml Particulate Filter Sample (All Continuous 7 days Principal 1 E-11 Ci/ml Building Vents) (b)(c) Gamma Emitters (a) Not required when Primary Containment is not required.

(b) 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 RFOs 6.2.2.1, 6.2.2.2, and 6.2.2.3.

(c) 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 the sampler.

Columbia Generating Station 6.2.2.1-3 Amendment 50, May 2013

Dose Rate 6.2.2.1 Table 6.2.2.1-1 Part 1 (Page 2 of 5)

Radioactive Gaseous Waste Sampling and Analysis Program Requirements Applicable At All Times SAMPLE TYPE SAMPLE MINIMUM TYPE OF SAMPLE LOWER FREQUENCY ANALYSIS ACTIVITY LIMIT OF FREQUENCY ANALYSIS DETECTION (LLD)

Composite of Particulate Continuous(b) 31 days Gross 1 E-11 Ci/ml Filter Samples (All Building Alpha Vents)

Composite of Particulate Continuous(b) 92 days Sr-89, 1 E-11 Ci/ml Filter Samples (All Building Sr-90 Vents)

Noble Gas (All Building Continuous Gross Beta 1 E-6 Ci/ml Vents) or Gamma (Xe-133 Equivalent)

(b) 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 RFOs 6.2.2.1, 6.2.2.2, and 6.2.2.3.

Columbia Generating Station 6.2.2.1-4 Amendment 50, May 2013

Dose Rate 6.2.2.1 Table 6.2.2.1-1 Part 2 (Page 3 of 5)

Radioactive Gaseous Waste Sampling and Analysis Program Requirements Applicable During Purge and Vent SAMPLE TYPE SAMPLE MINIMUM TYPE OF SAMPLE LOWER FREQUENCY ANALYSIS ACTIVITY LIMIT OF FREQUENCY ANALYSIS DETECTION (LLD)

Primary Containment Purge 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to Principal 1 E-4 Ci/ml and Vent Noble Gas, Iodine, each Purge each Purge Gamma and Particulate Grab and Vent and Vent Emitters Sample(d)(e)

(d) Sampling and analysis is not required for a Primary Containment Vent when the Vent path is through the Standby Gas Treatment System via the two-inch bypass line and when containment noble gas monitoring instrumentation indicates less than the alarm setpoint.

(e) If the Reactor Building Elevated Discharge Low Range Radiation Monitor is not Functional, sampling and analysis of the containment shall be completed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during Vent or Purge.

Columbia Generating Station 6.2.2.1-5 Amendment 50, May 2013

Dose Rate 6.2.2.1 Table 6.2.2.1-1 Part 3 (Page 4 of 5)

Radioactive Gaseous Waste Sampling and Analysis Program Requirements During Startup and Shutdown SAMPLE TYPE SAMPLE MINIMUM TYPE OF SAMPLE LOWER FREQUENCY ANALYSIS ACTIVITY LIMIT OF FREQUENCY ANALYSIS DETECTION (LLD)

Primary Containment and Once following Once following Principal 1 E-4 Ci/ml Reactor Building Elevated startup or startup or Gamma Discharge Noble Gas, shutdown shutdown Emitters Iodine, and Particulate Grab Sample Charcoal Filter Sample (All Continuous(b) (f) I-131 1 E-12 Ci/ml Building Vents)

I-133 1 E-10 Ci/ml Particulate Filter Sample (All Continuous(b) (f) Principal 1 E-11 Ci/ml Building Vents) Gamma Emitters (b) 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 RFOs 6.2.2.1, 6.2.2.2, and 6.2.2.3.

(f) Filters shall be removed from the continuous sampler at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown or startup, and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of filter removal. 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.

Requirement (f) does not apply if:

(1) a. Analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant is less than or equal to 1.0E-03 Ci/cc.

Or

b. When the DOSE EQUIVALENT I-131 concentration in the primary coolant is greater than 1.0E-03Ci/cc, but has not increased more than a factor of 3; And (2) a. When any building vent noble gas monitor is less than or equal to 2.0% of the setpoint determined in accordance with ODCM Section 3.4.

Or

b. When any building vent noble gas monitor is greater than 2.0% of its setpoint, but shows that effluent activity has not increased by more than a factor of 3.

Columbia Generating Station 6.2.2.1-6 Amendment 50, May 2013

Dose Rate 6.2.2.1 Table 6.2.2.1-1 Part 4 (Page 5 of 5)

Radioactive Gaseous Waste Sampling and Analysis Program Requirements During Reactor Power Changes SAMPLE TYPE SAMPLE MINIMUM TYPE OF SAMPLE LOWER FREQUENCY ANALYSIS ACTIVITY LIMIT OF FREQUENCY ANALYSIS DETECTION (LLD)

Primary Containment and (g) (g) Principal 1 E-4 Ci/ml Reactor Building Elevated Gamma Discharge Noble Gas, Emitters Iodine, and Particulate Grab Sample Charcoal Filter Sample (All Continuous(b) (h) I-131 1 E-12 Ci/ml Building Vents)

I-133 1 E-10 Ci/ml Particulate Filter Sample (All Continuous(b) (h) Principal 1 E-11 Ci/ml Building Vents) Gamma Emitters (b) 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 RFOs 6.2.2.1, 6.2.2.2, and 6.2.2.3.

(g) Grab sampling and analysis shall be performed following a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period when the noble gas release rate, as indicated by the main condenser offgas pretreatment monitor or temporary replacement monitor installed in accordance with Condition H of RFO 6.1.2, is greater than 15,000 Ci/sec.

(h) Filters shall be removed from the continuous samplers at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour when the noble gas release rate, as indicated by the main condenser offgas pretreatment monitor or temporary replacement monitor installed in accordance with Condition H of RFO 6.1.2, is greater than 15,000 Ci/sec. Analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of filter change. 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.

Requirement (h) does not apply if:

(1) a. Analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant is less than or equal to 1.0E-03 Ci/cc.

Or

b. When the DOSE EQUIVALENT I-131 concentration in the primary coolant is greater than 1.0E-03 Ci/cc, but has not increased more than a factor of 3; And (2) a. When any building vent noble gas monitor is less than or equal to 2.0% of the setpoint determined in accordance with ODCM Section 3.4.

Or

b. When any building vent noble gas monitor is greater than 2.0% of its setpoint, but shows that effluent activity has not increased by more than a factor of 3.

Columbia Generating Station 6.2.2.1-7 Amendment 55, August 2016

Dose - Noble Gases 6.2.2.2 6.2 RADIOACTIVE EFFLUENTS 6.2.2 Gaseous Effluents 6.2.2.2 Dose - Noble Gases RFO 6.2.2.2 The air dose at and beyond the Site Boundary from noble gases in gaseous effluents from the site shall be limited to the following:

a. 5 mrads gamma radiation and 10 mrads beta radiation during any calendar quarter; and

b. 10 mrads gamma radiation and 20 mrads beta radiation during any calendar year.

APPLICABILITY: At all times.

COMPENSATORY MEASURES

NOTE-----------------------------------------------------------

Enter applicable Conditions and Required Compensatory Measures of 6.2.3, Total Dose, when gaseous effluent (noble gas) dose exceeds twice the limits of RFO 6.2.2.2.

REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Calculated air dose from A.1 Submit a Special Report to 30 days radioactive noble gases the NRC that identifies in gaseous effluents in causes for exceeding the the Unrestricted Area limits, corrective actions not within limits. taken to reduce releases, and corrective actions to assure that subsequent releases are within limits.

Columbia Generating Station 6.2.2.2-1 Amendment 50, May 2013

Dose - Noble Gases 6.2.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.2.2.1 Verify the cumulative dose contributions from noble 31 days gases in gaseous effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Columbia Generating Station 6.2.2.2-2 Amendment 50, May 2013

Dose - I-131, I-133, Tritium, and Radionuclides in Particulate Form 6.2.2.3 6.2 RADIOACTIVE EFFLUENTS 6.2.2 Gaseous Effluents 6.2.2.3 Dose - I-131, I-133, Tritium, and Radionuclides in Particulate Form RFO 6.2.2.3 The dose to any organ of a Member of the Public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released to the Unrestricted Area shall be limited to the following:

a. 7.5 mrems during any calendar quarter; and

b. 15 mrems during any calendar year.

APPLICABILITY: At all times.

COMPENSATORY MEASURES

NOTE-----------------------------------------------------------

Enter applicable Conditions and Required Compensatory Measures of 6.2.3, Total Dose, when gaseous effluent dose from I-131, I-133, Tritium, and Radionuclides in Particulate Form exceeds twice the limits of RFO 6.2.2.3.

REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Calculated dose from A.1 Submit a Special Report to 30 days the release of iodine- the NRC that identifies 131, iodine-133, tritium, causes for exceeding the and radionuclides in limits, corrective actions particulate form with taken to reduce releases, half-lives > 8 days, in and corrective actions to gaseous effluents in the assure that subsequent Unrestricted Area not releases are within limits.

within limits.

Columbia Generating Station 6.2.2.3-1 Amendment 50, May 2013

Dose - I-131, I-133, Tritium, and Radionuclides in Particulate Form 6.2.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.2.3.1 Verify the cumulative dose contributions from 31 days iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives > 8 days, in gaseous effluents for the current calendar quarter and current calendar year are within limits in accordance with the methodology and parameters in the ODCM.

Columbia Generating Station 6.2.2.3-2 Amendment 50, May 2013

Gaseous Offgas Treatment System 6.2.2.4 6.2 RADIOACTIVE EFFLUENTS 6.2.2 Gaseous Effluents 6.2.2.4 Gaseous Offgas Treatment System RFO 6.2.2.4 The Gaseous Offgas Treatment System shall be in operation in either:

a. The normal mode; or

b. The charcoal bypass mode, provided the offgas post-treatment radiation monitor is Functional as specified in Table 6.1.2-1.

APPLICABILITY: Whenever the main condenser steam jet air ejector system is in operation.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Gaseous Offgas A.1 Place Gaseous Offgas 7 days Treatment System not in Treatment System in the the normal mode of normal mode of operation.

operation.

B. Required Compensatory B.1 Submit a Special Report to 30 days Measure A.1 and the NRC that identifies the associated Completion required nonfunctional Time not met. equipment and the reasons for the non-functionality, corrective actions taken to restore the required nonfunctional equipment to Functional status, and the corrective actions to prevent recurrence.

Columbia Generating Station 6.2.2.4-1 Amendment 50, May 2013

Gaseous Offgas Treatment System 6.2.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.2.4.1 Verify Gaseous Offgas Treatment System in 7 days operation in either:

a) The normal mode; or b) The charcoal bypass mode, provided the offgas post-treatment radiation monitor is Functional.

Columbia Generating Station 6.2.2.4-2 Amendment 50, May 2013

Ventilation Exhaust Treatment System 6.2.2.5 6.2 RADIOACTIVE EFFLUENTS 6.2.2 Gaseous Effluents 6.2.2.5 Ventilation Exhaust Treatment System RFO 6.2.2.5 The appropriate portions of the Ventilation Exhaust Treatment System shall be Functional. The system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent, from the reactor unit to a Member of the Public in the Unrestricted Areas when averaged over 31 days, would exceed 0.3 mrem to any organ in a 31 day period.

APPLICABILITY: At all times.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Gaseous waste being A.1 Submit a Special Report to 30 days discharged without the NRC that identifies Ventilation Exhaust nonfunctional equipment or Treatment System subsystems and the treatment when reasons for non-projected organ dose functionality, the corrective exceeds 0.3 mrem. actions taken to restore the nonfunctional equipment to Functional status, and the corrective actions to prevent recurrence.

Columbia Generating Station 6.2.2.5-1 Amendment 50, May 2013

Ventilation Exhaust Treatment System 6.2.2.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.2.5.1 Determine the projected organ doses due to 31 days gaseous releases to a Member of the Public in the Unrestricted Area in accordance with the methodology and parameters in the ODCM.

SR 6.2.2.5.2 The installed Ventilation Exhaust Treatment System Once per 92 days shall be demonstrated Functional by operating by complying with RFOs 6.2.2.1 and 6.2.2.3.

Columbia Generating Station 6.2.2.5-2 Amendment 50, May 2013

Venting or Purging 6.2.2.6 6.2 RADIOACTIVE EFFLUENTS 6.2.2 Gaseous Effluents 6.2.2.6 Venting or Purging RFO 6.2.2.6 Venting or Purging of the primary containment shall be:

a. Through one functional-for-filtration Standby Gas Treatment (SGT) System train during MODES 1, 2, or 3 provided the other train is OPERABLE during the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of any Venting or Purging operation; or

b. Through one or two functional-for-filtration SGT System train(s) when deinerting the containment in MODE 4 during the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of any Venting or Purging operation; or

c. Through the Primary Containment Vent and Purge System when not using SGT following the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of any Venting and Purging operation.

APPLICABILITY: MODES 1, 2, and 3 when Venting or Purging and when deinerting the containment. Not applicable during containment depressurization following 10 CFR 50, Appendix J, Type A testing.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Requirements of 6.2.2.6 A.1 Suspend Venting and Immediately not met. Purging of the containment.

Columbia Generating Station 6.2.2.6-1 Amendment 50, May 2013

Venting or Purging 6.2.2.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.2.6.1 Verify the containment is aligned for Venting or Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Purging through the SGT System or the Primary prior to the start Containment Vent and Purge System. and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during Purging or Venting Columbia Generating Station 6.2.2.6-2 Amendment 50, May 2013

Total Dose 6.2.3 6.2 RADIOACTIVE EFFLUENTS 6.2.3 Total Dose RFO 6.2.3 The annual dose or dose commitment to a Member of the Public in the Unrestricted Area beyond the Site Boundary due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to:

a. 25 mrem to the whole body or any organ except the thyroid; and

b. 75 mrem to the thyroid.

APPLICABILITY: At all times.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Calculated dose to any A.1 ---------------NOTE--------------

Member of the Public in Calculations shall include the Unrestricted Area direct radiation exceeds twice the limits contributions from the of 6.2.1.2, 6.2.2.2, or reactor, outside storage 6.2.2.3. tanks, and the Independent Spent Fuel Storage Installation (ISFSI).

Calculate the dose or dose Immediately commitment to a Member of the Public from all uranium fuel cycle sources to determine if specified limits of RFO 6.2.3 were exceeded.

Columbia Generating Station 6.2.3-1 Amendment 50, May 2013

Total Dose 6.2.3 COMPENSATORY MEASURES (continued)

REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME B. Calculated dose or dose B.1 Submit a Special Report to 30 days commitment exceeds the NRC pursuant to specified limits of 10 CFR 50, Appendix I, RFO 6.2.3. Section IV.A, that includes corrective actions taken to prevent recurrence, the schedule for achieving conformance with required limits, an analysis that estimates the radiation exposure to a Member of the Public from uranium fuel cycle sources for the calendar year, descriptions of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

AND B.2 ---------------NOTE--------------

1. Only applicable if the release condition resulting in violation of 40 CFR 190 has not been corrected.

2. Special Report submitted is considered a timely request and a variance is granted until NRC action on the request is complete.

Submit a request for a 30 days variance in accordance with 40 CFR 190 in the Special Report to the NRC.

Columbia Generating Station 6.2.3-2 Amendment 50, May 2013

Total Dose 6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.2.3.1 Cumulative dose contributions from liquid and 31 days gaseous effluents shall be determined in accordance with SRs 6.2.1.2.1, 6.2.2.2.1, and 6.2.2.3.1.

Columbia Generating Station 6.2.3-3 Amendment 50, May 2013

Radiological Environmental Monitoring Program 6.3.1 6.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.3.1 Radiological Environmental Monitoring Program RFO 6.3.1 The Radiological Environmental Monitoring Program shall be as follows:

a. Radiological Environmental Monitoring samples shall be collected at locations and analyzed as specified in Table 6.3.1-1;

b. The level of radioactivity as the result of plant effluents for a single radionuclide in each environmental sampling medium at a required location shall be less than the limits specified in Table 6.3.1-2, when averaged over the calendar quarter;

c. The total level of radioactivity in multiple detected radionuclides as the result of plant effluents in each environmental sampling medium at a required location shall be less than the limit specified in Table 6.3.1-2, when averaged over the calendar quarter; and

d. The potential annual dose to the Member of the Public from all radionuclides other than those in Table 6.3.1-2 in each environmental sampling medium at a required location shall be less than the calendar year limits of RFOs 6.2.1.2, 6.2.2.2, and 6.2.2.3.

APPLICABILITY: At all times.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. One or more samples A.1 Prepare and submit, in the Upon submittal of not collected or analyzed Annual Radiological current Annual as specified in Environmental Operating Radiological Table 6.3.1-1. Report, a description for not Environmental conducting the Radiological Operating Report Environmental Monitoring sampling and analysis requirements as required and the corrective actions to prevent recurrence.

Columbia Generating Station 6.3.1-1 Amendment 50, May 2013

Radiological Environmental Monitoring Program 6.3.1 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME B. ------------NOTE------------ B.1 Identify locations for 30 days Separate Condition entry obtaining replacement is allowed for each samples and replace, in the sample location. Radiological Environmental

Monitoring Program, the location(s) from which One or more sample samples are unavailable locations required by with the new location(s).

Table 6.3.1-1 with milk or fresh leafy vegetable AND samples unavailable.

B.2 Prepare and submit, in the Upon submittal of Radiological Environmental current Radiological Operating Report, the Environmental cause of the unavailability Operating Report of samples, the new locations for obtaining replacement samples, and the revised figure(s) and table(s) for the ODCM reflecting the new locations.

Columbia Generating Station 6.3.1-2 Amendment 50, May 2013

Radiological Environmental Monitoring Program 6.3.1 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME C. ------------NOTE------------ C.1 Submit a Special Report to 30 days Separate Condition entry the NRC which includes the is allowed for each cause(s) for exceeding the sample location. limit(s) and the corrective

actions to reduce radioactive effluents so that One or more sample the potential annual dose to locations with the level a Member of the Public is of radioactivity for one less than the calendar year radionuclide as the reporting limits of RFOs result of plant effluents 6.2.1.2, 6.2.2.2, and in an environmental 6.2.2.3.

sampling medium not within the limits of Table 6.3.1-2 when averaged over the calendar quarter.

OR One or more sample locations with the total level of radioactivity for more than one radionuclide as a result of plant effluents in an environmental sampling medium not within the limits of Table 6.3.1-2 when averaged over the calendar quarter.

Columbia Generating Station 6.3.1-3 Amendment 50, May 2013

Radiological Environmental Monitoring Program 6.3.1 COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME D. One or more sample D.1 ---------------NOTE--------------

locations with the Only required if the potential annual dose to radionuclides are the result the Member of the of plant effluents.

Public from -------------------------------------

radionuclides other than those in Table 6.3.1-2 Submit a Special Report to 30 days not within limits. the NRC which includes the cause(s) for exceeding the limit(s) and the corrective actions to reduce radioactive effluents so that the potential annual dose to a Member of the Public is less than the calendar year limits of RFOs 6.2.1.2, 6.2.2.2, and 6.2.2.3.

AND D.2 ---------------NOTE--------------

Only required if the radionuclides are not the result of plant effluents.

Describe the condition in Upon submittal of the the Annual Radiological current calendar year Environmental Operating Annual Radiological Report. Environmental Operating Report Columbia Generating Station 6.3.1-4 Amendment 50, May 2013

Radiological Environmental Monitoring Program 6.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.3.1.1 Verify radiological environmental monitoring In accordance samples collected at the locations and analyzed as with Table 6.3.1-1 specified in Table 6.3.1-1 are within limits.

Detection capabilities for the analysis are specified in Table 6.3.1-3.

Columbia Generating Station 6.3.1-5 Amendment 50, May 2013

Radiological Environmental Monitoring Program 6.3.1 TABLE 6.3.1-1 (page 1 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND PATHWAY SAMPLES AND SAMPLE COLLECTION FREQUENCY AND/OR SAMPLE LOCATIONS (a) FREQUENCY OF ANALYSIS

1. DIRECT Thirty-four routine monitoring stations Quarterly Gamma dose RADIATION (b) either with two or more dosimeters or quarterly 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.

An outer ring of stations, one in each of the meteorological sectors of NE, ENE, E, ESE, SE in the six to ten km (3.73 to 6.21 miles) range from the site, and one in each of the meteorological sectors of N, NNE, SSE, S, SSW in the nine to thirteen km (5.59 to 8.08 miles) range from the site.

The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and one or two areas to serve as control stations.

Additional monitoring stations for the Independent Spent Fuel Storage Installation (ISFSI).

(a) Specific parameters of distance and direction sector relative to the reactor are provided for each sample location in Table 5-1. Refer to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. When sample media is unobtainable due to equipment malfunction, corrective actions should be taken to ensure equipment is returned to Functional status prior to the end of the next sampling period. In some cases, alternate sample collection may be substituted for the missing specimen.

(b) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor card with multiple readout areas; a phosphor card in a packet is considered to be equivalent to two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation. (The number of direct radiation monitoring stations may be reduced according to geographical limitations. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.)

Columbia Generating Station 6.3.1-6 Amendment 54, March 2016

Radiological Environmental Monitoring Program 6.3.1 TABLE 6.3.1-1 (page 2 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND PATHWAY SAMPLES AND SAMPLE COLLECTION FREQUENCY AND/OR SAMPLE LOCATIONS (a) FREQUENCY OF ANALYSIS

2. AIRBORNE Samples from six locations: Continuous Radioiodine Radioiodine sampler operation Canister:

and One sample from close to the Site with sample I-131 analysis Particulates Boundary location, having a high collection weekly, weekly.

calculated annual average ground- or more frequently level D/Q. if required by dust Particulate loading. Sampler:

Three samples from close to the Gross beta three Columbia River locations having radioactivity the highest calculated D/Q. analysis following filter change,(c)

One sample from the vicinity of a community having the highest calculated annual average ground-level D/Q.

One sample from a control location, Gamma greater than 30 km (18.64 mi) from isotopic Columbia Generating Station (CGS) analysis (d) of and in a sector not likely to be composite (by influenced by CGS. location) quarterly.

(a) Specific parameters of distance and direction sector relative to the reactor are provided for each sample location in Table 5-1. Refer to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. When sample media is unobtainable due to equipment malfunction, corrective actions should be taken to ensure equipment is returned to Functional status prior to the end of the next sampling period. In some cases, alternate sample collection may be substituted for the missing specimen.

(c) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 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 thorium daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall 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.

Columbia Generating Station 6.3.1-7 Amendment 54, March 2016

Radiological Environmental Monitoring Program 6.3.1 TABLE 6.3.1-1 (page 3 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND PATHWAY SAMPLES AND SAMPLE COLLECTION FREQUENCY AND/OR SAMPLE LOCATIONS (a) FREQUENCY OF ANALYSIS

3. WATERBORNE

a. Surface (e) One sample upstream Composite sample Gamma One sample downstream over one month isotopic period.(f) analysis (d) monthly.

Composite for tritium analysis quarterly.

b. Ground Samples from one or two sources Quarterly. Gamma only if likely to be affected.(g) isotopic (d) and tritium analysis quarterly.

(a) Specific parameters of distance and direction sector relative to the reactor are provided for each sample location in Table 5-1. Refer to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. When sample media is unobtainable due to equipment malfunction, corrective actions should be taken to ensure equipment is returned to Functional status prior to the end of the next sampling period. In some cases, alternate sample collection may be substituted for the missing specimen.

(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 "upstream sample" shall be taken from the Tower Makeup (TMU) intake line. The "downstream" sample shall be taken from the Circulating Water Blowdown (CBD) discharge line.

(f) A composite sample is one in which the quantity (aliquot) of liquid is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(g) Groundwater samples shall 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.

Columbia Generating Station 6.3.1-8 Amendment 54, March 2016

Radiological Environmental Monitoring Program 6.3.1 TABLE 6.3.1-1 (page 4 of 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND PATHWAY SAMPLES AND SAMPLE COLLECTION FREQUENCY AND/OR SAMPLE LOCATIONS (a) FREQUENCY OF ANALYSIS

3. WATERBORNE (continued)

c. Drinking One sample of each of one to three of Composite sample I-131 analysis the nearest water supplies that could over two week on each (f) be affected by its discharge. period when composite I-131 analysis is when the dose performed; calculated for monthly composite the otherwise. consumption of the water is greater than one mrem per (h) year.

One sample from a control location. Composite for gross beta and gamma isotopic analysis (d) monthly.

Composite for tritium analysis quarterly.

d. Sediment One sample from downstream area Semiannually. Gamma from with existing or potential recreational isotopic (d) shoreline value. analysis semiannually.

(a) Specific parameters of distance and direction sector relative to the reactor are provided for each sample location in Table 5-1. Refer to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. When sample media is unobtainable due to equipment malfunction, corrective actions should be taken to ensure equipment is returned to Functional status prior to the end of the next sampling period. In some cases, alternate sample collection may be substituted for the missing specimen.

(d) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(f) A composite sample is one in which the quantity (aliquot) of liquid is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(h) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

Columbia Generating Station 6.3.1-9 Amendment 54, March 2016

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Radiological Environmental Monitoring Program 6.3.1 TABLE 6.3.1-2 (page 1 of 1)

REPORTING LEVELS FOR RADIOACTIVITY (b)

CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE PARTICULATE FOOD WATER OR GASES FISH MILK PRODUCTS ANALYSIS (pCi/L) (pCi/m3) (pCi/kg, wet) (pCi/L) (pCi/kg, wet)

(a)

H-3 2 E4 Mn-54 1 E3 3 E4 Fe-59 4 E2 1 E4 Co-58 1 E3 3 E4 Co-60 3 E2 1 E4 Zn-65 3 E2 2 E4 Zr-Nb-95 4 E2 I-131 2 0.9 3 1 E2 Cs-134 30 10 1 E3 60 1 E3 Cs-137 50 20 2 E3 70 2 E3 Ba-La-140 2 E2 3 E2 (a) For drinking water samples. The value given is the 40 CFR 141 value. If no drinking water pathway exists, a value of 30,000 pCi/L may be used.

(b) The limits are for samples that have only one radionuclide detected. When a sample contains more than one radionuclide, the total level of radioactivity limit is concentration (1) concentration (2)

... d 1.0 reporting level (1) reporting level (2)

Columbia Generating Station 6.3.1-12 Amendment 50, May 2013

Radiological Environmental Monitoring Program 6.3.1 TABLE 6.3.1-3 (page 1 of 1)

(a)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (b)(c)

LOWER LIMIT OF DETECTION (LLD)

AIRBORNE PARTICULATE FISH FOOD WATER OR GASES (pCi/kg, MILK PRODUCTS SEDIMENT 3

ANALYSIS (pCi/L) (pCi/m ) wet) (pCi/L) (pCi/kg, wet) (pCi/kg, dry)

Gross beta 4 1 E-2 H-3 2000(d)

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 7 E-2 1 60 Cs-134 15 5 E-2 130 15 60 150 Cs-137 18 6 E-2 150 18 80 180 Ba-La-140 15 15 (a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

(b) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, except for specification regarding energy dependence.

Correction factors shall be provided for energy ranges not meeting the energy dependence specification.

(c) The LLD is defined in the ODCM definitions section. 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.

(d) If no drinking water pathway exists, a value of 3,000 pCi/L may be used.

Columbia Generating Station 6.3.1-13 Amendment 50, May 2013

Land Use Census 6.3.2 6.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.3.2 Land Use Census RFO 6.3.2 A Land Use Census shall be conducted and:

a. Shall identify the location of the nearest milk animal, residence, and garden of greater than 500 ft2 producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 5 miles;

b. The calculated dose and dose commitment at each newly identified census location shall be less than the most recent values calculated by SR 6.2.2.3.1 at the previous census location.

APPLICABILITY: At all times.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Land Use Census not A.1 Prepare and submit the Upon submittal of conducted. reasons for not conducting current calendar year the Land Use Census and Radiological OR the corrective actions to Environmental prevent recurrence. Operating Report All required locations not identified.

B. One or more newly B.1 Identify new location(s) in Upon submittal of the identified census the Radioactive Effluent current calendar year locations with the Release Report. Radioactive Effluent calculated dose or dose Release Report commitment greater than the values calculated by SR 6.2.2.3.1 at the current census locations.

Columbia Generating Station 6.3.2-1 Amendment 50, May 2013

Land Use Census 6.3.2 COMPENSATORY MEASURES (continued)

REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME C. One or more newly C.1 Add the new location to the 30 days identified census Radiological Environmental locations with the Monitoring Program.

calculated dose or dose commitment, via the AND same exposure pathway, > 120% of the C.2 Delete the sampling After October 31 of calculated dose or dose location having the lowest the year in which commitment from the calculated dose or dose Land Use Census current sample location commitment, via the same was conducted identified in exposure pathway, from the Table 6.3.1-1. Radiological Monitoring Program.

AND C.3 Identify the new location(s) Upon submittal of the in the Radioactive Effluent current calendar year Release Report, and the Radioactive Effluent revised figures and tables Release Report for the ODCM reflecting the new location.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.3.2.1 Conduct a Land Use Census during the growing Each calendar season by a door-to-door survey, aerial survey, or year during the by consulting local agriculture authorities and report growing season the results in the Annual Radiological Environmental Operating Report.

Columbia Generating Station 6.3.2-2 Amendment 50, May 2013

Interlaboratory Comparison Program 6.3.3 6.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.3.3 Interlaboratory Comparison Program RFO 6.3.3 Analyses shall be performed on all radioactive materials supplied as part of an Interlaboratory Comparison Program approved by the NRC.

APPLICABILITY: At all times.

COMPENSATORY MEASURES REQUIRED CONDITION COMPENSATORY MEASURE COMPLETION TIME A. Requirements of A.1 Prepare and submit, in the Upon submittal of RFO 6.3.3 not met. Annual Radiological current calendar year Environmental Operating Annual Radiological Report, corrective actions Environmental to prevent recurrence. Operating Report SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 6.3.3.1 Perform analysis on all radioactive material supplied Annually as part of the Interlaboratory Comparison Program as described in the OCDM and submit the results in the next annual Radiological Environmental Operating Report.

Columbia Generating Station 6.3.3-1 Amendment 50, May 2013

Annual Radiological Environmental Operating Report 6.4.1 6.4 REPORTING REQUIREMENTS 6.4.1 Annual Radiological Environmental Operating Report Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year.

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 Requirement for Operability 6.3.2.

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 the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. 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(a) covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor; the results of license participation in the Interlaboratory Comparison Program, required by Requirement for Operability 6.3.3; discussion of all deviations from the sampling schedule of Table 6.3.1-1; and discussion of all analyses in which the LLD required by Table 6.3.1-3 was not achievable.

(a)

One map shall cover stations near the Site Boundary; a second shall include the more distant stations.

Columbia Generating Station 6.4.1-1 Amendment 50, May 2013

Radioactive Effluent Release Report 6.4.2 6.4 REPORTING REQUIREMENTS 6.4.2 Radioactive Effluent Release Report The routine Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a(a)(2).

The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents 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 Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year.

This annual summary may be either in the form of an hour-by-hour listing 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 (ODCM Figure 3-1) 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 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 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

Columbia Generating Station 6.4.2-1 Amendment 50, May 2013

Radioactive Effluent Release Report 6.4.2 Radioactive Effluent Release Report (continued)

The Radioactive Effluent Release Report shall include a report of solid waste transported from the site during the year as specified by Regulatory Guide 1.2.1, Revision 1, June 1974, "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."

The Radioactive Effluent Release Reports shall 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.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the Process Control Program (PCP) and to the ODCM, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to RFO 6.3.2.

Columbia Generating Station 6.4.2-2 Amendment 50, May 2013

Major Changes To Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems 6.4.3 6.4 REPORTING REQUIREMENTS 6.4.3 Major Changes To Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems

NOTE-----------------------------------------------------------

Licensees may choose to submit the information called for in this specification as part of the periodic FSAR update.

Licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):

a. Shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the POC.

The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made without prior NRC approval;

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3. A detailed description of the equipment, components, and processes involved and the interface with other plant systems;

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

5. An evaluation of the change, which shows the expected maximum exposures to a Member of the Public in the Unrestricted Area and to the general population that differ from those previously estimated in the license application and amendments thereto;

6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

7. An estimate of the exposure to plant operating personnel as a result of the change; and Columbia Generating Station 6.4.3-1 Amendment 50, May 2013

Major Changes To Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems 6.4.3 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid): (continued)

a. (continued)

8. Documentation of the fact that the change was reviewed and found acceptable by the POC.

b. Shall become effective upon review and acceptance by the POC.

Columbia Generating Station 6.4.3-2 Amendment 50, May 2013

ODCM APPENDIX COLUMBIA GENERATING STATION Bases For Radiological Effluent And Radiological Environmental Monitoring Controls

Radioactive Liquid Effluent Monitoring Instrumentation B 6.1.1 B 6.1 INSTRUMENTATION B 6.1.1 Radioactive Liquid Effluent Monitoring Instrumentation BASES BACKGROUND The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, releases of radioactive material in liquid effluents during normal plant operation. They are also provided to monitor potential releases from anticipated operational transients. These instruments are required by General Design Criteria 60, 63, and 64 of Reference 1. Setpoints for these instruments are established by the methodology of ODCM Section 2.0 to ensure compliance with the limits of Reference 2. Specific requirements for this instrumentation are provided in the Radiological Effluent Technical Specifications for BWRs (Ref. 3).

Additional guidance is provided in References 4 and 5.

APPLICABLE The radioactive liquid effluent monitoring instrumentation provides SAFETY assurance that radioactive releases resulting from normal operation and ANALYSES any potential radioactive releases caused by Anticipated Operational Transients are monitored. Chapter 15, Accident Analysis, of the FSAR (Ref. 6) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased radioactive liquid effluent releases. Additional information on the Radioactive Liquid Process and Effluent Radiation Monitoring System can be found in Reference 7. The liquid process and effluent radiation monitors are listed in Reference 8.

REQUIREMENTS 1. Liquid Radwaste Effluent Line Gross Radioactivity Monitor FOR OPERABILITY This monitor measures the radioactivity in the liquid effluent prior to its entering the cooling tower blowdown line. All radioactive liquid effluent passes through this four inch line. The detector has seven decades of range and has a sensitivity of 10E-6 Ci/cc for Cs-137. This monitor will automatically close a valve stopping the effluent release if its setpoint is exceeded. Reference 9 provides additional information on this monitor.

2. Deleted

3. Turbine Service Water (TSW) System Gross Radioactivity Monitor The TSW System provides for the removal of heat from balance of plant auxiliary equipment (Ref. 11). It is normally a non-radioactive system but it has the potential to become contaminated because it provides cooling to some reactor auxiliary systems. This radioactivity monitor is provided to detect that off-normal condition Columbia Generating Station B 6.1.1-1 Amendment 50, May 2013

Radioactive Liquid Effluent Monitoring Instrumentation B 6.1.1 BASES REQUIREMENTS FOR OPERABILITY (continued) by monitoring for radioactivity in the TSW return header to the Circulating Water System. The monitor is located on the 441' level of the turbine building. The readout meter and recorder are located in the main control room panel BD-RAD-24.

If the setpoint is exceeded, an alarm will activate in the main control room. The control room operator can then evaluate and take action to terminate the discharge and mitigate any uncontrolled release of radioactive material. Reference 12 provides additional information on this subsystem.

4. Standby Service Water (SW) System Gross Radioactivity Monitor The SW System provides cooling to the reactor during normal shutdown conditions. It also provides cooling of the reactor during emergency conditions (Ref. 13). The SW system has the potential to become contaminated because of its interface with the heat exchangers that cool the reactor. This radiation monitor is provided to detect any increase in radioactivity in the system.

The SW monitors are located on the 501 and 522 foot level of the reactor building, with meters located in the main control room on panel P-604.

If the setpoint is exceeded, an alarm will activate in the main control room. The control room operator can then evaluate and take action to terminate the discharge and mitigate any uncontrolled release of radioactive material. Reference 14 provides further information on this subsystem.

5. Liquid Radwaste Effluent Line Flow Rate Monitor This flow rate monitor measures the flow of effluent from the Liquid Waste Management System. This flow is variable from zero to 190 gpm. The flow rate recorder is located in the radwaste control room. Two displays of flow are provided: the red pen spans a flow rate from zero to 270 gpm and the green pen from zero to 35 gpm.

6. Plant Discharge Blowdown Line Flow Rate Monitor This instrument measures the flow in the circulating water (CW) blowdown line. Water from the CW System is returned to the Columbia River in order to prevent the buildup of dissolved solids in the cooling water. This flow is recorded (range 0 - 7500 gpm) in the Columbia Generating Station B 6.1.1-2 Amendment 50, May 2013

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Radioactive Liquid Effluent Monitoring Instrumentation B 6.1.1 BASES COMPENSATORY MEASURES (continued) in 30 days, it must be reported in the Radioactive Effluent Release Report. This provides the NRC with information on the status of nonfunctional equipment.

A.1, C.1, C.2, and E.1 These Compensatory Measures are required to be taken if the TSW, or SW Gross Radioactivity Monitors (Functions 3, and 4) are nonfunctional.

Grab samples are required to be taken and analyzed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months frequency provides an adequate indication of the trend of radioactivity in these locations when the monitor is not Functional. The channel instrument must also be restored to Functional status within 30 days. The 30 day limit provides an acceptable risk for this loss of monitoring condition. If the monitor is not restored to Functional status in 30 days, it must be reported in the Radioactive Effluent Release Report.

A.1, D.1, D.2, and E.1 These Compensatory Measures are associated with the Liquid Radwaste Effluent Line and Plant Discharge Line Flow Rates. These flow rates are required to determine the concentration of the effluents released. If the Liquid Radwaste Effluent Flow Monitor is not Functional and a release is to occur the flow must be estimated. This is done by observing the level in the tank being pumped initially and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The combination of tank level and time can be used to estimate the flow. If the Plant Discharge Blowdown Line Flow Rate Monitor is not Functional during a radioactive release, blowdown flow must also be estimated. Methods of estimating this flow rate using pump differential pressure are given in plant procedures. A release can occur with no dilution from the blowdown line if the concentration of radioactivity being releases is low enough to meet limits without dilution.

SURVEILLANCE SR 6.1.1.1 REQUIREMENTS A CHANNEL CHECK is required every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when a monitor is required to be functional. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months time interval provides assurance that the instrument will perform its function if needed.

A CHANNEL CHECK for the flow instruments associated with a batch release is required before a radioactive release and every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter until the release is complete. This ensures the flow instruments are Functional prior to and during a batch release.

Columbia Generating Station B 6.1.1-4 Amendment 50, May 2013

Radioactive Liquid Effluent Monitoring Instrumentation B 6.1.1 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 6.1.1.2 The Liquid Radwaste Effluent Line Monitor is used for batch releases and a Source Check must be performed prior to each release. This provides increased confidence that the instrument will operate as required to prevent further releases if its trip setpoint is exceeded.

SR 6.1.1.3 A Source Check is required monthly to ensure all gross radioactivity monitors are functional. The monthly interval provides adequate reliability of instrument operation if needed to perform its function.

SR 6.1.1.4 A CHANNEL FUNCTIONAL TEST is required on all Radioactive Liquid Monitoring Instrumentation listed on Table 6.1.1-1 quarterly. This test interval is adequate to ensure the instrument will perform its complete function. The CHANNEL FUNCTIONAL TEST for the Liquid Radwaste Effluent Line must demonstrate automatic isolation of the effluent pathway.

The CHANNEL FUNCTIONAL TEST for all gross radioactivity monitors must demonstrate that control room annunciation occurs if the:

a) instrument indicates measured levels above the alarm setpoint, b) high voltage abnormally low, and c) instrument indicates downscale failure.

These tests are required to provide assurance of channel operation. In addition, the Liquid Radwaste Effluent Line and SW Gross Radioactivity Monitors must demonstrate control room alarm annunciation if the instrument controls are not set in the operate mode. This test provides increased assurance that the plant operators are aware of a nonfunctional instrument.

Columbia Generating Station B 6.1.1-5 Amendment 50, May 2013

Radioactive Liquid Effluent Monitoring Instrumentation B 6.1.1 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 6.1.1.5 A CHANNEL CALIBRATION shall be performed on all Radioactive Liquid Monitoring Instrumentation listed on Table 6.1.1-1 every 18 months. This time interval provides adequate protection against drift and other changes in the instrument performance. For the gross radioactivity monitors the initial CHANNEL CALIBRATION shall be performed using one or more reference standards certified by the National Institute of Science 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. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. These standards provide assurance of instrument accuracy.

REFERENCES 1. 10 CFR 50, Appendix A.

2. 10 CFR 20.1001-20.2402.

3. NUREG-0473, Revision 2.

4. NUREG-0133.

5. NUREG-1302.

6. FSAR Section 15.0.3.

7. FSAR Section 11.5.2.2.2.

8. FSAR Table 11.5-2.

9. FSAR Section 11.5.2.2.2.3.

10. FSAR Section 11.5.2.2.2.5.

11. FSAR Section 9.2.1.

12. FSAR Section 11.5.2.2.2.4.

13. FSAR Section 9.2.7.

14. FSAR Section 11.5.2.1.4.

15. FSAR Section 11.2.3.1.

Columbia Generating Station B 6.1.1-6 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 B 6.1 INSTRUMENTATION B 6.1.2 Radioactive Gaseous Effluent Monitoring Instrumentation BASES BACKGROUND The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, releases of radioactive material in gaseous effluents. These instruments are required by General Design Criteria 60, 63, and 64 of Reference 1. Setpoints for these instruments are established by the methodology of ODCM Section 3.0 to ensure compliance with the limits of Reference 2. Specific requirements for this instrumentation are provided in the Radiological Effluent Technical Specifications for BWRs (Ref. 3). Additional guidance is provided in References 4 and 5.

APPLICABLE The radioactive gaseous effluent monitoring instrumentation provides SAFETY assurance that radioactive releases resulting from normal operation and ANALYSES any potential radioactive releases caused by Anticipated Operational Transients are monitored. Chapter 15, Accident Analysis, of the FSAR (Ref. 6) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased gaseous effluent releases. The FSAR (Ref. 7) provides additional information on the Gaseous Process and Effluent Radiation Monitoring System.

Reference 8 provides additional detail on the Gaseous Process and Effluent Radiation Monitors.

REQUIREMENTS 1. Main Condenser Offgas Post-Treatment Radiation Monitors FOR OPERABILITY Two monitors measure the radioactivity in the offgas piping downstream of the off gas system charcoal vessels and upstream of the offgas system discharge valve. The normal mode of operation for the offgas system is to have the charcoal beds in service. The purpose of these radiation monitors is to provide information on the concentration of radioactivity in the offgas process stream after treatment and to automatically isolate the offgas system or to automatically initiate offgas treatment if the system is being operated in the bypass mode. Radiation is measured by a scintillation detector and the activity concentration is displayed in the main control room. An auxiliary trip unit uses the signal from both of these two detectors to isolate the effluent of the offgas system if the logic is satisfied by a combination of high-high-high radiation and downscale trips.

Another trip signal from either of these monitors initiates opening of the charcoal absorber treatment valve and closure of the bypass valve if the system is being run in the bypass mode during plant startup. Alarms are provided in the main control room that show monitor system status.

Further information on the subsystem can be found in Reference 9.

Columbia Generating Station B 6.1.2-1 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES REQUIREMENTS FOR OPERABILITY (continued)

2. Main Condenser Offgas Pre-Treatment Radiation Monitor This monitor is located at the outlet of the water separator downstream of the catalytic recombiners. The monitor measures the radioactivity due to fission gases and activation products produced in the reactor and transported with the steam through the turbine to the condenser. The purpose of this monitor is to provide the main control room with information on the amount of gamma radioactivity in the untreated offgas stream. The detector is a gamma-sensitive ion chamber. Trip outputs are used for alarm only. Further information on this subsystem can be found in Reference 10.

2a. Mechanical Vacuum Pump Discharge Radiation Monitor This Geiger Mueller type radiation monitor is designed to alarm, stop, and isolate the mechanical vacuum pumps in the event of high levels of radioactive gases in the air being exhausted from the condenser. The mechanical vacuum pumps are operated during plant start-ups to remove bulk air from the condenser. They are stopped when the steam jet air ejectors are put into service. Further information on this radiation monitoring system can be found in Reference 11.

3. Reactor Building Elevated Discharge Radiation Monitor This monitoring system measures radioactivity in the reactor building elevated release duct from the:

a) offgas effluent, b) the Gland Seal System, c) Mechanical Vacuum Pump, d) the Standby Gas Treatment System, and e) the exhaust air from the Reactor Building Ventilation System.

The purpose of this monitoring subsystem is to characterize the radioactivity being released through the reactor building elevated discharge vent and to provide alarms in the event of abnormal operation.

The monitor has no control function but an alarm is provided in the control room if the setpoint is exceeded.

Columbia Generating Station B 6.1.2-2 Amendment 50, May 2013

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Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES REQUIREMENTS FOR OPERABILITY (continued)

Footnote (b) of Table 6.1.2-1 is intended to address the condition when the Turbine Building Ventilation System is not operating. If there is no flow through the turbine building exhaust this monitor is not Functional and the Compensatory Measures are also not effective. The turbine building is a conventional steel structure so leakage of radioactive material could be significant. Under these conditions building ambient air samples, building equipment status including potential radioactivity sources, and meteorological data can be used to estimate the out-leakage from the building.

5. Radwaste Building Ventilation Exhaust Radiation Monitor This monitoring system measures radioactivity in the radwaste building ventilation air exhaust. Radioactivity originates from radwaste tank vents, processing equipment, sampling hoods, as well as from process treatment systems within the building. The purpose of this monitoring subsystem is to characterize the radioactivity being released through radwaste building discharge vent and to provide alarms in the event of abnormal operation. The monitor is read and recorded in the main control room. An alarm is provided in the control room if the setpoint is exceeded.

A continuous sample is extracted from the exhaust duct, through a multi-ported isokinetic probe. The sample is filtered to collect particulates and passes through an impregnated charcoal cartridge to collect iodine.

These samples are collected and analyzed per SR 6.2.2.1.2 and Table 6.2.2.1-1.

Further information on this subsystem can be found in Reference 14.

Footnote (b) of Table 6.1.2-1 is intended to address the condition when the Radwaste Building Ventilation System is not operating. If there is no flow through the radwaste building exhaust this monitor is not Functional and the Compensatory Measures are also not effective. Under these conditions building ambient air samples, building equipment status including potential radioactive sources, and meteorological data can be used to estimate the out-leakage from the building.

6. Alarm/Trip Setpoints The Function 1 monitors are normally operated in the mode where they are monitoring the output of the gaseous effluent stream from the charcoal beds. Under these conditions a High-High-High Radiation signal from both monitors initiates closure of OG-V-60 terminating the effluent Columbia Generating Station B 6.1.2-4 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES REQUIREMENTS FOR OPERABILITY (continued) release. The setpoints are established to assure the valve will be closed before the site boundary dose rate criteria is exceeded. A downscale trip of both monitors or a combination of downscale trip and High-High-High radiation will also cause isolation of the effluent release. The Function 1 monitors can also be operated in the mode where the charcoal beds are being bypassed. In this case a High radiation trip from either monitor will cause closure of the bypass valve, OG-V-45. Prior to placing the gaseous radwaste treatment system in the charcoal bypass mode, the alarm setpoints on the main plant vent release monitor shall be set to account for the increased percentages of short-lived noble gases. Noble gas percentages shall be based either on actual measured values or on primary coolant design base noble gas concentration percentages adjusted for 30-minute decay. ODCM Table 3-15, Design Base Percent Noble Gas (30-minute Decay), lists the percentage values for 30-minute decay.

The setpoint for this action is well below the site boundary dose rate criteria. Control room alarms are provided for a downscale condition, High Radiation, and High-High-High Radiation.

The Function 2, High Radiation alarm setpoint is required to be set at 1.5 times the steady state full power nominal radiation level per Reference 15. This provides assurance that the control room will be aware of increasing radiation levels in the untreated gaseous effluent stream from the main condenser. A second High-High Radiation alarm is provided giving the control room indication if the level continues to rise.

The Function 2a, 3a, 4a, and 5a monitors have their setpoints established in a manner that assures the instantaneous dose rate limits to the unrestricted area are less than the limits given in RFO 6.2.2.1. ODCM Section 3.4 provides the methodology for establishing these setpoints.

The calculations take into account the partition of the limiting dose rate between the three release points. The maximum normalized diffusion coefficient (X/Q) at and beyond the site boundary is used to model the decrease in radionuclide concentration between the point of release and the receptor location. Both whole body and skin dose setpoints are calculated and the lower setpoint is used for the instrument. The dose rate limits are provided in Reference 2.

Functions 3b, 3c, 4b, 4c, 5b, and 5c do not have established setpoints.

These functions collect iodine and particulate samples for further analysis and no setpoints are associated with these activities. It is not considered to be practicable to apply instantaneous alarm/trip setpoints to integrating radiation monitors sensitive to radioiodines or radioactive materials in particulate form.

Columbia Generating Station B 6.1.2-5 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES REQUIREMENTS FOR OPERABILITY (continued)

Functions 3d, 4d, and 5d are associated with the flow rate of effluent from the three buildings. Design ventilation rates are given in Reference 16.

These setpoints are established to provide the plant operators with an alarm indicating abnormal flow conditions.

Functions 3e, 4e, and 5e are associated with flow rate in the iodine and particulate sampling devices. The flow through these filters must be maintained to obtain a representative sample. Setpoints are established to provide plant operators with an alarm if the sample flow fails to register the required value.

Further guidance on setpoint determination can be found in Reference 4.

APPLICABILITY The Main Condenser Offgas Post-Treatment and Pre-Treatment Monitors are required to be Functional when the Steam Jet Air Ejectors are put into operation. Prior to this time condenser offgas is exhausted by the mechanical vacuum pump. The Mechanical Vacuum Pump Radiation Monitor is required to be Functional when the mechanical vacuum pumps are being used to create and maintain a condenser vacuum and there is a potential for radioactive release from the condenser area. During startup and shutdown when vacuum is being maintained with a mechanical vacuum pump and the Steam Seal System is operational the Mechanical Vacuum Pump Radiation Monitor must be Functional.

All other instruments are required to be Functional when there is exhaust flow through the building exhaust vent. If there is no flow through the exhaust, the monitors do not provide any useful information. In this case footnote (b) of Table 6.1.2-1 shall be followed to prevent an unmonitored release condition.

Separate entry is allowed for each channel. The note allows a Condition to be entered separately for each nonfunctional instrument and completion times tracked on a per instrument basis.

COMPENSATORY A.1 and B.1 MEASURES This Compensatory Measure gives the action required if the Mechanical Vacuum Pump Radiation Monitor is not Functional when it is required.

The Reactor Building Elevated Discharge Radiation Monitor monitors the effluent pumped from the condenser by the mechanical vacuum pump. If the Reactor Building Elevated Discharge Radiation Monitor is Functional, this provides adequate assurance that potential releases will be monitored. If this monitor is nonfunctional, then sampling is required.

Columbia Generating Station B 6.1.2-6 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES COMPENSATORY MEASURES (continued)

A.1, C.1, C.2, C.3, and G.1 The Compensatory Measures give the actions required to be taken if the Reactor Building Elevated Discharge Low Range Activity Monitor, the Turbine Building Ventilation Exhaust Noble Gas Activity Monitors, or the Radwaste Building Ventilation Exhaust Noble Gas Activity Monitors are nonfunctional. A grab sample must be taken at the associated sample location within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

The grab sample must be analyzed for noble gas gamma emitters within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the sample is taken. This sampling and analysis provides adequate assurance that the noble gases being released are characterized. If the channel is not restored to Functional status in 30 days, the event must be reported to the NRC in the calendar year Radioactive Effluent Release Report. This allows the NRC to monitor equipment that has been nonfunctional for an extended time period.

A.1, D.1, D.2, and G.1 These Compensatory Measures are required to be taken if the Effluent Flow Rate Monitors in the Reactor Building Elevated Discharge, the turbine building ventilation exhaust, or the radwaste building ventilation exhaust are nonfunctional. An estimate of the flow rate from the associated building is required every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . An estimate of the flow can be obtained by noting the number of fans in operation.

These same Compensatory Measures are also required to be taken if associated building Iodine and Particulate Sampler Flow Rate Monitors are nonfunctional. Sample line flow rates are needed to determine the concentration (activity in a given volume of air) of radioactive material in gaseous effluents. The flow rate at each release point is necessary to determine the total activity of radioactive material released in a given time period. There is flexibility in the method by which these estimates can be made for the purpose of obtaining best-available estimates. For example, if a flow rate or alarm signal is not being received at the control room, but the installed, calibrated, mechanical flow rate device is working properly, the best-available estimate would come from the mechanical flow rate device as opposed to using auxiliary sampling equipment. On the other hand, if the local flow rate indication is electronic, as is the case with the reactor building sample flow rate, and out of service, then auxiliary flow rate instruments may be used. The operation of the sampling equipment and sample flow is recorded every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Columbia Generating Station B 6.1.2-7 Amendment 50, May 2013

Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES COMPENSATORY MEASURES (continued)

If any flow related channel above is not restored to Functional status in 30 days the event must be reported to the NRC in the calendar year Radioactive Effluent Release Report. This allows the NRC to monitor equipment that has been nonfunctional for an extended time period.

A.1, E.1.1, E.1.2, E.2, and G.1 These Compensatory Measures are required to be taken if the iodine and particulate samplers associated with the reactor building elevated discharge, the turbine building ventilation exhaust, or the radwaste building ventilation exhaust are nonfunctional. Auxiliary sampling equipment is used to collect samples from the associated effluent release pathway within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . This auxiliary sampler is to be used continuously to provide a sample for later analysis.

Compensatory Measure E.1.2 can be used if auxiliary sampling is not available. Relevant information should be collected to characterize the particulate and iodine effluent releases during the period of time the auxiliary sampling equipment was not available when required by Compensatory Measure E.1.1. If Compensatory Measure E.1.2 is used this must be reported to the NRC upon submittal of the current calendar year Radioactive Effluent Release Report.

A.1, F.1, F.2, F.3 and G.1 These Compensatory Measures are required to be taken if a Main Condenser Offgas Post-Treatment Radiation Monitor is nonfunctional.

Compensatory Measure F.1 ensures that the effluent of the offgas system is being monitored by verifying one Main Condenser Offgas Post-Treatment Radiation Monitor is Functional or take a grab sample at the associated sample location within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

The grab sample must be analyzed for noble gas gamma emmiters within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the sample is taken. This sampling and analysis provides adequate assurance that the noble gases being released are characterized.

Compensatory Measure F.2 ensures the capability of terminating releases from the offgas system to prevent exceeding any off site dose limits by verifying one of the following methods. Actions should be taken to place the failed channel in a trip condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Alternatively, appropriate administrative controls may be used to manually terminate a release prior to exceeding any off site dose limits.

Columbia Generating Station B 6.1.2-8 Amendment 50, May 2013

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Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES SURVEILLANCE REQUIREMENTS (continued) in operation. The CHANNEL CHECK for the Radwaste Building Effluent System Flow Rate Monitor shall be performed by comparing a computer reading or power signal comparing each fans local amperage reading with pre-established baseline values.

SR 6.1.2.2 A daily Source Check is required for the Main Condenser Offgas Post-Treatment Radiation Monitors. This provides increased confidence that the instruments will operate as required to detect excess radioactivity in the treated gas process stream. This test is required whenever the steam jet air ejectors are in operation.

SR 6.1.2.3 A CHANNEL CHECK for the iodine and particulate samplers is required weekly. The change-out of the filters is considered the equivalent of a CHANNEL CHECK. The weekly check of sampler operation is sufficient to provide assurance of a quality sample for analysis. This CHANNEL CHECK is required at all times.

SR 6.1.2.4 The monthly Source Check is required for the Main Condenser Offgas Pre-Treatment Monitor whenever the steam jet air ejectors are in operation. A monthly Source Check is also required for the Reactor Building Elevated Discharge Low Range Activity Monitor, the Turbine Building Ventilation Exhaust Noble Gas Activity Monitor, and the Radwaste Building Ventilation Exhaust Noble Gas Activity Monitor. The building effluent noble gas gamma monitors require a source check at all times. The monthly Source Check provides adequate assurance of channel Functionality.

SR 6.1.2.5 A CHANNEL FUNCTIONAL TEST is required for all instruments except the iodine and particulate samplers and the Mechanical Vacuum Pump Discharge Radiation Monitor quarterly or every 92 days. This test frequency provides adequate assurance of the channel function. A CHANNEL FUNCTIONAL TEST is not required for the samplers as the routine analysis of the samples provides assurance of sample function.

The CHANNEL FUNCTIONAL TEST for the Main Condenser Offgas Post and Pre-Treatment Monitors, the Reactor Building Elevated Discharge Low Range Noble Gas Monitor require a demonstration that control room alarm annunciation occurs if:

Columbia Generating Station B 6.1.2-10 Amendment 55, August 2016

Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES SURVEILLANCE REQUIREMENTS (continued) a) the instrument indicates measured levels above the alarm setpoint, and b) circuit failure occurs.

The CHANNEL FUNCTIONAL TEST for the Turbine Building Ventilation Exhaust and Radwaste Building Ventilation Exhaust Noble Gas Monitors must demonstrate that circuit failures or instrument controls when set in the off position produce control room alarm annunciation. The CHANNEL FUNCTION TEST for the Radwaste Building Ventilation Exhaust Effluent System Flow Rate Monitor shall be performed by measurement of the phase currents for each fan.

SR 6.1.2.5a A CHANNEL CHECK of the Mechanical Vacuum Pump Radiation Monitor is required prior to its use. This check is required only if it has not been performed during the past 30 days. During shutdowns this check can be performed by verifying that the instrument was on-scale prior to shutdown.

SR 6.1.2.6 A CHANNEL CALIBRATION is required for all instruments except the iodine and particulate samplers, the Offgas Post Treatment Monitor, and the Mechanical Vacuum Pump Discharge Radiation Monitor every 18 months. This test frequency provides adequate protection against drift or other instrument inaccuracies. The CHANNEL CALIBRATION is not required for the samplers as the routine analysis of the samples provides assurance of sample integrity. The CHANNEL CALIBRATION of the Main Condenser Offgas Pre-Treatment Monitors, the Reactor Building Elevated Discharge Low Range Activity Monitor, and the Turbine and Radwaste Building Low Range Noble Gas Activity Monitors have special requirements. For these gross radioactivity monitors the initial CHANNEL CALIBRATION shall be performed using one or more reference standards traceable to the National Institute of Science 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 monitor response. Subsequent CHANNEL CALIBRATION shall be performed using the equivalent quality and radioactive sources that have been related to the initial calibration. The CHANNEL CALIBRATION for the Radwaste Building Ventilation Effluent System Flow Rate Monitor shall be performed by using a flow measurement device to determine the fan current to flow relationship.

Columbia Generating Station B 6.1.2-11 Amendment 55, August 2016

Radioactive Gaseous Effluent Monitoring Instrumentation B 6.1.2 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 6.1.2.7 The CHANNEL CALIBRATION for the Offgas Post Treatment Monitor and the Mechanical Vacuum Pump Discharge Radiation Monitor is required during refueling outages. This longer frequency is acceptable since this monitor is backed up by the Reactor Building Elevated Discharge Radiation Monitor. The initial calibration of the Offgas Post Treatment Monitor shall be performed using sufficient NIST traceable sources to permit calibrating the system over its intended range of energy and monitor response.

Subsequent CHANNEL CALIBRATION shall be performed using equivalent quality and radioactive sources that have been related to the primary calibration.

REFERENCES 1. 10 CFR 50, Appendix A.

2. 10 CFR 20.1-20.602.

3. NUREG-0473, Revision 2.

4. NUREG-0133.

5. NUREG-1302.

6. FSAR Section 15.0.3.

7. FSAR Section 11.5.2.2.1.

8. FSAR Table 11.5-1.

9. FSAR Section 11.5.2.2.1.2.

10. FSAR Section 11.5.2.2.1.1.

11. FSAR Section 11.5.2.2.1.4.

12. FSAR Section 11.5.2.2.1.5.

13. FSAR Section 11.5.2.2.1.6.

14. FSAR Section 11.5.2.2.1.7.

15. Technical Specification Amendment 112 (GI2-93-028).

16. FSAR Table 11.3-8.

Columbia Generating Station B 6.1.2-12 Amendment 55, August 2016

Liquid Concentration B 6.2.1.1 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.1 Liquid Effluents B 6.2.1.1 Liquid Concentration BASES BACKGROUND This RFO is focused on the concentration of radionuclides released to the Columbia River. The radionuclide concentrations shall not exceed 10 times those given in Appendix B, Table 2, Column 2 of Reference 1. The RFO also implements the requirements of Technical Specification 5.5.4.b.

APPLICABLE The radionuclide concentration limits provide assurance that any liquid SAFETY radioactive releases caused by normal operation and Anticipated ANALYSES Operational Transients result in very low exposures to the general public.

A hypothetical person using water at the outlet of the blowdown line at the RFO limits would receive a whole body dose of 500 mrem/year.

Chapter 15, Accident Analysis, of the FSAR (Reference 2) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased liquid effluent release concentrations. Further information on liquid radioactive releases can be found in Chapter 11 of the FSAR (Ref. 3). Reference 4 provides initial estimated isotopic annual releases of liquid effluent.

REQUIREMENTS This RFO provides assurance that the concentration of radioactive FOR OPERABILITY materials in bodies of water in Unrestricted Areas will result in exposures within the limits of 10 CFR 20.1302(b)(2)(i) of Reference 1. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in Reference 6.

APPLICABILITY This RFO is applicable at all times since liquid effluents can be released at any time.

COMPENSATORY The concentration of radionuclides being released can be decreased by MEASURES decreasing the amount of activity being released or by increasing the dilution. The amount of radioactivity will decrease with time due to decay.

The recycling of water within the plant prior to release will, therefore, decrease the amount of activity available. The dilution of the waste can occur within the plant prior to release or during blowdown to the river.

Columbia Generating Station B 6.2.1.1-1 Amendment 50, May 2013

Liquid Concentration B 6.2.1.1 BASES SURVEILLANCE This SR defines the radioactive liquid waste sampling and analysis REQUIREMENTS needed to determine the radionuclide concentrations in the effluent. This program meets the requirements of General Design Criteria 64 in Appendix A of Reference 5. It also uses the guidance provided in References 7 and 8.

Liquid Release Type At Columbia Generating Station batch releases are the only release type.

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in plant procedures to assure representative sampling. SR 6.2.1.1.1 requires a pre-release analyses of each batch release.

Sample and Analysis Frequency A sample is required to be taken prior to the release of each batch. This provides assurance of a representative sample of the radioactivity to be released. The samples must be analyzed prior to the release of each batch. This allows for a review of the results of the analysis prior to release. SR 6.2.1.1.2 requires a post-release analysis of samples composited from the batch releases. For tritium and gross alpha a composite sample is collected prior to the release of each batch. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. This may be accomplished through composites of grab samples obtained prior to discharge after the tanks have been recirculated. Every 31 days the composite sample made up of all the releases during the prior 31 days must be analyzed. If no releases are made during the previous 31 day period no analysis is required. This 31 day composite analysis for tritium and gross alpha is considered adequate to characterize the liquid release during this time period.

For Fe-55, Sr-89, and Sr-90 a composite sample is also required for each batch released. In this case the composite samples may be collected for 92 days prior to analysis. If no releases occur during the previous 92 day period no analysis is required.

Columbia Generating Station B 6.2.1.1-2 Amendment 50, May 2013

Liquid Concentration B 6.2.1.1 BASES SURVEILLANCE REQUIREMENTS (continued)

Sample Lower Limit of Detection The LLD is defined in the definitions section of the ODCM Appendix. The principle gamma emitters for which the LLD definition applies in this RFO includes 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 5 E-6. 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 Radioactive Effluent Release Report.

Detailed discussions of the LLD and other detections limits can be found in References 9, 10, and 11.

REFERENCES 1. 10 CFR 20.1001 - 20.2402.

2. FSAR Section 15.0.3.

3. FSAR 11.2.3.

4. FSAR Table 11.2-14.

5. 10 CFR 50.

6. ICRP Publication 2.

7. Reg. Guide 1.21.

8. Reg. Guide 4.15.

9. HASL Procedures Manuals, HASL-300 (revised annually).

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

11. Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

Columbia Generating Station B 6.2.1.1-3 Amendment 50, May 2013

Liquid Dose B 6.2.1.2 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.1 Liquid Effluents B 6.2.1.2 Liquid Dose BASES BACKGROUND This RFO requires a calculation of the dose resulting from the routine release of liquid radioactive effluents. It implements the requirements of Sections II.A, III.A, and IV.A of Appendix I of Reference 1. It should be noted that these RFO limits apply to a Member of the Public. The dose calculation models are, therefore, allowed to take into account dilution and other factors which decrease the dose between the point of release and the persons location.

APPLICABLE This dose calculation provides assurance that any liquid radioactive SAFETY releases caused by normal operation and Anticipated Operational ANALYSES Transients are evaluated to determine their impact on a Member of the Public. Chapter 15, Accident Analysis, of the FSAR (Ref. 2) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased liquid effluent releases. The FSAR (Ref. 3) and the Columbia Generating Station Environmental Report (Ref. 4) calculate estimated annual exposure due to liquid effluent release. The estimated whole body dose of 2.3 mrem per year and the largest calculated single organ dose of 1.6 mrem per year to the bone are well below the guidelines of Appendix I of Reference 1.

REQUIREMENTS The dose calculation methodology and parameters in the ODCM FOR OPERABILITY implement the requirements of Section III.A of Appendix I of Reference 1.

Conformance with the guidance of Appendix I must be shown by calculational procedures based on models and data, such that the actual exposure of the Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the dose due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Reference 5 and Reference 6. 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 Reference 7.

APPLICABILITY This RFO is applicable when radioactive liquid effluents are released.

During the periods of time when no radioactive liquids are released this RFO is not applicable.

Columbia Generating Station B 6.2.1.2-1 Amendment 50, May 2013

Liquid Dose B 6.2.1.2 BASES COMPENSATORY The general note is provided to implement the guidance in Reference 8.

MEASURES This NUREG states that as long as the calculated dose does not exceed twice the limits of this RFO no extra analysis is required to demonstrate compliance with RFO 6.2.3.1. If the dose levels exceed twice those cited in this RFO additional analysis must be performed to determine if additional limitations on plant operation will be necessary to ensure compliance with Reference 9.

The Compensatory Measures statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I of Reference 1 to ensure that the releases of radioactive material in liquid effluents to Unrestricted Areas will be kept "as low as is reasonably achievable."

SURVEILLANCE This SR for this RFO requires a dose calculation every 31 days to REQUIREMENTS provide assurance that the radioactive liquid effluents released do not result in a dose above the limits stated. The dose to the whole body is calculated for the quarter and year prior to the date of the calculation.

The dose to each organ is calculated for the quarter and year prior to the date of the calculation. All calculated doses must be below the limits given in this RFO or the Compensatory Measures must be implemented.

When no liquid radioactive releases occur during the time period no new calculation is required since the RFO is not applicable.

REFERENCES 1. 10 CFR 50.

2. FSAR Section 15.0.3.

3. FSAR Section 11.2.3.3.

4. Columbia Generating Station Environmental Report, Operating License Stage, Section 5.2.

5. Regulatory Guide 1.109.

6. Regulatory Guide 1.13.

7. 40 CFR 141.

8. NUREG-0543.

9. 40 CFR 190.

Columbia Generating Station B 6.2.1.2-2 Amendment 50, May 2013

Liquid Waste Management System B 6.2.1.3 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.1 Liquid Effluents B 6.2.1.3 Liquid Waste Management System BASES BACKGROUND This RFO requires the Liquid Waste Management System to be Functional at all times. In addition it requires the Liquid Waste Management System to be in service whenever the projected dose calculated prior to release indicates a value above the limit given in the RFO. The requirement that the appropriate portions of this system be used, when specified, provides assurance that the release of radioactive materials in liquid effluent will be kept as low as is reasonably achievable. This RFO implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A and the design objective given in Section II.D of Appendix I to Reference 1. It also implements the requirements of Technical Specification Section 5.5.4.f. Further guidance on the implementation of the RFO is provided in References 2, 3, and 4.

APPLICABLE This RFO provides assurance that liquid radioactive releases caused by SAFETY normal operating and Anticipated Operational Transients are treated if ANALYSES they are above the given limits. Chapter 15, Accident Analysis, of the FSAR (Ref. 5) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased liquid effluent releases.

REQUIREMENTS The Functionality of the Liquid Radioactive Waste Management FOR OPERABILITY System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The term "Liquid Waste Management System" involves all of the installed and available Liquid Radioactive Waste Management System equipment, as well as their controls, power, instrumentation, and services that make the system function. Equipment that is considered standby or redundant is also included, since their function is to assure Functionality. The RFO also permits alternate treatment paths using alternate subsystems and equipment to be used in the event that the normal treatment equipment is nonfunctional. Further information on the design bases, system description, and process description of the Liquid Waste Management System is given in Reference 6.

Columbia Generating Station B 6.2.1.3-1 Amendment 50, May 2013

Liquid Waste Management System B 6.2.1.3 BASES REQUIREMENTS FOR OPERABILITY (continued)

This RFO requires the Liquid Waste Management System to be in use when the projected doses due to the liquid effluent released to the Unrestricted Area would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period. Thus, the Liquid Waste Management System is required to be in use well before the limits of RFO 6.2.1.2 are reached as required by Section II.A of Appendix I to Reference 1. If the system is in use, radioactive liquid waste can be released up to the limits of RFO 6.2.1.2.

APPLICABILITY This RFO is applicable at all times since the Liquid Waste Management System must be Functional at all times.

COMPENSATORY A Special Report to the NRC is required if the Liquid Waste Management MEASURES System is not Functional for more than 31 days, or if the system was not in use and the calculated dose values were found to be above those given in the RFO. This allows the NRC to be kept informed of any nonfunctional or unused equipment needed to reduce the dose and the corrective actions being taken to restore it to Functional status.

SURVEILLANCE SR 6.2.1.3.1 REQUIREMENTS To determine if use of the installed equipment is necessary, the cumulative liquid effluent releases over the ensuing 31 days must be projected. These releases should include all plant effluents from all Liquid Radioactive Waste Management and Liquid Waste Disposal System components that are planned to be operated. These releases should include a margin, based on operating data, for anticipated and unplanned operational occurrences. The ODCM methodology used to project the dose shall be the same as that used for SR 6.2.1.2.1. The impact of this projected cumulative release is to be compared to 0.06 mrem for the whole body and 0.2 mrem for any organ. If the projection indicates these values will be exceeded, then the installed Liquid Waste Management System components that will reduce these radioactive materials in the liquid effluent and their projected dose impact must be used.

Columbia Generating Station B 6.2.1.3-2 Amendment 50, May 2013

Liquid Waste Management System B 6.2.1.3 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 6.2.1.3.2 The Liquid Waste Management System is considered Functional if the requirements of RFO 6.2.1.1, Liquid Concentration and RFO 6.2.1.2, Liquid Dose are met. RFO 6.2.1.1 limits the concentration of radioactive material released in liquid effluents to Unrestricted Areas. These low concentration limits are an indicator of a properly functioning Liquid Waste Management System. In a similar manner, RFO 6.2.1.2 limits the dose from liquid effluents. A low dose from liquid effluents is an indication of a Functional Liquid Waste Management System.

REFERENCES 1. 10 CFR 50.

2. NUREG-0473, Revision 2.

3. NUREG-0133.

4. NUREG-1302.

5. FSAR Section 15.0.3.

6. FSAR Section 11.2.

Columbia Generating Station B 6.2.1.3-3 Amendment 50, May 2013

Dose Rate B 6.2.2.1 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.2 Gaseous Effluents B 6.2.2.1 Dose Rate BASES BACKGROUND This ODCM requirement for OPERABILITY (RFO) provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure to 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 50. This specification 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 50. For Members of the Public who may at times be within the Site Boundary, the occupancy of that Member of the Public will 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, are provided in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background, at or beyond the Site Boundary, to less than or equal to 500 mrem/year to the whole body, or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child, via the inhalation pathway, to less than or equal to 1500 mrem/year. This specification does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).

APPLICABLE The gaseous effluent dose rate limits provide assurance that any SAFETY gaseous effluent releases caused by normal operation and Anticipated ANALYSES Operational Transients result in very low exposures to the general public.

A hypothetical person living at or beyond the Site Boundary would receive a whole body dose of 500 mrem/year. Chapter 15, Accident Analysis, of the FSAR (Ref. 2) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased gaseous effluent dose rates. Further information on gaseous radioactive releases can be found in Chapter 11 of the FSAR (Ref. 3).

Estimated gaseous releases from the plant are given in Reference 4.

REQUIREMENTS This RFO provides the dose rate limits for gaseous radioactive FOR OPERABILITY materials released from the plant.

APPLICABILITY This RFO is applicable at all times since gaseous effluents can be released at any time.

Columbia Generating Station B 6.2.2.1-1 Amendment 51, December 2013

Dose Rate B 6.2.2.1 BASES COMPENSATORY The dose rate resulting from the release of gaseous radionuclides can be MEASURES decreased by decreasing the amount of radioactivity being released. The amount of radioactivity will decrease with time due to decay. The use of the charcoal beds greatly decreases the iodine and particulates released and will delay the release of noble gases. This will decrease the amount of activity available for release. Other actions that would result in a decreased source of radioactivity should be considered. The Ventilation Exhaust Treatment System can be used to decrease the amount of radioactivity released.

SURVEILLANCE These surveillance requirements define the radioactive gaseous waste REQUIREMENTS sampling and analysis needed to determine the radionuclide concentrations and dose rates in the effluent. This program meets the requirements of General Design Criteria 64 in Appendix A of Reference 5.

It also conforms to the References 6 and 7.

Table 6.2.2.1-1 defines the radioactive gaseous waste sampling and analysis program. The table is divided into four sections: 1) those sampling and analysis requirements that are required to be in place at the plant at all times, 2) those requirements applicable during Purge and Vent operations, 3) additional sampling and analysis required during startup and shutdown, and 4) additional requirements that must be followed during significant reactor power changes.

Radioactive Gaseous Sampling and Analysis Required at All Times (Table 6.2.2.1-1, Part 1)

A primary containment grab sample for tritium is required to be taken and analyzed every 31 days. This analysis provides information on any releases that might be occurring within the primary containment structure.

The 31 day sampling period is sufficient to identify trends during power operation. Footnote (a) recognizes the plant configuration when the primary containment is open and the reactor building becomes the primary confinement space. In this case the grab sampling being done at the reactor building elevated discharge is representative of all space inside the reactor building including primary containment.

A reactor building elevated discharge grab sample for tritium is required every seven days. This analysis determines the tritium release in the ventilation exhaust from the spent fuel pool area. It is required whenever spent fuel is in the fuel pool.

A reactor building elevated discharge noble gas grab sample and analysis for gamma emitters is required every 31 days. The principal gamma emitters for noble gas effluents are defined under the LLD discussion in Columbia Generating Station B 6.2.2.1-2 Amendment 50, May 2013

Dose Rate B 6.2.2.1 BASES SURVEILLANCE REQUIREMENTS (continued) this bases. This analysis identifies the gamma emitters in the gaseous effluent stream that are needed to perform the dose rate calculations. A 31 day sampling and analysis period is sufficient to characterize this release.

Turbine and radwaste building vent noble gas and tritium grab samples and analysis for principal gamma emitters and tritium are required every 31 days. The principal gamma emitters for noble gas effluents are defined under the LLD discussion in this bases. This analysis identifies the gamma emitters and tritium in the gaseous effluent stream that is needed to perform the dose rate calculations. The tritium analysis provides information on the trend of steam leaks in these two areas. A 31 day analysis period is sufficient to characterize this release.

Continuous charcoal filter samples are collected from all three building vent gaseous effluent streams. Every seven days the charcoal filters are to be removed and analyzed. This analysis provides information on the halogen (iodine) isotopes being released from the plant and is used to calculate the halogen dose rate due to gaseous effluents.

Continuous particulate filter samples are collected from all three building vent gaseous effluent streams. Every seven days these particulate filters are removed and analyzed. This analysis provides information on the gamma emitters collected in the sample.

A composite of the continuous particulate filter sample is collected from all building vents. Every 31 days these samples are totalized for gross alpha. Every 92 days these composite samples are analyzed for strontium. These analyses provide information on possible trends in fuel performance.

The noble gas monitor provides a continuous record of noble gas release from the plant. The gross gamma and beta count rates along with the periodic grab samples are used to characterize the noble gas release and calculate the dose rate.

Footnote (b) of Table 6.2.2.1-1, Part 1, notes the importance of the ratio of sample flow rate to the sampled effluent stream flow. This provides one of several values needed for estimating the dose rate.

Columbia Generating Station B 6.2.2.1-3 Amendment 50, May 2013

Dose Rate B 6.2.2.1 BASES SURVEILLANCE REQUIREMENTS (continued)

Radioactive Gaseous Sampling and Analysis Required During Purge or Vent (Table 6.2.2.1-1, Part 2)

Primary containment grab sampling and analysis is not required if a Vent release (by the two inch exhaust lines) is through the Standby Gas Treatment System and the noble gas monitors in containment are reading below their setpoint as stated in footnote (d). Under these conditions, grab sampling is not required as the gaseous effluent will be released at a slow rate, will be filtered, and will be measured by the reactor building elevated discharge noble gas, iodine, and particulate monitors. Additional requirements on Venting and Purging are found in RFO 6.2.2.6.

During other Purge or Vent conditions, primary containment noble gas, iodine, and particulate grab samples are required prior to each Purge or Vent. The sample must be taken no more than eight hours before the Purge or Vent. The sample must be analyzed for gamma emitters prior to the Purge or Vent. This analysis determines the status of radioactivity in the primary containment atmosphere prior to the release.

If the Reactor Building Elevated Discharge Low Range Radiation Monitor is not Functional, sampling and analysis of the containment shall be completed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during Purge and Vent. With a nonfunctional Reactor Building Elevated Discharge Low Range Radiation Monitor this additional sampling provides additional data to characterize the release from containment. This additional sampling is required for a Vent release through the Standby Gas Treatment System even when the noble gas monitors in containment are reading below their setpoint if the Vent exceeds 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Radioactive Gaseous Sampling and Analysis Required During Startup and Shutdown (Table 6.2.2.1-1, Part 3)

Noble gas, iodine, and particulate grab samples are required from the primary containment and the reactor building following startup and shutdown. These grab samples are analyzed for gamma emitters to provide information about any changes in gaseous activity during large power changes. Grab samples in the reactor building vent are normally taken during startup following the start of the steam jet air ejectors and shutdown of the mechanical vacuum pump. During shutdown, reactor building vent samples are taken after the steam jet air ejector is turned off and transition is made to the mechanical vacuum pump. Taking grab samples at this time allows a better definition of the radioactivity being released during this transition.

Columbia Generating Station B 6.2.2.1-4 Amendment 50, May 2013

Dose Rate B 6.2.2.1 BASES SURVEILLANCE REQUIREMENTS (continued)

Additional steps must be taken during startup and shutdown to determine if additional sampling is required. The first step is taken between two to six hours after the beginning of a startup or shutdown. At this point, the DOSE EQUIVALENT I-131 concentration in the primary coolant is evaluated. If it is less than 1.0E-03 Ci/cc, or if it is above 1.0E-03 Ci/cc but has not changed more than a factor of three, additional sampling is not required because of high iodine concentration in the primary coolant.

The low concentration or lack of change of concentration in the primary coolant is an indication of stable fuel performance that does not require additional effluent sampling.

The second step to determine if additional sampling is required involves the building vent Noble Gas Monitors. If all of the building vent monitors are less than or equal to two percent of their setpoint, or if they are greater than two percent of the setpoint but have not increased more than a factor of three, then additional tests are not required. A high and changing noble gas radioactivity reading from the building monitors during startup or shutdown operation could be an indication of an unusual condition within that building and additional sampling is required.

If the high and changing primary coolant radioactivity, or high and changing building vent activity, triggers additional testing, filters shall be removed from the continuous sampler at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This additional sampling must take place for at least seven days following shutdown or startup. The analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of filter removal. 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. Once this condition is entered it must be followed to completion for the seven day time period even if the primary coolant or building vent radioactivity levels decrease below the trigger point.

Footnote (b) of Table 6.2.2.1-1, Part 3, notes the importance of the ratio of sample flow rate to the sampled effluent stream flow. This provides one of several values needed for estimating the dose rate.

Radioactive Gaseous Sampling and Analysis Required During Reactor Power Changes (Table 6.2.2.1-1, Part 4)

Following THERMAL POWER changes exceeding 15% of RATED THERMAL POWER within a 1-hour period a determination must be made to see if radioactive grab sampling is required from the containment and reactor building elevated discharge. If the Main Condenser Offgas Pre-treatment Monitor, or temporary replacement monitor, is indicating less Columbia Generating Station B 6.2.2.1-5 Amendment 55, August 2016

Dose Rate B 6.2.2.1 BASES SURVEILLANCE REQUIREMENTS (continued) than or equal to 15,000 Ci/sec, no sampling is required. The process for converting monitor readings in mr/hr to ECi/sec is outlined in CI-11.1 (Reference 11). A low pre-treatment monitor reading is an indication of stable fuel performance during reactor power changes that does not require sampling. If the Main Condenser Offgas Pre-treatment Monitor is greater than 15,000 Ci/sec, noble gas, iodine, and particulate grab samples are required from the primary containment and the reactor building.

Additional steps must also be taken during reactor power changes to determine if additional continuous filter sampling is required. Between two to six hours after the beginning of a reactor power change, with the Offgas Pre-treatment Monitor greater than 15,000 Ci/sec, the DOSE EQUIVALENT I-131 concentration in the primary coolant is evaluated. If it is less than the 1.0E-03 Ci/cc, or if it is above 1.0E-03 Ci/cc but has not changed more than a factor of three, additional sampling is not required because of high iodine concentration in the primary coolant. The low concentration, or lack of change of concentration in the primary coolant, is an indication of stable fuel performance that does not require additional effluent sampling.

The second step to determine if additional continuous filter sampling is required involves the building vent Noble Gas Monitors. If all of the building vent monitors are less than or equal to two percent of their setpoint, or if they are greater than two percent of the setpoint but have not increased more than a factor of three, then additional tests are not required. A high and changing noble gas radioactivity reading from the building monitors during startup or shutdown operation could be an indication of an unusual condition within that building and additional sampling is required. If the DOSE EQUIVALENT I-131 concentration and the building vent monitors meet the criteria above, no additional continuous filter sampling is required, even if the Main Condenser Offgas Pre-treatment Monitor reading is greater than 15,000 Ci/sec.

However, a high and changing primary coolant radioactivity or high and changing building vent activity requires additional continuous filter testing.

Filters shall be removed from the continuous samplers in all building vents at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This additional sampling must take place for at least seven days following THERMAL POWER changes as defined above. The analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of filter removal. 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. Once this condition is entered it must be followed to completion for the seven day time period even if the primary coolant or building vent radioactivity levels decrease below the trigger point.

Columbia Generating Station B 6.2.2.1-6 Amendment 55, August 2016

Dose Rate B 6.2.2.1 BASES SURVEILLANCE REQUIREMENTS (continued)

Footnote (b) of Table 6.2.2.1-1, Part 4, notes the importance of the ratio of sample flow rate to the sampled effluent stream flow. This provides one of several parameters needed for estimating the dose rate.

Sample Lower Limit of Detection The LLD is defined in the definitions section of the ODCM.

The principal gamma emitters for which the LLD specification applies in this RFO includes the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

Detailed discussion of the LLD and other detections limits can be found in References 8, 9 and 10.

REFERENCES 1. 10 CFR 20.1-20.602.

2. FSAR Section 15.0.3.

3. FSAR Section 11.3.3.

4. FSAR Section 11.3.3.3.

5. 10 CFR 50.

6. Regulatory Guide 1.21.

7. Regulatory Guide 4.15.

8. HASL Procedures Manuals, HASL-300 (revised annually).

9. Currie, L.A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal.

Chem. 40, 586-93 (1968).

10. Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

11. CI-11.1 Offgas Release Rate.

Columbia Generating Station B 6.2.2.1-7 Amendment 55, August 2016

Dose - Noble Gases B 6.2.2.2 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.2 Gaseous Effluents B 6.2.2.2 Dose - Noble Gases BASES BACKGROUND This ODCM Requirement for Operability (RFO) requires a calculation of the noble gas air dose resulting from gaseous effluent release. It implements the requirements of Sections II.B, III.A, and IV.A of Appendix I, of Reference 1. It also implements Technical Specification Sections 5.5.4.e and 5.5.4.h. These RFO limits apply at any location at or beyond the site boundary.

APPLICABLE This air dose calculation provides assurance that any gaseous noble gas SAFETY radioactive releases caused by normal operation and Anticipated ANALYSES Operational Transients are evaluated to determine their impact on a Member of the Public. Chapter 15, Accident Analysis, of the FSAR (Ref. 2) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased gaseous effluent releases. The FSAR (Ref. 3) lists a number of events that result in steam being discharged to the suppression pool. The non-condensible noble gases present in this steam will migrate from the primary containment to the reactor building and be released through the reactor building elevated release vent. The Columbia Generation Station Environmental Report (Ref. 4) calculates the estimated annual exposure due to gaseous effluent release.

REQUIREMENTS The dose calculation methodology and parameters in the ODCM FOR OPERABILITY implement the requirements of Section III.A of Appendix I of Reference 1.

Conformance with the guidance of Appendix I must be shown by calculational procedures based on models and data, such that the actual exposure at locations at or beyond the Site Boundary is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of noble gases in gaseous effluents are consistent with the methodology provided in References 5 and 6.

APPLICABILITY This RFO is applicable at all times since gaseous effluents can be released at any time.

Columbia Generating Station B 6.2.2.2-1 Amendment 50, May 2013

Dose - Noble Gases B 6.2.2.2 BASES COMPENSATORY The general note is provided to implement the guidance in Reference 7.

MEASURES This NUREG states that as long as a nuclear plant operates at a level below twice the reporting requirement of this RFO no extra analysis is required to demonstrate compliance with RFO 6.2.3.1. If the dose levels cited in this RFO are exceeded by a factor of two, additional analysis must be performed to determine if additional limitations on plant operation will be necessary to ensure compliance with Reference 8.

The Compensatory Measures statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I of Reference 1 to assure that the releases of radioactive material in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable."

SURVEILLANCE The surveillance requirement for this RFO requires a dose calculation REQUIREMENTS every 31 days to provide assurance that the air dose due to noble gases does not result in a dose above the limits stated. The dose is calculated for the quarter and year based on actual and projected effluents for the 31 day period being analyzed. All calculated doses must be below the limits given in this RFO or the Compensatory Measures must be implemented.

REFERENCES 1. 10 CFR 50.

2. FSAR Section 15.0.3.

3. FSAR Table 11.3-10 Section 11.3.3.3.

4. Columbia Generating Station Environmental Report, Operating License Stage, Table 5.2-14.

5. Regulatory Guide 1.109.

6. Regulatory Guide 1.111.

7. NUREG-0543.

8. 40 CFR 190.

Columbia Generating Station B 6.2.2.2-2 Amendment 50, May 2013

Dose - I-131, I-133, Tritium, and Radionuclides in Particulate Form B 6.2.2.3 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.2 Gaseous Effluents B 6.2.2.3 Dose - I-131, I-133, Tritium, and Radionuclides in Particulate Form BASES BACKGROUND This ODCM Requirement for Operability (RFO) requires a calculation of the dose resulting from gaseous effluent release containing I-131, I-133, tritium, and radionuclides in particulate form (I-T-P). It implements the requirements of Sections II.C, III.A, and IV.A of Appendix I, of Reference 1. It also implements Technical Specification Sections 5.5.4.e and 5.5.4.i. These RFO limits apply to a Member of the Public. The dose calculation models are, therefore, allowed to take into account the additional diffusion and other source depletion between the point of release and locations occupied by individuals in the Unrestricted Area.

APPLICABLE This organ dose calculation provides assurance that any I-T-P radioactive SAFETY releases caused by normal operation and Anticipated Operational ANALYSES Transients are evaluated to determine their impact on a Member of the Public. Chapter 15, Accident Analysis, of the FSAR (Ref. 2) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased I-T-P gaseous effluent releases.

The Columbia Generating Station Environmental Report (Ref. 3) calculates the estimated annual exposure due to gaseous effluent release. Gaseous Waste Management System radioactive releases are discussed in Reference 4.

REQUIREMENTS The dose calculation methodology and parameters in the ODCM FOR OPERABILITY implement the requirements of Section III.A of Appendix I of Reference 1.

Conformance with the guidance of Appendix I must 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 I-T-P in gaseous effluents are consistent with the methodology provided in References 5 and 6. The release rate specifications for I-T-P are dependent upon the existing radionuclide pathways to man in Unrestricted Areas. 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.

Columbia Generating Station B 6.2.2.3-1 Amendment 50, May 2013

Dose - I-131, I-133, Tritium, and Radionuclides in Particulate Form B 6.2.2.3 BASES APPLICABILITY This RFO is applicable at all times since I-T-P effluents can be released at any time.

COMPENSATORY The general note is provided to implement the guidance in Reference 7.

MEASURES This NUREG states that as long as a nuclear plant operates at a level below twice the reporting requirement of this RFO no extra analysis is required to demonstrate compliance with RFO 6.2.3.1. If the dose levels cited in this RFO are exceeded by a factor of two, additional analysis must be performed to determine if additional limitations on plant operation will be necessary to ensure compliance with Reference 8.

The Compensatory Measures statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I of Reference 1 to assure that the releases of I-T-P radioactive material in gaseous effluents to Unrestricted Areas will be kept "as low as is reasonably achievable."

SURVEILLANCE The surveillance requirement for this RFO requires a dose calculation REQUIREMENTS every 31 days to provide assurance that the organ dose due to I-T-P does not result in a dose above the limits stated. The dose is calculated for the quarter and year based on actual and projected effluents for the 31 day period being analyzed. All calculated doses must be below the limits given in this RFO or the Compensatory Measures must be implemented.

REFERENCES 1. 10 CFR 50.

2. FSAR Section 15.0.3.

3. Columbia Generating Station Environmental Report, Operating License Stage, Table 5.2-14.

4. FSAR Section 11.3.3.

5. Regulatory Guide 1.109.

6. Regulatory Guide 1.111.

7. NUREG-0543.

8. 40 CFR 190.

Columbia Generating Station B 6.2.2.3-2 Amendment 50, May 2013

GASEOUS OFFGAS TREATMENT SYSTEM B 6.2.2.4 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.2 Gaseous Effluents B 6.2.2.4 Gaseous Offgas Treatment System BASES BACKGROUND This ODCM Requirement for Operability (RFO) requires the Gaseous Offgas Treatment System be available for use in either the normal or charcoal bypass mode of operation. 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 is reasonably achievable." This Requirement for Operability implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A of Reference 1. It also implements the design objectives given in Section II.D of Appendix I of Reference 1 and Technical Specification Section 5.5.4.f. Further guidance on the implementation of this RFO is provided in References 2, 3, and 4.

A Gaseous Offgas Treatment System is defined as 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.

APPLICABLE This RFO provides assurance that gaseous radioactive releases from the SAFETY Main Condenser when the Steam Jet Air Ejectors are in service are ANALYSES monitored or processed. These radioactive releases occur as a result of normal operation or could be caused by Anticipated Operational Transients. Chapter 15, Accident Analysis, of the FSAR (Ref. 5) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased gaseous effluent releases.

REQUIREMENTS The Functionality of the Gaseous Offgas Treatment System FOR OPERABILITY ensures that this system will be available for use whenever these gaseous effluents require treatment prior to release to the environment.

The term "Gaseous Offgas Treatment System" involves all of the installed and available gaseous radioactive waste management system equipment, as well as their controls, power, instrumentation, and services that make the system functional. Equipment that is considered standby or redundant is also included, since their function is to assure Functionality. The RFO also permits alternate treatment paths using alternate subsystems and equipment to be used in the event that the normal treatment equipment is nonfunctional. In the bypass mode of operation the Offgas Post-treatment Monitors must be operational and capable of automatically changing to normal mode of operation if their Columbia Generating Station B 6.2.2.4-1 Amendment 50, May 2013

BASES REQUIREMENTS setpoint is exceeded. Further information on the design bases, system FOR OPERABILITY description, and process description of the Gaseous Waste Management System is given in Reference 6.

APPLICABILITY This RFO is applicable when the Main Condenser Steam Jet Air Ejector (evacuation) System is in operation. During plant startup, prior to the use of the Steam Jet Air Ejector, a Mechanical Vacuum Pump is used to remove air from the condenser.

COMPENSATORY The normal mode of operation of the Gaseous Offgas Treatment System MEASURES is with the charcoal beds in operation. This provides for the removal of most iodine and particulate radioactive isotopes and delays the release of noble gases. If the system is not being operated in the normal mode Compensatory Measure A.1 requires it to be placed in the normal mode in seven days.

If the required Compensatory Measure A.1 and the associated seven day completion time is not met a Special Report must be submitted to the NRC that identifies the required inoperable equipment and the reasons for the inoperability, corrective actions taken to restore the required nonfunctional equipment to Functional status, and the corrective actions to prevent recurrence.

The NRC requires the report once the Gaseous Offgas Treatment System is not in the normal mode of operation for more than seven days. The report must be completed 30 days after Condition B is entered.

SURVEILLANCE SR 6.2.2.4.1 REQUIREMENTS This surveillance provides verification of Gaseous Offgas Treatment System operation in either the normal mode or the bypass mode provided the Offgas Post-Treatment Radiation Monitor is Functional every seven days. The main purpose of this surveillance is to provide assurance that the system is being operated in the normal mode with the charcoal beds in service.

REFERENCES 1. 10 CFR 50.

2. NUREG-0473, Rev. 2.

3. NUREG-0133.

4. NUREG-1302.

5. FSAR Section 15.0.3.

6. FSAR Section 11.3.

Columbia Generating Station B 6.2.2.4-2 Amendment 50, May 2013

Ventilation Exhaust Treatment System B 6.2.2.5 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.2 Gaseous Effluents B 6.2.2.5 Ventilation Exhaust Treatment System BASES BACKGROUND The Gaseous Waste Management System is designed to ensure that gaseous radioactive effluents are as low as reasonably achievable (ALARA). This ODCM Requirement for Operability (RFO) for the Ventilation Exhaust Treatment System is in accordance with the Standard Radiological Effluent Technical Specifications for BWRs (Refs. 1 and 2).

Examples of the Ventilation Exhaust Treatment System would include the following components: TG 441 Sample Hood Exhaust HEPA; Reactor Building Sump Vent Exhaust Filter System; CRD Rebuild Room Exhaust HEPA; Sampler and Analyzer Room 1A Exhaust HEPA; Radwaste Building Exhaust Ventilation HEPAs; and the Chemistry Lab Sample Hood Exhaust HEPA (Ref. 3). The system(s) appropriate for reducing the gaseous radioactive effluents must be in service if the projected 31 day organ dose is greater than 0.3 mrem. The determination of the appropriate system to be in service is based on the source of the gaseous radioactive effluent.

The Functionality of the Ventilation Exhaust Treatment System ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in gaseous effluent will be kept ALARA. This RFO implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A, and the design objective given in Section II.D of Appendix I of Reference 4. The specified limits governing the use of appropriate portions of the system were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I of Reference 4 for gaseous effluents.

APPLICABLE The Gaseous Waste Management System is designed to ensure that SAFETY gaseous radioactive effluents are ALARA. This RFO requires that ANALYSES the Ventilation Exhaust Treatment System be maintained Functional with the appropriate systems in service to provide assurance that gaseous radioactive releases caused by normal operation and Anticipated Operational Transients are treated. Chapter 15, Accident Analysis, of the FSAR (Ref. 5) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased gaseous effluent releases.

Columbia Generating Station B 6.2.2.5-1 Amendment 50, May 2013

Ventilation Exhaust Treatment System B 6.2.2.5 BASES REQUIREMENTS This RFO has two parts. The first requirement is for the system to be FOR OPERABILITY Functional and the second is for the system to be used. The Ventilation Exhaust Treatment System involves all of the installed and available system equipment, as well as their controls, power, instrumentation, and services that make the system functional.

The Ventilation Exhaust Treatment System to be used whenever the projected gaseous effluent 31 day organ dose is above 0.3 mrem. This dose is calculated for all gaseous releases from all buildings. The 0.3 mrem organ dose specified in this RFO is a fraction of the quarterly limit of RFO 6.2.2.3.

APPLICABILITY This RFO is applicable at all times as the Ventilation Exhaust Treatment System may be required at any time.

COMPENSATORY If the Ventilation Exhaust Treatment System is not in service when the MEASURES projected 31 day organ dose is above 0.3 mrem a Special Report must be written to the NRC in the next 30 days. This 31 day organ dose calculation is required by SR 6.2.2.5.1 SURVEILLANCE SR 6.2.2.5.1 REQUIREMENTS This surveillance requires a projection of the 31 day organ dose every 31 days. This dose calculation is used to determine if the Ventilation Exhaust Treatment System must be used during that time period.

SR 6.2.2.5.2 The installed Ventilation Exhaust Treatment System shall be demonstrated to be Functional by complying with RFOs 6.2.2.1 and 6.2.2.3. These RFOs provide the dose and dose rate limits applicable to the iodine and particulate gaseous radioactive releases that the Ventilation Exhaust Treatment System is designed to treat.

REFERENCES 1. NUREG-0473, Rev. 2.

2. NUREG-1302.

3. FSAR Section 9.4.

4. 10 CFR 50.

5. FSAR Section 15.0.3.

Columbia Generating Station B 6.2.2.5-2 Amendment 51, December 2013

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Total Dose B 6.2.3 B 6.2 RADIOACTIVE EFFLUENTS B 6.2.3 Total Dose BASES BACKGROUND This RFO is provided to ensure conformance to the U. S. Environmental Protection Agency (EPA) radiation protection standard contained in Reference 1. In Reference 2 the NRC issued guidance on how the EPA standard is to be implemented and interfaced with its own regulations.

The NRC guidance states that compliance with the EPA regulations is assured if the calculated dose from liquid and gaseous effluents remains below twice the limits of Reference 3. This RFO implements this guidance.

APPLICABLE This dose calculation provides assurance that all radioactive releases SAFETY and direct radiation caused by normal operation and Anticipated ANALYSES Operational Transients are evaluated to determine their impact on a Member of the Public. Chapter 15, Accident Analysis, of the FSAR (Ref.

4) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased effluent releases and direct radiation. The Columbia Generating Station Environmental Report (Ref. 5) provides estimated calculated annual doses for Columbia Generating Station.

REQUIREMENTS This RFO requires a calculation of the dose or dose commitment from FOR OPERABILITY all uranium fuel cycle sources. The method of calculation is given in the ODCM and uses the standard methodology required to satisfy the requirements of Reference 6. The dose is to be calculated for a Member of the Public in the Unrestricted Ares beyond the Site Boundary. This RFO adds the additional requirement that direct radiation must be added to the total dose. While the direct radiation from Turbine Building shine can be measurable at distances near the building it is not expected to be significant in the Unrestricted Ares beyond the Site Boundary. This calculation must also consider other direct radiation sources such as spent fuel storage facilities. A direct measurement of the direct radiation can be obtained from Environmental Monitoring devices.

APPLICABILITY This RFO is applicable at all times since effluents can be released at any time.

Columbia Generating Station B 6.2.3-1 Amendment 50, May 2013

Total Dose B 6.2.3 BASES COMPENSATORY This RFO is related to RFOs 6.2.1.2, (Dose-Liquid Effluent),

MEASURES 6.2.2.2, (Dose-Noble Gases), and 6.2.2.3, (Dose-I-T-P). Condition A is entered when the dose calculated by the surveillance requirements associated with any of these RFOs reaches twice the limit specified. The compensatory measure requires a calculation of the total dose including the contribution from direct radiation. The direct radiation calculation shall include the contribution from the plant, outside storage tanks, and any outside fuel storage facilities.

If the calculated total dose exceeds the limits of this RFO Compensatory Measure B.1 must be implemented. This requires a Special Report to the NRC within 30 days. The Special Report shall be submitted pursuant to Appendix I,Section IV.A of Reference 3. The Special Report shall define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the RFO limits including a schedule for achieving conformance with the above limits. This Special Report must also conform to the requirements of 10 CFR 20.2203.A of Reference 7.

The special report 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 within a radius of eight km, for the calendar year that includes release(s) covered by the report. 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. 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 limits of this RFO, and if the release condition resulting in violation of Reference 1 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provision of Reference 1. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of Reference 1, and does not apply in any way to the other requirements for dose limitation of References 3 and 7.

SURVEILLANCE This surveillance requires a determination of the dose or dose REQUIREMENTS commitment to any Member of the Public in the Unrestricted Area beyond the Site Boundary from liquid and gaseous effluents. This surveillance requirement is related to the surveillance requirements 6.2.1.2.1, (Dose-Liquid Effluent), 6.2.2.2.1, (Dose-Noble Gases), and 6.2.2.3.1, (Dose-I-T-P). When the calculated dose in these surveillances reach twice the limit specified it triggers a calculation of the total dose.

Columbia Generating Station B 6.2.3-2 Amendment 50, May 2013

Total Dose B 6.2.3 BASES REFERENCES 1. 40 CFR 190.

2. NUREG-0543.

3. 10 CFR 50, Appendix I.

4. FSAR Section 15.0.3.

5. Columbia Generating Station Environmental Report, Operating License Stage, Table 5.2-14.

6. Regulatory Guide 1.109.

7. 10 CFR 20.

Columbia Generating Station B 6.2.3-3 Amendment 50, May 2013

Radiological Environmental Monitoring Program B 6.3.1 B 6.3 RADIOLOGICAL ENVIRONMENTAL MONITORING B 6.3.1 Radiological Environmental Monitoring Program BASES BACKGROUND The Radiological Environmental Monitoring Program (REMP) required by this Requirement for Operability (RFO) provides representative measurements of radiation and of radioactive materials in the environment near Columbia Generating Station. It includes all exposure pathways for those radionuclides that lead to the highest potential radiation exposures of members of the public resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I of Reference 1 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 Reference 2.

APPLICABLE The REMP provides assurance that radiation levels in the environment SAFETY caused by normal operation and Anticipated Operational Transients are ANALYSES evaluated to determine their impact on a Member of the Public.

Chapter 15, Accident Analysis, of the FSAR (Ref. 3) analyzes a number of anticipated process disturbances and component failures that have the potential of causing increased environmental impact.

REQUIREMENTS This RFO, through Table 6.3.1-1, specifies sample locations, analyses, FOR OPERABILITY and frequencies for several different exposure pathways. The RFO is a comprehensive radiological environmental surveillance program to assess the impact of plant operation on the environment. The results of this program are intended to supplement the results of the Radiological Effluent Monitoring Program. The REMP verifies that the measurable concentrations of radioactive materials and levels of radiation are no higher than expected based on the effluent measurements and modeling of the exposure pathways. The program uses the guidance of References 2, 4, 5, 6, and 7. The following describes the environmental sampling categories of Table 6.3.1-1.

Columbia Generating Station B 6.3.1-1 Amendment 50, May 2013

Radiological Environmental Monitoring Program B 6.3.1 BASES REQUIREMENTS FOR OPERABILITY (continued)

Direct Radiation Pathway Thirty-four direct radiation monitoring stations are required. One or two of these are to serve as control stations located in area(s) not impacted by direct radiation from the plant. The other stations are to be located at various distances from the plant (as noted to Table 6.3.1-1) in order to obtain a representative measurement of possible direct radiation in the environment surrounding Columbia Generating Station. These measurements are normally made with thermoluminescent dosimeter (TLDs). However, one or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of Table 6.3.1-1, a TLD is considered to be one phosphor card with multiple readout areas; a phosphor card in a packet is considered to be equivalent to two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and selected to obtain optimum dose information with minimal fading. TLDs are to meet the requirements of Reference 6 except for specified energy-dependence response.

Energy Northwest has chosen to use the controls of the ODCM associated with the 10 CFR 50 license to provide the required environmental monitoring for ISFSI TLDs. Refer to the ISFSI 10 CFR 72.212 Evaluation.

Airborne Pathway-Particulate/Iodine Samples are required from six locations:

x One sample from close to the Site Boundary location, having a high calculated annual average ground level D/Q. (Station 57) x Three samples from close to the three Columbia River locations having the highest calculated D/Q. (Stations 8, 40, 48) x One sample from the vicinity of a community having the highest calculated annual average ground level D/Q. (Station 4) x One sample from a control location. (Station 9A)

Samples are obtained through the use of constant flow-rate sampling units that collect both particulate and the iodine samples. Gross beta, gamma isotopic and radioiodine analysis are required.

Columbia Generating Station B 6.3.1-2 Amendment 54, March 2016

Radiological Environmental Monitoring Program B 6.3.1 BASES REQUIREMENTS FOR OPERABILITY (continued)

Waterborne Pathway-Surface Water An upstream and a downstream sample are required. At Columbia Generating Station the upstream sample is considered the control sample. It is taken from the plant water intake which is located upstream of the plant discharge into the river. The downstream sample requirement allows for dilution in the mixing zone associated with the plant discharge line into the Columbia River. However, it is not feasible to perform flow-proportional composite sampling in the mixing zone area of the river downstream from the plant discharge point. Therefore, the downstream sample is taken from the plant discharge prior to river dilution. This provides a very conservative measurement. Gamma isotopic, gross beta, and tritium analyses are required for these samples.

Waterborne Pathway-Ground Water Groundwater samples from one or two sources are required when the source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

At Columbia Generating Station the deep well just north of the Reactor Building is sampled as it is a backup source of drinking water at the plant.

Two wells at WNP-1 that provide drinking water for that site are also sampled. Gamma isotopic and tritium analysis are required.

Waterborne Pathway-Drinking Water One sample is required of each of one to three of the nearest water supplies that could be affected. A sample is also required from a control location. The primary indicator station for drinking water is the City of Richland Water Treatment Plant that obtains its drinking water from the Columbia River. The control location is the plant intake water sampler that provides a sample of the Columbia River water upstream of the discharge line. Gross beta, gamma isotopic, and tritium analysis is required periodically. If the calculated dose from the consumption of water is greater than 1 mrem per year I-131 analysis is also performed.

Waterborne Pathway - Sediment From Shoreline One sample is required from a downstream area with existing or potential recreational value. This sample is collected approximately one mile downstream from the plant effluent line. Gamma isotopic analysis is required of this sample.

Columbia Generating Station B 6.3.1-3 Amendment 54, March 2016

Radiological Environmental Monitoring Program B 6.3.1 BASES REQUIREMENTS FOR OPERABILITY (continued)

Ingestion-Milk For the Ingestion-Milk pathway, there historically have been no milking animals identified within the distances specified in the regulatory guidance (Reference 2). Additionally, the regulatory guidance for the Ingestion-Milk pathway assumes that the milking animals are on pasture during the growing season. Most modern commercial dairies, however, are feed lot operations where milking animals are not placed on pasture.

The nearest dairy to CGS is located 7.7 miles ESE of CGS; CGS has historically obtained milk samples from this location. The milking animals at this location are routinely kept in a feed lot environment and fed stored feed. The CGS ODCM directs milk samples to be obtained out to a 10 miles distance and to obtain, if available, milk samples from milking animals known to be on pasture during the grazing season. This direction goes beyond the regulatory guidance in order to insure milk samples are obtained from locations that have the highest probability of being impacted by CGS operation. If no milking animals are identified within a 10 mile distance, vegetation samples in lieu of milk samples are required.

This is similar direction as given in the regulatory guidance for the situation when milk sampling is not performed.

A sample from milking animals is also required at a control location greater than 30 kilometers distance and in a sector not likely to be influenced by Columbia Generating Station. The control sample is obtained from the lower Yakima Valley area. Indicator samples are obtained from cattle across the Columbia River in Franklin County.

Gamma isotopic and I-131 analysis are required from all samples. In addition, if Cs-134 or Cs-137 is measured in an individual milk sample in excess of 30 pCi/liter, then Sr-90 analysis shall be performed.

Ingestion-Fish One sample of each of three recreationally important species (one anadromous and two resident) is required from the vicinity of the plant discharge. A control sample, of the same three species is required from an area not influenced by the plant discharge. Resident samples are taken from the vicinity of the plant discharge. Anadromous species are obtained from the Ringold Fish Hatchery. Control samples for resident fish are collected from the Snake River or other acceptable location.

Anadromous control samples may be obtained from the Lyons Ferry Fish Hatchery on the Snake River. Gamma isotopic analysis is required on the edible portions.

Columbia Generating Station B 6.3.1-4 Amendment 54, March 2016

Radiological Environmental Monitoring Program B 6.3.1 BASES REQUIREMENTS FOR OPERABILITY (continued)

Ingestion-Food Products The Ingestion-Food Product has two potential pathways of concern: crops irrigated by water downstream of plant discharge and crops contaminated by airborne deposition.

For crops irrigated by water downstream of plant discharges: one sample of each principal class of food products is required from any area that is irrigated by water in which liquid plant wastes have been discharged.

Produce is routinely obtained from farms using Columbia River water for irrigation. One sample of a root crop, leafy vegetable, and a fruit should be collected each sample period if available. Gamma isotopic analysis is required.

For crops potentially contaminated by airborne deposition: the preferred method is by analysis of milk samples. If milk sampling is not performed, then samples of three different kinds of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground-level D/Q are required.

A control sample of broad leaf vegetation is required from a location greater than 30 kilometers in a sector not likely to be influenced by Columbia Generating Station if milk sampling is not performed. Gamma isotopic and I-131 analyses are required.

APPLICABILITY This RFO is applicable at all times since effluents can be released at any time.

COMPENSATORY Required Compensatory Measure A.1 requires any deviations from the MEASURES program to be reported in the next annual Radiological Environmental Operating Report. This allows the NRC to be aware of any samples not collected and analyzed in compliance with the program detailed in Table 6.3.1-1.

The Condition B note allows separate condition entry for each milk and fresh leafy vegetable sample. If one or more of the milk and leafy vegetable samples are unavailable, a location for replacement samples must be identified within 30 days. The new sample locations along with revised tables and figures must be submitted in the next Radiological Environmental Operating Report. The NRC considers the sampling of milk and fresh leafy vegetables important and thus requires replacement sample locations to be identified within 30 days.

Columbia Generating Station B 6.3.1-5 Amendment 54, March 2016

Radiological Environmental Monitoring Program B 6.3.1 BASES COMPENSATORY MEASURES (continued)

The Condition C note allows separate condition entry for each sample.

The first condition involves the detection of the concentration of any single radionuclide in the environment exceeding the value given in Table 6.3.1-2. The concentrations given approximate the dose levels allowed by Appendix I of Reference 1. The detection of this level of radioactivity in the environment requires a Special Report to the NRC within 30 days. If more than one radionuclide is detected, the concentration level that requires a report is decreased. The formula given in the footnote of Table 6.3.1-2 requires a report whenever the sum of the detected concentrations divided by the concentration limits is greater than one. The Special Report must describe the corrective actions being taken to reduce the dose below those given in the Appendix I of Reference 1 (RFOs 6.2.1.2, 6.2.2.2, and 6.2.2.3). The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

Condition D involves the detection of radionuclides other than those listed on Table 6.3.1-2. If these radionuclides are detected, a dose calculation is required to determine the annual dose that would result if this concentration were present in the environment for a year. If the dose is equal to or greater than the limits given by RFOs 6.2.1.2, 6.2.2.2, or 6.2.2.3, the condition is reportable unless it can be shown that the radionuclides were not the result of Columbia Generating Station operation. The Special Report must state the corrective actions being taken to reduce the dose below the limits and must be written in 30 days.

The NRC requires timely information on unexpected radionuclides in the environment. The detection of these non-Table 6.3.1.-2 radionuclides must also be reported in the Annual Radiological Environmental Operating Report. In this report, the detection of any non-Table 6.3.1-2 radionuclides regardless of the calculated dose and source of the radiation is to be reported. The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

SURVEILLANCE This surveillance requires sampling and analysis presented in REQUIREMENTS Table 6.3.1-1 be performed to verify all environmental radiological conditions are within limits. All sampling and analysis is to be performed according to the frequency given in the Table.

Columbia Generating Station B 6.3.1-6 Amendment 54, March 2016

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Land Use Census B 6.3.2 B 6.3 RADIOLOGICAL ENVIRONMENTAL MONITORING B 6.3.2 Land Use Census BASES BACKGROUND The Land Use Census required by this RFO provides assurance that changes in the use of land in the unrestricted area 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 a door-to-door survey, from an 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 of Reference 1. Guidance for the Land Use Census is provided by Reference 2.

APPLICABLE This Land Use Census provides assurance that changing conditions in SAFETY the environment surrounding Columbia Generating Station are identified.

ANALYSES This allows more accurate evaluation of the impact of radionuclide releases caused by normal operation and Anticipated Operational Transients. Chapter 15, Accident Analysis, of the FSAR (Ref. 3) analyzes a number of anticipated process disturbances and component failures that have the potential of causing measurable environmental impact.

REQUIREMENTS This RFO provides for a periodic update of the location of the nearest FOR OPERABILITY milk animal, residence, and garden greater than 500 square feet. At Columbia Generating Station the closest residence is across the Columbia River at a distance of approximately four miles. Because of the restrictions of the Hanford Site, the only land use area that has the potential for milk animals, residences, or gardens within five miles is a narrow strip of land just east of the Columbia River. However, the Radiological Environmental Monitoring Program evaluates land use beyond the five mile limit. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Reference 4 for consumption by a child. To determine this minimum garden size, the following assumptions were made:

a) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage) and b) a vegetation yield of two kg/m2.

APPLICABILITY The RFO is applicable at all times.

Columbia Generating Station B 6.3.2-1 Amendment 50, May 2013

Land Use Census B 6.3.2 BASES COMPENSATORY If a Land Use Census is not conducted or if all required locations are not MEASURES identified Compensatory Measure A.1 requires this condition to be reported in the next Annual Radiological Environmental Operating Report.

Condition B requires notification in the next submission of the Radioactive Effluent Release Report if the new Land Use Census identifies a new location of a milk animal, residence, or garden greater than 500 square feet and the calculated dose of dose commitment at this new location is greater than that calculated by the current census at the current locations.

Condition C is an escalation of Condition B. It occurs if one of the newly identified census locations has a calculated dose greater than 120 percent of the dose from the current locations via the same exposure pathway. In this case the new location must be added to the Radiological Environmental Monitoring Program within 30 days. The compensatory measures also state that the sample location having the lowest calculated dose can be deleted from the Radiological Monitoring Program after October 31 of the year the newly discovered location was found. In addition, the NRC is to be notified in the next Effluent Release Report.

This notification must include a revised figure(s) and table for the ODCM reflecting the new location(s).

The Compensatory Measures associated with Conditions B and C are structured to assure action is taken to evaluate and implement the results of the Land Use Census.

SURVEILLANCE This surveillance requires a Land Use Census to be conducted every REQUIREMENTS year. The results of the Land Use Census are to be included in the annual Radiological Environmental Operating Report.

REFERENCES 1. 10 CFR 50.

2. NUREG-1302.

3. FSAR Section 15.0.3.

4. Regulatory Guide 1.109.

Columbia Generating Station B 6.3.2-2 Amendment 50, May 2013

Interlaboratory Comparison Program B 6.3.3 B 6.3 RADIOLOGICAL ENVIRONMENTAL MONITORING B 6.3.3 Interlaboratory Comparison Program BASES BACKGROUND The requirement for participation in an approved 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. This comparison is part of the quality assurance program for environmental monitoring to demonstrate that the sampling results are valid for the purposes of Section IV.B.2 of Appendix I of Reference 1.

APPLICABLE This Interlaboratory Comparison Program contributes to safety by SAFETY providing assurance that environmental sampling will be accurate and ANALYSES precise. This allows more accurate evaluation of the impact of radionuclide releases caused by normal operation and Anticipated Operational Transients.

REQUIREMENTS The Interlaboratory Comparison Program is a major component of the FOR OPERABILITY quality assurance program for the Radiological Environmental Monitoring Program. It involves the comparison of Columbia Generating Station analytical results obtained and compared to samples containing known concentrations of various radionuclides. The program participates in the Environmental Measurements Laboratory (EML) intercomparison program. It also participates in local and regional intercomparison studies.

APPLICABILITY The RFO is applicable at all times.

COMPENSATORY Failures associated with the Interlaboratory Comparison Program must be MEASURES reported to the NRC in the next Radiological Environmental Operating Report.

SURVEILLANCE This surveillance requires analysis of radioactive material REQUIREMENTS supplied as part of the Interlaboratory Comparison Program.

REFERENCES 1. 10 CFR 50, Appendix A.

Columbia Generating Station B 6.3.3-1 Amendment 50, May 2013

GO2-22-048, 2021 Annual Radioactive Effluent Release Report

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1.0 INTRODUCTION

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GO2-22-048, 2021 Annual Radioactive Effluent Release Report

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Subject:

Dear Sir or Madam:

REFERENCES:

1.0 INTRODUCTION

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